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Category:Inspection Plan
MONTHYEARIR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20220062023-03-0101 March 2023 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report, Units 1 and 2 (Report 05000282/2022006 and 05000306/2022006) ML23055B0562023-02-27027 February 2023 Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010 IR 05000282/20220052022-08-29029 August 2022 Updated Inspection Plan for Prairie Island Nuclear Generating Plant (Report 05000282/2022005; 05000306/2022005) ML22007A1542022-01-0707 January 2022 Notification of NRC Fire Protection Team Inspection Request for Information Inspection Report 05000282/2022010 and 05000306/2022010 ML21363A0542021-12-29029 December 2021 Prairie Nuclear Generating Plant - Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information; Inspection Report 05000282/2022002 05000306/2022002 IR 05000282/20210052021-09-0101 September 2021 Updated Inspection Plan for Prairie Island Nuclear Generating Plant Units 1 and 2 (Report 05000282/2021005 and 05000306/2021005) IR 05000282/20200062021-03-0404 March 2021 Annual Assessment Letter for the Prairie Island Nuclear Generating Plant (Report 05000282/2020006 and 05000306/2020006) ML21062A0532021-03-0202 March 2021 Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant IR 05000282/20200052020-09-0101 September 2020 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2020005 and 05000306/2020005) ML20189A1782020-07-0606 July 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004 IR 05000282/20190062020-03-0303 March 2020 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2019006 and 05000306/2019006) IR 05000282/20190052019-08-28028 August 2019 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2019005; 05000306/2019005) ML19136A1562019-05-15015 May 2019 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Garza) ML19071A3532019-03-12012 March 2019 Ltr. 03/12/19 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information; Inspection Report 05000282/2019012; 05000306/2019012 (DRS-A.Dahbur) IR 05000282/20180062019-03-0404 March 2019 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2018006 and 05000306/2018006) ML18324A6122018-11-20020 November 2018 Ltr. 11/20/18 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2019001 and 05000306/2019001 (DRS-N.Feliz-Adorn IR 05000282/20180052018-08-28028 August 2018 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2018005 and 05000286/2018005) ML18156A5532018-06-0505 June 2018 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2018004; 05000306/2018004 (DRS-M.Holmberg) IR 05000282/20170062018-03-0202 March 2018 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2017006; 05000306/2017006) IR 05000282/20170052017-08-28028 August 2017 Updated Inspection Plan (Report 05000282/2017005 and 05000306/2017005) IR 05000282/20160062017-03-0101 March 2017 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2016006) ML16265A1652016-09-20020 September 2016 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2016004; 05000306/2016004 (Gfo) IR 05000282/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2016005; 05000306/2016005) ML16222A7022016-08-0909 August 2016 Notification of NRC Supplemental Inspection (95001) and Request for Information IR 05000282/20150062016-03-0202 March 2016 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Inspection Report 05000282/2015006 and 05000306/2015006) ML15261A7182015-09-15015 September 2015 Ltr. 09/15/2015 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information 05000282/2016008; 05000306/2016008. (Dxs) IR 05000282/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2015005; 05000306/2015005) IR 05000282/20140012015-03-0404 March 2015 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2, (Report 05000282/2014001 and 05000306/2014001) ML14245A2012014-09-0202 September 2014 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 ML14209A9342014-07-28028 July 2014 Notification of NRC Inspection and Request for Information IR 05000282/20130012014-03-0404 March 2014 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2(Report 05000282/2013001; 05000306/2013001) ML13246A2392013-09-0303 September 2013 2013 Prairie Island MOC Letter Combined ML13203A2862013-07-22022 July 2013 Notification of Baseline Inspection and Information Request ML13077A4742013-03-18018 March 2013 Information Request for a Post-approval Site Inspection for License Renewal IR 05000282/20120012013-03-0404 March 2013 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2012001 and 05000306/2012001) ML12249A4252012-09-0404 September 2012 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 IR 05000282/20110072012-03-0505 March 2012 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2011007 and 05000306/2011007) IR 05000282/20110062011-09-0101 September 2011 Mid-Cycle Letter for Prairie Island Nuclear Plant, Units 1 and 2, 05000282-11-006; 05000306-11-006 ML1106203132011-03-0404 March 2011 EOC Annual Assessment Letter and Inspection/Activity Plan ML1024400922010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Prairie Island Nuclear Power Plant IR 05000282/20100012010-03-0303 March 2010 Prairie Island Power Plant EOC Assessment Letter (05000282-10-001; 05000306-10-001) ML0924403672009-09-0101 September 2009 Prairie Island - Mid-Cycle Performance Review and Inspection Plan IR 05000282/20090012009-03-0404 March 2009 Annual Assessment Letter - Prairie Island Nuclear Generating Plant, Units 1 and 2 (05000282-09-001 and 050000306-09-001) ML0824603142008-09-0202 September 2008 Prairie Island, Units 1 & 2 - Mid-Cycle Performance Review and Inspection Plan IR 05000282/20080012008-03-0303 March 2008 Prairie Island, EOC Annual Assessment Letter (Inspection Report 05000282-08-001 and 05000306-08-001) ML0735402802007-12-19019 December 2007 Change to the Inspection Plan 1/1/08 - 12/31/08 ML0724302372007-08-31031 August 2007 8/31/07 Prairie Island - Mid-Cycle Performance Review and Inspection Plan 2024-08-28
