ML070520635: Difference between revisions
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{{#Wiki_filter:Exelon Nuclear | {{#Wiki_filter:Exelon Nuclear www.exeloncorp.com 2 0 0 Exelon Way Kennett Square, PA 19348 February 20,2007 US. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 uclear 10 CFR 50.55a | ||
==Subject:== | ==Subject:== | ||
Withdrawal of Proposed Alternative Associated with the Second Ten-Year lnterva lnservice Testing (IST) Program - Relief Request No. 51-VRR-3 | Withdrawal of Proposed Alternative Associated with the Second Ten-Year lnterva lnservice Testing (IST) Program - Relief Request No. 51 -VRR-3 | ||
==Reference:== | ==Reference:== | ||
Letter from P. B. Cowan (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, dated October 10, 2006 In the referenced letter, Exelon Generation Company, LLC (EGC), requested relief from the American Society of Mechanical Engineers (ASME) OM Code, 1990 Edition, Code for Operation and Maintenance of Nuclear Power Plants. Specifically, this relief request proposed an alternative for Limerick Generating Station (LGS), Units 1 and 2, that would have permitted testing (i.e., disassembly, inspection, and partial flow testing) of Residual Heat Removal (RHR) | Letter from P. B. Cowan (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, dated October 10, 2006 In the referenced letter, Exelon Generation Company, LLC (EGC), requested relief from the American Society of Mechanical Engineers (ASME) OM Code, 1990 Edition, Code for Operation and Maintenance of Nuclear Power Plants. Specifically, this relief request proposed an alternative for Limerick Generating Station (LGS), Units 1 and 2, that would have permitted testing (i.e., disassembly, inspection, and partial flow testing) of Residual Heat Removal (RHR) | ||
System check valves during any plant mode (Relief Request No. 51-VRR-3). | System check valves during any plant mode (Relief Request No. 51 -VRR-3). | ||
Upon further review, EGC is withdrawing this request. | Upon further review, EGC is withdrawing this request. | ||
If you have any questions, please contact Thomas R. Loomis ( | If you have any questions, please contact Thomas R. Loomis (61 0) 765-551 0. | ||
Very truly yours, Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC cc: | Very truly yours, Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC cc: | ||
S. J. Collins, Regional Administrator, Region I, USNRC S. Hansell, USNRC Senior Resident Inspector, LGS J. Shea, Project Manager [LGS] USNRC}} | |||
Latest revision as of 03:10, 15 January 2025
| ML070520635 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/20/2007 |
| From: | Cowan P Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML070520635 (1) | |
Text
Exelon Nuclear www.exeloncorp.com 2 0 0 Exelon Way Kennett Square, PA 19348 February 20,2007 US. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 uclear 10 CFR 50.55a
Subject:
Withdrawal of Proposed Alternative Associated with the Second Ten-Year lnterva lnservice Testing (IST) Program - Relief Request No. 51 -VRR-3
Reference:
Letter from P. B. Cowan (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, dated October 10, 2006 In the referenced letter, Exelon Generation Company, LLC (EGC), requested relief from the American Society of Mechanical Engineers (ASME) OM Code, 1990 Edition, Code for Operation and Maintenance of Nuclear Power Plants. Specifically, this relief request proposed an alternative for Limerick Generating Station (LGS), Units 1 and 2, that would have permitted testing (i.e., disassembly, inspection, and partial flow testing) of Residual Heat Removal (RHR)
System check valves during any plant mode (Relief Request No. 51 -VRR-3).
Upon further review, EGC is withdrawing this request.
If you have any questions, please contact Thomas R. Loomis (61 0) 765-551 0.
Very truly yours, Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC cc:
S. J. Collins, Regional Administrator, Region I, USNRC S. Hansell, USNRC Senior Resident Inspector, LGS J. Shea, Project Manager [LGS] USNRC