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MONTHYEARML15100A2282015-04-10010 April 2015 Submittal of Relief Requests 13R-10, 1ISl-004, and 21Sl-013 Concerning Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Project stage: Request ML15288A5652015-10-15015 October 2015 NRR E-mail Capture - Clinton Power Station, Unit 1, and Nine Mile Point Nuclear Station, Units 1 and 2 - Request for Additional Information Regarding Relief Requests I3R-10, 1ISI-005, and 2ISI-013 (CAC Nos. MF6115-MF6117) Project stage: RAI ML16012A3442016-03-10010 March 2016 Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Project stage: Other 2015-04-10
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Category:Code Relief or Alternative
MONTHYEARML22047A1272022-02-22022 February 2022 Relief from the Requirements of the American Society of Mechanical Engineers Code ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML20268C2322020-11-0404 November 2020 Proposed Alternative I4R-06 to the Requirements of the ASME Code ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20218A6602020-09-0202 September 2020 Proposed Alternative I4R-01 to the Requirements of the ASME Code ML20219A2022020-09-0101 September 2020 Proposed Alternative I4R-05 to the Requirements of the American Society of Mechanical Engineers Code ML20232A1882020-09-0101 September 2020 Proposed Alternative I4R-02 to the Requirements of the ASME Code RS-20-095, Response to Request for Additional Information Related to Relief Request I4R-06 for the Fourth Inservice Inspection Interval2020-08-13013 August 2020 Response to Request for Additional Information Related to Relief Request I4R-06 for the Fourth Inservice Inspection Interval ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)2020-02-28028 February 2020 Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) ML20036D9622020-02-0404 February 2020 Dresden Nuclear Power Station, Nine Mile Point Nuclear Station, Peach Bottom Atomic Power Station, & Quad Cities Nuclear Power Station - Proposed Alternative to Extend Reactor Pressure Vessel Safety Relief Valve Testing Frequency ML20010E8702020-01-27027 January 2020 Proposed Alternative to the Requirements of the ASME Code ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML16012A3442016-03-10010 March 2016 Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements ML15301A8702015-11-0505 November 2015 Relief from the Requirements of the ASME Code Concerning Snubber Inspection Interval for the Thrid10-Year Interval Inservice Inspection Program (CAC No. MF5334)(RS-14-295) ML15180A4072015-07-15015 July 2015 Request for Alternatives from ASME OM Code Requested Frequency (TAC Nos. MF5344 and MF5345)(RS-14-291) and RS-14-292) ML13107A0992013-04-18018 April 2013 Relief Request I3R-09 Alternative to VT-2 Visual Examination of Combustible Gas Control System Piping ML12121A6372012-05-10010 May 2012 Request to Use Code Case N-789 JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP2011-10-0303 October 2011 Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP ML1033603352010-12-22022 December 2010 Relief Requests I3R-01, I3R-02, I3R-03, I3R-04, and I3R-05 Associated with the Third Inservice Inspection ML1013406912010-06-10010 June 2010 Safety Evaluation of Relief Request Nos. 2201, 2202, and 3201, for the Third 10-Year Inservice Testing Interval ML1008801262010-04-21021 April 2010 Relief from the Requirements of the ASME Code ML0936400232009-12-30030 December 2009 Request for Alternative 4215 Class 1 Reactor Vessel Circumferential Shell Welds, ME0407 ML0923005872009-08-20020 August 2009 Relief Request for Use of Subsequent Edition and Addenda or American Society of Mechanical Engineers Code for Inservice Testing RS-08-156, Proposed Alternative to 10CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections2008-12-0303 December 2008 Proposed Alternative to 10CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections RS-08-144, Request for Relief from ASME OM Code 5-Year Test Interval for Safety Relief Valves (Relief Request No. 2210)2008-11-0303 November 2008 Request for Relief from ASME OM Code 5-Year Test Interval for Safety Relief Valves (Relief Request No. 2210) ML0809803112008-04-30030 April 2008 Relief Request to Use Boiling Water Reactor Vessel & Internals Project Guidelines.. ML0731904792007-12-0606 December 2007 Relief Request No. 2209 from 5-Year Test Requirement for Safety Valves ML0725405502007-09-12012 September 2007 Temporary Relief from 5-year Test Requirement for Safety Relief Valves ML0601104852006-01-17017 January 2006 Unit - SE for Relief Request No. 4211 Core Shroud Repair ML0536200832005-12-28028 December 2005 Draft SE for Relief Request No. 4211 Core Shroud Repair ML0330802462003-11-17017 November 2003 Safety Evaluation of Relief Request RR-2206 Related to the Second 10-Year Inservice Testing Interval ML0315005112003-06-27027 June 2003 Safety Evaluation of Relief Request 2207 for the Second Ten-Year Pump and Valve Inservice Testing Program ML0203800532002-03-0606 March 2002 Relief Requests CIP 6111 and 4207 2022-02-22