[Table view] Category:Letter
MONTHYEARML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 To Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) 2024-09-27
[Table view] |
See also: IR 05000282/2022010
Text
January 7, 2022
Mr. Christopher P. Domingos
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company, Minnesota
1717 Wakonade Drive East
Welch, MN 55089-9642
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT NOTIFICATION OF NRC
FIRE PROTECTION TEAM INSPECTION REQUEST FOR INFORMATION;
INSPECTION REPORT 05000282/2022010; 05000306/2022010
Dear Mr. Domingos:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region III staff will conduct a Fire Protection Team Inspection at your Prairie Island Nuclear
Generating Plant beginning March 28, 2022. The inspection will be conducted in accordance
with Inspection Procedure 71111.21N.05, Fire Protection Team Inspection, dated June 12,
2019.
The inspection will verify that plant structures, systems and components (SSCs) and/or
administrative controls credited in the approvedFire Protection Program can perform their
licensing basis function.
The schedule for the inspection is as follows:
Preparation week (R-III office): March 21 - 25, 2022
Week 1 of onsite inspection: March 28 - April 1, 2022
Week 2 of onsite inspection: April 11 - 15, 2022
Experience has shown that the baseline fire protection team inspections are extremely resource
intensive, both for the NRC inspectors and the licensee staff. In order to minimize the
inspection impact on the site and to ensure a productive inspection for both organizations, we
have enclosed a request for documents needed for the inspection. These documents have
been divided into three groups.
The first group lists information necessary to aid the inspection team in choosing
specific focus areas for the inspection and to ensure that the inspection team is
adequately prepared for the inspection. It is requested that this information be
provided to the lead inspector via mail or electronically no later than February 21, 2022.
The second group of requested documents consists of those items that the team will
review, or need access to, during the inspection. Please have this information
available by the first day of the first onsite inspection week March 28, 2022.
C. Domingos -2-
The third group lists the information necessary to aid the inspection team in tracking
issues identified as a result of the inspection. It is requested that this information be
provided to the lead inspector as the information is generated during the inspection. It is
important that all of these documents are up to date and complete in order to minimize
the number of additional documents requested during the preparation and/or the onsite
portions of the inspection.
The lead inspector for this inspection is Ms. J. Gilliam. We understand that our regulatory
contact for this inspection is Ms. C. Seipp of your organization. If there are any questions about
the inspection or the material requested, please contact the lead inspector at 630-829-9831 or
via e-mail at Jasmine.Gilliam@nrc.gov.
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, Control
Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection requirement unless the
requesting document displays a currently valid Office of Management and Budget Control
Number.
This letter and its enclosure will be made available for public inspection and copying at
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
accordance with Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,
Exemptions, Requests for Withholding.
Sincerely,
Signed by Gilliam, Jasmine
on 01/07/22
Jasmine Gilliam, Senior Reactor Inspector
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50-282 and 50-306
License Nos. DPR-42 and DPR-60
Enclosure:
Fire Protection Team Inspection Supporting
Documentation
cc: Distribution via LISTSERV
C. Domingos -3-
Letter to Christopher P. Domingos from Jasmine Gilliam dated January 7, 2022.
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT NOTIFICATION OF NRC
FIRE PROTECTION TEAM INSPECTION REQUEST FOR INFORMATION;
INSPECTION REPORT 05000282/2022010; 05000306/2022010
DISTRIBUTION:
Jessie Quichocho
Linda Howell
RidsNrrPMPrairieIsland Resource
RidsNrrDorlLpl3
RidsNrrDroIrib Resource
John Giessner
Mohammed Shuaibi
Shelbie Lewman
Allan Barker
DRPIII
DRSIII
ADAMS Accession Number: ML22007A154
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
OFFICE RIII
NAME JGilliam:mb
DATE 01/07/2022
OFFICIAL RECORD COPY
FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
I. Information Requested prior to the Inspection Preparation Week
The following information is requested by February 21, 2022. If you have any questions
regarding this request, please call the lead inspector as soon as possible. All information
should be sent to Jasmine Gilliam (e-mail address Jasmine.Gilliam@nrc.gov). Electronic
media or database is preferred. The preferred file format is a searchable pdf or Microsoft
Excel file. If a CD is use it should be indexed and hyper-linked to facilitate ease of use, if
possible. Please provide three copies of each CD submitted (one for each inspector).
