|
|
(13 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML15352A207 | | | number = ML15352A207 |
| | issue date = 04/14/2016 | | | issue date = 04/14/2016 |
| | title = Oconee Nuclear Station, Units 1, 2, and 3 (PUBLIC)- Staff Assessment of Response to Request for Information Pursuant to 10 CFR 50.54(f) Flood-Causing Mechanisms Reevaluation (CAC Nos. MF1012, 1013 and 1014) | | | title = (PUBLIC)- Staff Assessment of Response to Request for Information Pursuant to 10 CFR 50.54(f) Flood-Causing Mechanisms Reevaluation (CAC Nos. MF1012, 1013 and 1014) |
| | author name = Boland A, Davis J R | | | author name = Boland A, Davis J |
| | author affiliation = NRC/NRR/DORL, NRC/NRR/JLD | | | author affiliation = NRC/NRR/DORL, NRC/NRR/JLD |
| | addressee name = Batson S | | | addressee name = Batson S |
Line 14: |
Line 14: |
| | page count = 4 | | | page count = 4 |
| | project = CAC:MF1012, CAC:MF1013, CAC:MF1014 | | | project = CAC:MF1012, CAC:MF1013, CAC:MF1014 |
| | | stage = RAI |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:OFFICJAL USE ONLY SECURITY RELATED INFORMATION Mr. Scott Batson UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 14, 2016 Site Vice President, Ocon e Nuclear Station Duke Energy Carolinas, L C 7800 Rochester Highway Seneca, SC 29672-0752 1 SUBJECT: OCONEE STATION, UNITS 1, 2, AND 3-STAFF ASSESSMENT OF RESPONSq TO REQUEST FOR INFORMATION PURSUANT TO 10 CFR 50.54(f) FLcpOD-CAUSING MECHANISMS REEVALUATION (CAC NOS. MF1012, Mf1013, AND MF1014) AND PATH FORWARD ON CONFIRMATORY ACTION LE TER Dear Mr. Batson: The purpose of this letter to provide the results of the staff's review of the Flood Hazard Reevaluation Report and t<D communicate the NRC's approach to address the regulatory matters associated with thJ Confirmatory Action Letter related to flooding at Oconee Nuclear Station. J By letter dated March 12, 012, the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pur. uant to Title 10 of the Code of Federal Regulations, Section 50.54(f) (hereafter referred to as 50.54(f) letter). The request was issued as part of implementing lessons-learned from the abcident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter licensees to reevaluate flood-causing mechanisms using present-day methodologieiand guidance. By letter dated March 12, 2013 (Agencywide Documents Access and M nagement System (ADAMS) Accession No. ML 13079A227), Duke Carolinas, LLC (Duke, the icensee) submitted its flood hazard reevaluation report (FHRR) for Oconee Nuclear Station, U its 1, 2 and 3 (Oconee). Duke also provided supplemental information resulting from rEquests for additional information and audits. The supplemental information included the licr.nsee's revised FHRR for Oconee and was submitted on March 6, 2015 (ADAMS Accession 10. ML 15072A099). By letter dated September 2015 (ADAMS Accession No. ML 15239B261), the NRC staff transmitted to Duke a sumrrary of the staff's review of the licensee's reevaluated flood-causing mechanisms. The staff assessment provides the documentation supporting the NRC staff's conclusions sumhia ized in that letter1. As stated in that letter, the 2015 reevaluated flood hazard results for lloc!I intense precipitation; rivers and streams; and dam failure, were not bounded by the current pla t design-basis analyses. In order to complete its response to Enclosure 2 to the (f) letter, the licensee is expected to submit an integrated assessment or a focused evaluation as appropriate, to address these reevaluated flood hazards, as described in the NRC's Se tember 1, 2015, letter (ADAMS Accession No. ML 15174A257). The I The Enclosures trans nitted herewith contain Security-Related Information. When from the Enclosures, this document is decontrolled. OFFICIAL USE ONLY SECURITY RELATED INFORMATION OFFICIAL ONLY SECURITY RELATED INFORMATION -2-NRC staff has determined 1hat Duke has appropriately completed steps 1 through 6 of the 10-step process described in nclosure 2 of the 50.54(f) letter. This closes out the NRC's efforts associated with CAC F1012, MF1013, and MF1014. New CAC numbers will be assigned for future NRC re iew of the new information submitted to address the revised flood hazards. Flooding hazards at the 0 site have been the subject of significant interactions between the NRC and Duke prior to he 10 CFR 50.54(f) letter issued in response to the Fukushima ichi accident. Enclosure 2 f this letter provides a summary comparison of Duke's 2015 flood hazards evaluation and Du e's prior flood hazards evaluation docketed in 2010, relative to a postulated Jocassee dam f ilure. The NRC staff has determined that the 2010 licensee evaluation reflects a boLnd;ng flood hazard analysis for Oconee based on conservative assumptions. The 20151 ev | | {{#Wiki_filter:OFFIC JAL USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 14, 2016 Mr. Scott Batson Site Vice President, Ocon e Nuclear Station Duke Energy Carolinas, L C 7800 Rochester Highway Seneca, SC 29672-0752 1 |
