ML16120A118
| ML16120A118 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/27/2016 |
| From: | Shaeffer S M Division of Nuclear Materials Safety IV |
| To: | Shea J W Tennessee Valley Authority |
| References | |
| IR 2016011 | |
| Download: ML16120A118 (14) | |
See also: IR 05000259/2016011
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257
April 27, 2016
Mr. Joseph W. Shea
Vice President, Nuclear Licensing
Tennessee Valley Authority
Chattanooga, TN 37402-2801
SUBJECT: BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION-
U. S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT
NOS. 05000259/2016011, 05000260/2016011, AND 05000296/2016011
Dear Mr. Shea:
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 the Browns Ferry Nuclear Plant, Units 1, 2, and 3, in July & August 2016. The inspection will be conducted in accordance with IP 71111.05XT, the NRC's 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 Jonathan Montgomery, a Senior Reactor Inspector from the NRC Region II Office. The team will be composed of personnel from the Region II Office, and one member from NRC headquarters.
On April 21, 2016, during a telephone conversation between Baruch Calkin 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: July 12-14, 2016
- Week 1 of onsite inspection: July 25-29, 2016
- Week 2 of onsite inspection: August 8-12, 2016
The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the Browns Ferry Nuclear Plant's 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.
J. Shea 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 Browns Ferry 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 Browns Ferry 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 Offi
ce 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 NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
J. Shea 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: Shakur A. Walker for/
Scott M. Shaeffer, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos: 50-259; 50-260; 50-296 License Nos: DPR-33, DPR-52, DPR-68
Enclosures:
1. Triennial Fire Protection Inspection Supporting Documentation 2. Mitigating Strategies Supporting
Documentation
cc: Distribution via ListServ
________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE JMM9 SAW4 FOR SMS NAME MONTGOMERY SHAEFFER DATE 4/27/2016 4/27/2016 5/ /2016 E-MAIL COPY? YES NO YES NO YES
N YES NO YES NO YES NO YES NO
Enclosure 1
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 Document or full PRA Document (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)
- Analysis that demonstrates nuclear safe
ty performance criteria can be achieved and maintained for those areas that require recovery actions (request A.7)
- List of the top 25 highest CDF scenarios for each of the 3 units
- List of the top 25 highest LERF scenarios for each of the 3 units
Based on review of the above nine 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.
2 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 Document or full PRA Document (if summary document not
available).
A.4 NFPA 805 Transition Report, developed in accordance with NEI 04-02.
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 Analysis that demonstrates nuclear sa
fety performance criteria can be achieved and maintained for those areas that require recovery actions.
A.8 Fire Protection Program and/or Fire Protection Plan.
A.9 LIST of post-fire safe shutdown components (i.e., safe shutdown equipment list).
A.10 Fire Protection System Design Basis Document.
A.11 LIST of applicable NFPA codes and standards and issuance dates (i.e., codes of
record). A.12 LIST of deviations from (a) NFPA codes of record, or (b) NFPA 805 fundamental fire protection program and design elements (i.e., NFPA 805, Chapter 3).
A.13 NFPA Compliance Review Report.
A.14 Report or evaluation that compares the fire protection program to the NRC Branch Technical Position (BTP) 9.5-1 Appendix A.
A.15 COPY of licensee submittals and NRC safety evaluation reports that are specifically listed in the facility operating license for the approved fire protection program.
A.16 COPY of NRC Safety Evaluation Reports that form the licensing basis for:
- Post-fire Nuclear Safety Capability.
A.17 COPY of NRC approved exemptions for plant fire protection and post-fire nuclear safety capability features.
3 A.18 COPY of exemption requests submitted but not yet approved for plant fire protection and post-fire nuclear safety capability features.
A.19 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.20 Facility Operating License.
A.21 Technical Specifications (electronic format only).
A.22 Technical Requirements Manual (electronic format only).
A.23 Updated Final Safety Analysis Report (electronic format only).
