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MONTHYEARML14041A4082014-02-10010 February 2014 License Amendment Request (LAR) 14-01, One-Time Extension of Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3 Project stage: Request LIC-14-0128, License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements2014-11-0707 November 2014 License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements Project stage: Request ML14311A6612014-11-10010 November 2014 FRN, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months Project stage: Other ML14311A6602014-11-10010 November 2014 Letter, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months Project stage: Other NRC-2014-0249, FRN, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months2014-11-10010 November 2014 FRN, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months Project stage: Approval ML14322A9262014-11-18018 November 2014 NRR E-mail Capture - RAIs for Urgent LAR for Fort Calhoun SRs That Expire Before the Spring RFO Project stage: RAI LIC-14-0131, Response to NRC Request for Additional Information Regarding License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements2014-11-21021 November 2014 Response to NRC Request for Additional Information Regarding License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements Project stage: Response to RAI ML14337A0892014-12-0202 December 2014 NRR E-mail Capture - OPPD Response to Technical Specification 3.7(1)c.ii Question Project stage: Request LIC-14-0135, Supplement to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements2014-12-10010 December 2014 Supplement to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements Project stage: Supplement ML14349A7912014-12-12012 December 2014 NRR E-mail Capture - Clarification Request from Technical Staff on FCS Supplement to License Amendment Request; One-Time Extension of Technical Specification Surveillance Requirements (MF5143) Project stage: Other ML14349A7922014-12-15015 December 2014 NRR E-mail Capture - Clarification Request from Technical Staff on FCS Supplement to License Amendment Request; One-Time Extension of Technical Specification Surveillance Requirements (MF5143) Project stage: Supplement ML14352A0132014-12-17017 December 2014 NRR E-mail Capture - Clarification Request from Technical Staff on FCS Supplement to License Amendment Request; One-Time Extension of Technical Specification Surveillance Requirements (MF5143) Project stage: Supplement ML14352A4242014-12-18018 December 2014 NRR E-mail Capture - One Last Question from Eeeb (MF5143) Project stage: Other LIC-14-0141, Update to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements2014-12-19019 December 2014 Update to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements Project stage: Request ML14356A0122014-12-29029 December 2014 Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months Project stage: Approval 2014-12-15
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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML21271A4982021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Ce-144 Soil Uncertainty Report ML21271A1932021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 18 Omaha Public Power District, FC-20-012, Fort Calhoun Station Decommissioning Project Radiological Character 1 ML21271A1962021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3, 1, Omaha Public Power District, Defueled Safety Analysis Report CAC 2 ML21271A1802021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 19, Omaha Public Power District, FC-20-012, Fort Calhoun Station Decommissioning Project Radiological Characterization Report ML21271A2102021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 4 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC 2 ML21271A1722021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 8 Omaha Public Power District, Offsite Dose Calculation Manual cac2 ML21271A1502021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Defueled Safety Analysis Report ML21271A4802021-08-0303 August 2021 License Amendment Request (LAR) 21-01, C-14 Soil Uncertainty Report ML21271A2652021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 7 FC-20-007, Fort Calhoun Station Potential Radionuclides of Concern CAC2 ML21271A2682021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 12 FC-20-006, Rev 0, End State Concrete Surface Areas Volumes, CAC2 ML21271A5032021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Ce-144 Soil Regression and Correlation Report ML21271A1442021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS LTP Rev 0. Final - All ML21271A5102021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Am-241 Soil Uncertainty Report ML21271A2582021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 8 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun -1 ML21271A2672021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC2 ML21271A2692021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 19 E. A. Napier, Hanford Environmental Dosimetry