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| | number = ML15239B261 | | | number = ML15239B261 |
| | issue date = 09/24/2015 | | | issue date = 09/24/2015 |
| | title = Oconee Nuclear Station, Units 1, 2, and 3 - Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation | | | title = Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation |
| | author name = Uribe J F | | | author name = Uribe J |
| | author affiliation = NRC/NRR/JLD | | | author affiliation = NRC/NRR/JLD |
| | addressee name = Batson S | | | addressee name = Batson S |
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| | docket = 05000269, 05000270, 05000287 | | | docket = 05000269, 05000270, 05000287 |
| | license number = | | | license number = |
| | contact person = Uribe J F, NRR/JLD, 415-3809 | | | contact person = Uribe J, NRR/JLD, 415-3809 |
| | case reference number = TAC MF1012, TAC MF1013, TAC MF1014 | | | case reference number = TAC MF1012, TAC MF1013, TAC MF1014 |
| | package number = ML15239B243 | | | package number = ML15239B243 |
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| | page count = 7 | | | page count = 7 |
| | project = TAC:MF1012, TAC:MF1013, TAC:MF1014 | | | project = TAC:MF1012, TAC:MF1013, TAC:MF1014 |
| | stage = | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:OFFICIAb USE ONLY SECURITY RELATED INFORMATION Mr. Scott Batson UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 24, 2015 Vice President, Oconee Nuclear Station Duke Energy Corporation 7800 Rochester Highway Seneca, SC 29672-0752 SUBJECT: OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3-INTERIM STAFF RESPONSE TO REEVALUATED FLOOD HAZARDS SUBMITTED IN RESPONSE TO 10 CFR 50.54(f) INFORMATION FLOOD-CAUSING MECHANISM REEVALUATION (TAC NOS. MF1012, MF1013, AND MF1014) Dear Mr. Batson: The purpose of this letter is to provide a summary of the U.S. Nuclear Regulatory Commission (NRC) staff's assessment of the re-evaluated flood-causing mechanisms described in the March 12, 2013 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 13079A227), flood hazard reevaluation report (FHRR) submitted by Duke Energy Carolinas, LLC (Duke, the licensee) for Oconee Nuclear Station Units 1, 2 and 3 (Oconee), as well as supplemental information resulting from requests for additional information and audits. This supplemental information included the licensee's revised FHRR for Oconee, submitted on March 6, 2015 (ADAMS Accession No. ML 15072A099) By letter dated March 12, 2012, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Section 50.54(f) (hereafter referred to as the 50.54(f) letter) (ADAMS Accession No. ML 12053A340). The request was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to re-evaluate flood-causing mechanisms using present-day methodologies and guidance. Concurrently, with the reevaluation of flooding hazards, licensees were required to develop and implement mitigating strategies in accordance with NRC Order EA-12-049, "Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML 12054A735). On March 30, 2015, the Commission provided Staff Requirements Memorandum (SRM) (ADAMS Accession No. ML 15089A236) to COMSECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards," dated November 21, 2014 (ADAMS Accession No. ML 14309A256), affirming that licensees need to address the reevaluated flooding hazards within their mitigating strategies for beyond-design-basis external events. Enclosure 2 transmitted herewith contains Security-Related Information. When separated from the Enclosure, this document is decontrolled. use ONbY SECYRITY RELATED INFORMATION OFFICIAL USE..o.N.L.Y-SECURITY RELATED INFORMA.TION S. Batson -2-The NRC staff has reviewed the information submitted by the licensee and has summarized the results of the review in the tables provided as Enclosure 1 to this letter. Table 1 provides the current design-basis flood hazard mechanisms. Table 2 provides reevaluated flood hazard mechanisms; however, reevaluated hazard mechanisms bounded by the current design-:basis (Table 1) are not included. Because Table 2 includes security-related information, Enclosure 1 contains the redacted version of Table 2. Enclosure 2 is withheld from public disclosure and restores the security-related information to Table 2. The NRC staff has concluded that the licensee's reevaluated flood hazards information, as summarized in the Enclosure, is suitable for the assessment of mitigating strategies developed in response to Order EA-12-049 (i.e., defines the mitigating strategies flood hazard information described in guidance documents currently being finalized by the industry and NRC staff), for Oconee. Further, the NRC staff has concluded that the licensee's reevaluated flood hazard information is a suitable input