integrated startup test program.' · 2019. 12. 27. · startup network list of major preoperational...

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APPENDIX A

APPENDIX B

APPENDIX C

APPENDIX D

LIST OF APPENDICES

STARTUP NETWORK

LIST OF MAJOR PREOPERATIONAL TESTS AND CHECKS

LIST OF MAJOR STARTUP TESTS AND CHECKS

PROCEDURE FOR CONDUCTING THE INTEGRATED STARTUP PROGRAM

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APPENDIX A

STARTUP NETWORK

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Construction Test Phase

SEC. HYDRO

PRIMARY HYDRO·

e STARTUP NETWORK SURRY UNIT NO. 2 ,

"~' LEAK TEST

ECCS INTEGM D

TEST

FUEl-LDAD

HOT NCTION L START

HOT NCTIO

COMPLET

Preoperatlonal Test Phase Startup Test Phase

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('IOTg - All Construction tests ara not required prior to tho Preoperatlona/ test phase.

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APPENDIX B

LIST OF MAJOR PREOPERATIONAL TESTS AND CHECKS

TITLE OF TEST OR CHECK

1. Nuclear Instrumentation

2. Process Instrumentation

1. Pressure Boundary Integrity Tests

a. Hydrostatic test

b. Baseline data for inservice inspection

2. Component Tests

a. Pressurizer Safety Valve

APPENDIX B Pagel of 5

LIST OF PREOPERATIONAL TESTS AND CHECKS

PLANT CONDITION/PREREQUISITE

I. PLANT INSTRUMENTATION

Prior to core loading

Ambient and/or at temperature

TEST OBJECTIVE

Nuclear instruments are aligned and source range detector reponse to a neutron source checked as the primary source is loaded.

Required equipment is aligned per station. procedure.a.

II. REACTOR COOLANT SYSTEM

Below 200°F (after verification of cleanliness and fill of system)

During preoperational testing

Ambient pressure

Cold hydrostatic testing of each Reactor Coolant System loop will be performed at test pressures as specified by ASME standards for the system. Prior to pressuriza-tion, the effected portions of the system will be heated above the minimum temperature for pressurization. The pressure is then increased in increments, and at each increment inspections are made for leakage. Leaky valves or mechanical joints are not a basis for rejecting the test, Overpressure protection is provided during testing.

Systems and components that require inspection in accor-dance with Section XI of the ASME Code are examined for base line data. Data from these inspections provide base line data for subsequent inservice inspections,

The setpoints of the safety valves are verified using existing station procedures,

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1. Automatic Reactor Power Control Test Systems

1. Reactor Protection System

2. Engineered Safety Features

1. Residual Heat Removal System Test

APPENDIX B Page 2 of 5


PLANT CONDITION/PREREQUISITE TEST OBJECTIVE

III. REACTIVITY CONTROL SYSTEMS

Preoperational testing The system alignment is verified at preoperational con-ditions to demonstrate the repsonse of the system to simulated inputs. These tests are performed to verify that the systems will operate satisfactorily at power.

IV. REACTOR PROTECTION SYSTEMS

Prior to .core loading


Prior to core loading the Reactor Protection is tested to demonstrate operability, proper logic, redundancy, and coincidence. The protection channels are verified through to tripping of the reactor trip breakers.

Prior to core loading the Engineered Safey Features logic systems are tested to demonstrate operability, proper logic, redundancy, and coincidence.

V, POWER CONVERSION SYSTEM

Done under Startup Testing

VI. AUXILIARY SYSTEMS


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Thia aystem i!j tested by verifying pressure and flow. 111 1·, "• I 11•

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2. Containment Instrument Air System

3. Neutron Shield Tank Cooling System

4. Leak Detection System Tests

1. F.mergency Power Systems

1. Reactor Containment Tests

APPENDIX B Page 3 of 5





Prior to and during preoperational tests

VII. ELECTRICAL SYSTEM


VIII. CONTAINMENT SYSTEMS


TEST OBJECTIVE

characteristics of the pumps and operation of the iso-lation valves.

The instrument air system. including air receivers and compressors. is tested to verify proper operation.

The system is operationally checked out to verify heat exchange operability.

Temperature detectors in the drain lines from pressurizer safety valves and the reactor vessel head 'seal and their alarm functions are checked. Pressurizer relief tank level and temperature sensors are calibrated and associ-ated alarms checked.

The automatic starting and loading of the diesel genera-tors is demonstrated under loss of emergency bus alter-nating current power.

Containment Type A leakage tests will be performend in accordance with USNRC approved topical report BN-TOP-1 Rev. 1, which provides for a reduced duration test.

Containment Type B & C leakage tests will be performed in accordance with Appendix J to lOCFRSO •

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2. Containment Isolation Tests

1. High pressure Safety Injection Tests

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2. Low Pressure Safety Injection Tests

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TEST OBJECTIVE

The operation of actuation systems and components used for containment isolation is verified.

IX. GASEOUS RADIOACTIVITY REMOVAL SYSTEMS

Done under St:artup Testing

X. EMERGENCY CORE COOLING SYSTEM



This system is operationally tested to verify pressure/ flow values. Tests are also conducted to check pump operating characteristics. More specifically that:

a. Valves installed for redundant flow paths operate as desigend,

b. Pump operating characteristics are verified.

c. Valves and pumps operate on operator and/or automatically on initiation of injection signal.

initiation a safety

d. Level and pressure instruments are properly cali-brated.

The low head Safety Injection System is checked to verify design flow, flow paths, and pump operating characteris-tics. More specifically that:

a. Valves installed for redundant flow paths operate as designed.

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TITJ.E OF TEST OR CHECK

1. Refueling Equipment (hand tools and power equipment, including protective interlocks)

1. Criticality and area monitor tests

APPENDIX B Page 5 of 5·



b. Pump the

TEST OBJECTIVE

operating characteristics reactor coolant system at

are verified with ambient conditions.

c. Valves and motors operate on operator initiation and/or automatically on initiation of a safety in-jection signal.

d. Level and pressure instruments are properly cali-brated.

In addition a 100 hr. endurance test witl be performed, the pump disassembled and inspected.

XI. FUEL STORAGE AND HANDLING SYSTEM

Prior to core loading Tests are performed prior to core loading to demonstrate · the fun~tioning of the fuel transfer system.

XII. REACTOR COMPONENTS HANDLING SYSTEM

Done during startup

XIII. RADIATION PROTECTION SYSTEM

Prior to core loading The radiation alarms aasociated with core loading are checked out and the alarm setpoints verified.

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APPENDIX C

LIST OF MAJOR STARTUP TESTS AND CHECKS


I. Nuclear Instrumentation (excore)

2. Process Instrumentation (Temperature, pressure, level, and flow instruments)

1. Vibration and amplitude

2. Expansion and Restraint

3. Integrated Hot Functional Tests

APPENDIX C Page 1 of 11

LIST OF STARTUP TESTS AND CHECKS

PLANT CONDITION/ PREREQUISITE

I. PLANT INSTRUMENTATION

Prior to criticality

Ambient and/or at temperature

TEST OBJECTIVE

Just before criticality all channels are checked to verify high level trip functions, alarm set points, audible count rates where applicable, and operation of strip chart re-corders, and any auxiliary equipment.

Equipment is aligned per station procedures,

II. REACTOR COOLANT SYSTEM

After fuel load

During plant heat-up

Heat-up and at temperature Hydrostatic testing has been satisfactorily com-completed and Reactor Coolant System instruments aligned and operational. Associated auxiliary systems shall be operational to the

Vibration sensors are placed on the main coolant pumps and main cooling piping in order to check for excessive vibration while starting and stopping the pumps. ·

During the heat-up to operating temperature, selected point on components and piping of the Reactor Coolant System are checked at various temperatures to verify unrestricted expansion. Points of interference detected during the heat-up are corrected prior to increasing the temperature.