[Table view] Category:Letter
MONTHYEARIR 05000461/20230042024-02-0202 February 2024 Integrated Inspection Report 05000461/2023004 ML23361A1572024-01-24024 January 2024 Audit Plan in Support of Review of License Amendment Request Regarding Revision of Technical Specifications Related to Reactor Water Cleanup Isolation ML24004A0792024-01-18018 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0041 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000461/20234022023-12-27027 December 2023 Security Baseline Inspection Report 05000461/2023402 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 IR 05000461/20235012023-12-0505 December 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000461/2023501 ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000461/20230032023-11-0808 November 2023 Integrated Inspection Report 05000461/2023003 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000461/20233012023-09-12012 September 2023 NRC Initial License Examination Report 05000461/2023301 RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000461/20234202023-08-29029 August 2023 Security Baseline Inspection Report 05000461/2023420 RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation IR 05000461/20230022023-08-0404 August 2023 Integrated Inspection Report 05000461/2023002 RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release ML23209A8102023-07-28028 July 2023 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23198A0152023-07-27027 July 2023 License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23202A0992023-07-24024 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000461/2023004 ML23200A2592023-07-24024 July 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting-Meeting Summary IR 05000461/20234012023-07-19019 July 2023 Cyber Security Inspection Report 05000461/2023401 ML23194A1662023-07-19019 July 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Partial Site Release ML23191A8772023-07-11011 July 2023 Operator Licensing Examination Approval Clinton Power Station July 2023 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release IR 05000461/20230102023-05-26026 May 2023 Triennial Fire Protection Inspection Report 05000461/2023010 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23143A3182023-05-23023 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1 IR 05000461/20230012023-05-0404 May 2023 Integrated Inspection Report 05000461/2023001 ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000461/20220062023-03-0101 March 2023 Annual Assessment Letter for Clinton Power Station, Unit 1 (Report 05000461/2022006) RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 ML23039A1852023-02-10010 February 2023 Integrated Inspection Report 05000461/2022004 07201046/2022001 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 IR 05000461/20220112023-01-27027 January 2023 Biennial Problem Identification and Resolution Inspection Report 05000461/2022011 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing ML23005A0682023-01-0505 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000461/2023010 ML22341A6042022-12-0808 December 2022 Confirmation of Initial License Examination IR 05000461/20224022022-12-0606 December 2022 Security Baseline Inspection Report 05000461/2022402 RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI 2024-02-02
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22292A0352022-11-10010 November 2022 Issuance of Amendment No. 246 Secondary Containment and the Fuel Building Railroad Airlock (EPID L-2022- LLA-0055) ML22263A4732022-11-10010 November 2022 Issuance of Amendment No. 247 Adoption of TSTF-230, Revision 1 ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML22047A1272022-02-22022 February 2022 Relief from the Requirements of the American Society of Mechanical Engineers Code ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21306A0002021-12-21021 December 2021 License Amendment to Revise Degraded Voltage Relay Allowable Values ML21307A3422021-12-0707 December 2021 Issuance of Amendments to Adopt Reactor Pressure Vessel Water Inventory Control Enhancements (EPIDs L-2020-LLA-0253 and L-2020-LLA-0254) ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21132A2882021-06-28028 June 2021 Issuance of Amendment No. 238, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21166A1682021-06-25025 June 2021 ML21090A1932021-05-19019 May 2021 Issuance of Amendment