|
---|
Category:Code Relief or Alternative
MONTHYEARML23198A3212023-07-27027 July 2023 Authorization and Safety Evaluation for Proposed Alternative RV-1 ML23121A2202023-05-0404 May 2023 Proposed Alternative P-1 Regarding Safeguard Building Sump Pumps ML22077A8412022-03-24024 March 2022 Proposed Alternative SNB-3 for the Snubber Inservice Program Third Interval Extension ML21021A1002021-02-0101 February 2021 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0095 (Covid 19)) ML21013A1282021-01-28028 January 2021 Approval of Proposed Alternative to the Requirements of the ASME Code to Extend the Third Inservice Inspection Interval (EPID L-2020-LLR-0092 (COVID-19)) ML21021A0022021-01-28028 January 2021 Approval of Proposed Alternatives 1A4-1 and 1A4-2 from Certain Requirements of 10 CFR 50.55a for Inservice Inspection of Nuclear Power Plants ML20253A1172020-10-0505 October 2020 Approval of Request for Alternative from Certain Requirements of 10 CFR 50.55a for Operation and Maintenance of Nuclear Power Plants (EPIDs L-2020-LLR-0063, L-2020-LLR-0064, and L-2020-LLR-0065 (COVID-19)) CP-202000431, Relief Request 1A4-1 Supplement - Reactor Vessel (Rv) Upper Head Examinations2020-08-0505 August 2020 Relief Request 1A4-1 Supplement - Reactor Vessel (Rv) Upper Head Examinations ML20196L8232020-07-14014 July 2020 Relief Request SNB-1, Snubber Testing ML20196L8242020-07-14014 July 2020 Relief Request 1A3-2, Inservice Inspection (Isi), Table 1 ML20196L8252020-07-14014 July 2020 Relief Request SNB-1, Snubber Testing, Table 1 ML20196L8262020-07-14014 July 2020 Relief Request V-3, Inservice Testing (IST) ML20196L8292020-07-14014 July 2020 Relief Request 1A3-2, Inservice Inspection (ISI) ML20196L8272020-07-14014 July 2020 Relief Request 1A4-2, Reactor Vessel (Rv) Bottom Mounted Instrumentation (Bmi) Nozzle Penetration Examination ML20196L8302020-07-14014 July 2020 Relief Request V-3, Inservice Testing (Ist), Table 1 CP-202000262, Snubber Testing and Snubber Visual Examinations Relief Request2020-04-10010 April 2020 Snubber Testing and Snubber Visual Examinations Relief Request CP-202000261, Inservice Inspection (ISI) and Inservice Testing (IST) Program Relief Requests2020-04-0707 April 2020 Inservice Inspection (ISI) and Inservice Testing (IST) Program Relief Requests ML17095A2512017-04-0707 April 2017 Request for Alternative 2B3-1 Re Examination of Reactor Vessel Closure Head Penetration Nozzles ML16179A4052016-07-11011 July 2016 Relief Request Nos. B-9, B-3, B-10, and B-11 for Piping Welds, Second 10-year Inservice Inspection Interval ML16074A0012016-03-14014 March 2016 Relief Request 1B3-3, Alternative for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency from Not to Exceed 7 Years to 9 Years for the Third 10-Year Inservice Inspection Interval ML16063A0012016-03-11011 March 2016 Relief Request No. B-15, C-2, and C-4 for Welds in the RPV and Containment Spray and Residual Heat Removal Heat Exchanger Shells, Second 10-year Inservice Inspection Interval ML16011A0732016-01-19019 January 2016 Relief Request T-1; Alternative to the ASME OM Code Frequency Specifications for Inservice Testing for the Third 10-Year IST Interval ML15259A0042015-10-30030 October 2015 Relief Request 1B3-4, Alternative for Reactor Pressure Vessel Head Penetration Weld Inspection Frequency (from 10 to 15 Years), Third 10-Year Inservice Inspection Interval ML15257A2422015-09-18018 September 2015 Relief Request 2A3-1, from ASME Code Section XI Requirements, Risk-Informed Process for Selection of Class 1 and Class 2 Piping Weld Examinations, Third 10-Year Inservice Inspection Interval ML15257A2402015-09-15015 September 2015 Relief Request 2C3-1, from ASME Code, Section XI Requirements Reactor Pressure Vessel Leak-Off Flange for the Third 10-Year Inservice Inspection Interval CP-201500671, Relief Request T-1 for Inservice Testing Program for Application of an Alternative to the ASME OM Code Frequency Specifications, (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date: August 3.2015-06-30030 June 2015 Relief Request T-1 for Inservice Testing Program for Application of an Alternative to the ASME OM Code Frequency Specifications, (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date: August 3. ML15090A1042015-04-0303 April 2015 Relief Requests B-7, B-12, and B-13 - Steam Generator