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Category:Code Relief or Alternative
MONTHYEARML16104A0742016-04-15015 April 2016 Relief Request, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI, Fourth 10-Year Inservice Inspection Interval ML16041A3082016-02-19019 February 2016 Relief Requests P-1 - LPSI and CS Pumps; P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21; G-1 - Test Frequency Consistent W/Code Case OMN-20, Fifth 10-Year Inservice Testing Interval LIC-15-0114, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI2015-11-24024 November 2015 Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI LIC-15-0089, Submits Relief Requests Associated with the Fifth Inservice Testing Interval2015-08-27027 August 2015 Submits Relief Requests Associated with the Fifth Inservice Testing Interval ML15232A0032015-08-21021 August 2015 Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval LIC-15-0086, Supplement to License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section III, 1980 Edition (No Addenda) as an Alternative to Current Code of Record2015-07-0202 July 2015 Supplement to License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section III, 1980 Edition (No Addenda) as an Alternative to Current Code of Record ML15139A0102015-05-26026 May 2015 Summary of 5/17/15 Telephone Call, Verbal Authorization of Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, 4th 10-Year Inservice Inspection Interval LIC-15-0066, Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds2015-05-0909 May 2015 Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds ML14323A5992014-12-0202 December 2014 Relief Request RR-13, Relief from Inservice Testing Requirements to Perform Testing of 4 Valves During the April 2015 Refueling Outage ML14316A1672014-11-19019 November 2014 Relief Request RR-14, Proposed Alternative for Temporary Acceptance of a Pin Hole Leak in Raw Water System 20-Inch Elbow Located in Room 19 of Auxiliary Building ML1022101332010-08-20020 August 2010 Request for Use of Alternative to Depth-Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds for 4th 10-year Inservice Inspection Interval ML0712300902007-04-27027 April 2007 Part 21 Interim Report, Dresser Investigation File No. 2007-02, Interim Reporting of a Potential Defect Involving Power Actuated Pressure Relief Valves Supplied to Calvert Cliffs, Fort Calhoun and Oconee Plants ML0634504072007-01-0505 January 2007 Request for Relief Use of Later Edition and Addenda of ASME Code for Examination of Cast Austenitic Stainless Steel Piping ML0609701242006-04-0606 April 2006 Relief E-2, 4-th 10-year Pump and Valve Inservice Testing Program ML0519600742005-10-0303 October 2005 Relief Request - Alternative Test Requirements for Containment Repairs ML0514407352005-05-24024 May 2005 5/24/05 Fort Calhoun - Relaxation Request from U.S. NRC Order EA-03-009 for the Control Element Drive Mechanism Nozzles ML0501203572005-02-28028 February 2005 Request for Relief from ASME Code Repair Requirements and Using an Alternative for the Pressurizer Nozzle Repair. LIC-04-0008, Relief Request Pertaining to Reactor Vessel Nozzle Inspections for the Third 10-Year Interval, Revision2004-04-0202 April 2004 Relief Request Pertaining to Reactor Vessel Nozzle Inspections for the Third 10-Year Interval, Revision ML0326000132003-09-12012 September 2003 Relief Request - Third and Fourth 10-Year Interval Inservice Inspection Program Plan - Request for Relief RR-8 LIC-03-0062, Relief Request Pertaining to Visual Inspection of Inaccessible Piping & Components2003-05-0101 May 2003 Relief Request Pertaining to Visual Inspection of Inaccessible Piping & Components LIC-02-0142, Relief Requests Pertaining to the Fort Calhoun Inservice Inspection (ISI) of the Reactor Pressure Vessel (RPV) for the Third Ten Year ISI Interval (1993-2003)2002-12-20020 December 2002 Relief Requests Pertaining to the Fort Calhoun Inservice Inspection (ISI) of the Reactor Pressure Vessel (RPV) for the Third Ten Year ISI Interval (1993-2003) 2016-04-15
[Table view] Category:Letter
MONTHYEARIR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 LIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) ML24255A0962024-09-12012 September 2024 License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285) IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 ML24235A0822024-08-10010 August 2024 Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024 ML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter ML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24079A1702024-03-10010 March 2024 ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML24019A1672024-01-31031 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 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 IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 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 Commissions Analysis of Omaha Public Power Districts 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 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, 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 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 2024-09-18
[Table view] Category:Safety Evaluation
