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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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
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James W. Langenb h Vice President and Director, TMI AWM Attachment TMI l Senior Resident Inspector f
TMI-I Senior Project Manager
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NRC Regional Administrator, Region I gl s
9709230017 970911 l l l
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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.
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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 leak tested. If any increased leakage above baseline is due to defects in the tube i
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