Head-to-Tube Sheet Welds for the Second 10-Year Inservice Inspection Interval ML14087A0662014-04-10010 April 2014 Relief Request No. 1/2E-1 for Containment Electrical Penetrations for the Third 10-Year Inservice Inspection Interval ML14073A5442014-04-0101 April 2014 Relief Request No. B-14 for Reactor Pressure Vessel Hot Leg Nozzle Weld Examinations for the Second 10-Year Inservice Inspection Interval ML13158A0932013-06-26026 June 2013 Relief Request No. E-1 Containment Electrical Penetrations, for the Second 10-Year Inservice Inspection Interval ML13148A4372013-06-26026 June 2013 Relief Request No. P-1 for Pumps and Valves, Third 10-Year Inservice Testing Plan Interval ML13113A3792013-05-0808 May 2013 Relief Request No. V-1, from ASME Code for Operation and Maintenance of Nuclear Power Plants Requirements for Pumps and Valves, for the Third 10-Year Inservice Testing Interval ML13046A3852013-03-19019 March 2013 Relief Request C-2 for the Reactor Pressure Vessel Flange Leak-Off Piping, Third 10-Year Inservice Inspection Interval ML13056A5032013-03-15015 March 2013 Relief Request B-2, Alternative to ASME Code Requirements for Examination of Reactor Vessel Hot-Leg Nozzle Welds, for the Third 10-Year Inservice Inspection Interval CP-201300003, Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010)2013-01-16016 January 2013 Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010) CP-201201384, Response to Request for Additional Information for Relief Request No. E-12012-11-14014 November 2012 Response to Request for Additional Information for Relief Request No. E-1 ML12194A2502012-08-14014 August 2012 Relief Request A-1 for Approval of Risk-Informed Alternative to ASME Code, Section XI for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval ML1131100922011-12-19019 December 2011 Relief Request No. C-9, Reactor Pressure Vessel Flange Leak-off Piping Configuration, Second 10-Year Inservice Inspection Interval ML1126500832011-11-10010 November 2011 Approval of Relief Request Nos. B-10 and B-11 for the Second 10-Year Inservice Inspection Interval CP-201001546, Relief Request No. B-11 for the Second 10 Years ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000)2010-12-15015 December 2010 Relief Request No. B-11 for the Second 10 Years ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000) CP-201001544, Relief Request No. C-9 for the Second 10 Year Interval from 10 CFR 50.55a Inspection Requirements Due to Hardship (Second Interval Start Date: August 13, 2000)2010-12-15015 December 2010 Relief Request No. C-9 for the Second 10 Year Interval from 10 CFR 50.55a Inspection Requirements Due to Hardship (Second Interval Start Date: August 13, 2000) CP-201000890, Relief Request No. C-7 for the Second 10 Year ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000)2010-12-15015 December 2010 Relief Request No. C-7 for the Second 10 Year ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000) ML0928706372009-12-22022 December 2009 Relief Request B-9 for Unit 1 and B-8 for Unit 2 to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination CP-200901227, Revision to Request for Relief to Extend the Unit 1 and 2 in Service Inspection Interval for the Reactor Vessel Weld Examination and Withdrawal of License Amendment Request 09-004 to Add License Condition for Submittal of ISI Informatio2009-09-14014 September 2009 Revision to Request for Relief to Extend the Unit 1 and 2 in Service Inspection Interval for the Reactor Vessel Weld Examination and Withdrawal of License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information an ML0916205482009-07-23023 July 2009 Relief Request P-2, Inservice Testing Plan for Pumps and Valves for Second Interval CP-200801132, Relief Request No. P-2 for the Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval)2008-09-24024 September 2008 Relief Request No. P-2 for the Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval) ML0821301472008-08-22022 August 2008 Request for Relief B-2 for Second 10-Year Inservice Inspection Interval from 10 CFR 50.55a Inspections Requirements Due to Physical Interferences CP-200800927, (Cpnpp), Relief Request B-8 for Unit 1 Second 10 Year ISI Interval & B-6 for Unit 2 Second 10 Year ISI Interval from 10 CFR 50.55a Requirements for Reactor Vessel Hot & Cold Leg Nozzle Weld