i fpg-trt-cs 1-0101 i nrw-fpga-based prm system ... › docs › ml1831 › ml18319a307.pdf ·...

!PSNN-2018-0209

• Safety-related D Non-Safety-related DASMECODE Dothers ( )

I Document No. I FPG-TRT-CS 1-0101 I Rev I 3

NRW-FPGA-Based PRM System Qualification Project

Document Title Qualification Test Summary Report

CUSTOMER NAME None PROJECT NAME NRW-FPGA-Based PRM

System Qualification Project ITEM NAME PRM Equipment ITEM NO. C51 JOB NO. FPG

TOSHIBA ESS NED verified this Design Document;

Method: Design Review

Verification Re2ort No.: DVR-E2-20180528-1

Verified by I.Ito

Groug Name: Second Electrical System Design & Engineering GrouJ;!

Date May 31, 2018

See DCN-FPG-TRT-C51-0101-003

3 May 31, 2018 7:.?11~ 7:.?11~ /T.c//~·

May 31, 2018 May 31, 2018 May 28, 2018

Rev. No. Issue Date Description Approved by Reviewed by Prepared by

Initial Issue Issued by Approved Reviewed Prepared

Document Filing No. Date by by by

Second Electrical System Apr 16,2008 Design &Engineering N. Oda N. Oda H. Sakai RS-5125699

Grouo

Nuclear Energy Systems & Services Division

1/151

FPG-TRT-C51-0101 Rev.3

Date History Approved Reviewed

Rev No. by by

0 Apr 16,2008 The first issue N.Oda T.Ito

1 Mar 31,2016 Clarification of test

N.Oda N.Oda configuration

2 Sept. 28, 2017 See DCN-FPG-TRT-C51-0101-002 N.Oda N.Oda

3 See cover page See cover page See cover See cover

page page

TOSHIBA ENERGY SYSTEMS & SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

2/151

Prepared by

H.Sakai

T.Miyazaki

T.Miyazaki

See cover page

FPG-TRT-C51-0101 Rev. 3

Table of Contents

1. Introduction .................................................................................................................. 5

1.1. Background ............................................................................................................. 5

1.2. Scope of the Qualification Test.. ............................................................................ 8

2. Description of Test Specimen and Test Equipment.. .................................................... 8

2.1. Description of Test Specimen ................................................................................ 8

2.2. Description of Test Equipment .............................................................................. 9

2.3. Test Configuration ................................................................................................. 9·

2.4. Modifications ......................................................................................................... 9

3. Performance Specifications ........................................................................................ 11

3 .1. Environmental Test .............................................................................................. 11

3 .1.1. Test Conditions ............................................................................................. 11

3 .1.2. Performance Requirements ........................................................................... 11

3.2. Seismic Test ......................................................................................................... 11

3 .2.1. Test Conditions ............................................................................................. 11

3.2.2. Performance Requirements ........................................................................... 12

3.3. Electromagnetic Compatibility (EMC) Tests ...................................................... 13

3.3.1. EMI/RFI Emission Tests .............................................................................. 13

3.3.2. EMI/RFI Susceptibility Test.. ....................................................................... 14

3.3.3. Surge Withstand Capability Test .................................................................. 15

3.3.4. EFT/B Test .................................................................................................... 16

3.3.5. ESD Test ....................................................................................................... 16

3.3.6. Class IE to Non-IE Isolation Test.. .............................................................. 17

4. Description of Test Facility and Equipment ............................................................... 18

4.1. Test Facility .......................................................................................................... 18

4.2. Mounting ............................................................................................................. 18

4.2.1. Environmental Test ....................................................................................... 18

4.2.2. Seismic Test .................................................................................................. 19

4.2.3. EMI/RFI, Surge Withstand Capability, EFT/B, ESD and Isolation Tests .... 20

4.3. Test System Configuration and Electrical Connections ...................................... 22

4.4. Instrumentation .................................................................................................... 22

5. Test Procedures ........................................................................................................... 23


3/151


5.1. Pre-Qualification Test .......................................................................................... 29

5.2. Enviromnental Test. ............................................................................................. 30

5.3. Seismic Test ......................................................................................................... 31

5.4. EMI/RFI Test ....................................................................................................... 32

5.4.1. Conducted Susceptibility (Power Leads) ..................................................... 33

5.4.2. Radiated Susceptibility ................................................................................. 34

5.4.3. Conducted Emission ..................................................................................... 34

5 .4 .4. Radiated Emission ........................................................................................ 3 5

5.5. Surge Withstand Capability Test ......................................................................... 35

5.6. EFT /B Test ......................................................................................................... 36

5.7. ESD Test .............................................................................................................. 36

5.8. Class lE to Non-lE Isolation Test ....................................................................... 36

5.9. Performance Proof Test ....................................................................................... 37

5 .10. Testing Conclusion .............................................................................................. 3 8

6. Test Data and Results ................................................................................................. 39

6.1. Baseline Performance of Test Specimen Units .................................................... 39

6.2. Enviromnental Test .............................................................................................. 39

6.2.1. Summary of Enviromnental Test.. ................................................................ 39

6.2.2. Data Evaluation ............................................................................................ 40

6.3. Seismic Test ......................................................................................................... 49

6.3.1. Summary of Seismic Test .......................... ; .................................................. 49

6.3.2. Data Evaluation ............................................................................................ 50

6.4. EMC Test ............................................................................................................. 54

6.4.1. Summary of EMC Test ................................................................................. 54

6.4.2. Data Evaluation ............................................................................................ 57

7. Conclusion .................................................................................................................. 63

8. References, Definitions and Acronyms ...................................................................... 67

8.1. References ........................................................................................................... 67

8.2. Definitions and Acronyms ................................................................................... 68

APPENDIX A Test results data for Seismic Tests ............................................... 70

APPENDIX B Test results data for EMC Tests .................................................. 94

APPENDIX C Details of the Operability Test and the Prudency Test ...................... 135


4/151


1. Introduction

Qualification Test Summary Report Revision 1 incorporates the following:

Clarification of hardware configuration in the Master Configuration List

(Reference (29))

Correction of description for design change of the AO module in Section 2.4

Correction of reference errors

Correction of minor errors

Clarification of description


Correction of minor errors

Correction of Figure of APPENDIX A and B


Correction of inconsistencies with other documents and errors.

1.1. Background

Toshiba Nuclear Energy System & Service Division (NED) performed a genenc

qualification of the Non Re-writable Field Programmable Gate Array (NRW-FPGA)

technology for safety-related Instrumentation and Control (I&C) systems. These systems

use programmable logic in the FPGA for all functions and have neither central processing

units (CPUs) nor operating systems. These systems have high testability and are designed

for a long operational life. Toshiba is qualifying the NRW-FPGA-Based I&C systems for

use in safety-related systems at nuclear power plants in the U.S.A.

The specific system to be qualified in this project is the BWR Power Range Monitor (PRM).

The PRM system monitors the reactor power by measuring the neutron flux level,

converting the measured flux to percent power, averaging many measured percent power

readings, and issuing a trip signal when the average percent power exceeds the specified set

point value. The PRM is a safety-related (Class lE) system. Figure 1-1 shows the

overview of this project, which comes from Figure 9-1 of the Qualification Plan

lOSHIBA ENERGY SYSl1:MS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

5/151


(Reference (11)).

The qualification ofNRW-FPGA-Based systems was performed in based on the applicable

guidance provided in EPRI TR-107330 (Reference (3)). The generic qualification

approach described in EPRI TR-107330 includes both hardware qualification and software

qualification. EPRI TR-107330 requires tests to be performed as part of the qualification

process, under a 10 CFR 50 Appendix B nuclear quality assurance program. This

Qualification Test Summary Report documents Toshiba's Qualification Tests. The tests

were performed according to the Master Test Plan (MTP) (Reference (12)) in which the

applicable EPRI TR-107330 requirements are implemented.

TOSHIBA ENERGY SYSTEMS I SOWTIONS CORPOIIJD"ION Nuclear Energy Systems & Services Division

6/151

Specified in this qualification plan

ERS

Procurement Planning Sheet

Qualification Plan


.......................................................................... SQAP

I . . Preliminary Technical Evaluation Report

~co_p~-<?:f. "fu_i~ _e_p_q_~ _., Master Test

Plan

1-------- ------, : Qualification : : Testing : : Activities : , ______________ ,

Qualification Test

Summary Report

L--·-·-·-· ·-·-·-·

Acceptance Plan for CGI

Procurement /QA Spec for

CGI

1------ --------, : Procurement : : Activities I I I , ______ --------1

Acceptance Record for

CGI

Acceptance Plan for CGS

Procurement /QA Spec for

CGS

1---------------, : Procurement : : Activities I I I I , ______ --------·

Acceptance Record for

CGS

Final Technical Evaluation Report

CGD . Packaae

,--- ------ ----, : Software : : Qualification : : Activities : I I , ______________ ,

Qualification · Analysis

report

Software Qualification

Report

l. ........................................................................................................................................................................................................................................................................................................................... : Figure 1-1 Relationship Between Project Documents

(Figure 9-1 of the Qualification Plan)

iUSHIBA ENERGY S'IS11:MS I SOWTIONS CORPORlll"ION Nuclear Energy Systems & Services Division

7/151


1.2. Scope of the Qualification Test

This Qualification Summary Report was issued to document the test results and evaluate

the test results against the acceptance criteria provided in the MTP.

The PRM qualified in this project differs from PLC-based equipment typically qualified

using EPRI TR-107330. The qualification tests were customized to eliminate unnecessary

tests, including incorrect EPRI requirements for aging equipment installed in mild

environments. Equipment Requirement Specification (ERS) (Reference (13)) specifies

equipment requirements of the units to be qualified.

2. Description of Test Specimen and Test Equipment

The Test Specimen Units tested in this qualification proj~ct were designed and

manufactured in accordance with the ERS, which was established to summarize the

applicable requirements from the following three. documents:

• EPRI TR-107330

• PRM System design specification provided for a typical Japanese plant

• Fuchu Complex vendor information

2.1. Description of Test Specimen

The Test Specimen was composed of all units needed to create a Test System which provides

the typical PRM functions for a BWR-5. The Test Specimen for the project consisted of one

LPRM Unit, one LPRM/ APRM Unit, one Flow Unit, interconnecting cables, and the spare

modules and the spare chassis that were provided for maintenance of the Test Specimen

Units. Appendix 1 of the MTP provides a detailed description of the Test Specimen.

TOSHIBA ENERGY SYSTEMS I SOLUTIONS CORPORAJIOII Nuclear Energy Systems & Services Division

8/151


2.2. Description of Test Equipment

The Test Equipment was composed of equipment needed to generate input signals and to

monitor the output signals of the Test Specimen during the Qualification Test. As

described in Section 6.3 of MTP, this included data recording equipment, a variable power

supply, and input simulators. The Test Equipment was provided and controlled based on the

ERS Section 7.3.1.3, which satisfies the requirements of EPRl TR-107330 Section 6.2.3.

The Preliminary Technical Evaluation Report (PTER) (Reference (14)) specified the Test

Equipment requirements. Detailed Test Equipment specifications are described in MTP

Section 6.3.

2.3. Test Configuration

The Qualification Tests were performed on a Test System, which contains the Test

Specimen and Test Equipment. The configuration of the Test System used in this

qualification project is shown in Figure 4-1 of the PTER.

2.4. Modifications The Radiation Exposure Test was conducted in July 2006 with the hardware configuration

identified by the date May 25th, 2.006 in the Master Configuration List (Reference (29)).

The Environmental Test was performed during June 2006 through October 2006 with

hardware configuration identified by the date May 25th, 2006 and August 7th, 2006 in the

Master Configuration List. The Hardware configuration was changed during the

environmental test after a Test System failure caused by incorrect operation of the

environmental chamber, where water condensing on the top of the chamber fell into the

powered electronics. Details for the hardware configuration change are described in Section

6.2.2.2 of this report.

TOSHIBA ENERGY SYSl1:MS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

9/151


The EMI/RFI, Surge Withstand Capability, EFT/B, ESD and Class lE to Non-IE Isolation

Tests, were performed from October 2006 through March 2007 with the hardware

configuration identified by the date August 7th, 2006 in the Master Configuration List.

However, the EMI Susceptibility Test failed. The hardware was re-designed to resolve the

test failure. Therefore, for the second EMI/RFI, Surge Withstand Capability, EFT /13, ESD

and Class lE to Non-IE Isolation tests, the LPRM module HNSOll and the AO modules

HNS511, HNS512, HNS513, and HNS514 were replaced with the LPRM module HNS013

and the AO modules HNS515, HNS516, HNS517 and HNS518. This test configuration is

identified with the August 24th 2007 date in.the Master Configuration List. The re-designed

LPRM and AO modules had additional · capacitors to enhance

electric-noise-withstand-capability and passed the test.

Two capacitors were added on the LPRM module. Those two capacitors are the same

capacitors used in the other locations in the LPRM module.

Several changes were made to the multiple output channels on the AO board. The changes

can be grouped into six categories as follows:

(1) Toshiba added 16 capacitors of the same type and capacity used in the LPRM module.

(2) Toshiba added 18 capacitors that are .of the same type as those used in the LPRM

module but have a different capacity.

(3) Toshiba replaced 16 capacitors with the same capacitor described in Item (2).

(4) Toshiba added 16 capacitors of the same type and capacity that were originally used in

the same AO module in different locations.

· (5) Toshiba enhanced the grounding connection in the module

(6) Toshiba moved some labels.

Because the same types of capacitors as the added capacitors had been used in other

modules that passed the EQ tests (the environmental 'test and seismic . test), Toshiba

considered that the results of the environmental test and seismic test for the LPRM and AO

modules without the additional capacitors were applicable to the LPRM and AO modules

with the additional capacitors. Toshiba repeated the electromagnetic qualification tests

with the revised modules.

After the second EMI/RFI, Surge Withstand Capability, EFT/B, ESD and Class lE to

Non-IE Isolation Tests, the replaced modules were removed and the origina:l modules were

re-installed on February 20th, 2008, as shown in the Master Configuration List.

MSHIBA ENERGY SYS1EMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

10/151


Figure 2.4.1 [Deleted]

Figure 2.4.2 [Deleted]

3. Performance Specifications

3.1. Environmental Test

3.1.1. Test Conditions

3.1.1.1. Radiation Exposure

The Test Specimen Units were subjected to the total dose of 11 Gy +30%/- 9% gamma

radiation (to satisfy the ERS section 5.5.1 of 10 Gy with 10% margin) using a 6°Co gamma

ray source. The dose rate was measured at 4.27 Gy-air/hour.

3.1.1.2. Temperature and Humidity

The Test Specimen Units were subjected to the temperature and humidity conditions as

shown in Figure 5-2 of ERS to evaluate the effects of temperature and humidity on Test

Specimen operability.

3.1.2. Performance Requirements After the test, the performance of the Test Specimen Units was compared to the baseline

performance measured during the Pre-Qualification Test. The test demonstrated that the

Test Specimen was not impacted by these tests.

3.2. Seismic Test

3.2.1. Test Conditions Figure 5-3 of the ERS shows the Required Response Spectra (RRS) for the Operation Basis

Earthquake (OBE) and Safe Shutdown Earthquake (SSE). The peak amplitudes of this

TOSHIBA ENERGY SYS1EMS I SOLUTIONS CORPORRrlON Nuclear Energy Systems & Services Division

11/151


figure are shown in Table 3-1.

Table 3-1 Peak Amplitude of Seismic Test

Seismic Amplitude Requirement from ERS Section 5.5.2 and EPRI TR-107330

Event Section 4.3.9

OBE 9.8 g

SSE 14 g

3.2.2. Performance Requirements During the initial part of seismic testing, a resonance search was performed to verify that no

resonances exist in the frequency range defined in the applicable standards. During the test,

the Test Specimen Units performed normal processing of input data and produced the

expected output data.

Following the Seismic Test, the Test Specimen Units were determined to be structurally

intact. Specifically, the Test Specimen Units were examined to ensure no parts are damaged

or loosened.

Following the Seismic Test, the Test Specimen Units were determined to be able to perform

the safety functions as required in the ERS Section 4.1.2. Specifically, the Test Specimen

Units met the acceptance criteria specified for the Operability Test following the SSE.

ERS Section 7.2.2 provides the general acceptance criteria for the Operability Test.

The EPRI requirement for performing Prudency and Operability Tests during the seismic

testing cannot be performed, as the seismic test would have to be extended from seconds to

days to provide sufficient time to perform Prudency and OperabHity Tests. Since this is not

reasonable, testing was performed during the seismic events to demonstrate that the

equipment remained operable during application of seismic stressors. Additional testing

was performed after the seismic events to demonstrate that the equipment was still

operable.

Following the test, the performance of the Test Specimen was compared to the baseline

performance (measured during the Pre-Qualification Test) to demonstrate that the test did

TOSHIBA ENERGY SYS1EMS I SOLUTIONS CORPORID'ION Nuclear Energy Systems & Services Division

12/151


not impact the performance and operability of the Test Specimen. Appendix C shows the

detailed scope and the timing of the Operability Tests and the Prudency Tests in the Seismic

Test.

3.3. Electromagnetic Compatibility (EMC) Tests

The EMC Test includes the following tests:

(1) EMIIRFI Emission Test

(2) EMI/RFI Susceptibility Test

(3) Surge Withstand Capability Test

(4) Electrically Fast Transient and Burst (EFT/B) Test

(5) Electrostatic Discharge (ESD) Test

(6) Class lE to Non-lE Isolation Test

All ab~ve Tests were performed in an anechoic chamber.

3.3.1. EMI/RFI Emission Tests

3.3.1.1. Test Conditions

(1) Radiated Emissions

The tests followed the guidance of MIL-STD-461E (Reference (6)), RE101 and RE102.

The emissions were measured from 30 Hz to 100 kHz (RE101) and 2 MHz to 1 GHz

(RE102).

(2) Conducted Emissions

The tests followed the guidance of MIL-STD-461E, CElOl and CE102. Since the PRM

uses less than 1 KVA, the tests were conducted using less restrictive low power curves,

from 60 Hz for AC Power less than or equal to 1 KVA to 10 kHz (CE101) and 10 kHz to

2MHz (CE102).

TOSHIBA ENERGY SYSl1:MS I SOLUTIONS CORPORUION Nuclear Energy Systems & Services Division

13/151


3.3.1.2. Performance Requirements

Conducted emissions were within the limits defined by Figure 5-7 of the ERS, complying

with NRC Regulatory Guide 1.180 Revisionl (RG l.180Rl, Reference (1)) Figure 3.1, and

Figure 5-8 of the ERS, complying with RG l. l 80Rl Figure 3 .2.

Radiated emissions were within the limits defined by Figure 5-9 of the ERS, complying

with RG l.180Rl Figure 3.3, and Figure 5-10 of the ERS, complying with RG l.180Rl

Figure 3.4.

3.3.2. EMI/RFI Susceptibility Test


(1) Radiated Susceptibility, Magnetic Fields

The test followed the guidance of MIL-STD-461E, RSlOl. The applicable frequency

range is 30 Hz to 100 kHz. Field strength is defined by Figure 5-6 of the ERS, complying

with RG l. l 80Rl Figure 4.3.

(2) Radiated Susceptibility, Electric Field

The test followed the guidance of MIL-STD-461E, RS103. The applicable frequency

range is 30M Hz to 1 GHz. Field strength is 10 V/m defined by section 5.5.3.5 of the ERS,

complying with RG 1.180Rl Section 4.3.2.

(3) Low-Frequency Conducted Susceptibility Test at AC Power Leads

The test followed the guidance of MIL-STD-461E, CSlOl. The applicable frequency

range is 120 Hz (the second harmonic of the power line frequency) to 150 kHz. The test

input signal amplitude is defined by Figure 5-4 of the ERS, complying with RG l. l 80Rl

Figure 4.1.

(4) High-Frequency Conducted Susceptibility Test at AC Power Leads

The test followed the guidance of MIL-STD-461E, CS114. The applicable frequency

TOSHIBA ENERGY SYSTEMS I SOWTIONS CORPOIIAJIOlil Nuclear Energy Systems & Services Division

14/151


range is 10 kHz to 30 MHz. The test input signal amplitude is defined by Figure 5-5 of the

ERS, complying with RG l. l 80Rl Figure 4.2.

(5) High-Frequency Conducted Susceptibility (Signal Leads)


range is 10 kHz to 30 MHz. The test input signal amplitude is 91 dBµA defined by Section

5.5.3.3 of the ERS, complying with RG1.180Rl Table 14.

(6) Conducted Susceptibility (Signal Leads, Bulk cable injection, impulse excitation)

The test followed the guidance of MIL-STD-461E, CS115. The test input signal

amplitude is 2 amperes (A) defined by Section 5.5.3.3 of the ERS, complying with

RG1.180Rl Table 14.

(7) Conducted Susceptibility (Signal Leads, Damped sinusoidal transients)


range is 10 kHz to 100 MHz. The test input signal amplitude is 5 amperes (A) defined by

Section 5 .5 .3 .3 of the ERS, complying with RG l .180Rl Table 14.


During the EMI/RFI Susceptibility Test, the Test Specimen performed the safety functions

as required in ERS Section 4.1.2.

The performance of the Test Specimen Units after the test was compared to the baseline

performance and demonstrated that the test did not impact the performance and operability

of the Test Specimen Units.

3.3.3. Surge Withstand Capability Test


The Surge Withstand Capability Test was performed at 2 kV for the AC power line to meet

the requirements in the ERS Section 5.5.4, complying with RG 1.180 RI Sections 5.1 and

TOSHIBA ENERGY SYS1EMS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

15/151


5.2. The ring wave test was performed in accordance with IEC 61000-4-12 (Reference

(10)). The Combination wave test was performed in accordance with IEC 61000-4-5 (Reference (9)).


During the surge application, the Test Specimen Units performed its safety functions as

required in ERS Section 4.1.2.

The performance of the Test Specimen after the test was compared to the baseline



3.3.4. EFT/8 Test


The EFT/B Test was performed at 2 kV for the AC power lines to meet the requirements

shown in ERS Section 5.5.5, complying with RG1.180Rl Section 5.3. The test was

performed in accordance with IEC 61000-4-4 (Reference (8)).


During the EFT/B Application, the Test Specimen Units performed its safety functions as

required in ERS Section 4.1.2.




3.3.5. ESD Test


The ESD Test was performed at 8 kV (Contact Discharge) and 15 kV (Air Discharge) to

meet the requirements shown in ERS Section 5.5.6, complying with EPRI TR-102323

(Reference (2)), Appendix B, Section 3.5. The test was performed in accordance with IEC


16/151


61000-4-2 (Reference (7)).


The ESD was applied to the test points which can be touched by persons during normal

operation and the points that can be touched with maintenance personnel with wristband

under the administrative permission during maintenance as a special case. During ESD

Testing the Test Specimen Units performed its safety functions as required in the ERS

Section 4.1.2.




3.3.6. Class 1 E to Non-1 E Isolation Test


The Cla_ss lE to Non-IE Isolation Test was performed at 600 VAC and 250 VDC to meet

the requirements shown in the ERS Section 5.5.7, complying with EPRI TR-107330

Section 4.6.4.


During the test level voltage application to the test points, the Test Specimen Units

demonstrated the ability to perform safety functions as required in ERS Section 4.1.2.



of the Test Specimen Units. Appendix C shows the detailed scope and the timing of the

Operability Tests and the Prudency Tests in the EMC Test.

TOSHIBA ENERGY sYSTEMS I SOWTIONS CORPOIIAJION Nuclear Energy Systems & Services Division

17/151


4. Description of Test Facility and Equipment

4.1. Test Facility

All Qualification Tests except the

[ [ ]"personnel at the [

Facility in July 2006.

, [ Ja,c Radiation Exposure Test were conducted at r The Radiation Exposure Test was performed by

]"High Level Radiation Effects

The Environmental Test was performed during June 2006 through October 2006. During

August 2006, the test was suspended due an equipment fault caused by incorrect operation

of the environmental chamber.

The other tests, EMI/RFI, Surge Withstand Capability, EFT/B, ESD and Class lE to

Non-IE Isolation Tests, were first performed during October 2006 through March 2007.

However, the . EMI Susceptibility Test failed. The LPRM and AO modules were

re-designed by adding capacitors on the printed circuit boards to enhance noise rejection.

The re-designed modules were installed in the Test Specimen. The retest was performed

during October 2007 to March 2008 and completed successfully.

After the completion of these tests, the replaced modules were removed and the original

modules were installed. After installation of the original modules, the Performance Proof

Test was performed to demonstrate that the safety functions required in the ERS Section

4.1.2 were still operable after testing.

4.2. Mounting

4.2.1. Environmental Test

For the Environmental and Radiation Exposure Tests, the Test Specimen Units were placed

1USH1BA ENERGY SYSTEMS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

18/151


in a :free-standing instrument rack. Figure 4-1 shows the mounting of the Test Specimen.

a.c

Figure 4-1 Mounting of Test Specimen for Temperature and Humidity Test

4.2.2. Seismic Test

Figure 4-2 shows the mounting of the Test Specimen. The Test Specimen Units were

mounted on a structure that was sufficiently stiff. The mounting structure was constructed

as follows:

Two pieces of 6 inches x 3 inches x 3/8 inch steel tubing were welded to the test table

with 3/16 inch fillet welds approximately 4 inches in length (two at each comer).

The test fixture was constructed from 2 inch by 2 inch steel angle and was welded to the

lower mounting tubes on each comer of the test fixture to form vertical 2 inch by 2 inch

rails.

The fixture was installed on the [ rrriaxial Seismic Simulator Table such that its

horizontal axes were collinear with the horizontal axis of the table.

The Test Specimen Units were mounted in the [ Jprovided test fixture using MS

mounting hardware located in the front of the chassis and M4 screws located in the rear

of each unit. The three varistor panels were mounted horizontal to the test table using

MS mounting hardware.

nJSHIBA ENERGY SYSTEMS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

19/151


a,c

Figure 4-2 Mounting of Test Specimen for Seismic Test

4.2.3. EMI/RFI, Surge Withstand Capability, EFT/B, ESD and Isolation Tests

The Test Specimen Units were installed in the free-standing instrument rack used in the

Environmental Test. This rack was designed not to shield . emissions from the Test

Specimen Units, and not to shield the applied fields used to evaluate the susceptibility of

the Test Specimen Units.

The Test Specimen Units were installed in [

Figures 4-3 and 4-4.

ranechoic chamber as shown m


20/151


rn

1 meters

11 S VAC Power Strip

Anecboic Mllterial

Protective Earth Ground LISN shown connected to the Green Wu-c or bottom LJ.S.N. wa,; used only during CElOl and CE102 tests when mei,suring the Protective Earth Ground. Protective Ean.h Ground was nornully connttted to 1he shiddcd m c1osurc floor

Power line filter

atcb Panel

EUT Support Equipment Rack

ComputN"S

Decoupling Nen\•orb

Door

Patch Paud withMTK M1833 Fil1ers

Drnwiug is not to scale

Figure 4-3 Layout in the test chamber

Figure 4-4 Picture in the test chamber

a,c

TOSHIBA EJIERGY SYSTEMS I SOLUTIONS CORPOllfllON Nuclear Energy Systems & Services Division

21/151


4.3. Test System Configuration and Electrical Connections

The Schematic Diagram (Reference (15)) shows the representative electrical connections.

The Schematic Diagram was developed according to the requirements provided in Figure

4-1 of the PTER, as described in Section 2.3 of this report.

The Schematic Diagram shows the representative configuration. The specific modifications

required for the test conditions, such as penetrations through the EMC chamber walls, were

implemented as required.

4.4. Instrumentation

The instrumentation measuring and test equipment used for this test was calibrated by

equipment traceable to the National Institute of Standard and Technology (NIST) or the

National Metrology Institute of Japan (NMIJ). Both NIST and NMIJ are signatories to the

Bureau International des Poids et Mesures (BIPM). The test signal inputs and data

acquisition system were located outside the anechoic chamber.

TOSHIBA ENEJIGY SYSTEMS I SOWTIONS CORPORfllON Nuclear Energy Systems & Services Division

22/151


5. Test Procedures

The initial tests were performed for the assembled Test System in Japan. Then, the Test

Specimen and some of the Test Equipment were shipped to the U.S for the test at the [ r [ r The tests performed were as follows:

• Pre-Qualification Tests, conducted prior to Qualification Test to determine that the

system operates correctly and to provide baseline data on equipment performance.

