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| {{#Wiki_filter:July 19, 2006Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. | | {{#Wiki_filter:July 19, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. |
| Post Office Box 550 Fort Calhoun, NE 68023-0550 | | Post Office Box 550 Fort Calhoun, NE 68023-0550 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION (RAI) RELATED TO REVISING THE FORT CALHOUN STATION UPDATED SAFETY ANALYSIS REPORT (TAC NO. MC8857)Dear Mr. Ridenoure | | FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO REVISING THE FORT CALHOUN STATION UPDATED SAFETY ANALYSIS REPORT (TAC NO. MC8857) |
| :By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted anamendment request to revise the Fort Calhoun Station, Unit 1, Updated Safety Analysis Reportfor the radiological consequences of events affected by the planned 2006 replacement of the steam generators and pressurizer.The U.S. Nuclear Regulatory Commission staff has reviewed OPPD's submittal and hasdetermined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on July 5, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.If you have any questions, please contact me at (301) 415-1445. Sincerely,
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| /RA/ Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No.
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| 50-285
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| ==Enclosure:== | | ==Dear Mr. Ridenoure:== |
| RAIcc w/encl: See next page July 19, 2006Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
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| Post Office Box 550 Fort Calhoun, NE 68023-0550
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| ==SUBJECT:==
| | By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted an amendment request to revise the Fort Calhoun Station, Unit 1, Updated Safety Analysis Report for the radiological consequences of events affected by the planned 2006 replacement of the steam generators and pressurizer. |
| FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION (RAI) RELATED TO REVISING THE FORT CALHOUN STATION UPDATED SAFETY ANALYSIS REPORT (TAC NO. MC8857)Dear Mr. Ridenoure
| | The U.S. Nuclear Regulatory Commission staff has reviewed OPPDs submittal and has determined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on July 5, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter. |
| :By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted anamendment request to revise the Fort Calhoun Station, Unit 1, Updated Safety Analysis Reportfor the radiological consequences of events affected by the planned 2006 replacement of the steam generators and pressurizer.The U.S. Nuclear Regulatory Commission staff has reviewed OPPD's submittal and hasdetermined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on July 5, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.If you have any questions, please contact me at (301) 415-1445. Sincerely,/RA/
| | If you have any questions, please contact me at (301) 415-1445. |
| Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. | | Sincerely, |
| 50-285 | | /RA/ |
| | Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 |
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| ==Enclosure:== | | ==Enclosure:== |
| RAIcc w/encl: See next pageDISTRIBUTION
| | RAI cc w/encl: See next page |
| :PUBLICLPLIV R/FRidsOgcRpRidsRgn4MailCenter(DGraves) RidsNrrLALFeizollahiRidsNrrPMAWangRidsAcrsAcnwMailCenterRidsNrrDorlLpl4 RidsNrrDorlDprADAMS ACCESSION NO.: ML061930417OFFICELPL4/PMLPL4/LALPL4/BCNAMEAWangLFeizollahiDTeraoDATE07/17/0607/17/0607/19/06OFFICIAL RECORD COPY
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| REQUEST FOR ADDITIONAL INFORMATIONREGARDING UPDATED SAFETY ANALYSIS REPORTRADIOLOGICAL CONSEQUENCE ANALYSISOMAHA PUBLIC POWER DISTRICTFORT CALHOUN STATION, UNIT 1DOCKET NUMBER 50-285By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted anamendment request to revise the Fort Calhoun Station, Unit 1 (FCS), Updated Safety Analysis Report (USAR) for the radiological consequences of events affected by the planned 2006 replacement of the steam generator and pressurizer. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed OPPD's submittal and has determined that the followingadditional information is needed to complete our review: 1.The NRC staff notes that the atmospheric dispersion factors (/Q values) provided in theOctober 31, 2005, license amendment request (LAR) are the same as those approved in the safety evaluation associated with FCS Amendment No. 201. Amendment No. 201 implements use of the alternative source term in the FCS design-basis accident dose assessments. Therefore, for each design-basis accident or event addressed in the October 31, 2005, LAR, please discuss any differences between the two sets of release scenarios. If there are differences, please justify how the differences do not impact the applicability of the /Q values associated with Amendment No. 201 to the doseassessment associated with the October 31, 2005, LAR.2.Which water mass inventories (both primary and secondary) were used in calculatingcoolant activities? Please indicate if the used values are the minimum, nominal or maximum.3.The submitted S-RELAP5 analysis indicates 0 percent/0 percent fraction of failed/meltedfuel. Is this a change from the analysis of record? 4.Attachment 4 (AREVA document 86-5064251-00) describes the thermal-hydraulic inputin support of the consequence analysis. Please confirm that the main steam safety valves and atmospheric dump valves actuation setpoints used are those specified in thetechnical specifications.5.Presumably, the cumulative steam releases used in the Attachment 6 (Stone & Websterreport) came from the Attachment 4 (AREVA document). However, it is not immediately obvious which tables in Attachment 4 were used to generate Tables 7.6 - 7.9 in . Please clarify.
