ML121280086: Difference between revisions

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| document type = E-Mail, Acceptance Review Letter
| document type = E-Mail, Acceptance Review Letter
| page count = 1
| page count = 1
| project = TAC:ME8455
| stage = Other
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=Text=
{{#Wiki_filter:From: Kim, James Sent: Monday, May 07, 2012 10:06 AM To: 'William D Bartron' Cc: 'Wanda.D.Craft@dom.com' Subject: Acceptance Review: MPS3 Amendment Request for Permanent Alt. Repair Criteria for SG Tube Inspection and Repair (ME8455)  Dear Mr. Bartron:  By letter dated April 12, 2012 (Agencywide Documents Access and Management System Accession No. ML12110A114), Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request to permanently revise Technical Specification (TS) 6.8.4.g, "Steam Generator (SG) Program," to exclude a portion of the steam generator tubes below the top of the steam generator tubesheet from periodic inspections. Inclusion of the permanent alternate repair criteria (PARC) in TS 6.8.4.g permits deletion of the previous temporary alternate repair criteria (TARC) for Cycle 15. In addition, this amendment request also proposes to revise the reporting criteria in TS 6.9.1.7, "Steam Generator Tube Inspection Report," to remove reference to the previous Cycle 15 TARC, and add reporting requirements specific to the PARC. Consistent with 10 CFR 50.90 an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. If you have any questions, please contact me at (301) 415-4125.
Sincerely,  James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation   
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Revision as of 02:17, 2 April 2018

Acceptance Review Millstone Power Station No. 3 - Amendment Request for Permanent Alternate Repair for Steam Generator Tube Inspection and Repair (TAC No. ME8455)
ML121280086
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/07/2012
From: Kim J S
Plant Licensing Branch 1
To: Bartron W D
Dominion Nuclear Connecticut
Kim J, NRR/DORL, 415-4125
References
TAC ME8455
Download: ML121280086 (1)
v • d • e


Text

From: Kim, James Sent: Monday, May 07, 2012 10:06 AM To: 'William D Bartron' Cc: 'Wanda.D.Craft@dom.com' Subject: Acceptance Review: MPS3 Amendment Request for Permanent Alt. Repair Criteria for SG Tube Inspection and Repair (ME8455) Dear Mr. Bartron: By letter dated April 12, 2012 (Agencywide Documents Access and Management System Accession No. ML12110A114), Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request to permanently revise Technical Specification (TS) 6.8.4.g, "Steam Generator (SG) Program," to exclude a portion of the steam generator tubes below the top of the steam generator tubesheet from periodic inspections. Inclusion of the permanent alternate repair criteria (PARC) in TS 6.8.4.g permits deletion of the previous temporary alternate repair criteria (TARC) for Cycle 15. In addition, this amendment request also proposes to revise the reporting criteria in TS 6.9.1.7, "Steam Generator Tube Inspection Report," to remove reference to the previous Cycle 15 TARC, and add reporting requirements specific to the PARC. Consistent with 10 CFR 50.90 an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. If you have any questions, please contact me at (301) 415-4125.

Sincerely, James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

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