ML053480360
| ML053480360 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/13/2005 |
| From: | Thomas J. Palmisano Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-04-002, L-PI-05-108 | |
| Download: ML053480360 (2) | |
Text
N Commftted to Nuclear Excellence Prairie Island Nuclear Generating Plant Operated by Nuclear Management Company, LLC L-PI-05-108 10 CFR 50.540 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Supplement 1 to Nuclear Management Companv Response to Generic Letter 2004-02, "Potential Impact of Debris Blockaqe on Emergencv Recirculation Durinq Desi~n Basis Accidents at Pressurized-Water Reactors," for the Prairie Island Nuclear Generatinq Plant By letter dated September 13, 2004, the Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2004-02. In GL 2004-02, the NRC required that specific information be provided by September I, 2005. By letter dated August 31, 2005, Nuclear Management Company, LLC (NMC) provided the required September 1,2005, response to GL 2004-02.
As part of the GL 2004-02 response, NMC made the commitment, "NMC will submit a license amendment request to change the Technical Specification Surveillance Requirement 3.5.2.8 to reflect the new design by December 31, 2005." This letter revises the commitment to submit the license amendment request (LAR) by December 31, 2006.
Technical Specification (TS) Surveillance Requirement (SR) 3.5.2.8 requires verification by visual inspection that the containment sump suction inlet protective structures show no evidence of structural distress or abnormal corrosion. The terminology in this SR describes the containment sump suction inlet protective structures as "trash racks and screens". In response to GL 2004-02, NMC plans to replace these structures during the Spring 2006 Unit 1 refueling outage and the Autumn 2006 Unit 2 refueling outage. An administrative change to this SR is required because the replacement structures will not be described as "trash racks and screens".
NMC is revising the commitment date because the change to SR 3.5.2.8 is an administrative change which does not affect plant operation. SR 3.5.2.8 as currently written will continue to adequately require the containment sump suction inlet protective structures to be inspected following implementation of the modifications which replace the containment sump suction inlet protective structures. Since the modifications will be performed during two different unit refueling outages in 2006, the revised SR 3.5.2.8 171 7 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121
Document Control Desk Page 2 terminology may not be applicable to one or both units for some period of time, regardless of when the NRC approves the revised SR 3.5.2.8; thus, there is no advantage to revising the SR prior to making the modifications.
Summary of Commitments This letter contains no new commitments and revises commitment 3 in NMC letter dated August 31, 2005 to state:
NMC will submit a license amendment request to change the Technical Specification Surveillance Requirement 3.5.2.8 by December 31, 2006.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on QEC 1 3 2009 Thomas J. Palmisano Site Vice President, Prairie Island Nuclear Generating Plant Units 1 and 2 Nuclear Management Company, LLC cc:
Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC