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MONTHYEARLIC-14-0098, License Amendment Request 14-06 to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2014-12-26026 December 2014 License Amendment Request 14-06 to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors Project stage: Request ML15008A0892015-01-0808 January 2015 NRR E-mail Capture - Acceptance Review Project stage: Acceptance Review ML15194A2722015-07-14014 July 2015 Request for Additional Information, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors Project stage: RAI LIC-15-0102, Response to NRC Request for Additional Information Re License Amendment Request to Adopt Emergency Action Level Scheme Per NEI 99-01, Rev. 62015-09-11011 September 2015 Response to NRC Request for Additional Information Re License Amendment Request to Adopt Emergency Action Level Scheme Per NEI 99-01, Rev. 6 Project stage: Response to RAI LIC-15-0115, ISFSI - Response to NRC Request for Clean Copy of Emergency Action Level Technical Basis Document2015-09-18018 September 2015 ISFSI - Response to NRC Request for Clean Copy of Emergency Action Level Technical Basis Document Project stage: Request LIC-15-0121, ISFSI - Supplemental OPPD Response to NRC Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62015-11-0202 November 2015 ISFSI - Supplemental OPPD Response to NRC Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 Project stage: Supplement LIC-15-0139, ISFSI - Supplemental OPPD Response to NRC Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62015-12-0808 December 2015 ISFSI - Supplemental OPPD Response to NRC Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 Project stage: Supplement 2015-12-08
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Category:Letter
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, Shpo; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1262022-08-0303 August 2022 Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, Re., Ft Calhoun LTP Section 106 ML22101A1092022-08-0303 August 2022 Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1292022-08-0303 August 2022 Letter to Tiauna Carnes, Chairperson, Sac and Fox Nation of Missouri in Kansas, Re., Ft Calhoun LTP Section 106 ML22138A1212022-08-0303 August 2022 Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1282022-08-0303 August 2022 Letter to Victoria Kitcheyan, Chairwoman, Winnebago Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1232022-08-0303 August 2022 Letter to Mr. Leander Merrick, Chairperson, Omaha Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1272022-08-0303 August 2022 Letter to Vern Jefferson, Chairman, Sac and Fox Tribe of the Mississippi in Iowa, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22159A2152022-06-28028 June 2022 Letter Forwarding FRN on Public Meeting and Request for Comment on License Termination Plan LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information IR 05000285/20220032022-06-15015 June 2022 NRC Inspection Report 05000285/2022003 ML22119A2472022-05-0303 May 2022 Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review IR 05000285/20220022022-04-28028 April 2022 NRC Inspection Report 050-00285/2022-002 LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report 2024-01-31
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information ML22034A5592022-01-13013 January 2022 Response to Fort Calhoun Station, Unit No. 1 - Acceptance Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Supplemental Information (EPID L-2021-LIT-OOOO) Ml21350A02 ML20202A6542020-07-16016 July 2020 Response for Fort Calhoun Station Fort Calhoun Station, Unit No. 1, Revised Post-Shutdown Decommissioning Activities Report LIC-19-0021, Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme2019-11-20020 November 2019 Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme LIC-18-0018, Independent Spent Fuel Storage Installation - Emergency Plan Update2018-04-18018 April 2018 Independent Spent Fuel Storage Installation - Emergency Plan Update ML18088B3782018-03-29029 March 2018 Response to Request for Additional Information Regarding Omaha Public Power District'S Decommissioning Funding Plan Update for Fort Calhoun Station Independent Spent Fuel Storage Installation ML17348A6232017-12-14014 December 2017 Response for Fort Calhoun Station Specific Questions and Concerns Regarding Omaha Public Power District'S Post-Shutdown Decommissioning Activities Report (PSDAR) LIC-17-0068, Reply to Final Request for Additional Information (RAI) for Fort Calhoun Exemption from 10 CFR 140.11 (a)(4), Off-site Primary and Secondary