Letter Sequence Response to RAI |
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MONTHYEARML18156A1312018-05-29029 May 2018 Proposed Alternative Request P-06 for 'C' Charging Pump Test Project stage: Request ML18186A4282018-07-0505 July 2018 Acceptance Review Determination (E-mail 7/5/2018), Proposed Alternative Request P-06 for 'C' Charging Pump Test Project stage: Acceptance Review ML18213A1152018-08-0101 August 2018 Request for Additional Information Alternative Request P-06 'C' Charging Pump (08/01/2018 E-mail from R. Guzman to M. Whitlock) Project stage: RAI ML18235A3212018-08-17017 August 2018 Response to Request for Additional Information for Proposed Alternative Request P-06 for 'C' Charging Pump Project stage: Response to RAI ML18275A0122018-10-0404 October 2018 Alternative Request P-06 for the 'C' Charging Pump Test Frequency Project stage: Other 2018-07-05
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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information ML23124A3642023-04-20020 April 2023 Response to Request for Additional Information for Spring 2022 Steam Generator Tube Inspection Report ML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI ML21259A0852021-09-15015 September 2021 North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition ML21209A7622021-07-26026 July 2021 Response to Request for Additional Information for Alternative Request V-01 - Proposed Request for Alternative Frequency to Supplemental Valve Positionn Verification Testing Requirements ML21153A4132021-06-0202 June 2021 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML21147A4772021-05-27027 May 2021 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Final Supplemental Response ML21140A2992021-05-20020 May 2021 Response to Request for Additional Information for Proposed License Amendment Request to Add an Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident ML21133A2852021-05-13013 May 2021 Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21105A4332021-04-15015 April 2021 Final Supplemental Response to NRC Genetic Letter 2004-02 on Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pressurized-Water Reactors ML21105A4822021-04-15015 April 2021 Response to Request for Additional Information for Proposed License Amendment Request to Revise the Millstone, Unit 2 Technical Specification for Steam Generator Inspection Frequency ML21081A1362021-03-19019 March 2021 Response to Request for Additional Information for Alternative Request RR-05-06 - Inspection Interval Extension for Steam Generator Pressure-Retaining Welds and Full-Penetration Welded Nozzles ML20274A3462020-09-30030 September 2020 Response to Request for Additional Information for License Amendment Request to Revise Battery Survillance Requirements ML20261H5982020-09-17017 September 2020 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20252A1912020-09-0404 September 2020 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Deferral of the Millstone Unit 3 Steam Generator Inspections ML20209A5362020-07-27027 July 2020 Response to Request for Additional Information Regarding Relief Request IR-3-33 for Limited Coverage Examinations Performed in the Second Period of the Third 10-Year Inspection Interval ML20079K4242020-03-19019 March 2020 Response to Request for Additional Information for License and Request to Revise TS 3.8.1.1, A.C Sources - Operating, to Support Maintenance and Replacement of the Millstone Unit 3 'A' Reserve Station Service Transformer and 345 Kv South Bu ML20076C8332020-03-16016 March 2020 Response to Request for Additional Information (E-mail Dated 3/16/2020) Alternative Request IR-4-03 for Use of Alternative Non-Code Methodology ML20048A0192020-02-11011 February 2020 Response to Request for Additional Information for License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of a Reserve Station Service Transformer and 345 Kv South Bus. ML20042D9962020-02-10010 February 2020 Response to March 12, Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal ML19284A3972019-10-0303 October 2019 Response to NRC Request for Additional Information on License Amendment Request to Adopt 10 CFR 50.69 ML19249B7672019-08-29029 August 2019 Enclosure 1 - Millstone, Units 2 and 3 and ISFSI; North Anna, Units 1 and 2 and ISFSI; and Surry, Units 1 and 2 and ISFSI - Response to EAL Scheme Change RAIs ML19092A3322019-03-27027 March 2019 Response to Request for Additional Information for Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage ML19011A1112018-12-18018 December 2018 Supplement to the Flooding Hazard