LR-N04-0299, Inservice Inspection Program Relief Requests S1-RR-04-V01 and V02

Inservice Inspection Program Relief Requests S1-RR-04-V01 and V02

ML042080244
Person / Time
Site:	Salem
Issue date:	07/09/2004
From:	Mannon S Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N04-0299, S1-RR-04-V01, S1-RR-04-V02
Download: ML042080244 (39)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 JUL 0 9 2004 0 PSEG LR-N04-0299 NuclearLLC U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS S1-RR-04-VOI and V02 SALEM GENERATING STATION UNIT 1 FACILITY OPERATING LICENSES NO. DPR-70 DOCKET NO. 50-272

References:

PSEG Letter LR-N96437, Dated December 26,1996, "Inservice Testing Program Relief Request Salem Generating Station Unit Nos. 1 and 2".

NRC Letter dated March 12,1999, "Relief Requests V-24 and V-25 Regarding Inservice Testing of Accumulator Check Valves at Salem Nuclear Generating Station, Units 1 and 2 (TAC NOS. M98259 and M98260)".

NRC Letter dated January 2, 2004, "Relief Requests S2-RR-03-V01 and S2-RR-03-V02 Regarding Testing of Accumulator Check Valves Salem Nuclear Generating Station Unit 2 (TAC NO. MC1 102)".

Pursuant to 10CFR50.55a(f)(5)(iii), PSEG Nuclear is submitting, in Attachment 1 to this letter, Inservice Testing (IST) Relief Requests S1-RR-04-VOI and V02 for NRC approval. These requests address Salem Unit 1 and are revisions to the engineering basis for the previously approved Relief Requests 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.

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 safety injection (SI)

Accumulator Outlet Check Valves I 1SJ55, 12SJ55, 13SJ55, 14SJ55, I 1SJ56, 12SJ56, 13SJ56 and, 14SJ56 could perform their safety function.

95-2168 REV. 7/99

Document Control Desk 2

JUL 0 9 2004 LR-N04-0299 On March 12, 1999 the NRC approved Relief Requests V-24 and V-25 that imposed an acceptance criterion of 27.0 seconds for alternate testing. In addition, relief requests S2-RR-03-V01 and S2-RR-03-V02 sought to increase the acceptance criteria from 27 to 28.1 seconds to reflect new system dynamics due to modifications of the safety injection (SI) Accumulator Isolation Valves 21 SJ54, 22SJ54, 23SJ54, 24SJ54 valves. These relief requests were approved in a letter dated January 2, 2004 (TAC No. MCI 102).

The same modifications for Salem Unit 1 Accumulator Isolation Valves 13SJ54 and 14SJ54 were made during 1 RI 6. Similar changes are planned for 11 SJ54 and 12SJ54 during 1 RI 7. The modification increases the valve stroke time to address a maintenance issue and results in an increase in the acceptance criteria from 27 to 28.1 seconds for the SJ55 and SJ56 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. The engineering calculations for Relief Requests Sl-RR-04-VOI and V02 change the acceptance criterion to 28.1 seconds due to physical plant changes, which altered the original testing acceptance criterion basis.

Accumulator Isolation Valve testing is performed during shutdown prior to entering refueling. Since, Accumulator Isolation Valves 13SJ54 and 14SJ54 have been modified, this relief request allows valves 13SJ55, 56 and 14SJ55, 56 to be tested to the 28.1 second acceptance criteria. Accumulator Isolation Valves 1 1SJ54 and 12SJ54 are being modified during 1 R17, valves 11SJ55, 56 and 12SJ55, 56 will be tested to the current 27 second acceptance criteria for 1 R17 and the 28.1 second acceptance criteria in subsequent refueling outages.

Attachment I to this letter contains the specific relief requests, S1-RR-04-VO0 and V02. Attachment 2 to this letter provides the General Approach Proposed For Full Open Testing Of Accumulator Check Valves. Attachment 3 to this letter is calculation S-1 -SJ-MDC-1 539 Rev 1, "Accumulator Pressure Decay Time During Discharge Test", which is used to determine the acceptance criteria associated with the Alternate Testing. This calculation has been revised based on the revised opening time of the SJ54 valves.

This relief request is applicable to PSEG Nuclear Salem Generating Station Unit 1.

