ML19227A399: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
Line 1: Line 1:
{{Adams
#REDIRECT [[IR 05000250/2019012]]
| number = ML19227A399
| issue date = 08/15/2019
| title = Notification of Conduct of a Triennial Fire Protection Baseline Inspection Report Nos. 05000250/2019012 and 05000251/2019012
| author name = Shaeffer S
| author affiliation = NRC/RGN-II/DRS/EB2
| addressee name = Moul D
| addressee affiliation = Florida Power & Light Co
| docket = 05000250, 05000251
| license number = DPR-031, DPR-041
| contact person =
| document report number = IR 2019012
| document type = Inspection Report, Letter
| page count = 10
}}
See also: [[see also::IR 05000250/2019012]]
 
=Text=
{{#Wiki_filter:UNITED STATES
                                  NUCLEAR REGULATORY COMMISSION
                                                  REGION II
                              245 PEACHTREE CENTER AVENUE NE, SUITE 1200
                                        ATLANTA, GEORGIA 30303-1257
                                            August 15, 2019
Mr. Don Moul
Vice President, Nuclear Division and Chief Nuclear Officer
Florida Power & Light Company
Mail Stop: NT3/JW
15430 Endeavor Drive
Jupiter, FL 33478
SUBJECT: TURKEY POINT NUCLEAR PLANT, UNITS 3 AND 4 - NOTIFICATION OF
              CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION-
              U. S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT
              NOS. 05000250/2019012 AND 05000251/2019012
Dear Mr. Moul:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
staff will conduct a triennial fire protection baseline inspection at your Turkey Point Plant Units 3
& 4 in October and November 2019. The inspection will be conducted in accordance with IP
71111.05XT, the NRCs baseline fire protection inspection procedure for plants that have
transitioned their fire protection program to meet the requirements of Title 10 of the Code of
Federal Regulations (10 CFR) 50.48(c). The inspection team will be led by Mr. Jonathan
Montgomery, a Senior Reactor Inspector from the NRC Region II Office. The team will be
composed of personnel from the Region II Office.
On August 7, 2019, during a telephone conversation between Olga Hanek of your staff and
Mr. Montgomery, our respective staffs confirmed arrangements for a three-day information
gathering onsite visit and a two-week onsite inspection. The schedule for the inspection is as
follows:
    *  Information gathering visit: September 24-26, 2019
    *  Week 1 of onsite inspection: October 21-25, 2019
    *  Week 2 of onsite inspection: November 4-8, 2019
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, to become familiar with the Turkey Point plants fire protection
program, fire protection features, post-fire safe shutdown capabilities, plant layout, mitigating
strategies to address 10 CFR 50.54(hh)(2), and, as necessary, obtain plant specific site access
training and badging for unescorted site access.
 
D. Moul                                        2
The types of documents the team will be reviewing during conduct of the inspection are listed in
Enclosures 1 and 2. Please contact Mr. Montgomery at (404) 997-4880 prior to preparing
copies of the materials listed in the Enclosures. The inspection team will try to minimize your
administrative burden by specifically identifying those documents required for inspection
preparation.
During the information gathering visit, the team will also discuss the following inspection support
administrative details: office space; specific documents to be made available to the team in their
office space; arrangements for unescorted site access (including, as necessary, radiation
protection training, security, safety and fitness for duty requirements); and the availability of
knowledgeable plant engineering and licensing organization personnel to serve as points of
contact during the inspection.
We request that during the onsite inspection weeks you ensure that copies of analyses,
evaluations or documentation regarding the implementation and maintenance of the Turkey
Point fire protection program, including post-fire safe shutdown capability, be readily accessible
to the team for their review. Of specific interest for the fire protection portion of the inspection
are those documents which establish that your fire protection program satisfies NRC regulatory
requirements and conforms to applicable NRC and industry fire protection guidance (i.e. fire
protection compliance assessment documents). For the 10 CFR 50.54(hh)(2) portion of the
inspection, those documents implementing your mitigating strategies and demonstrating the
management of your commitments for the strategies are of specific interest. Also, personnel
should be available at the site during the inspection who are knowledgeable regarding those
plant systems required to achieve and maintain safe shutdown conditions from inside and
outside the control room (including the electrical aspects of the relevant post-fire safe shutdown
analyses), reactor plant fire protection systems and features, and the Harris fire protection
program and its implementation.
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, under 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 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosures will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRCs document system
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
 