Reevaluation Report in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding ML18340A0282018-11-29029 November 2018 Response to Request for Additional Information for Proposed Technical Specifications Changes for Spent Fuel Pool Storage and New Fuel Storage ML18302A1202018-10-22022 October 2018 Response to Request for Additional Information for License Amendment Request to Revise the Technical Specification for Control Building Ventilation Inlet Instrumentation ML18235A3212018-08-17017 August 2018 Response to Request for Additional Information for Proposed Alternative Request P-06 for 'C' Charging Pump ML18225A0662018-08-0606 August 2018 Response to Request for Additional Information for Alternative Requests Associated with the In-Service Testing Program for Pumps, Valves, and Snubbers Fifth and Fourth 10-Year Interval Updates ML18205A1762018-07-19019 July 2018 Response to Request for Additional Information for Alternative Requests Associated with the In-Service Testing Program for Pumps, Valves, and Snubbers Fifth and Fourth 10-Year Interval Updates for Units 2 and 3 ML18170A0932018-06-14014 June 2018 Response to Request for Additional Information Regarding License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals ML18151A4672018-05-24024 May 2018 Response to Request for Additional Information Regarding License Amendment Request to Revise Integrated Leak Rate Test (Typed a) and Type C Test Intervals ML17338A0572017-11-22022 November 2017 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML17300A2202017-10-24024 October 2017 Response to Information Need Request Regarding Mitigating Strategies Assessment (MSA) Report for Flooding ML17053A1062017-02-16016 February 2017 Response to Request for Additional Information Regarding Proposed Alternative Requests RR-04-24 and IR-3-30 for Elimination of the Reactor Pressure Vessel Threads in Flange Examination ML17038A0052017-01-31031 January 2017 Response to RAI Regarding End of Cycle 23 and End of Cycle 17 Steam Generator Tube Inspection Reports, CAC MF8507 & MF8506 ML16365A0362016-12-22022 December 2016 Response to March 12, 2012 Information Request High Frequency Sensitive Equipment Functional Confirmation for Recommendation 2.1 ML16365A0322016-12-21021 December 2016 Response to March 12, 2012 Information Request, Spent Fuel Pool Seismic Evaluation for Recommendation 2.1 ML16321A4542016-11-10010 November 2016 Connecticut and Virginia Electric & Power Company Response to Request for Additional Information Revision 22 of Quality Assurance Program Description Topical Report ML16312A0642016-11-0101 November 2016 Units 1 & 2, Surry, Units 1 & 2, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML16294A2702016-10-18018 October 2016 Response to Request for Additional Information for License Amendment Request Regarding Realistic Large Break Loss of Coolant Accident Analysis - RAI Questions 1 Through 3 ML16291A5082016-10-12012 October 2016 Response to Follow Up Request to Revise ECCS TS 3/4.5.2 and FSAR Chapter 14 to Remove Charging ML16202A0402016-07-14014 July 2016 Response to Request for Additional Information Regarding Spent Fuel Pool Heat Load Analysis License Amendment Request ML16188A1962016-06-30030 June 2016 NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations ML16182A0372016-06-27027 June 2016 Response to Request for Additional Information for License Amendment Request to Revise ECCS TS 3/4.5.2 and FSAR Chapter 14 to Remove Charging ML16159A2382016-06-0101 June 2016 Isfsis, Response to NRC Request for Information Security Plan, Training and Qualification Plan, Safeguards Contingency Plan and ISFSIs Security Program, Rev. 21 ML16148A7012016-05-20020 May 2016 Response to Request for Additional Information Regarding ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval 2023-08-30
[Table view] |
Text
5000 Dominion Boulevard. Glen Allen, VA 23060 ~ Dominion DominionEnergy.com pi' Energy August 17, 2018 U.S. Nuclear Regulatory Commission Serial No.18-310 Attention: Document Control Desk NRA/WDC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR PROPOSED ALTERNATIVE REQUEST P-06 FOR 'C' CHARGING PUMP By letter dated May 29, 2018, Dominion Energy Nuclear Connecticut, Inc. (DENG) requested Nuclear Regulatory Commission (NRC) approval of the proposed alternative request associated with the 'C' Charging Pump for Millstone Power Station Unit 3 (MPS3). In an email dated August 1, 2018, the NRC transmitted a request for additional information (RAI) related to the alternative request. The attachment to this letter provides DENC's response to the NRC's RAI.