Upgrade Project, Gen II the Hanford Environmental Radiation D-1 ML21271A5992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2 ML21271A2612021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 1 Haley & Aldrich, Hydrogeological Conceptual Site Model, Rev. 2, Fort Calhoun Station, Blair, Ne, 2021 CAC2 ML21271A2192021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 12 FC-20-007, Fort Calhoun Station Potential Radionuclides of Concern CAC2 ML21271A2622021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 2 Radiation Safety and Control Services, Tsd 20-001, Historical Site Assessment for Fort Calhoun Station - F-1 ML21271A2142021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 17 Omaha Public Power District, NO-FC-10, Quality Assurance Topical Report CAC2 ML21271A2592021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Copy of Calculations in Support of FCS LTP Chapter 6 Revision 0 ML21271A1532021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 1 7 SUNSI EA 12-10, Flood Assessment HDR Report Placeholder Akb ML21271A4082021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Eu-152 ML21271A1992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 16 Omaha Public Power District, Offsite Dose Calculation Manual CAC 2 ML21271A1762021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 5 Omaha Public Power District, FCSD-RA-LT-200, Characterization Survey Plan CAC2 ML21271A2112021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 18 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan ML21271A2002021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 14 Backfill Attachment Final CAC 2 ML21271A1832021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 11 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report cac2 ML21271A1432021-08-0303 August 2021 License Amendment Request (LAR) 21-01, LIC-21-0005 LTP Cover Letter Final Fisher Signature ML21271A1732021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Omaha Public Power District, FCSD-RA-LT-100, Quality Assurance Project Plan for the License Termination Plan Development~1 ML21271A1752021-08-0202 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 14 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan ML21271A1982021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 3, 6, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2082021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 5, 10, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2602021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 6 4, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2132021-07-23023 July 2021 License Amendment Request (LAR) 21-01, Chapter 5 9 Oddp FC-20-006 - End State Concrete Surface Areas and Volumes Rev 0 CAC2 ML21271A2062021-07-23023 July 2021 License Amendment Request (LAR) 21-01, Chapter 4 10 Omaha Public Power District FC-20-006 - End State Concrete Surface Areas Volumes, Rev 0 CAC 2 ML21271A4452021-06-0505 June 2021 License Amendment Request (LAR) 21-01, FCS Embedded Pipe Dsr ML21271A2882021-06-0202 June 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Regression and Correlation Report Cm-244 ML21271A4362021-05-17017 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Pu-240 ML21271A3932021-05-16016 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Pu-240 ML21271A4062021-05-15015 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Cs-137 ML21271A4072021-05-15015 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Cs-137 ML21271A4142021-05-14014 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Np-237 ML21271A4392021-05-14014 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Cm-244 ML21271A4232021-05-14014 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Np-237 ML21271A3972021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Sb-125 ML21271A4012021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report H-3 ML21271A3942021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Fe-55 ML21271A4032021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Cm-243 2021-08-03
[Table view] Category:Technical Specifications
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML16084A7552016-04-0505 April 2016 Issuance of Amendment No. 287, Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using CLIIP ML15307A0132016-02-23023 February 2016 Issuance of Amendment No. 286, Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition ML15288A0052015-12-15015 December 2015 Issuance of Amendment No. 285, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors LIC-15-0076, License Amendment Request 15-06; Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2015-09-11011 September 2015 License Amendment Request 15-06; Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. LIC-15-0085, License Amendment Request 15-05; Application to Revise Technical Specification to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6B & 6C, Using the Consolidated Line Item.2015-09-11011 September 2015 License Amendment Request 15-05; Application to Revise Technical