1. One set of hard-copy documents for facility layout drawings which identify plant fire area
delineation; areas protected by automatic fire suppression and detection; and locations
of fire protection equipment.
2. Licensing Information:
a. All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)
applicable to fire protection (specifically including those SERs referenced by the
plant fire protection license condition) and all licensing correspondence referenced by
the SERs;
b. All licensing correspondence associated with the comparison to Standard Review
Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing purposes;
c. Exemptions from Title 10 of the Code of Federal Regulations (CFR), Part 50.48 and
10 CFR Part 50, Appendix R, and associated licensing correspondence;
d. For pre-1979 plants, all licensing correspondence associated with those sections of
10 CFR Part 50, Appendix R, that are not applicable to the plant under
10 CFR 50.48(b)(1). Specifically, the licensing correspondence associated with
those fire protection features proposed or implemented by the licensee that have
been accepted by the NRC staff as satisfying the provisions of Appendix A to Branch
Technical Position APCSB 9.5-1 reflected in the NRC fire protection SERs issued
before February 19, 1981 (10 CFR 50.48(b)(1)(i)); or those fire protection features,
which were accepted by the NRC staff in comprehensive fire protection SERs issued
before Appendix A to Branch Technical Position APCSB 9.5-1 was published in
August 1976 (10 CFR 50.48(b)(1)(ii)); and
e. The final safety analysis report sections applicable to fire protection, fire hazards
analysis (FHA), and safe shutdown analysis (SSA) in effect at the time of original
licensing.
3. Fire Protection Program:
a. A listing of changes made to the Fire Protection Program since the last triennial fire
protection inspection;
b. For pre-1979 plants, a listing of the protection methodologies identified under
10 CFR Part 50, Appendix R, Section III.G used to achieve compliance for fire
zones/areas. That is, please specify whether 3-hour rated fire barriers;
(Section III.G.2.a), 20-foot separation along with detection and suppression;
(Section III.G.2.b), 1-hour rated fire barriers with detection and suppression;
Enclosure
FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
(Section III.G.2.c), or alternative shutdown capability; (Section III.G.3) is used as a
strategy for each selected fire zone/area;
c. A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe shutdown
evaluations);
d. A list of applicable codes and standards related to the design of plant fire protection
features. The list should include National Fire Protection Association (NFPA) code
versions committed to (i.e., the NFPA Codes of Record);
e. List of plant deviations from code commitments and associated evaluations;
f. Fire Protection Program and/or Fire Protection Plan document;
g. (If available) Fire Probabilistic Risk Assessment (PRA) Summary Report or full PRA
document (if summary document not available);
h. List of the top 25 highest fire core damage frequency (CDF) scenarios for each unit;
i. List of Fire Areas/Zones ranked by contribution to CDF (i.e., ranking of highest to
lowest risk fire areas/zones);
j. List of the top 25 highest fire large early release frequency (LERF) scenarios for
each unit; and
k. Risk ranking of operator actions and/or recovery actions from your site-specific PRA
sorted by risk assessment worth (RAW) and human reliability worksheets for these
items.
4. Facility Information:
a. Piping and instrumentation (flow) diagrams showing the 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;
b. One-line schematic drawings of the electrical distribution system for 4160 Volts
alternating current (Vac) down to 480 Vac;
c. One-line schematic drawings of the electrical distribution system for 250 Volts direct
current (Vdc) and 125 Vdc systems as applicable;
d. Logic diagrams showing the components used to achieve and maintain hot standby
and cold shutdown; and
e. Safe shutdown cable routing database (requested electronically, such as on compact
disc, if available).
5. Operations Response for Fire Protection:
a. Pre-fire plans for fire zones/areas; and
2
FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
b. Plant operating procedures which specify the initial operations response to a fire
alarm or annunciator.
6. Corrective Actions:
a. Listing of open and closed fire protection condition reports (i.e., problem identification
forms and their resolution reports) since the date of the last triennial fire protection
inspection; and
b. List of current fire impairments, including duration.