If you have any questions regarding this submittal, please contact Michael Whitlock at (804) 273-3123.
Sincerely, Mark D. Sartain Vice President - Nuclear Engineering & Fleet Support
Attachment:
Response to Request for Additional Information for Proposed Alternative Request P-06 for 'C' Charging Pump Commitments made in this letter: None i
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Serial No.18-310 Docket No. 50-423 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Richard V. Guzman Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C 2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.18-310 Docket No. 50-423 ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR PROPOSED ALTERNATIVE REQUEST P-06 FOR 'C' CHARGING PUMP MILLSTONE POWER STATION 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
Serial No.18-310 Docket No. 50-423 Attachment, Page 1 of 5 By letter dated May 29, 2018, Dominion Energy Nuclear Connecticut, Inc. (DENG) requested Nuclear Regulatory Commission (NRG) approval of the proposed alternative request associated with the 'C' Charging Pump for Millstone Power Station Unit 3 (MPS3). In an email dated August 1, 2018, the NRG transmitted a request for additional information (RAJ) related to the alternative request. This attachment provides DENC's response to the RAJ.
RAI - P-06-1 The letter for proposed alternative request P-06 states, in part:
Realignment of the charging pumps to support required quarterly testing results in pressure, temperature and flow transients on the reactor coolant pump (RCP) seals, which have been identified as contributors to RCP seal degradation.
DENG recently identified a shift in the RCP seal differential temperature trend, which is a precursor to seal degradation. The RCP seals remain capable of performing their safety function. RCP seal replacement is planned at the next refueling outage. However, to minimize challenges to the RCP seals and to support continued plant operation, DENG requests expedited review of this proposed alternative by October 18, 2018.
It is the NRG staff's understanding that the new RCP seals will not be degraded by the realignment of the charging pumps. Explain why this alternative request is required for the entire fourth 10-year /ST interval instead of until the new RCP seals are installed on all RCPs.
DENC Response The RCP seals are not a part of the alternative request except to establish a basis for the request for an expedited review. The increased unavailability of the High Pressure Safety Injection system* function during performance of the quarterly surveillance test without a compensating increase in quality or safety is the reason for the alternative request and is applicable for the remainder of the life of the plant.
RAI - P-06-2 It is stated in the proposed alternative request that, "if it becomes necessary to use 3CHS*P3C, a quarterly Group A test will be performed prior to declaring the pump OPERABLE."
ISTB-3300(e)(2) in the 2001 Edition of the ASME OM Code states that, "reference values shall be established within +/- 20% of pump design flow 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-3300(e)(2) in the 2012 Edition of the ASME OM Code states that, "reference values shall be established at the
Serial No.18-310 Docket No. 50-423 Attachment, Page 2 of 5 comprehensive pump test flow rate for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate can be established at the highest practical flow rate." State whether the Group A test is performed at the comprehensive pump test flow rate. If it is not, explain why not and provide the Group A test flow rate and the pump curve for 3CHS*P3C.
DENC Response The Group A test is not performed at the comprehensive pump test flow rate. The quarterly Group A test reference flow is 67.2 gpm, which is limited by the capacity of the fixed resistance recirculation line. The comprehensive test, which is performed during reactor cavity fill while in Mode 6, is through the common discharge header feeding the four cold leg injection lines and has a reference flow rate of 505.8 gpm. It is not possible to perform the quarterly Group A test at or near the comprehensive reference flow rate since this flow rate cannot be achieved at normal reactor coolant system operating pressure.
A copy of the charging pump performance curve from the Final Safety Analysis Report (FSAR) is attached.
RAI - P-06-3 It is stated in the proposed alternative request that, "when idle, the pump bearings will not be subjected to wear and therefore would not be expected to degrade."
Pump 3CHS*P3C can sit idle for up to two years between comprehensive pump tests if it is not connected to a bus and tested during that two year time period. During that idle time, pump bearings can develop flat spots from inactivity. Describe what maintenance activities will be performed to prevent bearing flat spots from developing.
