ML20043G819

Forwards Rev 5A to Pump Valve Inservice Testing Plan,For Review.Rev Provides Addl Info & Clarification for Requests for Relief Noted in Rev 5

ML20043G819
Person / Time
Site:	River Bend
Issue date:	06/12/1990
From:	Odell W GULF STATES UTILITIES CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RBG-33012, NUDOCS 9006210163
Download: ML20043G819 (14)

Text

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GULF STATES UTILETZES COMPANY .

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June 12,1990 RBG- 33012 File Nos. G9.5, GL 2.5.2. 6, h

G12.5.2.7 U. S. Nuclear Regulatory Ccnndssion Document Control Desk Washington, D.C. 20555 Genticment River Bend Station - Unit 1 Docket No. 50-458 Gulf States Utilities Campany (GSU) is providing Pavision SA of the River Bend Station Pump Valve Inservice Testing Plan for your review. This revision provides additional infornation and  !

clarification for the Requests for Relief provided in Revision 5.

As discussed in a telephone conference conducted on May 3, 1990  !

between your Ms. Abbate and Messrs. Paulson and Shaw and GSU's  !

Messrs. Dietrich, Kugler and Walling GSU is subnitting revisions to the following Pump and Valve Requests for Relief (PRR and VRR, respo:tively):

PRR No. 3 VRR No. 17 VRR No. 19 VRR No. 20 VRR No. 22 VRR No. 27  !

VRR No. 33 l VRR No. 58 l Should you have any questions, please contact Mr. L. L. Dietrich j of my staff at (504) 381-4866.

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W.11. Odell i Manager-Oversight River Bend Nuclear Group

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9 N .* cot; U. S. Nuclear Regulatory Cannission Region IV s 611 Ryan Plaza Drive,; Suite 1000 Arlington, TX 76011.

Senior Resident Inspector.

- Post Office Box 1051 St. Francisville, LA. 70775

- Mr. W.' A. Paulson j '

- Nuclear Regulatory Cattnission One White Flint North 6 - 11555 Rockville Pike

, - Rockville, MD 20952

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TUNCTION, To pump sodium pentaborate solution into the reactor vessel TEST REQUIREMENTS: per IWP-3400(a), an inservice test shall be run on each pump nmiinally every three months during nomal plant operation.

PASIS TVR RELIEF: The operability test of these pumps during nomal operation will require both punps to be made inoperable during the '

testing since they have a cmmon suction line. Also, running the punps for the code required 5 minutes prior to data collection at their rated 41 gal. per minute would not allow use of a portable container (ie 55 gal. drum) . Due to the refilling and measurennot of the test tank the necessity of flushing of the sodium pentaborate solution frcm the suction lines which requires the chemistry department to perfom 5A sampling prior to discharge to the suppression pool, the time required to perform testing of both pumps could easily exceed the short tire (8 hr.) allowed for the lintiting condition for operation. This rystem would also require manual realignment of valves insiSe containment should anergency conditions require system operation during testing. Containment may not be accessible during an accident for this regttired manual valve realignment.

ALTEINATE TESTING: The pumps will be tested during cold shutdown if not perfomed within the previous 92 days.

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VALVE RRQUEST FOR RELIFF NO.19 (Cbld Shutdown Justification) f q -. COMPONENT IUJCTION CLASS CATEGORY

' IE12*MOF008 Reactor coolant pressure 1 A IE12*McNhl09 boundary isolation and r dryw11 isolation for MIR

, shutdown cooling suction

~1E12*MOVF042A,B,C Reactor coolant pressure 1 A-

boundary isolation, containment isolation and

{ LPCI injection

[ 1El2*M WF053A,B RHR chutdoan cooling return 2 A E to feedwater line containnent and press.tro isolation g

1E12*FOVF023 Reactor coolant pressure 1 A boundary isolation, containment isolation and MIR to RCIC head spray 1E21*MWF005 Reactor coolant pressure 1 A boundary isolation, containment isolation and LPCS injection 1E22*MOVF004 HPCS injection, containment 1 A E6 isolation, and reactor coolant SA' s pressure boundary TEST REOUIREMEN_T: Per IW-3411, Category A and B valves shall be exercised at least once every three months.

