ML20236K116

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

ML20236K116
Person / Time
Site:	Millstone
Issue date:	07/29/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236K073	List: ML20236K070 ML20236K081 ML20236K116 ML20244E190
References
NUDOCS 8708060415
Download: ML20236K116 (2)

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 5/  ; '

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Enclosure 2 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GENERIC LETTER 83-28, ITEM 2.1 (PART 2)

VENDOR INTERFACE PP,0 GRAMS fRT5 COMPONENTS)

MILLSTONE NUCLEAR POWER STATION, UNIT 2 DOCKET NO. 50-336

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 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 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 (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." Asaresultofthisinvestigatign, the Commission (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 permits to respond to generic issues raised by the analyses of these two ATWS events.

This report is an eveluation of the response submitted by Northeast Nuclear -

Energy Company, the licensee for the Millstone Nuclear Power Station, Unit 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 each of the components of the Reactor Trip System which includes:

o periodic communication between the licensee / applicant and the NSSS or the vendors of each of the components of the Reactor Trip System, and, o a system of positive feedback which confirms receipt by the licensee /

applicant of transmittals of vendor technical information.

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2.0 EVALUATION -

The licensee for the Millstone Nuclear Power Station, Unit 2, respondeg to the requirements of Item 2.1 (Part 2) with a submittal dated April 2,1987 . The licensee stated in this submittal that Combustion Engineering is the NSSS vendor for the Millstone Unit 2 plant and that the RTS is included as part of the Combustion Engineering interface program established for these plants. The response also confirms that this interface program includes both periodic communication between Combustion Engineering and the licensee and positive ,

feedback from the licensee in the form of signed receipts for technical l information transmitted by Combustion Engineering. i

3.0 CONCLUSION

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, and is therefore acceptable.

4.0 REFERENCES

1. NRC Letter, D. G. Eisenhut to all Licensees of Operating j Reactors, Applicants for Operating License, and Holders of .

Construction Pennits, " Required Actions Based on Generic l Implications of Salem ATWS Events (Generic Letter 83-28)," j July 8, 1983. <

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2. Northeast Utilities letter to NRC, E. J. Mroczka to l Document Control Desk, " Generic Letter 83-28, Salem l ATWS," April 2, 1987.

Attachment:

EGG-NTA-7720 '

Dated: JUL 2 91987 )

Principal Contributor :

D. Lasher

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CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28

, REACTOR TRIP SYSTEM VENDOR INTERFACE CALVERT CLIFFS-1 AND -2 MILLSTONE-2 PALISADES F. G. Farmer Published June 1987

. Idaho National Engineering Laboratory .

EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 I

i Prepared for the  ;

U.S. Nuclear Regulatory Comission .l Washington, D.C. 20555 under 00E Contract No. DE-AC07-161001570 FIN Nos. D6001 and 06002

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l ABSTRACT Tnis'EG&G Idaho, Inc. report provides a review of the submittals for l some of the Combustion Engineering (C-E) nuclear plants for conformance to

' Generic Letter 83-28, Item 2.1 (Part 2). The report includes the following i Combustion Engineering plants, and is in partial fulfillment of the following TAC Nos.:

Plant _

Docket Number TAC Number Calvert C1)ffs-1 50-317 52825 Calvert C11ffs-2 50-318 52826 M111 stone-2 50-336 52855 Palisades 50-255 52864 e

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FOREWORD This report is provided as pa-t 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 i conducted for the U. S. Nuclear Regulatory Comission, Office of ' Nuclear Reactor Regulation, Division of Engineering and System Technology by EG&G l Idaho,.Inc.

The U. S. Nuclear Regulatory Comission funded the work under the

t. authorization, B&R 20-19-19-11-3, FIN Nos. D6001 and 06002.

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CONTENTS ABSTRACT ....................................................... ..... 11 FOREWORD ............................................................. iii

1. INTRODUCTION .................................................. . I

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

3. GROUP REVIEW RESULTS ............................................ 3 4 REVIEW RESULTS FOR CALVERT CLIFFS-1 AND -2 ...................... 4 4.1 Evaluation ................................................ 4 4.2 Conclusion ................................................ 4

5. REVIEW RESULTS FOR HILLSTONE-2 .................................. 5 5.1 Evaluation ................................................ 5 5.2 Conclusion ................................................ 5

6. REVIEW RESULTS FOR PALISADES .................................... 6 6.1 Evaluation ................................................ 6 6.2 Conclusion ................................................ 6  !

