ML20216B906

Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Limerick 1 & 2, Final Informal Rept

ML20216B906
Person / Time
Site:	Limerick
Issue date:	05/31/1987
From:	Udy A EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML20216B816	List: ML20216B812 ML20216B906
References
CON-FIN-D-6001, CON-FIN-D-6002 EGG-NTA-7599, GL-83-28, TAC-56257, NUDOCS 8706300177
Download: ML20216B906 (17)

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q n j 1 a .] I j i i i -DISCLAIMER ' This book was prepared as an account of work sponsored by an agency of the United States Government. Neither the, United States Government not any agency thereof, nor any of their employees, makes any warranty, express or implied, or asscmes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product or process disclosed, or represents that its use would .not infringe privately owned nghts. References herein to any specific commercial - product, process, or service by trade name, trademark, manufacturer, or otharwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring. by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessanly state or reflect those of the United States - - Government or any agencythereof. t t e, 9-f f j

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,7,.. ,r. i l ~ TECHNICAL EVALVATIONLREPORT-' 1 - As. v.... .CONFORMANCE'TO GENERIC LETTER 83-28, ITEM 2.2.2-- ): VENDOR INTERFACE PROGRAMS.FOR ALL:OTHER' SAFETY.-RELATED COMPONENTSi i-LIMERICK-1/AND..-2 ..c. t. 6'. ' Docket-Nos..-50-352/50-353' .'O j Alan.C, Udy J - 1 4 i -: i. 6 1 Published May 1987 o 'h Idaho National Engineering Laboratory EG&G Idaho, Inc.:... Idaho' Falls, Idaho :83415 l o .g. 4 i j i -} 1 y9 f.' [l Prepared for-the.. U S. Nuclear Regulatory.Comeissioni +- Washington, D.C.E 20555 Under DOE. Contract No.vDE-AC07-76ID01570-t . 'l 1 FIN No,"D6001/D6002 >0 9; 2 i r !:c _ (- M' '.! f r-3

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{ J 'j e j i V l N - (' _ }.j c ABSTRACT' d l si f ,This'EG&G Idaho,;Inc.,' report'providesta review ofttheisubmittals fromE the~ Philade'1hhia Electric' Company /regarding: conformance.to Generic

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3 1 i ~ . FOREWORD. [ 4 s LThis report is supplie'd as part'of th'e: program for. evaluating ~ q licensee / applicant conformanc'e to' Generic, Letter 83-28, " Required. Actions" - Based'on Generic Implications of. Salem ATWS Events'." This work.is--being conducted:for.the..U.S. Nuclear._ Regulatory' Commission, Office of" Nuclear 1 Reactor} Regulation, Division of PWR Licensing-A,, by EG&G -Idaho,: Inc., NRR. 3 and I&E Support-Branch.' . i The.U.S. Nuclear Regula' tory Commission funded'this. work under the authorization B&R Nos. 20-19-10-11-3 and 20-19-40-41-3, FIN Nos..06001-j -i and 06002. \\ .i -\\ DocketNos.L.50-352/50-353L 4 TAC No. 56257 i f I A

i CONTENTS-s ABSTRACT............................................................... ii FOREWORD.............................................................. iii 1. INTRODUCTION..................................................... 1 2. REVIEW CONTENT AND FORMAT........................................ 2 3. ITEM 2.2.2 - PROGRAM DESCRIPTION................................. 3 3.1 - Guideline.................................................. 3 3.2 Evaluation................................................. 3 3.3 Conclusion................................................. 5 1 4. PROGRAM WHERE VENDOR INTERFACE CANNOT PRACTICABLY BE ESTABLISHED....................................................... 6 4.1 Guideline.................................................. 6 4.2 Evaluation................................................. 6 ) 4.3 Conclusion................................................. 7 5. RESPONSIBILITIES OF LICENSEE / APPLICANT AND VENDORS THAT PROVIDE. SERVICE ON SAFETY-RELATED EQUIPMENT.............................. 8 5.1 Guideline.................................................. 8 5.2 Evaluation................................................. 8 5.3 Conclusion.................................................. 8 1 i 1 6. CONCLUSION....................................................... 9-7. REFERENCES....................................................... 10 1 ) O iv i }

-i L L 'CONFORMANCE TO-GENERIC LETTER 83-28, ITEM 2.2.2- ' l 1

VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS

j LIMERICK-1 AND -2 i 1. INTRODUCTION -l On February 25, 1983, both'of the scram circuit breakers at Unit 1 of .the Salem Nuclear Power Plant failed to open upon an' automatic reactor trip.

.1 signal from the. reactor protection system.

