Letter Sequence Supplement |
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CAC:MF7102, Implement 10 CFR 50, Appendix J, Option B (Approved, Closed) |
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MONTHYEARRNP-RA/15-0090, Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test Interval And..2015-11-19019 November 2015 Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test Interval And.. Project stage: Other RNP-RA/16-0065, Supplement to Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test.2016-08-18018 August 2016 Supplement to Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test. Project stage: Supplement ML16201A1952016-10-11011 October 2016 Issuance of Amendment to Extend Containment Leakage Test Frequencies Project stage: Approval 2016-10-11
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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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AUG 1 *s: 201& Serial: RNP-RA/16-0065 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 I RENEWED LICENSE NO. DPR-23 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 1704 F: 843 857 1319 Mike. G/o1*er@d11ke-energy
.com 10 CFR 50.90 SUPPLEMENT TO PROPOSED AMENDMENT TO TECHNICAL SPECIFICATION 5.5.16 FOR THE ADOPTION OF OPTION B OF 10 CFR 50, APPENDIX J FOR TYPE B AND TYPE C TESTING AND THE PERMANENT CHANGE IN 10 CFR 50, APPENDIX J, INTEGRATED LEAK RATE TEST INTERVAL AND TYPE C LEAK RATE TESTING FREQUENCY
References:
- 1. Letter from R. Michael Glover (Duke Energy Progress , Inc.) to the U.S. Nuclear Regulatory Commission (Serial: RNP-RA/15-0090), Proposed Amendment to Technical Specification
- 5. 5. 16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 1 O CFR 50, Appendix J, Integrated Leak Rate Test Interval and Type C Leak Rate Testing Frequency, dated November 19, 2015, ADAMS Accession Number ML15323A085.
Dear Sir/Madam:
By letter dated November 19, 2015 (Reference 1 ), Duke Energy Progress, Inc. submitted a request for an amendment to the Technical Specifications (TS) for H.B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2).
The proposed change requests to revise TS 5.5.16, Containment Leakage Rate Testing Program, TS 3.6.1, Containment, and TS 3.6.2, Containment Air Lock, for HBRSEP2, to allow the following:
Increase in the existing integrated leak rate test (ILRT) program test interval from 10 to 15 years, Adopt 1 O CFR 50, Appendix J, Option B, as modified by approved exemptions, for the performance-based testing of Types B and C tested components in accordance with the guidance of Technical Specification Task Force (TSTF)-52, Implement 10 CFR 50, Appendix J , Option B (Reference 11 of the Enclosure),
U.S. Nuclear Regulatory Commission Serial: RNP-RA/16-0065 Page2 Allow an extension to the 120-month frequency currently permitted by Option B for Type B leakage rate testing, Allow an extension from the 60-month frequency currently permitted by Option B to a 75-month frequency for Type C leakage rate testing, The proposed change would also adopt a more conservative grace interval of 9 months, for Type B and Type C tests in accordance with Nuclear Energy Institute (NEI) Topical Report NEI 94-01, revision 3-A. Duke Energy Progress, Inc. is submitting this supplement to Reference 1 as discussed with the NRC Project Manager via teleconference held on August 10, 2016. Updated markup and retyped TS pages are provided in the enclosure to this letter. Please address any comments or questions regarding this matter to Mr. Tony Pilo, Acting Manager-Nuclear Regulatory Affairs at (843) 857-1409.
I declare under penalty of perjury that the foregoing is true and correct. Executed on
\ 5 I 2016. Sincerely, R. Michael Glover Site Vice President RMG/jmw Enclosure cc: Region Administrator, NRC, Region II Dennis Galvin, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP2 Ms. S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC)
U.S. Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/16-0065 3 Pages (including this cover page) Supplemental Technical Specifications Markup and Retyped Page The markup and retyped Technical Specifications Page has been revised as discussed per teleconference.
The revised pages are provided by means of this Enclosure and supersedes those pages conveyed via the original submittal.
Please replace the pages of the original submittal as indicated below. Original Page Revised Page TS Markup: 5. 0-22 TS Markup: 5.0-22 TS Retyped: 5.0-22 TS Retyped: 5.0-22 Insert 1: NEI 94-01 , "Industry Guideline for Implementing Based Option of 10 CFR Part 50, Appendix J ," Revision 3-A , dated July 2012 , and the conditions and limitations specified in NEI 94-01 , Revision 2-A. dated October 2008. Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16 The containment design pressure is 42 psig. Containment Leakage Rate Testing Program The peak containment pressure.
Pa, is specified as the containment design pressure of 42 psig, whieh exeeeas the peak calculated eoAtainment iAternal pressure for the design basis loss of coolant accident.
The maximum allowable containment leakage rate. La, at Pa, shall be O." U of the containment air weight per day. Leakage rate acceptance criteria are: LJ---7 v. Containment leakage rate acceptance criteria is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are< 0.60 La.for the Type Band Type C tests, and !Insert 2 1-7 < 0. 75 La for Type A tests. The provisions of SR 3.0.3 applicable to the Containment Leakage Rate Testing Program.
The program shall include the followino elements:
Insert 2: 2. Air lock testing acceptance criteria are: a. Overall air lock leakage rate 0.05 La when tested Pa. (continued)
- b. For each door , leakage rate 0.01 La when pressurized 42 psig. Insert 3: Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50 , Appendix J. HBRSEP Unit No. 2 5.0-22 Amendment No.-fi9-Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16 5.5.17 Containment Leakage Rate Testing Program A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in NEI 94-01, "Industry Guideline for Implementing Based Option of 10 CFR Part 50, Appendix J," Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008. The peak containment pressure, Pa. is specified as the containment design pressure of 42 psig. The containment design pressure is 42 psig. The maximum allowable containment leakage rate, La. at Pa. shall be 0.1 % of the containment air weight per day. Leakage rate acceptance criteria are: 1. Containment leakage rate acceptance criterion 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria 0.60 La for the Type B and Type C tests, and 0. 75 La for Type A tests. 2. Air lock testing acceptance criteria are: a. Overall air lock leakage rate is s 0.05 La when tested Pa. b. For each door, leakage rate is s 0.01 La when pressurized to 42 psig. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J. Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be implemented to ensure that, with an OPERABLE Control Room Emergency Filtration System, CRE occupants can control the nuclear power unit safely following a radiological event, hazardous chemical release, or a smoke challenge.
The program shall include the following elements: (continued)
HBRSEP Unit No. 2 5.0-22 Amendment No.