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| | issue date = 02/18/2016 | | | issue date = 02/18/2016 |
| | title = Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals | | | title = Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals |
| | author name = Glover R M | | | author name = Glover R |
| | author affiliation = Duke Energy Corp | | | author affiliation = Duke Energy Corp |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Serial: RNP-RA/16-0011 FEB 18 Z0\6 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 R. Michael Glover H B Rob i nson Steam Electric Plant Unit 2 Site Vice President Duke Energy Progress 3581 West Entrance Road Hartsville. SC 29550 0 843 857 1701 F 843 8571319 Mike.GI01**rlF_duk*-<n*rgy.com 10 CFR 54.21 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTOR INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (TAC NO. ME9633) Ladies and Gentlemen: By letter dated February 08 , 2016 (ADAMS Accession Number: ML 16019A053), the NRC requested that Duke Energy Progress, Inc., respond to a request for additional information (RAI) regarding the Aging Management Program for the Reactor Vessel Internals at H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. The Duke Energy Progress response to this request (RAl-5(b)-1-2 and RAl-6) is provided in Enclosures 1, 2 and 3 to this letter. Response to RAl-5(b)-1-2, is contained in Enclosures 1 and 2. Enclosure 2, establishes a commitment related to the HBRSEP, Unit No. 2, Cast Austenitic Stainless Steel(CASS) | | {{#Wiki_filter:R. Michael Glover H B Robinson Steam Electric Plant Unit 2 Site Vice President Duke Energy Progress 3581 West Entrance Road Hartsville. SC 29550 0 843 857 1701 F 843 8571319 Mike.GI01**rlF_duk*-<n*rgy.com 10 CFR 54.21 Serial: RNP-RA/16-0011 FEB 18 Z0\6 United States Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTOR INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (TAC NO. ME9633) |
| Lower Support Columns (LSC) in the Reactor Vessel. Response to RAl-6 , is provided in Enclosure 3, to this letter. One regulatory commitment is made in this submittal (Enclosure 2). All other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. It is noted, Robinson has completed all inspections required by ASME Section XI and MRP 227-A, which require removal of the Core Barrel. Indeed, no inspection that requires removal of the Core Barrel, prior to the calendar year 2019, is required by the stated governing consensus codes and standards. Hence, Robinson hereby confirms it is compliant with its Current Licensing Basis (CLB), as prescribed in the requirements and expectation of ASME Section XI and MRP 227-A. If you have any questions regarding this submittal, please contact Mr. Scott Connelly, Manager (Acting) -Nuclear Regulatory Affairs, at (843) 857-1569. | | Ladies and Gentlemen: |
| United States Nuclear Regulatory Commission Serial: RNP-RN16-0011 Page 2 of 3 I declare under penalty of perjury that the foregoing is true and correct. Executed On: Ed,ru.o..°1 1'6 1 :Loi(, Sincerely, R. Michael Glover Site Vice President United States Nuclear Regulatory Commission Serial: RNP-RA/16-0011 Page 3 of 3 RMG/am Enclosure 1: RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTORS INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (RAl-S(b)-1-2) | | By letter dated February 08, 2016 (ADAMS Accession Number: ML16019A053), the NRC requested that Duke Energy Progress, Inc., respond to a request for additional information (RAI) regarding the Aging Management Program for the Reactor Vessel Internals at H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. |
| Enclosure 2: REGULA TORY COMMITMENT Enclosure 3: RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTORS INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (RAl-6) cc: NRC Regional Administrator, NRC, Region II Ms. Martha Barillas, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP Unit No. 2 United States Nuclear Regulatory Commission Enclosure 1 to Serial: RNP-RA/16-0011 2 Pages (including cover page) RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTOR INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (TAC NO. ME9633) DOCKET NO. 50-261 (RAl-S(b)-1-2)
| | The Duke Energy Progress response to this request (RAl-5(b)-1-2 and RAl-6) is provided in Enclosures 1, 2 and 3 to this letter. Response to RAl-5(b)-1-2, is contained in Enclosures 1 and 2. , establishes a commitment related to the HBRSEP, Unit No. 2, Cast Austenitic Stainless Steel(CASS) Lower Support Columns (LSC) in the Reactor Vessel. Response to RAl-6, is provided in Enclosure 3, to this letter. |
| United States Nuclear Regulatory Commission Enclosure 1 to Serial: RNP-RA/16-0011 2 Pages (including cover page) NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 26, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12278A398), Duke Energy Progress, Inc., formerly known as Carolina Power and Light Company, submitted an aging management program for the reactor vessel internals for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No.2. The NRC staff has been reviewing the submittal and has determined that additional information is needed to complete its review. RAl-5(b)-1-2 Action Item 7 addressed based on PWROG-14048-P The NRC staff has determined that the flaw tolerance analysis contained in report PWROG-14048-P utilized conservative assumptions to demonstrate that the likelihood of failure of the LSCs is low during the period of extended operation (PEO). It is reasonable to infer that the functionality of the LSCs will be maintained during the PEO if the likelihood of failure of the LSCs is shown to be low. Therefore, the staff requests the licensee to demonstrate how the flaw tolerance analysis in PWROG-14048-P is applicable to the Robinson LSCs using plant-specific parameters (such as LSC geometry and number of LSCs) and conditions (such as loading conditions and LSC stresses). | | One regulatory commitment is made in this submittal (Enclosure 2). All other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. |
