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See also: [[see also::IR 05000373/2017010]]
See also: [[followed by::IR 05000373/2017010]]


=Text=
=Text=
{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES  
                            NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION  
                                              REGION III
REGION III  
                                    2443 WARRENVILLE RD. SUITE 210
2443 WARRENVILLE RD. SUITE 210  
                                          LISLE, IL 60532-4352
LISLE, IL 60532-4352  
                                        September 5, 2017
Mr. Bryan C. Hanson
September 5, 2017  
Senior VP, Exelon Generation Company, LLC
Mr. Bryan C. Hanson  
President and CNO, Exelon Nuclear
Senior VP, Exelon Generation Company, LLC  
4300 Winfield Road
President and CNO, Exelon Nuclear  
Warrenville, IL 60555
4300 Winfield Road  
SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2NOTIFICATION OF NRC
Warrenville, IL 60555  
            TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR
SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2NOTIFICATION OF NRC  
            INFORMATION 05000373/2017010; 05000374/2017010
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR  
Dear Mr. Hanson:
INFORMATION 05000373/2017010; 05000374/2017010
On October 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) will begin a Triennial
Dear Mr. Hanson:  
Fire Protection Baseline Inspection at your LaSalle County Station, Units 1 and 2. This
On October 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) will begin a Triennial  
inspection will be performed in accordance with Inspection Procedure (IP) 71111.05T,
Fire Protection Baseline Inspection at your LaSalle County Station, Units 1 and 2. This  
the NRCs Baseline Fire Protection IP.
inspection will be performed in accordance with Inspection Procedure (IP) 71111.05T,  
Changes were made to the IP 71111.05T which now requires the Fire Protection Inspection
the NRCs Baseline Fire Protection IP.  
to review your actions to mitigate postulated events that could potentially cause loss of large
Changes were made to the IP 71111.05T which now requires the Fire Protection Inspection  
areas of power reactor facilities due to explosions or fires. This requirement was implemented
to review your actions to mitigate postulated events that could potentially cause loss of large  
by the issuance of the Interim Compensatory Measures Order EA-02-026, Section B.5.b,
areas of power reactor facilities due to explosions or fires. This requirement was implemented  
and the subsequent requirements of Title 10 of the Code of Federal Regulations (CFR),
by the issuance of the Interim Compensatory Measures Order EA-02-026, Section B.5.b,  
Part 50.54(hh)(2), which are collectively referred to as B.5.b requirements. During this
and the subsequent requirements of Title 10 of the Code of Federal Regulations (CFR),  
inspection, the B.5.b requirements review will be performed during the first onsite week of
Part 50.54(hh)(2), which are collectively referred to as B.5.b requirements. During this  
the inspection starting on November 1, 2017.
inspection, the B.5.b requirements review will be performed during the first onsite week of  
The schedule for the onsite inspection activity is as follows:
the inspection starting on November 1, 2017.  
          Information Gathering Visit: October 30, 2017;
The schedule for the onsite inspection activity is as follows:  
          B.5.b Requirements: November 1-3, 2017; and
          Fire Protection Inspection: November 13-17, 2017, and
Information Gathering Visit: October 30, 2017;  
                                        November 27-December 1, 2017.
The purpose of the information gathering visit is: (1) to obtain information and documentation
B.5.b Requirements: November 1-3, 2017; and  
needed to support the inspection; (2) to become familiar with the LaSalle Fire Protection
Programs, fire protection features, post-fire safe shutdown capabilities, and plant layout; and
Fire Protection Inspection: November 13-17, 2017, and
(3) to arrange administrative details, such as office space, availability of knowledgeable office
November 27-December 1, 2017.  
personnel and to ensure unescorted site access privileges.
The purpose of the information gathering visit is: (1) to obtain information and documentation  
needed to support the inspection; (2) to become familiar with the LaSalle Fire Protection  
Programs, fire protection features, post-fire safe shutdown capabilities, and plant layout; and  
(3) to arrange administrative details, such as office space, availability of knowledgeable office  
personnel and to ensure unescorted site access privileges.  


