ML20217A844
| ML20217A844 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/11/1997 |
| From: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 6710-97-2412, NUDOCS 9709230017 | |
| Download: ML20217A844 (3) | |
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o l GPU Nuciear,Inc.
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Route 441 South NUCLEAR Post Office Con 480 Middletown. PA 17057 0480 6710-97-2412 M 7ums21 U.S. Nuclear Regulatory Commission September 11, 1997 Attn: Decument Control Desk Washington, DC 20555
Dear Sir:
Subject:
Three Mile Island Nueicar Station, Unit 1 (TMI 1) l Operating License No. DPR-50 Dacket No. 50-289 Tecimical Specifications Change Request No. 260 Change in the Trade Name of the Owners and the Operator of TMI Unit 1 - Clarification GPU Nuclear letter to the NRC (6710-96 2361), dated December 16,1996, :ransmitted Technical Specification Change Request No. 260 tc, reflect name changes in the TMI-l license and Technical Specifications.
The purpose of this letter is to provide two clarifications. The first clarification involves the purpose statement given in letter 6710-96-2361. This statement implied that both the TMI-l license and the Technical Specifications would require changes due to the registered trade name "GPU Energy." H<> wever only the TM1 1 license requires a change. The second clarification involves page 6 of the TMI-l license.
A typographical error is on the last line of the page in which a 0.1 was incorrectly typed as 0.2. 'I his error ;
is corrected on the attached revised TMI-l license page 6. GPU Nuclear requests that the attached Till-1 license page 6 replaces the corresponding page contained in the above referenced December 16,1916
, submittal.
These clarifications do not affect the significant hazards censideratien analysis contained in the December 16,1996 GPU Nuclear submittal and are considered administrative chtnges.
Since.x1, 3
- 445 %dA i James W. Langenb h Vice President and Director, TMI AWM Attachment cc
- TMI l Senior Resident Inspector f
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TMI-I Senior Project Manager NRC Regional Administrator, Region I gl (( '
s 9709230017 970911 PDR ADOCK 75000209 ll l l P PDR
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.(8) Repaired Steam Generators in order to confimi the leak-tight integrity of the Reactor Coolant System including the steam generators, operation of the facility shall be in sccordance with the following:
- 1. Prior to initial criticality, GPU Nuclear, Inc. shall submit to NRC the results of the steam gecerator hot test program and a summary ofits management resiew.
- 2.- GPU Ne: lear, Inc. shall confirm baseline primary-to- secondary leakage rate l
established during the steam generator hot test program, ifleakage exceeds the baseline leakage rate by more than 0.1 gpm*, the facility shall be shut down and i leak tested. If any increased leakage above baseline is due to defects in the tube free span, the leaking tubc(s) shall be removed from senice. The baseline leakage j shall be re-established, provided that the leakage limit of Technical Specification 3.1.6.3 is not exceeded.
- 3. GPU % clear, Inc. shall complete its post-critical test program at each power l range (0 5%,5%50%,50%100%) in conformance with the program described in Topical Report 008, Rev. 3, and shall have available the results of that test program and a summary ofits management review, prior to ascension from each power range and prior to normal power operation.
- 4. GPU Nuclear, Inc. shall conduct cddy-current examinations, consistent with the l
extended inservice inspection plan defmed in Table 3.3-1 of NUREG-1019, either 90 calendar days after reaching full power, or 120 calendar days after exceeding 50% power operation, whichever comes first. In the event of plant operation for an extended period at less than 50% power, GPU Nuclear, Inc. shall proside an l
assessment at the end of 180 days of operation at power levels between 5% and -
50%, such assessment to contain recommendations and supporths information as to the riccessity of a special eddy-current testing (ECT) shutdown before the end of the refueling cycle. (De NRC staff will evaluate that assessment and determine the time of the next cddy-current examination, consistent with die other provisions of the license conditions.) In the absence of such an assessment, a special ECT -
shutdown shall take place before an additional 30 days of operation at power above 5%.
- Ifleakage exceeds the baseline leakage rate by more than 0.2 gpm during the remainder of the Cycle 8 operation, the facility shall be shutdown and leak tested. Operation at leakage' rates of up to 0.2 gpm above the baseline leakage rate shall be acceptable during the remainder of Cycle 8 operation. After the 9R refuelinE outage, the leakage limit and accompanying shutdowv requirements revert to 0.1 gpm above the baseline leakage rate.
Amendment No.103, !O d