ML20237A697

Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 2.1,Part 1 Requiring Confirmation That All Reactor Trip Sys Components Identified as safety-related.Response Acceptable

ML20237A697
Person / Time
Site:	Fermi
Issue date:	12/10/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237A694	List: ML20237A692 ML20237A697 ML20237A705
References
GL-83-28, NUDOCS 8712150180
Download: ML20237A697 (3)

Text

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a ENCLOSURE 1 i

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

EQUIPMENT CLASSIFICATION (RTS COMPONENTS)

ENRICO FERMI ATOMIC POWER PLANT, UNIT 2 DOCKET NOS. 50-341 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 circ"it 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 f

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 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..

8712150180 871210 DR ADOCK 0500 1

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2-This report is an evaluation of the response submitted by Detroit Edison Company, the applicant for the Enrico Fermi Atomic Power Plant, Unit 2, 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 1) requires the applicant to confirm that all Reactor Trip System ccmponents are fdentified, classified and treated as safety-related as indicated in the following statement: l f

Licensees and applicants shall confirm that all components whose functioning is required to trip the reactor are identified as I 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 Enrico Fermi Atomic Power Plant, Unit 2 responded to the requirements of Item 2.1 (Part 1) with submittals dated November 3,19832 and 3 '

July 5, 1985 . The lic'ensee stated in this first submittal that all components that are required to perform the reactor trip function had been identified and that the procedures and documents used to control safety-related activities, w

t including maintenance, work orders, and parts replacement were being reviewed to ensure that such components were correctly identified as safety-related in -

them. The licensee further stated his intent to complete the review and cor-rect any deficiencies found. In the latter submittal, the licensee reported completion of the program and stated their belief that the results met the requirements of Item 2.1 (Part 1).

CONCLUSION Based on our review of these responses, we find the licensee's statements confirm that a program exists for identifying, classifying and treating f

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, 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.

2. Letter, W. H. Jens, Detroit Edison Company, to B. J. Youngblood, NRC, November 3, 1983.

3. Letter, W. H. Jens, Detroit Edison Company, to B. J. Youngblood, NRC, July 5, 1985.

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