Letter Sequence Supplement |
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CAC:MF8060, Clarify Application of Setpoint Methodology for LSSS Functions (Open) |
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MONTHYEARGO2-16-096, License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate2016-06-28028 June 2016 License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate Project stage: Request ML16218A3902016-08-0808 August 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Request for Measurement Uncertainty Recapture (Mur) Power Uprate (from 3486 Mwt to 3544 Mwt) Project stage: Acceptance Review GO2-16-124, Response to License Amendment Request, Opportunity to Supplement2016-08-18018 August 2016 Response to License Amendment Request, Opportunity to Supplement Project stage: Supplement ML16243A3662016-09-0101 September 2016 Acceptance of Requested Licensing Action Measurement Uncertainty Recapture Project stage: Acceptance Review ML16246A2812016-09-14014 September 2016 Request for Withholding Information from Public Disclosure, 6/9/16 Affidavit Executed by J. Harrison, GE-Hitachi and 6/14/16 Affidavit Executed by N. Wilmshurst, EPRI, Related to NEDC-33853P, Revision 0 Project stage: Withholding Request Acceptance ML16207A0162016-09-14014 September 2016 Request for Withholding from Public Disclosure - 5/18/16 Affidavit Executed by E. Hauser, Caldon Ultrasonics Technology Center, Cameron Engineering Report ER-1074, Revision 0 Project stage: Other ML16207A0332016-09-14014 September 2016 Request for Withholding from Public Disclosure - 5/18/16 Affidavit Executed by E. Hauser, Caldon Ultrasonics Technology Center, Cameron Engineering Report ER-1049, Revision 3 Project stage: Other ML16302A0392016-10-27027 October 2016 NRR E-mail Capture - Request for Additional Information, Columbia Mur LAR: Fire Protection Project stage: RAI ML16306A2942016-11-0101 November 2016 NRR E-mail Capture - Request for Additional Information, Columbia Mur LAR: Esgb, Coating and FAC, CAC MF8060 Project stage: RAI ML16323A1192016-11-16016 November 2016 NRR E-mail Capture - Eicb RAIs for Columbia Mur Project stage: RAI ML16327A1842016-11-22022 November 2016 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate Project stage: RAI GO2-16-161, Response to Request for Additional Information, Columbia Mur LAR: Esgb, Coating and FAC2016-12-0808 December 2016 Response to Request for Additional Information, Columbia Mur LAR: Esgb, Coating and FAC Project stage: Response to RAI ML17006A0902017-01-0404 January 2017 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate Project stage: RAI ML17006A0922017-01-0404 January 2017 NRR E-mail Capture - Eicb RAIs for Columbia Mur Project stage: RAI GO2-17-015, Energy Northwest - Transmittal of Response to Request for Additional Information, Columbia Mur LAR: Electrical Instrument and Controls Branch (Eicb) and Reactor Systems Branch (Srxb)2017-01-12012 January 2017 Energy Northwest - Transmittal of Response to Request for Additional Information, Columbia Mur LAR: Electrical Instrument and Controls Branch (Eicb) and Reactor Systems Branch (Srxb) Project stage: Response to RAI GO2-17-049, Response to Request for Additional Information, Columbia Mur LAR Evib Rais, Enclosure 22017-02-16016 February 2017 Response to Request for Additional Information, Columbia Mur LAR Evib Rais, Enclosure 2 Project stage: Response to RAI ML17047A7492017-02-16016 February 2017 Response to Request for Additional Information, Columbia Mur LAR Evib Rais Project stage: Request ML17087A5692017-04-12012 April 2017 Request for Withholding Information from Public Disclosure for Columbia Generating Station Project stage: Withholding Request Acceptance 2016-08-18
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Category:Letter type:GO
MONTHYEARGO2-24-109, Summary of Changes and Analysis for Revision 42 of Plant Procedures Manual 13.8.1, Emergency Dose Projection System Operations2024-11-0404 November 2024 Summary of Changes and Analysis for Revision 42 of Plant Procedures Manual 13.8.1, Emergency Dose Projection System Operations GO2-24-110, Summary of Changes and Analysis for Revision 45 of Plant Procedures Manual 13.4.1, Emergency Notification2024-11-0404 November 2024 Summary of Changes and Analysis for Revision 45 of Plant Procedures Manual 13.4.1, Emergency Notification GO2-24-088, Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-24024 September 2024 Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan GO2-24-051, Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements2024-09-23023 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements GO2-24-082, Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-10010 September 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan GO2-24-060, Reply to a Notice of Violation, EA-21-170 and EA-23-0542024-07-30030 July 2024 Reply to a Notice of Violation, EA-21-170 and EA-23-054 GO2-24-070, Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program2024-07-29029 July 2024 Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program GO2-24-063, Notification of Extension to Columbias Fourth 10-Year Interval Inservice Testing Program Plan2024-07-15015 July 2024 Notification of Extension to Columbias Fourth 10-Year Interval Inservice Testing Program Plan GO2-24-057, Notice