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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
[Table view] |
Text
ENERGY NORTHWEST March 30, 2004 PO. Box 968
- Richland, Washington 99352-0968 G02-04-047 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 EMERGENCY RESPONSE DATA SYSTEM, CHANGE TO DATA POINT LIBRARY
Dear Sir or Madam:
The following information is provided to the NRC in accordance with 10 CFR Part 50, Appendix E, Section VI.3a requirements. This regulation requires, in part, that hardware and software changes that affect the transmitted data points identified in the Emergency Response Data System (ERDS) Data Point Library be submitted to the NRC within 30 days after the changes are completed. On March 3, 2004, the following Meteorological Point IDs were changed:
NRC ERDS Parameter: Wind-Speed 2 was changed from F142AV to F142 NRC ERDS Parameter: Wind-Dir 2 was changed from F143AV to F143 NRC ERDS Parameter: Wind-Speed 1 was changed from F144AV to F144 NRC ERDS Parameter: Wind-Dir 1 was changed from F145AV to F145 NRC ERDS Parameter: Stab-Class 1 was changed from F146AV to F146 Please see the attached ERDS Data Point Library reference file with the changes noted above.
Should you have any questions or desire additional information regarding this matter, please contact Ms. CL Perino at (509) 377-2075.
Respectfully, DW Coleman Manager, Regulatory Programs Mail Drop PE20
Attachment:
as noted cc: BS Mallett - NRC RIV TC Poindexter - Winston & Strawn BJ Benney - NRC NRR RN Sherman - BPA - 1399 NRC Senior Resident Inspector - 988C AOe 9'
/.
DATA POINT LIBRARY REFERENCE FILE Date: 03 March 04 I Reactor Unit: WPP2 Data Feeder: N/A NRC ERDS Parameter: Wind Speed 2 Point ID: F142 I Plant Specific Point Desc.: MET TWR WIND SPEED EL 245' -AVERAGE Generic/Cond Desc.: Wind Speed 2 at the Reactor Site Analog/Digital: A Engr Units/Dig States: MPH Engr Units Conversion: N/A Minimum Instr Range: 0 Maximum Instr Range: 90 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: I How Processed: Average Sensor Locations: MET Tower, at 245' above grade Alarm/Trip Set Points: N/A NI Detector Power Supply N/A Cut-off Power Level:
NI Detector Power Supply N/A Turn-on Power Level:
Instrument Failure Mode: Low Temperature Compensation N For DP Transmitters:
Level Reference Leg: N/A Unique System Desc.: Wind speed at 245' level on the Met Tower 3/4/2004 I W:\EP\ERDSDPrevised.doc
I DATA POINT LIBRARY REFERENCE FILE Date: 03 March 04 Reactor Unit: WP2 Data Feeder: N/A NRC ERDS Parameter: Wind Dir 2 Point ID: F143 Plant Specific Point Desc.: MET TWR WIND DIRECT EL 245' -AVERAGE Generic/Cond Desc.: Wind direction 2 at the Reactor Analog/Digital: A Engr Units/Dig States: DEGREES Engr Units Conversion: N/A Minimum Instr Range: 0 Maximum Instr Range: 540 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: Average Sensor Locations: Met Tower, at 245' above grade Alarm/Trip Set Points: N/A NI Detector Power Supply N/A Cut-off Power Level:
NI Detector Power Supply N/A Turn-on Power Level:
Instrument Failure Mode: Low Temperature Compensation N For DP Transmitters:
Level Reference Leg: N/A Unique System Desc.: Wind direction at 245' level on the Met Tower 3/4/2004 2 W:\EP\ERDS_DP_revised.doc
DATA POINT LIBRARY REFERENCE FILE Date: 03 March 04 I Reactor Unit: WP2 Data Feeder: N/A NRC ERDS Parameter: Wind-Speed 1 Point ID: F144 I Plant Specific Point Desc.: MET TWR WIND SPEED EL 33' -AVERAGE Generic/Cond Desc.: Wind Speed I at the Reactor Site Analog/Digital: A Engr Units/Dig States: MPH Engr Units Conversion: N/A Minimum Instr Range: 0 Maximum Instr Range: 90 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: Average Sensor Locations: MET Tower, at 33' above grade Alarm/Trip Set Points: N/A NI Detector Power Supply N/A Cut-off Power Level:
NI Detector Power Supply N/A Turn-on Power Level:
Instrument Failure Mode: Low Temperature Compensation N For DP Transmitters:
Level Reference Leg: N/A Unique System Desc.: Wind speed at 33' level on the Met Tower 3/4/2004 3 W:\EP\ERDSDP_revised.doc
r-DATA POINT LIBRARY REFERENCE FILE Date: 03 March 04 I Reactor Unit: WP2 Data Feeder: N/A NRC ERDS Parameter: WIND-DIR 1 Point ID: F145 I
Plant Specific Point Desc.: MET TWR WIND DIRECT EL 33' -AVERAGE Generic/Cond Desc.: Wind direction I at the Reactor Analog/Digital: A Engr Units/Dig States: DEGREES Engr Units Conversion: N/A Minimum Instr Range: 0 Maximum Instr Range: 540 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: Average Sensor Locations: MET Tower, at 33'above grade Alarm/Trip Set Points: N/A NI Detector Power Supply N/A Cut-off Power Level:
NI Detector Power Supply N/A Turn-on Power Level:
Instrument Failure Mode: Low Temperature Compensation N For DP Transmitters:
Level Reference Leg: N/A Unique System Desc.: Wind direction at 33' level on the Met Tower 3/4/2004 4 W:\EP\ERDSDP revised.doc
-. f ..- ,
DATA POINT LIBRARY REFERENCE FILE Date: 03 March 04 I Reactor Unit: WP2 Data Feeder: N/A NRC ERDS Parameter: STAB-Class 1 Point ID: F146 I Plant Specific Point Desc.: MET TWR DELTA T EL 245-33' -AVERAGE Generic/Cond Desc.: Air Stability at the Reactor Analog/Digital: A Engr Units/Dig States: DEG F Engr Units Conversion: N/A Minimum Instr Range: -15 Maximum Instr Range: 15 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: P Number of Sensors: 2 How Processed: Average Difference Sensor Locations: MET Tower at 33' and 245' above grade.
Alarm/Trip Set Points: NIA NI Detector Power Supply N/A Cut-off Power Level:
NI Detector Power Supply N/A Turn-on Power Level:
Instrument Failure Mode: Low Temperature Compensation N For DP Transmitters:
Level Reference Leg: N/A Unique System Desc.: Temperature difference between 33' and 245' levels on the MET Tower.
314/2004 5 W:\EP\ERDSDPrevised.doc