Liability Insurance (MF9664)2017-10-0404 October 2017 Reply to Final Request for Additional Information (RAI) for Fort Calhoun Exemption from 10 CFR 140.11 (a)(4), Off-site Primary and Secondary Liability Insurance (MF9664) LIC-17-0065, Submittal of Response to Request for Additional Information Re Fort Calhoun Request to Revise Their Technical Specifications to Align to Those Requirements for Decommissioning2017-09-26026 September 2017 Submittal of Response to Request for Additional Information Re Fort Calhoun Request to Revise Their Technical Specifications to Align to Those Requirements for Decommissioning ML17268A2212017-09-25025 September 2017 Response to Request for Additional Information (RAI) Regarding License Amendment Request 16-04 Revising Current Licensing Basis to Use Aci Ultimate Strength Requirements ML17264A7502017-09-21021 September 2017 Response to Request for Additional Information (RAI) License Amendment Request Regarding Removal of Dry Cask Loading Limits Fort Calhoun Station, Unit 1 Docket No.: 50-285 (MF9831) LIC-17-0054, Submission of Corrected Pages for Response to Request for Additional Information, Fort Calhoun Station, Unit No. 1 - Request for Additional Information Certified Fuel Handler Training Program2017-06-0606 June 2017 Submission of Corrected Pages for Response to Request for Additional Information, Fort Calhoun Station, Unit No. 1 - Request for Additional Information Certified Fuel Handler Training Program LIC-17-0047, Final Request for Additional Information Concerning License Amendment Request 16-07: Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2017-05-15015 May 2017 Final Request for Additional Information Concerning License Amendment Request 16-07: Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme LIC-17-0048, Response to Request for Additional Information Regarding the Fort Calhoun Station Request to Revise Technical Specifications to Align Staffing Requirements for Permanently Defueled Condition2017-04-27027 April 2017 Response to Request for Additional Information Regarding the Fort Calhoun Station Request to Revise Technical Specifications to Align Staffing Requirements for Permanently Defueled Condition LIC-17-0045, Response to Request for Additional Information Defueled Emergency Plan Exemption Request2017-04-20020 April 2017 Response to Request for Additional Information Defueled Emergency Plan Exemption Request LIC-17-0037, Response to Request for Additional Information, Fort Calhoun Station, Unit No.1 - Final Request for Additional Information Concerning Exemption from the Requirements of 10 CFR 50.47 and Appendix E2017-04-14014 April 2017 Response to Request for Additional Information, Fort Calhoun Station, Unit No.1 - Final Request for Additional Information Concerning Exemption from the Requirements of 10 CFR 50.47 and Appendix E LIC-17-0036, Supplemental Response to Request for Additional Information - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment2017-04-0505 April 2017 Supplemental Response to Request for Additional Information - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment ML17089A5442017-03-30030 March 2017 Response to Request for Additional Information Certified Fuel Handler Training Program LIC-17-0020, Response to Request for Additional Information, Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment2017-03-0303 March 2017 Response to Request for Additional Information, Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment LIC-17-0024, Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 4 of 4)2017-02-10010 February 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 4 of 4) ML17041A4432017-02-10010 February 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 1 of 4) ML17041A4442017-02-10010 February 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 2 of 4) LIC-16-0107, Final Response to the Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident and Corresponding Commitments2016-11-18018 November 2016 Final Response to the Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident and Corresponding Commitments LIC-16-0090, Response to Request for Additional Information Regarding Certified Fuel Handler Training Program2016-10-0707 October 2016 Response to Request for Additional Information Regarding Certified Fuel Handler Training Program LIC-16-0078, Revision to Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - Flood Hazard Reevaluation Report2016-09-14014 September 2016 Revision to Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - Flood Hazard Reevaluation Report ML16165A0282016-06-0909 June 