The Reactor Coolant System is tested using pump heat to reverify heat-up procedures and to demonstrate satis-factory performance of components and systems exposed to reactor coolant system temperature. Proper operation of instrumentation, controllers and alarms, is checked against design operating conditions of auxiliary systems and set points verified. Among the demonstrations per-formed are:

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4. Component Tests

a. Pressurizer




extent required to support hot functional testing,

At operating temperature,

TEST OBJECTIVE

a. To check that water can be charged by the Chemical and Volume Control System at rated flow against normal reactor coolant pressures,

b. To check letdown design flow rate for each operating mode,

c. To check response of system to change in pressurizer level,

d, To check operation of the excess letdown and seal water flow paths.

e, To check steam generator level instrumentation re-sponse to level changes.

f. To check thermal expansion of selected system com-ponents and piping.

g, To perform temperature

isothermal detectors

calibration and incore

of resistance thermocouples,

h. To operationally check out the Residual Heat Removal System,

During the hot functional testing the pressure controlling capability of the pressurizer is demonstrated to be with-in the controlling band, With reactor coolant pumps operating and with full spray, the pressure-reducing capa-bility of the pressurizer is verified. With the spray secured and all heaters energized, the pressure-increasing

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TITLE OF TEST OR MEASUREMENT

b. Reactor Coolant Pumps and Motors

c. Steam Generators

5. Pressure Test of Reactor Coolant System

APPENDIK C . Page 3 of 11



At ambient conditions and during heat-up and at temperature.

At ambient conditions and during heat-up and at temperature.


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TEST OBJECTIVE

capability of the pressurizer is verified. Pressurizer Relief valves are functionally checked.

As the pumps and motors are placed in operation they are checked for:

1. Direction of rotation (initial start only)·

2. Vibration

3. Power requirements

4. Lubrication

5. Cooling

6. Megger and hi pot test (as applicable)

7. Overload protection

8. Correct power supply voltage

The proper operation of instrumentation and control systems of steam generators are checked during heat-up and at temperature. The heat transfer capability of the steam generators is demonstrated. The functioning of the blowdown system will be checked.

Following core loading and installation of the Reactor Vessel head and torquing of the reactor vessel heads studs, pressure testing is performed in accordance to Tech. Spec.

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6. Chemical Tests (to establish water quality)

7. Reactor Coolant Flow Test

l. Chemical and Volume Control System Tests

2. Emergency Boration System Teats




Prior to heat-up during startup testing

Prior to plant criticality

TEST OBJECTIVE

Water fr Reactor Coolant System fill and makeup is analyzed for chloride content, conductivity, total sus-pended solids, pH, clarity, and fluorides to requirements specified by the chemistry manual for ~SSS. Following core loading and prior to exceeding 250 F, hydrazine is added to scavenge oxygen prior to critical operation. Prior to, at criticality, and during power escalation, chemical analysis is performed to verify requirements.

Following core loading, measurements are made of elbow tap differential pressures to make relative comparison. At hot shutdown conditions following core loading, measurements of loop elbow differential pressure drops were made. Using these data with the reactor coolant pump performance curve, the calculated flow is verified to the design flow. Flow coastdown and transients following reactor coolant pump stoppages are also determined at shutdown conditions following core loading.

III. REACTIVITY CONTROL SYSTEMS

At ambient and/or at operating conditions. System components are operationally checked out,

During hot functional testing.

Makeup and letdown operations are conducted with the Chemical and Volume Control System to check out the dif-ferent modes of dilution and boration and verify flows in the different modes. The adequacy of heat tracing to main-tain the required Boric Acid concentration in solution is verified. The ability to adequately sample is demon-strated.

The pressure/flow characteristics of the emergency bora-tion system are verified . by pumping into the Reactor Coolant System.

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3. Incore Monitor System Test

a. Incore Thermocouples

b. Moveable Detector System

4. Control Rod Systems Tests

a. Rod Control System

b. Rod Drop Tests

c. Rod Position Indication




During heat-up and at temperature.

At ambient conditions following core loading and critical testing.

Ambient conditions following core loading and hot conditions after core loading. '

Cold and hot plant conditions following core loading,

At ambient conditions and at temperature following core loading.

TEST OBJECTIVE

During heat-up and at temperature the incore thermocouples are calibrated to the average of the Reactor Coolant System resistance temperature detectors. All readout and tempera-ture compensating equipment is checked during the calibra-tion and isothermal corrections for the operative thermo-couples are determined.

After core loading, the installation checkout of the move-able detector system will be completed.

During the installation check of this system it is ener-gized and operationally checked out with mechanisms connected to each power supply. The ability of the system to step the mechanism is verified, the alarm and inhibit functions checked out and the correct values of system parameters adjusted to specified values. After core load-ing the operation of each rod over its full range of travel is demonstrated.

At cold and hot plant conditions following core loading the drop times of the full length rods are measured, The drop time is measured from the release of the rod until the rod enters the top of the dashpot. This time was verified to be less than the maximum value specified in the Technical Specifications.

During rod control system tests the position indication system was aligned to provide rod movement indication. Rod bottom set points will b!! adjusted during these tests. After plant heat-up individual rod positions a["e cali-brated to within tolerances specified by the test proce-dure,

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• TITLE OF TEST OR CHECK

1. System Tests

a. Vibration Frequency and Amplitude

'' ··-b. Expansion and Restraint ··:::• ·

2. Components and Individual System

a. Steam Generator Pressure Relief and Safety Valves



l PLANT CONDITION/PREREQUISITE TEST OBJECTIVE

IV. REACTOR PROTECTION SYSTEM

Done during Properational Testing

V. POWER CONVERSION SYSTEM

Hot Functional Testing and/or plant heat-up following criticality

During heat-up, and at temperature.

Pressure Conditions

When the main turbine is rolled, vibration readings are monitored. · (Turbine vibrations are also monitored throughout the power escalation program.) Major equip-ment (e.g., feedwater pumps and condensate pumps are operated as they become available and are observed for indications of excessive vibration.

During heat-up to operating termperature, selected points on the components and piping of -the systems are checked at various temperatures to verify that they can expand un-restricted.

The set point of safety valves was verified by in-plant tests at pressure and temperature conditions when the unit was shut down. Setpoints were checked by using a pressure assist device which adds to the force due to pressure. Once the valve leaves the seated position the assist device was vented, allowing the valve to reseat immediately. Steam relief valve set point checks were made during instrument alignment •

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b. Emergency Feedwater (Auxiliary) System

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d.

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f.

T~rbine Control and Bypass Valves

Feedwater and Feedwater Co·· ,:-rol System

Condenser Circulating Water

Makeup Water and Chemical

• APPENDIX C Page 7 of 11 •• LIST OF STARTUP TESTS AND CHECKS


Prior to citicality

Hot Functional test:1.ng and/or power operat:l.on following criticality

Hot functional testing and at Power

Prior to bot functional testing

During Steam generator fill, hot functional testing and

TEST OBJECTIVE

During bot functional testing prior to criticality the emergency feedwater system is checked out to verify its ability to feed the steam generators. Automatic starting is checked during checkout of the safeguards logic system tests. The auxiliary feedwater piping is checked for excessive vibration while starting and stopping the auxi-liary -feedwater pump with normal operation of the associ-ated motor operated discharge valves in the auxiliary feedwater system,

During hot functional testing the turnbine control system will be demonstrated in turbine operation up to and in-cluding a period of operation at synchronous speed, The turbine bypass valves to the condenser and their associat-ed control systems are operationally checked out during hot functional testing.

The feedwater and condenstate pumps are operationally checked out during hot functional testing. During· power escalation the power is increased and the ability of the feedwater pumps and control system to maintain level in the system generators are aligned prior to filling the system and during fill, the system is used to monitor level in the steam generator.

Prior to hot functional testing the main circulating water system valves are tested to verify operability.

The makeup system to the system generators is checked out during hot functional testing and at Power at power. The chemical treatment system is checked out when chemicals are added to the steam generators at heat-up to steaming conditions.

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1, Reactor Coolant System Makeup Test (CVCS)

2. Seal and Pump Cooling Water Test (CVCS)

3. Secondary Vent and Drain System Test

4. Component Cooling System Test

5. Residual Heat Removal System Test

6. Service Water System Test

7. Control Rod Drive Mechanism and Rod Position Indication Coil Cooling System Test

8. Primary Sampli~g System



VI. AUXILIARY SYSTEMS

Prior to heat-up and at temperature

During hot functional testing

Ambient and/or hot plant conditions

Prior to and during hot functional testing

Prior to hot functional

Prior to and/or during hot functional tesintg

Prior to and/or during hot functional testing

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See III REACTIVITY CONTROL SYSTEM, Item 1.

Prior to reactor coolant pump operation and with the system pressurized flow to the pump seals and cooling water is set, flow is adjusted to specified values using installed instruments. During hot functional testing when at operating temperature and pressure, seal and cooling flows and temperatures are checked, ·

During hot functional testing following core loading the secondary system is vented while pressurizing the second-ary system, Secondary drains are tested for unrestricted flow in accordance with operating procedures,

Component cooling flow to the various components in the affected systems is adjusted, the system operationally checked out, and set points verified,

Heat removal capability demonstrated,

The system is operationally checked out to verify pressure and flow. Service water flow is verified to components in the system.

The system is operationally checked out to verify air flow, temperatures and motor current,

Operations are performed to:

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9, Primary Pressure Relief System

1, Containment Ventilation System Test

2, Post Accident Heat Removal System Tests (Containment Sprays)



Prior to hot functional · testing and at pressure conditions

TEST OBJECTIVE

a. Demonstrate that liquid and gas samples can be obtain-ed from sample points.

b. Demonstrate that valves, instruments, and controls funtion properly.

c. Verify power functioning of the sample cooler.

The pressurizer relief tanks associated valves, and in-strumentation are checked out to verify performance of design functions, For testing of pressurizer relief and safety valves see II REACTOR COOLANT SYSTEM. '

VII. ELECTRICAL SYSTEM TESTS

Done during Preoperational Testing

VIII. CONTAINMENT SYSTEMS

Prior to and/or during hot functional testing


The system is operated to balance air flows and to verify the ability to maintain temperatures below maximum allow-able limits,

Testa are performed to verify pump operating charcteris-tics, and response to control signals, sequencing of the pumps, valves and controller, (and to ensure that spray nozzles were unobstructed,)

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1. Accumulator Tests

l. Spent Fuel Storage Radiation Monitoring Equipment

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l, Initial Criticality

l. Power Ascension


PLANT CONDITION/PREREQUISITE TEST OBJECTIVE

XIV. INITIAL CRITICALITY AND LOW POWER TESTS

Plant at hot shutdown

XV. POWER ASCENSION

Criticality

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-The objective is to bring the reactor critical from the plant conditions specified. Prior to start of rod with-drawal, the nuclear instrumentation had been aligned, checked, and conservative reactor trip set points made per procedures, At preselected points in rod withdrawal, data is taken and inverse count rate plots made to enable extrapolating to the expected critical rod position, In addition, the following teats associated with modified system will be performed: steam generator water hammer test, blowdown system capability test and thermal expan-sion monitoring.

Normal poet refueling testing will apply for power ascen-sion, In addition the following design tests associated with modified systems will be performed.

steam generator carryover tests

steam generator recirculation ratio test

steam generator thermal and hydraulic perfomrance verifi-cation

steam generator water level stability and control demon-stration

condensate polishing performance testing

load rejection testing with condensate polisher

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APPENDIX D

PROCEDURE FOR CONDUCTING THE INTEGRATED STARTUP TEST PROGRAM

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I Issue Date: AUG 8 1979

PROCEDURE

FOR CONDUCTING THE

INTEGRATED STARTUP TEST PROGRAM

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A,HA!P.'.,,1/\N- SUR~ PO\NER STATION .NlJCU.:1\R s.:1FET AND OPERATING

. COM.MiHEE

FOR POST

STEAM GENERATOR REPLACEMENT

AND

P.O. & M. DESIGN CHANGES

SURRY POWER STATION

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA

Superintendent Operations:

Lead Advisory Engineer:

PO & M Resident Engineer:

DA TE

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TABLE OF CONTENTS

1. 0 Purpose and Scope

2 • 0 References

3 • 0 Definitions

4, 0 Participating Organizations

5. 0 Construction Test Phase

5, l General 5. 2 Responsibilities 5. 3 Release for Preoperational Testing

6. 0 Preoperational Test Phase

6 .1 General 6. 2 Respons bili ties 6. 3 Release for Startup Testing

7, 0 Startup Test Phase

7 .1 General 7, 2 Responsibilities 7. 3 Startup Release Points

8. 0 Attachments

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1. 0

SURRY UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY

RICHMOND, VIRGINIA

PURPOSE AND SCOPE

1.1 To provide a procedure for the accomplishment of the tests and checks to be completed prior to plant operations.

1. 2 To define the phases of the Integrated Startup Test program.

1. 3 To define the responsibilities of the organizations participating in the Integrated Startup Test program.

1. 4 To provide the necessary administrative controls to ensure all pre-requisites are complete prior to commencing the next phase of test-ing.

1. 5 To define responsibilies for the preparation of test procedures and test matrices.

2 .0 REFERENCES

2.1 ES-119, Equipment and System Tagging, Surry Power Station Units Nos. 1 and 2

2. 2 VEPCO Nuclear Power Station Quality Assurance Manual

2. 3 Stone & Webster Logic Diagrams and System Descriptions

2. 4 VEPCO Calibration Procedures

2. 5 Final Design Change Packages for each modification

3.0 DEFINITIONS

3 .1 Phases of the Integrated Startup Test Program

The Integrated Startup Test program is divided into three phases: Construction Tests, Preoperational Tests and Startup Tests. The objectives and responsibilities of each phase are defined below.

The Construction tests are under the direction of the Release Coordi-nator and are designed to assure proper construction of modified or new systems. Construction deficiencies are resolved by the Release Coordinator •

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The Preoperational Tests are under the direction of the Startup Group and are designed to assure proper functioning of new, modified and existing equipment, subsystems and systems.

The Startup Tests are under the direction of Station Operations and are designed to assure the proper integrated operation of all re-quired systems prior to the next sequence of power operation.

3. 2 General Electrical, Instrument and Mechanical Test Procedures

These procedures are referred to as TEP's TIP's and TMP's. These generic procedures are approved by the Station Nuclear Safety and Operating Committee and are used to verify proper installation and initial operability of equipment. These procedures are used during the Construction Test phase and Preoperation Test phase.

3. 3 Cleaning And Flushing

3. 3 .1 Cleaning Procedures

Cleaning will be performed in accordance with issued guides and general procedures to ensure satisfactory cleanliness of systems and components. Cleaning will include mechanical cleaning and hand cleaning, The Station Nuclear Safety and Operating Committee shall designate cleanliness grades for individual systems via approved design change packages •

3. 3. 2 Flushing Procedures

A written procedure to ensure strict compliance with cleanli-ness requirements for nuclear steam supply and safety related systems. Station Nuclear Safety and Operating Com-mittee approval is required for generic flushing procedures and design change controlling procedures.

3 . 4 Electrical Checks

Checks performed as part of design change package to ensure that an instrument or electrical control loop is complete and correctly connected. These checks shall include, but not be limited to, breaker tests, insulation tests, and motor control center tests to ensure the integrity of the control circuit or equipment.

3. 5 Mechanical Checks

A set of checks performed for the purpose of verifying that a piece of mechnical equipment (pump, compressor, blower, etc.) is ready for initial startup. These checks shall include, but not be limited to, alignment, coupling, manufacturers' recommended lubri-cation, packing gland adjustment, etc., as applicable for the equip:-ment being readied for startup •

3. 6 Hydrostatic Test

Pressure testing to meet the applicable erection code and to ensure

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system integrity. The Station Nuclear Safety and Operating Com-mittee approval is required for these generic procedures.

Calibration

Quantitative adjustments of instruments and control devices, includ-ing characterization of analog signals, quantitive setting on all control and monitoring loop elements and verification of response characteristics.

It also applies to those calibration checks which verify quantitive accuracy and functional integrity of the devices or instruments loop previously calibrateq. by others, or to verify functional inte-grity of the devices or instruments which are not adjustable by normal means, such as thermocouples, conductivity cells, thermo-meters, etc.

