ML20214R068

Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept

ML20214R068
Person / Time
Site:	Brunswick, Duane Arnold, 05000000
Issue date:	04/30/1987
From:	Farmer F EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML20214R064	List: ML20214R062 ML20214R068
References
CON-FIN-D-6001, CON-FIN-D-6002 EGG-NTA-7613, GL-83-28, TAC-52823, TAC-52824, TAC-52835, NUDOCS 8706050331
Download: ML20214R068 (14)

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L INFORMAL REPORT

' idaho National CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC Engineering LETTER 83-28, REACTOR TRIP SYSTEM VENDOR INTERFACE, Laboratoy: ARNOLD, BRUNSWICK-1 AND -2 i

Managed by the U.S. .

i F. G. Farmer Department ofEnergy  ;

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'f4EGEGum Prepared for the Wort Devfonned under y, o,J ffgl'yj ,

U.S. NUCLEAR REGULATORY COMMISSION 8706050331 070417 PDR ADOCK 05000324 P PDR ,

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OlSCLAIMER This book was prepared as an account of work sponsored by an agency of the United States Government. Nether the United States Government not any agency thereof, not any of ther employees, makes any warranty, express or imphed, or assumes any legal habekty or responsability for the accuracy, Completeness, or usefulness of any information, apparatus, product or process disclosed, of represents that its use would not ininnge pnvately owned rights. References heren to any specific commercial prodet, process, or serwce by trade name, trademark, manufacturer, or otherwise, does #U necessanly constitute or imply its endorsement, recommendatet, or favonng by the United States Government or any agency thereof. The wews and openons of authors esprefsej heren do not necessarily state or reflect thoSe of the United States Government or any agency thereof.

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EGG-NTA-7613 CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE ARNOLD BRUNSWICK-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 Commission -

Washington, D.C. 20555 Under DOE Contract No. DE-AC07-761001570 FIN Nos. 06001 and 06002

A8STRACT This EG6G Idaho, Inc, report provides a review of the submittals for some of the General Electric (GE) nuclear plants for conformance to Generic Letter 83-28, Item 2.1 (Part 2). The report includes the following General Electric plants, and is in partial fulfillment of the following TAC Nos.:

Plant Docket Number TAC Number Arnold , 50-331 52835 Brunswick-1 50-325 52823 Brunswick-2 50-324 52824

FOREWORD This report is provided as part of the program for evaluating licensee / 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.

The U. S. Nuclear Regulatory Commission funded the work under the authorization, 86R 20-19-19-11-3, FIN Nos, 06001 and 06002.

CONTENTS A8STRACT ............................................................. 11 FOREWORD ............................................................. 111

1. INTRODUCTION .................................................... 1

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

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

4. REVIEW RESULTS FOR ARNOLD ....................................... 4 4.1 Evaluation ................................................ 4 4.2 Conclusion ................................................ 4

5. REVIEW RESULTS FOR BRUNSWICK-1 AND -2 ........................... 5 5.1 Evaluation ................................................ 5 5.2 Conclusion ................................................ 5

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

7. REFERENCES ...................................................... 7 m

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CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE ARNOLD BRUNSWICK-1 AND 2

1. INTRODUCTION I

On July 8, 1983, Generic Letter 83-28 was issued by D. G. Eisenhut, Director of the Division of Licensing, Office of Nuclear Reactor Regulation, to all licensees of operating reactors, applicants for operating licenses, and holders of construction permits. This letter included required actions based on generic implications of the Salem ATWS events. These requirements have been published in Volume 2 of NUREG-1000, " Generic Impitcations of ATWS Events at the Salem Nuclear Power Plant."

This report documents the EG&G Idaho, Inc. review of the submittals of three of the General Electric plants. Arnold and Brunswick-1 and -2, for conformance to Item 2.1 (Part 2) of Generic Letter 83-28. The submittals from the licensees and applicants utilized in these evaluations are referenced in Section 7 of this report.

