ML20199K402

Safety Evaluation of Applicant 831105 & 840601 Responses to 830708 Generic Ltr 83-28,Item 2.1 (Part 1),requiring Identification of Reactor Trip Sys Components as safety- Related.Licensee Program Approved

ML20199K402
Person / Time
Site:	Braidwood
Issue date:	06/25/1986
From:	NRC
To:
Shared Package
ML20199K385	List: ML20199K380 ML20199K402
References
GL-83-28, NUDOCS 8607090147
Download: ML20199K402 (3)

Text

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SAFETY EVALUATION REPORT

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

EQUIPMENT CLASSIFICATION (RTS COMP 0NENTS)

BRAIDWOOD STATION, UNITS 1,2

_D0_CKET NOS. 50-456/457 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. The incident was terminated manually by the j 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 coin-cidentally 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 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, 19831 )'

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.

860709o147 860625 PDR A

ADOCK 05000456 .

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This report is an evaluation of the response submitted by Comonwealth Edison Company, the applicant for the Braidwood Station, Units 1,2,for ItanT.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 1) requires' the applicant to confinn 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 applicant for The Braidwood Station, Units 1,2 responded to the require-ments of Item 2.1 (Part 1) with submittals dated November 5, 19832 and June 1, 19843 . The applicant stated in these submittals that some reactor trip compo-nents such as turbine trip components were not included in the safety-related classification of components required to perfom the reactor trip function, however all components that are required to perform the reactor trip function were reviewed to verify that these components are classified as safety-related equipment. The licensee further stated that these components were identified as safety-related on applicable documents, procedures, and in information handling systems.

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CONCLUSION Based on our review of these responses, 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.

REFERENCES

1. NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applic;nts 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.

2. Letter, P. L. Barnes, Commonwealth Edison Company, to H. R. Denton, NRC, November 5, 1983.

3. Letter, P. L. Barnes, Commonwealth Edison Company, to H. R. Denton, NRC, i

June 1, 1984.

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