2016 Response to NRC Request for Additional Information Revise Current Licensing Basis to Use American Concrete Institute Ultimate Strength Requirements LIC-16-0044, Calculation FC08499 Evaluation of FCS Concrete Compressive Strength Test Data2016-06-0101 June 2016 Calculation FC08499 Evaluation of FCS Concrete Compressive Strength Test Data LIC-16-0025, Ft. Calhoun, Unit 1 - Response to Request for Additional Information Adoption of TSTF-501, Revision 12016-04-0808 April 2016 Ft. Calhoun, Unit 1 - Response to Request for Additional Information Adoption of TSTF-501, Revision 1 LIC-16-0022, Response to NRC Request for Additional Information Revise Current Licensing Basis to Allow Use of Equipment Classification Methodology from ANSI/ANS-58.14-20112016-04-0808 April 2016 Response to NRC Request for Additional Information Revise Current Licensing Basis to Allow Use of Equipment Classification Methodology from ANSI/ANS-58.14-2011 ML16057A0742016-02-26026 February 2016 Response to Regulatory Information Summary (RIS) 2015-16, Planned Licensing Action Submittals for All Power Reactor Licensees. LIC-16-0001, Response to NRC Request for Additional Information Technical Specification Administrative Changes2016-01-27027 January 2016 Response to NRC Request for Additional Information Technical Specification Administrative Changes LIC-15-0147, Response to NRC Request for Additional Information Fifth Lnservice Testing Interval Relief Requests P-1 and P-22016-01-11011 January 2016 Response to NRC Request for Additional Information Fifth Lnservice Testing Interval Relief Requests P-1 and P-2 LIC-15-0139, ISFSI - Supplemental OPPD Response to NRC Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62015-12-0808 December 2015 ISFSI - Supplemental OPPD Response to NRC Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 ML15350A0192015-11-30030 November 2015 Enclosure 6, Response to Remaining Questions from NRC Request for Additional Information (RAI) Regarding Reactor Vessel Internal Component Aging Management Program. (Non-Proprietary) ML15350A0182015-11-30030 November 2015 Transmittal of Response to Remaining Questions from NRC Request for Additional Information (RAI) Regarding Reactor Vessel Internal Component Aging Management Program LIC-15-0129, Addendum to Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - Flood Hazard Reevaluation Report2015-11-0404 November 2015 Addendum to Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - Flood Hazard Reevaluation Report LIC-15-0121, ISFSI - Supplemental OPPD Response to NRC Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62015-11-0202 November 2015 ISFSI - Supplemental OPPD Response to NRC Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 LIC-15-0113, Response to Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation2015-09-28028 September 2015 Response to Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation LIC-15-0115, ISFSI - Response to NRC Request for Clean Copy of Emergency Action Level Technical Basis Document2015-09-18018 September 2015 ISFSI - Response to NRC Request for Clean Copy of Emergency Action Level Technical Basis Document LIC-15-0102, Response to NRC Request for Additional Information Re License Amendment Request to Adopt Emergency Action Level Scheme Per NEI 99-01, Rev. 62015-09-11011 September 2015 Response to NRC Request for Additional Information Re License Amendment Request to Adopt Emergency Action Level Scheme Per NEI 99-01, Rev. 6 2023-09-28
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LIC-15-0139 December 8, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Fort Calhoun Station (FCS), Unit 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285 Fort Calhoun Station Independent Spent Fuel Storage Installation NRC Docket No.72-054
Subject:
Supplemental OPPD Response to NRC Request for Additional Information RE: License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (TAC No. MF5466)
References:
Page 3 Following a teleconference with NRC Staff on November 23, 2015, the Omaha Public Power District (OPPD) is supplementing its Reference 3 response to the Reference 2 NRC request for additional information (RAI) regarding License Amendment Request (LAR) 14-06 (Reference 1 ). LAR 14-06 proposes to revise the Emergency Plan for Fort Calhoun Station to adopt the Nuclear Energy lnstitute's (NEl's) revised Emergency Action Level (EAL) scheme described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.
Enclosure 1 contains a revised response to RAI 24 to be more consistent with guidance contained in the Emergency Operating Procedures.