Examinations (Unit 1 Second Interval Start..2008-07-10010 July 2008 (Cpnpp), Relief Request B-8 for Unit 1 Second 10 Year ISI Interval & B-6 for Unit 2 Second 10 Year ISI Interval from 10 CFR 50.55a Requirements for Reactor Vessel Hot & Cold Leg Nozzle Weld Examinations (Unit 1 Second Interval Start.. ML0805201952008-03-10010 March 2008 Relief Request B-5 for Second 10-Year ISI Interval from 10 CFR 50.55a Requirements for Class 1 Repair/Replacement of Control Rod Drive Mechanism Canopy Seal Welds ML0804306622008-02-29029 February 2008 Request for Relief No. B-4 from Certain Requirements of ASME Code, Section XI for Implementation of the EPRI-PDI Supplement 11 Program and Application of Weld Overlays 2023-07-27
[Table view] Category:Letter
MONTHYEARCP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 IR 05000445/20230042024-01-29029 January 2024 Integrated Inspection Report 05000445/2023004 and 05000446/2023004 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) ML24024A2102024-01-29029 January 2024 Summary of Regulatory Audit Regarding a License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24025A0052024-01-25025 January 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23159A2082023-12-20020 December 2023 Request for Withholding Information from Public Disclosure ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23348A2392023-12-19019 December 2023 Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 ML23333A0872023-12-13013 December 2023 Transmittal of Dam Safety Inspection Report - Public CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23291A4382023-11-30030 November 2023 Notice of Availability of the Draft Plant-Specific Supplement 60, to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Comanche Peak Nuclear Power Plant, Unit Numbers 1 and 2, License Renewal Applica ML23325A0182023-11-30030 November 2023 Schedule Revision for the License Renewal Application Review IR 05000445/20234022023-11-30030 November 2023 NRC Security Inspection Report 05000445/2023402 and 05000446/2023402 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation ML23308A0032023-11-17017 November 2023 Letter to R. Nelson, Executive Director; Achp; Re., Comanche Peak Draft Environmental Impact Statement ML23308A0022023-11-17017 November 2023 Letter to M. Wolfe, Executive Director; Shpo; Re., Comanche Peak Draft Environmental Impact Statement ML23317A3002023-11-13013 November 2023 Letter to R. Sylestine, Chairman, Alabama-Coushatta Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2972023-11-13013 November 2023 Letter to R. Martin, President, Tonkawa Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2872023-11-13013 November 2023 Letter to J. Garza, Chairman, Kickapoo Traditional Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2832023-11-13013 November 2023 Letter to D. Dotson, President, Delaware Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2852023-11-13013 November 2023 Letter to E. Martinez, President, Mescalero Apache Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23306A0302023-11-13013 November 2023 Letter to J. Cernek, Chairman; Coushatta Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2902023-11-13013 November 2023 Letter to M. Pierite, Chairman, Tunica Biloxi Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2982023-11-13013 November 2023 Letter to R. Morrow, Town King, Thlopthlocco Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2842023-11-13013 November 2023 Letter to D. Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2822023-11-13013 November 2023 Letter to D. Cooper, Chairman, Apache Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2962023-11-13013 November 2023 Letter to M. Woommavovah, Chairman, Comanche Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2812023-11-13013 November 2023 Letter to C. Hoskin, Principal Chief, Cherokee Nation; Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2862023-11-13013 November 2023 Letter to J. Bunch, Chief, United Keetoowah Band of Cherokee Indians Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3032023-11-13013 November 2023 Letter to W. Yargee, Chief, Alabama-Quassarte Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2882023-11-13013 November 2023 Letter to L. Johnson, Chief, Seminole Nation of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3012023-11-13013 