LR-N03-0450, Inservice Inspection Program Relief Requests SC-RR-03-V01 and V02

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Inservice Inspection Program Relief Requests SC-RR-03-V01 and V02
ML033040100
Person / Time
Site: Salem  PSEG icon.png
Issue date: 10/22/2003
From: Salamon G
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N03-0450, SIP Test Sample upto2-6-04
Download: ML033040100 (67)
v • d • e


Text

{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 §I PSEG Nuclear LLC U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Gentlemen: INSERVICE INSPECTION PROGRAM RELIEF REQUESTS SC-RR-03-VOI and V02 SALEM GENERATING STATION UNITS 1 AND 2 FACILITY OPERATING LICENSES NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311

References:

PSEG Letter LR-N96437, Dated 12/26/1996 "Inservice Testing Program Relief Request V-24 and V-25. NRC Letter Dated February 13,1997 " Evaluation of Inservice Testing Program Relief Requests for Salem Nuclear Generating Station Units 1 and 2 (TAC NOS. M97480 and M97481)" NRC Letter Dated September 10, 1998 Request for additional information regarding Relief Request V-24 and V25 (TAC NOS. M98259 and M98260) PSEG Letter LR-N980515 Dated Nov 2,1998 " Response to Request for Additional Information Regarding Testing of Accumulator Check Valves NRC Letter dated March 12, 1999, "Relief Requests V-24 and V-25 Regarding Testing of Accumulator Check Valves Salem Nuclear Generating Station Units 1 and 2 (TAC NOS. M98259 and M98260) {Granted Relief and Forwarded SE) Pursuant to 1 OCFR50.55a(f)(5)(iii), PSEG Nuclear is submitting, in Attachment 1 to this letter, Inservice Inspection (ISI) relief requests SC-RR-03-VOI and V02 for NRC approval. These requests address Salem Units 1 and 2 and are revisions to previously approved Relief Request V-24 and V-25. The earlier requests were sought based on the impracticality of performing testing in accordance with the code requirements and in consideration of the burden on the Licensee if the Code requirements were imposed on the facility. 7 95-2168 REV. 7/99

Document Control Desk LR-N03-0450 Specifically, relief requests V-24 and V-25 sought approval for the use of an alternate testing methodology to the testing specified in IWV-3522(b) in order to allow the use of a partial accumulator dump test to verify that each check valve is verified to its safety position. In the NRC's March 12, 1999 approval of Relief Requests V-24 and V-25, an acceptance criterion of 27.0 seconds was imposed by the staff on the alternate testing. Relief Request SC-RR-03-VOI and V02 seek to alter this acceptance criterion to 28.1 seconds due to physical plant changes which altered the original testing acceptance criterion basis. Modifications were undertaken to the Unit 2 SJ54 Accumulator Isolation Valves to increase the valve stroke times in order to address a maintenance issue. The design change process failed to identify the function performed by the SJ54 valve's in the in service testing of the of the SJ55 and SJ56 check valves. With the SJ54 valves opening more slowly the system dynamics have changed and accordingly the measured time for the partial accumulator dump test has lengthened. This change does not invalidate the conclusions made in the original relief request. These changes are also planned for Unit 1. to this letter contains the specific relief requests, SC-RR-03-VOI and V02: Attachment 2 to this letter provides General Approach Proposed For Full Open Testing Of Accumulator Check Valves. Attachment 3 to this letter is calculation S-2-SJ-MDC-1394 Rev 2- "Accumulator Pressure Decay during Discharge Test" which is used to determine the acceptance criteria associated with the Alternate Testing. This calculation has been revised to reflect the new opening time of the SJ-54 valves. This relief request is applicable to PSEG Nuclear Salem Generating Station Unit 1 and 2. PSEG Nuclear requests that the NRC approve this request by October 24, 2003 in order to support Salem Unit 2 refueling outage 2R13 in progress. Should you have any questions regarding this request, please contact Mr. Howard Berrick at 856-339-1862. Sincer . Salamon Manager - Nuclear Licensing Attachments C: Mr. H. Miller, Administrator-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road 2

Document Control Desk LR-N03-0450 Mr. R. Fretz, Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 8B2 Washington, DC 20555 USNRC Senior Resident Inspector - Salem (X24) Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625 3

Document Control Desk LR-N03-0450 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS SC-RR-03-VOI and V02 SALEM GENERATING STATION UNITS I AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 1

Salem Units 1 and 2 Inservice Test Program VALVE RELIEF REQUEST - SC-RR-03-VO0 COMPONENTS: 11SJ55,12SJ55.13SJ55.14SJ55 21SJ55,22SJ55,23SJ55,24SJ55 FUNCTION: These check valves are located in the discharge lines from the respective safety injection accumulators. The valves perform an active safety function in the open and closed positions. The valves must be capable of opening during a large break LOCA to provide a flow path for Si accumulator discharge to the RCS cold legs when reactor pressure drops below accumulator pressure. The valve must be capable of closure to prevent divergence of safety injection and recirculation flow subsequent to the accumulators dumping their contents. This valve also functions as an RCS pressure isolation valve. This function prevents exposing the Si accumulators to RCS pressure which would compromise accumulator pressure boundary integrity. CATEGORY: AC CLASS: 1 TEST REQUIREMENTS: Open & Closed Position - Check valves shall be exercised at least once every 3 months in accordance with the requirements of Part 10-4.3.2.1. BASIS FOR RELIEF: During power operation, these valves are maintained in the closed position by RCS pressure on the downstream side of the valve disk. Quarterly exercising these valves to the full or partially open position during power operation is impracticable because the only flow path is into the RCS. The operating accumulator pressure cannot overcome normal operating RCS pressure to establish flow. Full stroke exercising these valves at cold shutdown is impracticable because of' the potential for low temperature overpressurization due to insufficient expansion volume in the RCS to accept required flow. This testing could also result in the intrusion of nitrogen into the core which could interrupt the normal circulation of cooling water flow. Partial stroke exercising these valves going into cold shutdown is burdensome without a commensurate increase in the level of quality and safety. The associated motor-operated isolation valve (one per accumulator) cannot be partially stroked, but must complete a full stroke before changing direction. This could cause a complete discharge of the water volume in the accumulator and possibly inject nitrogen into the reactor coolant system, causing gas binding of the residual heat removal pumps and a subsequent loss of shutdown cooling. These valves are also verified to close by leak testing per plant technical specifications for Pressure Isolation Valves (PIV's). Reverse exercising these check valves at any time other than refueling is burdensome without a commensurate increase in the level of 1

Salem Units 1 and 2 Inservice Test Program VALVE RELIEF REQUEST - SC-RR-03-VO0 quality and safety. The valves are normally in the closed position. Accumulator pressure is continuously monitored to ensure that an adequate nitrogen blanket is maintained and to verify the lack of RCS inleakage. ALTERNATE TESTING: These check valves shall be full stroke exercised to the open position during refuelings utilizing a reduced pressure, partial accident flow test method. This controlled method is performed with the reactor vessel head removed. The test method establishes accumulatr pressure between 67 and 70 psig, accumulator level between 96 and 100% and refueling cavity level between 125.5 and 126.5 feet. After establishment of the fixed parameters, the test then measures the time interval required for the pressure in the associated safety injection accumulator to drop from an initial pressure to 35 psig. Engineering calculation S-2-SJ-MDC-1394 - "Accumulator Pressure Decay during Discharge Test" establishes the test conditions and acceptance criterion and concludes that this methodology is adequate in determining the associated check valve disk moves to the full open position. Information from other nuclear stations was reviewed regarding partial flow, full stroke exercising using a calculational method. The testing performed at Salem provides a valid methodology for verifying the open function even though the test method differs from the various methods reviewed. In attempting to utilize the guidance of NUREG 1482, Section 4.1.2 - "Exercising Check Valves with Flow and Nonintrusive Techniques", nonintrusive equipment was used during informational testing. These valves are Darling Valve & Manufacturing Co. "Clear Waterway" swing checks that are fabricated without a backstop. The valve design permits the disk to move sufficiently out of the flow path without contacting the valve body. Nonintrusive testing using acoustic and magnetic technology provides sufficient data for monitoring degradation on a periodic basis, however, full open acoustic indication is not detected nor is expected to show on the test trace. Nonintrusive testing does not verify full stroke exercising, however occasional use of this equipment during the pressure decay test provides useful condition monitoring information. This method of forward flow check valve testing complies with the guidance provided in Generic Letter 89-04, Attachment 1, Position 1. Regarding reverse flow exercise testing, these valves shall be verified in the closed position during the process of performing seat leakage testing at the frequency specified in Unit I TS 4.4.6.3 and Unit 2 TS 4.4.7.2.2. The open stroke frequency change was previously approved in NRC Safety Evaluation April 15,1994 (TAC Nos. M88144 and M881451) The use of the alternate testing methodology was previously approved in NRC Safety Evaluation March 12,1999 (TAC Nos M98259 and M98260) 2