3. 8 Calibrated Loop Check

A set of tests performed for the purpose of verifying that an in-strument loop is acceptable in terms of quantitive agreements, proper inter-relationship, and expected responsiveness of several loop elements. This set of tests is performed with all loop com-ponents in place, individually calibrated and documented, and devices energized by applying simulated inputs and measuring or observing loop performance .

3 • 9 Functional Loop Check

A set of tests performed for the purpose of verifing that a control and/ or telemetering loop is acceptable in terms of functional in-tegrity and interrelationship of the several loop elements. This set of tests is performed with all loop components in place, structurally complete, and engergized, by applying simulated inputs and observ-ing loop performance. Loop elements need not be individually calibrated.

3 .10 VEPCO Electrical Check-Out

VEPCO electricians, for 480 V circuit breakers, will perform contact inspection, dashpot and mechanism inspection, set trip valves with multi-amp tester, and megger insulation. For 4160V, they will perform contact and mechanism inspection and check trip and close times with analyzer. Additionally, dielectric checks will be made on 4160V cables, doble tests and ratio 4160 / 480V transformers and doble test 4160V circuit breakers.

3 .11 Preoperational Check-Out

Test of an individual item of equipment, subsystem or minor system to verify readiness for operations •

3 .12 Operating Procedure (OP)

A station procedure developed by VEPCO and approved by the

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Station Nuclear Safety and Operating Committee for normal opera-tion of equipment and systems.

Periodic Test Procedure (PT)

A station procedure developed by Vepco and approved by the Station Nuclear Safety and Operating Committee to meet Tech. Spec. or surveillance requirements for operability.

3.14 Special Test Procedure (ST)

A station procedure developed by Vepco and approved by the Station Nuclear Safety and Operating Committee to obtain data, associated equipment performance, or other technical data required for engineering or operational evaluation.

3 .15 Functional System Operability Procedure ( FSOP)

3.16

A procedure developed by the Startup Group to verify and docu-ment the functional operation of equipment and/or controls. It will verify and document the functional operation of critical controls. FSOP's are generally written to utilize existing logic diagrams.

Electrical, Instrument and Mechanical Maintenance Procedures And Maintenance Operability Procedure

These generic station procedures are referred to as EMP's, IMP's, MMP's and MOP's. These procedures are used by station person-nel to checkout previously installed equipment that has undergone maintenance and to remove and replace safety related equipment in service.

3 .17 Test Matrix

A matrix that indicates which TEP, TIP, TMP, and/or existing station procedure (OP, PT, ST, IMP, EMP, MMP or MOP) will be performed on an individual test loop, instrument, valve, device or component.

4.0 PARTICIPATING ORGANIZATIONS AND RESPONSIBILITIES

4.1 Station Nuclear Safety and Operating Committee

4.2

Consisting of representatives from Surry Power Station as desig-nated in the Vepco Nuclear Power Station Q. A. Manual. The Station Nuclear Safety and Operating Committee reviews and approves all test procedures. The committee reviews a summary of test results and approves release of the next phase of Startup Testing.

VEPCO Operating Staff

Consists of VEPCO employees engaged in the operation and main-tenance of systems, subsystems, or portions of the station under the supervision of the station manager.

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VEPCO Operating Staff may witness Construction tests as desired for correct operation, testing and verification of design performance during final construction testing. VEPCO Operating Staff will per-form necessary and timely inspections and perform evaluations as necessary to effect a smooth release of systems for Preoperational testing.

VEPCO Operating Staff will conduct Preoperational and Startup test-ing and is responsible for the operation of the plant and the per-manently installed plant process equipment connected to an ener-gized power source.

4. 3 Westinghouse Electric Corporation (W)

The term Westinghouse or W shall be limited to equipment and services furnished as part of or under the contract for the nuclear steam supply and turbine generator systems.

4.4 NUS Corporation (NUS)

The term NUS shall be limited to equipment and services furnished as a part of or under the contract between Vepco and NUS Corpora-tion. NUS shall furnish engineering services where required by Vepco.

4. 5 Stone & Webster Engineering Cor oration - Engineerin Department S&W-BOSTON

S&W shall furnish engineering services where required by VEPCO.

4. 6 Daniel Construction Company ( Daniel)

Daniel shall furnish construction services as required by Vepco.

4. 7 Vepco Project Engineers

This group of engineers is responsible to resolve component and system deficiencies discovered during the Construction Test and Preoperational Test phases.

4. 8 Quality Control

Consists of Quality Control related functions as defined in approved design change packages and test procedures.

4.8.1 Vepco SGRP Q.C.

This group is responsible for quality control for all con-struction work and construction testing as defined in the Vepco Nuclear Power Station Quality Assurance Manual. Daniel Q. C. supplements Vepco Construction Q. A, as directed by Vepco .

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4. 8. 2 Vepco Station Q. C.

This group is responsible for quality control during the Preoperation Test phase and Startup Test phase. The level and extent of Q. C. coverage is defined in the individual procedure,

4. 9 Startup Group

The Startup Group is responsible for the development and implemen-tation of the Integrated Startup Test program. It consists of S & W Advisory Engineers under the direction of the S & W Lead Advisory Engineer and designated VEPCO operators under the direction of the designated VEPCO Shift Supervisor each responsible to the Station Superintendent of Operations.

The S & W Lead Advisory Engineer is responsible for the implemen-tation of the Integrated Startup Test program described herein and as outlined in station directives and applicable regulatory guides. In conjunction with the VEPCO Shift Supervisor, he will provide the technical direction and expertise to ensure the timely completion of the required testing. He will also be responsible for the develop-ment and management of the necessary documentation to support the Integrated Startup Test program.

The designated VEPCO Shift Supervisor is responsible for the execution of the Integrated Startup Test program. He will provide coordination with the operating staff for the safe operation and the interfacing of existing plant systems to support the Integrated Startup Test program. In conjunction with the Lead Advisory En-gineer, he will direct the assigned personnel and provide operational guidance to ensure the timely completion of the required testing.

The Startup Group is responsible for conducting the test and checks under their jurisdiction. The group will ensure that all required test procedures and test matrices are developed and are available for use. The Startup Group is responsible for assuring all tests in the Integrated Startup Test program are performed in accordance with approved test procedures and for reviewing and approving all test data through the Preoperational Test Phase. The group is responsible that all design change test procedures and test matrices are written and approved to support Construction, Preopera-tional and Startup testing. The group is responsible for records management for the Preoperational and Startup Test phases.

4 .10 VEPCO Construction Staff

The construction program is functioning under the direction of two resident engineers, the Resident Engineer for the Steam Generator Replacement Project (SGRP) and the Resident Engineer for the Production Operation Modifications ( P. 0. M.) .

The Resident Engineer (SGRP) will be responsible for all rework associated with the Stearn Generator Replacement Project.

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-- -- -- --~----- - -, - ---- --·----------------··------------~- --~----- ---~--- -----------·----

-7-

All the rework associated with the other modfications and the Construction Test phase will be the responsibility of the Resident Engineer (P. 0 .M.) who is designated the Release Coordinator. The Release Coordinator is responsible to the Superintendent of Operations for the Construction Test phase.

VEPCO Construction Test Group ( CTG)

The Construction Test Group is composed of designated individuals from each organization participating in the construction program,-and is directed by the Release Coordinator.

The CTG is responsible for timely completion of all segments of the Construction Test phase. Also, the CTG will provide support, as required, to the Startup Group during the Preoperational and Startup Test phase.

4, 12 Superintendent of Operations

The overall responsibility for the direction and management of the Integrated Startup Test program is under the control of the Station Superintendent of Operations. The responsiblity for the direction and management within the Construction Test and· Pre-operational Test phases is assigned to the Release Coordinator and Startup Group respectively .

4 .13 Startup Coordinator

The Startup Coordinator works directly for the Superintendent of Operations. His sole responsibility is to ensure the smooth day-to-da y operation of all phases of the Integrated Startup Test program.

