Letter Sequence Response to RAI |
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Category:Letter type:GO
MONTHYEARGO2-24-004, 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 GO2-24-005, 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 GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report 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 GO2-22-110, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor2022-10-17017 October 2022 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-085, Docket No. 50-397, Evacuation Time Estimate Analysis2022-08-30030 August 2022 Docket No. 50-397, Evacuation Time Estimate Analysis GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves2022-07-11011 July 2022 Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves GO2-22-072, Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing2022-07-11011 July 2022 Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-22-062, Registration of Spent Fuel Cask Use2022-05-19019 May 2022 Registration of Spent Fuel Cask Use GO2-22-049, Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors2022-05-10010 May 2022 Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors GO2-22-054, Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report2022-05-0909 May 2022 Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report GO2-22-056, Registration of Spent Fuel Cask Use2022-04-21021 April 2022 Registration of Spent Fuel Cask Use GO2-22-055, 2021 Annual Environmental Operating Report2022-04-20020 April 2022 2021 Annual Environmental Operating Report GO2-22-048, 2021 Annual Radioactive Effluent Release Report2022-04-15015 April 2022 2021 Annual Radioactive Effluent Release Report GO2-22-045, Registration of Spent Fuel Cask Use2022-04-0606 April 2022 Registration of Spent Fuel Cask Use GO2-22-044, Level of Financial Protection - Annual Reporting Requirement2022-03-21021 March 2022 Level of Financial Protection - Annual Reporting Requirement GO2-22-038, Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462022-03-0909 March 2022 Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-22-031, Response to Audit Plan and Online Reference Portal Request2022-02-15015 February 2022 Response to Audit Plan and Online Reference Portal Request GO2-22-011, Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report2022-02-0808 February 2022 Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report GO2-22-001, License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-02-0303 February 2022 License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-012, Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report2022-01-24024 January 2022 Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report 2024-01-08
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{{#Wiki_filter:ENERGY NORTHWEST Sudesh K. Gambhir.Vice President, Technical Services P.O. Box 968, PE04 Richland, WA 99352-0968 Ph. 509.377.8313 I F. 509.377.2354 sgambhir@energy-northwest.com June 5, 2008 G02-08-090 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR CONDENSATE STORAGE TANK TECHNICAL SPECIFICATIONS
References:
1)Letter dated May 2, 2008, CF Lyon (NRC) to JV Parrish (Energy Northwest),."Columbia Generating Station -Request for Additional Information Related to License Amendment Request Associated with Condensate Storage Tank Level (TAC No. MD6i 76))" 2) Letter dated August 8, 2007, SK Gambhir (Energy Northwest) to NRC,"License Amendment Request to Technical Specifications Associated With Condensate Storage Tank Level"
Dear Sir or Madam:
Transmitted herewith in the attachment is Energy Northwest's response to the subject request for additional information (Reference
- 1) regarding the license amendment request (Reference
- 2) to revise Columbia Generating Station Technical Specifications associated with Condensate Storage Tank level.There are no new commitments being made. If you have any questions, please contact MC Humphreys, Licensing Supervisor at (509) 377-4025.I declare under penalty of perjury that the foregoing is true and correct. Executed on the date of this letter.SK ambhir Vice President, Technical.Services Attachments cc: EE Collins, Jr.- NRC RIV CF Lyon- NRC NRR NRC Senior Resident, Inspector/988C RN Sherman -BPA/1 399 WA Horin -'Winston
& Strawn 4c~Df RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR CONDENSATE STORAGE TANK TECHNICAL SPECIFICATIONS Attachment 1 Page 1 of 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Item 1 The application dated August 8, 2007, states "...The level switches are not connected directly to the CSTs but rather on a standpipe located downstream on the suction line in the reactor building..." Please provide a drawing or sketch showing/illustrating the arrangement of the switches and standpipe.
Response See Attachment 2 for a simplified sketch.Item 2 The application dated August8, 2007, states "...Thus, they are influenced by such factors as differential head between the tank and the standpipe (due primarily to flow losses), reactor building temperature, and reactor building pressure.
Previously the calculation did not address the head loss that occurs in the switches when the HPCS pump is drawing water from the CST..." Please provide either: a. A copy of the calculation that determined the new levels for the sensors, or b. A description/summary of the calculation describing the methodology, assumptions and significant parameters (e.g., pressures, temperatures, etc.).The description should be sufficient to support simplified confirmatory calculations by the staff.Response The following is a summary from the calculation describing the methodology, assumptions and significant parameters:
Description The Condensate Storage Tanks (CSTs) are located outside the reactor building, subject to atmospheric pressure and temperature.