PSEG Nuclear requests that the NRC approve this request by August 31, 2005 in order to support Salem Unit 1 refueling outage 1 R17.

Document Control Desk 3

UJUL 0 9 2004 LR-N04-0299 Should you have any questions regarding this request, please contact Mr. Michael Mosier at 856-339-5434.

Sincerely St en R. Mannvn Manager - Nuclear Safety and Licensing Attachments C:

Regional Administrator - NRC Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Collins, Project Manager-Salem U.S. Nuclear Regulatory Commission Mail Stop 08C2 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS SI-RR-04-VOI and V02 SALEM GENERATING STATION UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272

Salem Unit 1 Inservice Test Program VALVE RELIEF REQUEST -

Sl-RR-04-VO0 COMPONENTS:

11 SJ55, 12SJ55, 13SJ55 and, 14SJ55 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 Loss of Coolant Accident (LOCA) to provide a flow path for Safety Injection (SI) accumulator discharge to the Reactor Coolant System (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 that would compromise accumulator pressure boundary integrity.

CATEGORY:

AC CLASS:

I TEST REQUIREMENTS:

Open & Closed Position - Check valves shall be exercised at least once every 3 months in accordance with the requirements of OMa-1988, 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 over pressurization 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 I

Salem Unit 1 Inservice Test Program VALVE RELIEF REQUEST -

S1-RR-04-VOl 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.

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 refueling 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 of 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-1 -SJ-MDC-1 539 Rev. 1, "Accumulator Pressure Decay Time 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 2

Salem Unit 1 Inservice Test Program VALVE RELIEF REQUEST -

SI-RR-04-VO0 frequency specified in Unit I Technical Specification (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) 3

Salem Unit 1 Inservice Test Program VALVE RELIEF REQUEST -

S1-RR-04-V02 COMPONENTS:

11 SJ56, 12SJ56, 13SJ56 and, 14SJ56 FUNCTION:

These check valves are located in the discharge lines from the respective safety injection accumulators downstream of the branch connection from Residual Heat Removal System (RHR). The valves perform an active safety function in the open position. The valves must be capable of opening during, a large break Loss of Coolant Accident (LOCA) to provide a flow path for Safety Injection (SI) accumulator discharge to the Reactor Coolant System (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 OMa-1988, 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 over pressurization 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 1

Salem Unit 1 Inservice Test Program VALVE RELIEF REQUEST -

SI-RR-04-V02 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.

ALTERNATE TESTING:

These check valves shall be full stroke exercised to the open position during refueling 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-1-SJ-MDC-1539 Rev. 1, "Accumulator Pressure Decay Time 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 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.

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 2

Salem Unit 1 Inservice Test Program VALVE RELIEF REQUEST -

SI -RR-04-V02 frequency specified in Unit 1 Technical Specification (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) 3 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS Sl-RR-04-VOI and V02 SALEM GENERATING STATION UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 General Approach Proposed For Full Open Testing Of Accumulator Check Valves

General Approach Proposed For Full Open Testing Of Accumulator Check Valves PSEG procedure SI.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 11SJ55 and 11SJ56 -13 Accumulator Discharge to Cold Leg o 12SJ55 and 12SJ56 - 14 Accumulator Discharge to Cold Leg o 13SJ55 and 13SJ56 - 13 Accumulator Discharge to Cold Leg o 14SJ55 and 14SJ56 - 14 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 70 psig.

Flow is initiated by opening the tank motor operated valve (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 reactor coolant system (RCS). Velocities achieved should also be sufficient to fully stroke the valves, according to calculation.

The bases for the testing are captured in Calculation No. S-1 -SJ-MDC-1 539 Rev.1, Accumulator Pressure Decay Time 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 describes 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 Intemals 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.

o Failure of testing to result in corrective action for both SJ55 and 56.

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. The 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.

