ML20214Q898
| ML20214Q898 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, 05000000 |
| Issue date: | 04/30/1987 |
| From: | Farmer F EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML20214Q884 | List: |
| References | |
| CON-FIN-D-6001, CON-FIN-D-6002 EGG-NTA-7591, GL-83-28, TAC-52844, TAC-52845, TAC-52854, NUDOCS 8706050250 | |
| Download: ML20214Q898 (14) | |
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EGG-NTA-7591 April 1987 INFORMAL REPORT Idaho National CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC Engineering LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE Laboratory HATCH-1 AND -2, MILLSTONE-1 Managed by the U S.
Department F. G. Farmer ofEnergy l
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0706050250 070417 PDR ADOCK 05000245 P
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DISCLAIMER This book was prepared as a 1 account of work sponsored by en agency of the United Stains Government. Nether the United States Gosernment nor any agency thereof, nor any of their employees, makes any warranty, express or imphed, or assumes any legal habaty or resconsibikty for the accuracy. completeness, or usefulness of any inforrnation, apparatus, product or process eisclosed, or represents that its use would not intnnge pnvately owned rights. References herein to any specife commercial product, process. or servce by trade name. trademark, manufacturer, or otherwise, does not necessanly constitute or imply its endorsemeet. recommendation, or favonng by the Uneted States Govemrrent or any agency thereof. The views and opinions of authors expressed herein do not necessardy state or reflect those of the United States Government or any agency thereof.
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EGG-NTA-7591 CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE HATCH-1 AND -2 MILLSTONE-1 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-AC07-76ID01570 FIN Nos, 06001 and 06002
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A8STRACT t
This EG&G Idaho, Inc. report provides a review of the submittals for some of the General Electric (GE) nuclear plants for conformance to Generic l
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Letter 83-28. Item 2.1 (Part 2). The report includes the following General l
Electric plants, and is in partial fulfillment of the following TAC Nos.:
Plant-Docket Number TAC Number l'
Hatch-1 50-321 52844
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Hatch-2 50-366 52845 i
Millstone-1 50-245 52854 1
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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, B&R 20-19-19-11-3, FIN Nos. 06001 and 06002.
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A8STRACT.............................................................
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F O R E WO R D.............................................................
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INTRODUCTION....................................................
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REVIEW REQUIREMENTS.............................................
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GROUP REVIEW RESULTS............................................
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REVIEW RESULTS FOR HATCH-1 ANO -2...............................
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j 4.1 Evaluation................................................
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4.2 Conclusion................................................
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REVIEW RESULTS FOR MILLSTONE-1..................................
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6 5.1 Evaluation................................................
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i 5.2 Conclusion................................................
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GROUP CONCLUSION................................................
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REFERENCES......................................................
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CONFORMANCE TO ITEM 2.1 (PART 0) 0F GENERIC LETTER 83-28 i
REACTOR TRIP SYSTEM VENDOR INTERFACE HATCH-1 AND -2 MILLSTONE-1 1.
INTRODUCTION On July 8, 1983, Generic Letter 83-28 was issued by D. G. Eisenhut, f
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Director of the Division of Licensing, Office of Nuclear Reactor j
Regulation, to all licensees of operating reactors, applicants for I
operating licenses, and holders of construction permits. This letter l
included required actions based on generic implications of the Salem ATWS events. These requirements have been published in Volume 2 of NUREG-1000, j
" Generic Implications of ATWS Events at the S41em Nuclear Power Plant."2 l
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j This report documents the EG&G Idaho, Inc. review of the submittals of j
three of the General Electric plants, Hatch-1 and -2 and M111 stone-1, for j
conformance to Item 2.1 (Part 2) of Generic Letter 83-28.
The submittals from the licensees and applicants utilized in these evaluations are j
referenced in Section 7 of this report.
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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 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 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:
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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.
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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 Systene.
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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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GROUP REVIEW RESULTS l
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 establish that Item 2.1 (Part 2) was specifically addressed.
Second, the submittals were evaluated j
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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REVIEW RESULTS FOR HATCH-1 AND -2 l
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Georgia Power, the licensee for Hatch-1 and
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responses to Item 2.1 (Part 2) of the Generic Letter on November 7, 1983, February 29, 1984, and June 3, 1983.
In those responses, the licensee I
confirms that the NSSS for Hatch-1 and -2 is General Electric and that the l
Reactor Protection System (RPS) for Hatch, which includes those components j
necessary to trip the reactor, is included as a part of the GE interface j
program established for the Hatch NSSS.
3 The GE interface program for the NSSS includes both periodic l
communication between GE and licensees / applicants and aperiodic communications such as " Service Information Letters" (SILs) containing j
information and recommendations concerning GE systems, and a system of
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positive feedback from licensees / applicants in the form of signed receipts for SILs transmitted bl GE.
4.2 Conclusion i
We find the licensee's confirming statement that Hatch 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, l
therefore, acceptable.
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REVIEW RESULTS FOR MILLSTONE-1 5.1 Evaluation Northeast Utilities, the licensee for M111 stone-1, provided their respoase to Item 2.1 (Part 2) of the Generic Letter on January 16, 1987.
In that response, the licensee confirms that the NSSS for Millstone-1 is General Electric and that the Reactor Protection System (RPS) for Millstone-1, which includes those components necessary to trip the reactor, is included as a part of the GE interface program established for the Millstone-1 NSSS.
The GE intc.' face 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.
I 5.2 Conclusion We find the licensee's confirming statement that Millstone-1 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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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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REFERENCES 1.
NRC Letter, D. G. Eisenhut to all licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits,
" Required Actions 8ased on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
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Generic Implications of ATWS Fvents at the Salem Nuclear Power Plant NUREG-1000, Volure 1, April 1983; Volume 2 July 1983.
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Georgia Power Company letter to NRC, L. T. Gucwa to Director of Nuclear Reactor Regulation, " Status Report on Salem Generic Requirements," November 7, 1983.
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Georgia Power Company letter to NRC, L. T. Gucwa to Director of Nuclear Reactor Regulation, " Response to Generic Letter 83-28, Salem Requirements," February 29, 1984.
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Georgia Power Company letter to NRC, L. T. Gucwa to Director of Nuclear Reactor Regulation, " Response to Request for Additional Information," June 3, 1985.
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Northeast Utilities letter to NRC, E. E. Mrotzka to Document Control Desk, " Generic Letter 83-28, Item 2.1.2," January 16, 1987.
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~IQ SPONSORsNG ORGANi2 AbON NAME A40 MAsLING ADOmtSS isarsvarle Cears 1is TYPE 08 AGPOmr Division of PWR Licensing A Office of Nuclear Reactor Regulation
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U.S. Nuclear Regulatory Commission Washington, DC 20555 12 Su**LEMENrany NOTES i3 f_05f m ACT (100 eerwe er esst This EG&G Idaho, Inc. report presents the results of our evaluation of the submittals of some of the Westinghouse nuclear plants for conformance to Generic Letter 83-28, Item 2.1 (Part 2).
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