attachment 3 calculation epm-dtn-071392 · 2012. 11. 30. · revision log. sheet 2 of 34 eb-wbn-63,...

ATTACHMENT 3

CALCULATION EPM-DTN-071392

9608020072 960726PDR ADOCK 05000390P PDR

DNE CALCULATIONSTVA 10697 (DNE-686)

TITLE:DOCUMENTATION OF DESIGN BASIS REVIEW, REQUIRED THRUST/TORQUECALCULATIONS, AND VALVE AND ACTUATOR CAPABILITY ASSESSMENT FOR VALVE1 -FCV-63-26

QARecordSHEET 1 of 34

PLANT/UNITWATTS BAR NUCLEARPLANT/# 1

PREPARING ORGANIZATION KEY NOUNS (Consult RIMS DESCRIPTORS LIST)DNE, ABB IMPELL, EBASCO, MECHANICAL MOV, VALVE OPER, VALVE ACTUATORS

BRANCH/PROJECT IDENTIFIERS Each tiure iihoze c&lcu;latns are issued, preparer must ensure that theMEB-WBN-63 original (RO) P.IMS .cc:asion number i6 filled in.WBN-63-D053 Rev. (for RIMS' use) RIMS accession numberEPM-DTN-071392 / '

R0~ ~~~~q IpC ~fia S 1 n 5APPLICABLE DESIGN DOCUMENT(S) q WOY 2 S 19 3 B H 9 4 X X

t4/AfA //iZ2fc 2 R - t~D]R 2,6 94 122 i 4 iSAR SECTION(S) UNID SYSTEM(S) R3

3.9.3.2 063 Se-lBe2 Y '95[08 0 3REVISION 0 Ri R2 R3 Ssf ety-related? YES (X) No [ECN No. (or Indicate Not Applicable)

SKAf~ /D/2/5j2 5 -3 8, 41 -A S-3F9 5- -A

Prepared: .D. T. Nakahata Y f/& £-7o, ,kjA /ow

Checked/Verified:: /3/9Z g R{614oLL s a

T. S. Snead g,, . 1 Ao/Reviewed:

T. J. Miller_<_ _ _ _

Approved: - MCFiT. J. Miller 7 -'

Date: lL- 2-<

List all pages added by thisrevision

.See. E'

List all pages deleted by this -erevision -

List all pages changed by thisI revision - -

Statement of Problem:

NRC Generic Letter 89-10requires that each licenseedevelop, implement, anddocument a program whichensures that specified safety-related motor-operated valves(MOVs) will perform their safetyfunction for the life of the plant.

Part of this program involves thedocumentation of MOV designbasis review, determination ofrequired thrust/orque andassessment of valve andactuator capability.

ORI GINAL

Abstract: These calculations contain an unverified assumption(s)that must be verified later. Yes [ ] No [X1

This calculation documents the design basis review and required thrustttorque for MOV 1-FCV-63-26. The design basis reviewhas been performed and the required thrust/torque has been determined per the methodology specified in Mechanical DesignStandards DS-M18.2.21 and DS-M18.2.22. This methodology addressed the new requirements specified in NRC Generic Letter89-10. As summarized in Section 8.0 this calculation shows that the valve and valve actuator are capable of meeting the newthrust/torque requirements. Therefore, based on the results of this calculation 1-FCV-63-26 is able to perform its design basisfunction.

7ra, f C. Cc/C'C./0h no0 s>> / re c-,f5I

Microfilm and store calculations in RIMS Service Center Microfilm and destroy. [][X) Microfilm and return calculations to: Calculation Library Address: 10-1 E

cc: C o mas e e f -r G .o~a ,, . rai , 'ho

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USE FORMTVA 10534 IFMORESPACEREQUIRED

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REVISION LOG

SHEET 2 OF 34. EB-WBN-63, WBN-63-D053, EPM-DTN-071392

TITLE: DOCUMENTATION OF MOV DESIGN BASIS REVIEW AND THRUST/TORQUE CALCULATIONS FOR

I -FCv-6A-2fil-

REVISION DESCRIPTION OF REVISION DATE

NUMBER APPROVED

Prepared By: D. Nakahata 6&71- Vz' 7-

0 ORIGINAL ISSUE /1 51Checked By: T. Snead I -~ // i/9 Jz II-

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REVISION LOG

*A *7/*0RS

MEB-WBN-63, WBN-63-D053, EPM-DTN-&73192 07'/3Z- SHEET 2A OF 34

TITLE: DOCUMENTATION OF MOV DESIGN BASIS REVIEW AND THRUST/TORQUE CALCULATIONS

FOR 1-FCV-63-25

REVISION DESCRIPTION OF REVISION DATE

NUMBER APPROVED

This revision incorporates the following MOV issues: 3 ' - v

3revise Reconciliation, update References

Pages Revised: I, tY y 7//9 1,22,3, 25 3 73

Pages Deleted: 33/33l

Pages Added: Z/4 C, 3C3 3 /; /2*A ( ,P/.

DCCM and CCRIS search was performed on 7/20/92 and no changes were

found which affect this calculation revision.

Prepared: 74A441 ;7

Checked: j kJ

THIS PAGE ADDED BY REVISION 3

Il

EBASCO SERVICES INCORPORATEDSHEET 3 OF 34

CLIENT: TENNESSEE VALLEY AUTHORITY PROJECT: WATTS BAR NUCLEAR PLANT UNIT - 1

SUBJECT: DOCUMENTATION OF MOV DESIGN BASIS REVIEW AND THRUST/TORQUE CALCULATIONS FOR

1 -FCV-63-26

CALCULATION DESIGN VERIFICATION (INDEPENDENT REVIEW) FORM

MEB-WBN-63, WBN-63-D053, EPM-DTN-071392 0

Calculation No. Revision

Method of design verification (independent review) used(Check method used):

1. Design Review X2. Alternate Calculation NR3. Qualification Test NR

Justification (explain below):

Method 1: In the design review method, justify the technical adequacy of the calculation and explain how the

adequacy was verified. (Calculation is similar to another, based on accepted handbook methods,

appropriate sensitivity studies included for confidence, etc.)

Method 2: In the alternate calculation method, identify the pages where the alternate calculation has been

included in the calculation package and explain why this method is adequate.

Method 3: In the qualification test method, identify the QA documented source(s) where testing adequately

- demonstrates the adequacy of this calculation and explain.

This design review was conducted in accordance with TVA Desiqn Standards DS-M18.2.21 and DS-M18.2.22.

Calculation Methodology and results were compared to these standards and were found to meet the technical

requirements contained therein. The design input and assumptions were verified and found to be reasonable. The

calculation results are adequately conservative. The computations were checked, and the evaluation of the

differential and line pressure scenarios was confirmed using the references in Section 5.0

Design Verifier Date(Independent Reviewer)

SHEET 3A OF 34

WATTS BAR NUCLEAR PLANT UNIT 1

U BJECT: DOCUMENTATION OF MOV DESIGN BASIS REVIEW AND THRUST/TORQUE

CALCULATION FOR 1-FCV-63-26


1IvPfl-DVD N -o , VVIN -t: 0.), '. .) . s . , 1-v D ; - ; -4

Calculation No.

Method of design verification (independent review) used

(Check method used):

1.2.3.

Design ReviewAlternate CalculationQualification Test

x

NRNR


Method 1:

ethod 2:

Method 3:

In the design review method, justify the technical adequacy

of the calculation and explain how the adequacy was

verified. (Calculation is similar to another, based on

accepted handbook methods, appropriate sensitivity studies

included for confidence, etc.)

In the alternate calculation method, identify the pages

where the alternate calculation has been included in the

calculation package and explain why this method is adequate.

In the qualification test method, identify the QA documented

source(s) where testing adequately demonstrates the adequacy

of this calculation and explain.

This desian review was conducted in accordance with TVA Design Standards DS-

Calculation methodology and results were compared

to these standards and were found to meet the technical requirementsr-rr~-; nod -hi-rmin. The cip-eirn innut and assumptions were verified and found

Thebo JJ L)(7 * III t_ ~_.a..L%.U.-uCZ±kL I-J. ± - ------- -

computations were checked, and the evaluation of the differential and line

pressure scenarios was confirmed using the references in Section 5.0.

))229) / ~ /psig4 Verifier

(Independent Reviewer)

zD a( /teDate

THIS PAGE ADDED BY REV 1

-

-_ 1O-.T1- IT -f TTr) ?T C)- nn RPr I v M-nTmn-71q92KMzEV ~Iz LU I

M18.2.2 ?1 a)nd DSTq-M18. -2.-2 2

__1 - -- -o -11 A _-"- _ -r} lll +;.^n_ -I r +cile n-rP A al tR V conservative

SHEET 3B OF 34

CLIENT: TENNESSEE VALLEY AUTHORITY

PROJECT: WATTS BAR NUCLEAR PLANT UNIT 1

k BJECT: DOCUMENTATION OF MOV DESIGN BASIS REVIEW AND THRUST/TORQUE


CALCULATION DESIGN VERIFICATION (INDEPENDENT REVIEW)

MEB-WBN-63, WBN-63-D053, EPM-DTN-071392Calculation No.

FORM

2Revision

Method of design verification (independent review) used(Check method used):

1.2 .3 .

Design ReviewAlternate CalculationQualification Test

XNRNR


Method 1: In the design review method, justify the technical adequacy of the

calculation and explain how the adequacy was verified.

(Calculation is similar to another, based on accepted handbook

methods, appropriate sensitivity studies included for confidence,

etc.)

Method 2: In the alternate calculation method, identify the pages where the

alternate calculation has been included in the calculation package

and explain why this method is adequate.

thod 3: In the qualification test method, identify the QA documentedsource(s) where testing adequately demonstrates the adequacy of

this calculation and explain.

This design review was conducted in accordance with TVA Design Standards DS-M18.2.21 and DS-

M18.2.22. Calculation methodology and results were compared to these standards and were

found to meet the technical requirements contained therein. The design input and assumptions

were verified and found to be reasonable. The calculation results are adequately

conservative. The computations were checked, and the evaluation of the differential and line

pressure scenarios was confirmed using the references in Section 5.0. This revision

addresses increased actuatorrthrust ratings. /

I l 4Design Verifier/ -(Independent Reviewer)


Date1;I

SHEET 3C OF 34

CLIENT: TENNESSEE VALLEY AUTHORITY

0OJECT: WATTS BAR NUCLEAR PLANT UNIT 1

UBJECT: DOCUMENTATION OF MOV DESIGN BASIS REVIEW AND THRUST/TORQUE



MEB-WBN-63, WBN-63-D053, EPM-DTN-071392 3

Calculation No. Revision

Method of design verification (independent review) used

(Check method used):

1. Design Review X

2. Alternate Calculation NR3. Qualification Test NR


Method 1: In the design review method, justify the technical adequacy of the

calculation and explain how the adequacy was verified.

(Calculation is similar to another, based on accepted handbook

methods, appropriate sensitivity studies included for confidence,

etc.)

Method 2: In the alternate calculation method, identify the pages where the

alternate calculation has been included in the calculation package

and explain why this method is adequate.

3: In the qualification test method, identify the QA documented

source(s) where testing adequately demonstrates the adequacy of

this calculation and explain.

This design review was conducted in accordance with TVA Design Standards DS-M18.2.21 and DS-

M18.2.22. Calculation methodology and results were compared to these standards and were

found to meet the technical requirements contained therein. The design input and assumptions

were verified and found to be reasonable. The calculation results are adeauately

conservative. The computations were checked, and the evaluation of the differential and line

pressure scenarios was confirmed using the references in Section 5.0. This revision

incorporates revised reconciled test dat,??

|`esign Verifier / Date(Independent Reviewer)



CLIENT: TENNESSEE VALLEY AUTHORITY PROJECT: WATTS BAR NUCLEAR PLANT UNIT - 1

SUBJECT: DOCUMENTATION OF MOV DESIGN BASIS REVIEW AND THRUST/TORQUE CALCULATIONS FOR1 -FCV-63-26

BRANCH/PROJECT IDENTIFIERS: MEB-WBN-63, WBN-63-D053, EPM-DTN-071392

PREPARER: D. Nakahata griLd

CHECKER: T. Snead

DATE: by/ " '

DATE: V/' i/5-2

TABLE OF CONTENTS

TITLE NH

CALCULATION COVER SHEET .......................................................

REVISION LOG ...................................................................

CALCULATION DESIGN VERIFICATION (INDEPENDENT REVIEW) FORM .........................

TABLE OF CONTENTS .............................................................

SUMMARY OF ANALYSIS

1.0 PURPOSE AND SCOPE ........................................................

2.0 CRITERIA .................................................................

3.0 APPUCABLE CODES AND STANDARDS ...........................................

4.0 ASSUMPTIONS .............................................................

5.0 REFERENCES ..............................................................

6.0 DESIGN INPUT DATA ........................................................

7.0 CALCULATIONS

8.0 SUMMARY OF CALCULATION RESULTS ..........................................

9.0 CONCLUSIONS.............................................................

ATTACHMENT 1: Simplified Sketch (Sheet 1 of 1) X

THIS CALCULATION PACKAGE CONTAINS X2 TOTAL SHEETS

7,AnF3 &-J A- DlO7E (l7 as) W1~1

1EETOS.

1

2

3

4

5

6

7

7

8

11

12

33

34

~Z P

I(

14t ,f 4/


SUBJ: DESIGN BASIS REVIEW; THRUST/TORQUE CALCULATIONS FOR 1-FCV-63-26BRANCH/PROJECT IDENTIFIERS: MEB-WBN-63, WBN-63-Do53, EPM-DTN-071392

PREPARER: D. Nakahata DATE: //0/2

CHECKER: T. Snead n DATE: _______-

1.0 PURPOSE AND SCOPE

1.1 PURPOSE

This calculation documents the design basis review, performsthe required thrust and torque calculations, and assessesvalve and actuator capability for 1-FCV-63-26, the BoronInjection Tank Outlet Isolation Valve (Train A). Thiscalculation contains the comprehensive Generic Letter 89-10engineering analysis for 1-FCV-63-26. The results of thisanalysis are based on implementati of DCN M-21009-A (Ref. R(25.41) for this valve.

1.2 SCOPE J

T h e d e s i g n b as is C r e v i e w is rjdThe design basis review is perfo;Zed in accordance with TVAMechanical Design Standard DS-M18.2.22. It identifies thefunctional, seismic, and electrical considerations whichinfluence the ability of valve 1-FCV-63-26 to perform itsdesign function.

Sections 7.1 through 7.4 of this calculation document specificdesign information for both the valve and its operator.Section 7.5 calculates the maximum thrust/torque capabilitiesof the operator and the thrust/torque required to operate thevalve, using the methodology in TVA Mechanical Design StandardDS-M18.2.21. Section 7.5 also summarizes the manufacturer'sweak-link analysis of the valve. The calculated maximumthrust/torque capability and weak-link analysis are comparedto the required thrust/torque to ensure the operability of thevalve.

The capabilities and requirements of the valve and operatorare based on the worst case line and differential pressuresand electrical conditions, as identified in the design basisreview.


SUBJ: DESIGN BASIS REVIEW; THRUST/TORQUE CALCULATIONS FOR 1-FCV-63-26BRANCH/PROJECT IDENTIFIERS: MEB-WBN-63, WBN-63-D053, EPM-DTN-071392

PREPARER: D. Nakahata 22 DATE: ________

CHECKER: T. Snead DATE: (V3/ L

1.3 CORRELATION

This calculation is presented in Ebasco Project ProcedureE-30-TVA format. To identify the location of data required byTVA Design Standard DS-M18.2.22 the following correlation isprovided.

DS-M18.2.22 ANALYSIS Section

Purpose

Assumptions

1. 0

2.0

E-30-TVA Format

1.0

4.0

References

Design Basis Review

Calculations

Walkdown

Conclusion

3.0

4.0 - 4.4

4.5

5.0

6.0

5.0

7.0 - 7.4

7.5

7.6

8.0 & 9.0

2.0 CRITERIA

The motor-operated valve, 1-FCV-63-26, shall be evaluatedusing TVA Nuclear Design Standards DS-M18.2.21 and DS-M18.2.22.



PREPARER: D. Nakahata DATE: ________2

CHECKER: T. Snead DATE: _____9__

3.0 APPLICABLE CODES AND STANDARDS

3.1 TVA Nuclear Power Mechanical Design Standard DS-M18.2.21,"Motor-Operated Valve Thrust and Torque Calculations",Revisio ,NZ dated 7,'7/95.

3.2 TVA Nuclear Power Mechanical Design Standard DS-M18.2.22, "MOVDesign Basis Review Methodology", Revision 1. dztcd '/9/91. l

3.3 NRC Generic Letter 89-10, "Safety-Related Motor-Operated ValveTesting and Surveillance", dated 6/28/89JO/

3.4 Cuppl=±;,lt 1 to }NRe G LteLte0-9 1, ±tesulL~ vi publi'-Jg6e 'Workshops"', dated 67tt379- a-

r q It A 1 ,B4A a. d cAp-plicaton Guide ror Motor-Operated Valves in Nuclear Power

Plants", EPRI Report NP-6660-D, Final Report dated March 1990.

4.0 ASSUMPTIONS

4.1 Valves are assumed to be in and remain in their normalposition during normal operation or an accident condition suchthat the effects of mispositioning can be determined. Thetechnical justification is to assure that the valves areevaluated at the maximum line/differential pressures and flowvelocity.