I

General Approach Proposed For Full Open Testing Of Accumulator Check Valves 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:

o Accumulator level elevation o Accumulator gas pressure o MOV loss factor o Check valve Delta P o Derivatives o Values at new time step 2

INSERVICE INSPECTION PROGRAM RELIEF REQUESTS SI-RR-04-VOI and V02 SALEM GENERATING STATION UNIT I FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Calculation S-1-SJ-MDC-1539 (Rev 1)

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FORM I CALC NO.: S-1-SJ-MDC-1539 CALCULATION COVER SHEET Page 1 of 26 REVISION: I CALC. TITLE:

Accumulator Pressure Decay Time DurIng Discharge Test

1. SHTS (CALC): l 26 l ATT I # SHTS: I 0/0 l

IDVI50.59 SHTS: l 4

1. TOTAL SHTS:

l 30 CHECK ONE:

E FINAL O INTERIM (Proposed Plant Change)

O FINAL (Future Confirmation Req'd)

E VOID SALEM OR HOPE CREEK:

0 Q-LIST E IMPORTANTTOSAFETY a NON-SAFETYRELATED HOPE CREEK ONLY:

OQ EQs OQsh OF OR 0 STATION PROCEDURES IMPACTED, IF SO CONTACT RELIABILITY ENGINEER O CDsIADs INCORPORATED (IF ANY):

DESCRIPTION OF CALCULATION REVISION (IF APPL.):

The calculation was revised because the opening stroke times of 13SJ54 and 14SJ54 valves will be Increased. The opening times of 11SJ54 and 12 SJ54 valves will remain the same. The change will be done under DCP's 80017350 and 80017351.

PURPOSE:

The purpose of this calculation Is to determine the acceptance criterion for the pressure decay time of the accumulator discharge test In support of the testing of SJ55 and SJ56 check valves.

CONCLUSIONS:

1. The acceptance criterion for the pressure decay time for the 11 and 12 loops that have SJ54 opening stroke time of 12.5 seconds Is 27 seconds.

2. The acceptance criterion for the pressure decay time for the 13 and 14 loops that have SJ54 opening stroke time of 22 seconds Is 28.1 seconds (reactor head Is off).

I Printed Name I Signature l

Date ORIGINATORICOMPANY NAME:

Vijay ChandrawPSEG May 13,2004 REVIEWERICOMPANY NAME:

b A~&eMtY PJ/A May 13,2004 VERIFIER/COMPANY NAME:

James Murphy May 13,2004 PSEG SUPERVISOR APPROVAL:

Paul Lindsay

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REFERENCE:

V. Chandra 1

ORIGINATORDATE REV:

Feb.25,2004 REVIEWERNERIFIERDATE Originally, the Rev. 0 of this calculation was done with the opening stroke time of valve SJ54 = 12.5 seconds. Therefore, Rev. 0 appiles for those loops that still have SJ54 valve opening stroke time of 12.5 seconds (11SJ54 and 12SJ54 valves). The actuators of valves 13SJ54 and 14SJ54 of Salem Unit 1 are being replaced with a longer opening stroke time. All the Salem Unit 2 SJ54 valves have been replaced by longer opening valves. The Salem UnIt 2 calculation 8-2-SJ-MDC-1394 was revised and the Rev. 2 Is the current calculation. This fact Is mentioned here because the details of analytical method Is presented In the Unit 2 calculation and have not been repeated here. Since the Unit I valves have not boon replaced yet, there exact opening time Is not available. For unit 2, the largest opening stroke time for SJ543 valves Is 21.9 seconds. Therefore, 22 seconds opening stroke time will be used for the replacement valves of the unit 1. Please note that the loops that still have the original valves (opening stroke time 12.5 seconds) are unaffected by this revision to the calculation.

This calculation has two sets of results:

1. The original acceptance criterion of 27 seconds [Ref. 8] applies to those loops that have SJ54 stroke time = 12.5 seconds.

2.

Since the exact stroke time of valves 13SJ54 and 14SJ54 Is not known at this time, a reasonable value for the stroke time was chosen to be 22 sec. As shown In the results section, for the stroke time of 22 seconds for Unit 1, the pressure decay time for units I Is the same as the value calculated for Unit 2 In Ref. 11]. According to Ref [8], the pressure decay acceptance criterion for Units I and 2 Is same. Therefore for the Increased SJ54 valve stroke time, following the spirit of Ref

[8], the Unit I pressure decay time criterion will be kept equal to pressure decay time criterion for Unit 2 pressure decay criterion calculated In Ref. [8].

The following note was added after the Installatlon of the DCP's:

After (he replacement of actuators of`13SJ54 and 14SJ54 valves, the opening stroke times of these valves were measured.