| * luation reflects a reasonable analysis that removes some conservatism from the 201 analysis, and is consistent with recent Commission direction regarding licensees' flobd reevaluation in response to the 50.54(f) letter. Therefore, the NRC staff concluded thrt licensee's estimated flood levels at the ONS are considered reasonable and satisfy the nformation requests for each letter. Further, the staff concludes that the revised 2015 FHRR pr vides an acceptable alternative flood hazard analysis for ONS for the purpose of meeting the terms of the June 22, 2010, NRC Confirmatory Action Letter (CAL). Following the completion of the associated flooding modifications by June 2016, the NRC will evaluate whether the term of the CAL have been satisfied. By letter dated January 8, 4016, Duke submitted supplemental information regarding the external flooding hazards fd>r Oconee. In that letter, Duke indicated its intent to maintain in effect certain actions implemented in response to the CAL. The NRC views these actions as an import nt element in Duke's overall strategy to mitigate the risks associated with a potential failure of th Jocassee Dam. Also in that letter, you stated your intent to revise the Oconee Updated Final afety Analysis Report to reflect the results of the revised FHRR and the related actions taken b Duke to resolve external flooding issues, in accordance with forthcoming NRC guidance. Going forward, the NRC staff will address ongoing external flooding issues for Oconee rithin the framework of the Fukushima Near-Term Task Force Recommendation 2.1 proc,ss, to ensure consistency in the staff's approach to addressing these issues for all plants. OFFICIALJUSE ONLY SECURITY RELATED INFORMATION OFFICIAJ USE ONLY SECURtTY RELATED INFORMATION S.Batson -3 -If you have any questions, please contact Juan Uribe or Randy Hall at (301) 415-3809 and (301) 415-4032 respeqtive y, or via e-mail at Juan.Uribe@nrc.gov and Randy.Hall@nrc.gov, respectively. Docket Nos. 50-269, 50-2 O and 50-287 Enclosures: 1 . Staff Assessment of Flo d Hazard Reevaluation Report 2. Comparison of 2010 and 2015 Jocassee Dam Failure Evaluations cc w/o encl: Distribution vi Listserv Sincerely, :/?}/ Jack R. Davis, Director Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Ol'l'IClil.L ISE ONLY S&CURITV RELATED INFORMATION S.Batson -3 -If you have any questions, please contact Juan Uribe or Randy Hall at (301) 415-3809 and (301) 415-4032 respective y, or via e-mail at Juan.Uribe@nrc.gov and Randy.Hall@nrc.gov, respectively. Docket Nos. 50-269, 50-2 0 and 50-287 Enclosures: 1. Staff Assessment of Flood Hazard Reevaluation Report 2. Comparison of 2010 and 2015 Jocassee Da[ Failure Evaluations cc w/o encl* Distribution v a Listserv DISTRIBUTION: NON-PUBLIC JLD R/F Sincerely, IRA Gregory Bowman for/ Jack R. Davis, Director Japan Lessons-Learned Division Office of Nuclear Reactor Regulation IRA/ Anne Boland, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNRRJLD Resource JUribe, NRR LQuinn-Willingham, NRO RidsNroDsea Resource RidsNrrDorllpl2-1 Resource RidsNrrDorl Resource RidsNrrPMOconee Resource RidsRgn2MailCenter Resource RidsNrrLASLent RidsOgcMailCenter Resource RidsOpaMail Resource RidsAcrsAcnw_MailCtr Resource CCook, NRO ARivera-Varona, NRO KErwin, NRO ACampbell, NRO MWillingham, NRO RRivera-Lugo, NRO BHarvey, NRO MShams, NRR RHall, NRR RidsNRRDra Resource ADAMS Accession Nos.: Pkg. ML15356A161; Letter ML15352A207 (PUBLIC); Enclosures 1&2 ML15356A158 (NON-PUBLIC) *via email OFFICE NRR/JLD/JHMB/PM* NIRR/JLD/LA NRO/DSENRHM1/BC* NRR/JLD/JHMB/BC NRR/DRND NAME JUribe Silent I CCook MS hams JGiitter DATE 03/24/2016 0 /07/2016 03/30/2016 03/24/2016 04/03/2016 OFFICE NRR/DE/D (A) I OGC (NLO) NRR/DORUD NRR/JLD/D NAME MBailey (MJRoss-Lee for) B. Harris ABoland (E. Benner for) JDavis (G.Bowman for) DATE 04/05/2016 0-' /04/2016 04/11/2016 04/14/2016 OFFICIAL RECORD COPY A I ii '"'C n*ol V C'Cl"l IDITV '"'0-:1 ATCn 1111.ICr'\DllllATlr\lll.I --** *-----**-------... *--.. --*--. *- | | |
| }} | | ==SUBJECT:== |
| | OCONEE ~UCLEAR STATION , UNITS 1, 2, AND 3-STAFF ASSESSMENT OF RESPONS q TO REQUEST FOR INFORMATION PURSUANT TO 10 CFR 50.54(f) FLcpOD-CAUSING MECHANISMS REEVALUATION (CAC NOS . |
| | MF1012, Mf 1013, AND MF1014) AND PATH FORWARD ON CONFIRMATORY ACTION LE TER |