for other assessments associated with Near-Term Task Force Recommendation 2.1 "Flooding". The NRC staff plans to issue a staff assessment documenting the basis for these conclusions in the near future. The staff also intends to address the impact of this reevaluated flood hazard review on the previous Oconee flooding analyses submitted in response to the NRC's Confirmatory Action Letter, dated June 22, 2010 (ADAMS Accession No. ML 101730329). In addition, NEI 12-06 "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide" is currently being revised. This revision will include a methodology to perform a Mitigating Strategies Assessment (MSA) with respect to the reevaluated flood hazards. Once this methodology is endorsed by the NRC, flood event duration parameters and applicable flood associated effects should be considered as part of the Oconee MSA. The NRC staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood-related associated effects developed by the licensee during the NRC staff's review of the MSA. As stated above, Table 2 of the enclosure to this letter describes the reevaluated flood hazards that exceed the current design-basis. In order to complete its response to the information requested by Enclosure 2 to the 50.54(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 letter, "Coordination of Request for Information Regarding Flooding Hazard Reevaluation and Mitigating Strategies for Beyond-Design-Basis External Events," dated September 1, 2015 (ADAMS Accession No. ML 1517 4A257). This letter describes the changes in the NRC's approach to the flood hazard reevaluations that were approved by the Commission in its SRM to COMSECY-15-0019, "Closure Plan for the Reevaluation of Flooding Hazards for Operating Nuclear Power Plants" (ADAMS Accession No. ML 15209A682). OFFICIAL IJSli ONLY SECURITY RELATED INFORMATION | | {{#Wiki_filter:OFFICIAb USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 24, 2015 Mr. Scott Batson Vice President, Oconee Nuclear Station Duke Energy Corporation 7800 Rochester Highway Seneca, SC 29672-0752 |
| *OISfii'ICll\L USE ONLY SECURITY RELATED INFORMATION S. Batson -3-If you have any questions, please contact me at (301) 415-3809 or e-mail at Juan.Uribe@nrc.gov. Docket Nos. 50-269, 50-270 and 50-287 Enclosures: 1. Summary of Results of Flooding Juan F. Uribe, Pr ject Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Hazard Re-Evaluation Report (Redacted Version) 2. Summary of Results of Flooding Hazard Re-Evaluation Report {Non-Public Version) cc w/encl: Distribution via Listserv .OFFICIAL USli ONLY SECURITY RELATED INFORMJ'.TION ENCLOSURE 1: SUMMARY TABLES OF REEVALUATED FLOOD HAZARD LEVELS (REDACTED VERSION) | | |
| Oconee, Units 1, 2, & 3 Table 1. Current Design Basis Flood Hazards for Use in the MSA --------*---** --_" ____ .. -------------*-"----------------------------------Mechanism Stillwater Waves/ Design Basis Reference Elevation Run up Hazard -Elevation Local Intense Precipitation Not included Not included Not included Staff Assessment in DB in DB in DB Streams and Rivers Flooding in Reservoirs -Keowee 808.0 ft MSL Not 808.0 ft MSL Staff Assessment Reservoir {not calculated at applicable Power Block) Failure of Dams and Onsite Water Control/Storage Structures Not included Not included Not included Staff Assessment in DB in DB in DB Storm Surge Not included Not included Not included Staff Assessment in DB in DB in DB Seiche Not included Not included Not included Staff Assessment in DB in DB in DB Tsunami Not included Not included Not included Staff Assessment in DB in DB in DB Ice-Induced Flooding Not included I Not included Not included Staff Assessment in DB in DB in DB Channel Migrations/Diversions Not included Not included Not included Staff Assessment in DB in DB in DB [ ____ --*------,_____ ___ -------*----*----------Note 1: Reported values are rounded to the nearest one-tenth of a foot. | | ==SUBJECT:== |
| Oconee, Units 1, 2, & 3 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Stillwater Waves/ Reevaluated Reference Elevation Run up Hazard Elevation Local Intense Precipitation 800.4 ft MSL Minimal 800.4 ft MSL FHRR Section 3.1 Streams and Rivers Streams and Rivers (Flooding in 808.9 ft MSL 3.3 ft 812.2 ft MSL I FHRR Section 3.2 Reservoirs, Keowee) Failure of Dams and Onsite Water Control/Storage Structures [Redacted] [Redacted] [Redacted] [Redacted] [Redacted] --------------------.