ML20043C824
| ML20043C824 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/01/1990 |
| From: | Silady J COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20043C825 | List: |
| References | |
| GL-88-16, NUDOCS 9006060225 | |
| Download: ML20043C824 (2) | |
Text
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Cammanwealth Ediscn '
G-1400 Opus Place Downers Grove, Illinois 60515 June 1, 1990
.Dr. Thomas E.'Murley Office of Nuclear Reactor Regulation JU.S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTN USNRC Document Control Desk
Subject:
LaSalle County Station Unit 2 Cycle 4 Reload 30 Docket No. 50-374
Reference:
(a) J.A. Silady letter to Dr. T.E. Murley, dated August 18, 1989 "LaSalle' County Nuclear Power Station Units 1 and 2 Proposed Amendtnent to Remove Cycle-Specifin r
Core Limita from the Technical 'iecifications."
(b) r.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.
(c) M.l!. Richter letter to U.S. NRC (Document Control Desk) dated Aril 26, 1990.
'Dr. Murley:
LaSalle Unit 2, which has completed its third cycle of operation is currently preparing for Cycle 4 startup. The purpose of this letter.ia 4
twofold (1) to advise you of Commonwealth Edison's intentions'to review and
-approve the Cycle 4 reload under the provisions of 10 CFR 30.59, and (2) to transmit the Core Operating Limits Report (COLR) for the upcoming cycle consistent.with Generic Letter 88-16.
References (a) and (b) implemented Generic Letter 88-16-for the LaSalle units.
The LaSalle Unit 2 Cycle 4 (L204) core consists of NRC approved. fuel designs and:was designed to operate under the currently approved fuel desigu
. parameters, Technical Specifications, and related bases such that:
1)
Core operating characteristics will be less limiting than those previously reviewed and accepted; or J-2)
.For those postulated incidents analyzed and reported in the Final Safety Analysis Report (FSAR) which could potentially be affected by the fuel reload, re-analysis using NRC approved methods has demonstrated that the results of the postulated events are within allowable limits.
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Dr. T.E. Murley June 1,1990 The Cycle 4 reload core contains 212 fresh GE9B fuel assemblies representing the-first use of this fuel design at LaSalle Unit 2.
The GE9B fuel design was approved for use of this fuel design at LaSt'le Unit 2.
The GE9B fuel design was approved for use by the NRC in Amendmen 9 to GESTAR and was also used.in the most recent Unit I reload.
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 10CFR50.59 (a,b).
As in the past, the General Electric licensing documents were prepared using previously approved methodologies as reported in
.NEDE-24011 (GESTAR), the FSAR, and other generally approved documents.
boason has reviewed the cycle specific licensing results and concluded that additional Technical Specification changes are not required for Cycle 4 operation at LaSalle Unit 2.
The Onsite Review and Offsite Review of the reload licensing analyses and safety evaluation have also been completed.
In addition, Edison has evaluated the effects of channel bow as required by NRC Bulletin 90-02.
This response was submitted in Reference (c) and is currently under NRC review. General Electric's generic channel bow methodology, described in the referene.e,-has been implemented for L2C4 including the necessary changes to the onsite core monitoring software update for the cycle.
Therefore, application for an amendment to the LaSalle 2 operating licensing is not required for resumption of operation with the Cycle 4 reload core. The estimated startup date it June 10, 1990.
Very truly yours, J.A. Silady Nuclear Licensing Administrator
Attachment:
LaSalle Unit 2 Reload 3 (Cycle 4) COLR cc: A.B. Davis - Regional Administrator, RIII R.M. Pulsifer - Project Manager, NRR T.M. Tongue - Sr. Resident Inspector, LSCS D.B. Fieno - Reactor Systen:.< Prnnch, NRR
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