Salem Units 1 and 2 Inservice Test Program VALVE RELIEF REQUEST - SC-RR-03-V02 COMPONENTS: 11SJ56, 12SJ56,13SJ56, 14SJ56 21SJ56, 22SJ56, 23SJ56, 24SJ56 FUNCTION: These check valves are located in the discharge lines from the respective safety injection accumulators downstream of the branch connection from RHR. The valves perform an active safety function in the open position. The valves must be capable of opening during, a large break LOCA to provide a flow path for Si accumulator discharge to the RCS cold legs when reactor pressure drops below accumulator pressure. The valve must also be capable of opening to provide a path for low head safety injection and cold leg recirculation flow. This valve also functions as an RCS pressure isolation valve. This function prevents exposing the SI accumulators and RHR system piping to RCS pressure. CATEGORY: AC

CLASS, 1

TEST REQUIREMENTS: Open & Closed Position - Check valves shall be exercised at least once every 3 months, in accordance with the requirements of Part 10-4.3.2.1. BASIS FOR RELIEF: During power operation, these valves are maintained in the closed position by RCS pressure on the downstream side of the valve disk. Quarterly exercising these valves to the full or partially open position during power operation is impracticable because the only flow path is into the RCS. The operating accumulator pressure cannot overcome normal operating RCS pressure to establish flow. Full stroke exercising these valves at cold shutdown is impracticable because of the potential for low temperature overpressurization due to insufficient expansion volume in the RCS to accept required flow. This testing could also result in the intrusion of nitrogen into the core which could interrupt the normal circulation of cooling water flow. The associated motor-operated isolation valve (one per accumulator) cannot be partially stroked, but must complete a full stroke before changing direction. This could cause a complete discharge of the water volume in the accumulator and possibly inject nitrogen into the reactor coolant system, causing gas binding of the residual heat removal pumps and a subsequent loss of shutdown cooling. These valves are also verified to close by leak testing per plant technical specifications for Pressure Isolation Valves (PIV's). Reverse exercising these check valves at any time other than refueling is burdensome without a commensurate increase in the level of quality and safety. 1

Salem Units 1 and 2 Inservice Test Program VALVE RELIEF REQUEST - SC-RR-03-V02 ALTERNATE TESTING: These check valves shall be full stroke exercised to the open position during refuelings utilizing a reduced pressure, partial accident flow test method. This controlled method is performed with the reactor vessel head removed. The test method establishes accumulator pressure between 67 and 70 psig, accumulator level between 96 and 100% and refueling cavity level between 125.5 and 126.5 feet. After establishment of the fixed parameters the test then measures the time interval required for the pressure in the associated safety injection accumulator to drop from an initial pressure to 35 psig. Engineering calculation S-2-SJ-MDC-1394 - "Accumulator Pressure Decay during Discharge Test" establishes the test conditions and acceptance criterion and concludes that this methodology is* adequate in determining that the associated check valve disk moves to the full open position. Information from other nuclear stations was reviewed regarding partial flow, full stroke exercising using a calculational method. The testing performed at Salem provides a valid methodology for verifying the open function even though the test method differs from the various methods reviewed. In attempting to utilize the guidance of NUREG 1482, Section 4.1.2 - "Exercising Check Valves with Flow and Nonintrusive Techniques", nonintrusive equipment was used during informational testing. These valves are Darling Valve & Manufacturing Co. "Clear Waterway" swing checks that are fabricated without a backstop. The valve design permits the disk to move sufficiently out of the flow path without contacting the valve body. Nonintrusive testing using acoustic and magnetic technology provides sufficient data for monitoring degradation on a periodic basis however, full open acoustic indication is not detected.or expected to show on the test trace. Nonintrusive testing does not verify full stroke exercising however occasional use of this equipment during the pressure decay test provides useful condition monitoring information. The valves shall be partial stroke exercised at cold shutdown during normal RHR shutdown cooling operations. This method of forward flow check valve testing complies with the guidance provided in Generic Letter 89-04, Attachment 1, Position 1. Regarding reverse flow exercise testing, these valves shall be verified in the closed position during the process of performing seat leakage testing at the frequency specified in Unit 1 TS 4.4.6.3 and Unit 2 TS 4.4.7.2.2 The open stroke frequency change was previously approved in NRC Safety Evaluation April 15,1994 (TAC Nos. M88144 and M88145). The use of the alternate testing methodology was previously approved in NRC Safety Evaluation March 12,1999 (TAC Nos M98259 and M98260) 2 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS SC-RRO3-V01 and V02 SALEM GENERATING STATION UNITS I AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 General Approach Proposed For Full Open Testing Of Accumulator Check Valves 1

General Approach Proposed For Full Open Testing Of Accumulator Check Valves PSEG procedure S2.OP-ST.SJ-0006(Q). Inservice Testing Safety Injection Valves Mode 6 provides instructions necessary to perform Inservice Inspection and Testing IAW Technical Specification 4.0.5 for the following Safety Injection (Accumulator) check valves: o 21SJ55 and 21SJ56 - 21 Accumulator Discharge to Cold Leg o 22SJ55 and 22SJ56 - 22 Accumulator Discharge to Cold Leg o 23SJ55 and 23SJ56 - 23 Accumulator Discharge to Cold Leg o 24SJ55 and 24SJ56 - 24 Ac.umulator Discharge to Cold Leg The testing procedure involves open-stroke testing each tank's discharge check valves with the reactor depressueized and the vessel head removed. The initial tank liquid volume is set to 96 - 100%, and initial tank pressure is set at 67 - 70 psig. Flow is initiated by opening the tank MOV. Per the procedure, the valve is to be stroked fully open, left in the open position until the Accumulator reaches a pressure of 35 psig, and then closed. Tank pressure is set low enough t prevent injection of nitrogen gas into the RCS. Velocities achieved should also be sufficient to fully stroke the valves, according to calculation. The bases for the testing is captured in Calculation No. S-2-SJ-MDC-1 394, Accumulator Pressure Decay During Discharge Test. The purpose of this calculation is to establish a mathematical model of test conditions to develop acceptance criterion for establishing the valves tested go full open. The description, below, will describe the calculation with reactor head removed as is currently performed during testing. The following parameters are fixed by procedure. o The Unit is in Mode 6 (Defueled) with the Upper Internals installed. o Safety Injection Accumulators are at a fixed and defined pressure. o Safety Injection Accumulators are at a fixed and defined level. o Refueling Cavity is at a fixed and defined level. o Acceptance criteria - Maximum blowdown time in seconds. During valve stroking, Accumulator pressure and level measurements, which are acquired from inputs from normal plant instrumentation, are recorded. Based on the measured level and pressure change with time, the relationship between the check valve disc angle, flow rate and pressure difference are calculated using information supplied by Westinghouse Letter PSE 530 for full lift velocity for the valves being tested. Loss factor for the MOV isolation valve as well as friction losses associated with the piping system are calculated. Equations of motion are then solved simultaneously. The calculation solves six unknown variables simultaneously using a FORTRAN computer program. The following are calculated to determine flow and pressure at a point in time under a variety of disc angles: 1

General Approach Proposed For Full Open Testing Of Accumulator Check Valves o Accumulator level elevation o Accumulator gas pressure o MOV loss factor o Check valve Delta P o Derivations o Values at new time step This will be the same for Unit 1. 2 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS SALEM GENERATING STATION UNITS I AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Calculation S-2-SJ-MDC-1394 (Rev 2) 1

NC.DE-AP.ZZ-0002(Q) FORM I CALC NO.: S-2-SJ-MDC-1394 CALCULATION COVER SHEET Page 1 of 4/j C' REVISION: 2 K CALC. TITLE: Accumulator Pressure Decay During Discharge Test

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-l #TOTAL SHTS: 55 CHECK ONE: ED FINAL a INTERIM (Proposed Plant Change) l FINAL (Future Confirmation Req'd) El VOID SALEM OR HOPE CREEK: 0 Q - LIST 0 IMPORTANT TO SAFETY E] NON-SAFETY RELATED HOPE CREEK ONLY: E]Q ElQs ElQsh ElF OlR 0 STATION PROCEDURES IMPACTED, IF SO CONTACT RELIABILITY ENGINEER E CDs/ADs INCORPORATED (IF ANY): DESCRIPTION OF CALCULATION REVISION (IF APPL.): DCP's 80017352, 80017353, 80017354, 80017355 changed the stroke times of valves 21SJ54, 22SJ54, 23SJ54, and 24SJ54. This change will increase the accumulator pressure decay time. The revised acceptable pressure decay time has been recalculated in this revision of the calculation. PURPOSE: Determine the acceptance criterion of the pressure decay time for the accumulator discharge test. criterion will be incorporated in procedure S2.OP-ST.SJ-0006. The acceptance CONCLUSIONS: The pressure decay time acceptance criterion is 28.1 seconds. Printed Name / Signature Date ORIGINATOR/COMPANY NAME: Vijay Chandra/PSEG Nuclear 1101A Oct. 21, 2003 REVIEWER/COMPANY NAME: James Murphy/PSEG Nuu k 1 I2 l Lct3 VERIFIER/COMPANY NAME: James Murphy/PSEG Nar' t 6 1 22 2 12C3 PSEG SUPERVISOR APPROVAL: Paul Lindsay / yJ

