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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
[Table view] |
Text
January 27, 2020 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION, UNIT 1 - PROPOSED ALTERNATIVE TO THE REQUIREMENTS OF THE ASME CODE FOR WATER LEG PUMP TESTING (EPID L-2019-LLR-0052)
Dear Mr. Hanson:
By letter dated May 23, 2019, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19143A305), Exelon Generation Company, LLC (EGC, the licensee), submitted a request for the use of an alternative to the requirements of certain American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (OM Code), requirements at Clinton Power Station (CPS), Unit 1.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use an alternative for testing certain waterleg pumps on the basis that the alternative testing provides an acceptable 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 EGC has adequately addressed the regulatory requirements of 10 CFR 50.55a(z)(1). The NRC staff finds that the proposed alternative relief request (RR)-3201 provides an acceptable level of quality and safety.
Therefore, the NRC staff authorizes RR-3201 for the fourth 10-year inservice testing interval at CPS, Unit 1, which is currently scheduled to start on July 1, 2020, and end on June 30, 2030.
All other ASME OM Code requirements for which relief was not specifically requested and approved remain applicable.
B. Hanson If you have any questions, please contact the Senior Project Manager, Joel S. Wiebe, at (301) 415-6606 or Joel.Wiebe@nrc.gov.
Sincerely,
/RA/
Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensin Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosure:
Safety Evaluation cc: Listserv
ML20010E870 *via email OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA EMIB/BC NRR/DORL/LPL3/BC NAME JWiebe SRohrer SBailey* NSalgado DATE 01/16/2020 01/14/2020 01/06/2020 01/27/2020 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO USE PROPOSED ALTERNATIVE RR-3201 REGARDING THE TESTING OF CERTAIN WATERLEG PUMPS EXELON GENERATION COMPANY, LLC CLINTON POWER STATION, UNIT 1 DOCKET NO. 50-461
1.0 INTRODUCTION
By letter dated May 23, 2019 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML19143A305), Exelon Generation Company, LLC, (EGC, the licensee), submitted an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code),
associated with pump inservice testing (IST) at Clinton Power Station (CPS), Unit 1.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use the proposed alternative in relief request (RR)-3201 on the basis that the alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
Regulation 10 CFR 50.55a(f), states, in part, that IST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with the specified ASME OM Code and applicable addenda incorporated by reference in the regulations.
Regulation 10 CFR 50.55a(z) states that alternatives to the requirements of paragraph (f) of 10 CFR 50.55a may be used, when authorized by the U.S. Nuclear Regulatory Commission (NRC),
if the licensee demonstrates: (1) the proposed alternatives 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.
Enclosure
3.0 TECHNICAL EVALUATION
3.1 Licensees Alternative RR-3201 The licensee requested an alternative to the pump testing requirements of the ASME OM Code.
Table ISTB-3000-1, Inservice Test Parameters, specifies the parameters to be measured during inservice tests.
ISTB-3300, Reference Values, (e)(2) states, Reference values shall be established at the comprehensive pump test flow rate for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow rate.
ISTB-3400, Frequency of Inservice Tests, states, An inservice test shall be run on each pump as specified in Table ISTB-3400-1.
Table ISTB-3400-1, Inservice Test Frequency, specifies that a Group A pump test shall be performed on a quarterly frequency.
ISTB-5121, Group A Test Procedure, states, in part, Group A tests shall be conducted with the pump operating as close as practical to a specified reference point and within the variances from the reference point as described in this paragraph . . . .
ISTB-5121(b) states, The resistance of the system shall be varied until the flow rate is as close as practical to the reference point with the variance not to exceed +2% or 1% of the reference point. The differential pressure shall then be determined and compared to its reference value.
Alternatively, the flow rate shall be varied until the differential pressure is as close as practical to the reference point with the variance not to exceed +1% or 2% of the reference point and the flow rate determined and compared with the reference flow rate.
The licensee has requested to use the proposed alternative described below for the pumps listed in Table 1. The pumps are ASME Code, Section III, Class 2, and are classified as Group A pumps.