Enclosure 2 contains a revised procedure matrix reflecting the change and an editorial correction to mode titles contained in the footnote.
Enclosure 3 contains revised pages for the EAL Basis Document for EALs MS3, MA3, and MU3. This letter contains no regulatory commitments
. ..---------------
..:...44'-"-'4 SOUTH 16TH STREET MALL* OMAHA, NE 68102-2247 U.S. Nuclear Regulatory Commission LIC-15-0139 Page 2 If you should have any questions regarding this submittal or require additional information
, please contact Mr. Bill R. Hansher at 402-533-6894.
Louis P. Cortopassi Site Vice President and CNO LPC/EJP/mle
Enclosures:
- 1. Revised OPPD Response to NRC RAI 24 Regarding License Amendment Request (LAR) 14-06 2. Procedure Matrix Revised Page for EALs MS3, MA3, and MU3 3. EAL Basis Document Revised Pages for EALs MS3, MA3, and MU3 c: M. L. Dapas, NRC Regional Administrator, Region IV (w/o Enclosures 2, 3, 4) C. F. Lyon, NRC Senior Project Manager S. M. Schneider, NRC Senior Resident Inspector (w/o Enclosures 2, 3, 4) Manager Radiation Control Program, Nebraska Health & Human Services, R & L Public Health Assurance, State of Nebraska (w/o Enclosures 2, 3, 4)
U. S. Nuclear Regulatory Commission LIC-15-0139 Page 3
References:
- 1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), "License Amendment Request 14-06 to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors,"
dated December 26, 2014 (LIC-14-0098)
(ML 14365A123)
- 2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi)
, "Fort Calhoun Station, Unit No. 1 -Request for Additional Information Re: License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (TAC No. MF5466)," dated July 14, 2015 (NRC-15-061)
(ML 15194A272)
- 3. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), "OPPD Response to NRC Request for Additional Information RE: License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (TAC No. MF5466)," dated September 11, 2015 (LIC-15-0102)
- 4. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), "Supplemental OPPD Response to NRC Request for Additional Information RE: License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (TAC No. MF5466)," dated November 2, 2015 (LIC-15-0121)
LIC-15-0139 Enclosure 1 Page 1 Revised OPPD Response to NRC RAI 24 Regarding License Amendment Request (LAR) 14-06 LIC-15-0139 Enclosure 1 Page2 REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ADOPT EMERGENCY ACTION LEVEL SCHEME PURSUANT TO NEI 99-01. REVISION 6 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION.
UNIT NO. 1 DOCKET NO. 50-285 By letter dated December 26, 2014, Omaha Public Power District (OPPD, the licensee) requested approval for an emergency action level (EAL) scheme change for the Fort Calhoun Station, Unit 1 (FCS) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14365A123).
OPPD proposes to revise its current EAL scheme to one based upon Revision 6 to Nuclear Energy Institute (NEI) document NEI 99-01 , "Development of Emergency Action Levels for Non-Passive Reactors,"
November 2012 (ADAMS Accession No. ML 12326A805)
, instead of Revision
- 5. The requests for additional information (RAls) listed below, in regards to Attachment 2, Enclosure 2C, "Emergency Action Level Basis Document," of the submittal
, are needed to support U.S. Nuclear Regulatory Commission (NRC) staffs continued technical review of the proposed EAL scheme change. FC-RAl-24 For ICs MU3, MA3, and MS3, please justify why the words:" ... as indicated by reactor 2%," were added to the EALs, or revise accordingly.
Relying solely on a reactor power level of 2 percent is not consistent with EOP criteria as provided by NEI 99-01, Revision
- 6. FC-RAl-24 Response (REVISED)
Revised to add "Reactor power is not < 2%" and "Startup rate is not negative" to the existing reactor power indication to be consistent with guidance provided in EOPs.