| | |
| | ==Dear Mr. Batson:== |
| | |
| | The purpose of this letter i~ to provide the results of the staff's review of the Flood Hazard Reevaluation Report and t<D communicate the NRC's approach to address the regulatory J |
| | matters associated with thJ Confirmatory Action Letter related to flooding at Oconee Nuclear Station. |
| | By letter dated March 12, 012, the U.S . Nuclear Regulatory Commission (NRC) issued a request for information pur . uant to Title 10 of the Code of Federal Regulations, Section 50.54(f) |
| | (hereafter referred to as th~ 50.54(f) letter). The request was issued as part of implementing lessons-learned from the abcident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter reque~ted licensees to reevaluate flood-causing mechanisms using present-day methodologieiand guidance. By letter dated March 12, 2013 (Agencywide Documents Access and M nagement System (ADAMS) Accession No. ML13079A227), Duke Carolinas, LLC (Duke, the icensee) submitted its flood hazard reevaluation report (FHRR) for Oconee Nuclear Station , U its 1, 2 and 3 (Oconee) . Duke also provided supplemental information resulting from rEquests for additional information and audits. The supplemental information included the licr.nsee's revised FHRR for Oconee and was submitted on March 6, 2015 (ADAMS Accession 10. ML15072A099). |
| | By letter dated September ~4 , 2015 (ADAMS Accession No. ML15239B261), the NRC staff transmitted to Duke a sum rr ary of the staff's review of the licensee's reevaluated flood-causing mechanisms. The enclbse~ staff assessment provides the documentation supporting the NRC staff's conclusions sumhia ized in that letter1 . As stated in that letter, the 2015 reevaluated flood hazard results for lloc! I intense precipitation; rivers and streams; and dam failure, were not bounded by the current pla t design-basis analyses. In order to complete its response to to the 50.5~! (f) letter, the licensee is expected to submit an integrated assessment or a focused evaluation as appropriate, to address these reevaluated flood hazards, as described in the NRC's Se tember 1, 2015, letter (ADAMS Accession No. ML15174A257). The I |
| | The Enclosures trans nitted herewith contain Security-Related Information. When separate~ from the Enclosures, this document is decontrolled. |
| | OFFICIAL USE ONLY SECURITY RELATED INFORMATION |
| | |
| | OFFICIAL ~SE ONLY SECURITY RELATED INFORMATION NRC staff has determined hat Duke has appropriately completed steps 1 through 6 of the 10-1 step process described in nclosure 2 of the 50.54(f) letter. This closes out the NRC's efforts associated with CAC N~s. F1012, MF1013, and MF1014. New CAC numbers will be assigned for future NRC re iew of the new information submitted to address the revised flood hazards. |
| | Flooding hazards at the 0 ~onee site have been the subject of significant interactions between the NRC and Duke prior to he 10 CFR 50.54(f) letter issued in response to the Fukushima Dai-ichi accident. Enclosure 2 f this letter provides a summary comparison of Duke's 2015 flood hazards evaluation and Du e's prior flood hazards evaluation docketed in 2010, relative to a postulated Jocassee dam f ilure. The NRC staff has determined that the 2010 licensee evaluation reflects a boLnd; ng flood hazard analysis for Oconee based on conservative assumptions. The 20151ev |
| | * luation reflects a reasonable analysis that removes some conservatism from the 201 analysis, and is consistent with recent Commission direction regarding licensees' flobd ~azard reevaluation in response to the 50.54(f) letter. Therefore, the NRC staff concluded thrt t ~ e licensee's estimated flood levels at the ONS are considered reasonable and satisfy the nformation requests for each letter. Further, the staff concludes that the revised 2015 FHRR pr vides an acceptable alternative flood hazard analysis for ONS for the purpose of meeting the terms of the June 22, 2010, NRC Confirmatory Action Letter (CAL). |
| | Following the completion of the associated flooding modifications by June 2016, the NRC will evaluate whether the term of the CAL have been satisfied. |
