ML20137M836
| ML20137M836 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/23/1986 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20137M841 | List: |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR 10CFR50.61, 5211-86-2007, NUDOCS 8601290081 | |
| Download: ML20137M836 (2) | |
Text
e GPU Nuclear Corporation ggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
January 23, 1986 5211-86-2007 Office of Nuclear Reactor Regulation Attn:
J. F. Stolz, Director PWR Projects Directorate No. 6 U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 USNRC Final Rulemking - Analysis of Potential Pressurized Therm 1 Shock Events (10CFR50.61)
USNRC Rule 10CFR50.61 requires that licensees submit projected values of reference temperatures for pressurized therm 1 shock evaluation (RTPTS) and the bases for those projections by January 23, 1986.
In accordance with these requirements, enclosed as Attachment 1 is Babcock and Wilcox Owners Group Report BAW-1895, Rev. O entitled " Pressurized Therm 1 Shock Evaluations in Accordance with 10CFR50.61 for Babcock and Wilcox Owners Group Reactor Pressure Vessels".
GPU Nuclear Corporation (GPUN) endorses the Owners Group report with respect to Three Mile Island Unit 1.
The calculated RTpis of the limiting SA-1526 weld is 207*F as of January 23,1986.
As shown in Table 4-4 of Attachment 1, the calculated RTPTS of this limiting weld meets the screening criterion at the expiration of the operating license.
Table 4-4 of Attachment 1 indicates that the calculated RTPTS for the SA-1526 weld will exceed the screening criteria before the 32 EFPY design l ifetime.
GPUN intends to monitor reactor vessel fluence throughout plant life.
If later projections still indicate that the screening criteria will be exceeded during some extended plant life up to 32 EFPY, plant-specific reactor vessel integrity evaluations will be undertaken at the appropriate time, rgj290001060123 h
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GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
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1 5211-86-2007 January 23, 1986 i
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f Also, we are continuing to participate in efforts to refine materials
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chemistry chara(terization, fluence analyses and dosimetry, and further flux j
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Sincerely, Director, TMI-1 SK:HDH:jh 0463A 1
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