These tests were performed at the Toshiba Fuchu Complex, and repeated at the [ r test facility. The Pre-Qualification testing includes:

•

• System Set-up and Check-out Test at Fuchu Complex, performed as a part of

the System Validation Test for V &V activities

• Burn-in Test at Fuchu Complex, performed as a part of the System Validation

Test for V & V activities

• System Set-up and Check-out Test at[ ]"(after shipping and re-assembly)

• Operability Test

• Prudency Test

Qualification Tests, conducted to demonstrate compliance with the ERS requirements,

and to demonstrate suitability of the Test Specimen while being subjected to stress

conditions. The Qualification Tests were performed at [ ron the assembled Test

System after the Test System has passed the Pre-Qualification Test acceptance criteria.

The Qualification testing includes:

• System Set-up and Check-out Test, after each Test System disassembly,

reassembly, or relocation

• Radiation Exposure Test

• Environmental Test

• Seismic Test

• EMI/RFI Test

• Surge Withstand Capability Test

• EFT/B Test

TOSHIBA ENERGY SYSTEMS I SOWTIONS CORPORUION Nuclear Energy Systems & Services Division

23/151


• ESD Test

• Class lE to Non-lE Isolation Test

• Power quality Test (performed during other tests)

• Performance Proof Tests, conducted to confirm satisfactory operation after being

subjected to Qualification Test conditions. The Performance Proof Tests are a repeat

of the operability test and prudency test performed in the Pre-Qualification Tests to

identify any changes in equipment performance. Performance Proof Tests were

performed at[ J~d included:

• System Set-up and Check-out Test

• Operability Test (retest)

• Prudency Test (retest)

The sequence of tests is shown in Table 5-1 (a), (b) and Figure 5-1 below. Table 5-1 (a) lists

the Reference page in the ERS, Test procedure document number, and the Test Lab test

procedure number. Table 5-1 (b) lists the contents of the Operability Test and the Prudency

Test for the PRM. Please note Figure 5-1 does not show the points where the Operability

Test and/or the Prudency Test were performed during the Qualification test. Appendix C

shows the detailed scope and the timing of the Operability Test and the Prudency Test.

TOSHIBA ENERGY SYS1EWS I SOWTIONS CORPOIUO"ION Nuclear Energy Systems & Services Division

24/151

Test

1. Pre-Qualification Test

2. Qualification Test

3. Performance Proof Test


Table 5-1 Qualification Test Overview

(a)

ERS Toshiba Test Procedure Ref. Para. Number

1.1 System Set-up Not applicable and Check-out Test FPG-TPRC-C51-0001

1.2 Burn-in Test 7.2.1 8 1.3 System Set-up

N_ot applicable FPG-TPRC-C51-1001 and Check-out Test

1.4 Operability Test 7.2.2, 7.2.4 FPG-TPRC-C51-1 009

1.5 Prudency Test 7.2.3, 7.2.4 FPG-TPRC-C51-1010

2.2 Environmental Test (Radiation 7.3.2.4, 5.5.1 FPG-TPRC-C51-1002

Exposure)

2.4 Environmental 7.3.2.4, 5.5.1 FPG-TPRC-C51-1002 Test (Temperature

and Humidity)

2.6 Seismic Test 7.3.2.5, 5.5.2 . FPG-TPRC-C51-1003

2.8 EMI/RFI Test 7.3.2.2, 5.5.3 FPG-TPRC-C51-1004

2.9 Surge Withstand Capability Test

7.3.2.7, 5.5.4 FPG-TPRC- C51-1005

2.10 EFT/ 8 Test 7.3.2.9, 5.5.5 FPG-TPRC- C51-1006

2.11 ESDTest 7.3.2.10, 5.5.6 FPG-TPRC- C51-1007

2.12 Class 1 E to Non-1 E Isolation 7.3.2.8, 5.5.7 FPG-TPRC- C51-1008

Test

3.2 Operability Test 7.2.2, 7.2.4 FPG-TPRC-C51-1009

3.3 Prudency Test 7.2.3, 7.2.4 FPG-TPRC- C51-1010

[ r Test Procedure Number

Not applicable

Not applicable

Not applicable

Not applicable

Not applicable

FPG-VDN-C51-0200

FPG-VDN-C51-0200

FPG-VDN-C51-0200

FPG-VDN,C51-0201

FPG-VDN-C51-0201

FPG-VDN-C51-0201

FPG-VDN-C51-0201

FPG-VDN-C51-0201

Not applicable

Not applicable

TOSHIBA BIERGY SYS1EIIIS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

25/151


(b)

Operability Test Prudency Test

Pre-Qualification Test Conducted Conducted

Radiation Exposure - -Environmental Before High Temperature and High Conducted for specific scope -

Test Humidity Exposure (Note 1)

During High Temperature and High - -Humiditv Exoosure

After High Temperature and High Conducted for specific scope Conducted for specific scope Humidity Exposure (Note 1) (Note 3)

During Low Temperature Exposure - -

After Low Temperature Exposure Conducted for specific scope -(Note 1)

During Low Humidity Exposure - -

After Low Humidity Exposure Conducted for specific scope -(Note 1)

After all Environmental Conducted for specific scope -(Note 1)

Seismic Test Before Seismic Test - -During Seismic Test - -

After Seismic Test Conducted -

Replacement of Modules (LPRM Modules were replaced with HNS013 from HNS011.AO Modules were replaced with HNS515/516/517/518 from HNS511/512/513/514.

EMC Test Before EMC Test Conducted for specific scope -(Note 2)

During EMC Test - -After EMC Test - -

Isolation Test(Class 1 E to Non 1 E Test) - -

Post Qualification Test(Before re-replacement of Conducted for specific scope -modules) (Note 2)

Re-Replacement of Modules (LPRM Modules were replaced with HNS011 from HNS013. AO Modules were replaced with HNS511/512/513/514from HNS515/516/517/518.

Post-Qualification Test(After re-replacement of Conducted Conducted modules)

Notes for this table are listed in the next page.

IUSHIBA ENERGY SYS1EMS a SOWTIONS CORPORKl'IOIII Nuclear Energy Systems & Services Division

26/151


The Operability Test and the Prudency Test conducted in the Pre-Qualification Test and the

Post-Qualification Test (After re-replacement of modules) include the following Tests.

Operability Test:

(1) Linearity test for APRM level, TPM level, and LPRM level at the LPRM gains 40µA/100%

(2) Linearity test for APRM level, TPM level, and LPRM level at the LPRM gains 400µA/100%

(3) Linearity test for APRM level, TPM level, and LPRM level at the LPRM gains

2400µA/100%

( 4) APRM Upscale (High-High) trip and TPM Upscale trip response time test at the LPRM gains

40µA/100%

(5) APRM Upscale (High-High) trip and TPM Upscale trip response time test at the LPRM gains

400µA/100%·

(6) APRM Upscale (High-High) trip and TPM Upscale trip response time test at the LPRM gains

2400µA/100%

(7) Linearity test for FLOW level

(8) APRM Inoperable trip function test

(9) DI function test

(10) Low voltage power supply failure test for LPRM unit

(11) Low voltage power supply failure test for LPRM/APRM unit

(12) Low voltage power supply failure test for FLOW unit

(13) Watchdog function test for LPRM unit

(14) Watchdog function test for LPRM/APRM unit

(15) Watchdog function test for FLOW unit

(16) Current value test of Square Root module in FLOW unit

(17) Loss of power test

(18) Power interruption test

Prudency Test:

(19) DI Toggling test

(20) AI Toggling test

(21) Failure simulation test

Note 1: Toshiba did not conduct (1), (3), (4), (6), (8), (10), (11), (12), (13), (14), (15).

Note 2: Toshiba did not conduct (2), (3), (5), (6), (13), (14), (15), (16), but Toshiba conducted watchdog timer function test for the LPRM module inserted Slotl ofLPRM and LPRM/APRM units.

Note 3: Toshiba did not conduct (21).

TOSHIBA BIIERGY SYS1EMS I SOWTIONS CORPORBION Nuclear Energy Systems & Services Division

27/151


r-r-· ·--·-,·---···--·-i I I

-----,-------------n·11~~~--=:.· .. := i ··----c-:-T 1----·-·-- ...... i !

Sy stem Validation I FPG-TPRC-C51-0001 '

-=~1=== i

-. .L -··--· .. ! I·- --·-· i-·· i-

i

' ': ·;· I : Trailsvortation 1o I"·' (rn"s1,T,;;-j},;~ -' .. ,

r-1----,---·n------- ·-_____ ! ____

>- ·- -- .. ·-· l!L ____ ...;, ___

'"""'j :c- ·--- ,.,.. ' ' ' ' -,-

: ' .

! Sy stem Set Up and

Operability Prudency Check-out , •.. FPG-TPRC-C51-1001 - FPG-TPRC-C51-1009 FPG-TPRC-C51-1010

' I

. -•··--····•· .....

Pre-Qualification Test r---·-·, ---······-··· ''' ' ... ,, ... .• L J•,c .. , ... 1 -··"r ·----·. to Radiation Testing Facility in . '" I I I i I I I I I I

·-r- ! I i ,~. ,, to.!a1Jan ·- ---- -I I ! i I I

I I

Environmental Test Environmental Test Modification of the (Radiation) I I (Temperature &

Seismic Test

-l- rmdules ta enhance the , ............... FPG-TPRC-C51-1002 I Humidity) - FPG-TPRC-C51-1003

noise withstand FPG-TPRC-C51-1002 capability r

'.Jc L ,~. ,c ~-

- ·-I'" J1;st Procedure J1;st Procedure < J~;st I - i!~---····

Rmlint;n» Testing Facility [ ,.,,, .......... '""·"·-·

-··1---~- ·--l"T i ......... i''

·- .... I IOL J ,,c

I I : i I. i I l i I ..•..

System Set Up and EMI/RFI Test

Surge Withstand EFT/8 Test ESD Test Class 1E to Non-1E

-- Check-out for re-setup FPG-TPRC-C51-1004

Capability Test FPG-TPRC-C51-1006 - FPG-TPRC-C51-1007 ->-

Test FPG-TPRC-C51-1001 FPG-TPRC-C51-1005

FPG-TPRC-C51-100B

-.... , ...... ' ' '' '

I a,c ]'r~st Procedure [ L JTest ..

]~~st Procedure ..

]~;st Procedure ,-- [ ]~;st Procedure Procedure "'

.... ,. I

, I i

I : I I i I

I I I Qualification Test i I I I I

i I ' i I ! ! 1 i I I i i i i j

! I t 11 I ! I ·f-· ..... _.+ ·-l- ·--t-i I I i I i .... .. .. Re-install the original modules to evaluate

Operability Prudency TransEortation 11 ,F~chu

- the aging effects ' INSPECT

during environmental FPG-TPRC-C51-1009 FPG,TPRC-C51-1010 I & STORE

testing

" ·-·"" , ........... I I -··· I

I

1~--~·-··· .U .. lj '

I Toshiba r.. . ... ; ... , ""

Performance Proof Test "! ... T

I .

- i -' i ·--f- ·-

~ _,.. ·-· ~ - '" '

-· i

i

I I 11 '

Figure 5-1. Actual Test Flow Diagram

TIJSHIBA ENERGY SYS1EMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

28/151

-·-

--··-

---: ....

. --

, .....

f- "

, __

......

··+-·" -

' +-

··-··

I I

....


5.1. Pre-Qualification Test

The Pre-Qualification Test was performed pnor to the Qualification Test. The

Pre-Qualification Test demonstrated that the Test Specimen operated as intended, and

provided a performance baseline for the Qualification Test.

The NRW-FPGA-Based PRM Units were manufactured with the correct application logic,

and thus required no application software objects testing.

All Test Specimen module parameters and switches were set and checked in the System

Set-up and Check-out Test.

The Burn-in Test was carried out on the Test Specimen to detect any failures in early life

that would corrupt the Qualification Test results. The Burn-in Test required 352 hours of

continuous operation of the Test Specimen.

The Operability Test and the Prudency Test were performed to establish the baseline

performance. The Operability Test was performed in order to demonstrate the

functionality of the Test Specimen. The Prudency Test was performed to demonstrate the

operability of the Test Specimen under highly dynamic conditions. The test requirements

are provided in the ERS Section 7.2.

Table 5-1 and Figure 5-1 show the order for the Pre-Qualification Test, and the procedures

used. The Pre-Qualification Test was performed as follows:

(1) System Set-up and Check-out Test (FPG-TPRC-CSl-0001). This test verifies

proper assembly, integration and operation of the assembled Test System for the

Pre-Qualification Test in the Toshiba's facility. 1'his test confirmed proper

connection and operation of the Test System including the monitoring instruments,

variable power supplies, and signal simulators. This test was performed as a part

of the System Validation Test for V & V activities.

(2) Burn-in Test (FPG-TPRC-CSl-0001) .. This test implemented a 352 hour burn-in

TOSHIBA ENERGY SYS1DIS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

29/151


of the assembled Test System, to detect any failures in early life that might

otherwise impact the subsequent Qualification Test activities. This test was

performed as a part of the System Validation Test for V & V activities.

(3) System Set-up and Check-out Test (FPG-TPRC-CSl-1001). After the.Bum-in

Test, the Test Specimen and Test Equipment were transported to the [ r [ Jin the U.S. The System Set-up and Check-out Test was performed

before the Operability Test. This test verified proper assembly, integration, and

operation of the assembled Test System in [ r This test confirmed proper

connection and operation of the Test System including monitoring instruments,

variable power supplies, and signal simulators.

(4) Operability Test (FPG-TPRC-CSl-1009). This test verified the Test System

functions correctly before starting Qualification Tests. The initial· performance

confirmed in the Operability Test procedure also established the baseline Test

System performance. The baseline performance was used for comparison to

performance measured during the Qualification Tests.

(5) Prudency Test (FPG-TPRC-CSl-1010). This test verified that the Test System . .

functions correctly while being exercised in various ways to simulate potential

in-service stresses. The initial performance of the Prudency Test procedure also

established baseline performance of the Test System for comparison to performance

measured during Qualification Tests.


The Environmental · Test was performed to demonstrate that the Test Specimen Units

provide the performance required under the environmental conditions provided in ERS

Section 5.5.1. The conditions in the ERS comply with the conditions in EPRI TR-107330.

The required conditions of temperature and humidity used for testing are provided in the

ERS Section 5.5.1.

TOSHIBA ENERGY SYSTDIIS I SOWTIDNS CORPORATION Nuclear Energy Systems & Services Division

30/151


According to the requirements of ERS Section 7 .3 .2.11, a power quality tolerance test was

performed, at the end of the elevated temperature test while still at high temperature.

Input voltage ranges and frequency ranges of power supplies for connection to AC and DC

sources are given in ERS Section: 5.5.8, and the margin is given in IEEE Std 323 (Reference

(5)).

Radiation Exposure Testing was included in the environmental evaluation in ERS Section

5 .5.1. A 11 Gy gamma dose was applied, including a 10% margin above the requirement

of 10 Gy. The 10 Gy exposure requirement is stated in the ERS Section 5.5.1 and satisfies

the requirements of EPRI TR-107330 Section 4.3.6.1. The Radiation Exposure Test was

performed in accordance with the guidance of IEEE Std 323.

Abnormal environmental conditions for each Environmental Test were defined by the

abnormal.environmental basic conditions provided in the ERS Section 5.5.1 considering the

margins for each condition.

5.3. Seismic Test

The Seismic Test was performed to assure that the Test Specimen Units provide the

performance and seismic withstand capability under the Seismic Test conditions provided

in the ERS Section 5.5.2. These conditions in the ERS comply with the conditions in

EPRI TR-107330 to the extent achievable at[ r This test involved the following activities:

• Mounting of the Test Specimen Units on a vibration table,

• Setting up the Test System,

• Performing a System Set-up and Check-:-out Test to verify correct setup,

• Performing a Resonance Search Test,

• Performing five tri-axial Seismic Tests representative of an Operating Basis

Earthquake (QBE) of the Test Specimen, followed by an inspection to verify

TOSHIBA ENERGY SYSTEMS I SOWTIONS CORPOIIJITION Nuclear Energy Systems & Services Division

31/151


structural integrity of the affected Test System components,

• Performing a Seismic Test representative of a Safe Shutdown Earthquake (SSE) ,

followed by an inspection to verify structural integrity of the affected Test System

components,

• Performing an Operability Test to compare the system performance to baseline

performance.

Figure 5-3 of the ERS shows the Required Response Spectra (RRS) for the QBE and SSE.

The peak amplitudes of this figure are shown in Table 3-1. Based on the information

provided by [ r:roshiba _expected that the seismic test facility at [ J~ould not be

capable of performing a test according to the ERS spectra requirement. Toshiba

negotiated with [ Jto determine the achievable spectra for the Test Specimen Seismic

Qualification Test, which was performed to the table limits. Details of the results are

provided in section 6.

5.4. EMI/RFI Test

This test demonstrates the suitability of the Test Specimen Units to withstand exposure to

EMI/RFI and verifies that the Test Specimen does not emit more than acceptable levels of

EMI/RFI. The EMI/RFI levels shown in the ERS comply with the levels shown in RG

l.180Rl.

Nate that the test levels specified were not the same as those specified in the EPRI

TR-107330 requirements. Instead, the test levels used were obtained from RG1.180Rl,

which was issued in October 2003. Toshiba considered these new Regulatory Guide

values were to better reflect the current requirements of US utilities. Note that EPRI

TR-107330 was published in December 1996, prior to issuance of RG l .180Rl.

The EMI/RFI susceptibility and emissions withstand capability given in NRC RG l. l 80Rl

were tested using the following test methods from MIL-STD 461E:

1USH1DA ENERGY SYS11:MS a SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

32/151

Test Type

(a) Low-Frequency Conducted Susceptibility (Power):

(b) High-Frequency Conducted Susceptibility (Power):

(c) High-Frequency Conducted Susceptibility (Signal):

( d) Radiated Susceptibility, Magnetic Field:

( e) Radiated Susceptibility, Electric Field:

(f) Low-Frequency Conducted Emissions:

(g) High-Frequency Conducted Emissions:

(h) Radiated Emissions, Magnetic Field:

(i) Radiated Emissions, Electric Field:


Test Method

CS101

CS114

CS114

CS115

CS116

RS101

RS103

CE101

CE102

RE101

RE102

5.4.1. Conducted Susceptibility (Power Leads)

5.4.1.1. Low-Frequency Conducted Susceptibility (Power Leads)

This test was performed on the input power leads of the AC power sources. The test was

performed according to MIL-STD-461E requirement CS101. The envelope is shown in

ERS Figure 5-4. The test was performed from 120 Hz to 150 kHz.

5.4.1.2. High-Frequency Conducted Susceptibility (Power Leads)

This test was performed on the input power leads to the AC power sources. The test was

performed according to MIL-STD-461E requirement CS114. The envelope is shown in

ERS Figure 5-5. The test is performed from 10 kHz to 30 MHz.

5.4.1.3. High-Frequency Conducted Susceptibility (Signal Leads)

This test was performed on all signal leads in accordance with MIL-STD-461E requirement

CS114. The envelope was set from 10 kHz to 30 MHz, and 91 dBµA.

TOSHIBA ENERGY SYSTEMS I SOLUTIONS CORPOIIIIFION Nuclear Energy Systems & Services Division

33/151


5.4.1.4. High-Frequency Conducted Susceptibility (Signal Leads - Impulse

Excitation)

This test was performed according to MIL-STD-461E requirement CS115. The operating

envelope was set to 2 amperes (A).

5.4.1.5. High-Frequency Conducted Susceptibility (Signal Lead - Damped

Sinusoidal Transients)


envelope was set to 5 amperes (A). The test was performed from 10 kHz to 100 MHz.

5.4.2. Radiated Susceptibility

5.4.2.1. Radiated Susceptibility, Magnetic Field

This test was performed according to MIL-STD-461E requirement RS101. The Test

Specimen Units were installed in close proximity (< 1 m) to sources of large magnetic

fields (> 600 Alm). The frequency is set from 30 Hz to 100 kHz. The test level is shown

in ERS Figure 5-6.

5.4.2.2. Radiated Susceptibility, Electric Field

This test was performed according to MIL-STD-461E requirement RS103. The test

frequency was set from 30 MHz to 1 GHz, and the applied electric field level was 10 V/m

for all frequencies. The test was performed with both vertical and horizontal polarized

waves.

5.4.3. Conducted Emission

5.4.3.1. Low-Frequency Conducted Emissions

This test was performed on the power input leads, according to MIL-STD-461E

requirement CElOl. Envelope limits were the "envelope for less than lkVA AC" limits

shown in ERS Figure 5-7. Data is reported in dBµA. The frequency range was from 60

TOSHIBA ENERGY SYS1D1S I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

34/151


Hz to 10 kHz since the PRM consumes less than 1 KV A.

5.4.3.2. High-Frequency Conducted Emissions

This test was performed on the power input leads, according to MIL-STD-46IE

requirement CE102. The recommended emissions limits are shown in ERS Figure 5-8.

The test frequency was set from 10 kHz to 2 MHz. Data was reported in dBµ V.

5.4.4. Radiated Emission

5.4.4.1. Radiated Emissions, Magnetic Field

This test was performed according to MIL-STD-46IE requirement RElOl. The envelope

limits are shown in ERS Figure 5-9. The test frequency was set from 30 Hz to 100 kHz.

All measurements were performed at 7 cm, as specified by REI01.

5.4.4.2. Radiated Emissions, Electric Field

This test was performed according to MIL-STD-46IE requirement RE102. The

recommended emissions limits are shown in ERS Figure 5-10. The test frequency was set

from 2 MHz to 1 GHz. This test was performed with both vertical and horizontal

polarized waves.

5.5. Surge Withstand Capability Test

This test demonstrates the suitability of the Test Specimen Units as a safety-related device

for lightning induced electrical perturbations, using surge withstand capability test

protocols. As stated in ERS Section 5.5.4, IEC 61000-4-5 and IEC 61000-4-12 tests were

performed.

The Surge Withstand Capability Test was performed to assure that the Test Specimen Units

withstand the surge limits given in the ERS Section 5.5.4. The Surge Withstand

Capability Test levels shown in the ERS comply with RG l. l 80Rl.

The Surge Withstand Capability Test was performed in the same location as the EMIIRFI

test.


35/151


5.6. EFT/ 8 Test

This test demonstrates the suitability of the Test Specimen Units as a safety-related device

for electrical perturbations from relay coil collapse, using the EFT/B withstand capability

test. As stated in the ERS Section 5.5.5, IEC 61000-4-4 test was performed.

The EFT/B Test was performed to assure that the Test Specimen Units withstand the EFT/B

waveforms provided in ERS Section 5.5.5. The EFT/B Test levels shown in the ERS

comply with the levels shown in RG1.180Rl. The EFT/B Test was performed in the same

location as the EMI/RFI Test.

5.7. ESD Test

This test demonstrates the ability of the Test Specimen Units to withstand Electro Static

Discharge (ESD). IEC 61000-4-2 was performed.

The ESD Test was performed to assure that the Test Specimen withstands the ESD levels

given in ERS Section 5.5.6. The ESD Test levels comply with the levels shown in EPRI

TR-107330 Section 4.3.8. One restriction was added to the User's Guide for maintenance,

requiring use of grounded wrist straps when contacting the normally enclosed back of the

units.

The tests were performed according to EPRI TR-102323-Rl Appendix B Section 3.5. The

test was performed at 58% ( day 1) and 51 % ( day 2) of the ESD testing relative humidity,

which is within the required 30 to 60% relative humidity. The ESD Test was performed in

the same location as the EMI/RFI, Surge Withstand Capability and EFT/B Tests.

5.8. Class 1 E to Non-1 E Isolation Test

This test demonstrates the ability of the Test Specimen Units to provide electrical isolation

from the Class lE PRM to Non-IE field connections. The testing performed to

TOSHIBA ENERGY SYSTEMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

36/151


demonstrate ERS Section 5.5.7 requirements demonstrates compliance to IEEE Std 384

(Reference (4)). The test levels shown in the ERS comply with the level shown in Section

4.6.4 ofEPRI TR-107330 and IEEE Std 384.

The isolation device prevents any short, ground, or open circuits or application of the

maximum credible voltage on the Non-Class lE side from degrading the operation of the

circuits on the Class 1 E side.

The Class lE to Non-lE Isolation Test was performed in the same physical location as the .

EMI/RFI, Surge Withstand Capability, EFT/Band ESD Tests. For the NRW-FPGA-Based

PRM System, the AO module is required to have a Non-lE to Class lE isolation capability.

A high voltage was applied to the Non-lE side of the AO module, and the test confirmed

that the safety-related functions which were performed in Class lE side were not affected

by this isolation test.

5.9. Performance Proof Test

In the Pre-Qualification Test (section 5.1), the acceptable operation and baseline

performance data of the Test Specimen Units were confirmed by conducting Operability

and Prudency Tests. In the Qualification Tests (Sections 5.2 to 5.8), operability and

performance of the Test Specimen under and after applying the environmental stressors

were confirmed.

At the Performance Proof Tests, the Operability and Prudency Tests were performed

repeated to confirm that the Test Specimen provided the required operability and

performance even after being exposed to the environmental stress factors of the complete

Qualification Test.

The Performance Proof Test was carried out as follows:

(1) System Set-up and Check-out Test (Test Procedure: FPG-TPRC-CSl-1001). This test verified proper assembly, integration, and operation of the assembled Test

TOSHIBA ENERGY SYS1EMS I SOLUTIONS CORPOIUO"ION Nuclear Energy Systems & Services Division

37/151


System for the Performance Proof Test. This test confirmed proper connection and

operation of the Test System peripherals including monitoring instruments, power

supplies, signal simulators, and communication links.

(2) Operability Test (Test Procedure: FPG-TPRC-CSl-1009). This test demonstrated

acceptable system operability at the end of the Qualification Test.

(3) Prudency Test (Test Procedure: FPG-TPRC-CSl-1010). This test demonstrated

acceptable system performance at the end of the Qualification Test.

5.10. Testing Conclusion

Successful completion of these tests demonstrates that there are no common cause

environmental stressors that could preclude operation, as long as the PRM is installed and

maintained in accordance with Toshiba instructions, in an environment that complies with

the assumptions made to generate the limits defined by the U.S. Nuclear Regulatory

Commission in RG l. l 80Rl.

TOSHIBA EJIBIGY SYS1EMS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

38/151


6. Test Data and Results

6.1. Baseline Performance of Test Specimen Units

Prior to the Environmental, Seismic, and EMC Tests, the Pre-Qualification Test described

in Section 5.1 was performed to confirm the baseline performance of the Test Specimen

Units. The Test Specimen Units passed all tests included in the Pre-Qualification Test,

and the baseline performance was established.

After the Environmental, Seismic, and EMC Tests, the Performance Proof Test described in

Section 5.9 was performed, and the test confirmed that the Test Specimen Units provided

the required operability and performance even after being exposed to aging and stress

factors of the complete Qualification Test. The Test Specimen Units passed all tests.

included in the Performance Proof Test, and the baseline performance was verified.


6.2.1. Summary of Environmental Test The Test Specimen Units were subjected to a radiation exposure, temperature and humidity

tests.

The Test Specimen Units passed the Radiation Exposure Test with no signs of physical or

functional degradation. The Test Specimen Units also passed the temperature and

humidity test. In the first test opportunity, the Test Specimen Units stopped functioning in

the high temperature and high humidity condition after incorrect operation of the chamber

resulted in condensed water on the chamber ceiling dripping into the powered Test

Specimen Units. By adding a condensation shield to the environmental chamber, a retest

was performed and the Test Specimen Units passed all temperature and humidity tests.


39/151


6.2.2. Data Evaluation

6.2.2.1. Radiation Exposure

The irradiation was performed at [ J'!Iigh Level

Radiation Effects Facility. For this irradiation, [ J~uries (Ci) 60Co was used, at the

exposure rate shown in the dosimetry data in Table 6.1.1

The Test Specimen Units were irradiated at a gamma dose rate of 4.27 Gy-air/hr for 3 hours

for a total integrated dose of 12.81 Gy-air. Due to the size of the Test Specimen Units, the

irradiation was conducted on half of the units at a time. All the Test Specimen Units were

rotated 180 degrees at the midpoint of their radiation, to be exposed in a uniform dose.