B. GENERAL PLANT DESIGN DOCUMENTS
B.1 Piping and instrumentation diagrams (P&IDs) and legend list for components 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 di
agrams, from off-site power down to the highest safety-related bus level (typically 4kV, EDG bus) (C-size paper drawings & electronic format).
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).
B.6 Equipment location drawings which identify the physical plant locations of post-fire nuclear safety capability equipment (electronic format).
B.7 Plant layout drawings which identify: (electronic format)
- Plant fire area boundaries;
- Combustible control zone drawings;
- Areas protected by automatic fire suppression and detection; and
- Locations of fire protection equipment.
4 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 Last five hot work permits (at power).
C.11 Last five transient combustible permits (at power).
C.12 For Fire Brigade Drills, provide the following:
- Last five fire brigade drill critiques;
- Last drill critique for a drill with off-site fire department support;
- Last unannounced drill critique;
- Last back-shift drill critique;
- Dates, shifts, and locations of unannounced drills for last three years;
- 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.13 For fire brigade equipment provide the following:
- Procedure for inventory and inspection; and
- Most recent inspection and inventory results.
5 C.14 Fire Brigade Qualifications, including self-contained breathing apparatus (SCBA) and training lesson plans.
C.15 COPY of the mutual aid agreement for the "first-due" local fire department that is currently in effect.
C.16 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
- 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.17 Pre-fire plans for all fire areas.
C.18 For Emergency Lighting Units (ELU), provide the following:
- COPY of performance based emergency light assessments;
- LIST of Preventive Maintenance tasks, frequencies, and bases;
- Most recently performed monthly or quarterly functional test;
- Most recently performed battery discharge performance test;
- ELU battery loading analysis;
- vendor manual(s) for on-site inspector use;
- results of black-out testing (if performed);
- Maintenance Rule program information related to the ELU; and
- Compensatory measures taken when ELU are out of service
C.19 Impairment Log (at start of inspection), for fire protection features that are out of service. C.20 Three Fire Protection screening reviews for recent design changes, modifications, or temporary modifications (i.e., an NFPA 805 plant change evaluation that screened
out). C.21 LIST of penetration seal work, re-work, or installation activities, in the last three years.
C.22 LIST of fire wrap work, re-work, or installation activities, in the last three years.
C.23 Fire protection system health reports for the two most recent quarters.
C.24 Fire protection program health report for the two most recent quarters.
6 C.25 Emergency lighting system health reports for the two most recent quarters.
C.26 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.27 LIST of fire protection system NFPA 805 engineering equivalency evaluations completed in the last three years.
C.28 Licensee evaluation of industry operating experience, such as: (specific items to be selected by the inspector)
- NRC IN 2005-03, Inadequate Design and Installation of Seismic-Gap Fire Barriers;
- NRC IN 2006-22, Ultra-Low Sulfur Diesel Fuel Oil Usage, for diesel fire pump;
- NRC IN 2009-02, Bio-Diesel Fuel Oil Usage, for diesel fire pump; and
- NRC IN 2009-29, Fire Pumps Fail to Start due to a Fire.
C.29 COPY of any test, surveillance, or maintenance procedure (current revision), including any associated data forms, for any requested "last performed" test, surveillance, or maintenance.
D. ELECTRICAL
D.1 Identify whether the cables in the selected fire areas are predominantly Thermoset or Thermoplastic. Specifically identify any Thermoplastic cable in the selected fire
areas. D.2 Nuclear safety circuit coordination analysis for fuse and breaker coordination of nuclear safety capability components.
D.3 Administrative or configuration control procedures that govern fuse replacement (e.g., fuse control procedures).
D.4 Maintenance procedures that verify breaker over-current trip settings to ensure coordination remains functional, for post-fire nuclear safety capability components.
D.5 Electrical system health reports for the two most recent quarters.
D.6 Last surveillance demonstrating operability of those components operated from the primary control stations.
D.7 LIST of post-fire nuclear safety capability system and component design changes completed, in the last three years.
D.8 LIST of identified fire induced circuit failure configurations (only for selected fire
areas).