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2. REVIEW REQUIREMENTS Item 2.1 (Part 2) (Reactor Trip System - Vendor Interface) requires licensees and applicants to establish, implement and maintain a continuing program to ensure that vendor information on Reactor Trip System (RTS) components is complete, current and controlled throughout the life of the '

plant, and appropriately referenced or incorporated in plant _ instructions and procedures. The vendor interface program is to include periodic communications with vendors to assure that all applicable information has been received, as well as a system of positive feedback with vendors for mallings containing technical information, e.g., licensee / applicant acknowledgement for receipt of technical information.

That part of the vendor interface program which ensures that vendor 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.

Because the Nuclear Steam System Supplier (NSSS) is ordinarily also the supplier of the entire RTS, the NSSS is also the principal source of information on the components of the RTS. This review of the licensee and applicant submittals will:

1. Confirm that the licensee / applicant has identified an interface with either the NSSS or with the vendors of each of the components of the Reactor Trip System.

2. Confirm that the interface identified by licensees / applicants includes periodic communication with the NSSS or with the vendors of each of the components of the Reactor Trip System. ,

3. Confirm that the interface identified by licensees / applicants includes .

a system of positive feedback to confirm receipt of transmittals of 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 from each plant were reviewed to estabitsh that Item 2.1

- (Part 2) was specifically addressed. Second, the submittals were evaluated to determine the extent to which each of the plants complies with the staff guidelines for Item 2.1 (Part 2).

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4. REVIEW RESULTS FOR ARNOLO 4.1 Evaluation Iowa Electric Light and Power Company, the licensee for Arnold, provided their response to Item 2.1 (Part 2) of the Generic Letter on -

February 29, 1984. In that response, the licensee confirms that the NSSS for Arnold is General Electric and that the Reactor Protection System (RPS) '

for Arnold, which includes those components necessary to trip the reactor, is included as a part of the GE Interface program established for the Arnold NSSS.

The GE Interface program for the NSSS includes both periodic communication between GE and licensees / applicants and aperiodic communications such as " Service Information Letters" (SILs) containing information and recommendations concerning GE systems, and a system of positive feedback from licensees / applicants in the form of signed receipts for SILs transmitted by GE.

4.2 Conclusion We find the licensee's confirming statement that Arnold is a participant in the General Electric 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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5. REVIEW RESULTS FOR BRUNSWICK-1 AND -2 5.1 Evaluation Carolina Power and Light Company, the licensee for Brunswick-1 and -2, a provided their response to Item 2.1 (Part 2) of the Generic Letter on November 7, 1983. In that response, the licensee confirms that the NSSS for Brunswick is General Electric and that the Reactor Protection System (RPS) for Brunswick, which includes those components necessary to trip the reactor, is included as a part of the GE interface program established for the Brunswick NSSS.

The GE interface program for the NSSS includes both periodic communication between GE and licensees / applicants and aperiodic communications such as " Service Information Letters" (SILs) containing information and recommendations concerning GE systems, and a system of positive feedback from licensees / applicants in the form of signed receipts for SILs transmitted by GE.

5.2 Conclusion We find the licensee's confirming statement that Brunswick is a participant in the General Electric 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 / applicant responses for the listed General Electric plants for Item 4.5.2 of Generic Letter 83-28 are acceptable.

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7. 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 Impitcations of Salem ATWS Events (Generic Letter 83-28)," July 8,1983.

2. Generic Impitcations of ATWS Events at the Salem Nuclear Power Plant NUREG-1000, Volume 1, April 1983; Volume 2, July 1983.

. 3. Iowa Electric Light and Power Company letter to NRC, R. W. McGaughy to Har61d R. Denton, Director, Office of Nuclear Reactor Regulation, February 29, 1984.

4. Carolina Power and Light letter to NRC, P. W. Howe to D. G. Eisenhut.

Director, Division of Licensing, " Generic Implications of Salem ATWS Events," November 7, 1983.

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