At the end of the all Qualification Tests, the Performance Proof Test was performed, as

described, and all safety fiuictions were confirmed to be within the required tolerance

provided in the ERS Section 4.1.2 post-exposure.

TOSHIBA ENERGY SYS1EMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

40/151


Table 6.1.1 Dosimetry test data

RADCAL INSTRUMENT MEASUREMENT FORM

- -

Meter Model No. 2025 SIN: .;t, () 3 Probe Model No.:'.'lnVJ,-Q,C. SIN: ct 5"J..O

CalibrationDate: 'i\ I-;:).. S'-OC. Calibrat:ionDate: Cl-~":;~()G,

Probe Correction Factor (PCF): 137Cs 60Co f0,()~'7 ,R/''R"..,d"'

Measured Exnosure or EX1Jomre Rate, in RoentJ;1ens lR oilR/1iour J L. 6. 2. 7. 3. 8. 4. 9. 5. 10. Aw:.- '-U •• ~ 'R/J....,.

Tamnera:ture; '8'3 "For !l ~ oc WF-32) 519-= •c1

Atmosnheric Pressure: a-<1.0 a in.Ha: '1 ~ q mm Hg (l mc:h = 25.4 mm)

Tomperature & Pressure Correction Factor (TPCF):

::).,B ~C+273°C 760mmH3 TPCF"" ws0 c X .:i .. ~ 9 rrunHg = l.oJ..f9

Total Co:rrectionFactor= IO,il~, vl,o'IC/:::- io ,':)::> (TPCFxPCF)

Actual Exnosure or Exoosure Rate. in R oi\R/hour 1

1. 6. 2, 7. 3. 8. 4. 9. 5_ 10. A\H;.: 4 il.'1 "lJ...~

-.. rads (µ-IP=) Rllfuroncc: Ccmber, 1996 (Pa~ 179 and Appendix F)~ I Gray= I 00 rad rads=o.sn-

µ,Ari Po1, R - .

Actual Dose or Dose Rnte. in rads ow , n, 1smour 1

I. 6. 2. 1. 3. 8. 4, 9. 5. 10. 0.. If a l.f;).'7 i..rtds/kh.

\e, ,.__ j),,~i . S1f¢llture: lJ - - ' - -, - <> Date: ~ V ('\ I '1J ~\li:)0

-

TOSHIBA ENERGY SYSlD1S I SOWTIONS CORPORID"ION Nuclear Energy Systems & Services Division

41/151

'

I


6.2.2.2. Temperature and Humidity Exposure

The Test Specimen Units were placed in a free-standing instrument rack and installed in the

temperature and humidity test chamber. For the Temperature and Humidity exposure,

specific test patterns shown in Table 6.1.2 were applied, repeating the pattern throughout

the test. The output data were monitored during the tests.

Table 6.1.2 Input and Expected Output Pattern Input Expected Output

LPRMCH 1 APRM/TPM'1> TPM (H) Set LPRMinput Loop FLOW FLOW Output APRM

Time Output Output point TPMHTrip Current Input Current (Computer) HHTrip

(min) (Computer) (Computer) (Computer) DO (microampere) (mA)

(mV) (mV) (mV)

(mV) Output

0-15 0 4 0 0 0 79.36 Not

!Not Occur'3l Occur'2>

15-30 200 14.24 64 128 128 147.2 Not Occur Not Occur

30-45 350 14.24 112 177.79 128 147.2 Occur2> Occur'3l

45-60 500 6.56 160 177.79 64 119.04 Occur Occur

Note: * 1) TPM Output will be delayed from APRM Output with the time constant of 6 seconds. *2) Status change of APRM HH will be made within about 40 ms after the change ofLPRM Signal. *3) Status change ofTPM H will be made within about 40 ms from the TPM Output change.

(1) First Test

APRMINOP

Trip DO

Not Occur

Not Occur

Not Occur

Not Occur

The Temperature and humidity profiles at the first exposure are shown in Figures 6.1.1 and

6.1.2.

The test started at 8:00 AM on Jul 28, 2006. The temperature and humidity were raised

gradually, and at 2:00 PM on July 28, 2006, the temperature and humidity reached the

expected values (140 degree-F and 95 %RH). The high-temperature and high-humidity

conditions were kept for about 96 hours.

During the high-temperature and high-humidity conditions, the Test Specimen Units

stopped functioning at 3:00 AM on Jul. 29, 2006. The trouble shooting performed at that

timing found that some modules included in the Test Specimen Units were broken. Toshiba

decided to interrupt the test and detailed cause investigation was performed. During the


42/151


investigation, Toshiba personnel found marks which indicated water drops from the ceiling

of the chamber were falling on the top face of the Test Specimen Units. Toshiba analyzed

the failed modules in Toshiba's laboratory, and found an electro-migration due to the water

dropped on the IC pins, as shown in Figure 6.1.3. This electro-migration caused a short

circuit between the IC pins and failures in the Test Specimen Units.

The test condition required was non-condensing environment and these results shows the

environmental condition was deviated from the required conditions. By the discussion

with[ Jroshiba determined to add a condensation shield, which prevents the water drop

from the ceiling of the environmental chamber from falling into the Test Specimen Units, as

shown in Figure 6.1.4 (b ).

The broken modules were removed and spare modules which were also subjected to the

radiation exposure were installed in the Test Specimen Units. After these corrective actions,

the second exposure test was started and completed.

160 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

140 ~--~------~-------------------

120

100

2006/7/29 03:00

BO _________ StoJJ_ped functioning_ _ _______________ _

60 ---------------------------------------------

40 ---------------------------------------------

20 ---------------------------------------------

a~-----~~------~-----~ 2006/7/28 2006/7/30 2006/8/1 2006/8/3

Date

Figure 6.1.1 Temperature Profile in First Exposure Test

TOSHIBA ENERGY SYSTEMS I SOLUTIONS CORPORUION Nuclear Energy Systems & Services Division

43/151


1~ ----------------------------------------------·

90 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ·

~ ----------- -----------------------------------

5: 70 "' ~ z, '5 60 -~ :,: ~ 50 >

- - - - - - - - -2006/U29.. Ol:00 - - - _____ - - - - - - - - - - - - - - . ·-g -;; Stopped functioning "' 40

30

20

10

O'-------~-------~----------' 2006/7/28 2006/7/30 2006/8/1 2006/8/3

Date

Figure 6.1.2 Humidity Profile in First Exposure Test

TOSHIBA ENERGY SYS1EMS I SOLUTIONS CORPORIO'IOil Nuclear Energy Systems & Services Division

44/151


(a)

a,c

Figure 6.1.3 Results of the analysis of the IC chip.

(b)

Figure 6.1.4 Photographs of the inside of the environmental chamber

(a) For First Exposure

(b) For Second Exposure

TOSHIBA EJIEIIGY SYS1EMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

45/151

tl,C:


(2) Second Test (Retest)

The Temperature and humidity profiles for the second exposure are shown in Figures 6.1.5 and 6.1.6.

At 1 : 00 PM on Oct. 1 7, 2006, the test started. The temperature and humidity were raised

gradually, and at 5:00 PM on Oct 17, 2006, the temperature and humidity reached the

expected values, 140 degrees F and 95 %RH). The high-temperature and high-humidity

conditions were maintained for about 90 hours.

After the 48 hours of exposure to high-temperature and high humidity condition, the

Operability and Prudency Tests were performed and the Test Specimen Units passed the

Operability and Prudency Tests under the following conditions.

• AC Power Supply: 81V, Frequency: 51Hz

• AC Power Supply: 81 V, Frequency: 70Hz



After the high-temperature and high-humidity conditions, the temperature was lowered

gradually, and at 3:00 PM on Oct. 21, 2006, the temperature reached the expected value, 35

degrees F. The low temperature conditions were kept for about 67 hours. During this

period, the specified relative humidity could not be achieved. The low temperature test was

performed independent of the low humidity test. After 8 hours of low temperature

conditions, Operability and Prudency Tests were performed and the Test Specimen Units

passed the Operability and Prudency Tests. The tests that require manual operation of Test

Specimen switches and jumpers were skipped.

After the low-temperature conditions, the humidity was lowered gradually and at 11 :00 PM

on Oct. 24, 2006, the humidity reached the expected value, below 10 %RH. The low

humidity conditions were kept for about 16 hours. After the first 8 hours of low humidity

conditions, Operability and Prudency Tests were performed and Test Specimen Units

YOSHIDA ENERGY sYS1EMS I SOLUTIONS CORPORUION Nuclear Energy Systems & Services Division

46/151


passed the Operability and Prudency Tests. The tests require manual operation of Test

Specimen switches and jumpers were skipped.

After the low-humidity conditions, the temperature and humidity were moved to ambient

conditions and the Test Specimen Units passed the Operability Tests under the normal

condition.

The period of high temperature and high humidity, low temperature, and low humidity

conditions satisfied the required length shown in Figure 5-2 of the ERS, and the Test

Specimen Units performed correctly as shown in Table 6.1.3.

At the end of the all Qualification Tests, the Performance Proof Test was performed, as

described in Section 6.1, and all safety functions were confirmed that they were within the

required tolerance provided in ERS Section 4.1.2 after the Test Specimen Units was

exposed to the abnormal environmental conditions.

Table 6.1.3 Results of Temperature and Humidity Test

Condition Required Period of Actual Period of Performance of Test

Condition Condition Specimen

High Temperature 48 hours minimum 90 hours Performed correctly

and High Humidity

Low Temperature 8 hours minimum 67 hours Performed correctly

Low Humidity 8 hours minimum 16 hours Performed correctly

The PRM systems were qualified as follows, based on EPRl TR-107330 Figure 4-4 and

Section 4.3.6:

a. High Temperature and Humidity: 140 °F and 95% relative humidity, which

meets EPRl TR-107330 Section 4.3.6 and Figure 4-4 requirements

(Toshiba notes that adding 5% margin to the relative humidity would most

likely induce condensation, which is not included in Toshiba's

qualification envelope).

TOSHIBA ENERGY SYS11:MS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

47/151


b. Low Temperature and Humidity: 35 °F and 10% relative humidity, which

meets EPRI TR-107330 Section 4.3.6 requirements (Figure 4-4

requirements for humidity could not be met in this chamber, even with

relaxation for non-simultaneous temperature and humidity, and Toshiba

notes that the OPRM is constructed of similar components and had no

issues at 40 °F and 5% relative humidity which could be achieved in the

environmental test chamber used for testing the OPRM).

1~ -------------------------------------------------

1 Oct. 21 3:00PM Oct. 24 10:00AM I

140 - - - - - - c-:-=--=--~~~--=--=-::i· I I I i r--1

90 hours · i i . ·i 67hours i

1W ------~--------------J-~----~~--------------j j I ! i i I ! · · I I

100 ------~--------------~1-----------j --------------1 I· · i i ! I

i i ! ! i ----------- I~ ! ---- ---------j i ! !

80

· · I I 60 - - - - - - I - - - - - - - - - - - - - - I 1 - - - - - - - - - - -j - - - - - - - - - - - - - -

I I· . i i ! ! i i ! I

~ ------r--------------1 1--------------------------i i.

20 - -Oct_ l7_5;0Ql?M- - - - -Oct_2J _Jj :ODAM - - - - - - - - - - - - - - - - - - - - - - -

0 '------'-----'-----'-------'--------'------'

2006/10/16 2006/10/18 2006/10/20 2006/10/22 2006/10/24 2006/10/26 2006/10/28

Date

Figure 6.1.5 Temperature Profile in Second Exposure Test


48/151


1W ------------------------------------------------

I

100 -----+--------------1-1

Oct. 24 11 :OOPM I

- - - - - - - - _i_ --Oct.-25 .J;OOP-M - -I i j

I ! I . I • w --------------------~ ---------~----------

! ! 16ihours I i_j 90 hours

e+-------+'11 I · I . I

w -----~--------------J--------------~-j _________ _ I . I

i i I i i i ! i

40 i i I i ·--------------1------------ -r-,----------

• I • I . I i I i

I j I j~~-W --- -~--------------i------------ -~-i ---------

Oct. 17 5:00PM Oct. 21 11 :OOAM 1 • • I

o~--~----'-----~--~---~--~ 2006/10/16 2006/10/18 2006/10/20 2006/10/22 2006/10/24 2006/10/26 2006/10/28

Date

Figure 6.1.6 Humidity Profile in Second Exposure Test

6.3. Seismic Test

6.3.1. Summary of Seismic Test

In this test, the maximum level of acceleration in the SSE was limited to about 10 g, due to

the limitation in [ J~ibration table. Other than this deviation, the tests successfully

completed with no signs of physical or functional degradation of the Test Specimen Units.

Accelerometers are attached to the text fixture, the Test Specimen Units (LPRM,

LPRM/APRM, and FLOW), the power line panel, and the test table. Appendix A

provides the Seismic Tests results.

TOSHIBA ENERGY SYS1EMS I SOWTIONS CORPOIIID"ION Nuclear Energy Systems & Services Division

49/151



(1) Resonance Search

A low-level, approximately 0.2 g, single-axis sine sweep was performed in each of the three

orthogonal axes to search for any major resonance of the Test Specimen Units in a defined

frequency band. The sweep was performed at a sweep rate of one octave per minute.

Figures A.1.1 through A.1.15 show the results for the resonance search along vertical axis.

Figures A.1.1, A.1.6, and A.1.11 are the spectra of the test fixtures.

Toshiba performed resonance searches in accordance with IEEE Std. 344-1987. Toshiba

understands that the seismic tests based on IEEE Std. 344-1987 also satisfy IEEE

Std. 344-2004 because the requirements for seismic tests in these versions are essentially

the same. Section 7.1.4.1 of IEEE Std. 344-1987 (and Section 8.1.4.1 of IEEE Std.

344-2004) recommends, " ... that the resonance search be carried beyond 33 Hz, for

example, to 50 Hz, or to the RRS cutoff frequency, whichever is higher, to obtain data on

equipment dynamic characteristics that may be valuable to justify qualification for other

dynamic loads." The required response spectrum used in the testing has a seismic cutoff

frequency of about 40 Hz. Furthermore, since the neutron monitoring system equipment

described in the L TR is installed near the control room (versus the reactor building), there

are no other higher frequency dynamic loads of interest. Accordingly, Toshiba is only

concerned with resonances below 50 Hz: Resonance search data was gathered up to 100 Hz

based on the test facility standard practice and equipment capabilities.

Three accelerometers for three orthogonai axes were located at the Test table for the

acceleration control. Fifteen accelerometers were located for the response of the EDT

acceleration. Three for front-back, side to side and vertical at the following five locations:

1) the top right comer of the test fixture (EDT were mounted),

2) the right side top center of FLOW Unit chassis,

3) the power module mounting plate,

4) the right side top center ofLPRM/APRM Unit chassis,

5) the right side top center ofLPRM Unit chassis

Note) Right/left in above description means right/left wheri a person faces the front panel of


50/151


the FLOW, LPRM/APRM, and LPRM Unit

No resonances are identified below 50 Hz on the transmissibility plots. Several resonant

peaks are identified above 50 Hz. As discussed above, resonances above the 50 Hz cutoff

frequency are not considered consequential. The acceptable seismic test results confirm this

conclusion.

Resonant peaks are identified in the transmissibility plots at about 75 Hz in the side-to-side

(SS) direction and at about 95 Hz in the front-to-back (FB) direction. The results of the

transmissibility plots of the test specimens (the Flow unit, the LPRM/APRM unit, and the

LPRM unit) can be compared to the transmissibility plot of the test fixture. This

comparison shows that the test specimen responses are essentially the same as the test

fixture response. Any resonant peaks in the fixture response are mirrored in the test

specimen response. Therefore, the test specimens are moving with the fixture and any

resonant peaks are a result of the test fixture and not the test specimens. The resonant peaks

are sufficiently high and outside the frequency range of interest. Furthermore, examination

of the survey accelerometer response during the seismic tests show that no filtering of test

input occurred below the test facility standard practice 100 Hz frequency limit.

Thus, Toshiba evaluates the Test Specimen Units and the power line panel do not show

major resonan~e.

(2) Random Multifrequency Tests (5 OBEs and 1 SSE)

The Test Specimens were subjected to 30 second duration triaxial multifrequency random

motion, which was amplitude-controlled in one-sixth octave bandwidth spaced one-sixth

octave apart over the frequency range of 1 to 100 Hz. These simultaneous, but

independent random signals were used as the excitation to produce phase-incoherent

motions in the vertical and two horizontal axes. The amplitude of each one-sixth octave

bandwidth was independently adjusted in each of the three axes until the Test Response

Spectra (TRS) enveloped the Required Response Spectra (RRS). The resulting table

motion was analyzed by a response spectrum analyzer and plotted at one-sixth octave

intervals over the frequency range of 1 to 1 OOHz.

MSHIBA ENERGY SYSIEMS I SOWTIONS CORPORMION Nuclear Energy Systems & Services Division

51/151


The Test Specimen was subjected to five Operating Basis Earthquake (OBE) Tests and one

Safe Shutdown Earthquake (SSE). The required peak amplitude of the SSE should be 14

g according to ERS Figure 5-3. · Due to [ J~eismic table limits, the peak amplitude of

SSE was approximately 10 g.

Figures in sections A.2.1 to A.2.5 show the TRS for OBE tests and Figures in Section A2.6

show Test Response Spectra for the SSE test. Figures A.2.6.4 to A.2.6.6 show the

coherency plot of the SSE.

Toshiba planned to conduct the seismic test with the RRS provided in Figure 4-5 of EPRI

TR-107330 dated October 1997. The TRS listed in figures in Appendix A.2 of the

Qualification Test Summary Report were achievable. Toshiba considers that exceedances

below about 3.5 Hz are generally acceptable based on IEEE Std. 344 2004 Section

8.6.3. lG) since there are clearly no resonances below 5 Hz. Toshiba evaluated the higher

frequency area. Toshiba found that Figure 4-5 of a later version of EPRI TR-107330 is

slightly different from Figure 4-5 in the original October 1997 version which is the basis

for the current Toshiba RRS. Toshiba evaluated the difference. The later version (available

from the EPRI website) provides Figure 4-5 with a narrow peak spectral band. Specifically,

the 5% damped SSE response spectrum control points of Figure 4-5 of the later version of

EPRI TR-107330 are (1 Hz, 0.42 g); (4.5 Hz, 14 g); (16 Hz, 14 g); (33 Hz, 6.13 g); and

(100 Hz, 6.13 g). The original version of Figure 4-5 includes a broader frequency.

Specifically, the 5 % damped SSE response spectrum break points of this version of Figure

4-5 are (0.5 Hz, 0.1 g); (1 Hz, 0.8 g); (3 Hz, 14 g); (33 Hz, 14 g); ( 40 Hz, 7 g); and (1 OOHz,

7 g). The discussion here refers to the version of EPRI TR-107330 Figure 4-5 of the later

version of EPRI TR-107330 as the "narrow" spectrum, and the other version of EPRI

TR-107330 Figure 4-5 as the "broad" spectrum.

Because of test table limitation of 9.8 g, Toshiba has had to take exception to the EPRI

TR-107330 requirement of 14 gin the PRM testing. The PRM testing was conducted at a

laboratory where the table could not satisfy the EPRI TR-107330 peak spectral limits.

Specifically, the table could only satisfy a peak spectral demand of 9.8 g. PRM test results

show that the "narrow" spectrum demand is satisfied with the following exceptions.

The 14 g peak in the narrow spectrum was above the table capacity. The table capacity

MSHIBA ENERGY SYSTEMS I SOLUTIONS CORPORIO"IOII Nuclear Energy Systems & Services Division

52/1!:il


produced a peak that exceeded 9.8 g.

Exceedances in the frequency lower than 3.5 Hz are acceptable based on Clause 8.6.3.lG) of IEEE Std. 344-2004 since there are clearly no resonances below 5 Hz.

An additional exception to the "broad" EPRI TR-107330 spectrum demand would have to be taken for the exceedance at the peak above 30 Hz.

Figure 6.3.1 shows the qualified SSE response of the PRM seismic test.

12

I I

I I 10

/ , J \

/ I

I .,

\ J ~ 8 a 0

I \ :;3 c:! M

I I I I I I

<I) ...... G <I) i:.>

I

I ~

I I

,1

I I I I

I I I / I

I I/ -Qualified SSE for Pfu\.f

I (l

0.1 10 100

Frequency (Hz)

Figure 6.3.1 Qualified SSE for PRM

During the vibration application period, the Test Specimen Units were powered and their

MSHIBA ENERGY SYSTEMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

53/151


representative signals (Analog Outputs and Digital Outputs) were monitored. The results

of the test confirmed that all signals were within the required tolerance during the vibration

application period.

Following the seismic testing, the performance of the Test Specimen was compared to the

baseline performance, measured during Pre-Qualification Test, to determine if the test

impacted the performance and operability of the Test Specimen. There was no deviation

from the baseline performance.

6.4. EMC Test

6.4.1. Summary of EMC Test

After the first series of EMC Tests (EMI/RFI, Surge Withstand Capability, EFT/B, ESD and

Class lE to Non lE Isolation), modifications of the Test Specimen Units were performed as

discussed in Section 2.4 of this report. The EMC tests were then repeated.

The EMC Test with modified modules was performed from October 18th 2007 to

December 5th 2007 as shown in Table 6.4.1. The Test Specimen Units passed all tests

except CE101 without any deviations from the requirements in Section 3.3. For CE101,

some mitigation is required for the Test Specimen Units as shown in Section 6.4.2.1 (2).

Appendix B shows the detailed test results.

For all EMC Tests, specific test patterns were applied in repetition. For this purpose,

system inputs were varied during the EMC Test as shown in Table 6.4.2. The pattern was

repeatedly applied.

During the susceptibility tests, the output data were continuously compared to the expected

values with the tolerance.

TOSHIBA ENERGY SYSTEMS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

54/151


Table 6.4.1 Compliance Matrix for EMC Test Test

Test ID Test Description Completed Compliance with Specification On

CE101 Conducted Emissions - Power 19 Oct. Complied with limited scope and/or Leads 60 Hz to 10 kHz 2007 condition (Mitigation needed)

CE102 Conducted Emissions - Power

7 Nov. 2007 Yes Leads, 10 kHz to 2MHz Low Frequency Conducted

CS101 Susceptibility Test at AC 5 Nov. 2007 Yes Power Leads High Frequency Conducted

29 Oct. CS114 Susceptibility Test at AC Power

2007 Yes

Leads and Signal Leads Conducted Susceptibility

31 Oct. CS115 (Signal Leads, Bulk cable

2007 Yes

injection, impulse excitation) Conducted Susceptibility

CS116 (Signal Leads, Damped 2 Nov. 2007 Yes sinusoidal transients)

RE101 Radiation Emissions, Magnetic

9 Nov. 2007 Yes Field

RE102 Radiated Emissions, Electric 12 Nov.

Yes Field 2007

RS101 Radiated Susceptibility, 24 Oct.

Yes MaQnetic Field 2007

RS103 Radiated Susceptibility, 30 Oct. Yes Electric Field 2007 (Note 1)

swc Surge Withstand Capability 27 Nov. Yes

2007 (Note 2)

EFT/B Electrical Fast TransienUBurst 28 Nov.

Yes 2007

ESD Electrical Discharge 26 Nov. Yes

2007 (Note 3) Class 1E

to Class 1 E to Non-1 E Isolation

05 Dec. Yes Non-1 E 2007

Isolation Note 1: Toshiba did not test for radiated susceptibility (RS 103) above 1 GHz for the PRM, and thus accepts that either a utility employing this equipment must preclude the use of cell phones and radios near this equipment or accept an open issue from the USNRC in the SER requiring an evaluation by the utility. Note 2: The application of one repetition each second is described in IEC 61000-4-12. However, the Test Lab's equipment could not operate this rapidly. This is only an issue in the application period and has no adverse effect on the equipment qualification envelope. Toshiba and the Test Lab cannot find the record of the coupling impedance value used 12 D or 30 D for the ring wave test Note 3: Some test points in the back panel of the Test Specimen Units showed susceptibilities, but recovered without degradation. These results complied with the requirements of the ESD Test.

TOSHIBA ENERGY SYS1EMS I SOLUTIONS CORPOIIIO'ION Nuclear Energy Systems & Services Division

55/151


Table 6.4.2 Input and Expected Output pattern Input Expected Output

LPRM Loop FLOW HNS HNS

Time Input Input 511/515 HNS 514/518 HNS 514/518 HNS512/5 HNS513/517

512/516 LPRM APRM 16FLOW FLOW

(sec) Current Current LPRM APRM

(µA) (mA) (V) (mV)

(V) (mV) (V) (V)

0 0.00 20.00 1.00 0.00 0.00 0.00 1.00 5.00

1 37.33 18.67 1.30 11.95 0.15 23.89 0.96 4.79

2 74.67 17.33 1.60 23.89 0.30 47.79 0.91 4.56

3 112.00 16.00 l.90 35.84 0.45 71.68 0.87 4.33

4 149.33 14.67 2.19 47.79 0.60 95.57 0.82 4.08

5 186.67 13.33 2.49 59.73 0.75 119.47 0.76 3.82

6 224.00 12.00 2.79 71.68 0.90 143.36 0.71 3.54

7 261.33 10.67 3.09 83.63 1.05 167.25 0.65 3.23

8 298.67 9.33 3.39 95.57 1.11 177.79 0.58 2.89

9 336.00 8.00 3.69 107.52 l.11 177.79 0.50 2.50

10 373.33 6.67 3.99 119.47 1.11 177.79 0.41 2.04

11 410.67 5.33 4.29 131.41 1.11 177.79 0.29 1.44

12 448.00 4.00 4.58 143.36 1.11 177.79 0.00 0.00

13 485.33 2.67 4.88 155.31 1.11 177.79 0.00 0.00

14 522.67 1.33 167.25 1.11 177.79 0.00 0.00 5.18

15 560.00 0.00 5.44 177.79 1.11 177.79 0.00 0.00

16 522.67 1.33 5.18 167.25 I.l l 177.79 0.00 0.00

17 485.33 2.67 4.88 155.31 1.11 177.79 0.00 0.00

18 448.00 4.00 4.58 143.36 1.11 177.79 0.00 0.00

19 410.67 5.33 4.29 131.41 I.11 177.79 0.29 1.44

20 373.33 6.67 119.47 1.11 177.79 0.41 2.04 3.99

21 336.00 8.00 107.52 1.11 177.79 · 0.50 2.50 3.69

22 298.67 9.33 95.57 1.11 177.79 0.58 2.89 3.39

23 261.33 10.67 3.09 83.63 1.05 167.25 0.65 3.23

24 224.00 12.00 2.79 71.68 0.90 143.36 0.71 3.54

25 186.67 13.33 2.49 59.73 0.75 119.47 0.76 3.82

26 149.33 14.67 2.19 47.79 0.60 95.57 0.82 4.08

27 112.00 16.00 1.90 35.84 0.45 71.68 0.87 4.33

28 74.67 17.33 1.60 23.89 0.30 47.79 0.91 4.56

29 37.33 18.67 1.30 11.95 0.15 23.89 0.96 4.79

30 0.00 20.00 1.00 0.00 0.00 0.00 1.00 5.00

* 1: After 2-3 cycles from the starting of pattern input

*2: 1: Trip, 0: Not Trip

*3: Threshold contains the hysteresis

APRM

High LPRM

High (%)

Trip"'2

0 0.00

0 9.33

0 18.67

0 28.00

0 37.33

0 46.67

0 56.00

1 65.33

1 74.67

1 84.00

1 93.33

1 102.67

1 112.00

1 121.33

1 130.67

1 138.90

l 130.67

l 121.33

I 112.00

1 102.67

1 93.33

I 84.00

l 74.67

I 65.33

0 56.00

0 46.67

0 37.33

0 28.00

0 18.67

0 9.33

0 0.00

Internal Value

APRM FLOW

(%) ("lo)

0.00 125.00

18.67 119.68

37.33 114.11

56.00 108.25

74.67 102.06

93.33 95.47

112.00 88.39

130.67 80.69

138.50 72.17

138.50 62.50

138.50 51.03

138.50 36.08

138.50 0.00

138.50 0.00

138.50 0.00

138.50 0.00

138.50 0.00

138.50 0.00

138.50 0.00

138.50 36.08

138.50 51.03

138.50 62.50

138.50 72.17

130.67 80.69

112.00 88.39

93.33 95.47

74.67 102.06

56.00 108.25

37.33 114.ll

18.67 119.68

0.00 125.00

TOSHIBA ENERGY SYSTEMS I SOWTIDNS CORPORATION Nuclear Energy Systems & Services Division

56/151

APRMHigh TPM

High (%tt

Threshold

68.26 120.00

59.99 120.00

56.22 120.00

56.18 120.00

59.26 120.00

64.94 120.00

72.78 120.00

82.43 120.00

91.78 118.75

99.56 118.75

106.05 118.75

111.46 118.75

115.97 118.75

119.72 118.75

122.85 118.75

125.46 118.75

127.63 118.75

129.44 118.75

130.95 118.75

132.21 118.75

133.26 118.75

134.13 118.75

134.86 118.75

134.16 118.75

130.47 118.75

124.28 120.00

116.01 120.00

106.01 120.00

94.56 120.00

81.91 120.00

68.26 120.00



6.4.2.1. EMI/RFI Emission Test

(1) Radiated Emissions, Magnetic Field

This test measured radiated magnetic field emissions in the frequency range 30 Hz to 100

kHz with the field applied 7 cm from the surface of test point, according to MIL-STD-461

requirements RE101. Table Bl summarized the test points and results. All emissions were

below the allowable level specified in Section 5.4.2.1. Figures B.1.1 to B.1.5 shows the

example of the emission data obtained.