of Readiness for Supplemental Inspection2024-06-19019 June 2024 Notice of Readiness for Supplemental Inspection GO2-24-056, Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing2024-06-11011 June 2024 Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing GO2-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-13013 May 2024 2023 Annual Radiological Environmental Operating Report GO2-24-050, Annual Environmental Operating Report2024-04-30030 April 2024 Annual Environmental Operating Report GO2-24-042, 2023 Annual Radioactive Effluent Release Report2024-04-22022 April 2024 2023 Annual Radioactive Effluent Release Report GO2-24-044, Voluntary Response to Regulatory Issue Summary 2024-012024-04-11011 April 2024 Voluntary Response to Regulatory Issue Summary 2024-01 GO2-24-034, Supplement to License Amendment Request to Revise Columbia Generating Station Emergency Plan2024-03-20020 March 2024 Supplement to License Amendment Request to Revise Columbia Generating Station Emergency Plan GO2-24-041, Level of Financial Protection - Annual Reporting Requirement2024-03-12012 March 2024 Level of Financial Protection - Annual Reporting Requirement GO2-24-039, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462024-03-11011 March 2024 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-24-036, Presentation Information for Pre-Application Meeting Regarding Columbia’S Replacement Steam Dryer Evaluation Approach for Extended Power Uprate2024-03-11011 March 2024 Presentation Information for Pre-Application Meeting Regarding Columbia’S Replacement Steam Dryer Evaluation Approach for Extended Power Uprate GO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing GO2-24-014, Independent Spent Fuel Storage Installation, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-01-15015 January 2024 Independent Spent Fuel Storage Installation, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-23-019, Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-012023-02-0808 February 2023 Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-01 GO2-22-131, Guarantee of Payment of Deferred Premium2022-12-19019 December 2022 Guarantee of Payment of Deferred Premium GO2-22-122, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-11-28028 November 2022 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-076, Status of License Renewal Commitments2022-10-31031 October 2022 Status of License Renewal Commitments 2024-09-24
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Alex L. Javorik Vice President, Engineering P.O. Box 968, Mail Drop PE04 Richland, WA 99352-0968 Ph. 509-377-8555 F. 509-377-2354 aljavorik@energy-northwest.com 10 CFR 50.90 August 18, 2016 GO2-16-124 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 RESPONSE TO LICENSE AMENDMENT REQUEST - OPPORTUNITY TO SUPPLEMENT
Reference:
- 1. Letter GO2-16-096 from A. L. Javorik (Energy Northwest) to NRC:
License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture (MUR) Power Uprate, dated June 28, 2016 (ADAMS Accession No. ML16183A365)
- 2. E-mail from NRC to L. L. Williams (Energy Northwest), Request for conference call, Columbia MUR LAR list of insufficiencies, within 5 working days from today, dated August 2, 2016
- 3. Letter from NRC to M. E. Reddemann (Energy Northwest),
Supplemental Information Needed for Acceptance of Requested Licensing Action Re: Measurement Uncertainty Recapture Power Uprate Amendment, dated August 8, 2016
Dear Sir or Madam:
By letter dated June 28, 2016 (Reference 1) Energy Northwest submitted a Measurement Uncertainty Recapture license amendment request (LAR) for Columbia Generating Station (Columbia) to revise the operating license and technical specifications to implement an increase in rated thermal power from the current licensed thermal power of 3486 megawatts thermal (MWt) to 3544 MWt.
By e-mail dated August 2, 2016, (Reference 2) Energy Northwest was informed of the current results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of the LAR and concluded that to make an assessment as to the acceptability of the LAR, more information was needed regarding electrical equipment design. By letter dated August 8, 2016, (Reference 3) the NRC detailed the requested information which was discussed during the phone conversation between the NRC staff and Energy
GO2-16-124 Attachment Page 1 of 4 In response to the August 8, 2016 letter, Energy Northwest submits the following responses.
- 1. Emergency Diesel Generators The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the Columbia Generating Station measurement uncertainty recapture power uprate license amendment request (LAR) dated June 28, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16183A365), Section 3.4.5, "Grid Stability Studies," and LAR Enclosure 9, 1 NED0-33853, Revision 0, "Safety Analysis Report for Columbia Generating Station, Thermal Power Optimization," June 2016, Section 6.1, "AC [Alternating Current] Power, and Section 6.1.2, "On-Site Power," and found there is no documentation on emergency diesel generator loading impact due to the power uprate (i.e., the impact of the increased thermal power from 3486 MWt to 3544 MWt on emergency diesel generator loads). Additionally, there is no documentation discussing the LAR's impacts and assessment against battery chargers.
