ML20215E006
| ML20215E006 | |
| Person / Time | |
|---|---|
| Site: | Fermi, 05000000 |
| Issue date: | 12/12/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20214G411 | List: |
| References | |
| GL-83-28, NUDOCS 8612170183 | |
| Download: ML20215E006 (3) | |
Text
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UNITED STATES
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/o NUCLEAR REGULATORY COMMISSION g
.,i WASHINGTON, D. C. 20555
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ENCLOSURE (1)
SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 1)
EQUIPMENT CLASSIFICATION (RTS COMP 0NENTS)
FERMI-2 000%Er NO. 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 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.
i Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the staff to investigate and report on the generic i
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 l
Events at the Salem Nuclear Power Plant." As a result of this investigation,-
1 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.
8612170183 861212 DR ADOCK 05000341' PDR
I This report is an evaluation of the response submitted by Detroit Edison Company, the applicant for Fermi-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 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 h'ndling a
systems used in the plant to control safety-related activities, in-cluding maintenance, work orders, and parts replacement.
EVALUATION The licensee for Fermi-2 responded to the requirements of Item 2.1 (Part 1 2
3 ith submittals dated November 3, 1983 and July 5, 1985.
The licensee w
tstated in this first submittal that all components that are required to per-tform the reacter trip function had been identified and that the procedures and documents used to control safety-related activities, including maintenance, work orders, and parts replacement were being reviewed to ensure that such i
components were correctly identified as safety-related in them.
The licensee further stated their intent to complete the review and correct 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).
i basen.---
- 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.
REFERENCh$
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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