(2) Radiated Emissions, Electric Field

Vertically and horizontally polarized ennss1ons were measured with antenna placed

one meter from the test boundary. A RF-survey was performed as a pre-scan to determine

that the measurement at th~ front of the Test Specimen would be the worst case. The data

documented in Appendix B Figures B2.1 and B2.2 show that the emissions were below the

allowable level specified in Section 5.4.2.2.

(3) Low Frequency Conducted Emissions

The test setup followed the guidance ofMIL-STD-461E requirement CE101. Table B.3.1

summarized the test points. Figures B.3.1 to B.3.9 are the Test plots. Table B3.2 to Table

B3.6 show the detailed test results between 60 Hz to 1 kHz.

For the CE 101 requirement, appropriate compensatory mitigation should be provided for

the NRW-FPGABased PRM Units. For example, Figure B.3.1 shows the emission from the

power leads. From 100 Hz to approximately 1200 Hz, the emission exceeded the limit

shown in RG l .180Rl. This emission results from waveform distortion from the AC to

DC converter included in the PRM Units. To suppress this emission, inserting a coil was

effective, as shown in Figure B.3.4 through B.3.9. If the suppression is not applied, the

distortion should be evaluated to ensure that the distortion will not affect any other

equipment connected to the same power train.


57/151


( 4) High Frequency Conducted Emissions

The test setup followed the guidance of MIL-STD-461E requirement CE102. Figures

B.4.1 to B.4.3 are the Test plots. Table B4 summarized the test points. All emissions

were below the allowable level specified in Section 5.4.3.2.

6.4.2.2. EMI/RFI Susceptibility Test

(1) Radiated Susceptibility, Magnetic Fields

The Test Specimen Units were tested for susceptibility to radiated magnetic fields in

accordance with MIL-STD-461E requirement RSlOl. The test level is shown in ERS

Section 5.5.3 Figure 5-6. The test frequency range was from 30 Hz to 100 kHz. The

radiated magnetic fields were applied to the test points shown in Table B5 and the Test

Specimen Units operated normally before, during, and after application of the radiated

magnetic field.

(2) Radiated Susceptibility, Electric Field

This test confirmed that the Test Specimen is not susceptible to the radiated electric fields.

The test applied an electric field at 10 volts/meter, with frequency ranging from 30 MHz to

1 GHz, as shown in ERS Section 5.5.3.

The radiated electric field was applied to the front panel of the Test Specimen Units rack

according to MIL-STD-461E requirement RS103. The Test Specimen Units operated

normally before, during, and after the application of the radiated electric field.

Note: Toshiba did not test for radiated susceptibility (RS103) above 1 GHz for the PRM, and thus accepts that

either a utility employing this equipment must preclude the use of cell phones and radios near this

equipment or accept an open issue from the USNRC in the SER requiring an evaluation by the utility.

(3) Low-Frequency Conducted Susceptibility Test at AC Power Leads

This test was performed on the input power cable No. 10 of the AC power sources. The

test was performed according to MIL-STD-461E requirement CSlOl. The envelope limits

are shown in ERS Figure 5-4. The test was performed from 120 Hz, which is the second

harmonic of Power Frequency (60 Hz) to 150 kHz.

TOSHIBA ENERGY SYSTEMS I SOWTIONS CORPORIIJION Nuclear Energy Systems & Services Division

58/151


The Test Specimen Units operated normally before, during, and after the testing.

(4) High-Frequency Conducted Susceptibility Test at AC Power Leads

This test was performed to the input power leads to the AC power sources. the test was

performed according to MIL-STD-461E requirement CS114. The envelope limits are

shown in ERS Figure 5-5. Test was performed from 10 kHz to 30 MHz. The test signals

were applied to the test points shown in Table B6.

The Test Specimen Units operated normally before, during, and after testing.

(5) High-Frequency Conducted Susceptibility (Signal Leads)

This test was performed on signal leads in accordance with MIL-STD-461E requirement

CSl 14. The envelope was set from 10 kHz to 30 MHz, and 91 dBµA. The test signals

were applied to the test points shown in Table B 7.


(6) Conducted Susceptibility (Signal Leads, Bulk cable injection, impulse excitation)


envelope is set to 2 amperes (A). The test signals were.applied to the test points shown in

Table B8.


(7) Conducted Susceptibility (Signal Leads, Damped sinusoidal transients)

This test was performed according to MIL-STD-461E req~irement CSl 16. The operating

envelope was set to SA. The test is performed from 10 kHz to 100 MHz. The test signals

were applied to the test points shown in Table B9.


TUSHIBA ENERGY SYSTEMS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

59/151


6.4.2.3. Surge Withstand Capability Test

In this test, surges were applied to the Test Specimen Units in accordance with IEC

61000-4-12 .(for Ring Wave) and IEC 61000-4-5 (for Combination Wave). Surges were

applied to the leads of power cable No. 10. The combinations of the power leads to which

the surges were applied were as follows:

Line and Neutral

Line and Ground

Neutral and Ground

[Line and Neutral] and Ground, only for Ring Wave*

*Note: IEC 61000-4-5 (for Combination Wave) does not require the test for "[Line

and Neutral] and Ground." Only Edition 1 (1995) of IEC 61000-4-12

(for Ring Wave) required the test for "[Line and Neutral] and Ground,"

while later Editions of the same standard do not..

The Ring Wave test signals had the following requirements:

Voltage:+/- 2kV

Pulse Shape: 1 OOkHz, 0.5 microsecond rise time, 10 microseconds pulse

width

Repetition at 1 per 5 second*

Number oftests: Five positive and five negative at the selected points

Phase:O degree, 90 degree and 270 degree

*Note: The application of 1 repetition each second is in IEC 61000-4-12.

However, [ J"~quipment could not operate this rapidly. This is only

the application period issue and this does not create any adverse effects

on the equipment qualification envelope.

The Combination Wave had the following requirements:

Voltage: +/- 2 kV

Pulse Shapes:

• Impulse of 1.2 microsecond(+/- 30 %) rise time, 50 microseconds

pulse width, open circuit, double exponential

• Impulse of 8 microseconds (+/- 20 %) rise time, 20 microseconds


60/151


pulse width, short circuit, double exponential

Repetition: 1 per minute

Number of tests: Five positive and five negative at the selected points

- Phase:O degree, 90 degree and 270 degree

The surges were applied to the test points shown in Tables B 10.1 and B 10.2. The Test

Specimen Units operated normally before, during, and after testing.

Toshiba and the Test Lab cannot find the record of the impedance value used. RG 1.180

Revision 1 does not specify the impedance, and references IEEE Std. C62.41-199 l. IEEE

Std. C62.41 specifies 12 Q for the Category B Location. Toshiba conducted the IEC

61000-4-12 test at Low Exposure for a Category B Location; therefore the impedance was

likely 12 0. A HAEFLEY PIM 110 was used for the surge test and the factory default

impedance is 12 n.

The test was intended to be performed at 12 0, but Toshiba and the Test Lab cannot

confirm the actual setting used. Test results show that the specimen passed the short

circuit test that was performed. This leaves two possibilities. First, the test was actually

performed at the 12 Q setting, and there is no issue. This is the default setting of the test

equipment and the most likely scenario. However, there is still a possibility that the test

was performed with 30 0. For this case, the test results are not confirmed against 12 Q

for Category B location test that brings more energy to the test specimen.

Toshiba considers that it should be assumed that 30 Q was applied for the test to take

conservative position for the appropriate evaluation in a situation where the impedance

value cannot be confirmed. Toshiba considers that the assumption of 30 Q is appropriate,

because the PRM is designed to be connected to the end of the power supply system in

nuclear power plants. Therefore, Toshiba assumes either impedance is workable, and that

the higher impedance would not impact the surge withstand capabilities of the PRM.

6.4.2.4. EFT/8 Test

In this test, EFT/B transients were applied to the Test Specimen Units in accordance with

IEC 61000-4-4 (Reference (8)). The EFT/B transient was applied to the leads of power

cable No. 10. The EFT/B was applied to the following cables, as follows:

TUSHIBA ENERGY SYS1EMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

61/151

Line

Neutral

Ground

Line, Neutral and Ground simultaneous


The specification for the EFT/B applied in this test was as follows:

Limits (Applied peak voltage): Voltage=+/- 2 kVp-p

Pulse Shape: Impulse of 5 nanoseconds(+/- 30 %) rise time, 50 nanoseconds(+/-

30 %) pulse width, double exponential

Repetition rate: 5 kHz(+/- lk Hz)

Burst duration: 15 ms(+/- 20 %)

Burst period: 300 ms(+/- 20 %)

- Test Signal Application Duration: Not less than 1 minute

The EFT/B transients were applied to the test points shown in Tables Bll. The Test

Specimen Units operated normally before, during, and after testing.

6.4.2.5. ESD Test

This test showed that the ESD features of the NRW-FPGA-Based PRM system conformed

to IEC 61000-4-2 and the ESD levels complied with the levels shown in Section 4.3.8 of

EPRI TR-107330 and EPRI TR-102323 Rev.I Appendix B Section 3.5 (+8kV for contact

discharge or + 15kV for air discharge). Detailed results are shown in Table B.12.

No temporary degradation or loss of function or performance at the ESD application were

shown when the ESD transients were applied to the front panels and the parts placed on

the front panels, which can all be touched by people during normal operation. In addition

no temporary degradation, or loss of function or performance occurred with ESD

transients applied to the side panels. Temporary degradation or recoverable loss of

function were identified when the ESD transients were applied to the rear panels, or the

parts placed on these panels, which will not be exposed to ESD during normal operation.

lOSHIBA ENERGY SYS1EMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

62/151


There is no reason for an operator to access the rear panels. Technicians accessing the rear

panels will do so under work order, with the equipment bypassed. The work order will

specify that grounded wrist straps are required. The back panels in the units are accessible

only when locked cabinet doors are opened. Thus, the back panels are not normally

exposed to ESD.

The cabinet in which the NRW-FPGA-Based PRM Units are installed should be placarded

as containing ESD sensitive equipment, and plant administrative procedures written to

limit access to the rear panels during normal plant operation. A notification that any

person who accesses the rear panels of NRW-FPGA-Based PRM Units shall wear an

anti-BSD wrist strap during normal plant operation should be added to the User's Manual.

6.4.2.6. Class 1 E to Non-1 E Isolation Test

The test levels applied were 600 VAC and 250 VDC at 25 amperes for 30 seconds.

These test level voltages were applied to the test points shown in Tables B 13 .1 and B 13 .2.

The Test Specimen Units were not affected by the voltages, and the modules were not

affected.

7. Conclusion

Table 7.1 summarizes the results of this testing. When the NRW-FPGA-Based PRM

System is applied to actual plants, the following limitation should be considered:

(1) In the Seismic Test, due to the limitation of the [ J~ibration table, the peak

amplitude of SSE was approximately 10 g. The seismic withstand capability of the

NRW-FPGA-Based PRM Units should be evaluated against the plant's maximum

requirements. Retest may be required if the plant SSE maximum requirements are not

enveloped by the testing.

TOSHIBA ENERGY SYS11:MS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

63/151


(2) For conducted emissions (CElOl), appropriate compensatory mitigation should be

provided for the NRW-FPGA-Based PRM Units. To suppress the low frequency

conducted emission, mitigations such as inserting a coil should be considered.

(3) The cabinet in which the NRW-FPGA-Based PRM Units were installed should be

placarded to limit access to the rear panels during normal plant operation and plant

administrative procedures written to limit access to the rear panels during normal plant

operation. A notification that any person . who accesses the rear panels of the

NRW-FPGA-Based PRM Units during the normal plant operation shall wear an anti-ESD

wrist strap should be added to the user's manual.

With the above considerations, the NRW-FPGA-Based PRM Units achieved the required

performance shown in the ERS Section 5 in accordance with the test requirements given in

the ERS Section 7.

TOSHIBA EJIERGY SYSTEMS I S0l.Ufl0NS CORPORATION Nuclear Energy Systems & Services Division

64/151


Table 7.1 Summary of Qualification Test

Test ERS Ref. Toshiba Test [ ]¥est Procedure

Results Para. Procedure Number Number

1.1 System Set-up Not Not applicable

and Check-out Test applicable FPG-TPRC-C51-0001

1. 1.2 Burn-in Test 7.2.1 B Not applicable Complied for

Pre- 1.3 System Set-up Not application specific

Qualification and Check-out Test applicable FPG-TPRC-C51-1001 Not applicable requirements for the

PRM defined by the Test

7.2.2, ERS. 1.4 Operability Test

7.2.4 FPG-TPRC-C51-1009 Not applicable

1 .5 Prudency Test 7.2.3,

FPG-TPRC-C51-1010 Not applicable 7.2.4

2.2 Environmental 7.3.2.4,

Test (Radiation FPG-TPRC-C51-1002 FPG-VDN-C51-0200 Complied Exposure)

5.5.1

1•1 Test:Failed due to the problem of

2.4 Environmental 7.3.2.4, environmental

Test (Temperature FPG-TPRC-C51-1002 FPG-VDN-C51-0200 Chamber and Humidity)

5.5.1 2nd Test: Complied with EPRI TR-107330 with limited marain. Complied with limited scope and/or condition.

7.3.2.5, (due to the limitation of

2.6 Seismic Test FPG-TPRC-C51-1003 FPG-VDN-C51-0200 the [ ]Vibration 5.5.2

table, the peak amplitude of SSE was approximately 10 g.) Complied with limited scope and/or condition.

2. (Before this test, modifications of AO

Qualification and LPRM modules to Test enhance the noise

7.3.2.2, withstand capability 2.8 EMI/RFI Test

5.5.3 FPG-TPRC-C51-1004 FPG-VDN-C51-0201 were performed.

For CE101 test, choke coil should be added for mitigation. RS103 test was not conducted for the frequency above 1 GHz. See Note 1.)

2.9 Surge Withstand 7.3.2.7, FPG-TPRC- C51-1005 FPG-VDN-C51-0201

Complied Capability Test 5.5.4 (Note 2)

2.10 EFT/ B Test 7.3.2.9,

FPG-TPRC- C51-1006 FPG-VDN-C51-0201 Complied 5.5.5

2.11 ESD Test 7.3.2.10, FPG-TPRC-C51

FPG-VDN-C51-0201 Complied

5.5.6 -1007 (Note 3)

2.12 Class 1E to 7.3.2.8, FPG-TPRC-C51

Non-1 E Isolation FPG-VDN-C51-0201 Complied Test 5.5.7 -1008

TOSHIBA ENERGY SYSTEMS I SOLUTIONS CORPORIJIOil Nuclear Energy Systems & Services Division

65/151


[ r Test ERS Ref. Toshiba Test Test Procedure

Results Para. Procedure Number Number

Complied for 3.

7.2.2, application specific Performance 3.2 Operability Test

7.2.4 FPG-TPRC-C51-1009

Not applicable requirements for the

Proof Test PRM defined by the ERS.

Note 1: Toshiba did not test for radiated susceptibility (RSI03) above 1 GHz for the PRM, and thus accepts that either a utility employing this equipment must preclude the use of cell phones and radios near this equipment or accept an open issue from the USNRC in the SER requiring an evaluation by the utility. Note 2: The application of one repetition each second is described in IEC 61000-4-12. However, the Test Lab's equipment could not operate this rapidly. This is only an issue in the application period and has no adverse effect on the equipment qualification envelope. Toshiba and the Test Lab cannot find the record of the coupling impedance value used 12 nor 30 n for the ring wave test. Note 3: Some test points in the back panel of the Test Specimen Units showed susceptibilities, but recovered without degradation. These results complied with the requirement of the ESD Test.

TOSHIBA ENERGY SYS1B111S I SOLUTIONS CORPOIUD"ION Nuclear Energy Systems & Services Division

66/151


8. References, Definitions and Acronyms

8 .1 . References

(1) U.S. NRC Regulatory Guide RG-1.180 Revision 1

Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in

Safety-Related Instrumentation and Control Systems, revised October 2003. Chapters 3 and

4

(2) EPRI TR-102323-R2

Guidelines for Electromagnetic Interference Testing in Power Plant Equipment, Subsystems

and Equipment, November 2000

(3) EPRI TR-107330

Generic Requirements Specification for Qualifying a Com.m.ercially Available PLC for

Safety-Related Applications in Nuclear Power Plants, Final Report dated December 1996

(4) IEEE Std 384-1992

IEEE Standard Criteria for Independence of Class lE Equipment and Circuits

(5) IEEE Std 323-1983

Standard for Qualifying of Class lE Equipment for Nuclear Power Generating Stations

(6) MIL-STD-461E

Requirements for the Control of Electromagnetic Interference Characteristics of

Subsystems and Equipment

(7) IEC61000-4-2: 1995, Amendment 1 (1998), Amendment 2 (2000)

Electros.tatic discharge im.m.unity test

(8) IEC61000-4-4: 1995, Amendment 1 (2000), Amendment 2 (2001)

Electrical fast transient / burst im.m.unity test

(9) IEC61000-4-5: 1995, Amendment 1 (2000)

Surge im.m.unity test

(10) IEC61000-4-12: 1996

Oscillatory Waves Imm.unity Tests

(11) FPG-PLN-C51-0003

NRW-FPGA-Based PRM System. Qualification Project Qualification Plan, Rev.4

(12) FPG-PLN-C51-0005

TOSHIBA ENERGY SYS1EMS I SOWTIONS CORPOIUO'ION Nuclear Energy Systems & Services Division

67/151


NRW-FPGA-Based PRM System Qualification Project Master Test Plan, Rev.5

(13) FPG-RQS-C51-0001

NR W-FPGA-Based PRM System Qualification Project Equipment Requirement

Specification ofFPGA based Units, Rev.8

(14) FPG-DRT-C51-0001

NRW-FPGA-Based PRM System Qualification Project Preliminary Technical Evaluation

Report, Rev .10

(15) FPG-VDN-C51-0047 Schematic Diagrams (PRM System for Qualification), Rev.9

(16) FPG-VDN-C51-0200 Radiation Exposure, Environmental, and Seismic Qualification

Test Procedure for a Toshiba FPGA-Based PRM System, Rev.1

(17) FPG-VDN-C51-0201 EMI MIL-STD-461E Test Procedure on a new-FPGA-Based

PRM System, Rev.5

(18) FPG-TPRC-C51-0001 System Validation Test Procedure, Rev.2

(19) FPG-TPRC-C51-1001 System Set-Up and Check-out Test Procedure, Rev.6

(20) FPG-TPRC-C5 l-1002 Environmental Test Procedure, Rev.3

(21) FPG-TPRC-C51-1003 Seismic Test Procedure, Rev.3

(22) FPG-TPRC-C51-1004 EMI/RFI Test Procedure, Rev. 7

(23) FPG-TPRC-C51-1005 Surge Withstand Capability Test Procedure, Rev.4

(24) FPG-TPRC-C51-1006 EFT/B Test Procedure, Rev.4

(25) FPG-TPRC-C51-1007 ESD Test Procedure, Rev.5

(26) FPG-TPRC-C5 l-1008 Class lE to Non-IE Isolation Test Procedure, Rev.5

(27) FPG-TPRC-C51-1009 Operability Test Procedure, Rev.5

(28) FPG-TPRC-C51-1010 Prudency Test Procedure, Rev.5

(29) FPG-CFM-C51-0001 Master Configuration List, Rev.9

8.2. Definitions and Acronyms

Test System, Test Specimen, and Test Equipment. The Qualification Project performs

qualification of PRM Units installed in a Test System. Terms relating to the Test System

are d~fined as follows:

• Test System means a system consisting of Test Specimen and Test Equipment.

• Test Specimen means NRW-FPGA-Based PRM Units, and the cable between the


68/151

FPG-TRT-CS 1-0101 Rev.3

Units, to be tested for Qualification.

• Test Equipment means support equipment for the Qualification Test of the Test

Specimen such as the simulator, cable, and data logger.

APRM:

EFT/B:

ERS:

ESD:

FPGA:

LPRM:

MTP:

NED:

NRW-FPGA

OBE:

PRM:

PTER:

SSE:

Average Power Range Monitor

Electrically Fast Transients and Burst

Equipment Requirement Specification

Electro Static Discharge

Field Programmable Gate Array (a programmable logic device).

Local Power Range Monitor

Master Test Plan

Nuclear Energy Systems & Services Division

Non-Rewritable-FPGA

Operating Basis Earthquake

Power Range Monitor

Preliminary Technical Evaluation Report

Safe Shutdown Earthquake

lDSHIBA ENERGY SYS1EMS I SOWTIONS CORPOIUD"ION Nuclear Energy Systems & Services Division

69/151


APPENDIX A Test results data for Seismic Tests APPENDIX A Test results data for Seismic Tests ..... ~ .................................................... 70

A.1 Resonance Search ................................................................................................ 71

A.2 Random Multi Frequency Tests ........................................................................... 79

A2.1 lst OBE .......................................................................................................... 79

A 2.2 2nd OBE ....................................................................................................... 80

A 2.3 3rd OBE ........................................................................................................ 82

A 2.4 4th OBE ........................................................................................................ 83

A 2.5 5th OBE ...................................................................................................... ,. 85

A2.6 SSE ................................................................................................................ 87

fflSIIBA BIER&Y SYSll:MS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

70/151

A. 1 Resonance Search <Vertical>

jl8;55'22 . ()2,f'lov,2006

Lag l'<IXJUGl'icy(Ht)

VERTICAL RESONANCE SEARCH . i'OSHfBA ~ss'R,UNJ . .

· ~lneTe,;INam;,:.VERTRS:901.


.5VVSVCA

Figure A.1.1 Test Fixture Vertical Vibration Resonance Search Results

H(n Magnitude 1-911-3'

Ratio

08:55:25 02-Nov-2006

Log

VERHCAL RESONANCESEARCH TOSHIBA 53298 F!UN 1

Sina Tes! Namo: VEATA:S.001

10 100

Frequency (fll)

6VVSVCA

Figure A.1.2 Flow Unit Vertical Vibration Resonance Search Results

mSHIBA BtER&Y SYSTEMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

71/151

H(~ Magnllude 1-1211·3

log

Ratio

Sweep Numbe<: 1.00 Sweep Rale: V•rlab'.e

10 · Comarosslcin: Variable'


Remaining Tlmo: 000:00:00 Tes! Range: 1.000, 10.0.000 Hz · PoinlS Per s,....,p: 1000

· ···· '"' , ........ ····c· ···-··t·· -·-··· ······················· ·---·--········-·· 'f~::::1··-.... -~-=f.=: .. , ...... ~~--··---+----J-·-·"··---'-·-f-·-J--+-c +--··············-······················-·+----····-······+··-·······--·····'·····-·I--+-++-1

i i ·---·····

;--··--····----,·----- --- . 1·--+-·-+--10-•--+--------·1------

l ············ ·······i·•'""······ ·······-··········

............. [ ............................... .

l··-···l·-··1-···l-1--l--···---+---·--I·· ·

- i .. 1. ,..,../--.. ·-· , .. , .. - : __

,-· ... - ··-······---·---·- ··-- ·~'----- --·--········ ··- I·-- il····f··+···+·· ······ ··-··-------·--·· -···- ······-·-·-·'···· ... , ........... , ...•.. , ... , ... ; ..•

ACP: 1 · 0.1

011;55;.29 02·NOY·200S '

+--

·-- >····-+······•··-+····•- • -- - - - - -- ---- ---- -- -

·-- --···--··-·-·----- •-·-·----······+·-····- ··• , ·••· 1--1---1--+-·IH-------+---·--·--l--·· -+·--+---1---,---l·-+

0.01-.~-~----~-------~~------~--~-~!--~~--1

·Log

VERTICAL, RESONANCE SEARCH TOSHIBA 53298 RUN· 1 . . Sino Tosi Namo: VERTRS.oo(

10 100

· Frequency (Hz)

9VVSVCA

Figure A.1.3 Power Line Panel Vertical Resonance Search Results

ll(Q Magnitude · 1-1S'1-3

Log

Ratio

ACP: 1

08:55:40 02·i'IOY·2006

Sweep Number. 1.00 . Sweep Rate: Variatl.e

10 CompreSSOn: Vnrfabta-· ·

, I·-- :---- ; ··--·l·-···-i··-->··- •· ,- ---·· --··-·-····-·· · -,

.'-.

L .. --- r

+··-+--1-1--c--,,,. -·-·-······---·+.

! , .. . .. .. -··-·-··--····! ·--·-·--···-·, ·- -·. ,_ ..... ·-··-·· ··~-· -··-·--···-· -·· - .:,

-··-- -·-·· -- !-· ------~--->---!---+--+-~-•-+-------,-

.. ·-··--·-·--···- . ····-·--·-·· ·- --- ----··•·--·<·······-+--·•·-··-•

'

""'""""'"' '"'~' 000:00:00 Pomts p,ii s,!;:11~.000 Hz

-

............ , ............... , ................ .

' !J,,-/'

·····-··

•········--···•··--•·-- --i- ~:-1

i !-f

··1·········-----+·--··-·--1'--- ······i··--·+······-1·····1 ···+·····+····1-···················-··-··--·+-················· ~-····-··--·- •-··-····-···· ····----··1···--·~:-1=~~:!=~

rr--O.Ot-L--,-----'-------------''--.,_ ............. _._ ____ _,_ __ ..__ ___ ...... __.___,__,_-'-1

1

log

VERTICAi. RESONANCE SEARCH iOSHIBA 5321l8 RUN 1 . .Slno Tosi N.Imo: VERTRS.001.

.JO 100

Frequency (Hz)

12VVSVCA.

Figure A.1.4 LPRM/ APRM Unit Vertical Resonance Search Results

lUSIIBA BIER6Y SYSTEIIS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

72/151

H(Q Mogniluda 1-111'1·3

t.00 Elaps«I Tm\o: 000:04:44 Filter Typo: Proportiopat Fundamental: 80.000 .%. BO RMS: 39B. mcvc

+ ·i :··-·-·"',··--· ··- .--··!-·- ·······-··· ···-······--,··-··


Remaining Time; 000:00:00 Tost Range:: 1.000; 100.000 Hz POOlts Por,Sweop: 1000 .

::.1 .. ... -i -····· ............ '""'T'"

•--·-----·---•----~--- L ... -----,-- ------ i i ·-------·= ·1---· ---- ·--- ............... + ..... ~ ... -+---- _,,_,, _____ -;_ .... _ --··" .... , ......

i

L.

log

ACP: 1·

09:S!i:45 ONlov-200&

,.,

: -,---: j +.----,-t--t--+----- ---,-------

I i .!