| | By letter dated January 8, 4016, Duke submitted supplemental information regarding the external flooding hazards fd>r Oconee. In that letter, Duke indicated its intent to maintain in effect certain compensato~ I actions implemented in response to the CAL. The NRC views these actions as an import nt element in Duke's overall strategy to mitigate the risks associated with a potential failure of th Jocassee Dam . Also in that letter, you stated your intent to revise the Oconee Updated Final afety Analysis Report to reflect the results of the revised FHRR and the related actions taken b Duke to resolve external flooding issues, in accordance with forthcoming NRC guidance. Going forward , the NRC staff will address ongoing external flooding issues for Oconee r ithin the framework of the Fukushima Near-Term Task Force Recommendation 2.1 proc, ss, to ensure consistency in the staff's approach to addressing these issues for all plants. |
| | OFFICIAL JUSE ONLY SECURITY RELATED INFORMATION |
| | |
| | OFFICIAJ USE ON LY SECURtTY RELATED INFORMATION S.Batson If you have any questions, please contact Juan Uribe or Randy Hall at (301) 415-3809 and (301 ) 415-4032 respeqtive y, or via e-mail at Juan.Uribe@nrc.gov and Randy.Hall@nrc.gov, respectively. |
| | Sincerely, |
| | ~4,J/'-MJ :/?}/ |
| | Jack R. Davis, Director Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-269 , 50-2 O and 50-287 |
| | |
| | ==Enclosures:== |
| | |
| | 1 . Staff Assessment of Flo d Hazard Reevaluation Report |
| | : 2. Comparison of 2010 and 2015 Jocassee Dam Failure Evaluations cc w/o encl : Distribution vi Listserv Ol'l'IClil.L I SE ONLY S&CURITV RELATED INFORMATION |
| | |
| | Pkg. ML15356A161; Letter ML15352A207 (PUBLIC); Enclosures 1&2 ML15356A158 (NON-PUBLIC) *via email OFFICE NRR/JLD/JHMB/PM* NIRR/JLD/LA NRO/DSENRHM1/BC* NRR/JLD/JHMB/BC NRR/DRND NAME JUribe Silent I |
| | CCook MS hams JGiitter DATE 03/24/2016 0 /07/2016 03/30/2016 03/24/2016 04/03/2016 I |
| | OFFICE NRR/DE/D (A) OGC (NLO) NRR/DORUD NRR/JLD/D NAME MBailey (MJRoss-Lee for) B. Harris ABoland (E. Benner for) JDavis (G.Bowman for) |
| | DATE 04/05/2016 0-' /04/2016 04/11/2016 04/14/2016}} |
Letter Sequence RAI |
---|
|
|
MONTHYEARML15174A2572015-09-0101 September 2015 Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events Project stage: Request ML15352A2072016-04-14014 April 2016 (PUBLIC)- Staff Assessment of Response to Request for Information Pursuant to 10 CFR 50.54(f) Flood-Causing Mechanisms Reevaluation (CAC Nos. MF1012, 1013 and 1014) Project stage: RAI 2015-09-01
[Table View] |
|
---|
Category:Letter
MONTHYEARML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency IR 05000269/20240052024-08-26026 August 2024 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 (Report 05000269/2024005, 05000270/2024005, and 05000287-2024005) IR 05000269/20243012024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 IR 05000269/20240102024-08-0101 August 2024 Focused Engineering Inspection - Age-Related Degradation Report 05000269/2024010 and 05000270/2024010 and 05000287/2024010 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24179A1102024-06-27027 June 2024 Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 ML24088A3052024-03-25025 March 2024 Fws to NRC, Agreement with Nlaa Determination for Tricolored Bat for Oconee Lr IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) ML24045A3072024-02-16016 February 2024 Ltr. to Pete Parr Chief Pee Dee Indian Tribe Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3082024-02-16016 February 2024 Ltr. to Ralph Oxendine Chief Sumter Tribe of Cheraw Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2952024-02-16016 February 2024 Ltr. to Chuck Hoskin, Jr, Principal Chief Cherokee Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2962024-02-16016 February 2024 Ltr. to David Hill Principal Chief Muscogee Creek Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2992024-02-16016 February 2024 Ltr. to Eric Pratt Chief the Santee Indian Organization Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3042024-02-16016 February 2024 Ltr. to Lisa M. Collins Chief the Wassamasaw Tribe of Varnertown Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3032024-02-16016 February 2024 Ltr. to John Creel Chief Edisto Natchez-Kusso Tribe of Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3012024-02-16016 February 2024 Ltr. to Harold Hatcher Chief the Waccamaw Indian People Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3022024-02-16016 February 2024 Ltr. to Joe Bunch United Keetoowah Band of Cherokee Indians in Ok Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3052024-02-16016 February 2024 Ltr. to Louis Chavis Chief Beaver Creek Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2942024-02-16016 February 2024 Ltr. to Carolyn Chavis Bolton Chief Pee Dee Indian Nation of Upper Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3062024-02-16016 February 2024 Ltr. to Michell Hicks, Principal Chief Eastern Band of Cherokee Re Oconee Nuclear Station Units 1,2, and 3 Section 106 ML24030A0052024-02-16016 February 2024 Ltr. to Brian Harris, Chief, Catawba Indian Nation; Re., Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2972024-02-16016 February 2024 Ltr. to Dexter Sharp Chief Piedmont American Indian Assoc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML24030A5212024-02-13013 February 2024 Letter to Elizabeth Johnson, Director, Shpo; Re Oconee Nuclear Stations Units 1, 2, and 3 Section 106 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) 2024-08-08
