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Category:Letter
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 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 ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information 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 ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position 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 IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 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 IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 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) ML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 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 IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 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 ML23206A2442023-07-25025 July 2023 Energy Northwest Columbia Generating Station, Response to Apparent Violation in NRC Inspection Report 05000397/2023092; EA-23-054 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 ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance ML23163A2502023-06-12012 June 2023 Summary of Changes and Analysis for Revision 41 of Plant Procedures Manual 13.8.1 Emergency Dose Projection System Operations GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report ML23157A2702023-06-0101 June 2023 4-2022-011 -022 Letter - OI Closure to Licensee IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 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 IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 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 IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 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 ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection 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 ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B 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 2024-01-08
[Table view] Category:Inspection Report
MONTHYEARIR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 IR 05000397/20220062023-03-0101 March 2023 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2022006) IR 05000397/20234022023-02-23023 February 2023 NRC Security Baseline Inspection Report 050003972023402 (Full Report) IR 05000397/20220042023-01-23023 January 2023 Integrated Inspection Report 05000397/2022004- 4th Quarter IR 05000397/20224062023-01-18018 January 2023 NRC Security Baseline Inspection Report 05000397/2022406 (Cover Letter) IR 05000397/20224042023-01-17017 January 2023 Amended - Columbia Generating Station - Security Baseline Inspection Report 05000397/2022404 (Public) IR 05000397/20224012022-11-12012 November 2022 Cyber Security Inspection Report 05000397/2022401 (Cover Letter Only) IR 05000397/20220032022-10-31031 October 2022 Integrated Inspection Report 05000397/2022003 IR 05000397/20224052022-09-15015 September 2022 Material Control and Accounting Program Inspection Report 05000397 2022405 Cover Ltr Only IR 05000397/20224032022-09-0101 September 2022 NRC Security Inspection Report 05000397/2022403 (Full Report) IR 05000397/20220022022-07-28028 July 2022 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000397/2022002 and 07200035/2022001 IR 05000397/20220102022-06-30030 June 2022 Design Basis Assurance Inspection (Team) Inspection Report 05000397/2022010 IR 05000397/20224022022-06-23023 June 2022 Security Baseline Inspection Report 05000397/2022402 IR 05000397/20220012022-04-29029 April 2022 Integrated Inspection Report 05000397/2022001 IR 05000397/20210062022-03-0202 March 2022 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2021006) IR 05000397/20210042022-01-20020 January 2022 Integrated Inspection Report 05000397/2021004 IR 05000397/20214012022-01-19019 January 2022 Security Baseline Inspection Report 05000397/2021401 IR 05000397/20210902022-01-13013 January 2022 NRC Inspection Report 05000397/2021090 and Preliminary White Finding IR 05000397/20214202021-11-0404 November 2021 Security Baseline Inspection Report-Cover Letter - 05000397/2021420 IR 05000397/20210122021-11-0303 November 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000397/2021012 IR 05000397/20210032021-11-0202 November 2021 Integrated Inspection Report 05000397/2021003 IR 05000397/20210112021-09-21021 September 2021 Triennial Fire Protection Inspection Report 05000397/2021011 IR 05000397/20214022021-09-0909 September 2021 Security Baseline Inspection