ML18102A708

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Forwards Proposed Rev to Inservice Testing Program,Including Relief Requests for V-24 & V-25 for Check Valves SJ55 & SJ56
ML18102A708
Person / Time
Site: Salem  PSEG icon.png
Issue date: 12/26/1996
From: Storz L
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N96437, NUDOCS 9701020241
Download: ML18102A708 (70)
v • d • e


Text

{{#Wiki_filter:INSERVICE TESTING PROGRAM RELIEF REQ1JEST. REC'D W/LTR DTD 12/26/96 .. -NOTICE** THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE INFORMATION & RECORDS MANAGEMENT BRANCH. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS & ARCHIVES SERVICES . SECTION, T5 C3. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.

    • NOTICE -

Document Control Desk LR-N96437 ATTACHMENT 1 INSERVICE TESTING PROGRAM RELIEF REQUEST SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 DEC 2 6 1996

  • Attachment (1) Document Control Desk LR-N96437 C Mr. Hubert J. Miller, Administrator

-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 DEC 2 6 1996 Mr. L. N. Olshan, Licensing Project Manager -Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall -Salem (S09) USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

  • Document Control Desk LR-N96437 EHV/ DEC 2 6 1996 BC CNO & President

-Nuclear Business Unit (N09) Senior Vice President -Nuclear Engineering (N19) Senior Vice President -Nuclear Operations (X04) Director -Nuclear Business Support (NlO) Director -QA/Nuclear Safety Review (XOl) Director -Nuclear System Engineering (X07) General Manager -Nuclear Operations Services (XlO) General Manager -Salem Operations (S05) General Manager -Hope Creek Operations (H07) Manager -Nuclear Safety Review (N38) Manager -External Affairs (N28) Manager -Licensing & Regulation (X09) Onsite Safety Review Engineer -Salem (Xl5) Onsite Safety Review Engineer -Hope Creek (Hll) General Solicitor, E. J. Selover (Newark, 5G) Perry Robinson, Esq. Records Management (N21) Microfilm Copy File Nos. 1.2.1,

  • Salem Units 1 and 2 Inservice Test Progam
  • VALVE RELIEF REQUEST -V -24
  • COMPONENTS:

l 1SJ55, 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 oflWV-3521. 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 quality and safety. The valves are normally in the closed position and accumulator pressure is continuously monitored to ensure that an adequate nitrogen blanket is maintained and to verify the lack of RCS inleakage.

  • Salem Units 1 and 2 Inservice Test Progam \! -24 (Cont) 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

-"Acumulator 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. 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. M88 l 44 and M88 I 45) . "' .

  • Salem Units 1 and 2 Inservice Test Progam VALVE RELIEF REQUEST-V -25 COMPONENTS:

11SJ56, 12SJ56, 13SJ56, 14SJ56 21 SJ56, 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 ofIWV-3521. 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 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 .

  • *
  • Salem Units 1 and 2 lnservice Test Progam V -25 (Cont) AL TERNA TE 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-l\1DC-1394

-"Acumulator 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 ofNUREG 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 l 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. M88 I 44 and M88 I 45) .

  • General Approach Proposed For Full Open Testing Of Accumulator Check Valves PSE&G procedure S2.0P-ST.SJ-0006(Q), lnservice Testing Safety Injection Valves Mode 6, provides instructions necessary to perform lnservice Inspection and Testing IAW Technical Specification 4.0.5 for the following Safety Infection (Accumulator) check valves:
  • 21 SJ55 and 21 SJ56 -21 Accumulator Discharge to Cold Leg
  • 22SJ55 and 21 SJ56 -22 Accumulator Discharge to Cold Leg
  • 23SJ55 and 21 SJ56 -23 Accumulator Discharge to Cold Leg
  • 24SJ55 and 21 SJ56 -24 Accumulator Discharge to Cold Leg The testing procedure involves open-stroke testing each tank's discharge check valves with the reactor depressurized 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 to 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-1394, 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: .. The Unit is in Mode 6 (Defueled) with the Upper Internals installed.

  • Safety Injection Accumulators are at a fixed and defined pressure.
  • Safety Injection Accumulators are at a fixed and defined level. .. Refueling Cavity is at a fixed and defined level. " 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-90-530 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:

  • Accumulator level elevation
  • Accumulator gas pressure
  • MOV loss factor
  • Check valve Delta P .. Derivations " Values at new tirT)e step
  • Results The following three cases were run:
  • Check valve is free (72 degrees swing angle)
  • Check valve maximum swing angle form closed position is 60 degrees.
  • Check valve maximum swing angle form closed position is 30 degrees. Tables 4.1, 4.2 and 4.3, provided in the calculation, show the accumulator pressure time history and discharge flow rate time history for each case. These curves are plotted in figures 4.1 and 4.2. Only curves with the reactor head on are shown since the pressure decay time is nearly equal for both test configurations, reactor head on and reactor head off. These curves show approximatly a 4 second (or 14 percent difference) between the two values of the disc being free (72 degrees open) and a disc maximum swing of 60 degrees. Conclusion The calculation concluded that the pressure decay time from 70 psig to 35 psig is nearly 24 seconds when the check valve is free. lmperical test results were then compared to the value calculated.

A pressure decay time of 23.9 seconds (maximum value of four lines tested) was measured on Salem Unit 1. On Salem Unit 2 three Accumulator pressure decay tests were performed with pressure decay times of just below 24 seconds. One test was not considered do to a motor failure of the Accumulator isolation MOV. Therefore, a 24 second decay time, as calculated , is a very good representation of the transient and has been verified empirically over seven tests. The valves tested were known to be in new or good condition based on recent disassembly and inspections of the valves' internals. It is reasonable to conclude that the test method described is valid at providing reasonable assurance that the valves tested go to there full open position . t:'i1llO."" -* FORM NC.DE-AP.ZZ*0002-l P&g* 1 of 2 CALCULATION COVER SHEET Cover Shee:. Page I of 41 C!ALC. NO. I s s J -""' D c -I 9 '+ REVIS I OH: __;;j=-------- me. TITLZ1 A cc UM ULAT6R. PRf:SSuR.£ Dr= cA '-/ q 'DISCJ.lftR..fi,; l Es 1 # SKTS. (CA.LC) i 41 A'l'TACBMENTS1

  1. /TOTAL SHTS. a Z.cf<O TOTAL SR'1'S.: 4 / ' CHECK ONE; 0 INTERIM {Proposed Plant Change) FINAL !Supports Installed Condition)

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  • PROCEDURES

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  • CALCULATION CONTINUATION SHEET Fl Ci u Rr .2.