-Note 1: The licensee is expected to develop flood event duration parameters and applicable flood associated effects to conduct the MSA consistent with the guidance. The NRC staff has reviewed information related to flood event duration parameters (including warning time and period of inundation). Note 2: Reevaluated hazard mechanisms bounded by the current design basis (see Table 1) are not included in this table. Note 3: Reported values are rounded to the nearest one-tenth of a foot. I I OFFICIAL USE ONbY SiCURITY RebATiD INi;:'.ORMATION S. Baston -3 -If you have any questions, please contact me at (301) 415-3809 or e-mail at Juan.Uribe@nrc.gov. Sincerely, Juan F. Uribe, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287 Enclosures: 1. Summary of Results of Flooding Hazard Re-Evaluation Report (Redacted Version) 2. Summary of Results of Flooding Hazard Re-Evaluation Report (Non-Public Version) cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC JUribe, NRR RidsNrrDorllpl2-1 Resource RidsRgn2MailCenter Resource RidsOpaMail Resource ARivera-Varona, NRO MWillingham, NRO MShams, NRR JLD R/F LQuinn-Willingham, NRO RidsNrrDorl Resource RidsNrrLASLent RidsAcrsAcnw_MailCtr Resource KErwin, NRO RRivera-Lugo, NRO RHall, NRR RidsNRRJLD Resource RidsNroDsea Resource RidsNrrPMOconee Resource RidsOgcMailCenter Resource CCook, NRO ACampbell, NRO BHarvey, NRO ADAMS Accession Nos.: PKG ML 152398243 LTR: ML152398261; ENCL 1: ML 152388723 (PUBLIC) ENCL 2* ML 152228209 (NON-PUBLIC) *via email OFFICE NRR/JLD/JHMB/PM* NRR/JLD/LA NRO/DSEA/RHM2/TR* NAME JUribe SLent NTiruneh DATE 8/28/2015 8/28/2015 8/17/2015 OFFICE NRO/DSEA/RHM2/BC* NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME ARivera-Varona MShams JUribe DATE 8/17/2015 8/28/2015 9/24/2015 OFFICIAL RECORD COPY
| | OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3- INTERIM STAFF RESPONSE TO REEVALUATED FLOOD HAZARDS SUBMITTED IN RESPONSE TO 10 CFR 50.54(f) INFORMATION REQUEST-FLOOD-CAUSING MECHANISM REEVALUATION (TAC NOS. MF1012, MF1013, AND MF1014) |
| }} | | |
| | ==Dear Mr. Batson:== |
| | |
| | The purpose of this letter is to provide a summary of the U.S. Nuclear Regulatory Commission (NRC) staff's assessment of the re-evaluated flood-causing mechanisms described in the March 12, 2013 (Agencywide Document Access and Management System (ADAMS) Accession No. ML13079A227), flood hazard reevaluation report (FHRR) submitted by Duke Energy Carolinas, LLC (Duke, the licensee) for Oconee Nuclear Station Units 1, 2 and 3 (Oconee), as well as supplemental information resulting from requests for additional information and audits. This supplemental information included the licensee's revised FHRR for Oconee, submitted on March 6, 2015 (ADAMS Accession No. ML15072A099) |
| | By letter dated March 12, 2012, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Section 50.54(f) (hereafter referred to as the 50.54(f) letter) |
| | (ADAMS Accession No. ML12053A340). The request was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to re-evaluate flood-causing mechanisms using present-day methodologies and guidance. Concurrently, with the reevaluation of flooding hazards, licensees were required to develop and implement mitigating strategies in accordance with NRC Order EA-12-049, "Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML12054A735). On March 30, 2015, the Commission provided Staff Requirements Memorandum (SRM) (ADAMS Accession No. ML15089A236) to COMSECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards," dated November 21, 2014 (ADAMS Accession No. ML14309A256), affirming that licensees need to address the reevaluated flooding hazards within their mitigating strategies for beyond-design-basis external events. |
| | Enclosure 2 transmitted herewith contains Security-Related Information. When separated from the Enclosure, this document is decontrolled. |
| | OfflCl.'~.b use ONbY SECYRITY RELATED INFORMATION |
| | |
| | OFFICIAL USE..o.N.L.Y- SECURITY RELATED INFORMA.TION S. Batson The NRC staff has reviewed the information submitted by the licensee and has summarized the results of the review in the tables provided as Enclosure 1 to this letter. Table 1 provides the current design-basis flood hazard mechanisms. |
| | Table 2 provides reevaluated flood hazard mechanisms; however, reevaluated hazard mechanisms bounded by the current design-:basis (Table 1) are not included. Because Table 2 includes security-related information, Enclosure 1 contains the redacted version of Table 2. |
| | Enclosure 2 is withheld from public disclosure and restores the security-related information to Table 2. |
| | The NRC staff has concluded that the licensee's reevaluated flood hazards information, as summarized in the Enclosure, is suitable for the assessment of mitigating strategies developed in response to Order EA-12-049 (i.e., defines the mitigating strategies flood hazard information described in guidance documents currently being finalized by the industry and NRC staff), for Oconee. Further, the NRC staff has concluded that the licensee's reevaluated flood hazard information is a suitable input for other assessments associated with Near-Term Task Force Recommendation 2.1 "Flooding". The NRC staff plans to issue a staff assessment documenting the basis for these conclusions in the near future. The staff also intends to address the impact of this reevaluated flood hazard review on the previous Oconee flooding analyses submitted in response to the NRC's Confirmatory Action Letter, dated June 22, 2010 (ADAMS Accession No. ML101730329). |