| | July 19, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. |
| | Post Office Box 550 Fort Calhoun, NE 68023-0550 |
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| April 2006Ft. Calhoun Station, Unit 1 cc:Winston & Strawn ATTN: James R. Curtiss, Esq.
| | ==SUBJECT:== |
| 1700 K Street, N.W.
| | FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO REVISING THE FORT CALHOUN STATION UPDATED SAFETY ANALYSIS REPORT (TAC NO. MC8857) |
| Washington, DC 20006-3817ChairmanWashington County Board of Supervisors
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| P.O. Box 466 Blair, NE 68008Mr. John Hanna, Resident InspectorU.S. Nuclear Regulatory Commission
| | ==Dear Mr. Ridenoure:== |
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| P.O. Box 310 Fort Calhoun, NE 68023Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007Mr. David J. Bannister, ManagerFort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant
| | By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted an amendment request to revise the Fort Calhoun Station, Unit 1, Updated Safety Analysis Report for the radiological consequences of events affected by the planned 2006 replacement of the steam generators and pressurizer. |
| | The U.S. Nuclear Regulatory Commission staff has reviewed OPPDs submittal and has determined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on July 5, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter. |
| | If you have any questions, please contact me at (301) 415-1445. |
| | Sincerely, |
| | /RA/ |
| | Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 |
| | |
| | ==Enclosure:== |
| | RAI cc w/encl: See next page DISTRIBUTION: |
| | PUBLIC LPLIV R/F RidsOgcRp RidsRgn4MailCenter(DGraves) |
| | RidsNrrLALFeizollahi RidsNrrPMAWang RidsAcrsAcnwMailCenter RidsNrrDorlLpl4 RidsNrrDorlDpr ADAMS ACCESSION NO.: ML061930417 OFFICE LPL4/PM LPL4/LA LPL4/BC NAME AWang LFeizollahi DTerao DATE 07/17/06 07/17/06 07/19/06 OFFICIAL RECORD COPY |
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| P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Joe L. McManisManager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
| | REQUEST FOR ADDITIONAL INFORMATION REGARDING UPDATED SAFETY ANALYSIS REPORT RADIOLOGICAL CONSEQUENCE ANALYSIS OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NUMBER 50-285 By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted an amendment request to revise the Fort Calhoun Station, Unit 1 (FCS), Updated Safety Analysis Report (USAR) for the radiological consequences of events affected by the planned 2006 replacement of the steam generator and pressurizer. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed OPPDs submittal and has determined that the following additional information is needed to complete our review: |
| | : 1. The NRC staff notes that the atmospheric dispersion factors (/Q values) provided in the October 31, 2005, license amendment request (LAR) are the same as those approved in the safety evaluation associated with FCS Amendment No. 201. Amendment No. 201 implements use of the alternative source term in the FCS design-basis accident dose assessments. Therefore, for each design-basis accident or event addressed in the October 31, 2005, LAR, please discuss any differences between the two sets of release scenarios. If there are differences, please justify how the differences do not impact the applicability of the /Q values associated with Amendment No. 201 to the dose assessment associated with the October 31, 2005, LAR. |
| | : 2. Which water mass inventories (both primary and secondary) were used in calculating coolant activities? Please indicate if the used values are the minimum, nominal or maximum. |
| | : 3. The submitted S-RELAP5 analysis indicates 0 percent/0 percent fraction of failed/melted fuel. Is this a change from the analysis of record? |
| | : 4. Attachment 4 (AREVA document 86-5064251-00) describes the thermal-hydraulic input in support of the consequence analysis. Please confirm that the main steam safety valves and atmospheric dump valves actuation setpoints used are those specified in the technical specifications. |
