ML20214R557
| ML20214R557 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 03/31/1987 |
| From: | Haroldsen R EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML20214R552 | List: |
| References | |
| CON-FIN-D-6001 EGG-NTA-7645, GL-83-28, TAC-52851, NUDOCS 8706080195 | |
| Download: ML20214R557 (11) | |
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l EGG-NTA-7645 March 1987 l
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INFORMAL REPORT r
idaho National CONFORfMNCE TO GENERIC LETTER 83-28, ITEM 2.1 Engineer /ng (PART 1) EQUIPMENT CLASSIFICATION,fMINE YANKEE Laboratory L
Managed by the U.S.
t Department R. O. Haroldsen ofEnorgy I
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PYC90Y'd ICY th0 wors pernamat unear w ouc%'#lff U.S. flVCLEAR REGULATORY COMMISS10fl 0706000195 070421 l'DR ADOCK 03000309 l'
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DISCLAIMER This boot was prepared as an account of work sconsored by an agency of the United l
States Govenment. Nethe the Uruted $tates Govenment nor any agency thwoof, i
not any of their employees, menes any warranty, escrees or implied, or soeumee any l
legal habety or resconsin.hty for the accuracy, como6etences, or usefulnese of any mformate, soperatus, product or process disclosed, or represents that its use would l
not ininnge pnvate#v owned nghts References herein to any spoofe commercial j
product, process, or service by trade name, trademark, manufacturer, et otherwise.
l does not necessardy constitute or imply 6ts endorsement, recommendation, or favonng by the Uruted States Government or any agency thereof. The vens and op+nions of l
authors espressed hereen do not necessanly state or reflect those of the United Statee Government or any agency thereof
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EGG-NTA-7645 A
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CONFORMANCE TO GENERIC LETTER 83-28 ITEM 2.1 (PART 1) EQUIPMENT CLASSIFICATION (RTS CDNPONENTS)
MAINC YANKEE r
Docket No. 50-309 l
R. Haroidsen Published March 1987 j
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i Idaho National Engineering Laboratory EG&G Idaho, Inc.
Prepared for the U.S. Nuclear Regulatory Commission Washington. 0.C.
20555 under DOE Contract No. DE-AC07-761001570 FIN No. 06001
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A8STRACT
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This EGMi Idaho, Inc. report provides a review of the submittals from i
Maine Yankee for conformance to Generic Letter 83-28. Item 2.1 (Part 1),
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equipment classification of reactor trip system components.
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Docket No. 50-309 TAC No. 52851 4
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l FOREWORD This report is supplied as part of the program for evaluating Licensee / applicant conformance to Generic Letter 83-28, " Required Actions Based on Generic Impitcations of Salem ATWS Events." This work is being conducted for the U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, Division of PWR Licensing-A, by EG&G Idaho, Inc.
I The U.S. Nuclear Regulatory Commission funded this work under the authortration B&R No. 20-19-10-11-3, FIN No. 06001.
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CONTENTS A8STRACT..............................................................
11 FOREWORD..............................................................
111 1.
INTRODUCTION AND
SUMMARY
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PLANT RESPONSE EVALUATION.......................................
3 2.1 Conclusion................................................
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3.
GENERIC REFERENCES..............................................
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CONFORMANCE TO GENERIC LETTER 83-28 ITEM 2.1 (PART 1) EQUIPMENT CLASSIFICATION (RTS COMPONENTS)
MAINE YANKEE 1.
INTRODUCTION AND
SUMMARY
I 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 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 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 Salen Nuclear Power Plant based on steam generator low-low level during plant startup.
In this case, the reactor was tripped manually oy the operator almost coincidentally with the automatic trip.
Following these incidents, on February 28, 1983, the NRC Executive Director of Operations (EDO), directed the staff to investigate the report' on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem Unit 1 incidents are reported in NUREG-1000
" Generic Impitcations of the ATWS Events at the Salem Nuclear Power Plant."
As a result of this investigation, the Conuitssion (NRC) requested (by Generic Letter 83-28, dated.luly 8, 1983)2 all licensees of t
operating reactors, applicants for an 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 I
identified, classified, and treated as safety-related as indicated in the following statement:
Licensees and applicants shall confirm that all components whose functioning is required to trip the reactor are identified as 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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PLANT RESPONSE EVALUATION The licensee for the Maine Yankee Nuclear Plant, Maine Yankee Atomic Power Co., provided a response to Item 2.1 (Part 1) in a submittal dated November 10, 1983.
The section of the submittal addressing this item states that the components required to function to trip the reactor include the reactor protective system relays and trip breakers (including shunt trip, undervoltage trip and manual trip button) which are classified safety-related.
The statement by itself is insufficient to determine compliance with the Items requirements. However, the licensee's responses to Items 2.2.1.2 and 2.2.1.3 provide additional information.
Documents are identified in l
these sections which are used to control safety-related activities from start to finish. The safety-related activities are appropriately identified.
2.1 Conclusion Based on our review of the licensee's submittal, we find that the licensee has identified the components necessary to perform reactor trip and that these components are classified safety-related in an equipment classification system which controls activities relating to the safety-related components. We therefore, find that the licensee's response met the requirements of Item 2.1 (Part 1) of Generic Letter 83-28 and is acceptable, i
Reference Letter, C. D. Frizzle, Yankee Atomic Power Co., to J. R. Miller, NRC, November 10, 1983.
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GENERIC REFERENCES 1.
Generic Implications of ATWS Events at the Salem Nuclear Power Plant, NUREG-1000, Volume 1, April 1983; Volume 2, July 1983.
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NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits,
" Required Actions 8ased on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
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