The opening stroke time of 13SJ54 valve Is 20.5 sac [Ref. notification 201888101 The opening stroke time of 145J54 valve Is 21.3 seac [Ref. notification 20188884]

Therefore, the original estimate of 22 second was quite good and the calculation need not be redone.

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S DATA VVOF/O.,.05,.1,.2,.3,.4,.5,.6,.7,.8,.9,1./

DATA CVCV/O., 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 COr4PU7C* PROCYi~wY LI ST/AJ (

G=32.174 RHO=1.94 g

CT6W

-(CFrIE)

IS O k AREA=0.394 DT=0.01 5

-k ETM PPRES=14.7*144.

SJ5L STR1E TlW C INITIAL CONDITIONS l

Ser-TIME=0.1 g5 eC NSTEP=-1 VNAZ=408.3 VNA--VNAZ PAZ=84.7*144.

PA=PAZ Q=.001 VWP=758.

WRITE(*, 101) 101 FORMAT(T19'TIME',

T28'ACCUMULATOR PRESSURE FLOW RATE')

103 FORMAT(T19'(SEC.)',T28' (PSIG)

(GPM)

,//)

WRITE(*,103) 31 NSTEP=NSTEP+1 TIME=TIME+DT C CALCULATE ACCUMULATOR LEVEL ELEVATION VWA-13 50. -VNA ZA=(VWA+7801.2) /95.76 C CALCULATE PRESSURIZER LEVEL ELEVATION ZP=(VWP+4092.3)/38.34 CALCULATE ACCUMULATOR GAS PRESSURE PA=PAZ*(VNAZ/VNA)**GAM C CALCULATE SJ54 LOSS FACTOR VOT1=12.5 GVKZ=.15 IF(TIME.LT. VOTI) 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-PPRES-RHO*G*ZP-34.88*Q*ABS(Q)

-0.5*GVK*1.94*Q*ABS(Q)/AREA**2 -

DPCHK)/534.8 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(*,102) TIME,+(PA/144.-14.7),

- # Q*7.48*60.

ELSE IF(MOD((NSTEP+10),100)

.EQ.

0)WRITE(*,102) TIME,+(PA/144.-14.7),

Q*7.48*60.

ENDIF

OUTSTANDING CHANGES MUST BE ATTACHED FOR WORKING COPY 20040706 102 FORMAT(F23.3,8F17.2)

S Si-MDC-1539 p 2:o C UPDATE THE OLD VARIABLES g-4

i VNA-VVNA REfACt fir" Isom vwp=VVWP IF(TIME.GT. 100.) STOP 5 J 5 Tg6mEE T1MU GO TO 31 1

END SUBROUTINE INTER(X,Y,N,XX,YY)

('2' 5 SeC.

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 2 101 Y=YY(J-1)+(YY(J)-YY(J-1))*(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',G1O.4,5X,20Gl0.4)

RETURN END C:\\SALEM\\REACTOR\\ECCS>

m

OUTSTANDING CHANGES MUST BE ATTACHED FOR WORKING COPY 20040706ENSION WVOF(12),CVCV(12)

OPEN(l,FILE-'slAcchon free.out', STATUS-told')

DATA VVOF/O.,.05,.1,.2,.3,.4,.5,.6,.7,.B,.9,1./

DATA CVCV/0., 0.0194, 0.055, 0.1, 0.146, 0.204,

-I-if 0.277,0.3536,0.4613,0.6086,0.767,1./

C PARAMETERS GXsM-1.3 C cmpv (332.174 RHO-1.94~C AREA=0.394 REACT DT-0.01 PPRES=14.7*144.

C INITIAL CONDITIONS TIME-0.1 2

XSTEPu-1 VNAZ=408.3ICHcr VNA-VNAZ PAZ-E4.7*144.

PAt2PAZ Q-.001 VWP-758.

WRITE(1,101) 101 FORMAT(T19'TIME',

T28'ACCUMULATOR PRESSURE FLOW RATE')

103 FORMAT(T19'(SEC.)IT28'

{PSIG)

(GPM)

',//)

WRITE(1,103) 31 NSTEPmNSTEP+1 TIME-TIME+DT C

CALCULATE ACCUMULATOR LEVEL ELEVATION VWAal350.-VNA ZA=(VWA+7801.2)/95.76 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 VOT1l22.

GVKZ=.15 IF(TIME.LT.

