ML20235X527

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SER Supporting Util Response to Generic Ltr 83-28,Item 2.1, (Part 2) Re Vendor Interface Programs (Reactor Trip Sys Components)
ML20235X527
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 07/20/1987
From:
NRC
To:
Shared Package
ML20235X525 List:
References
GL-83-28, NUDOCS 8707240225
Download: ML20235X527 (3)


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( %54 SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 2)

VENDOR INTERFACE PROGRAMS (RTS COMPONENTS)

HATCH NUCLEAR PLANT UNITS 1&2 DOCKET NOS. 50-321/366

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 seconds after the initiation of the automatic trip signal.  ;

The failure of the circuit breakers was detennined 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 operai;or almost coincidentally with the automatic trip.

Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (ED0), 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, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8,19831 ) i I

all licensees of operating reactors, applicants for an operating license, and holders of construction permits to respond to generic issues raised by the analyses of these two ATWS events.

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This report is an evaluation of the response submitted by Georgia Power Company, the licensee for the Hatch Nuclear Plant, 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.

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Item 2.1 (Part 2) requires the licensee to conform that an interface has been I established with the NSSS or with the vendors of each 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, ,

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i a system of positive feedback which confirms receipt by the licensee / l l applicant of transmittals of vendor technical information.

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l 2.0 EVALUATION The licensee for the Hatch Nuclear Plant, Units 1&2, responded to the require-ments of Item 2.1 (Part 2) with submittals dated November 7,19832 , February 29, 3 4 1984 , and June 3, 1985 . The licensee stated in these submittals that General l

Electric is the NSSS vendor for the Hatch Nuclear Plant, Units 1&2 and that the l RTS is included as part of the General Electric interface program established l l for these plants. The response also confirms that this interface program includes both periodic communication between General Electric and the licensee j l and positive feedback from the licensee in the form of signed receipts for l technical information transmitted by Ger.eral Electric.

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3.0 CONCLUSION

i Based on our review of these responses, we find the licensee's statements 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, ano is therefore acceptable.

4.0 REFERENCES

1. NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicanttt for Operating License, and Holders of Construction Permits, " Required Actions Based on Generic ImplicationsofSalemATWSEvents(GenericLetter83-28),"

July 8, 1983.

2. 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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3. 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.
4. Georgia Power Company letter to NRC, L. T. Gucwa to Director of Nuclear Reactor Regulation, " Response to Request for Additional Information," June 32 1985.

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1 DISCLAIMER 1 I

This book was prepared as an account of work sponsored by an agency of the United j States Government. Nether the United States Govemment nor any agency thereof, l nor any of ther employees, makes any warranty, express or irnplied, or assumes any legal habihty or responsibikty for the accuracy, completenses, or usefulness of ar'y informecon, apparatus, product or process disclosed, or represents that its use would l not istnnge pnvately owned nghts. References heren to any specific commercal product, process, or service by trade name, trademark, manufacturer, or otherwnse, does f et necessanly constitute or imply its endorsement, recommendation, or favonng by the Urwted States Government or any agency thereof. The views and operwons 0 4 authors expressed heren do not necessanly state or reflect those of the United States Govemment or any agency thereof.

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L CONFORMANCE TO l ITEM 2.1 (PART 2) 0F GENERIC. LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE HATCH-1 AND'-2 MILLSTONE-1

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F. G. Farmer Published April 1987 IdahoNationalEngineeringi.aboratory EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 9

Prepared for the '

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 '

Under DOE Contract No. DE-AC07-761001570 FIN Nos. 06001 and 06002 l

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l A8STRACT- 1 I

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

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Letter 83-28, Item 2.1 (Part 2). The report includest'he following General l Electric plants, and is in partial fulfillment of the following TAC Nos.:

Plant Docket Number TAC Number 1

Hatch-1 50-321 52844 Hatch-2 50-366 52845_ )

1 Millstone-l 50-245 52854 l

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'F OREWORD .. j i

This report is provided as part of the program for evaluating licensee / applicant conformance to Generic Letter 83-28, " Required Actions l Based on Ger.eric 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 Consission funded the work under the authorization, B&R 20-19-19-11-3, FIN Nos. 06001 and 06002.

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CONTENTS ABSTRACT ............................................................. 11 FOREWORD ............................................................. 111 4

1. INTRODUCTION .................................................... 1 1
2. REVIEW REQUIREMENTS ............................................. 2
3. GROUP REVIEW RESULTS ....!....................................... 3  !

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4. REVIEW RESULTS FOR HATCH-1 AND -2 ............................... 4 I 4.1 Evaluation ................................................ 4 4.2 Conclusion ................................................ 4
5. REVIEW RESULTS FOR MILLSTONE-1 .................................. 5 5.1 Evaluation ................................................ 5 5.2 Conclusion ................................................ 5-V""'
6. GROUP CONCLilSION ................................................ 6
7. REFERENCES ...................................................... 7 i l

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l CONFORMANCE TO l ITEM 2.1 (PART 2) Of GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR lhTERFACE  !

HATCH..J AND -2 MILLS [0NE-1

1. INTRODUCTION

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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 includedreq$1redactionsbasedongenericimplicationsofthe'SalemATWS events. These requirements have been published in Volume 2 of NUREG-1000,

" Generic Implications of ATWS Events at the Salem Nuclear Power Plant."

