ML20153E692

Safety Evaluation Accepting Licensee Program for Equipment Classification & Vendor Interface

ML20153E692
Person / Time
Site:	Wolf Creek
Issue date:	09/01/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20153E683	List: ML20153E681 ML20153E692
References
GL-83-28, NUDOCS 8809060390
Download: ML20153E692 (3)

Text

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'g NUCLEAR REGULATORY COMMISSION

, WASHINGTON, D. C. 20656

1 9.....l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

_ GENERIC LETTER 83-28, ITEM 2.1 (PART 1) -

EQUIPMENT CLAS$1FICAT10N - RTS COMPONENTS GENERIC LETTER 83-28, ITEM 2.1_(PART 2) -

VENDOR INTERFACE PROGRAM - RTS COMPONENTS KANSAS GAS & ELECTRIC _ COMPANY KANSAS CITY POWER AND LIGHT COMPANY KANSAS ELECTRIC POWER COOPERATIVE. INC.

WOLF CREEK GEhERATING STATION DOCKET NO._5_0-482

1.0 INTRODUCTION

On February 25. 1983, both of the scram circuit breaker, at Unit 1 of the

• Salem Nuclear Power Plan 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 circui? breakers was determined to be related to the sticking of the undervoltage trip attachment. Prior to this ir.cident, 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 coincidentally 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 investigatio I. the Comission (NRC) requested (by Generic letter 83-29 dated July 8. 1983 ) all licensees of opersting reactors, applicants for an operating license, and holders of construction pennits to respond t,o generic issues raised by the analyses of these two ATWS events.

This report is an evaluation of the responses submitted by the Wolf Creek Nuclear Operating for Item 2.1 (Part ) Company,(Part and 2) of Generic letter 83-28the licensee for the Wolf treek G The actual documents reviewed as part of this evt.luation are listed in the references et the end of the report. ,

8809060370 0G0901 DR ADOCK 050 2

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Item 2.1 (Part 1) requires the licensee to confim 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 infomation handling systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement.

Item 2.1 (Part 2) requires the licensee to confim 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 comunication between the licensee / applicant and the NSSS or the vendors of each of the components of the Reactor Trip System, and a system of positive feedback which confims receipt by the licensee / applicant of transmittals of vendor technical infomation.

2.5 EVALUATION Item _2.1(Part1)

The licensee for the Wolf Creek Generating Station, Unit I responded to the requirements of item 2.1 (Part 2) with a submittal dated February 29, 1984'.

The Itcensee stated in this ';ubmittal that Westinghouse is the NSSS for the j Wo1f Creek Generating Station, Unit I and that the RTS is included as part of L the Westinghouse interface program established for this plant. The response

also confims that this interface program includes both periodic comunication between Westinghouse and the licensee and positive feedback from the licensee in the fem of signed receipts for technical information transmitted by Westinghouse.

l Item 2.1 (Part 2)

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The licensee for the Wolf Creek Generating Station responded to the 1

requirementsofitem2.1(Part1)githsubmittalsdatedNovember 15, 19833 ,

February 29, 1984 and May 29, 1987 . The initial submittal stated that the Itcensee was developing a list identifying all of the safe.ty-related components that are required to function to trip the reactor and confirmed that this list would be used to verify that these components were identified as safety related in documents, procedures, and infomation handling systems.

The February 29, 1984 response stated that the program would be completed by fuel load. The May 29, 1987 response stated that the program had been implemented and that the Q-list approval process had been changed to provide that the Nuclear Plant Engineering Division now has the responsibility for approving all changes, additions, and revision to the Q-List.

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3.0 CONCLUSION

Item 2.1 (Part 1)

Based on our review, we find the licensee's statements confinn 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 Generic Letter 83-28, and is therefore acceptable.

Item 2.1 (Part 2)

Based on our review of these responses, we find the licensee's staterrents confirm that a vendor interface program exists with the NSSS vendor for cottponents that are required for performance of the reactor trip function.

This program meets the requirerrents of Item 2.1 (Part 2) of Generic letter i 83-28, and is therefore acceptable. ,

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4.0 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 j t

(Generic letter 83-28)," July 8, 1983 ,

2. Letter, Kansas Gas & Electric Company (G. L. Koester) to NRC (H. R. Denton, February 29, 1984

3. Letter Kansas Gas a Electric Company (G. L. Koester) to NRC (H. R. Denton),

November 15, 1983, l i

4 4 Letter Wolf Creek Nuclear Operating Corporation (B. D. Withers) to NRC, May 29, 1987.

f Dated: September 1,1988 Principal Contributors: P. O'Connor, D. Lather l

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