_ BASIS FOR 7 RELIEh The exercise testing of the valves during normal ' operation could subject sme of the system low pressurd* piping to .

greater than design pressure and tmperature,- assuming an 5A upstream check valve (if alplicable) and leaks. Valves

____ 1E12*bDVF008 and 9 are interlocked w.ith reactor pressure.

_ - ALTERIATE TESTING: An exercise test for each valve during cold shutdown if not performed within the previous 92 days as allowed by IW-3412

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VAINE RHOURST FOR RRLUF NO. 20 COMPCNFNI' FUNCJT ON CIASS CATmORY lE12*VF050A,B High pressure isolation check 2 C for RHR shutdown cooling return line to reactor feedwater line TEST RECUIREMENT: Per IW-3521, check valves shall be exercised at least once every three months.

BASIS 10R RELIFF: The RHR system head is inadequate to open the valves against }

feedwater operating pressure. The valves are opened when the  ;

RHR system is placed into the shutdown cooling (SDC) nYxle during plant shutdowns. To verify the valves close during plant shutdowns would require the shutdown cooling loop of  !

the RHR systs to be mde inoperable. I Technical Specification 3.4.9.2 requires two (2) loops of SDC  ;

to be available or at least one alternate available for wch inoperable loop. Because of decay heat, it requires at least 30 days for an alternate method such as 16CU or fuel pool cooling to be able to handle the existing heat loads .for SDC. 3 During refueling outages, this requirment is reduced to cae loop of SDC when the technical specification does permit one  !

loop to be made inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for testing. 5A Hcuever, because of the difficulty and- tim required in performing this test using hoses connected for drain down of ,

tbo column of water beneath the valve in order to verify disk c1ceure, operations personnel will ,ng pennit this testing as.

a caervative measure.

Thts test cannot be accmplished with- the loop in SDC. In addition, a significant volume of contaminated water is released to radwaste. Finally, since the- drain hub is located in a high radiation area for the VF050A valve and the drain valve connections are also located in high radiation areas and contamination zones during outages as a result of  ;

SDC, significant radiation exposure can be received. '

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VAINE RP(1FBP POR RF2JEF 10. 22 COMPONENT FUNCTICN CLASS CATEGORY 1821*RVF041A, Main steam safety and relief 1 B,C B,C,D,P,G,L valves and. automatic.

1821*RVFG47A depressurization system relief

.B,C,D,F,G,L valves 1B21*RVF051B C,D,G l TEST RECdIRIM Nr: Per IWV-3411, Category A and B valves shall be exercired at least once overy three nonths.

BASIS FOR. .

The exercise testing of the valves every three nonths during:

RELIEP: I operation would interrupt plant operation by suddenly J

-reducing reactor pressure and adding heat to the suppression pool. Technical Specification 4.5.1.e.2 requires testing the valves which are part of ADS only once per 18 months.

Safety relief valves (SRVs) have a history of leakage past the seat during operations which causes the temperature of the su;pression pool to rise. As there are sixteen (16) ',

SRVs, this heating of the suppression pool can be significant should there by any ,severt eakers. l The technical specification 3.6.3.1 limit of 957 in the suppression . pool j during operations is a legitimate concern especially in the l sunmer months when there .is little cooling water delta T j margin available. Testing of these valves increases the- ,

likelihood of trapping contaminants on the seat thus 1' pennitting steam leakage and further steam cutting of the seat to occur. Often, a nonleaking valve will begin to leak after . exercising. Such conditions may require shutdown of- 5A the reactor as a result of exacerbating the, situation by testing.

Also, in order to address the NRC concern described in j NUREG-0737, II.K.3.16 and NUREG-0626, Appendix B and F, challenges to SRVs failing to close during testing and consequently leading to a sman-break IOCA can be returned by [

reducing the frequency of testirg.

l Since these are main steam safety relief valves, they will be I functional tested in accordance with 'Ibchnical . Specification l 4.5.1.e.2.

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U VALVE RRQUEST FOR NF2JPF NO. 27 l (Cold shutdown Jtstification)-

COMTOENP _q1CN CIASS CATEGORY 1SWP*V172 Stardby service water supply 3 C header to normal service water supply header isolation check TEST REOUIREMENT: Per IWV-3521, check valves shall be exercised at least Once every three months.