| | : 5. Presumably, the cumulative steam releases used in the Attachment 6 (Stone & Webster report) came from the Attachment 4 (AREVA document). However, it is not immediately obvious which tables in Attachment 4 were used to generate Tables 7.6 - 7.9 in Attachment 6. Please clarify. |
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| P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Daniel K. McGheeBureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319}}
| | Ft. Calhoun Station, Unit 1 cc: |
| | Winston & Strawn Mr. Daniel K. McGhee ATTN: James R. Curtiss, Esq. Bureau of Radiological Health 1700 K Street, N.W. Iowa Department of Public Health Washington, DC 20006-3817 Lucas State Office Building, 5th Floor 321 East 12th Street Chairman Des Moines, IA 50319 Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. |
| | P.O. Box 550 Fort Calhoun, NE 68023-0550 April 2006}} |
Letter Sequence RAI |
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MONTHYEARML0610401792006-04-20020 April 2006
RAI, Alternative Source Term Implementation Review
Project stage: RAI
ML0619304172006-07-19019 July 2006
Request for Additional Information (RAI) Related to Revising the Fort Calhoun Station Updated Safety Analysis Report
Project stage: RAI
ML0627006402006-10-27027 October 2006
Issuance of License Amendment 243 Changes to the Updated Safety Analysis Report Related to Radiological Consequences of 2006 Replacement of Steam Generators and Pressurizer
Project stage: Approval
ML0633901582006-12-11011 December 2006
Request for Withholding Information from Public Disclosure Engineering Information Record 51-9004433-01, FCS RSG - Afas Verification - RAI Responses
Project stage: RAI
2006-12-11
[Table View] |
|
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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:Request for Additional Information (RAI)
MONTHYEARML23151A0042023-06-0606 June 2023
Second Set RAIs Rev 4
ML22357A0672022-12-30030 December 2022
Enclosure RAI Re Approval of License Termination Plan
ML22119A2472022-05-0303 May 2022
Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review
ML20111A2162020-05-20020 May 2020
Revised PSDAR Request for Additional Information - RAI
ML19241A1812019-08-21021 August 2019
Request for Additional Information on Proposed Changes to the FCS Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-only Status
ML18067A1432018-03-0808 March 2018
Enclosurequest for Additional Information (Letter to M. J. Fisher Request for Additional Information Regarding Omaha Public Power District'S Decommissioning Funding Plan Update for Fort Calhoun Station ISFSI)
ML17236A3442017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Exemption from 10 CFR 140.11(a)(4), Off-site Primary and Secondary Liability Insurance (MF9664)
ML17236A3462017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567)
ML17234A4692017-08-22022 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Removal of Dry Cask Loading Limits (MF9831)
ML17194A9732017-07-13013 July 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525)
ML17112A0362017-04-20020 April 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Permanently Defueled EP and EAL Scheme Change LAR
ML17090A3942017-03-31031 March 2017
NRR E-mail Capture - Fort Calhoun - Final RAI Regarding Administrative Control TS Change LAR (MF8437)
ML17082A0022017-03-22022 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final Nsir/Dpr RAI Regarding Proposed Emergency Planning Exemption
ML17081A0192017-03-21021 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Proposed Emergency Planning Exemption
ML17067A3862017-03-15015 March 2017
Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML17033A9692017-02-0202 February 2017
NRR E-mail Capture - Fort Calhoun Station - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment
ML16263A0492016-09-20020 September 2016
Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML16174A1502016-06-27027 June 2016
Request for Additional Information, Relief Request, Use of Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML16146A1782016-05-27027 May 2016
Request for Additional Information, Round 2, Request to Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011
ML16106A0232016-04-29029 April 2016
Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML16104A2872016-04-25025 April 2016