4.14 Superintendent of Technical Services

The Superintendent of Technical Services engineering review and analysis of the Program. He will be responsible for analysis, engineering review and analysis tional tests and the major Startup tests.

will provide the required Integrated Startup Test

the development, safety of the selected Preopera-

5.0 CONSTRUCTION TEST PHASE

5.1 General

The Construction Test Phase for new and modified systems is the responsibility of the Release Coordinator and will be accomplished by construction personnel. The Construction Test Phase includes all nondynamic tests and checks included in the design change package to verify proper installation of equipment. A list of unre-solved system deficiencies will be recorded during the test period and transmitted to the Startup Test Group with the system release. All systems will be released as soon as possible to support pre-operational tests.

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All activities of the Construction Test Phase shall be performed in accordance with specifications and design change packages and other approved procedures, as applicable.

The tests associated with this phase include: insulation resistance measurements, control circuitry checkout, low-voltage switchgear inspection, MOV (static) checkout, Circuit breaker and overload checkout (Vepco A & C), 480V MCC inspection, I & C electrical checkout, I & C mechanical checkout, annunciatior checkout, heat trace checkout and general hydrostatic tests.

5. 2 Responsibilities

5.2.1 Vepco Construction Staff

5. 2 .1.1 Construction Test Group

5.2.1.2

5.2.1.3

Works directly for the Release Coordinator and in conjunction with the Startup Group and is responsi-ble for ensuring the timely completion and testing of systems and components, The group is addi-tionally responsible for correction of outstanding construction deficiencies found as a result of accep-tance tests, or Q, C. inspection during the next phase of testing .

All Category I deficiency corrections shall be docu-mented by a Daniel or VEPCO generated noncon-formance report.

Release Coordinator

The responsibilities of the Release Coordinator are assigned to the PO&M · Resident Engineer for new and modified .systems.

He is responsible for seeing that System Releases are promptly processed and he will maintain a status of all outstanding design change deficiencies. For operating systems that did not require modifica-tions, the Startup Group will maintain the status.

Responsible System Engineer

As the Construction Test phase of the Design Change Package is completed, the responsible construction System Engineer will walkdown the release and ensure that all work has been completed and the system is ready for initial operation and Preoperational testing. Any items that are found to be incomplete shall be documented on a Deficiency List. Those deficiencies that limit Preoperational testing will be resolved prior to System Release.

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5 , 2. 2 Startup Group

5.2.3

The Startup Group is responsible to provide technical advice in the preparation of systems and components to support planned Construction Tests.

The Startup Group is responsible for assuring that all Elec-trical, Mechanical and Instrument Construction tests are performed in accordance with established test procedures (TEP, TIP and TMP's) and for reviewing and verifying com-pleteness of all test data. It is also responsible for writing additional detailed procedures as needed for implementation of general procedures. It will be responsible for obtaining resolutions for all deficiencies,

The Startup Group shall verify that a System released by the Release Coordinator has reached a point of construction completion to be accepted for Preoperational testing.

Vepco Construction Quality Control

Shall perform required inspections and audits to assure that the Construction Test Program is conducted in accordance with the design change packages.

5.2.4 Vepco Station Quality Control

VEPCO station QC shall ensure the requirements for system documentation of the Station Nuclear Safety and Operating Cammi ttee are met,

5, 3 Release For Preoperational Testing

When construction testing on a system or subsystem thereof is complete, the responsible system engineer will perform a walkdown of the system to ensure completion, markup II as-built" conditions on DC package drawings and generate a 1 deficiency list based on the test results and visual inspection.

The· system is presented to the Startup Group for Preoperational Testing via a (Design Change-Construction) System Release form ( Attachment 8 .1) and a Deficiency Punch List ( Attachment 8, 2).

The Startup Group either "accepts" or "rejects" the system release, A rejected system release is returned to the Release Coordinator for completion of Preoperational Test limiting deficiences,

6.0 PREOPERATIONAL TEST PHASE

6.1 General

When a system or subsystem is sufficiently complete and other re-lated systems have progressed for enough so it can perform its

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assigned function, the Startup Group, accepts the released system for Preoperational Testing.

Prior to signing the system release form ( Attachment 8 .1), the Startup Group will make a thorough review of all the attached documents and a member of the Startup Group will walkdown the system to insure that there is no outstanding item that will affect safe operation of equipment or system. If any items are found to be unsatisfactory the required acceptance signatures will then be withheld by the Startup Group until these items are resolved.

The Preoperational Test Phase for modified, new and existing systems is the responsibility of the Startup Group and will be accomplished by Vepco operations staff supplemented by construction personnel.

As the system releases for new and modified systems are accepted by the Startup Group, the required Preoperational testing will begin. During this phase, field changes will be generated to resolve problems discovered during testing and operations, These field changes will be forwarded to Release Coordinator for resolution and implementation. Any rework that is needed will be controlled by a "Rework Control Form" (Attachment 8.3) issued by the Start-up Group listing the required retests.

System release forms will be generated by the Startup Group for all remaining systems associated. with the Unit. The existing systems not associated with design changes can be classified as follows: remained in service, removed from service for maintenance and re ... turned to service, did not remain in service and is in the area of design change construction, and did not remain in the service but is not in an area affected by design change construction, The extent and level of testing assigned by the Startup Group to testing of these systems will be based on this classification.

Vepco I & C will calibrate instruments and controls as the precali-bration tests are completed by the Startup Group.

Preoperational testing includes all designated tests procedures (TIP, TEP and TMP) along with applicable station procedures (ST, PT, OP, MOP, EMP, IMP, MMP).

The tests associated with this phase include: dynamic MOV check-out, uncoupled and coupled motor runs, uncoupled and coupled vibration tests, I & C functional checkout, AOV / AOD setup and checkout, I & C hydrostatic test, AOV / AOD dynamic checkout, air balancing, pump curve verification, flushing and FSOP 1S.


6.2.1 Construction Test Group

Responsible as noted on the Deficiency Punch List (Attach-ment 8. 2) for correction of construction deficiencies found as a result of testing or Q • C, inspection.

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6, 2, 2 Startup Group

6.2.3

6.2.4

The Startup Group is responsible for: ensuring the timely Preoperational testing of systems and components., documen-tation of discrepancies determined during testing; maintain-ing a status of all outstanding deficiencies for existing systems that did not require modification, providing technical direction in the preparation of systems and components to support planned Preoperational tests, assuring that all Electrical, Mechancial and Instrument tests are performed in accordance with established test procedures, (TEP, TIP and TMP's), reviewing and approving of all test data, writing additional detailed procedures as needed for implmentation of general procedures and obtaining resolutions for all defi-ciencies. The group will also be responsible for initial I & C and electrical setup of new equipment.

The Startup Group shall be responsible for determining if a system has reached a point where it can be presented to the Station for approval for unrestricted operation.

Vepco Station Quality Control

This group shall perform required inspections and audits to assure that the Preoperational Test phase is conducted in accordance with the approved procedures •

Vepco Station Q , C, shall ensure the requirements for system documentation of the Station Nuclear Safety and Operating Committee are met.

Vepco I & C and Electrical

These groups shall perform calibration and maintenance on equipment per system test matrices. All TIP and TEP data sheets will be completed and returned to the Startup Group,

6, 3 Release For Startup Testing

Upon successful completion of all Preoperational tests, the Startup Group will review all system documentation and test data as re-quired to verify the functional operability of the system, The Startup Group system engineer will walkdown the equipment to ensure the system is· ready for unrestricted operations by the station.

Any items found to be incomplete but not limiting for unrestricted operation will be documented on the Deficiency Punch List ( Attach-ment 8, 2). The Startup Group will then sign the System Release form (Attachment 8.1), The System Release and the required documentation will then be turned over to the Startup Coordinator for review and acceptance .

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7.0

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·- - - -- -- ---=--------···----_-_-_ -_ -

-12-

Prior to the Superintendent of Operations review of the system, the Station Quality Control Department will review the documentation to insure that all documents are complete. Any deficient items will be turned back to the Startup Group for resolution. Upon completion and acceptable audit, the Station Quality Control Department will sign the required signature block on the release. The Station Superintendent of Operations will then review the deficiency list to approve the items to be carried on the Master Deficiency List. Any items that are not acceptable will be returned to the Startup Group for resolution. When all deficient items are acceptable to the Station Superintendent of Operations, he will then sign the transmittal accepting the Release for the Station allowing Unrestricted Opera-tions of the system.

