Letter Sequence Request |
---|
|
|
MONTHYEARML12278A3992012-08-31031 August 2012 WCAP-17077-NP, Rev 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant Project stage: Request RNP-RA/12-0100, Review Request for the PWR Vessel Internals Program Plan for Aging Management of Reactor Internals2012-09-26026 September 2012 Review Request for the PWR Vessel Internals Program Plan for Aging Management of Reactor Internals Project stage: Request ML12307A4082012-11-0202 November 2012 NRR E-mail Capture - Acceptance Review for the PWR Rector Vessel Internals Program Plan for Aging Management for H.B. Robinson Steam Electric Plant Unit No. 2 Project stage: Acceptance Review ML13079A2932013-03-27027 March 2013 Request for Additional Information Related to the Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals Project stage: RAI RNP-RA/13-0053, Response to NRC Request for Additional Information Related to Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals2013-05-23023 May 2013 Response to NRC Request for Additional Information Related to Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML13135A1842013-05-29029 May 2013 Request for Additional Information Related to the Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals Project stage: RAI RNP-RA/13-0073, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2013-07-25025 July 2013 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML13240A4992013-08-27027 August 2013 NRR E-mail Capture - Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Requests for Additional Information (Rais) Project stage: RAI ML13249A0002013-09-0505 September 2013 NRR E-mail Capture - Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Requests for Additional Information (Rais) (TAC No. ME9633) - Correction to RAI-3-3 Project stage: RAI ML13266A2402013-09-23023 September 2013 NRR E-mail Capture - Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Revised Requests for Additional Information (Rais) Project stage: RAI ML14016A2792014-01-0808 January 2014 NRR E-mail Capture - Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Request for Additional Information (Rais) Project stage: RAI RNP-RA/13-0134, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2014-01-0909 January 2014 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI RNP-RA/14-0028, Response to NRC Request for Additional Information Re Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2014-02-19019 February 2014 Response to NRC Request for Additional Information Re Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML14115A4402014-04-24024 April 2014 NRR E-mail Capture - H. B. Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Request for Additional Information (Rais) Project stage: RAI ML14167A3452014-06-16016 June 2014 NRR E-mail Capture - H. B. Robinson MRP-227-A RAI Status Project stage: RAI RNP-RA/14-0097, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2014-09-0505 September 2014 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML15009A2842015-01-22022 January 2015 Request for Withholding of Proprietary Information from Public Disclosure Project stage: Withholding Request Acceptance RNP-RA/16-0011, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2016-02-18018 February 2016 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML16063A1032016-02-18018 February 2016 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML16280A2002016-10-0505 October 2016 Response to Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI RNP-RA/17-0042, Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2017-06-29029 June 2017 Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Other 2013-09-05
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000261/20244012024-09-11011 September 2024 Security Baseline Inspection Report 05000261/2024401 ML24242A2612024-08-29029 August 2024 Operator Licensing Examination Approval 05000261/2024301 IR 05000261/20240052024-08-22022 August 2024 Updated Inspection Plan for H.B. Robinson Steam Electric Plant - Report 05000261/2024005 ML24169A2712024-08-14014 August 2024 – Issuance of Amendment No. 280 to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification 5.7, High Radiation Area IR 05000261/20240022024-08-0101 August 2024 Integrated Inspection Report 05000261/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000261/20240112024-06-0303 June 2024 Focused Engineering Inspection- Commercial Grade Dedication Report 05000261/2024011 ML24114A0152024-06-0303 June 2024 Unit 2 – Issuance of Amendment No. 279 Regarding Application of Leak-Before-Break Methodology for Auxiliary Reactor Coolant System Piping IR 05000261/20240012024-05-0909 May 2024 Integrated Inspection Report 05000261/2024001 IR 05000261/20240102024-04-30030 April 2024 Biennial Problem Identification and Resolution Inspection Report 05000261/2024010 IR 05000261/20230062024-02-28028 February 2024 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 - Report 05000261-2023006 IR 05000261/20243012024-02-0606 February 2024 – Notification of Licensed Operator Initial Examination 05000261/2024301 ML24033A0592024-02-0202 February 2024 Response to Request for Additional Information License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology IR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000261/20230032023-11-0707 November 2023 Integrated Inspection Report 05000261 2023003 and 07200060 2023001 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) IR 05000261/20230022023-08-0707 August 2023 Integrated Inspection Report 05000261/2023002 IR 05000261/20234022023-05-30030 May 2023 Cyber Security Inspection Report 05000261/2023402 ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality IR 05000261/20230012023-05-0202 May 2023 Integrated Inspection Report 05000261/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000261/20220062023-03-0101 March 2023 Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23041A2272023-02-13013 February 2023 2022 Q4 Robinson_Workflow Final ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22339A1362022-12-0101 December 2022 2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000261/20220032022-11-0303 November 2022 Integrated Inspection Report 05000261 2022003 IR 05000261/20224022022-10-19019 October 2022 Security Baseline Inspection Report 05000261/2022402 IR 05000261/20220102022-09-26026 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010 IR 05000261/20223012022-09-23023 September 2022 301 Operator License Exam Approval Letter (05000261/2022301) ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000261/20220052022-08-26026 August 2022 Updated Inspection Plan for the H.B Robinson Steam Electric Plant - Report 05000261/2022005-Final IR 05000261/20214042022-08-10010 August 2022 Reissue - H.B. Robinson Steam Electric Plant Security Baseline Inspection Report 05000261/2021404 2024-09-11
[Table view] |
Text
jProgress Energy 10 CFR 54.21 Serial: RNP-RA/12-0100 SEP 2.6 2012 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 REVIEW REQUEST FOR THE PWR VESSEL INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS AT ROBINSON NUCLEAR PLANT
Dear Sir or Madam:
In a letter dated August 10, 2011 (Serial: RNP-RA/1 1-0029), WITHDRAWAL OF REACTOR VESSEL INTERNALS AGING MANAGEMENT PROGRAM INSPECTION PLAN (TAC NO. ME2362), Carolina Power and Light Company (CP&L), now doing business as Progress Energy, had expressed its intention to withdraw the Reactor Vessel Internals Aging Management Program Inspection Plan submittal, dated September 24, 2009.Pursuant to the provisions of Renewed Operating License DPR-23 and consistent with the recommendation of U.S. Nuclear Regulatory Commission ML1 11990086, "NRC Regulatory Issue Summary 2011-07, License Renewal Submittal Information for Pressurized Water Reactor Internals Aging Management," July 21, 2011, CP&L hereby requests NRC approval of the following:
- 1. Withdrawal of the previously submitted Reactor Vessel Internals Aging Management Program Inspection Plan based on the draft Revision 0 of MRP-227, Materials Reliability Program: "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines." 2. The enclosed PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant, which is developed in accordance with the requirements and expectation contained in MRP-227-A.