D. Moul                                      3
Your cooperation and support during this inspection will be appreciated. If you have questions
concerning this inspection, or the inspection team's information or logistical needs, please
contact Mr. Montgomery, the team leader, in the Region II Office at (404) 997-4880, or me
at (404) 997-4521.
                                              Sincerely,
                                              /RA/
                                              Scott M. Shaeffer, Chief
                                              Engineering Branch 2
                                              Division of Reactor Safety
Docket Nos: 50-250, 50-251
License Nos: DPR-31, DPR-41
Enclosures:
1. Triennial Fire Protection Inspection
    Supporting Documentation
2. Mitigating Strategies Supporting
    Documentation
cc: Distribution via ListServ
 
 
ML19227A399                  SUNSI REVIEW COMPLETE    FORM 665 ATTACHED
    OFFICE                RII:DRS          RII:DRS
    SIGNATURE              JMM          RJF2 r SMS
    NAME              MONTGOMERY        SHAEFFER
    DATE                8/ 14 /2019      8/ 15 /2019
    E-MAIL COPY?        YES      NO    YES      NO
     
                    Triennial Fire Protection Inspection Supporting Documentation
The documents and information requested below should generally be made available to the
inspection team during the on-site information gathering visit for the team's use both on-site and
off-site during the inspection. Electronic format is the preferred media, except where specifically
noted. If electronic media is made available via an internet based remote document
management system, then the remote document access must allow inspectors to download,
save, and print the documents in the NRC's regional office. Electronic media on compact disc
or paper records (hard copy) are acceptable. At the end of the inspection, the documents in the
team's possession will not be retained.
Approximately three weeks before the on-site information gathering visit, the following
documents should be made available to the team leader for review in the regional office:
    *  Post-fire Nuclear Safety Capability, Systems, and Separation Analysis (request A.1)
    *  Fire Hazards Analysis and/or NFPA 805 Design Basis Document (request A.2)
    *  Fire Probabilistic Risk Assessment (PRA) Summary Report (request A.3)
    *  Fire Risk Evaluations (i.e., NFPA 805 Section 2.4.3) (request A.5)
    *  Plant Change Evaluations (i.e., NFPA 805 Section 2.4.4) (request A.6)
    *  List of the top 25 highest CDF scenarios for each unit
    *  List of the top 25 highest LERF scenarios for each unit
    *  Status of committed modifications and implementation items listed in Attachment S of
        the NFPA 805 Transition Report
Based on review of the above eight documents, the team leader should identify a preliminary list
of fire areas being considered for inspection prior to the on-site information gathering visit.
During the information gathering visit, or shortly thereafter, the fire areas selected for inspection
will be determined.
This document request is based on typical documents that a generic plant might have. As such,
this generic document request is not meant to imply that any specific plant is required to have all
of the listed documents. It is recognized that some documents listed below may not be
available for your plant. In addition, the document titles listed below are based on typical
industry document names; your plant specific document titles may vary.
                                                                                          Enclosure 1
 