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  • ATTACHMENT2 l...,117PMl-N

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  • 0 5 , . 1,
  • 2 I
  • 3 , . 4 , . 5 , . 6 , . 7 I
  • 8 I
  • 9 , 1 . I DATA CVCV/O., 0.0194, 0.055, 0.1, 0.146, 0.204, # 0.277,0.3536,0.4613,0.6086,0.767,1./ . ...__. PARAMETERS GAM=l.3 G=32.174 RHO=l.94 AREA=0.394 DT=0.01 PPRES=14.7*144.

C INITIAL CONDITIONS TIME=O.l NSTEP=-1 VNAZ=419.9 VNA=VNAZ PAZ=84.7*144. PA= PAZ Q=.001 VWP=758. REf\CTG1\ 11dt-D ts oN Ct\tf.-t vALvt"" IS F"R.EE WRITE(*,101) 101 FORMAT(T19'TIME', T28'ACCUMULATOR PRESSURE 103 FORMAT(T19'(SEC.)',T28' (PSIG) FLOW RATE') (GPM) I, I/) WRITE(*,103} 31 NSTEP=NSTEP+l TIME=TIME+DT C CALCULATE ACCUMULATOR LEVEL ELEVATION VWA=l350.-VNA ZA=(VWA+7869.6)/95.72 C CALCULATE PRESSURIZER LEVEL ELEVATION ZP=(VWP+4092.3)/38.34 -CALCULATE ACCUMULATOR GAS PRESSURE

  • PA=PAZ*(VNAZ/VNA)**GAM CALCULATE SJ54 LOSS FACTOR VOTl=lO. GVKZ=.15 IF(TIME .LT. VOTl) THEN VOF=TIME/VOTl CALL INTER(VOF,CVND,12,VVOF,CVCV)

GVK=GVKZ/(CVND*CVND) ELSE GVK=GVKZ END IF 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*(l.-SINPHI) C CALCULATE DERIVATIVES DQDT=(PA+RHO*G*ZA-PPRES-RHO*G*ZP-35.75*Q*ABS(Q)

  1. -0.5*GVK*l.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. O)WRITE(*,102) TIME,+(PA/144.-14.7), # Q*7.48*60. ELSE IF(MOD((NSTEP+l0),100) .EQ. D)WRITE(*,102) TIME,+(PA/144.-14.7), # Q*7.48*60. END IF ...._.. 102 FORMAT(F23.3,8F17.2) UPDATE THE OLD VARIABLES Q=QQ VNA=VVNA VWP=VVWP IF(TIME .GT. 100.) STOP GO TO 31 END SUBROUTINE INTER(X,Y,N,XX,YY) DIMENSION XX(N),YY(N) IF(X .LT. XX(l) .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 2 101 Y=YY(J-l)+(YY(J)-YY(J-l))*(X-XX(J-1))/ 1 (XX(J)-XX(J-1)) RETURN 2 CONTINUE 3 WRITE(6,l) X,(XX(I),I=l,N) 1 FORMAT(' BEYOND RANGE',Gl0.4,5X,20G10.4) RETURN END C:\SALEM\REACTOR\ECCS>

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  • DIMENSION VVOF(12),CVCV(12)

DATA VVOF /0. I

  • 05 I .1,. 2 I
  • 3 I
  • 4 I
  • 5, . 6, . 7, . 8 I
  • 9 I l. I DATA CVCV/O., 0.0194, 0.055, 0.1, 0.146, 0.204, # 0.277,0.3536,0.4613,0.6086,0.767,1./

'-" PARAMETERS GAM=l.3 G=32.174 RHO=l.94 AREA=0.394 DT=0.01 PCAV=14.7*144. Clh'r'\Pu1a<. L1S1"trJG R nc T61Z M t}\-i) l OF F C INITIAL CONDITIONS TIME=O.l 'JAL-\iG \5 Fr\t=E* NSTEP=-1 VNAZ=419.9 VNA=VNAZ PAZ=84.7*144. PA= PAZ Q;:;;. 001 ZCAV=127. WRITE(*,101) 101 FORMAT(Tl9 1 TIME 1 , T28 1 ACCUMULATOR PRESSURE 103 FORMAT(Tl9 1 (SEC.)',T28 1 (PSIG) WRITE(*,103) 31 NSTEP=NSTEP+l TIME=TIME+DT C CALCULATE ACCUMULATOR LEVEL ELEVATION VWA=1350.-VNA ZA=(VWA+7869.6)/95.72 C CALCULATE ACCUMULATOR GAS PRESSURE PA=PAZ*(VNAZ/VNA)**GAM CALCULATE SJ54 LOSS FACTOR VOTl=lO. GVKZ=.15 IF(TIME .LT. VOTl) THEN VOF=TIME/VOTl CALL INTER(VOF,CVND,12,VVOF,CVCV) GVK=GVKZ/(CVND*CVND) ELSE GVK=GVKZ END IF 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*(l.-SINPHI) FLOW RATE') (GPM) ',//) C CALCULATE DERIVATIVES DQDT=(PA+RHO*G*ZA-PCAV-RHO*G*ZCAV-35.75*Q*ABS(Q)

  1. -0.5*GVK*l.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. O)WRITE(*,102) TIME,+(PA/144.-14.7), # Q*7.48*60. ELSE IF{MOD({NSTEP+l0),100) .EQ. O)WRITE(*,102) TIME,+(PA/144.-14.7), # Q*7.48*60.

  • .._. END IF 02 FORMAT(F23.3,BF17.2)

UPDATE THE OLD VARIABLES Q=QQ VNA==VVNA IF(TIME .GT. 100.) STOP

  • GO TO 31 END _ SUBROUTINE INTER(X,Y,N,XX,YY)

DIMENSION XX(N),YY(N) ...._. IF(X .LT. XX(l) .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 2 101 Y=YY(J-l)+(YY(J)-YY(J-l})*(X-XX(J-1))/ 1 (XX(J)-XX(J-1)) RETURN 2 CONTINUE J WRITE(6,1) X,(XX(I),I=l,N) 1 FORMAT(' BEYOND RANGE',Gl0.4,5X,20Gl0.4} RETURN END C:\SALEM\REACTOR\ECCS>

* ......_.