No. 237 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20268C2322020-11-0404 November 2020 Proposed Alternative I4R-06 to the Requirements of the ASME Code ML20266G3432020-10-14014 October 2020 Issuance of Amendment No. 235 Regarding Operation of the Emergency Auxiliary Reserve Transformer Load Tap Changer ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20218A6602020-09-0202 September 2020 Proposed Alternative I4R-01 to the Requirements of the ASME Code ML20232A1882020-09-0101 September 2020 Proposed Alternative I4R-02 to the Requirements of the ASME Code ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20219A2022020-09-0101 September 2020 Proposed Alternative I4R-05 to the Requirements of the American Society of Mechanical Engineers Code ML20212L3902020-08-31031 August 2020 Proposed Alternative I4r-03 to the Requirements of the Asme Code (Epid L-2019-Llr-0114) ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20163A7172020-06-26026 June 2020 Proposed Alternative to the Requirements of the ASME Code ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML20010E8702020-01-27027 January 2020 Proposed Alternative to the Requirements of the ASME Code ML19238A3082019-09-30030 September 2019 Issuance of Amendment - Regarding Adoption of TSTF-476, Improved Banked Position Withdrawal Sequence Control Rod Insertion Process ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19109A0012019-06-12012 June 2019 Issuance of Amendment Regarding Recapture of Low-Power Testing Time ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18303A3132019-01-0303 January 2019 Issuance of Amendment 221 Regarding Revised Alternative Source Term Dose Calculation 2023-04-28
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Mr. Bryan Senior Vice President Mm:h 10, 2016 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT: CLINTON POWER STATION, UNIT 1 -USE OF BWRVIP GUIDELINES IN LIEU OF SPECIFIC ASME CODE REQUIREMENTS (CAC NO. MF6115)
Dear Mr. Hanson:
By letter dated April 10, 2015, as supplemented by letters dated September 29 and November 24, 2015 (Agencywide Documents Access and Management System (ADAMS) Nos. ML 15100A228, ML 15272A029, and ML 15328A514, respectively), Exelon Generation Company, LLC (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) concerning the use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) requirements at Clinton Power Station, Unit 1 (CPS), and Nine Mile Point Nuclear Station, Units 1 and 2 (NMPNS). This letter applies to CPS only. The request related to NMPNS is still under review at the NRC. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(z)(1), the licensee requested to use the proposed alternative on the basis that it provides an acceptable level of quality and safety. The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the alternative proposed by the licensee will ensure that the integrity of the reactor pressure vessel interior surfaces, attachments, and core support structures, is maintained with an acceptable level of quality and safety and has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). The licensee clarified that any revised version of a BWRVIP report used to satisfy the alternatives will meet or exceed the BWRVIP inspection and evaluation (l&E) guidelines of its original version, and if it does not meet this criteria, NRC staff approval is mandatory prior to its implementation. All other requirements of ASME Code,Section XI, for which the alternative has not been specifically requested remain applicable, including third-party review by the Authorized Nuclear In-service Inspector. Any ASME Code,Section XI, reactor vessel internals (RVI) components that are not included in Section 3.1.1 of this safety evaluation will continue to be inspected in accordance with the ASME Code,Section XI, requirements. The inspection and evaluation guidelines addressed in the relevant BWRVIP reports should be implemented for the non-ASME Code,Section XI, RVI components at CPS. The NRC staff acknowledges that the BWRVIP Executive Committee periodically revises the BWRVIP guidelines to include enhancements in inspection techniques and flaw evaluation methodologies. While the licensee may choose to implement enhancements described in a revised version of the referenced BWRVIP inspection guideline, the licensee is expected to continue to meet the requirements of the version of the BWRVIP inspection guidelines that forms the safety basis for the NRC staff authorized proposed alternative to the requirements of 10 CFR 50.55a. If you have any questions, please contact Ms. Eva A. Brown at 301-415-2315 or via e-mail at Eva.Brown@nrc.gov. Docket No. 50-461
