ML20137C297
| ML20137C297 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/14/1997 |
| From: | Ross M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 6710-97-2062, NUDOCS 9703240214 | |
| Download: ML20137C297 (2) | |
Text
-,
W I
s I
t
{
GPU Nuclear,Inc.
(
Route 441 South l
M dd a wn PA 17057-0480 Tel 717-944-7621 3
March 14,1997 6710-97-2062 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Three Mile Island Nuclear Generating Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Independent Core Reload Evaluations NRC review of the final GPU Nuclear Topical Report (TR-092P) supporting the licensing application for TMI-l independent core reload evaluation methodology and criteria is proceeding. Upon receipt of an NRC Safety Evaluation Report approving this remaining Topical Report, GPU Nuclear plans to submit a Technical Specification Change Request to add the NRC approved Topical Reports describing TMI-l core reload evaluations to TMI-l Technical Specification Section 6.9.5.2. This section of the TMI-1 Technical Specifications specifies the approved analytical methods used to determine the TMI-l core operating limits.
It is our understanding that NRC approval of the TMI-l Topical Reports describing the core reload evaluation methods and incorporation of these methods into TMI-l Technical Specification Section 6.9.5.2 will complete the current licensing application and satisfy the associated regulatory requirements allowing continued development of TMI-l cycle-specific core operating limits under 10 CFR 50.59. If the TMI-1 Cycle 12 core reload design remains within the NRC-approved licensing basis, as currently planned, a TMI-l Cycle 12 Reload Report application submittal will not be required. The TMI-1 Cycle 12 Core Operating Limits Report will be submitted to NRC for information upon issuance.
Our present schedule is to submit this Technical Specification Change Request to incorporate the GPU Nuclear NRC approved core reload evaluation methods no later than l
March 31,1997 in order to support TMI-l Cycle 12 core reload evaluation activities.
9703240214 970314
~
h!
PDR ADOCK 05000289 I
~
@%5E%%E%%ll
)
-t, 6710-97-2062 l
Page 2 l
i Additionally, it is noted that Framatome Technologies Topical Report BAW-10192P, Revision 0, February 1994, "BWNT Loss-of-Coolant Accident Evaluation Model for Once-Through Steam Generator Plants" is currently under NRC review for use on TMI-l l
LOCA analyses. NRC estimated approval date of this Topical Report is March 1997.'
This methodology topical also will be incorporated into TMI-l Technical Specification Section 6.9.5.2. Information supporting the application of this Topical Report to TMI-l has been provided to NRC as part of the ongoing review. A TMI-l specific application-i report for the approved methodology will not be submitted. The detailed results of the application of this approved methodology would then be documented in the GPU Nuclear safety evaluation for TMI-1 Cycle 12 core reload design in accordance with 10 CFR 50.59 as outlined above.
1 GPU Nuclear is proceeding with TMI-l Cycle 12 core reload activities, which are planned to be completed by March 31,1997, based on the above approach. It is requested that any questions or concerns regarding this approach be identified prior to this completion date. If any additional information or clarification is required, please contact Mr. David J.
Distel at (201) 316-7955.
Sincerely,
}f M. }. Ross Director, TMI(Acting)
JK/DJD/ cap cc: Administrator, Region I USNRC Senior Project Manager, TMI-l USNRC Senior Resident Inspector, TMI-l i
1