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MONTHYEARML16034A3032016-02-12012 February 2016 Request for Relief RC3-01 for Alignment of Inservice Inspection and Containment Inservice Inspection (CAC No. MF6333 Project stage: Other 2016-02-12
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Category:Code Relief or Alternative
MONTHYEARML24117A2482024-05-0707 May 2024 Authorization and Safety Evaluation for Relief Request No. RC3-02 ML24033A3092024-02-12012 February 2024 Summary of Regulatory Audit Regarding the Relief Request RC3-02 Regarding Drywell Head Bolting ML22111A1382022-05-13013 May 2022 Proposed Inservice Testing Alternative RS-01, Revision 0 NLS2020053, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR5-042020-08-26026 August 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR5-04 NLS2019034, 10 CFR 50.55a Relief Request RP5-02 and RI5-02, Revision 22019-06-28028 June 2019 10 CFR 50.55a Relief Request RP5-02 and RI5-02, Revision 2 ML19092A1402019-04-29029 April 2019 Proposed Inservice Inspection Alternative PR5-02 NLS2018029, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RR5-032018-05-16016 May 2018 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RR5-03 NLS2017032, 10 CFR 50.55a Request Number RI-21, Revision 12017-03-29029 March 2017 10 CFR 50.55a Request Number RI-21, Revision 1 ML16034A4792016-02-17017 February 2016 Request for Relief RI5-02, Alternative to Use Boiling Water Reactor Vessel and Internals Project Guidelines in Lieu of Specific ASME Code Requirements ML16014A1742016-02-12012 February 2016 Request for Relief RP-01 Through RP-09, RV-01 Through RV-05, and RG-01 Alternative to ASME OM Code Requirements for Inservice Testing for the Fifth Ten-Year Program Interval (CAC Nos. MF5911, MF5913, MF5914, MF5915, MF5916, Etc.) ML16034A3032016-02-12012 February 2016 Request for Relief RC3-01 for Alignment of Inservice Inspection and Containment Inservice Inspection (CAC No. MF6333 ML15134A2422015-05-20020 May 2015 Relief Request RI-08, Revision 0, Relief from Reactor Vessel Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections, for the Fourth 10-Year Inservice Inspection Interval ML12313A1112013-01-22022 January 2013 Relief Request RI-07 from ASME Code Requirements for Residual Heat Removal Shell Circumferential and Nozzle to Head Welds, Fourth 4th 10-Year Inservice Inspection Interval ML12233A1762012-08-28028 August 2012 Relief Request Nos. RV-07, Revision 0, and RV-01, Revision for Fourth 10-Day Inservice Inspection Interval Regarding Weld Overlay Repair NLS2011085, Relief Request from Certain Inservice Testing Code Requirements2011-08-24024 August 2011 Relief Request from Certain Inservice Testing Code Requirements ML1101205402011-02-18018 February 2011 Relief Request RI-36 for Alternative Weld Overlay Repairs for the Fourth 10-Year Inservice Inspection Interval ML1022204492010-10-0808 October 2010 Request for Relief No. RI-04 for the Fourth 10-Year Inservice Inspection Interval Regarding Inspection of Reactor Vessel Nozzle-to-Vessel Shell Welds ML1009703402010-04-26026 April 2010 Relief, Relief Request No. RV-06 from Certain Inservice Testing Requirements Related to Valves in the Control Rod Drive System, for Fourth 10-Year IST Interval NLS2010013, Request Relief from Certain Inservice Inspection (ISI) Code Requirements2010-02-0505 February 2010 Request Relief from Certain Inservice Inspection (ISI) Code Requirements NLS2010014, Request Relief from Certain Inservice Inspection Code Requirements2010-02-0505 February 2010 Request Relief from Certain Inservice Inspection Code Requirements NLS2009038, Relief Request from Certain Inservice Test Code Requirements, RV-06, Revision 02009-06-18018 June 2009 Relief Request from Certain Inservice Test Code Requirements, RV-06, Revision 0 ML0821304832008-08-15015 August 2008 Request for Relief No. Ri - 35 for Fourth Year Inservice Inspection Interval Regarding Weld Overlay Repair ML0802302882008-02-0606 February 2008 Request for Relief No. RI-29, Revision 1, for Fourth 10-Year Inservice Inspection Volumetric Examination of Reactor Pressure Vessel Circumferential Shell Welds ML0631802502006-12-0505 December 2006 Request for Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Vessel Code, Relief Request No. RI-06, Revision 3, for Weld HMC-BB-1 ML0630402412006-11-0303 November 2006 Correction to and Clarification