TITLEACt'UMULI\ Tr/Z._ IDNO. S-2-SJ-/Yll)C-13 "31* SHEET PF?_t: SSURE: [){:{'fl/ T D V R I N (J D I S CH n R (j' [ REFERENCE > 0 IE S\. OF ORIGINATOR v.t11t.1JoR4lo --L L --L '-\I CALCULATION CONTINUATION SHEET 4. RE'SuL T'S DATE Jl-tOCT PEER REVIEW 1 DA TE I c/ ( 7-"l_(9"1 lti!Z FoLLO.WIJJ{7 TH R£ £ Wf"Rt RvtJ F<f'R Hcfroc')J C.tHIT IC, v RA 'TION . 1 CH'f.CK V/JLvE IS 2.. CHt;Ck \J/lLVL Mfl1-JfYl!l[r') SvvtAJG FRtfW1 ftJ.S/TIO/\J IS Go DEGR.£ES, 3. Cftrc.K VflLvr MA-x1mvM sc.-v1rJ(7 f+NGLr f/?..{)r(I CL-t>ScD PoSITJtJN IS 3o 7 irB L £ s 4. / , 4. 2, lrNO '-t* 3 s HO i.J THE /J Ctv M vL.!iTd1Z_i TIJYJr H15 TtrR.j f\KD DJSCHHt;t:: FLot.J RA--r £ "TIME 1-11s1cR.y rtR £-ftL.A{ rA lru::sG" CfJf?VE s !ti?£ PLOTTED JN FI 4 v R £ s '1-*I {)-Ni) 4. 2-. tflSt. 4 it_JAS RurJ Rnfz"TcR HFfrDt.f"f In-if) -r Ht. CHnl:-vAL vc; Wt' s t.arJ s1 DfRrD F Ta JY)u\J E.

  • 1 HE A c (" cJfll v LA 'T tR. PR E s <:: c:: ,Ar.lf'i 1J1 c NM t7 c fLtH-'1 fr-R[ SHOWN \N llrf3,L£ 4*l.i. 'J <' () M p frR I s o*tJ of RE Su L I S 6F 1 AA L £ 4 * ( fh..-p 4 .4 , I 1 I S CO Al ('_ L u j) [{) I t1 ft 1 1 H E P R E 5 <: u-.P. E f) fl A-y \lrvlf lg, NE1rf?.L')

r:.QUA-'L WHE.'THcR -1Hc lE Sr IS. DrJNE w l ,-t Ii I H E 11 t. 07\f OJ\ err F

  • OE-AP.ZZ-0002(0)

ATTACHMENT 2 _,., __

  • TA-BL£ '-t I TIME (SEC.) .110 .210 .310 .410 .510

.610 .710 .810 .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 42.009 43.009 A (' (' u n1 VL" T oR. p R £ s s u R f ANO DI s c H ftf{ 6 E FLoLu RAif 1/nlt HISToRl£S (Cli/;ZI<. WlLVG 15 F(U.t:) ACCUMULATOR PRESSURE FLOW RATE Oft.\\ (PSIG) (GPM) 70.00 69.99 69.97 69.94 69.90 69.85 69.80 69.73 69.64 69.55 69.44 69.33 69.20 69.07 68.93 68.79 68.64 68.48 68.32 68.15 66.23 64.04 61. 75 59.48 57.29 55.21 53.26 51.43 49.72 48 .13 46.65 45.26 43.97 42.75 41. 60 40.53 39.51 38.55 37.65 36.79 35.98 35.22 34.50 33.82 33.18 32.58 32.01 31. 47 30.95 30.47 30.0l 29.58 29.17 28.78 28.41 28.06 27.73 27.'12 27.12 26. 84 26.58 .45 300.49 440.81 578.47 713.81 902.74 1115.94 1330.04 1541. 08 1747.67 1930.52 2087.50 2229.64 2362.35 2488.29 2608.84 2724.74 2836.38 2943.97 3047.65 3875.55 4401. 87 4713.27 4839.18 4872.79 4849.09 4779.05 4688.39 4574.63 4454.73 4338.16 4225.73 4117.26 4012.45 3911. 02 3812.72 3717.33 3624.65 3534.47 3436.45 3330.96 3225.19 3121.06 3019.06 2919.24 2821. 52 2725.84 2632.09 2540.20 2450.10 2361.72 2275.02 2189.97 2106.55 2024.74 1944.57 1866.05 1789.22 1714.15 1640.91 1569.61 S 5 J-('() DC-t 30J4 CnECK '\11\L\J[ FREE R 1::.At:TD'R Hcit1) IS ON ---*-------- TABL£ 4*2 PRESSURE AtJP 'DISCH/tf.C,t; FLOW RA'Tf: 31. -qr<\£ HIS WX'\ £5 lfYlA.X* SWlt\ll] AIJ(jLE: 60 Dc-tS.) oF

  • TIME ' ACCUMULATOR PRESSURE FLOW RATE 4\ (SEC.) {PSIG) (GPM) ...........

.110 70.00 .45 5-2-SJ-f'flf)C-1:,°,)4 .210 69.99 300.49 .310 69.97 440.81 .410 69.94 578.47 .510 69.90 713.81 .610 69.85 902.74 .710 69.80 1115.94 .810 69.73 1330.04 .910 69.64 1541. 08 1.010 69.55 1747.67 1.110 69.44 1930.52 1.210 69.33 2087.17 l.310 69.20 2224.09 1.410 69.07 2347.27 1. 510 68.94 2460.90 1. 610 68.79 2567.13 1.710 68.64 2667.11 cfi£Ct"-VAL\J( 1.810 68.49 2761.49 1.910 68.33 2850.70 /\1JIJCIMUM SL-VI rJt; 2.010 68.17 2935.03 {;o R££ 3.010 66.36 3561.19 = 4.010 64.37 3937.09 R t1'rc T d{ H CIT() 5.010 62.33 4135.53 6.010 60.31 4198.94 I s t1 rJ 7.010 58.37 4202.26 8.010 56.53 4169.33 9.010 54.79 4108.03 10.010 53.15 4035.44 11.010 51. 60 3948.75 12.010 50.15 3859.57 13.010 48.79 3773.05 14.010 47.50 3689.36 15.010 46.29 3608.35 16.010 45.14 3529.82 17.010 44.06 3453.60 18.010 43.03 3379.54 19.010 42.05 3307.51 20.010 41.12 3237.37 21. 010 40.24 3169.00 22.010 39.40 3102.31 23.010 38.60 3037.19 24.010 37.84 2973.55 25.010 37.11 2911.31 26.010 36.41 2850.39 27.011 35.74 2790.71 28.011 35.10 2732.22 29.011 34.49 2674.85 30.011 33.91 2618.55 31.011 33.35 2563.25 32.011 32.81 2508.91 33.010 32.29 2455.49 34.010 31. 80 2402.93 35.010 31. 32 2351.20 36.010 30.86 2300.26 37.010 30.42 2250.07 38.010 30.00 2200.59 39.009 29.59 2151.80 40.009 29.20 2103.67 41. 009 28.82 2056.16 42.009 28.46 2005.5!) 43.009 28 .11 1941.39