This. incident was terminated manually by the operator about 30 seconds after the initiation of the automatic trip signal. The failure of the~ circuit' breakers was determined 3 to be related to the sticking of the undervoltage. trip attachment. Prior-to this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear ) Power Plant,-an automatic. trip. signal was generated based on steam generator. low-low level during plant startup'. In this' case,-the reactor was-tripped manually by:the: operator almost coincidentally with the automatic trip. ~ ~ Following these incidents, on February 28, 1983, the NRC' Executive a Director for Operations (EDO), directed the NRC' staff to' investigate and' report on the generic' implications of these occurrences at U' nit 1 of the' Salem Nuclear Power Plant. The results of the staff's inquiry into the j generic implications of the Salem unit incidents are reported in NUREG-1000, " Generic Implications of the ATWS Ev9nts at the Salem Nuclear-Power Plant." As a result of this investigation, the Commission (NRC) 1 requested (by Generic Letter 83-28 dated. July'8,' 1983 ) all: licensees of-operating reactors, applicants for an operating license,'and' holders of' construction permits to respond to the generic issues ' raised by the analyses of these two ATWS events. This-report is an evaluation'of the-responses submitted:by the P.hiladelphia Electric Company, the< licensee!for Unit 1 and the applicant ~ ~ ' for Unit 2 of the Limerick Generating;. Station, for Item 2'.2.2 of Generic. -Letter 83-28.- The documents reviewed as a part of this evaluation are y. listed in the references at the end of this' report. f I { 'I 5 n

r m m a '2, REVIEW CONTENT AND FORMAT N '^ Item 2.2.2 of Generic Letter 83-28 requests the licensee or applicant to submit, for the staff review, a description of their prografiis for interfac}ng with the vendors of all safety-related components including.- supporting information, in considerable detail, as indicated in the guideline section for each case within this report' j t' s Thesa guidelines treat cases where direct vendor contact programs.are <l pursued, treat cases where such contact cannot' practically be establi.shed, ') and establish responsibilities of. licensees / applicants and vendors that~ J provide-service on safety-related components or equipmenti j 1 } . +. ~As previously indicated, the cases of. Item 2.2.2 are evaluated.in.a" i i separate section in which the guideline.is presented; an evaluation of'the j licensee's/ applicant's response is made; and. conclusions about the programs-f of the ifcensee or applicant for their vendor interface program for safety-relqted components and equipment are drawn. a o ~ N 1 .S "t

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g w t + 3. ITEM 2.2.2--. PROGRAM DESCRIPTION 3.1 Guideline The licensee or applicant response should' describe th'eir program for establishing and. maintaining interfaces with vendors of safety-related components which ensures that vendors are contacted on a periodic basis and y ~ Lthat. receipt of. vendor equipment technical information (ETI) is acknowledged ~ ~ j.- or'otherwise verified. Th'is program description should establish that such interfaces are stablished with..their NSSS iendor, as..well'as w'ith the vendors of key e safety-related componentsisuch as di.esel generators, electrical switchgear,. - apiliary [feldpdmps, JemeNgency core cooling system (ECCS)' pumps, batteries, battery chargeq, anciiabe. operators, to facilitate the exchange of current technical infor.mation. The fescription should verify.that controlled ~ procedures exist for. handling.this vendor. technical information which ensure-thatitisKcatcurrentandcohleteandthatitisincorporatedintoplant-operating, maintenance and' test procedures as.is appropriate, v. ,.} 3.2 Evaluation s s The Philadelphia Electric Company responded to these. requirements with submittals dated November 10, 1983,2 May 8, 1984,3 April 1, 1985,4 5 May 29,1985 'an'd June 7, 1985.6 These submittals include information that describes their past and current vendor interface programs. In the review of.the Essp9nse to this item, it was assumed that the information and - documentation suppleting this program is available for audit upon request. We have review \\d this information and note the following. The response' states that the' Philadelphia Electric Company.(PECo)- actively participates in: the. Nuclear Utility Task: Action Committee (NUTAC). program. The. Vendor Equipment Technical Information Program (VETIP)Lwas developed by NU1'AC\\ ' VETIP includes interaction with the NSSS' vendor and' y with other eleci.g ric utilitlis. NSSS vendor contact'with the. licensee'- 3 ,3x i y-i m 3 a b L iL

is } ?' 't .O M consists of technical' bulletins. PECo also' states that the following new or ,ex, < existing-procedures to implement the NUTAC/VETIP program are being used. y 9