-!--------+---··!·- -- , ---- --•-s----1-t--+,-----------•---,----,------t-·-t---t---+---+-l -t---·--------'---+--+---r---,~,--,--·-r-+--·---····.---··-··•~ ·-·--,~· -·~- ···· .... ,.1,., .... ··-,····· ,·······1--·

log

VERTICAL RESONANCE SEARCH TOSHiBA 53290 RUii\

Sine Test Name: VEl'ITRS.001•

Frequency (l-lz)

to 100

15VVSVCI\

Figure A.1.5 LPRM Unit Vertical Resonance Search Results

<North to South>

H(I) Magnituda 1-511-2

log

Ratro

ACP: 1

09:12:10 02-Nov-2006

Sweep Number: 1.00 Swoop Rote: Variable

100. Ccmpcession~Va.dablo

1Q

, ........ .. --

----•-----

Elapsed ;-;,,,v ... v.-.

1 ;•,;,;,;,:..,,, •• ii'n IWJ %, BB RMS: 398. mcvc

, ---

' '

+·i • - ---· 1 --!-··+··

t \

· · ···-li 1~· ·~

L,_-_·_ -----l---,-----t---------• -r---t---·>--+-;- .. --.. ---~--1/\"' .... ·i··-·-··"f"""·-;---,--·-t--t--+--+----·- --·+-----;---;c--t---+-t--+--1

0.1 '------'----'----'---'----'---'--'--'-'-----'----'-_..--'---'---'--'-'--I; 10 100

LCQ • Fre'ltlency (Hz)

SIDE/SIDE RESONANCE SEARCH 2SSVSSSHCA

TOSHIBA 53298 RUN 2 ·

Sine Test Namir. NSAS.001

Figure A.1.6 Test Fixture Horizontal (North to South) Resonance Search Results

TOSIIBA BIER6Y SYSltllS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

73/151

H(~ Magnitude H\11·2

Ratio

ACP: l

09:12:14 02-Nov-2000

Loa·

SIDE/SIDE RESONANCE SEARCH TOsliiBA 53298 RUN 2 · .

Sina Tes! Name: NSRS.001


10 .100

5SSVSSSHCA

FigureA.1.7 Flow Unit Horizontal (North to South) Resonance Search

H{ij Magnillldo Hl/1-2

Log

Ralio

ACP: 1

EJap$f)d Time: OOO:o4:44 Alter Type: Plt'l)(!tllonal

0.01.. '"'. ----'----'---'----"'-----~'-'-__._ ___ ___. __ _..._-'---'--"---'--'....-"-' ·1 10 100

Log FroQ1J!!ncy.(Hz)

SIDE/SIDE RESONANCE SEARCH TOSH!SA 53298 RUN 2 . .

&SSVSSSHCA

Sin• Test Nome, NSRS.OOt ·

FigureA.1.8 Power Line Panel Horizontal (North to South) Resonance Search Results

1DSIIU BIER6Y SYSTEIIS I SOLUTIONS CORPORATHIN Nuclear Energy Systems & Services Division

74/151

H(Q Magnitude 1-1411·2

tog,

ACP: 1

09:12:21, 02•NoY•2000

S10£1S!OE RESONANCE SEARCfl ' TOSHIBA 53298 RUN 2· · .

Sine Test Na""1: NSRS.001.


10 100 Frequency (Hz!

11SSVSSSHCA.

FigureA.1.9 LPRM/APRM Unit Horizontal (North to South) Resonance Search Results

H(Q Magnitude 1-1711·2

log

Ratio

ACl'i I

10 .100 Frequency {Hz)

S10EISIOE RESONANCE SfARCli 14SSVSSSHCA

TOSHIBA S3200 RUN 2 . .

Sine Test Name: NSRS.001

Figure A.1.10 LPRM Unit Horizontal (North to South) Resonance Search Results

1USIIBA BIER&Y SYSTEMS I SOLUTIONS CDRP111A11DN Nuclear Energy Systems & Services Division

75/151

<East to West>

H(f) Magnitude 1-4/M

Leg

ACP: 1

09:19:64 OHl<W-200&

Log Frequency (Hz) .

FRONT/BACK RESONANCE SEARCH TOSHIBA 53200 AUN 3 .Sino Tosi Namll: EWRS.001 ·


10 100

1FBVSFBHCA

Figure A.1.11 Test Fixture Horizontal (East to West) Resonance Search Results

H(f) Magnl!ude Filf.t

log

ACP; 1

09:19:58 02-Nav-2006

Log Fraqoonc:y (Hz)

. FAONTlllACK RESONANCl',SEARCH TOSHIBA 5329S RUN ;I SlnaTestl-lame; EWFIS.091 ·

10 100

4FB.VSFJ3HCA

Figure A.1.12 Flow Unit Horizontal (East to West) Resonance Search Results

TOSIIBA BIER&Y SVUEIIIS I SOLUTIONS CORPCIIATKIH Nuclear Energy Systems & Services Division

76/151

H(I), Magriluda HM-l

Log

Ratio

ACP: 1

09:20:06 02-~ov-2006

O.L,:.::.... . .1.... l: .... ,-.. , __ _

- ---------+---l--+--f--i--t,-»-i .. ·-l-


-·-····-'--·-·f--..... -,----·-+-+-+--··-'-• ·-- ~---·~~ \--· · ··········· ······ :··-···t··-·····r--·-t-··- ....

·---····-·········--···--···"·•

-- t ·---·- --------·t--i--i-+-i--1

........... -------+--·-f-----·f----+-·l-i-l··-1----------,:-----t-- -:---t--t--1--+·+-I . ---·-·------·1--·---, ........ -;------t-··t--t-·!--t-!--·---····· - ------,--·-------;---------,-------,-----,-. ,-., •• , .•. ,

!

om .. .._ ___ ..... -----~---~~---~----------. !·

Log Frequency (Hz)

FRONT/BACK RESONANCE SEARCH T0SHIBA53298RUN3 .

Sino Tesi Name-: EWflS.OOt'

10 100

7FBVSFBHCA

FigureA.1.13 Power Line Panel Horizontal (East to West) Resonance Search Results

H(U Magnitude 1-1311-1

Log

Ratio

ACP: 1

09:20:16 02•NOV•2006

S\\!oop l'lumoor: 1.00 Sweep Rate: Vanat!e

8apsed Time: 000:04:44 Filler Tl'Jl": Propaitiona!

100. Comcmssion: Vartable Fundumanial: 00-000 'l(,, BB RMS: 398. mc:yc

Ramai~il'l!l Time: 000;00;00 Test Range: 1.000, 100.000Hz Points Par SWOC!J! 1 COO

-. ... , ... _,_ ,-, __ __

, ___ ..... ......... , .... ,_

_, ___ ---·- ------+----.. +···--· •-----. i

i

-----, __ ;

i ! I I :

Leg Freqooncy (Hz)

FRONT/BACK RESONANCE SEARCH TOSHIBA 53298 RUii S

Sina Test Name: EWRS.001

····-· ---l --~-- -~· ' ·1 • •• +-+.-: .. i--

.... ,: .. ,- ; : ·=--v--·r-· t--·

L.-- ....

-

f -r-----+---+-----f--1

-~---------~----~'-i

10 100

10FB VS FB HCA

Figure A.1.14 LPRM/ APRM Unit Horizontal (East to West) Resonance Search Results

TOSIIBA BIER6Y fflTEIIS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

77/151

H(Q Magni1Uoo 1-16/M

Log

Ratio

ACP: 1

09:20:20 02·Nov-2006

Log Frequency (Hz)

FRONT/BACK RESONANCE SEARCH TOSHIBA Sl2B8 RUN 3

Sine Test Name: EY/RS.001


10 ,co

13FB VS FB HCA

Figure A.1.15 LPRM Unit Horizontal (East to West) Resonance Search Results

TOSIIBA BIER6Y SYSIEIIS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

78/151


A.2 Random Multi Frequency Tests

A2.1 1st QBE

Coo!ro4 Maxi-Max

log

Peak: 16.227 0.010

07:46:47.7 Frllrov032006

100

Testle\<Of: O.OOOdB Pulse: \ o1 t

·•····· ·-·······--··-··---- ··--

- ····-···----" -- .----

Ccntrol .f ZPA: 7.001 PulsnPo!.iri!y: +

Pulse Typc:lmpolt Roforenoo SAS Damping (%): 5.000

10_, ______ .. ·--· --- ..... •:

' ·',; -- ..

l----.--.. /,/-A'A-/--··,.-+----.-;--+-+--H+ij·r~n-n't'ro-1°]~ -~1------r----+-+-~-~-+-t

.~---~- -----+---+~i-+-+-t-+-+-----;---.. -·--+----+--t---t--1 .. ·,

. ------- .... ·---- ,--·--~-- .. •----+--+·-, .... , ..... _____ .. __ ......... - ... ~.-...... _ ........ , .... _ . .,. ... _.,. ___ ,_,_ ..... ,_L I O.t..~---~-~-~~~~~------~-~-~~~~~-'--'

10 100 Log freQUOrJC'f (Hz)·

TOSH<BA 53298 OB5 FBHCA(EW)

RUN#4'

MIMO Shocl< Test TOSHIBA_OBE.001

Figure A.2.1.1 TRS for 1st OBE for Horizontal Axis (East to West)

Log g

P"1k:

13.738

O.COB

07:46:47.7 Fri Nov 03 2006

Test Level: 0.000 dB PulS!l: 1 of f

C-Onficl 2 ZPA: 6.558 PulsoPolority:+

10 Log Frequency (Hz)

T0SH<8A 53200 OBE AUN/14

t.!IMO Shock Test TOSHIB!\__OBE.001

Pulse Type:lmport Reference . SAS Damping (%): 5.000

SSHCA(NS)

Figure A.2.1.2 TRS for 1st OBE for Horizontal Axis (North to South)

100

fflSIIU BIER6Y SVSll:IIS I SOLUTIONS CDRPORA1111N Nuclear Energy Systems & Services Division

79/151

Conlrol Maxl•Max

Log

Peale 19.859

0.010

07:46,47.7 Fri Nov(l(l2006

Control 3 zPA: • 7,408 Pulse Polari\r, +

:....... ·······i···--~· '····-·····-l·-·-···:-... ···i· .. ! i··· 11rnl l., } ;-/.............. ·--- '. ·r;:;n:..:c~-

I ! i

! -,--!•· ~--!-----·-··-··

,!


l'llloo Typc:lmp<1rt Rc!ornnco SRS Damping(%): 5.000

,--.-- - -··---- . - ; ... µJ.L., .....

:

...

-- ---, .. -

-1----.,---,--,_ ... H-~.

.................... ;,. ......................... 1--"•·l-··---i---+- I +-0.L '--------'---'----'---'---'---'---'--"-'-----'----'----'---'--"---'--'--"-'I

t 10 100 Log Frequency (Hz)

TOSHIBA 53298 QBE VOA

RUl'll!4 '

MIMO Shoekiest TOSHIBA_OBE.001

Figure A.2.1.3 TRS for 1st OBE for Vertical Axis

A2.2 2nd QBE

Con!rol Maxi-Max

Log g

Pea'<: 15.642

0.012-

00:11:2.ui FrfNov002006.

Test Level: 0.000 6ll 'Pulse: .1 of 1

·100·

.... .. ......... _

Conirm 1 ZPA! 7.150 Pulse Polarity: t

·------- -...... ,_ ____ .... _ .. _ ..... +------,--+ ·+ ' - : + <--~,;'fi,,, t\.ppi,P,(l

Pulse Typo:lmport Ro!ornnm SAS Damping (%): 5.000

,LI

-•--; • • I'

·--------r-; ___ -+-----,-----1--+--- 0---------~---'------+----~---+-l ! ! .)--t\_

10 .. ,_ ... ,

/

····f=:F , .. _,_

·.~_: __ !,:;: - : ... I .L

'

... , ; ;··1·----1·····----··------·· ..... ,............................ ................... • ·+

-+-----i .. -+ .. --~,---,--,-_,l .... _,_n_:o·-n·t-ro--1·1-c~·;:;,.,;~,;:,hu1";;~+----·i""""'" : , .......... .

- ----·----- ---1--1---,---+--l---'--.,--·~-----+---l---l---'~1--'--·•-'-1 : =----·---:-._-----·~==:=·=:=::::=:;::::;.::::-..:f--___ ---__ --.. _--_----... ;-... _ .• ~:=~=:--·.--·l'c-_-... 1.--.---· , .... l= ~-

Log Frequency (Hz)

TOSHIBA S32l)8 OBE FOHCA(EW).

RUN#S '

MIMO Shcc:k.Tesl: T0SHIBI\..08E:002

Figure A.2.2.1 TRS for 2nd OBE for Horizontal Axis (East to West)

fflSIIBA BIER&Y SYSTEIIS I SOLUTIONS CORPORA11DN N~clear Energy Systems & s~rvices Division

80/151

Control Maxi-Max

Log g

Peak: 13.722 0.009

OB:11:24.5 Fri Nert 03 2006 .

------ - -- --------------

Tc•1 LoV<ll: O.ODO dB Pulse:· 1 of 1

10_ -··

O.l

,,---

, __

TOSHIBA. 532.."8 QBE RUN#S

Ccntrtl 2 7PA: 6.671 Pulw P<llarity: +

i ' 10

Freqllsncy (Hz)

MIMO ShockTest TOSHlBA_OBE,002


Poise Type:fmport Relerence SAS Oampir.g (%): 5.000

-----

·-··· 1-.-·- .••. '·-

·-t---------+-----1----f·----,!--t---·I- -1~

100

SSI-ICA(NS)

Figure A.2.2.2 TRS for 2nd OBE for Horizontal Axis (North to South)

Conlrol 3· Mald·l,lax

L<Jg g

Peak: 19.666 0.011

08;11:24.5 Fri Nov 03 2000

Test Llwa~ O.OOD dB Pulse: I ol 1

C-0n!rol· 3 ZPA: 7.276 Pulse Polarity:+

. Pulse T\'Pe:lmpCl't Reference :SAS Damping(%): 5.000

100 r:::-::-:=======-;:==::::::::".'.j'.'.'.:==========-:--;:==:-::-========r=-===::-r-:=-=~::=i==;--:-==r;:i

10_

L

!.<Jg

TOSHIBA 53298 OBE RUN,5

Fwquoncy (Hz)

MIMO Shock Test: TOSHJBA...OBE.002

10

VCA

Figure A.2.2.3 TRS for 2nd OBE for Vertical Axis

100-

mSIIBA EIIER&Y SYSTEMS I SOLUTIONS CDRP111A11DN Nuclear Energy Systems & Services Division

81/151


A2.3 3rd OBE

Control · Maxi-Max

Peal<: 1&.237 0.012

Tostlo,al: 0.000<1!1 Pulse: 1 of l

Conlrlll 1 2PA: 6.970 Ptdso Polarity:+

Pulse Type:lmport Reference SAS Damping (%): 5.000

ioo:·f -::=:::::---==:::=:~==:::::=:E:=:'::::::=.=t==:=:T-=:::::E=.::~EI:i::cE:=~~'?::::F===:":'E'~F:::::::=E:::E:3=:ETJ f· .:.::::):: · ······· ··········· ,., ..•. :t:::::· ,···-· --, --.r :F··'·--- -.-·f=:J. ·

..... !../ i

, i i i I .. .. ···--:;-··· , .... '····r··ipp·i "i~ -..1 e1 1 ... I ·-···;---,A:<:m"l1,Aat ,~ ~ ,_.;u'um----·-- ---

' - • '-··. i : y I\,. --'---1--.J_.,,. __ __

10, ·:-~· .. ,- c:::.:..:::.::i ...................... •.. .. . ,,. '..· -- ... _ ·--~-,-

··---·-------·--:----~;;:.i-"' ' - . - .·.; ·----'i-l--l--~ -!-----------~-\,-,.-~·_ :__-_··.:..+0 .1·.·_·-----_--_ .. ___ ·····.·_-----/-1·/, :;,,-,,: ........ :.: .. .• • . . . '"'--···········-·····-··---··-'"' ··- ~==t r--- //' i , __ --J-i-Jr-·11--,,~;:-~1'-1-;t:;-;:;-+;;;'~ Control S1 1ectr11m

// i t ___ /,/. __ LL ---·-- _ __J_ ....

-·--+·- :___ ...i

= : -•--·--·····-···········---- r-··· 1... ..'. ... . 1-- --•-4-·..!--1----·-

i

i i

.J

! l 0.1_4,.; ___ __, __ _,___-"---'--'----'--'--'-...._-----'----

Leg

TOSHIBA 53298 OBE AUN~6

Fmquency (Hz)

MIMOShool<TestTOSHIBf\...OOE.003

10

FBHCA(EW)

I

! :

I

! l I

I ·1 !

I

I I 100

Figure A.2.3 .1 TRS for 3rd OBE for Horizontal Axis (East to West)

Test Lewi: O.OOO(IB P~lsa: 1 of 1

Control 2 ZPA: 6.533 Pulse Polarity: +

Pulse Type:lmport Reference SAS Damping (%): s.ooo

100 .. ,.f ===========;:'-::1::-:-:;::::;::+'===========:::;:-:===i Control 2 t,!axH.lax

Log g

Peak: 13.964 0.009

08:33:22.7 Fri Nov032006

Log

TOSHIBA 53298 OBE AllNUG

Frequency (Hz)

MIMO Shock Tosi: TOSHIBA.,.OBE.003

SSHCA(NS)

FigureA.2.3.2 TRS for 3rd OBE for Horizontal Axis (North to South)

1USIIBA BIER6Y SYSTEMS I SOLUTIONS CORPORA11DN Nuclear Energy Systems & Services Division

82/151

100


Control 3 MaiU-IMX

Peak: 20.528 0.011

08:33:22.7 Fri Nov 03 2006

Tool Level:· 0.000 dB Pulso; 1 of 1

10 ..

TOSHIBA 53298 QBE RUN~6

Conlrcl 3 ZPA: 7.690 Pulse Polari!y: +

10 Frequency (Hz)

MJMO Shock Test TOSHiBA...OBE.003

Pulse Type:lmport Reference SRS Damping (%): 5.000

VCA

Figure A.2.3.3 IRS for 3rd OBE for Vertical Axis

A2.4 4th OBE

Control 1 · Ma>!-MaX

Leg

~

Peak: 16:604 0.012

06:50:.21.3 Fn Nov os 2006

10

Tool Level: 0.000 dB Pulse: t of · 1

log

TOSHIBA 5329/J QBE RUNN7

Con1ro1 1 iPA: 6.687 Pulse Polarl!y: +

10 Frequency (Hz)

MIMO Shock Test TOSHIBA~OBE.004

Pulse Type:lmpOf\ Reference SAS Damping ("k); s.ooo

FBHCA(EW)

Figure A.2.4.1 IRS for 4th OBE for Horizontal Axis (East to West)

100

1USJIB1 DIER6Y SYSl"EIIIIS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

83/151

100

Conitol Maxi-I.tax

Log

9

Pon!<: 13.611 0.009

08:50:21.3 Frt Nov032006

Tes! Level: 0.000 d8 Pulse: 1 of 1

100·.

· Conlrof 2 2PA: 6.519 Pulse Polarity: +


l'\Jlse Type:lmport Reference SAS Damping (%): 5.000

• ---H• •,,.,,., .. _,•••-• •• '"'" ""' ,e-<- ,•• ••-•"o• '••••••••m

---f.-· --· _[. f-·"-'"·---f--------,·1'··----.j---·+-l--+··i .. ,-1 ..,.·.·-... ·.-_·,· __ ·_-_··.,.. =:==~=i= . '"-------·· .. ,------···+-··-····1-··

;, .... ·······!···!

10 , •

......................................

J. .. ....... , ....... .

· f----·--·· ···---i--·-+--1---f--+-+-+-+-·'-·--------·· i----+-·---1---i---+-+-l· •.

0.1. ,__ ___ _._ __ ~l _ _._ _______ .._~'------'----'-----'--'---'--'---"-'--t

Log

TOSHIBA 532ll8 OBE RUN/17

Frequency (Hz)

t.!IM0$hocl<Tooi: TOSHIBA...OBE.004

10 100

5SHCA(N$)

Figure A.2.4.2 TRS for 4th OBE for Horizontal Axis (North to South)

Cornrol Maxl•Max

L-09 g

Peak: 21.341 0.012

08:50:21.3 Fri Nov 03 2000

Control 3 ZPA: 8.049 Pulse Po!arity: +

I

i I ........ l .......

.. ·i---·,-··-

--~------+,···-----~---~--t--1---~-l-f-+---------I ; ....... •·

I

;

' I i

Purse Type:Jmport Reference SRS Damping (%): 5.000

I ....... .. ---i •.

!

.. ::::±. ·-:-' i

i I I \

... \· .

0.1. '----'-----'----------~----"'---....... ---'-----------------''---'---'---'-'--

TOSHIBA 53298 OBE RUN#7

frequen"l (Hz)

: Ml MO Shock Test TOSHIBI\..OBE.004

10

VCA

Figure A.2.4.3 TRS for 4th OBE for Vertical Axis

100

1USIIBA BIER&Y SYSTEMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

84/151


A2.5 5th QBE

Control ·1 Mald·Max

Log g

Peal<: 17.011

0.012

09:12:19.6 Fri tlov 03 2006

10.

Test L.e·rol: 0.000 dB .Pulse: 1.ol 1

Log

TOSHIBA 53298 OBE RUNiB

Ceo!rol 1 ZPA: G.891 Pulse Polarity: +

10

Frequency (Hz)

IJIMO Shock Test: TOSHl!lA_OBE.005

Pulse lype:llrport Reference SAS Camping (%): 5.000

FBHCA(EW)

Figure A.2.5 .1 TRS for 5th OBE for Horizontal Axis (East to West)

Test-Lewt. O.OOO.d3. .• Puts,J: 1-01 .1· !Oll,:·.1 ·:-:-==:r

10

Control 1 ZPk 6ES1 f'~sof'oijrlty;.,:

. ·t1_fl ,- -l-.--'H--L -4--1-'-l

i '

0.1 i I . 10

'l'u!c.,,T:,pe:hr'l"'rl Reieran,eSAS Dilm,iilg 1%1: 5.000

FigureA.2.5.l(a) TRS for 5th OBE for Horizontal Axis (East to West)

with EPRI TR-107330 "narrow" RRS and 1/6 octave grid line

mSIIBA BIER6Y SYSTEMS I SOLUTIDIIS CORPORATION Nuclear Energy Systems & Services Division

85/151

100

100

Corurol 2 1.!a11M,\ax

Log g

Peak: 13.794 0.010

09:12:19.6 Fil Nov032006

Tcstl.!wcl: O.ODOdB Con!rof 2 Z~A: 6.592 PIJls.9: 1 of·c 1 Pulse Polaiil)': +


Palso Typa:lmpO<t Roforonco SRS Damping (%}: 5.000 ·

100~~~~~~~~~~~~~~~~~~~~~~

Log

TOSHIBA 5;32980BE RUN NO

Frequency (Hz)

MitJO,Shack Test: TOSHl8A,OSE.005

10 100

SSHCA(NS)

Figure A.2.5.2 TRS for 5th OBE for Horizontal Axis (North to South)

Canlro/ S M°axl•Max

Lag g

Peak 21.555 0.012

09;12;19.6 Fri No~ 03 2000

Test Level: 0.000 dB Pu!se: 1 of 1

Coo1Jol 3 ZPA: 8.330 . Pulse Polarity;+

Pulse Type;lmport Reference SAS Damping(%): 5.C<Xl

0.1 "-----~--~~-~~~~I~'-.-----~-~--~~~----10 100

Frequency (Hz)

VCA TOSHIBA 5~298 OBE RUN#8 .

MIMO Sh0ck Test TOSHIBA_OBE.OOS

FigureA.2.5.3 TRS for 5th OBE for Vertical Axis

IDSHIBA ENERGY SYSTEMS I SOUITIONS CDRPOIIAl'IDN Nuclear Energy Systems & Services Division

86/151

A2.6 SSE

Control Maxl·Max

Log g.

Peak: 14.224 0.010

09:33:54.2 FriNC'(032006

Tosi Level: 0.000 <lll Pulse: 1 of I

100

Cc<llro1 1 iPA". 5.705 Pulse Polamy. t

•r-··-"·-··-··-i·-~-+--+--·-1-·.,-..... _ ..... -·-·+-·-··-t--1---,---1-+-,-·H-·····------··-·"'"-

10

Leg Frequency (Hz)

TOSHIBA 5329Ji SSE AUr1#9

Mll.!0 Shock Test: TOSHIBAoSSE.001 ·


Pulso Typo:lmpon Aafercnco SRS Damping (%): 5.000

FBHCA(EW)

100

Figure A.2.6.1 TRS for SSE for Horizontal Axis (East to West)

TaSI~ 0.0JOllB Pul!t,: Id t

Coo:ro! t ZPA::5,705 Piitse-Pclality:;

10 Log Frnqooncy IHi)

. Pu!Sll Typo:lrnport Reference. ~RS [JamJi<,g f%): 5.000

100

Figure A.2.6.l(a) TRS for SSE OBE for Horizontal Axis (East to West)

with EPRI TR-107330 "narrow" RRS and 1/6 octave grid line

lUSIIU EIIER&Y SYSTEMS I SOLUTIONS CORPORATHIN Nuclear Energy Systems & Services Division

87/151

Comrcl Maxl·Max

Log g

Peale 13.901 0.012

09:33:54.2

.2

Fd Nov 03 2006

0.1

Tes\ Level: 0.000 dB Pufso: 1 of 1

'"'

. ·-·-·· ·-··-··-i-·--·

.... : ... ,.

• Control 2 ZPA: 8.513 Pulse P"!arily: +


Pulse Typc:lmpcd Refcrenro SRS Drunplng (%): 5.000·

, _ _, --::'.1---,·····- :··-·--·, - -1--·· ·····r·--

' ...... -,t:....; _____ .c..,_ ____ ,, ·! ----·-1---+-+--,--,--,~------t---- --+-+---'---r;---t-·1-

.j ________ -+----·, 1 .. - ... --..... \,---l--1--+-+-+--!-.. -·-----f---.... ;·---~--·t---~-,-·

1--·"""'----,.---·-~: ........ +·· .. -+--f-c-f-c-l--t--:---------1-·--"+----·-+--f---+---i-+··,..,

1

T0Sli1BA 53298 SSE .RLIN 19 .

I I

Frequency (Hz).

Mlt.10 Shock Tes\; 1'0Sfil1!A..SS€.C01

:

10 100

SSHCA(NS)

Figure A.2.6.2 TRS for SSE for Horizontal Axis (North to South)

Log g

Peak:· 28.325, 0.010

09:33:54.2

3

~rl Nov o:3°2006

10 . .: ........ .

, ... . ....... ········-:1'"

A' . "'i'" .1. ... tt ... i

-- -,·

Pulso Type:lmport Reference SAS Damping (%): 5:000

Utll···.1 ·

............. ·!

, ..

_ _L. ....

-1--, ................ ,-J--·---t--.... , .. -;-,----l···"·"i·'·""'I•·""'" ,\ ... ;., .... _ ... ,. ..... -· .....:t. ·--·l···-+ ......... , .. ,., ..... ,· .... , ...... ,: .... ,

.1

I · ! ' t 0.1.. . ._ ___ .....,_ __ ....c._ _ _,_--'---"-'---'-----~---'--~------

.Log

TOSHIBA 53200 SSE' RUN#9 . .

Frequency (Hz)

MIMO Slx>d<TestJOSHIBA_SSE.001

10

VCA

Figure A.2.6.3 TRS for SSE for Vertical Axis

100

TOSIIBA BIER&Y SYSIEIIS I SOLUTIONS CORPDIIAllON Nuclear Energy Systems & Services Division

88/151


TOSHIBA 53298 ssr; , .. AUN/19

Ch X : TOSHIBA_sse.001.FB_HCA.ulf @ Fn Nov 03 2006 09:33:54.2 ,Ch Y: TOSHIBA._SSE.001.SS_HCA.uff@ Fri Nov 0~2006 09:33:54'2.

·Mfj_ ! '~ IH~ .:::.:1········:········i n]jJ j;~: 0·: , ... ,, .. 2 .. blYcJv/1' .. ,; .... , .... i, ... , ... ,, , ... ,. ·4,·--r, ,.

O 10 20 30 40 50 60 70 80 90 100

-~~WIJI _,.,===== =·,,, ... ,,,. t•· T L '••••l········i· T.L: ...• 1. -200 .