Energy Northwest Response:
Columbia Generating Station's (Columbia's) onsite power system is designed to supply the power requirements of all auxiliary plant loads during normal operation and engineered safety feature (ESF) loads when required to support shutdown and to maintain the unit in a safe condition following a design basis accident.
Alternating current (AC) power to the onsite power system is supplied by (i) the main generator through a 25 kV connection to two auxiliary transformers TR-N1 (4.16 kV) and TR-N2 (6.9 kV) during normal plant operation, (ii) from two General Design Criteria (GDC) 17 offsite power circuits from a 230 kV and 115 kV network interconnection at the startup and backup transformers, TR-S and TR-B, respectively, when the main generator is not available to supply station auxiliaries, or (iii) from standby power system emergency diesel generators dedicated to three divisional (1, 2, 3) load group Class-1E 4.16 kV switchgear buses if the offsite power connections are not available to support emergency core cooling system (ECCS)/ESF design functions as described in the Columbia Final Safety Analysis Report (FSAR).
The two redundant ESF electrical load groups (Division 1 and 2) supplying low pressure ECCS and ESF systems are provided with separate onsite standby power sources (emergency diesel generators), electrical buses, branch circuit distribution cables, pump and valve motor loads for low-pressure core spray (LPCS), low-pressure coolant injection (LPCI), standby service water (SW), control rod drive (CRD), and other ESF functions, associated motor controls, protective relays and other support electrical equipment (including battery chargers supporting the Division 1 and 2 Class1E 125 V and 250 V DC stationary batteries). The third electrical load group supplies power required for the high-pressure core spray (HPCS) ECCS. The HPCS power supply consists of the 4.16 kV HPCS switchgear bus, HPCS pump motor and standby diesel generator, and the associated 480 V HPCS auxiliary distribution system supplying 1
Enclosure 7 is the proprietary version designated as NEDC-33853, Revision 0, "Safety Analysis Report for Columbia Generating Station, Thermal Power Optimization," June 2016
GO2-16-124 Attachment Page 2 of 4 motor-operated valves, and other supporting electrical equipment (including the battery charger supporting the Division 3 Class 1E 125 V DC stationary battery). Note that the Division 3 HPCS dedicated load group 4.16kV switchgear bus does not feature a backup offsite source connection to the 115 kV network.
Each ECCS/ESF (Division 1 and 2) and HPCS (Division 3) load groups capacity to supply connected loads is based upon requirements for normal, transient and accident operating conditions as described in the FSAR.
Emergency operation at the thermal power optimization (TPO) level is achieved by utilizing existing equipment operating at or below equipment nameplate ratings and within the calculated brake-horsepower necessary for the respective ECCS/ESF pump motors and associated valve motors to meet ECCS and ESF performance objectives.
Energy Northwest has reviewed the emergency diesel generator loading calculations and results from the TPO uprate review. This review shows that there will be no reactor power dependent increase in pump motor or valve motor flow or pressure requirements that would result in brake-horsepower drive motor increases. Additionally, the analysis of ECCS system performance is bounded by the 102% analysis of the current licensed thermal power which shows the present standby power system (emergency diesel generators) capacity remains adequate.
As a result, with plant operation at the TPO level, the standby power systems (emergency diesel generators) supplying the Division 1, 2 and 3 load groups will continue to have sufficient capacity to support all required loads necessary for safe shutdown, to maintain a shutdown condition, and to support required ECCS/ESF equipment following a design bases accident.
The AC power requirements for the Division 1, 2, and 3 battery chargers were also reviewed against the FSAR requirement to supply connected loads while simultaneously recharging the associated stationary battery. Similar to the onsite AC power systems' larger power apparatus evaluated above, there are no TPO power level related changes to DC loads that would require higher charger capacities. Therefore, the present battery charger capacity remains adequate.
- 2. AC Power Off-Site and Switchyard Equipment The NRC staff reviewed LAR Enclosure 9,1 NED0-33853, Revision 0, Section 6.1, "AC Power," and Section 6.1.1, "Off-Site Power," and found a lack of information regarding the power uprate's impact on electrical equipment ratings in switchyard. Specifically, the LAR does not discuss what switchyard equipment was reviewed for impacts, how an assessment was made against this equipment (by what analyses or standard), nor does the LAR state a cumulative summary of the impact made, if any, of the power uprate against the switchyard and its equipment.