B. Hanson                                     -2-
B. Hanson  
Experience has shown that the Baseline Fire Protection Inspections are extremely resource
-2-  
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
Experience has shown that the Baseline Fire Protection Inspections are extremely resource  
enclosed a request for documents needed for the inspection. These documents have been
intensive both for the NRC inspectors and the licensee staff. In order to minimize the inspection  
divided into four groups.
impact on the site and to ensure a productive inspection for both organizations, we have  
            The first group lists information necessary to aid the inspection team in
enclosed a request for documents needed for the inspection. These documents have been  
            choosing specific focus areas for the inspection. It is requested that this
divided into four groups.  
            information be provided to the lead inspector via mail or electronically no
            later than October 20, 2017.
The first group lists information necessary to aid the inspection team in  
            The second group also lists information and areas for discussion necessary to
choosing specific focus areas for the inspection. It is requested that this  
            aid the inspection team in choosing specific fire protection focus areas for the
information be provided to the lead inspector via mail or electronically no  
            inspection and to ensure that the inspection team is adequately prepared for the
later than October 20, 2017.  
            inspection. It is requested this information be available during the information
            gathering visit on October 30, 2017.
The second group also lists information and areas for discussion necessary to  
            The third group of requested documents consists of those items that the
aid the inspection team in choosing specific fire protection focus areas for the  
            team will review, or need access to, during the inspection. Please have this
inspection and to ensure that the inspection team is adequately prepared for the  
            information available by the first day of the second onsite inspection week of
inspection. It is requested this information be available during the information  
            November 13, 2017.
gathering visit on October 30, 2017.  
            The fourth 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
The third group of requested documents consists of those items that the  
            information be provided to the lead inspector as the information is generated
team will review, or need access to, during the inspection. Please have this  
            during the inspection.
information available by the first day of the second onsite inspection week of  
It is important that all of these documents are up to date and complete in order to minimize the
November 13, 2017.  
number of additional documents requested during the preparation and/or the onsite portions of
the inspection.
The fourth group lists the information necessary to aid the inspection team in  
The lead inspector for this inspection is Mr. Alan Dahbur. We understand that our
tracking issues identified as a result of the inspection. It is requested that this  
regulatory contact for this inspection is Mr. Terry Lanc of your organization. If there are
information be provided to the lead inspector as the information is generated  
and questions about the inspection or the material requested, please contact the lead
during the inspection.  
inspector at 630-829-9810, or via e-mail at Alan.Dahbur@nrc.gov.
It is important that all of these documents are up to date and complete in order to minimize the  
This letter does not contain new or amended information collection requirements subject
number of additional documents requested during the preparation and/or the onsite portions of  
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
the inspection.  
collection requirements were approved by the Office of Management and Budget, Control
The lead inspector for this inspection is Mr. Alan Dahbur. We understand that our  
Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to
regulatory contact for this inspection is Mr. Terry Lanc of your organization. If there are  
respond to, a request for information or an information collection requirement unless the
and questions about the inspection or the material requested, please contact the lead  
requesting document displays a currently valid Office of Management and Budget Control
inspector at 630-829-9810, or via e-mail at Alan.Dahbur@nrc.gov.  
Number.
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.  


B. Hanson                                   -3-
B. Hanson  
This letter and its enclosure will be made available for public inspection and copying at
-3-  
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
This letter and its enclosure will be made available for public inspection and copying at  
                                            Sincerely,
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in  
                                            /RA/
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.  
                                            Alan Dahbur, Senior Reactor Inspector
Sincerely,  
                                            Engineering Branch 3
                                            Division of Reactor Safety
/RA/  
Docket Nos. 50-373; 50-374
License Nos. NPF-11; NPF-18
Enclosure:
Alan Dahbur, Senior Reactor Inspector  
Triennial Fire Protection Baseline
Engineering Branch 3  
Inspection Document Request
Division of Reactor Safety  
cc: Distribution via LISTSERV
Docket Nos. 50-373; 50-374  
License Nos. NPF-11; NPF-18  
Enclosure:  
Triennial Fire Protection Baseline
  Inspection Document Request  
cc: Distribution via LISTSERV  


B. Hanson                               -4-
B. Hanson  
Letter to Bryan C. Hanson from Alan Dahbur dated September 5, 2017
-4-  
SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2NOTIFICATION OF NRC
            TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR
Letter to Bryan C. Hanson from Alan Dahbur dated September 5, 2017  
            INFORMATION 05000373/2017010; 05000374/2017010
SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2NOTIFICATION OF NRC  
DISTRIBUTION:
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR  
Jeremy Bowen
INFORMATION 05000373/2017010; 05000374/2017010
RidsNrrDorlLpl3
DISTRIBUTION:  
RidsNrrPMLaSalle
Jeremy Bowen  
RidsNrrDirsIrib Resource
RidsNrrDorlLpl3  
Cynthia Pederson
RidsNrrPMLaSalle  
James Trapp
RidsNrrDirsIrib Resource  
Richard Skokowski
Cynthia Pederson  
Allan Barker
James Trapp  
Carole Ariano
Richard Skokowski  
Linda Linn
Allan Barker  
DRPIII
Carole Ariano  
DRSIII
Linda Linn  
ADAMS Accession Number ML17249A826
DRPIII  
  OFFICE RIII                     RIII             RIII           RIII
DRSIII  
  NAME       ADahbur:cl
  DATE       09/05/17
                                OFFICIAL RECORD COPY
ADAMS Accession Number ML17249A826  
OFFICE  
RIII  
RIII  
RIII  
RIII  
NAME  
ADahbur:cl  
DATE  
09/05/17  
OFFICIAL RECORD COPY  


    TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST  
Inspection Report:               05000373/2017010 AND 05000374/2017010
Enclosure
Onsite Inspection Dates:         October 30, 2017                       (Information Gathering Visit)
Inspection Report:  
                                  November 1-3, 2017                     (B.5.b Requirements)
05000373/2017010 AND 05000374/2017010  
                                  November 13-17, 2017                   (Fire Protection Inspection)
Onsite Inspection Dates:  
                                  November 27-December 1, 2017           (Fire Protection Inspection)
October 30, 2017  
Inspection Procedures:           IP 71111.05T, Fire Protection (Triennial)
                                  IP 71152, Identification and Resolution of Problems
(Information Gathering Visit)  
Inspectors:                       Alan Dahbur
November 1-3, 2017  
                                  Senior Reactor Inspector (Lead)
                                  630-829-9810
(B.5.b Requirements)  
                                  Alan.Dahbur@nrc.gov
November 13-17, 2017  
                                  Atif Shaikh                       Jasmine Gilliam
                                  Senior Reactor Inspector         Reactor Inspector
(Fire Protection Inspection)  
                                  630-829-9824                     630-829-9831
November 27-December 1, 2017  
                                  Atif.Shaikh@nrc.gov               Jasmine.Gilliam@nrc.gov
(Fire Protection Inspection)  
I.     Information Requested Prior To the Information Gathering Visit:
Inspection Procedures:  
      The following information is requested by October 20, 2017. If you have any
IP 71111.05T, Fire Protection (Triennial)  
      questions regarding this request, please call the lead inspector as soon as possible. All
IP 71152, Identification and Resolution of Problems  
      information should be sent to Mr. Alan Dahbur (e-mail address Alan.Dahbur@nrc.gov).
Inspectors:  
      Electronic media is preferred. The preferred file format is a searchable pdf file on a
Alan Dahbur  
      compact disk (CD). The CD should be indexed and hyper-linked to facilitate ease of
Senior Reactor Inspector (Lead)  
      use, if possible. Please provide four copies of each CD submitted (one for each
630-829-9810  
      inspector).
Alan.Dahbur@nrc.gov  
      1.       The most risk-significant fire areas as determined by probabilistic risk analyses, if
Atif Shaikh  
                available. Otherwise, the reactor plant's Individual Plant Examination for External
Jasmine Gilliam  
                Events for fire and results of any post-Individual Plant Examination for External
Senior Reactor Inspector
                Events reviews for fire.
Reactor Inspector  
      2.       A copy of the current version of the Fire Protection Program, fire hazards
630-829-9824  
                analysis, safe shutdown analysis, Updated Safety Analysis Report, technical
630-829-9831  
                specifications, license (including the fire protection license condition), and
Atif.Shaikh@nrc.gov
                technical requirements manual or equivalent for fire protection structures,
Jasmine.Gilliam@nrc.gov  
                systems, and components.
I.  
      3.       A list of fire areas requiring alternative shutdown capability, (i.e., those areas for
Information Requested Prior To the Information Gathering Visit:  
                which Title 10 of the Code of Federal Regulations (CFR), Part 50, Appendix R,
The following information is requested by October 20, 2017. If you have any  
                Section III G, requirements are satisfied under Section III.G.3), or where both
questions regarding this request, please call the lead inspector as soon as possible. All  
                safe shutdown trains can be affected.
information should be sent to Mr. Alan Dahbur (e-mail address Alan.Dahbur@nrc.gov).
                                                                                            Enclosure
Electronic media is preferred. The preferred file format is a searchable pdf file on a  
compact disk (CD). The CD should be indexed and hyper-linked to facilitate ease of  
use, if possible. Please provide four copies of each CD submitted (one for each  
inspector).  
1.  
The most risk-significant fire areas as determined by probabilistic risk analyses, if  
available. Otherwise, the reactor plant's Individual Plant Examination for External  
Events for fire and results of any post-Individual Plant Examination for External  
Events reviews for fire.  
2.  
A copy of the current version of the Fire Protection Program, fire hazards  
analysis, safe shutdown analysis, Updated Safety Analysis Report, technical  
specifications, license (including the fire protection license condition), and  
technical requirements manual or equivalent for fire protection structures,  
systems, and components.  
3.  
A list of fire areas requiring alternative shutdown capability, (i.e., those areas for  
which Title 10 of the Code of Federal Regulations (CFR), Part 50, Appendix R,  
Section III G, requirements are satisfied under Section III.G.3), or where both  
safe shutdown trains can be affected.  


    TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST  
    4.     Plant operating procedures which would be used and describe shutdown for a
2
            postulated fire (for both areas requiring alternative shutdown and areas which do
4.  
            not require alternative shutdown). Only those procedures with actions specific to
Plant operating procedures which would be used and describe shutdown for a  
            shutdown in the event of a fire need be included. In addition, please include
postulated fire (for both areas requiring alternative shutdown and areas which do  
            those procedures which operators would use for initial response to a fire, such as
not require alternative shutdown). Only those procedures with actions specific to  
            annunciator or alarm response procedures, the procedure used for activating the
shutdown in the event of a fire need be included. In addition, please include  
            fire brigade, and the procedure which directs operators to the applicable safe
those procedures which operators would use for initial response to a fire, such as  
            shutdown procedure.
annunciator or alarm response procedures, the procedure used for activating the  
    5.     Analysis performed in support of plant evaluation regarding multiple spurious
fire brigade, and the procedure which directs operators to the applicable safe  
            operation (MSO), which includes the following:
shutdown procedure.  
            a. List of identified multiple spurious fire-induced circuit failure configurations.
5.  
            b. List of the generic and plant specific MSOs.
Analysis performed in support of plant evaluation regarding multiple spurious  
            c. Results of expert panel process and associated review/evaluation of the
operation (MSO), which includes the following:  
                  generic and plant specific MSOs and existing safe shutdown analysis.
a. List of identified multiple spurious fire-induced circuit failure configurations.  
            d. Evaluations and corrective actions taken for resolution of MSO issues.
b. List of the generic and plant specific MSOs.  
II. Information Requested During the Information Gathering Visit (October 30, 2017):
c. Results of expert panel process and associated review/evaluation of the  
    The following information is requested to be provided to the inspection team during the
generic and plant specific MSOs and existing safe shutdown analysis.  
    onsite information gathering visit. Except for Item 8, it is requested that the following
d. Evaluations and corrective actions taken for resolution of MSO issues.  
    information be provided on four sets of CDs (searchable, if possible) with the B.5.b
II.  
    Mitigating Strategies information (Items 8.a through 8.h) provided on one separate CD.
Information Requested During the Information Gathering Visit (October 30, 2017):  
    In addition, one set of hard copy drawings are requested for Items 4.a. through 4.d.
The following information is requested to be provided to the inspection team during the  
    1.     One set of hard-copy documents for facility layout drawings which identify plant
onsite information gathering visit. Except for Item 8, it is requested that the following  
            fire area delineation; areas protected by automatic fire suppression and
information be provided on four sets of CDs (searchable, if possible) with the B.5.b  
            detection; and locations of fire protection equipment.
Mitigating Strategies information (Items 8.a through 8.h) provided on one separate CD.
    2.     Licensing Information:
In addition, one set of hard copy drawings are requested for Items 4.a. through 4.d.  
            a. All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)
1.  
                  applicable to fire protection (specifically including those SERs referenced by
One set of hard-copy documents for facility layout drawings which identify plant  
                  the plant fire protection license condition) and all licensing correspondence
fire area delineation; areas protected by automatic fire suppression and  
                  referenced by the SERs;
detection; and locations of fire protection equipment.  
            b. All licensing correspondence associated with the comparison to Standard
2.  
                  Review Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing
Licensing Information:  
                  purposes;
a. All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)  
            c. Exemptions from 10 CFR 50.48 and 10 CFR Part 50, Appendix R, and
applicable to fire protection (specifically including those SERs referenced by  
                  associated licensing correspondence;
the plant fire protection license condition) and all licensing correspondence  
            d. All licensing correspondence associated with those sections of
referenced by the SERs;  
                  10 CFR Part 50, Appendix R, that are not applicable to the plant under
b. All licensing correspondence associated with the comparison to Standard  
                  10 CFR 50.48(b)(1). Specifically, the licensing correspondence associated
Review Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing  
                  with those fire protection features proposed or implemented by the licensee
purposes;  
                  that have been accepted by the NRC staff as satisfying the provisions of
c. Exemptions from 10 CFR 50.48 and 10 CFR Part 50, Appendix R, and  
                                                  2
associated licensing correspondence;  
d. 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  


TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST  
          Appendix A to Branch Technical Position APCSB 9.5-1 reflected in
3
          the NRC fire protection SERs issued before February 19, 1981,
Appendix A to Branch Technical Position APCSB 9.5-1 reflected in  
          (10 CFR 50.48(b)(1)(i)); or those fire protection features, which were
the NRC fire protection SERs issued before February 19, 1981,  
          accepted by the NRC staff in comprehensive fire protection SERs issued
(10 CFR 50.48(b)(1)(i)); or those fire protection features, which were  
          before Appendix A to Branch Technical Position APCSB 9.5-1 was published
accepted by the NRC staff in comprehensive fire protection SERs issued  
          in August 1976 (10 CFR 50.48(b)(1)(ii)); and
before Appendix A to Branch Technical Position APCSB 9.5-1 was published  
      e. The Final Safety Analysis Report sections applicable to fire protection, fire
in August 1976 (10 CFR 50.48(b)(1)(ii)); and  
          hazards analysis, and safe shutdown analysis in effect at the time of original
e. The Final Safety Analysis Report sections applicable to fire protection, fire  
          licensing.
hazards analysis, and safe shutdown analysis in effect at the time of original  
3.   Fire Protection Program:
licensing.  
      a. A listing of changes made to the Fire Protection Program since the last
3.  
          Triennial Fire Protection Inspection;
Fire Protection Program:  
      b. A listing of the protection methodologies identified under 10 CFR Part 50,
a. A listing of changes made to the Fire Protection Program since the last  
          Appendix R, Section III.G used to achieve compliance for selected fire
Triennial Fire Protection Inspection;  
          zones/areas (to be determined during information gathering visit). That is,
b. A listing of the protection methodologies identified under 10 CFR Part 50,  
          please specify whether 3-hour rated fire barriers; (Section III.G.2.a), 20 foot
Appendix R, Section III.G used to achieve compliance for selected fire  
          separation along with detection and suppression; (Section III.G.2.b), 1-hour
zones/areas (to be determined during information gathering visit). That is,  
          rated fire barriers with detection and suppression; (Section III.G.2.c), or
please specify whether 3-hour rated fire barriers; (Section III.G.2.a), 20 foot  
          alternative shutdown capability; (Section III.G.3) is used as a strategy for
separation along with detection and suppression; (Section III.G.2.b), 1-hour  
          each selected fire zone/area;
rated fire barriers with detection and suppression; (Section III.G.2.c), or  
      c. A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe-
alternative shutdown capability; (Section III.G.3) is used as a strategy for  
          shutdown evaluations);
each selected fire zone/area;  
      d. A list of applicable codes and standards related to the design of plant fire
c. A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe-
          protection features. The list should include National Fire Protection
shutdown evaluations);  
          Association code versions committed to (i.e., the National Fire Protection
d. A list of applicable codes and standards related to the design of plant fire  
          Association Codes of Record); and
protection features. The list should include National Fire Protection  
      e. List of plant deviations from code commitments and associated evaluations.
Association code versions committed to (i.e., the National Fire Protection  
4.   Facility Information:
Association Codes of Record); and  
      a. Piping and instrumentation (flow) diagrams showing the components used to
e. List of plant deviations from code commitments and associated evaluations.  
          achieve and maintain hot standby and cold shutdown for fires outside the
4.  
          control room, those components used for those areas requiring alternative
Facility Information:  
          shutdown capability, and systems relied upon for B.5.b mitigation strategies.
a. Piping and instrumentation (flow) diagrams showing the components used to  
          These can be of the type that are used for training;
achieve and maintain hot standby and cold shutdown for fires outside the  
      b. One-line schematic drawings of the electrical distribution system for 4160
control room, those components used for those areas requiring alternative  
          Volts alternating current (Vac) down to 480Vac;
shutdown capability, and systems relied upon for B.5.b mitigation strategies.
      c. One-line schematic drawings of the electrical distribution system for 250 Volts
These can be of the type that are used for training;  
          direct current and 125 Volts direct current systems as applicable;
b. One-line schematic drawings of the electrical distribution system for 4160  
      d. Logic diagrams showing the components used to achieve and maintain hot
Volts alternating current (Vac) down to 480Vac;  
          standby and cold shutdown; and
c. One-line schematic drawings of the electrical distribution system for 250 Volts  
                                          3
direct current and 125 Volts direct current systems as applicable;  
d. Logic diagrams showing the components used to achieve and maintain hot  
standby and cold shutdown; and  


TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST  
      e. Safe shutdown cable routing database (requested electronically, such as on
4
          compact disc, if available).
e. Safe shutdown cable routing database (requested electronically, such as on  
5.   Operations Response for Fire Protection:
compact disc, if available).  
      a. Pre-fire plans for selected fire zones/areas (to be determined during
5.  
          information gathering visit);
Operations Response for Fire Protection:  
      b. Plant operating procedures which specify the initial operations response to a
a. Pre-fire plans for selected fire zones/areas (to be determined during  
          fire alarm or annunciator; and
information gathering visit);  
      c. Procedure for calling out the fire brigade and requesting off-site assistance.
b. Plant operating procedures which specify the initial operations response to a  
6.   Corrective Actions:
fire alarm or annunciator; and  
      a. Listing of open and closed Fire Protection Condition Reports (i.e., problem
c. Procedure for calling out the fire brigade and requesting off-site assistance.  
          identification forms and their resolution reports) since the date of the last
6.  
          Triennial Fire Protection Inspection; and
Corrective Actions:  
      b. List of current fire impairments, including duration.
a. Listing of open and closed Fire Protection Condition Reports (i.e., problem  
7.   General Information:
identification forms and their resolution reports) since the date of the last  
      a. A listing of abbreviations and/or designators for plant systems;
Triennial Fire Protection Inspection; and
      b. Organization charts of site personnel down to the level of fire protection staff
b. List of current fire impairments, including duration.  
          personnel; and
7.  
      c. A phone list for onsite licensee personnel.
General Information:  
8.   B.5.b Mitigating Strategies:
a. A listing of abbreviations and/or designators for plant systems;
      a. A list of all modifications to regulatory commitments made to meet the
b. Organization charts of site personnel down to the level of fire protection staff  
          requirements of Section B.5.b of the ICM Order, EA-02-026, dated
personnel; and
          February 25, 2002, the subsequently imposed license conditions, and
c. A phone list for onsite licensee personnel.  
          10 CFR 50.54(hh)(2);
8.  
      b. Copies of procedures/guidelines that were revised or generated to implement
B.5.b Mitigating Strategies:  
          the mitigation strategies. These could be extensive damage mitigation
a. A list of all modifications to regulatory commitments made to meet the  
          guidelines, severe accident management guidelines, emergency operating
requirements of Section B.5.b of the ICM Order, EA-02-026, dated  
          procedures, abnormal operating procedures, etc.;
February 25, 2002, the subsequently imposed license conditions, and  
      c. A matrix that shows the correlation between the mitigation strategies
10 CFR 50.54(hh)(2);  
          identified in Nuclear Energy Institute 06-12 and the site-specific procedures
b. Copies of procedures/guidelines that were revised or generated to implement  
          or guidelines that are used to implement each strategy;
the mitigation strategies. These could be extensive damage mitigation  
      d. A listing of engineering evaluations/calculations that were used to verify
guidelines, severe accident management guidelines, emergency operating  
          engineering bases for the mitigation strategies;
procedures, abnormal operating procedures, etc.;  
      e. Copies of procedures used to inventory equipment (hoses, fittings, pumps,
c. A matrix that shows the correlation between the mitigation strategies  
          etc.) required to be used to implement the mitigation strategies;
identified in Nuclear Energy Institute 06-12 and the site-specific procedures  
                                          4
or guidelines that are used to implement each strategy;
d. A listing of engineering evaluations/calculations that were used to verify  
engineering bases for the mitigation strategies;  
e. Copies of procedures used to inventory equipment (hoses, fittings, pumps,  
etc.) required to be used to implement the mitigation strategies;  


    TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST  
              f. A list of B.5.b mitigating strategies, if any, which have implementing details
5
                  that differ from that documented in the submittals and the SER;
f. A list of B.5.b mitigating strategies, if any, which have implementing details  
              g. Copies of Memoranda of Understanding (e.g., with local fire departments)
that differ from that documented in the submittals and the SER;  
                  required to implement any mitigating strategies; and
g. Copies of Memoranda of Understanding (e.g., with local fire departments)  
              h. A list of changes made to B.5.b mitigating strategies and associated
required to implement any mitigating strategies; and  
                  procedures since the previous NRC inspection of B.5.b mitigating strategies
h. A list of changes made to B.5.b mitigating strategies and associated  
                  (June 16, 2014).
procedures since the previous NRC inspection of B.5.b mitigating strategies  
      9.     Onsite Discussions:
(June 16, 2014).  
              In addition, during the information gathering visit, it is requested that licensee
9.  
              staff be available for the following:
Onsite Discussions:  
              a. Informal discussion on plant procedures operators would use in the event of
In addition, during the information gathering visit, it is requested that licensee  
                  fire or explosion (including B.5.b mitigation strategies) and under what
staff be available for the following:  
                  conditions would the plant be shutdown using alternative shutdown
a. Informal discussion on plant procedures operators would use in the event of  
                  methodology;
fire or explosion (including B.5.b mitigation strategies) and under what  
              b. Informal discussion on the plants safe shutdown cable routing database and
conditions would the plant be shutdown using alternative shutdown  
                  the plant-wide cable routing database, as applicable; and
methodology;  
              c. A tour of alternative shutdown and risk-significant fire areas.
b. Informal discussion on the plants safe shutdown cable routing database and  
              d. A discussion of scheduling of fire drills which may occur during the inspection
the plant-wide cable routing database, as applicable; and  
                  so that the inspectors may be able to observe a fire drill, if possible.
c. A tour of alternative shutdown and risk-significant fire areas.  
III. Information Requested to be Available on first Day of the Second Onsite
d. A discussion of scheduling of fire drills which may occur during the inspection  
      Inspection Week (November 13, 2017):
so that the inspectors may be able to observe a fire drill, if possible.  
      The following information is requested to be provided on the first day of inspection. It is
III.  
      requested that this information be provided on four sets of CDs (searchable, if possible).
Information Requested to be Available on first Day of the Second Onsite  
      1.     Program Procedures:
Inspection Week (November 13, 2017):  
              a. Procedures for:
The following information is requested to be provided on the first day of inspection. It is  
                      i. Administrative controls (such as allowed out of service times and
requested that this information be provided on four sets of CDs (searchable, if possible).  
                          compensatory measures) for fire protection systems and components
1.  
                      ii. Control of transient combustibles
Program Procedures:  
                    iii. Control of hot work
a. Procedures for:  
              b. List of maintenance and surveillance testing procedures for alternative
i.  
                  shutdown capability and fire barriers, detectors, pumps, and suppression
Administrative controls (such as allowed out of service times and  
                  systems; and
compensatory measures) for fire protection systems and components  
              c. List of maintenance procedures which routinely verify fuse breaker
ii.  
                  coordination in accordance with the post-fire safe shutdown coordination
Control of transient combustibles  
                  analysis.
iii.  
                                                  5
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.  


      TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST  
        2.   Design and Equipment Information:
6
              a. Coordination calculations and/or justifications that verify fuse/breaker
2.  
                  coordination for selected fire zones/areas (to be determined during
Design and Equipment Information:  
                  information gathering visit) that are fed off of the same electrical buses as
a. Coordination calculations and/or justifications that verify fuse/breaker  
                  components in the protected safe shutdown train;
coordination for selected fire zones/areas (to be determined during  
              b. Copies of significant fire protection and post-fire safe shutdown related
information gathering visit) that are fed off of the same electrical buses as  
                  design change package descriptions (including their associated 10 CFR
components in the protected safe shutdown train;  
                  50.59 evaluations) and Generic Letter 86-10 (or adverse to safe shutdown)
b. Copies of significant fire protection and post-fire safe shutdown related  
                  evaluations;
design change package descriptions (including their associated 10 CFR  
              c. Gaseous suppression system pre-operational testing, if applicable, for
50.59 evaluations) and Generic Letter 86-10 (or adverse to safe shutdown)  
                  selected fire zones/areas (to be determined during information gathering
evaluations;  
                  visit);
c. Gaseous suppression system pre-operational testing, if applicable, for  
              d. Hydraulic calculations and supporting test data which demonstrate operability
selected fire zones/areas (to be determined during information gathering  
                  for water suppression systems, if applicable, for selected fire zones/areas (to
visit);  
                  be determined during information gathering visit);
d. Hydraulic calculations and supporting test data which demonstrate operability  
              e. Alternating current coordination calculations for 4160Vac down to 480Vac
for water suppression systems, if applicable, for selected fire zones/areas (to  
                  electrical systems; and
be determined during information gathering visit);  
              f.   List of all fire protection or Appendix R calculations.
e. Alternating current coordination calculations for 4160Vac down to 480Vac  
        3.   Assessment and Corrective Actions:
electrical systems; and  
              The three most recent fire protection Quality Assurance audits and/or fire
f. List of all fire protection or Appendix R calculations.  
              protection self-assessments.
3.  
IV.     Information Requested to Be Provided Throughout the Inspection:
Assessment and Corrective Actions:  
        1.   Copies of any corrective action documents generated as a result of the
The three most recent fire protection Quality Assurance audits and/or fire  
              inspection teams questions or queries during this inspection.
protection self-assessments.  
        2.   Copies of the list of questions submitted by the inspection team members and
IV.  
              the status/resolution of the information requested (provided daily during the
Information Requested to Be Provided Throughout the Inspection:  
              inspection to each inspection team member).
1.  
Copies of any corrective action documents generated as a result of the  
inspection teams questions or queries during this inspection.  
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).  
If you have questions regarding the information requested, please contact the lead inspector.
If you have questions regarding the information requested, please contact the lead inspector.
                                                    6
}}
}}

Latest revision as of 12:00, 8 January 2025

Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information 05000373/2017010; 05000374/2017010 (Akd)
ML17249A826
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 09/05/2017
From: Alan Dahbur
Engineering Branch 3
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
References
IR 2017010
Download: ML17249A826 (10)


See also: IR 05000373/2017010

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE RD. SUITE 210

LISLE, IL 60532-4352

September 5, 2017

Mr. Bryan C. Hanson

Senior VP, Exelon Generation Company, LLC

President and CNO, Exelon Nuclear

4300 Winfield Road

Warrenville, IL 60555

SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2NOTIFICATION OF NRC

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR

INFORMATION 05000373/2017010; 05000374/2017010

Dear Mr. Hanson:

On October 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) will begin a Triennial

Fire Protection Baseline Inspection at your LaSalle County Station, Units 1 and 2. This

inspection will be performed in accordance with Inspection Procedure (IP) 71111.05T,

the NRCs Baseline Fire Protection IP.

