ML19325C115
| 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: |
| References | |
| CON-FIN-D-6002 EGG-NTA-7438, GL-83-28, NUDOCS 8612090641 | |
| Download: ML19325C115 (7) | |
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IG6.NTA.7434 i
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l CONFORMANCE TO GENERIC LtiTER 33 23 i
IT(M 2.1 (PART 1) (QUIPM(NT CLAS$1FICAtl0N (RTS COMPONENTS) t i
l SHOR(HAM NOCLEAR POWER STATION i
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l Docket No. 50 322 r
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l R. Heroidsen l
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l Pub 11thed November 1986
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1 Idaho Nettonal Engineering Laboratory l
EG64 Idaho, Inc.
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i Frepared for the U.S. Nuclear Regulatory Comission I
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'_.Under-DOf-tentract No. Of-AC07 761001570 t
FINlio?04002 1
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Al$ 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 componentp 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...............................................
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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) requested (by Generic Letter 83-28, dated July 8, 1983)2 all licensees of s
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 safety-related on documents, procedures, and information handling I
systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement.
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PLANT R(Sp0N$t IVALUATION f
The appittant for the shoreham Nucle 6r plant (Long Island Lighting-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 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 l
Letter 83 28 and are acceptable.
4 References i
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Letter, 8. J. McCaf frey, Long Island Lighting Co., to H. R. Denton,
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NRC, March 9, 1984.
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Letter, J. O. Leonard, Jr., Long Island Lighting Co., to H. R. Denton, NRC, December 4, 1984.
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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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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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