A. DESIGN AND LICENSING BASIS DOCUMENTS
  A.1  Post-fire Nuclear Safety Capability, Systems, and Separation Analysis.
  A.2  Fire Hazards Analysis and/or NFPA 805 Design Basis Document.
  A.3  Fire PRA Summary Report
  A.4  LIST of Fire PRA Calculations (i.e. Component Selection Calculation, Partitioning and
        Frequency Calculation, etc.)
  A.5  Fire Risk Evaluations (i.e., NFPA 805 Section 2.4.3).
  A.6  Plant Change Evaluations (i.e., NFPA 805 Section 2.4.4).
  A.7  Fire Protection Program and/or Fire Protection Plan.
  A.8  LIST of post-fire safe shutdown components (i.e., safe shutdown equipment list), if
        not already included in A.1 document.
  A.9  Fire Protection System Design Basis Document.
  A.10 COPY of NRC approved exemptions for plant fire protection and post-fire nuclear
        safety capability features.
  A.11 LIST of nuclear safety capability design changes completed in the last three years
        (including their associated 10 CFR 50.59 and NFPA 805 plant change evaluations).
  A.12 Facility Operating License.
  A.13 Technical Specifications (electronic format only).
  A.14 Technical Requirements Manual, or equivalent (electronic format only).
B. GENERAL PLANT DESIGN DOCUMENTS
  B.1  Piping and instrumentation diagrams (P&IDs) and legend list for systems used to
        achieve and maintain nuclear safety performance criteria for: (C-size paper drawings
        & electronic format)
        * Fires outside the main control room; and
        * Fires in areas requiring recovery actions at other than primary control stations.
  B.2  P&IDs and legend list for fire protection systems, including fire water supply, water
        suppression sprinklers & deluge, and CO2 and Halon systems (C-size paper
        drawings & electronic format).
  B.3  Yard layout drawings for underground fire protection buried piping (C-size paper
        drawings & electronic format).
  B.4  AC and DC electrical system single line diagrams, from off-site power down to the
        highest safety-related bus level (typically 4kV, EDG bus) (C-size paper drawings &
        electronic format).
                                              2
 
  B.5  Single line diagrams for motor control centers (MCCs) that supply post-fire nuclear
        safety component loads (only for selected fire areas) (C-size paper drawings &
        electronic format).
C. CLASSIC FIRE PROTECTION
  C.1  COPY of fire protection program implementing procedures (e.g., administrative
        controls, surveillance testing, fire brigade).
  C.2  LIST of calculations and engineering analyses, studies, or evaluations for the fire
        protection system, including the fire water system.
  C.3  Hydraulic calculation or analysis for fire protection water system.
  C.4  Last two completed surveillance's of fire protection features in the selected fire areas
        (detection, suppression, damper inspections, damper tests, penetration inspections,
        barrier inspections, etc.).
  C.5  LIST of routine tests, surveillances, and preventive maintenance on fire pumps,
        including pump controllers and batteries.
  C.6  Last two completed annual fire pump pressure and flow tests.
  C.7  Last two completed monthly and/or quarterly fire pump tests.
  C.8  Last two completed fire loop flow tests and loop flushes.
  C.9  CO2 and Halon initial discharge testing or calculation that determined appropriate
        concentrations and soak or hold times can be achieved (only for selected fire areas).
  C.10 For Fire Brigade Drills, provide the following:
        * Last five fire brigade drill critiques;
        * Summary of any unsatisfactory drill performance items for last three years; and
        * Last unannounced drill critique by a qualified individual independent of the
            licensee's staff.
  C.11 For fire brigade equipment provide the following:
        * Procedure for inventory and inspection; and
        * Most recent inspection and inventory results.
  C.12 Fire Brigade Qualifications, including self-contained breathing apparatus (SCBA) and
        training lesson plans.
  C.13 COPY of the evaluation or analysis of the effects of fire suppression activities on the
        ability to achieve the nuclear safety performance criteria (only for selected fire areas),
        including:
        * An automatic or manually actuated suppression system, due to a fire in a single
            location, will not indirectly cause damage to the success path; and
                                                3
 
        * inadvertent actuation or rupture of a suppression system will not indirectly cause
            damage to the success path; and
        * demonstration of adequate drainage for areas protected by water suppression
            systems;
        * hydrostatic rating of any floor penetration seals installed within the fire areas that
            are credited with keeping water from leaking into fire areas below.
  C.14 LIST of work orders for work performed on any credited fire barrier (i.e., door,
        penetration seal, fire wrap, etc.) in the last three years.
  C.15 Fire protection system health reports for the two most recent quarters.
  C.16 Fire protection program health report for the two most recent quarters.
  C.17 LIST of fire protection system design changes completed in the last three years
        (including their associated 10 CFR 50.59 and NFPA 805 plant change evaluations).
  C.18 LIST of fire protection system NFPA 805 engineering equivalency evaluations
        completed in the last three years.
D. ELECTRICAL
  D.1  Identify whether the cables in the selected fire areas are predominantly Thermoset or
        Thermoplastic.
  D.2  Nuclear safety circuit coordination analysis for fuse and breaker coordination of
        nuclear safety capability components.
  D.3  Last surveillance demonstrating operability of those components operated from the
        primary control stations.
  D.4  LIST of post-fire nuclear safety capability system and component design changes
        completed, in the last three years.
E.    OPERATIONS
  E.1  LIST of licensed operator Job Performance Measures (JPMs) for recovery actions
        required to achieve and maintain post-fire nuclear safety performance criteria.
  E.2  LIST of non-licensed operator training associated with recovery actions required to
        achieve and maintain post-fire nuclear safety performance criteria (including JPMs,
        in-field training walkdowns, simulations, or initial qualification).
  E.3  For required and defense-in-depth recovery actions, provide the following:
        *  Recovery Action Feasibility Study;
        *  Operator Time Critical Action Program;
        *  Time lines for time-critical recovery actions; and
        *  Time line validations.
                                                4
 