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REFERENCE:

ORIGINATOR,DATE REVIEWERIVERIFIER,DATE Revision History Revision No. Date Description 0 Oct. 24, 1994 Calculation was issued to correct the existing acceptance criterion of 37 sec. 1 Feb. 5, 1996 Minor typographical errors were corrected. There was no change in the results. 2 Oct. 21, 2003 DCP's 80017352, 80017353, 80017354, 80017354 changed the stroke times of 21SJ54, 22SJ54, 23SJ54, and 24 SJ54 valves. This change would result in a revised acceptance criterion. A minor error in the accumulator tap elevation was corrected. Page Revision Index Page Revision Page Revision Page Revision Page Revision I 2-I0 0 g 0 2.S 2.9 2-2 1L 0 20 0 2. 2A 2-0 2 2 1 ..L 3 0 2 2- / 0 2-4 q74 0 2-3 0 3 0 0 O 2 24 6 0 J4. 0 25 3 5 2X 0 / 7 O2 C I 26 2-2-17A a 2 -7 ° 3 2-02 2-2 3 Nuclear Common Revision 9 Nuclear Common Revision 9

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REFERENCE:

V. Chandra 2 ORIGINATOR,DATE REV: Oct. 20, 2003 James Murphy REVIEWERNVERIFIER,DATE 1012 22 12o3

1. INTRODUCTION Accumulator dump test is done in Mode 6 in accordance with procedure S2.OP-ST.SJ-0006(Q), Rev. 8. According to this procedure, the reactor head is off during the test condition. In revision 1 of this calculation (S-2-SJ-MDC-1394), an acceptance criterion of the pressure decay time was calculated based on the 12.5 second opening stroke time of SJ54 valves. DCP's 80017352, 80017353, 80017354, 80017355, revised the stroke time of SJ54 valves. However, the acceptance criterion calculated in revision 1 was not revised. As a result, when discharge test was performed on 21 accumulator by opening 21SJ54 valve, the pressure decay time exceeded the acceptance criterion and 21SJ55 and 21SJ56 valves were declared inoperable (Notification 20162455).

In this revision of the calculation, a revised acceptance criterion of the accumulator pressure decay time has been calculated. The SJ54 valve opening stroke times were measured and are given in Attachment land were used. Although the test is done with the reactor head off, the acceptance criterion was also calculated for the situation when the reactor head is on and the venting occurs through the pressurizer. Nuclear Common Revision 9 Nuclear Common Revision 9

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TITLE A(0Lh, L-Lil _l IDNO. SHEET I'ranSeI1;<'! efi~ -:t tREFERENCE OF ORIGINATOR ts j I I L CALCULATION DATE r CONTINUATION SHEET PEER REVIEW and DATE . " Lqr z7, C~H E'C \\/VALV E JI~J THTiI £ E C -[I ON J -T m e R e L A 71 CtJ -SI I I f [I-E T t1l F E AJ I -f E C H &ck \\ZP VL v FD Wc-Ihd(7LtE, FLCJI oJ F~A-T C Di F F rgP EiN L-vPM Ee~m C AL0VLfLtT C-1 V h/ FLU ID FoRcE \\/v =1' F 011 E q ' 3-I C'-J NTP - 5Lf47 WE~ I(fT f pe4 I y PACIE 3-7c C-F~( e-~E CP6?7T THE f 7L A-TI MhSHIP P, T 1JEETU J() I~kK FLOW% \\jE-LCCIT~J I1-~J1 Dr SK-4wI7GLC, 1s c v (K.~ / ~ ,-m RFFL-r~hU JE-7f AD/ FLUI E-,, r-.! ~~C V;UO'iA?jci FATc&,1 l1 =2-DE-AP.ZZ-0002(Q) ATTACHMENT 2 05-0327 2SM 3-92

-s TITLE AC c Ln ID NO. A 2-m NO SHEE 'O' rPSE&P Gh CDihc ir REFERENCE OF ORIGINATOR a} resL t CALCULATION DATE v, if An CONTINUATION SHEET PEER REVIEW Ago DATE (act ttt 7_ U S 1 JG crp F I -u1iv c-- J o -r [l(T i r r? F tC uk C U -' I r C'I~ i, A, T H(E CO~' Pz2 l [?, Cr-FLI UIt F rf k r I T!/ r i-I Ip 5 - (RFL-CF A c P P eAF6 \\ Z9 - A F jtit v E FFL IC F-) /h'fL c-At A.r,,r A ',,,I'm = ~ IV A4 10 A F-(I - -- (#) 2- \\1. (4) F A(7rRK rL £&Crv~ Pr~vAP, PE IL i " l - li_1 call 2, e - ~ c V L E F K~- f l 2PAD ATT CHM NT_ DE-AP.ZZ-0002(0I ATTACHMENT 2 gS-0327 ZSM 3-92 9"32 2SM 3*92

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C -Last change: VC 21 Oct 2003 4:22 pm DIMENSION VVOF(12),CVCV(12) OPEN(1,FILE='Acchon free.out', STATUS='old') DATA VVOF/O.,.05,.1,.2,.3,.4,.5,.6,.7,.8,.9,1./ DATA CVCV/0., 0.0194, 0.055, 0.1, 0.146, 0.204, 0.277,0.3536,0.4613,0.6086,0.767,1./ C PARAMETERS GAM=1.3 s G=32.174 RHO=1.94 AREA=0.394 om0 K ff DT=0.01 ~7 PPRES=14.7*144. C INITIAL CONDITIONS TIME=0.1 sEh( Te NSTEP=-1 VNA=VNAZ PAZ=84.7*144. PA=PAZ Q=.001 VWP=758. WRITE(1,101) 101 FORMAT(T19'TIME', T28'ACCUMULATOR PRESSURE FLC 103 FORMAT(Tl9'(SEC.)',T28' (PSIG) WRITE(1,103) 31 NSTEP=NSTEP+1 TIME=TIME+DT C CALCULATE ACCUMULATOR LEVEL ELEVATION VWA=1350.-VNA ZA=(VWA+7814.85)/95.72 C CALCULATE PRESSURIZER LEVEL ELEVATION ZP=(VWP+4092.3)/38.34 C CALCULATE ACCUMULATOR GAS PRESSURE PA=PAZ*(VNAZ/VNA)**GAM C CALCULATE SJ54 LOSS FACTOR VOT1=19.3 GVKZ=.15 IF(TIME.LT. VOT1) THEN VOF=TIME/VOT1 CALL INTER(VOF,CVND,12,VVOF,CVCV) GVK=GVKZ/(CVND*CVND) ELSE GVK=GVKZ - 2 .2 - S J-mb C-IS9Lk 2-H ETA]) I'S Ot\\J 1C, \\7LvE ( S FR E OL-W I N C7 -T I M I = I ) - " See-. )W RATE')

GPM)

',//) ENDIF C CALCULATE CHECK VALVE DP VEL=Q/AREA AV2=38.3/(VEL*VEL) SINPHI=0.5*(SQRT(AV2**2+4.)-AV2) IF (SINPHI.GE. 0.9532) SINPHI=0.9532 DPCHK=2.*8.98*RHO*VEL*VEL*(1.-SINPHI) C CALCULATE DERIVATIVES DQDT=(PA+RHO*G*ZA-PPRES-RHO*G*ZP-35.75*Q*ABS(Q) -0.5*GVK*1.94*Q*ABS(Q)/AREA**2 DPCHK)/468.9 DVNADT=Q DVWPDT=Q C CALCULATE VALUES AT NEW TIME STEP QQ=Q+DQDT*DT VVNA=VNA+DVNADT*DT VVWP=VWP+DVWPDT*DT IF (TIME .LE. 2.) THEN IF(MOD(NSTEP,10) .EQ. 0)WRITE(1,102) TIME,+(PA/144.-14.7), Q*7.48*60. ELSE IF(MOD((NSTEP+10),100) .EQ. 0)WRITE(1,102) TIME,+(PA/144.-14.7), Q*7.48*60. ENDIF \\,_2 FORMAT(F23.3,8F17.2) C UPDATE THE OLD VARIABLES Q=QQ VNA=VVNA VWP=VVWP IF(TIME.GT. 40.) STOP

TO TO 321 END SUBROUTINE INTER(X,Y,N,XX,YY) DIMENSION XX(N),YY(N) IF(X.LT. XX(1).OR. X.GT. XX(N)) GO TO 3 DO 2 J=2,N IF(X.GE. XX(J-1) AND. X.LE. XX(J)) GO TO 101 GO TO 2 1Y=YY(J-l)+(YY(J)-YY(J-l))*(X-XX(J-l))/ 1 (XX(J)-XX(J-1)) RETURN 2 CONTINUE 3 WRITE(6,1) X,(XX(I),I=1,N) 1 FORMAT(' BEYOND RANGE',G10.4,5X,20G10.4) RETURN END s - 2.- J-mbJ c-i194 4ev. 2 P 2 5

