ML20108A881
| ML20108A881 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/26/1996 |
| From: | Kaup K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9605030050 | |
| Download: ML20108A881 (2) | |
Text
1 Commonwealth Edison Company 1
tiraidwood Generating Station
, Route # 1, llox 8 i
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liraces ille,11. N) aO7%l9 i
Tel H 15-158-2801 April 26,1996 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Clarification of November 16,1995, Letter to the NRC on Braidwood Interim Cycle Length for Eraidwood Unit 1 Braidwood Nuclear Power Station Unit 1 NRC Docket Number 50-456 i
l
References:
1.
Teleconference dated April 25,1996, between the Nuclear Regulatory Commission and the Commonwealth Edison Company 2.
K. Kaup letter to the Nuclear Regulatory Commission dated April 16,1996, on Braidwood Cycle Length 3.
K. Kaup letter to the Nuclear Regulatory Commission dated February 23,1996, on Braidwood Cycle Length 4.
D. Saccomando letter to the Nuclear Regulatory Commission dated November 16,1995, on Braidwood Cycle Length During the Reference teleconference, the Nuclear Regulatory Commission referred to a commitment made by the Commonwealth Edison Company (Comed) in a letter dated November 16,1995 (Reference 4).
This commitment, which was subsequently revised in References 2 and 3, was to limit the operation of Braidwood Unit 1 between eddy current inspection of the steam generator top-of-tube sheet for a time not to exceed 24 weeks at operating temperature above a T-Hot of 500 F during Cycle 6. This time frame was selected because it was believed at that time to be equivalent to the length of operation prior to the Braidwood Cycle 5 Refueling Outage.
Subsequent to the transmittal of Reference 4, it was discovered that the length of operation during Cycle 5 between eddy current inspections had been greater than 24 weeks at operating temperature above a T-Hot of 500 F.
The Staff asked Comed to clarify the actual previous length of operation and to determine how long Braidwood Unit 1 could operate if the Staff held Comed to an equivalent time frame of operation.
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l Document Control Desk April 26,1996 l
l Specifically, i
i Braidwood Unit 1 operated above a T-Hot of 500 F from March 11, 1995, (the end of the Braidwood 1995 mid cycle outage) to the September 30,1995 (the beginning of the refueling outage). The total time above a T-Hot of 500 F was 202 days; therefore, instead of the 24 week commitment, the time frame should have been equivalent to 202 days above a T-Hot of 500 F.
Also, since the start up of Cycle 6, Braidwood Unit 1 has not been l
l continuously above a T-Hot of 500 F. The unit was shut down to l
replace Battery 112, which resulted in Braidwood Unit 1 being below 500 F T-Hot for 17 days, i
I Noting both of these factors, and if Braidwood continuously operates until time of shut down, Braidwood Unit 1 would be able to operate until at least July 13,1996.
l Comed intends to continue its evaluation of circumferential cracking data with the intention of further supporting the appropriate cycle length, as discussed in References 2 and 3. It is anticipated that further discussions with the NRC will take place on this topic in the near future.
if you have any questions concerning this correspondence, please contact Denise Saccomando at 708-663-7283.
Sincerely, Karl L. Idup i
Site Vice President Braidwood Generating Station cc:
D. Lynch, Senior Project Manager-NRR R. Assa, Braidwood Project Manager-NRR l
H. Miller, Regional Administrator-Rill C. Phillips, Senior Resident inspector-Braidwood i
Office of Nuclear Safety-IDNS 4
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