Progress Energy Carolinas, Inc. 74 0c )Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550 U.S. Nuclear Regulatory Commission Serial: RNP-RA/12-0100 Page 2 of 3 Through utilization of the NRC guidance and expectation, as reflected in Licensee/Action Item 2 of the NRC SE on MRP-227, Revision 0, the Robinson Nuclear Plant (RNP) Aging Management Program Plan (AMP) analysis has concluded that the requirement for application of MRP-227-A as a strategy for managing age-related material degradation in reactor internals components is warranted.
H. B. Robinson Steam Electric Plant Unit No. 2 (HBRSEP), also known as RNP, entered the license renewal period on August 1, 2010. The enclosed AMP is submitted prior to the required submittal date of October 1, 2012. The enclosed AMP for the RNP reactor internals demonstrates that the program adequately manages the effects of aging for reactor internals components and establishes the basis for providing reasonable assurance that the internals components will continue to perform their intended function through the RNP license renewal period of extended operation.
RNP has developed this AMP in conformance with the 10 attributes reflected in, U.S. Nuclear Regulatory Commission NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," Revision 2. Consistent with the protocols of NEI 03-08, Revision 2, "Guidelines for the Management of Materials Issues," RNP adopts MRP-227-A and MRP-228 for development and implementation of its AMP for reactor internals.
The RNP AMP utilizes a combination of prevention, mitigation, and condition monitoring.
Where applicable, credit is taken for existing programs such as water chemistry, inspections prescribed by the ASME Section XI In-service Inspection Program, thimble tube inspections, and mitigation projects such as split pin replacement, combined with augmented inspections or evaluations as recommended by MRP-227-A.
CP&L has actively participated in past and ongoing Electric Power Research Institute (EPRI)and Pressurized Water Reactor Owners Group (PWROG) Reactor Vessel Internals (RVI)activities.
CP&L will continue to maintain cognizance of industry activities related to PWR internals inspection and aging management; and will address/implement industry guidance, stemming from those activities, as appropriate under NEI 03-08 practices.
CP&L will further develop, maintain and implement an AMP program, which is compliant and consistent with the requirements and expectation of top-tier regulatory drivers in which it is rooted.This letter satisfies CP&L's commitment to submit a new AMP no later than October 1, 2012.This letter contains no new commitments.
It is noted, the dates in Table 7-1 of the enclosure are provided for informational purposes to reflect the current projected dates for the performance of these inspections as currently known.The preamble to the table and Note 1 at the end of the table was provided to explain that these dates are subject to change based on plant operation.
However, the requirements of MRP-227-A shall continue to be met. Also, as merger activities between Progress Energy and Duke Energy proceed, additional changes to engineering organizational structure and responsibilities will continue to evolve. This evolution of the organization will facilitate ongoing review of this enclosed document.
As these reviews proceed it is possible that administrative changes to the document may be warranted.
U.S. Nuclear Regulatory Commission Serial: RNP-RA/12-0100 Page 3 of 3 RNP's strategy will continue to be bounded by the parameters given in the enclosed AMP to ensure aging management strategy reflected in the AMP is not negated, the assumptions and the conclusions of the AMP are not rendered invalid, and no undue risk to the workers, the public and the environment is posed.The RNP AMP ensures the long-term integrity and safe operation of the reactor internals components.
The RNP AMP will manage aging effects of the RVIs so that the intended functions will be maintained consistent with the current licensing basis for the period of extended operation.
The Enclosure provides the basis for the preceding statements.
If you should have any questions regarding this submittal, please contact Mr. Richard Hightower, Supervisor
-Regulatory Affairs at (843) 857-1329.I declare under penalty of perjury that the foregoing is true and correct. Executed On: Sincerely, Sharon A. Wheeler Manager -Support Services -Nuclear SAW/am Enclosure 1. Westinghouse Report, WCAP-1 7077-NP, Revision 1, "PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant," August 2012.cc: Mr. V. M. McCree, NRC Region II Ms. A. T. Billoch-Colon, NRC Project Manager, NRR NRC Resident Inspectors, HBRSEP