MONTHYEARML24019A1682024-01-31031 January 2024 Safety Evaluation Report for Approval of License Termination Plan 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 ML20056E4872020-02-26026 February 2020 Staff Review of Fort Calhoun Independent Spent Fuel Storage Installation Physical Security Plan, Security Training and Qualification Plan, and Safeguard Contingency Plan, Revision 0 and the Verification of Additional Security Measures (ASM) ML19297D6742019-12-0909 December 2019 FCS ISFSI Only Tech Specs SER ML18017B0052018-03-30030 March 2018 Review of the Irradiated Fuel Management Plan (CAC No. MF9553; EPID L-2017-LLL-0009) ML18047A6612018-03-28028 March 2018 Issuance of Amendment No. 298, Request to Modify License Condition 3.C to Delete Requirement for Commission-Approved Cyber Security Plan (CAC No. MF9850; EPID L-2017-LLA-0236) ML18010A0872018-03-0606 March 2018 Issuance of Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML17338A1722018-01-19019 January 2018 Issuance of Amendment No. 296, Revise Technical Specifications (TS) to Delete Dry Spent Fuel Cask Loading Limits from TS 3.8.3(6), Figure 2-11, Table 3-4, Table 3-5, and TS 4.3.1.3 (CAC No. MF9831; EPID L-2017-LLA-0235) ML17276B2862017-12-12012 December 2017 Issuance of Amendment No. 295, Revise the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MF8951; EPID L-2016-LLA-0036) ML17263B1982017-12-11011 December 2017 Letter and Safety Evaluation, Request for Exemption from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition (CAC MF9067; EPID L-2016-LLE-0003) ML17289A0602017-11-22022 November 2017 Issuance of Amendment No. 294, Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9559; EPID L-2017-LLA-0184) ML17275A2642017-11-21021 November 2017 Safety Evaluation Input on Fort Calhoun Station Request for Approval of Permanently Defueled Emergency Plan and Emergency Action Level Scheme, Docket No. 50-285 ML17278A6072017-11-17017 November 2017 Issuance of Amendment No. 293, Request to Revise Current Licensing Basis for the Auxiliary Building to Use American Concrete Institute Ultimate Strength Requirements (CAC No. MF8525; EPID L-2016-LLA-0013) ML17165A4652017-07-28028 July 2017 Fort Calhoun Station, Unit 1 - Issuance of Amendment No. 292, Revise Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (CAC No. MF8437) ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML17144A2462017-06-21021 June 2017 Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management ML17053A0992017-04-0707 April 2017 Issuance of Amendment No. 290, Request to Delete License Condition 3.D., Fire Protection Program, No Longer Needed for Permanently Shutdown and Defueled Condition ML16141A7392016-05-27027 May 2016 Safety Evaluation, Review of Aging Management Program of Reactor Vessel Internals Based on MRP-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines ML16104A0742016-04-15015 April 2016 Relief Request, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI, Fourth 10-Year Inservice Inspection Interval 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 ML16041A3082016-02-19019 February 2016 Relief Requests P-1 - LPSI and CS Pumps; P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21; G-1 - Test Frequency Consistent W/Code Case OMN-20, Fifth 10-Year Inservice Testing Interval 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 ML15294A2792015-11-19019 November 2015 Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15232A0032015-08-21021 August 2015 Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval 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 ML14323A5992014-12-0202 December 2014 Relief Request RR-13, Relief from Inservice Testing Requirements to Perform Testing of 4 Valves During the April 2015 Refueling Outage ML14316A1672014-11-19019 November 2014 Relief Request RR-14, Proposed Alternative for Temporary Acceptance of a Pin Hole Leak in Raw Water System 20-Inch Elbow Located in Room 19 of Auxiliary Building 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) ML14003A0032014-01-28028 January 2014 Issuance of Amendment No. 274, Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13296A5842013-10-25025 October 2013 Issuance of Amendment No. 273, Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks (Exigent Circumstances) ML13203A0702013-07-26026 July 2013 Issuance of Amendment No. 272 - Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact (Exigent Circumstances) ML13141A6082013-06-25025 June 2013 Safety Assessment in Response to Request for Information Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13070A0422013-03-29029 March 2013 Issuance of Amendment No. 271, Relocate Technical Specification LCO 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report ML13043A6612013-02-28028 February 2013 Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits ML13017A4672013-01-31031 January 2013 Approval of Request for Change to the Reactor Vessel Surveillance Capsule Removal Schedule ML12333A1192012-12-31031 December 2012 Issuance of Amendment No. 269, Incorporate New Radial Peaking Factor Definition and Clarify Limiting Condition for Operation (LCO) 2.10.2(6) ML1126204022011-09-30030 September 2011 Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications ML1118615712011-08-31031 August 2011 Issuance of Amendment No. 267, Revise Technical Specification (TS) 2.15 and TS 3.1 Related to Operability of Secondary Control Element Assembly Position Indication System Channels; Correction to TS 2.10.2(7)c ML1122702902011-08-18018 August 2011 Relief Request RR-12 from Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Fourth 10-Year Inservice Inspection Interval ML1118010942011-07-27027 July 2011 Issuance of Amendment No. 266, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1022101332010-08-20020 August 2010 Request for Use of Alternative to Depth-Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds for 4th 10-year Inservice Inspection Interval ML1009100772010-05-14014 May 2010 License Amendment, 264, Revision of Tech Spec Sections 2.0.1 and 2.7 for Inoperable System, Subsystem, or Component Due to Inoperable Power Source and Deletion of Diesel Generator Surveillance Requirement 3.7(1)e 2024-01-31
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 19, 2014 Mr. Louis P. Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station 9610 Power Lane, Mail Stop FC-2-4 Omaha, NE 68008
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 -RELIEF REQUEST RR-14, PROPOSED ALTERNATIVE, TEMPORARY ACCEPTANCE OF A PINHOLE LEAK IN RAW WATER SYSTEM PIPING ELBOW (TAC NO. MF4643)
Dear Mr. Cortopassi:
By letter dated August 15, 2014, as supplemented by letter dated August 19, 2014, Omaha Public Power District (OPPD, the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Section XI, IWD-3120(b), at Fort Calhoun Station, Unit No. 1 (FCS). Pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(ii), the licensee submitted Relief Request RR-14, which proposed to use an alternative methodology to ASME Code Case N-513-3 to disposition a pinhole leak in lieu of immediately performing a repair on a leaking elbow of the raw water system piping, on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii). Therefore, the NRC authorizes the use of Relief Request RR-14 at FCS until September 5, 2014, or the predicted flaw size from periodic inspection exceeds the acceptance criteria, whichever occurs first.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
L. Cortopassi The NRC staff provided verbal authorization for Relief Request RR-14 during a teleconference with your staff on August 15, 2014. Your staff repaired the pinhole leak on August 15, 2014, in accordance with Work Order 00528986. If you have any questions, please contact Fred Lyon at 301-415-2296 or via e-mail at Fred. Lyon@nrc.gov.
Sincerely, Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST RR-14 FOR TEMPORARY ACCEPTANCE OF A PINHOLE LEAK IN A RAW WATER SYSTEM PIPING ELBOW OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285
1.0 INTRODUCTION
By letter dated August 15, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14230A157), and supplement dated August 19, 2014 (ADAMS Accession No. ML14231B310), Omaha Public Power District (OPPD, the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWD-3120(b), at Fort Calhoun Station, Unit No. 1 (FCS). The proposed alternative is documented in Relief Request RR-14 for the temporary acceptance of a pinhole in an elbow of the raw water (RW) system piping.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(ii),
the licensee requested the temporary use of modified ASME Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping,Section XI, Division 1 ," to disposition the pinhole on the basis that complying with the specified ASME Code requirement to repair the degraded elbow would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
On August 15, 2014, the U.S. Nuclear Regulatory Commission (NRC) staff verbally authorized the use of Relief Request RR-14 at FCS (ADAMS Accession No. ML14230A080) until September 5, 2014, or when the leakage flaw size exceeds the allowable flaw size, whichever occurs first. This safety evaluation documents the NRC staffs technical basis for the verbal authorization.
2.0 REGULATORY EVALUATION
In the Relief Request, the licensee requests authorization of an alternative to the requirements of article IWD-3120(d) of Section XI of the ASME Code pursuant to 10 CFR 50.55a(a)(3)(ii).
Enclosure
Article IWD-3120(b) of the ASME Code,Section XI, requires that unacceptable flaws in ASME Code Class 3 components be corrected by repair or replacement activity or be accepted by supplemental examination and flaw evaluation, to the extent necessary to meet the acceptance standards in ASME Code,Section XI, Article IWD-3000, which refers to the requirements of IWC-3000.
Adherence to Section XI of the ASME Code is mandated by 10 CFR 50.55a(g)(4), which states, in part, that ASME Code Class 1, 2, and 3 components (including supports) will meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI.
The regulations in 10 CFR 50.55a(a)(3) state, in part, that alternatives to the requirements of paragraph (g) of 10 CFR 50.55a may be used, when authorized by the NRC, if the licensee demonstrates that: (i) the proposed alternative provides an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request the use of an alternative and the NRC to authorize the proposed alternative.
