ML20042A669
| ML20042A669 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/17/1982 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 5211-82-060, 5211-82-60, NUDOCS 8203230666 | |
| Download: ML20042A669 (1) | |
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GPU Nuclear
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Q P.O. Box 480 Middletown, Pennsylvania 17057 717-944-7621 Writer's Direct Dial Number:
March 17, 1982 g
5211-82-060 RECEPMD
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Office of Nuclear Reactor Regulation 7
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Attn: Darrell G. Eisenhut g'
D Director of Division of Licensing am, U.
S. Nuclear Regulatory Commission C
Washington, D.C.
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Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (D1I-1)
Operating License No. DPR-50 Docket No. 50-289 Pressurized Thermal Shock (PTS) to Reactor Pressure Vessel This letter is to keep you appraised of our current efforts in addressing PTS as well as to respond to your letter of 10/23/81 where you encouraged us to provide plant specific information as soon as it is available con-cerning the PTS issue.
As we indicated in our letter of 10/1/81, we intended to submit our plant specific information for the 150 day response consistent with the schedule of the B&W Owners Group program. To facilitate our response, we arranged to have the analysis for D11-1 scheduled subsequent to Oconee 1 submittal.
The analysis has progressed to the point where we can take advantage of experimental results used to develop a benchmarked mixing model for use by the B&W Owners's Group Program.
Since these results are imminent (around the end of March) we have instructed B&W to use the more realistic mixing model in deriving the projected EFPY for various related transients.
Because we are aware of the Staff's needs in obtaining realistic data for a presentation to the Commission, we feel that our response will provide the staff with a logical progression to the results obtained in the Oconee I analysis which used very conservative miximg assumptions.
Additionally, you may be aware that EPRI is also conducting a program of investigating the PTS concern using a representative reactor from each of the main PWR vendors. TMI-l is the B&W reactor represented in this program.
Therefore, we intend to submit our second phase response (150 day response and response to NRC 12/18/81 request for additional information) as soon as the final mixing results can be inputed.into the' B&W 0wner's Group plant specific analysis, subject to our review (estimated completion - 6/82).
We also believe that since the current status of U11-1 is nonoperating, no immediate safety coacerns due to thermal shock are possible.
Sincerely,
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