Specification to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6B & 6C, Using the Consolidated Line Item. LIC-15-0053, License Amendment Request (LAR) 15-04; Application to Revise Technical Specification for Administrative Changes2015-08-20020 August 2015 License Amendment Request (LAR) 15-04; Application to Revise Technical Specification for Administrative Changes ML15209A8022015-08-10010 August 2015 Issuance of Amendment No. 283, Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML15111A3992015-06-30030 June 2015 Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood ML15035A2032015-03-27027 March 2015 Issuance of Amendment No. 281, Revise Technical Specification 3.1, Table 3-3 to Correct Administrative Error in Surveillance Method for Containment Wide Range Radiation Monitors ML15015A4132015-02-20020 February 2015 Issuance of Amendment No. 280, Revise Technical Specification 3.2, Table 3-5 to Add New Surveillance Requirement ML14356A0122014-12-29029 December 2014 Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months ML14328A8142014-12-22022 December 2014 Issuance of Amendment No. 278, Revise Technical Specification 2.5, Auxiliary Feedwater (AFW) System to Allow 7-Day Completion Time for Turbine-Driven AFW Pump Based on TSTF-340, Revision 3 LIC-14-0128, License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements2014-11-0707 November 2014 License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements ML14279A2752014-11-0606 November 2014 Issuance of Amendment No. 277, Revise Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3, for One-Time Extension of Frequency to Maximum of 28 Months ML14209A0272014-08-0707 August 2014 Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis ML14098A0922014-06-16016 June 2014 Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML14115A2972014-04-10010 April 2014 Enclosure 1: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants ML14041A4082014-02-10010 February 2014 License Amendment Request (LAR) 14-01, One-Time Extension of Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3 ML14108A0442013-12-31031 December 2013 Omaha Public Power District Fort Calhoun Station Unit Radiological Environmental Operating Report for Technical Specification Section 5.94.b January 1, 2013 to December 31, 2013 ML14108A0422013-12-31031 December 2013 Omaha Public Power District Fort Calhoun Station Unit No. 1 - Annual Report for Technical Specification Section 5.94.a January 1, 2013 to December 31, 2013 ML12128A1702012-04-12012 April 2012 Technical Specification (TS) Basis Change Index, Page 2 of 2 and TS 2.10 - Page 18 LIC-12-0006, License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO)2012-02-10010 February 2012 License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO) LIC-12-0052, Annual Report for Technical Specification Section 5.9.4a2011-12-31031 December 2011 Annual Report for Technical Specification Section 5.9.4a LIC-10-0034, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c.2010-07-12012 July 2010 License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c. LIC-10-0043, Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication2010-06-0101 June 2010 Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication ML0935611192010-01-22022 January 2010 Correction to Amendment No. 263 Request to Add Steam Generator Blowdown Isolation Requirements to Technical Specifications ML0925405912009-10-0909 October 2009 License Amendment, Issuance of Amendment No. 263 Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip ML0912502752009-05-0505 May 2009 Replacement Page TS 2.1 - Page 8, License Amendment Request for Administrative Revisions ML0907108912009-03-27027 March 2009 License Amendment, Issuance of Amendment No. 258, Revise Limiting Condition for Operation 2.7(2)j in TS 2.7, Electrical Systems, to Clarify Allowed Outage Time for Emergency Diesel Generators ML0911703682009-02-18018 February 2009 Updated Tech Spec Pages, from Licensee, License Amendment Request Lic 08-0078, Administrative Revisions to the Technical Specifications to Correct Typographical Errors and Provide Clarification LIC-09-0008, License Amendment Request for Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-01-30030 January 2009 License Amendment Request for Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. LIC-08-0074, License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT)2008-07-31031 July 2008 License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT) LIC-08-0049, License Amendment Request (LAR) Clarification of Technical Specification (TS) 2.7(2)j, Regarding Emergency Diesel Generators Allowed Outage Time2008-04-22022 April 2008 License Amendment Request (LAR) Clarification of Technical Specification (TS) 2.7(2)j, Regarding Emergency Diesel Generators Allowed Outage Time LIC-08-0008, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.5(1)A, Auxiliary Feedwater (AFW) System.2008-02-0505 February 2008 License Amendment Request (LAR) Revision to Technical Specification (TS) 