ML14304A344
| ML14304A344 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 10/30/2014 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Vehec T NextEra Energy Duane Arnold |
| Dariusz Szwarc | |
| References | |
| IR 2015008 | |
| Download: ML14304A344 (12) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION LISLE, IL 60532-4352 October 30, 2014 Mr. Thomas Vehec Vice President NextEra Energy Duane Arnold, LLC 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION 05000331/2015008
Dear Mr. Vehec:
On January 12, 2015, the U.S. Nuclear Regulatory Commission (NRC) will begin a Triennial Fire Protection Baseline Inspection at your Duane Arnold Energy Center. This inspection will be performed in accordance with Inspection Procedure (IP) 71111.05XT, the NRCs Baseline National Fire Protection Association (NFPA) 805 Fire Protection Inspection Procedure. The inspection team will be composed of personnel from the NRC Region III office and accompanying personnel from the NRC Office of Nuclear Reactor Regulation.
Inspection Procedure 71111.05XT 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 January 14, 2015.
The schedule for the onsite inspection activity is as follows:
Information Gathering Visit: January 12 - 14, 2015; B.5.b Requirements: January 14 - 16, 2015; and Fire Protection Inspection: January 26 - 30 and February 9 - 13, 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 Duane Arnold Energy Center 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.
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 December 22, 2014.
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 January 12, 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 of January 26, 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 Ms. Tracy Weaver 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.
T. Vehec In accordance with Title 10, Code of Federal Regulations (CFR), Section 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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).
Sincerely,
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-331 License No. DPR-49
Enclosure:
Fire Protection Inspection Document Request cc w/encl: Distribution via LISTSERV
FIRE PROTECTION INSPECTION DOCUMENT REQUEST Enclosure 1
Inspection Report: 05000331/2015008 Onsite Inspection Dates:
January 12 - 14, 2015 (Information Gathering Visit)
January 14 - 16, 2015 (B.5.b Requirements)
January 26 - 30, 2015 (Fire Protection Inspection)
February 9 - 13, 2015 (Fire Protection Inspection)
Inspection Procedures:
Inspection Procedure 71111.05XT, Fire Protection - NFPA 805 (Triennial)
Inspection Procedure 71152, "Identification and Resolution of Problems" Inspectors:
Ijaz Hafeez Senior Reactor Inspector Reactor Inspector (630) 829-9803 (630) 829-9843 dariusz.szwarc@nrc.gov ijaz.hafeez@nrc.gov Mark Jeffers Robert Winter Reactor Inspector Reactor Inspector (630) 829-9798 (630) 829-9758 mark.jeffers@nrc.gov robert.winter@nrc.gov I. Information Requested Prior To the Information Gathering Visit The following information is requested by December 22, 2014. If you have any questions regarding this request, please call the lead inspector as soon as possible. All information should be sent to Dariusz Szwarc (e-mail address dariusz.szwarc@nrc.gov). Electronic media is preferred. The preferred file format is a searchable pdf or Microsoft Excel 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. Design and Licensing Basis Documents:
- a. Post-Fire Nuclear Safety Capability, Systems, and Separation Analysis;
- b. Fire Hazards Analysis and/or NFPA 805 Design Basis Document;
- e. Fire Risk-Evaluations (i.e., NFPA 805 Section 2.4.3);
- f. Plant Change Evaluations (i.e., NFPA 805 Section 2.4.4);
FIRE PROTECTION INSPECTION DOCUMENT REQUEST 2
- g. Analysis that demonstrates nuclear safety performance criteria can be achieved and maintained for those areas that require recovery actions;
- h. Fire Protection Program and/or Fire Protection Plan; and
- i.
Copies of the current versions of the Facility Operating License and Technical Requirements Manual.
- 2. Operations:
- a. Operating procedures to achieve and maintain nuclear safety performance criteria from the control room, with a postulated fire in the selected fire areas.
- b. 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).
II.
