ML20141E149
| ML20141E149 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/08/1997 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20141E135 | List: |
| References | |
| NUDOCS 9705200346 | |
| Download: ML20141E149 (3) | |
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~ 6.9.5 -
CORE OPERATING LIMITS REPORT 6.9,5.1-The core operating limits addressed by the individual Technical Specifications shall be established and documented in the CORE OPERATING LIMITS REPORT pnor.
to each reload cycle or prior to any remaining part of a reload cycle.
6.9'5.2 The analytical methods used to determine the core operating limits addressed by the individual Technical Specifications shall be those previously reviewed and approved by the NRC for use at TMI-1, specifically:
(1)
BAW-10179 P-A, " Safety and Methodology for Acceptable Cycle Reload Analyses."
t (2)
TR-078-A, "TMI-I Transient Analyses Using the RETRAN Computer Code" (3)
TR-087-A, "TMI-l Core Thermal-Hydraulic Methodology Using the VIPRE-01 Computer Code".
(4)
TR-091-A, " Steady State Reactor Physics Methodology for TMI-1".
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-(5)
TR-092P-A, "TMI-l Reload Design and Setpoint Methodology" 1
The current revision level shall be specified in the COLR.
6.9.5.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient / accident analysis timits) of the safety analysis J
i are met.
e 6.9.5.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or
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supplements thereto, shall be provided upon issuance for each reload cycle to the 4
NRC Document Control Desk with copies to the Regional Administrator and l
Resident Inspector.
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6-19 Aaicisi. cat No.72,77,I 29,I3 7,I41,I'49,150,168,I73 1%
9705200346'970500 l
.PDR ADOCK 05000299 i
P PDR y
1 Certificate of Senice for TMI-l Technical Specification Change Request No. 264 r
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e UNITED STATES OF AMERICA' NUCLEAR REGULATORY COMMISSION--
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IN THE MATTER OF DOCKET NO. 50-289 GPU NUCLEAR INC.
LICENSE NO. DPR-50 CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 264 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given i
below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania;.
- Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, t
Bureau of Radiation Protection, by deposit in the United States mail,' addressed as follows:
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Mr. Darryl LeHew, Chairman Ms. Sally S. Klein, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County.
R. D. #1, Geyers Church Road Dauphin County Courthouse
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Middletown, PA 17057 Harrisburg, PA 17120 Director, Bureau of Radiation Protection PA Dept. of Environmental Resources Rachael Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Att: Mr. Stan Maingi i
GPU NUCLEAR INC.
r BY:
6frEsident and Dihtor, TMI
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((9[97 DATE:
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