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 Reactors
Letter Sequence Response to RAI | |
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EPID:L-2020-LLL-0000, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. (Open) | |
Initiation Administration | |
MONTHYEARML18099A1302018-04-0505 April 2018
[Table View]Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. Project stage: Request 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 Project stage: Request 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 .. Project stage: Response to RAI 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 Project stage: Response to RAI RA-20-0007, Request to Correct Administrative Renewed Facility Operating License Error2020-01-21021 January 2020 Request to Correct Administrative Renewed Facility Operating License Error Project stage: Request ML20049A0342020-02-16016 February 2020 NRR E-mail Capture - Accepted for Review - Robinson Unit 2 to Correct Administrative Renewed Facility Operating License Error in the 50.69 LAR EPID: L-2020-LLL-0000 Project stage: Acceptance Review ML20083F6172020-04-0606 April 2020 Correction to Amendment No. 266 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Project stage: Other 2019-05-06 |
ML19126A143 | |
Person / Time | |
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Site: | Robinson |
Issue date: | 05/06/2019 |
From: | Kapopoulos E Duke Energy Progress |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
RA-19-0154 | |
Download: ML19126A143 (24) | |
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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/16-0073, 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 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 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 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. 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Pages 1-21 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. 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 2024-07-26 |
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Ernest J. Kapopoulos, Jr. H. B. Robinson Steam Electric Plant Unit 2 Site Vice President Duke Energy 3581 West Entrance Road Hartsville, SC 29550 O: 843 951 1701 F: 843 857 1319
Application to Adopt 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors" Supplement to the Application to Adopt 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors"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 Reactors"Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69 Risk-Informed Categorization of Structures, Systems, and Components
The process to categorize each system will be consistent with the guidance in NEI 00-04, "10 CFR 50.69 SSC Categorization Guideline," as endorsed by RG 1.201. RG 1.201 states that "the implementation of all processes described in NEI 00-04 (i.e., Sections 2 through 12) is integral to providing reasonable confidence" and that "all aspects of NEI 00-04 must be followed to achieve reasonable confidence in the evaluations required by §50.69(c)(1)(iv)."
In accordance with NEI 00-04, sensitivity studies will be used to determine whether other conditions might lead to the component being safety significant. The assessment of the uncertainties, therefore, is appropriately addressed by the sensitivity studies required by this risk-informed application.
UU
HBRSEP, Unit No. 2 1 Amendment No. 246 APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-23
Duke Energy Progress, LLC. (the term licensee in Appendix B refers to Duke Energy Progress, LLC.) shall comply with the following conditions on the schedules noted below:
Amendment Number Additional Conditions Implementation Date 176 The licensee is authorized to relocate certain requirements included in
Appendix A and the former Appendix B to licensee-controlled documents.
Implementation of this amendment
shall include the relocation of these
requirements to the appropriate
documents, as described in the licensee's letters dated September 10, 1997, and October 13, 1997, evaluated in the NRC staff's Safety
Evaluation enclosed with this
amendment.
This amendment is
effective immediately
and shall be implemented within
90 days of the date of
this amendment.
219 Upon implementation of the amendment adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by TS 5.5.17.c.(i), the assessment of CRE habitability as required by TS 5.5.17.c.(ii),
and the measurement of CRE pressure as
required by TS 5.5.17.d, shall be considered met. Following implementation:
(a) The first performance of TS 5.5.17.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from January 27,2003, the This amendment is
effective immediately and shall be implemented as specified APPENDIX B ADDITIONAL CONDITIONS HBRSEP, Unit No. 2 2 Amendment No. 219 date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than
6 years.
(b) The first performance of the periodic assessment of CRE habitability, TS 5.5.17.c.(ii), shall be within the next 9 months.
(c) The first performance of the periodic measurement of CRE pressure, TS 5.5.17.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as
measured from the date of the most recent successful pressure measurement test.