Changes were made to the IP 71111.05T which now requires the Fire Protection Inspection

to review your actions to mitigate postulated events that could potentially cause loss of large

areas of power reactor facilities due to explosions or fires. This requirement was implemented

by the issuance of the Interim Compensatory Measures Order EA-02-026, Section B.5.b,

and the subsequent requirements of Title 10 of the Code of Federal Regulations (CFR),

Part 50.54(hh)(2), which are collectively referred to as B.5.b requirements. During this

inspection, the B.5.b requirements review will be performed during the first onsite week of

the inspection starting on November 1, 2017.

The schedule for the onsite inspection activity is as follows:

Information Gathering Visit: October 30, 2017;

B.5.b Requirements: November 1-3, 2017; and

Fire Protection Inspection: November 13-17, 2017, and

November 27-December 1, 2017.

The purpose of the information gathering visit is: (1) to obtain information and documentation

needed to support the inspection; (2) to become familiar with the LaSalle Fire Protection

Programs, fire protection features, post-fire safe shutdown capabilities, and plant layout; and

(3) to arrange administrative details, such as office space, availability of knowledgeable office

personnel and to ensure unescorted site access privileges.

B. Hanson

-2-

Experience has shown that the Baseline Fire Protection 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 four groups.

The first group lists information necessary to aid the inspection team in

choosing specific focus areas for the inspection. It is requested that this

information be provided to the lead inspector via mail or electronically no

later than October 20, 2017.

The second group also lists information and areas for discussion necessary to

aid the inspection team in choosing specific fire protection focus areas for the

inspection and to ensure that the inspection team is adequately prepared for the

inspection. It is requested this information be available during the information

gathering visit on October 30, 2017.

The third 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 second onsite inspection week of

November 13, 2017.

The fourth 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 Mr. Alan Dahbur. We understand that our

regulatory contact for this inspection is Mr. Terry Lanc of your organization. If there are

and questions about the inspection or the material requested, please contact the lead

inspector at 630-829-9810, or via e-mail at Alan.Dahbur@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.

B. Hanson

-3-

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Alan Dahbur, Senior Reactor Inspector

Engineering Branch 3

Division of Reactor Safety

Docket Nos. 50-373; 50-374

License Nos. NPF-11; NPF-18

Enclosure:

Triennial Fire Protection Baseline

Inspection Document Request

cc: Distribution via LISTSERV

B. Hanson

-4-

Letter to Bryan C. Hanson from Alan Dahbur dated September 5, 2017

SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2NOTIFICATION OF NRC

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR

INFORMATION 05000373/2017010; 05000374/2017010

DISTRIBUTION:

Jeremy Bowen

RidsNrrDorlLpl3

RidsNrrPMLaSalle

RidsNrrDirsIrib Resource

Cynthia Pederson

James Trapp

Richard Skokowski

Allan Barker

Carole Ariano

Linda Linn

DRPIII

DRSIII

ADAMS Accession Number ML17249A826

OFFICE

RIII

RIII

RIII

RIII

NAME

ADahbur:cl

DATE

09/05/17

OFFICIAL RECORD COPY

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST

Enclosure

Inspection Report: 05000373/2017010 AND 05000374/2017010

Onsite Inspection Dates:

October 30, 2017

(Information Gathering Visit)

November 1-3, 2017

(B.5.b Requirements)

November 13-17, 2017

(Fire Protection Inspection)

November 27-December 1, 2017

(Fire Protection Inspection)

Inspection Procedures:

IP 71111.05T, Fire Protection (Triennial)

IP 71152, Identification and Resolution of Problems

Inspectors:

Alan Dahbur

Senior Reactor Inspector (Lead)

630-829-9810

Alan.Dahbur@nrc.gov

Atif Shaikh

Jasmine Gilliam

Senior Reactor Inspector

Reactor Inspector

630-829-9824

630-829-9831

Atif.Shaikh@nrc.gov

Jasmine.Gilliam@nrc.gov

I.

Information Requested Prior To the Information Gathering Visit:

The following information is requested by October 20, 2017. If you have any

questions regarding this request, please call the lead inspector as soon as possible. All

information should be sent to Mr. Alan Dahbur (e-mail address Alan.Dahbur@nrc.gov).

Electronic media is preferred. The preferred file format is a searchable pdf file on a

compact disk (CD). The CD should be indexed and hyper-linked to facilitate ease of

use, if possible. Please provide four copies of each CD submitted (one for each

inspector).

1.

The most risk-significant fire areas as determined by probabilistic risk analyses, if

available. Otherwise, the reactor plant's Individual Plant Examination for External

Events for fire and results of any post-Individual Plant Examination for External

Events reviews for fire.

2.

A copy of the current version of the Fire Protection Program, fire hazards

analysis, safe shutdown analysis, Updated Safety Analysis Report, technical

specifications, license (including the fire protection license condition), and

technical requirements manual or equivalent for fire protection structures,

systems, and components.