| | In addition, NEI 12-06 "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide" is currently being revised. This revision will include a methodology to perform a Mitigating Strategies Assessment (MSA) with respect to the reevaluated flood hazards. Once this methodology is endorsed by the NRC, flood event duration parameters and applicable flood associated effects should be considered as part of the Oconee MSA. The NRC staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood-related associated effects developed by the licensee during the NRC staff's review of the MSA. |
| | As stated above, Table 2 of the enclosure to this letter describes the reevaluated flood hazards that exceed the current design-basis. In order to complete its response to the information requested by Enclosure 2 to the 50.54(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 letter, "Coordination of Request for Information Regarding Flooding Hazard Reevaluation and Mitigating Strategies for Beyond-Design-Basis External Events," dated September 1, 2015 (ADAMS Accession No. ML15174A257). This letter describes the changes in the NRC's approach to the flood hazard reevaluations that were approved by the Commission in its SRM to COMSECY-15-0019, "Closure Plan for the Reevaluation of Flooding Hazards for Operating Nuclear Power Plants" (ADAMS Accession No. ML15209A682). |
| | OFFICIAL IJSli ONLY SECURITY RELATED INFORMATION |
| | |
| | *OISfii'ICll\L USE ONLY SECURITY RELATED INFORMATION S. Batson If you have any questions, please contact me at (301) 415-3809 or e-mail at Juan.Uribe@nrc.gov. |
| | f~ ~~ |
| | Juan F. Uribe, Pr ject Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287 |
| | |
| | ==Enclosures:== |
| | : 1. Summary of Results of Flooding Hazard Re-Evaluation Report (Redacted Version) |
| | : 2. Summary of Results of Flooding Hazard Re-Evaluation Report {Non-Public Version) cc w/encl: Distribution via Listserv |
| | .OFFICIAL USli ONLY SECURITY RELATED INFORMJ'.TION |
| | |
| | ENCLOSURE 1: |
| | |
| | ==SUMMARY== |
| | TABLES OF REEVALUATED FLOOD HAZARD LEVELS (REDACTED VERSION) |
| | |
| | Oconee, Units 1, 2, &3 Table 1. Current Design Basis Flood Hazards for Use in the MSA |
| | --------*---** -- ----~ |
| | Mechanism Stillwater Waves/ Design Basis Reference Elevation Run up Hazard |
| | - Elevation Local Intense Precipitation Not included Not included Not included Staff Assessment in DB in DB in DB Streams and Rivers Flooding in Reservoirs - Keowee 808.0 ft MSL Not 808.0 ft MSL Staff Assessment Reservoir {not calculated at applicable Power Block) |
| | Failure of Dams and Onsite Water Control/Storage Structures Not included Not included Not included Staff Assessment in DB in DB in DB Storm Surge Not included Not included Not included Staff Assessment in DB in DB in DB Seiche Not included Not included Not included Staff Assessment in DB in DB in DB Tsunami Not included Not included Not included Staff Assessment in DB in DB in DB Ice-Induced Flooding Not included I Not included Not included Staff Assessment in DB in DB in DB Channel Migrations/Diversions Not included Not included Not included Staff Assessment in DB in DB in DB |
| | [ ____ ---------~---- - -*------ |
| | Note 1: Reported values are rounded to the nearest one-tenth of a foot. |
| | |
| | Oconee, Units 1, 2, &3 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Stillwater Waves/ Reevaluated Reference Elevation Run up Hazard Elevation Local Intense Precipitation 800.4 ft MSL Minimal 800.4 ft MSL FHRR Section 3.1 I I |
| | Streams and Rivers Streams and Rivers (Flooding in 808.9 ft MSL 3.3 ft 812.2 ft MSL I FHRR Section 3.2 Reservoirs, Keowee) |
| | Failure of Dams and Onsite Water Control/Storage Structures |
| | [Redacted] [Redacted] [Redacted] [Redacted] [Redacted] |
| | -----------~--~----- **-*-----------------~ ---- ---- -~--------- - --*----~---- ------- ----.- |
| | Note 1: The licensee is expected to develop flood event duration parameters and applicable flood associated effects to conduct the MSA consistent with the guidance. The NRC staff has reviewed information related to flood event duration parameters (including warning time and period of inundation). |
| | Note 2: Reevaluated hazard mechanisms bounded by the current design basis (see Table 1) are not included in this table. |
