ML20084J096
| ML20084J096 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/17/1995 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19344C928 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR C311-95-2190, GL-87-02, GL-87-2, NUDOCS 9506060093 | |
| Download: ML20084J096 (2) | |
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Parsippany. New Jersey 07054 201-316-7000 TELEX 136-482 Wnter's Direct Dial Nurnbet (717) 948-8005 May 17, 1995 C311-95-2190 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Three Mile Island Nuclear Station Unit 1, (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 US! A-46 Seismic Evaluation Report j
On February 9,1987 the NRC issued Generic Letter (GL) 87-02, " Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety issue (USI) A-46". This Generic letter encouraged utilities to participate in a generic program to resolve the seismic verification issues associated with USI A-46. As a result, the Seismic Qualification Utility Group (SQUG) developed the " Generic Implementation procedure (GIP) for Seismic Verification of Nuclear Plant Equipment."
On May 22,1992, the NRC staff issued Generic Letter 87-02 supplement I which required that all addressees provide either (1) a commitment to use both the SQUG commitments and the implementation guidance described in the GIP, Revision 2, as corrected on February 14, 1992, and as supplemented by the staff's Supplemental Safety Evaluation Report No. 2 (SSER-2) or (2) an alternative method for responding to GL 87-02. The supplement also required that those addressees committing to implement GIP-2 provide an implementation schedule as well as detailed information including the procedures and criteria used to generate the instructure response spectra to be used for USI A-46.
By letter dated September 21,1992 GPU Nuclear provided its response to Supplement I to GL 87-02 for Three Mile Island, Unit 1 (TMI-1). In the letter GPU Nuclear committed to follow the SQUG commitments set fonh in the GIP, including the clarifications and exceptions identified in SSER-2. The letter also stated that the GPU Nuclear would submit
[]f. g j the summary report following implementation of GIP-2 by May 22,1995, within three (3)
(b.
years after the issuance of the SSER-2. The NRC staff accepted the GPU Nuclear response in their letter dated November 18, 1992.
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,1 C311-95-2190 Page 2 On August 19,1993 GPU Nuclear submitted infonnation concerning the method of developing in-structure response spectra for the resolution of USI A-46. After the review the NRC staff in their letter dated September 26,1994 concluded that the seismic inputs utilized in the development of the in-stmeture response spectra are in accordance with the licensing l
commitment and it was the staff's judgement that the method used in developing the spectra is consistent with the applicable NRC Standard Review Plan (SRP) provisions and the current staff provisions.
The attached summary repon, "Three hiile Island Unit 1, USI A-46 Seismic Evaluation Report" (Repon No. 42105-002) documents the results of the safe shutdown equipment identification, the screening verification and walkdown, the relay evaluation, the tank and heat exchanger review, the cable and conduit raceway review and the outlier identification and resolution. The report also provides the modification schedule for resolving outliers.
Of the 658 items reviewed during the USI A-46 walkdown eighty two (82) items remain to be m(xlified. The majority (68) of the items will be modified during the upcoming refueling outage iIR which is scheduled to begin in September,1995 while some (14) will be modified during 12R refueling outage scheduled to commence in September,1997. It must be noted that the outliers identified during the walkdown were evaluated for operability concems and as a result some items (5) were repaired immediately.
If you have any questions concerning the information provided in the summary report, please contact bl. Laggart, hianager, Corporate Licensing, at (201) 316-7968.
Sincerely, h~[k d/h T. G. Brou n
Vice President and Director, Th1I YN/ctb I
c: Administrator, Region I Th!I NRC Senior Resident Inspector Th11-1 NRC Senior Project hianager 1
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