on Safety Evaluation - Risk Informed Inservice Inspection Program for the Fourth 10-Year Interval; Relief Request No. RI-34 ML0628500512006-10-23023 October 2006 Risk-Informed Inservice Inspection Program for Fourth 10-Year Interval; Relief Request No. RI-34 ML0626202782006-10-13013 October 2006 Fourth 10-year Interval Inservice Inspection Request for Relief No. RI-15, Examination of Peripheral Control Rod Drive Housing Welds ML0625400642006-10-11011 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief RI-02 ML0622601952006-10-0202 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief No. PR-02 ML0622602172006-10-0202 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief No. PR-06 ML0622602202006-10-0202 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief No. PR-11 ML0622602032006-10-0202 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief No. PR-04 ML0623405482006-09-0808 September 2006 Relief, Request for Relief No. RI-13 Fourth 10-Year Interval Inservice Inspection ML0405603182004-02-25025 February 2004 Code Relief-RP-06-IST, Core Spray Pump CS-P-B, MB6821 NLS2003120, Inservice Testing Program Relief Request RP-06, Revision 22003-11-25025 November 2003 Inservice Testing Program Relief Request RP-06, Revision 2 ML0309003842003-03-31031 March 2003 Relief, Inservice Testing of All Pumps as Required by Asme/Ansi OMA-1988, Part 6, Paragraph 6.1, MB6822 2024-05-07
[Table view] Category:Letter
MONTHYEARML24250A2052024-10-0808 October 2024 Issuance of Amendment No. 278 Regarding Revision to Technical Specification Table 3.3.2.1-1 and Transfer of Minimum Critical Power Ratio Values to Core Operating Limit Report ML24227A0822024-09-0303 September 2024 Summary of Regulatory Audit in Support of License Amendment Request to Modify the High Pressure Coolant Injection Low Flow Value IR 05000298/20240052024-08-22022 August 2024 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2024005) IR 05000298/20240022024-07-25025 July 2024 Integrated Inspection Report 05000298/2024002 ML24183A1722024-07-17017 July 2024 Issuance of Amendment No. 277 to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML24197A1462024-07-15015 July 2024 NRC Region IV Ltr to Cooper Nuclear Station Re FEMA Level 1 Finding IR 05000298/20243012024-07-12012 July 2024 NRC Examination Report 05000298/2024301 ML24134A1782024-07-0303 July 2024 Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33 ML24197A0682024-06-24024 June 2024 FEMA Ltr to Missouri State Emergency Management Agency - Level 1 Finding, 24 June 2024 ML24192A0112024-06-13013 June 2024 2024-06-Post Exam Comments 05000298/LER-2023-002-01, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2024-06-0606 June 2024 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications IR 05000298/20244012024-06-0404 June 2024 Security Baseline Inspection Report 05000298/2024401 ML24151A1082024-05-30030 May 2024 NRC Initial Operator Licensing Examination Approval 05000298/2024301 ML24137A0942024-05-17017 May 2024 Regulatory Audit Plan in Support of License Amendment Request to Modify Allowable Value Regarding Technical Specification for High Pressure Coolant Injection Pump Discharge Low Flow 05000298/LER-2024-005, High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical2024-05-13013 May 2024 High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical. 05000298/LER-2024-004, Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications2024-05-0909 May 2024 Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications IR 05000298/20240012024-05-0303 May 2024 Integrated Inspection Report 05000298/2024001 ML24129A0952024-04-25025 April 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000298/20240102024-04-24024 April 2024 Comprehensive Engineering Team Inspection Report 05000298/2024010 05000298/LER-2024-003, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications2024-04-22022 April 2024 High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) ML24093A2282024-04-0202 April 2024 Notice of Enforcement Discretion for Cooper Nuclear Station IR 05000298/20240902024-04-0101 April 2024 – Notice of Violation, NRC Inspection Report 05000298/2024090 IR 05000298/20230062024-02-28028 February 2024 Annual Assessment Letter for Cooper Nuclear Station - Report 05000298/2023006 IR 05000298/20230042024-02-12012 February 2024 Integrated Inspection Report 05000298/2023004 IR 