Text

SER Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.1 (Part 2) Requirement to Confirm That Interface Program Exists W/Nsss Vendor for Components Required for Performance of RTS Function
	ML14188B270
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Site:	Robinson
Issue date:	01/20/1987
From:	; Office of Nuclear Reactor Regulation
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ML14188B269	List: ML14188B268; ML14188B270;
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	GL-83-028 NUDOCS 8701210452
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SAFETY EVALUATION REPORT GENERIC LETTER 83-27, ITEM.1 (PART ?I VENDOR INTERFACE PROGRAMS (RTS COMPONENTS)

H. R. RORTNSON STEAM ELECTRIC PLANT, uNIT 2 DOCKET NO. 50-?61 On February 25, 1q83, both of the scram circuit breakers at Unit I of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip sional 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 2?,

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 (EDO), 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 AT14S Events at the Salem Nuclear Power Plant."

As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28 dated luly 8, 1983 1) all licensees of operating reactors, applicants for an operating license, and holders of construction permits to respond to generic issues raised by the analyses o these two ATWS events.

8701210452 870120 PDR ADOCK 05000261 P

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This report is an evaluation of the response submitted by Carolina Power and Light Company, the licensee for the H. B. Robinson S. E. Plant, Unit 2, for Item 2.1 (Part 2) of Generic Letter 83-?8. 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:

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

EVALUATION The licensee for the H. B. Robinson S. E. Plant, Unit 2 responded to the require ments of Item 2.1 (Part 2) with a submittal dated November 7, 1832. The licensee stated in this submittal that Westinghouse is the NSSS for the H. R. Robinson S. E. Plant, Unit 2 and that the RTS is included as part of the Westinghouse interface program established for this plant. The response also confirms that this interface program includes both periodic communication between Westinghouse and the licensee and positive feedback from the licensee in the form of signed receipts for technical information transmitted by Westinghouse.

-3 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 ?.I (Part 2 of the Generic Letter 83-?8, and is there fore acceptable.

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-?8)," -uly 8, 1983.

2. Carolina Power and Light letter to NRC, A. B. Cutter to D. G. Eisenhut, Director, nivision of Licensing, "Generic Implications of Salem ATWS Events," November 7, 1q83.

EGG-NTA-7448 INPUT FOR SAFETY EVALUATION REPORT KEWAUNEE NUCLEAR POWER PLANT McGUIRE NUCLEAR STATION UNITS 1 AND 2 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNITS 1 AND 2 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 SALEM GENERATING STATION UNITS 1 AND 2 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 SOUTH TEXAS PROJECT UNITS 1 AND 2 VIRGIL C. SUMMER NUCLEAR STATION TROJAN NUCLEAR PLANT REACTOR TRIP SYSTEM VENDOR INTERFACE ITEM 2.1 (PART 2) OF GENERIC LETTER 83-28 F. G. Farmer Published November 1986 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-ACO7-761DO1570 FIN Nos. D6001 and D6002

ABSTRACT This EG&G Idaho, Inc. report provides a review of the submittals for some of the Westinghouse (W) nuclear plants for conformance to Generic Letter 83-28, Item 2.1 (Part 2).

The report includes the following plants, all Westinghouse, and is in partial fulfillment of the following TAC Nos.:

Plant Docket Number TAC Numbee Kewaunee Nuclear Power Plant 50-305 52848 McGuire Nuclear Station Unit 1 50-369 52852 McGuire Nuclear Station Unit 2 50-370 52853 Prairie Island Unit 1 50-282 52870 Prairie Island Unit 2 50-306 52871 Robinson 2 50-261 52875 Salem Unit 1 50-272 52876 Salem Unit 2 50-311 52877 Shearon Harris Unit 1 (OL) 50-400 N/A South Texas Unit 1 (OL) 50-498 N/A South Texas Unit 2 (OL) 50-499 N/A Virgil C. Summer 50-395 52885 Trojan Nuclear Plant 50-344 52890

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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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CONTENTS ABSTRACT..........

FOREWORD..........

1.

INTRODUCTION.......................................

2.

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

3.

GROUP REVIEW RESULTS................................********

3

4.

REVIEW RESULTS FOR KEWAUNEE NUCLEAR POWER PLANT..................

4 4.1 Evaluation................................**********..

4.2 Conclusion...........................................

5. REVIEW RESULTS FOR McGUIRE NUCLEAR STATION UNITS 1 AND 2........

5 5.1 Evaluation........................................

5 5.2 Conclusion........................................

5

6.

REVIEW RESULTS FOR PRAIRIE ISLAND NUCLEAR GENERATING6 PLANT UNITS 1 2........................................6 6.1 Evaluation.......................................

6 6.2 Conclusion.................................................

6

7.

REVIEW RESULTS FOR H. B. ROBINSON STEAM ELECTRIC PLANT,7 UNIT NO. 2............................................7 7.1 Evaluation 7.2 Conclusion.....................................7

8.

REVIEW RESULTS FOR SALEM GENERATING STATION UNITS 1 AND 2....

8 8.1 Evaluation.....................................

8 8.2 Conclusion......................................

8

9.

REVIEW RESULTS FOR SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1.............................................9 9.1 Evaluation....................................9 9.2 Conclusion........................................9

10.

REVIEW RESULTS FOR SOUTH TEXAS PROJECT UNITS 1 AND 2..............

10 10.1 Evaluation......................................

10 iv

10.2 Conclusion.................

10

11.

REVIEW RESULTS FOR VIRGIL C. SUMMER NUCLEAR STATION..............

11 11.1 Evaluation...............................

- - - - 11 11.2 Conclusion...............................

- - - - II

12.

REVIEW RESULTS FOR TROJAN NUCLEAR PLANT.........................

12 12.1 Evaluation...................... *******.............. 12 12.2 Conclusion............................

............. 12

13.

GROUP CONCLUSION.-.................... ******............13

14.

REFERENCES...............

V

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

KEWAUNEE NUCLEAR POWER PLANT McGUIRE NUCLEAR STATION UNITS 1 AND 2 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNITS 1 AND 2 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 SALEM GENERATING STATION UNITS 1 AND 2 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 SOUTH TEXAS PROJECT UNITS 1 AND 2 VIRGIL C. SUMMER NUCLEAR STATION TROJAN NUCLEAR PLANT

1. INTRODUCTION On July 8, 1983, Generic Letter 83-281 was issued by 0. 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 Implications of ATWS Events at the Salem Nuclear Power Plant."

This report documents the EG&G Idaho, Inc. review of the submittals of a group of Westinghouse plants including Kewaunee, McGuire Units 1 and 2, Prairie Island Units 1 and 2, Robinson 2, Salem Units 1 and 2, Shearon Harris Unit 1, South Texas Units 1 and 2, Summer and Trojan 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 14 of this report.

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 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:

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 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 KEWAUNEE NUCLEAR POWER PLANT 4.1 Evaluation Wisconsin Public Service Corporation, the licensee for Kewaunee, provided their response to Item 2.1 (Part 2) of the Generic Letter on November 15, 1984. In that response, the licensee confirms that the NSSS for Kewaunee is Westinghouse and that the RTS for Kewaunee is included as a part of the Westinghouse interface program established for the Kewaunee NSSS.