NRC 2006-0018, License Amendment Request 242, Supplement 1 Technical Specification 5.5 Programs and Manuals: Difference between revisions

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{{#Wiki_filter:Committed to Nuclear Excellen Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC January 30, 2006 NRC 2006-0018 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 License Amendment Request 242, Supplement I Technical Specification 5.5, Programs and Manuals  
{{#Wiki_filter:Committed to Nuclear Excellen                                                 Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC January 30, 2006                                                                       NRC 2006-0018 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 License Amendment Request 242, Supplement I Technical Specification 5.5, Programs and Manuals


==Reference:==
==Reference:==
(1) Letter from NMC to NRC dated November 12, 2004 (NRC 2004-0107)
In Reference 1, Nuclear Management Company, LLC (NMC), submitted a request for an amendment to the Technical Specifications (TS) for Point Beach Nuclear Plant, Units 1 and 2. The proposed amendment would revise TS 5.5.7, "Inservice Testing Program," and TS 5.5.8, "Steam Generator (SG) Tube Surveillance Program." The revision updates references to the American Society of Mechanical Engineers code and certain associated periodicities for inservice testing activities consistent with the requirements of 10 CFR 50.55a.
NMC is preparing to submit a proposed amendment to revise the TS related to steam generator tube integrity, consistent with TS Task Force (TSTF) Change Traveler TSTF-449, "Steam Generator Tube Integrity". This upcoming submittal will supersede the revision to TS 5.5.8 that was proposed in Reference 1.
Therefore, NMC requests that the revision to TS 5.5.8 proposed in Reference 1 be withdrawn. The remainder of the amendment requested in Reference 1 remains in effect.
NMC has determined that this supplement to the proposed amendment remains bounded by the No Significant Hazards Consideration Determination submitted in Reference 1.
This letter contains no new commitments or revisions to existing commitments.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Wisconsin Official.
6590 Nuclear Road ' Two Rivers, Wisconsin 54241 Telephone: 920.755.2321 A/-J


(1) Letter from NMC to NRC dated November 12, 2004 (NRC 2004-0107)
Document Control Desk Page 2 I declare under penalty of perjury that the foregoing is true and correct.
In Reference 1, Nuclear Management Company, LLC (NMC), submitted a request for an amendment to the Technical Specifications (TS) for Point Beach Nuclear Plant, Units 1 and 2. The proposed amendment would revise TS 5.5.7, "Inservice Testing Program," and TS 5.5.8, "Steam Generator (SG) Tube Surveillance Program." The revision updates references to the American Society of Mechanical Engineers code and certain associated periodicities for inservice testing activities consistent with the requirements of 10 CFR 50.55a.NMC is preparing to submit a proposed amendment to revise the TS related to steam generator tube integrity, consistent with TS Task Force (TSTF) Change Traveler TSTF-449, "Steam Generator Tube Integrity".
Executed on January 30, 2006.
This upcoming submittal will supersede the revision to TS 5.5.8 that was proposed in Reference 1.Therefore, NMC requests that the revision to TS 5.5.8 proposed in Reference 1 be withdrawn.
Dennis L. Koehl Site Vice-President, Point Beach Nuclear, Plant Nuclear Management Company, LLC cc:   Regional Administrator, Region 111, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW}}
The remainder of the amendment requested in Reference 1 remains in effect.NMC has determined that this supplement to the proposed amendment remains bounded by the No Significant Hazards Consideration Determination submitted in Reference 1.This letter contains no new commitments or revisions to existing commitments.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Wisconsin Official.6590 Nuclear Road ' Two Rivers, Wisconsin 54241 Telephone:
920.755.2321 A/-J Document Control Desk Page 2 I declare under penalty of perjury that the foregoing is true and correct.Executed on January 30, 2006.Dennis L. Koehl Site Vice-President, Point Beach Nuclear, Plant Nuclear Management Company, LLC cc: Regional Administrator, Region 111, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW}}

Latest revision as of 23:34, 23 November 2019

License Amendment Request 242, Supplement 1 Technical Specification 5.5 Programs and Manuals
ML060380528
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/30/2006
From: Koehl D
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2006-0018
Download: ML060380528 (2)
v • d • e


Text

Committed to Nuclear Excellen Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC January 30, 2006 NRC 2006-0018 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 License Amendment Request 242, Supplement I Technical Specification 5.5, Programs and Manuals

Reference:

(1) Letter from NMC to NRC dated November 12, 2004 (NRC 2004-0107)

In Reference 1, Nuclear Management Company, LLC (NMC), submitted a request for an amendment to the Technical Specifications (TS) for Point Beach Nuclear Plant, Units 1 and 2. The proposed amendment would revise TS 5.5.7, "Inservice Testing Program," and TS 5.5.8, "Steam Generator (SG) Tube Surveillance Program." The revision updates references to the American Society of Mechanical Engineers code and certain associated periodicities for inservice testing activities consistent with the requirements of 10 CFR 50.55a.

NMC is preparing to submit a proposed amendment to revise the TS related to steam generator tube integrity, consistent with TS Task Force (TSTF) Change Traveler TSTF-449, "Steam Generator Tube Integrity". This upcoming submittal will supersede the revision to TS 5.5.8 that was proposed in Reference 1.

Therefore, NMC requests that the revision to TS 5.5.8 proposed in Reference 1 be withdrawn. The remainder of the amendment requested in Reference 1 remains in effect.

NMC has determined that this supplement to the proposed amendment remains bounded by the No Significant Hazards Consideration Determination submitted in Reference 1.

This letter contains no new commitments or revisions to existing commitments.

In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Wisconsin Official.

6590 Nuclear Road ' Two Rivers, Wisconsin 54241 Telephone: 920.755.2321 A/-J

Document Control Desk Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on January 30, 2006.

Dennis L. Koehl Site Vice-President, Point Beach Nuclear, Plant Nuclear Management Company, LLC cc: Regional Administrator, Region 111, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW

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