ML20213G808

SER Re Util 850208 Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs (Reactor Trip Sys Components. Program Acceptable

ML20213G808
Person / Time
Site:	North Anna
Issue date:	05/11/1987
From:	NRC
To:
Shared Package
ML20213G805	List: ML20213G802 ML20213G808
References
GL-83-28, NUDOCS 8705180457
Download: ML20213G808 (3)

Text

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. - , ENCLOSURE SAFETY EVALUATION REPORT GENERIC LETTER 83-26, ITEM 2.1 (PART 2)

VEhDOR INTERFACE PROGRAMS (RTS COMPONENTS)

NORTH ANNA POWER STATION, UNIT 5 1,2 DOCKET N05. 50-338/339 ,

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 teminated manually by the operator about 30 seconds after the initiation of the automatic trip signal.

The failure of the circuit breakers was detemined 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 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 investigation, 1

the Comission (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 pemits to respond to generic issues raised by the analyses of thess two ATWS events.

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This report is an evaluation of the response submitted by Virginia Electric and Power Company, the licensee for the North Anna Power Station, Units 1,2 for

" Item 2.1 (Part 2) 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 2) requires the licensee to confirm that an interface has been established with the NSSS or with the vendors of e,ach of the components of the Reactor Trip System which includes:

periodic communication 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 confirms receipt by the licensee / applicant of transmittals of vendor technical information.

EVALUATION The licensee for the North Anna Power Station, Units 1,2 responded to the require-ments of Item 2.1 (Part 2) with a submittal dated February 8, 19852 . The licensee stated in this submittal that Westinghouse is the NSSS for the North Anna Power Station, Units 1,2 and that the RTS is included as part of the Westinghouse interface program established for this plant. The response also confirms that this interface program includes both periodic communication between Westinghouse and the applicant and positive feedback from the applicant in the form of signed receipts for technical information transmitted by Westinghouse.

CONCLUSION Based on our review of the licensee's response, we find the licensee's state-ments confirm that a vendor interface program exists with the NSSS vendor for components that are required for performance of the reactor trip function. This program meets the requirements of Item 2.1 (Part 2) 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. Virginia Electric and Power Company letter to NRC, W. L. Stewart, to Harold R. Denton, Director, Office of Nuclear Reactor Regulation,

" Revision to Generic Letter 83-28," February 8, 1985.

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EGG-NTA-7625 .

CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC ' LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE NORTH ANNA-1 AND -2 SURRY-1 AND -2 F . G. Farmer Published April 1987 Idaho National Engineering Laboratory EG&G Idaho, Inc.

Idaho falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Consission Washington, D.C. 20555 under DOE Contract No. DE-AC07-761001570 ,

FIN Nos. D6001 and D6002 '

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B ABSTRACT This EG&G Idaho, Inc. report provides a review of the submittals for four of the Westinghouse (W) nuclear plants for conformance to Generic Letter 83-28, Item 2.1 (Part 2). The report includes the following Westinghouse plants, and is in partial fulfillment of the following TAC Nos.:

Plant Docket Number TAC Number t'

North Anna-1 50-338 52858 North Anna-2 50-339 52859 i

Surry-1 50-280 52886 Surry-2 50-281 52881 O

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h FOREWORD This report is provided as part of the program for evaluating Itcensee/ applicant conformance to Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events." This work is conducted for the U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, Division of PWR Licensing-A by EG&G Idaho, Inc.

l The U. S. Nuclear Regulatory Commission funded the work under the authorization, B&R 20-19-19-11-3, FIN Nos. D6001 and 06002.

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i CONTENTS .

ABSTRACT ............................................................. 11 FOREWORD ............................................................. 111

1. INTRODUCTION .................................................... 1 ,

2. REVIEW REQUIREMENTS ............................................. 2

3. GROUP REVIEW RESULTS ............................................ 3 i

4. REVIEW RESULTS FOP. NORTH ANNA-1 AND -2 .. ."...................... 4 d

, 4.1 Evaluation ................................................ 4 4.2 Conclusion ................................................ 4 4

5. REVIEW RESULTS FOR SURRY-1 AND -2 ...........'.................... 5 7

i 5.1 Evaluation ................................................ 5 j 5.2 Conclusion ................................................ 5

6. GROUP CONCLUSION ................................................ 6

7. REFERENCES ...................................................... 7 1

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CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE ,

NORTH ANNA-1 AND -2 SURRY-1 AND -2

1. INTRODUCTION I

On July 8,1983. Generic Letter 83-28, wa.s .tssued by D. G. Eisenhut, Director of the Division of Licensing, Office of Nuclear Reactor

! Regulation, to all licensees of operating reactors, applicants for operating Ilcenses, and holders of construction permits. This letter included required actions based on generic implications of the Salem ATWS events. These requirements have been pubitshed in Volume 2 of NUREG-1000

" Generic Impilcations of ATWS Events at the Salem Nuclear Power Plant.,2 This report documents the EG&G Idaho, Inc. review of the submittals of four of the Westinghouse plants, North Ar.na-1 and -2 and Surry-1 and -2, for conformance to Item 2.1 (Part 2) of Generic Letter 83-28. The submittal from the licensee utilized in these evaluations is referenced in Section 7 of this report.

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2. REVIEW REQUIREMENTS .

i Item 2.1 (Part 2) (Reactor Trio System - Vendor Interface) requires licensees and app 11 cants to establish, implement and maintain a centinuing program to ensure that vendor information on Reactor Trip System (RTS) ,

components is complete, current and controlled throughout the 11fe of the plant, and appropriately referenced or incorporated in plant instructions j and procedures. The vendor interf4ce program is to include periodic  ;

communications with vendors to assure that all, applicable information has j been received, as well as a system of positive feedback with vendors for i mailings containing technical information, e. g., licensee / applicant acknowledgement for receipt of technical information.

That part of the vendor interface program which ensures that vendor f information on RTS components, once acquired, is appropriately controlled, referenced and incorporated in plant instructions and procedures, will be evaluated as part of the review of Item 2.2 of the Generic Letter. '

f j 8ecause the Nuclear Steam System Supplier (NSSS) is ordinar11y also

the supplier of the entire RTS, the NSSS is also the principal source of i f information on the components of the RTS. This review of the licensee and l

applicant submittals will

l I 1. Confirm that the licensee /appilcant has identified an interface with I

either the NSSS or with the vendors of each of the components of the j Reacter Trtp System.

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2. Confirm that the interface identified by licensees /appittants includes periodic connunication with the NSSS or with the vendors of each of l

l the components of the Reactor Trip System.

I j 3. Confirm that the interface identifled by licensees / applicants includes j a system of positive feedback to confirm receipt of transmittals of l technical information.

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3. GROUP REVIEW RESULTS The relevant submittals from each of the included reactor plants were reviewed to determine compliance with Item 2.1 (Part 2). First, the submittals froni each plant were reviewed to establish that Item 2.1 (Part 2) was specifically addressed. Second, the submittals were evaluated j to determine the extent to which 'ach of the plants complies with the staff

! guidelines for Item 2.1 (Part 2) . .

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4. REVIEW RESULTS FOR NORTH ANNA 1 AND -2 4.1 Evaluation .

Virginia Electric and Power Company, the licensee for North Anna-1 and -2, provided their responie to Item 2.1 (Part 2) of the Generic Letter on February 8, 1985. In that response, the licensee confirms that the NSSS for North Anna is Westinghouse and,that the Reactor Trip System (RTS) for North Anna is included as a part of the Westinghcuse interface program established fo'r the North Anna NSSS. ,

The Westinghouse interface program for the NSS$ includes both periodic communication between Westinghouse and Ilcensees/a'pplicants and positive feedback from licensees / applicants in the form of signed receipts for technical information transmitted by Westinghouse.

4.2 Conclusion '

We find the licensee's confirming statement that North Anna is a participant in the Westinghouse interface program for the RPS meets the staf f position on Item 2.1 (Part 2) of the Generic letter and is, therefore, acceptable.

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5. REVIEW RESULTS FOR SURRY-1 AND -2 5.1 Evaluation ,

Virginia Electric and Power Company, the licensee for Surry-1 and 2, provided their response to Ite'm 2.1 (Part 2) of the Generic Letter on February 8, 1985. In that response, the licensee confirms that the NSSS for Surry is Westinghouse and that.the Reactor Trip System (RTS) for Surry is included as a part of the Westinghouse interf ace program established for the Surry NSSS.

The Westinghouse interface program for the NSSS includes both periodic communication between Westinghouse and licensees / applicants and positive feedback from licensees / applicants in the form of signed receipts for technical information transmitted by Westinghouse.

5.2 Conclusion We find the Itcensee's confirming statement that Surry is a participant in the Westinghouse interface program for the RPS meets the staff position on Item 2.1 (Part 2) of the Generic Letter and is, therefore, acceptable.

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6. GROUP CONCLUSION We conclude that the licensee /appitcant responses for the listed Westinghouse plants' for Item 4.5.2 of Generic Letter 83-28 are accep' table.

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7. REFERENCES

1. NRC Letter, D. G. Eisenhut to all Itcensees of Operating Reactors, Applicants for OperatinC 61 cense, and Holders of Construction Permits, i " Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8,1983.

2. Generic Implications of ATWS Events at the Salem Nuclear Power Plant NUREG-1000 Volume 1. Aprt) 1983; volume 2. July 1983.

i 3'. Virginia Electric and Power Company letter to NRC, W. L. Stewart, to Harold R. Denton, Otrector, Office of Nuclear Reactor Regulation,

" Revision to Generic Letter 83-28,' february 8, 1985.

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