| | Note 3: Reported values are rounded to the nearest one-tenth of a foot. |
| | |
| | PKG ML152398243 LTR: ML152398261; ENCL 1: ML152388723 (PUBLIC) |
| | ENCL 2* ML152228209 (NON-PUBLIC) *via email OFFICE NRR/JLD/JHMB/PM* NRR/JLD/LA NRO/DSEA/RHM2/TR* |
| | NAME JUribe SLent NTiruneh DATE 8/28/2015 8/28/2015 8/17/2015 OFFICE NRO/DSEA/RHM2/BC* NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME ARivera-Varona MShams JUribe DATE 8/17/2015 8/28/2015 9/24/2015}} |
Letter Sequence Other |
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|
MONTHYEARML13079A2272013-03-12012 March 2013
Flood Hazard Reevaluation Report in Response to NRC Ltr. Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendations 2.1, 2.3, and 9.3, of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
Project stage: Request
ML13077A1782013-03-18018 March 2013
3/25/13 Forthcoming Meeting with Duke Energy Carolinas to Discuss Response to NRC Request for Information for a Flooding Hazard Reevaluation for Oconee Nuclear Station, Units 1, 2, and 3
Project stage: RAI
ML13092A3632013-04-0404 April 2013
3/25/2013 - Oconee Nuclear Station, Units 1, 2, and 3 - Summary of Meeting with Duke Energy Carolinas, LLC, to Discuss the Flood Hazard Reevaluation Report
Project stage: Meeting
ML13254A2262013-09-11011 September 2013
Meeting Notice with Duke Energy Carolinas, LLC, to Discuss the Seismic Review of the Jocassee Dam for the Oconee Nuclear Station, Units 1, 2, and 3 (Tac Nos. MF0518, MF0519, MF0520, MF1012, MF1013, and MF1014)
Project stage: Meeting
ML13275A2252013-09-24024 September 2013
9/24/13 Meeting Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Jocassee Dam Seismic Analysis
Project stage: Request
ML13281A5412013-10-21021 October 2013
9/24/2013 - Oconee Nuclear Station, Units 1, 2, and 3, Summary of Meeting with Duke Energy Carolinas, LLC, to Discuss the Jocassee Dam Seismic Analysis
Project stage: Meeting
ML14064A5912014-03-20020 March 2014
Request for Additional Information Regarding Fukushima Lessons Learned Flood Hazard Reevaluation Report (TAC Nos. MF1012, MF1013, and MF1014)
Project stage: RAI
ML14258B2222014-09-15015 September 2014
NRR E-mail Capture - Request for Additional Informaiton - Oconee Flooding Hazard Reevaluation Report (TAC Nos. MF1012, MF1013, and MF1014)
Project stage: Other
ML14356A0062014-12-0303 December 2014
Presentation at December 3, 2014, Category 1 Public Meeting with Duke Energy Carolinas, LLC to Discuss NTTF Recommendation 2.1, Flooding Response
Project stage: Request
ML14356A0052014-12-31031 December 2014
Summary of December 3, 2014, Category 1 Public Meeting with Duke Energy Carolinas, LLC to Discuss NTTF Recommendation 2.1, Flooding Response for Oconee Nuclear Station, Units 1, 2, and 3
Project stage: Meeting
ONS-2015-011, Submittal of Revised Flood Hazard Reevaluation Report Per Nrc'S Request for Additional Information2015-03-0606 March 2015
Submittal of Revised Flood Hazard Reevaluation Report Per Nrc'S Request for Additional Information
Project stage: Request
ML15118A4602015-05-0808 May 2015
Audit Plan for the Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding
Project stage: Other
ML15239B2612015-09-24024 September 2015
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation
Project stage: Other
ONS-2016-001, Transmittal of Supplemental Information Regarding NRC 2008 and 2012 Requests for Information, Pursuant to 10 Cer 50.54(f) Pertaining to External Flooding - Revision 12016-01-0808 January 2016
Transmittal of Supplemental Information Regarding NRC 2008 and 2012 Requests for Information, Pursuant to 10 Cer 50.54(f) Pertaining to External Flooding - Revision 1
Project stage: Supplement
ML15355A1642016-01-12012 January 2016
Nuclear Regulatory Commission Report for the Audit of Duke Energy Carolinas, Llc'S Flood Hazard Reevaluation Report Submittal Related to the Near-Term Task Force Recommendation 2.1-Flooding for Oconee Nuclear Station, Units 1, 2 and 3
Project stage: Other
ONS-2016-042, Notification of External Flood Modifications Completion2016-04-29029 April 2016
Notification of External Flood Modifications Completion
Project stage: Other
2014-12-31
[Table View] |
|
|---|
Category:Graphics incl Charts and Tables
MONTHYEARRA-20-0263, Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-09-16016 September 2020
Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv)
ML16056A1392016-03-11011 March 2016
Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
ML15239B2612015-09-24024 September 2015
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation
ML15238B7232015-08-26026 August 2015
Interim Letter Public Tables (Tables 1 and 2)
ONS-2014-164, Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitment 17T2014-12-19019 December 2014
Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitment 17T
ML14307B7072014-12-10010 December 2014
Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T
ML14058A0462014-02-0404 February 2014
NRC Staff Comments to Duke Energy Request for Information Response
ML11347A1932011-12-0808 December 2011
Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model
ML1102105652011-01-20020 January 2011
NFPA 805 Pilot License Amendment Request Review Schedule Update, January 2011
ML1029805882010-10-26026 October 2010
NFPA 805 Pilot License Amendment Request Review Schedule Update, October 2010
ML1020401472010-07-22022 July 2010
NFPA 805 Pilot License Amendment Request Review Schedule Update, July 2010
ML0932400582009-11-19019 November 2009
NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, November, 2009
ML0917603592009-06-25025 June 2009
NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, June 2009
ML0914201292009-05-21021 May 2009
NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, May 2009
ML0908403602009-03-25025 March 2009
NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, March, 2009, Revised
ML0834001812008-12-0404 December 2008
NFPA 805 Pilot License Amendment Request Review and Infrastructure Update
ML0821300962008-07-29029 July 2008
Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model
ML0812605492008-04-29029 April 2008
Transmittal of a Relief of Request Fourth Ten Year Inservice Inspection Interval
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
ML0713603512007-05-14014 May 2007
Revised Table from 05/14/2007 Meeting on FRP
ML0708005572007-03-13013 March 2007
Report Pursuant to 10 CFR 50.46, Changes to or Errors in ECCS Evaluation Model for January 1, 2005 - December 31, 2005
ML0609403712005-11-0101 November 2005
Conference Call Summary Regarding Fall 2005 Steam Generator Inspections at Oconee Nuclear Station, Unit 2
ML0209805952002-04-0808 April 2002
EA-02-048, Oconee Nuclear Station, Supplemental Graphs
2020-09-16
[Table view]
Category:Letter
MONTHYEARML23304A1422024-02-0101 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)
IR 05000269/20243012024-01-11011 January 2024
Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301
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
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
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
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 05000269/20230112023-08-25025 August 2023
Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011
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 05000269/20230022023-07-28028 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)
IR 05000269/20230012023-05-12012 May 2023
Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001
ML23121A0552023-05-0303 May 2023
Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program
ML23118A0762023-05-0101 May 2023
Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML23117A0432023-04-20020 April 2023
Framatome, Inc., Part 21 Notification of Existence of a Defect
ML23075A0732023-04-0505 April 2023
License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002)
ML23045A1332023-03-15015 March 2023
Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter
ML23045A1402023-03-15015 March 2023
Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter
ML23045A1432023-03-15015 March 2023
Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter
ML22332A4932023-03-10010 March 2023
William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility
ML23069A1102023-03-10010 March 2023
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
ML23061A1772023-03-0303 March 2023
Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011
IR 05000269/20220062023-03-0101 March 2023
Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006)
ML23039A1632023-02-0808 February 2023
Requalification Program Inspection
ML23037A0772023-02-0606 February 2023
402 Cyber Notification and RFI Letter Final
IR 05000269/20220042023-02-0202 February 2023
Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004
ML22363A3942023-01-12012 January 2023
Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule
ML22356A0512022-12-14014 December 2022
Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl
ML22321A0492022-12-0808 December 2022
Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints
ML22329A1042022-11-29029 November 2022
Review of the Fall 2021 Steam Generator Tube Inspection Report
ML22321A1582022-11-22022 November 2022
Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections
ML22096A0032022-11-18018 November 2022
McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations
ML22256A2532022-11-14014 November 2022
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2
IR 05000269/20220032022-11-0707 November 2022
Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003
ML22301A0112022-11-0303 November 2022
Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022
ML22298A0752022-10-27027 October 2022
Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022
ML22264A0322022-10-20020 October 2022
_Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022
IR 05000269/20220112022-09-26026 September 2022
NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011
ML22258A0302022-09-15015 September 2022
Evacuation Time Estimate Reports
ML22222A0072022-09-14014 September 2022
Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application
ML22231B1362022-09-0101 September 2022
Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi
ML22234A0062022-08-30030 August 2022
SLRA - Closed Public Meeting Summary - August 18, 2022
2024-02-01
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Text
OFFICIAb USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 24, 2015 Mr. Scott Batson Vice President, Oconee Nuclear Station Duke Energy Corporation 7800 Rochester Highway Seneca, SC 29672-0752
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3- INTERIM STAFF RESPONSE TO REEVALUATED FLOOD HAZARDS SUBMITTED IN RESPONSE TO 10 CFR 50.54(f) INFORMATION REQUEST-FLOOD-CAUSING MECHANISM REEVALUATION (TAC NOS. MF1012, MF1013, AND MF1014)
Dear Mr. Batson:
The purpose of this letter is to provide a summary of the U.S. Nuclear Regulatory Commission (NRC) staff's assessment of the re-evaluated flood-causing mechanisms described in the March 12, 2013 (Agencywide Document Access and Management System (ADAMS) Accession No. ML13079A227), flood hazard reevaluation report (FHRR) submitted by Duke Energy Carolinas, LLC (Duke, the licensee) for Oconee Nuclear Station Units 1, 2 and 3 (Oconee), as well as supplemental information resulting from requests for additional information and audits. This supplemental information included the licensee's revised FHRR for Oconee, submitted on March 6, 2015 (ADAMS Accession No. ML15072A099)
By letter dated March 12, 2012, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Section 50.54(f) (hereafter referred to as the 50.54(f) letter)
(ADAMS Accession No. ML12053A340). The request was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to re-evaluate flood-causing mechanisms using present-day methodologies and guidance. Concurrently, with the reevaluation of flooding hazards, licensees were required to develop and implement mitigating strategies in accordance with NRC Order EA-12-049, "Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML12054A735). On March 30, 2015, the Commission provided Staff Requirements Memorandum (SRM) (ADAMS Accession No. ML15089A236) to COMSECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards," dated November 21, 2014 (ADAMS Accession No. ML14309A256), affirming that licensees need to address the reevaluated flooding hazards within their mitigating strategies for beyond-design-basis external events.
Enclosure 2 transmitted herewith contains Security-Related Information. When separated from the Enclosure, this document is decontrolled.
OfflCl.'~.b use ONbY SECYRITY RELATED INFORMATION
OFFICIAL USE..o.N.L.Y- SECURITY RELATED INFORMA.TION S. Batson The NRC staff has reviewed the information submitted by the licensee and has summarized the results of the review in the tables provided as Enclosure 1 to this letter. Table 1 provides the current design-basis flood hazard mechanisms.
Table 2 provides reevaluated flood hazard mechanisms; however, reevaluated hazard mechanisms bounded by the current design-:basis (Table 1) are not included. Because Table 2 includes security-related information, Enclosure 1 contains the redacted version of Table 2.
Enclosure 2 is withheld from public disclosure and restores the security-related information to Table 2.
The NRC staff has concluded that the licensee's reevaluated flood hazards information, as summarized in the Enclosure, is suitable for the assessment of mitigating strategies developed in response to Order EA-12-049 (i.e., defines the mitigating strategies flood hazard information described in guidance documents currently being finalized by the industry and NRC staff), for Oconee. Further, the NRC staff has concluded that the licensee's reevaluated flood hazard information is a suitable input for other assessments associated with Near-Term Task Force Recommendation 2.1 "Flooding". The NRC staff plans to issue a staff assessment documenting the basis for these conclusions in the near future. The staff also intends to address the impact of this reevaluated flood hazard review on the previous Oconee flooding analyses submitted in response to the NRC's Confirmatory Action Letter, dated June 22, 2010 (ADAMS Accession No. ML101730329).