ST ART UP TEST PHASE

7 .1 General

When a system has completed Preoperational testing and is accepted by the station for unrestricted operations it is ready for Startup testing. Prior to initiation of the Startup Test phase the Station Nuclear Safety and Operating Committee will review the systems that are available for unrestricted operation to ensure safe operation and testing conditions.

The first event is fuel loading. The sequence for subsequent Startup testing is determined by the Integrated Startup Test Sche-dule and the initial conditions and prerequisites of the station startup procedures.

The Station Nuclear Safety and Operating Committee will review the status of systems and test results at major milestones throughout the Startup Test phase. At no time will the safety of the plant be totally dependent on the performance of untested structures, systems or components.

The comprehensive Startup Testing phase is to ensure that equip-ment and systems perform in accordance with design criteria. This phase includes tests, adjustments, calibrations, and system opera-tions necessary to ensure that criticality and subsequent power operation can be safely undertaken. These procedures will be normal station startup procedures, PT's, OP's supplemented as required by Special Tests.

Preoperational tests are performed to verify as near as possible, the performance of the system under actual operating conditions. Where required, simulated signals or inputs are used to verify the full operating range of the system and to calibrate and align the systems and instruments at these conditions. During Startup testing, systems and instruments that are used for normal opera-tions are verified and calibrated under actual operating conditions. Systems that are not used during normal plant operation, but must be in a state of readiness to perform safety functions, are checked under test conditions prior to unit startup.

e

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-13-


7. 2 .1 VEPCO Operating Staff

Virginia Electric and Power Company has the overall respon-sibility for development, supervis10n, performance, and documentation of all Startup Testing at the Surry Power Station. Test preparation and all test performance during Startup Testing are under control of VEPCO to ensure proper and effective emphasis is maintained on personnel and plant safety by all individuals participating in the testing program.

The Superintendent of Technical Services will be responsible for providing the safety analysis for all major tests and will provide engineering review and coverage to ensure the con-duct of the major tests satisfies the necessary design and safety criteria.

7. 2. 2 Startup Test Group

The Startup Test Group will act as advisers and consultants to the VEPCO staff in all areas of the Startup Testing.

7. 3 Startup Release Points

The following milestones in the Startup Test phase of the Integrated Startup Test Program Schedule require Station Nuclear Safety and Operating Committee review and approval prior to implementation:

a. Fuel Loading b. Hot Functional Testing c. Criticality and Low Power Physics Testing d. Power Range Testing e. Extended Full Power Operation

The Startup Group and the Station Operations department will be responsible to present evidence that all required testing is success-fully complete and proper documentation available.

8.0 ATTACHMENTS

8 .1 Equipment Release for Checkout and Operation

8. 2 Deficiency Punch List

8. 3 Rework Control Form

8. 4 Overall System Test Matrix

8. 5 Test Program Flow Chart

8. 6 Organization Chart

8. 7 List of Construction and Preoperational Tests

. . ATTACHMENT 8.1

SURRY POWER STATION UNIT NO.

SYSTEM RELEASE FOR PRF~l'ERATIONAL TESTING AND UNRESTRICTED OPERATI.ONS SYSTEM NO. ---

DESCRIPTION OF EQUIPMENT:

THE ATTACHMENTS WITH THIS RELEASE ARE INTENDED TO INDICATE THE BOUNDARIES OF THIS RELEASE. FUTURE CHANGES THAT MAY BE MADE TO THIS SYSTEM ARE INTENDED TO BE CON-SIDERED A PART OF THIS RELEASE IF WITHIN THESE ESTABLISHED BOUNDARIES.

ATTACHMENTS DEFINING. BOUNDARIES:

RELEASED FOR PREOPERATIONAL TESTING:

Daniel's Proj. Mgr/Asst. Proj. Mgr. Date

e Vepco Q. C. Date The Following Items Are Attached:

Test Matrix ----Completed Construction Tests ----Construction Deficiency List ----ACCEPTED FOR PREOPERATIONAL TESTING:

Vepco S/U Supervisor

All Documentation Received: (Initials)

RELEASED FOR UNRESTRICTED OPERATIONS:

Vepco S/U Supervisor

Vepco Q. C.

The Following Items Are Attached: Test Matrix ----Completed Construction Tests

Date

Date

Date

----Completed Pre-Op Tests Master Deficiency List e

ACCEPTED FOR UNRESTRICTED OPERATIONS:

S/U Coordinator Date

SEO Project Engineer Date

Release Coordinator Date

Lead Advisory Engineer Date

Lead Advisory Engineer Date

Supt. of Operations Date

s~s. tio. .- ATTACHMENT 8. 2

,•, • • I

'JEPCO

DEF IC I rncv flU/iCH LI ST

• 0/\TE: -----------PAGE OF ---- ------== --~!~-=-==.:====-=--=-== f DEFICIE!ICY ~ DESCRIPTIOU • NO. C

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, • ATTACHMENT 8. 3 R!:'N O~l< CO NT!< Oi. FORM RCF = . -· ----

1- DATE f-------------- ------~-----·-·-·------.-·--------·---····· ..

I S'(c;.T, ;:M EQUl?,"EN·r1'CO'\PONEN-, ~ ~ V\ IV EQUIPMENT S::R!AL.::: ystem Number

i------:---------i------------+-----------+--------------DRAWING/REVISION SPECIFICATION/REV. LOCATION F.C. ATTACHED

YES D NO 0 REASON FOR REWORK:

WORK DESCRIPTION:

RETEST REQUIREMENTS:

ADVISORY ENGINEER DATE:

AUTHORIZATION FOR DISASSEMBLY ACKNOWLEGMENT 1------------~---=---------1,------------1-----------·· R!:SIDENT ENGINEER

REASSEMBLY COMPLETE

Release Coordinator

DATE

' ADVISORY ENGINEER FIELD QUALITY CONTROL

REWORK COMPLETION STATUS

RETESTS COMPLETE REASSEMBLY INSPECTIONS COMPLETE

RETEST INSPECTIONS COMPLETE

----+------- ----ADVISORY ENGINE::R

DATE FQC

INSPECTION CHECKLIST ATTA.CHED

DATE

YES D NO 0

FQC DAT

.•

• SYSTEM NO.

2-2-2-1 2-2-2-2 2-2...:2-3

2-2-3-1 2-2-4-1

2-2-5-1 2-2-6-1 2-3-1-1 2-3-2-1 2-3-3-1 2-3-3-2 2-3-3-3 2-4-1-1 2-4-1-2

a-4-1-3 W-4-2-1

2-4-2-2 2-4-3 2-4-3-1 2-4-3-2 2-4-3-3 2-4-3-4 2-4-3-5

2-4-3-6 2-4-3-7 2-4-3-8

2-4-3-9 2-4-3-10 2-4-3-11 2-4-3-12

2-4-3-13

2-4-3-14

2-4-3-15 2-4-3-16 2-4-3-17

A-4-3-18 ·-4-3-19

2-4-3-20 2-4-3-21

SURRY POWER STATION UNIT NO. 2

SYSTEM MATRIX

QUALITY. SYSTEM GROUP

Gire. Water-Water Box Vac. Prim. Gire. Water & Serv. Wtr. Rad. I Monitors Disch. Vac. Prim. Screen Wash Pps & Traveling Screen Condenser Tube Cleaning H.P. Heater Drain Main Steam Extraction Steam Aux. Steam Aux. Boiler & Controls Fuel Oil Sys. Condensate Storage Tk Main Condenser Condensate Sys. L. P. Htr. Drns. Secondary Misc. Drns. Condensate Polishing System

C.P.S. SWGR & MCC's Neutralization Sumps Low Conductivity Sumps Instrument Air Hdr. C.P.S. Control Pnl (Interior) Condensate By-Pass Condenser Connection #57 Connecting Piping Turb. Bldg. Demineralizers Resin. In/Out Demins. 8 11 Piping Demin. to Cond. 4 11 Piping Demin to L. C. Sumps Regen. & Demin. Piping to Sumps Sluice Water & Air to Demin. Air to Demin. Vessels Regen. Vessels Acid to Cation Vessel Caustic to Anion Vessel Water Rec. to Regen. Vessels Air Compressor Air Compressor Cooling

I

I

affected by affected by remained in

remained in affected by

affected by in the area affected by in the area in the area remained in in the area affected by affected by affected by affected by in the area affected by

-- --- ------ ---- ----------------

Attachment 8.4 Page 1 of 5

BASIS FOR TESTING

design change construction design change construction service

service maintenance

design change construction of design change construction design change construction of design change construction of design change construction service of design change construction design change construction design change construction design change construction design change construction of design change construction design change construction

-f ••

e SYSTEM NO.