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C 41ast change: VC 21 Oct 2003 4:28 pm DIMENSION VVOF(12),CVCV(12) OPEN(1,FILE='Acchoff free.out', STATUS='OLD') DATA VVOF/0.,.05,.1,.2,.3,.4,.5,.6,.7,.8,.9,1./ DATA CVCV/0., 0.0194, 0.055, 0.1, 0.146, 0.204, 0.277,0.3536,0.4613,0.6086,0.767,1./ C PARAMETERS S - m GAM=1.3 G=32.174 RHO=1.94 AREA=0.394 Coo PVUrd PRoC/ DT=0.01 PCAV=14.7*144. C INITIAL CONDITIONS RC A C TCR H i~$ TIME=0.1 C fP zC. \\ff\\L\\JE VNAZ=419.9 e ~~Er(i VNA=VNAZ C tJ p~ PAZ=84.7*144. PA=PAZ Q=.001 ZCAV=127. WRITE(1, 101) 101 FORMAT(T19'TIME', T28'ACCUMULATOR PRESSURE FLOW RATE') 103 FORMAT(Tl9'(SEC.)',T28' (PSIG) (GPM) ',//) WRITE(1,103) 31 NSTEP=NSTEP+1 TIME=TIME+DT C CALCULATE ACCUMULATOR LEVEL ELEVATION VWA=1350.-VNA ZA=(VWA+7814.85)/95.72 C CALCULATE ACCUMULATOR GAS PRESSURE PA=PAZ*(VNAZ/VNA)**GAM C CALCULATE SJ54 LOSS FACTOR VOT1=19.3 v GVKZ=.15 IF(TIME.LT. VOT1) THEN VOF=TIME/VOT1 CALL INTER(VOF,CVND,12,VVOF,CVCV) GVK=GVKZ/(CVND*CVND) ELSE GVK=GVKZ ENDIF C CALCULATE CHECK VALVE DP VEL=Q/AREA AV2=38.3/(VEL*VEL) SINPHI=0.5*(SQRT(AV2**2+4.)-AV2) IF (SINPHI .GE. 0.9532) SINPHI=0.9532 DPCHK=2.*8.98*RHO*VEL*VEL*(1.-SINPHI) C CALCULATE DERIVATIVES DQDT=(PA+RHO*G*ZA-PCAV-RHO*G*ZCAV-35.75*Q*A8S(Q) -0.5*GVK*1.94*Q*ABS(Q)/AREA**2 - DPCHK)/428.7 DVNADT=Q C CALCULATE VALUES AT NEW TIME STEP QQ=Q+DQDT*DT VVNA=VNA+DVNADT*DT IF (TIME.LE. 2.) THEN IF(MOD(NSTEP,10) .EQ. 0)WRITE(1,102) TIME,+(PA/144.-14.7), Q*7.48*60. ELSE IF(MOD((NSTEP+10),100) .EQ. 0)WRITE(1,102) TIME,+(PA/144.-14.7), 0 Q*7.48*60. ENDIF 102 FORMAT(F23.3,8F17.2) C UPDATE THE OLD VARIABLES Q=QQ VNA=VVNA IF(TIME.GT. 41.) STOP GO TO 31 END SUBROUTINE INTER(X,Y,N,XX,YY) DIMENSION XX(N),YY(N) IF(X.LT. XX(1) .OR. X.GT. XX(N)) GO TO 3 P. 2 g ~C-I 3 ~/j PE 7 oFF T I pi F-x- 1, -  fc-e-,

a)Z\\ '-DO 2 J=2,N IF(X.GE. XX(J-1) AND. X.LE. XX(J)) GO TO 101 GO TO 2 101 Y=YY(J-l)+(YY(J)-YY(J-l))*(X-XX(J-l))/ 1 (XX(J)-XX(J-1)) RETURN 2 CONTINUE 3 WRITE(6,1) X,(XX(I),I=1,N) _'1 FORMAT(' BEYOND RANGE',G10.4,5X,20G10.4) RETURN END ! 2 - s & mJ 'ic-S t

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ff AE? S H OA JM r1 I 0 3 PLE Lf..L1 E'j C V`M P H-I S 0-hJ CPE S UL-T S CF T /friL c 4 '( Ajf ~,4 iT IS CO&MCLUbT)F TKT 71HE PFES`&FE E// _T I rC. 1'AJI7 KE? (7rf C t-&U -GcrHET CK 7HE -TizS 1 ~ bdfr z, THE Hr ( CT , TH DE-AP.ZZ-0002(0) ATTACHMENT 2 5-032Z7 25M 3-92

TA FILE Cl t ACCL/ Lv/rrTJ P P sR c ^ Z3I CHHrJE FLOJ PA17C P. '~ TIME ACCUMULATOR PRESSURE (SEC.) (PSIG) FLOW RATE (GPM)

0. 110 0.210 0.310 0.410 0.510 0.610 0.710 0.810 0.910 1.010 1.110 1.210 1.310 1.410 1.510 1.610 1.710 1.810 1.910 2.010 3.010 4.010 5.010 6.010 7.010 8.010 9.010 10.010 11.010 12.010 13.010 14.010 15.010 16.010 17.010 18.010 19.010 20.010 21.010 22.010 23.010 24.010 25.010 26.010 27.011 28.011 29.011 30.011 31.011 32.011 33.010 34.010 35.010 36.010 37.010 38.010 39.009 40.009 70.00 69.99 69.98 69.97 69.95 69.92 69.89 69.86 69.82 69.78 69.73 69.67 69.61 69.54 69.47 69.39 69.30 69.20 69.10 68.99 67.69 66.09 64.31 62.42 60.48 58.55 56.64 54.79 53.02 51.33 49.73 48.21 46.77 45.41 44.12 42.91 41.77 40.69 39.67 38.71 37.80 36.94 36.13 35.36 34.64 33.96 33.32 32.72 32.15 31.61 31.09 30.61
30. 15 29.72 29.31 28.92 28.55 28.20 0.45 164.18 241.78 318.75 394.99 470.45 545.13 619.07 692.35 772.14 887.79 1010.82 1134.00 1256.11 1376.81 1495.91 1613.26 1728.74 1842.21 1947.45 2638.34 3170.58 3589.22 3874.58 4107.54 4257.08 4361.32 4404.47 4404.78 4377.50 4340.18 4285.90 4222.96 4148.19 4066.23 3981.22 3895.71 3805.64 3711.51 3618.71 3528.14 3428.49 3322.20 3215.85 3111.24 3008.78 2908.51 2810.37 2714.27 2620.13 2527.84 2437.36 2348.62 2261.57 2176.19 2092.45 2010.35 1929.90 S~- 2^ -S Js -Alp-1394 i CHeViCK \\SOLVE I'S FRED f'CT(fG. HC.

ttAf IS ON J 5 It V o- -. 7 Z.- I 9 - ' 6 > TIME = '2 6-5 <- Awo PT '3 -e p.4

TA1S, L L4-29 t)C C gLf7Ct PE TIME (SEC.) ACCUMULATOR PRESSURE (PSIG)

0. 110 0.210 0.310 0.410 0.510 0.610 0.710 0.810 0.910 1.010 1.110 1.210 1.310 1.410 1.510 1.610 1.710 1.810 1.910 2.010 3.010 4.010 5.010 6.010 7.010 8.010 9.010 10.010 11.010 12.010 13.010 14.010 15.010 16.010 17.010 18.010 19.010 20.010 21.010 22.010 23.010 24.010 25.010 26.010 27.011 28.011 29.011
30. 011 31.011 32.011 33.010 34.010 35.010 36.010 37.010 38.010 39.009 40.009 70.00
69. 99 69.98 69.97 69.95 69.92 69.89 69.86 69.82 69.78 69.73 69.67 69.61 69.54 69.47 69.39 69.30 69.20 69.10
68. 99
67. 70 66.16 64.48 62.74 60.97 59.21 57.49 55.83 54.23 52.70 51.25 49.86 48.55 47.30 46.11 44.98 43.91
42. 90
41. 93 41.01 40.14 39.31 38.52 37.76 37.04 36.35 35.69 35.06 34.46 33.88 33.32 32.79 32.28 31.79 31.32 30.86 30.43 30.01 FLOW RA (GPM) 0.45 164.18 241.78 318.75 394.99 470.45 545.13 619.07 692.35 772. 14 887.79 1010.82 1134.00 1256.11 1376.81 1495. 91 1613.26 1728.74 1842.21 1947.45 2582.12 3015.34 3323.85 3532.50 3695.60 3790.50 3849.96 3865.05 3851.21 3819.73 3782.07 3733.64 3680.10 3619.34 3554.57 3488.44 3422.33 3353.34 3282.19 3212.35 3144.20 3077.69 3012.73 2949.23 2887.12 2826.31 2766.73 2708.33 2651.03 2594.79 2539.54 2485.24 2431.85 2379.31 2327.60 2276.66 2226.47 2176. 98

<SUpe f<D 1 SCH6E f~oV I TE CPqEC4< VPVF MhL En7) M V P SIAJI M( = G O fE RACTOI HEf rSOrJ SJ54 aPENI C 7 S,f TI1M E - 2 >~~ I1 * -d--;e. hit~rl f w --