7 E. OPERATIONS
E.1 LIST of calculations and engineering analyses, studies, or evaluations for the nuclear
safety capability methodology.
E.2 LIST of licensed operator Job Performance Measures (JPMs) for operator actions required to achieve and maintain post-fire nuclear safety performance criteria.
E.3 LIST of non-licensed operator training associated with non-licensed operator actions
to achieve and maintain post-fire nuclear safety performance criteria (including JPMs, in-field training walkdowns, simulations, or initial qualification).
E.4 Lesson plans for post-fire nuclear safety capability training for licensed and non-licensed operators.
E.5 For recovery actions and defense-in-depth actions, provide the following:
- Manual Action Feasibility Study;
- Operator Time Critical Action Program;
- Time lines for time-critical recovery actions; and
- Time line validations.
E.6 If applicable, thermal hydraulic calculation or analysis that determines the time requirements for recovery actions and defense-in-depth actions.
E.7 Operating procedures to achieve and maintain nuclear safety performance criteria from the control room, with a postulated fire in the selected fire areas.
E.8 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.9 For safe shutdown equipment and tools, provide the following:
- Procedure for inventory and inspection; and
- Most recent inspection and inventory results.
E.10 LIST of procedures that implement Cold Shutdown Repairs.
E.11 For Cold Shutdown Repairs, provide the following:
- Procedure for inventory and inspection (i.e., needed tools, material, etc.); and
- Most recent inspection and inventory results.
8 E.12 For Radio communications, provide the following:
- Communications Plan for fire fighting and post-fire recovery actions and defense-
in-depth actions;
- Repeater locations;
- Cable routing for repeater power supply cables;
- Radio coverage test results; and
- Radio Dead Spot locations in the plant.
E.13 Environmental and habitability evaluations for post-fire recovery actions and defense-
in-depth actions (temperature, smoke, humidity, SCBAs, etc.).
F. ADMINISTRATIVE CONTROL, OVERSIGHT, AND CORRECTIVE ACTION PROGRAMS
F.1 Corrective actions for fire-induced circui
t failures (including but not limited to NRC IN 92-18), both single and multiple spurious actuations (only for selected fire areas).
F.2 Corrective actions associated with operator actions to achieve and maintain post-fire nuclear safety performance criteria.
F.3 Self assessments, peer assessments, and audits of fire protection activities for the
last three years.
F.4 Self assessments, peer assessments, and audits of post-fire nuclear safety capability
methodology for the last three years.
F.5 LIST of open and closed condition reports for the fire protection system for the last
three years.
F.6 LIST of fire event analysis reports for the last three years.
F.7 LIST of open and closed condition reports for emergency lighting units for the last
three years.
F.8 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.9 LIST of procedures that control the configuration of the fire protection program, features, and post-fire nuclear safety capability methodology and system design.
Enclosure 2 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 A matrix that shows the correlation between the mitigation strategies identified in Nuclear Energy Institute 06-12, Revision 2, "B.5.b Phase 2 & 3 Submittal Guideline," issued December 2006, and the site-specific procedures or guidelines that are used to implement each strategy.
G.4 LIST of engineering evaluations or calculations that were used to verify the engineering bases for the mitigating strategies.
G.5 Piping and instrumentation diagrams (P&ID) and legend list or simplified flow diagrams for systems relied upon in the mitigating strategies. These could be the type used for training (C-size paper drawings).
G.6 LIST of modification packages or summary descriptions of modifications with simplified drawings, for necessary facility changes to implement the mitigating
strategies.
G.7 LIST of routine tests, surveillances, and preventive maintenance for equipment and tools needed to implement 10 CFR 50.54(hh)(2) strategies.
G.8 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.9 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.
2 G.10 Site general arrangement drawings that show the majority of buildings and areas referenced in 10 CFR 50.54(hh)(2) documents (C-size paper drawings).
G.11 Training records, training matrix, and lesson plans related to 10 CFR 50.54(hh)(2).
G.12 Copies of memoranda of understanding (MOU) (e.g., with local fire departments) required to implement any mitigating strategies.