LIC-15-0139 Enclosure 2 Procedure Matrix Revised Page FC 3-16 for EALs MS3, MA3, and MU3 I System Malfunction
"' LL "' c.. 0::: (/) c: 0 ;; "' (.) =s c: E 0 0 0::: 0 i.. -c: 0 u Table M1 Control Room Parameters
- In Core/Core Exit Temperature
- Level in at least one OTSG.
- Auxiliary Feed Water Flow MS3 Inability to shutdown the reactor causing a challenge to core cooling or RCS heat removal. 1 Emergency Action Levels (EAL) : 11 1 . Automatic or Manual Trip failed to shutdown the reactor as 1 indicated by ANY of the following:
I i
- Reactor power is not < 2%
- Startup rate is not negative AND 2. All manual actions failed to shutdown the reactor as indicated by ANY of the following:
- Reactor power is not < 2%
- Startup rate is not negative AND 3. EITHER of the following conditions exist: a. Core exit thermocouples
> 1550°F. OR b. RVLMS indicates 0.0% OR c. Once-Through-Cooling, EOP-20 HR4 in effect. Table M2 Significant Transients
- Electrical Load Rejection
>25% full electrical load *
- Reactor Trip ECCS Actuation Mode: 1 -Power Operations 2 -Hot Standby 3 -Hot Shutdown 4 -Cold Shutdown Month 20XX COLD SHUTDOWN/REFUELING MATRIX MA3 Automatic or manual trip fails to shutdown ff]!] 1 the reactor, and subsequent manual actions taken at the reactor control consoles are not successful in shutting down the reactor. I Emergency Action Levels (EAL) : Note: A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.
- 1. Automatic or Manual Trip failed to shutdown the reactor as indicated by ANY of the following:
- Reactor power is not < 2%
- Startup rate is not negative AND 2. Manual actions taken at the Console Center failed to shutdown the reactor as indicated by ANY of the following:
- Reactor power is not < 2%
- Startup rate is not negative MA4 UNPLANNED loss of Control Room indications for 15 minutes or longer with a significant transient in progress. ; Emergency Action Levels (EAL) : Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded
- 1. a An UNPLANNED event results in the inability to monitor ANY Table M1 parameters from within the Control Room 15 minutes.
AND b. ANY Table M2 transient in progress. 5 -Refueling Shutdown D -Defueled I MU3 Automatic or manual trip fails to shutdown the reactor. I Emergency Action Levels (EAL): I Note: A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.
- 1. a. Automatic Trip failed to shutdown the reactor as indicated by ANY of the following
- Startup rate is not negative AND b. Subsequent manual action taken at the Console Center is successful in shutting down the reactor. OR 2. a. Manual Trip failed to shutdown the reactor as indicated by ANY of the following
- Reactor power is not < 2%
- Startup rate is not negative AND b. EITHER of the following:
- 1. Subsequent manual action taken at the Console Center is successful in shutting down the reactor.
OR .2. Subsequent automatic Trip is successful in shutting down the reactor.
MU4 UNPLANNED loss of Control Room indications for 15 minutes or longer. Emergency Action Levels (EAL) : Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded An UNPLANNED event results in the inability to monitor ANY Table M1 ! parameters from within the Control Room 15 minutes.
FC 3-16 COLD SHUTDOWN/REFUELING MATRIX EP-XX-XXXX (Revision XX)
LIC-15-0139 Enclosure 3 EAL Basis Document Revised Pages for EALs MS3, MA3, and MU3 Ft. Calhoun Station Omaha Public Power District Initiating Condition:
RECOGNITION CATEGORY SYSTEM MALFUNCTIONS Inability to shutdown the reactor causing a challenge to core cooling or RCS heat removal.