4.2 The pressure drop for piping losses is neglected. Thetechnical justification is that it allows for a conservativedetermination of line/differential pressures and flowvelocity.

, I.L. �/Y01r


SUBJ: DESIGN BASIS REVIEW; THRUST/TORQUE CALCULATIONS FOR 1-FCV-63-26

BRANCH/PIJJECT IDENTIFIERS: MEB-WBN-63, WBN-63-D053, EPM-DTN-071392

PREPARER: D. Nakahata "' DATE: (Z

CHECKER: T. Snead DATE: //_3/_ L

5.0 REFERENCES Pl

5.1 TVA WBN Calculation EPM-TSS-110791, Rev.kRX "Generic Letter

89-10 MOV Population at Watts Bar (Unit 1)" ok l

5.2 TVA WHN System Description, N3-63-4001, Rev. K through DCN44 8tx-4 ire, "Safety Injection System"

5.3 TVA WBN Flow Diagram CCD, 1-47W811-1, Rev. A, "Safety

Injection System"

5.4 TVA WBN System Description, N3-62-4001, Rev.32 through DCN

£ 1250D A, "Chemical and Volume Control System"5- 3 46?J'77

5.5 TVA WBN Mechanical Piping Drawing 47W435-1, Rev. P, "Auxiliary

Building; Safety Injection System Piping"

5.6 TVA WBN Environmental Data Drawing, 47E235-61, RevJ/[

"Auxiliary Building, El. 713, Environment - Harsh" I

5.7 Westinghouse letter WAT-D-8939, dated 7/30/92, "Seismic

Qualification of Westinghouse Gate Valves for Watts Bar (RIMS#

T33 920730 983)

5.8 Westinghouse Engineering Memorandum EM-4995, dated 1/28/77,

"Onerability Test Report of Westinghouse Nuclear Gate Valves"

5.9 TVA WBN Mechanical Piping Drawing 47W435-2, Rev.'/, "AuxiliaryBuilding; Safety Injection System Piping"

5.10 TVA WEN Mechanical Piping Drawing 47W435-4, Rev. P, "Auxiliary

Building; Safety Injection System Piping"

5.11 TVA WBN Mechanical Piping Drawing 47W309-3, Rev. B, "Yard &

Auxiliary Building; Large Reservoirs"L3

5.12 TVA WBN Mechanical Piping Drawing 4,'W406-3, Rev.o'f, "Chemical

and Volume Control System"

5.13 TVA WBN Mechanical/Nuclear Design Study dated 5/16/91,

"Identification of Gate Valves Subject to Thermal Binding and

Bonnet Overpressurization" (RIMS# B26 910618 302)

4g.k3 rz




PREPARER: D. Nakahata &- DATE: /l2/Z-

CHECKER: T. Snead DATE: /_//3/5__

5.0 REFERENCES (Continued) 3 l

5.14 TVA WBN Calculation EPM-MA-030292, Rev.'> , "Evaluation of Gate

Valves Subject to Thermal Binding and Bonnet Pressurization

per SOER 84-7" (RIMS# B18 920326 269)

/-5;C -0 103 -19 -A v

5.15 TVA WBN Surveillance Instruction SI Rev ,

"Valve Full Stroke Exercising During Plant Opqration - Safety

Injection System (Train' i)" Gsd S4MOS

5.16 TVA WBN EQIR WBNEQC91046 dated 8/28/91, "Environmental

Qualification Field Verification" (RIMS# T48 911002 998)

5.17 Westinghouse Drawing, 115EO11, TVA Rev. 901, "Motor Op Gate

Valve Model 04000GM88FNBOOB"

5.18 Westinghouse Process Flow Diagram 119OE37, Sh. 1, Rev. 5,

"Safety Injection System"

5.19 TVA WBN Calculation WBN-EEB-MS-TI06-0010, Rev. 8'Auxiliary

Power Systems Analysis on lE Buses Via CSST C and CSST D with

Auto Load Tap Changers," Attachment 10.6, "Motor Control

Center Motor Starting Voltages" 1

W5.20 TVA WBN DCN'M,-11466-A

5.21 TVA WBN Schematic Diagram, CCD, 1-45W760-63-3, Rev. 2, "Safety

Injection System"

5.22 Limitorque Bills of Material provided by letter dated 7/17/86,

under Contract No. 86PNQ-961556 (Microfilm reel #684426)

5.23 TVA WBN System Description, N3-72-4001, Rev. 5 through DCN e3S-18=55 A, "Containment Heat Removal Spray Systems"

5.24 TVA WBN Calculation WBN-EEB-MS-TI08-0008, Rev. .21-, "480V lE

Coordination/Protection" Z

5.25 Crane Technical Paper No. 410, "Flow of Fluids through Valves,

Fittings, and Pipe," 1988

-71V +IVIZOK




PREPARER: D. Nakahata DATE: /1 Z 9

CHECKER: T. Snead DATE: _____

5.0 REFERENCES (Continued)

5.26 TVA WBN Unit 1 Valve Index by Location, WAT-LOC, Rev. 10,

(RIMS# B26 861230 901)

5.27 Westinghouse letter WAT-D-6874, dated 2/24/86, "Data Base for

Motor Operated Valves" (RIMS# B45 860228 601)

5.28 Westinghouse letter WAT-D-8584, dated 6/25/91, "Maximum

Allowable Thrusts for MOVs" (RIMS# B26 910805 300)

5.29 Westinghouse letter WAT-D-8830, dated 4/23/92, "EMD Gate Valve

Wedge Angle Information" (RIMS# T33 920423 954)

09010 Rv5.30 TVA.WBNgCalculato WB EVAR89 -e1 , Rev.i, "Cable atior e

an Epeaomi -,k YAi Ampacityr, System 63, 67 andSpcfe

Cablac"-(Calculation WBPE.^R0312CC± CUTILdAIns all ulmverIfieu

ii-m.p-inn that i;s qgvi fied by Rafarence 5. ±.)

5.31 TVA WBN dMaoran~"l, dated 10/30/9 " e[ui Yf L up able-

,g4f Sizing foz the Generi r Tottpr p9-10 Mater Opca-at-J ValvU (HWOV)

gE; P;lam" '(RIMS~e T41 rQ21n020 Ri)

5.32 ANSI/IEEE Standard 242-1986, "IEEE Recommended Practice for

Protection and Coordination of Industrial and Commercial Power

Systems"

5.33 Westinghouse Equipment Specification G-678852, Rev. 2, "Motor

Operated Gate Valves, ASME Boiler and Pressure Vessel Code

Section III Class 1, 2, & 3," Contract No. 71C62-54114-1.

5.34 WVA WiBN ETutyc.,y Instruction ES 0.2, Rev. 2, "SI TarmŽnation"

5.35 Limitorque Selection Guides:

5.35.1 Application Factors, SEL-4, 7/1/77

5.35.2 Gate & Globe Valve Efficiency, SEL-7, 11/89

5.35.3 Rating Sheets, SEL-9, Rev. 2

5.35.4 Stem Factors, SEL-10, 5/21/79

1S 7 z,4/I

EBASCO SERVICES INCORPORATED

SHEET 11 OF 34


PREPARER: D. Nakahata DATE: /z t/z

CHECKER: T. Snead DATE: ________

5.0 REFERENCES (Continued) 3)t41hJ,17,?do041J 1/kg W,9 -73(? (,84?,7W6Y2pbs3J 7 /2 5 .5.36 RTVA W4N F'nel Safety Analci& Rcp4rt (F£A1 Trajniittal

Packago Nco. 401, dat ~ '1/14,'8, "Chapter 15 NRC QucstionRespo z az~d- Otlier FSAR Revisions Duc to-Uppor IHcad Inj ationRcmcval an~d Uflcw,'Downflcw Ccnvcrsiorw"

5.37 Limitorque letter dated 7/28/92, "Identification of Minimumand Maximum Torque Settings with Output Torque for TVA WBN'sOlder Spring Packs" (RIMS# T33 920728 969)

5.38 TVA WBN Design Criteria WB-DC-30-15, Rev. ,Z, "Motor OperatedValve Thermal Overload and Torque Switch Bypass"

5.39 TVA WBNdn to b usd iqalulati "

5.40 TVA WBN Calcukation WBN-OSG4-091, Rev. p, "Maximum ContainmentWater Level"

5.41 TVA WBN DCN M-21009-A

A review of DCCM was performed and no outstanding changes affectthis calculation.

6.0 DESIGN INPUT DATA

The design input for determining the Motor-Operated valvedesign basis, minimum thrust/torque requirements and operatorcapability were obtained from the references in Section 5.0with the exception of references 5.15 and 5.31. gl

s-,Z 7> -4 /4o t Q 8 , YE~s-qvez

5,3 -rva V BA VeIo- icA-v0 4"- 2-cC/ C'"- vi- c)eor-5o o/o

ReZ,4 leci-kg ° <O , oszea 1111 'c/015Y/so

,%zv75/S 2f33 Y,//10 R035f-p0

5.;rc5 Mleftie? He/r B'T -)Yo1P2 , kd //-/97, S' /' /j8-2 (,)'/0o0d ra/- *, cr 7 /Z?9C, D



PREPARER: D. Nakahata DATE: (/22 r?2

CHECKER: T. Snead' DATE: ///3/9z

7.0 CALCULATIONS

7.1 SYSTEM DESIGN BASIS DATA DATA SOURCER3

1. VALVE NO: 1-FCV-63-26

2. MARK NO: 8801A

3. DESCRIPTION: Boron Inlection TankOutlet Isolation Valve (Train A)

4. FUNCTION: To open upon receipt of aSafety Inlection Sianal to allowCCP flow to the RCS throuah theBoron Injection Tank

5. SEISMIC CLASS: CateQorv I (Active)

6. SYS DESIGN PRESSURE: 2800 psiq

SYS DESIGN TEMPERATURE: 2000 F

7. NORMAL POSITION:

SAFETY POSITION:

8. FLOW RATE:

Closed

Open

354.5 gpm (9.1 fps)

Ref. 5.1,-Att 4, p. '

Ref. 5.2 p. 105

Refs. 5.2..-.P1 ; 5.21

Refs. 5.2.--.-2--3; 5.21

See Comment 7.1.5

Ref. 5.3

Ref. 5.3

See Comment 7.1.7

See Comment 7.1.7

See Comment 7.1.8

9. MAXIMUM LINE/DIFFERENTIAL PRESSURE: SeLine P/Diff. P

Normal Plant Operation: OPEN -- /--Testing: OPEN &235/21706Accident: OPENMisposition: OPEN 2-38/2-2-

276/ .774'10. FLUID TYPE:

FLUID TEMP:

e Comment 7.1.9Line P/Diff. P

CLOSE -- /--CLOSE S2E%/0CLOSE 2350/115CLOSE 57-3/ - -

,2 76 1 .27Y4Licauid (borated water) Ref. 5.2. p. 2 3

1500F. max. operating Ref. 5.18

kres3 17AoAr2_10131zt9_15

73



PREPARER: D. Nakahata DATE:

CHECKER: T. Snead DATE: ______

7.0 CALCULATIONS (Continued)

7.1 SYSTEM DESIGN BASIS DATA (Continued)

11. REQUIRED STROKE TIME: 10 seconds

APPLICABLE SI: SI 1. -5.6 OV.-/B. --

12. LEAK TIGHTNESS REQUIREMENT: 12 cc/hr

DATA SOURCE

Re f. 5. 2 e 10 -

Ref. 5.2 -p-.10See Comment 7.1.12

13. MOV CAN BE FULL FLOW TESTED?: Y (Y/N) See Comment 7.1.13

14. BONNET OVERPRESSURIZATION/THERMAL See Comment 7.1.14BINDING/PRESSURE LOCKING?: N (Y/N)

15. ORIENTATION OF VALVE: Refs. 5.9, 5.10

Line: Horiz X Vert Degrees from vertical_Stem: Horiz Vert X Degrees from vertical_

16. BUTTERFLY VALVE CHARACTERISTICS:

Flow velocities: Not Reauired for Gate Valves

Piping arrangement: Not Recquired for Gate Valves

17. AMBIENT TEMPERATURE: 600 F to 1040 F Ref. 5.6(normal); .-24- 9F (max. accident)

157'

Al

Iif

-



PREPARER: D. Nakahata DATE: (0 zfr0

CHECKER: T. Snead . DATE: _______


7.1 SYSTEM DESIGN BASIS DATA (Continued)

AX0/ ;(; fYU~ i Or sari'-' eJ gry/e ow Als'et *e-COMMENTS /-4- S7P e j I e. F,/ A/ yoA,.Iv/-t'V- ~-2~' ~j&/~i 'e/ i-:.','t ,h'5; i VQI Sei'l -m~.9/{j 7 Ir llxe/.

/~~ix± ..De1mCiCass - 'cRorX1-' S R ProvCK~ide O:I~bilityE testda-f-er- smic qualification of 4" and 12" Westinghouse GateValves. Referenc rizes various sizes ofWestinghouse gate valves into rent groups with the 4"valve representing one group and the 12" va entingte-te gru.1FMG-wsG( "Ydte Vd!Ve)--ts repreeP=

- t OsfV: aooc5,F" # 0 5,yy# /Z6oBased on Reference -7 ility test

operati hrust values of 7,000 lbs. in the opening directionand 13,000 1 'n the closing direction were noted duringstroking at 2500 p

Although Section 7.5.1 of t ign basis review calculatesa required opening thrust of 13,13 (which is greater thanthe Reference 5.8 value), since Referenc demonstratedoperability of the valve under differential preseconditions similar to Section 7.5.1 it may be conclua that

7.1.7 Valve position - This normally closed valve automaticallyopens upon a Safety Injection Signal to provide a flow pathfrom the CCPs to the RCS through the Boron Injection Tank.(Ref. 5.21 p. 23)

7.1.E3 Flow rate - Reference 5.18 provides a maximum flow ratethrough the Boron Injection lines of 709 gpm during Cold LegRecirculation conditions. Since there are two Boron InjectionTank (BIT) Outlet isolation valves, the flow rate through eachis 354.5 gpm. The flow velocity is 9.1 fps (354.5 gpm * [1ft3 /7.48 gal] * [4/{nr * (0.333 ft)2)J * [1 min/60 sec]). Thisconversion is obtained from Ref. 5.25, p.'1-4. The full flowrate of 709 gpm would exist if, due to a single failure, onlyone of the BIT outlet isolation valves opened.

k'7 1 r- c A d- - - - - To - - -, 11 'O I

ls44r



PREPARER: D. Nakahata DATE: _________

CHECKER: T. Snead DATE: ii/3/9Z


7.1 SYSTEM DESIGN BASIS DATA, COMMENTS (Continued)

7.1.9 Computation of maximum line and differential pressures -(Refer to Attachment 1, Simplified Sketch) The pressuresources applicable to this calculation are as follows:

ahd 5.Io The Centrifugal Charging Pump(CCP) differential head is

obtained from References5.4~riPgu-rc3.2 1. During an accidentcondition after isolation of the normal charging path, with a60 gpm CCP recirculation flow rate (Ref. 5.4,-p-.-1-4-0), plus 32gpm o the RCP seals (Ref. -p---2-), the maximum CCP head(dey;

;4f) is &4ft * 0.433 psi/ft psig. (The 0.433 psi/ftconversion factor is taken from Reference 5.25, p. B-ll.)

During normal operation at a minimum charging flow rate of 107gpm [the regenerative heat exchanger requires 15 gpm (Ref.5.4,-p ->e), the RCP seals require 32 gpm, and the CCPrecirculation flow is 60 gpm], the m7i-ftutlCCP head is 5800 ft* 0.433 psi/ft = 2511 psiq.(iuS)

o The elevation head upstream of the valve due to the RWST is763'9,5n(maximum RWST level, Ref. 5.11) - 730'0" (valveelevation, Ref. 5.9) = 33'>5 * 0.433 psi/ft = 14 psi.

O During normal operations the maximum head upstream of thevalve is 65 psig (maximum VCT pressure, Ref. 5.4,- tb-l 3.f-1)minus the elevation difference between the valve (730'0", Ref.5.9) and the maximum VCT level tfhrc betteo lcLe4(44.C 5Iz)instrumantation tap is 717 (flf. 5.12) plus a high-level limit of--65" a oe t~he Ioe dineent tap (Ref. r 4,4'bi-la e 41 723',71/8"J. 65 psig - (730'0" - 723'71/8")*

0.433 psi/ft =5&2 psi.*

o The RCS pressure during normal operation is 2235 psig (Ref.5.4,Tp * 1-; ). Following an accident the RCS pressure would be250 Psig; - Reference 5.36 shows that 20seconds after a coli leg double-ended shear, the pressurewould be 265 psia. (sftIn of /f6/-6?-g6 Qf ;/.ro.c z~'w

* Re-evaluation indicated that the pressure is 62 psi. The technical justificationfor no change is that the resultant DP values are conservative since the 59 psiis the downstream pressure source in determining the DP.

EBASCO SERVICES INCORPORATED

SHEET 16 OF 34


PREPARER: D. Nakahata DATE: ________

CHECKER: T. Snead 2 DATE: /3/XL


7.1 SYSTEM DESIGN BASIS DATA, COMMENTS (Continued)

7.1.9 Computation of maximum line and differential pressures(Continued)

Opening (Accident Conditions) - The valve opens upon thereceipt of a Safety Injection signal which is indicative of adecreasing RCS pressure. Both 1-FCV-63-25 and 1-FCV-63-26should open as the normal charging valves close (Ref. 5 .2 r,-1pP.63 a4-64). For conservatism it is postulated that the normalcharging valves close before either 1-FCV-63-25 or 1-FCV-63-26opens, maximizing the CCP discharge pressure. The line Z555pressure at 1-FCV-63-26 would b e2 5* ipsig which is the -5-ipsig CCP-head plus 14 psi RWST head. The differential pressurewill b k3 84- psl~awhich is the 2X54- 1psig line pressure minus250 psig RCS pressure.

