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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
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Category:Letter type:RNP
MONTHYEARRNP-RA/21-0035, Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-18018 February 2021 Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/20-0234, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2020-07-23023 July 2020 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RNP-RA/20-0199, Registration of Use of Spent Fuel Casks2020-06-25025 June 2020 Registration of Use of Spent Fuel Casks RNP-RA/18-0063, Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal2018-11-29029 November 2018 Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal RNP-RA/18-0060, Transmittal of Core Operating Limits Report2018-10-17017 October 2018 Transmittal of Core Operating Limits Report RNP-RA/18-0050, Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change2018-08-0101 August 2018 Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/18-0039, Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis2018-06-27027 June 2018 Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis RNP-RA/18-0041, Independent Spent Fuel Storage Installation - Register as User for Cask2018-06-13013 June 2018 Independent Spent Fuel Storage Installation - Register as User for Cask RNP-RA/18-0036, Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ...2018-05-16016 May 2018 Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ... RNP-RA/18-0029, Submittal of 2017 Annual Radiological Environmental Operating Report2018-05-0808 May 2018 Submittal of 2017 Annual Radiological Environmental Operating Report RNP-RA/18-0031, (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 352018-04-23023 April 2018 (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 35 RNP-RA/18-0015, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program2018-04-16016 April 2018 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2018-04-0202 April 2018 Report of Changes Pursuant to 10 CFR 50.59(d)(2) RNP-RA/18-0020, Notification of Change in Licensed Operator Status2018-02-20020 February 2018 Notification of Change in Licensed Operator Status RNP-RA/18-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2018-01-23023 January 2018 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2018-01-0808 January 2018 Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0086, Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses2017-12-14014 December 2017 Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses RNP-RA/17-0081, Submittal of Change in Licensed Operators Medical Status2017-12-11011 December 2017 Submittal of Change in Licensed Operators Medical Status RNP-RA/17-0079, Operator License Renewal Application2017-12-0707 December 2017 Operator License Renewal Application RNP-RA/17-0071, Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks2017-10-19019 October 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks RNP-RA/17-0068, Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-09-28028 September 2017 Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0037, License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers2017-09-27027 September 2017 License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/17-0043, Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-42017-09-22022 September 2017 Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4 RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report2017-09-18018 September 2017 Refueling Outage 30 Steam Generator Tube Inspection Report RNP-RA/17-0060, Notification of Change in Licensed Operator Status2017-08-10010 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0058, Notification of Change in Licensed Operator Status2017-08-0303 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0055, Transmittal of Core Operating Limits Report for Cycle 312017-07-26026 July 2017 Transmittal of Core Operating Limits Report for Cycle 31 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 RNP-RA/17-0051, Submittal of Nine Day Inservice Inspection Summary Report2017-06-29029 June 2017 Submittal of Nine Day Inservice Inspection Summary Report RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions RNP-RA/17-0038, (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report2017-05-0909 May 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) RNP-RA/17-0036, (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 342017-04-25025 April 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 34 RNP-RA/17-0031, Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 02017-04-20020 April 2017 Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 0 RNP-RA/17-0033, Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal2017-04-12012 April 2017 Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal RNP-RA/17-0014, Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0028, Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0021, Transmittal of Core Operating Limits Report2017-03-13013 March 2017 Transmittal of Core Operating Limits Report RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 22017-03-0808 March 2017 Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RNP-RA/17-0015, Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/17-0016, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2017-02-22022 February 2017 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RNP-RA/17-0015, H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/16-0100, Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-2272017-01-24024 January 2017 Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-227 RNP-RA/16-0097, Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/20154052016-12-15015 December 2016 Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/2015405 RNP-RA/16-0089, Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2016-11-10010 November 2016 Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/16-0090, Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise2016-11-10010 November 2016 Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-31031 October 2016 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-0505 October 2016 Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-10-0505 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. 2021-02-18
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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 ML111990086, "NRC Regulatory Issue Summary 2011-07, License Renewal Submittal Informationfor Pressurized Water Reactor InternalsAging 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, MaterialsReliability Program: "PressurizedWater Reactor InternalsInspection 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.
Robinson Nuclear Plant 74 0c )
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, "Guidelinesfor the Management of MaterialsIssues," 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