Energy Northwest Response:
The off-site power analysis included a comparison of the off-site power system components before and after a 1.66 percent MWt power uprate to determine if sufficient
GO2-16-124 Attachment Page 3 of 4 design margin exists to perform its functions at the uprated conditions. The analysis was performed by establishing which of the off-site power systems design parameters change as a result of the uprated conditions and then evaluating those changes relative to the off-site power systems existing capacity. The evaluation considered the existing generator running MW from November 2012 to March 2015. The average summer generator output was determined to be 1158 MWe and the average winter generator output was 1172 MWe. The generator typically operates at approximately 1172 MWe.
Assuming a 1.66% increase in generator output, the generator would provide approximately 1192 MWe which is below the generator rating shown in Table 6.1 of of Reference 1; therefore, the generator capacity is sufficient for the uprated conditions.
The generator and switchyard transformer ratings were previously provided in of Reference 1. The existing plant equipment has been sized to permit nameplate full power operation of the main generator within its capability curve when connected to the Federal Columbia River Transmission System (FCRTS) under normal and abnormal operating conditions.
Operation of Columbia at the TPO level will not require modifications to the generator, bus duct, main transformer, transmission line, or Ashe 500 kV bus power circuit breaker capacity. No changes to associated high voltage structures are required under normal operation or abnormal faulted equipment conditions (as from short circuits). There are no modifications required to the offsite power equipment supporting station service along the qualified GDC-17 circuit paths. There are no TPO level power changes to ECCS and ESF equipment capacity and any incremental increase in brake-horsepower requirements for thermal power related to the condensate system equipment in the turbine generator thermal cycle for power generation remain within the rating of the normal auxiliary and startup transformer, the associated 4.16 kV and 6.9 kV bus duct, the 230 kV transmission line and 230 kV PCB at the Ashe 230 kV bus to support the offsite power connection to TR-S for initial shutdown following a turbine generator trip.
Therefore, the offsite circuit path from the main generator output along the 25 kV iso-phase bus duct through the main transformer bank to the 500 kV Ashe bus power circuit breakers (PCBs), including the 500 kV line and associated 500 kV hard bus connections to Columbias main step up transformers in the transformer yard will continue to support operation at the nameplate output capacity of the unit.
- 3. DC Power The NRC staff reviewed LAR Enclosure 9,1, NED0-33853, Revision 0, Section 6.2, "DC
[Direct Current] Power," and found a lack of information regarding the power uprate's impact on Class 1 E 125 Volt DC electrical loading. The LAR does not also state if a review of the leading edge flow meter's electrical distribution loading was complete and did not provide a summary of those results.
GO2-16-124 Attachment Page 4 of 4 Energy Northwest Response:
The direct current (DC) loading requirements documented in the FSAR and station load calculations were reviewed, and no reactor power-dependent loads were identified. The Class 1E 125 V and 250 V DC power distribution system provides control and motive power for various systems and components (DC valves, protection circuits, instrumentation and controls, etc.)
Typically, these loads are used as inputs for the computation of capacity for distribution equipment, voltage drop for operation of connected equipment, and short circuit current values for selection of protection devices and specification of equipment with adequate withstand ratings. Operation at the TPO level does not increase any load capacity, available short circuit capacity (affecting selection of protective devices) or revise control circuit burden or operating logic (affecting equipment selection or affecting control or periodic testing of connected loads).
There are no changes to the DC system load, voltage drop or short circuit current values required to operate at the TPO level. The plants DC equipment and the design basis analysis of the DC power systems, including the Class 1E 125 V DC and 250 V DC systems, remain adequate and unaffected by this change.
The Leading Edge Flow Meter (LEFM) modification was installed in refueling outage R22 (2015). The LEFM electronics required additional 120 V AC power. The modification was completed in accordance with the station's design modification and work control procedures which require updating associated calculations and drawings that included in a revision to the low voltage loading calculation and the associated AC distribution calculations. All changes to supporting calculations for the LEFM modification were evaluated and found to be within the applicable acceptance criteria.
References
- 1. Letter GO2-16-096 from A. L. Javorik (Energy Northwest) to NRC: License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture (MUR) Power Uprate, dated June 28, 2016
- 2. E-mail from NRC to Energy Northwest: Request for conference call, Columbia MUR LAR list of insufficiencies, within 5 working days from today, dated August 2, 2016
- 3. Letter from NRC to Energy Northwest, Supplemental Information Needed for Acceptance of Requested Licensing Action Re: Measurement Uncertainty Recapture Power Uprate Amendment, dated August 8, 2016