-TrL E 4f3 Cam thWL IFTe AMJI) 0I*~1' C rl-a'/,A7r TIME (SEC.) ACCUMULATOR PRESSURE (PSIG) FLOW RATE (GPM) 0.110 0.210 0.310 0.410 0.510 0.610 0.710 0.810 0.910 1.010 1.110 1.210 1.310 1.410 1.510 1.610 1.710 1.810 1.910 2.010 3.010 4.010 5.010 6.010 7.010 8.010 9.010 10.010 11.010 12.010 13.010 14.010 15.010 16.010 17.010 18.010 19.010 20.010 21.010 22.010 23.010 24.010 25.010 26.010 27.011 28.011 29.011 30.011 31.011 32.011 33.010 34.010 35.010 36.010 37.010 38.010 39.009 40.009

70. 00 69.99
69. 98 69.97 69.95
69. 92 69.89 69.86 69.82 69.78 69.73
69. 67 69.61 69.54 69.47 69.39 69.30 69.21 69.12 69.02 67.87 66.57 65.20 63.81 62.43 61.08 59.76 58.48 57.25 56.06 54.92 53.82 52.76 51.75 50.77 49.83 48.93 48.07 47.23 46.43 45.66 44.91 44.19 43.50 42.83 42.19 41.56 40.96 40.37 39.81 39.26 38.73 38.22 37.72 37.24 36.77 36.32 35.88 0.45 164.18 241.78 318.75 394.99 470.45 545.13 619.07 692.35 772.14 887.79 1008.44 1124.97 1236.94 1344.11 1446.32 1543.50 1635.61 1722.68 1799.65 2226.40 2475.50 2624.60 2709.49 2765.92 2789.03 2796.51 2786.43 2766.27 2740.57 2712.97 2682.00 2649.57 2615.01 2579.47 2543.88 2508.46 2472.12 2435.41 2399.42 2364.17 2329.62 2295.74 2262.51 2229.88 2197.84 2166.36 2135.42 2104. 99 2075.06 2045.60 2016.60 1988.04 1959.90 1932.17 1904.83 1877.87 1851.27 S -S J-rA ) i-I'I9L Add, 1. 2.

C8jflnel ANGL - z 6 Sb& s41tur74& wrH) IS OM 3 5c 4 op cc-. ST C rC E. TIMsEz '^

T/ALE t 1t4 /)CC2 J[L A Tca PqSSSE twc AM-) f( P Aoc S fi - 4 TIME (SEC.) ACCUMULATOR PRESSURE (PSIG) FLOW RATE (GPM) 0.110 0.210 0.310 0.410 0.510 0.610 0.710 0.810 0.910 1.010 1.110 1.210 1.310 1.410 1.510 1.610 1.710 1.810 1.910 2.010 3.010 4.010 5.010 6.010 7.010 8.010 9.010 10.010 11.010 12.010 13.010 14.010 15.010 16.010 17.010 18.010 19.010 20.010 21.010 22.010 23.010 24.010 25.010 26.010 27.011 28.011 29.011 30.011 31.011 32.011 33.010 34.010 35.010

36. 010 37.010 38.010
39. 009 40.009 41.009 70.00 69.99 69.98 69.97 69.94 69.92 69.89 69.86 69.82 69.78 69.73 69.67 69.61 69.54 69.47 69.38 69.29 69.20 69.09 68.98 67.68 66.08 64.29 62.40 60.46 58.51 56.60 54.74 52.96 51.26 49.64 48.11 46.65 45.28 43.97 42.74 41.58 40.48 39.44 38.46 37.52 36.64 35.80 35.00 34.25 33.53 32.85 32.21 31.60 31.02 30.47 29.94 29.44 28.97 28.52 28.08 27.67 27.28 26.90 0.45 164.61 242.41 319.57 395.99 471.63 546.48 620.59 694.04 774.60 892.36 1016.66 1140.75 1263.64 1385.05 1504.82 1622.79 1738.85 1852.87 1958.04 2645.61 3179.17 3599.07 3885.53 4122.29 4275.47 4384.67 4432.70 4438.69 4417.98 4387.92 4340.99 4285.74 4218.67 4144.63 4067.87 3990.75 3908.79 3822.80 3738.42 3656.46 3576.87 3497.20 3407.30 3315.17 3224.22 3135.23 3048.34 2963.48 2880.56 2799.50 2720.20 2642.58 2566.58 2492.12 2419.14 2347.60 2277.46 2208.67 s; < j - rAlp) -

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FLOt k' AF T I ME 1f I <~ 7rff ( I I 78 1 I9-' V- 0.7. 1-9 NC.DE-AP.ZZ-0002(Q) FORM 2 r l - ~~~~CALCULATION CONTINUATION SHEET lSHEET: 34 CALC. NO.: S-2-SJ-MDC-1394

REFERENCE:

V. Chandra 2 ORIGINATOR,DATE REV: Oct. 20, 2003 James Murphy REVIEWERIVERIFIER,DATE 1 22 12 003

5. CONCLUSIONS As calculated in Section 4.0, the pressure decay time from 70 psig to 35 psig is nearly 26.5 seconds when the check valves are free. The pressure decay time when the check valve swings to a maximum open angle of 60 degrees is 30.1 seconds. As recommended in SER 99-028 issued for Relief Request V-24 and V-25 on March 12, 1999, the acceptance criterion should be 1.5 second less than the pressure decay time for 60 degree swing case. This would reduce the acceptance criterion to 28.6 seconds. Also since the test is done with reactor head off, the pressure decay time acceptance criterion will be further reduced by 0.5 seconds because the pressure decay time with the reactor head off is 0.5 second less than the pressure decay time with the head on.

Therefore, the acceptance criterion to declare the valves operable shall be 28.1 seconds. It is clear from the plots of flow rate (Fig. 4.2), the maximum flow rate during the test exceeds the minimum flow rate required (3537 gpm corresponding to 20 ft/sec velocity in 0.394 ft2 flow area) to open the valve to its full open position. rs A 50.59 Safety Evaluation and the. ~4ffmiemr chane fofie attached to this calculation. Nuclear Common Revision 9 Nuclear Common Revision 9

a kO PSEG CALCULATION CONTINUATION SHEET TITLE II Ccrir25'L /)1Tfn~ FfSI P PC. I ORIGINATOR I -tofA DATE f~&I*'>,4 PEER REVIEW a DATE ICV/LUt LI ST C-F RE FER NJCE <-

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ELLVU ("orvc-- DE-AP.ZZ-0002(0) ATTACHMENT 2 950"27 ISM 3-92

,11~ CCV-F\\NEN 7NG G FAX 609, 339-2210 TU)1.21' 3j:~S %~-7H~-S'OTCHANr'ES MdUST BE ATTACL-EIC POR 17ELO tj S - 2 ~.14:30/N. 3561l-265576 _ A I p i 6f i SH.MD-EU.ZZ-oO1 1(Q) ATTACHMENT 15 (Cont'd) Orden r Ps Valve MD EST )DATA REVIEW TEST RESULTS TEST RESULTS TARGET TEST SETPOINTS TES TIYP TOEST TYPEjgASb PARAMETERS TEST No. -TEST NO,. .i8 77ST DA / TS DATE. ctDSE OPEN CCLCLE PE Tar a (_ _.(CST), N/A 7A N/A Minl Rcq Torquep ,I Trus Riding ~j~ Att. 13 _/_____ Maxry Torque Si4 w Satog (TSS) 'L' ,0

-0}

X~ M sxmm Allowabl (C14) Torque (FT-tLS) (l ?/A N/A Assumed Staffizg Box _s5o o AVG: AVG. AVG:;Yq VG:i7s Ld (SBL) - (paking lod) MA! MX AX:3;n :7 Maximum Savoke Tm (SECONDS) 2_ I_7 Ou llp_ ri NtA NIA T A 15 - 50 s_ rlThdicon None SAT/IUNSAT _____S,_ Data Qtuined By: 2'! lAM PAEUI-C Reviewed By:Ji o se/Opr Creo Page 64 of 67 Rev. 6

0R11 C0,V?OVNENTi ---NG' I-,

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jf% P Z..u U, ,::_ - 2 -  r- !.Z-P-) - s I - M. %) C - I ` C-11. /v T I. j:: z dF SH.MD-EU.ZZ-OOLIL(QJ ATTACMDENT 15 (Cont'd) oren f ( o po/I (s~ 4'_valve 1D Z2 S-5JS4 TEST DATA REVIEW TS RESULTS TES RESULTS TARGET CM POUN (S LEt TEST SE-OINTS TEST TYPE / TEST TYPE PARAMETERS (P - kb)NO TEST NO. / lJ_ TEST DATE Z TESDATE CLOSE OPM LO N ._ OPEN -"ti T4/ NIA /A 5 N/A Mi Req Torque @ a (C1) (Fr-LNBS) Nh N/A NIA Maximm Allowable Tnm Readiig Of3[ -6 3 Amt 13 073 Maximum Torque Switch SCing (TSS) o 3 Maximum Allowable (C14) TorMe (FT-LBS) 7C16 N/A N/A Assmed Smfftg Box -GG AVG: AVG:,r° AVG: 17P_ Jd (SBL) - (LIM .; /q?{X (pdn 10o) MAX.!>: M{AX',(.L7O MAX Maimu Smoke Tim ec 5 / (SECONM C~19 7.0,6

