ML20205H151

Safety Evaluation of Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components)

ML20205H151
Person / Time
Site:	Yankee Rowe, 05000000
Issue date:	08/15/1986
From:	NRC
To:
Shared Package
ML20204G196	List: ML20204G192 ML20205H136 ML20205H151
References
GL-83-28, NUDOCS 8608190736
Download: ML20205H151 (3)

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SAFETYEVAld1ATIONREPORT l

GENERIC LtITER 83-28, ITEM 2.1 (PART 1)

EQUIPMENT CLASSIFICATION (RTS COMPONENTS) l YANKEE-ROWE NUCLEAR POWER STATION DOCKET NO.50-029 I

INTRODUCTION AND

SUMMARY

l On February 25, 1983, both of the scran circuit breakers at Unit I of the Salem l

Nuclear Power Plant failed to open upon an automatic reactor trip signal from l

the reactor protection system. This incident was terminated manually by the 9perator about 30 seconds after the initiation of the automatic trip signal.

E The failure of the circuit breakers was detennined to be related to the sticking of the undervoltage trip attachment. Prior to this incident, on February 22, l

1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal' was' l 1

generated based on steam generator low-low level during plant start-up. In this case, the reactor was tripped manually by the operator almost coin- .

cidentally 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 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 Comission (NRC) requested (by Generic Letter 83-28 dated July 8,1983I )

all licensees of operating reactors, applicants for an operating license, and holders of construction pennits to respond to generic, issues raised by the analyses of these two AWS events.

8608190736 860815 9 DR ADOCK 0500 l

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-l This report is an evaluation of the response submitted by the Yankee Atomic Electric Company, the licensee for the Yankee-Rowe Nuclear Power Station, 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 this report.

Item 2.1 (Par 1) 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:

Licensee 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 hardling systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement.

EVALUATION

, The licensee for the Yankee-Rowe Nuclear Power Station, responded' to the requirements of Item 2.1 (Part 1) with a submittal dated November 5,19832 ,

The submittal stated that the reactor trip system and components whose function is required to trip the reactor are identified as (safety-related) on appropriate documents, procedures and infonnation handling systems used in the plant to con-trol safety-related activities, including maintenance, job orders, and parts replacement.

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l l CONCLUSION Based on our review of these responses, we find the licensee's statements

! confirm that a program exists for identifying, classifying and treating 1

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) cf 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 ATWS Events l

(Generic Letter 83-28)," July 8,1983.

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2. Letter, L. H. Heider, Yankee Atomic Electric Company, to D. G. Eisenhut, NRC, November 5, 1983.

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