| Action Item 7 addressed based on alternative approach If the licensee determines that PWROG-14048-P is not applicable to the Robinson LSCs or chooses not to apply it, the staff requests that the licensee identify its approach to demonstrating that the functionality of the LSCs will be maintained during the PEO. Response to RAl-S(b)-1-2: | | It is noted, Robinson has completed all inspections required by ASME Section XI and MRP 227-A, which require removal of the Core Barrel. Indeed, no inspection that requires removal of the Core Barrel, prior to the calendar year 2019, is required by the stated governing consensus codes and standards. Hence, Robinson hereby confirms it is compliant with its Current Licensing Basis (CLB), as prescribed in the requirements and expectation of ASME Section XI and MRP 227-A. |
| Duke Energy Progress, Inc., is an active participant in a Pressurized Water Reactor Owners Group (PWROG) program to address lower support column (LSC) functionality analysis on a generic basis. The final phase of this program, currently in process, uses the methodology documented in PWROG-14048-P and is intended to provide justification of plant-specific applicability for all participating plants. This phase also considers the conclusions documented in the NRC Staff Assessment of PWROG-14048-P (ADAMS Accession No. ML 15334A462). Upon completion of this final phase of the program, a revision to PWROG-14048-P will be submitted to the NRC Staff, currently scheduled to be submitted by June 30, 2017. This program will consider H.B. Robinson specific parameters and will provide the applicability justification necessary to address RAl-5(b)-1-2. Duke Energy Progress, Inc., H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2), hereby commits (Enclosure | | If you have any questions regarding this submittal, please contact Mr. Scott Connelly, Manager (Acting) - Nuclear Regulatory Affairs, at (843) 857-1569. |
| : 2) to submit the final phase revision of PWROG-14048-P, which accounts for H.B. Robinson specific parameters and operating conditions and includes the corresponding applicability justification.
| | |
| United States Nuclear Regulatory Commission Enclosure 2 to Serial: RNP-RN16-0011 2 Pages (including cover page) REGULATORY COMMITMENT United States Nuclear Regulatory Commission Enclosure 2 to Serial: RNP-RA/16-0011 2 Pages (including cover page) REGULA TORY COMMITMENT The following table identifies the action committed to by H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, in this submittal. | | United States Nuclear Regulatory Commission Serial: RNP-RN16-0011 Page 2 of 3 I declare under penalty of perjury that the foregoing is true and correct. |
| All other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. | | Executed On: Ed,ru.o..°1 1'61 :Loi(, |
| TYPE (Check One) SCHEDULED COMMITMENT ONE-COMPLETION TIME CONTINUING DATE/EVENT ACTION COMPLIANCE 1 Robinson will submit a copy of the x June 30, 2017 Technical Report associated with .asks related to PWROG PA-MSC-1103, Revision 2, to the NRC by June 30, 2017. The stated Technical Report will contain RNP applicable flaw tolerance analysis developed based upon PWROG-14048-P, as reflected in RAI-5(b)-1-2, of the NRC Letter, dated February 08, 2016 (ADAMS Accession Number: ML 16019A053). | | Sincerely, |
| In particular, this Technical Report will address Action Item 7 from the NRC final safety evaluation (SE) (ADAMS Accession No. ML 11308A770) of the Materials Reliability Program (MRP)-227-A report, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines" (ADAMS Accession No. ML 120170453) in reference to the functionality of the Lower Support Columns. | | ~.4,~~ ~~- |
| United States Nuclear Regulatory Commission Enclosure 3 to Serial: RNP-RA/16-0011 2 Pages (including cover page) RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTOR INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (TAC NO. ME9633) DOCKET NO. 50-261 (RAl-6) | | R. Michael Glover Site Vice President |
| United States Nuclear Regulatory Commission Enclosure 3 to Serial: RNP-RA/16-0011 2 Pages (including cover page) NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 26, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12278A398), Duke Energy Progress, Inc., formerly known as Carolina Power and Light Company, submitted an aging management program for the reactor vessel internals for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No.2. The NRC staff has been reviewing the submittal and has determined that additional information is needed to complete its review. RAl-6 In Section 6.2.5, "SE ApplicanULicensee Action Item 5: Application of Physical Measurements as part of l&E [Inspection and Evaluation] | | |
| Guidelines for B&W [Babcox and Wilcox], CE [Combustion Engineering], and Westinghouse RVI Components," of WCAP-17077-NP, Revision 1, "PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant" (ADAMS Accession No. ML 12278A399), the licensee describes actions to address Action Item 5 from the NRC final SE for the MRP-227-A report. The actions include plans to replace the hold down spring instead of performing MRP-227-A inspections/physical measurements at Robinson. | | United States Nuclear Regulatory Commission Serial: RNP-RA/16-0011 Page 3 of 3 RMG/am : RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTORS INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (RAl-S(b)-1-2) : REGULATORY COMMITMENT : RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTORS INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (RAl-6) cc: NRC Regional Administrator, NRC, Region II Ms. Martha Barillas, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP Unit No. 2 |