2.5(1)A, Auxiliary Feedwater (AFW) System. LIC-07-0084, License Amendment Request, Change to Diesel Generator Surveillance Testing.2007-10-0505 October 2007 License Amendment Request, Change to Diesel Generator Surveillance Testing. LIC-07-0082, License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent.2007-09-11011 September 2007 License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent. LIC-07-0046, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-05-16016 May 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707100982007-04-0303 April 2007 Technical Specifications, Editorial Changes to Apply Certain Limiting Conditions for Operation Requirements ML0705905082007-02-28028 February 2007 License and Technical Specification Pages - Amendment No. 248 to Facility Operating License Relocation of T.S. 2.22, Toxic Gas Monitors, and T.S. Table 3-3, Item 29 to Updated Safety Analysis Report LIC-06-0146, License Amendment Request, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Purge System Using the Consolidated Line Item Improvement Process.2006-12-20020 December 2006 License Amendment Request, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Purge System Using the Consolidated Line Item Improvement Process. LIC-06-0147, License Amendment Request for Administrative Revisions to Fort Calhoun Station, Unit No. 1 Technical Specifications2006-12-20020 December 2006 License Amendment Request for Administrative Revisions to Fort Calhoun Station, Unit No. 1 Technical Specifications ML0631105582006-11-0707 November 2006 Technical Specifications, Revising TS Steam Generator Tube Suveillance Program ML0631202592006-10-27027 October 2006 Tech Spec Pages for Amendment 244 Modifications to Technical Specification 2.4, Containment Cooling to Reduce Operable Containment Spray Pumps ML0628604282006-10-10010 October 2006 Response to Request for Additional Information (RAI) Related to the Replacement of Trisodium Phosphate ML0624201602006-08-30030 August 2006 Tech Spec Pages for Amendment 241 Regarding Use of M5 Fuel Cladding ML0624304022006-08-30030 August 2006 Revised License Amendment Request, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Deletion of Sleeving as a Steam Generator.. ML0624301302006-06-27027 June 2006 Tech Spec Pages for Amendment 240 Deletion of Design Features in Technical Specifications 4.3.1.2b and 4.3.1.2c LIC-06-0063, Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements.2006-06-0202 June 2006 Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements. 2024-01-31
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Omaha Public Power Oistrict 444 South 1e h Street Mall Omaha, NE 68102-2247 10 CFR 50.90 LlC-14-0011 February 10, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No.1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285
SUBJECT:
License Amendment Request (LAR) 14-01 , One-Time Extension of Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3 Pursuant to 10 CFR 50.90, the Omaha Public Power District (OPPD) hereby requests an amendment to the Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station (FCS), Unit No.1. The proposed amendment would allow a one-time extension of the surveillance frequency for the pressurizer safety valves from a refueling frequency (Le., 18 months +25%) to a maximum of 28 months.
The proposed change is necessary due to the extended shutdown of Fort Calhoun Station for the refueling outage that commenced in April 2011. Testing of the safety valves is performed by shipping the valves offsite to a vendor facility. The last performance of the test was completed on January 14, 2013. Due to the extended shutdown, the valves will be required to be tested prior to the next scheduled refueling outage of April 13, 2015. These components are the only components that will not meet the required refueling frequency due to the extended outage and cannot be performed while the Unit is at power.
OPPD has determined that this LAR does not involve a significant hazard consideration as determined per 10 CFR 50.92. Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of this amendment.
The enclosure contains a description of the proposed changes, the supporting technical analyses, and the significant hazards consideration determination. Attachment 1 of the enclosure provides the existing TS pages marked-up to show the proposed changes.
Attachment 2 of the enclosure provides the retyped (clean) TS pages.
OPPD requests approval of the proposed amendment by November 1, 2014. Once approved, the amendment shall be implemented upon issuance.
Employment with Equal Opportunity
U. S. Nuclear Regulatory Commission LlC-14-0011 Page 2 There are no regulatory commitments associated with this proposed change.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated State of Nebraska official.
If you should have any questions regarding this submittal or require additional information, please contact Mr. Bill R. Hansher at (402) 533-6894.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 10, 2014.