VOT1)

THEN VOF-TIME/VOT1 CALL INTER(VOF,CVND,12,VWOF,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) SINPHInO.9532 DPCHlK=2.*8.98*RHO*VEL*VEL*(1.-SINPHI)

C CALCULATE DERIVATIVES DQDT=(PA+RHO*G*ZA-PPRES-RUIO*G*ZP-34.88*Q*ABS(Q) 0.5*GVK*1.94*Q*ABS(O)/AREA**2 DPCHK)/534.B 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 102 FORMAT(F23.3,8F17.2)

C UPDATE THE OLD VARIABLES Q-QQ VNA-VVNA VWP=VVWP IP(TIME.GT. 40.) STOP P2 1 J-MD C-I S.s, Pevp I Tr PRoCUA-m Lzi j [I nE~

I s O 74 s-uT1f7; TmE

2 2gec vALvc-: I-FR cC

OUTSTANDING CHANGES MUST BE ATTACHED FOR WORKING COPY 20040706

'IV SUBROUTINE INTER(X,Y,N,XX,YY)

DIMENSION XX(N),YY(N)

IF(X.LT. XX(1W

.OR. X.GT. XX(N)) GO TO 3 DO 2 J=2,N IP(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-xxgJ-i))/

L Ad n

1 (XX(J)-XX(J-1))

935>

RETURN 2 CONTINUE

-2 2

i 3 WRITE(6,1) X,(XX(I),II1,N) 1 FORMAT(

BEYOND RANGE',G10.4,5X,2DG10.4)

RETURN END P 22 b I geii TE -TIEn

OUTSTANDING CHANGES MUST BE ATTACHED FOR WORKING COPY 20040706 NC.DE-AP.ZZ.0002(Q)

FORM 2 CALCULATION CONTINUATION SHEET SHEET: 23 CALC. NO.: S-1-SJ-MDC-1539

REFERENCE:

V. Chandra I

ORIGINATOR,DATE REV:

Feb. 25,2004 REVIEWERNERIFIER,DATE

4.

RESULTS Table 4.1 shows the time histories of the accumulator pressure and the discharge flow rate when the SJ54 valve opening stroke Utme Is 12.5 seconds. As suggested by Ref. [8], the acceptance criterion for the pressure decay time was set to 27 seconds.

This value was obtained by subtracting 1.5 seconds from the pressure decay time obtained for 6o degree maximum open angle case.

Table 4.2 shows the accumulator pressure and discharge flow rate time histories for the situation when the reactor head Is on, check valve Is free, and the SJ54 valve stroke time Is 22 sec. The 22 second stroke time was selected to reasonable bound the data collected for Unit 2. The pressure decay time for this situation for Unit I1s nearly the same as It was calculated In Ref. (I]

for Unit 2. NRC approved the acceptance criterion for the pressure decay tme for Unit 2 on Jan 2,2004 through reief requests S2-RR.03-VO1 and S2-RR-03-V02 (TAO No. MCI 102). Following the spirit of Ref. [8], the Unit I pressure decay time criterion will be made equal to Unit 1 pressure decay time criterion of 28.1 sec. Please note that the pressure decay time Is a relatively weak function of SJ54 stroke time. It Is emphasized, that In order to provide some flexibility In data collection, the actual acceptance criterion needs to be slightly greater than the calculated value for the free check valve case.

The following note was added after the Installation of the DCP's After the replacement of actuators ofI 3SJ54 and 14SJ54 valves, the opening stroke times of these valves were measured.

The opening stroke time of 13SJ54 valve Is 20.5 sec IRef. notification 201888101 The opening stroke time of 14SJ54 valve Is 21.3 sec IRef. notification 20188884]

Therefore, the original estimate of 22 second was quite good and the calculation need not be redone.

5. CONCLUSION As suggested by Ref. [81, the acceptance criterion for pressure decay time should be made equal to 27 seconds for the situation when the SJ54 opening stroke time Is 12.5 seconds. This criterion applies to loops 11 and 12.

Following the rationale provided In Ref [1], the Unit I pressure decay time acceptance criterion for 13 and 14 loops will be set equal to 28.1 seconds.

This calculation revision is In support of DCPs 80017350 and 80017351. Therefore, a 50.59 Safety Evaluation Is not required.