| Confirm that the hold down spring has been replaced at Robinson and identify the materials used. Response to RAl-6: Consistent with the actions that were described to address Action Item 5 from the NRC final SE for the MRP-227-A report, Robinson replaced the original Type 304 Stainless Steel hold down spring with a hold down spring fabricated from a modified Type 403 Stainless Steel, which meets and exceeds the requirements from the original code of construction.
| | |
| In particular, the modified Type 403 Stainless Steel is more resistant to stress relaxation and creep than the original Type 304 material. | | United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page) |
| Although in Table 7-1 of the RNP aging management program plan for the reactor vessel internals (ADAMS Accession No. ML 12278A398), Robinson had stated that it tentatively planned (footnote | | RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTOR INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (TAC NO. ME9633) |
| -Note 1) to do a preemptive replacement of the hold down spring in the Fall of 2013 (during Refueling Outage 28), the replacement occurred in the Spring of 2015 (during Refueling Outage 29). It is noted, the revised replacement schedule did not adversely impact the integrity of the core support structures because it occurred in accordance with the requirements and expectation prescribed in MRP-227-A. | | DOCKET NO. 50-261 (RAl-S(b)-1-2) |
| Namely, the replacement occurred within the timeframe specified in MRP-227-A, which is within three cycles of the beginning of the license renewal period. Hence, Robinson hereby confirms that it is compliant with its Current Licensing Basis (CLB). As it was stated earlier, Robinson replaced its 304 Stainless Steel hold down spring with that of the modified Type 403 Stainless Steel hold down spring in the Spring of 2015.}} | | |
| | United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page) |
| | NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) |
| | By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 26, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12278A398), Duke Energy Progress, Inc., formerly known as Carolina Power and Light Company, submitted an aging management program for the reactor vessel internals for H. B. |
| | Robinson Steam Electric Plant (HBRSEP), Unit No.2. The NRC staff has been reviewing the submittal and has determined that additional information is needed to complete its review. |
| | RAl-5(b)-1-2 Action Item 7 addressed based on PWROG-14048-P The NRC staff has determined that the flaw tolerance analysis contained in report PWROG-14048-P utilized conservative assumptions to demonstrate that the likelihood of failure of the LSCs is low during the period of extended operation (PEO). It is reasonable to infer that the functionality of the LSCs will be maintained during the PEO if the likelihood of failure of the LSCs is shown to be low. Therefore, the staff requests the licensee to demonstrate how the flaw tolerance analysis in PWROG-14048-P is applicable to the Robinson LSCs using plant-specific parameters (such as LSC geometry and number of LSCs) and conditions (such as loading conditions and LSC stresses). |
| | Action Item 7 addressed based on alternative approach If the licensee determines that PWROG-14048-P is not applicable to the Robinson LSCs or chooses not to apply it, the staff requests that the licensee identify its approach to demonstrating that the functionality of the LSCs will be maintained during the PEO. |
| | Response to RAl-S(b)-1-2: |
| | Duke Energy Progress, Inc., is an active participant in a Pressurized Water Reactor Owners Group (PWROG) program to address lower support column (LSC) functionality analysis on a generic basis. The final phase of this program, currently in process, uses the methodology documented in PWROG-14048-P and is intended to provide justification of plant-specific applicability for all participating plants. This phase also considers the conclusions documented in the NRC Staff Assessment of PWROG-14048-P (ADAMS Accession No. ML15334A462). Upon completion of this final phase of the program, a revision to PWROG-14048-P will be submitted to the NRC Staff, currently scheduled to be submitted by June 30, 2017. This program will consider H.B. Robinson specific parameters and will provide the applicability justification necessary to address RAl-5(b)-1-2 . Duke Energy Progress, Inc., H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2), hereby commits (Enclosure 2) to submit the final phase revision of PWROG-14048-P, which accounts for H.B. Robinson specific parameters and operating conditions and includes the corresponding applicability justification. |
| | |
| | United States Nuclear Regulatory Commission to Serial: RNP-RN16-0011 2 Pages (including cover page) |
| | REGULATORY COMMITMENT |
| | |
| | United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page) |
| | REGULATORY COMMITMENT The following table identifies the action committed to by H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, in this submittal. All other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. |
| | TYPE (Check One) SCHEDULED COMMITMENT ONE- COMPLETION CONTINUING DATE/EVENT TIME COMPLIANCE ACTION 1 Robinson will submit a copy of the x June 30, 2017 Technical Report associated with |
| | .asks related to PWROG PA-MSC-1103, Revision 2, to the NRC by June 30, 2017. |
