ML20237B150
| ML20237B150 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/10/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20237B133 | List: |
| References | |
| GL-83-28, NUDOCS 8712160058 | |
| Download: ML20237B150 (3) | |
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l-ENCLOSURE 1 p#%+ -
UNITED STATES y"J
t NUCLEAR REGULATORY COMMISSION 3 k%L()k j WASHINGTON, D. C. 20555 A v g,i g....+
SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 2)
VENDOR INTERFACE PROGRAMS (RTS COMPONENTS)
THREE MILE ISLAND NUCLEAR STATION, UNIT l' DOCKET NO. 50-289
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 tenninated 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 investigation, I
the Consnission (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.
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This report is an evaluation of the response submitted by GPU Nuclear Corporation, the licensee for the Three Mile Island Nuclear Station, Unit 1 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:
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.
2.0 EVALUATION The licensee for the Three Mile Island, Unit 1 plant responded to the require-I ments of Item 2.1 (Part 2) with submittals dated November 8, 1983, August 5,
- 1985, and May 29, 1987. The licensee stated in these submittals that Babcock and Wilcox is the NSSS vendor for the TMI-1 plant and that the RTS is included as part of the Babcock and Wilcox interface program established for this plant.
The response also confirms that this interface program includes both periodic communication between Babcock and Wilcox and the licensee and positive feedback from the licensee in the form of signed receipts for technical information j
transmitted by Babcock and Wilcox.
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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.
GPU Nuclear letter to NRC, H. B. Hukill to Office of Nuclear Reactor Regulation, " Required Actions Based on Generic Implications of Sclem/ATWS Events," November 8, 1983.
3.
GPU Nuclear letter to NRC, R. F. Wilson to Office of Nuclear Reactor Regulation, " Response to NRC Request for Additional Information -
Generic Letter 83-28," August 5, 1985.
4.
GPU Nuclear letter to NRC, H. B. Hukill to Office of Nuclear Reactor
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Regulation, " Response to NRC Request for Additional Information -
GL 83-28 Item 2.1 and 2.2," May 29, 1987.
Principal Contributor:
D. Lasher Dated:
ENCLOSURE 2 EGG-NTA-7756 I
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j CONFORMANCE TO ITEM 2.1.(PART 2) 0F GENERIC' LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE THREE MILE ISLAND-1 F. G. Farmer Published September 1987 Idaho National Engineering Laboratory EG&G Idaho, Inc.
Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Under DOE Contract No. DE-AC07-76ID01570 FIN Nos. D6001 and 06002 O
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1 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 Nucisar Reactor Regulation, Division of Engineering and System Technology by EG&G Idaho, Inc.
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The U.S. Nuclear Regulatory Commission funded the work under the authorization, B&R 20-19-19-11-3, FIN Nos. D6001 and D6002.
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CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE J
THREE MILE ISLAND-1 1.
INTRODUCTION 1
On July 8, 1983, Generic Letter 83-28 was issued by D. G. Eisenhut, 5
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 one of the Babcock and Wilcox (B&W) plants, Three Mile Island-1, 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.
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REVIEW RESULTS FOR THREE MILE ISLAND-1
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GPU Nuclear Corporation, the licensee for Three Mile Island-1 (TMI-1),
provided their responses to Item 2.1 (Part 2) of the Generic Letter on November 8, 1983, August 5, 1985, and May 29, 1987.
In those responses, the licensee confirms that the NSSS for THI-1 is Babcock and Wilcox and that the RTS for TMI-1 is included as a part of the B&W interface program established for the TMI-1 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 cuncerning 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 an on-site representative from B&W.
In addition, the licensee's participation in the B&W Owners Group provides frequent supplementary contact with B&W.
i 3.2 Conclusion We find the licensee's statement confirming that THI-1 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
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acceptable.
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BIBUOGRAPHIC DATA SHEET EGG-NTA-7756 Sat rxstavCTeoms o. T-t ag venst 3 65.vs 96.est 3 vif 64.aso.vetit63 CONFORENCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28,
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REACTOR TRIP SYSTEM VENDOR INTERFACE, THREE MILE ISLAND-1
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This EG&G Idaho, Inc. report presents the results of our evaluation of the submittals of one of the Babcock and Wilcox nuclear plants for conformance to Generic Letter 83-28 Item 2.1 (Part 2).
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