Closing (Accident Conditions) - During restoration from SafetyInjection, the valve is closedW+T-r"thc RCS proEsuro fs abocv

.1500 p&g, SI has been reset and normal charging has beenrestored-(--t-ur.-F-4->-. Reference 5.4,-pa-e-i9- provides a normalcharging line pressure of 2350 psig when the RCS pressure is2235 psig. Under these conditions the differential pressureacross 1-FCV-63-26 is (2350 psig - 2235 psig) = 115 psid. (Forconservatism RCS pressure of 2235 psig is used, maximizing theline pressure.)

Opening and Closing (Normal/Test Operations) - The valve isnot cycled during normal operations; it is stroked forsurveillance testing per SI A..0. ..3.V.2.D.. /Ref. 5.15/, withthe positive displacement pump aligned to supply normalcharging and the CCPs stopped and isolated from the chargingheader. For opening the valve, the downstream pressure couldbe as high as 2235 psig (RCS pressure) if any back leakageexists through the check valves in the boron injection line.The pressure upstream of the valve is5~&6-psig, since the VCTremains aligned to the CCP suction. The differential pressureacross 1-FCV-63-26 is (2235 -5S- psig) = 21726psid. Forclosing, the line pressure would betl- psig (VCT head) and thedifferential pressure would be zero.

Az3 77



PREPARER: D. Nakahata (7L/ - DATE: ______

CHECKER: T. Snead DATE: /I/5/St


7.1 SYSTEM DESIGN BASIS DATA. COMMENTS (Continued)

7.1.9 Maximum line and differential pressures (Continued)

Inadvertent Mispositioning - The valve could be mispositionedopen during normal operations; it could be mispositionedclosed during accident conditions. During normal operations,the reclosing of 1-FCV-63-26 after mispositioning would resultin a maximum line pressure of 25700psig which is the 2511 psigCCP head plusl6y psi due to the VCT pressure and elevationdifference. The differential pressure would be (257p - 2235psig RCS pressure) = 330fpsid.

During accident conditions (RHR recirculation, with 1-FCV-63-25 having failed to open), the reopening of 1-FCV-63-26 after27,mispositioning would iesult in a maximum line pressure of 23-8psia which is the 254. psig CCP head plus 20fipsig for themaximum RHR pump discharge pressure. The latter value is thesum of the RHR pump shutoff head of 195 psig (Ref. 5. 2 ,T -1-:-16-2 , the containment maximum pressure of 15 psig (Ref. 5.23,-

-~-. 1- , and -,'psi elevation difference between the maximumcontainmet sump level (Ref. 5.4 0--ri---2-) and the valve (Ref.5.9). (-'47.A'- 730')* 0.433 psi/ft = -%9psi. Postulating theRCS pressure to be equal to the containment pressure of 15psig, the differential pressure is 72. - 15 = 9FF pisid.

7.1.12 Leak tightness - This leak rate is based on an allowedvalue for gate valves of 3 cc/hr per inch of nominalvalve size * 4 inches = 12 cc/hr (Ref. 5.2r-,-.--03).

7.1.13 Full flow testing - The valve can be full flow tested,although not during normal operations.

7.1.14 Bonnet overpressurization - Reference 5.13 (Section 5.0)states that this valve is susceptible to pressure lockingand bonnet overpressurization. However, Reference 5.14-pge--36) further analyzed the valve and its operatingconditions, and concluded that pressure locking andbonnet overpressurization do not exist for 1-FCV-63-26.

rv nhaswrd 6-ro PV4/"4,,1 - /*9x' DP AeAre4611oA P'I st -S i>< i 1

W40 rlr< Pnpa sh)io)s4v fwv

fAs r7//



PREPARER: D. Nakahata 2v DATE:

CHECKER: T. Snead X DATE: _ /____9L_


7.2 VALVE DESIGN DATA

Valve Tag No. 1-FCV-63-26

Valve Contract No. 71C62-54114-2

Valve Drawing 115EOll

VALVE DESIGN DATA

1. Valve Serial No. 00S710010

2. Valve Model No. 4 GM78FN

3. Valve Manufacturer Westinghouse

4. Valve Pressure Class 1500 psiq

5. Valve Size/Type 4" Gate

6. Seat Diameter 3.87"(Mid point of seat)

7. Seat Angle 70

8. Stem Diameter 1.250"

9. Stem Pitch 0.333"

10. Stem Lead 0.333"

11. Stem Travel 4.3"

12. Disc Type - gate valves (solid wedge,flex wedge, double disc, etc.)

Flex wedge gate valve

DATA SOURCE

Ref. 5.17

Ref. 5.26. p. 11

Ref. 5.27. p.2 of Att.

Ref. 5.26. p. 11

Ref. 5. 2.. 105-

Ref. 5.33, p. 176

Ref. 5.33. p. 176

See Comment 7.2.6

Ref. 5.29

Ref. 5.17

Ref. 5.17

Ref. 5.17

Ref. 5.17

Ref. 5.17



PREPARER: D. Nakahata DATE: ___3__t_7

CHECKER: T. Snead DATE: ell____


7.2 VALVE DESIGN DATA (Continued)

COMMENT

7.2.6 The valve seat diameter at midpoint (Ref. 5.17) wasdetermined by taking the valve throat diameter (3.44")plus 1/2 of the distance between the throat diameter andvalve lift (4.3"). [3.44" + (4.3" - 3.44")/2 ] = 3.87"



PREPARER: D. Nakahata DATE: /&/R0 5A

CHECKER: T. Snead DATE: /1 3/?Z

CALCULATIONS (Continued)

OPERATOR DESIGN DATA

Valve Tag Number 1-FCV-63-26

Operator Mfg. Limitorcque

Operator Type/Size SBD-00

Order Number 378447E

Serial Number 213326

Spring Pack No. 60-600-0022-1

Overall Gear Ratio (OAR) 38.6

Pullout/Run Efficiency 0.45 / 0.6

Stem Factor (FS 0.15) 0.0116

HBC Size Not Applicable

HBC Serial No. Not Applicable

HBC Order No. Not Apolicable

HBC Gear Ratio Not Applicable

13. HBC Gear Efficiency Not Applicable

DATA SOURCE

Ref. 5.16, Att. 1. p.4

Ref. 5.16, Att. 1. p.4

Ref. 5.16, Att. 1, p.4

Ref.-5.16, Att. 1. p.4

Ref. 5.20, p. 5

Ref. 5.41

Ref. 5.35.2

See Comment 7.3.8

No HBC Unit Installed





7.0

7.3

1 .

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12 .




CHECKER: T. Snead . DATE: _______


7.3 OPERATOR DESIGN DATA (Continued)

COMMENT

7.3.5 Spring Pack Capability - Reference 5.20, p. 5 lists thevalve's spring pack as 60-600-0022-1. For this springpack Reference 5.37 recommends a minimum torque setting

7.3.8

of 1, and a maximum of 3, which correspond to outputtorque values of 80 ft-lbs and 253 ft-lbs respectively.

Thew~iimu tvQ~treqire toopn the vale s z--l-bs-ani crque. al 7J ft lLb, is, Heded Ltu lu I iL(-Setion 7.5.1).