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-24-0197, Subsequent License Renewal Application Response to Request for Additional Information 2024 Annual Update and Subsequent License Renewal Application Supplement 5 Addition2024-07-31031 July 2024 Subsequent License Renewal Application Response to Request for Additional Information 2024 Annual Update and Subsequent License Renewal Application Supplement 5 Addition RA-24-0103, Response to Request for Additional Information (RAI) Regarding License Amendment Request for a One-Time Extension to the Integrated Leak Rate Test Interval2024-04-19019 April 2024 Response to Request for Additional Information (RAI) Regarding License Amendment Request for a One-Time Extension to the Integrated Leak Rate Test Interval RA-23-0275, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-10-12012 October 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-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-23-0146, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-06-20020 June 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-23-0104, Response to Request for Additional Information (RAI) Regarding Oconee Unit 3, Refuel 31 (O3R31) Steam Generator Tube Inspection Report2023-04-26026 April 2023 Response to Request for Additional Information (RAI) Regarding Oconee Unit 3, Refuel 31 (O3R31) Steam Generator Tube Inspection Report RA-23-0051, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities2023-03-0909 March 2023 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities RA-22-0270, Response to Request for Additional Information Regarding License Amendment Request to Address Technical Specifications Mode Change Limitations2022-10-0707 October 2022 Response to Request for Additional Information Regarding License Amendment Request to Address Technical Specifications Mode Change Limitations RA-22-0192, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a2022-09-0202 September 2022 Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a RA-22-0160, Subsequent License Renewal Application: Responses to ONS SLRA - Second Round RAIs - Trp 76 (Irradiation Structural) - FE 3.5.2.2.2.62022-07-25025 July 2022 Subsequent License Renewal Application: Responses to ONS SLRA - Second Round RAIs - Trp 76 (Irradiation Structural) - FE 3.5.2.2.2.6 RA-22-0193, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4b2022-07-0808 July 2022 Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4b RA-22-0158, Subsequent License Renewal Application - Response to ONS SLRA Second Round RAI B2.1.9-2a2022-06-0808 June 2022 Subsequent License Renewal Application - Response to ONS SLRA Second Round RAI B2.1.9-2a RA-22-0159, Subsequent License Renewal Application Response to ONS SLRA Request for Additional Information (RAI) 3.1.2-12022-05-27027 May 2022 Subsequent License Renewal Application Response to ONS SLRA Request for Additional Information (RAI) 3.1.2-1 RA-22-0137, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI 4.6.1-1a2022-05-20020 May 2022 Subsequent License Renewal Application Response to ONS SLRA Second Round RAI 4.6.1-1a 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-22-0145, Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information - RAI 3.5.2.2.2.6-L2022-05-11011 May 2022 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information - RAI 3.5.2.2.2.6-L RA-22-0124, Subsequent License Renewal Application Responses to NRC Request for Additional Information Set 42022-04-22022 April 2022 Subsequent License Renewal Application Responses to NRC Request for Additional Information Set 4 RA-22-0129, Subsequent License Renewal Application, Response to ONS SLRA 2nd Round RAI B4.1-32022-04-20020 April 2022 Subsequent License Renewal Application, Response to ONS SLRA 2nd Round RAI B4.1-3 RA-22-0089, Response to Request for Additional Information Regarding Application to Revise Technical Specification 3.7.7, Low Pressure Service Water System, to Extend the Completion Time for One Required Inoperable LPSW2022-04-14014 April 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specification 3.7.7, Low Pressure Service Water System, to Extend the Completion Time for One