3.0 TECHNICAL EVALUATION
3.1 Relief Request RR-14 3.2 ASME Code Component Affected The affected component is an ASME Code, Class 3, 90 degree Elbow in the 20-inch East Raw Water Header, piping class 152, with a wall thickness of 3/8 inches. The design Code is [USAS]
831.7 Class 1. The design pressure is 150 pounds per square inch and design temperature is 500 degrees Fahrenheit.
3.3 Applicable Code Edition and Addenda FCS is currently in the fourth 10-year inservice inspection (lSI) interval, which ends on June 6, 2016. The Code of record for the fourth 10-year lSI interval is the ASME Code, 1998 Edition through 2000 Addenda.
3.4 Applicable Code Requirement ASME Code,Section XI, IWD-3120(b) requires that components exceeding the acceptance standards of IWD-3400 be subject to supplemental examination, or to a repair/replacement activity.
3.5 Reason for Request On August 14, 2014, the licensee identified a leak in an elbow on the east raw water (RW) piping in Room 19 of the auxiliary building. The leak required the plant entry into Technical Specification (TS) 2.4(2)d. The licensee reported that the pinhole leak was approximately 600 milliliters (ml) per hour on the inside of the elbow towards the middle of the pipe. The licensee performed an UT of the area around the pinhole and found no additional areas of significant pipe wall thinning. On August 15, 2014, the licensee reported that the leak rate had increased to 1100 ml/hour.
The licensee stated that performing an ASME Code repair or replacement activity to correct the pinhole in the RW elbow would require the plant to shut down (i.e., entry into a 24-hour hot shutdown TS requirement) and create a hardship based on the potential risks associated with unit cycling and emergent equipment issues incurred during shutdown and startup evolutions.
The licensee further stated that no compensating increase in the level of quality and safety would be gained by immediate repair of the flaw because the RW system continues to be capable of performing its required safety functions and is not susceptible to sudden or catastrophic failure.
Article IWD-3500 of the ASME Code,Section XI, establishes flaw size acceptance standards and IWD-3600 provides analytical evaluation criteria for flaws identified during performance of in-service inspections and tests. The licensee noted that the ASME Code does not include analytical evaluation criteria for acceptance of 100 percent through-wall flaws in pressure retaining base material offerritic pipe or fittings. NRC Regulatory Guide 1.147, Revision 17, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1,"August 2014 (ADAMS Accession No. ML13339A689), conditionally approves ASME Code Case N-513-3 which provides analytical evaluation rules for temporary acceptance of 100 percent through-wall flaws in piping. The licensee noted that Code Case N-513-3 does not apply to through-wall flaws located in elbows.
3.6 Proposed Alternative and Basis for Use In lieu of repair or replacing the degraded elbow, the licensee proposed to use Code Case N-513-3 to disposition the pinhole in the subject elbow. However, the licensee proposes to deviate from paragraph 1(c) of Code Case N-513-3 that prohibits its application to pipe elbows. Instead, the licensee proposed to use the methodology in a pending revision to Code Case N-513-3 (i.e., N-513-4) to evaluate and disposition the flaw in the subject elbow. Code Case N-513-4 includes rules for the evaluation of piping components such as elbows, branch tees, and reducers. Flaws in an elbow may be evaluated per N-513-4 as if in a straight pipe provided that the stresses used in the evaluation are adjusted to account for geometric differences. For elbows, hoop stress is adjusted by considering flaw location and primary stress due to elbow ovalization from axial loads. For axial stresses, the stress scaling follows the same approach given in ASME Code, Section Ill, ND-3600 using stress indices and stress intensification factors for the adjustment.
Using the methodology in Code Case N-513-4, the licensee calculated allowable flaw sizes of 10 inches in the circumferential direction and 4 inches in the axial direction. The licensee also determined that the 100 percent through-wall flaw is stable and the pipe will not fail catastrophically under design loading conditions.
As part of the proposed alternative, the licensee will perform the following actions:
- The licensee will perform a daily visual walk down and measure leakage from the RW elbow, with the insulation removed, to confirm that the analysis supported by UT examinations remains valid (i.e., no new significant leakage).
- The licensee will examine a sample size of at least five of the most susceptible and accessible locations, or, if fewer than five, all susceptible and accessible locations within 30 days of detecting the flaw in accordance with the requirements (including scope expansion) of Code Case N-513-3.
- The licensee will repair the RW elbow no later than when either the predicted flaw size from periodic inspection exceeds the acceptance criteria, or by September 5, 2014.
3.7 Duration of Proposed Alternative The licensee stated that the relief request will be used until ASME Code repair activities are performed on the RW elbow which will be completed by September 5, 2014.
