ML17325A003

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Safety Evaluation Re Util 831104,840330,850410 & 1219 Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components.Util Program Meets Requirements of Generic Ltr & Acceptable
ML17325A003
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 03/27/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17324B295 List:
References
GL-83-28, NUDOCS 8704020154
Download: ML17325A003 (8)


Text

SAFETY EVALUATION REPORT GENERIC LET R

, I Et (PART 1)

E P<ENT CL SSIFIC TION RTS C

MP NENTS D.C.

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R RPLNT,UNTS DOC ET N S. 50-1 31 INTRODUCTION AND

SUMMARY

On February 25, 1983, both of the sc~am circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reacto~ trip signal from the reactor protection system.

This incident was terminated manually by the operator about 30 seconds afte~ 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 (EDO), 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 I

unit 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

)

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.

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This report is an evaluation of the response submitted by Indiana and Michigan Electric Company, the licensee for the 0.

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Cook Nuclear Power Plant, for Item 2.1 (Part 1) of Generic Letter 83-28.

The actual documents reviewed as part of this evaluation are listed in the references at the end of the report.

Item 2.1 (Part I) requires the licensee 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 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, in-cluding maintenance, work orders, and parts replacement.

EVALUATION The licensee for the 0.

C.

Cook Nuclear Power Plant responded to the requirements of Item 2.1 (Part 1) with submittals dated November 4, 1983

, March 30, 1984 April 10, 1985

, and Oecember 19, 1986 The submittals state that a document 4

5 called the N-list and other documents such as the FSAR, Technical Specifications, flow diagrams, isometrics and electrical diagrams are utilized to identify equipment as being safety related.

These are complemented and controlled by a

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k computerized component classification system which references existing documents and information systems to manage the purchase, maintenance and replacement of safety related components.

CONCLUSION 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 Z. 1 (Part 1) of the Generic Letter 83-28, and is therefore acceptable.

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 Implications of Salem ATMS Events (Generic Letter 83-28)," July 8, 1983.

2.

Letter, M. P. Alexich, Indiana and Michigan Electric Co., to D.

G. Eisenhut, NRC, November 4, 1983.

3.

Letter, M. P. Alexich, Indiana and Michigan Electric Co., to D.

G. Eisenhut, NRC, March 30, 1984.

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REFERENCES (CONT.)

4.

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

5.

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

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