Letter Sequence Acceptance Review |
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MONTHYEARML1112203132011-05-0202 May 2011
Acceptance Review Email, License Amendment Request for Administrative Revisions to Technical Specifications and to Remove Expired One-Time Exception to 5-Year Test Frequency for Single Safety Valve
Project stage: Acceptance Review
NLS2011085, Relief Request from Certain Inservice Testing Code Requirements2011-08-24024 August 2011
Relief Request from Certain Inservice Testing Code Requirements
Project stage: Request
ML1127304842011-09-30030 September 2011
Acceptance Review Email, Relief Request Nos. RV-07- Pressure Isolation Valve Leaking Testing and RV-01, Revision 1 - HPCI Solenoid Operated Drain Valve Testing - Fourth 10-Year IST Program Interval
Project stage: Acceptance Review
ML1201304542012-01-13013 January 2012
Draft Request for Additional Information, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval
Project stage: Draft RAI
ML1201304512012-01-13013 January 2012
Email, Draft Request for Additional Information, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval
Project stage: Draft RAI
ML1202701552012-02-13013 February 2012
Request for Additional Information, Relief Request No. RV-01, Revision 1, HPCI Solenoid Operated Drain Valve Testing, Fourth 10-Year Inservice Testing Program Interval
Project stage: RAI
ML1201302052012-02-16016 February 2012
Issuance of Amendment No. 241, Editorial Changes to Several Technical Specifications (Tss) and Revise TS 5.5.6 to Remove Expired One-Time Exception to 5-Year Test Frequency for a Safety Valve
Project stage: Approval
NLS2012016, Response to Nuclear Regulatory Commission Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Valve Inservice Testing Program2012-03-12012 March 2012
Response to Nuclear Regulatory Commission Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Valve Inservice Testing Program
Project stage: Request
ML1213905112012-05-18018 May 2012
Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval
Project stage: Draft RAI
ML1213905092012-05-18018 May 2012
Email, Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval
Project stage: Draft RAI
ML12157A5412012-06-11011 June 2012
Second Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Value Inservice Testing Program
Project stage: RAI
NLS2012057, Response to Nuclear Regulatory Commission Request for Additional Information Relief Request RV-01 Revision 12012-06-22022 June 2012
Response to Nuclear Regulatory Commission Request for Additional Information Relief Request RV-01 Revision 1
Project stage: Request
NLS2012082, Response to Nuclear Regulatory Commission Third Request for Additional Information Relief Requests RV-07 Revision 0 and RV-01 Revision 12012-08-14014 August 2012
Response to Nuclear Regulatory Commission Third Request for Additional Information Relief Requests RV-07 Revision 0 and RV-01 Revision 1
Project stage: Request
ML12233A1762012-08-28028 August 2012
Relief Request Nos. RV-07, Revision 0, and RV-01, Revision for Fourth 10-Day Inservice Inspection Interval Regarding Weld Overlay Repair
Project stage: Approval
2012-02-16
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Text
From:
Wilkins, Lynnea Sent:
Friday, September 30, 2011 3:28 PM To:
'McCutchen, Edward L.'
Cc:
Burkhardt, Janet; Lent, Susan
Subject:
Acceptance of Cooper Relief Requests (ME7021)
Ed, By letter dated August 24, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11242A129), Nebraska Public Power District submitted a request for relief from certain inservice testing (IST) code requirements for Cooper Nuclear Station pursuant to 10 CFR 50.55a. These relief requests are applicable to the fourth ten-year IST interval, which began March 1, 2006.
The purpose of this letter is to provide the results of the Nuclear Regulatory Commission (NRC) staff's acceptance review of this exemption request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
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 exemption 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) 415-1377.
Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377
