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MONTHYEARGNRO-2013/00032, Entergy’S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2013-04-26026 April 2013 Entergy’S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Response to RAI L-PI-13-038, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2013-04-29029 April 2013 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Response to RAI L-2013-265, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sites2013-09-0909 September 2013 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sites Project stage: Response to RAI LR-N13-0206, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f). Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident.2013-09-10010 September 2013 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f). Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. Project stage: Response to RAI L-PI-13-088, NSPMs Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS2013-09-12012 September 2013 NSPMs Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Si Project stage: Response to RAI GNRO-2013/00068, Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident 1.5 Year Response for CEUS Site2013-09-12012 September 2013 Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident 1.5 Year Response for CEUS Site Project stage: Response to RAI GNRO-2014/00025, Draft Plant-Specific Supplement 50 to the Generic Environmental Impact Statement for License Renewal2014-03-12012 March 2014 Draft Plant-Specific Supplement 50 to the Generic Environmental Impact Statement for License Renewal RBG-47453, Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-26026 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request L-PI-14-028, PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident Project stage: Response to RAI CP-201400324, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request HNP-14-035, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.32014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 Project stage: Request L-2014-085, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident Project stage: Response to RAI LR-N14-0035, PSEG Nuclear LLCs Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-03-28028 March 2014 PSEG Nuclear LLCs Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. 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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. William R. Gideon Vice President H. B. Robinson Steam Electric Plant Duke Energy Progress, Inc.
3581 West Entrance Road Hartsville, SC 29550 June 18, 2014
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 2 -ACCEPTANCE OF REQUESTED ACTION REGARDING RELIEF REQUEST (RR)-10, TO ASME SECTION XI CODE REQUIREMENT SUBPARAGRAPH IWA-2441 (b)
(TAC NO. MF4172)
Dear Mr. Gideon:
By letter dated May 9, 2014, Duke Energy Progress, Inc., submitted a relief request for H. B. Robinson Steam Electric Plant, Unit 2. The proposed relief request would defer the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI requirements of paragraph IWA-2441(b) of ASME Code Section XI, 2007 Edition through the 2008 Addenda. The H. B. Robinson Steam Electric Plant, Unit 2, fifth 1 0-year inservice inspection interval program is based on the ASME Boiler and Pressure Vessel Code,Section XI, 2007 Edition through the 2008 Addenda. Paragraph IAW-2441(b) requires Code Cases be applicable to the Edition and Addenda specified in the Inspection Plan.
H. B. Robinson Steam Electric Plant, Unit 2 requests the applicability of ASME Code Case N-532-4 be extended to the 2007 Edition through the 2008 Addenda for use in the plant's fifth 1 0-year in service inspection program interval.
The purpose of this letter is to provide the results of the U. S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this relief 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.
Pursuant to Section 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations, the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete 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 environ.ment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's
ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-2760.
Docket No. 50-261 cc: Distribution via Listserv Sincerely, IRA/
Martha Barillas, Project Manager Plant Licensing Branch 2-11 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML14168A072 OFFICE DORULPL2-2/PM DORULPL2-2/LA NAME MBarillas BCiayton DATE 6/18/14 6/18/14 Sincerely, IRA/
Martha Barillas, Project Manager Plant Licensing Branch 2-11 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
DORULPL2-2/PM TLupold LRegner MBarillas (KHoffman) for 6/13/14 6/18/14 6/18/14