Nuciesr Common RevisIon 9 Nuclear Common Revislon 9

OUTSTANDING CHANGES MUST BE 20040706 7tL E 4.

, acchon ATTACHED FOR WORKING COPY ACcUMULAroTve PRESSURE AA4 flJSjij FIO(A) RhTC 7/rji fIJS 75 1-r-S TIME ACCUMULATOR PRESSURE (SEC.)

(PSIG)

.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 70.00 69.99 69.97 69.95 69.92 69.88 69.84 69.78 69.72 69.64 69.56 69.46 69.36 69.25 69.13 69.00 68.87 68.73 68.58 68.43 66.70 64.66 62.48 60.25 58.05 55.94 53.93 52.03 50.25 48.58 47.02 45.56 44.20 42.92 41.73 40.60 39.55 38.55 37.61 36.73 35.89 35.11 34.37 33.67 33.02 32.40 31.81 31.26 30.74 30.25 29.79 29.35 28.94 28.55 28.18 27.83 27.50 27.19 26.90 26.62 26.36 FLOW RATE (GPM)

.45 242.54 356.39 468.61 579.16 688.20 824.00 993.71 1168.00 1341.52 1512.76 1681.01 1841.72 1979.86 2102.75 2216.12 2323.05 2425.24 2523.62 2618.72 3426.55 3977.46 4357.61 4597.21 4707.43 4733.72 4717.87 4669.58 4592.14 4500.25 4398.37 4284.26 4170.59 4060.25 3953.51 3850.18 3750.05 3652.87 3558.44 3460.78 3353.02 3243.26 3134.53 3027.76 2923.22 2820.90 2720.75 2622.67 2526.59 2432.44 2340.14 2249.66 2160.95 2074.00 1988.81 1905.40 1823.80 1744.07 1666.29 1590.57 1517.02

.sl-sj-mbc-j5309lp-.b CadX-JALVE IS Si Ts S2 DOFF Tl\\AF-= 12-salses.

men, -

OUTSTANDING CHANGES MUST BE ATTACHED FOR WORKING COPY 25z 20040706 (SEC.)

(PSIG)

(GPM) s-i-SJ-I^ts~l539, ar.

0.110 70.00

.0.45 0.210 69.99 144.06 0.310 69.98 212.26 TALE 4 2.

0.410 69.97 280.02 0.510 69.95 347.25 AcmLA6 0.610 69.93 413.89 L

Cf Er--

0.710 69.90 479.92 ftit> D;.Cfln lir FLOIWRJftJ 0.810 69.87 545.36 T-IFE WT6aN -sS 0.910 69.84 610.22 1.010 69.80 674.55 247 hSf D IS 09 1.110 69.76 738.40 1.710 69.71 8293640

-ka 22 AVC iss.

1.310 69.66 935.34 1.410 69.60 1043.46

~~~L1ETIME.

1.510 69.53 1151.27 8

1.610 69.46 1258.18 1.710 69.38 2364.00 1.810 69.30 21468.58 1.910 69.21 1571.84 2.010 69.12 1673.67 3.010 67.90 2406.15 4.010 66.40 2915.09 5.010 64.69 3329.83 16.010 62.85 3651.47 7.010 60.96 3878.40 8.010 59.04 4066.45 9.010 57.15 4186.74 10.010 55.29 4273.95 11.010 53.49 4312.81 12.010 51.76 4313.98 13.010 50.11 4287.20 14.010 48.55 4247.92 15.010 47.07 4198.90 16.010 45.66 4138.37 17.010 44.34 4071.83 18.010 43.08 3996.36 19.010 41.89 3915.35 20.010 40.77 3830.78 21.010 39.71 3746.64 22.010 38.71

.3661.49 23.010 37.77 3572.18 24.010 36.87 3477.56

• 25.010 36.03 3371.12

• 26.010 35.23 3261.53 27.011 34.49 3152.57 28.011 33.79 3045.47 29.011 33.12 2940.55 30.011 32.50 2837.87 31.011 31.91 2737.36 32.011 31.35 2638.94 33.010 30.83 2542.54 34.010 30.33 2448.06 35.010 29.87 2355.46 36.010 29.43 2264.68 37.010 29.01 2175.67 38.010 28.61 2088.43 39.009 28.24 2002.95 40.009 27.89 1919.24 m