2-4-3-22 2-4-3-23 2 4-3-24 2-4-3-25 2-4-3-26 2-4-3-27

2-4-3-28 2-4-3-29 2-4-3-30 2-4-3-31 2-4-3-32 2-4-3-33 2-4-3-34 2-4-3-35 2-4-3-36

2-4-3-37

2-4-3-38 2-4-3-39

•4-3-40 4-3-41

2-4-3-42 2-4-3-43

2-4-3-44 2-4-3-45 2-4-3-46 2-5-1-1 2-6-1-1 2-6-3-1 2-6-4-1 2-7-1-1 2-7-1-2 2-7-2-1

2-7-3-1 2-7-4-1 2-7-5-1

2-7-6-1

2-7-6-2

67-6-3 ·9-1-1

2-9-2-1 2-9-3-1

SYSTEM

Water Recovery Tank Spare Regen Vessels Air Blower Neut. Sumps Pumps to PND Low Cond. Sump Pumps Filters & Piping to CW Tunnel Caustic Recovery Tk Acid Rec. Tk Aux. Control Pand Fire Control Sys. Floor Drainage Caustic Storage Acid Storage Ammonia Storage Ammonia to Anion Vessel & Ammonia System Neut. Caustic & Acid Feed Pumps Sampling System Heat Trace Sys. Building Release URC Control RM A/C NUS Area Blowdown Fans Main Bldg. Vent. Storage Area Vent. Misc. Fans

Cond. Air Removal Feedwater Stm. Gen. Blowdown Aux. Feedwater Radiation Monitors Manipulator Rad. Monitors CRD-MG Sets, Full Rod Controls Nuclear Instrumentation Incore Instrumentation Rod Position Indication Racks & Controls, RPI Indicators Systems & Controls Solid State Protection Aux. Relay Rack Input Logic & Output Cabinets Safeguards Test Cabinets & Aux. Relay Circuits Aux. Relay Cabinets & Panels Component Cooling Chilled Comp. Cooling Chilled Water

QUALITY GROUP

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--------- --- --------


BASIS FOR TESTING

in the area of design change construction affected by design change construction affected by design change construction in the area of design change construction remained in service affected by design change construction affected by design change construction

remained in service in the area of design change construction affected by design change construction

remained in service

remained in service

remained in service in the area of design change construction affected by design change construction affected by design change construction

e SYSTEM NO.

2-9-4-1 2-9-5-1 2-9-5-2 2-9-5-3 2-9-6-1 2-12-1-1 2-12-1-2 2-12-2-1 2-12-2-2 2-12-3-1 2 12-4-1 2-13-1-1 2-13-2-1 2-13-2-2 2-13-2-3 2-13-2-4 2-13-2-5 2-13-2-6 ~-13-3-1 ~-13-3-2 ~-13-3-3 ~-13-3-4

•13-3-5 13-3-6

~-13-4-1

~-13-4-2 ~-13-4-3

~-13-4-4 ~-13-5-1

~-13-5-2 ~-13-5-3

~-13-5-4 ~-13-6-1 ~-13-6-2 2-13-7-2 2-13-7-3 2-14-1-1 2-14-1-2 ~-15-1-1 2-15-1-2 2-15-1-3 2-15-3-1 2-15-3-2 2-15-3-3

.15-3-4 915-3-5

2-15-3-6

SYSTEM

Neutron Shield TK Cooling Service Water

QUALITY GROUP

I I

Service Water to R.S.Ht. Exch. I Service Water to CH Pumps Coolers I Bearing Cooling Instrument Air Compressor Instrument Air Sys. Service Air Compressor Service Air System Containment Instru. Air. Air Start - Emerg. Diesels I Chemical Feed Flash Evap. System

Unit #2 M/U Demin. Unit #2 Acid Supply Unit #2 Caustic Supply M/U & Dilution Water #3 Demin. M/U & Filtered Water TK Influent & Effluent Air Supply Surface Wash Backwash & Backwash Sump Evaporator Makeup Caustic Supply - Waste Neut. Acid Supply - Waste Neut. Waste Neut. Supply from Demin. Sump Waste Neut. Sys. Distilate - Dilut. & Demin. Supply Distillate Truck Loading Distillate - Cond. Pol. Regen. Distillate - Seal Water Polyner Sys. Hypochlorite Sys. Unit 2 Blowdown Treat. Drain TK & Stor. Area

Nitrogen Supply Hydrogen Supply Fire Protection Pumps & Control Sprinkler & Deluge Hose Reel Stations Lo. Press. co

2 Cable Vault

Lo. Press. Co2

Emerg. Gen. Lo. Press. Co

2 Charc. Filters

Lo. Press. co2

- Turb. Gen. Lo. Press. Co

2 - Exciter

Lo. Press. co2

Cable Trays

I


BASIS FOR TESTING

affected by design change construction affected by design change construction in the area of design change construction remained in service remained in service remained in service in the area of design change construction remained in service in the area of design change construction affected by design change construction remained in service affected by design change construction affected by design change construction

affected by design change construction remained in service remained in service remained in service remained in service remained in service remained in service remained in service affected by maintenace affected by maintenance remained in service

e SYSTEM NO.

2-15-5-1 2-15-5-2 2-15-5-3 2-16-1-2 2-16-2-1 2-16-2-2 2-16-2-3 2-16-3-1 2-16-4-1 2-16-5-1 2-16-6-1 2-16-7-1 2-16-8-1 2-16-9-1 2-16-9-2 2-16-9-3 2-21-1-1 2-21-2-1 2-22-1-1 2-22-4-1 2-22-5-1

• 22-6-1 22-7-1

2-22-7-2 2-22-8-1 2-22-9-1 2-22-10-1 2-22-11-1 2-22-11-2

2-22-12-1 2-22-13-1 2-22-14-1 2-22-15-1 2-22-16-1 2-23-5-2 2-23-5-3 2-23-5-4 2-23-5-5 2-23-5-6 2-24-1-1 2-24-1-2 2-24-1-3 2-24-1-4 2-24-1-5 2-24-2-1 2-24-3-1

A-24-4-2 ~-24-6-1

2-24-6-2 2-24-7-1

QUALITY SYSTEM GROUP

Smoke Detector - Control Rm Smoke Detector - System Radiant Heat Sensors Turb. Gen. Gland Stm & Seals Emgerg. Turb. Oil Pump Bearing Oil Pump HP Seal Oil Backup Pump Turn. Lube Oil Sys. Turning Gear & Bearing Lift EH Control Fluids Sys. Generator Seal Oil Generator H

2 & co

2 Generator Leads Main Gen. & Exciter & Controls Turbine Supervisory Main Turbine Turb. Plant Sampling Reactor Sampling Station Transformers 4160V Busses & Controls Station Batteries & DC I Dist rib • Emergency Diesels I 480V Mcc's & Controls 480V Emerg. Bus & Mcc's I Vital Busses I 120V AC Distribution Station Lighting Heat Tracing (Borated Systems) I Heat Tracing (NonBorated Systems) Computer & Controls Main Control Board (Unit 2) I Secondary Plant Process Racks I Primary Plant Process Racks I RC#2 Electrical Penetrations I Safeguards & Valve Pit Sumps Containment Sumps Subsurface Sumps RC Floor Drainage Turbine Sumps CRD Cooling Fans I RC Air Recirc Fans I RC Iodine Fans I Sfgd. Supply & Exhaust I MCC Cable Vault Vent. Switchgear Vent. Turbine Exhaust Turbine Supply Air Control & Relay Rm. A/C I Control & Relay Rm. Vent. Turb. Bldg. Stm. Heat


BASIS FOR TESTING

remained in service remained in service remained in service affected by maintenance remained in service remained in service remained in service affected by maintenance affected by maintenance affected by maintenance remained in service remained in service remained in service affected by maintenance affected by maintenance affected by maintenance remained in service affected by design change construction remained in service affected by design change construction remained in service

remained in service remained in service affected by design change construction remained in service remained in service remained in service remained in service remained in service

remained in service remained in service remained in service remained in service remained in service remained in service affected by design change construction remained in service affected by design change construction remained in service affected by design change construction affected by design change construction in the area of design change construction remained in service remained in service remained in service remained in service remained in service remained in service remained in service in the area of design change construction

e SYSTEM NO.

