ML19325C115

Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Shoreham Nuclear Power Station.

ML19325C115
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	11/30/1986
From:	Haroldsen R EG&G IDAHO, INC.
To:	NRC
Shared Package
ML19325C116	List: ML19325C115
References
CON-FIN-D-6002 EGG-NTA-7438, GL-83-28, NUDOCS 8612090641
Download: ML19325C115 (7)

Text

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i l CONFORMANCE TO GENERIC LtiTER 33 23

IT(M 2.1 (PART 1) (QUIPM(NT CLAS$1FICAtl0N (RTS COMPONENTS) t i

i l SHOR(HAM NOCLEAR POWER STATION i i l Docket No. 50 322  ;

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1 Idaho Nettonal Engineering Laboratory l EG64 Idaho, Inc. l Idaho Falls, Idaho 83415 i

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i Frepared for the U.S. Nuclear Regulatory Comission t I

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'_.Under-DOf-tentract No. Of-AC07 761001570 t FINlio?04002 1

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' I L Al$ TRACT This EEG Idaho Inc. report provides a review of the submittais from

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the Shoreham Wuclear power Station for conformance to Generic Letter 83-28 t i

Ites 2.1 (Part 1), equipment classification of reactor trip system i

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FOR(WORD This report is suppiled as part of the program for evaluating 1tcenset/appittant conformance to Generic Letter 43-28. ' Required Actions Based on Generic Impitcations of Salem ATWS Events.' This work is being

• conducted for the U.S. Nuclear Regulatory Comission. Of fice of Nuclear Reactpr Regulation. Olvision of PWR Licensing-A, by the E MG Idaho, Inc.

The b.S. Nuclear Regulatory Coantssion funded this work under the authortaatton B&R No. 20-19-40-41-3. FIN No. 06002.

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CONTENTS At$ TRACT .............................................................. 11 FOREWORD .............................................................. tti 1.

I N T R O DUC T I ON AN D S UMA R Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1 . . . . .

2. PL ANT RE SPON SE E VAL UATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.1 Conclusion ................................................. 2

3. GE N E R I C R E F E R [ N C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. .

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1. INTRODUCTION AND

SUMMARY

On February 25, 1983, both of the scram circuit breakers at Unit 1 of !

the $41em Nuclear Power Plant f ailed to open upon an automatic reactor trip !

signal from the reactor protection system. This incident was terminated '

, annually by the operator about 30 seconds af ter the initiation of the '

automatic trip signal. The fatture of the circuit breakers was determined

• to be related to the sticking of the undervoltage trip attachment. Prior '

to the incident, on February 22, 1983, an automatic trip signal was generated at Unit 1 of the Sales Nuclear Power Plant based on steam i generator low-low level during plant startup. In this case, the reactor was tripped manually by the operator almost coincidentally with the  !

automatic trip.

(0110 wing these incidents, on February 28, 1983, the NRC [xecutive Otrector of Operations {t00), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salen Nuclear Power Plant. The results of the staff's inquiry into the generic lapitcations of the Sales Unit 1 incidents are reported in NUREG-1000, i

' Generic Implications of the ATWS twents at the Salem Nuclear Power Plant.' As a result of this investigation, the Connission (NRC) s requested (by Generic Letter 83-28, dated July 8, 1983)2 all licensees of operating reactors, applicants for en operating license, and holders of construction permits to respond to generic issues raised by the analyses of  !

these two ATWS events.

Part 1 of Item 2.1 of Generic Letter 83-28 requires the licensee or applicant to confirm that all reactor trip system components are identified, classified, and treated as safety-related as indicated in the i following statement:

4 Licensees and applicants shall conf trm that all components whose functioning is required to trip the reactor are identified as I safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement.

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2. PLANT R(Sp0N$t IVALUATION f

' The appittant for the shoreham Nucle 6r plant (Long Island Lighting-l Co.) provided responses to item 2.1 (part 1) of Generic Letter 43 28 in j submittals dated March 9, 1984 and December 4, 1984.

l The Merch 9,1984 submittal stated that the applicant had identified

. l the reactor trip system components that should be classified j safety related. These items were being incorporated into the plant l

Composite Compor.ent List (CCL) which is part of the plant information

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hand 11ag system. The December 4, 1984 submittel states that the applicant ,

had completed a review of the Shoreham specific RTS Component List and identified several additional components which were added to the Itst.

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2.1 Conclusion lased on our review of the appittant's submittell we find that the  ;

appittant has identified the components necessary to perform reactor trip  ;

and that these components are classif ted safety-r' elated on associated j

procedures and documents. We, therefore, find that the applicant's

responses meet the requirements of Item 2.1 (Part 1) of Generic Letter 83 28 and are acceptable. l 4 ,

4 References i

1. Letter, 8. J. McCaf frey, Long Island Lighting Co., to H. R. Denton, NRC, March 9, 1984. [;

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2. Letter, J. O. Leonard, Jr., Long Island Lighting Co., to H. R. Denton, NRC, December 4, 1984.

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3. GENERIC ttftRINCtl

1. Generit lam 11tations of ANS fvenin at the tales Nutlear Power Plant.

Nuttl.1000. Volume 1 Apr11 1983 Volume 2. July 1983.

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t. NRC trtter. 9. 6. Itsenhut to all Licensee of Operating kvatters. '

i App 11 cants for Operating License, and Helders of Construction Permits, i . ' Required Attuns Based on Generic laplications of Salem AWS (vents (Generte Letter 43 28).* July 8.1943.

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