ML20217G007
| ML20217G007 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/03/1997 |
| From: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20217G013 | List: |
| References | |
| 6710-97-2440, NUDOCS 9710090144 | |
| Download: ML20217G007 (2) | |
Text
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l GPU Nucleer,Inc.
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Route 441 South NUCLEAR Post Office Boa 480 Middletown, PA 17057 0480 isl 717-944-7621 4
j October 3,1997 6710 97-2440 a
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Three hiile Island Nuclear Station, Unit 1 (Thil-l)
Docket No. 50-289 Operating License No. DPR-50 Additional Information and Supplement to Technical Specification Change Request (TSCR) No. 268 - OTSG Inspection Criteria for 12R Examinations q,
This letter provides additiona! information in response to NRC questions faxed to GPU Nuclear 1 and discussed in a GPU Nuclear /NRC conference call on September 30,1997 and documented in the NRC's letter dated October 1,1997. Included in attachment I aro replacement pages for pages 4 80 and 4-81 previously submitted with Thil-l License Amendment Reques
' August 12, 1997 (6710-97-2357). The replacement pages incorporate a more restrictive repair limit than that proposed on August 12,1997. Therefore, this revision to the Thil-1 License Amendment Request No. 268 does not afTect the safety evaluation justifying the proposed license amendment and does not change any of the conclusions supporting the no significant hazards consideration analysis provided in TSCR No. 268. The GPU Nuclear response to the NRC's request for additional information is provided as attachment 2.
The attached Technical Specification pages 4-80 and 4 81 are provided to adopt a 0.52 inch circumferential repair limit for inside diameter (ID) intergranular attack (IGA) indications
. instead of the 0.57 inch value originally proposed. Since it was our intent that the degraded tube criteria limit for circumferential extent be one half the repair limit, we are therefore also reducing the corresponding degraded tube criteria limit from 0.28 inches to 0.26 inches. Since the 12R eddy current examination results are unaffected by these changes, which are being requested for Thil-1 Cycle 12 Refueling (12R) Outage examinations and Operating Cycle 12 only, GPU Nuclear prefers to expedite NRC approval of the amendment by accepting the more restrictive limits.
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'6110 97 2440 Page 2 i
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- Also enclosed as attachment 3 is the Certi0cate of Service for this request certifying service to j
the chief executives of the townhip and county in which the facility is located, as well as the i.
designated of6cial of the Commonwealth of Pennsylvania, Bureau of Radiation Protection.
1 l[
Sincerely, AW
$4t/ 4
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l James W. Langenba i Vice President and Director, TMl MRK 4
Attachments: (1) Revised TMl-1 Technical Specification Pages (2) GPU Nuclear Response to NRC Request for Additional Information Regarding Technical Specification Change Request No. 268 i
j (3) Certificate of Service for Supplement to TMI-l License Amendment l
Request No. 268 i
}.
cc:
Administrator, NRC Region I l
TMl Senior NRC Resident inspector j
TMl-1 Senior NRC Project Manager 1
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