ML20236K385

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Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs (Reactor Trip Sys Components)
ML20236K385
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/04/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236K362 List:
References
GL-83-28, NUDOCS 8708070100
Download: ML20236K385 (2)
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SAFETY E'/AltlATIriN LY THE OFFICE OF NUCLEAP REACTOR PECULATION GENERIC LETTER E3-78, ITEM ?.1 (PART 2)

VENDOR INTERFACE PPDGRAMS (RT5 COMPONENTS)

P U.l 5 TONE NUCLEAR POWER STATION, UNIT 3 DOCKET NOS. 50 623

1.0 INTRODUCTION

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 seconos after the initiation of the autometic trip sisral.

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.sional was generated based on steam generator low-low level during plant start-up. In this case, the reacter was trippec tranually by the operator elmost coincidentally with the auton.atic trip.

Following these incic'ents, on February 28, 1983, the NRC Executive Director for l Operations (ED0), directed the staff to investigate and report on the generic l implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant.

The results of the staff's incuiry into the generic implications of the Salem unit incidents are reported in NUREG-1000, " Generic Implications of the ATWS Events at the Saler Fuclear Power Plant." Asaresulti,'thisinvestigatign,  ;

the Commission (NRC) recuested (by Generic Letter 83-28 dated July 8, 1C83 i all licensees of operating reactors, applicants for an operating licerse, and holders of construction permits tc respond to generic issues raised by the analyses of these two ATWS events.

This report is an evaluation of the response submitted by Northeast Nuclear Energy Company the licensee for the Millstone huclear Power Station, Unit 3, for Item 2.1 (Part P1 of Generic Letter 83-28. The actual docurents reviewec as part of this evaluatinn are listed in the references at the end of the re. port.

Item 2.1 (Part 2) requires the licensee to confirri that an interface has been established with the NSSS or with the vendors of each of the components of the Ptuctor Trip System which includes:

periodic communication between the licensee /aprlican' and the NSSS or the vendors of each of the components of the Reactor Trip Syster., j and, a system of positive feedback which confirms receipt by the licensee /

applicent of transmittals of ver. dor technical information.

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2.0 Ei4t'lAT!0N The lictrsee for the Pillstonc Nuclear rc wer Station, Unit ? responced to-thc l rec:uirements of Iter ?.1 (Part 21 witt a submitte' dateo November 8, 198?'  ;

The licensee stateo' ir this subnittal that kcetinghcuse is the NSSS verdor #cr i the Millstone, Ur;it ? Plant end that the kiS is included as part of the l Westir.ghouse interface progr am es tal lished for this plant. Thc response o it confirros that this ir.terface prcgrar incleces both periodic communication, between Westingtcuse and the licensee and positive feedback from the lictriee in the form of signed receiptr for technical informet'on transrritted by i Westinghouse. i

'.0 CONCLUSION Pased or our review of these responses, we find the licenset's stater.crts

. ccn'irm that a vendor inter # ace prograt' exists with the NSSS ver. dor for componerits that arc recuired for perforra6rce of the reector trip fLrction.

This prcgram meets the requirements of iter' P.1 (Part P' of the Generic letter 83-28, and is there' ore acceptable.

l 4.0 P F FF R E_N_ C_E_S

1. NPC Letter, D. C. Eisenhut to all Licensees of Operating I Reacters, Applicants for Operating Licer.se, and Holders of Construction Perrits, "Pequired Actior.s Basad on Ger eric Implications of Salem ATWS Ever.ts (Generic Letter A3-2fi,'

July E:, 1983.

T. Northeast Utilities letter to NRC, V. G. Counsil to D. G. Eisenhut. Director, Division of Licensing, Response to Generic letter 03-?8, Generic Implications of Saler ATWS Fvents ," t'ovember 8,19?3.

Attachrent:

[GC-NTA-7f41 Dated: 3 Prfrcical Contributor:

D. Lashcr

EGG-NTA-7641

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CCNFCRMANCE TO j ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDCR INTERFACE DIABLO CANYON-1 AND -2 MILLSTONE-3 I l^ l l

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F. G. Farmer l

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Puoitshed April 1987 Idaho National Engineering Laboratory EG&G Idaho, Inc.  ;

Idaho Falls, Idaho 83415 l Prepared for the U.S. Nuclear Regulatory Commission

. Washington, D.C. 20555 Under DOE Contract No. DE-AC07-761D01570 FIN Nos. D6001 and D6002

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ABSTRACT This EG&G Idano, Inc. report provides a review of the submittals for j three 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, anc is in partial fulfillment of the following TAC Nos.

Plant Docket Number TAC Numoer Diablo Canyon-1 50-275 52832 l

Dia:10 Cany:n-2 50-323 61717 Millstone-3 50-423 G0388 i

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FOREWORD This recort is provided as part of the program for evaluating licensee /acolicant conformance to Generic Letter $3-28, "Recuired Actions j Sasec on Generic Implications of Salem ATWS Events." This work is concuctec for the U. S. Nuclear Regulatory Commiss;cn, 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 j 1

autheri:ation, E&R 20-19-19-11-3, FIN Nos. D6001 and 06002. '

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. CONTENTS I _

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4. REVIEW RESULTS FOR DIABLO CANYON-1 AND -2 . .. .. .... . 4 4.1 Evaluation . .. . . .. . . . ... . . . .