Report 05000397/2021402 IR 05000397/20210102021-08-29029 August 2021 Biennial Problem Identification and Resolution Inspection Report 05000397/2021010 IR 05000397/20210022021-08-0202 August 2021 Integrated Inspection Report 05000397/2021002 IR 05000397/20210132021-07-20020 July 2021 NRC Post - Approval Site Inspection for License Renewal (Phase I) Inspection Report 05000397/2021013 ML21141A1752021-05-24024 May 2021 Notification of NRC Design Bases Assurance Inspection (Programs) (05000397/2021012) and Initial Request for Information IR 05000397/20210012021-05-0707 May 2021 CGS2021001-IR-NH, Columbia Generating Station - Integrated Inspection Report 05000397/2021001 IR 05000397/20213012021-04-21021 April 2021 NRC Exam Report 05000397/2021301 IR 07200035/20214012021-03-25025 March 2021 Independent Spent Fuel Storage Installation Nrc Security Inspection Report 07200035/2021401 IR 05000397/20200062021-03-0303 March 2021 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2020006) IR 05000397/20200042021-02-0303 February 2021 Integrated Inspection Report 05000397/2020004 IR 05000397/20200032020-12-21021 December 2020 Revised Integrated Inspection Report 05000397/2020003 ML20302A2312020-10-28028 October 2020 Integrated Inspection Report 05000397/2020003 IR 05000397/20204112020-09-28028 September 2020 Security Baseline Inspection Report 05000397/2020411 IR 05000397/20200052020-09-0101 September 2020 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2020005) IR 05000397/20200022020-07-29029 July 2020 Integrated Inspection Report 05000397/2020002 2024-01-29
[Table view] |
See also: IR 05000397/2009006
Text
July 1, 2009
J. V. Parrish
Chief Executive Officer
Energy Northwest
P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT: COLUMBIA GENERATING STATION - NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (05000397/2009006)
Dear Mr. Parrish:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),
Region IV staff will conduct a triennial fire protec
tion baseline inspecti
on at the Columbia
Generating St
ation in September and October of 2009. The inspection team will be comprised of four reactor inspectors from the NRC Region IV offi
ce and a Reliability and Risk Engineer from the Office of Nuclear Regulatory Research (RES)accompanying the team for training
purposes. The inspection will be conducted in accordance with Inspection Procedure 71111.05T, "Fire Protection (Triennial)," the NRC
=s baseline fire protection inspection procedure.
The schedule for the inspection is as follows:
$ Information gathering visit: September 1 - 4, 2009
$ Onsite inspection: September 21 - 25, 2009 October 5 - 9, 2009
Members of the inspection team will vi
sit the Columbia G
enerating St
ation on September 1 - 4, 2009, to meet with selected members of your staff in order to gather
information and documentation needed to support the inspection, to obtain unescorted access to
the facility, to discuss office
space assigned to the team, to become familiar with your fire protection program, and to select the fire areas of interest for the inspection.
Experience has shown that this inspection is resource intensive both for the NRC inspectors and
your staff. In order to minimize the impact to your onsite resources and to ensure a productive
inspection, we have enclosed a request for documents needed for this inspection. Please note
that some of the documents are requested to be provided prior to the information gathering visit.
We request that during the onsite inspection weeks, you ensure that copies of analyses,
evaluations, or documentation regarding the implementation and maintenance of the fire
protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest are those documents that establish that your fire
protection program satisfies NRC regulatory requirements and conforms to applicable NRC
and industry fire protection guidance. Also, appropriate personnel knowledgeable of: (1) those UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV612 EAST LAMAR BLVD, SUITE 400ARLINGTON, TEXAS 76011-4125
Energy Northwest - 2 -
plant systems required to achieve and maintain safe shutdown conditions from inside and outside the control room, (2) the electrical aspects of the post-fire safe shutdown analyses,
(3) reactor plant fire protection systems, (4) the fire protection program and its implementation
and (5) the operational implementation of fire response procedures should be available to
support the team at the site during the inspection.