4.0 NRC Staff Evaluation The NRC staff reviewed the licensee's flaw evaluation, monitoring of the flaw, extent of condition, and hardship to determine the structural integrity of the subject elbow for the duration between August 14, 2014, when the leak was identified and September 5, 2014, when the elbow is repaired.
The NRC staff has not approved Code Case N-513-4 in Regulatory Guide 1.147. Therefore, the NRC staff evaluated the proposed alternative based on Code Case N-513-3 and the flaw calculation methodology of the ASME Code,Section XI, Appendix C.
Flaw Evaluation The licensee modeled the pinhole as a planar flaw and performed a linear-elastic fracture mechanics calculation to demonstrate the structural integrity of the degraded elbow. Using the stress intensity factor of the flaw and the pipe material, the licensee has demonstrated that the pipe material has sufficient toughness to resist the flaw to propagate suddenly and in an unstable manner. Based on its independent calculations, the NRC staff verified that the allowable flaw size of 10 inches in the circumferential direction and 4 inches in the axial direction are acceptable and that the flaw will not propagate uncontrollably.
The licensee measured wall thickness of the degraded elbow extensively. Based on an independent calculation, the NRC staff verified that the elbow, except at the pinhole area, satisfies the minimum required wall thickness in accordance with the ASME Code, Section Ill, ND-3640.
The NRC staff concludes that the licensee has demonstrated by analysis that the pinhole will not challenge the structural integrity of the elbow during the effective period of the relief request.
In addition, the licensee will monitor the degraded area of the elbow periodically as discussed below to provide additional assurance of the structural integrity of the elbow.
Monitoring of the Flaw The licensee has not requested deviation from and, therefore, will follow the monitoring requirements of Code Case N-513-3. The licensee stated that it will monitor the pinhole in a daily walk-down, consistent with Paragraph 2(f) of N-513-3, to confirm the analysis conditions used in the evaluation. Should the pinhole size grow, Paragraph 2(g) of N-513-3 requires a repair or replacement be performed.
Paragraph 2( e) of N-513-3 requires that periodic inspections of no more than 30 day intervals be performed to determine if flaws are growing. However, as the leak was discovered on August 12, 2014 and the elbow will be repaired at the latest on September 5, 2014, the duration of the leakage is less than 30 days. Therefore, paragraph 2(e) of N-513-3 is not applicable.
The NRC staff concludes that the flaw evaluation and the daily monitoring of the flaw will provide reasonable assurance of the structural integrity of the degraded elbow.
Extent of Condition The licensee will examine a sample size of at least five of the most susceptible and accessible locations, or, if fewer than five, all susceptible and accessible locations within 30 days of detecting the flaw in accordance with the requirements (including scope expansion) of Code Case N-513-3. The NRC staff concludes that the licensee has satisfied the extent of condition inspection in accordance with Code Case N-513-3.
Flooding Analysis The licensee has performed a flooding analysis in the vicinity of the leak and has identified the equipment that may be affect by the flooding or spray from the leakage. The licensee stated that some equipment may be at risk from either spray or flood if the leakage increases.
However, at the time of the discovery none of the equipment was affected.
The NRC staff concludes that a current leak rate would not be a flooding concern. Should the leak rate increase. paragraph 2(g) of N-513-3 requires the licensee to perform a Code repair or replacement.
Hardship Justification The NRC staff concludes that shutting down the unit to repair the subject elbow would cycle the unit and increases the potential of an unnecessary transient, resulting in undue hardship. The NRC staff further concludes that the leakage is small and the elbow continuously maintains its structural integrity based on the above evaluation. Therefore, the NRC staff determines that no compensating increase in the level of quality and safety would be gained by performing an ASME Code repair at the time of discovery of the leakage.
5.0 CONCLUSION
Based on the above, the NRC staff determines that the proposed alternative provides a reasonable assurance of structural integrity of the subject raw water piping. The NRC staff concludes that complying with IWD-3120(b) of the ASME Code,Section XI, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii). Therefore, the NRC authorizes the use of Relief Request RR-14 at FCS until September 5, 2014, or the predicted flaw size from periodic inspection exceeds the acceptance criteria, whichever occurs first.
All other requirements of the ASME Code,Section XI, for which relief has not been specifically requested and authorized by NRC staff remain applicable, including a third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: J. Tsao, NRR/DE/EPNB Date: November 19, 2014
ML14316A167 *email dated OFFICE NRR/DORL/LPL4-1/PM NRR/DORLILPL4-1/LA NRR/DE/EPNB/BC NRR/DORL/LPL4-1/BC NAME Flyon JBurkhardt DAlley* MMarkley DATE 11/19/14 11/18/14 11/10/14 11/19/14