19. 3 is -so 50 N/A NIA None I

(%ATrIPNSAT I a a+ Dana OtwaimdlBy: KP,12WFeg' Reviewed By: / ee -)'7 To-c-7 u f-se tp ,,61_4. 6 K SaJRIEWHopc Creek Page 64 of 67 Re. 6

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AT7T J. -) pI O7F f A¶ITALCHENWT 15 (Coft'd) SH.MD-EU.ZzWO 11(Q) Orde r 6 a z Valve ID 2 3 5 S-- TEST DATA RENTEW TEST RESULTS TEST RESULTS (AS FOUND). /M L TARGET / TEST SETPO[S TEST TYPE I MEST TWYPE6; C PARAMETRS at h NO. No. ? #-II EST DATE DATE,9/D CUM CW C rf P~mOf Target 1bru= a (CM N/A A t el/ 7 NWA Min Raq Torque a (CST) (Fr-LES) 4 N/A / N/ N/A Mazimam llowable 0 kO rC Thru 'Ain -- .4 qPA:5 6Y?7 5 A u. 13 Maximilm Torqu Swi-c Maxim= Allwable (C14) 7 5N Torue (FT-S) /(C6) /A NA Asswmu Stffg Bm AVG: /VG:J'/A VG:c Load (11B1) - LBS) MAX: bA:sfbX.i Mai= Sftm=¢ T-_ 'Ril IC),5 1Sa -ip Th N/A /NA NIA ; NOW~ ~ ~~~~~/ SAT/UNSAT Dom Obts~i By: Reviewed By:, e-, SaknVlHap CM ae 4of6 Page 64 uf 67 Rev. 6

  • HAN0ES MUST GE ATTACHED rOR Fi'ELO USE 3A INO, ;5F, ZO1 r

-2: -1 ).,O.] ) s 2 - -C I - rr. r", C-I'l ( 4-t. I P /W'-r T I r, 4 /-F , SH.MD-EU.ZZ-OO11(Q) AIlACBMENT IS (Cont'd) Ores#kaq ValVr ID 2-LIS TEST DATA RWhEW TEST RESULTS TEST RESULTS TARGET As FFOUND)(AS LEs TEST SETI[NTS TEST TYPE TEST TYPE2 PARAMETERS (Pre - Job) TEST No. - T NO. /, z IES-DATE _ / TEST DATE iA.°L CUM~E OPN CLOSE CLOSE OE Target Ting @_(CST) N4 l N/A Min Req Torque @ (CS (Fr-LBS) l l /NIA NIA Maximum Allowable flmist Reaing Yoe/ i ~ ~ ~ J70-6 An. 13 5 '/o Maximum Torque Swimb Scing,(T) o 33 3 Maxlimum Allowable (C1) Torque (FT-LB) (C14) It C. N__ NJA Assumesl Stuffing Boxc VG: AV: AVG:.5 CVGZ Lowd (SBL) - (LBS) (packing load) AX _X'9 Maximum Smt~bz. Time (SECONDS) ___/___ Opc _ysM N/ IA D IIA N7,:A 15 -50 h t 5AdicarIk Now SATIUNSAT Data Obuinedi By: ha eerL Reviewed B yy: Z- -SaJwnHope Crek Page 64 of 67 Rev. 6

r117 NC.CC-AP.ZZ-001 0(Q) FORM-I CERTIFICATION FOR DESIGN VERIFICATION (SAP Standard Text Key "NR/CDV1") Reference No. S-2-SJ-MDC-1394, Revision 2

SUMMARY

STATEMENT The calculation revision affected pages were reviewed line-by-line. All revised input was reviewed and it corresponding output was reviewed and found acceptable. The methodology of devising the acceptance criteria is equivalent to the SER and is con-sidered acceptable. An additional margin of 0.5 seconds was given to the acceptance criteria to account for when the IST is done with the reactor head is off is acceptable and conservative. The individual named below in the right column hereby certifies that the design verification for the subject document has been completed, the questions from the generic checklist have been reviewed and addressed as appropriate, and all comments have been adequately incorporated. SAP Order/Operation final confirmations are the legal equivalent of signatures. I I, Paul Lindsay 41 Design Verifier Assigned By (print name of Manager/Director) J azzs M~u rp hy / KOt r 21, 2003 Name of Design Verifier / Date Design Verifier Assigned By (print name of Manager/Director) Name of Design Verifier'/ Date Design Verifier Assigned By (print name of Manager/Director) Name of Design Verifier / Date Design Verifier Assigned By (print name of Manager/Director)' Name of Design Verifier / Date 'if the Manager/Supervisor acts as the Design Verifier, the name of the next higher level of technical management is required in the left column. Page 1 of 1

NC.CC-AP.ZZ-001 0(Q) FORM-2 COMMENT / RESOLUTION FORM FOR DESIGN DOCUMENT REVIEW/CHECKING OR DESIGN VERIFICATION (SAP Standard Text Key "NRICDV2") REFERENCE DOCUMENT NO. /REV. S-2-SJ-MDC-1394, Revision 2 COMMENTS 1.0 Section 1: See minor editorial comments on marked up sheet. ' 2.0 Calculation needs to Reference the following DCPs for the following valves: 21SJ54 - DCP 80017352 22SJ54 - DCP 80017353 23SJ54 - DCP 80017354 24SJ54 - DCP 80017355 3.0 Section 3.1 & Figure 2: Elevation of taps for Accumulator Level could not be verified through References given. Drawing 218213 states that drawings RH23, sheet 16 and 17, give the elevation of taps to be approximately 91.46 feet and 85.92 feet versus the calculation values of 92.03 and 86.49. This is a difference of 0.57 feet and 0.57 feet respectively. Make necessary adjustments.,. 4.0 Reference 4 (S2.OP-DD.ZZ-OD74) is now voided and should be replaced by S2.OP-TM.ZZ-0002, revision 7. 5.0 Section 3.4: Valve stroke times are for closing stroke times but the calculation is using it for valve opening stroke times. Make a note in the calculation that the two are approximately equal (if they are). If opening stroke times are different then reanalyze the calculation. n 6.0 Add calculation and revision number to figures 4.1 and 4.2. V 7.0 Since the SER actually used 1.5 seconds from the decay time of the 60 degree case to determine the acceptance criteria, the calculation should also use 1.5 seconds from 30.8 seconds plus the additional 0.5 seconds for the reactor head off difference for a new acceptance criteria of 28.8 seconds., RESOLUTION

1. -Do WE
a.

r t-Fo vR DX P'S 1ej ff L L\\ STE fID4 2. LL~E-AT71I.I. W E(AE PV F t). 7V Iy&)r DuiA g \\Jen1 ) A .cci.I/E

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  • Tr7ET TIME.S W EE US>. ATTACf M I'J S I.

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7. Bow ACCEPTANCE OF RESOLUTION ARk es(6bWo (esp&icrS OLQ mccert,,\\e_,

James Murphy October 21, 2003 Vijay Chandra lC T. 2 I 2003 SUBMITTED BY DATE RESOLVED BY DATE Page.1 of 1

I FORM-I REGULATORY CHANGE PROCESS DETERMINATION Document I.D.: S-2-SJ-MDC-1394 _J

Title:

ACCUMULATOR PRESSURE DECAY DURING DISCHARGE TEST NC.NA-AS.ZZ-0059(Q) Revision: 2 Page I of 3 Activitv

Description:

The acceptance criteria for Accumulator pressure decay time has been increased due to an increased stroke time of the SJ54 valves (seeScreening for a more detailed description). Note that more than one process may appl). If unsure ofany answver, contact the cognizant departmentfor guidance. Activities Affected No Yes Action

1. Does the proposed activity involve a change to the Technical F

O If Yes, contact Licensing; process in Specifications or the Operating License? accordance with NC.NA-AP.ZZ-0035(Q) LCR No.

2.

Does the proposed activity involve a change to the Quality 1 J If Yes, contact Quality Assessment; process Assurance Plan? Examples: in accordance with ND.QN-AP.ZZ-0003(Q) Changes to Chapter 17.2 of UFSAR

3.