05000298/20230122024-02-12012 February 2024 NRC Inspection Report 05000298/2023012 ML24033A3092024-02-12012 February 2024 Summary of Regulatory Audit Regarding the Relief Request RC3-02 Regarding Drywell Head Bolting ML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23311A1122023-11-0909 November 2023 Project Manager Assignment IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report ML23102A0282023-04-19019 April 2023 U.S. Nuclear Regulatory Commission Presentation at the May 8, 2023, Brownville Village Meeting IR 05000298/20230012023-04-17017 April 2023 Integrated Inspection Report 05000298/2023001 ML23060A1582023-03-0808 March 2023 Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001 IR 05000298/20220062023-03-0101 March 2023 Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006 ML23041A1622023-02-10010 February 2023 Licensed Operator Positive Fitness-for-Duty Test Request for Additional Information IR 05000298/20220042023-01-30030 January 2023 Integrated Inspection Report 05000298/2022004 IR 05000298/20220112022-12-23023 December 2022 License Renewal Phase 4 Inspection Report 05000298/2022011 2024-09-03
[Table view] Category:Safety Evaluation
MONTHYEARML24250A2052024-10-0808 October 2024 Issuance of Amendment No. 278 Regarding Revision to Technical Specification Table 3.3.2.1-1 and Transfer of Minimum Critical Power Ratio Values to Core Operating Limit Report ML24183A1722024-07-17017 July 2024 Issuance of Amendment No. 277 to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML24134A1782024-07-0303 July 2024 Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33 ML24117A2482024-05-0707 May 2024 Authorization and Safety Evaluation for Relief Request No. RC3-02 ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) ML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML22286A2072022-11-30030 November 2022 Issuance of Amendment No. 272 Revision to Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML22200A2772022-07-21021 July 2022 Correction to Proposed Inservice Testing Alternative RS-01, Revision of Error in Safety Evaluation ML22152A1232022-07-18018 July 2022 Issuance of Amendment No. 271 Request for Exception from Certain Primary Containment Leak Rate Testing Requirements ML22140A1612022-06-0808 June 2022 Proposed Inservice Inspection Alternative RR5-01 Revision 1 ML22111A1382022-05-13013 May 2022 Proposed Inservice Testing Alternative RS-01, Revision 0 ML22045A0012022-03-31031 March 2022 Proposed Inservice Inspection Alternative RI5- 02 Revision 3 ML21340A2362021-12-20020 December 2021 Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements ML21040A3002021-03-29029 March 2021 Issuance of Amendment No. 269 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML20314A2352020-12-0202 December 2020 Issuance of Amendment No. 268 Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process ML20282A1762020-10-22022 October 2020 Issuance of Amendment No. 267 Regarding Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, Clarify Use and Application Rules ML20255A2172020-09-15015 September 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML20077L3392020-03-19019 March 2020 Proposed Inservice Inspection Alternatives RP5-02 and RI5-02 ML19352G1942020-01-28028 January 2020 Issuance of Amendment No. 264 Elimination of Technical Specification Requirements for Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML19238A0072019-10-30030 October 2019 Issuance of Amendment No. 263 Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML19079A0702019-05-0707 May 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4384; EPID No. L-2014-JLD-0046) ML19092A1402019-04-29029 April 2019 Proposed Inservice Inspection Alternative PR5-02 ML18348B1032019-02-21021 February 2019 Issuance of Amendment No. 262 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML18218A4832018-09-0606 September 2018 Issuance of Amendment No. 261 Safety Limit Minimum Critical Power Ratio ML18186A5492018-08-0101 August 2018 Issuance of Amendment No.260 Revision to Technical Specifications to Adopt (TSTF) Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC No. MG0138; EPID L-2017-LLA-0290) ML18183A3252018-07-31031 July 2018 Requests for Relief Associated with - the Fifth 10-year Inservice Inspection Interval Program (CAC Nos. MG0175 Through MG0179; Epids L-2017-LLR-0062 Through L-2017-LLR-0066) ML18064A1022018-03-22022 March 