Louis P. Cortopassi Site Vice President and CNO LPC/brh
Enclosure:
OPPD's Evaluation of the Proposed Change c: M. L. Dapas, NRC Regional Administrator, Region IV J. W. Sebrosky, NRC Senior Project Manager J. C. Kirkland, NRC Senior Resident Inspector Director of Consumer Health Services, Department of Regulation and Licensure, Nebraska Health and Human Services, State of Nebraska
LlC-14-0011 Enclosure Page 1 OPPD's Evaluation of the Proposed Change License Amendment Request (LAR) 14-01, One-Time Extension of Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 Significant Hazards Consideration 4.4 Conclusions 5.0 ENVIRONMENTAL-CONSIDERATION
6.0 REFERENCES
ATTACHMENTS:
- 1. Technical Specification Page Markups
- 2. Retyped ("Clean") Technical Specifications Pages
LlC-14-0011 Enclosure Page 2 1.0
SUMMARY
DESCRIPTION License amendment request (LAR) 14-01 proposes a change to the Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station (FCS), Unit No.1. The Omaha Public Power District (OPPD) proposes to allow a one-time extension of the surveillance frequency for the pressurizer safety valves from a refueling frequency (Le., 18 months +25%) to a maximum of 28 months.
2.0 DETAILED DESCRIPTION The proposed TS changes for LAR 14-01 are as follows:
SR 3.2. Table 3-5. Item 3 Add footnote "During PLANT OPERATING CYCLE 27 only, in lieu of the Technical Specification specified refueling frequency and 4.5 month grace period allowance, the maximum allowed surveillance test interval shall not exceed 28 months."
Plant Operating Cycle is a defined term in the FCS Unit No. 1 Technical Specifications and is defined as, The time period from a REFUELING SHUTDOWN to the next REFUELING SHUTDOWN."
3.0 TECHNICAL EVALUATION
The Fort Calhoun Station, Unit No.1 (FCS) has two installed pressurizer safety valves. Technical Specification 3.2, Table 3-5, Item 3, requires that the pressurizer safety valves be tested to "Verify each pressurizer safety valve is OPERABLE in accordance with the Inservice Testing Program.
Following testing, lift settings shall be 2485 psig +/-1% and 2530 psig +/-1% respectively." The table specifies a frequency of "R", designating a "Refueling" interval.
The FCS Inservice Testing Program is based on the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), 1998 Edition, through 2000 Addenda. Appendix I of the ASME OM Code specifies frequency requirements for testing of pressure relief valves. Requirements applicable to the Fort Calhoun Station pressurizer safety valves appear in Section 1-1330, Test Frequencies, Class 1 Pressure Relief Valves. This section specifies that the test interval for any individual valve shall not exceed 5-years. In addition, it indicates that at least 20% of the valves from each valve group shall be tested within any 24-month interval. Testing requirements may be satisfied by installing pre-tested valves if certain additional requirements are met regarding testing of the removed valves.
Both FCS pressurizer safety valves were removed from service in April 2011 at the end of the last operating cycle (i.e., Operating Cycle 26). At that time, both valves were tested and found to open within the lift settings specified in TS 2.1.6(1} (Le., 2485 psig +1%/-3% and 2530 psig +1%/-
3% respectively). In January 2013, in anticipation of plant restart in 2013, the two pressurizer safety valves that had been removed and tested in April 2011 were re-tested. The as-left lift settings for these two valves were demonstrated by testing at a vendor facility on January 14, 2013, and January 15, 2013 respectively. The lift settings of both valves were within a tolerance of +/-1 % of setpoint, as discussed in the TS 2.1.6 Basis. These pre-tested replacement valves were subsequently installed and are now inservice.
The proposed one-time frequency change would allow performance of the next valve tests during the next scheduled refueling outage that is scheduled to begin April 13, 2015. Technical Specification 2.1.6(1}, requires two pressurizer safety valves to be operable in Modes 1 and 2.
The valves were required to be operable beginning in December 2013, when the plant was first
LlC-14-0011 Enclosure Page 3 returned to Mode 2 after the extended plant shutdown. With the proposed one-time frequency change, the period during which the valves are required to be operable will be less than 18 months (i.e., from December 2013 to April 2015). Therefore, the period of required operability will be no longer than a typical operating cycle. Also, the time interval between tests with the proposed frequency change remains well within the maximum 5-year test interval for any individual valve as specified by the ASME Code and Inservice Testing Program.