November 2023 Letter to S. Yahola, Mekko, Kialegee Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2792023-11-13013 November 2023 Letter to B. Gonzalez, Chairman, Caddo Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3022023-11-13013 November 2023 Letter to T. Parton, President, Wichita and Affiliated Tribes Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2892023-11-13013 November 2023 Letter to L. Spottedbird, Chairman, Kiowa Indian Tribe Regarding Comanche Peak Draft Environmental Impact Statement 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 ML23360A6312023-10-26026 October 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the Comanche Peak Nuclear Power Plant Medical Services Drill Evaluated on August 23, 2023 CP-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23263A0242023-09-21021 September 2023 Revision of Schedule for the Environmental Review of the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application 2024-01-31
[Table view] |
Text
May 4, 2023 COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 - AUTHORIZATION AND SAFETY EVALUATION FOR PROPOSED ALTERNATIVE P-1 (EPID L-2022-LLR-0058)
LICENSEE INFORMATION Recipients Name and Address: Mr. Ken J. Peters Senior Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Vistra Operations Company LLC Comanche Peak Nuclear Power Plant 6322 N FM 56 P.O. Box 1002 Glen Rose, TX 76043 Licensee: Vistra Operations Company LLC (Vistra OpCo)
Plant Name and Unit: Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (Comanche Peak, Units 1 and 2)
Docket Nos. 50-445 and 50-446 APPLICATION INFORMATION Submittal Date: July 20, 2022 Submittal Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML22201A555 Supplement Date: December 7, 2022 Supplement ADAMS Accession No. ML22342B279 Applicable Inservice Testing (IST) Program Interval and Interval Start/End Dates:
Comanche Peak, Units 1 and 2, fourth 10-year interval IST program start date are August 3, 2023, and are scheduled to end on August 2, 2033.
Alternative Provision: The applicant submitted Proposed Alternative P-1 for Comanche Peak, Units 1 and 2, under Title 10 of the Code of Federal Regulations (10 CFR),
paragraph 50.55a(z)(2), on the basis that compliance with the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants (ASME OM Code) as incorporated by reference in 10 CFR 50.55a, Codes and standards, would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
Proposed Duration of Alternative: The licensee requests that this alternative be authorized for the Comanche Peak, Units 1 and 2, fourth 10-year interval IST program.
Applicable Code Edition and Addenda: ASME OM Code, Division 1, Section IST, 2017 Edition, as incorporated by reference in 10 CFR 50.55a, for the fourth 10-year interval IST program at Comanche Peak, Units 1 and 2.
Applicable Components and or System
Description:
The Vents and Drains System Safeguards Building Sump Pumps (SBSPs):
CP1-WPAPSS-01 CP2-WPAPSS-01 CP1-WPAPSS-02 CP2-WPAPSS-02 CP1-WPAPSS-03 CP2-WPAPSS-03 CP1-WPAPSS-04 CP2-WPAPSS-04 Applicable IST Requirements:
ASME OM Code, subsection ISTB, Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power Plants - Pre-2000 Plants, paragraph ISTB-5200, Vertical Line Shaft Centrifugal Pumps, subparagraph (a), Duration of Tests, sub subparagraph (1) states that For the Group A test and the comprehensive test, after pump conditions are as stable as the system permits, each pump shall be run at least 2 min. At the end of this time at least one measurement or determination of each of the quantities required by Table ISTB-3000-1 shall be made and recorded.
ASME OM Code, subsection ISTB, paragraph ISTB-3540, Vibration, paragraph (b), states that On vertical line shaft pumps, measurements shall be taken on the upper motor-bearing housing in three approximately orthogonal directions, one of which is the axial direction.
ASME OM Code, subsection ISTB, paragraph ISTB-5221, Group A Test Procedure, states in part that 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. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph.
ASME OM Code, subsection ISTB, paragraph ISTB-5223, Comprehensive Test Procedure, states in part that Comprehensive 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. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph.