Request for Additional Information, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML16048A1542016-02-23023 February 2016
Request for Additional Information, License Amendment Request, Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011
ML16048A0242016-02-23023 February 2016
Request for Additional Information, License Amendment Request to Adopt Technical Specification Task Force (TSTF)-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML15343A1082015-12-15015 December 2015
Request for Additional Information, License Amendment Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition
ML15323A0362015-11-24024 November 2015
Request for Additional Information, Relief Requests P-1 - LPSI and CS Pumps and P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21, Fifth 10-Year Inservice Testing Interval
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
ML15057A0152015-03-0303 March 2015
Request for Additional Information, Materials Reliability Program (MRP)-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, Implementation Review
ML15043A0612015-02-25025 February 2015
Request for Additional Information, Round 2, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML14353A0512014-12-22022 December 2014
Request for Additional Information, Request to Revise Updated Safety Analysis Report, Design and Evaluation of Seismic Class I Structures Using Ascm (Alternate Seismic Criteria and Methodologies) Developed Floor Response Spectra
ML14259A3652014-09-24024 September 2014
Request for Additional Information, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML14195A0862014-07-16016 July 2014
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report
ML13317A5832013-11-25025 November 2013
Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML13304B4182013-11-0101 November 2013
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
ML13282A5362013-10-0909 October 2013
Request for Additional Information Email, Round 2, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7)
ML13290A0022013-10-0909 October 2013
Request for Additional Information Email, License Amendment Request to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks
ML13270A2872013-09-27027 September 2013
Email, Request for Additional Information Round 4 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
ML13261A2122013-09-18018 September 2013
Request for Additional Information Email, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7)
ML13233A2482013-08-26026 August 2013
Supplemental Information Needed for Acceptance of Requested Licensing Action; Request for Exemption, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage in Lieu of 10 CFR 26.205(d)(7)
ML13235A1682013-08-23023 August 2013
Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
ML13234A4352013-08-22022 August 2013
Request for Additional Information Email, Round 2, Request to Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem. or Component Due to Inoperable Power Source
ML13226A1222013-08-14014 August 2013
Email, Request for Additional Information Round 3 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
ML13212A0092013-07-30030 July 2013
Request for Additional Information Email, Request to Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source
ML13205A1252013-07-24024 July 2013
Request for Additional Information Email Round 2, Exigent Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact
ML13205A0182013-07-23023 July 2013
Request for Additional Information Email, Exigent License Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact
ML13144A4822013-05-23023 May 2013
Request for Additional Information Email, Decommissioning Funding Status Report
ML13100A1752013-04-10010 April 2013
Request for Additional Information Email, Request for One-Time Exemption from Requirements of 10 CFR 26.205(d)(7) to Allow Less Restrictive Working Hour Limitations to Support Activities for Plant Startup
ML13086A4732013-03-27027 March 2013
Request for Additional Information Email, Request to Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan
ML13120A0842013-03-22022 March 2013
Request for Additional Information Email Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 20 (TAC No. D91660)
ML13053A2262013-02-22022 February 2013
Email, Second Round Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.
