ML20195C557

SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components)

ML20195C557
Person / Time
Site:	Rancho Seco
Issue date:	06/08/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195C481	List: ML20195C475 ML20195C557 ML20195C931
References
GL-83-28, NUDOCS 8806220229
Download: ML20195C557 (4)

Text

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p o g UNITED STATES d n NUCLEAR REGULATORY COMMISSION y ,

WASHINGTON, D. C. 20655 pf SAFETY EVALUATION REPORT GENERIC Lt11ER 83-28 ITEM 2.1 (PART 1)

EOUIPMENT CLASSIFICAT!0N (RTS COMPONENTS)

FANCHO SECO NUCLEAR GENERATING STATION DOCKET NOS. 50-312 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.

Following these incidents, on February 28, 1983, the NRC Executive Director for l 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 1

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, 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 resoond to generic issues raised by the j analyses of these two ATWS events.

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4 This report is an evaluation of the response submitted by Sacramento Municipal Utility District, the licensee for the Rancho Seco Nuclear Generating Station, for : tem 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.

Iten 2.1 (Part 1) requires the licensee to ccnfirm that all Reactor Trip System components are identified, classified and treated as safety-related as indicated in the following statement:

Licensees and applic.ir.ts shall confinn that all components whose functioning is required to trip the reactor are icentified as l safety-related on documents, procedures, and informatlon handling systems used in the plant to control safety-related activities, in-cluding maintenance, work orders, and parts replacement.

EVALUATION The licensee for the Rancho Seco Nuclear Generating Station responded to the re-quirements of Item 2.1 (Part 1) with rubmittals dated November 4, 19832 , October 4

5, 19843 , and May 23, 1985 . The first submittal described the licensee's existing equipment classification program and his plans for upgrading that program to meet the requirements of Item 2.1 (Part 1). The second submittal advised of a schedule change and the third submittal confirmed that the classification upgrade program

C had been completed. A Master Equipment List (MEL) was developed which lists equipment and components and forms the basis for classification and handling of components in documents, drawings, procedures, and information handling systems.

The computerized Maintenance Information Management System (MIMS) which is used to control safety-related activities in the plant including maintenance, modifi-cations, tests, procedures, and parts procurement uses the MEL for classification of components.

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.

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, R. J. Rodriguez, Sacramento Municipal Utility District, to D. G. Eisenhut, NRC, November 4, 1983.

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i REFERENCES (CONT.)

3. Letter, R. J. Rodriguez, Sacramento Municipal Utility District, to J. F. Stolz, NRC, October 5, 1984

4. Letter, R. J. Rodriguez, Sacrament Municipal Utility District, to H. L. Thompson, NRC, May 23, 1985.

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