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Category:Acceptance Review Letter
MONTHYEARML24094A3282024-04-17017 April 2024 Acceptance of Exemption Request from Certain Requirements in 10 CFR 50.55a(h)(2) ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) ML21006A4302021-01-0606 January 2021 Acceptance Review - Duke Fleet RA-20-0207 Request to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML20157A1062020-06-24024 June 2020 Review of the Fall 2019 Steam Generator Tube Inspections During Refueling Outage No. 22 ML20133K0722020-05-12012 May 2020 Acceptance of Requested Licensing Action Technical Specifications Related to Reducing the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits ML19311C3412019-11-0707 November 2019 Acceptance Review: Shearon Harris License Amendment Request for TSTF-505 ML18270A1292018-10-0404 October 2018 Acceptance of Requested Licensing Action ML17319A5012017-11-21021 November 2017 Acceptance Review Letter, License Amendment Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML17261A7272017-09-20020 September 2017 Shearon Harris Nuclear Power Plant, Unit 1 - Acceptance of Requested Licensing Action Regarding Spent Fuel Storage Pool Criticality Analyses (CAC No. MF9996) ML16308A3702016-11-0707 November 2016 Results of Acceptance Review of Requested Licensing Action Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422-MF8429) ML16152A5962016-06-0303 June 2016 NRC Acceptance of Requested Licensing Action Amendment Request ML15309A7282015-12-0101 December 2015 Acceptance of Requested Licensing Action Regarding Duke Energy Progress, Inc. Application to Revise Technical Specifications to Adopt Methodology Report ML14157A0552014-06-13013 June 2014 Acceptance of Requested Relief Request I3R-14-Deferral of Reactor Vessel Inspections Inservice Inspection Program-Third 10-Year Interval ML13329A4572013-11-25025 November 2013 Accepted for Review Shearon Harris--Acceptance Review for Relief Request I3R-13 Reactor Vessel Closure Head Nozzle 37 ML13324B0812013-11-20020 November 2013 E-mail Re. Acceptance Review for Relief Request I3R-12 Repair of Accumulator Fill Valve Piping Weld ML11181A0162011-07-0101 July 2011 Acceptance for Review of Measurement Uncertainty Recapture Power Uprate License Amendment Request ML1105300792011-02-18018 February 2011 E-mail, Acceptance Review of ME5410, Application for Exemption for M5 Cladding: 1/19/11 ML1018707202010-07-0909 July 2010 Acceptance Review Regarding a Relief Request for Approval of an Alternative Inservice Inspection Method for Six Pressure Retaining Dissimilar Metal Welds in the Reactor Pressure Vessel Nozzles ML0935801382009-12-30030 December 2009 Acceptance Review Regarding Request for Exemption from the Requirements of 10 CFR Part 73, Section 73.55 ML0912705692009-05-15015 May 2009 Acceptance Review Re Amendment to Adopt Tech Spec Task Force (TSTF) Standard Tech Spec Change Traveler, TSTF-447, Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors ML0903603132009-02-0606 February 2009 Acceptance Review Regarding Amendment to Remove Credit for Boraflex in Boiling Water Reactor Spent Fuel Pool Storage Racks ML0903000302009-01-30030 January 2009 Acceptance Review Regarding Amendment to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition ML0902100672009-01-29029 January 2009 Acceptance Review Regarding Relief Request to Defer an ASME Code Repair of an Emergency Service Water System Weld Until the Next Refueling Outage ML0902100112009-01-27027 January 2009 Acceptance Review Regarding Amendment to Remove Credit for Boraflex in BWR Spent Fuel Pool Storage Racks ML0827011582008-09-26026 September 2008 Acceptance Review Regarding the License Amendment Request to Transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants. 2024-04-17
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 9, 2010 Christopher Burton, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - ACCEPTANCE REVIEW REGARDING A RELIEF REQUEST FOR APPROVAL OF AN ALTERNATIVE INSERVICE INSPECTION METHOD FOR SIX PRESSURE RETAINING DISSIMILAR METAL WELDS IN THE REACTOR PRESSURE VESSEL NOZZLES (TAC NO. ME3894)
Dear Mr. Burton:
By letter dated May 27,2010, Carolina Power & Light Company (the licensee), now doing business as Progress Energy Carolinas, Inc., submitted a relief request for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed relief request seeks approval to allow an alternative to the inservice inspection requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," for six pressure retaining dissimilar metal welds in the reactor pressure vessel nozzles. The proposed alternative pertains to the third 10-year inspection interval at HNP.
Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of 10 CFR 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
The purpose of this letter is to provide the final results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this 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 and make an independent assessment regarding the acceptability of the proposed change. 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 the licensee's relief request 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 request in terms of regulatory requirements and the protection of public health and safety and the environment.
C. Burton -2 If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. Should you have any questions regarding this review, please contact me at (301) 415-3178.
Marlayna Vaaler, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400 cc: Distribution via ListServ
C Burton - 2 If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. Should you have any questions regarding this review, please contact me at (301) 415-3178.
Sincerely, IRA!
Marlayna Vaaler, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400 cc: Distribution via ListServ DISTRIBUTION:
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