ML20134M256
| ML20134M256 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 02/07/1997 |
| From: | Hosmer J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9702200166 | |
| Download: ML20134M256 (2) | |
Text
,
Commonwealth lilison Company I MX) Opus Place Downers Grove, IL 6051M701 February 7,1997 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Additional Information Pertaining to the Response to the Request for Additional Information Related to the Proposed Extension of the Byron 1 and the Braidwood 13.0 Volt License i
Amendment for ODSCC Byron Nuclear Power Station Unit 1 NRC Docket Number: 50-454 i
Braidwood Nuclear Power Station Unit 1 NRC Docket Number: 50-456
References:
1.
J. Hosmer letter to the Nuclear Regulatory Commission dated February 5,1997, transmitting Response to Request for Additional Information Related to the Proposed Extension of the Bryon 1 and the Braidwood 13.0 Volt License Amendment for ODSCC
~
2.
M. Lynch letter to I. Johnson dated January 27,1997, transmitting Request for Additional Information Related to the Proposed Extension of the Byron 1 and the Braidwood 1 3.0 Volt License Amendment for ODSCC 3.
H. Stanley letter to the Nuclear Regulatory Commission dated August 19,1996, transmitting Request for Technical Specification Amendment Pertaining to the 3 Volt Renewal Reference 1 provided the Commonwealth Edison's Company's (Comed) i response to the Request for Additional information (RAI) that was transmitted via Reference 2 from the Nuclear Regulatory Commission (NRC). This RAI pertained to Comed's request to amend the Technical Specifications for Byron and Braidwood Stations to allow for the extension of a 3.0 Volt Interim Plugging Criteria for the Unit 1 steam generators for Cycle 9 and Cycle 7, respectively 4
(Reference 3).
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NRC Document Control Desk February 7,1997 4
To clarify Comed's response to RAI #7, if circumferential indications are detected at either the sleeve expanded joint or top-of-tubesheet, they will be repaired.
Repairs of circumferential indications at the top-of-tubesheet will consist of j
installation of a welded or a mechanical sleeve to maintain a tube support i
plate displacement of less than 0.1 inches during a mainsteam line break event.
Repairs of circumferential indications at the sleeve expanded joint will j
consist of installation of a new expansion to replace the affected expansion.
This approach will ensure that the margin of safety as discussed in the Staff's l
Safety Evaluation (dated November 9,1995) for the 3 Volt IPC is maintained.
Comed hopes that this information clarifies our intentions. If you have any questions concerning this correspondence, please contact Denise Saccomando, Senior PWR Licensing Administrator at 630-663-7283.
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Sincerely
()ggju }i/
s John B. Hosmer j
Engineering Vice President i
cc:
M. D. Lynch, Senior Project Manager-NRR G. Dick, Byron /Braidwood Project Manager-NRR C. Phillips, Senior Resident inspector-Braidwood S. Burgess, Senior Resident inspector-Byron l
A. B. Beach, Regional Administrator - Rlli Office of Nuclear Safety-IDNS e
I i
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