O 10 20 30 40 50 60 70 80 90 100

Figure A.2.6.4 Coherency Plot between Horizontal Axes (East to West and North to

South)

TOSHIBA 53298 SSE· RUN,9

Ch X : TOSHIBA_SSfo.001.FB_HCA.ulf @ Fri Nov 03 2000 09:33:54.2

Figure A.2.6.5 Coherency Plot for Horizontal Axis (East to West) and Vertical Axis

mSIIBA BIER6Y SYSTEMS I SOLUTIOIIS CORPORATION Nuclear Energy Systems & Services Division

89/151


TOSHIBA 53298 SSE .RUN#9

Ch X :TOSBIOA,__SSE,001.SS HCA.ufl @ Fri Nov 03 2006 09:33:54.2 Ch Y: TOSHIBl\:..SSE.001.\/CA.ufl@ Fil Nov 03 2006 09:33:54.2 .02,--,--,--,------,,--,--;--...:.._,-----,,---i---;;::====::i

· - Coherence 0:15 . -.. ' ..... ' : '~ .......... :

~ Q.1 \·r--0.05 ·:v. ··.w··· ... Huv:·· ·: . ....... ··-···· .. .

- . . . 00'----1-'-0-----'2'-o .___ __ 30_,__, _ ___c.~4,_0 ___ so...._ ___ sL.0---.,,...1.0__.\!.._---1,=----aL.o _ __.:,,_sa::o:__::....Y...J100

200,.------:-"1,--.---.-;:---.----r----:-r----.-:----.--:--====

V~?~,~ 'i 100 O> e.. 0

~ -100 - •

-200L----'----'----_l.---'-'----...L.~~-L----1---L---...1.._--....J ·a

0.8 --

~ 0.6 -- .

0.4 .,. .•.

0.2.

00

10

10

20 . 30

20, 30

40 50

".:.' .. , .. ~. . . : ...... .

40 50 Hz

60

60

70 80 90 100

70 80 90 100

Figure A.2.6.6 Coherency Plot for Horizontal Axis (North to South) and Vertical Axis

Conlrof Acceleration·

Linear .g

Peak:

TestLevel:.O.OOOdB Control l•ZPA: 5;705 Pulse: · 1 of 1 Pulse Polarii\<: +

Pulse Type:fmport R.elerence

10-,------,-----,--------------------I

\

5.077 · .5_ ---· ···--·--f---~ . .L

-5.705

09:33:542 Fri Nov 03 2006

-10.,.i.....,----'------'------'------1----_j_ ____ J._--I

CJ 5000 Linear.

TOSHIBA 53298 SSE RUNM9 .

1e+o4

Time (msec)

MIMO Shock Daia Review: TOSllfBI\..SSE.001·

1.5ef04 2e+04. 2.5e+o4 . ·3e+o4. 32<H04

FBHCA(EW)

Figure A.2.6.7 Time History for SSE for Horizontal Axis (East to West)

1USIIBA BIER&Y SYmlllS I SOLUTIONS CDRPlllATIDN Nuclear Energy Systems & Services Division

90/151

Control 2 AcceleraUon

Linear 9

Peak: 7.377 -ll.513

09:33:54.2 Fri Nov 03 2006

Tesl Level: 0.000 dB Puls.a: 1 of 1

Control 2 ZPA: 8.513 Pulse Polanly: -t


Pulse Type:lmport Relerence

10 ~----------~""'--~~.-'--'---~-----------~

o. 5000 Linear

T0SHIBA53298 SSE RUNtt9·

1e+04

Tune_ (msec)

MIMO Shock Data Review: TOSHIBA_SSE.001

·1.5e+04 28+-04 2.5e+04 3e-t04 3.2e+-04

SSHCA(NS)

Figure A.2.6.8 Time History for SSE for Horizontal Axis (North to South)

Control 3 Acceleration

Linear g

Peale 7.458

·8.321

09:33:54.2 Fri Nov032006

Test Level: 0.000 dB ·Pulse: 1 of' · 1

Control 3 ZPA: 8.321 Pulse Polarity: +·

PulseTYP.e:lmport Reference-

10 .. ~--------~----'----1-----------------~

0 . 5000

Linear.

TOSHIBA 53298 SSE RUN#9

.11lfll4 Time(msec)

MIMO Shock Data Review: TOSHIBA_SSE.001

. 1.5e+04 . 2e+04 2.59+04

VCA

Figure A.2.6.9 Time History for SSE for Vertical Axis

3e+04 3.2e+04

lUSIIBA BIEll6Y SYSTEIIS I SOLUTIONS CtJIPORATIDN Nuclear Energy systems & Services Division

91/151


TOSHIBA 53298 SSE • RUNff9

Ch X: TOSHIBA::..SSli.001.FB-'cHCA.uff @ Fri Nov 03 2006 09:33:54.2

.,:· : ... -·

0 0 msec Hz

100

Figure A.2.6.10 Time-Interval PSD Coherency Plot, SSE Horizontal Axis (East to West)

TOSHIBA 53298 SSE . RUN#9

Ch X: TOSHIBA.c.SSG.001:SS.cHCA.uff @ Fri Nov 03 2006 09:33:54.2

,.,:-····

100 .

0 msec ·Hz

Figure A.2.6.11 Time-Interval PSD Coherency Plot, SSE Horizontal Axis (North to

South)

TDSIIBA BIER6Y SYSIEIIS I SOLUTIONS CIIIPORAllDN Nuclear Energy Systems & Services Division

92/151


N f0-:4 ;;£"

"b,

10""'

10_,,

3.5

msec-

TOSHIBA 53298 SSE RUN#9

Ch X : TGSHIBA.:.SSE.001 ;VCA.ulf @ Fri Nov 03 200009:33:54.2

... '~.

0 0 Hz.

Figure A.2.6.12 Time-Interval PSD Coherency Plot, SSE Vertical Axis

TIISJIBA BIER6Y SYSTEMS I SOLUTIONS ctllPORA110N Nuclear Energy Systems & Services Division

93/151

100


APPENDIX 8 Test results data for EMC Tests

APPENDIX B Test results data for EMC Tests .................................................................... 94

B.1 Radiated Emission, Magnetic Field (RE101) ............................................................ 95

B.2 Results of Radiated Emission, Electric Field (REl 02) .............................................. 99

B.3 Results of Low Frequency Conducted Emissions (CElOl) ..................................... 100

B.4 Results of High Frequency Conducted Emissions (CE102) .................................... 110

B.5 Results of Radiated Susceptibility, Magnetic Fields (RSlOl) ................................. 112

B.6 Results of High-Frequency Conducted Susceptibility Testing at AC Power Leads

(CS114) ........................................................................................................................... 117

B.7 Results of High-Frequency Conducted Susceptibility (Signal Leads) (CS114) ...... 118

B.8 Results of Conducted Susceptibility (Signal Leads, Bulk cable injection, impulse

excitation) (CSllS) ......................................................................................................... 119

B.9 Results of Conducted Susceptibility (Signal Leads, Damped sinusoidal transients)

(CS116) ........................................................................................................................... 120

B.10 Results of Surge Withstand Capability Testing ...................................................... 121

B.11 Results ofEFT/B Testing ....................................................................................... 122

B.12 Results of ESD Testing .......................................................................................... 123

B.13 Results of Class lE to Non-lE Isolation Testing ................................................... 133

mBHIBA ENERGY ffl1EMS I SOWTIONS CORPORATION Nuclear Energy Systems & Services Division

94/151

---- ----------


B.1 Radiated Emission, Magnetic Field (RE101)

Table B.1 RE101 Test Matrix Test Point Compliant with Specification

Connector of LVPS Cable #18 Yes



Front Face of LPRM Unit Yes

Back Face of LPRM Unit Yes Top Face of LPRM Unit Yes Bottom Face of LPRM Unit Yes Right Face of LPRM Unit Yes Left Face of LPRM Unit Yes Connector of LPRM Cable #128 Yes Connector of AO Cable #169 Yes Connector of AO Cable #182 Yes Connector of DIO Cable #336 Yes Front Face of LPRM/APRM Unit Yes Back Face of LPRM/APRM Unit Yes Top Face of LPRM/APRM Unit Yes Bottom Face of LPRM/APRM Unit Yes Right Face of LPRM/APRM Unit Yes Left Face of LPRM/APRM Unit Yes Connector of LPRM Cable #105 Yes Connector of AO Cable # 195 Yes Connector of AO Cable # 208 Yes Connector of AO Cable# 215 Yes Connector of DIO Cable #332 Yes Front Face of FLOW Unit Yes Back Face of FLOW Unit Yes Top Face of FLOW Unit Yes Bottom Face of FLOW Unit Yes Right Face of FLOW Unit Yes Left Face of FLOW Unit Yes Connector of FLOW Cables(#139, 140) Yes Connector of AO Cable# 228 Yes Connector of AO Cable #234 Yes Connector of AO Cable # 240 Yes Connector of DIO Cable #333 Yes

IDSHIBA ENERGY SYSTEMS I SOUITIDNS CORPORATION Nuclear Energy Systems & Services Division

95/151

[

[ ML.S1D461E, Ridll1fc1Emissicm RE101

EUT Adive-PCEilknNa 1


EQ.ii:meitlD-NRW-IPGA-llasedPRMSy,m,1

s..-1~ t1-00J00011, 00J60015 & OOJ600l3

M:Il!I NIITil:Er -HNU JOO, HNU 100 & HNU ;m

JC0-15Il00

Figure B.1.1 RElOl Data for Connector ofLVPS cable (No,18)

f.SL-S1D-461E, Raclated Em issims RE101

EUTActive-PositiooHo.4

E(Jifrnen!ID-HRW.fPGA-BasedPRMSys!em

Serial #-00360017, 00360015 & 00360013

Mod>I Hunb,r-HNU 300, HNU 100 & HHU 200

JC0-1"53300

1B0.0

150.0

~ 120.0,+-····-·····--·················•·············-·· :---+ -+ -+ +·+-++-----·--··---+···--·--1--··--+--f--lll ;a. ~

" I 90.D+--··--·----+--~··-·--l

a

100.0 1.0K

Fre<p,ncy(Hz)

10.0K

Figure B.1.2 RElOl Data for Front Face ofLPRM Unit

IDSHIBA ENERGY SYS1EMS I SOUITIDNS CORPORATION Nuclear Energy Systems & Services Division

96/151

100.0K


[ r,'IL-S1D461E, R3Cl.tec1Emisslan RE101

EUT Adive-PosllklnHo.10

E(JiimentJD -NRW.fPGA.SasedPRMSystem

SEffal #-00360017, 00360015 & 00360013

l.bi,lllunbef -HIIU 300, HtlU 100& HtlU 200

JC0-153300

[

180.0

, .. o-l-----+---+-+---+--l--l---l--1-1----+--+----l-----l----l-----+-l---l-+-----l----l--i----+->-l--+-!-+---i-----+--+-' ~Wc\'!Jl!.~ 10.0 100,0 1.0K 10.0K 100.0K

M:L-SlD-461E, Racl.'te<IEmissicns RE101

EUT Adive-Pmitioollo.14

180.0

30.0

Freq.ency(Hz)

Figure B.1.3 RE101 Data for LPRM Unit Cable (No. 128)

E(JiimentlD -tlRW.fPGA.SasedPRMSystem

Serial#-00360017, 00360015 & 00360013

Mldll llun rer • HNU 300, HNU 100 & HIIU 200

JC0-1"53300

o-l------l-----l--+-+-+-l-+-./-l-----<r--1-+--+-+-+-+++---+--+--+-+-++-i-+-!----+--i---1r--'-i'-'i.-'f'"P--l-'1 10.0

Figure B.1.4 RE101 Data for LPRM/APRM Unit Front Face

mBHIBA ENERGY SYSTEMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

97/151


[ r.lL.S1D-461E. Rad.eel Emisskm RE101

EUTActive-PositiooNo.25

.....

Eq.ipnenf:ID -NRW..ffl GA.8asedPRri,system

SeriaJ#-00360017, OOJG0015& 00360013

~blel Hun b:r - HNU 300, HNU 100 & Hl·IU 200

JCO - lo330-0

~ 120.0-j-· .. ·· .. ··--...... - ......... 1 ..................... , ......... I ...... Jf ..... j. ti j.... ............... . ... j ........... -I " 1---1--! --i -1-1 .. J.......... -===t::=+--.-.L= .. I 1 .. j ...... , .. 1.J .. _____ ............ -... J ........... - ...... 1 al '.!!. .. J so.o+-----· .. ·--1---.. 1---:--,v,

i

100.D 1.DK

frecpn:y(llz)

10.DK

Figure B.1.5 RElOl Data for Flow Unit Front Face

MSHIBA ENERGY fflTEMS I SOUJTIONS CORPORATION Nuclear Energy Systems & Services Division

98/151

100.0K


8.2 Results of Radiated Emission, Electric Field (RE102)

e~m-11RW~a>odPR,lS1>-.. S<!fiaj#,«1Zdl017,~&ro!&lll13

~l!,&11).!iGJl!,_£,i,_RE102

Et!TM,'>--H<r--P<m~

~--·IINU:itl),HNU111)&HNU :00 JCO-'l!illXI

[

OM"rT"~------~---,--

nn

l'ji$JJ+---------+--•••i:======4;==,;=.,,+--

J •••+-·---··········-··--····+-···-·····-·-·-····+·--

i M» £i 4&13+--------

"' Si •••+-------+---: ill ·~· I ::: ........ ---------

a._,__ _______ _

wo.:ic----------------l--·--·---1---\.-------1

M+··-·-------+--·--J

Figure B.2.1 Results of REI 02 (Horizontal Antenna Position)

~•~,Ro,bbf£,i,-Rl!102

EIJTA<t,'ili'Ntll'i·V...blAmm~

l!~pmodlO,IIR\\!-fl"Gi\.ll_,,llMSy,t,,m SM!IN,CDSl!Y.)17,fflltro15&oo.l!ial13 ~-1-ll- .JMJ 3'U, HNU l!IJ S. H!-IIJ :00 JCO-'l!il:I)()

,~o,rr--,==c---rr----r---i---r

,~• 1•• t-l.:=->lllllU.!1.l!!c.:.m-1-1---r-- ·-1·· 1-··

i,11.u+--··----

f ••• ill oao+-------:e. s 4•o+---"' .!•llll'f-----;~4.0+---u. jllJl+-----i , .. ~---c

···+-----,

Figure B.2.2 Results of RE 102 (Vertical Antenna! Position)

IDSHIBA ENERGY SYSlEMS & SOUITIONS CORPORATION Nuclear Energy Systems & Services Division

99/151


8.3 Results of Low Frequency Conducted Emissions (CE101) Table B.3.1 CElOl Test Matrix

Test Point Compliant with Specification

Cable#10 (Line) No (approximately 1 OOHz to approximately 1200Hz, emission exceeds the limit)

Cable#10 (Neutral), No (approximately 1 OOHz to approximately 1200Hz, emission exceeds the limit)

Cable#10 (Ground) Yes

Cable#1 O (Line) with choke-coil (100 mH) Yes

Cable#10 (Neutral) with choke-coil (100 mH) Yes

Cable#10 (Ground) with choke-coil (100 mH) Yes

Cable#10 (Line) with choke-coil (120 mH) Yes

Cable#10 (Neutral) with choke-coil (120 mH) Yes

Cable#10 (Ground) with choke-coil (120 mH) Yes

Table B.3.2 Results of Line without coil

Frequency Peak

CE101 Limit CE101 Relaxed Limit Margin Compliant

Amplitude with (Hz)

(dB micro A) (dB micro A) (dB micro A) (dB micro A)

Specification

60.499 122.9 119.9 122.9 0.0

180.614 122.1 108.8 111.8 10.3

299.465 120.3 103.7 106.7 13.6

419.315 117.5 100.2 103.2 74.3

540.810 113.4 97.7 100.7 12.7

660.572 107.2 95.6 98.6 8.6

780.040 98.6 93.9 96.9 1.7

899.038 96.6 92.5 95.5 1.1

CElOl Relaxed Limit= CElOl Limit+ 20Log(Fundamental Current)

Margin= PeakAmplitude-CElOl RelaxedLimit

IDSHIBA ENERGY SYSTEMS I SOUJTIONS CORPORATION Nuclear Energy Systems & Services Division

100/151

Yes

No No No No No No No

Table B.3.3 Results of Line with 100 mH coil

Frequency Peak CE101 Limit CE101 Relaxed Limit Amplitude (Hz) (dB micro A) (dB micro A) (dB micro A)

60.764 122.5 119.9 122.5

74.188 72.1 117.8 120.5

75.304 66.1 117.7 120.3

76.949 65.8 117.5 120.1

78.095 68.1 117.3 119.9

82.061 65.6 116.8 119.4

84.088 69.4 116.6 119.2

86.496 67.7 116.3 118.9

88.729 66.0 116.0 118.6

90.609 66.3 115.8 118.4

111.230 67.4 113.7 116.4

128.326 68.7 112.3 114.9

180.438 111.2 108.8 111.4

299.876 101.5 103.7 106.3

419.403 94.5 100.2 102.9

530.000 66.3 97.9 100.5

540.927 88.1 97.7 100.3

660.396 81.8 95.6 98.3

779.805 75.7 93.9 96.6

899.273 68.7 92.5 95.1

CE101 Relaxed Limit= CE101 Limit+ 20Log(Fundamental Current)

Margin= Peak Amplitude- CE101 Relaxed Limit


Margin Compliant

with (dB micro A) Specification

0.0 Yes

-48.4 Yes

-54.2 Yes

-54.3 Yes

-51.8 Yes

-53.8 Yes

-49.8 Yes

-51.2 Yes

-52.6 Yes

-52.1 Yes

-49.0 Yes

-46.2 Yes

-0.2 Yes

-4.8 Yes

-8.4 Yes

-34.2 Yes

-12.2 Yes

-16.5 Yes

-20.9 Yes

-26.4 Yes

fflSHIBA ENERGY SYS1EMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

101/151

Table B.3.4 Results ofNeutral with 100 mH coil Frequency

Peak CE101 Limit CE101 Relaxed Limit

(Hz) Amplitude

(dB micro A) (dB micro A) (dB micro A)

60.6 122.7 119.9 122.7

75 69.6 117.7 120.5

77.6 66.5 117.4 120.2

82.5 68.3 116.8 119.6

84.1 64.7 116.6 119.4

86.5 67.2 116.3 119.1

90.3 66.6 115.8 118.6

110.8 66.7 113.8 116.6

125.7 67.1 112.5 115.3

129.1 65.6 112.2 115

132.6 65.1 111.9 114.7

180.4 111.3 108.8 111.6

192.7 71.8 108.1 110.9

299.9 101.5 103.7 106.5

419.4 94.3 100.2 103

530 66 97.9 100.7

540.9 87.8 97.7 100.5

550.5 61.7 97.5 100.3

780 74.9 93.9 96.7

899.5 67.6 92.5 95.3

CE101 Relaxed Limit= CElOl Limit+ 20Log(Fundamental Current)

Margin~ Peale Amplitude - CEl O 1 Relaxed Limit


Margin Compliant

(dB micro A) with

Specification

0 Yes

-50.9 Yes

-53.7 Yes

-51.3 Yes

-54.7 Yes

-51.9 Yes

-52 Yes

-49.9 Yes

-48.2 Yes

-49.4 Yes

-49.6 Yes

-0.3 Yes

-39.1 Yes

-5 Yes

-8.7 Yes

-34.7 Yes

-12.7 Yes

-38.6 Yes

-21.8 Yes

-27.7 Yes


102/151

Table B.3.5 Results of Line with 120 mH coil

Frequency Peak

CE101 Limit CE101 Relaxed Limit Amplitude

(Hz) (dB micro A)

(dB micro A) (dB micro A)

60.6· 122.5 119.9 122.5

74.6 65.4 117.8 120.3

76.8 66.6 117.5 120.1

80.9 66.6 117.0 119.5

85.3 67.0 116.4 119.0

87.2 68.0 116.2 118.8

89.9 67.6 115.9 118.4

93.6 65.7 115.5 118.0

110.7 66.9 113.8 116.3

114.2 66.4 113.5 116.0

124.3 65.4 112.6 115.2

131.2 66.1 112.0 114.6

180.4 109.3 108.8 111.4

. 299.9 99.8 103.7 106.2

419.5 92.4 100.2 102.8

530.0 65.3 97.9 100.4

540.9 85.9 97.7 100.2

660.4 79.3 95.6 98.2

779.9 73.0 93.9 96.5

899.3 66.4 92.5 95.1

CEIOl Relaxed Limit= CEIOl Limit+ 20Log(Fundamental Current)

Margin= Peak Amplitude- CElOl Relaxed Limit


Margin Compliant

with (dB micro A)

Specification

0.0 Yes

-54.9 Yes

-53.5 Yes

-52.9 Yes

-52.0 Yes

-50.8 Yes

-50.8 Yes

-52.3 Yes

-49.4 Yes

-49.6 Yes

-49.8 Yes

-48.5 Yes

-2.1 Yes

-6.4 Yes

-10.4 Yes

-35.1 Yes

-14.3 Yes

-18.9 Yes

-23.5 Yes

-28.7 Yes


103/151

Table B.3.6 Results of Neutral with 120 mH coil

Frequency Peak Amplitude CE101 Limit CE101 Relaxed

Limit (Hz) (dB micro A) (dB micro A) (dB micro A)

60.8 122.4 119.9 122.4

74.3 70.0 117.8 120.4

75.2 64.7 117.7 120.3

77.4 69.5 117.4 120.0

79.0 64.7 117.2 119.8

80.7 63.7 117.0 119.5

83.7 67.1 116.6 119.2

87.6 65.8 116.2 118.7

125.3 66.4 112.5 115.1

132.1 64.2 112.0 114.5

166.9 64.0 109.6 112.2

180.4 109.3 108.8 111.4

299.9 99.7 103.7 106.2

419.4 92.0 100.2 102.8

530.0 63.3 97.9 100.4

540.9 85.3 97.7 100.2

660.3 78.5 95.6 98.2

780.0 71.8 93.9 96.5

899.3 65.0 92.5 95.1

CElOl Relaxed Limit= CElOl Limit+ 20Log(Fundamental Current)

Margin= Peak Amplitude- CElOl Relaxed Limit


Margin Compliant with (dB micro A) Specification

0.0 Yes

-50.4 Yes

-55.6 Yes

-50.5 Yes

-55.1 Yes

-55.8 Yes

-52.1 Yes

-52.9 Yes

-48.7 Yes

-50.3 Yes

-48.2 Yes

-2.1 Yes

-6.5 Yes

-10.8 Yes

-37.1 Yes

-14.9 Yes

-19.7 Yes

-24.7 Yes

-30.1 Yes


104/151


40.0 --·-··-·--'---~~~~~'-'-+----~----·---~--~-·-

10.0 100.0 Frequency [Hz]

1.0K 10.0K

Figure B.3.1 Results of CElOl (Line, No coil)

150.0

140.0

130.0

120.0

j 110.0 I .co ~ 1000

I ~ ,, ::I 90.0 .t:: C. c 80.0

~

70.0

60.0

50.0

40.0

10.0 100.0 1.0K 10.0K

Frequency [Hz}

Figure B.3.2 Results of CElOl (Neutral, No coil)

mSHIBA ENERGY SYSTEMS I SOUITIDNS CORPORATION Nuclear Energy Systems & Services Division

105/151


50.0 -l-------+--+--1--1--!-

40.0 +······-·-·-·························'······--··-····-·········'-·····-'

10.0 100.0 Frequency [HzJ

1.0K 10.0K

Figure B.3.3 Results of CE101 (Ground, No coil)

150.0 ~----~~----.----~-~~~-~-c,----,-l---.------,---,--.,

I 140.0 -1------'-----1---1--'--+~-l---+--1------1---+--l---l-'--!----!---J-'-+-----+---!--l----+--i--+--+---'-I

··- ---1-130.0 +-----+--·.__-->--:-

~ 110.0 1----+--+--l--+-i--lHrl--t------"'~"'1-.::---l--t---+-l+-+--t-l-t----CO ::!:_. 100.0 +----+---i---+-+-+--Hrl--t----1-'!+---f--"'!'--..::"'c...-i;:--+--t-l-t---,--t--+-rl---+--1--t--t-H cu

""' :E 9J.o -l----!---1---l-__;_-1---W-!---1-----1-µ_ __ n_-l-l---+.-!---+-!-+-=;,,,,.....---L-+---'---+----+-....,....-'--+__.__,

ii. i 80.0 -1-----+----l--l-----+--!--~...l-+-1-----1-l-l----Fl---411-+llµ.Jl+-+-'-1---+---+--+--+-1 -;!-+I +, --HI

00.0

40.0 · -·---····-

10.0 100.0 1.0K Frequency [Hz]

Figure B.3.4 Results of CE101 (Line, with 100 mH coil addition)

roSHIBA ENERGY SYS11:MS I SOUlflDNS CORPORATION Nuclear Energy Systems & Services Division

106/151

10.0K


10.0 100.0 Frequency [Hz] 1.0K

Figure B.3.5 Results of CE101 (Neutral, with 100 mH coil addition)

10.0 100.0 Frequency [Hz]

1.01(

Figure B.3.6 Results of CElOl (Ground, with 100 mH coil addition)

IDSHIBA ENERGY SYSTEMS I SOUITIONS CORPORATION Nuclear Energy Systems & Services Division

107/151

10.0K

10.01<


~ iil 110..0 +----+---+----+--i--i-lt-+-+-t---'"""'-,aic:+--..-::--+-+.,Y--+-

"C ~ 100.0 CII

"Cl :I 90.0 :!= C. a 30.0 --;----t---t--+-+-+--tl-H-+---+-1.;---m--111-+11-1-1

70.0 +-----f---+---+----+-+l+-+-t----ll-l+--+H--lH--Hl-+-.1-

60.0

10.0 100.0 Frequency [Hz] 1.0K

Figure B.3.7 Results of CE101 (Line, with 120 mH coil addition)

10.0K

150.0 ~--~----~~~~~----~-~-~--,-~~--,-~.-----,-····----~·-···-···,·······-,--,-_,.~-···,

140.0 +-----+---+--i--+--,-+-+-t-+-----+----+--+--;--+--+-t-------,--+--+-i-+--,--;

120.0 -i-----+---+---i-+--i.\:::/'--+..-J-t-----i----+Afli3Will8le--b6'1eH-bi'f±lli-Kecli00:){1-b,Hffilf---+-+-+-+-+-H -·-···-··r-···············1-t··-1: 1 t! I

~ 110.0 +----+---f---i-+--i-+--+-1-t--""'""-~--+--i--'rl.--+--t-+-+-H----t---t--+-+-+-+-+-H CQ

::!, 100.0 +----+---++--ic--+--i-+--i--t----H-l--i:--::;,-......J"--..-:;-:-+-l--Hf----+--t--CII

"C £ 90.0 +------------+-+--+---+-H---tl---ff--j--f-i--+-f-?-----'-----'--

c. ~ 30.0 +------+----+--f----i-+lc+-;H---i-H---f-t---+tl--t-1-+--;-+-+-1----+---+--,-~---0--,-+-+-1

10.0 100.0 Frequency [Hzl

1.0K 10.0K

Figure B.3.8 Results of CE101 (Neutral, with 120 mH coil addition)

IDSHIBA ENERGY SYSTEMS I SOUITIONS CORPORATION Nuclear Energy Systems & Services Division

108/151


~o ~---.----.---r---,----,--.-.,-,-,--------.---.-----,-----.-----.--.-T"""T".,------,--.-------.------,----.----,--,-,---, ---···-·----1----l--l--···-·-1 l·-c--l-H------··-··---l---·---t---+----!-··--l·----l·-·-l--:,--1---·--- ··----·-··-- ·-L_~·-t-··-·1--···l-l

140 -l-----l---+---+----<--+--'----++----l---+----+--i---+-+-+--+-+----t---\---t---'i--1---+-+--t-1

~o +----+---'---+--1-+-+-+++-----+---+----+--+--+-+-+--+-t-----+---t---+-i--f-t--t-t-l ~·-----·····-··-··i-·····---e--·---l- 1--1-t--:-+-1----·-----1----f--·--t--·-·1----1·--1--t-f-t-----------!---+----l-+--f--t-t-H

uo+----+---+---+--1i-,...d:--+++----+--:--:-:--t,f-:-:--i::--+-:--t=l:-:+:tt--:---:--:--:-:-l:--:::--1_!---±::::-:+:-:r.t:T--H ':.' r-----+--+---+-+-+-!-r-..._,;::,,-"'-l-.=-----+-"All.o.wable.lLeYl1et Cl JJ, ll

1E _elaxe_d..L.imi )_(S.ame_asJ:EJ 1Lioi10. ~ ..., I I -........ I I I

:I 110 1 I :::::b..___LI I - I ! !8 i I --r-..--i--rt~-- Allowab e Leve (CBIOI Girilt- ~ -~

100 I j !"'""- j / I i

,, I I I I ,....., ~ I f : +----+---+---+-'---··!-·······_····}·_·-+-I++++-+· -·_··--_--_···_·······_········_········+-······_········_-·····-_l,----·-+·1-_····· ·-+···· l_·······+--f-+++---+---!----t--+--1-+---1--+··--H·-·'·--

~ m -~ - --.t~ i--i:- -i;r,--' --

:-i----+--+--:-t·-.--·~--·+_-~"~J.-i.T ~~-rr 10.0 1000

Frequency [Hz] 1 OK 100K

Figure B.3.9 Results of CElOl (Ground, with 120 mH coil addition)

IDSHIBA ENERGY SYS1EMS I SOUJTIDNS CORPORATION Nuclear Energy Systems & Services Division

109/151


8.4 Results of High Frequency Conducted Emissions (CE102)

Table B4 CE102 Test Matrix

Test Point

Cable#1 O(Line)

Cable#1 O(Neutral)

Cable#1 O(Ground)

[ J•.c ML.SID461E, ~EmlssicnsCE102Re&lls 10kHz-10fvllz

EUT Adive Resutsfa- Ure L1

eo.o

> &) 10.0+--.. --·-·--V-----'-<~ ................ , ............... , ............. +.";" .... , ...... .