We have discussed the schedule for these inspection activities with your staff and understand
that our regulatory contact for this inspection will be Fred Schill of your licensing organization. If there are any questions about this inspection or the material requested, please contact the lead
inspector, Sam Graves, at 817-860-8102 or by email, samuel.graves@nrc.gov.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be available electronically for public ins
pection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/ Neil F. O'Keefe, Chief
Engineering Branch 2
Division of Reactor Safety
Docket: 50-397
License: DPR-21
Enclosure: Triennial Fire Protection
Inspection Documentation Requested
cc w/enclosure:
Chairman
Energy Facility Site Evaluation Council P.O. Box 43172
Olympia, WA 98504-3172
Gregory V. Cullen
Manager, Regulatory Programs
Energy Northwest
P.O. Box 968, Mail Drop PE20
Richland, WA 99352-0968
Chairman
Benton County Board of Commissioners
P.O. Box 190
Prosser, WA 99350-0190
Energy Northwest - 3 -
William A. Horin, Esq. Winston & Strawn
1700 K Street, NW
Washington, DC 20006-3817
Lynn Albin
Washington State Department of Health
P.O. Box 7827
Olympia, WA 98504-7827
Ken Niles
Assistant Director
Nuclear Safety and Energy Siting Division
Oregon Department of Energy
625 Marion Street NE
Salem, OR 97301-3737
Special Hazards Program Manager
Washington Emergency Management Division
127 W. Clark Street
Pasco, WA 99301
Chief, Technological Hazards Branch
FEMA Region X
Federal Regional Center
130 228 th Street, SW Bothell, WA 98021-9796
Energy Northwest - 4 -
Electronic distribution by RIV: Regional Administrator (Elmo.Collins@nrc.gov ) Deputy Regional Administrator (Chuck.Casto@nrc.gov ) DRP Director (Dwight.Chamberlain@nrc.gov) DRP Deputy Director (Anton.Vegel@nrc.gov ) DRS Director (Roy.Caniano@nrc.gov ) DRS Deputy Director (Troy.Pruett@nrc.gov) Senior Resident Inspector (Ron.Cohen@nrc.gov ) Resident Inspector (Nicholas.Hernandez@nrc.gov ) Resident Inspector (Mahdi.Hayes@nrc.gov ) Branch Chief, DRP/A (Wayne.Walker@nrc.gov ) Senior Project Engineer, DRP/A (Clyde.Osterholtz@nrc.gov ) Columbia Site Secretary (Crystal.Myers@nrc.gov ) Public Affairs Officer (Victor.Dricks@nrc.gov ) Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov ) RITS Coordinator (Marisa.Herrera@nrc.gov ) Regional Counsel (Karla.Fuller@nrc.gov) OEMail Resource
File located: S:\DRS\REPORTS\COL FPT 2009006 RFI- STG ML SUNSI Rev Compl. X Yes No ADAMS X Yes No Reviewer Initials GAP Publicly Avail X Yes No Sensitive Yes X No Sens. Type Initials GAP RIV: DRS/EB2/SRI C: EB2 STGraves CFO'Keefe /RA/ /RA/ 6/26/09 6/30/09 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
- 1 - Enclosure
ENCLOSURE Triennial Fire Protection Inspection Documentation Requested
Please provide the following documentation prior to the onsite information gathering trip,
preferably no later than August 24, 2009. Where practical, please provide copies electronically.
1. The current version of your Fire Protection program and Fire Hazards Analysis.
2. Post-fire safe shutdown analysis, post-fire alternative shutdown analysis, and any supporting calculations which demonstrate acceptable plant response.
3. Copies of the licensing basis documents for fire protection (Safety Evaluation Reports, pertinent sections of the Final Safety Analysis Report, exemptions, deviations, letters
to/from the NRC regarding fire protection/fire safe shutdown, etc.).
Please provide the following documentation during the onsite information gathering trip
September 1 - 4, 2009. Where practical, please provide copies electronically. However,
drawings should be provided as paper copies of sufficient size that all details are legible. Fire
protection pr
ogram implementing
procedures (e.g., administrative controls, surv
eillance testing).
4. Operating procedures used for achieving and maintaining hot and cold shutdown conditions from the control room in the event of a fire
outside the contro
l room (III.G.2 areas).
5. Operating
procedure(s)
used to implement alternative shutdown (III.G.3 areas) capability with or without control room evacuation.
6. Pre-fire plans for the selected fire areas (areas to be selected by the team during the information-gathering trip).
7. A list of equipment used to achieve and maintain hot standby and cold shutdown in the event of a fire (safe shutdown equipment list), and two copies of the piping and
instrumentation (flow) diagrams for these systems of a size sufficient to read all details.
These should include the systems used for RCS makeup, RCS pressure control, decay
heat removal, and reactivity control, including the essential support systems.