Brief Description of the Proposed Alternative:
The licensee proposes an alternative to the requirements of the ASME OM Code to test the SBSPs to ensure that the pumps start on the proper level switch actuation, are capable of delivering the required flow to the waste holdup tank (WHT), and have a satisfactory vibration reading. The SBSP test will be conducted by pumping fluid while measuring flow and vibration (only in one direction). The licensee has proposed not to perform differential pressure measurements due to the potential for excessive radiation exposure to plant personnel.
The licensee states that the sump will be filled to a predetermined level, and the SBSPs will operate until the automatic low-level cutoff switch actuates. The sump will be pumped down rapidly (approximately 50 seconds) by one SBSP. Suction pressure will vary as sump level
changes; therefore, the 2-minute stabilization time and differential pressure measurement are not achievable. The SBSP test will require pumping the same quantity of fluid along a repeatable system path while measuring flow and vibration. Baseline reference values shall be established for flow and vibration. Alert and Required Action Limits for vibration will be established and maintained per the ASME OM Code, table ISTB-5221-1, Vertical Line Shaft Centrifugal Pump Test Acceptance Criteria, for vertical line shaft centrifugal pumps. Vibration will be measured in a single direction due to the short pump run and the ability to acquire a single vibration reading during this time period. The acceptance criteria for flow will be greater than the design flow of 50 gallons per minute (gpm). The flowrate delivered will be trended to detect pump degradation and to ensure the SBSPs have adequate design margin.
The licensee states that U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.175, An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing, August 1998 (ML003740149) will be used to define the SBSPs as low significant safety components (LSSCs).
For additional details on the licensees request, please refer to the documents located at the ADAMS Accession Nos. identified above.
STAFF EVALUATION The SBSPs are vertical line shaft centrifugal pumps that are included in the risk-informed IST (RI-IST) plan for Comanche Peak, Units 1 and 2, and will remain in the RI-IST plan for the fourth 10-year interval IST program. As described in the letter dated December 7, 2022, the SBSPs will detect and mitigate passive failures in the emergency core cooling system and containment spray system following a postulated loss-of-coolant accident and prevent flooding of the safety-related systems. These pumps are classified as LSSCs in accordance with the licensees RI-IST plan, and have a 6-year staggered test frequency. The staggered test frequency results in one SBSP per unit tested every 18 months.
The SBSPs are classified as Group A pumps per the ASME OM Code at Comanche Peak, Units 1 and 2. ASME OM Code, subsection ISTB, paragraph ISTB-5200(a)(1), requires that for the Group A test and the comprehensive test, after pump conditions are as stable as the system permits, each pump shall be run at least 2 minutes. At the end of this time, at least one measurement or determination of each of the quantities required by [ASME OM Code, subsection ISTB,] Table ISTB-3000-1, shall be recorded.
The licensee requested an alternative to the 2-minute requirement for testing the SBSPs with the following bases:
- 1. The Safeguards Building sumps only contain sufficient water inventory for 50 seconds of pump run at 80 percent or greater design flow.
- 2. The SBSPs are not designed with a recirculation line to allow a pump to be run continuously at design flow conditions.
- 3. Direct access to the SBSPs would cause a significant burden because they are located inside the sump with the sump covered by 1 inch-thick steel plate.
- 4. Operating the pumps for greater than 50 seconds would require opening the sump and running water from a demineralized water source with temporary hoses. The resources
estimated to remove the steel plate, run demineralized water, and reestablish the design configuration are approximately 50 person-hours for each pump test versus approximately 9 person-hours for the proposed pump run of approximately 50 seconds.
Based on its review, the NRC staff finds that performance of the ASME OM Code-required test for the SBSPs at Comanche Peak, Units 1 and 2, would result in a hardship without a compensating increase in the level of quality or safety. In addition, the test would result in significant person-hours in potentially contaminated sump areas.
ASME OM Code, subsection ISTB, paragraphs ISTB-5221 and ISTB-5223, require that testing be performed where either pump flow or differential pressure is set, and the other parameter measured, recorded, and compared to its reference value. The licensee requested an alternative to these specific requirements of paragraphs ISTB-5221 and ISTB-5223 because, in the present design, there is no recirculation line from the discharge header back to the sumps.