2018 Request No. RI-21, Revision 1 - Request for Relief Concerning Examinations for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9623; EPID L-2017-LLR-0026) ML17226A0322017-09-20020 September 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17144A0822017-06-20020 June 2017 Issuance of Amendment No. 259 Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17061A0502017-03-31031 March 2017 Issuance of Amendment No. 258 Adoption of TSTF-425, Revision 3, ML16272A1372016-10-17017 October 2016 Issuance of Amendment No. 257 Revision of Technical Specifications - Safety Limit Minimum Critical Power Ratio ML16146A7492016-07-25025 July 2016 Issuance of Amendment No. 255 Replacement of Technical Specification Figure 4.1-1 with Text ML16119A4332016-07-25025 July 2016 Issuance of Amendment No. 254 Adoption of Technical Specification Task Force Change Traveler TSFT-535, Revision 0 ML16158A0222016-07-25025 July 2016 Issuance of Amendment No. 256 to Relocate the Pressure-Temperature Curves to a Pressure-Temperature Limits Report ML16048A3402016-02-24024 February 2016 Request for Inservice Inspection Program Alternative RP5-01 for Implementation of Code Case N-795 ML16042A3262016-02-24024 February 2016 Request for Relief RR5-01, Alternative Weld Overlay Repair for a Dissimilar Metal Weld Joining Nozzle to Control Rod Drive End Cap in Lieu of Specific ASME Boiler and Pressure Vessel Code Requirements ML16034A4792016-02-17017 February 2016 Request for Relief RI5-02, Alternative to Use Boiling Water Reactor Vessel and Internals Project Guidelines in Lieu of Specific ASME Code Requirements ML16034A3032016-02-12012 February 2016 Request for Relief RC3-01 for Alignment of Inservice Inspection and Containment Inservice Inspection (CAC No. MF6333 ML16014A1742016-02-12012 February 2016 Request for Relief RP-01 Through RP-09, RV-01 Through RV-05, and RG-01 Alternative to ASME OM Code Requirements for Inservice Testing for the Fifth Ten-Year Program Interval (CAC Nos. MF5911, MF5913, MF5914, MF5915, MF5916, Etc.) ML15343A3012016-01-22022 January 2016 Issuance of Amendment No. 253 to Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML15216A2592015-08-27027 August 2015 Issuance of Amendment No. 252, Revise Technical Specification 3.5.2, ECCS - Shutdown, to Delete Condensate Storage Tank as Alternate Source of Makeup Water ML15168A1712015-07-14014 July 2015 Issuance of Amendment No. 251, Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications ML15135A0052015-05-29029 May 2015 Issuance of Amendment No. 250, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-413, Elimination of Requirements for a Post Accident Sampling System (PASS) ML15134A2422015-05-20020 May 2015 Relief Request RI-08, Revision 0, Relief from Reactor Vessel Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections, for the Fourth 10-Year Inservice Inspection Interval ML14365A0932015-01-13013 January 2015 Correction to Safety Evaluation Dated December 12, 2014, Regarding Amendment No. 249, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML14323A6442014-12-12012 December 2014 Issuance of Amendment No. 249, Request to Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date ML14190A0042014-07-25025 July 2014 Redacted, Review of License Renewal Commitment Review Related to Core Plate Hold Down Bolt Inspection Plan and Analysis (TAC Nos. ME9550 and MF3557) ML14055A0232014-04-29029 April 2014 Issuance of Amendment No. 248, Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML13263A1532013-10-0707 October 2013 Correction to Amendment No. 247 Issued 9/12/13, Revise License Condition 2.E to Require All License Renewal Commitments Will Be Incorporated Into the Updated Safety Analysis Report 2024-07-03
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 12, 2016 Mr. Oscar A. Limpias Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR RELIEF RC3-01 FOR ALIGNMENT OF INSERVICE INSPECTION AND CONTAINMENT INSERVICE INSPECTION (CAC NO. MF6333)
Dear Mr. Limpias:
By letter dated June 9, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15167A066), Nebraska Public Power District (NPPD, the licensee) submitted Relief Request RC3-01, to the U.S. Nuclear Regulatory Commission (NRC), for the use of an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, "Rules for lnservice Inspection of Nucl~ar Power Plant Components" for Cooper Nuclear Station (CNS).
- Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, paragraph 50.55a(z)(1 ), the licensee is requesting relief to reduce the duration of the CNS second containment inservice inspection (CISI) interval in order to create a common inservice inspection (ISi) interval for CNS, on the basis that the alternative provides an acceptable level of quality and safety. This relief will permit subsequent CISI interval dates to be synchronized with the future ISi intervals. The net effect of this request is to establish one common interval for both the ISi and CISI programs at CNS. The CNS conversion to the common ISi interval start date would commence on March 1, 2016.
- Based on the NRC staff's evaluation of the information provided in the licensee's submittal, the staff concludes, as set forth in the enclosed safety evaluation, that the licensee's proposed alternative to the requirements of ASME Code,Section XI, Subarticle IWA-2430, is acceptable because it will provide an acceptable level of quality and safety. Accordingly, the staff concludes that the licensee has adequately addressed tre regulatory requirements set forth in 10 CFR 50.55a(z)(1) and is in compliance with the requirements of the ASME Code for which relief was not requested. Therefore, the staff authorizes the licensee to end the second CISI program interval early and commence the use of the 2007 Edition with the 2008 Addenda of the ASME Code,Section XI, for ISi of ASME Code Class MC Components as the common Code of record for the CISI program. third 10-year interval commencing on March 1, 2016.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable, including third party review by the Authorized Nuclear lnservice Inspector.
- 0. Limpias If you have any questions, please contact Thomas Wengert at 301-415-4037 or via e-mail at
Sincerely,
~,~...0 Meena K. Khanna, Chief Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
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 REQUEST FOR RELIEF RC3-01 ALIGNMENT OF INSERVICE INSPECTION AND CONTAINMENT INSERVICE INSPECTION NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298
1.0 INTRODUCTION
By letter dated June 9, 2015 (Agencywide Document Access and Management System (ADAMS) Accession No. ML15167A066), Nebraska Public Power District (NPPD, the licensee),
requested an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," for the Cooper Nuclear Station (CNS).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) Part 50, paragraph 50.55a(z)(1 ), the licensee is requesting relief to reduce the duration of the CNS second containment inservice inspection (CISI) interval in order to create a common inservice inspection (ISi) interval for CNS, on the basis that the alternative provides an acceptable level of quality and safety. This relief will permit subsequent CISI interval dates to be synchronized with the future ISi intervals. The net effect of this request is to establish one common interval for both the ISi and CISI programs at CNS. The CNS conversion to the common ISi interval start date would commence on March 1, 2016. *
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(g) specifies that ISi of nuclear power plant components shall be performed in accordance with the requirements of the ASME Code,Section XI.* Section 50.55a(z) of 10 CFR states, in part, that alternatives to the requirements of paragraph (g) may be used, when authorized by the Nuclear Regulatory Commission (NRC), if (1) the proposed alternative would provide an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), components that are classified as Class MC and Class CC pressure retaining components and their integral attachments, must meet the requirements, except the design and access provisions and preservice examination requirements, set forth in Enclosure
- 0. Limpias the ASME Code,Section XI, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations in 10 CFR 50.55a(g)(4) require that inservice examination of components and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements of the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in Paragraph (a) of 10 CFR 50.55a, 12 months before the start of th.e 120-month inspection interval, subject to the limitations and modifications listed therein.