7. GROUP CONCLUSION ................................................ 7

8. REFERENCES ...................................................... 8 1

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CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE CALVERT CLIFFS-1 AND -2 MILLSTONE-2 PALISADES 1

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 s

included required actions based on generic implications of the Salem ATWS 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 documents the EG&G Idaho, Inc. review of the submittals of four of the Combustion Engineering plants, Calvert Citffs-1 and -2, M111 stone-2 and Palisades, 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 8 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

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communications with vendors to assure that all applicable information has been received, as well as a system of positive feedback with vendors for mailtr.gs 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 l 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.

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

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

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 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 2.1 (Part 2).

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4. REVIEW RESULTS FOR CALVERT CLIFFS-1 AND -2 5.1 Evaluation i

Baltimore Gas and Electric Company, the licensee f or Calver t Clif f s, provided their response to Item 2.1 (Part 2) of the Generic Letter on April 6, 1987. In that response, the licensee confirms that the NSSS for Calvert Cliffs is Combustion Engineering and that the RTS for Calvert Cliffs is included as a part of the C-E interface program established for the Calvert Cliffs NSSS.

The C-E interface program for the NSSS includes periodic communication between C-E and licensees / applicants such as "INf08ULLETINS" containing information and recommendations concerning C-E systems, a system of

' positive feedback from licensees / applicants in the form of signed receipts for technical information transmitted by C-E, and periodic issuance by C-E of indices of INF0 BULLETINS.

5.2 Conclusion We find the licensee's statement confirming that Calvert Cliffs is a participant in the Combustion Engineering interface program for the RTS, which meets the staff position on Item 2.1 (Part 2) of the Generic Letter, i is acceptable.

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5. REVIEW RESULTS FOR MILLSTONE-2 5.1 Evaluation Northeast Utilities, the licensee for Millstone-2, provided their

. response to Item 2.1 (Part 2) of the Generic Letter on April 2, 1987. In that response, the licensee confirms.that the'NS$$ for Millstone-2 is Combustion Engineering and that the RTS for Millstone-2 is included as a part of the C-E interface program established for the Millstone-2 NSSS.

The C-E interface program for the NSSS includes periodic communication between C-E and licensees / applicants such as "INF0 BULLETINS" containing information and recommendations concerning C-E systems, a system of positive feedback from licensees / applicants in the form of signed receipts

- for technical information transmitted by C-E, and periodic issuance by C-E of indices of INF0 BULLETINS.

5.2 Conclusion We find the licensee's statement confirming that Millstone-2 is a participant in the Combustion Engineering interface program for the RTS, which meets the staff position on Item 2.1 (Part 2) of the Generic Letter, is acceptable.

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6. REVIEW RESUL(S FOR PALISADES 6.1 Evaluation I

Consumers Power, tne licensee for Palisades, provided their response to Item 2.1 (Part 2) of the Generic Letter on.May 8, 1987. In that response, the licensee confirms that the NSSS for Palisades is Combustion Engineering and that the RTS for Palisades is included as a part of the C-E interface progrzm established for the Palisades NSSS.

The C-E interface program for the NSSS includes periodic communication between C-Z and licensees / applicants such as "INF0 BULLETINS" containing information and recommendations concerning C-E systems, a system of positive feedback from licensees / applicants in the form of signed receipts

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for technical information transmitted by C-E, and periodic issuance by C-E of indices of INF0 BULLETINS.

6.2 Conclusion We find the licensee's statement confirming that Palisades is a participant in the Combustion Engineering interface program for the RTS, which meets the staff position on Item 2.1 (Part 2) of the Generic Letter, is acceptable.

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7. GROUP CONCLUSION We conclude that the licensee / applicant responses for the listed Combustion Engineering plants meet the staff position for Item 2.1 (Part 2) of Generic letter 83-28 and are acceptable.

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8. 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. 8altimore Gas and Electric Company letter to NRC, J. A. Tiernan to Office of Nuclear Reactor Regulation, " Additional Information

. Concerning 8G&E Responses to Generic Letter 83-28," April 6, 1987.

4. Northeast Utilities letter to NRC, E. J. Mroczka to Document Control Desk, " Generic Letter 83-28, Salem ATWS," April 2, 1987.

5. Consumers Power letter to NRC, J. L. Kuemin to Document Control Desk,

" Additional Information - Vendor Interface and Equipment Classification - Generic Letter 83-28," May 8, 1987.

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