Does the proposed activity involve a change to the Security Plan? D E If Yes, contact Security Department; process Examples: in accordance with NC.NA-AP.ZZ-0033(Q) Change program in NC.NA-AP.ZZ-0033(Q) Change indoor/outdoor security lighting Placement of component or structure (permanent or temporary) within 20 feet of perimeter fence Obstruct field of view from any manned post Interfere with security monitoring device capability Change access to any protected or vital area

4. Does the proposed activity involve a change to the Emergency a

If Yes, contact Emergency Preparedness Plan? Examples: Change ODCM/accident source term Change liquid or gaseous effluent release path Affect radiation monitoring instrumentation or EOP/AOP setpoints used in classifying accident severity Affect emergency response facilities or personnel, including control rm Affect communications, computers, information systems or Met tower

5. Does the proposed activity involve a change to the ISI Program I

a if Yes, contact Reliability Programs ISIPIST; Plan? Examples: process in accordance with Affect Nuclear Class 1, 2, or 3 Piping, Vessels, or Supports NC.NA-AP.ZZ-0027(Q) (Guidance in NC.DE-AP.ZZ-0007(Q) Form-I l)

6. Does the proposed activity involve a change to the IST Program a

If Yes, contact Reliability Programs ISI!IST; Plan? Examples: process in accordance with Affect the design or operating parameters of a Nuclear Class 1. NC.NA-AP.ZZ-0070(Q) 2, or 3 Pump or Valve (Guidance in NC.DE-AP.ZZ-0007(Q) Form-I5) Nuclear Common Rev. 5

NC.NA-AS.ZZ-0059(Q) FORM-I REGULATORY CHANGE PROCESS DETERMINATION Document L.D.: S-2-SJ-MDC-1394 Q>J

Title:

ACCUMULATOR PRESSURE DECAY DURING DISCHARGE TEST Revision: 2 Pacte 2of 3 Activities Affected No Yes Action

7.

Does the proposed activity involve a change to the Fire Protection Z If Yes, contact Design Engineering; process Program? Examples: in accordance with NC.DE-PS.ZZ-000 I(Q) Change program in NC.DE-PS.ZZ-000I (Q) Change combustible loading of safety related space Change or affect fire detection system Change or affect fire suppression system/component Change fire doors, dampers, penetration seal or barriers See NC.DE-AP.ZZ-0007, Forms 3,4 and 14 for details

8. Does the proposed activity involve Maintenance which restores If Yes, process in accordance with SSCs to their original design and configuration? Examples:

NC.WM-AP.ZZ-000 1(Q) CM or PM activity Implements an approved Design Change? Troubleshooting (which does not require 50.59 screen per SH.MD-AP.ZZ-0002)

9.

Is the proposed activity a temporary change (T-Mod) which meets F] If Yes, contact Engineering; process in tall thefollowing conditions? accordance with NC.DE-AP.ZZ-0030(Q) Directly supports maintenance and is NOT a compensatory measure to ensure SSC operability. Will be in effect at power operation less than 90 days. Plant will be restored to design configuration upon completion. SSCs will NOT be operated in a manner that could impact the function or operability of a safety related or Important-to-Safety system. l

10. Does the proposed activity consist of changes to maintenance 1

2 If Yes, process in accordance with procedures which do NOT affect SSC design, performance, NC.NA-AP.ZZ-000I(Q) operation or control? Note: Procedure information affecting SSC design, performance, operation or control, including Tech Spec required surveillance and inspection, require 50.59 screening. Examples include acceptance criteria for valve stroke times or other SSC function, torque values, and types of materials (e.g., gaskets, elastomers, lubricants, etc.) IL Does the proposed activity involve a minor UFSAR change Z O If Yes, process in accordance with (including documents incorporated by reference)? Examples: NC.NA-AP.ZZ-0035(Q) Reformatting, simplification or clarifications that do not change the meaning or substance of information Removes obsolete or redundant information or excessive detail Corrects inconsistencies within the UFSAR Minor correction of drawings (such as mislabeled ID)

12. Does the proposed activity involve a change to an Administrative Z

EJ If Yes, process in accordance with Procedure (NAP, SAP or-DAP) governing the conduct of station NC.NA-AP.ZZ-000I (Q) and operations? Examples: NC.DM-AP.ZZ-000 1(Q) Organization changes/position titles Work control/ modification processes Nuclear Common Rev. 5

NC.NA-AS.ZZ-0059(Q) FORM-1 REGULATORY CHANGE PROCESS DETERMINATION Document I.D.: S-2-SJ-MDC-1394

Title:

ACCUMULATOR PRESSURE DECAY DURING DISCHARGE TEST Revision: 2 Page 3 of 3 Activities Affected No Yes Action

13. Does the proposed activity involve a change to a regulatory O

3 If Yes, contact Licensing and process in commitment? accordance with NC.NA-AP.ZZ-0030(Q)

14. Does the activity impact other programs controlled by regulations, If Yes, process in accordance with operating license or Tech Spec? Examples:

applicable procedures such as: Chemical Controls Program NC.NA-AP.ZZ-0038(Q) NJ "Right-to-know" regulations NC.LR-AP.ZZ-0037(Q) OSHA regulations NJPDES Permit conditions State andlor local building, electrical, plumbing, storm water management or "other" codes and standards IOCFR20 occupational exposure

15. Has the activity already received a 10CFR50.59 Screen or Z

0 Take credit for 10CFR50.59 Screen or Evaluation under another process? Examples: Evaluation already performed. Calculation Design Change Package or OWD change ID: l Procedure for a Test or Experiment DR/Nonconformance Incorporation of previously approved UFSAR change If any other program or regulation may be affected by the proposed activity, contact the department indicated for further review in accordance with the governing procedure. If responsible department determines program is not affected, attach written explanation. If ALL of the answers on the previous pages are "No," then check A below: A. 2 None of the activity is controlled by any of the processes above, therefore a 1 OCFR50.59 review IS required. Complete a 1 OCFR50.59 screen. If one or more of the answers on the previous pages are "Yes," then check either B or C below as appropriate and explain the regulatory processes which govern the change: B. F] All aspects of the activity are controlled by one or more of the processes above, therefore a 1 OCFR50.59 review IS NOT required. C. Z Only part of the activity is controlled by the processes above, therefore a 1 OCFR50.59 review IS required. Complete a 50.59 screen. Explanation: I Preparer: Reviewer: James MurDhv October 22. 2003 Date Printed Name Viiav Chandra October 22. 2003 Date Printed Name V 'Signature Nuclear Common Rev. 5

NC.NA-AS.ZZ-0059(Q) FORNI-2 IOCFR50.59 SCREENING Page I of6 Revision 0 Document I.D.: S-2-SI-MDC-1394 Revision: 2

Title:

ACCUMULATOR PRESSURE DECAY DURING DISCHARGE TEST Applicability: Salem I Salem 3 (Gas Turbine) PSEG Common X Salem 2 Hope Creek Salem I & 2 Common Hope Creek & Salem Common

1. Brief Description of activity Change to: C Facility [ Procedures E Methodology aTestIExperiment r1 Fission Barrier What is being changed and why Surveillance test procedure S2.OP-ST.SJ-0006, Revision 8, tests that the forward flow of check valves SJ55 and SJ56 for Accumulators Numbers 21,22, 23, and 24 are unobstructed and the valve disc is non-degraded or free moving. The procedure and Relief Requests V-24 and V-25 satisfy Technical Specification section 4.0.5 requiring that in-service testing of ASME Code Class 1, 2 and 3 components be performed in accordance with ASME Section XI. The Accumulator check valves are said to be full open in the existing ST procedure when the Accumulator pressure reaches 35 psig in a time period no longer than 27 seconds. The justification for the time limit acceptance criteria is found in design calculation S-2-SJ-MDC-1394, Revision 1. The NRC accepted the results of the calculation (with some modifications) as a sufficient means of testing the Accumulator check valves (Reference SER 99-028).

Since the issuance of SER 99-028, the time to stroke isolation valve SJ54 for Accumulator Numbers 21, 22, 23. and 24 has increased (DCPs 80017352, 80017353, 80017354 and 80017355). The DCPs increased the stroke times and neglected to incorporate the appropriate configuration changes in design documentation. As a result of the increased stroke time of SJ54, the pressure decay time in 2R13 exceeded 27.0 seconds for 21 Accumulator (Reference Notification 20162455). Increasing the stroke time of SJ54 will increase the acceptance criteria for forward flow of the Accumulator check valves. As a result of the increased stroke times. design calculation S-2-SJ-MDC-1394 was revised to determine the appropriate acceptance criteria of 28.1 seconds. Design Functions The design function of check valves SJ55 and SJ56 is to freely open during a large break loss of coolant accident (LOCA) and provide a flow path for the Safety Injection (SI) Accumulator discharge to the cold legs of the Reactor Coolant System (RCS). The check valves must be capable of freely closing to prevent divergence of SI and Recirculation flow after Accumulator discharge. The check valves must also prevent leakage from the RCS back into the Accumulator when they are normally closed. Effect on Design Functions The revision of S-2-SJ-MDC-1394 to increase the forward flow acceptance criteria from 27 seconds to 28.1 seconds does not affect the check valves capabilities of opening, closing or the prevention of back leakage. It does not affect the reliability of the check valves to perform it design function of opening, closing or to prevent back leakage. It does not affect the time it would take for the check valves to open or close during a postulated accident. It does not affect the check valves ability to prevent back flow from the RCS to the Accumulator during normal operating conditions. Nuclear Common Rev. 5

FORM-2 IOCFR50.59 SCREENING Page 2 of 6 Revision 0 Document LD.: S-2-SJ-MDC-1394

Title:

ACCUMULATOR PRESSURE DECAY DURING DISCHARGE TEST NC.NA-AS.ZZ-0059(Q) Revision: 2 The revised acceptance criteria does not alter the performance of the check valves during a design basis event. This is used to validate that the check valves achieve the full open position and as precursor to indicate valve obstruction or degradation.