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ Justin C. Poole, Acting Branch Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NO. 13R-10 FOR THE THIRD 10 YEAR INTERVAL INSERVICE INSPECTION FOR 1.0 INTRODUCTION EXELON GENERATION COMPANY. LLC CLINTON POWER STATION, UNIT 1 DOCKET NO. 50-461 By letter dated April 10, 2015, as supplemented by letters dated September 29 and November 24, 2015 (Agencywide Documents Access and Management System (ADAMS) Nos. ML 15100A228, ML 15272A029, and ML 15328A514, respectively}, Exelon Generation Company, LLC (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC or Commission) concerning the use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) requirements at Clinton Power Station, Unit 1 (CPS}, and Nine Mile Point Nuclear Station, Units 1 and 2 (NMPNS). The NRC's review of the NMPNS submittal will be issued under separate cover. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(z)(1 ), the licensee requested to use the proposed alternative on the basis that it provides an acceptable level of quality and safety. 2.0 REGULATORY EVALUATION The inservice inspection (ISi) of ASME Code Class 1, 2, and 3 components is to be performed in accordance with Section XI of the ASME Code and applicable edition and addenda as required by 1 O CFR 50.55a(g}, except where specific relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i}. Pursuant to 10 CFR 50.55a(z), alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC if the proposed alternatives would provide an acceptable level of quality and safety. Pursuant to 10 CFR 50.55a(g)(4}, ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system Enclosure
-2 -pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(a)(1 )(ii), 12 months prior to the start of the 120-month interval, subject to the conditions listed in 10 CFR 50.55a(b)(2). The regulations in 10 CFR 50.55a(g)(4)(iv) state that the inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph 10 CFR 50.55a(a}, subject to the limitations and modifications listed in 10 CFR 50.55a(b}, and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met. The applicable ASME Code of Record for the third 10-year ISi interval for CPS is the ASME Code,Section XI, 2004 Edition. 3.0 TECHNICAL EVALUATION 3.1 Licensee's Request for Alternative 3.1.1 Components for Which an Alternative is Requested Section XI, ASME Code Class 1, Examination Categories B-N-1 and B-N-2, Code Item Nos. 813.10, Vessel Interior, 813.20, Interior Attachments within Beltline Region, 813.30, Interior Attachments Beyond Beltline Region, and 813.40, Core Support Structure. 3.1.2 Examination Requirements from Which an Alternative is Requested Section XI, ASME Code, requires the visual examination (VT) of certain reactor vessel internals (RVI) components. These examinations are included in Table IWB-2500-1, Categories B-N-1 and B-N-2, and are identified with the following item numbers: B 13.10 -Examine accessible areas of the reactor pressure vessel interior surfaces each period using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI (B-N-1 ). 813.20 -Examine interior attachment welds within the beltline region each interval using a technique which meets the requirements for a VT-1 examination as defined in paragraph IWA-2211 of the ASME Code,Section XI (B-N-2). 813.30 -Examine interior attachment welds beyond the beltline region each interval using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI (B-N-2). 813.40 -Examine surfaces of the core support structure each interval using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI (B-N-2). These examinations are performed to assess the structural integrity of the reactor pressure vessel interior surfaces, attachments, and core support structures.
-3 -3.1.3 Licensee's Basis for Requesting an Alternative and Justification for Granting Relief In the April 10, 2015 submittal, the licensee, in lieu of ASME Code,Section XI, requirements, submitted an alternative inspection program per the BWRVIP guidelines for Categories B-N-1 and B-N-2 reactor pressure vessel interior surfaces, attachments, and core support structures at CPS. The licensee stated that implementation of the alternative inspection program will maintain an adequate level of quality and safety of the affected welds and components and will not adversely impact the health and safety of the public. As part of its justification for the relief, the licensee stated that boiling-water reactors (BWRs) now examine the reactor pressure vessel interior surfaces, attachments, and core support structures in accordance with BWRVIP guidelines. The proposed alternative covers examination methods, examination volume, frequency, training, successive and additional examinations, flaw evaluations, and reporting. The BWRVIP guidelines have been written to address the examination of safety significant RVI components using appropriate methods and re-inspections at conservative intervals. In contrast, the code re-inspection intervals are less conservative than the intervals stipulated in the BWRVIP inspection and evaluation (l&E) guidelines. 