The installed spring pack provides a satisfactory marginfor this application, ,ef e t-t

~~~~~ I CZ 1 u± (Re-. I .1 o~~t ~th- edt~spr>Wjirz-pack will provide .Ch^c: QLaLviu~i-z-

.-c,*sihc ;trkcz cotr lrugoLL~

Stem Factor - Reference 5.35.4 (page 6) shows that, usinga valve stem diameter, pitch and lead of 1.250, 0.333 and0.333 inches, respectively, and coefficient of frictionof 0.15, the stem factor is 0.0116.



PREPARER: D. Nakahata '&J DATE: ________

CHECKER: T. Snead DATE: _/I/_/_9-

CALCULATIONS (Continued)

ELECTRICAL DATA

Valve Tag Number 1-FCV-63-26

Motor Mfg. Reliance

ID No. 710741-YE

Start Torque 15.0 ft-lbs (Al ep/qec)

Running Torque not listed

7.0

7.4

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

3400 rpm

1.9 hp

460 V

3.5 A

26.0 A

Duty Cycle 15 min.

Motor Code code not listed

Insulation Class B

Frame Designation P56

Electrical Cable Sizing Satisfactory

Control Circuit Logic Satisfactory

Degraded Voltage Cond. Satisfactory

Overload Sizing T29 - Satisfactory

DATA SOURCE

Ref. 5.16, Att. 1. p.5

Ref. 5.16. Att. 1. P.5

Ref. 5.16. Att. 1. p.5

Ref. 5.16. Att. 1. p.5"

Ref. 5.16, Att. 1. p.5

Ref. 5.16. Att. 1, p.593

Ref. 5.19. p. 180

Ref. 5.19. -P. 180

Ref. 5. 19. .10dbu

Ref. 5.16, Att. 1. p.5

Ref. 5.16. Att. 1. p.5

Ref. 5.16. Att. 1. p.5

Ref. 5.16. Att. 1, p.5

See Comment 7.4.14

See Comment 7.4.15

See Comment 7.4.16

See Comment 7.4.17

RPM

Horsepower

Volts i

Running Current

L. R. Current



PREPARER: D. Nakahata DATE: /nky? 2

CHECKER: T. Snead I21 DATE: //__3/_ _


7.4 ELECTRICAL DATA (Continued)

COMMENTS

7.4.14 Electrical cable sizing - For MOwN 1-FCWZC3-26 ferec5 . it n-- !-o 0 1US t etble 'lalnbe7 as ±V 2680A, tle cabtesize as 4l e the full load (run) current as 3.50amperes and the rotor current as 26.0 amperes. Thecable ampacity calcua. ef. 5.30).shows the derated71% full load ampacity (the us his value isdiscussed in Ref. 5.30) as 3.8 ampers the allowedcable ampacity as 9.4 amperes. (Use of Ref. . s

The cable sizing for this application, including theability to withstand locked rotor conditions, isconsidered satisfactory. Spet 73 JO)

7.4.15 Control circuit loaic - The valve has an active safetyfunction to open upon receipt of a Safety InjectionSignal to allow CCP flow to the RCS through the BoronInjection Tank (Ref. 5.2.rp---m-3), which requires theThermal Overload (TO) Protection Device to be bypassedand the Torque Switch to be bypassed in the openingdirection (Ref. 5.38, pp. 4-5).

The electrical schematic (Ref. 5.21) shows that the TO isbypassed by a safety signal; the valve traveal is limitswitch-controlled in the opening directionof'0torque switchcontro lcd with limit swrch bypacc in the-closingdirection; and the valve will open automatically uponreceipt of a SI signal. Therefore the control circuit for r 4<this valve meets its design application. 1p



PREPARER: D. Nakahata X DATE: /1 / 7CHECKER: T. Snead a DATE: 2//i/94_


7.4 ELECTRICAL DATA. COMMENTS (Continued)!8-3 6'>o lt6 416. 7

7.4.16 Degraded voltage condit' n - During load bl k start3'Y/Y-96.-: of 460 volts, or are av ilable t the valve £3(Ref 5.19 p. lee). During a LOCA/ ELB insi containment j(which results in the block start), the hi est ambienttemperature for this location is F or i'. PC (Ref.5.6). Since the terminal voltage calculations correct thecable resistance to 90'C (Ref. 5.39), for this accidentan evaluation for reduced voltage, due to elevated cableor motor temperatures, is not required.

3 2. Z. Is 6 /o-.7Following a HELB side con6 inment, he maximum ambienttemperature at t e valve is (2LF or C (Ref. 5.6), andthe temperature at the valve exceeds 90'C only-during theperiod of 3 to minutes after a HELB in the RHR systemr(aoSince the cable resistances are normalized to 900 C, )ambient temperature exceeds 900C for a4)minute period,and it takes 1 to 6 hours for cable temperatures to rise(Ref. 5.32, Chap. 8), an evaluation for reduced voltage,due to elevated cable r-mor temperatures, is notrequired. S!~ee ?'s 2'Y1 Or' o: ee/r Do Cf 1/oc<o'QgC4 on <hez ,0 for.~

The thrust and torque capability of the operator during Adegraded voltage conditions is calculated in Section 7.5, ,,f/Fand is shown to be greater than the thrust and torquerequired to operate the valve. Therefore, the valve andits operator are able to perform their safety function.

37.4.17 Overload sizinq - References 5.19 (pige 48.)-and 5.24( e-44~ 1determined that an overload size of T29 isrequired and is installed. The correct heater isinstalled for this application.

128v rr17)zo'SIr

•4r- /rX/- o -7/3 5V 5hw7/,rf ;i-/e 0 of !//

TART TORQE, N...at t.(R. 5./I

MAX ENVIRONMENTAL TEMPERATUREv.. 23 tern petnre (dg F = 1020 d.g..s C

ElevaBed Temperature Evaluatin lor

MOTOR INFORMATION... IS.... n

1-FCV-63-26-A (Re61. 5SY-?

VALVE INFORMATION ACTUATOR INFORMATION.~C..lr..d . :OAR

MOTORTOTAL TEMPERATURE106.4 tobl nWtr tefmpahu.

EVALUATION OF LRA AND LRT....... 9% .nsLRA kss(Lunitottne93-03)

&23% anl % LRA k=z bSnS "e b.mp23.9 wdjimd LRA

*:~~7 : 4;nxTQ km(Lunttorqtn93 -03)

13.67 xdjtwd TQ

TERMINAL VOLTAC.E EVALUATION

6.4AS FOUND 1-FCV-63-26-A 1.90

REVISED I-FCV-63-26-A 1.90

f .: . 4 3.b.

EVALUATION OP MISPOSITIONING4.45 tan1p ri"e S tormi~itic p rwroSke)

29.33 h4h n.' it -&80 Ntyck. hfni 5

0.15 StTck. tial. nuSu

EVALUATION OF VT (BLOCK} INDIVIDUAL) PERSTROKE

b~ck~a.txrt)bSc¢lkson (oprn./dc.e): <5 f.

hudiullwI

FLI LRA LRPF Zrn Re. PIn Rtct Rc jXc Sbzt3.50 260 0.90 101147 9.1932 4.4525 013700 1.1352 0.0404 391.5

3.50 23.9 0.90 11.1122 16.010

91o k

McoorS tn384.4

4.8437 013700 1.1352 0.0404 395.0 387.8

DETE RMINATION OF MOTOR CAPABILITY3860AR

0ll arn .fflc..cy.................

384.4 blocck rnec aor tart Ec fandin WBN-EEB- MS-TIK6-0010 (Rd. 5;/391.S indiv;d4ial nctorstxr *s*fcou rnWBN-EEB-BM -Tl06-0010(Rd. 5' / )387.8 n cw Uck nitoor sbrtvoibge b scen r4l.c.J LRA

0.8431

rletaonrlafran af whl F f dtor (VT-)

0.7108

ddt-rnmintil, 4l a ppiticu facc. (AF)

OPENING MOTOR CAPABILITY

168 It-IbL

..G .**.ff-5g*.S ...... . st n.a.. r

I 483 r.,.

0.8587

0.7374

taV=iul w ta rtio=

VF = 1. if noae lo >.9 othamims = (whage a oj ^2

I AF=I1 Lftt.rnulwltq F. 6o<.Ol~ = .9(Rd. .5 Y'q3

CLOSING MOTOR CAPABILITY

233 fh-1lh (re woric 75.2 for fomrndea.)

bSnsd "o C.n w itdu I" Jixnot

204S6 r6

THIS PAGE ADDED BY REVISION /



PREPARER: D. Nakahata / DATE: /OjA)fZ

CHECKER: T. Snead a DATE: /_/______


7.5 THRUST/TOROUE CALCULATIONS

7.5.1 Valve Thrust and Torque Requirements

Calculation of Piston Effect Load - F

=p*4

(D

Where:

27siP = closing maximum line pressure = 25--3 psig

2761P= Opening maximum line pressure = 2-7-"- psig

d = Stem diameter at packing = 1.25 inches

FClosing =-71 * lr(l.25)2 - 3P 1FP, Cloing * 4 -=-3-6-lbf

S-M18.2.21. - -2)

(Sect. 7.1.9)

(Sect. 7.1.9)

(Ref. 5.17)

FpOpening =4 9335 * _____ = 3-5- lbf

Calculation of Packing Friction Load - Fpck (DS-M18.2.21, p 4-)

F =1000 lbf * d

where:

d = Stem diameter at packing = 1.25 inches (Ref. 5.17)

Fpack= 1000 * 1.25 = 1250 lbf


SUBJ:- DESIGN BASIS REVIEW; THRUST/TORQUE CALCULATIONS FOR 1-FCV-63-26BRANCH/PROJECT IDENTIFIERS: MEB-WBN-63, WBN-63-D053, EPM-DTN-071392

PREPARER: D. Nakahata DATE: _________

CHECKER: T. Snead . DATE: ///3/92Z


7.5 THRUST/TORQUE CALCULATIONS (Continued)

7.5.1 Valve Thrust and Torque Requirements (Continued)

Differential Pressure Load - Fdp (DS-M18.2.21,-p- -3-)

FdpOpening = dp * 7rD' * FV *4 cos p + A sIno

7rD'Fdp,Closing = dp * - * FV * _

4 cos - in¢>

where: e3O-(

dp - Opening differential pressure =---3-& psid (Sect. 7.1.9)

dp =Closing differential pressure =4 epsid (Sect. 7.1.9)

D Seat diameter at midpoint = 3.87 inches (Sect. 7.2.6)

FV Valve safety factor = 1.2 (DS-M18.2.21, p.--3-)

/ Valve friction factor = 0.4 (DS-M18.2.21,p-3.)

Wedge angle = 70 (Ref. 5.29)

.0.4FdpOpening = 4 )1. 2 (cos 7+ (0.4 * sin 7)) =- bf

(dCoig=--- 4 1) ( cos 7 - (0. 4 * sin 7)) -2t2-tlb



PREPARER: D. Nakahata O%2 DATE: ______

CHECKER: T. Snead DATE: ____5Z



7.5.1 Valve Thrust and Torque Requirements (Continued) e3Required Closinq Thrust - Fr (DS-M18.2.21,r-p.1)

Fr'Closing = Fdp + Fpck + Fp

where:

Fdp = Differential Pressure load = -2e- lbf

Fpack Packing Friction load = 1250 lbf

Piston Effect load = 3-1-5-& lbf

/6Y27 332' 75FrClosing 2- + 1250 + 4-5-6 = -64-2-7 lbf

01r




CHECKER: T. Snead DATE: _/_5__




Calculation of Wedging Load - Fw (DS-Ml8.2.2l,1p,---p.)

Fw = Fk * fw* FV 1 -pta * ta Asino + Acosp cosp + 4sinp

where:

fw = Wedge factor = 0.6 (DS-M18.2.21, p. 5 & Ref. 5.17)

Fv = Valve safety factor = 1.2 (DS-M18.2.21, p. 3)

= Valve friction factor = 0.4 (DS-M18.2.21,r-p.3)

= Wedge angle = 70 (Ref. 5.29)

F = Maximum closing stem thrust (DS-M18.2.21, p,.-5rmax=1.15 * Fr = 1.15 (9p = 1 lbf

Fpack = Packing friction load = 1250 lbf (Sect. 7.5.1)

Fp = Piston effect load = 3:15G6-lbf

16'27F= Differential pressure load =.-2421 lbf

Fk Effective unseating force FrM Fpack F - Fd(only closing values) (DS-M18.2.2 p p)

- 4E - 1250 - 15 - 2 = = 9<r4- lbfZ~,2g5- 0 0 2?5

FW = 9 6.4(0.6) l.2( 1- (0.4 tan 7) + 0.4 7 = 448lbfsin 7 + (0. 4 cos 7T) cos 7 + (0.4 sin 7)

'ae 0 CO. ,4 4

/4,Veb -




CHECKER: T. Snead DATE: 9 Z.




Required Openina Thrust - Fr (DS-M18.2.21, -p-i)

Fr/Opening = Fdp + Fpack + FW - Fp

where:

Fd = Differential Pressure load = ±4-75-7 lbf

Fpack =Packing Friction load = 1250 lbf//6 4/3

FW Wedging load = -4- lbf333'?

Fp= Piston Effect load = 335l8 lbf

Fr,Opening = +4-77 + 1250 + -47 - 335 = 5.13-8-lbf

Required Operator Torque - AtorOpening and Closing(DS-M18.2. 2 5

Ator = F * F, where:- '/M373

Fr,Opening = 13138 lbf2/O6S

F ,Closing = -6- lbf

SF = stem factor = 0.0116 (Sect. 7.3.8)

•tOrIOpening = a--3-8 * 0.0116 =15-2- ft-lbs

tor' Closing = 16-4- * 0.0116 = ft-lbsA7/O65 .2



PREPARER: D. Nakahata DATE: 2(/ cjZ

CHECKER: T. Snead DATE: //3/91L



7.5.2 Actuator Capabilities

Opening Operator Torque and Thrust Capability - Ator and Athr(DS-M18.2.21, -p-. -)

A• Orpening = MT * OAR * AF * PE * VF ;A•thropening = AtorOpening / SF

where: i\

- Motor Starting Torque = 15 ft-lbs (Ref. 5.16, Att.1, p.5)

OAR - verall Gear Ratio = 38.6 (Ref. 5.41)

AF = Appl ation Factor = 0.9 (Ref. 5.35.1)

PE = Pullout ficiency = 0.45 (Ref. 5.35.2)

VF = Voltage Facto = 0.744 = 86.2% available voltage squaredor (396.7 volts vailable for block start / 460 volts)2 ,

(Ref. 5.19, p. 180)


A 0 rOpening = 15 * 38.6 * 0.9 * 45 * 0.744 = 174 ft-lbs

AthrOpening = 174 / 0.0116 = 15000 f

(ses- p3 2/14)




CHECKER: T. Snead DATE: ///3__2_


7.5 THRUST/TOROUE CALCULATIONS (Continued)

7.5.2 Actuator Capabilities (Continued)

P3Closing Operator Torque and Thrust Capability - Ator and Athr(DS-Ml8.2.2 1, p--

7-7/,I1otU-A ~rClosing = MT * OAR * AF * RE * VF;Athrl Closing = At Closing / SF

where:

- Motor Starting Torque = 15 ft-lbs (Ref. 5.16, Att.1, p.5)

OAR - verall Gear Ratio 38.6 (Ref. 5.41)

AF = App *cation Factor = 0.9 (Ref. 5.35.1)

RE = Running ficiency = 0.6 (Ref. 5.35.2)

VF = Voltage Fact = 0.772 = 87.85% available voltage squaredor (404.1 volt available for motor start / 460 volts) 2,

(Ref. 5.19, p. 180)


AtorClosing = 15 * 38.6 * 0.9 * 6 * 0.772 = 241 ft-lbs

Athr Closing = 241 / 0.0116 = 20776 f

ts p 5Y

AZl




CHECKER: T. Snead DATE: /___L



7.5.3 Valve/Operator Weak-Link

Valve Weak-Link (Maximum Allowable Valve Thrust)

The valve manufacturer provided the results of an analysiswhich determined the maximum allowable opening and closingthrust which can be applied to the valve and identified thespecific weak-link component. The results are summarizedbelow:

Opening:

Closing:

23995 lbf (valve disc)

36733 lbf (valve disc)

Since Ator = Athr * SF, the corresponding Maximum SBD outputtorque values are: 23995 * 0.0116 = 278 ft-lbs (Opening), and36733 * 0.0116 = 426 ft-lbs (Closing).

Operator Weak-Link

The maximum allowable output thrust/torque for an SBD-00operator is 14000 lbf thrust or 250 ft-lbs torque (Ref.5.35.3, p. 3). For this valeon th wauilont Torque fox 14000lbf thutF12f-ls( = i4flfl * n n i I6

WIDO DWALKDOWN DATA ?1

A walkdown has been previously performed and is documented inReference 5.16. This calculation is based on implementation ofDCN M-21009-A (Ref. 5.41), which will require another walkdownonce the DCN is completed for this valve.

?e(e 5; k/3 HlAe a /,e IiSf/

/ YV %0 do /z7 Ap 4Vr1yA/ 7 Zt6/1 1Rh (

.,/t. , ,- 1 ((/ 76 - bs

7.6

ell,'

Co9,. iL J vg A>

I ZIl / /qq(

SHEET 33 OF 34REVISION 3

SUBJECT: DOCUMENTATION OF MOV DESIGN BASIS REVIEW ANDTHRUST/TORQUE CALCULATIONS FOR 1-FCV-63-26


PREPARER: M. R. Johnson DATE: 7CHECKER :-R C -- Coll DATE: 7Z./9s

8.0 SUMMARY OF CALCULATION RESULTS

MOV Tag Number 1-FCV-63-26Required Thrust/Torque (Section 7.5.1)

Open: 24393 lbf/283 ft-lbs * Close: 21065 lbf/244 ft-lbs **

Seismic Max Thrust/Torque (Ref.5.44): 20,000 lbs/250 ft-lbs

Motor Actuator Capability (Section 7.5.2)Open Thrust/Torque 14483 lbf/168 ft-lbsClose Thrust/Torque 20086 lbf/233 ft-lbs

Valve/Actuator Allowables/Weak-Link Analysis (Section 7.5.3)Limiting Component Open SBD Actuator

Thrust/Torque 19600 lbf/250 ft-lbsLimiting Component Close SBD Actuator

Thrust/Torque 19600 lbf/250 ft-lbs

Thrust/torque Band Open Min. 24393 lbf/283 ft-lbs *Max. 19600 lbf/168 ft-lbs

Thrust/torque Band Close Min. 21065 lbf/244 ft-lbs **Max. 19600 lbf/233 ft-lbs

IS MOV ACCEPTABLE FOR THE APPLICATION? Y (Y/N)If "no", enter reference to design change document: NR

Comments:The thrust and torque bands for opening are information only, sincethe opening torque switch is bypassed in the MOV's control circuit(Sect. 7.4.15).

See Section 9.0 for design basis evaluation and justification, andsee Att. 2, pg. 3 for reconciliation justification.* Based on initial Accident event; the DP is bounded due to therecovery opening DP condition (after mispositioning closed)

that occurs after the Accident event.** Based on Mispositioning condition


SHEET 34 OF 34REVISION 3

CLIENT: TENNESSEE VALLEY AUTHORITYPROJECT: WATTS BAR NUCLEAR PLANT, UNIT 1SUBJECT: DOCUMENTATION OF MOV DESIGN BASIS REVIEW AND THRUST/TORQUE

CALCULATIONS FOR 1-FCV-63-26

BRANCH/PROJECT IDENTIFIERS: MEB-IWBN-63, WBN-63-D053, EPM-DTN-071392

PREPARER: M. R. Johnson DATE: 7/fY <

CHECKER : R. -. flzCzll -1' DATE: 9S

9.0 CONCLUSIONS

A design basis review has been performed and the requiredthrust/torque has been determined per the methodology specified inMechanical Design Standards DS-M18.2.21 & DS-M18.2.22.

OPENING STROKE:The minimum required opening thrust/torque reflects the accident DPconditions (DP is bounded by recovery opening stroke followingmispositioning closed) during which the MOV must perform its safetyfunction to open. During the calculated open stroke, the limits(motor and actuator) are exceeded primarily due to the calculatedunseating force. However, the DP test was performed at 98% of the DBRaccident conditions and the measured forces were much smaller thancalculated. Based on testing close to DBR accident conditions, thevalve ability to stroke open has been proven. Ample margin existsbetween the opening limits to the opening reconciled thrust for thevalve to perform its safety function. See Attachment 2 for the actualtest values.

