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Category:E-Mail
MONTHYEARML24002A7382024-01-0202 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Duke'S August 20, 2023, License Amendment Request for Robinson, Unit 2 ML23262B4502023-09-19019 September 2023 NRR E-mail Capture - H. B. Robinson Steam Electric Plant, Unit 2 - Acceptance of License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures Based on Leak-Before-Break Methodology ML23220A2342023-08-0808 August 2023 NRR E-mail Capture - Robinson, Unit 2 - Acceptance Review Results for Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML23172A0132023-06-20020 June 2023 Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23153A1892023-06-0202 June 2023 Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23131A4192023-05-10010 May 2023 003 Radiation Safety Baseline Inspection Information Request ML23124A1212023-05-0404 May 2023 Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) ML23011A0152023-01-11011 January 2023 NRR E-mail Capture - Request for Additional Information to Duke'S Request for Robinson to Add Feedwater Isolation Function to TS 3.3.2 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML22285A1552022-10-12012 October 2022 NRR E-mail Capture - H. B. Robinson, Unit 2 - Acceptance of License Amendment Request Regarding the Addition of Feedwater Isolation Function to TS 3.3.2 and Removal of Obsolete Content from TS 2.1.1.1 and TS 5.6.5.b ML22222A1082022-08-10010 August 2022 NRR E-mail Capture - Request for Additional Information Regarding Duke'S Request to Remove 4.160 Kv Bus 2 from Surveillance Requirement 3.8.1.16 ML22146A3652022-05-25025 May 2022 Acceptance of Requested Licensing Action License Amendment Request for Application to Revise Surveillance Requirement 3.8.1.16 ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22112A1482022-04-22022 April 2022 Correction_H. B. Robinson Steam Electric Plant, Unit 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 ML22080A0042022-03-18018 March 2022 Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22012A3662022-01-12012 January 2022 Acceptance of Requested Licensing Action License Amendment Re2uest for Application to Revise Technical Specification to Adopt TSTF-577, Revised Frequencies for Steam Generating Tube Inspections ML22005A0872022-01-0505 January 2022 Acceptance of Requested Licensing Action Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21295A2992021-10-22022 October 2021 Document Request for Robinson Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021004 ML21286A6612021-10-13013 October 2021 Acceptance for Review of Proposed Alternative ISI-05-017 for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21119A2272021-04-29029 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-9, EPID: L-2021-LLR-0024 ML21116A2592021-04-26026 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-8, EPID: L-2021-LLR-0023 ML21116A2582021-04-26026 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-3, EPID: L-2021-LLR-0020 ML21113A1312021-04-23023 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-5, EPID: L-2021-LLR-0021 ML21110A1462021-04-20020 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results: IST-RR-7, EPID: L-2021-LLR-0022 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20353A1302020-12-18018 December 2020 2021 Hbr 50.59 Info Request - E-mail Request- Upcoming 50.59 Inspection (IP71111.17T)- Week of March 1-5, 2021 ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20063M1942020-02-21021 February 2020 NRR E-mail Capture - Accepted for Review - Robinson Unit 2 One-Time Pressure Relief Valve Test Frequency Extension EPID: L-2020-LLR-0019 ML20085F9312020-02-20020 February 2020 SPRA - Spr Audit Questions - 2nd Batch 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 ML20063L4562020-02-0404 February 2020 NRR E-mail Capture - RAI - Robinson Relief Req Rx Vessel Cold Leg Nozzle Dissimilar Meter Butt Weld Inspection Interval EPID L-2019-LLR-0072 ML20087N6632020-02-0303 February 2020 SPRA - Spr Audit Questions Redacted ML20027C2042020-01-27027 January 2020 Audit Documents Needed for the Robinson Seismic Probabilistic Risk Assessment Review - FLEX and HRA References ML20015A1892020-01-13013 January 2020 Audit Documents Needed for the Robinson SPRA Review - Fragility Analysis ML20009C0922020-01-0808 January 2020 Audit Documents Needed for the Robinson SPRA Review - Seismic Hazard Analysis ML19365A0482019-12-30030 December 2019 Request for Eportal Access for Audit Review of the Robinson SPRA Supporting Documents ML19365A0462019-12-18018 December 2019 Audit Documents Needed for the Robinson SPRA Review ML19288A2942019-10-15015 October 2019 NRR E-mail Capture - RAIs for Robinson Revision to RPV Surveillance Program Withdrawal Schedule ML19283A0372019-09-26026 September 2019 Draft Requests for Additional Information for H.B. Robinson LAR to Revise TS 3.8.2, AC Sources - Shutdown, SR 3.8.2.1 ML19235A1202019-08-21021 August 2019 Acceptance Review for Robinson LAR to Add Feedwater Bypass Valve to TS 3.7.3 (L-2019-LLA-0170) 2024-01-02
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NRR-PMDAPEm Resource From: Galvin, Dennis Sent: Wednesday, June 15, 2016 2:50 PM To: Scott Connelly (Scott.Connelly@duke-energy.com); Lavin, Kelly (Kelly.Lavin@duke-energy.com)
Cc: Robinson, Jay; Barrett, Harold; Metzger, Brian; Orf, Tracy; Green, Kimberly
Subject:
Robinson NFPA-805 LAR Attachment L Draft RAI (MF2746)
Attachments: Robinson NFPA-805 LAR Attachment L Draft RAI MF2746.docx Scott By letter dated September 16, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML13267A211), Duke Energy Progress, Inc., (the licensee) submitted a license amendment request (LAR) for H. B. Robinson Steam Electric Plant Unit No. 2 (Robinson). This LAR would adopt a new fire protection licensing basis that complies with the requirements of Title 10 of the Code of Federal Regulations, Sections 50.48(a) and (c); the guidance in Regulatory Guide 1.205, Revision 1, "Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants"; and National Fire Protection Association (NFPA) 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants" (2001 Edition).