2.

Summarize regulatory change determination (Other applicable regulatory processes identified on Form-I) The proposed activity requires a change to SER 99-028, a regulatory commitment.

3. Does the proposed activity require a change to Technical Specifications or the Operating License?

Yes 2 If YES, then a License Amendment is required prior to implementation of the activity. LCR Number: N/A

4.

Does the proposal require a UFSAR change? Yes E UFSAR Change Notice No N/A (See below) Describe UFSAR change: No ED No A Nuclear Common Rev. 5

NC.NA-AS.ZZ-0059(Q) FORNI-2 IOCFR50.59 SCREENING Page 3 of 6 Revision 0 Document l.D.: S-2-SJ-MDC-1394 Revision: 2

Title:

ACCUMULATOR PRESSURE DECAY DURING DISCHARGE TEST

5. 50.59 Screening Questions Answer ALL screening questions Yes No
a.

Does the proposed activity involve a change to the facility that adversely affects a UFSAR described design function? E 0

b.

Does the proposed activity involve a change to procedures that adversely affects how UFSAR described SSC design functions are performed or controlled? O 0

c.

Does the proposed activity revise or replace evaluation methodology described in the UFSAR that either: is used in the safety analyses or 0 establishes the design bases?

d.

Does the proposed activity involve a test or experiment NOT described in the UFSAR? (SSC is utilized or controlled in a manner that is outside the reference bounds of its design or inconsistent with analyses or E 0 descriptions in the UFSAR)

e.

Does the proposed activity affect a design basis limit for a fission product barrier (fuel cladding, reactor coolant system boundary or containment? El 0

6.

If a 50.59 Evaluation is not required, provide justification for that determination: Calculation S-2-SJ-MDC-1394, Revision 2, determined that the Accumulator would reach a pressure of 35 psig from 70 psig in 26.5 seconds with a free check valve disc. The time span is based on an increased stroke time of SJ54, with the reactor head on and non-degraded check valve discs that are free floating and able to fully open to approximately a travel angle of 72.4 degrees. Partially degraded valves whose discs only traveled 60 degrees from the fully closed position were able to decay the Accumulator from 70 psig to 35 psig in 30.1 seconds. Recent measured decay times from 2R13 indicate that the Accumulator pressure decay times are in the range of 24.0 to 27.9 seconds (21 Accumulator is 27.9 seconds; 22 Accumulator is 24.4 seconds; 23 Accumulator is 24.0 seconds; 24 Accumulator is 27.0 seconds: Reference Operation Logs on October 15,2003 for Procedure S2.OP-ST.SJ-0006). The revised acceptance criteria used in the ST procedure is chosen based on a decay time that is less than the decay time determined for the case with the valve 60 degrees open and greater than the decay time determined for the free disc case. In addition, the calculation states the decay time is 0.5 second less when the reactor head is off. In order to be consistent with SER 99-028, the acceptance criteria is determined to be 1.5 seconds less than the decay time for the 60 degree case and an additional 0.5 second less for when the IST is performed with the reactor head off or 28.1 seconds. The acceptance criteria of 28.1 seconds is considered to bound the analysis data and all future In-service Tests to ensure the Accumulator check valves are non-degraded and unobstructed. The proposed activity does not involve a change to the facility that adversely affects a UFSAR described design function. The design functions of the Accumulator check valves as stated in Section I of this Screening are to freely open without obstruction during a LOCA and provide a flow path for the Si Accumulator discharge to the cold legs of the RCS. The check valves must be capable of closing to prevent divergence of SI and Recirculation flow after Accumulator discharge. The check valves must also prevent leakage from the RCS back into the Accumulator when they are normally closed. The In-service Test determines the time the Accumulator pressure decays to ensure the check valves are non-degraded and free of obstruction. The decay Nuclear Common Rev. 5

NC.NA-AS.ZZ-0059(Q) FORM-2 IOCFR50.59 SCREENING Page 4 of 6 Revision 0 Document l.D.: S-2-Si-hiDC-1394 Revision: 2

Title:

ACCUMULATOR PRESSURE DECAY DURING DISCHARGE TEST time has changed due to a longer stroke time of motor-operated SJ54 valve during the IST. During normal operating conditions though, the SJ54 valves are normally open to ensure an unobstructed and free flow path from the Accumulator to the RCS: Therefore, the proposed activity of increasing the acceptable value of the Accumulator's pressure decay time does not hinder or alter by any means the check valves' abilities to perform their design functions to freely open, close or prevent back leakage. The proposed activity does not involve a change to procedures that adversely affects how UFSAR described SSC design functions are performed or controlled. The operation of the Accumulator check valves is not specifically proceduralized in the UFSAR, but Section 5.2.8 does state how the Accumulator check valves should be inspected. The Salem UFSAR states that In-service Testing of ASME Code Class 1, 2 and 3 components be performed in accordance with ASME Section Xl. This is accomplished through Procedure S2.OP-ST.SJ-0006 and Relief Requests V-24 and V-25. The proposed change does not alter the purpose or methodology of the procedure or adversely affect the way in which the check valves will operate during a postulated accident. The increased acceptance criteria of decay time will ensure the Accumulator check valves are non-degraded and unobstructed. Therefore, the proposed activity does not adversely affect ho' the UFSAR described design functions are performed or controlled. The proposed activity does not revise or replace evaluation methodology described in the UFSAR that is used in safety analyses or to establish design bases. Calculation S-2-SJ-MDC-1394 is used to establish acceptance criteria to demonstrate the time it would take to decay the Accumulator pressure with non-degraded and unobstructed check valves. Although the methodology and results of the calculation are not used in safety analyses or used to establish design bases, it can still be shown that the methodology has not been altered to establish the new acceptance criteria for decay time. The only revision to the calculation is the input parameter for stroke time for valve SJ54 and does not constitute a fundamental change to the methodology used to establish the decay time. The revision of the calculation to determine pressure decay time does not involve a test or experiment of any kind. Therefore, the proposed activity does not involve a test or experiment NOT described in the UFSAR. The design functions of the Accumulator check valves and consequently the Accumulator are unaffected. Therefore, the Accumulator will deliver the required flow to the RCS as analyzed during a postulated accident and the design basis limits for a fission product barrier are unaffected. All the Screening questions, as explained in section 5 and 6, are answered NO. Therefore, further evaluation is not warranted. Nuclear Common Rev. 5

NC.NA-AS.ZZ-0059(Q) FORMI.-2 IOCFR50.59 SCREENING Pag~e 5 of 6 Revision 0 Document I.D.: S-2-SJ-MDC-1394

Title:

ACCUMULATOR PRESSURE DECAY DURING DISCHARGE TEST Revision: 2 6.

Conclusions:

Ifall Screening questions in Section 5 are answered NO, then a 50.59 Evaluation is not required. E If any Screening question is YES, then perform a 50.59 Evaluation (Form-3). 50.59 Evaluation No:

7. List the documents reviewed containing relevant information, including section numbers (UFSAR, Tech Specs, and others):

UFSAR Sections 5.2.7.1.5 5.2.8 5.5.3 6.3 UFSAR Tables Table 6.3-10 Intersystem Leakage Detection, Revision 20 Inservice Inspection Program. Revision 20 Reactor Coolant Piping, Revision 20 Emergency Core Cooling System, Revision 20 Accumulator Inleakage, Revision 6 Technical Specifications 4.0 4.0 Salem Unit I Applicability, Surveillance Requirements, sub-section 4.0.5, Amendment 256 Salem Unit 2 Applicability, Surveillance Requirements, sub-section 4.0.5, Amendment 237 SER 99-028 Relief Requests V-24 and V-25 Regarding Testing Of Accumulator Check Valves, Salem Nuclear Generating Station, Unit Nos. I and 2 (TAC No. M98259 and M98280), March 12. 1999. Nuclear Common Rev. 5

NC.NA-AS.ZZ-0059(Q) FORM-2 IOCFR50.59 SCREENING Page 6 of 6 Revision 0 Document I.D.: S-2-SJ-MDC-1394

Title:

ACCUMULATOR PRESSURE DECAY DURING DISCHARGE TEST Revision: 2 COMPLETION AND APPROVAL (J PREPARER (SIGN) V "kEVIEWER (SIGN) APPRGKAL (SIGN) October 21. 2003 DATE October 22. 2003 DATE James Murphy NAME (PRINT) Vijay Chandra NAME (PRINT) February 20, 2004 QUAL EXPIRES February 20. 2004 QUAL EXPIRES October 22. 2003 DATE Paul Lindsay NAME (PRINT) 3 /s/oy QUAL EXPIRES Nuclear Common Rev. 5}}

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