ML17264A690

Rev 0 to Inservice Testing Program

ML17264A690
Person / Time
Site:	Ginna
Issue date:	02/23/1996
From:	Muller K ROCHESTER GAS & ELECTRIC CORP.
To:
References
PROC-960223, NUDOCS 9610180150
Download: ML17264A690 (11)

Text

CATEGORY j.

REGULAT INFORMATION DISTRIBUTIONOZSTEM (RIDE)

ACCUS(ION NBR:9610180150 DOC.DATE: 96/02/23 NOTARIZED: NO DOCKET FA(:IL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MULLER,K.A.

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Rev 0 to "Inservice Testing Program."

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL TITLE: OR Submittal: General Distribution SIZE:

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

A'5000244Ti RECIPIENT ID CODE/NAME PD1-1 LA VISSINGFG.

INTERNA CENTER 1

NRR/SR'/HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1

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E NOTE TO ALL MRIDSN RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 12 ENCL 11'

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FROM:

Cnty, Guy Kissing, NRC (301) 415-2102 Mark I'laherty, RAFF.

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~g gpss I am Earing you the followinginforination:

One-Itne dtagrams ofthe SafutyInicctron gJ) and Conrarnnrenthpnry(CS) sv~Ccrns

~Hdch rhombi rhe sirblocth&t.s (8o; and b'28), Thmc valves arc required to be open during power operation since thc PSPAS signai withrespect to RCS pressure can actuate the Si pumps prior to rcachiig the shtttoft'ead ofthc SI puaps (1700 iisig veiiuis 14tln psig'). Thercforc, nutintaining thc MOVs open ensures that the SI pimps are not dcadltcadcd during the time frame ittakes fnrthe R('.S prvssui e to drop frotn 1700 psig to 1400 paid. The valve are abri ieiiilhed io b>> capable ofclosing during use ofthe SI system for high-liead i ech imitation The ii:, closure ofthe MOVs prevents the addition of liighlp iadhm:live siimliiluirito the RNST. Per Technical Spwifications LCO '3.5,2 and 3 S '1, at leal oiie SI iiiunniust be operable above 200 9.

(2)

Cuop ofthe Ginna Station IST Pro@am MrhRespect to MOV~ 8PCf roid'8>6',

As shown on the one-line diagrams, hdOVs 896A and 8'rovide suction to the SI end 'CS systems.

Per Cold Shutdown 1ustification CS. I",Nil;8only cxccrciscs these valves.

during cold shutdown since closure of the MVVs renders both Sl and CB innpersh1e, This is very similar to thc N7 and 898 valves.

{3)

(,'os ofthe MCSZR 1PhichAp~ovcd th>> Carrant ICT Pnigncm Fur Ciilma, There is only a single sentence v hich apilrove% CS 17.

Based on tLie above, llieie is iu ~~enfant for only nerclslng 897 and 898 at cold shutdov e, The next Ieilulleiltali.i>ftheie valves is 11(11/96 (incJudes 25",o extension). Ifthe alternate testing f'reyiency ic not luovided by Ibis date, R68rE would be forced to enter LCO 3.0.3 to perfortnian AShK tequirad test or shutdown Ginna.

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913814 iS2182 P. 83 l

S4O INSERYICE TESTING

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XNSERVXCE 'XXST1NG PROGRAM Effective Date:

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913814152182 P.84 INSERV(CE TESTlNG PROGRAM Revision 0 Page 19'of 87 CS - 15a Valves 852A a 8 are Residual Heat Removal (RHR) discharge motor operated valves to the roactor vessel.

Those valves open to provide safety injection flow to

%he reactor vs~eel.

These valves should not bc exercised during no'rmal power operation as this would reduce the system to single-valve-protection between the RCS and RHR system and could result in an intersystem LOCA outside of cohtainmont.

Testing will bo performed durhsg auld shutdown.

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16:

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<<~ ceo CS - 17:

Valves 896 A 0 B are Refueling Rater Storage Tank (RWS outlet. isolation valves.

Exercising these valves during power operation is impractical.

Pai3.ure of one of these valves in the clvsed position during power operation would render both containment spray and safety in)ection trains inoperable which would require shutting down the reactors Testing will be performed during cold shutdown.

CS - 18 CS 19:

Valve 702 provides a flow path from the Residual Heat Removal (RHR) discharge line to the letdown headei juror pressure relief, Exercising this check valve durj.ng power operation would require isolating letdown which could result in loss of pressurizer level control

and, cause a reactor trip.

Testing will be performed during cold shutdown.

Valves 1819A thru G are containment pressure tv.ansmitter isolation valves.

These normally open valves are containment isolation valves.

Rxazcising thesa valves during power operation can disable associated pressure channels and cause a

plant trip function to ;be inoperable.

Testing will be performed during cold shutdown.