3.0 TECHNICAL EVALUATION
3.1 ASME Code Components Affected
ASME Section XI, Code Class MC Components.
3.2 Applicable Code Edition and Addenda The licensee stated that the current Code of record for the GISI Program Second 10-Year Interval is the ASME Code,Section XI, 2001 Edition, 2003 Addenda. However, if the requested alternative is approved, the GISI program third 10-year interval start date will be aligned with the ISi program fifth 10-year interval and synchronized with the ASME Code,Section XI, 2007 Edition, 2008 Addenda requirements of these programs.
3.3 Applicable ASME Code Requirement ASME Code,Section XI, Subarticle IWA-2432 (2001 Edition, 2003 Addenda; IWA-2431, 2007 Edition, 2008 Addenda) requires that each inspection interval consist of a 10-year duration and permits the inspection interval to be reduced or extended by as much as 1 year, provided that successive intervals are not altered by more than 1 year from the original pattern of intervals, except as modified by IWA-2430(d), and IWA-2430(c) for the 2007 Edition, 2008 Addenda.
3.4 Licensee Proposed Alternative and Basis for Use Currently, the CNS fifth 10-year ISi program interval is scheduled to begin on March 1, 2016, while the GISI third 10-year program interval is scheduled to begin on May 9, 2018. CNS proposes to reduce the duration of the GISI third 10-year program interval to coincide with the start of the ISi fifth. 10-year program interval. This proposed alternative will permit the subsequent ISi and GISI programs to share a common inspection interval and to implement a common ASME Code Section XI Edition and Addenda (2007 Edition, 2008 Addenda). The licensee stated that since this proposed alternative will shorten the current GISI program second 10-year interval by approximately 2 years, CNS has completed all the required GISI examinations for the GISI second 10-year interval during the last refueling outage (RE28 in October 2014) in preparation for this submittal. The licensee further stated that the examinations performed, to date, have satisfied the acceptance standards contained in Article IWE-3000.
The licensee stated that 10 CFR 50.55a(g)(4)(ii) does not prohibit licensees from updating to a .
later Edition and Addenda of the ASME Code midway through a 10-year IWE and IWL examination interval. The licensee further stated that using the common interval date justified above and based on the current ISi program, the ASME Code of record for the fifth 10-year
- 0. Limpias interval ISi and third 10-year interval CISI programs, is to be set on March 1, 2016. The latest edition and addenda of the ASME Code incorporated by reference in 10 CFR 50.55(a)(1 )(ii) of the regulation is the 2007 Edition, 2008 Addenda. Currently, the CISI program second 10-year interval is using the ASME Code,Section XI, 2001 Edition, 2003 Addenda. Thus, CNS will utilize the 2007 Edition, 2008 Addenda of Section XI to develop the ISi program update for the fifth 10-yeai" ISi interval and third 10-year CISI interval. The licensee asserts that the proposed alternative, as described above, provides an acceptable level of quality and safety and does not adversely impact the health and safety of the public.
3.5 NRC Staff Evaluation In the supplementary information contained in Section 2.2 of the Final Rule (67 FR 60520),
dated September 26, 2002, the NRC staff stated, in part, that 10 CFR 50.55a(g)(4)(ii) does not prohibit licensees from updating to a later edition and addenda of the ASME Code midway through a 10-Year IWE or 5-Year IWL examination interval. Additionally, the staff advised.that licensees wishing to synchronize their 120-month intervals may submit a request in accordance with 10 CFR 50.55a(a)(3), currently reflected in 10 CFR 50.55a(z), to obtain authorization to extend or reduce 120-month intervals.
In the subject alternative request, the licensee proposed an alternative to the requirements of the ASME Code,Section XI, IWA-2430(b) and IWA-2432 requirements. The proposed alternative will reduce the duration of the second 10-year CISI program interval by approximately 26 months (March 1, 2016 versus May 9, 2018). However, ASME Code,Section XI, IWA-2432(d) allows only a 1-year change to the original pattern of the 10-year ISi interval. Therefore, to determine whether the proposed alternative will provide an acceptable level of quality and safety, the NRC staff's review focused on its effect on the implementation of the ASME Code-required CISI program.
