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{{Adams
#REDIRECT [[IR 05000440/2015008]]
| number = ML15204A829
| issue date = 07/23/2015
| title = IR 05000440/2015008, 09/21/15, Perry Nuclear Power Plant - Notification of NRC Triennial Fire Protection Baseline
| author name = Daley R
| author affiliation = NRC/RGN-III/DRS/EB3
| addressee name = Harkness E
| addressee affiliation = FirstEnergy Nuclear Operating Co
| docket = 05000440
| license number = NPF-058
| contact person =
| document report number = IR 2015008
| document type = Inspection Plan, Letter
| page count = 11
}}
See also: [[see also::IR 05000440/2015008]]
 
=Text=
{{#Wiki_filter:UNITED STATES
                            NUCLEAR REGULATORY COMMISSION
                                              REGION III
                                    2443 WARRENVILLE RD. SUITE 210
                                          LISLE, IL 60532-4352
                                            July 23, 2015
Mr. Ernest Harkness
Site Vice President
FirstEnergy Nuclear Operating Company
Perry Nuclear Power Plant
P. O. Box 97, 10 Center Road, A-PY-A290
Perry, OH 44081-0097
SUBJECT: PERRY NUCLEAR POWER PLANT - NOTIFICATION OF NRC TRIENNIAL FIRE
              PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION
              05000440/2015008
Dear Mr. Harkness:
On September 21, 2015, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial
fire protection baseline inspection at your Perry Nuclear Power Plant. This inspection will be
performed in accordance with Inspection Procedure (IP) 71111.05T, the NRCs baseline fire
protection inspection procedure.
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 10 CFR 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 September 23, 2015.
The schedule for the onsite inspection activity is as follows:
    Information Gathering Visit: September 21 - 23, 2015;
    B.5.b Requirements: September 23 - 25, 2015; and
    Fire Protection Inspection: October 5 - 9 and October 19 - 23, 2015.
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 Perry Nuclear Power Plant 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.
 
E. Harkness                                    -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 September 11, 2015.
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 (September 21, 2015). 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 (October 5, 2015). 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. Dariusz Szwarc. We understand that our regulatory
contact for this inspection is Mr. David Lockwood of your organization. If there are any
questions about the inspection or the material requested, please contact the lead inspector at
(630) 829-9803 or via e-mail at dariusz.szwarc@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.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy
of this letter, its enclosure, and your response (if any) will be available electronically for public
 
E. Harkness                              -3-
inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html
(the Public Electronic Reading Room).
                                          Sincerely,
                                          /RA George Hausman Acting for/
                                          Robert C. Daley, Chief
                                          Engineering Branch 3
                                          Division of Reactor Safety
Docket No. 50-440
License No. NPF-58
Enclosure: Fire Protection Inspection
  Document Request
cc w/encl: Distribution via LISTSERV
 
    NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
                                  REQUEST FOR INFORMATION
Inspection Report:            05000440/2015008
Onsite Inspection Dates:      September 21 - 23, 2015        (Information Gathering Visit)
                              September 23 - 25, 2015        (B.5.b Requirements)
                              October 5 - 9, 2015            (Fire Protection Inspection)
                              October 19 - 23, 2015          (Fire Protection Inspection)
Inspection Procedures:        IP71111.05T, Fire Protection (Triennial)
                              IP71152, "Identification and Resolution of Problems"
Inspectors:                    Dariusz Szwarc                          Alan Dahbur
                              Senior Reactor Inspector (Lead)        Senior Reactor Inspector
                              (630) 829-9803                          (630) 829-9810
                              dariusz.szwarc@nrc.gov                  alan.dahbur@nrc.gov
                              George Hausman                          Robert Winter
                              Senior Reactor Inspector                Reactor Inspector
                              (630) 829-9743                          (630) 829-9758
                              george.hausman@nrc.gov                  robert.winter@nrc.gov
I. Information Requested Prior To the Information Gathering Visit
  The following information is requested by September 11, 2015. If you have any questions
  regarding this request, please call the lead inspector as soon as possible. All information
  should be sent to Mr. Dariusz Szwarc (e-mail address dariusz.szwarc@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 (IPEEE) for fire and results of any post-IPEEE reviews for fire.
  2. A copy of the current version of the fire protection program (FPP), fire hazards
      analysis (FHA), safe shutdown analysis (SSA), updated safety analysis report (USAR),
      technical specifications, license (including the fire protection license condition), and
      technical requirements manual (TRM) 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
      10 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.
                                                                                          Enclosure
 
      NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
                                  REQUEST FOR INFORMATION
    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; and
        d. Evaluations and corrective actions taken for resolution of MSO issues.
II. Information Requested During the Information Gathering Visit (SEPTEMBER 21, 2015)
    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;
                                                    2
 
NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
                              REQUEST FOR INFORMATION
  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 (BTP) 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 BTP APCSB 9.5-1 was published in
          August 1976 (10 CFR 50.48(b)(1)(ii)); and
  e.    The final safety analysis report (FSAR) sections applicable to fire protection, FHA,
          and SSA in effect at the time of original licensing.
3. Fire Protection Program:
  a.    A listing of changes made to the FPP 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
          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
          (NFPA) code versions committed to (i.e., the NFPA 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;
                                              3
 
  NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
                              REQUEST FOR INFORMATION
    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 (Vdc) and 125Vdc 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 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);
                                              4
 
NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
                              REQUEST FOR INFORMATION
  b.    Copies of procedures/guidelines that were revised or generated to implement the
        mitigation strategies. These could be extensive damage mitigation guidelines
        (EDMGs), severe accident management guidelines (SAMGs), emergency
        operating procedures (EOPs), abnormal operating procedures (AOPs), 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;
  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 safety evaluation report;
  g.    Copies of Memoranda of Understanding (MOUs) (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 (March 13, 2012).
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;
  c.    A tour of alternative shutdown and risk significant fire areas; and
  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.
                                              5
 
      NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
                                    REQUEST FOR INFORMATION
III. Information Requested to be Available on First Day of the Second ONSITE Inspection
    Week (OCTOBER 5, 2015)
    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; 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:
        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 (GL) 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 (ac) coordination calculations for 4160Vac down to 480Vac
                electrical systems; and
        f.    List of all fire protection or Appendix R calculations.
                                                    6
 
      NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
                                  REQUEST FOR INFORMATION
    3. Assessment and Corrective Actions:
                The three most recent fire protection Quality Assurance (QA) audits and/or fire
                protection self-assessments.
    4. Any updates to information previously provided.
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.
                                                7
 
E. Harkness                                                                -3-
inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS
is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic
Reading Room).
                                                                          Sincerely,
                                                                          /RA George Hausman Acting for/
                                                                          Robert C. Daley, Chief
                                                                          Engineering Branch 3
                                                                          Division of Reactor Safety
Docket No. 50-440
License No. NPF-58
Enclosure: Fire Protection Inspection
  Document Request
cc w/encl: Distribution via LISTSERV
DISTRIBUTION w/encl:
Kimyata MorganButler
RidsNrrPMPerry Resource
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Cynthia Pederson
Darrell Roberts
Richard Skokowski
Allan Barker
Carole Ariano
Linda Linn
DRPIII
DRSIII
Jim Clay
Carmen Olteanu
ROPreports.Resource@nrc.gov
ADAMS Accession Number ML15204A829
    Publicly Available                          Non-Publicly Available                    Sensitive                Non-Sensitive
To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
OFFICE              RIII                                RIII                            RIII                              RIII
NAME                DSzwarc:jw                          GHausman for
                                                          RDaley
DATE                07/23/15                            07/23/15
                                                            OFFICIAL RECORD COPY
}}

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