| | The stated Technical Report will contain RNP applicable flaw tolerance analysis developed based upon PWROG-14048-P, as reflected in RAI-5(b)-1-2, of the NRC Letter, dated February 08, 2016 (ADAMS Accession Number: ML16019A053). |
| | In particular, this Technical Report will address Action Item 7 from the NRC final safety evaluation (SE) (ADAMS Accession No. ML11308A770) of the Materials Reliability Program (MRP)- |
| | 227-A report, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines" (ADAMS Accession No. ML120170453) in reference to the functionality of the Lower Support Columns. |
| | |
| | United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page) |
| | RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTOR INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (TAC NO. ME9633) |
| | DOCKET NO. 50-261 (RAl-6) |
| | |
| | United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page) |
| | NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) |
| | By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 26, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12278A398), Duke Energy Progress, Inc., formerly known as Carolina Power and Light Company, submitted an aging management program for the reactor vessel internals for H. B. |
| | Robinson Steam Electric Plant (HBRSEP), Unit No.2. The NRC staff has been reviewing the submittal and has determined that additional information is needed to complete its review. |
| | RAl-6 In Section 6.2.5, "SE ApplicanULicensee Action Item 5: Application of Physical Measurements as part of l&E [Inspection and Evaluation] Guidelines for B&W [Babcox and Wilcox], CE |
| | [Combustion Engineering], and Westinghouse RVI Components," of WCAP-17077-NP, Revision 1, "PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant" (ADAMS Accession No. ML12278A399), the licensee describes actions to address Action Item 5 from the NRC final SE for the MRP-227-A report. The actions include plans to replace the hold down spring instead of performing MRP-227-A inspections/physical measurements at Robinson. Confirm that the hold down spring has been replaced at Robinson and identify the materials used. |
| | Response to RAl-6: |
| | Consistent with the actions that were described to address Action Item 5 from the NRC final SE for the MRP-227-A report, Robinson replaced the original Type 304 Stainless Steel hold down spring with a hold down spring fabricated from a modified Type 403 Stainless Steel, which meets and exceeds the requirements from the original code of construction. In particular, the modified Type 403 Stainless Steel is more resistant to stress relaxation and creep than the original Type 304 material. Although in Table 7-1 of the RNP aging management program plan for the reactor vessel internals (ADAMS Accession No. ML12278A398), Robinson had stated that it tentatively planned (footnote - Note 1) to do a preemptive replacement of the hold down spring in the Fall of 2013 (during Refueling Outage 28), the replacement occurred in the Spring of 2015 (during Refueling Outage 29). It is noted, the revised replacement schedule did not adversely impact the integrity of the core support structures because it occurred in accordance with the requirements and expectation prescribed in MRP-227-A. Namely, the replacement occurred within the timeframe specified in MRP-227-A, which is within three cycles of the beginning of the license renewal period. Hence, Robinson hereby confirms that it is compliant with its Current Licensing Basis (CLB). As it was stated earlier, Robinson replaced its 304 Stainless Steel hold down spring with that of the modified Type 403 Stainless Steel hold down spring in the Spring of 2015.}} |
Letter Sequence Response to RAI |
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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
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0015, Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-02-0909 February 2023 Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-22-0245, Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.162022-09-0808 September 2022 Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 RA-22-0210, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-07-28028 July 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0106, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-04-28028 April 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0230, Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2021-09-30030 September 2021 Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan2021-03-11011 March 2021 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-20-0048, Response to Request for Additional Information for Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections2020-03-0404 March 2020 Response to Request for Additional Information for Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections RA-20-0018, Supplement to Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding; Integrated Assessment Submittal2020-01-23023 January 2020 Supplement to Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding; Integrated Assessment Submittal RA-19-0460, Revised Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal2019-12-19019 December 2019 Revised Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal RA-19-0452, Seismic Probabilistic Risk Assessment (Spra), Response to March 12, 2012, Request for Information Regarding Recommendation 2.1: Seismic, of the Near-Term Task Force Related to the Fukushima Dai-ichi Accident2019-12-12012 December 2019 Seismic Probabilistic Risk Assessment (Spra), Response to March 12, 2012, Request for Information Regarding