~ -a 60.Q+-----------<---+---.,..--,-c-111,-;i l ... ,+------!---!--+--+-!-

Compliant with Specification

Yes

Yes

Yes

100.QK 1~M

FigureB.4.1 Results ofCE102 (Line)

EcµpmrtlD-NRW-IPGA-BasedPRMSystem S11 lalli'-OCWI017, OOJl'OOIS& 003{1)()13 r.tx.l><i'Q>armlal-HNU JOO, HNU 100& HNU 200 JC0-153300

10.0M

mBHIBA ENERGY SYSTEMS I SOUlflDNS CORPORATION Nuclear Energy Systems & Services Division

110/151

[

[ Ja,c 1nL-S1D-l61E. C<nll:IEdEmlssirn;, CE102 Resuts 10 l<llz-10 ~Hz

EUTAcliwReslllsfcr Urel2

- -CE102 ,J C leJd B A.:tiv~

120.0

110.0 ~ ................................. , .........

100.0 - -90.0 --. . ,z:,:·

··--~'\"' -· -.. --

80.0

> tS 70.0

,rr; l''r,

........... - ....

~ i 60.0

t 50.0

40.0

30. 0

20. 0

10. 0

0 10.0K

tttJ=~ A . I ,.__ ~

!. n IU ·-:,Tl ,JI l"•· LJ,~ ''l'I \

I I

10 .OK

. , .. ., Cl

.................

' .1 7 ·x·-........ .................

; i


- ..

.................

, .......................... 1. M

E(Jlpnl!tlD -NRW-ll'GA-BasooPRM Symn Serial #-00Jro017, 00360015 & 00360013 M:xlld(lp,rmi<n-HNU 300, HNU 100& HNU 200 JC0-15lll0

.......

' ........................ .......... ~j;~;8J~FH

'

I

' ........... , ......... '

' 10.0 M

Figure B.4.2 Results of CEI02 (Neutral)

t/lL-SlD-461E Caru:tedEmisskm, CE102 101<1lz-10 P.flz USN C

EUT ActiveResutsfcr Ural:!

EqiµmrtlD -NRW-ll'GA-BasooPRM S)'&flll Se-iol #-OOJWOf/, OOJW015 & O!OO'.X)1J M:xlld0p,r!licn-HNU300, HNU 100&HNU200 JCO-T53JOO

110.0 -·.CE102· I

110.0 - C le;id C Active-I

100A - -so.o , ....... ................. . ............... ................

ao.o

> ffi 70.0

:l!. ~.,, ........... ; .... .................. ,_ .. -. Q 60.0 i t 50.0

40.0 ~-·--- ... ............. , ......

30.0 ~---

20.0

10.0

• 10.0K

'

=: -

-! I I

I ...

....

'tr I 111\1.J~hlP. µuµ

I I ' .. , ..... , ....... ..... .. .....

-k. I ,,. ................. , .................. . ...... , ....... --'-.

.............. ......... , .. l<'E ,,n IT~

~ .......... ........... ·:.; i

, ........

. '" I

I

I I , .............. .........

I I

' i a ....... i I

i I I I I ; i I ' I ' I !

100.0K ,!,,

Figure B.4.3 Results of CEI02 (Ground)

IDSHIBA ENERGY SYS1EMS I SDUJTIDNS CORPORATION Nuclear Energy Systems & Services Division

111/151

, ........ ...... , ........ , ..

, ....... i

, ....

I I i I

10.0 u


8.5 Results of Radiated Susceptibility, Magnetic Fields (RS101)

Table BS Summary of test results for RS 101

Test Points Test Specimen Operation Compliant with Specification

Connector of LVPS Cable #18 Within the required tolerance of the normal

Yes operation


Yes operation


Yes operation

116mm from the left edge and 89 mm Within the required tolerance of the normal from bottom edge on the front Panel operation Yes of LPRM Unit 116mm from the right edge and 89 Within the required tolerance of the normal mm from bottom edge on the front operation Yes panel of LPRM Unit 116mm from the left edge and 89 mm Within the required tolerance of the normal from bottom edge on the back Panel operation Yes of LPRM Unit 116mm from the right edge and 89 Within the required tolerance of the normal mm from bottom edge on the back operation Yes panel of LPRM Unit 111 mm from the front panel and 89 Within the required tolerance of the normal mm from the bottom edge on the operation Yes right side wall of LPRM Unit 111 mm from the back panel and 89 Within the required tolerance of the normal mm from the bottom edge on the operation Yes right side wall of LPRM Unit 111 mm from the front panel and 89 Within the required tolerance of the normal mm from the bottom edge on the left operation Yes side wall of LPRM Unit 111 mm from the back panel and 89 Within the required tolerance of the normal mm from the bottom edge on the left operation Yes side wall of LPRM Unit 111 mm from the front panel and 116 Within the required tolerance of the normal mm from the right side wall on the operation Yes upper surface of LPRM Unit 111 mm from the front panel and 116 Within the required tolerance of the normal mm from the left side wall on the operation Yes upper surface of LPRM Unit 111 mm from the back panel and 116 Within the required tolerance of the normal mm from the right side wall on the operation Yes upper surface of LPRM Unit

mSHIBA ENERGY SYSilMS I SDUfflONS CORPORATION Nuclear Energy Systems & Services Division

112/151


Test Points Test Specimen Operation Compliant Specification

111 mm from the back panel and 116 Within the required tolerance of the normal mm from the left side wall on the operation Yes upper surface of LPRM Unit 111 mm from the front panel and 116 Within the required tolerance of the normal mm from the right side wall on the operation Yes bottom surface of LPRM Unit 111 mm from the front panel and 116 Within the required tolerance of the normal mm from the left side wall on the operation Yes bottom surface of LPRM Unit 111 mm from the back panel and 116 Within the required tolerance of the normal

mm from the right side wall on the operation Yes bottom surface of LPRM Unit

111 mm from the back panel and 116 Within the required tolerance of the normal mm from the left side wall on the operation Yes

bottom surface of LPRM Unit

Connector of LPRM Cable #128 Within the required tolerance of the normal

Yes operation

Connector of AO Cable #169 Within the required tolerance of the normal

Yes operation


Yes operation

Connector of DIO Cable #336 Within the required tolerance of the normal

Yes operation

116mm from the left edge and 89 mm Within the required tolerance of the normal from bottom edge on the front Panel operation Yes

of LPRM/APRM Unit 116mm from the right edge and 89 Within the required tolerance of the normal mm from bottom edge on the front operation Yes

panel of LPRM/APRM Unit 116mm from the left edge and 89 mm Within the required tolerance of the normal from bottom edge on the back Panel operation Yes

of LPRM/APRM Unit 116mm from the right edge and 89 Within the required tolerance of the normal mm from bottom edge on the back operation Yes

panel of LPRM/APRM Unit 111 mm from the front panel and 89 Within the required tolerance of the normal

mm from the bottom edge on the operation Yes right side wall of LPRM/APRM Unit 111 mm from the back panel and 89 Within the required tolerance of the normal

mm from the bottom edge on the operation Yes right side wall of LPRM/APRM Unit 111 mm from the front panel and 89 Within the required tolerance of the normal mm from the bottom edge on the left operation Yes

side wall of LPRM/APRM Unit

IDSHIBA ENERGY SYSTEMS I SDUITIDNS CORPORATION Nuclear Energy Systems & Services Division

113/151

with



111 mm from the back panel and 89 Within the required tolerance of the normal mm from the bottom edge on the left operation Yes

side wall of LPRM/APRM Unit 111 mm from the front panel and 116 Within the required tolerance of the normal

mm from the right side wall on the operation Yes upper surface of LPRM /APRM Unit 111 mm from the front panel and 116 Within the required tolerance of the normal

mm from the left side wall on the operation Yes upper surface of LPRM /APRM Unit

111 mm from the back panel and 116 Within the required tolerance of the normal mm from the right side wall on the operation Yes upper surface of LPRM/APRM Unit


upper surface of LPRM /APRM Unit

111 mm from the front panel and 116 Within the required tolerance of the normal mm from the right side wall on the operation Yes

bottom surface of LPRM /APRM Unit 111 mm from the front panel and 116 Within the required tolerance of the normal

mm from the left side wall on the operation Yes bottom surface of LPRM/APRM Unit 111 mm from the back panel and 116 Within the required tolerance of the normal

mm from the right side wall on the operation Yes bottom surface of LPRM/APRM Unit 111 mm from the back panel and 116 Within the required tolerance of the normal

mm from the left side wall on the operation Yes bottom surface of LPRM /APRM Unit

Connector of LPRM Cable #105 Within the required tolerance of the normal

Yes operation

Connector of AO Cable # 195 Within the required tolerance of the normal

Yes operation


Yes operation

Connector of AO Cable# 215 Within the required tolerance of the normal

Yes operation


Yes operation

116mm from the left edge and 89 mm Within the required tolerance of the normal from bottom edge on the front Panel operation Yes

of FLOW Unit 116mm from the right edge and 89 Within the required tolerance of the normal mm from bottom edge on the front operation Yes

panel of FLOW Unit


114/151



116mm from the left edge and 89 mm Within the required tolerance of the normal from bottom edge on the back Panel operation Yes

of FLOW Unit 116mm from the right edge and 89 Within the required tolerance of the normal mm from bottom edge on the back operation Yes

panel of FLOW Unit 111 mm from the front panel and 89 Within the required tolerance of the normal

mm from the bottom edge on the operation Yes right side wall of FLOW Unit

111 mm from the back panel and 89 Within the required tolerance of the normal mm from the bottom edge on the operation Yes

right side wall of FLOW Unit 111 mm from the front panel and 89 Within the required tolerance of the normal mm from the bottom edge on the left operation Yes

side wall of FLOW Unit 111 mm from the back panel and 89 Within the required tolerance of the normal mm from the bottom edge on the left operation Yes

side wall of FLOW Unit 111 mm from the front panel and 116 Within the required tolerance of the normal

mm from the right side wall on the operation Yes upper surface of FLOW Unit

111 mm from the front panel and 116 Within the required tolerance of the normal mm from the left side wall on the operation Yes

upper surface of FLOW Unit 111 mm from the back panel and 116 Within the required tolerance of the normal

mm from the right side wall on the operation Yes upper surface of FLOW Unit


upper surface of FLOW Unit 111 mm from the front panel and 116 Within the required tolerance of the normal

mm from the right side wall on the operation Yes bottom surface of FLOW Unit

111 mm from the front panel and 116 Within the required tolerance of the normal mm from the left side wall on the operation Yes bottom surface of FLOW Unit

111 mm from the back panel and 116 Within the required tolerance of the normal mm from the right side wall on the operation Yes

bottom surface of FLOW Unit 111 mm from the back panel and 116 Within the required tolerance of the normal

mm from the left side wall on the operation Yes bottom surface of FLOW Unit

Connector of FLOW Cables Within the required tolerance of the normal Yes

(#139,149) operation


Yes operation

IDSHIBA ENERGY SYSTEMS I SDUJrlONS CORPORATION Nuclear Energy Systems & Services Division

115/151

with




Yes operation


Yes operation


Yes operation

mSHIBA ENERGY SYS1EMS I SDUITIDNS CORPORATION Nuclear Energy Systems & Services Division

116/151


8.6 Results of High-Frequency Conducted Susceptibility Testing at AC Power Leads (CS 114)

Table B6 Summary of test results for CS 114 (Power)


Cable#9 and Cable#10 Within the required tolerance of the normal Yes

simultaneously operation

Cable #10 only Within the required tolerance of the normal

Yes operation

'L' lead of Cable #10 only Within the required tolerance of the normal

Yes operation

Note: Cable 9 is the Chassis ground. Cable 10 is the Chassis Power Lme (Hot), Neutral, and Ground Lines.


117/151


B. 7 Results of High-Frequency Conducted Susceptibility (Signal Leads) (CS114)

Table B7 Summary of test results for CS 114 (Signal)


Bundle of LPRM Cables Within the required tolerance of the normal Yes (#123~#134) operation

Bundle of LPRM Cables (#101 ~ Within the required tolerance of the normal Yes #110) operation Bundle of FLOW Cables Within the required tolerance of the normal Yes (#139,140) operation

DIO Cable #332 Within the required tolerance of the normal Yes operation

DIO Cable#333 Within the required tolerance of the normal Yes operation


Bundle of AO Cables Within the required tolerance of the normal Yes (#169, #195 and #228) operation Bundle of AO Cables Within the required tolerance of the normal Yes (#208 and #234) operation Bundle of AO Cables Within the required tolerance of the normal Yes (#182, #215 and #240) operation

IDSHIBA ENERGY SYS1IMS I SDUITIDNS CORPORATION Nuclear Energy Systems & Services Division

118/151

with


8.8 Results of Conducted Susceptibility (Signal Leads, Bulk cable injection, impulse excitation) (CS115)

Table B8 Summary of test results for CS 115


Bundle ofLPRM Cables Within the required tolerance of the normal Yes (#123"-'#134) operation

Bundle of LPRM Cables (#101 Within the required tolerance of the normal Yes "-'#110) operation Bundle of FLOW Cables Within the required tolerance of the normal Yes (#139,140) operation





IDSHIBA ENERGY SYSTEMS I SOUJTIDNS CORPORATION Nuclear Energy Systems & Services Division

119/151

with


8.9 Results of Conducted Susceptibility (Signal Leads, Damped sinusoidal transients) (CS 116)

Table B9 Summary of test results for CS 116 ; Compliant with Test Points Test Specimen Operation

Specification Bundle of LPRM Cables Within the required tolerance of the normal

Yes (#123-#134) operation Bundle of LPRM Cables Within the required tolerance of the normal Yes (#101-#110) operation Bundle of FLOW Cables Within the required tolerance of the normal Yes (#139,140) operation

010 Cable #332 Within the required tolerance of the normal Yes operation


010 Cable #336 Within the required tolerance of the normal Yes operation



120/151


8.10 Results of Surge Withstand Capability Testing

Table B 10.1 Summary of test results for Surge Withstand Capability (Ring wave)


'Line' and 'Neutral' Within the required tolerance of the normal

Yes operation

'Line' and 'Ground' Within the required tolerance of the normal Yes operation

'Neutral' and 'Ground' Within the required tolerance of the normal Yes operation

['Line' & 'Neutral'] and 'Ground' Within the required tolerance of the normal Yes operation

Note: The ring wave test was expected to be performed with 12 0 coupling impedance. This is the default setting of the test equipment and the most likely scenario. However, this is not described in the record and it cannot be reconfirmed that the test was performed with 12 0, not 30 0. If the possibility that the test was performed with 30 0 cannot be fully denied, in this possibility, the test results are not confirmed against 12 0 that brings more energy to the test specimen. Toshiba considers that it should be assumed that 30 0 was applied for the test to take conservative position for the appropriate evaluation in a situation where the impedance value cannot be confirmed. Toshiba considers that the assumption of 30 0 is appropriate, because the PRM is designed to be connected to the end of the power supply system in nuclear power plants. Therefore, Toshiba assumes either impedance is workable, and·that the higher impedance would not impact the surge withstand capabilities of the PRM.

Table BI0.2 Summary oftest results for Surge Withstand Capability (Combination Wave)


'Line' and 'Neutral' Within the required tolerance of the normal

Yes operation

'Line' and 'Ground' Within the required tolerance of the normal Yes operation

'Neutral' and 'Ground' Within the required tolerance of the normal Yes operation

IDSHIBA ENERGY SYSTEMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

121/151

with


B.11 Results of EFT/B Testing Table B 11 Summary of test results for EFT /B


'Line' Within the required tolerance of the normal

Yes operation

'Neutral' Within the required tolerance of the normal Yes operation

Ground' Within the required tolerance of the normal Yes operation

Line', 'Neutral' and 'Ground' Within the required tolerance of the normal Yes simultaneous operation

IDSHIBA ENERGY SYSTEMS I SDUfflONS CORPORATION Nuclear Energy Systems & Services Division

122/151

__J


B.12 Results of ESD Testing

Table B12 Test Results ofESD Test (1/9) Test Levels

Test Point without any Compliant with

Note temporary Specification degradations

LPRM Unit Contact Discharge On the right edge on the front surface of the +8kV

Yes chassis of LPRM Unit -8kV On the left edge on the front surface of the +8kV Yes chassis of LPRM Unit -8kV

On the top of the status module front panel +8kV Yes -8kV

On the mode key switch of LPRM module in +8kV Yes FSL-7 -8kV On the mode key switch of LPRM module in +8kV Yes FSL-1 -8kV

On the bottom of the status module front panel +8kV Yes -BkV

On the mode key switch of LPRM module in +8kV Yes FSL-12 -8kV On the surface of the connector of the signal +8kV Yes cable (No. 123) connected to the LPRM Unit -8kV On the surface of the connector of the optical +8kV Yes cable (No. 328) connected to the LPRM Unit -8kV On the fixing screw of the connector of the signal +8kV Yes cable (No. 169) connected to the LPRM Unit -8kV

On the fixing screw of the connector of the signal +8kV Yes cable (No. 182) connected to the LPRM Unit -8kV

On the fixing screw of the connector of the signal +8kV Yes cable (No. 336) connected to the LPRM Unit -BkV

mSHIBA ENERGY SYSTEMS & SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

123/151


Table B12 Test Results ofESD Test (2/9) Test Levels without

Compliant with Test Point any temporary Note degradations

Specification

LPRM Unit Air Discharge

On the "RESET" switch of the status module +15kV

Yes -15kV

On the upper side 3 digits LED indicator of +15kV Yes

LPRM module in FSL-1 -15kV On the lower side 3 digits LED indicator of +15kV

Yes LPRM module in FSL-1 -15kV On the mode "SELECT" switch of LPRM +15kV

Yes module in FSL-1 -15kV

On the"+" switch of LPRM module in FSL-1 +15kV

Yes -15kV

On the "-" switch of LPRM module in FSL-1 +15kV

Yes -15kV

On the"~" switch of LPRM module in FSL-1 +15kV

Yes -15kV

On the "RESET" switch of LPRM module in +15kV Yes

FSL-1 -15kV On the "SET" switch of LPRM module in +15kV

Yes FSL-1 -15kV On the upper side 3 digits LED indicator of +15kV

Yes LPRM module in FSL-7 -15kV On the lower side 3 digits LED indicator of +15kV

Yes LPRM module in FSL-7 -15kV On the mode "SELECT" switch of LPRM +15kV



Yes -15kV

On the"-" switch of LPRM module in FSL-7 +15kV

Yes -15kV


Yes -15kV


FSL-7 -15kV

On the "SET" switch of LPRM module in +15kV Yes

FSL-7 -15kV

On the upper side 3 digits LED indicator of +15kV Yes

LPRM module in FSL-12 -15kV

On the lower side 3 digits LED indicator of +15kV Yes

LPRM module in FSL-12 -15kV

IDSHIBA ENERGY ffl1EMS I SOWTIDNS CORPORATION Nuclear Energy Systems & Services Division

124/151


Table B 12 Test Results of ESD Test (3/9)

Test Point Test Levels without any Compliant with

Note temporary deQradations Specification LPRM Unit Air Dischari:te (Continued) On the mode "SELECT" switch of LPRM +15kV



Yes -15kV

On the"-" switch of LPRM module in FSL-12 +15kV

Yes -15kV


Yes -15kV


FSL-12 -15kV On the "SET" switch of LPRM module in +15kV

Yes FSL-12 -15kV On the surface of the connector of the power +15kV

Yes cable connected to the LVPS-1 module -15kV On the surface of the connector of the power +15kV

Yes cable connected to the LVPS-2 module -15kV LPRM Unit Indirect Dischari:te

Left vertical side of the LPRM Unit +BkV Yes -BkV

Right vertical side of LPRM Unit +BkV Yes -BkV

Back vertical side of LPRM Unit +BkV Yes -BkV

Front vertical side of LPRM Unit +BkV Yes -BkV

IDSHIBA ENERGY SYSTEMS I SDUITIDNS CORPORATION Nuclear Energy Systems & Services Division

125/151



Compliant Test Point without any

with Note temporary Specification

degradations LPRM/APRM Unit Contact Discharge On the right edge on the front surface of the +BkV Yes chassis of LPRM/APRM Unit -BkV On the left edge on the front surface of the +BkV Yes chassis of LPRM/APRM Unit -BkV

On the top of the status module front panel +BkV Yes -SkV

On the bottom of the status module front panel +BkV Yes -BkV

On the mode key switch of LPRM module in +BkV Yes FSL-1 -BkV On the mode key switch of LPRM module in +BkV Yes FSL-10 -BkV

On the mode key switch of APRM module in +BkV Yes FSL-11 -BkV On the surface of the connector of the signal

+BkV Yes cable (No. 101) connected to the

-BkV LPRM/APRM Unit

On the surface of the connector of the optical Yes Temporary

cable (No. 330) connected to the +2kV Degradation was -2kV observed at +4/-4

LPRM/APRM Unit kV levels

On the fixing screw of the connector of the Yes +BkV

signal cable (No. 195) connected to the -BkV

LPRM/APRM Unit

On the fixing screw of the connector of the Yes signal cable (No. 208) connected to the +BkV LPRM/APRM Unit -BkV

On the fixing screw of the connector of the Yes Temporary signal cable (No. 215) connected to the +4kV Degradation was LPRM/APRM Unit -4kV observed at +6/-6

kV levels

On the fixing screw of the connector of the Yes Temporary +OkV Degradation was

signal cable (No. 332) connected to the -4kV observed at +2/-4

LPRM/APRM Unit kV levels


126/151


Table Bl2 Test Results ofESD Test (5/9) Test Levels without

Compliant with Test Point any temporary Note degradations Specification

LPRM/APRM Unit Air Discharae On the "RESET" switch of the status +15kV

Yes module -15kV On the upper side 3 digits LED +15kV

Yes indicator of LPRM module in FSL-1 -15kV On the lower side 3 digits LED indicator +15kV

Yes of LPRM module in FSL-1 -15kV On the mode "SELECT" switch of +15kV

Yes LPRM module in FSL-1 -15kV On the "+" switch of LPRM module in +15kV

Yes FSL-1 -15kV On the "-" switch of LPRM module in +15kV

Yes FSL-1 -15kV On the ...... switch of LPRM module in +15kV

Yes FSL-1 -15kV On the "RESET" switch of LPRM +15kV

Yes module in FSL-1 -15kV On the "SET" switch of LPRM module +15kV

Yes in FSL-1 -15kV On the upper side 3 digits LED +15kV

Yes indicator of LPRM module in FSL-10 -15kV On the lower side 3 digits LED indicator +15kV

Yes of LPRM module in FSL-10 -15kV On the mode "SELECT" switch of +15kV

Yes LPRM module in FSL-10 -15kV On the "+" switch of LPRM module in +15kV

Yes FSL-10 -15kV On the "-" switch of LPRM module in +15kV

Yes FSL-10 -15kV On the ...... switch of LPRM module in +15kV

Yes FSL-10 -15kV On the "RESET" switch of LPRM +15kV

Yes module in FSL-10 -15kV On the "SET" switch of LPRM module +15kV

Yes in FSL-10 -15kV On the upper side 3 digits LED +15kV

Yes indicator of APRM module in FSL-11 -15kV On the middle side 3 digits LED +15kV

Yes indicator of APRM module in FSL-11 -15kV On the lower side 3 digits LED indicator +15kV

Yes of APRM module in FSL-11 -15kV


127/151



Compliant with Test Point any temporary Note

deoradations Specification

LPRM/APRM Unit Air Discharae On the "mode SELECT" switch of +15kV

Yes APRM module in FSL-11 -15kV


128/151




degradations Specification

LPRM/APRM Unit Air Discharge (Continued)

On the upper "SELECT" switch of APRM +15kV Yes module in FSL-11 -15kV

On the lower "SELECT" switch of APRM +15kV Yes module in FSL-11 -15kV

. On the"+" switch of APRM module in FSL-11 +15kV

Yes -15kV

On the"-" switch of APRM module in FSL-11 +15kV

Yes -15kV

On the"~" switch of APRM module in FSL-11 +15kV

Yes -15kV

On the "RESET" switch of APRM module in +15kV Yes FSL-11 -15kV

On the "SET" switch of APRM module in +15kV Yes FSL-11 -15kV

On the surface of the connector. of the power +15kV Yes cable connected to the LVPS-1 module -15kV

On the surface of the connector of the power +15kV Yes cable connected to the LVPS-2 module -15kV

LPRM/APRM Unit Indirect Discharge

Left vertical side of the LPRM/APRM Unit +8kV

Yes -8kV

Right vertical side of LPRM/APRM Unit +8kV

Yes -8kV

Back vertical side of LPRM/APRM Unit +8kV

Yes -8kV

Front vertical side of LPRM/APRM Unit +8kV

Yes -8kV

MSHIBA ENERGY SYSTEMS I SDUITIDNS CORPORATION Nuclear Energy Systems & Services Division

129/151



Test Point without any Compliant with Note

temporary Specification degradations

FLOW Unit Contact Dischan:1e

On the right edge on the front surface of the +8kV Yes chassis of FLOW Unit -8kV ·.