    • ------* *-*-** . TABL(: lt*3 A ccurouLsrrcR._

PR 1.::s s u R c: AJJD 015 CJ-f FLOhJ IUJTE \I "1 G'" HISIOR.1£"$ ( Sw/rJG ANG£::. 3o DtiCt.). 33 TIME ACCUMULATOR PRESSURE FLOW RATE Of' (SEC.) {PSIG) (GPM) t; I -* .110 70.00 .45 5-2-.SJ-Ml)C-r39ft .210 69.99 300.49 .310 69.97 440.81 .410 69.94 578.47 .510 69.90 713.81 .610 69.85 902.74 .710 69.80 1110.33 69.73 1308.20 .910 69.65 1492.50 1.010 69.56 1661.97 1.110 69.46 1800.72 1.210 69.35 1911..17 1.310 69.24 2005.29 1.410 69.12 2088.58 1.510 69.00 2163.68 1. 610 68.87 2232.04 1.710 68.74 2294.51 1.810 68.61 2351. 71 1.910 68.48 2 4 o 4 . 11 e H £ L' "-v AL. V £ 2.010 68.34 2 4 5 2

  • 11 MAX I P'I u M Sl-'11 Ill (.j 3.010 66.88 2759.92 .R _ 4.010 65.35 2902.46 = DE"l*1 ££ 5.010 63.83 2957.44 6.010 62.34 2959.75 Ri HE.11-D 7. 010* 60.90 2942.94 8.010 59.53 2914.56 1s 0 tJ 9.010 58.21 2877.51
  • 10.010 56.95 2837.78 11.010 55.74 2793.53 12.010 54.59 2749.34 13.010 53.49 2706.28 14.010 52.43 2664.32 15.010 51.42 2623.40 16.010 50.45 2583.46 17.010 49.52 2544.45 18.010 48.63 2506.33 19.010 47.77 2469.05 20.010 46.95 2432.56 21.010 46.15 2396.84 22.010 45.38 2361.85 23.010 44.65 2327.55 24.010 43.93 2293.91 25.010 43.25 2260.90 26.010 42.58 2228.50 27.011 41. 94 2196.68 28.011 41. 32 2165.41 29.011 40.73 2134.67 30.011 40.15 2104.44 31.011 39.59 2074.71 32.011 39.04 2045.44 33.010 38.52 2016.62 34.010 38.01 1988.24 35.010 37.51 1960.28 36.010 37.03 1932.72 37.010 36.57 1905.55 38.010 36.12 1878.75 39.009 35.68 1852.30 40.009 35.25 1826.21 41.009 34.84 1800.45 42.009 34.44 1775.02 43.009 34.05 1749.89

......... sooo \!-\.} l:l t-" :? l\Ol>> C) lu Q::'.' Cl: E 3000 Vl a. ot. <::i :3 200D 'E: " q: 1000 ( (]\ I N 1 I}\ L I 3 0 ,...., I ....... s-to 1s 20 2s 3o 35 itME' (Sec.) Ft4. 4°1 DISC.fi/\R.CJC FLOW ftA'fE TIME" H\5\0'RlES.

  • ( 70 50 VALV£ f S F'Ri=:ri . ti\" IV c..., 1 30 3 C7 ""\ 1 lP \J) --F"" 5 I 0 15 20 25 3o 35 l>> -\)\ T 1 IVl E ( s ('C ') Ace u P R(;Ss uf?t ttl s To-RI E" S. ( R Efrt..T'*-.

t1 efrO 1 so"')

  • ---** *-* --. 1 ML£ 4. A c r t1 m u L. Al cfZ p £ s .-,; l*l? £ ftN D cHM()r-3, FLoi.v RA'T£ Tl ME E..S TIME ACCUMULATOR PRESSURE FLOW RATE (SEC.) (PSIG) (GPM) --.110 70.00 .45 C H £L..f< \i 1l L. VE .210 69.99 302.62 IS F RE£ .310 69.97 443.73 .410 69.94 582.24 R Fl\-r T af\.. .510 69.90 718.41 .610 69.85 912.06 HttrlJ 1$ .710 69.79 1129.44 OFF-.810 69.72 1346.85
  • 910. 69.64 1560.72 1.010 69.54 1769.78 1.110 69.44 1952.89 1.210 69.32 2108.73 1.310 69.19 2249.72 1.410 69.06 2381. 56 l.510 68.92 2506.95 1.610 68.78 2627.17 1. 710 I 68.62 2742.87 1.810 68.47 2854.40 1.910 68.30 2961. 92 2.010 68.13 3065.54 3.010 66.20 3889.94 4.010 64.01 4415.41 5.010 61. 72 4727.30 6.010 59.44 4854.45 7.010 57.25 4892.59 8.010 55.16 4874.61 9.010 53.20 4810.78 10.010 51. 36 4727.42 11.010 49.64 4620.66 12.010 48.03 4508.55 13.010 46.54 4400.16 14.010 45 .13 4296.01 15.010 43.82 4195.86 16.010 42.58 4099.41 17.010 41. 42 4006.38 18.010 40.32 3916.53 19.010 39.28 3829.62 20.010 38.30 3745.47 21.010 37.37 3663.87 22.010 36.49 3584.68 23.010 35.65 3506.31 24.010 34.86 3417.82 25.010 34.10 3326.38 26.010 33.39 3235.94 27.011 32.71 3147.41 28.011 32.07 3060.95 29.011 31. 46 2976.50 30.011 30.88 2894.00 31.011 30.33 2813.J3 32.011 29.81 2734.42 33.010 29.31 2657.18 34.010 28.83 2581. 54 35.010 28.38 2507.44 36.010 27.94 2434.82 37.010 27.53 2363.62 38.010 27.14 2293.81 -39.009 26.76 2225.34 40.009 26.40 2158.18 41. 009 26.06 2092.31 42.009 25.73 2027.71 43.009 25.42 1964.38
  • 10 NO. S $ J-l'1 !) ( -I 3 5 Lt SHEET TITLE Arr U fl -r PRc-.S<;uRl on-fl'j '11 CY\ t [)URI tJ f1 REFERENCE 3 7 /)J <;CtJfrR(J[.

/ £ 5 -, CALCULATION CONTINUATION SHEET OF ORIGINATOR --L c --L DATE 21 PEER REVIEW 0A-t£L DATE td(U{°r' __ $'. CoNCLUSION

  • fi5 CALl'.'UL.AltD IN S,[(1/0N 4, "THE PRES<>URE b Et A j It rY1 E F R (JYr1 7 0 f s 1 'd To S

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  • cJ S:ITCt"-rO.