Recommendation 2.1: Seismic, of the Near-Term Task Force Related to the Fukushima Dai-ichi Accident RA-19-0421, Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (RA-19-0145)2019-11-13013 November 2019 Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (RA-19-0145) RA-19-0386, Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.12019-10-24024 October 2019 Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 RA-19-0154, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2019-05-0606 May 2019 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-18-0185, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.46 Annual Report, Including Revised Robinson Large Break Loss of Coolant Accident Report2018-12-10010 December 2018 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.46 Annual Report, Including Revised Robinson Large Break Loss of Coolant Accident Report RA-18-0194, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt TSTF-425, Revision 32018-11-13013 November 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt TSTF-425, Revision 3 RA-18-0193, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power ..2018-11-13013 November 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power .. 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 RA-18-0016, Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses2018-06-0505 June 2018 Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses 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/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 RA-17-0055, Response to Second Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 02017-12-19019 December 2017 Response to Second Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 0 RA-17-0048, Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2)2017-10-30030 October 2017 Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2) RA-17-0043, Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 02017-10-0909 October 2017 Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 0 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 RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)2017-08-0909 August 2017 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001) RA-16-0042, Response to Request for Additional Information Application to Revise Technical Specifications for Methodology Reports DPC-NF-2010, Revision 3 & DPC-NE-2011-P, Revision 2. Redacted Version Enclosed2016-11-17017 November 2016 Response to Request for Additional Information Application to Revise Technical Specifications for Methodology Reports DPC-NF-2010, Revision 3 & DPC-NE-2011-P, Revision 2. Redacted Version Enclosed ML16315A2722016-11-10010 November 2016 Duke Energy Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3008, Revision 0 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. 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 RA-16-0036, Regarding Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-1008, Rev 02016-10-0303 October 2016 Regarding Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-1008, Rev 0 RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation2016-10-0303 October 2016 Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation RNP-RA/16-0072, Response to Request for Additional Information Regarding Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Rev. 22016-09-14014 September 2016 Response to Request for Additional Information Regarding Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Rev. 2 RNP-RA/16-0073, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-09-14014 September 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits ML16230A2342016-07-25025 July 2016 Response to Request for Additional Information License Amendment Request to Adopt National Fire Protection Association Standard 805 RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations2016-07-14014 July 2016 Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations ML16158A0062016-05-25025 May 2016 Response to Request for Additional Information Re License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. Pages 1-21 RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-1742016-05-25025 May 2016 Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 RNP-RA/16-0031, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-05-0909 May 2016 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits RNP-RA/16-0024, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-03-31031 March 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits RNP-RA/16-0017, 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.2016-03-16016 March 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. 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 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 RNP-RA/15-0117, Supplement to Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits2015-12-22022 December 2015 Supplement to Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits 2023-07-07
[Table view] |
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R. Michael Glover H B Robinson Steam Electric Plant Unit 2 Site Vice President Duke Energy Progress 3581 West Entrance Road Hartsville. SC 29550 0 843 857 1701 F 843 8571319 Mike.GI01**rlF_duk*-<n*rgy.com 10 CFR 54.21 Serial: RNP-RA/16-0011 FEB 18 Z0\6 United States Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTOR INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (TAC NO. ME9633)
Ladies and Gentlemen:
By letter dated February 08, 2016 (ADAMS Accession Number: ML16019A053), the NRC requested that Duke Energy Progress, Inc., respond to a request for additional information (RAI) regarding the Aging Management Program for the Reactor Vessel Internals at H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2.