On the left edge on the front surface of the +8kV Yes

chassis of FLOW Unit -8kV

On the top of the status module front panel +8kV

Yes -8kV

On the bottom of the status module front panel +8kV

Yes -8kV

On the mode key switch of FLOW module in +8kV Yes

FSL-12 -8kV On the surface of connector of the signal cable +8kV (No. 139 and No.140) connected to the FLOW

-8kV Yes

Unit Temporary

On the surface of the connector of the optical +4kV Yes

Degradation was cable (No. 330) connected to the FLOW Unit -2kV observed at +6/-4 kV

levels

On the fixing screw of the connector of the signal +8kV Yes

cable (No. 228) connected to the FLOW Unit -8kV





On the fixing screw of the connector of the signal +8kV Yes cable (No. 333) connected to the FLOW Unit -8kV


130/151

FPG-TRT-CS 1-0101 Rev. 3



degradations Specification

FLOW Unit Air Discharge On the "RESET" switch of the status +15kV

Yes module -15kV On the upper side 3 digits LED indicator +15kV

Yes of FLOW module in FSL-12 -15kV On the middle side 3 digits LED indicator +15kV

Yes of FLOW module in FSL-12 -15kV On the bottom side 3 digits LED indicator +15kV

Yes of FLOW module in FSL-12 -15kV On the "+" switch of FLOW module in +15kV

Yes FSL-12 -15kV On the "-" switch of FLOW module in +15kV

Yes FSL-12 -15kV On the "~" switch of FLOW module in +15kV

Yes FSL-12 -15kV On the "RESET" switch of FLOW module +15kV

Yes in FSL-12 -15kV On the "SET" switch of FLOW module in +15kV

Yes FSL-12 -15kV On the "SELECT" switch of SQ-ROOT +15kV

Yes module in FSL-11 -15kV On the "mode SELECT" switch of FLOW +15kV


IDSHIBA ENERGY SYSTEMS I SOLUTIONS CORPORATION Nuclear Energy Systems & Services Division

131/151


Table B12 Test Results ofESD Test (9/9)

Test Point Test Levels without any Compliant with Note

temporary degradations Specification FLOW Unit Air Discharge (Continued) On the upper side 3 digits LED +15kV indicator of SQ-ROOT module in Yes FSL-11 -15kV

On the lower side 3 digits LED +15kV indicator of SQ-ROOT module in Yes FSL-11 -15kV

On the "RESET" switch of SQ-ROOT +15kV Yes module in FSL-11 -15kV

On the volume knob of SQ-ROOT +15kV Yes module in FSL-11 -15kV

On the surface of the connector of +15kV the power cable connected to the Yes LVPS-1 module -15kV

On the surface of the connector of +15kV the power cable connected to the

-15kV Yes

LVPS-2 module FLOW Unit Indirect Discharge

Left vertical side of the FLOW Unit +8kV

Yes -8kV

Right vertical side of FLOW Unit +8kV

Yes -8kV

Back vertical side of FLOW Unit +8kV

Yes -8kV

Front vertical side of FLOW Unit +8kV

Yes -8kV

IDSHIBA ENERGY ffl1EMS & SDUJTIONS CORPORATION Nuclear Energy Systems & Services Division

132/151


8.13 Results of Class 1 E to Non-1 E Isolation Testing

Table BI3.I Summary oftest results for Class IE to Non-IE Isolation for 600VAC


Between pin D and pin K of the output connector { ]" c Within the required tolerance of the normal

Yes [ Jot HNS518 AO module operation installed in BSL 1 of LPRM Unit Between pin N and pin T of the output connector { ]" c Within the required tolerance of the normal

Yes [ Jot H NS515 AO module operation installed in BSL3 of LPRM Unit

Between pin JJ and pin PP of the output connector { ]"

C

[ Jot HNS518 AO module Within the required tolerance of the normal

Yes installed 'in BSL 1 of LPRM/APRM

operation

Unit

Between pin JJ and pin PP of the Within the required tolerance of the normal output connector { ]" c operation [ Jot HNS516 AO module Yes installed in BSL2 of LPRM/APRM Unit Between pin A and pin E of the Within the required tolerance of the normal output connector { ]" c operation [ Jot HNS515 AO module Yes installed in BSL3 of LPRM/APRM Unit Between pin L and pin R of the output connector { ]"

C

[ Jot HNS518 AO module Within the required tolerance of the normal

Yes installed in BSL 1 of FLOW Unit

operation

Between pin L and pin R of the output connector { ]" c Within the required tolerance of the normal

Yes [ Jot HNS516 AO module operation installed in BSL2 of FLOW Unit Between pin L and pin R of the Yes output connector { ]" c Within the required tolerance of the normal [ Jot HNS517 AO module operation installed in BSL3 of FLOW Unit

IDIHIBA ENERGY SYSTEMS & SDUITIDNS CORPORATION Nuclear Energy Systems & Services Division

133/151


Table B13.2 Summary oftest results for Class lE to Non-IE Isolation for 250VDC

Test Points Test Specimen Operation Compliant · Specification

Between pin D and pin K of the output connector ( ]" c Within the required tolerance of the normal

Yes [ Jot HNS518 AO module operation installed in BSL 1 of LPRM Unit Between pin N and pin T of the output connector ( ]" c Within the required tolerance of the normal

Yes [ Jof HNS515 AO module operation installed in BSL3 of LPRM Unit

Between pin JJ and pin PP of the output connector ( ]"

C

[ Jof HNS518 AO module Within the required tolerance of the normal

Yes installed in BSL 1 of LPRM/APRM

operation

Unit

Between pin JJ and pin PP of the Within the required tolerance of the normal output connector ( ]" c operation [ Jof HNS516 AO module Yes installed in BSL2 of LPRM/APRM Unit Between pin A and pin E of the Within the required tolerance of the normal output connector ( ]" c operation [ Jof HNS515 AO module Yes installed in BSL3 of LPRM/APRM Unit Between pin L and pin R of the output connector ( ]"

C

[ Jof HNS518 AO module Within the required tolerance of the normal

Yes installed in BSL 1 of FLOW Unit

operation

Between pin L and pin R of the output connector ( ]" c Within the required tolerance of the normal

Yes [ Jof HNS516 AO module operation installed in BSL2 of FLOW Unit Between pin L and pin R of the output connector ( ]" c Within the required tolerance of the normal

Yes [ Jof HNS517 AO module operation installed in BSL3 of FLOW Unit

mSHIBA ENERGY SYSTEMS I SOUJTIDNS CORPORATION Nuclear Energy Systems & Services Division

134/151

with


APPENDIX C Details of the Operability Test and the Prudency Test


135/151

Table C 1 Description ofEPRI-TR-107330 Table 5-1 and Detailed Scope and Timing of PRM Operability Tests

J~sg:~[1~ti,oiiC(~.~~,\2~ ', . quaUfi~atioh test~r · .

Pre-Qualification Test(Base Line)

Radiation Exposure

Environmental

Test

Before High

Temperature and High Humidity Exposure

'

.... ,· ·" •.·

§c9pe "'''

"All"

No Description

A. Accuracy

B. Response time

C. Discrete input operability

D. Discrete output operability

E. Communication operability

F. Coprocessor operability

G. Timer Tests

H. Test of failure to complete scan

detection

I. Failover Operability Tests

J. Loss of power test

K. Power Interrupt Test.

----------No Description A. Accuracy

B. Response time




(1), (2), (3), (7)

(4), (5), (6)

(9)

( 4), (5), (6), (8)

Confirm no communication alarms

occurred

NIA

NIA

(13), (14), (15)

(10), (11), (12), (16)

(17)

(18)

(2), (7)

(5)

Response time measurement of

TPM H, in which the TPM time

constant is set to[ J~cond was not

performed

(9)

(5)


occurred.


136/151


The PRM does not use coprocessors.

The PRM does not provide any separate timer

functions.

--------See Note B (i)

See Note B (ii)

See Note B (v)

--------

· T~st <;:ondition(Toshiba

qualific~tion.Je~is)

During High Temperature

and High

Humidity Exposure

After (End of) High

Temperature

and High

Humidity

Exposure


. ', ' , . . ,, Description of'tR-J07330 'rable·5~i

I,

Operability Test for PRM . . '. Op~~ability fe. sts ($e.ction.5.3)_ ·..... . · ..

... ' . ' . . ' . ,,. ' 7 .. ' .• ,,. ' . ' ' ' ' .·• ' .' "' •·. <:.

No Description

"ALL" at the point per

Figure 4-4


G. Timer Tests


detection


NIA The PRM does not use coprocessors.

NI A The PRM does not provide any separate timer function.

Test Items (13), (14), and (15) were See Note B (iii)

not performed.

(16)

Test Items (10), (11), and (12) were

not performed.

See Note B (iv)

J. Loss of power test (17)

K. Power Interrupt Test. (18)

~~ A. Accuracy

B. Response time





(2), (7)

(5)



constant is set to[ Js'econd was not

performed

(9)

(5)

Confirmed no communication

alarms occurred.

NIA

Toshiba monitored the equipment operation during the tests. Table C 4 in this Appendix shows the

acceptance criteria for the output signals.

See Note B (i)

See Note B (ii)

See Note B (v)

--------The PRM does not use coprocessors.


137/151

Tcisj qhnditicni(Tosliip~

. , R4:a11fi~~tia~ t~·s1~\l(: .. : . p·e~cription ofTR:J07330 Table5;-J

·: :\\6perabliity'.f~~t{(S~~ti6n 5.3) ' . '~";.'~'" ,;,:;," . ,' ,., '"'--"~ '-::,, " . ., . '

G. Timer Tests



function.


detection

Test Item (13), (14), and (15) were See Note B (iii)

During Low

Temperature

Exposure

After (End of)

Low Temperature

Exposure




No Description

"ALL" at the A. Accuracy

point per

Figure 4-4 B. Response time





G. Timer Tests

not performed.

(16)


not performed.

(17)

(2), (7)

(5)



constant is set to[]s~cond was not

performed

(9)

(5)


alarms occurred.

NIA

NIA


138/151

See Note B (iv)

Toshiba monitored the equipment operation during

the tests. Table C 4 in this Appendix shows the


See Note B (i)

See Note B (ii)

See Note B (v)



functions.

Test Coh<lition(Tbshiba ·

quali±ic~tion tests f ...

. Des,~ription of'T,]{.:I07pgT,abl(~-':J : . · Op~rabilify_T¢st~ (Se:ctioI1 5.3): : · · ·

Test Iterii •


.

P!!i:fClrllled Tes,(:?, (S(,e Note A at the ~cop~, .. .. , ....... "_, .. . : .. ·· · · · · · ·· ·· · · · · Justjfication/.Etis'lariatiqn

. , •. .: ·· . end qfTable) •••- .. . . -•. · ••• .· .. · ... ·. ;'. . ··. .r · ·• · :. : .· ..

During Low

Humidity

Exposure

After (End of)

Low Humidity

Exposure

No Description

"ALL" at the

point per

Figure 4-4


detection





not performed.

(16)


not performed.

(17)

(18)

See Note B (iv)

~~ Toshiba monitored the equipment operation during

the tests. Table C 4 in this Appendix shows the


A. Accuracy

B. Response time





G. Timer Tests


detection


(2), (7)

(5)



constant is set to[]s·econd was not

performed

(9)

(5)

Confmned no communication

alarms occurred.

NIA

NIA

See Note B (i)

See Note B (ii)

See Note B (v)


not performed.

(16) See Note B (iv)


not performed.


139/151

.

...

:rest C:ondition(Tgshiba

. \q1,1alifi,c;afip11 t;~t~) ' '

After all

Environmental

;. ··•

"ALL" at the

point per

Figure 4-4



A. Accuracy

B. Response time





G. Timer Tests


detection

(18)

(2), (7)

(5)



constant is set to[Jecond was not

performed

(9)

(5)


alarms occurred.

NIA

NIA


not performed.


.,.,.,, --• y/.-<·

' -:

See Note B (i)

See Note B (ii)

See Note B (v)

-------The PRM does not use coprocessors.


functions.

See Note B (iii)

' .. · .. •:,,:::.

' ':

I. Failover Operability Tests (16) See Note B (iv)

Seismic Test Before Seismic

Test

No Description

"All"


not performed.



A. Accuracy


140/151

qualific:a,tion tests) . t, :. Scope . T~~t'It~rn,:

..... \:. : ' " ·. ,,': : . ':,.,. , ;:: " ''""''': ·: , .. , .. ::,'<

During Seismic

Test

After Seismic Test

"All"

B. Response time




F. Coprocessor operability ,__ ____________ _, No operability test was performed

G. Timer Tests


detection




A. Accuracy

B. Response time





G. Timer Tests


detection

but output signals are monitored.

(1), (2), (3), (7)

( 4),(5),(6)

(9)

( 4),(5),(6),(8)


occurred

NIA

NIA

(13), (14), (15)

I. Failover Operability Tests (10), (11), (12), (16)




••• , : • ' : ; <

<,

, C<•

Due to the short duration of the seismic tests,

Operability Tests cannot be performed during the

seismic event. Toshiba chose to monitor the equipment operation during the test and performed

the operability tests before and after the tests to

ensure that the PRM remained operable during and

after the seismic event.

The acceptance criteria during the Seismic test is

described in the Seismic test procedure.

The analog outputs and discrete outputs of each unit

are set as shown in Table C 3 in this Appendix with

their acceptance criteria.



functions.

Exchange of Modules (LPRM Modules was exchanged for HNSO 13 from HNSOl 1. AO Modules was exchanged for HNS515151615171518 from HNS5 l l/512l513l5 l4.


141/151

'"··

> .· Te,st CCll).~itigp(Toshib11

· " qtialifi6ati6ii te_sts Y: · .•,, ..

EMC Test Before EMC

Test

During EMC

Test


No Description A Accuracy (1), (7) The LPRM and AO modules were modified to

B. Response time





G. Timer Tests


detection




Test Items (2) and (3) were not

performed.

(4)


performed.

(9)

( 4), (8)


performed.


alarms occurred

NIA

NIA

(13), (14)

Test Item (15) was not performed.

Test Items (13) and (14) were only

performed for the LPRM module.

(10), (11), (12)

Test (16) was not performed.

(17)

(18)

enhance immunity against EMC.

As a test after modification, accuracy was tested

using worst case configuration for the LPRM

modules.

The LPRM and AO modules were modified to




modules.

Because modification to the LPRM and AO

modules does not influence discrete outputs, Tests

( 4) and (8) are sufficient.



functions.

Because the LPRM module was the only module

that was modified and contained FPGAs.

Because the LPRM module and AO modules were

only modules that were modified.

"All except A" ,__A_. _A_c_c_ur_a_cy _________ ,__ ___________ _____, Due to the special set-up required for the EMC

B. Response time The operability tests were not tests, Operability Tests cannot be performed during

performed. EMC testing. Toshiba chose to monitor the '--------------'-'"----------------'


142/151

..

.. Te~tCondition(To~liiba

. :',qualification tes,ts)


' ,,·, ,. :_ '. , • , , • ,, ' • ' " • '<> ,, ' ~- '" :

· Description cifTR'-:107330 Table g,l . bp~rability Jests (Section !qf ' "' '. : , : .',' : ~ . •, ;; ."'.,'" .

OperabilifyT¢st for PRM < . ' '., .•. ' ', .. ,. ' ' •. ',

' Scope<. ' ' ,,,, Tekdt~~

'-"·:r·,rc-: ,·<:

C. Discrete input operability The operability tests were not equipment operation during the test and perform the ,__ _____________ _,__,p_e_rfi_o_rm_e_d. _________ __, operability tests before and after the tests to ensure

D. Discrete output operability The operability tests were not that the PRM remained operable during and after performed. the EMC testing.

E. Communication operability Confirmed no communication Table C 5 in this Appendix shows the acceptance alarms occurred criteria for the output signals. t---------------+-----------------1


G. Timer Tests

H. Test of failure to complete scan detection




NIA

NIA

The operability tests were not performed.

The operability tests were not

performed.


performed.


performed.

After EMC Test "All" A. Accuracy The operability tests were not Tests were carried out as Post Qualification Tests (After re-exchange of modules).

Isolation Test(Class 1E to Non

Class 1E Isolation Test)

No Description

,__ ____________ ___,

B. Response time performed.




F. Coprocessor operability .

G. Timer Tests


detection




Note: Toshiba conducted Class 1E to Non Class 1E Isolation Test


143/151


" .. : i ,,,

.

Post Qualification Test(Before re- No Description A. Accuracy (1), (7) The LPRM and AO modules were modified to

exchange of modules)

B. Response time





G. Timer Tests


detection


Tests (2) and (3) were not

performed.

(4)


performed.

(9)

( 4), (8) Test Items (5) and (6) were not

performed.


alarms occurred

NIA

NIA

(13), (14)


Test Items (13) and (14) were

performed only on LPRM module.

(10), (11), (12)


J. Loss of power test ( 17)





modules.

The LPRM and AO modules were modified to




modules.

Because modification to the LPRM and AO

modules does not influence discrete outputs, Tests

( 4) and (8) are sufficient.



functions.

Because the LPRM module was the only module

that was modified and contained FPGAs.

Because the LPRM module and AO modules were

only modules that were modified.

Re-Exchange of Modules (LPRM Modules was exchanged for HNS011 from HNS013. AO Modules was exchanged for HNS51ll512l51315 l4 from HNS5151516l517l5 l8.

No Description A. Accuracy (1), (2), (3), (7)


144/151

FPG-TRT-C51-0101 Rev.3 '.,

·.·' ,·,·

"

Description ofTR•l07330 Tabk5~1

Test Conditioii(Tosluba · Opyral:Jility Tests (Sectiori5jj ·• OperabilityTest for PRM

' • ," •• • '" < " '·, '"''

, .. '" ·''

" ,,. " qualifica,tion tests) ,,,' '. -,,·> , c·,C

P.~;cfQ~~~~ T\<~ts (S,ey NC?tr 4 at tliy ... ,'

1 ·Scope:. . Tesdtem ,,.·:.,,,;•[': ... ' J u~tifi~atfon/ExphmatiQri; ,.

,: ·:,',;",; ,: ', elid•gf:Table) ··.,,, ·, .'.}·; ,, ". .. , ' :\:;.c· ·.:.,, ,, '

'' '

B. Response time (4), (5), (6)

C. Discrete input operability (9)

D. Discrete output operability (4), (5), (6), (8)

E. Communication operability Confirmed no communication alarms occurred

F. Coprocessor operability NIA Post-Qualification Test(After re-

G. Timer Tests NIA exchange of modules)

H. Test of failure to complete scan (13), (14), (15) detection

I. Failover Operability Tests (10), (11), (12), (16)



Note A ( 1) Linearity test for APRM level, TPM level, and LPRM level at the LPRM gains 40 µA/100% (2) Linearity test for APRM level, TPM level, and LPRM level at the LPRM gains 400 µA/100% (3) Linearity test for APRM level, TPM level, and LPRM level at the LPRM gains 2400 µA/100% ( 4) APRM Upscale (High-High) trip and TPM Upscale trip response time test at the LPRM gains 40 µA/100% (5) APRM Upscale (High-High) trip and TPM Upscale trip response time test at the LPRM gains 400 µA/100% (6) APRM Upscale (High-High) trip and TPM Upscale trip response time test at the LPRM gains 2400 µA/100% (7) Linearity test for FLOW level (8) APRM Inoperable trip function test (9) DI function test (10) Low voltage power supply failure test for the LPRM unit (11) Low voltage power supply failure test for the LPRM/APRM unit (12) Low voltage power supply failure test for the FLOW unit (13) Watchdog function test for the LPRM unit (14) Watchdog function test for the LPRM/APRM unit (15) Watchdog function test for the FLOW unit (16) Current value test of the Square Root module in the FLOW unit ( 17) Loss of power test (18) Power interruption test


145/151

.. ;(;:•;,,·, '' ,; . ·.::: .... ;., ,· '·: ' ,: '' "i .· ..


The PRM does not provide any separate timer functions.


NoteB (i) Test Items (1) and (3) were not performed, because the LPRM gain or the leal setting change can be made only by manual operation on the front panel, which was not accessible while

the PRM was in the chamber. Fresh LPRM detectors send over 400 µA signals to the LPRM module, and the signal level decreases by aging in the core. Toshiba chose 400 µA setting as the leal value, which is

generated to simulate the LPRM detectors signal for testing. The LPRM module is calibrated using data from a Traversing In-core Probe (TIP) in actual plants.

The lea! setting is implemented by selecting one resistor from a resistor array in the input of each LPRM module. Since all three selectable resistors are in the same resistor array and all

selectable resistors were tested in the factory test, Toshiba selected the 400 µA setting that is the most commonly used in actual operation due to the limitation mentioned above.

Toshiba chose to confirm the accuracy of the PRM for all lea! settings in the Post qualification testing. Toshiba did not observe any degradation in accuracy for all lea! settings.

(ii) Test ( 4) and (5) with the TPM time constant[J;·~cond were not performed, because the TPM time constant can be changed only by manual operation on the front panel of the PRM

module, which was not accessible while the PRM was in the chamber. Toshiba set the TPM time constant to 6 seconds, which is consistent with Toshiba recommendations for the initial

value in the plant.

(iii) Test (13), (14), and (15) were not performed, because the watchdog function test requires intentionally expiring the watchdog timer by removing a jumper pin on the PC board of the

test specimen and stop the reset signals from FPGAs to the watchdog timer. This was not possible while the PRM was in the chamber. Instead, Toshiba monitored the equipment operation

during the tests. An alarm was generated by the watchdog timer when the jumper pin was removed.

(iv) Test (10), (11), and (12) were not performed, because the output voltage of the LVPS module, which is in the chamber, can be changed only by manual operation on the front panel of

the L VPS module. Toshiba monitored the equipment operation during the tests. An alarm is generated when the voltage ofLVPS module was lowered.

(v) Tests ( 4) and (6) were not performed, because the LPRM gain or the lea! setting change can be made only by manual operation on the front panel, which was not accessible while the

PRM was in the chamber. Since the lea! value does not influence discrete output operability, Test (5) is sufficient to ensure discrete output operability.

Test (8) was not performed, because the APRM Inoperable trip is generated only by manual operation on the front panel of the APRM or LPRM modules. The operation changes the mode

of the APRM or LPRM module to other than "OP," and makes the number of the operable LPRM modules, i.e., LPRM modules in the "OP" mode, less than the "minimum number of

operable LPRM modules" set value. Toshiba monitored the equipment operation during the tests. An inoperable signal is generated when the mode of the APRM module and LPRM

modules were changed.


146/151

Table C 2 Description ofEPRI-TR-107330 Table 5-1 and Detailed Scope and Timing of PRM Prudency Tests

Test ¢ondition(Tostib~ · quai~(i~~tion te~ts) :- . . ....

Pre-Qualification Test(Base Line)

Radiation Exposure

Environmental Before High Test Temperature and

High Humidity

Exposure

During High

Temperature and

High Humidity

Ex osure

After( End of) *)High

Temperature and High Humidity

Exposure

_Desc:riptio_nofTR'.~1onJqTable_5~1 .Prµtl~li~y°Tests(Settioiif4) .. ;, < X :, ,<, X \:, < : ; ' •,, a' ',' '• ~' ,.~" 0 > \ C

testl>tiint

"All"

No Description

No Description

No Description

"ALL at end of

high temp/RH only"

'·Item A Burst of events test.

B. Failure of serial port receiver test.

C. Serial port noise test.

D. Fault simulation.

A Burst of events test.

B. Failure of serial port receiver test.


(19), (20)

NIA

NIA

(21)

(19), (20)

NIA

NIA


147/151


There is no serial port receiver in the PRM.

The Toshiba NRW-FPGA-based PRM uses fiber

optic links.

The test was performed during the operability test.

(Note A (10), (11), and (12)) Failure simulation test is to disconnect the one AC Power source for L VPS I module of each test specimen unit.


The Toshiba NRW-FPGA-based PRM uses fiber

optic links.

_J

Test.Conditiori(Toshiba

qtalif{9~t,iqn tests) · · Description of TR-1073.JQ'J:able 5-1 Pr~dy~cy ,'f ests(Se9ti9~t4): ·; ...

Seismic Test

During Low Temperature Exposure

No Description

After (End of)*) No Description

Low Temperature Exposure

During Low No Description

Humidity

Exposure

After (End of)*) No Description

Low Humidity Exposure

After*) all Environmental

Before Seismic Test

During Seismic

Test

No Description

No Description

"All"

After Seismic "None"

Test

D. Fault simulation. The tests were not performed.

A. Burst of events test. The all Prudency tests were not t-------------,

B. Failure of serial port performed.

receiver test.




Test (21) was not performed because the AC Power

of the test specimen in the chamber could not be disconnected.

Toshiba chose to monitor the equipment operation

during the test. Table C 4 in this Appendix shows

the acceptance criteria for the output signals. An

alarm is generated when the voltage was lowered.

Due to the short duration of the seismic tests,

Prudency Tests cannot be performed during the

seismic event. Toshiba chose to monitor the

equipment operation during the test.

Exchange of Modules (LPRM Modules was exchanged for HNSO 13 from HNSOI l. AO Modules was exchanged for HNS515/516/5 l 7 /518 from HNS5 ll/512/513/514.

EMC Test Before EMC Test No Description


148/151

Test'<::ohdition(Toshibti. < qualification tests~ <

Description ofTR0 l07330 Table s~1 ', Pnid~ncr Tests(SectioI15.4). .

During EMC Test "A only"

After EMC Test Isolation Test(Class 1E to Non 1E Test) Post Qualification Test(Before reexchange of modules)

"None"

No Description

No Description

Prude#p)."Test

The tests were not performed.


Due to the special set-up required for the EMC tests, Prudency Tests cannot be performed during EMC testing. Toshiba chose to monitor the equipment operation during the test and perform the operability tests before and after the tests to ensure that the PRM remained operable during and after the EMC testing. Table C 5 in this Appendix shows the acceptance criteria for the output signals.

Re-Exchange of Modules (LPRM Modules was exchanged for HNS011 from HNS013. AO Modules was exchanged for HNS51ll512l513l514 from HNS515l516l517l518.

Post-Qualification Test(After reexchange of modules)

Note: Prudency Test item (19) DI Toggling test (20) AI Toggling test (21) Failure simulation test

No Description · A. Burst of events test.

B. Failure of serial port receiver test. C. Serial port noise test.


(19), (20)

NIA

NIA

(21)


149/151


The Toshiba NRW-FPGA-based PRM uses fiber optic links.

The test was performed during the operability test. (Note A (10), (11), and (12)) Failure simulation test is to disconnect the one AC Power source for L VPS I module of each test specimen unit.


Table C 3 Acceptance Criteria for Output Signals Monitored during Seismic Test of the PRM

.;'l)gget, Viil.iie '"'

•.;itrts~tt:i:ttt~ttttl!!::~i:1,•·:· .. . , .. Ac,sipfa?.~~ mit~r"if.c;:.,:':, .: (F9r an~l'.9) £t1~µls, ~c,c:~?t~~lt:, qeviatioiif[om the targefval,ii~}

Analog output LPRM # 1 in LPRM/ APRM unit

APRM in LPRM/APRM unit

TPM in LPRM/ APRM unit

FLOW in LPRM/ APRM unit

LPRM # 1 in LPRM unit

Loop a FLOW in FLOW unit

FLOW in FLOW unit

Discrete output APRM FAIL in LPRM/ APRM unit

APRM !NOP in LPRM/APRM unit

APRM High-High in LPRM/APRM unit

TPM High in LPRM/ APRM unit

i>~tp.ut,signal b~ciim~:·~~:th~ target v~l~i · .. shown: below) ,,L.

Occurred*

Not Occurred

Not Occurred

Not Occurred

Not change

Not change

Not change

Not change

* To simulate the APRM Fail during seismic test, removed the [

[ . ]Norn the FLOW Unit.

]from the LPRM/APRM Unit during the seismic test. The

Table C 4 Acceptance Criteria for Output Signals Monitored during Environmental Test of the PRM

Time

(min)

0-15

15-30

30-45

45-60

Note:

Input

Current Current

(µA) (mA)

FLOW Output TPMHigh Set

Output (Computer) point

(Computer) (mV) (Computer)

(mV) (mV)

1) TPM Output is a first order lag of APRM Output with 6 seconds time constant.

2) APRM High-High trip occurs about 40 ms after the change of LPRM Signal.

3) TPM High trip occurs about 40 ms after the TPM Output change.


150/151

APRM TPMHigh

High-High Trip

Trip Discrete

Discrete Output

Output

"· · Not Occur2> Not Occur3>

Not Occur Not Occur

Occur2> Occur3>

Occur Occur

APRM

INOP

Discrete

Output

Not Occur

Not Occur

Not Occur

Not Occur


Table C 5 Acceptance Criteria for Output Signals Monitored during EMC Test of the PRM

Input Expected Output (Acceptance Criteria)

Time LPRM FLOW HNS511/ HNS514/ HNS512/ HNS514/ HNS512/ (s) (µA) (mA) HNS515 HNS518 HNS516 HNS518 HNS516

LPRM LPRM APRM APRM FLOW r) (mV) (V) (mV) (V)

:t_J Ll LU: 1a,c 0 1 2 3 4 5 6 7 8 9 10

11

12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30


151/151

HNS513/ APRM

HNS517 High-High

FLOW Trip Discrete

(V) Output

a,

--

,_ Not Occur

I-

--

-e--

e--

,_ ,_

~

,_

~

Occur ~

,_

e--

,_ e--

e--

e--

. e--

~

~

~

Not Occur ,_

-

-