The proposed alternative will align the 10-year CISI interval with the ISi interval starting on March 1, 2016. This will establish a common 10-year interval for both the CISI and the ISi programs at CNS and allow the use of a common ASME Code of record. The common Code of record for this interval, which was set on February 28, 2015 (i.e., 12 months prior to the start of the successive interval in accordance with 10 CFR 50.55a(g)(4)(ii)), currently is ASME Code,Section XI, 2007 Edition, 2008 Addenda.
CNS has different 10-year CISI and ISi program interval dates, which may result in implementation of different governing code editions and requirements in subsequent ISi program intervals. The 10-year program interval dates are different because the CISI program was not implemented until the NRC's amended rule became effective on September 9, 1996.
The proposed alternative will align and synchronize both 10-year programs and establish the use of the ASME Code,Section XI, 2007 Edition, 2008 Addenda, as the common Code of record. The licensee stated that there are distinct advantages in implementing the same Code requirements in a common interval, such as the reduction of administrative burden in developing and maintaining different sets of procedures and requirements, thus reducing possible errors associated with applying two different ASME Code Editions and Addenda*requirements at the same time. The licensee also stated that any CISI examinations unique to and specifically required for the remainder of the second 10-year interval hm(e already been performed and not deferred to the end of the interval. The. licensee stated that it has completed all of the required CISI examinations for the second 10-year interval during the last refueling outage (RE28 in
- 0. Limpias October 2014) in preparation of this request, and that the completed examinations performed to date have satisfied the acceptance standards of Article IWE-3000. The licensee stated that upon authorization by the NRC staff of this proposed alternative, CNS intends to use the same start and end dates for the CISI program third 10-year interval and the ISi program fifth 10-year interval along with the same ASME Code,Section XI, 2007 Edition with the 2008 Addenda requirements.
The 2007 Edition, 2008 Addenda, is the latest edition and addenda available and have been previously reviewed by the NRC staff and incorporated by reference into 10 CFR 50.55a for use by licensees. Since the licensee did not request relief from any of the conditions applicable to the 2007 Edition, 2008 Addenda, any applicable conditions will remain in effect. Since the licensee completed all of the examinations applicable to the second 10-year CISI interval, implementation of this request would not result in any fewer examinations.
The NRC staff review addressed the ability of the licensee to maintain an acceptable level of quality and safety after altering its ISi programs and to ensure integrity of the containment.
Based on these considerations, the staff has determined that the licensee's proposed alternative to allow the CISI program third 10-year interval start date to be aligned with the ISi program fifth 10-year interval and to synchronize the ASME Code,Section XI, 2007 Edition, 2008 Addenda, requirements of these programs (e.g., use of a common ASME Code of record),
with no change to the inspection frequency of examinations, provides reasonable assurance of quality and safety.
4.0 CONCLUSION
Based on the NRC staff's evaluation of the information provided in the licensee's submittal, the staff concludes that the licensee's proposed alternative to the requirements of ASME Code,Section XI, Subarticle IWA-2430, is acceptable because it will provide an acceptable level of quality and safety. Accordingly, the staff concludes that the licensee has adequately addressed
. the regulatory requirements set forth in 10 CFR 50.55a(z)(1) and is in compliance with the requirements of the ASME Code for which relief was not requested. Therefore, the staff authorizes the licensee to end the second CISI program interval early and commence the use of the 2007 Edition with the 2008 Addenda of the ASME Code,Section XI, for inservice inspection of ASME Code Class MC Components as the common Code of record for the CISI program third 10-year interval at Cooper Nuclear Station, commencing on March 1, 2016.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized herein by the staff remain applicable, including third party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: R. Pettis Date: February 12, 2016
ML16034A303 *by email dated OFFICE N RR/LPL4-2/PM NRR/LPL4-2/LA NRR/DE/EMCB/BC* NRR//LPL4-2/BC NAME TWengert PBlechman Tlupold MKhanna DATE 02/09/16 02/08/16 01/29/16 02/12/16