ML13308A983
| ML13308A983 | |
| Person / Time | |
|---|---|
| Site: | Point Beach, San Onofre, 05000000 |
| Issue date: | 04/30/1987 |
| From: | Farmer F EG&G Idaho, Idaho National Engineering & Environmental Lab (INEEL) |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13308A982 | List: |
| References | |
| CON-FIN-D-6001, CON-FIN-D-6002, GL-83-028, TAC-52868, TAC-52869, TAC-52878 EGG-NTA-7642, NUDOCS 8706260324 | |
| Download: ML13308A983 (15) | |
Text
EGG-NTA-7642 April 1987 INFORMAL REPORT Idaho CONFORMANCE TO ITEM 2.1 (PART 2) OF GENERIC Engineering LETTER 83-28, REACTOR TRIP SYSTEM VENDOR Laboratory INTERFACE, POINT BEACH-1 AND -2, SAN ONOFRE Managed by the U S, Department F. G. Farmer of Energyv EGzGldaho Work erfomed nderPrepared for the DOE~otractU.S.
NUCLEAR REGULATORY COMMISSION No DE ACO7 76/DO157 976260324 87056 PDR ADOCK 050002 6 P
DISCLAIMER This book was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
EGG-NTA-7642 CONFORMANCE TO ITEM 2.1 (PART 2) OF GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE POINT BEACH-1 AND -2 SAN ONOFRE-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-ACO7-76ID01570 FIN Nos. D6001 and 06002
ABSTRACT This EG&G Idaho, Inc. report provides a review of the submittals for 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, and is in partial fulfillment of the following TAC Nos.:
Plant Docket Number TAC Number Point Beach-1 50-266 52868 Point Beach-2 50-301) 52869 San Onofre-1 50-206J 52878 11
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. D6001 and D6002.
111
CONTENTS ABSTRACT..........................................................
11 FOREWORD
- 1. INTRODUCTION.............................................
1.....
- 2.
REVIEW REQUIREMENTS............................................
2
- 3. GROUP REVIEW RESULTS...........................................
3
- 4.
REVIEW RESULTS FOR POINT BEACH-1 AND -2.........................
4 4.1 Evaluation..............................................
4 4.2 Conclusion 4
- 5.
REVIEW RESULTS FOR SAN ONOFRE-1................................
5 5.1 Evaluation...........................................
5 5.2 Conclusion................................................ 5
- 6. GROUP CONCLUSION..............................................
6
- 7.
REFERENCES 7
iv
CONFORMANCE TO ITEM 2.1 (PART 2) OF GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE POINT BEACH-1 AND -2 SAN ONOFRE-1
- 1. INTRODUCTION On July 8, 1983, Generic Letter 83-281 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 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 three of the Westinghouse plants, Point Beach-1 and -2 and San Onofre-1, 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 this report.
1
- 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., licersee/applicant acknowledgment 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.
2
- 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).
3
- 4. REVIEW RESULTS FOR POINT BEACH-1 AND -2 4.1 Evaluation Wisconsin Electric Power Company, the licensee for Point Beach-1 and -2, provided their response to Item 2.1 (Part 2) of the Generic Letter on April 5, 1984. In that response, the licensee confirms that the NSSS for Point Beach is Westinghouse and that the Reactor Trip System (RTS) for Point Beach is included as a part of the Westinghouse interface program established for the Point Beach NSSS.
The Westinghouse interface program for the NSSS includes both periodic communication between Westinghouse 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 Point Beach 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.
4
- 5.
REVIE RESULTS FOR SAN ONOFRE-1 5.1 Evaluation Southern California Edison Company, the licensee for San Onofre-1, provided their response to Item 2.1 (Part 2) of the Generic Letter on November 28, 1983. In that response, the licensee confirms that the NSSS for San Onofre-1 is Westinghouse and that the Reactor Trip System (RTS) for San Onofre-1 is included as a part of the Westinghouse interface program established for the San Onofre-1 NSSS.
The Westinghouse interface program for the NSSS includes both periodic communication between Westinghouse and licensees/applicants and positive feedback from licensees/applicants in the form of signed receipts for technical information transmitted by Westinghouse.
5.2 Conclusion We find the licensee's confirming statement that San Onofre-1 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.
- 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.
6
- 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 83-28)," 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. Wisconsin Electric Power Company letter to NRC, C. W. Fay, to H. R. Denton, Director, Office of Nuclear Reactor Regulation, "Required Actions Based on Generic Implications of Salem ATWS Events,"
April 5, 1984.
- 4. Southern California Edison Company letter to NRC, M. 0. Medford to Director, Office of Nuclear Reactor Regulation, "Generic Implications of Salem ATWS Events (Generic Letter 83-28)," November 28, 1983.
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NRC FORM 335 U..
NUCLEAR REGULATORY COMMISSION 1
REPORT NUMBER (Auipwdby TIOC, add Vol No, dt any) 12-41 32c13202 BIBLIOGRAPHIC DATA SHEET EGG-NTA-7642 SEE INSTRUCTIONS ON THE REVERSE 2 TITLE AND SUBTITLE J LEAVE BLANK CONFORMANCE TO ITEM 2.1 (PART 2) OF GENERIC LETTER 83-28, REACTOR TRIP SYSTEM VENDOR INTERFACE, POINT BEACH-1 AND -2, SAN ONOFRE-1
- 4. DATE REPORT COMPLETED MONTH YEAR
. AUTHoRss April 1987 F. G. Farmer
- 6. DATE REPORT ISSUGO MONTH YEAR April 1987
- 7. PERFORMING ORGANIZATION NAME AND MAILING ADDRESS IIctudleZ COa
- 8. PROJECTITASKMWORK UNIT NUMBER EG&G Idaho, Inc.
P. 0. Box 1625 oIN OR GRANT NUMIER Idaho Falls, Idaho D6001/D6002
- 10. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS (Inefuelip CoA I1. TYPE OF REPORT Division of PWR Licensing A Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
- b. PERIOD COVERED inclusie dorm)
Washington, DC 20555 12 SUPPLEMENTARY NOTES
- 13. ABSTRACT (200 words r eul 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).
14 DOCUMENT ANALYSIS
- KE"WORDS/OESCRIPTORS 15 AVAILABILITY STATEMENT Unlimited 16 SECURITY CLASSIFICATION
. i0ENTIFIERS/OPEN-ENDED TERMS Unclassified (Th,,s report)
Unclassified
- 17. NUMBER OF PAGES 18 PRICE