7. General Information:
a. A listing of abbreviations and/or designators for plant systems;
b. Organization charts of site personnel down to the level of fire protection staff
personnel; and
c. A phone list for onsite licensee personnel.
II. Information Requested to Be Available on First Day of the FIRST ONSITE Inspection
Week (MARCH 28, 2022)
The following information is requested to be provided on the first day of inspection. It is
requested that this information be provided on three sets of CDs (searchable, if possible).
1. Program Procedures:
a. Procedures for:
i. Administrative controls (such as allowed out of service times and
compensatory measures) for fire protection systems and components;
ii. Control of transient combustibles; and
iii. Control of hot work.
b. List of maintenance and surveillance testing procedures for alternative shutdown
capability and fire barriers, detectors, pumps, and suppression systems; and
c. List of maintenance procedures which routinely verify fuse breaker coordination in
accordance with the post-fire safe shutdown coordination analysis.
2. Design and Equipment Information (for only selected fire zone/area(s) and/or SSCs
to be determined during inspection preparation week):
a. Coordination calculations and/or justifications that verify fuse/breaker coordination for
SSCs that are fed off of the same electrical buses as components in the protected
safe shutdown train;
3
FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
b. Copies of significant fire protection and post-fire safe shutdown related design
change package descriptions (including their associated 10 CFR 50.59
evaluations) and Generic Letter 86-10 (or adverse to safe shutdown) evaluations;
c. Gaseous suppression system pre-operational testing, if applicable, for selected fire
zones/areas;
d. Hydraulic calculations and supporting test data which demonstrate operability for
water suppression systems;
e. Alternating current (ac) coordination calculations for 4160 Vac down to 480 Vac
electrical systems; and
f. List of all fire protection or Appendix R calculations.
3. Assessment and Corrective Actions:
The three most recent fire protection Quality Assurance audits and/or fire protection
self-assessments.
4. Any updates to information previously provided.
5. Classic Fire Protection (for only selected fire zone/area(s) and/or SSCs to be
determined during inspection preparation week):
a. Copy of Fire Protection Program implementing procedures (e.g., administrative
controls, surveillance testing, and fire brigade);
b. Pre-fire plans for selected fire area(s); and
c. List of fire protection system design changes completed in the last 3 years.
6. Electrical (for only selected fire zone/area(s) and/or SSCs to be determined during
inspection preparation week):
a. Nuclear safety circuit coordination analysis for fuse and breaker coordination of safe
shutdown components;
b. Administrative or configuration control procedures that govern fuse replacement
(e.g., fuse control procedures);
c. Maintenance procedures that verify breaker over-current trip settings to ensure
coordination remains functional, for post-fire nuclear safety capability components;
d. Last surveillance demonstrating operability of those components operated from the
primary control stations;
e. Schematic or elementary diagrams for circuits (only for selected SSCs) to be
reviewed (C-size paper drawings);
4
FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
f. Cable routing for components and equipment credited for post-fire nuclear safety
capability systems and components;
g. List of post-fire nuclear safety capability system and component design changes
completed, in the last 3 years; and
h. List of identified fire induced circuit failure analyses.
7. Operations:
a. List of procedures that implement Cold Shutdown Repairs (if applicable for selected
fire area);
b. For Cold Shutdown Repairs, provide the following:
i. Procedure for inventory and inspection (i.e., needed tools, material, etc.); and
ii. Most recent inspection and inventory results.
c. List of licensed operator Job Performance Measures for operator actions required to
achieve and maintain post-fire nuclear safety performance criteria (for selected SSCs
and fire area);
d. For Radio communications, provide the following:
i. Communications Plan for firefighting and post-fire safe shutdown manual
actions;
ii. Repeater locations;
iii. Cable routing for repeater power supply cables;
iv. Radio coverage test results; and
v. Radio Dead Spot locations in the plant.
e. Environmental and habitability evaluations for post-fire operator actions (temperature,
smoke, humidity, SCBAs, etc.).
8. Administrative Control, Oversight, and Corrective Action Programs:
a. Self-assessments, peer assessments, and audits of fire protection activities for the
last 3 years;
b. Self-assessments, peer assessments, and audits of post-fire nuclear safety capability
methodology for the last 3 years; and
c. List of fire event analysis reports for the last 3 years.
9. Any updates to information previously provided.
III. Information Requested to Be Provided Throughout the Inspection
1. Copies of any corrective action documents generated as a result of the inspection teams
questions or queries during this inspection.
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FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
2. Copies of the list of questions submitted by the inspection team members and the
status/resolution of the information requested (provided daily during the inspection to
each inspection team member).
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