ML13016A4322013-01-16016 January 2013
E-mail, Request for Additional Information, Round 2, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
2023-06-06
[Table view] |
Text
July 19, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO REVISING THE FORT CALHOUN STATION UPDATED SAFETY ANALYSIS REPORT (TAC NO. MC8857)
Dear Mr. Ridenoure:
By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted an amendment request to revise the Fort Calhoun Station, Unit 1, Updated Safety Analysis Report for the radiological consequences of events affected by the planned 2006 replacement of the steam generators and pressurizer.
The U.S. Nuclear Regulatory Commission staff has reviewed OPPDs submittal and has determined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on July 5, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.
If you have any questions, please contact me at (301) 415-1445.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
RAI cc w/encl: See next page
July 19, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO REVISING THE FORT CALHOUN STATION UPDATED SAFETY ANALYSIS REPORT (TAC NO. MC8857)
Dear Mr. Ridenoure:
By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted an amendment request to revise the Fort Calhoun Station, Unit 1, Updated Safety Analysis Report for the radiological consequences of events affected by the planned 2006 replacement of the steam generators and pressurizer.
The U.S. Nuclear Regulatory Commission staff has reviewed OPPDs submittal and has determined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on July 5, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.
If you have any questions, please contact me at (301) 415-1445.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLIV R/F RidsOgcRp RidsRgn4MailCenter(DGraves)
RidsNrrLALFeizollahi RidsNrrPMAWang RidsAcrsAcnwMailCenter RidsNrrDorlLpl4 RidsNrrDorlDpr ADAMS ACCESSION NO.: ML061930417 OFFICE LPL4/PM LPL4/LA LPL4/BC NAME AWang LFeizollahi DTerao DATE 07/17/06 07/17/06 07/19/06 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION REGARDING UPDATED SAFETY ANALYSIS REPORT RADIOLOGICAL CONSEQUENCE ANALYSIS OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NUMBER 50-285 By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted an amendment request to revise the Fort Calhoun Station, Unit 1 (FCS), Updated Safety Analysis Report (USAR) for the radiological consequences of events affected by the planned 2006 replacement of the steam generator and pressurizer. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed OPPDs submittal and has determined that the following additional information is needed to complete our review:
- 1. The NRC staff notes that the atmospheric dispersion factors (/Q values) provided in the October 31, 2005, license amendment request (LAR) are the same as those approved in the safety evaluation associated with FCS Amendment No. 201. Amendment No. 201 implements use of the alternative source term in the FCS design-basis accident dose assessments. Therefore, for each design-basis accident or event addressed in the October 31, 2005, LAR, please discuss any differences between the two sets of release scenarios. If there are differences, please justify how the differences do not impact the applicability of the /Q values associated with Amendment No. 201 to the dose assessment associated with the October 31, 2005, LAR.
- 2. Which water mass inventories (both primary and secondary) were used in calculating coolant activities? Please indicate if the used values are the minimum, nominal or maximum.
- 3. The submitted S-RELAP5 analysis indicates 0 percent/0 percent fraction of failed/melted fuel. Is this a change from the analysis of record?
- 4. Attachment 4 (AREVA document 86-5064251-00) describes the thermal-hydraulic input in support of the consequence analysis. Please confirm that the main steam safety valves and atmospheric dump valves actuation setpoints used are those specified in the technical specifications.
- 5. Presumably, the cumulative steam releases used in the Attachment 6 (Stone & Webster report) came from the Attachment 4 (AREVA document). However, it is not immediately obvious which tables in Attachment 4 were used to generate Tables 7.6 - 7.9 in Attachment 6. Please clarify.
Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn Mr. Daniel K. McGhee ATTN: James R. Curtiss, Esq. Bureau of Radiological Health 1700 K Street, N.W. Iowa Department of Public Health Washington, DC 20006-3817 Lucas State Office Building, 5th Floor 321 East 12th Street Chairman Des Moines, IA 50319 Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550 April 2006
