ML20207R648
| ML20207R648 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Fort Saint Vrain |
| Issue date: | 03/11/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205E376 | List: |
| References | |
| GL-83-28, TAC-52840, NUDOCS 8703170501 | |
| Download: ML20207R648 (2) | |
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l SArFTv EVALUATI6" E v THE OFFICE OF NUCLE AP REACT 0P PEGULATI0f:
RFLATING TO GENEr'C LETTEP P3-28, ITEP ?.1 (PAPT l' EQUIPMENT CLASSIFICATION l
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAP GENERATIFG STATION l
DOCKET NO. 50-?67 1.0 INTR 000CTION AND
SUMMARY
On February 25, 1983, both of the scran circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon ar automatic reactor trip signal from the reactor protection system. This incident was terminated manually by the operator about 30 seccrds after the initiatier.
of the automatic trip signal. Thc 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 autenatic trip signal was generated based on steam cenerator low-low level during plant start-up.
In this case, the reactor was tripped manually by the operator almost coincidentally witF the autoratic trip.
Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the staff to investigate and I
report on the generic implications of these occurrences at Ur.it 1 of the Salem Nuclear Power Plant. The results of the staff's ircuiry 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, tge Comission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983 ) all licensees of operating reactors, applicants for an operating license, ard holders of construction permits to respond to generic issues raised by the analyses of there two ATWS events.
This report is an evaluotion of the response submitted by Public Sersice Company of Colcrado, the licensee for the Fort St. Vrain Nuclear Generating Statiun, for item 2.1 (Part 1) of Generic Letter 83-28. The actual docurents reviewed as part of this evaluation are listed in the references at the end of this report.
8703170501 870311 PDR ADOCK 05000267 P
. Item P.1 (Part 1) requires the licenscc to confirn, that all Reactor Trip Syster (RTS) components are identifico, classified erd treated es safety-related as indicated in the fcllowino statement:
Licensees 6nd applicarts shall confirm that r11 componchts whose fur.ctionino is required to trip the reactor are idertified as safety-related on documents, procedures, arc informaticr handlinn systems used in the plart to contrcl safety-related activities, including maintenarce, work creers, ano parts replacement.
P0 EVALUATION The licensee for the Ft. St. Vrain Nuclear Generating Statior, responded tcthepequirementsofiteg2.1(Part1)withsubmittalsdatedNovember 4, 1983 and June 17, 198F. The licensee stated ir the first submittal that they were engaged in a project to identify Class I electrical equipment required to perforn the reactor trip functior on schtnatic drawings and that an audit was completed which verified that safety-related ccaponents were so indicated in a computerized safety-related component list and on process and instrumentation diagrams.
The licensee further stated in the second submittal that the plant maintenance procedures were being rewritten and that all RTS components would be identified as safety-related in th(. revised procedures. This program was expected to be completed by January 3,1986.
3.0 CONCLUSION
Based on our review of these responses, we find the licensee's statt-ments 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 thc requirements of item 2.1 (Part 1) of the Generic Letter 83-28, and is therefore acceptable.
4.0 REFEPENCES 1.
NPC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Perrits, "Recuired Actions Based on Generic implications of Salen ATUS Events (Generic Letter 83-28)," July P, 1903.
P.
Letter, O. F. Lee, Public Service Co cf Colorado, to D. G. Eisenhut, NRC, Noven,ber 4,1903.
3.
Letter, J. W. Gahm, Public Service Co. of Colorado, to Regionul fdniinistrator, Regior IV, NRC, June 12, 1985.
Principal Centributor:
D. Lasher Dated: March 11, 1987