DENC Response Review of the component design confirms both the motor and pump bearings are journal type bearings and not roller type. Flat spots are not a significant concern on journal type bearings. A potential concern for long term reliability with allowing the charging pump to remain idle for extended periods of time (up to 2 years) is lack of lubrication in the motor and pump bearings. Preventive maintenance activities will be revised to include an annual requirement to manually rotate the pump and motor.
RAI - P-06-4 It is stated in the alternative request, "Should plant operators elect to align 3CHS*P3C during an abnormal or emergency event, performance of a quarterly test may be deferred until after plant conditions are stabilized."
Serial No. 18-31 O Docket No. 50-423 Attachment, Page 3 of 5 Explain how 3CHS*P3C can be aligned during an abnormal or emergency event without the performance of a quarterly test, when it is stated in the alternative request that a quarterly test is required to be performed prior to declaring the pump OPERABLE.
DENC Response DENG will perform the quarterly Group A test prior to declaring 3CHS*P3C OPERABLE. The statement in the submittal, "Should plant operators elect to align 3CHS*P3C during an abnormal or emergency event, performance of a quarterly test may be deferred until after plant conditions are stabilized." was included to recognize that there may be unanticipated emergency situations that are beyond the design basis of the plant (i.e., loss of two OPERABLE charging pumps) where operators may need to take immediate action and place the pump in service without testing in order to protect the health and safety of the public. In all other situations, DENG will perform the quarterly Group A test prior to declaring the pump operable.
RAI - P-06-5 It is stated in the alternative request:
Additionally, MPS3 TS Bases for entry into the 14-day allowed outage time (TS 3.8.1.1b ACTION) for an emergency power source out of service require 3CHS*P3C be available to replace an inservice charging pump, if necessary. The proposed alternate testing plan does not affect the availability of the spare pump to fulfill these functions. Charging pump 3CHS*P3C would be considered available provided a current satisfactory comprehensive test is documented.
TS 3.8.1.1b ACTION states, in part, that "all required systems, subsystems, trains, components and devices that depend on the remaining OPERABLE diesel generator as a source of emergency power are OPERABLE ... " Discuss whether or not a Group A test will be performed on 3CHS*P3C prior to it replacing an inservice charging pump, in order to declare it OPERABLE. If not, explain why not.
DENC Response MPS3 TS Bases requires the charging pump and charging pump cooling pump in operation be powered from the bus not associated with the out of service diesel generator. In addition, the spare charging pump will be available to replace an inservice charging pump, if necessary.
DENG will perform the quarterly Group A test prior to declaring 3CHS*P3C OPERABLE when replacing an inservice charging pump that needs to be removed from service. If the charging pump associated with the OPERABLE diesel generator becomes inoperable, applicable TS ACTIONS will apply until the Group A test is performed and 3CHS*P3C is declared OPERABLE.
Serial No.18-310 Docket No. 50-423 Attachment, Page 4 of 5 RAI - P-06-6 In the alternative request, pump 3CHS*P3C is designated as a "spare" pump. Currently in licensee documents, pump 3CHS*P3C is designated as a "swing" pump. Discuss the differences between a swing pump and a spare pump, and any effect on protecting the plant if the pump is changed from a swing pump to a spare pump.
DENC Response The ASME OM Code Subsection ISTA 2000 and ISTB 2000 do not provide definitions for the terms "spare" or "swing". DENG has used the terms "swing" and "spare" interchangeably to describe 3CHS*P3C in licensing documents. A change to the FSAR has been prepared to consistently refer to the pump as a "spare." The change is editorial only and has no effect on protecting the plant. As stated in the alternative request, the third "spare" charging pump has no assigned FSAR Chapter 15 accident mitigation function.
Serial No.18-310 Docket No. 50-423 Attachment, Page 5 of 5 MPS-3 FSAR FIGURE 6.3-4 CHARGING PUMP CURVE ASSUMED FOR SAFETY ANALYSIS sano. I I I ,
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