Required Inoperable LPSW RA-22-0111, Subsequent License Renewal Application, Follow-up Request for Additional Information Set 2 and 3 Updates2022-03-31031 March 2022 Subsequent License Renewal Application, Follow-up Request for Additional Information Set 2 and 3 Updates RA-22-0105, Subsequent License Renewal Application - Responses to NRC Requests for Confirmation of Information - Set 42022-03-22022 March 2022 Subsequent License Renewal Application - Responses to NRC Requests for Confirmation of Information - Set 4 ML22075A2032022-03-11011 March 2022 Email from Duke to NRC - Follow-Up Items from March 7, 2022 Public Meeting ML22074A0022022-03-11011 March 2022 Email from Duke to NRC - Follow-up Item from March 7, 2022 Public Meeting - SSW Tendon AMP RA-22-0040, Subsequent License Renewal Application: Responses to NRC Request for Additional Information Set 32022-02-21021 February 2022 Subsequent License Renewal Application: Responses to NRC Request for Additional Information Set 3 RA-22-0023, Subsequent License Renewal Application - Response to NRC Requests for Confirmation of Information - Set 32022-01-21021 January 2022 Subsequent License Renewal Application - Response to NRC Requests for Confirmation of Information - Set 3 RA-22-0025, Supplemental Information for Relief Request to Utilize an Alternative Acceptance Criteria for Code Case, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material2022-01-20020 January 2022 Supplemental Information for Relief Request to Utilize an Alternative Acceptance Criteria for Code Case, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material RA-21-0332, Subsequent License Renewal Application Responses to NRC Request for Additional Information Set 1 and Second Round Request for Additional Information B2.1.27-1a2022-01-0707 January 2022 Subsequent License Renewal Application Responses to NRC Request for Additional Information Set 1 and Second Round Request for Additional Information B2.1.27-1a ML22019A1182022-01-0707 January 2022 Enclosures 1,2 & 3: Oconee Nuclear Station, Units 1, 2 & 3, Subsequent License Renewal Application, Appendix E, Environmental Report - Index of Duke Energy'S Responses, Responses to NRC Requests for Confirmation of Information and NRC Reque ML22019A1232022-01-0707 January 2022 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information and Request for Confirmation of Information ML22019A1202022-01-0707 January 2022 Appendix K ML22019A1242022-01-0707 January 2022 Attachment 1: Oconee Nuclear Station, Units 1, 2 & 3, Subsequent License Renewal Application, Appendix E - HDR, Inc., 2020 Clean Water Act Documents ML22019A1192022-01-0707 January 2022 Appendix 1-A - Oconee Nuclear Station 122.21(r)(2)-(13) Submittal Requirement Checklist ML22019A1212022-01-0707 January 2022 Appendix 13-B Peer Reviewer Communication Log ML22019A1222022-01-0707 January 2022 Calculation of Permeability by the Falling Head Method RA-22-0002, Appendix 10-B - Pump and Pipe Selection Calculations for a Hypothetical Cooling Tower Retrofit at Oconee Nuclear Station2022-01-0707 January 2022 Appendix 10-B - Pump and Pipe Selection Calculations for a Hypothetical Cooling Tower Retrofit at Oconee Nuclear Station ML22007A0152022-01-0707 January 2022 Subsequent License Renewal Application, Appendix E Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information RA-21-0325, Response to NRC Requests for Confirmation of Information - Set 22021-12-17017 December 2021 Response to NRC Requests for Confirmation of Information - Set 2 RA-21-0307, Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information - Set 12021-12-0202 December 2021 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information - Set 1 RA-21-0269, Response to Request for Additional Information Regarding Alternative Request to Utilize American Society of Mechanical Engineers (ASME) Code Case OMN-282021-11-0909 November 2021 Response to Request for Additional Information Regarding Alternative Request to Utilize American Society of Mechanical Engineers (ASME) Code Case OMN-28 RA-21-0270, Response to Second Request for Additional Information (RAI) Regarding Relief Request to Utilize an Alternative Acceptance Criteria for Code Case N-8532021-10-28028 October 2021 Response to Second Request for Additional Information (RAI) Regarding Relief Request to Utilize an Alternative Acceptance Criteria for Code Case N-853 RA-21-0242, Response to Request for Additional Information, Regarding Relief Request to Utilize an Alternative Acceptance Criteria for Code Case N-853, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection2021-08-31031 August 2021 Response