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---* .... --* -_*I

  • SHEET REFERENCE 38 OF CALCULATION CONTINUATION SHEET

---L L ---L ft-( PEER REVIEW """"'-((" DATE t cJ(t. l{'1 "( (;. L 1 s T aF R E r r=1{ 1: N c [ s i. .. Mp L I ('A T I 0 N (; I) I D E L \ N t s F crR c /-1 t:: C..K v ()L v L s I N N u c L £ r cHJ £P r L t) /\r( f_ Pr< ]. R CP O'f T f: r R .7 "'p -s 4 7 °.). JAN I CJ F8. 2. DRAL,JtrJC, 218213 8ev. 18; /ir'((Jf\?ULf11t't.. il'ID P1 f/N(] /rRRAN(,£Mt NI. 3. Lt. S" . (;. 7. fj .. psBP D£LT(l re. [)f<.lr""J11Jf} ff t)/.J/T 2. (' (' V1'1 V L /I '7 er((_ 52.of>.'DD-'Z'Z.- OD74fZ) 5 ALE M 2 A('(' u M UL VOL u f\*) E. vs. r B D D [ -(' . R c -00L1 ) r rx. ) R fv. 1 PRE 5 <;uR1z r:K klfl 1CR VuL ume: Vs. LE. 1 1 d. f R ('¥'\ 1 .,,1 F s -r r ,.,ic; H () u s C 1 MO. D1. M Aj 2 I; IC) 'Jl) 1/c LE::Vl:.L <'uPvc flt(; c FI 7-l. fo LEVt.L PSE-c:>CJ-s OE-AP.ZZ-0002(0) ATIACHMENT2 lll-01117 UM HI

  • -FORM NC.DE-AP.ZZ-0010-1 Page 2 of 4 CERTIFICATION FOR DESIGN VERIFICATION Reference No. SJ -IY1 I)( -I -JL1

SUMMARY

STATEMENT

1) d c ( cvrA (.JlG The undersigned hereby certifies (in the right column) 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.

JAGK Design Verifier Assigned By Design Verifier I Date (signature of Manager/Supervisor) /20./fi'." /// Desigrl' Verifier Assigned By Sigvature (signature of Manager/Supervisor) /;:QrL I z.-E-!'19.EJ Design Verifier Date Design Verifier Assigned By Sigvature of Design Verifier / Date (signature of Manager/Supervisor) Design Verifier Assigned By Sigvature of Design Verifier / Date {signature of Manager/Supervisor)

  • If the Functional Manager/Supervisor acts as the Design Verifier, the signature of the next higher level of technical management is required.

Page of --* 'llev. 2 Page 13 of 17 Jtuclear Common

  • Rev. 2 FORM NC.DE-AP.ZZ-0010-1 Page 3 of 4 CERTIFICATION FOR DESIGN VERIFICATION Page __ of __ Page 14 of 17 :VUclear Cammon FORM NC.DE-AP.ZZ-0010-1 Page 4 of 4 CERTIFICATION FOR DESIGN VERIFICATION REFERENCE DOCUMENT NO. /REV. *-2 -SJ -M DC-13 CJ 't COMMENTS SUBMITTED BY y oJ(TE RESOLUTION JIT 6J t.>> Ill Al)I:) 70 S ff 1' 0 t: 0 ({.. Die. Acceptance of Resolution Jl.ev. 2 Page 15 of 17 Nuclear Common
  • .! 'b. _ __, ----,-USE CATEGORY : I REVISION SUMl\llARY SALEMJOPERATIONS S2.0P-ST.SJ-0006(Q)

-REV. 4 INSERVICE TESTING SAFETY INJECTION VALVES MODE6 Page_l of_l + Incorporated "MODE 6" in procedure title to accurately reflect perfonnance requirement. t Procedure revised throughout to reflect performance requirements of "Unit is in Mode 6 with the Reactor Vessel He.ad REMOVED, OR is DEFUELED with the Reactor Vessel Head REMOVED and the Upper Internals installed" versus "Mode 5, 6 or DEFUELED with the upper internals installed". This change provides additional clarification, and is in response to AR 960206344. + Revised Purpose 1.1 to indicate the respective Safety Injection (Accumulator) Check Valves being tested and "This requirement is applicable in Modes I and 2, and Mode 3 with Pressurizer Pressure above 1000 psig". + Incorporated Purpose 1.2 to indicate "To partially satisfy the requirements of Technical Specification 4.4.7.2.2 for the RCS Pressure Isolation Valves identified in I.I. This requirement is applicable in Modes 1-4". + Incorporated Purpose 1.3 to delineate performance requirements. t Incorporated Prerequisite Step 2.1 to ensure applicable Work Order number(s) and Reason for Test are recorded on Attachment

1. + Step 5.3.2 and Attachment 3 revised to incorporate IST Program Manager review following procedure completion.

+ Revised Reference Section 7.0 to reflect appropriate required references. + Revised Reference 7.5.10 to reflect Rev. 1 of Calculation No. S-2-SJ-MDC-1394. + Revised procedure to reflect current procedure fonnat requirements (no revision bars used). IMPLEl\.llENTATION REQUIREMENTS t None APPROVED: -Salem Operations \. INSERVICE TESTING SAFETY INJECTION VALVES MODE6 TABLE OF CONTENTS s2.or-ST .sJ-0006(Q) SECTION TITLE PAGE 1.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.0 PREREQUISITES ......................................... 2 3.0 PRECAUTIONS AND LIMIT A TIO NS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 4.0 EQUIPMENT/MATERIAL REQUIRED ........................... 3 5.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5.1 Forward Flow IST of Accumulator Check Valves ............... 4 5.2 Acceptance Criteria .................................. 8 5.3 Completion and Review ............................... 8

  • 6.0 RECORDS .............................................

9

7.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

9 ATIACHMENTS Attachment 1 Instrumentation and Test Equipment Data . . . . . . . . . . . . . . . . . . . . 11 Attachment 2 Check Valve Data and Independent Verification ................. 12 Attachment 3 Completion Sign-Off Sheet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 Salem 2 Page 1 of 14 Rev. 4

  • s2.oP-S T .sJ-0006(Q) l 1.0 PURPOSE 1.1 Provides instructions necessary to perfonn Inseivice Inspection and Testing C0265 JAW Technical Specification 4.0.5 for the following Safety Injection (Accumulator)

Check Valves: + 21SJ55 and 21SJ56 (21 Accumulator Discharge to Cold Legs) + 22SJ55 and 22SJ56 (22 Accumulator Discharge to Cold Legs) + 23SJ55 and 23SJ56 (23 Accumulator Discharge to Cold Legs) + 24SJ55 and 24SJ56 (24 Accumulator Discharge to Cold Legs) This requirement is applicable in Modes 1 and 2, and Mode 3 with Pressurizer Pressure above 1000 psig. 1.2 To partially satisfy the requirements of Technical Specification 4.4. 7.2.2 for the RCS Pressure Isolation Valves identified in 1.1. This requirement is applicable in Modes 1-4. 1.3 Perfonnance of this procedure is required once per Refueling Outage, or as otherwise . specified in the post-maintenance operational retest requirements. 2.0 PREREQUISITES 2.1 Applicable Work Order number(s) and Reason for Test are recorded on Attachment I, Section 1.0. 2.2 C0289 2.3 2.4 2.5 2.6 2.7 2.8 2.9 Calibration data for the Instruments and Test Equipment listed in Attachment 1, Section 2.0 is obtained. Unit is in Mode 6 with the Reactor Vessel Head RE.M:OVED, OR is DEFUELED with the Reactor Vessel Head REMOVED and the Upper Internals installed. Safety Injection Accumulators are pressurized between 67 and 70 psig. Safety Injection Accumulator levels arc between 96 and 100 %