This report d'ocuments the EG&G Idaho, Inc. review of the submittals of three of the General Electric plants, Hatch-1 and -2 and M111 stone-1, 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 REQUIREMENT 3 Item 2.1 (Part 2) (Reactor Trip Systein - Vendor interface) requires

~ licensees and applicants to establish, implement and maintain a continuing program to ensure that vendor information' on Reactor Trip System (RTS) compoaents is cortplete, current and controlled throughout the life of the plant, and appropriately referenced o'r 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.

  • 1 That part of the vendor interface program which ensures that vender information on RTS components, once acquired, is appropriately controlled, j

referenced and incorporated in plant instructions and procedures, will be evaluated as part of the review of Item 2.2 of the Generic Letter.

1 Because the Nuclear Steam System Supplier (NSSS)'Is ordinarily also the supplier of the entire RTS, the NSSS is also the principal source of

'nformation on the components of the RTS.

, This review of the licensee and appilcant 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 Ti;)p System.

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2. Confirm that the interface identified by licensees / applicants includes parlodic 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 confirra 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

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submittals from each plant were reviewed to establish that Item 2.1 (Part 2) was specifically addressed. Second, the submittals were evaluated

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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 f6R HATCH-1 AND -2

- 4.1 Evaluation Georgia Power, the licensee for Hatch-1 and -2, provided their responses to Item 2.1 (Part 2) of the Generic Letter on November 7, 1983, February.29, 1984, and June 3, 1985. In those responses, the licensee.

confirms that the NSSS for Hatch-1 and -2 is General Electric and that the Reactor Protection System (RPS) for Hatch, which includes those components necessary to trip the reactor, is included as a part of the GE interface program established for the !iatch NSSS.

l The GE interface program for the NSSS includes both periodic commur.ication between GE and licensees / applicants and aperiodic j 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 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, therefore, acceptable. ,

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5. REVIEW RESULTS FOR MILLSTONE-1 5.1 Evaluation Northeast Utilities, the itcensee for M111 stone-1, provided their response 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

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General Electric and that the Reactor Protection System (RPS) for M111 stone-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 interface program for the NSSS includes both periodic communication between GE and licensees / applicants and aperiodic coremunications such as " Service Information Letters" (SILs) containing l

' information and recommendations concerning GE systems, and a system of l TT'- positive feedback from licensees / applicants in the form of signed receipts for SIls transmitted by GE.

5.2 Conclusion l

l l We find the licensee's confirming statement that Millstone-1 is a participant in the General Electric interface program for the RPS meets the i 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 itcensee/ applicant responses for the listed General Electric plants for Item 4.5.2 of Generic Letter 83-28 are acceptable.

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.1. 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. Generic Implications of ATWS Events at the Salem Nuclear Power Plant NUREG-1000, Volume 1 April 1983; Volume 2, July 1983.
3. 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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4. 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.
5. Georgia Power Company letter to NRC, L. T. Gucwa to Director of Nuclear Reactor Regulation, " Response to Request for Additional Information," June 3, 1985.
6. Northeast Utilities letter to MRC, E. E. Mroczka to Document Control Desk, " Generic Letter 83-28, Item 2.1.2," January 16, 1987.

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2M"2,3' 818UOGRAPHIC DATA SHEET EGG-flTA-7591 348 omst UCr,ONS 0. rene .tvt.sg I firLt .40 $ut tsTL4 J Lt..IBL.ms CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 33-28 REACTOR TRIP SYSTEM VENDOR INTERFACE, HATCH-1 AND -2, MILLSTONE-1 a n.re aucar ==*urio

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. .uracaai April- 1987 F. G. Farmer e o*ri apoar '=ueo a.QN1M v3..

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,o ,,o..o..~o o.c.~ a . r .o. .... ... ...u.o .oo.u. ,, ,_ ,, c , ,,,r,..o,,,,,o.1 Division of PWR Licensing A j Office of Nuclear Reactor Regulation 1 3

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Washington, DC 20555 l 12 sus'.L4 MtN T..v 40148 ,

,3 6857..Cf gJGD mes.e or 'ess, This EG&G Idaho, Inc. report presents the results of our evaluation of the l submittals of some of the Westinghouse nuclear plants for conformance to Generic Letter 83-28, Item 2.1 (Part 2).  ;

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Mr. James P. O'Reilly Edwin I. Hatch Nuclear Plant,  !

Georgia Power Company Units Nos. I and 2 l l

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G. F. Trowbridge, Esq. {

l Shaw, Pittman, Potts and Trowbridge 2300 N Street, N. W.

Washington, D.C. 20037 i

Mr. L. T. Gucwa j l

Engineering Department  !

Georgia Power Company P. O. Box 4545 Atlanta, Goorgia 30302 Nuclear Safety and Compliance Manager Edwin I. Hatch Nuclear Plant {

Georgia Power Company P. O. Box 442 Baxley, Cecrgia 31513 i Mr. Louis B. Long Southern Company Services, Inc.  ;

1 P. O. Box 2625 I Birmingham, Alabama 35202 I Resident Inspector l U.S. Nuclear Regulatory Comission Route 1, P. O. Box 279 Baxley, Georgia 31513 Regional Administrator, Region II O.S. Nuclear Regulatory Commission l 101 Marietta Street, Suite 2900 l Atlanta, Georiga 30323 j i

y Mr. Charles H. Badger i Office of Planning and Budget Room 610 {

270 Washington Street, S.W. 1 i

Atlanta, Georgia 30324 I Mr. J. Leonard Ledbetter, Commissioner Departrnent of Natural Resources j

270 Washington Street, N.W. -

i Atlanta, Georgia 30334 i Chairman '

Appling County Commissioners County Courthouse Baxley, Georgia 31513 i

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