By letter dated May 25, 2016 (ADAMS Accession Nos. ML16158A006 and ML16158A267), the licensee provided a response to a staff request for additional information (RAI) and revisions to several sections of the LAR. In LAR Attachment L, NFPA 805, Chapter 3 Requirements for Approval, the licensee included new Approval Request 5 that requested NRC staff approval for the use of certain insulation materials. The NRC staff has determined that additional information is needed to complete its review related to that request and as such, Fire Protection Engineering (FPE) RAI 16 is attached.
A Sensitive Unclassified Non-Safeguards Information (SUNSI) review was completed by the staff on the draft RAIs and the staff concluded the RAIs do not contain SUNSI. If you find any information needs to be withheld from the public, please notify me within 5 days of receipt of this email.
Please submit your response to these RAIs within 30 days of this email. If you need a clarification call for the attached draft RAIs, or you need to change the RAI response due date, please contact me at (301) 415-6256.
Respectfully, Dennis Galvin Project Manager U.S Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Licensing Project Branch 2-2 301-415-6256 1
Hearing Identifier: NRR_PMDA Email Number: 2904 Mail Envelope Properties (Dennis.Galvin@nrc.gov20160615144900)
Subject:
Robinson NFPA-805 LAR Attachment L Draft RAI (MF2746)
Sent Date: 6/15/2016 2:49:55 PM Received Date: 6/15/2016 2:49:00 PM From: Galvin, Dennis Created By: Dennis.Galvin@nrc.gov Recipients:
"Robinson, Jay" <Jay.Robinson@nrc.gov>
Tracking Status: None "Barrett, Harold" <Harold.Barrett@nrc.gov>
Tracking Status: None "Metzger, Brian" <Brian.Metzger@nrc.gov>
Tracking Status: None "Orf, Tracy" <Tracy.Orf@nrc.gov>
Tracking Status: None "Green, Kimberly" <Kimberly.Green@nrc.gov>
Tracking Status: None "Scott Connelly (Scott.Connelly@duke-energy.com)" <Scott.Connelly@duke-energy.com>
Tracking Status: None "Lavin, Kelly (Kelly.Lavin@duke-energy.com)" <Kelly.Lavin@duke-energy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 2101 6/15/2016 2:49:00 PM Robinson NFPA-805 LAR Attachment L Draft RAI MF2746.docx 23268 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD (NFPA) 805, PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS, DUKE ENERGY PROGRESS, INC.
H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 DOCKET NO. 50-261 Fire Protection Engineering (FPE) Request for Additional Information (RAI) 16 In accordance with 10 CFR 50.48(c)(2)(vii), a licensee may request NRC approval for use of a performance-based (PB) method as a means of demonstrating compliance with the prescriptive NFPA 805, Chapter 3, fundamental fire protection program (FPP) elements and minimum design requirements. Paragraph 50.48(c)(2)(vii) of 10 CFR requires that an acceptable PB approach accomplish the following:
(A) Satisfy the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release; (B) Maintain safety margins; and (C) Maintain fire protection defense-in-depth (fire prevention, fire detection, fire suppression, mitigation, and post-fire safe shutdown capability).
In a letter dated May 25, 2016 (ADAMS Accession Nos. ML16158A006 and ML16158A267), the licensee revised the license amendment request (LAR) Attachment L, NFPA 805, Chapter 3 Requirements for Approval, by adding an additional approval request not submitted with its original LAR. The licensee requested NRC staff review and approval of a PB method to demonstrate an equivalent level of fire protection for the requirements of NFPA 805 Section 3.3.4, Insulation Materials because the insulation materials do not meet the definition of limited combustible due to the heat value exceeding 3500 Btu/Lb. Based on the information provided by the licensee in its request, the NRC staff was unable to complete its review.
The licensee did not fully address the requirements of 10 CFR 50.48(c)(2)(vii) in the following sections of the approval request: Basis for Request, Nuclear Safety and Radiological Release Performance Criteria, and Safety Margin and Defense-In-Depth. In particular, the licensee did not fully address the requirements for using insulation materials with a heat value exceeding 3500 Btu/Lb.
The NRC staff requests that the licensee revise the approval request to fully address 10 CFR 50.48 (c)(2)(vii). The revised approval request should address how the PB method (1) satisfies the performance goals, performance objectives, and performance criteria specified in NFPA 805
related to nuclear safety and radiological release; (2) maintains safety margins; and (3) maintains fire protection defense-in-depth per 10 CFR 50.48 (c)(2)(vii).