3.1.4 Alternative Examination In lieu of the requirements of the applicable Edition and Addenda of Section XI of the ASME Code, the licensee proposed to examine the CPS RVI components in accordance with BWRVIP guideline requirements. In their request, the licensee included only the RVI components that come under the jurisdiction of Section XI of the ASME Code. The following reports include the relevant BWRVIP l&E guidelines for the reactor pressure vessel interior surfaces, attachments, and core support structures. Furthermore, the licensee clarified that not all RVI components listed in the following BWRVIP reports are ASME Code,Section XI, components:
- BWRVIP-38, "BWR Shroud Support Inspection and Flaw Evaluation Guidelines"
- BWRVIP-41, Revision 3, "BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines"
- BWRVIP-47-A, "BWR Lower Plenum Inspection and Flaw Evaluation Guidelines"
- BWRVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines"
- BWRVIP-76, Revision 1, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines"
- BWRVIP-138, Revision 1-A, "BWRVIP Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines"
- BWRVIP-180, "Access Hole Cover Inspection and Flaw Evaluation Guidelines"
-4 -The licensee stated that inspection services by an authorized inspection agency will be applied to the proposed alternative. The licensee further indicated that the 8WRVIP has established reporting protocol for examination results and deviations that are consistent with the requirements of 8WRVIP-94. The licensee clarified that any revised version of a 8WRVIP report used to satisfy the alternatives will meet or exceed the l&E guidelines of its original version, and if it does not meet this criteria, NRC staff approval is mandatory prior to its implementation. In Table 1 of Attachment 1 of the April 10, 2015 submittal, the licensee provided a comparison of the ASME Code,Section XI, examination requirements for Categories 8-N-1 and 8-N-2 for the reactor pressure vessel interior surfaces, attachments, and core support structures to the 8WRVIP l&E Guidelines examination requirements. In Attachment 2 of the April 10, 2015, submittal, the licensee provided additional information regarding the 8WRVIP inspection requirements for the following welds (shown as examples) of the reactor pressure vessel interior surfaces, attachments, and core support structures and their subcomponents representing each of the ASME Code,Section XI, Item Nos. 813.10, 813.20, 813.30, and 813.40:
- Core Shroud Support and Core Support Structure (813.40) The licensee claimed that these examples demonstrated that the inspection techniques that are recommended by the 8WRVIP inspection guidelines are superior to the inspection techniques mandated by the ASME Code,Section XI, ISi program. Additionally, these examples demonstrated that the 8WRVIP inspection guidelines require more frequent inspections of some RVI components compared to the corresponding ASME Code,Section XI, ISi program. The licensee stated that by implementing the 8WRVIP inspection guidelines, the aging degradation of the reactor pressure vessel interior surfaces, attachments, and core support structures can be identified in a timely manner so that proper corrective action can be taken to restore the integrity of the applicable component. Therefore, the licensee concluded that implementation of the 8WRVIP inspection guidelines for the CPS reactor pressure vessel interior surfaces, attachments, and core support structures would provide an acceptable level of quality and safety. Furthermore, the licensee referenced an April 7, 2014 EPRI (Electric Power Research Institute) inspection summary (ADAMS Accession No. ML 14241A014), which included inspection methods used on the RVI components, inspection dates, the results of the inspection and corrective actions related to the findings of the inspections at CPS for the fall 2013 refueling outage. 3.2 NRC Staff Evaluation The NRC staff found the referenced 8WRVIP reports (other than 8WRVIP-180 and 8WRVIP-183) to be acceptable for use because l&E guidelines addressed in these reports are consistent with ASME Code,Section XI ISi criteria. In addition, for CPS compliance with inspection criteria included in the reports would provide reasonable assurance that the Aging Management Program is effective in identifying the aging degradation in the RVI components in a timely manner.