As the valves are sent offsite to a vendor facility, the setpoints were last set in January 2013 with the expectation of startup from the refueling outage in the spring of 2013; therefore, the need for this extension was not expected.
4.0 REGULATORY EVALUATION
4.1 Applicable Requlatory Requirements/Criteria 4.1.1 Regulations Code of Federal Regulations 10 CFR Part 50.55a Codes and Standards 4.1.2 Design Basis As stated in USAR Section 4.3.10, two safety valves located on the pressurizer provide overpressure protection for the reactor coolant system. They are totally enclosed, backpressure-compensated, spring-loaded safety valves meeting ASME Code requirements.
4.1.3 Approved Methodologies The approved testing methods as contained in the Inservice Testing Program are:
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition (ASME OM Code - 1998), through 2000 Addenda ASME SECTION XI, 1989 Edition, Requirements for Inservice Performance Testing of Nuclear Power Plant Pressure Relief Devices and the ASME/ANSI O&M Manual, Part 1, 1987 Edition 4.1.4 Analysis No analyses were conducted in support of the proposed amendment.
4.2 Precedent A number of plants have previously submitted LARs for extension of surveillance intervals due to extended refueling outages. Recently approved and/or submitted applications include the following:
LlC-14-0011 Enclosure Page 4 4.2.1 License Amendment Request (LAR 2008-08) Surveillance Frequency Extension Request, River Bend Station, Unit 1, dated December 8, 2008 (Reference 6.1).
4.2.2 River Bend Station, Unit 1 - Issuance of Amendment 162 Re: One-time Surveillance Interval Extension (TAC No. ME0215), dated April 1, 2009 (Reference 6.2).
4.2.3 License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d, Turkey Point Unit 3, dated March 8, 2013 (Reference 6.3).
4.3 Significant Hazards Consideration The proposed change would allow a one-time extension of the surveillance frequency for the pressurizer safety valves from refueling frequency (18 months +25%) to a maximum of 28 months.
The Omaha Public Power District (OPPD) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The requested change is a one-time extension to the performance interval of one TS surveillance requirement. The performance of the surveillance, or the failure to perform the surveillance, is not a precursor to an accident. Performing the surveillance or failing to perform the surveillance does not affect the probability of an accident. Even with the requested extension, the period during which the plant is in Modes 1 or 2 and the valves are required to be operable will be no longer than a typical operating cycle. Also, the proposed interval between tests will remain well within the maximum 5-year test interval for this type of valve specified by the American Society of Mechanical Engineers (ASME)
Code for Operation and Maintenance of Nuclear Power Plants (OM Code), 1998 Edition, through 2000 Addenda, Appendix I, frequency requirements for testing of pressure relief valves.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not alter the physical design, safety limits, or safety analysis assumptions associated with the operation of the plant. Hence, the proposed change does not introduce any new accident initiators, nor does it reduce or adversely affect the capabilities of any plant structure or system in the performance of their safety function.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
LlC-14-0011 Enclosure Page 5
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed change is a one-time extension of the periormance interval for one surveillance requirement. Even with the proposed change in interval, the extended interval remains well within the maximum 5-year test interval for this type of valve specified by the ASME OM Code, 1998 Edition, through 2000 Addenda. Also, the period during which the plant is in Modes 1 or 2 and the valves are required to be operable will be no longer than a typical operating cycle. This change does not alter any safety margins.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, OPPD concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.4 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a Significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
6.1 Letter from Entergy (J. C. Roberts) to NRC (Document Control Desk) ,"License Amendment Request (LAR 2008-08) Surveillance Frequency Extension Request, River Bend Station - Unit 1," dated December 8, 2008 (ML083460043) 6.2 Letter from NRC (C. F. Lyon) to Entergy (Vice President, Operations),"River Bend Station, Unit 1 - Issuance of Amendment Re: One-time Surveillance Interval Extension (TAC No.
ME0215)," dated April 1, 2009 (ML090270163) 6.3 Letter from Florida Power & Light (M. Kiley) to NRC (Document Control Desk), "License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d," dated March 8, 2013 (ML13071A469)
LlC-14-0011 Enclosure, Attachment 1 Page 1 Technical Specification Page Markups
[Word-processor mark-ups using "double underline/strJkool:Jt" feature for "new text/deleted text" respectively.]
