ML20204G418

Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components) Cook Units 1 & 2

ML20204G418
Person / Time
Site:	Cook
Issue date:	03/31/1987
From:	Haroldsen R EG&G IDAHO, INC.
To:	NRC
Shared Package
ML17324B295	List: ML20204G418
References
CON-FIN-D-6001 EGG-NTA-7609, GL-83-28, TAC-52989, TAC-52990, NUDOCS 8703260393
Download: ML20204G418 (9)

Text

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EGG-NTA-7609 e

CONFORMANCE TO GENERIC LETTER 83-28 ITEM 2.1 (PART 1) EQUIPMENT CLASSIFICATION (RTS COMPONENTS)

COOK UNITS 1 AND 2 Docket Nos. 50-315/316 R. Haroldsen 1

Published March 1987 EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 Prepared for.the U.S. Nuclear Regulatory Commission Washington, D.C. 20555

' Ur.Jer DOE Contract No. DE-AC07-76ID01570.

FIN No. D6001 . _ _ . _ _ _ . .

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ABSTRACT This EG&G Idaho, Inc. report'provides a rev'ew of the submittals from Cook Units 1 and 2 for conformance to Generic Letter 83-28, Item 2.1 (Part s 1), equipment classification of reactor trip system components.

Docket Nos. 50-315/316 TAC Nos. 52989 and 52990

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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 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 the EG&G Idaho, Inc.

The U.S. Nuclear Regulatory Commission funded this work under the authorization B&R No. 20-19-10-11-3, FIN No. 06001.

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CONTENTS ABSTRACT . ................................ ........................... ii FOREWORD ... ....................... .................................. iii

1. INTRODUCTION AND

SUMMARY

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2. PLANT RESPONSE EVALUATION ... .. .... ........................... 2 2.1 Conclusion ................................................. 2

3. GENERIC REFERENCES .............................. ................ 4 1

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1. INTRODUCTION AND

SUMMARY

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 Salem Nuclear Power Plant based on steam generator low-low level during plant startup. In this case, the reactor was tripped manually by the operator almost conincidentally with the automatic trip.

Following these incidents, on February 28, 1983, the NRC Executive Director of Operations (EDO), directed the staff to investigate the reoort 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."I As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28, dated July 8,1983)2 all licensees of operating reactors, applicants for an operating license, and holders of contstruction permits to respond to generic issues raided 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 following statement:

Licensees and applicants shall confirm that all components whose fundtioning 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 Cook Units 1 and 2, Indiana and Michigan Electric Co., provided responses relating to Item 2.1 (Part 1) in submittals dated November 4, 1983, March 30, 1984, April 10, 1985 and December 19, 1986.

The first of these submittals describes the criteria used by the licensee to identify the safety-related components of the reactor trip system.

The submittal states that the method used to control activities relating to safety-related components is different than that described in Item 2.1 (Part 1) of the Generic Letter 83-28. It is stated that the N-list is one of the documents utilized to identify equipment as being safety-related. However, it also states that the list is not all inclusive and therefore not the sole source of reference. Other documents such as the FSAR, Technical Specifications, communications to the NRC, flow diagrams, isometrics, electrical one line and elementary diagrams are also consulted.

In the subsequent submittals, the licensee stated that a computerized component classification data-base was being implemented which~will incorporate references to existing relevant drawings and procedures. The data-base has been designed to integrate existing documents and information systems to manage purchase, maintenance and replacement of safety-related components.

The December 19, 1986 submittal confirmed that computerized component classification system had been completed and is functional.

2.1 Conclusion Based on our review of the licensee's submittals, 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

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s'afety-related components. We therefore, find that the licensee's responses meet the requirements of Item 2.1 (Part 1) of Generic Letter 83-28 and are acceptable, i

, References

1. Letter, M. P. Alexich, Indiana and Michigan Electric Co., to D. G. Eisenhut, NRC, November 4, 1983.

2. Letter, M. P. Alexich, Indiana and Michigan Electric Co., to D. G. Eisenhut, NRC, March 30, 1984.

3. Letter, M. P. Alexich, Indiana and Michigan Electric Co., to D. G. Eisenhut, NRC, April 10, 1985.

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4. Letter, M. P. Alexich, Indiana and Michigan Electric Co., to H. R. Denton, NRC, December 19, 1986.

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3. GENERIC REFERENCES-

1. Generic Imolications of ATWS Events at the Salem Nuclear Power Plant, NUREG-1000, Volume 1 April 1983; Volume 2, July 1983.

2. NRC Letter, D. G. Eisenhut to all . Licensees of Operating Reactors, 1 Applicants for Operating License, and Holders of Construction Permits,

, " Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983. .1 O

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+ Mr. John Dolan.  ?

Indiana and Michigan Electric $obpany Donald C. Cook Nuclear Pla w

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Mr. M. P. Alexich -, The Hon'orable' John _ E. Grotberg Vice President ' , ,

( United States House of Representatives Nuclear Operations <-

Washington. DC".-20515

' American Electric Power Service 'i e' .

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Region 51 Administrator, Region. III Columbus, Ohio 43215 t U.S. . Nuclear Regulatory Comission 799 Roosevelt Road Attorney General ' Glen Ellyn,- Illinois - 60137 Department of Attorney General __

525 West Ottawa Street '

'J. Feinstein .

Lansing, Michigan. 48913~ American Electric Power-Service Corporation Township. Supervisor 1 Riverside-Plaza Lake Township Hall Columbus, Ohio _43216 Post Office Box 818 Bridgeman, Michigan 49106-W. G. Smith,- Jr., Plant Managee Donald C. Cook Nuclear Plant 7 -

Post Office. Box 458 ,

Bridgman,~ Michigan 49106 e >

U.S. Nuclear Regulatory Comission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street. N.W.

Washington, DC 20037 Mayor, City of Bridgeman Post Office Box 366 Bridgeman, Michigan 49106 i Snecial ^ Assistant to the Governor 'l Room 1 - State Capitol l Lansing, Michigan _ 48909 l l

Nuclear. Facilities and Environmental 1 Monitoring Section Office l Division of Radiological Health -!

Department of Public Health  :

3500 N. Logan Street  !

Post Office Box 30035  !

. Lansing, Michigan 48909~

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