Further, there are no installed in-line pressure and flow instruments on the pump suction or discharge. The NRC staff finds that imposing the ASME OM Code-required test for the SBSPs at Comanche Peak, Units 1 and 2, would result in a hardship without a compensating increase in the level of quality or safety because it would require major piping modifications and installation of in-line pressure and flow instruments in the potentially contaminated sump area.
ASME OM Code, subsection ISTB, paragraph ISTB-3540(b), requires that for vertical line shaft pumps, [vibration] measurements shall be taken on the upper motor-bearing housing in three approximately orthogonal directions, one of which is the axial direction. The licensee stated that direct access to the SBSPs would involve a significant burden because the pumps are inside the sump that is covered by 1-inch-thick steel plate with only the motors accessible to workers.
These are small motors with only one location available for vibration measurement (i.e., motor inboard horizontal). As such, the licensee proposed to collect vibration measurements in the motor inboard horizonal direction, which is similar to that employed during the third 10-year interval IST program for Comanche Peak, Units 1 and 2. The licensee noted that the 1-inch thick steel plate will dampen any vibrations from these small motors. Therefore, taking vibration in three directions per the ASME OM Code would not provide significant information beyond the proposed single measurement. With respect to the single vibration measurement, the NRC staff finds additional vibration readings would not provide significant information, and installing additional vibration locations on these small motors would result in a hardship without a compensating increase in the level of quality and safety.
Because of the burden and hardship of performing the SBSP test in accordance with the ASME OM Code, subsection ISTB requirements in paragraphs ISTB-5200(a)(1), ISTB-5221, ISTB-5223, and ISTB-3540(b), the licensee proposed an alternative test as described above and, in the subsection, Full Description of the Proposed Alternative, in the attachment to the proposed alternative dated July 20, 2022.
In Proposed Alternative P-1, the licensee requests to test the SBSPs to ensure that the pumps start on the proper level switch actuation, are capable of delivering the required flow to the WHT, and have a satisfactory vibration reading. The flow path to the WHT has a greater system resistance than the normal lineup due to the piping configuration at Comanche Peak, Units 1 and 2. Pumping 50 gpm or more to the WHT demonstrates that adequate head was developed to overcome system resistance with greater confidence that the ASME OM Code requirements for operational readiness of the SBSPs have been met. The licensee noted that the required head to pump to the WHT is greater than the required head to discharge to the floor drain tank, which is the normal lineup. The NRC staff finds that this proposed alternative test provides
reasonable assurance that the SBSPs are capable of performing their safety functions.
Therefore, the NRC staff finds this proposed alternative test for the SBSPs to be acceptable.
Based on the above, the NRC staff finds that compliance with the ASME OM Code, subsection ISTB requirements in paragraphs ISTB-5200(a)(1), ISTB 3540(b), ISTB-5221, and ISTB-5223 for the SBSPs at Comanche Peak, Units 1 and 2, would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC staff also finds that the proposed alternative test provides reasonable assurance that the SBSPs will be operationally ready to perform their safety functions at Comanche Peak, Units 1 and 2.
CONCLUSION The NRC staff has determined that complying with the specified requirements described in the licensees request referenced above would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The proposed alternative provides reasonable assurance that the Comanche Peak, Units 1 and 2, SBSPs are operationally ready.
The NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(2).
The NRC staff authorizes the use of Proposed Alternative P-1 at Comanche Peak, Units 1 and 2, for the fourth 10-year interval IST program for Comanche Peak, Units 1 and 2, which begins on August 3, 2023, and ends on August 2, 2033.
All other ASME OM Code requirements for which an alternative was not specifically requested and authorized remain applicable.
Principal Contributors: Gurjendra Bedi Thomas Scarbrough Date: May 4, 2023 Digitally signed by Jennifer L. Jennifer L. Dixon-Herrity Date: 2023.05.04 Dixon-Herrity 07:52:26 -04'00' Jennifer Dixon-Herrity, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc: Listserv
ML23121A220 *via email NRR-028 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA* NRR/DEX/EMIB/BC*
NAME DGalvin PBlechman SBailey DATE 5/3/2023 5/3/2023 4/14/2023 OFFICE NRR/DORL/LPL4/BC*
NAME JDixon-Herrity DATE 5/4/2023