RASIS FOR

.,REIJEF: The exercise testing of the V172 valve during normal operation could challenge plant safety syspems. Standby service water systen is approximately 20'T cooler than normal service water when started. ~This is a rapid 5A increase in the flVAC delta T's of unit coolers supplied by service water. In particular, llIVR*tC8 (main steam tunnel) could exceed its delta T setpoint causing an-isolation of the MSIVs and a reactor scram. Therefore, a test of #V172 in the open direction is considered hazardous to plant operation / reliability.

ALTFJNATE TESTING: An open exercise test. for this valvo during cold shutdown.

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VALVE RHQUEST FOR RPLTPF NO. 33 4 FUNCTICN . CLASS CATfm RY

_004P%7NT

. (1 ea. for each-of' 145 lICU's):

-IC11*V114 _ Outlet scram check valve 2 C 4

1C11*V115 Scram accunulator charging 2 -C water check valve SA

j. IC11*V138 Scram accumulator cooling 2 -C'  !

water check valve l TIC 11*A0V126 Inlet scram valve 2 B

'1C11*A0V127 Outlet scram valve 2 B O TEST .!

REOUIRFMENT: Per IWV-3411 and IWV-3521, . Category A and B valves and '

check valves shall be exercised at least. once'..every -]

three months. Per IhV-3413 (b), the stroke of tine of -

"all power operated valves shall.be' measured..."

1.

. BASIS FOR RELIEP: Exercise and stroke time testing of the valves would

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a require - scranming the associated control rod during power operation. The stroke tine testing of the -scram valves is adequately perfonned by the CRD scram tine, d

, and rod notion would be inhibited hv failure of the valves to seat. This confirms valve V138 closes. SA Improper operation of any of the other valves will also 7 adversely affect the: CRD scram tine. A surveillance-

. test confirms

• hat the CRD: scram accumulators hold pressure ~ for a minimum period . ' of . tine. This also confirms' that V115 closes, i

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., o . . - ,,:2 AT1rEINATE TPSTING: Scram testing of-the associated control rod drive as required by Technical- Specifications- 4.1.3.2.c of at.

least once per 120 days will prove proper ~ operation - of the subject valves. Acceptable scram tinr:s will be the

. acceptance criteria' for the subject . valves -for exercising the stroke timing. . Valve V138 will be tested on the same frequency as the air operated scram valves.

Valve V115 is confirmed . closed during- the= HCU accumulator pressure decay test performed per Technical SA Specification 4.1.3.3.b every refueling.. t This ' alternate. testing is in conformance.with NRC Generic Letter 89-04, Attachment 1, Item 7,_ for alternate testing of individual CRD valves in BWRs.

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3 VALVE RIKKEST FOR RELIEP NO. 58 COMPCNFNP FUNCTION CIASS CATETORY -

ISWP*V326 Standby service water supply 3 C header loop A isolation check with normal service water ISNP*V327 Standby service' water supply 3 C header loop B isolation check with nonnal service water t

ISWP*MOV57A,B StaMby service water supply 3 B header isolation with nonnal

(' service water  !

TEST REOUIRIM WP: Per IWV-3411 and IWV-3521, Category A and B valves and I

-check valves shall be exercised at least once every three nonths.

. I BASIS FOR RELIEP: Check valves V326 and V327 are verified open by normal plant operations. In order to test these valves closed it is necessary to secure the normal service water locp resulting in the shutdown of e sential equipnm t for the safe operation of the plant such as instrument air. As  !

a minimum, this requires supplying a temporary backup instrument air canpressor. In most shutdowns 'it would also be necessary to supply a temporary neans of cooling the condensate punp which would be in service for RPV level control.

In'a short shutdown > these activities' would be too 5A expensive and difficult to set- up. In a refueling outage, these items are prearranged and can be carried out without risk to the plant or public.

Closing bOV57A/B without operating standby service water in advance would cause an automatic initiation (ESP) of i standby service water. Operating Division ~I . standby service water at power is ~likely to cause an MSIV isolation on high HVAC delta T due to the sudden inrush 1 of cold water to the unit cooler for the main steam tunnel from the staMby cooling tower.

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ALTEINATE' An exercise test' for each valve during every_ refueling-.

TESTINGr.

outage, I

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