ML20236F644
| ML20236F644 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 07/29/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236F636 | List: |
| References | |
| GL-83-28, NUDOCS 8708030412 | |
| Download: ML20236F644 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION e
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WASHINGTON, D. C. 20555
%,*****pl SAFETY EVALUATION REPORT-GENERIC LETTER 83-28, ITEM 2.1 (PART 1)
EOUIPMENT CLASSIFICATION (RTS COMP 0NENTS)
MAINE YANKEE ATOMIC POWER PLANT
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DOCKET NO. 50-309
1.0 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 signal from the redctor 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 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 start-up.
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 Director for Operations (ED0), directed the staff to investigate and 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 l
unit incidents are reported in NUREG-1000, " Generic Implications of the ADIS hB03041g9797py p
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j Events at the Salem Nuclear Power Plant." As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8,1983 )
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all licensees of 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.
This report is an evaluation of the responses submitted by Maine Yankee Atomic
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Power Company, the licensee for the Maine Yankee Atomic Power Plant, for Item 2.1 (Part 1) of Generic Letter 83-28. The actual documents reviewed as part l
of this evaluation are listed in the references at the end of the report.
1 Item 2.1 (Part 1) requires the licensee to confirm that all reactor trip j
i system components are identified, classified and treated as safety-related as indicated in the following statement:
I 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.
i 2.0 EVALUATION The licensee for the Maine Yankee Atomic Power Plant responded to the require-2 ments of Item 2.1 (Part 1) with a submittal dated November 10, 1983.
In this submittal the licensee stated that the components which must function to trip the reactor include the reactor protective system relays and trip breakers (including shunt trip, undervoltage trip, and manual trip button) are classified i
as safety-related.
This description failed to confirm that these components were identified as safety-related in plant documents such as procedures and drawings and in information handling systems used in the plant to control
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safety-related activities.
However, our review of the licensee's responses to Parts 2 and 3 of Item 2.2.1 provide additional infonnation which confirmed that activities which affect safety-related components are identified and controlled.
3.0 CONCLUSION
l Based on our review, we find the licensee's statements confirm that a program exists for identifying, classifying and treating components that are required for performance of the reactor trip function as safety related.
This program meets the requirements of Item 2.1 (Part 1) of the Generic Letter 83-28, and is therefore acceptable.
4.0 REFERENCES
1.
NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, " Required Actions Based on Generic j
Implications of Salem ATWS Events (Generic Letter 83-28),"
July 8, 1983.
2.
Letter, C. D. Frizzle, Yankee Atomic Power Company to J. R. Miller, NRC, November 10, 1983.
,8 ENCLOSURE 2 EGG-NTA-7645 r
March 1987
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..s INFORMAL REPORT Idaho National CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.1 Engineering (PART 1) EQUIPMENT CLASSIFICATION, MAINE YANKEE Laboratory
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Managed by the U.S.
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DISCLAIMER j
This book was prepared as an account of work sponsored by en egency of the United States Gevemment. Neither the United States Government not any agency thereof,
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nor any of their employees, makes any warranty, express or imphed, or assumes any Wal haDihty or responsibility for the accuracy, Completeness, or usefulness of any information, apparatus, product or process deosed, or represents that its use would not infnnge pnvately owned nghts. References herein to any spoofe commercal product, process, or service by trade name, trademart, manufacturer, or otherwise does not necessanly constitute or imply its endorsement, recommenoatson, or favonng by the United States Government or any agency thereof. The wwws and opinons of j
authors expressed herein do not necessardy state or rete those of the United States Government or any agency thereof.
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CONFORMANCE TO GENERIC LETTER 83-28 ITEM 2.1 (PART 1) EQUIPMENT CLASSIFICATION (RTS COMPONENTS)
MAINE YANKEE 1
Oocket No'. 50-309 R. Haroldsen Published March 1987 Idaho National Engineering Laboratory EG6G Idaho,. Inc.
Prepared for the-U.S. Nuclear Regulatory Comission Washington, D.C.
20555 under DOE Contract No. OE-AC07-761001570 FIN No. 06001
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i ABSTRACT This EG&G Idaho, Inc, report provides a review of the submittals from Maine Yankee f or conformance to Generic Letter 83-28, Item 2.1- (Part 1),
e uipment classification of reactor trip system components.
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Docket No. 50-309 TAC No. 52851
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FOREWORD 1
This report is supplied as part of the program for evaluating
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Licensee / applicant'conformance 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 Reactor Regulation, Division of PWR Licensing-A, by EG&G Idaho, Inc.
1 The U.S. Nuclear Regulatory Commission funded this work under the authorization B&R No.~20-19-10-11-3, FIN No. D6001.
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CONTENTS f
ABSTRAC.T..........................................................'.....
33 FOREWORD..............................................................
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INTRODUCTION AND
SUMMARY
1 2.
PLANT RESPONSE EVALUATION.......................................
3 2.1 Conclusion................................................
3 3.
GENERIC REFERENCES..............................................
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CONFORMANCE TO GENERIC LETTER 83-28 ITEM 2.1 (PART 1) E0VIPMENT CL OSSIFICATION (RTS COMPONENTS) i MAINE YANKEE 1.
INTRODUCTION AND
SUMMARY
On February 25, 1983, bothof'NescramcircuitbreakersatUnitiof 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 af ter the initiation of the automatic trip signal.
The failure of the circuit breakers was determined l
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 Salem Nucl:ar Power Plant based on steam generator low-low level during plant startup.
In this case, the reactor l
was tripped manually by the operator almost coincidentally with the automatic trip.
Following these incidents, on february 28, 1983, the NRC Executive l
Director of Operations (EDO), directed the staff to investigate the report l
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 Implications of the ATWS Events at the Salem Nuclear Power Plant."
As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28, dated July 8, 1983)2 a11 licensees of 1
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.
l 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
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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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2.
PLANT RESPONSE EVALUATION The licensee for the M.)ine Yankee Nuclear Plant, Maine Yankee Atomic
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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 rela'ys and trip breakers (including shunt trip, ur.de* voltage trip and manual trip button) which are classified l
safety-related.
The statement by itself is insufficient to determine compliance with the Items requirntents.
However, the licenice's responses to Items 2.2.1.2 and 2.2.1.3 provide additional information4 Documents are identified in these sections which are used to control safety-related activities from
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start to finish. The safety-related activities are appropriately identified.
2.1 Conclusion l
Based on our review of the licensee's submittal, we find that the licer.see 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.
Reference Letter, C. D. Frizzle, Yankee Atomic Power Co., to J. R. Miller, NRC, Novenber 10, 1983.
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GENERIC REFERENCES 6
1.
Generic Implications of ATWS Events at the Salem Nuclear Power Plant, 1
NUREG-1000, Volume 1. April 1983; Volume 2 July 1983.
l 2..
NRC Letter D. G. Eisenhut to all Licensees of Operating Reactors, l
Appi) cants for Operating License, and Holders of Construction Permits,
' Required Actions Based on Generic Implications of Salem ATWS Events i
(Generic Letter 83-28)," July 8, 1983.
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CONFORMANCE TO CENERIC LETTER 83-28. ITEM 2.1 (PART 1),
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l).8)!..CT die -erGeerW i This EG&G Idaho, Inc. report provides a review of the submittals from Maine Yar,kee for conformance to Generic Letter 83-28 Item 2.1 (Part 1) Equipment Classification (RTS Components).
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