ML20207C080
| ML20207C080 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/22/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207C073 | List: |
| References | |
| GL-83-28, NUDOCS 8612300047 | |
| Download: ML20207C080 (3) | |
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s SAFETY EVALUATION REPORT GENERIC ~ LETTER 83-28 ITEM 2.1 (PART 1) EOUIPMENT CLASSIFICATION (RTS COMP 0NENTS)
ITEM 2.1 (PART 2) REACTCR TRIP SYSTEM VENDOR INTERFACE CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483' INTRODUCTION AND
SUMMARY
On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to ccen upon an automatic reactor trip signal from the reactor protection system. The 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 coinciden-tally 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 etcurrences,at Uni't 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 investigati n,9 the Connission (NRC) requested (by Generic Letter 83-28 dated July 8,1983 )
all licensees of operating reactors, applicants for an op rating license, and holders of construction peruits to respond to generic issues raised by the analyses of these two ATKS events.
This report is an evaluation of the response submitted by Union Electric Company, the licensee for the Callaway Plant, Unit I for Item 2.1 of Generic Letter 83-28.
The actual documents reviewed as part of this evaluation are listed in tFe references at the end of the report.
e Item 2.1 (Part 1) j_
Item 2.1 (Part 1) requires the licensee to confinn that all Reacter Trio System comperents are identified, classified and treated as safety-related as indicated in the following statement:
Licensees and applicants shall confinn that all cenpcrents whose functioning is required to trio the reactor are identified as safety-related on documents, procedures, and information handling sytems used in the plant to ccntrol safety-related activities, in-cluding maintenance, vork crders, and parts replacement.
8612300047 861222 PDR ADOCK 05000483 j'
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EVALUATION I
ThelicenseefortheCallawayPlant,UnitIrgggggg6to the requirements of Item 2.1 (Part 1) with a series of submittals referenced below. The first three submittals described the licensee's classification program that was being developed and provided progress reports. The licensee stated in the final two submittals that the program was fully implemented and reaffirmed that 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 the developed 0 list is used in the generation of work requests and in assignment of surveillance and preventative n;aintenance tasks.
Item 2.1 (Part 21 Item 2.1 (Part 2) requires the licensee to ccnfirm that an interface has been established with the NSSS or with the vendors of each of the components of the Reactor Trip System which includes:
periodic communication between the licensee / applicant and the
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NSSS or the vendors of each of the components of the Reactor Trip System, and i
a system of positive feedback which corfims receipt by the licensee /appliant of transnittals o,f vendor technical infomation.
EVALUATION The licensee for the Callaway Plant, Unit I responded to t)e requirements of Item 2.1 (part 2) with a submittal dated November 18, 1983. The licensee stated in this submittal that Westinghouse is the NSSS for the Callaway Plant, Unit I and that the RTS is included as part of the Westinghouse interface program established for this plant. The response also confirms that this interface pro-l gram includes both periodic communication t'etween Uestinghouse and the licensee / applicant and resitive feedback from the licensee / applicant in the form of signed receipts for technical infomation transmitted by Westinghouse.
CONCLUSION Based on our review of these responses, we find the licensee's statements confirm that a progrem exists for identifying, classifying and treating components that are required for performance of the reactor trip function as safety related and that a vendor interface program exists with the NSSS ver. dor for components that are required for perfomance of the reactor trip function.
These programs meet the requirements of Item 2.1 of the Generic Letter 83-28, and are therefore acceptable.
REFERENCES 1.
NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating Licerse, and l'olders of Construction Ferwits, "P.equired Actions Based on Generic Irplications of Salem ATWS Events (Ceneric letter 83-28)," July 8,1983.
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Letter, D. F. Schnell, Union Electric Co., to H. R. Denton, NRC, November 8,1983.
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Letter, D. F. Schnell, Union Electric Co., to H. R. Denton, NRC, i
March 12,1984.
4.
Letter, D. F. Schnell, Union Electric Co., to H. jR. Denton, NRC, May 21, 1984 5.
Letter, D. F. Schnell, Union Electric Co., to H. R. Denton, NRC, December 27, 1984.
6.
Letter, D. F. Schnell, Union Electric Co., to H. R. Denton, NRC, May 17,1985.
7.
Union Electrie Company letter to NRC, D. F. Schnell to Harold R. Denton, Director of Nuclear Reactor Regulation, NRC, " Response to Generic letter 83-28," November 18, 1983.
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