CS - 20:

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April 55, 1991

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gIS11 Certified By

-Z AQefZ lir. Robert c, liacredy, Yice President pinna Nuclear Production PV5LI I Repeater eas $ Clectric COrporation 89 Kast Avenue Rochester, New York 1%Say

Dear Nr,

5(ccredyi swami r.. x. ewe wcl.se pouts pue Iascavlcs TuTue (IsTl peeaw fOR P(95PS ND YALYES, NltI 1999 THIRD 10 VKAR IKKRYAL (TAC NO. 73380) ly letter dated Hay 23, 1989, and suhsayent letters dated October, 27, 3989; February l5, March la, Anril 6 ~ April lie 1990>

and January Rt, IMI ROCheater Oas and DectHc Corporation.subiaitted to the NRC'tha IST Pvagraa ed uMitional inforiation for the 1ST Pmiai, thi& ID-year interval, at the 0, K. Nnna Nuclear pmcr Plant.

The MAC has reviewed and evaluated the pro9raa and additional infor¹atien provided.

The enclosed safety Kvaluation (sE) uas prepared by the Nc to'provide the results of the staff reeien.'he COde of Federal Re9ulations, Ib CFR 'N,55a(g).

~vires cabin Class I, 2, and 3 pu¹ps and valves ia uater~led auclear.Nicer facilities to eieet the inservtce testing raqairweats stated ih taa As¹K Boiled and pressure Yassel code (code) section Rl> specifically sahsectfon Lo. 'Ia-servite Testing of Puiaps in %ac'fear poser plants~

and SuhaeCtion Iltvg "Inservice Testiny of Yalves

<n lluclear Peer Planta.'acil fac111>

1s teqelred to establish a pro9raa for the <nservice testia9 of ~s and valves 1555th fa opd'aied evarf ten years to ¹aot the tequircmais ia the latest agewH e4100a and addm4 to Section 0 of the Code.

The arogran is suh¹ittad to the M for rivfN Sed aPPreval Of the relief reqaaata.

The raVtau aaQila Verifying tlat the PrONra¹ iS based an the applicable code edition aad addenda, varigiaI taat all ~s and ve'ives included in the program ara subfaete4 to iata petio45c sessions +4 verifyin9 tsee acceptability of the requests far ri 5 free ~ reqe5~ts of Subsections IlIP and IN.

The IST proarai ai54 ad41tional fnfor¹atioa addressed in this evalwt1ee ceVers the interval fro¹ January I 1990 throu9h Oeceetiel 31 ~ I%8 404 suliersedes all preV5NS IST PPOgraa saba it4ls.

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TAC 73380

913814152182 P. 86 testing rendu)rements apply only to component testing ().e.~

Pumps and valves) and are not intended to provide the basis to change the 1)censee's current Technical Specifications for systel test requireients.

Section 8 of this report presents the Rochester Sas and E>ect&c Corporation bases for requesting relief frol the Section Nl requirements for the Robert E. Gonna Nuclear Power plant pulp testing prograa and the rev)ewer's evaluat)ons and conclusions regarding these requests.

Sim)lai information )s presented in Section 3 for the valve testing program.

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Justi Beat)ons for exercising Category A, B, and C valves during cold shutdowns and refueling autages instead of quarterly dur)ng power operations were reviewed and found acceptable except as noted in Appendix A.

Inconsistencies and omissions in the licensee's IST program noted du~ing the COurSe Of thiS reView are liSted in Appends@

A.

The liCensee Sheuld resolve these items in accordance with the evaluations, conclusions, and guidelines presented in thfs report,

TO 913814152182 P. 87

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r April lS, 1991 The HRC staff with technical assistance froid F656 Idaho Inc. {E616), has reviewed and evaluated the IST Progral and requests for relief subaftted for the Robert E. Gfnna Nuclear Power plant.

The staff adopts the evaluatfons

and, conclusions contained in the Technical Evaluation Repor t (TER) prepared by KCLC.

The enclosed SK incorporates the TER which is attached to this SK.

Ne are recasaendfng that relfef be granted fry the testfng rtaufresents whfch we have deter3afned would be fipractical to perform, where coap1(ance would result in a hardship without a c~ensatfng increase in safety and where the proposed alternative testing provides an acceptable level of quality and safety.

Me. have determined that the IST Program relief requests are acceptable for fipleiantatfon provided the items (dentfffed fn Appendix A of the TER (Attachaent 2 Of the Enclosure) are addressed within the time fraoe specified in the enclosed SE.

The licensee is required to comply with the IST Program defined in the above referenced letters where relief has been granted in the enclosed SE.

EST program changes such es additional relief requests or changes to approved relief requests should be submfttcd for staff review but shou1d not be imp'leaented Prior to revfew and approval by the NRC.

New or revised relief requests aeetfng the posftfons in Generic letter (GL) 89-04 (6L 89-04 Enclosure 1), should be subinftted to the NRC staff but can be implemented provided the guidance in 6L SS44, Section 6, is followed.

1ST Program changes that involve additions or delations of consonants from the IST Program should be provided to the NRC.

This submittal completes the technical review performed by the NRC staff under TAC Number 73380.

Sincerely,

Enclosure:

As Stated cc wfenclosur'e:

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