  • Two Control Room Operators are available to support testing. Refueling transfer tube gate valve is closed. Refueling Cavity level is 125.5 -126.5 ft. An Infrequently Performed Test or Evolution briefing session is completed by the Manager -Salem Operations, or designee, IAW NC.NA-AP.ZZ-0005(Q), Station Operating Practices .
  • Salem2 Page 2 of 14 Rev. 4
  • 3.0 C0329 s2.oP-ST .sJ-0006CQ>

PRECAUTIONS AND LIMITATIONS 3.1 Procedure Use and adherence policy as found in NC.NA-AP.ZZ-OOOl(Q), Nuclear Procedure System. is applicable to this procedure. 3.2 Steps identified with a dollar sign($) are those items required to meet Technical Specification acceptance criteria. Such steps, if not satisfactorily completed, may have reportability requirements and should be brought to the immediate attention of the SNSS/NSS. 3.3 Failure of a single SJ54 valve to close can lead to the following: + Introducing N 2 into the RCS which may lead to gas binding of RHR System. t Loss of RHR cooling [entry condition to S2.0P-AB.RHR-0001(Q), Loss of RHR]. t A 1h foot Refueling Cavity level increase. 3.4 Coordinate Refueling Cavity level changes with Radiation Protection. 4.0 EQUIPMENT/MATERIAL REQUIRED

  • 4.1 M&TE: + Calibrated Stopwatch(es)

Page 3 of 14 Rev. 4 s2.oP-ST .sJ-0006CQ> 5.0 PROCEDURE 5.1 Forward Flow IST of Accumulator Check Valves

  • sa1em2 5.1.1 IF testing 21 Accumulator (21SJ55 and 21SJ56) check valves, THEN: $ A. At Panel 2RP4, ENSURE 21SJ54 in the VALVE OPERABLE position.

B. SIMULTANEOUSLY PERFORM the following: OPEN 21SJ54, 21 ACCUMULATOR OUT + ST ART the Stopwatch C. When 35 psig is observed, SIMULTANEOUSLY PERFORM the following: STOP the Stopwatch + CLOSE 21SJ54 D. RECORD the following in Attachment 2, Section 1.0: + Stopwatch Reading and Number + 2ISJ55 and 21SJ56 OPEN "Test Results" by initialing the SAT or UNSAT column using the Acceptance Criteria in Attachment

2. E. DIRECT a second Operator to complete Attachment 2, Section 2.0, for 21SJ54 valve position . Page 4 of 14 Rev. 4
  • 5.1.2 $
  • Salem 2 s2.oP-ST .sJ-0006

IF testing 22 Accumulator (22SJ55 and 22SJ56) check valves, THEN; A. At Panel 2RP4, ENSURE 22SJ54 in the VALVE OPERABLE position.* B. SIMULTANEOUSLY PERFORM the following: t OPEN 22SJ54, 22 ACCUMULATOR OUT t ST ART the Stopwatch C. When 35 psig is observed, SIMULTANEOUSLY PERFORM the following: + STOP the Stopwatch t CLOSE 22SJ54 D. RECORD the following in Attachment 2, Section 1.0: *

  • Stopwatch Reading and Number 22SJ55 and 22SJ56 OPEN "Test Results" by initialing the SAT or UNSAT column using the Acceptance Criteria in Attachment
2. E. DIRECT a second Operator to complete Attachment 2, Section 2.0, for 22SJ54 valve position.

Page 5 of 14 Rev. 4

  • _;. \ 5.1.3 $ Salem 2 s2.oP-ST .sJ-0006CQ>

IF testing 23 Accumulator (23SJ55 and 23SJ56) check THEN: A. At Panel 2RP4, ENSURE 23SJ54 in the VALVE OPERABLE position. B. SIMULTANEOUSLY PERFORM the following: + OPEN 23SJ54, 23 ACCUMULATOR OUT + ST ART the Stopwatch C. When 35 psig is observed, SIMULTANEOUSLY PERFORM the following: + STOP the Stopwatch + CLOSE 23SJ54 D. RECORD the following in Attachment 2, Section 1.0: + Stopwatch Reading and Number + Z3SJ55 and 23SJ56 OPEN "Test Results'! by initialing the SAT or UNSA T column using the Acceptance Criteria in Attachment

2. E. DIRECT a second Operator to complete Attachment 2, Section 2.0, for 23SJ54 valve position.

Page 6 of 14 Rev. 4 I. '

  • Salem 2 s2 .OP-ST .s1-0006(Q) 5.1.4 IF testing 24 Accumulator (24SJ55 and 24SJ56) check valves, THEN: $ A. At Panel 2RP4, ENSURE 24SJ54 in the VALVE OPERABLE position.

B. SIMULTANEOUSLY PERFORM the following:

  • OPEN 24SJ54, 24 ACCUMULATOR OUT
  • START the Stopwatch C. When 35 psig is observed, SIMULTANEOUSLY PERFORM the following:
  • STOP the Stopwatch
  • CLOSE 24SJ54 D. RECORD the following in Attachment 2, Section 1.0:
  • Stopwatch Reading and Number
  • 24SJ55 and 24SJ56 OPEN "Test Results" by initialing the SAT or UNSAT column using the Acceptance Criteria in Attachment
2. E. DIRECT a second Operator to complete Attachment 2, Section 2.0, for 24SJ54 valve position.

Page 7 of 14 Rev. 4 s2.oP-ST .sJ-0006CQ> . ' 5 .2 Accq>tance Criteria 5.2.1 This surveillance procedure is satisfactory when Attachment 2 has been completed with valve(s) listed meeting the Acceptance Criteria stated in the Attachment. 5.2.2 This surveillance is unsatisfactory: A. INITIATE Action Request(s) to correct the unsatisfactory condition(s). B. RECORD Action Request number(s) AND reason for unsatisfactory completion on Attachment 3 in the Comments Section. 5.3 Completion and Review Salem 2 5.3.1 COMPLETE Attachment 3, Sections 1.0 and 2.0, and FORWARD this procedure to SNSS/NSS for review and approval. 5.3.2 SNSS/NSS PERFORM the following: A. REVIEW this procedure with Attachments 1 through 3 for completeness and accuracy. B. IF ANY Check Valve Surveillance is UNSAT, THEN:. I 1. DECLARE Check Valve INOPERABLE.