8. Plant layout and equipment drawings for the selected fire areas that identify (a) the physical plant locations of major hot standby and cold shutdown equipment; (b) plant fire
area and/or fire zone delineation; and (c) the locations of fire protection equipment, such
as detection, suppression, and post-fire emergency lighting units, and (d) fire area
boundaries.
9. Electrical schematics and cable raceway listings for circuits supplying power to components used to achieve and maintain hot standby and cold shutdown for fires
outside the control room and those components used for those areas requiring
alternative shutdown capability.
10. A listing of design change packages, which were determined to impact fire protection and post-fire safe shutdown, performed in the last 3 years.
- 2 - Enclosure
11. A listing of Generic Letter 86-10 evaluations performed in the last 3 years.
12. A listing of fire protection corrective action documents initiated in the last 3 years which relate to the fire protection program or equipment.
13. A listing of the applicable codes and standards (e.g. NFPA) related to the design of plant fire protection features and evaluations of any code deviations showing the version
committed
14. Drawings of the emergency lighting system which support fire response.
15. Procedures used to remove smoke from safety-related areas and the engineering studies or calculations which support the design basis.
16. Drawings of communication systems credited in the license basis for firefighting and plant operations during fires where control room is occupied and/or evacuated.
17. Piping and instrumentation (flow) diagrams for the fire water and sprinkler systems.
18. Maintenance Rule performance criteria and 3 years worth of performance history for fire protection program systems or functions monitored within the Maintenance Rule
program.
19. A copy of fire protection program requirements (e.g. limiting conditions for operation, surveillance test requirements) covered by Technical Specifications, Technical
Requirements Manual, UFSAR, or similar documents.
20. Copies of internal and external self-assessments, audits, peer-assessments or similar reviews related to post-fire safe shutdown capability or the fire prot
ection program completed within the last 3 years.
21. A list of manual actions taken outside the control room which are credited to mitigate the consequences of fires in
III.G.2 areas (non-alternative shutdown areas). The list should group actions by the initiating fire area or zone and indicate where the action must take
place.
22. Electronic copies of operator study guides (lesson plan text and graphics) or design basis documents that describe the purpose/function/operating characteristics of the safe
shutdown systems (RCS makeup, RCS pressure control, decay heat removal, and
reactivity control, including the essential support systems).
23. Two copies of one-line diagrams of the electrical distribution system. These should depict how power gets from the switchyard to ESF loads. Also include the vital DC
distribution system one-line diagrams.
- 3 - Enclosure 24. A copy of any analysis used to determine in which fire areas a fire could cause a loss of offsite power (or conversely, a fire could never cause a loss of offsite power). If there is
no analysis, please provide a list of fire areas where offsite power cables are routed, or
where key breakers, protective relaying, or transformers are located. We are interested
in the equipment that delivers/controls offsite power from the switchyard to the ESF
buses.
25. Please provide a list of automatic and manually initiated gaseous fire suppression systems in the plant, giving location and the key equipment being protected.
26. Please provide a list of repairs (and the procedure that controls the actions) needed to: a) reach and/or maintain hot shutdown; b) reach and/or maintain cold shutdown.
27. A list of high to low pressure interface valves.
28. A copy of procedures governing the training and operation of the fire brigade.
29. Copies of maintenance procedures which routinely verify fuse/breaker coordination in accordance with the post-fire safe shutdown coordination analysis.
30. The team would like to observe a fire brigade drill in the plant, if po
ssible. Pl
ease put us in contact with the appropria
te personnel to plan a drill dur
ing the onsite information gathering trip September 1 - 4, 2009.
31. Organization charts of site personnel down to the level of fire protection staff personnel.
32. A contact list of key site personnel who will be supporting this inspection, giving location of their office and phone number onsite.
Inspector Contact Information:
Samuel Graves
Senior Reactor Inspector
817-860-8102
Samuel.graves@nrc.gov
Mailing Address:
US NRC Region IV
Attn: Sam Graves
612 East Lamar Blvd., Suite 400
Arlington, TX 76011-4125