Information Requested During the Information Gathering Visit (January 12, 2015)
The following information is requested to be provided to the inspection team during the onsite information gathering visit. Except for Item 7, 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 (Item 7) provided on one separate CD.
- 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. Design and Licensing Basis Documents:
- a.
List of post-fire safe shutdown components (i.e., safe shutdown equipment list).
- b.
Fire protection system design basis document.
- c.
List of applicable NFPA codes and standards and issuance dates (i.e., codes of record).
- d.
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).
- e.
NFPA Compliance Review Report.
- f.
Report or evaluation that compares the Fire Protection Program to the NRC Branch Technical Position (BTP) 9.5-1 Appendix A.
FIRE PROTECTION INSPECTION DOCUMENT REQUEST 3
- g.
Copy of licensee submittals and NRC safety evaluation reports that are specifically listed in the facility operating license for the approved Fire Protection Program.
- h.
Copy of NRC Safety Evaluation Reports that form the licensing basis for the Fire Protection Program and post-fire nuclear safety capability.
- i.
Copy of NRC-approved exemptions for plant fire protection and post-fire nuclear safety capability features.
- j.
Copy of exemption requests submitted but not yet approved for plant fire protection and post-fire nuclear safety capability features.
- k.
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).
- 3. General Plant Design Documents (available onsite for inspector review):
- a.
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)
- i. Fires outside the main control room; and ii. Fires in areas requiring recovery actions at other than primary control stations
- b.
P&IDs and legend list for fire protection systems, including fire water supply, water suppression sprinklers and deluge, and carbon dioxide (CO2) and Halon systems (C-size paper drawings);
- c.
Yard layout drawings for underground fire protection buried piping (C-size paper drawings);
- d.
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);
- e.
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);
- f.
Equipment location drawings which identify the physical plant locations of post-fire nuclear safety capability equipment (C-size paper drawings); and
- g.
Logic diagrams showing the components used to achieve and maintain hot standby and cold shutdown.
FIRE PROTECTION INSPECTION DOCUMENT REQUEST 4
- 4. Operations:
- a. List of calculations and engineering analyses, studies, or evaluations for the nuclear safety capability methodology;
- b. For recovery actions, provide the following:
- i.
Manual Action Feasibility Study; ii.
Operator Time Critical Action Program; iii.
Time lines for time-critical recovery actions; and iv.
Time line validations
- c. Thermal hydraulic calculation or analysis that determines the time requirements for time-critical manual operator actions.
- 5. Administrative Control, Oversight, and Corrective Action Programs:
- a. Corrective actions associated with operator actions to achieve and maintain post-fire nuclear safety performance criteria;
- b. List of open and closed condition reports for the fire protection system for the last three years;
- c. 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; and
- d. List of procedures that control the configuration of the Fire Protection Program, features, and post-fire nuclear safety capability methodology and system design.
- 6. 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 personnel.
- 7. B.5.b Mitigating Strategies Documents (provided on one separate compact disk on January 12, 2015:
- a. 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);
- b. List of procedures and guidelines that were revised or generated to implement the mitigating strategies. These could be extensive damage mitigation guidelines
FIRE PROTECTION INSPECTION DOCUMENT REQUEST 5
(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, Revision 2, "B.5.b Phase II and III Submittal Guideline," issued December 2006, and the site-specific procedures or guidelines that are used to implement each strategy;
- d. List of engineering evaluations or calculations that were used to verify the engineering bases for the mitigating strategies;
- e. 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);
- f. List of modification packages or summary descriptions of modifications with simplified drawings, for necessary facility changes to implement the mitigating strategies;
- g. List of routine tests, surveillances, and preventive maintenance for equipment and tools needed to implement 10 CFR 50.54(hh)(2) strategies;
- h. For equipment and tools needed to implement 10 CFR 50.54(hh)(2) strategies, provide the following:
- i.
Procedures for inventory and inspection; and ii.
Most recent inspection and inventory results
- i.
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;
- j.