    E.4 If applicable, thermal hydraulic calculation or analysis that determines the time
        requirements for recovery actions and defense-in-depth actions.
    E.5 Operating procedures to achieve and maintain nuclear safety performance criteria
        from the control room, with a postulated fire in the selected fire areas.
    E.6 Operating procedures to achieve and maintain nuclear safety performance criteria
        from outside the control room, with a postulated fire in the control room, cable
        spreading room, or any area requiring recovery actions (other than recovery actions
        performed in the control room or primary control stations).
    E.7 For equipment and tools required for recovery actions, provide the following:
        *    Procedure for inventory and inspection; and
        *    Most recent inspection and inventory results.
F.  ADMINISTRATIVE CONTROL, OVERSIGHT, AND CORRECTIVE ACTION PROGRAMS
    F.1 Self assessments, peer assessments, and audits of fire protection activities for the
        last three years.
    F.2 Self assessments, peer assessments, and audits of post-fire nuclear safety capability
        methodology for the last three years.
    F.3 LIST of open and closed condition reports for the fire protection system for the last
        three years.
    F.4 LIST of fire event analysis reports for the last three years.
    F.5 LIST of open and closed condition reports for post-fire nuclear safety capability issues
        for the last three years. This includes issues affecting the nuclear safety capability
        analysis, fire hazards analysis, NFPA 805 design basis, fire risk evaluations, plant
        change evaluations, post-fire operating procedures and/or training, timeline
        evaluations for operator actions, and supporting engineering evaluations, analysis, or
        calculations.
  F.6  LIST of procedures that control the configuration of the fire protection program,
        features, and post-fire nuclear safety capability methodology and system design.
  F.7  Site procedure governing the NFPA 805 Monitoring Program
                                              5
 
                      Mitigating Strategies Supporting Documentation
G. 10 CFR 50.54(hh)(2) MITIGATING STRATEGIES DOCUMENTS
  G.1  LIST of all changes to regulatory commitments made to meet the requirements of
        Title 10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2).
  G.2  LIST of procedures and guidelines that were revised or generated to implement the
        mitigating strategies. These could be extensive damage mitigation guidelines
        (EDMGs), severe accident management guidelines (SAMGs), emergency operating
        procedures (EOPs), abnormal operating procedures (AOPs), etc.
  G.3  LIST of engineering evaluations or calculations that were used to verify the
        engineering bases for the mitigating strategies.
  G.4  LIST of modification packages or summary descriptions of modifications with
        simplified drawings, for necessary facility changes to implement the mitigating
        strategies.
  G.5  LIST of routine tests, surveillances, and preventive maintenance for equipment and
        tools needed to implement 10 CFR 50.54(hh)(2) strategies.
  G.6  For equipment and tools needed to implement 10 CFR 50.54(hh)(2) strategies,
        provide the following:
        * Procedures for inventory and inspection; and
        * Most recent inspection and inventory results.
  G.7  LIST of 10 CFR 50.54(hh)(2) strategies, if any, which have implementing details that
        differ from that documented in the submittals or the safety evaluation report.
  G.8  Training records, training matrix, and lesson plans related to 10 CFR 50.54(hh)(2).
  G.9 Copies of memoranda of understanding (MOU) (e.g., with local fire departments)
        required to implement any mitigating strategies.
                                                                                  Enclosure 2
}}

Revision as of 05:17, 5 March 2020

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML19227A399&oldid=2523227"