CLOSING STROKE:The minimum required closing thrust/torque reflects the mispositioningscenario DP conditions after the MOV has performed its safety functionto open and has been inadvertently mispositioned closed. During thecalculated closing stroke, the motor capability is exceeded. However,a design parallel flow path is available through 1-FCV-63-25 toprovide adequate boration in the event this valve fails inmidposition. Additionally, the DP test was performed at 98% of DBRconditions, which included closing under the misposition evaluatedpressures and resulted in the measured forces being smaller than thecalculated forces. Ample margin exists in the motor capability forthe valve to perform its safety function. See Attachment 2 for theactual test values.

This methodology determined that the motor operated valve 1-FCV-63-26is acceptable from a design standpoint for its application as the BITOutlet Isolation Valve (Train B).



SUBJECT: DESIGN BASIS REVIEW AND THRUST/TORQUE CALCULATIONS FOR1-FCV-63-26



CHECKER: T. Snead DATE: _______

ATTACHMENT 1

SIMPLIFIED SKETCH

.FCTDt

Ftl o/-, , 7

To PC5. NO&t/L

rL T YA,2./4 6

(-

I - Fv- l; -39) I-F(LV 63 - ZS

I-fLV- Co3-4O

£4F0 yS4 7 e(y

SAc ,rf- YI -FLv - lo3 - 2(S

B IT

EPM-DTN-071392 ATTACHMENT 2

MOV RECONCILIATIONWATTS BAR NUCLEAR PLANT UNIT 1non-shaded is caic input - other iS tracking data 20-Jul-95 |Pagc I

_ Va lve UN ID: Cioing control circuit:[1.0 INPUTn Gcncral Information ! | - 1 -FCV-63-0026-AA - ; imit. - i-5 . -Vaive inroneat oI Closing T.S. wir ed in paallel to closing T.S. Bvpass = 90+%

MAmIf.cturer WESTINGHOUSE - - Stein DianiLetr 1.2500 ichorSiae - 4.00 ijtchbe Mean Sect Disineter 3.8700 ichels

ressure Clas. -1500 p.; _ _ S An Ilot(ta 7.0 deDisc Stvy -FWG i_ _ cos( t)e 0.9925

Stoin Orn tationi VERTZ -_ _ theta 0.1219Valse Stein Load 0.3333 lead VAlve St.in Pitch 0.3333 itch ,;Actuator Infomris*tion [Roforonce- (DPTo t Dat.) (Rims N.snber.)

Ms.u .c....et imitonue I -T53 9501 06 933 l::-Tsp -~SM B -- |size:| - 00 - i - - __ ____-_ _- _ _- ___ ___ __- -- __

MOV Desi n Basis Review CalculationCakcslatioiNuibeL ! EPM-DTN-071392'.. : - : REVISION 3

Soat/WdF Friction Factor (VF) 0.4000 St| - Sta s, Nut Frictio F*ctor (SF) | 0.0116Closin Dir- cion,

0 nin DirectionMotorCa *bilit| 20086 lb. Motor shility 14483 lb.Moto Ca abili| 233.00 f-lb. MotorCability 168.00 ft-lb.

Actsitcr Lini| 19600 lb Ac-.tso, ability 19600 lb.ActuetorLimit 250.00 f!-lb. Actuetore abilit 250.00 f-lb.

Vs)l, Weak Liik V.36733 lb. Valve Cability 23995 lbV.le WaakLik 426.00 t R-lb L. VOW Capabiliy 278.00 fl-lb

SeisitcLbsit |20000 lb.* Seismic Linit 20000 lbSeismic LUnit 250.00 fl-lb. Seisin Linit 250.00 f-lb

Differential Pressure P 2746 sid Differential Pressure P 2746 aidR ouirrd)urstlR 21065 l R uiradlrust . 24393 lbRIuiredTor ue 244.00|ft-lb. R uirodTorque :i283.00 f-lb.

Piston Effect 3388 lb. Piston Effect 3388 lb.Packin Load 1250 lb. Psckhai Load ; B lbDP Lod | - 16427 1

lb. Un1-eting Load --: .. -11643 lb.

IPLoad 14888 l b

Static Test InformationStalic Tet. Line Pressure 0 si (ASSUMED Slsom Factor @ CST | 0.0079

Cim Direction 0 nin Direcios

Are Ruistii Load [D] ! 803 lb.! ! AvA Rwiining Load. L 926|IThrus @ CST 0G 13937 lb.l U slieei Load..!1 6444 !lb.Torauo@ CST [G| 10.41 R-lb. UeatinLoad. .4-i4.26 |ft-lb.

Cioain- Direction Closing Direction

TolalPoak. H 15339I! lb TolPoak. H 127.29 ft-lbTouIFaln1 15163||o1Fin|

DP Test Information F- Tova. Full Op.on 430 [gprn

aiimDP t- lconditio| 2700 |id CVCS Purp LinePror. Fsul Oen | 100 siCioasi Direction

0 fin DirectionRedCiog n.Thust IF 17194! lb Memsured DPTbrtu 0 . nm K 8195 lb.

R adClianr Toroue FI 145.54 fl-lb. M--radUnatin Tnrumt. 0Pssi F 9280! lb.Th'n@CSTCkin g[GLI 171591lb. Mea-urd DPTo _e. 0 asim 82.58 ft-b.To ue@CSTCioriss G0i 143.26 fl-lb. MessuredUnlsosiniTo tie. 0 aiim .1 70.26 f-lb.

Co P inL Direcion Closin. DirctionToual Pl IHI !1 7

19411b. !Total Pek H .145.54 l R-ibTota l FinA L 16 7

39ilb. Tota l Fil .L 139.61 f-lb.

~DagnOstic Equipment Error DeterminationrrCIN MOVATSDi.Sn/ ui Error! 3000jOSS I Y 1 If SMART SN civ N/A ! lb.SMARTSTEMI I | IfSMARTSTEM. C. icc N/A ft-lb..If T.S. Repeatabilitpp LoTSS N/A j|I lf SMARTSTEMGpReDWG i N/A i i

PREPARED BY: / 7/ig2/r7

CHECK BY: -,V 1/Z4/95.THIS PAGEADDED BY REVISION 3

fl

EPM-DTN-o7 lag? - ATTACHMENT 2

MUV HLCFNAILIA1 ION

29-Aug-95 Page 2

2.0 Closiny Stroke Reconciliation 1 I-f'CV-63-0026-A

DHR larem DIR CaeIlati n Xacondnled lr-aneten, Recondled Toet DIt.MinimunRcquiredThnrt: 21065 I RecondledThrust: 17472 lb.

Minimum Required ToreuC: 244M fl-lb. Recondled Torque 147,N fi-lb.Piston Effect: 3388 Ib Pis ton lffe 3(from DflRICeculaton): 33bS lb.

PaCking Load: 1250 Ib Averkge PNc&ing Load (Section 5.0. sLp3A): S65 lb.DPLoad: 164'7 lb DP lod: 13220 lb,

Seat Wed gFricion Factor (V : 0.40C0 Scat Contact. Seat Wedge Friction Factor (VF)I: 0.3SW

Ca.ihtoed P-r neter Load Senitivce Beh.vior (ROL): N/AConp-ri of Stom Yctoa

Stem Faacor (SF) DBR Caioulation: 0.0116| Sl @ Staic CST GC 0.0079

SF @ DP CSTIG): 0.00(S3

SF@ uired Closing Th. DP Test IFI: 0.00'5 |

MARGIN l!VAIUAlIONS OF DP llST DATA AND DIIR CAICUI.AllON D3AIA

csTrl hrus Mar n:J - i3i 1 - CSTTorque Mwpin:CSTl ruszNfMaxn: -1 - IS CSTTorque Mrrn:

Methodology M C: 1SJ5 lb. Thrur CapabilirvMargin: 3S0 lbMdehodolcg Marjn: 9.6f Thrr CapablirvMupin: 2.0 %

Torque CpabilirvMarpin: 70 fi-lb.Torqrue CapabilirvMargin: 43.2 *

3.0 O0cninx Siroke Reconciliation * RASEDON POINT: DP IJI

DBYR ?rrnem n DBR Caloulatian Rocandled Paromntcn Rcconlod Tea Det.Minimum Required Thriot: 24393 lb. Recondled Thrust: 9423 lb.

Minimum Required Torque: 283.00 ft-lb. Recondiled Torque: 7135 fh-lb.Piston Effect Load: 3388 lb Piston Effect (from DBR Calculation ) 3 lb.

Padde Lod:! 1250 Ib. Arage P-king Load (Section S.0.sep 3A): 865 Ib.Un U.atin Load: 11643 lb. Unseating( ased on DP ILL : 9280 Ib.

DPLoad: 14SSC lb. DP Load (baNed on DP 1;I-AC Pk Load+PE): 10843 lb.Scat Wed Friction Facor VF : 0.40| Seat Wedge Friction Factor (VF: 03474

Cornparison of Steen F1ctrao

Stem Facor SF: 0.0116 | SF @ Max Rcq d Opcning T: | 0.0076 |

MARGIN EVALUATIONS OF DP TEST DATA AND DBX CALCULATION DATAMerhodol Nyarin: 14027 lb. ThrustIt.ileMar n: 4117 lb.Methodol 353Man: 1253 % ThrustCap biltivMar;n: 39.7 %

I I TorqueCa aliliryMac n:J 9O!fr-lb.

I Tarr ue elilityMer n:| 11.!

4.0 PLAG INDICATION Ol7 UNSATISPACTORY MARGINS (-PROBIEM or OK-)

Closini Stroke CSTThrur Mtrgin d PROBLEM

CSTTorque Ma C: PROBLEMThru Cabiliry M ac : PROBLEM|Torq eCataiuiirv~arn : OK0Peninx Stroke ,

I Methodology Macpn :1 OK

Thrust Capalilyr Macain OK TorqueCapatilirvMacdn: OK

PREPARED BY:Z /?/CHECK BY: - THIS PAGE ADDED BY REVISION 3'OPENING RECONCILED THRUST METHODS:1. For DP test pressure < DBR pressure: Reconciled Thrust = MAX of

{STATIC [J] - Ave Static Run Load ) * (Design DP/Actual DP) + Ave Static Run Load{ DP [J] - Ave Static Run Load ) * (Design DP/Actual DP) + Ave Static Run Load

DP (K} - Ave Static Run Load } (Design DP/Actual DP) + Ave Static Run Load

- indicates METHOD used to determine the opening reconciled thrust.

.- ATTACHMENT 2EPM -DTN -0713C2

t MOV RECONCILIATIONWATTS BAR NUCLEAR PLANT UNIT 1

25-Jul-95 Pa 'c 31V alve UNID:

I1-I-:CV-63-on26-A

5.0 Rcnmarkus:A. Differential lrcssure (Dl ) testing was perforiicd with Charging Pump (CVCS) as pressure source with suppl) froml RWST.

and systcm line up for Boron Injection through I -FCV-63-25 and -26 to an open vessel.B. Differential Pressure (DP) testing was performcd in both directions at 9S% of the DI' reflected in WBN Desigti Basis

Review (DBR) Calculation.C. The seat wedge friction factor (VF) for closing is shown to be conservativc. The VF for opening is low, based on low DP cffect force

experienced during the DlI test. The DP load componcnt is smaller than the value calculated in the DIR calculation, and .is uscd to calculatc the opening VF. These low opening yVs denote conservative values whcn comparcd to the D131 calculationmethodology. The VFs are the result from actual DI' testing

D. The stetm friction factors (SF) for both closing and openitig are conservative.E. The "N/A' for the load sensitive behavior (ROL) ternm indicates that this issue does not apply to this limit closed valve.F. Tlhe opening reconciled thrust was calculated to result in the most conservative value (DlI unseatiitg force [Ji).G. For Mispositionittg (Closing) Scenario Evaluation:

The DP test was performed at 98% of design DP and represents the actual conditions the valve will experience.The closing reconciled thrust is 17472 lbf which is less than the closinig limits. especially the closing motor capability,and actuator rating. Based otn the DP test results (98% of DBR conditions and flow isolation) ample margin exists from the test resultsbetween the closing reconciled thrust to the upper limits (actuator thrust, motor torque). Additional motor capability is available due tothe low SFs based on the test results, and credit can also be taken for being limit controlled closed (position seated).

1-. For Accident (Openittg) Evaluation: (DP based on recovery openitg stroke which bounds the opening accident Dl)The DP test was perfortted at 98% of design DP and represents the actual conditions the valve will, experience.The openinig reconciled thrust is 9423 lbf which is less than the opening limits, especially motor capability,and actuator rating. Based on the 1)1 test results (98% of D13R conditions and flow isolation) ampIc margin existsin the motor capability to open the valve during accident conditionis.

1. Tile PlROB3LEM flag (Methodology Margin) indicates that the Reconcilcd thrust is within the calculated minimum required thrust dueto the Equipmcnit Error (EE) band. EE is not considercd in the calculation methodology' but is incorporated as part of the valve's setup.

J. The PROBLEM flag (CSTTII/TOR Margin) indicates that the reconciled thrust/torque is within the 10% band of the DlI CSTthrust/torque. The margins are ilined out since the valve's closing stroke is limit switch controlled (position seated).

K. The PROBLEM flag (Thrust Cap Margin) indicates that the reconcilcd thrust/torque is within the 10%o band of the nmost limlitingmaximunm limit. Credit is taken for this valve's closing circuit logic of limit closed to ensure valve closure is achieved. Also. additionalcredit can be used for the parallel design flow path that exists to ensure CVCS boration injection through 63-25.Therefore, the problem flag is not a concern.

L. To take into account the 'Aging Issue'. adequate margin exists to allow for degradation of packing coefficients,partial loss of lubrication. .vcar of valve/actuator's internal parts, and incrcase in the valve's surface friction coefficients.

6.0 Conclusions:A. The valve's final sClup is acceptable. DBR Calculation friction factor and methodology are proven to

be conservative with adequate margins.

B. This valve has been operated against 98% of the worst case DP conditions reflected itl the DBR calculation.By successful stroking of the valve during the DP test, and by adequate margins in the reconciled test data,the valve's operability has been demonstrated.

7.0 Rccommcndcd follow up actions:None.

PREPARED BY:

CHECKED BY: <61G'7/D5/- THIS PAGE ADDED BY REVISION 3

ATTACHMENT 2EPM-DTN-071392

EPM-DTN-071392 ATTACHMENT 2

MOV RECONCILIATIONWATTS BAR NUCLEAR PLANT UNIT 1

20-JuJ-95| Pa e 4Valve UNID I8.0 Determination of Paci nK Load I-PCV-63-0026-A

I Packing Load. Static Test Open & Close. lbs (Line Press = 0)803 . ARLSC - Ave RunningLod Static COse lbs. D'

| 926 = ARLSO . Ave Runin Load Sttic pen. lbs. L2A Piston Load Static Test (I'NLST). lbs (Line Pressure. STLP is known and not 0) (Used in Packing Load)

PNLST - I - PisxonLoad Staticet- STtPIPtxSDxSD/4 i28 Packing Load Static Test. lbs (Line Pressure, STLP, known & not = 0)

1 _ _ _8031 9 Pack Load StAricText now - ARUSC-PNLST

I 926 L 8 1 'acLoad SacTeusO c AJUL C - PNLST3A Estimated Pac aing Load Static Test, lbs (Line Pressure. STLP is not known)

| 8651 - (ARLSC + ARLSO) /2 - (-D *L /2 1238 Estimated Piston Effect Load Static Test. lbs (Line Pressure is not known) 9. o B PERCENTAGE DB DP

. PNSLsr - | -621 - (ARLSC-ARLSO) /2 - (-D- - /.- 12 98.3213C Estimated Static Line Pressure from Piston Effect Load. lbs (STLP')

___ Th-| -30 - 4xP [LST I'lxMx E2) 9.0A OPENING RECONCILED EVALUATION_ STATnC IJ o539 lbs .9.0 Miscellaneous Intermediate Calculations DP 9423 lbs .

P fK 8320 lbs .

Point J DP: Point K; DP: Point J STATIC:MaxR 'd nin Thn to overctm cDP. POIN'TS I J k 1: 9280 8195 6444 lbsMax Reqd 0 ntis To uc to overmrne DP, POINTS 1I k }1: 70.26 82.58 44.26 ft-lbsMaxmum Strem Factor (st). POINTs IJI or l}:l: 0.0076 0.0101t 0.0069 - SFMaxR 'd scin Thnbt to overcome DP GREATER OF POINTS J& K 1: 9280 lbsPiston Effect bssed on OP Test Line Pressure (Full Open): 1350F1 Ib

10.0 Equipment Error determination0S5 - ThrusrtSenor/EquipError YES 1 9.8 % Rea ding J TTC Islt,0.9%g'roRoful sale (indudin RcpoTTC - ThirusSensor/EquipError 1 0.0 % Reading SMB SIZE = 0TTC - TorqueSensor/EquipErrolJ 0.01 % Reading I 000 250 lbs.TTC - frrusa:ensor/ Eu Error 0 lbs. ---- >I 00 437 lbs.TTC-Torque enaor/EquipErro_ 0.001 ft-lbs. -- > _ _ _ 0 748 lbs.

SS - Thrust Sensor /Equip Error O 0 % Cap acitv | 1 1 403 lbs ._SS - ThrustSensor/ ul Error 0 lbs. _ 2 1870 lbs.SS - ThrustSessor/Ecuip Error 0.0ft-lbs. ] 31 3740 Ibs.

MOVATSDiaSvs/EquipError 3000 | 2.01 %Reading ! | °°°! 2.06 ft-lbsT.S.RepeatabiliyApliedNO 01 % Reading ! (Table below) 001 4.47 ft-lbs

TTC - Rep sitiotin Effec[ 0.0] % Reading | 0o 12.05ft-lbs

I iil 1 ! 18.92 ft-lbsToWalEEI 30mO.rrC.TSRe r I 0F00 %RTH/TORI 21 25.75 5ftl-lbsoo lbbs./ft-Ibs| 31 6 ft-lbs !

I ISvntin Fupmn En rlEwithoutT. S Rotb ilirr | T.S. Ropcubry -iinrJuatiorn|

MentError -I 10.0 I Percent As Left TSS = IDPTSTTOR =! II-I ! _ | N/A I N/A |

, __,_-___ CASE EVALUATION. As Left I - I %______> 1.00 | CASE 1 >50s# | 5

.00 CASE 2 <50 4t ! 101.00 CASE 3 1 >50 # - 101.00 CASE 4 <50'# | 20_| -

REFER NClS: Th7930114809.MOVATSER5.0 JWBS-VTM-L.2C-00l0.rsio.0350 i1TI7930t4a90 TE-LEDYN-ETR-A716-A- I F I!

PREPARED BY: 77/Z$;

CHECK BY: -7W 7/24I/9THIS PAGE ADDED BY REVISION 3

EPM-ThT'-071R92 1 A= p1R 1 TI3 - PAGE L OF 17

T53[ 950106 933 C-rU F S OTI-S5 .V07

r7.C N.I Cl.7L 1MT7 VOLIUME COTOLSy:

1 (C.CS) EIlCi PiLESSUTE SlY INJCGiOh RevisiOn 1

iMOTOR OPE1JtTED VALVE DMhJŽIC TEST Page 54Lof 119

. | t o -------

1 4 4,ate G /9 zData Package: Page __ of -P-A G E ("068 o F

6.1.1 BIT Outlet Isolation Valves 1-FCV-63-25 and 1-FCV-63-26 (Continued)

[38] PER-FORM MOVATS open stroke testing for 1-FCV-63-26 as

follows:, (Continued)

[d] WEEN 1-FCV-63-26 stops in the open direction, ThEN

SAVE MOVATS data in accordance with MI-0.006, and

RECOLD the following system data:

I


0579j

I - -2

J

EP____ ____ ____ -'kT L OF 17

T.53 950106 933TCf IC AI I D VOLUMS CONTROL SYST`¶M TI-85.0 7

1 (CV'CS) 111GE P}'ESSURE SAYETY INJECTION revision 1

MOTOR OPERATED VALVE DWLMIC TEST Page 56 of 119

Data Package: page .ofPAGE 070 n . I aje 6/7. ) -

6.1.1 BIT Outlet Isolation Valves I-FCV-63-25 and 1-FCV-63-26 (Continued)

[41] PERFORM MOVATS close stroke testing for 1-FCV-63-26 as

follows; (Continued)

[d] WHEN 1-FCV-63-26 stops in the close direction, ITHEN

SAVE MOVATS data in accordance with MI-0.006, and

RECORD the following system data:

PARAMETER

OPERATIONALCCP SUCTIONPRESSURE

CHARG HDR

:LO W CONTT

CiARG iDP?PRESS INiD

CVCS CHG PMP

TO BIT FLOWSIS B INJTK OUTLET

PRESSURE1-FCV-63-25 &1-FCV-63-26DOWNSTPREAMPRESSURESEAL WATERFILTER OUTLETPRESSCCP MINIFLOWREcIRCULATIONVT 3W DP