Site general arrangement drawings that show the majority of buildings and areas referenced in 10 CFR 50.54(hh)(2) documents;
- k. Training records, training matrix, and lesson plans related to 10 CFR 50.54(hh)(2);
and
- l.
Copies of memoranda of understanding (MOU) (e.g., with local fire departments) required to implement any mitigating strategies.
- 8. Onsite Discussions:
In addition, during the information gathering visit, it is requested that licensee staff be available for the following:
FIRE PROTECTION INSPECTION DOCUMENT REQUEST 6
- 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 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.
III.
Information Requested to be Available on First Day of the Second ONSITE Inspection Week (January 26, 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. Classic Fire Protection:
- a. Copy of Fire Protection Program implementing procedures (e.g., administrative controls, surveillance testing, and fire brigade).
- b. List of calculations and engineering analyses, studies, or evaluations for the fire protection system, including the fire water system.
- c. Hydraulic calculations or analyses for fire protection water system.
- d. Pre-fire plans for selected fire areas.
- e. 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).
- f. List of fire protection system NFPA 805 engineering equivalency evaluations completed in the last three years.
- g. Copy of any test, surveillance, or maintenance procedure (current revision),
including any associated data forms, for any requested "last performed" test, surveillance, or maintenance.
- 2. Electrical:
- a. Nuclear safety circuit coordination analysis for fuse and breaker coordination of nuclear safety capability components (only for selected fire areas);
- b. Administrative or configuration control procedures that govern fuse replacement (e.g., fuse control procedures);
FIRE PROTECTION INSPECTION DOCUMENT REQUEST 7
- c. Maintenance procedures that verify breaker over-current trip settings to ensure coordination remains functional, for post-fire nuclear safety capability components;
- d. Last surveillance demonstrating operability of those components operated from the primary control stations;
- e. Schematic or elementary diagrams for circuits to be reviewed;
- f. Cable routing for components and equipment credited for post-fire nuclear safety capability systems and components (only for selected fire areas);
- g. List of post-fire nuclear safety capability system and component design changes completed, in the last three years; and
- h. List of identified fire induced circuit failure analyses (only for selected fire areas).
- 3. Operations:
- a. For safe shutdown equipment and tools, provide the following:
- i.
Procedure for inventory and inspection; and ii.
Most recent inspection and inventory results.
- b. List of procedures that implement Cold Shutdown Repairs;
- c. For Cold Shutdown Repairs, provide the following:
- i.
Procedure for inventory and inspection (i.e., needed tools, material, etc.);
and ii.
Most recent inspection and inventory results
- d. For Radio communications, provide the following:
- i.
Communications Plan for firefighting and post-fire safe shutdown manual actions; ii.
Repeater locations; iii.
Cable routing for repeater power supply cables; iv.
Radio coverage test results; and
- v.
Radio Dead Spot locations in the plant
- 4. Administrative Control, Oversight, and Corrective Action Programs:
- a. Self-assessments, peer assessments, and audits of fire protection activities for the last three years.
- b. Self-assessments, peer assessments, and audits of post-fire nuclear safety capability methodology for the last three years.
- c. List of fire event analysis reports for the last three years.
FIRE PROTECTION INSPECTION DOCUMENT REQUEST 8
- 5. 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.
T. Vehec In accordance with Title 10, Code of Federal Regulations (CFR), Section 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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).
Sincerely,
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-331 License No. DPR-49
Enclosure:
Fire Protection Inspection Document Request cc w/encl: Distribution via LISTSERV DISTRIBUTION:
John Jandovitz RidsNrrDorlLpl3-1 Resource RidsNrrPMDuaneArnold Resource RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Steven Orth Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Carmen Olteanu DOCUMENT NAME: G:\\DRSIII\\DRS\\Ltr 103014 DAEC FP RFI DXS v2.docx 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 NAME DSzwarc:ls RCDaley DATE 10/30/14 10/30/14 OFFICIAL RECORD COPY