-5 -The NRC staff noted that the licensee must perform a plant-specific leakage assessment in core spray, jet pump and low-pressure coolant injection (LPCI) coupling systems. This requirement was established to ensure that the ability to cool the core is maintained during postulated of-coolant accident (LOCA) conditions. Maintaining core cooling capability is dependent upon the leakage assessment of the aforementioned RVI components considering any cracks that are present in the components that might lead to leakage outside of the core. Therefore, the NRC staff questioned whether a plant-specific leakage assessment was performed, as indicated by BWRVIP-18 (core spray), BWRVIP-41 Uet pump assembly), BWRVIP-42 (low pressure coolant injection system), and BWRVIP-76 (core shroud), for the internals at CPS, which accounts for the leakage from all internals that impact the ability to cool the core and maintain peak clad temperature within allowed limits during postulated loss of coolant accidents. Additionally, the NRC staff questioned whether a plant-specific integrated leakage assessment was performed at CPS for the RVI components associated with the BWRVIP documents listed above. In a response dated September 29, 2015, the licensee stated that a plant-specific leakage assessment was performed for core spray piping because cracks were identified in the core spray piping at CPS. The licensee also indicated that the calculated leakage from the identified cracking in the high and low pressure core spray piping is below the allowed leakage for the core spray system. The licensee further stated that the calculated leakage from the detected cracks is below the leakage assumed in the CPS LOCA analysis. In a response dated September 29, 2015, the licensee also stated that it did not perform a leakage assessment for the cracking found in the core shroud vertical weld because no wall cracking was identified. For the cracking detected in the core shroud horizontal weld, the licensee stated that the current plant-specific LOCA analysis considers leakage from core shroud circumferential welds, including consideration of the core shroud tie rod repair. Finally, the licensee stated that no plant-specific leakage assessment was performed for the LPCI coupling and jet pumps because no cracking has been detected to-date in these components. The NRC staff was concerned that the issues related to potential nonconservatisms loading conditions on RVI components raised in several of the General Electric-Hitachi safety communications (SCs), may lead to increased loads on the RVI components, which could potentially change the inspection and evaluation criteria of some of the BWRVIP guidelines. The NRC staff requested that the licensee identify whether the loads on the RVI components have been revised for CPS, based on those SCs. In a response dated November 24, 2015, the licensee indicated that SC 09-01 related to annulus pressurized loads did not apply to CPS, and repairs were implemented to the shroud tie rod for SC 09-03. Therefore, the NRC staff found that the license had sufficiently addressed the concerns identified in these SCs. However, regarding the response to SC 11-07, SC 12-20, Revision 1, SC 13-08, and SC-14-03, the NRC staff is currently pursuing resolution of these issues with the BWROG and the BWRVIP. In summary, the BWRVIP l&E guidelines require more frequent inspections than ASME Code,Section XI, criteria for the RVI components that are susceptible to aging degradation mechanisms. Therefore, subsequent inspections of the RVI components per the relevant BWRVIP l&E guidelines will provide adequate assurance that any emerging aging effects will be identified in a timely manner. In addition, frequent inspections per these guidelines will
-6 -enable the licensee to effectively monitor the existing aging degradation in reactor pressure vessel interior surfaces, attachments, and core support structures. The NRC staff finds that the licensee properly addressed all the applicable BWRVIP l&E guidelines listed in Section 3.1.4 of this SE. Therefore, the NRC staff further finds that the licensee's proposed alternative will identify aging degradation of the RVI components in a timely manner. Therefore, the NRC staff concludes that the implementation of the inspection requirements specified in the licensee's proposed alternative will ensure that the integrity of the RVI components will be maintained with an acceptable level of quality and safety. The NRC staff authorizes only the BWRVIP inspection guidelines proposed as an alternative. In the event the licensee wishes to take exceptions to, or deviations from the authorized alternative, the licensee must revise and resubmit its request for authorization to use the proposed alternative under 10 CFR 50.55a. 4.0 CONCLUSION As set forth above, the NRC staff determines that the alternative proposed by the licensee will ensure that the integrity of the reactor pressure vessel interior surfaces, attachments, and core support structures is maintained with an acceptable 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(z)(1 ), and is in compliance with the ASME Code's requirements. Therefore, the NRC staff authorizes the licensee's proposed alternative at CPS until June 30, 2020, with the condition that in the event the licensee wishes to take exceptions to, or deviations from, the NRC staff-approved BWRVIP inspection guidelines authorized as a proposed alternative, the licensee must revise and resubmit its request for authorization to use the proposed alternative under 10 CFR 50.55a. All other requirements of ASME Code,Section XI, for which the alternative has not been specifically requested remain applicable, including third-party review by the Authorized Nuclear In-service Inspector. Any ASME Code,Section XI, RVI components that are not included in this request for alternative will continue to be inspected in accordance with the ASME Code,Section XI, requirements. The l&E guidelines addressed in the relevant BWRVIP reports should be implemented for the non-ASME Code,Section XI, RVI components at CPS. Principal Contributors: Christopher Sydnor, NRR Ganesh Cheruvenki, NRR Date of issuance: Mm:h 10, 2016