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) W l\\f' Administrative Procedure for Review, Disposition and j LS-A-1 J. 'e Monitoring of Responses to NRC IE Bulletins, IE Information .y Notices, and Division of Licensing Generic Letters LS-A-2 Administrative Procedure for Participation in Nuclear Plant Reliability Data System 'LS-I Implementing Procedure for Utilization of the INPO NPRD System l b \\ \\,,' LS-I-6 Implementing Procedure for Review,' Disposition and Monitoring j. Nuclear Regulatory Commission IE Bulletins,-IE Information Notices and Division of Licensing Generic Letters s i NS-A Administrative Procedure for Review and Implementation of' Operating Experience Information for Vendor Manual Maintenance ) NSS-I-4 Procedure for Review and Utilization of Operating Experience I h Information l NSS-I-5 . Procedure Governing the Use of the Institute of Nuclear Power Oputa.tions Nuclear Network i a i [ j jERDP6.4 Prp ecure_fy Control of Vendor Technical Manuals } One of the Vt!TIP 1rt,,lementation responsicilities is to seek assistance l ,andequipmenttecNidalinformationfrom'thevendorsofsafety-related 1 4' equipment (c hhb tban tt6 @!Qvendnr)lwhen the licensee's evaluation of an- ). t e y Jeduipment problew ogl[an eqblyant,technicaljinfopnation problem concludes. j I th'it f such interaction'is necassary 'n woulr! te"benef+cial. PECo states that j // the] comp?y. with this NWTAC imMenientation coquirement, however, j Sec {cu ca.1 >f 4t% generic letter statt /[thaE' formal vendar interfaces. f. 'i ), y

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1 should be established with v'endors besides the NSSS vendor. PECoLhas not 11ndicated thatLany formal interface program has been established with >;-vendors other than the NSSS' vendor. ~ 3.3! Conclusion a .q We conclude that,'with'the exception--of~ interaction with the vendors of other safety-related equipment, the PEco response-regarding program I description'is complete and,.'therefore, acceptable. However, PEco should j establish a program to periodically contact vendors of key components (such. f a as auxiliary.feedwater. pumps, safety-related batteries, ECCS pumps'and safety-related' valve operators) to facilitate the exchange of current 'h ( .' technical information. In the case of the diesel generator and-q safety-related electrical switchgear vendors, PECo should establish a formal interface similar to that.with the NSSS vendor, if' practicable. j .) l u a l ,. I 5 J

n [" 93 k,5 1 ' 4.l PROGRAM:t4HEREVENDOR2NTERFACECANNOT. t PRACTICAELY BE ESTABLISHED 4.1~ Guideline The licensee / applicant response should describe their program for - compensating for the lack of a formal vendor interface where such an - interface cannot be practicably established. This. program may reference. the'.NUTAC/VETIP program, as described in INPOL84-010, issued in - March'1984. If the NUTAC/VETIP program is referenced, the response shouldl describe' how' procedure's were revised t'o properly, control and implement this . program 1and to incorporate.the: program-enhancements described in' Section 3.2 of the NUTAC/VETIP report. It should also be noted that the - lack of either' a formal-interface with each vendor'of _ safety-related equipment or a' program to periodically contact each' vendor;of ~ safety-related' equipment will not relieve the licensee / applicant of his ~ responsibility to obtain appropriate' vendor instructions and'information where necessary to provide. adequate confidence that a structure, system or-component will' perform satisfactorily in service and to ensure adequate quality assurance in accordance with Appendix B_to 10 CFR_Part 50. 4.2 Evaluation- ~ PECo provided a brief description of th'e vender. interface' program. Their description references the NUTAC/VETIP program. PECo states that plant instructions and procedures are currently in place to assure that the ~ VETIP program is properly controlled and implemented. VETIP is comprised of two basic elements related to vendor equipment problems; the Nuclear Plant Reliability Data System (NPRDS) and the Significant Event Evaluation and 'Information Network (SEE-IN) programs. VETIP is designed to ensure that vendor equipment problems are recognized, evaluated and corrective action taken. 6

Through participation in the NPRDS program, a licensee submits engineering information, failure reports and operating histories for review under the SEE-IN program. Through the'SEE-IN program, the Institute of Nuclear Power Operations (INP0) reviews nuclear plant events that have been reported through the NPRDS programs and Nuclear Network and NRC reports. Based on the significance of the event, as determined by the screening i review, INPO issues a report to all utilities outlining the cause of the event, related problems and recommends practical corrective actions. These reports are issued in Significant Event Reports, and Significant Operating Experience Reports and as Operations and Maintenance Reminders. Upon receipt of these documents, the utility evaluates the information to determine applicability to the facility. This evaluation is documented and corrective actions are taken as determined necessary. PECo's response' states that procedures exist to review and evaluate incoming equipment technical information and to incorporate it into existing procedures. 4.3 Conclusion We find that PECo's response to this concern is adequate and acceptable. This finding is based on the understanding that their commitment to implement the VETIP program includes the implementation of the enhancements described in Section 3.2 of the NUTAC/VETIP program to the extent that PEco can control or influence the implementation of these i recommendations. S 7 1