Operating Mode Applicability:
1, 2 Emergency Action Level (EAL}: MS3 1. Automatic or Manual Trip failed to shutdown the reactor as indicated by ANY of the following:
- Reactor power is not < 2%
- Startup rate is not negative AND 2. All manual actions failed to shutdown the reactor as indicated by ANY of the following:
- Reactor power is not < 2%
- Startup rate is not negative AND 3. EITHER of the following conditions exist: Basis: a. Core exit thermocouples>
1550°F. OR b. RVLMS indicates 0.0% OR c. Once-Through-Cooling, EOP-20 HR4 in effect. This IC addresses a failure of the RPS to initiate or complete an automatic or manual reactor trip that results in a reactor shutdown, all subsequent operator manual actions, both inside and outside the Control Room including driving in control rods and boron injection, are unsuccessful, and continued power generation is challenging the capability to adequately remove heat from the core and/or the RCS. This condition will lead to fuel damage if additional mitigation actions are unsuccessful and thus warrants the declaration of a Site Area Emergency.
In some instances, the emergency classification resulting from this IC/EAL may be higher than that resulting from an assessment of the plant responses and symptoms against the Recognition Category F ICs/EALs.
This is appropriate in that the Recognition Category F ICs/EALs do not address the additional threat posed by a failure to shutdown the reactor.
The inclusion of this IC and EAL ensures the timely Month 20XX FC 3-89 EP-XX-XXXX (Revision XX)
Ft. Calhoun Station Basis (cont): Omaha Public Power District RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MS3 (cont) declaration of a Site Area Emergency in response to prolonged failure to shutdown the reactor.
A reactor shutdown is determined in accordance with applicable Emergency Operating Procedure criteria.
Escalation of the emergency classification level would be via IC RG1 or FG1. Basis Reference(s):
- 1. NEI 99-01 Rev 6, SS5 Month 20XX FC 3-90 EP-XX-XXXX (Revision XX)
Ft. Calhoun Station Omaha Public Power District Initiating Condition:
RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MA3 Automatic or manual trip fails to shutdown the reactor, and subsequent manual actions taken at the reactor control consoles are not successful in shutting down the reactor. Operating Mode Applicability:
1, 2 Emergency Action Level (EAL): Note:
- A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.
- 1. Automatic or Manual Trip failed to shutdown the reactor as indicated by ANY of the following:
- Reactor power is not < 2%
- Startup rate is not negative AND 2. Manual actions taken at the Console Center failed to shutdown the reactor as indicated by ANY of the following:
- Reactor power is not < 2%
- Startup rate is not negative Basis: This IC addresses a failure of the RPS to initiate or complete an automatic reactor trip that results in a reactor shutdown, and subsequent operator manual actions taken at the Console Center to shutdown the reactor are also unsuccessful.
This condition represents an actual or potential substantial degradation of the level of safety of the plant. An emergency declaration is required even if the reactor is subsequently shutdown by an action taken away from the Console Center since this event entails a significant failure of the RPS. A manual action at the Console Center is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core (e.g., initiating a manual reactor trip. This action does not include manually driving in control rods or implementation of boron injection strategies.
If this action(s) is unsuccessful
, operators would immediately pursue additional manual actions at locations away from the Console Center (e.g., locally opening breakers)
. Actions taken at back-panels or other locations within the Control Room, or any location outside the Control Room, are not considered to be "at the Console Center. Month 20XX FC 3-91 EP-XX-XXXX (Revision XX)
Ft. Calhoun Station Basis (cont): Omaha Public Power District RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MA3 {cont) The plant response to the failure of an automatic or manual reactor trip will vary based upon several factors including the reactor power level prior to the event, availability of the condenser, performance of mitigation equipment and actions, other concurrent plant conditions, etc. If the failure to shutdown the reactor is prolonged enough to cause a challenge to the core cooling or RCS heat removal safety functions
, the emergency classification level will escalate to a Site Area Emergency via IC MS3. Depending upon plant responses and symptoms, escalation is also possible via IC FS1. Absent the plant conditions needed to meet either IC MS3 or FS1, an Alert declaration is appropriate for this event. It is recognized that plant responses or symptoms may also require an Alert declaration in accordance with the Recognition Category F ICs; however, this IC and EAL are included to ensure a timely emergency declaration.
A reactor shutdown is determined in accordance with applicable Emergency Operating Procedure criteria.