2. EVALUATE Technical Specification requirements for system operability. COMPLETE Attachment 3, Section 3.0. D. PLACE this procedure in the IST PROGRAM MANAGER REVIEW REQUIRED mail slot. END OF PROCEDURE SECTION Page 8 of 14 Rev.4 s2. OP-ST .sJ-0006(Q) ) ' 6.0 RECORDS 6.1 Retain the following IAW NC.NA-AP.ZZ-0003(Q), Document Management Program: + Attachment 1 + Attachment 2 + Attachment 3 7 .0 REFERENCES 7.1 Updated Final Safety Analysis Report: 7.1.1 Section 6.3, Emergency Core Cooling 7.2 Technical Specifications

-Unit 2: 7.2.1 3.5.1, Emergency Core Cooling Systems (ECCS) Accumulators

7. 3 Procedures:

7.3.l NC.NA-AP.ZZ-0012(Q), Technical Specification Surveillance Program 7.3.2 NC.NA-AP.ZZ-0022(Q), Measurement & Test Equipment, Lifting & Rigging and Tool Control 7.3.3 NC.NA-AP.ZZ-0050(Q), Station Testing Program 7.3.4 NC.NA-AP.ZZ-0070(Q), Inservice Testing and MOV Testing Programs 7 .4 Drawings: 7 .4.1 205334, Unit 2 Safety Injection 7.5 C>thers: Salem 2 7.S.1 Section XI of ASME Boiler and Pressure Vessel Code (1983 Edition with Addenda through Summer 1983) 7.5.2 OMa-10, Inservice Testing of Valves in Light-Water Reactor Power Plants (1987 Edition with 1988 Addenda) 7.5.3 Salem Generating Station IST Manual 7.5.4 NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants 7.5.5 SJ MECH 001, Safety Injection Valve Alignment Page 9 of 14 Rev. 4 s2.oP-ST .sJ-0006(Q) \ ' 7 .5 Others: (continued) 7 .5.6 NRC Information Notice 89-67, Loss of RHR caused by Accumulator Nitrogen Injection 7.5.7 NSO LER 272/89-019-00 7 .5. 8 Memo 92-027, dated 02/07 /92 7.5.9 Memo 92-189, dated 11/18/92 7.5.10 Calculation S-2-SJ-MDC-1394, Rev. 1 7.5.11 Memo SCl-94-0884 dated 12/21/94 7 .5.12 Westinghouse Letter NTD-NSRLA-OPL-94-441 7 .6 Cross-

References:

7 .6.1 Procedures: A. NC.NA-AP.ZZ-OOOl(Q), Nuclear Procedure System B. NC.NA-AP.ZZ-0003(Q), Document Management Program C. NC.NA-AP.ZZ-0005(Q), Station Operating Practices D. S2.0P-AB.RHR-0001(Q), Loss of RHR 7 .6.2 Technical Specifications -Unit 2: A. 4.0.5, Inservice Inspection and Testing B. 4.4. 7 .2.2, Reactor Coolant System Operational Leakage 7. 7 Commitments: 7.7.1 C0265 -NSO LER 311/89-015-00 7.7.2 C0283 -NRC VIOL 311187-18-01 7.7.3 C0289 -INSTRUMENT CALIBRATION REQUIREMENTS

7. 7 .4 C0329 -NRC PLAN NLR-189215-01 Salem 2 Page 10 of 14 Rev. 4
  • s2.oP-ST .sI-0006CQ>

' . ATTACHMENT 1 (Page 1of1) INSTRUMENTATION AND TEST EQUIPMENT DATA 1.0 WORK ORDER DATA Work Order Number(s): 2.0 INSTRUMENT/TEST EQUIPMENT Instrument/Test Description Equipment "'2PI'936A 21 Ace Pressure Channel A "'2PT937A 21 Ace Pressure Channel B \ ... 2PT937B 22 Ace Pressure Channel A

  • 2PT936B 22 Ace Pressure Channel B
  • 2PT936C 23 Ace Pressure Channel C
  • 2Pf937C 23 Ace Pressure Channel D
  • 2Pf937D 24 Ace Pressure Channel C "'2Pf936D 24 Ace Pressure Channel D Serial # Calibrated Stopwatch Serial # Calibrated Stopwatch
  • Only one channel is required per Accumulator.

Salem 2 Page 11 of 14 Reason for Test Scheduled Surveillance Post-Maintenance Operability Other (Explain in Comments) Calibration Initials Overdue Date Rev. 4 s2.oP-ST .s1-0006(Q) !

  • ATTACHMENT 2 (Page 1 of 1) CHECK VALVE DATA AND INDEPENDENT VERIFICATION 1.0 CHECK VALVE DATA Component Stopwatch Stopwatch Test Results Stroke Reading Description
  1. (seconds)

SAT UNSAT 21SJ55 and 21SJ56 21 Accumulator 0 Check Valves 22SJS5 and 22SJS6 22 Accumulator 0 Check Valves 23SJSS and 23SJS6 23 Accumulator 0 Check Valves 24SJSS and 24SJ56 24 Accumulator 0 Check Valves ACCEPTANCE CRITERIA: Accumulator blowdown time is 27 .5 seconds. 2.0 INDEPENDENT VERIFICATION Component Description Normal IV Position 21SJ54 21 Accumulator Out x 228.154 22 Accumulator Out x 23SJ54 23 Accumulator Out x 248.154 -. 24 Accumulator Out x Salem 2 Page 12 of 14 Date Date Rev. 4 1 , .. 1.0 COMMENTS: ATTACHMENT 3 (Page 1of2) COMPLETION SIGN-OFF SHEET (Include test deficiencies and corrective actions.) Salem 2 Page 13 of 14 s2.oP-ST.sJ-0006(Q) Rev. 4 s2.oP-ST.sJ-0006(Q) ) j

  • ATTACHMENT 3 (Page 2 of 2) COMPLETION SIGN-OFF SHEET 2.0 SIGNATURES:

Print Initials Signature Date INDEPENDENT VERIFICATION: 3.0 SNSS/NSS FINAL REVIEW AND APPROVAL: C0283 This procedure with Attachments 1-3 has been reviewed for completeness and accuracy. All deficiencies, including corrective actions, have been clearly recorded in the COMMENTS Section of this attachment. Technical Specification compliance, procedure compliance, and Acceptance Criteria have been evaluated. Signature: ___________________ _ (Senior) Nuclear Shift Supervisor Date: ------4.0 IST PROGRAM MANAGER REVIEW: Test Results have been reviewed for acceptability. Forward completed procedure to Operations Staff. Date: Signatu.re: _____ -=-==-=--==-------:-:---------- IST Program Manager -----Salem 2 Page 14 of 14 Rev. 4