A 4.2 Conclusion ......... .... ...... . ..... .... . ......... 4

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st V..42: nE.UL,,5 d ,0n r M,ILLSTCNt-3 .. ... ..... . ... ..... .... t l

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5.1 tvaluation . . ..... . . ... .. .... ........ . .. ... 5 5.2 Conclusion . ... . .. . . . .. ... ... ... 5

6. GRCUP CCNCLUSION . .... . . . .. .. .. ...... ....... 6  ;
7. REFERENCES .. ..... . ... . .......... . ....... . ... . . . 7 i

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l CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 53-28 REACTOR TRIP SYSTEM VENDOR INTERFACE q DIABLO CANYON-1 AND -2 MILLSTCNE-3

1. INTRODUCTION l

l On July 5, 1983, Generic Letter 83-281 was issued by D. G. Eisennut, Director of the Division of Licensing, Office of Nuclear Reactor l

Regulation, to all licensees of operating reactors, applicants for l operating licenses, and holders of construction permits. This letter incluced recuired actions based on generic implications of the Salem ATWS events. These requirements have been published in Volume 2 of NUREG-10CO,  ;

" Generic Implications of ATWS Events at the Salem Nuclear Power Plant."2 This report cocuments the EG&G Icaho, Inc. review of the submittals of three of tne Westinghouse plants, Diablo Canyon-1 and -2 and Millstone-3, for conformance to Item 2.1 (Part 2) of Generic Letter 83-28. The submittals from the licensees utilized in these evaluations are referenced in Section 7 of nis report.

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2. REVIEW REQUIREMENTS i

Item 2.1 (Part 2) (Reactor Trip System - Vendor Interface) requires licensees and applicants to establish, implement and maintain a continuing crogram to ensure that verdor information on Reactor Trip System (RTS) l l

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 /acolicant acknowledgment for receipt of technical informa+. ion.

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That part of tne 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 evalaated as part of the review of Item 2.2 of tne 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 interf ace with either the NSSS or with the vencors of each of the components of the l 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 comoonents of the Reactor Trip System.

3. Confirm that the interf ace identified by licensees / applicants includes a system of positive feedback to confirm receipt rf 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 su0mittals from each plant were reviewed to establish 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.I (Part 2).

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i 4 REVIEW RESULTS FOR DIABLO CANYON-1 AND -2 4.1 Evaluation Pacific Gas and Electric Comoary, the licensee for Diaolo Canyon-1 anc -2, provided their responses to Item 2.1 (Part 2) of the Generic Letter

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on April 18, 1955, and March 24, 1987. In those responses, the licensee 1 confirms that the NSSS for Diablo Canyon is Westinghouse and that the l Reactor Trip System (RTS) for Diabic Canyon is included as a part of the Westinghouse interface program established for the Diablo Canyon NSSS.

l The Westinghouse interface program for the NS$$ includes both periodic )

communication cetween WestinghoL,e and licensees / applicants 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 Diablo Canyon is a participant in the Westinghouse interface program for the RPS meets the i staff pcsition on Item 2.1 (Part 2) of the Generic Letter and is, therefore, acceptable.

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5. REVIEW RESULTS FOR MILLSTONE-3 4

l l 5.1 Evaluation i i

Nortneast Utilit es, tne licensee for Millstone-3, provicec their i

response to Item 2.1 (Part 2) of the Generic Letter on November 8,1983.

In that response, the licensee :c 'irms that the NSSS for Millstone-3 is Westinghouse and th1t the Reactor Trip System (RTS) for Millstone-3 is i included as a part 7f the Westinghouse interface program established for l l

theMillstone-3NS$d.

1 The Westinghouse interface program for the NSSS incluces both periodic  !

communication between Westinghouse and licensees / applicants and positive e feecback from licensees / applicants in the form of signed receipts for technical information transmitted by Westinghouse.

5.2 Conclusion l l

l We find the licensee's confirming statement that Millstone-3 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. i I

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    • 6. GROUP CONCLUSION We conclude that the licensee / applicant responses for the listed Westinghouse 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 Implications of Salem ATWS Events (Generic Letter 83-23)," July 8, 1983.

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2. Generic Implications of ATWS Events at the Salem Nuclear Power Plant I NUREG-1000, Volume 1, April 1983; Volume 2, July 1983.
3. Pacific Gas and Electric Company letter to NRC, J. D. Schif fer to G.

W. Knighton, Chief, Division of Licensing, " Generic Letter 83-28 Additional Information," April 18, 1985. l 4 Pacific Gas anc Electric Company letter to NRC, J. D. Schiffer to Document Control Desk, March 24, 1987. i i

5. Northeast Utilities letter to NRC, W. G. Counsil to D. G. Eisenhut, Director, Division of Licensing. " Response to Generic Letter 83-28, Generic Implications of Salem ATWS Events," November 8, 1983.

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