2-24-7-2 2-24-8-1 2-25-1-1 2-26-1-3 2-26-2-1

~-26-3-1 ~-26-3-2 2-26-3-3 2-27-1-1 2-27-1-2 2-27-2-1 2-27-3-1 2-27-4-2 2-27-4-3 2-27-4-4 2-27-4-5 2-27-6-1 2-27-6-2 2-27-6-3 ~-30~1-l ~-30-2-1

·-30-1-2

~-30-3-1 ~-30-4-1 ~-30-4-2 !2-30-5-1 ~-30-5-2 ~-30-5-3 ~-30-6-1 !:z:-30-6-2 2-31-1-1 2-31-4-1 2-33-1-1 2-34-1-1 2-34-1-2 2-34-1-3 2-35-1-2 2-35-1-3 2-36-1-1 2-36-1-2 2-37-1-1 2-37-1-2 2-38-1-1 2-40-1-1 2-41-1-1 2-42-1-1

&-43-1-1 W-44-1-1

2-45-1-1 2-46-1-1 2-47-1-1 2-48-1-1

SYSTEM

Safeguard Bldg. Stm. Heat RC Purge Reactor Coolant Charging Letdown Charging High Head SI & Seal Water Boric Acid Storage & Controls Boric Acid Transfer Boric Acid Blender & Controls Low Head S. I. S.I. Accumulators Residual Heat Removal Containment Vacuum RWST Recirc. Pumps Containment Spray RWST Chem. Add. TK Outside Recirc. Spray Inside Recirc. Spray Post DBA H

7 Recombiner

Liquid Waste Decontamination Sys. Liquid Waste Evaporation & Controls Solid & Liquid Waste Drumming Gaseous Waste Gaseous Waste Recombiners Boron Recovery Gas Strippers Boron Recovery Evaps Boron Recovery Sys. & Controls Primary Grade Water PG Water to RC #2 Primary Drains Process Vents Cont. L~akage Monitor Refueling Purification Reactor Cavity Fuel Pit Cleanup & Cooling RC Elevator Personnel and Equipment Hatch RC Polar Crane RC Jib Cranes Fuel Transfer Sys. RC Cavity Manipulator Crane S.G. Recirc. & Transfer Security Sys. Turb Bldg. Service Bldg. Aux. Bldg. Reactor Containment Excore Detectors Fuel Bldg. Decon. Bldg. Fire Pump House

QUALITY GROUP

I I I

I I I I I I I

I I I I I

I I I

I

I

I I

I I

I I I I I I I

~-----


BASIS FOR TESTING

remained in service affected by design change construction affected by design change construction

-----·---

in the area of design change construction in the area of design change construction

remained in service remained in service remained in service affected by design change construction in the area of design change construction affected by design change construction in the area of design change construction remained in service affected by design change construction affected by design change construction affected by design change construction affected by design change construction affected by design change construction in the area of design change construction remained in service remained in service remained in service

remained in service remained in service remained in service remained in service remained in service remained in service remained in service in the area of design change construction affected by design change construction in the area of design change construction remained in service affected by design change construction affected by design change construction remained in service affected by design change construction affected by design change construction affected by design change construction affected by design change construction in the area of design change construction affected by design change construction affected by design change construction affected by design change construction affected by design change construction remained in service remained in service affected by design change construction in the area of design change construction remained in service remained in service remained in service

...... __ ......

-

-

e

ATTACHMENT 8.5

b Conser. Forces

Perform Gonstr. Tests Field Chang~s initiated as required (TEP's, TIP's, hydros).,.-~~~, as re uired SEO reviews, modifies, as required,

approves Field Chan_ge rennests

"""',_. _ _._ __ -tSEO returns Field Change to Constr. Forces for im lementation

SEO review & approval 1-----~-i

Const •. phase _of D.C. pkg on ·system compl,.

SEO walk-down of system-. to insure completion and to generate deficiency·l-7-+-+-f'--r'-I~ list.

:..?:~-- : ,, ..

· >;{t;.t~.-~..;.:.';j sign-off Release Transmittal

Release to Start-up Grp. with deficiency list, for PRE-OP TES ING

.... ----------------'Jlo,fStart-up Group reviews sys·tem· for· ACCEPTANCE

S/U Grp "Accepts" Sys tell)

"Rejects" System returri to SEO for com-pletion of DISCREPANCIES

S/U Grp. performs required,-...~~~~~~--~~--, ,---------iTEP1s, TIP's, TMP's for

initial o eration

VEPCO I & C calibration as re uired.

$ystem returned to .. S/U Grp for completio of discrepancies

S/U Grp performs require~ flushing and pump verification

performing require TEP's TIP's TMP's

of syste!ll· -

Review

Field

S/U Grp to perform necessary tests to insure proper functional opera- 1

1

bility of systems that may have been damaged during construction activities.

Released with deficiency list SU Grp sign-off system OPERATIONS for PLANT -~,......-~ transmittal.

START-UP

OPERATIONS rejects system

OPERATIONS accepts sy~tem

VEPCO Station & S/U Grp to perform re uired S/U Tests

POWER OPERATION

ATTACH~ 8.6

SUPT. MAINT.

e ORGANIZATIONA. L CHART


STATION MGR

-----

SUPT. TECH SER\i

SAFETY COMMITTEE

SUPT. OPERATION: :

/ STARTUP /· COORD.

/

e ·. ;-

SGRP MGR

RELEASE COORD.

' . . ,,

(MAINT. TEST) (I a C TESTS) _JPROJECTENf __ 1---1

MAINTENANO ~ INST. TECH

__ ___._ __ (S/u , STARTUP TESTS GROUP

CONST. CONST. ----------- TEST

GROUP ENG.

~CONST. TESTS) -__.ea.-. , (PREOP TESTS) OPERATIONS DANIEL

--·· -- ---- -- -- - ---- ---··-·----- -- ----- ----

CTG REQUIRED TESTS CONSTRUCTION TEST PHASE

TEP-1

TEP-2

TEP-3

TEP-4

TEP-5

TEP-9

TIP-1

TIP-2

TMP-1

TEP-10

TEP-12

Insulation Resistance Measurements

Control Circuitry Checkout

Low-Voltage Swgr Inspection

Motor Operated Valve Check-Out (Static)

(VEPCO A & C) Circuit Bkr & 0/L's Checkout

Computer Point Checkout

I & C Electrical Checkout

I & C Mechanical Checkout

General Hydrostatic Tests

Annunciator Checkout

Heat Trace Checkout

---- -- -- ··-- ------------·---

Attachment 8.7

S/U GROUP REQUIRED TESTS PRE-OP TEST PHASE

TEP-40 TEP-8 TEP-7

TEP-70

TEP-llU

TEP-llC

TIP-3

TIP-4

TIP-5

TIP-40

TMP-2

TMP-3

Flushing

FSOP's

Dynamic MOV Checkout D.C. Motors Uncoupled Motor Runs

Coupled Motor Runs

Uncoupled Vibes

Coupled Vibes

I & C Functional Checkout

AOV/AOD Setup and Checkout

I & C Hydro

AOV/AOD Dynamic Checkout

Air Balancing

Pump Curve Verification

integrated startup test program.' · 2019. 12. 27. · startup network list of major preoperational...

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