ML20011D966
| ML20011D966 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/22/1989 |
| From: | Silady J COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20011D967 | List: |
| References | |
| GL-88-16, NUDOCS 9001030249 | |
| Download: ML20011D966 (2) | |
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Commonwellth E2 son
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I Projects and Construction Servicts e
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.1400 Opus Plac), Sult) 500 Downers Grove, Illinois 60515 j
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December 22, 1989
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Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555.
I Subject LaSalle County Station Unit 1 Cycle 4 Reload Core Operating Limits Report NRc Docket No. 50-373 References (a):
J.A. Silady letter to Dr. T.E. Murley.
LaSalle County Nuclear Power Station Units 1 and 2 Proposed Amendment to Remove Cycle-Specific Core Limits from the Technical Specifications, dated August 18, 1989.-
(b):
P.C. Shemanski letter'to T.J. Kovach dated December 18, 1989, issuing the SER for Amendments 70 and 54 to NPF-11 and NPF-18, respectively.
j Dr. Murley:
q LaSalle Unit 1, which has completed its third cycle of operation is currently preparing for Cycle 4 startup. The purpose of this letter is l
twofold (1) to advise you of Conunonwealth Edison's intentions to' review and approve the Cycle'4 reload under the provisions of 10 CFR 50.59, and (2) to transmit the attached Core Operating Limits Report (COLR):for the upcoming i
cycle consistent with Generic Letter 88-16. Note that: Edison submitted the necessary Technical Specification changes in Reference (a).to implement-the Core Operating Limits Report. Edison's 10 CFR~50.59 evaluation is based.on NRC approval of this amendment which was recently' received in Reference (b).
Cycle 4 startup is currently expected to' occur no earlier than December 28.-
1 1989.
1 The LaSalle Unit 1 Cycle 4 core consists of NRC. approved fuel designs'
'I and was designed to operate under the currently approved fuel design parameters, Technical Specifications, and related bases such that:
1 (a) Core operating characteristics will be less limiting than those-previously reviewed and accepted; or 9001030249 891222 a
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'Dr. T.E. Murley December 22,.1989-
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l (b) For those postulated incidents analyzed and reported in the Final
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Safety Analysis Report (FSAR) which could potentially be affected by
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t the fuel reload, re-analysis using NRC approved methods has demonstrated that the results of the postulated events are within j
allowable limits.
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The Cycle 4 reload core contains 172 fresh fuel assemblies of type j
"GE9B".
Although this represents the first use of this fuel design at i
LaSalle, the GE9B design was previously approved by the NRC in Amendment 9 to i
GESTAR (NEDE-24011). Commonwealth Edison has performed a' detailed review of the relevant licensing documents, the bases, and references. Based on this review, a safety evaluation was performed as required by 10 CPR 50.59(a,b). -
As in the past, the General Electric licensing analysis documents were prepared using previously approved methodologies as reported in the latest j
revision of NEDE-24011, the FSAR, and other generically approved documents.
Edison has reviewed the cycle-specific licensing analysis.results and d
concluded that no unreviewed safety questions exist as a result of this reload and that additional Technical Specification changes.are not required for Cycle 4 operation at LaSalle Unit 1.
The LSCS On-Site Review of the reload 10 CFR 50.59 evaluation has been completed and the Off-Site Review is in progress.
Therefore, NRC review and approval of the cycle-specific analysis are not required for resumption of operation with the Cycle 4 reload core.
Please contact this office should further information be required.
Very truly yours, d.
7 J.A. Silady Nuclear Licensing Administrator im i
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Attachment:
LaSalle Unit 1 Reload 3 (Cycle 4) COLR
'l ec:
A.B. Davis - Regional Administrator, Region III P.C. Shemanski - Project Manager, NRR R.D. Lanksbury - Senior Resident Inspector, LSCS 0474T:2
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