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test Frequency Reference
- 1. Control Element Drop times of all full-length CEA's Prior to reactor criticality after each 7.5.3 Assemblies removal of the reactor vessel closure head
- 2. Control Element Partial movement of all CEA's Q 7 Assemblies (Minimum of 6 in)
- 3. Pressurizer Safety Verify each Bressurizer safety valve Rill 7 Valves is OPERAS E in accordance with the Inservice Testing Program.
Following testin~, liff settings shall be 2485 psig +/-1 Yo and 2530 psig +/-1%
respectively.
- 4. Main Steam Safety Set Point R 4 Valves
- 5. DELETED
- 6. DELETED
- 7. DELETED 8a. Reactor Coolant Evaluate D* 4 System Leakage***
8b. Primary to Secondary Continuous process D* 4 Leakage **** radiation monitors or radiochemical grab sampling 9a Diesel Fuel Supply Fuel Inventory M 8.4 9b. Diesel Lubricating Oil Lube Oil Inventory M 8.4 Inventory 9c. Diesel Fuel Oil Test Properties In accordance with the Diesel Fuel 8.4 Properties Oil Testing Program 9d. Required Diesel Air Pressure M 8.4 Generator Air Start Receiver Sank Pressure 3.2 - Page 8 Amendment No. 16,24,128.160.166.169.171.219.229.
246, 2e7
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS
- Whenever the system is at or above operating temperature and pressure.
- Not applicable to primary to secondary LEAKAGE.
- Verify primary to secondary LEAKAGE is:S; 150 gallons per day through anyone SG.
This surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
(1) During PLANT OPERATING CYCLE 27. in lieu of the Technical Specification specified 18 month refueling frequency and 4.5 month grace period allowance. the maximum allowed surveillance test interyal will be extended to no more than 28 months.
3.2 - Page 9 Amendment No. ~, aa7
LlC-14-0011 Enclosure, Attachment 2 Page 1 Retyped ("Clean") Technical Specification Pages
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test Frequency Reference
- 1. Control Element Drop times of all full-length CEA's Prior to reactor criticality after each 7.5.3 Assemblies removal of the reactor vessel closure head
- 2. Control Element Partial movement of all CEA's Q 7 Assemblies (Minimum of 6 in)
Verify each pressurizer safety valve R(1) 7
- 3. Pressurizer Safety Valves is OPERABLE in accordance with the Inservice Testing Program.
Following testin~, lift settings shall be 2485 psig +/-1 Yo and 2530 psig +/-1%
respectively.
- 4. Main Steam Safety Set Point R 4 Valves
- 5. DELETED
- 6. DELETED
- 7. DELETED 8a. Reactor Coolant Evaluate D* 4 System Leakage***
8b. Primary to Secondary Continuous process D* 4 Leakage **** radiation monitors or radiochemical grab sampling 9a Diesel Fuel Supply Fuel Inventory M 8.4 9b. Diesel Lubricating Oil Lube Oil Inventory M 8.4 Inventory 9c. Diesel Fuel Oil Test Properties In accordance with the Diesel Fuel 8.4 Properties Oil Testing Program 9d. Required Diesel Air Pressure M 8.4 Generator Air Start Receiver Bank Pressure 3.2 - Page 8 ~, ~
Amendment No . 16,24,128.160.166.169.171.219. 229.
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS
- Whenever the system is at or above operating temperature and pressure.
- Not applicable to primary to secondary LEAKAGE.
- Verify primary to secondary LEAKAGE is::; 150 gallons per day through anyone SG.
This surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
(1) During PLANT OPERATING CYCLE 27, in lieu of the Technical Specification specified 18 month refueling frequency and 4.5 month grace period allowance, the maximum allowed surveillance test interval will be extended to no more than 28 months.
3.2 - Page 9 Amendment No. 246, 2&7