3.

A list of fire areas requiring alternative shutdown capability, (i.e., those areas for

which Title 10 of the Code of Federal Regulations (CFR), Part 50, Appendix R,

Section III G, requirements are satisfied under Section III.G.3), or where both

safe shutdown trains can be affected.

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST

2

4.

Plant operating procedures which would be used and describe shutdown for a

postulated fire (for both areas requiring alternative shutdown and areas which do

not require alternative shutdown). Only those procedures with actions specific to

shutdown in the event of a fire need be included. In addition, please include

those procedures which operators would use for initial response to a fire, such as

annunciator or alarm response procedures, the procedure used for activating the

fire brigade, and the procedure which directs operators to the applicable safe

shutdown procedure.

5.

Analysis performed in support of plant evaluation regarding multiple spurious

operation (MSO), which includes the following:

a. List of identified multiple spurious fire-induced circuit failure configurations.

b. List of the generic and plant specific MSOs.

c. Results of expert panel process and associated review/evaluation of the

generic and plant specific MSOs and existing safe shutdown analysis.

d. Evaluations and corrective actions taken for resolution of MSO issues.

II.

Information Requested During the Information Gathering Visit (October 30, 2017):

The following information is requested to be provided to the inspection team during the

onsite information gathering visit. Except for Item 8, it is requested that the following

information be provided on four sets of CDs (searchable, if possible) with the B.5.b

Mitigating Strategies information (Items 8.a through 8.h) provided on one separate CD.

In addition, one set of hard copy drawings are requested for Items 4.a. through 4.d.

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 10 CFR 50.48 and 10 CFR Part 50, Appendix R, and

associated licensing correspondence;

d. 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

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST

3

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, and safe shutdown analysis 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. A listing of the protection methodologies identified under 10 CFR Part 50,

Appendix R,Section III.G used to achieve compliance for selected fire

zones/areas (to be determined during information gathering visit). 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; (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 code versions committed to (i.e., the National Fire Protection

Association Codes of Record); and

e. List of plant deviations from code commitments and associated evaluations.

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, those components used for those areas requiring alternative

shutdown capability, and systems relied upon for B.5.b mitigation strategies.

These can be of the type that are used for training;

b. One-line schematic drawings of the electrical distribution system for 4160

Volts alternating current (Vac) down to 480Vac;

c. One-line schematic drawings of the electrical distribution system for 250 Volts

direct current and 125 Volts direct current systems as applicable;

d. Logic diagrams showing the components used to achieve and maintain hot

standby and cold shutdown; and

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST

4

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 selected fire zones/areas (to be determined during

information gathering visit);

b. Plant operating procedures which specify the initial operations response to a

fire alarm or annunciator; and

c. Procedure for calling out the fire brigade and requesting off-site assistance.

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.

8.

B.5.b Mitigating Strategies:

a. A list of all modifications to regulatory commitments made to meet the

requirements of Section B.5.b of the ICM Order, EA-02-026, dated

February 25, 2002, the subsequently imposed license conditions, and

10 CFR 50.54(hh)(2);

b. Copies of procedures/guidelines that were revised or generated to implement

the mitigation strategies. These could be extensive damage mitigation

guidelines, severe accident management guidelines, emergency operating

procedures, abnormal operating procedures, etc.;

c. A matrix that shows the correlation between the mitigation strategies

identified in Nuclear Energy Institute 06-12 and the site-specific procedures

or guidelines that are used to implement each strategy;

d. A listing of engineering evaluations/calculations that were used to verify

engineering bases for the mitigation strategies;

e. Copies of procedures used to inventory equipment (hoses, fittings, pumps,

etc.) required to be used to implement the mitigation strategies;

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST

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f. A list of B.5.b mitigating strategies, if any, which have implementing details

that differ from that documented in the submittals and the SER;

g. Copies of Memoranda of Understanding (e.g., with local fire departments)

required to implement any mitigating strategies; and

h. A list of changes made to B.5.b mitigating strategies and associated

procedures since the previous NRC inspection of B.5.b mitigating strategies

(June 16, 2014).

9.

Onsite Discussions:

In addition, during the information gathering visit, it is requested that licensee

staff be available for the following:

a. Informal discussion on plant procedures operators would use in the event of

fire or explosion (including B.5.b mitigation strategies) and under what

conditions would the plant be shutdown using alternative shutdown

methodology;

b. Informal discussion on the plants safe shutdown cable routing database and

the plant-wide cable routing database, as applicable; and

c. A tour of alternative shutdown and risk-significant fire areas.

d. A discussion of scheduling of fire drills which may occur during the inspection

so that the inspectors may be able to observe a fire drill, if possible.

III.

Information Requested to be Available on first Day of the Second Onsite

Inspection Week (November 13, 2017):

The following information is requested to be provided on the first day of inspection. It is

requested that this information be provided on four 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

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.

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST

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2.

Design and Equipment Information:

a. Coordination calculations and/or justifications that verify fuse/breaker

coordination for selected fire zones/areas (to be determined during

information gathering visit) that are fed off of the same electrical buses as

components in the protected safe shutdown train;

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 (to be determined during information gathering

visit);

d. Hydraulic calculations and supporting test data which demonstrate operability

for water suppression systems, if applicable, for selected fire zones/areas (to

be determined during information gathering visit);

e. Alternating current coordination calculations for 4160Vac down to 480Vac

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.

IV.

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.

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).

If you have questions regarding the information requested, please contact the lead inspector.