l Il -5. RESPONSIBILIT1ES OF. LZCENSEE/ APPLICANT AND. VENDOR l ] THAT PROVIDE l. SERVICE ON SAFETY-RELATED EQOIPMENT-q 5.1 Guideline 'The 1.icensee/ applicant response should verify that the responsibilities'ofLthe licensee or applicant and vendors that provide service on safety-related equipment are defined such:that control of .applicablefinstructions for maintenance work on safety-related equipment' are provided. 5.2 Evaluation i PECo's resp'onse c'ommits to'implementLthe NUTAC/VETIP program. They-further' state that procedure A-27.3, Administrative Procedure for the Procurement of Safety-Related Services for 'Limerickf adequately implements this' program. The VETIP guidelines' include implementation procedures for 'the internal handling of vendor services that PECo states are' included in -this-procedure.

5.3 Conclusion "We find that the information contai.ned in PECo's submittals is sufficient for us to conclude that the utility's and the: vendor's responsibilities are defined and controlled appropriately..Therefore, the-information provided by PECo for this item is acceptable..

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a .6. CONCLUSION' Based on our review!of the utility's response to the' specific requirements ofl item 2.2.2 for Limerick-l' and -2, we' find that PECo's interface program with its'NSSS supplier.(but not for vendors,of other l ~ . safety-related equipment), its internal handling of vendor-supplied- ~ . services,' along with their commitment to implement the NUTAC/VETIP program,- 'is acceptable. This is based on the' understanding-that PECo's' commitment: ~ to implement.the NUTAC/VETIP program includes.the enhancements described in' Section 3.2 of the report to the ~ extent' that. thc.< can control or. influence-i such enhancements. PEco should. establish a program to periodically contact vendors of key components '(such as auxiliary feedwater pumps, safety-related batteries, ECCS pumps and safety-related valve operators) to facilitate.the: exchange of: current techn'ical information. In'the case of the diesel-generator and safety-related switchgear. vendors, a formal interface, such as that-established with the NSSS vendor, should be established, if practicable. j l I i i r .I .~ e s t i a 9 a i

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17.. REFERENCES"

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.1. E letter,1NRC ;(0. G. Eisenhut),. to all Licensees ~ of Operating. Reactors, l ~ ' Applicants-for'; Operating License, and Holders of Construction ~ Permits, 'i " Required Actions. Based on Generic Implications of Salem ATWS Events ' ] (Generic. Letter 83 28)," JulyJ8,L1983.. "2. ' Letter', Philadelphia: Electric' Company!(VL S. Boyer) to NRC. ~ -(0. G.-Eisenhut), November. 10, 1983. ' ~ 2. ! Letter,: Philadelphia Electric Company (V. S.- Boyer) to NRC 3. ..(0. - G... Ei senhut),: May,8,.1984. 4.1 ' Letter, Philadelphia Electric ' Company. (V. S.j Boyer).to NRC - ( A~~. : Schwe'ncer), '" Generic Letter 83-28 (Salem ATWS Event),"L April 1, 1985. 5.- . Letter, Philadelphia Electric Company (S. L. Daltroff) to NRC - '(A'.1Schwencer), " Generic LetterL83-28 Required Action Based on Generic. Implications of. Salem ATWS Events," May' 29,.1985. '6. . Letter, Philadelphia Electric-Company (S.' L.L Daltroff) to NRC i(W. R.1 Butler), " Generic Letters 83-28 (Salem ATWS Event)," June 7, 1985.. 7. Vendor Equipment Technical Information Program,' Nuclear Utility Task Action. Committee on Generic-Letter 83-28,rSection 2.2.2,_ March'1984,. INPO 84-010. ~ ~ I' f .% 'j >\\

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90. SPON80 RING ORGANIZATION NAME AND MaaLING ADORES $ fis.cfuer de Ceses 114. TYPE of REPoMT Division of PWR Licensing - A I

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Piaioo Coveaso <,-,..-, !!ashington. DC 20555 i 12 SUPPL 8 MENT ARv NOTES

13. AS$1R ACT fJ00 worse er *ess, This EG&G Idaho, Inc., report provides a review of the submittals from the Philadelphia Electric Company regarding conformance to Generic Letter 83-28, Item 2.2.2, for Limerick-1 and -2.

14 DOCUMtNT ANabilis e El vWQRD5/DESCni' TONS IS Ava LAtiLiTv STAttMENT Unlimited Distribution 16 SECUntTYCLA8SIFICAftoN Ithan onees . io Nri...as,o,iN Nono reams Unelassified iTh.s reportl Unclassified

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