Table 1 Component Description Rated Flow Rated Differential (gallons per Pressure (Feet) minute) 1E21-C002 Low Pressure Core Spray 43 199 (LPCS) and Residual Heat Removal (RHR) A Waterleg Pump 1E12-C003 RHR Loop B/C Waterleg 43 199 Pump 1E51-C003 Reactor Core Isolation 50 130 Cooling (RCIC) Waterleg Pump The CPS, Unit 1, fourth 10-year IST program interval begins on July 1, 2020, and is scheduled to end on June 30, 2030. The applicable ASME OM Code edition for the fourth 10-year IST program interval is the 2012 Edition.
Reason for RR The waterleg pumps operate continuously to keep their supported systems pump discharge header filled with water. Their hydraulic performance is not critical.
In order to perform a quarterly ASME OM Code Group A test on these pumps, they must be isolated from their supported system, which means the main system must be declared inoperable or an abnormal alignment is required to keep the main header pressurized and full of water.
Proposed Alternative Quarterly monitoring of the pumps discharge pressure (i.e., main system header pressure) and bearing vibration will be performed during normal operating conditions in lieu of the ASME OM Code quarterly Group A test. Changes in the supported systems main header pressure and vibration levels identified during testing will be evaluated and trended to assess the waterleg pumps performance. A biennial comprehensive pump test will continue to be performed on the waterleg pumps in accordance with the requirements specified in ISTB-5123, Comprehensive Test Procedure.
In addition to this proposed quarterly testing, each waterleg pumps supported system pump discharge header has instrumentation that continuously monitors the main header pressure and provides an alarm in the main control room when its low pressure setpoint is reached. This will provide indication that the associated waterleg pump is no longer performing its safety function.
The waterleg pumps are also currently being monitored under the CPS, Unit 1, Vibration Monitoring Program.
Each of these waterleg pumps supported system pump discharge header is verified to be sufficiently filled with water in accordance with technical specification (TS) surveillance requirements (SRs) 3.5.1.1 and 3.5.3.1. Any indication that the supported systems pump discharge header piping is not sufficiently filled with water would provide timely indication that the associated waterleg pump's performance has degraded.
NRC Staff Evaluation
The RHR, LPCS, and RCIC waterleg pumps are continuously operating pumps. Their safety function is to keep their respective discharge header piping in a filled condition to prevent water hammer upon the start of the main pump(s) for the supported system(s). The actual output and hydraulic performance of the waterleg pumps are not critical to the safety function, as long as the pumps can maintain their associated discharge header piping full of water.
In lieu of the ASME OM Code-required Group A test, the licensee proposes to monitor the pump discharge header pressures and bearing vibrations on a quarterly basis. In addition to this, there are alarms on the main headers that would alert plant operators of a low-pressure condition indicative of a waterleg pump malfunction or any other condition that allows pressure to degrade (e.g., excessive leakage beyond waterleg pump make-up capabilities). The low-pressure alarm will provide an early detection of a low header pressure. Also, CPS, Unit 1, TS SRs 3.5.1.1 and 3.5.3.1 require periodic verification that the respective RHR/LPCS/RCIC headers are filled with water from the main pump discharge valve to the injection valve. The continuous monitoring of discharge header pressure in the control room and periodic verification that the headers are filled with water will provide reasonable assurance that the waterleg pumps are operable, or that the system leakage has not exceeded the capacity of the waterleg pumps.
In addition, the quarterly vibration measurement of the pump bearings meets the ASME OM Code requirements and will provide the required test results reflecting the mechanical condition of the pumps. Also, the pumps are monitored in the CPS, Unit 1, Vibration Monitoring Program, which exceeds the vibration monitoring requirements in the ASME OM Code. The proposed alternative will therefore provide an acceptable level of quality and safety for waterleg pumps 1E12-C003, 1E21-C002, and 1E51C003.
4.0 CONCLUSION
As set forth above, the NRC staff determined that alternative RR-3201 for CPS, Unit 1, provides an acceptable level of quality and safety for the pumps listed in Table 1. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes the use of the alternative RR- 3201 for CPS, Unit 1, for the fourth 10-year IST program interval which begins on July 1, 2020, and is scheduled to end on June 20, 2030.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable.
Principal Contributor: R. Wolfgang