Basis Reference(s):
- 1. NEI 99-01 Rev 6, SA5 Month 20XX FC 3-92 EP-XX-XXXX (Revision XX)
Ft. Calhoun Station Omaha Public Power District Initiating Condition:
RECOGNITION CATEGORY SYSTEM MALFUNCTIONS Automatic or manual trip fails to shutdown the reactor.
Operating Mode Applicability:
1, 2 Emergency Action Level (EAL): Note: MU3
- A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.
- 1. a. Automatic Trip failed to shutdown the reactor as indicated by ANY of the following:
- Reactor power is not < 2%
- Startup rate is not negative AND b. Subsequent manual action taken at the Console Center is successful in shutting down the reactor.
OR 2. a. Manual Trip failed to shutdown the reactor as indicated by ANY of the following:
- Reactor power is not < 2%
- Startup rate is not negative AND b. EITHER of the following:
Basis: 1 . Subsequent manual action taken at the Console Center is successful in shutting down the reactor.
OR 2. Subsequent automatic Trip is successful in shutting down the reactor.
This IC addresses a failure of the RPS to initiate or complete an automatic or manual reactor trip that results in a reactor shutdown, and either a subsequent operator manual action taken at the Console Center or an automatic trip is successful in shutting down the reactor.
This event is a precursor to a more significant condition and thus represents a potential degradation of the level of safety of the plant. Month 20XX FC 3-93 EP-XX-XXXX (Revision XX)
Ft. Calhoun Station Basis (cont): EAL #1 Basis Omaha Public Power District RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU3 (cont) Following the failure on an automatic reactor trip, operators will promptly initiate manual actions at the Console Center to shutdown the reactor (e.g., initiate a manual reactor trip). If these manual actions are successful in shutting down the reactor, core heat generation will quickly fall to a level within the capabilities of the plant's decay heat removal systems.
EAL#2 Basis If an initial manual reactor trip is unsuccessful, a concurrent plant condition, may lead to the generation of an automatic reactor trip signal. If a subsequent automatic trip is successful in shutting down the reactor, core heat generation will quickly fall to a level within the capabilities of the plant's decay heat removal systems. A manual action at the Console Center is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core (e.g., initiating a manual reactor trip). This action does not include manually driving in control rods or implementation of boron injection strategies
. Actions taken at back-panels or other locations within the Control Room, or any location outside the Control Room, are not considered to be "at the Console Center".
The plant response to the failure of an automatic or manual reactor trip will vary based upon several factors including the reactor power level prior to the event, availability of the condenser, performance of mitigation equipment and actions, other concurrent plant conditions, etc. If subsequent operator manual actions taken at the Console Center are also unsuccessful in shutting down the reactor, then the emergency classification level will escalate to an Alert via IC MA3. Depending upon the plant response, escalation is also possible via IC FA1. Absent the plant conditions needed to meet either IC MA3 or FA 1, an Unusual Event declaration is appropriate for this event. A reactor shutdown is determined in accordance with applicable Emergency Operating Procedure criteria.
Should a reactor trip signal be generated as a result of plant work (e.g., RPS setpoint testing),
the following classification guidance should be applied.
- If the signal generated as a result of plant work causes a plant transient that creates a real condition that should have included an automatic reactor trip and the RPS fails to automatically shutdown the reactor, then this IC and the EALs are applicable
, and should be evaluated.
- If the signal generated as a result of plant work does not cause a plant transient but should have generated an RPS trip signal and the trip failure is determined through other means (e.g., assessment of test results),
then this IC and the EALs are not applicable and no classification is warranted.
Month 20XX FC 3-94 EP-XX-XXXX (Revision XX)
Ft. Calhoun Station Basis Reference(s):
- 1. NEI 99-01 Rev 6, SU5 Month 20XX Omaha Public Power District RECOGNITION CATEGORY SYSTEM MALFUNCTIONS FC 3-95 MU3 (cont) EP-XX-XXXX (Revision XX)