The Duke Energy Progress response to this request (RAl-5(b)-1-2 and RAl-6) is provided in Enclosures 1, 2 and 3 to this letter. Response to RAl-5(b)-1-2, is contained in Enclosures 1 and 2. , establishes a commitment related to the HBRSEP, Unit No. 2, Cast Austenitic Stainless Steel(CASS) Lower Support Columns (LSC) in the Reactor Vessel. Response to RAl-6, is provided in Enclosure 3, to this letter.
One regulatory commitment is made in this submittal (Enclosure 2). All other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
It is noted, Robinson has completed all inspections required by ASME Section XI and MRP 227-A, which require removal of the Core Barrel. Indeed, no inspection that requires removal of the Core Barrel, prior to the calendar year 2019, is required by the stated governing consensus codes and standards. Hence, Robinson hereby confirms it is compliant with its Current Licensing Basis (CLB), as prescribed in the requirements and expectation of ASME Section XI and MRP 227-A.
If you have any questions regarding this submittal, please contact Mr. Scott Connelly, Manager (Acting) - Nuclear Regulatory Affairs, at (843) 857-1569.
United States Nuclear Regulatory Commission Serial: RNP-RN16-0011 Page 2 of 3 I declare under penalty of perjury that the foregoing is true and correct.
Executed On: Ed,ru.o..°1 1'61 :Loi(,
Sincerely,
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R. Michael Glover Site Vice President
United States Nuclear Regulatory Commission Serial: RNP-RA/16-0011 Page 3 of 3 RMG/am : RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTORS INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (RAl-S(b)-1-2) : REGULATORY COMMITMENT : RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTORS INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (RAl-6) cc: NRC Regional Administrator, NRC, Region II Ms. Martha Barillas, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP Unit No. 2
United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page)
RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTOR INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (TAC NO. ME9633)
DOCKET NO. 50-261 (RAl-S(b)-1-2)
United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page)
NRC REQUEST FOR ADDITIONAL INFORMATION (RAI)
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 26, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12278A398), Duke Energy Progress, Inc., formerly known as Carolina Power and Light Company, submitted an aging management program for the reactor vessel internals for H. B.
Robinson Steam Electric Plant (HBRSEP), Unit No.2. The NRC staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
RAl-5(b)-1-2 Action Item 7 addressed based on PWROG-14048-P The NRC staff has determined that the flaw tolerance analysis contained in report PWROG-14048-P utilized conservative assumptions to demonstrate that the likelihood of failure of the LSCs is low during the period of extended operation (PEO). It is reasonable to infer that the functionality of the LSCs will be maintained during the PEO if the likelihood of failure of the LSCs is shown to be low. Therefore, the staff requests the licensee to demonstrate how the flaw tolerance analysis in PWROG-14048-P is applicable to the Robinson LSCs using plant-specific parameters (such as LSC geometry and number of LSCs) and conditions (such as loading conditions and LSC stresses).
Action Item 7 addressed based on alternative approach If the licensee determines that PWROG-14048-P is not applicable to the Robinson LSCs or chooses not to apply it, the staff requests that the licensee identify its approach to demonstrating that the functionality of the LSCs will be maintained during the PEO.