  • } ) FORM NC.NA-AP.ZZ-0001-7 Page 1of1 PROCEDURE TRANSMITTAL FORM PROCEDURE NO: S2.0P-ST.SJ-0002(Q)

TO: TDR/DDG Supervisor FROM: Procedure Maintenance Group REV:_5_ DATE: __ _ PLEASE DISTRIBUTE CONTROLLED COPIES OF THE ATTACHED PROCEDURE IN ACCORDANCE WITH THE CONTROLLED DISTRIBUTION LIST. REFERENCES (Use additional sheet if necessary) The following references and cross-references have been deleted from this procedure:

References:

NC.NA-AP.ZZ-0027(Q), Inservice Inspection Program Cross-

References:

NC.NA-AP.ZZ-OOll(Q), Records Management Program The following references and cross-references have been added to this procedure:

References:

UFSAR Section 9.2.1, Service Water System and P&ID 205342, No. 2 Unit Service Water Nuclear Area rum OMa-10, Inservice Testing of Valves in Light-Water Reactor Power Plants (1987 Edition with 1988 Addenda) and C0297 -NRC GL 89-13, Service Water System Problems Affecting Safety Related Equipment Cross-

References:

NC.NA-AP.ZZ-OOOl(Q), Nuclear Procedure System and NC.NA-AP.ZZ-0003(Q), Document Management Program !!!ill S2.RA-ST.SJ-0002(Q), Inservice Testing -22 Safety Injection Pump Acceptance Criteria The following references and cross-references have been revised in this procedure:

References:

NC.NA-AP.ZZ-0022(Q), Measurement & Test Equipment, Lifting & Rigging and Tool Control and NC.NA-AP.ZZ-0070(Q), Inservice Testing and MOV Testing Programs Cross-

References:

None

  • l } j FORM NC.NA-AP.ZZ-0001-4 Page 1 of l PROCEDURE SIGNOFF SHEET PROCEDURE NO: S2.0P-ST.SJ-0002(Q)

Page _1 of _L PROCEDURE TITLE: INSERVICE TESTING -22 SAFETY INJECTION PUMP Refer to Attachment 6, Procedure Review Matrix for required reviews. N/A if not applicable. Biennial Review Performed by this Revision: No A. B. c. D. E. F. G. Writer Review Randall Department Review Date :<\\s.\qJ,. Date: QA Review ...... ---ALARA Review NIA Date: ---

f (ii..,sk;ll

/Gijt;v Cross-Disciplinary Review Performed Not Applicable: D Technical Review SQRReview Date: Date: iJiif;i Discipline: IST Program Manager Reviewer:

  1. Date: __ '4-=-f-."/1oc..::c"-J./'i_._h"---

SORC Review SALEM: SALEM SORC Recommend with no further action. Recommend approval after actions listed below are completed. SORC Chairman: Date: -----Mtg. No. D Procedure/revision and 10CFR50.59 Safety Evaluation transmitted to QA/NSR. T/S 6.5.2.4.2 SPONSOR --------DATE ___ _ HOPE CREEK: NONE:X HOPE CREBX SORC Recommend with no further action. [=::::J Recommend approval after actions listed below are completed. SORC Chairman: Date: D -----Mtg. No. Procedure/revision and lOCFRS0.59 Safety Evaluation transmitted to QA/NSR. T/S 6.5.2.4.2 SPONSOR ------DATE ---SPONSOR APPROVAL (for NAPs only): DATE: __,,N_,_,/.._,A,___ __

  • J-J .. FORM NC.NA-AP.ZZ-0059-1 lOCFRS0.59 APPLICABILITY REVIEW FOR PROCEDURE REVISIONS Page _1_ of _2_ I.D. Number (Procedure

_______ Revision: 2... Title: INSERVICE TESTING -22 SAFETY INJECTION PUMP Applicability: Salem 1 Salem 3 (Gas Turbine) Salem 2 Hope Creek Common to Salem 1 & 2 Common to Hope Creek & Salem 1.0 Applicable SAR sections, Technical Specifications, and other documents reviewed: 2.0 + UFSAR Section 9. 2.1, Service Water System + P&ID 205342, No. 2 Unit Service Water Nuclear Area + OMa-10, Inservice Testing of Valves in Light-Water Reactor Power Plants (1987 Edition with 1988 Addenda) + NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants + C0297 -NRC GL 89-13, Service Water System Problems Affecting Safety Related Equipment

  • U

'3.. q . It lf1 1./1.f'IC. .. 'g A\.\)O C\ J(J'°llJ/ltl. + (4515'l....:h '--3 "' '/vif' t SEL !iUP'oUi.r'r'cf\TS '3. S ..> S* 3 N (/"(<if.

  • SC.llL :Sr..IPpu.me!>l'lt"'.:S I 4'-h1'1)11'i...

S :> E.. 3 Jt;1 'IUf/tJ. The proposed procedure revision does not change the facility as described in the SAR, because (check those that are true): ,/ a. The change does not result in an unauthorized alteration to plant systems, structures or components. L b. The change does not deviate from Technical Specification Acceptance Criteria nor requires a change to the Technical Specifications. ,/ c. The change will not result in equipment or systems being operated in configurations different than those described in the SAR or not permitted by Technical Specifications.

    • i_ *
  • FORM NC.NA-AP.ZZ-0059-1

,._ . 10CFR50.59 APPLICABILITY REVIEW FOR PROCEDURE REVISIONS Page _2_ of _2_ l.D. Number (Procedure Number):=S2=.'-"0""'P--'-=S-=-T""".S=J--'-000"-"-"=2-'-'(Q,._),__ ________ Revision: 2.. 3.0 The proposed procedure revision does not change the procedures as described in the SAR, because (check those that are true): L a. The change does not conflict with procedural steps or a system or component's operation as described in the SAR or cause any information in the SAR to be incorrect.

b. The change does not alter or delete the descriptions of the applicable procedure topics in UFSAR Section 13 . .L c. The change does not delete a procedure either listed or described in the SAR. 4.0 The proposed procedure revision does not constitute a "test or experiment not described in the SAR, " because (check those that are true): L a. The procedure, as changed, does not conflict with the descriptions of tests (such as surveillance tests) described in the UFSAR or Technical Specifications . b. The procedure, as changed, does not implement an experiment as defined in NAP-8. 5.0 Completion and Approval Preparer:

Based upon ALL of the above screening criteria being checked true, 10CFR50.59 does not apply to the procedure change. Peer Reviewer: Approval:}}

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