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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: Barillas, Martha Sent: Tuesday, March 31, 2015 1:28 PM To: Richard.Hightower@duke-energy.com; Connelly, Scott (Scott.Connelly@duke-energy.com)
Cc: Helton, Shana; Miller, Barry
Subject:
Robinson NFPA-805 DRAFT follow-up RAI to 90-day RAI responses Attachments: Robinson Draft Follow-up 90 day_FM and RR RAI.docx Richard/Scott, By letter dated September 16, 2013, Duke Energy Progress Inc., the licensee of H. B. Robinson Steam Electric Plant, Unit 2 (HBRSEP), submitted a license amendment request to change its fire protection program to one based on the National Fire Protection Association (NFPA) Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, as incorporated into Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.48(c) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13267A211). By letter December 22, 2014 (ADAMS Accession No. ML15005A073), you provided 90-day responses to staff request for additional information (RAI).
To complete its review, the NRC staff has the following follow-up draft request for additional information (RAI) attached.
Please see the attached RAI in DRAFT form.
A Sensitive Unclassified Non-Safeguards Information (SUNSI) review was completed by the staff on the draft RAI and the staff concluded the RAI 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 RAI within 30 days of this email. If you need a clarification call for the attached draft 90-day follow-up RAI, or you need to change the RAI response due date, please contact me at (301)-415-2760.
Respectfully, Martha Barillas Project Manager Shearon Harris & H. B. Robinson NRR/DORL/Licensing Branch II-2 US Nuclear Regulatory Commission 301-415-2760 1
Hearing Identifier: NRR_PMDA Email Number: 1972 Mail Envelope Properties (Martha.Barillas@nrc.gov20150331132700)
Subject:
Robinson NFPA-805 DRAFT follow-up RAI to 90-day RAI responses Sent Date: 3/31/2015 1:27:41 PM Received Date: 3/31/2015 1:27:00 PM From: Barillas, Martha Created By: Martha.Barillas@nrc.gov Recipients:
"Helton, Shana" <Shana.Helton@nrc.gov>
Tracking Status: None "Miller, Barry" <Barry.Miller@nrc.gov>
Tracking Status: None "Richard.Hightower@duke-energy.com" <Richard.Hightower@duke-energy.com>
Tracking Status: None "Connelly, Scott (Scott.Connelly@duke-energy.com)" <Scott.Connelly@duke-energy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1675 3/31/2015 1:27:00 PM Robinson Draft Follow-up 90 day_FM and RR RAI.docx 28540 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
DRAFT Robinson NFPA-805 Follow-up RAIs to 90-Day RAI Response Fire Modeling (FM) RAI 01.o.01 In a letter dated December 22, 2014 (ADAMS Accession No. ML15005A073), the licensee responded to FM RAI 01.o and explained that the individual panels considered in the main control room (MCR) abandonment analysis were effectively separated by double wall construction and therefore, propagation to adjacent cabinets was not assumed. In NUREG/CR-6850, EPRl/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, Appendix S, Section S.1, it is recommended that in order to assume there is no fire propagation between cabinets, an air-gap must be present. However, the licensee did not state such an assumption (e.g., that an air-gap was present between the walls of the electrical cabinets,) only that the panels were of double wall construction.
State whether the individual panels considered in the MCR abandonment analysis are separated by a double wall with an air-gap or provide the technical justification for not assuming fire propagation between cabinets.
Radiation Release 02.01 In a letter dated December 22, 2014 (ADAMS Accession No. ML15005A073), the licensee responded to RR 02described its evaluationof the potential for radioactive release and radiation exposure to members of the public using a quantitative analysis (i.e., dose calculation) for radiological storage and sea-land containers in the RCA Yard. The dose calculation considered dry active waste (DAW) radionuclide distribution and activities, atmospheric dispersion, distance from the RCA Yard to the site exclusion boundary, release fraction, burn time, and plume exposure period.
From the NRC staffs review of the licensees analysis, it was determined that although gaseous radioactive releases and radiation exposures were evaluated, liquid radioactive releases and radiation exposures due to the direct effects of fire suppression activities were not evaluated.
a) Provide an analysis that demonstrates liquid radioactive releases and radiation exposures to members of the public are as low as reasonably achievable (ALARA) and do not exceed the applicable 10 CFR Part 20 dose limits. The analysis should describe:
- i. The liquid radionuclide distribution and activities (and their basis).
ii. The method, any inputs (and their basis), and assumptions used in the analysis.
b) Describe the administrative controls such as procedures and training that will limit the amount of activity which may be present in radiological storage and sea-land type containers in the RCA Yard.
c) Describe the engineering controls such as catch basins to collect leakage for sampling, storm drain covers, diversion equipment, or other means to prevent water runoff used to contain potentially contaminated fire suppression water runoff for radiological storage and sea-land containers in the RCA Yard.