Response to RAl-S(b)-1-2:
Duke Energy Progress, Inc., is an active participant in a Pressurized Water Reactor Owners Group (PWROG) program to address lower support column (LSC) functionality analysis on a generic basis. The final phase of this program, currently in process, uses the methodology documented in PWROG-14048-P and is intended to provide justification of plant-specific applicability for all participating plants. This phase also considers the conclusions documented in the NRC Staff Assessment of PWROG-14048-P (ADAMS Accession No. ML15334A462). Upon completion of this final phase of the program, a revision to PWROG-14048-P will be submitted to the NRC Staff, currently scheduled to be submitted by June 30, 2017. This program will consider H.B. Robinson specific parameters and will provide the applicability justification necessary to address RAl-5(b)-1-2 . Duke Energy Progress, Inc., H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2), hereby commits (Enclosure 2) to submit the final phase revision of PWROG-14048-P, which accounts for H.B. Robinson specific parameters and operating conditions and includes the corresponding applicability justification.
United States Nuclear Regulatory Commission to Serial: RNP-RN16-0011 2 Pages (including cover page)
REGULATORY COMMITMENT
United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page)
REGULATORY COMMITMENT The following table identifies the action committed to by H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, in this submittal. All other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TYPE (Check One) SCHEDULED COMMITMENT ONE- COMPLETION CONTINUING DATE/EVENT TIME COMPLIANCE ACTION 1 Robinson will submit a copy of the x June 30, 2017 Technical Report associated with
.asks related to PWROG PA-MSC-1103, Revision 2, to the NRC by June 30, 2017.
The stated Technical Report will contain RNP applicable flaw tolerance analysis developed based upon PWROG-14048-P, as reflected in RAI-5(b)-1-2, of the NRC Letter, dated February 08, 2016 (ADAMS Accession Number: ML16019A053).
In particular, this Technical Report will address Action Item 7 from the NRC final safety evaluation (SE) (ADAMS Accession No. ML11308A770) of the Materials Reliability Program (MRP)-
227-A report, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines" (ADAMS Accession No. ML120170453) in reference to the functionality of the Lower Support Columns.
United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page)
RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PRESSURIZED WATER REACTOR INTERNALS PROGRAM PLAN FOR AGING MANAGEMENT OF REACTOR INTERNALS (TAC NO. ME9633)
DOCKET NO. 50-261 (RAl-6)
United States Nuclear Regulatory Commission to Serial: RNP-RA/16-0011 2 Pages (including cover page)
NRC REQUEST FOR ADDITIONAL INFORMATION (RAI)
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 26, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12278A398), Duke Energy Progress, Inc., formerly known as Carolina Power and Light Company, submitted an aging management program for the reactor vessel internals for H. B.
Robinson Steam Electric Plant (HBRSEP), Unit No.2. The NRC staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
RAl-6 In Section 6.2.5, "SE ApplicanULicensee Action Item 5: Application of Physical Measurements as part of l&E [Inspection and Evaluation] Guidelines for B&W [Babcox and Wilcox], CE
[Combustion Engineering], and Westinghouse RVI Components," of WCAP-17077-NP, Revision 1, "PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant" (ADAMS Accession No. ML12278A399), the licensee describes actions to address Action Item 5 from the NRC final SE for the MRP-227-A report. The actions include plans to replace the hold down spring instead of performing MRP-227-A inspections/physical measurements at Robinson. Confirm that the hold down spring has been replaced at Robinson and identify the materials used.
Response to RAl-6:
Consistent with the actions that were described to address Action Item 5 from the NRC final SE for the MRP-227-A report, Robinson replaced the original Type 304 Stainless Steel hold down spring with a hold down spring fabricated from a modified Type 403 Stainless Steel, which meets and exceeds the requirements from the original code of construction. In particular, the modified Type 403 Stainless Steel is more resistant to stress relaxation and creep than the original Type 304 material. Although in Table 7-1 of the RNP aging management program plan for the reactor vessel internals (ADAMS Accession No. ML12278A398), Robinson had stated that it tentatively planned (footnote - Note 1) to do a preemptive replacement of the hold down spring in the Fall of 2013 (during Refueling Outage 28), the replacement occurred in the Spring of 2015 (during Refueling Outage 29). It is noted, the revised replacement schedule did not adversely impact the integrity of the core support structures because it occurred in accordance with the requirements and expectation prescribed in MRP-227-A. Namely, the replacement occurred within the timeframe specified in MRP-227-A, which is within three cycles of the beginning of the license renewal period. Hence, Robinson hereby confirms that it is compliant with its Current Licensing Basis (CLB). As it was stated earlier, Robinson replaced its 304 Stainless Steel hold down spring with that of the modified Type 403 Stainless Steel hold down spring in the Spring of 2015.