ML20078B998
| ML20078B998 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/24/1994 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9410270358 | |
| Download: ML20078B998 (1) | |
Text
c 4,s Ctmmonwnith Edison
[ A s}
1400 Opus Place Downers Grove, lilinois 60515 e
w October 24, 1994 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 At*ention:
Document Control Desk
Subject:
Additional Information relating to the request for TECHNICAL SPECIFICATION AMENDMENT to Application for Amendment to Facility Operating License:
Byron Station Units 1 and 2 (NPF-37/66; NRC Docket Nos. 50-454/455)
" Steam Generator Interim Plugging Criteria"
Reference:
D.
Saccomando letter to Document Control Desk transmitting Additional Information Regarding Application for Amendment to Facility Operating License Steam Generator Interim Plugging Criteria for Byron Station dated October 17, 1994 In the reference letter, Commonwealth Edison Company (Comed),
Byron Station transmitted to the Nuclear Regulatory Commission a summarp of the Byron Unit 1 inspection results, leak and burst calculational methodology, projected end-of-cycle 7 leak and burst results, and a safety assessment of these results.
In this letter, Byron Station also stated that they were planning a Unit I shutdown in mid-September of 1995 to perform steam generator eddy current inspections.
Comed would like to further clarify that Byron Station commits to initiate a shutdown of Unit 1 no later than September 15, 1995, in order to perform eddy current inspections of Unit 1 steam generators.
If you have any questions regarding this correspondence please contact this office.
Sincerely,
,M'
- m. j )
Denise M.I accomando j
Nuclear Licensing Administrator l
cc:
G.
Dick, Byron Project Manager-NRR H.
Peterson, Senior Resident Inspector-Byron Station i
J. Martin, Regional Administrator-RIII Office of Nuclear Facility Safety-IDNS Yb lli(
G C
4 PDR