to Request for Additional Information, Regarding Relief Request to Utilize an Alternative Acceptance Criteria for Code Case N-853, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection RA-21-0219, Response to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Intervals2021-08-0505 August 2021 Response to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Intervals 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-20-0267, Proposed License Amendment Request to Revise Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of Containment Building - Responses to Request for Additional Information2020-09-17017 September 2020 Proposed License Amendment Request to Revise Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of Containment Building - Responses to Request for Additional Information RA-19-0281, Response to NRC Request for Additional Information for the Fall 2018 Oconee Unit 1 Steam Generator Tube Rupture Inspection Report (RA-19-0093)2019-07-31031 July 2019 Response to NRC Request for Additional Information for the Fall 2018 Oconee Unit 1 Steam Generator Tube Rupture Inspection Report (RA-19-0093) RA-19-0301, Proposed Amendment to Renewed Facility Operating Licenses Regarding Revisions to Final Safety Analysis Report Sections Associated with Oconee Tornado Licensing Basis -Responses to Request for Additional Information2019-07-31031 July 2019 Proposed Amendment to Renewed Facility Operating Licenses Regarding Revisions to Final Safety Analysis Report Sections Associated with Oconee Tornado Licensing Basis -Responses to Request for Additional Information RA-19-0134, Duke Energy Response to NRC Request for Additional Information (RAI) Related to Oconee License Amendment Request 2018-052019-03-0707 March 2019 Duke Energy Response to NRC Request for Additional Information (RAI) Related to Oconee License Amendment Request 2018-05 2024-07-31
[Table view] |
Text
OFFIC JAL USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 14, 2016 Mr. Scott Batson Site Vice President, Ocon e Nuclear Station Duke Energy Carolinas, L C 7800 Rochester Highway Seneca, SC 29672-0752 1
SUBJECT:
OCONEE ~UCLEAR STATION , UNITS 1, 2, AND 3-STAFF ASSESSMENT OF RESPONS q TO REQUEST FOR INFORMATION PURSUANT TO 10 CFR 50.54(f) FLcpOD-CAUSING MECHANISMS REEVALUATION (CAC NOS .
MF1012, Mf 1013, AND MF1014) AND PATH FORWARD ON CONFIRMATORY ACTION LE TER
Dear Mr. Batson:
The purpose of this letter i~ to provide the results of the staff's review of the Flood Hazard Reevaluation Report and t<D communicate the NRC's approach to address the regulatory J
matters associated with thJ Confirmatory Action Letter related to flooding at Oconee Nuclear Station.
By letter dated March 12, 012, the U.S . Nuclear Regulatory Commission (NRC) issued a request for information pur . uant to Title 10 of the Code of Federal Regulations, Section 50.54(f)
(hereafter referred to as th~ 50.54(f) letter). The request was issued as part of implementing lessons-learned from the abcident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter reque~ted licensees to reevaluate flood-causing mechanisms using present-day methodologieiand guidance. By letter dated March 12, 2013 (Agencywide Documents Access and M nagement System (ADAMS) Accession No. ML13079A227), Duke Carolinas, LLC (Duke, the icensee) submitted its flood hazard reevaluation report (FHRR) for Oconee Nuclear Station , U its 1, 2 and 3 (Oconee) . Duke also provided supplemental information resulting from rEquests for additional information and audits. The supplemental information included the licr.nsee's revised FHRR for Oconee and was submitted on March 6, 2015 (ADAMS Accession 10. ML15072A099).
By letter dated September ~4 , 2015 (ADAMS Accession No. ML15239B261), the NRC staff transmitted to Duke a sum rr ary of the staff's review of the licensee's reevaluated flood-causing mechanisms. The enclbse~ staff assessment provides the documentation supporting the NRC staff's conclusions sumhia ized in that letter1 . As stated in that letter, the 2015 reevaluated flood hazard results for lloc! I intense precipitation; rivers and streams; and dam failure, were not bounded by the current pla t design-basis analyses. In order to complete its response to to the 50.5~! (f) letter, the licensee is expected to submit an integrated assessment or a focused evaluation as appropriate, to address these reevaluated flood hazards, as described in the NRC's Se tember 1, 2015, letter (ADAMS Accession No. ML15174A257). The I
The Enclosures trans nitted herewith contain Security-Related Information. When separate~ from the Enclosures, this document is decontrolled.
OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAL ~SE ONLY SECURITY RELATED INFORMATION NRC staff has determined hat Duke has appropriately completed steps 1 through 6 of the 10-1 step process described in nclosure 2 of the 50.54(f) letter. This closes out the NRC's efforts associated with CAC N~s. F1012, MF1013, and MF1014. New CAC numbers will be assigned for future NRC re iew of the new information submitted to address the revised flood hazards.
Flooding hazards at the 0 ~onee site have been the subject of significant interactions between the NRC and Duke prior to he 10 CFR 50.54(f) letter issued in response to the Fukushima Dai-ichi accident. Enclosure 2 f this letter provides a summary comparison of Duke's 2015 flood hazards evaluation and Du e's prior flood hazards evaluation docketed in 2010, relative to a postulated Jocassee dam f ilure. The NRC staff has determined that the 2010 licensee evaluation reflects a boLnd; ng flood hazard analysis for Oconee based on conservative assumptions. The 20151ev
- luation reflects a reasonable analysis that removes some conservatism from the 201 analysis, and is consistent with recent Commission direction regarding licensees' flobd ~azard reevaluation in response to the 50.54(f) letter. Therefore, the NRC staff concluded thrt t ~ e licensee's estimated flood levels at the ONS are considered reasonable and satisfy the nformation requests for each letter. Further, the staff concludes that the revised 2015 FHRR pr vides an acceptable alternative flood hazard analysis for ONS for the purpose of meeting the terms of the June 22, 2010, NRC Confirmatory Action Letter (CAL).
Following the completion of the associated flooding modifications by June 2016, the NRC will evaluate whether the term of the CAL have been satisfied.
By letter dated January 8, 4016, Duke submitted supplemental information regarding the external flooding hazards fd>r Oconee. In that letter, Duke indicated its intent to maintain in effect certain compensato~ I actions implemented in response to the CAL. The NRC views these actions as an import nt element in Duke's overall strategy to mitigate the risks associated with a potential failure of th Jocassee Dam . Also in that letter, you stated your intent to revise the Oconee Updated Final afety Analysis Report to reflect the results of the revised FHRR and the related actions taken b Duke to resolve external flooding issues, in accordance with forthcoming NRC guidance. Going forward , the NRC staff will address ongoing external flooding issues for Oconee r ithin the framework of the Fukushima Near-Term Task Force Recommendation 2.1 proc, ss, to ensure consistency in the staff's approach to addressing these issues for all plants.
OFFICIAL JUSE ONLY SECURITY RELATED INFORMATION
OFFICIAJ USE ON LY SECURtTY RELATED INFORMATION S.Batson If you have any questions, please contact Juan Uribe or Randy Hall at (301) 415-3809 and (301 ) 415-4032 respeqtive y, or via e-mail at Juan.Uribe@nrc.gov and Randy.Hall@nrc.gov, respectively.
Sincerely,
~4,J/'-MJ :/?}/
Jack R. Davis, Director Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-269 , 50-2 O and 50-287
Enclosures:
1 . Staff Assessment of Flo d Hazard Reevaluation Report
- 2. Comparison of 2010 and 2015 Jocassee Dam Failure Evaluations cc w/o encl : Distribution vi Listserv Ol'l'IClil.L I SE ONLY S&CURITV RELATED INFORMATION
Pkg. ML15356A161; Letter ML15352A207 (PUBLIC); Enclosures 1&2 ML15356A158 (NON-PUBLIC) *via email OFFICE NRR/JLD/JHMB/PM* NIRR/JLD/LA NRO/DSENRHM1/BC* NRR/JLD/JHMB/BC NRR/DRND NAME JUribe Silent I
CCook MS hams JGiitter DATE 03/24/2016 0 /07/2016 03/30/2016 03/24/2016 04/03/2016 I
OFFICE NRR/DE/D (A) OGC (NLO) NRR/DORUD NRR/JLD/D NAME MBailey (MJRoss-Lee for) B. Harris ABoland (E. Benner for) JDavis (G.Bowman for)
DATE 04/05/2016 0-' /04/2016 04/11/2016 04/14/2016