In addition, NEI 12-06 "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide" is currently being revised. This revision will include a methodology to perform a Mitigating Strategies Assessment (MSA) with respect to the reevaluated flood hazards. Once this methodology is endorsed by the NRC, flood event duration parameters and applicable flood associated effects should be considered as part of the Oconee MSA. The NRC staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood-related associated effects developed by the licensee during the NRC staff's review of the MSA.
As stated above, Table 2 of the enclosure to this letter describes the reevaluated flood hazards that exceed the current design-basis. In order to complete its response to the information requested by Enclosure 2 to the 50.54(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 letter, "Coordination of Request for Information Regarding Flooding Hazard Reevaluation and Mitigating Strategies for Beyond-Design-Basis External Events," dated September 1, 2015 (ADAMS Accession No. ML15174A257). This letter describes the changes in the NRC's approach to the flood hazard reevaluations that were approved by the Commission in its SRM to COMSECY-15-0019, "Closure Plan for the Reevaluation of Flooding Hazards for Operating Nuclear Power Plants" (ADAMS Accession No. ML15209A682).
OFFICIAL IJSli ONLY SECURITY RELATED INFORMATION
- OISfii'ICll\L USE ONLY SECURITY RELATED INFORMATION S. Batson If you have any questions, please contact me at (301) 415-3809 or e-mail at Juan.Uribe@nrc.gov.
f~ ~~
Juan F. Uribe, Pr ject Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287
Enclosures:
- 1. Summary of Results of Flooding Hazard Re-Evaluation Report (Redacted Version)
- 2. Summary of Results of Flooding Hazard Re-Evaluation Report {Non-Public Version) cc w/encl: Distribution via Listserv
.OFFICIAL USli ONLY SECURITY RELATED INFORMJ'.TION
ENCLOSURE 1:
SUMMARY
TABLES OF REEVALUATED FLOOD HAZARD LEVELS (REDACTED VERSION)
Oconee, Units 1, 2, &3 Table 1. Current Design Basis Flood Hazards for Use in the MSA
*---** -- ----~
Mechanism Stillwater Waves/ Design Basis Reference Elevation Run up Hazard
- Elevation Local Intense Precipitation Not included Not included Not included Staff Assessment in DB in DB in DB Streams and Rivers Flooding in Reservoirs - Keowee 808.0 ft MSL Not 808.0 ft MSL Staff Assessment Reservoir {not calculated at applicable Power Block)
Failure of Dams and Onsite Water Control/Storage Structures Not included Not included Not included Staff Assessment in DB in DB in DB Storm Surge Not included Not included Not included Staff Assessment in DB in DB in DB Seiche Not included Not included Not included Staff Assessment in DB in DB in DB Tsunami Not included Not included Not included Staff Assessment in DB in DB in DB Ice-Induced Flooding Not included I Not included Not included Staff Assessment in DB in DB in DB Channel Migrations/Diversions Not included Not included Not included Staff Assessment in DB in DB in DB
[ ____ ---------~---- - -*------
Note 1: Reported values are rounded to the nearest one-tenth of a foot.
Oconee, Units 1, 2, &3 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Stillwater Waves/ Reevaluated Reference Elevation Run up Hazard Elevation Local Intense Precipitation 800.4 ft MSL Minimal 800.4 ft MSL FHRR Section 3.1 I I
Streams and Rivers Streams and Rivers (Flooding in 808.9 ft MSL 3.3 ft 812.2 ft MSL I FHRR Section 3.2 Reservoirs, Keowee)
Failure of Dams and Onsite Water Control/Storage Structures
[Redacted] [Redacted] [Redacted] [Redacted] [Redacted]
~--~----- **-*-----------------~ ---- ---- -~--------- - --*----~---- ------- ----.-
Note 1: The licensee is expected to develop flood event duration parameters and applicable flood associated effects to conduct the MSA consistent with the guidance. The NRC staff has reviewed information related to flood event duration parameters (including warning time and period of inundation).
Note 2: Reevaluated hazard mechanisms bounded by the current design basis (see Table 1) are not included in this table.
Note 3: Reported values are rounded to the nearest one-tenth of a foot.
PKG ML152398243 LTR: ML152398261; ENCL 1: ML152388723 (PUBLIC)
ENCL 2* ML152228209 (NON-PUBLIC) *via email OFFICE NRR/JLD/JHMB/PM* NRR/JLD/LA NRO/DSEA/RHM2/TR*
NAME JUribe SLent NTiruneh DATE 8/28/2015 8/28/2015 8/17/2015 OFFICE NRO/DSEA/RHM2/BC* NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME ARivera-Varona MShams JUribe DATE 8/17/2015 8/28/2015 9/24/2015