Miniflow LineContact/SurfaceTemperature

INSTRU1ENT LOCATION DATA

(4.4 [2]) A4U/692

1-PI-62-109 [I1-PI-62-105-a

I-FI-62-9z

1-PI-62-92A .

l-FI-63-170

PT -1

1-L-108A or1-L- 112 B

MainControl Room

1-M-5Main

Control Room

1-M-5Main

Control Room

1-M-6Main

Control Room

1' l-M-61-TV-63-67 7-S

IC/734AZ 295

No. 4 Acc RmPANEL

1-L-46

.-- P--62-65 I A6T/713

DP-1(1-- -62-257')

TI-1

| 4U/692I Pie Chase1-FE-62-257A4U/692

IPipe Chase

. UNITS

0 ° PSIG

_LJ_ GPM

/_s-~O PSEI G

62 IGPM

A7, a2° I PSIG

/ 7t I ~IPSIG

-| 2 0 | In. WG

/

THIS PAGE ADDED BX REVISION 3

0579j

jI CJ-

!;)/A 1In

.

. . I

.°F

EPM-DTN-07 1392T53 950106 933

ATTACHMYENT 3 PAGE 3 OF-17

4 PAGE 118 OF 143

Data Package: Page - ofDate _______

WID No.W nV) - 8 4 - 2 4 3 7 5 - I 9

APPENDIX B

Page 1 of 7

HOV TEST DATA SHEET

VALVE ID \ > *OD3 0 TYPE OF TEST: STATIC 2 DYNAMICX t-S<

TABLE B-1: ADMINISTRATIVE INFOR.M.ATION

PERFORMANCE SECTIONS RELATED TESTS AND DATA

Motor Current Signature Acquisition Pre Maint LLRT Required? YES O NO

Switch Monitor Signature Accuisition S Post Maint LLRT Reouired? YES O NO

Soring Pack Signature Accuisition Post Maint Stroke Required? YES C NO O

Spring Pack Calibration Stroke Time Test Recuired? YES C NO [

Torque-Thrust Setcoint Adjustments > O ?reventive Maint Recu red? YES O No

Torcue-Thrust Cell Signature Accuisit m

. . IRao d Tmoact Overload Test/

Required? Y-S O NO

Quik SiemSenor igna-ure Acquis-itionIS

Smart Stem Signature Acquition 9e Actuator Mounting Torque: . ft-lbs

Other (specify): ||Actuator Mount Torque Source Document:

.I

Vendor Calculation Used'in Section 4.3:

C (\2. p \t -\W % '\3: c, r 3> o \ - O

Entcneer 0 -J

anner Opaxk\o A. ac\ ib!'wcvc- r em ea.

Pla2nner < kU- {-


.CN1

EP1!T53

E-DTN--071392 -- 1TTACH.MENT 3 PAGE OF 17

3 950106 933 pAGE 2 ° i. .3

-. I-0. 006

WEN' XOVATG TESTING OF Revision 7

0, 1, 2 hOTOR OPERjATED VA.LVES Page 34 of 43

Data Package: Page of Date 6 WID No. 0 o 2 4 3 / 5 0 9

APPENDIX' B

Page 4 of 7

VALVE ID

TABLE B-6: XOVATS SIGNATU-E DATA

T fl\ through T 5 T ¶n through T

CLOSING STROKE THRJST (lbs) OPENING STROKE THRUST (Ibs)

Zero (offse.) J. Unseating

S. Static Friction Brk Point K. D? Effect \

C initial Running Load L. Post DP/Avg Running Load

D. Average Running Load .H Final Running Load C\\

E. Final Running Load N 0. Con-r SW Trip (Stazic Only)

; FD? Effect |. T\ota Peak (Static Only)

G. Control SPi.ch Tr| \3 \a |. Total Final (S-atic On y)

Total Peak I

Totl Fi nal

CLOS-NG STROE TORQUE (ft-lbs) OPENING STROKE TORQUE (f-lbs)

A. Ze-o (offset) ] iJ. Unseat-in| \c- D

Static Fr-ct-icn Er- Po- - | PC ;? Effect

C. Initial Running -oad D % | osL t D?/A.vg Running Load I

.D Averace Running L2ad J I. Final Running Load

- Fina' R-nnn n cad | K. Contr Sw T'-r, (Sta.2C Only)

F D? Effect 0. Total Peak (Stat2.c Only) e /

G. Control swi-ch Tri- \\P..\ P. Total Final (S-2-ac Only)

jH -Total Peak

7. Tota Final |\

THIS PAGE ADDED BY REVISION3

-^ Enginee ,- VeT ie

I o.006

-.

,~Zz1A \ ~. \_J -'-4

H

N

i

H

mo~00

C>

iH

oi

E4

C-o)

E-1

NHA

01 r

m O

0 08

A4 U)X Ep

(< i-YCY-63-26-I ,9 C: W%968T75

mz

v qlEL

C: \W%\stA7

P4

> >-

In

HrH

FT-LB

2.430 Sec

9.800 1(.50

ITI M1OV(ATS MNATH PEOGRAMr1

C-, p

&f

( Secolas )3.w000 4.5 se 6.X0008

r,N

H

CQ-

41

C-DC\1lY4

u

7 .5a0

z

C: \W9 t'73pq

Pi* t

H

H-

LE

Z.5ZU Sec

(Secolnds)

ITI MOVAiTS MAtTH PR OGRAMI1

(10'm

ONm ax

0 0

Z; O

a oC1

P tnX lE-

i.50D 3.000 4.500 6.000

AiBE

�K I-FGV-63-26- )>-F C:WYIGST75

9 .00 18 .50

ITI MfOVTIS M1A TH PEOGE1AMC:W%9GTDO

z

-e . ond

V >RELmE

W

P4H

H

E-'

4FT-LB

2.94f See

(Secolas )3.0~i 4.50 GA.09.@Q IW

-<< i-ECU-63-26- ) >-

c :

\ 'L1

_\ru \

.5625AiBE

9.000 10-.503.000

ITI M1OVWTS MATH PEOGRAM (K i-ECU-63-26-

z

U >MPELm

H

7 W.0424LB (iBS

(seconlas)9.00 1W.50

) >-

N a

001r- I

Z o

Z; mE4 u)

H UEX Ed

! .

F C: Q96ST1O

c :

3 .

4.w500 6.N00 8

EPN-DTN-07-392 -- hTTACHMENT 3

53 950106 933 P AGE 1 3 A 4 -

X UOVA~T, -TESTIING OF 7,evi'sion 7

C) 0,1 ,OO-O-;<E ,X'- Leg

3- L-

of Date __ _ __ _ i W .3 0 9

Data Package: Page -

APPENDIX B

page 4 of 7

VALVE ID

TABL- B-6: MOVATS SIGNATUFE DATA

.T ~ through T uT \ through T 4j

CLOS;NC STRO1E THRJST (lbs) OPENIN STR~'E THUST (lbs)

Zero (offset) .J. Unseating

B. Static Friction 3-k Point

K. D? Effect

|C. Initial Running Load IL. Po. D?/Avg Running Load

| 35

'D. Average Running Load | \M. Final Running Load

|N. Contr Sw Trip (Static Orly)|

*c\ -o. To-al eak (Static Only)

) |G oont-ol Sitch Tr2ip |'p i 8. Toa Final (Static Only) /|

|HTotal peak.j\\

Tj: o tal F n al ' \ I,2

|

ILI

-IA. er° ( O -S et-) I u2 j U 5 eatn 2v - F 92t 213 t

KE StatIC - iCC 5)K E-?..0\>

\; ? EffeCt I X C°

jC. : ai -- C 2 | .C E5 jjL Post D?/|; g R- na ng LOa-| \S

Average R ning Load \. Running Load

1 Fn na RunnC Load IIN. COntr Sl Trap (StataC OnlY)I

? e0

p k (. OF0 Cntrl R SL4. Loa \N\.2j

TotalS -r (Static O

1.Total peak II

I Total Final~II

in r Lnleer HIS PAGE ADDED BY RE7,:T.JN- __

.00 6 C ,.

\

II MIOVATS MN THI PROGRAM

U D

. \' . . V

< I-N-63-T6- ) >Ie C:WU68T90

z

U >I PEL

.p4I

H

H

-8 .912S

PT-LB B

2 19W 9ec-i

3.I0. 4.500 69,0a

Ij

_1 A..

I W.

I I( Seconals.)1 .5DO MOD 10.50

wNH

0 'j

r-i

h rT0

P4

PzN

cr-

H

r-i

(4

-I)

Pu4

EN

E-19

r Do o

I HZ 0

F1 E

f N A

(J .- --- I

< i-'C:-\63-26- \>I F C: W%96T90

rn

I) >1REL':

n

C: \w9T188w

fp4

HH

-105 .564LB - OS

2.190 'Sc

I I I I

(Second&s)

IrTI MOVATS MA TH PEOGRAM

3.000 4.500 6A0I0 9.800 10.50II I

) -(< i-ECU-63-26-I ok C:WgGf96TD5

z

.) rwv M BEL

00' CrO

V1

HPi

zN

N

00

U

uE-4E-A

ZonrCa

p14 m

N A

Z; OEq u)z as

P4 EA

i .9499FT-LB AiBE

2.670 SecI I I I I ,_, I . .

ITI MOVN TS MATH PJ OGRAM

U]H

H

mu

\1 4

.___l/.1%

. I . ,

II

9.000 10.50 ( SE: Dlads)

O..

4.500 6.10003

(< I-FGU-63-26-I F C:WgG96TD5

MOO9 [email protected]

In

W

P.4

HH

Em

LB

(Seconas )

Cd

f:4

c4Cl

CN '1D

rA E

0 0z oIHZ O

NH4 n

Pq E-4

I.590

c :

I T I OVA TS MNATH PR OGRAM

4S.500 6.000

-(VKYT83 - THCCO)>-2 + QX:

R0 .DH34 LB (

3,408mSeW,

f A/7 1'-I

77

-'burg-- ,

0

H

H

>4

0H

..- . - -,, -a

H

WIVI

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22,939 3-539

(�K

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fix: .1I T M OVATS MATH PROGEAM1 )>AMr

.44

- ,_ ,

III

G .5412.^339

-0.6000 v

7. 1414 .7,40 5.94d4 .140

ITI MOUVTS MATH PRJOGWRI >)Al

Ill~Il .1

-(Q)%\T84 - TQCCO)>IIX: 2 +1X: I

P.- ,,. I

z0HLOH

N' hw

i- .,. ,.

11 ~l k-

HH

I I I I I

2,750 3.350

11.4H62 FT- A2,751. Sec,

r---

mCY)

0rA0

0'

U)Hq

l To

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Ed

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0.521 0.902 9.204

2 + 'YX:

-7.5803 1--1674 .3 LB

rQ,

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p4 mPa UsPO E-

[ix :

ii .571.1 .i

<<n ITS MOVNTS MAfTH PROGRfAM

10 .43

(< ITI MOVATS MATH PROGRAM T89 - TQCOC)>-liX: 2 + Vx:

-7.50W3

1

1 R

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CIl

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m as

re Jo

0 0I 1Z; OIr-

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9 .53980.750

F+ -139 .1560

9.149

ATTACHMENT 4

CALCULATION EPM-MA-030292

lt6(,5Z6~

DECAcwCLT 2

TITLE: EVALUATION OF GATE VALVES SUBJECT TO THERMAL BINDING AND BONNET PLANT/UNIT WBN / UNIT 1PRESSURIZATION PER SOER 84-7 WBNP 1

PREPARING ORGANIZATION KEY NOUNS (Consult RIMS DESCRIPTORS LIST) RHR, GATE VALVES, MEB, CALC, MAINDNE, EBASCO, MECHANICAL ISTEAM SYS, CVCS. SAFETY INJECTION, CNTMT SPRAY SYS, EFSBRANCH/PROJECT IDENTIFIERS Each lime these calculations are issued, preparers must ensure that the original (RO) RIMS accessionMEB-WBN-00 number is filled in.WBN-00-D053 Rev (for RIMS' use) RIMS accession numberEPM-MA-030292

R 0 APR 01 1992 B18 92 0326 269APPLICABLE DESIGN DOCUMENT(S) .WB-DC-40-64 Rev 1 _4 SEP 1 995 /i B. 2 6 '95 0 9 0 1 3 7 2

R26 60304 300R 5 B ~2 6 96o3oaSAR SECTION(S) UNID SYSTEMS R1 -l

None | 1,3,62,63,72,74,63 R 6 6 9 6 0D

DCN No. (or indicate Not Applicable),DCN IVM-18044.A

PreparedSEE REV 0

CheckedSEE REV 0

ReviewedSEE REV 0

ApprovedSEE REV 0 l

Date

3-26-92

List all pages addedI by this revision.

List all pages deletedby this revision.

List all pages changedby this revision.

Abstract

~DCN S-37876-A

.H -

V5�A-95.

,u� I

. ... Statement of Problem

0o determine active gate valves that are subject to thermalbinding and/or bonnet pressurization per SOER 84-7 andNRC Generic Letter 95-07.

-

ISafety-related?Yes B No 0

7/i sc-

See Rev Loo 55f gE"I 5gEE fjEV| See RevLogPs

(SeeRev ogr SEE FZ_ 0, r,

See Rev Log |Se FEZ I

-Loc�

SE:E hF-V.LDC~

ORIGINAL

-CA,'C167.r0evJ X6V=S=-0.

S LLC JD7 PAd es: Li

HIS CALCULATION CONTAINS AN UNVERIFIED ASSUMPTION(S) THAT MUST BE VERIFIED LATER: YES . NO B

HIS CALCULATION CONTAINS SPECIAL REQUIREMENTS OR LIMITING CONDITIONS: YES B NO [his calculation invokes special operation requirements on PORV block valves 1-FCV-68-332-B and -333-A. These special operating requirementshave been captured in system description N3-68-4001 by DCN S-37876-A.

SCAR WBSCA910231 Ri and PER WBPER940335 RO have identified gate valves that may be susceptible to bonnet pressurization. Thiscalculation implements the corrective action for WBSCA910231 R1 and WBPER940335 RO. In addition, this calc serves to document the evaluationperformed of the 76 WBN active gate valves for thermal binding and bonnet pressurization per INPO SOER 84-7 and NRC Generic Letter 95-7.

his calculation was prepared based on appropriate references and design inputs (See Section 5.0 and 6.0 of this calculation.)

his calculation shows that 2 valves (1-FCV-68-332 & -333) require procedure modifications to prevent thermal bindino. Seventeen valves requirephysical modifications to prevent bonnet pressurization: seven valves in system 063: 1-FCV-63-8, -11, 72. -73, -156, -157. & -172, six valves insystem 074: 1-FCV-74-1, -2, -8, -9, -33. & -35, and four valves in system 072: 1-FCV-72-40, -41, -44, & -45. See Section 8.0 of this calculation fora description of the required modifications.

LEGIBILITY EVALUATED andACCEPTEDto h Jve. /) Q, Ore

SXntu~ / Date0 Microfilm and store calculations in RIMS Service Center. Microfilm and destroy. 01 Microfilm and return calculations to: CALCS LIBRARY Address: IOB A' BLDG

cc: S bC-K

TVA 10697 (DNE-6-86)

I

-

VA. Rec or d

-- ...... ~. . ...- io

.-

PAGE, 1 o-f 6/-

I-- ----- I . I -1 I I

NA I.1Yes S No D

PGN

-�_/_ _- _�c

OCILI-�

3 - 2-- 1 (,

I

61cj��

* CALCULATION SHEETDocument: EN,--,m-A-030292 Rev: 5 Plant: WBNP 1 Page 15C

Subject: EVLAINOF GATEE VALVES SUBJECT TO Prepared By~: -,Date: t/z/?

THEPY.AL BINDING AND BONNET PRESSURIZATION Chckd y"(DaePER SOER 84-7 CekdB:. 4 ae /~(

5.0 REFERENCES: (Cont'd) NO CA~d:I!~II Jte 7-17-4k

5.14.10 EPM-CPH-080592, R2, Documentation of NOV Design Basis Review and

Thrust/Torque Requirements and Valve and Actuator. Capability Assessment for

1-FCV-03-136A.

5.14.11 EPM-CPH-080692, R2, Documentation of NOV Design Basis Review andThrust/Torque Requirements and Valve and Actuator Capability Assessment forI-FCV-03-136B.

5.14.12 EPM-CPH-081092,, R2, Documentation of NOV Design Basis Review andThrust/Torque Requirements and Valve and Actuator Capability Assessment for

1-FCV-03-179A.

5.14.13 EPM-Dt-3-081192, R3, Documentation of NOV Design Basis Review andThrust/Torque Requirements and Valve and Actuator Capability Assessment for

1-FCV-03-179B.

5.15 ASME Boiler and Pressure Vessel Code Secti~on 3, 1971 Edi4tion up) to andincluding Sunm-ner 1973 Addenda, Section !, Table 1-6.0 "Moduli of Eatct ofMaterials for Gi4ven Temperatures."

5.16 Mischke and Shigaley, "Mecharical Engi4neering Design," Fifth Edition,

McGraw-Hill, 1989. (Attachment K)

5.17 WB-DC-40-70, RO, Accident Analysi4s Parameter Checklist (A.APC).

5.18 Watts Bar Technical Specifications.

5.19 SSP-8.06, R4, ASMEE Section XT Pum-p and Valve inse~rvice Testing P-rog-ra-m.

5.20 Westi;nahouse Calculation, VE-EC-1606, RO, Verification of Pressu're Locki--ncAnalysis Program - Preslok. (!MUHP - 6050) (T30 960226 834).

5.21 Westinghouse Letter, Summary of January 4 & 5, 1996 Pressure Locking & ThermalBinding (PLTB) Task Team Meeting (KUHP-6050) (T30 960228 848).

5..Z2 rPr-FLTA-O(,3O¶Z,? 14-) ]oC1UMsYi1tqi16)oz Pestj bt_-s, Ha'viaw, Rc1Vurcd Thru&Tr/Torive.-GaICA0ukI'ons, avid Valve, - ,i Actuito Capqbihlt)~ As s5!m&t'- oVy V41vel I-FCV-&-3~32

C-AC'4Ic,'d;4Y)O, Ond VQlvtl 41) A,~,uqtor y I' 0 7p11,t? As55P55cytr ValvI-rV68335.~Z Vevl4or V~lVc.PriW~nj iIQlOc5,C~ rt TICd2-541111--O)) Vilyt, l-FCV-45-33z&-'13~

W This Page was Added by Revison 5

SHEET 59j OF 61

TENNESSEE VALLEY AUTHORITY PROJECT: WATTS BAR NUCLEAR PLANT UNIT 1

SUBJECT: EVALUATION OF GATE VALVES SUBJECT TO THERMAL BINDING AND BONNET PRESSURIZATION PER SOER 84-07

BRANCH/PROJECT IDENTIFIERS: MEB-WBN-00. WBN-00-D053. EPM-MA-030292

(Rev. 6) PREPARER: DATE: I

(Rev. 6) CHECKER: 1-1 t DATE: 7

7.0 CALCULATIONS (Cont'd)

GATE VALVETHERMAL BINDING AND PRESSURE LOCKING REVIEW

DATA SHEET

VALVE NO:FLOW DIAGRAM:SYSTEM:FLUID:SAFETY CLASS:VENDOR DRAWING:VENDOR:VALVE TYPE:

* ACTUATION:APPLICATION:

FLUID CONDITIONS:

.FLUID CONDITIONS

DESIGN

NORMAL

MAX

1-FCV-68-0332-B & -0333-A1 -47W813-1Reactor Coolant SystemReactor CoolantA115EO10Westinghouse3" Flexible Wedge GateElectric Motor Operated (EMO)Pressurizer PORV Block Valve

PRESS. PSIG

2485

2235

2485

TEMP. OF

680

653

673

COMMENTS:

Valves are normally open. The active safety function of the valves is to close in the event of a "stuckopen" PORV. Consideration of thermal binding and pressure locking for the active closure function is notrequired. However, consideration is required of the condition in which a block valve is closed duringnormal operation due to a "leaking' PORV and then needed to reopen to comply with Tech Spec 3.4.12which requires that either two PORVs or one PORV and the RHR suction relief valve be operable for theCold Overpressure Mitigation System (COMS) during Modes 4, 5, and 6. Consideration of this condition isnecessary in the event that PORV leakage is of sufficient magnitude at normal operating pressure thatblock valve closure is necessary, but PORV leakage during Modes 4 - 6 at reduced RCS pressure wouldnot prevent their use for COMS if the RHR suction relief valve was not available.During a steam generator tube rupture (SGTR) event, operation of the PORV may be required todepressurize the RCS by reopening a PORV block valve if previously closed due to PORV leakage. ASGTR. event can cause a reduced pressure in the RCS, thus a pressure differential could exist between Fthe block valve bonnet which may equal initial RCS pressure and the valve disk, potentially leading tovalve pressure locking.

This page added by Rev. 4

REFERENCE

5.2.9

5.1.7b

5.1.7b

SHEET 59V OF 61

TENNESSEE VALLEY AUTHORITY PROJECT: WATTS BAR NUCLEAR PLANT UNIT 1

SUBJECT: EVALUATION OF GATE VALVES SUBJECT TO THERMAL BINDING AND BONNET PRESSURIZATION PER SOER 84-07

(Rev. 6) PREPARER:

(Rev. 6) CHECKER:

CONCLUSIONS:

VALVE NOS.: 1-FCV-68-332-B & -333-A

Thermal Binding:

DifferentialPressure Locking:

Liquid Entrapment:

When a PORV block valve is closed at normal operating pressurizer temperaturedue to a leaking PORV as described above in the Comments section, later it maybecome thermally bound as RCS temperature is reduced in association with plantshutdown. If the PORV were needed for COMS to allow entrance into Mode 4, theblock may not open under these conditions. Therefore operating proceduremodifications will be required to prevent thermal binding of these valves.

These valves have an active stroke requirement to close for a stuck openPORV. The condition of opening the block valve for entrance into Mode 4 aftervalve closure at full RCS pressure will also be addressed for the differentialpressure locking concern. Note 52 of Attachment J explains the basis for whypressure locking does not occur during this operating condition.Attachment F evaluates the condition of a block valve having to be closed due to aleaking pressurizer PORV and then having to be reopened after a SGTR event.

Consideration of liquid entrapment for these valves is not required because theiractive valve stroke is to close for a stuck open PORV. However the condition ofopening the block valve for entrance into Mode 4 after valve closure at full RCSpressure will also be addressed for the liquid entrapment concern. If a block valvewere required to be closed at normal operating conditions due to a leaking PORVand then required to reopen to allow entrance into Mode 4, the valve specifictemperature conditions would be reversed from that required to induce valve lockingdue to the expansion of entrapped liquid. I.E., valve is closed HOT and thenopened COLD vs. closed COLD and then opened HOT. Therefore, valve lockingdue to liquid entrapment is not a concern for these valves.

RECOMMENDATIONS:

DCN S-37876-A has been issued to require that if the upstream MOV block valve is used to isolate thePORV in the event of leakage, then the block valve shall be stroked open/closed at pressurizertemperatures of 550 'F and 450 'F during reactor shutdown to Mode 4. These actions will assure that theupstream block valve remains operable for COMS, if necessary, and thermal binding does not occur.No action is necessary for these valves with respect to differential pressure locking or liquid entrapment.


DATE: 7/18/96

DATE: 7- /1 - fl

LL CALCULATION SHEETDocument: EPM-MA.-030292 Rev; 5 Plant: WBNP 1 'Page:,,,,

Subject: EVALUATION OF GATE VALVES SUBJECT TO Prepared By: Date:_3./THERMAL BINDING AND BONNET PRESSURIZATION 27PER SOER 84-7 Checked By:_ Date: -/m54

SURIKARY OF CALCULATION RESULTS (Continued)

Data sheets for twelve (12) additional valves plus the revised data sheets forl-FCV-63-72 & -73 show that six (6) are susceptible to bonnet pressurization dueto thermal expansion of trapped liquid. These valves are:

Valve No.

l-FCV-63-72

I-FCV-63-73

l-FCV-72-44

1-FCV-72-45

l-FCV-72-40

l-FCV-72-41

Proposed Modification

Install

Install

Install

Install

Install

Install

external bypass

external bypass

external bypass

external bypass

bonnet relief

bonnet relief

DCN W-36588A will show appropriate modifications

WBPER940335 has identified valves l-FCV-74-33-A and 1-FCV-74-35-B as failing toopen during MOVATS testing. This problem has been corrected as follows:

Valve No. Proposed Modification. Imlementina DON

l-F'CV-74-33-A

1-FCV-74-35-B

Drill hole in

upstream disc

W-32913-A

The pressurizer PORV block valves have been identified as being susceptible tothermal binding. The resolution is as follows:

Valve No.

l-FCV-68-332-B

I-FCV-68-333-A


Operator action to open/close

valves as plant is shutdown'

Imolementing DcN

S-37876-A

Utilizing the Commonwealth Edison methodology for the evaluation of gate valvesfor pressure locking, valve 1-FCV-1-16 was identified as having low margin (1.6%)with respect to the margin recommended by Reference 5.21 (20%). This problem willbe corrected by the end of the first refueling outage as follows:

Valve No.

1-FCV-1-16


Drill hole in upstream disc,

install external bypass, or

other as seen appropriate

Implementinc DCN

W-38663-A

This Page Was Replaced by Revision 5

LL CALCULATION SHEETDocument: EPMt-MJA-030292 SRev:, 5 Plant: WBNP I |Page:/

Subject: EV>ALUAT ON OF GATE VALVES SUBJECT TO Prepared By: Date:31|THERMAL BINDING A.ND BONNET PRESSURIZATION (9

PER OER 4-7Checked By: aoDate:wPE SOER 8A-

9 .0 CONCLUSION Rub ChK e 7.qg.Jl

This calculation only evaluates twenty-seven (27) gate valves as defined inSCAR No. WBSCA910231 RP corrective action Item (1) and one Unit 2 valverequired for the operation of Unit 1 identified in Ref. 5.3.2 forsusceptibility to thermal binding and bonnet pressurization (pressurelocking and liquid entrapment) as defined in Section 7.1 of this calculation.Nine (9) gate valves have been found to be susceptible to bonnetpressurization and proposed modifications are summarized in Section 8.0 ofthis calculation.

Design Change Notice DCN M-18044 & W-31677-A will implement appropriatemodifications to meet Design Criteria WB-DC-40-64 Rl, Appendix B.

WBPER940335 identified valves 1-FCV-74-33-A and 1-FCV-74-35-B as failing toopen during MOVATS testing. These valves will have a hole drilled in theupstream disc to prevent bonnet overpressurization.

Twelve additional-valves have been evaluated for susceptibility to thermalbindina and bonnet pressurization due to proposed NRC Generic Letter 95-07and NRC Information Notices 95-14 and 95-18 on the same subject. Six (6)additional gate valves have been found susceptible to bonnet pressurizationand proposed modification are summarized in Section 8.0 of this calculation.

PORV block valves I-FCV-68-332-3 and 333-A have been identified as beingsusceptible to thermal binding. Operator actions will be implemented as theresolution. See Section 8.0.

In support of TVA's response to NRC GL 95-07, all safety-related valves wereevaluated according to Attachment I "Valve Categorization for PressureLocking and Thermal Binding, and the results are presented in Attachment i'Watts Bar PLTB Evaluation Matrix Based on the WOG Valve CatecorizationCriteria". This evaluation yieldedenive1 G) valves that needed lfurther Rievaluation. This evaluation was performed using the Commonwealth Edisonmethodology for pressure locking analysis and is presented Attachment F"Pressure Locking Analysis Using the Commonwealth Edison Methodology." Theresults, summarized in Attachment G 'Summary of Pressure Locking Analysis5U 4ng the Commonwealth Edison Methodology', show that .- ) of the( ) valves have sufficient margin (greater than 20%) as suggested inReference 5.21. Valve 1-FCV-1-16 has been shown to be capable of performingits safety function with 1.6% available margin. However, to increase thedegradation marcin for 1-FCV-1-16, a modification will be implemented by DCNW-38663-A to eliminate the possibility for trapping pressure in thebonnet.DCN 1WJ-38663-A will rectify this situation before the end of the firstrefueling outage.

This Page was Replaced by Revision 5

CALCULATION SHEET

The following inputs were used to calculate the estimated opening force under pressure locking scenarios forflex-wedge gate valves using a calculational methodology that accounts for wedge stiffness resisting pressurelocking forces. The equations were prepared by the Westinghouse Owner's Group based upon thecalculational methods developed by Commonwealth Edison.

Analysis for 1-FCV-68-332-B:

INPUTS:

Bonnet Pressure

Upstream Pressure

Downstream Pressure

Disk Thickness(taken at centerline of the hub vertically)

Seat Radius(corresponding to mean seat diameter)

Hub Radius (taken at plane of symmetry,perpendicular to the hub, radius of circleof equivalent area for non-circular hubs)

Seat Angle

Poisson's Ratio (disk material at temperature)

Modulus of Elasticity (disk material at temperature)

Static Pullout Force(measured value from diagnostic test)

Close Valve Factor

Stem Diameter

Hub Length(from inside face of disk to inside face of disk)

P bonnet = 2285 psi(1e3 517,)Fl 4.3.4-2)

P up = 1645 -psi (Rek 5.17,Fag 4.3.4-2)

P down = ° -psi ('e - 22)

t =1.01 in (Afqchne-4t L)

a 1.62 -in (Al (hverV L)

b = 1.056 in (A4Ibrqct L)

0 =7 deg (Epchrcnt L)

E 2.951 1-1 7 0psi (hm .9

F p =5638 *1bf (Re 6 22)

VF = 0.4 (Re,; 5. 22)

D stem = 1.25 i-n (Aic hnenT L)

Hub Iength = 0.61 -in

(ell'qcn~rl L)


Document: EPM-MA-C30292

Subject: EVALUATION OF GATE VALVES SUBJECT TO THERMAL

BINDING AND BONNET PRESSURIZATION PER SOER 84-07

A TTACHIVENIT F

CALCULATION SHEET

Analysis for 1-FCV-68-332-B: (Cont)

PRESSURE FORCE CALCULATIONS

Coefficient of friction between disk and seat:cos(O)

I= VF -1 VF sin(0)

Average DP across disks:

P up t' P downDPavg := P bonnet - 2

Disk Stiffness Constants

E (t)-D :=

12(1 - V2)

E2 (1 v)

Geometry Factors:

D =2.36810 6 lbf-in

G = 9.654- 106 psi

C2:= 4 1 1 a z)'

b 11C3 4

.(I - 2 In ~a)) |I

-I1. In; )-( _)b2

(.a)

C 2 = 0.0529

11 C 3 =0.0057

(b\'21 C 8 = 0.7987

b f I . /a I - v 2b-1C g -In~ _ in

11

1 1(a2 n

C 9 = 0.2469

L 3 = 0

L 9 = 0I L (v)IIa


p =0.379

DPaVg = 1462.5 -psi

iCC8 r= i

a IL 9 = -

a l

ATTACHMENT F

I - ',I ( I - %'))

a [ 1, 2 �a a\2., i(a\, _ I 1.1rif -

:= _,� a [ 1��a/ ' I �a ' a/ -\ J \ ) � ( I

CALCULATION SHEET

Analysis for 1-FCV-68-332-B: (Cont)Geometry Factors: (continued)

L I1=5.1809 10 4L 11 .= 6 I -+ 4 (-) - 5 (-) - 4. ()9i- (-In ] l')

L 17 := 4 1- I - -() -(a I0 + (I + ' bL 17 =0.0488

Moment

-DPavg a2 f C 9 a2b4rb := - 8 (2ab(- b2) - L 171

DPQ b 2 2)Qb := (~a _ b)

M rb =-288.8 Ibf

lbfQ b = 1045.1

Deflection due to pressure and bending:

a2 a.Y bq:= M rb D C 2 + Q b-C 3D

DPav a4-L 11

DYbq =8.5139-10 in

Deflection due to pressure and shear stress:

K sa := -.z 2 ).n(-\a)

K sa =-0.0842

K sa'DPavgQa 2

Ysq := t-G- 5-Y'sq =-.) 1 59 1 0 *ln1

Deflection due to hub stretch:

P force : ̀ '(a2 - b 2) DPavg

P force Hub lengthY stretch '= b2 (2-B)

Y stretch = 2.4052 10 5 in

Total Deflection due to pressure forces:

3' q = Y bq Y sq - 3' stretch

Document: EPM-MA.03C292


BINDING AND BONNET PRESSURIZATION PER SOER 84-07


- q5Yq =-.572 -10 in

ATTACHMENT F-

CALCULATION SHE-ET

Analysis for 1-FCV-68-332-B: (Cont)

Deflection due to seat contact force and shear stress (per lbf/in.):

)t = -8.532- 1 0~ . 'SWi11

( I[IDeflection due to seat contact force and bending (per lbf/in.):

bY bw:=- - C - L 9 ]f L 3

Deflection due to hub compression:

2.7r.a Hub lengthlYcmpr 2b2 2*E

Total deflection due to seat contact force (per lbf/in.):

Yw :=' Ybw Y' sw 0 Y cmpr

Seat Contact Force for which deflection is equal topreviously calculated deflection from pressure forces:

Fs=.7~YqFs = 2 7,.- aS,

UNSEATING FORCES

Fpacking is included in measured static pullout Force

F piston := - D stem P bonnet

F vert := 7 a sin(0) (P bonnet - Pup -P down)

F preslock := 2 F s(pucos(O) - sin(e))

F total -F piston F vert F preslock F pO

F = 8036.5 IbfThis page added by Rev. 4

Y bw=-2.94 3-*10 *

(8 in)

Y cmpr= 10' lfn

( in

Y w = -1. 5 01 * 1 0 *

I .\ in

F s = 445S.2 1bf

F piston = 2804.1 -Ibf

F Vert = 2939 *lbf

F preslock =2263.6 Ibf

F = 5638 lbf

Document: EPM-MA-030292

Subject: EVALUATION OF GATE VALVES SUBJECT TO THERMALBINDING AND BONNET PRESSURIZATION PER SOER 84-07

ATTACHMENT r

Y SW := - *t-G

b)

CALCULATION SHEET ATTACHMENT F

The following inputs were used to calculate the estimated opening force under pressure locking scenarios forflex-wedge gate valves using a calculational methodology that accounts for wedge stiffness resisting pressurelocking forces. The equations were prepared by the Westinghouse Owner's Group based upon thecalculational methods developed by Commonwealth Edison.

Analysis for 1-FCV-68-333-A:INPUTS:

Bonnet Pressure

Upstream Pressure

Downstream Pressure

Disk Thickness(taken at centerline of the hub vertically)

Seat Radius(corresponding to mean seat diameter)

Hub Radius (taken at plane of symmetry,perpendicular to the hub, radius of circleof equivalent area for non-circular hubs)

Seat Angle

Poisson's Ratio (disk material at temperature)

Modulus of Elasticity (disk material at temperature)

Static Pullout Force(measured value from diagnostic test)

Close Valve Factor

Stem Diameter

Hub Length(from inside face of disk to inside face of disk)

P bonnet = 2285 psi(k; 5g17)Fl5 4.3.4-2)

Fl 4.34-2)

P down = 0 psi (f<eN 5.23)

t=1.01 in (Archrrent L)

a 1.62 iin (Attichpnr L)

b = 1.056 in (AA rh.t L)

G=7.deg (Aitt&hmcY L)

v =0.3' (Fei 5. 1;)

E=29.51 10 .7psi-(F,~ 15)

F Po = 6268 -bf (the 5.25)

VF =0.4(c .3

D stem = 1.25 in(Athltrient L)

Hub length = 0.61 -in

(AtaRcrnGNt LJ


Document: EPWM-MA*030292


ATTACHMENT FCALCUL ATION SHEEET

CALCULATION SHEET

Analysis for 1-FCV-68-333-A: (Cont)

PRESSURE FORCE CALCULATIONS

Coefficient of friction between disk and seat:cos(G)

I : VF-sin(o)

Average DP across disks:

D up := PP downDPavg 27 P bonnet - - 2

ji = 0.379

DPavg = 1462.5 -psi

Disk Stiffness Constants

D:= (t)'12.(1 - v2 )

E2.(1 , v)

6D =2.368*10 lbf-in

6G ==9.654-I0 *psi

Geometry Factors:

1 4\ i- (a)C -) = 0.0529

b I r Ib \2C o = H)I~ ~

I

8 := --2 .

I

I -, ( - v).

lb) /b) 2\b / \a / C 3 =0.0057I-

ka aC S = 0.7987

b I -v a1- v ./b\ 2 1C 9 = - - 1--I-n

a (a) 2 - an (a) 2 1

L 9 - Ina) - I -a2 IfIa 4[la

C 9 = 0.2469

L 3 =0

L 9 =0


Document: EPM-MA-030292


ATTACHMvENT F

0

Dt- Rev: 6 Plant: WBNP / Unit 1 Page:

P.epared 4 R :6: of 40I -- ...... . ... . .... ,N ,-_f 1 J-7A. }/41


BINDING AND BONNET PRESSURIZATION PER SOER 84-07Prepared By: w IaL : !''Ie '

Checked By: j P , Dale: 7-f-

Analysis for I-FCV-68-333-A: (Cont)

Geometry Factors: (continued)

a + 4aa) i ) (a)(b)2 (a)] L 1 =5.1809-10 4

L 17 :=-41 - 14 a (a)! (a) (+ v).1n (a) ] L 17=0.0488

Moment

-DPavg-a 2 C 9 2rb : C 2 -b) (a - b-)

DPaNtg 2 b2

- L 171 M rb =7288.8 *Ibf

lbfQb = 1045.1. .

Deflection due to pressure and bending:

a2 Q 3

Y bq : M rb'gC 2 ±Q b'CDPavg a4

I D L 11

Deflection due to pressure and shear stress:

K s= :0.3. 2-ln( ) - I (b )2 1 K sa =-0.0842

K sa'DPavg a2Y'sq-:= . t G

Deflection due to hub stretch:

P force = 7 (a2 - b2 ) Dpavg

P force Hub lengthY stretch - b2 (2 E)

) stretch 1

Total Deflection due to pressure forces:

Y q : Y' bq 1 Y7 sq - Y stretch y q = -6.5725 10 * in


L 11 := 64

-6-

ys.159 l n

CALCUL.AT|ION SHE-cT ATTACHMZENT r

CALCULATION SHEET ATTACHMENT F-r

Analysis for 1-FCV-68-333-A: (Cont) .Deflection due to seat contact force and shear stress (per Ibf/in.):

YSW := -Isw =-8.532* 10-8- II) SW lbf)

.in

Deflection due to seat contact force and bending (per lbf/in.):

aY C (.{r a(C 9 9 a).C)' bw r := - D -1 t L -

Deflection due to hub compression:

(2.T7a Hub length'\Yrcmpr : - 2 2. E I

?E /

Total deflection due to seat contact force (per Ibf/in.):

Y '= Ybw Y sw +Y cmpr

Seat Contact Force for which deflection is equal topreviously calculated deflection from pressure forces:

F = 2- ,.aS~ w%

UNSEATING FORCES

Fpacking is included in measured static pullout Force

F piston :'D stem P bonnet

F vert = 7L a sin(0) (2 P bonnet P up P downv)

F preslock := 2 F s5 (u cos(O) - sin(G))

F total =-F piston F vert + F preslock F pO

)' bw = -2. 94 3 1 0 -.

.(3bf)

Ycmpr-3 1 10 ()in

-7 * inY W 1.501-10

F s = 4458.2 -lbf

F piston = 2804.1 *lbf

F vert = 2939 *lbf

F preslock = 2263.6 Ibf

FPO = 6268 lbf

F total = 8666.5 *IbfThis page added by Rev. 4

Document: EPM-MA-030292 Rev: 6


I

ATTACHMENT FCALCULATION SHEET

ATTACHMENT JWATTS BAR PLTB EVALUATION MATRIX

BASED ON THE WOG VALVE CATEGORIZATION CRITERIA

EPM-MA-030292R5 Prep: _48. Date: 31/14R5 Chk: - Date:3

VALVE UNID/SIZEFUNCTION