The level switches, RCIC-LS-15A/B and HPCS-LS-1A/B are located on a standpipe inside the reactor building since the CSTs are not safety related.Parameters
- Top of suction pipe inside the CST is 446.302 feet elevation.
e Centerline of suction pipe is elevation 445.33 feet.0 Suction pipe diameter is 24 inches with 0.375" wall thickness.
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR CONDENSATE STORAGE TANK TECHNICAL SPECIFICATIONS Attachment 1 Page 2 of 3" Each 5.69 feet of water in a CST contains 67,500 gallons." HPCS-LS-1 A/B and RCIC-LS-15A/B are located on the standpipe in the Reactor Building, nominal elevation 448.25 feet. (Nominal Set point 448.25 feet, highest possible activation 448.38', reference Energy Northwest calculation E/I-02-91
-1011)* The CST sees outside, ambient pressure." The standpipe temperature was assumed to be between 40 and 150 0 F." The CST temperature was assumed to be between 40 and 150 0 F." GE Process Diagram 02E22-04,7,1 gives a HPCS flow of 6856 gpm (bounding flow for purposes of this calculation).
- Pipe resistance value (K) between the CST and the Standpipe is 348.386f, where f is the pipe friction factor for 24" pipe.Assumptions" The standpipe water in the reactor building sees a different ambient pressure than the water in the CST as the RB is kept at a negative pressure relative to its environment.
Appendix D to E/1-02-91
-1011 conservatively calculates this differential pressure to be -3.5 inches water gauge relative to the outside environment taking into account instrument uncertainties.
Thus, zero elevation at the CST is equivalent to a max of 3.5 inches at the standpipe." Ambient pressure difference may be less than 3.5 inches. However, this effect has been compensated for by the addition of 0.6ft (2 tanks) and 0.9ft (1 tank). After switch activation, additional water is. available (up to -1.8 inches depending on flow rate) since it takes time for the suction valve switchover to take place. This additional water volume is ignored for added conservatism." The standpipe water could be at a different temperature than the water in the CST, therefore it is assumed that the worst combinations of CST and Standpipe water temperatures are present (150°F at both tank and switch)." Although flow rate from each CST will be half of the total flow when two CST tanks are available, the analysis will assume all flow is from one CST tank, maximizing vortex height." Friction factor is 120% of Crane "Flow of Fluids" friction factor." Level switches activate at the highest possible point (when determining required level to ensure 135,000 gallons).
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR CONDENSATE STORAGE TANK TECHNICAL SPECIFICATIONS Attachment 1 Page 3 of 3 Method for ensuring 135,000 gallons available" To ensure that 135,000 gallons will be used prior to switchover to the suppression pool, the highest possible activation elevation must be obtained from the instrument uncertainty analysis.
This elevation is a combination of instrument setpoint, tolerances and instrument uncertainty.
This highest possible activation point, per E/1-02-91
-1011, is 448.38 feet." Flow losses are calculated as follows: Flow losses (ft) = KV 2/2g K = pipe resistance V = velocity g = gravity" Using the conservatively higher value of 448.42 feet, the required elevation of water in both tanks is determined as such:-The required water elevation is the highest possible switch activation level (448.42 feet), plus-Flow losses (2.40 ft) between the CST and the standpipe in the reactor building (assume high flow rate and hot water when converting to feet of water column to maximize required elevation), minus-3.5 in (0.29 ft) ambient pressure difference between reactor building and CST, plus-0.6 feet (for conservatism) and 5.69 ft for two tank elevation, or-0.9 feet (for conservatism) and 2(5.69 ft) for one tank elevation.
Required Level (2 tanks) = 448.42 ft + 2.40 ft -0.29 ft + 0.6 ft + 5.69 ft = 456.8 ft Required Level (1 tank) = 448.42 ft +2.40 ft -0.29 ft + 0.9 ft + 11.38 ft = 462.8 ft" The instruments used by operators for verifying minimum Technical Specification (TS) CST level (COND-LI-40A
& 40B) receive level from transmitters actually located on the side of the tanks (COND-LT-40A
& 40B) which have a zero indication equal to 446.5 ft. Therefore, the minimum TS Level as observed on COND-LI 40 A& B would be as follows: 2 Tanks = 456.8 ft -446.5 ft + 0.2 ft (rounded up for readability)
= 10.5 ft 1 Tank = 462.8 ft -446.5 ft + 0.2 ft (rounded up for readability)
= 16.5 ft Sf RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR CONDENSATE STORAGE TANK TECHNICAL SPECIFICATIONS Attachment 2 Page 1 of 1 Simplified CST Suction Schematic ArRe--act Seervice Buuilding Reactor HBuilding Suction.RCIC Suction Suction Condensate Supply}}