ML15244A347
| ML15244A347 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/11/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML15244A346 | List: |
| References | |
| GL-83-28, NUDOCS 8711100133 | |
| Download: ML15244A347 (11) | |
Text
VP REG,,
o UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ENCLOSURE 1 SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 2)
VENDOR INTERFACE PROGRAMS TRTS COMPONENTS)
OCONEE NUCLEAR PLANT, UNITS 1,2 AND 3 DOCKET NOS. 50-269/27U7287
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 (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 ATWS Events at the Salem Nuclear Power Plant."
As a result of this investigatiqn, 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 evaluation of the response submitted by Duke Power Company, the licensee for the Oconee Nuclear Plant, Units 1,2 and 3 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 nuclear steam system supplier (NSSS) or with the vendors of each of the components of the Reactor Trip System (RTS) 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.
8371110013 '7 0
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-2 2.0 EVALUATION The licensee for the Oconee Nuclear Plant, Units 1,2 and 3 responded to the requirements of Item 2.1 (Part 2) with submittals dated November 4, 1983, August 9, 1985, and June 9, 1987. The licensee stated in these submittals that Babcock & Wilcox is the NSSS vendor for the Oconee plants and that the RTS is included as part of the Babcock & Wilcox interface program established for these plants. The response also confirms that this interface program includes both periodic communication between Babcock & Wilcox and the licensee and positive feedback from the licensee in the form of signed receipts for technical information transmitted by Babcock & Wilcox.
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 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. Duke Power Company letter to NRC, H. B. Tucker to Office of Nuclear Reactor Regulation, November 4, 1983.
- 3. Duke Power Company letter to NRC, H. B. Tucker to Office of Nuclear Reactor Regulation, August 9, 1985.
- 4. Duke Power Company letter to NRC, H. B. Tucker to Office of Nuclear Reactor Regulation, June 9, 1987.
EGG-NTA-7765 CONFORMANCE TO ITEM 2.1 (PART 2) OF GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE OCONEE-1, -2, AND -3 F. G. Farmer Published August 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 No. 06001
ABSTRACT This EG&G Idaho, Inc., report provides a review of the submittals for three of the Babcock and Wilcox (B&W) nuclear plants for conformance to Generic Letter 83-28, Item 2.1 (Part 2).
The report is for Oconee-1, -2, and -3. Docket Nos. 50-269, -270, and -271, and is in partial fulfillment of TAC Nos. 52860, 52861, and 52862.
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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 Engineering and System Technology, 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 No. 06001.
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CONTENTS ABSTRACT FOREWORD.
- 1. INTRODUCTION..................................................
1
- 2. REVIEW REQUIREMENTS............................................
2
- 3. REVIEW RESULTS FOR OCONEE-1, -2, AND -3...................
3 3.1 Evaluation 3
3.2 Conclusion...............................................
3
- 4. REFERENCES 4
iv
CONFORMANCE TO ITEM 2.1 (PART 2) OF GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE OCONEE-1, -2, AND -3
- 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."2 This report documents the EG&G Idaho, Inc., review of the submittals of three of the Babcock and Wilcox (B&W) plants, Oconee-1, -2, and -3, for conformance to Item 2.1 (Part 2) of Generic Letter 83-28. The submittals from the licensee utilized in this evaluation are referenced in Section 4 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 is 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.
2
REVIEW RESULTS FOR OCONEE-1, -9 AND -3 3.1 Evaluation Duke Power Company, the licensee for Oconee-1, -2, and -3, provided their responses to Item 2.1 (Part 2) of the Generic Letter on November 4, 1983, August 9, 1985, and June 9, 1987.
In those responses, the licensee confirms that the NSSS for Oconee is Babcock and Wilcox and that the RTS for Oconee is included as a part of the B&W interface program established for the Oconee NSSS.
The B&W interface program for the NSSS includes communications between B&W and licensees/applicants such as Parts Bulletins, Operating Plant Service Bulletins and Site Instructions, and Preliminary Safety Concerns notices containing information and recommendations concerning B&W systems.
The program also includes a system of positive feedback from licensees and applicants in the form of signed receipts for technical information transmitted by B&W, and periodic notification (not to exceed one year) by B&W of all applicable items sent to Duke Power.
3.2 Conclusion We find the licensee's statement confirming that Oconee is a participant in the Babcock and Wilcox interface program for the RTS, which meets the staff position on Item 2.1 (Part 2) of the Generic Letter, is acceptable.
3
- 4. 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. Duke Power Company letter to NRC, H. B. Tucker to Office of Nuclear Reactor Regulation, November 4, 1983.
- 4. Duke Power Company letter to NRC, H. B. Tucker to Office of Nuclear Reactor Regulation, August 9, 1985.
- 5. Duke Power Company letter to NRC, H. B. Tucker to Office of Nuclear Reactor Regulation, June 9, 1987.
4
t4RC FORM 335, U.S NUCLEAR REGULATORY COMMISSION I REPORT NUMBER IAspeby 7I0C. dad Vel No_,Vdeyo (2-41 32c.22 BIBLIOGRAPHIC DATA SHEET EGG-NTA-7765 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, OCONEE-1, -2, AND -3 4 DATE REPORT COMPLETED MONTH YEAR S.MRSs August 1987 F. G. Farmer
- 6.
DATE REPORT ISSUED MONTH YEAR August 1987 7 PERFORMING ORGANIZATION NAME AND MAILING ADDRESS ictua Z COM
- a. PROCTTASK/WORK UNIT NUMBER EG&G Idaho, Inc.
P. 0. Box 1625
- 10. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS timctudeeCatl 11a. TYPE OF REPORT Division of Engineering and System Technology Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
- b. PERIOD COVERED inc.lusiwermJ Washington, DC 20555 12 SUPPLEMENTARY NOTES i3 ABSTRACT 1200wores 0'ess This EG&G Idaho, Inc. report presents the results of our evaluation of the submittals of three of the Babcock and Wilcox (B&W) nuclear plants for conformance to Generic Letter 83-28, Item 2.1 (Part 2).
t4 DOCUMENT ANALYSIS
- KE WORDSDESCRIPTORS 15 AVAILABILITY STATEMENT Unlimited 16 SECURITY CLASSIFICATION (ths p.pel 1 iDENTIFIERS/OPEN-ENDED TERMS Unclassified (TA,, 'eporr Unclassified 17 NUMBER OF PAGES I8 PRICE