ML18031A747
| ML18031A747 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/02/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18031A746 | List: |
| References | |
| GL-83-28, NUDOCS 8609050056 | |
| Download: ML18031A747 (4) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION EEIIEEIC EET~.E PA T EUP L
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9 INFORMATION 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 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 (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 CoIImission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983
)
1 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 ATMS events.
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This report is an evaluation of the response submitted by Tennessee Valley Authority, the licensee for the Browns Ferry Nuclear Power Station, Units 1, 2,
and 3, 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 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, including maintenance, work orders, and parts replacement.
EVALUATION The licensee for the Browns Ferry Nuclear Power Station, Units 1, 2, and 3
responded to the requirements of Item 2.1 (Part
- 1) with a submittal dated November 7, 1983 The licensee stated in this submittal that all components that are required to perform the reactor trip function are classified as safety-related equipment.
These components are outlined in TVA's Operational guality Assurance manual as critical systems, structures or components (CSSC).
TVA's corporate procedures require that all documentation related to maintenance or modification activities, and all procurement documents be identified as pertain-t ing to CSSC or non-CSSC equipment, and that the applicable procedures and quality requirements are adhered to.
CONCLUSInN 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 I) of I
the Generic Letter 83-?8, and i,s therefore acceptable.
I REFERENCES 1
1.
NRC Letter, D.
G. Eisenhut,, to all Licensees of Operating Reactors, Applicants for Operating License, and Holde'rs of Construction
- Permits, "Required Actions Based on, Generic Implications of 'Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
2.
Letter, L. M. Mills, Tennessee Valley Authority, to Harold R. Denton, NRC, November 7, 1983.
Principal Contributor:
A. Toalston Dated:
September 2,
1986
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