I-FCV-63-153 / 4'SIP 1B CL Inj Isol.

1-FCV-63-156 /4SIP 1A to HL 1 & 3Inj. Isoi.

1-FCV-63-157 / 4-SIP 1A to HL 2 & 4Inj. Isol.

INITIAL SCREENING TO ELIMINATE ALLNON-APPLiCABLE VALVES

It NO to Both, I If NO to Either, I If Yes, I if YES to ANY. I If YFS.then the valve isnot applicable.(See GeneralNote 3)

Y NNote 28

Y

Y

then thevalve isNA forPL.

then the valve isconsidered NAfor TB.

the vlvis notsuscept-ible toPL.

then Uhe valve isnot applicable.

V-

Y Y IY

Y V

Crit.

SYSTEM LEVEL SCREENING TO ELIMINATE NON-SUSCEPTIBLE VALVES

If NO to ALL,then the valve is susceptible to PL due to Thermalnot susceptible to I Effects.PL due toHydraulic Effects.

If NO to All, then the valveis not susceptible to TBdue to the Wedge Effect.

then the valve isnot susceptihleto TB due to theStem Effect.

_____ T 1 1 t ___________ ___________ ___________ __________

N N N YNote 29

i I I I I I11N

Note 30 N

I I I I I I I I

NNote

- I

N NNole 301 Note 30

N N N YNote 29

NNote 30

1 -FCV-63-172 / 12 Y Y Y Y N N N Y N N N N NRHR to HL 1 & 3 Ini. Note 31 Note 32 Note 32 Note 32 Note 32 Note 32]sol.

1-FCV-68-332 /3 Y Y Y Y N N N N N N N N N N N N N N NPress PORV Block Note 52 Note 52 Note 33 Note 33 Note 33 Note 33 Note 34 Note 34 Note 34 Note 34 Note 34Valve

NNote 30

NNote 30

N NNote 301 Note 30

i-Fr-Uv-u-jJJ / J3Press PORV BlockValve

y Y Y Y N N N N N o NNote 52 Note 52 Note 331Note 331 Note 331Note 33

N N N N NNote 34 Note 34 Note 34 Note 341 Note

____ - ____ - ____ ____ ..- ____ ____ ____ I ____ I ____ I ___ J ____ I ____ I ____ L ____ I ____ I� ____ I ____ I ____ I ____ I ____ I ____

PAGE 8 OF 21

This sheet added by Rev. 5

0

I .. . | I -- - -- - ., .. . | , No iIf NO to ALL. then the valve is not If No to ALL,

30 30

N N N N

EPM-M 1-030292ATTACHMENT J R5 Prep: Nh?, Date: ,. -/

WATTS BAR PLTB EVALUATION MATRIX R5 Ckd: ,J Date: Zf2-i5

BASED ON THE WOG VALVE CATEGORIZATION CRITERIA

transition from cold leg to hot leg recirculation. The only time 1-FCV-63-93 & -94 are positioned closed is fornormal RHR system operation during normal modes 4,5, or 6 or to perform ASME, Section Xl stroke testing.Because closure of either valve isolates the low safety injection flowpath to two of the four cold legs, the SectXI test is only performed during cold shutdowt'n conditions in accordance with Alternative Frequency JustificationAF-26 described in Attachment 1 of SSP-8.06. Since the subject valves are NO and are not closed in modeswhen RHR cold leg injection is required for accident mitigation, no further evaluation or action is required.Note that the Safety Injection System Description N3-63-4001, section 5.1 explains that RHR pump injectionfrom the RWST is not required for mitigation of a Mode 4 LOCA. The RHR pumps are only required to supplythe suction source for the high pressure injection pumps (in the piggyback alignment) following a Mode 4LOCA. This approach eliminates the need to demonstrate that FCV-63-93 & -94 can open following a Mode 4LOCA should normal RHR system operating pressure become trapped in these valve's bonnets.

28. 1-FCV-63-152 & -153 are normally open (NO). Their safety position at initiation of an accident is open toprovide a flowpath from the SIPs to the cold legs, and their only active valve stroke is to close during thetransition from cold leg to hot leg recirculation. The only time 1-FCV-63-152 & -153 are positioned closedduring normal operation is to perform ASME, Section Xl stroke testing. Surveillance Instructions 1-SI-63-902-A, App F and -902-B, App D ensure that Tech Spec LCO 3.5.2 will be followed while 1-FCV-63-152 & -153 areclosed and that the valves will be returned to their as-found position. No further evaluation or action isrequir~ed for 1-FCV-63-152 & -153. This approach satisfies the scope requirements of NRC GL 95-07 aspresented at the October 24,1995 Region II Public Workshop on GL 95-07.

29. A hole has been drilled in the downstream disc of 1-FCV-63-156 and -157 to eliminate the possibility forpressure locking. Ref. N3-63-4001 R5, section 3.2.2.7

30. 1 -FCV-63-156, & -157 are closed cold. The possibility does exist for these valves to be heated by the post-LOCA environment in the pipe chase prior to the transition from cold to hot leg recirculation during which thevalves are required to be opened, but temperature transients from cold to hot have not been identified as acause for gate valve thermal binding.

31. An external bypass has been installed on the bonnets for 1-FCV-63-172 to eliminate the possibility for pressurelocking. Ref. N3-63-4001 R5, section 3.2.4.10.

32. 1-FCV-63-172 is closed cold. The possibility does exist for the valve to be heated by the pos -LOCAenvironment in the pipe chase prior to the transition from cold to hot leg recirculation during which the valve isrequired to be opened, but temperature transients from cold to hot have not been identified as a cause for gatevalve thermal binding.

33. The safety function of l-FCV-68-332 & -333 is to close if one of the pressurizer PORVs leak. . A PORV whichmay have been closed at normal operating pressurizer temperature may require reopening prior to entry intoMode 4 for the Cold Overpressure Mitigation System (COMS). This will subject the valve to a hot-to-cold LTwhich must be addressed relative to thermal binding (See Note 34), but a hot-to-cold LT will not producepressure locking conditions in the valve bonnet.

34. Paragraph 3.2.6.1 of System Description N3-66-4001 contains the requirement that it a upstream block valve isused to isolate the POR\/ in the event of leakage, then the block valve shall be stroked open/closed atpressurizer temperatures of 550 0F and 450 'F during reactor cooldown to Mode 4. These actions will assurethat the upstream block valve remains operable for COMS, if necessary, and thermal binding does not occur.Note that the open/close valve strokes at 550 OF and 450 0F assure that the valves are not susceptible tothermal binding by preventing them from experiencing temperature gradients of ;- 100 "F. WestinghouseOwners Group work in the area of thermal binding has demonstrated that flex wedge gate valves are not

PAGE 17 OF 21

This sheet added by Rev.5

EPM-M -030292ATTACHMENT J R5 Prep: W Date: 3-1-1

WATTS BAR PLTB EVALUATION MATRIX R5 Ckd: 924/ Date3-ZN7BASED ON THE WOG VALVE CATEGORIZATION CRITERIA

susceptible to thermal binding unless they are subjected to a thermal gradient of >-100 OF.

35. 1-FCV-70-87, -90, -133, & -134 are containment isolation valves that have a safety related function to closeonly. These valves have no safety related function to open for design basis accident mitigation purposes.Therefore, no further pressure locking or thermal binding evaluation is required for these valves within thescope of NRC GL 95-07.

36. 1-FCV-70-183, & -215 have a safety related function to close to isolate the non-safety related sample heatexchanger piping from the safety related portions of the component cooling system. These valves have nosafety related function to open for design basis accident mitigation purposes. Therefore, no further pressurelocking or thermal binding evaluation is required for these valves within the scope of NRC GL 95-07.

37. The highest pressure that 1-FCV-72-2 & -39 could ever be exposed to is the dead head pressure from acontainment spray (CS) pump. This could only occur if the CS pump is inadvertently started for surveillancetesting without first opening the isolation valve (72-503 or -504) in the full flow test header to the RWST. If thisscenario were to occur and then a LOCA or MSLB were to subsequently occur, the CS pump would start afterreceipt of the "Hi-Hi" containment pressure signal. After 3-5 seconds the CS pump would come up to deadhead conditions, thereby duplicating the test scenario, and allow the valve to open. However to address thefact that the pump receives the start signal at the same time the valves receive the open signal, a pressurelocking evaluation for 1-FCV-72-2 & -39 using the Commonwealth Edison Model has been performed. Theevaluation addresses CS pump deadhead pressure trapped in the bonnet at the time these valves are requiredto open upon receipt of a Hi-Hi Containment Pressure signal. The evaluation demonstrates that the capabilityof the valve actuator exceeds the thrust required to unseat the valve with an available margin of greater than20 %. Therefore, no modification are required.

38. The environmental temperature in the El 676 pipe chase where 1-FCV-72-2 & -39 are located rises to amaximum of 115OF following a LOCA or HELB inside containment. As noted on environmental drawing47E235-58 R4, the 11i5F temperature occurs as a result of internally generated heat loads from equipmentoperating in the pipe chase rather than heat transmission from containment. A LOCA or inside containmentHELB having a severity which, in the long term, results in a pipe chase temperature increase will initiate start ofthe CS system, in the short term. I.E., a LOCA or HELB inside containment will initiate the "Hi-Hi" containmentpressure signal and open 1-FCV-72-2 & -39 before the pipe chase environmental temperature begins to rise.Note also that the environmental temperature in the pipe chase can rise to 215 0F after a RHR line break andto 180 OF after a CVCS line break. However, a LOCA or inside containment HELB which would require CSsystem operation does not have to be postulated concurrent with the RHR and CVCS HELBs inside theAuxiliary Building.Therefore, no further evaluation or action is required for 1-FCV-72-2 & -39 for pressure locking due to thermaleffects.

39. 1-FCV-72-2 & -39 are closed cold. As explained in note 38, these valves will be opened before theyexperience any form of temperature transient. Therefore, no further evaluation with respect to thermal bindingis required for these valves.

40. 1-FCV-72-21 .& -22 are normally open (NO). Their safety position at initiation of an accident is open to supplysuction to the CS Pumps from the RWST, and their only active valve stroke is to close during the swapoverprocess from the RWST to the containment sump. The only time 1-FCV-72-21 & -22 are positioned closedduring normal operation is to perform ASME, Section Xl stroke testing. Surveillance Instructions 1-SI-72-902-A, App A and -902-B, App A ensure that Tech Spec LCO 3.6.6 will be followed while 1-FCV-72-21 & -22 areclosed and that the valves will be returned to their as-found position. No further evaluation or action isrequired for 1-FCV-72-21 & -22. This approach satisfies the scope requirements of NRC GL 95-07 as

PAGE 18 OF 21

This sheet added by Rev.5

EPM -MA-030292ATTACHMENT J R6 Prep: to Date: 7d

WATTS BAR PLTB EVALUATION MATRIX R6 Ckd: D Date: IL Z!sBASED ON THE WOG VALVE CATEGORIZATION CRITERIA

required for passive failure protection. The maximum temperature at which the valves would be closed is thepost LOCA RHR heat exchanger discharge temperature of 150 'F. 1-FCV-74-33 is opened to align RHRP A-Afor hot leg recirculation. 1-FCV-74-35 is opened to align RHRP B-B for hot leg recirculation. WestinghouseOwners Group work in the area of thermal binding has demonstrated that flex wedge gate valves are notsusceptible to thermal binding unless they are subjected to a thermal gradient of >100 OF. To produce a hot-to-cold thermal gradient of 100 OF, the post accident RHR heat exchanger discharge temperature would have togo down to 50 OF. Since the Component Cooling System does not have the capability to do this, a hot-to-coldthermal gradient of 100 'F is not possible and no further evaluation or action for thermal binding is required for1-FCV-74-33 & -35.Note that the Safety Injection System Description N3-63-4001, section 5.1 explains that RHR pump injectionfrom the RWST is not required for mitigation of a Mode 4 LOCA. The RHR pumps are only required to supplythe suction source for the high pressure injection pumps (in the piggyback alignment) following a Mode 4LOCA. Based on this Mode 4 LOCA mitigation approach, the need to evaluate 1-FCV-74-33 & -35 for thermalbinding during Mode 4 plant operating conditions is not necessary. However, the following evaluation of thevalves for thermal binding during Mode 4 conditions is presented for completeness. 1-FCV-74-33 or -35 mayrequire closure during Mode 4 to isolate an operating train while performing maintenance on the non-operatingtrain. If closure of either of the valves becomes necessary during Mode 4, they are sufficiently isolated bystagnant piping (10 pipe diameters or more) that they would be closed at ambient temperature rather than thetemperature of the operating RHR system and the AT necessary to produce thermal binding can not occur.

50. Not Used.

51. 1-FCV-63-6 & -7 are normally closed and are closed cold. Their safety function is to open during the post-'LOCA swapover sequence between the RWST and the containment sump. Therefore, the potential to developa hot-to-cold temperature gradient on these valves does not exist and no further consideration for thermalbinding is required.

52. As explained in note 34, the potential exists to close 1-FCV-68-332 or -333 at the norma! operating pressurizertemperature of 652.7 'F (Ref. Westinghouse Process Flow Diagram 1188E75, sheet 2, R2, contract54114-1) and then reopen/close them at 550 OF and 450 'F. This could possibly result in saturated steam at652.7 'F and 2235 psig becoming trapped in the bonnet. However, the bonnet would then be cooled by thesurrounding environment which has a normal average operating temperature of 150 'F per drawing 47E235-42R7. As the bonnet is being cooled by the surrounding environment, the pressurizer temperature is beingreduced by a maximum of 100 OF/hour. This provides 1 hour for the bonnet, initially filled with steam, to giveup its heat, condense out the steam and drop pressure below the next required open stroke at the saturationpressure associated with 550 "F. Since neither the valve or bonnet is insulated and no source of bonnetheating exists after the valve is closed, it is clear that the bonnet pressure will drop faster than the thecontrolled pressure/temperature reduction of the pressurizer itself.The condition of a block valve having to be closed due to a leaking pressurizer PORV and then having to bereopened after a steam generator tube rupture event to depressurize the RCS has also been considered. Apressure locking evaluation for 1-FCV-68-332 & -333 using the Commonwealth Edison Model has beenperformed for this scenario. The evaluation demonstrates that the capability of the valve actuator exceeds thethrust required to unseat the valve with an available margin of greater than the 20 '/O. Therefore, nomodifications are required.

53. A pressure locking evaluation for 1-FCV-1-16 using the Commonwealth Edison Model has been performed forthe condition in which a main feedwater line break for steam generator 1 drops the steam line pressure fromsteam generator 4. The evaluation demonstrates that the capability of the valve actuator exceeds the thrustrequired to unseat the valve such that no modification is required. However to achieve the WVOGrecommended 20 % margin, a modification will be implemented during a future outage to eliminate the

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attachment 3 calculation epm-dtn-071392 · 2012. 11. 30. · revision log. sheet 2 of 34 eb-wbn-63,...

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