ML20129D279
| ML20129D279 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/18/1996 |
| From: | Graesser K COMMONWEALTH EDISON CO. |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20129D285 | List: |
| References | |
| BYRON-96-0266, BYRON-96-266, NUDOCS 9610240252 | |
| Download: ML20129D279 (2) | |
Text
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Commonweahh Frinon Company liyron Generating Station 4450 North German Church Road 3
- 11) ron, II. 610149'9 i Tel M I S-2.41444 I I
October 18,1996 i
LTR:
BYRON 96-0266 FILE:
1.10.0101 Oflice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
Subject:
Byron Station Unit 1 NRC Docket Number: 50-454 Operating Interval Between Eddy Current inspections for Circumferential Indications in the Byron Unit 1 Steam Generators i
Reference:
D. Wozniak letter to the Nuclear Regulatory Commission dated September 9,1996, transmitting the Byron Station Unit 1 Steam Generator Interim Plugging Criteria 90 Day Report for the End-of Cycle 7 Inspection In Reference Letter, the Commonwealth Edison Company (Comed) provided justification to the Nuclear Regulatory Commission (NRC) for the operation of the Byron Station Unit I during Cycle 8 for 448.5 days above a T-Hot 500 F. Comed plans to replace the Byron Unit I steam generators in the first quarter of 1998. Therefore, this is the last cycle of operation for the Westinghouse D-4 steam generators. The period of operation to shutdown for the replacement outage represents a 600 day operating cycle. As previously discussed with the Staff, Comed has been working diligently on an evaluation which ensures steam generator tube integrity will be met in the unlikely event of a main steam line break at the end of a 600 day operating period. This evaluation is provided in Attachment A. The results of the evaluation determined that Byron Unit I can operate 600 days and meet the criteria in Generic Letter 95-05 for the conditional probability of burst and leak rate at the end of the cycle. Also attached is a summary of the Braidwood Unit 1 Cycle Length Assessment R.equest for Additional Information (RAI) responses applicable to the Byron Unit I assessment (Attachment B), and the applicable Byron response to the RAls (Attachments C and D).
9610240252 961018 PDR ADOCK 05000454 G
PDR 240073
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NRC Document Control Desk
. Byron Ltr: 96-0266 October 18,1996 Page 2 l
Comed is requesting NRC concurrence with the conclusion that Byron Unit I can operate for 600 days. Concurrence by November 30,1996 is requested to allow for adequate time to plan for a steam generator inspection outage, if one is ' deemed necessary. Planning, scheduling, and procurement for an inspection outage is normally conducted over an eighteen month period. Scheduling an inspection contractor for a 1997 Byron Unit 1 outage requires commitments be put in place before December 1st. This need to resolve 1
this matter expeditiously is even more critical to avoid a dual unit outage in the Fall of 1997 and to avoid the peak summer load period. Approval of our request past November 30,1996, would result in unnecessary expenditures of resources.
If you have any questions concerning this correspondence, please contact Denise Saccomando, Senior PWR Licensing Administrator at (630) 663-7283.
Sincerely, d
y Kenneth L. Gr sser Site Vice President Byron Station KLG/DS/rp Attachments cc:
D. Lynch, Senior Project Manager-NRR
[
G. Dick, Byron Project Manager-NRR S. Burgess, Senior Resident Inspector-Byron i
A.W. Beach, Regional Administrator-Rill Office ofNuclear Safety lDNS (pA96byltrs/960266. doc /1018%)
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