ML072700490
| ML072700490 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/27/2007 |
| From: | Payne D NRC/RGN-II/DRS/EB2 |
| To: | Young D Florida Power Corp |
| References | |
| IR-08-006 | |
| Download: ML072700490 (9) | |
See also: IR 05000302/2008006
Text
September 27, 2007
Mr. Dale E. Young, Vice President
Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing &
Regulatory Programs
15760 West Power Line Street
Crystal River, FL 34428-6708
SUBJECT:
NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
WHILE TRANSITION TO 10 CFR PART 50.48(c) IS IN PROGRESS (NRC
INSPECTION REPORT NO. 05000302/2008006)
Dear Mr. Young:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a triennial fire protection baseline inspection at Crystal River Unit 3
in January and February 2008. The inspection team will be led by Mr. McKenzie Thomas, NRC
Senior Reactor Inspector, of the Region II Office. The team will be composed of personnel
from the NRC Region II Office and a contractor. The inspection will be conducted in
accordance with Inspection Procedure 71111.05TTP, the NRCs baseline fire protection
inspection procedure for plants in the process of implementing 10 CFR 50.48(c) and National
Fire Protection Association Standard (NFPA) 805. The inspection guidance is different from the
regular triennial inspections in that the inspectors will concentrate on the fire protection program
infrastructure and the adequacy of compensatory measures implemented for identified
departures from code requirements. Inspection of circuit analysis is not included in the
inspection procedure, however, electrical topics will be addressed by the team.
On September 25, 2007, during a telephone conversation between Mr. Dennis Herrin (Acting
Supervisor, Licensing and Regulatory Programs), of your staff, and Mr. Thomas, 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:
January 8 - 10, 2008
Week 1 of onsite inspection: January 28 - February 1, 2008
Week 2 of onsite inspection: February 11 - 15, 2008
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, and to become familiar with the Crystal River Unit 3 fire
protection program, fire protection features, post-fire safe shutdown capabilities and plant
layout. The types of documents the team will be interested in reviewing, and possibly obtaining,
are listed in the Enclosure.
Please contact Mr. Thomas prior to preparing copies of the materials listed in the Enclosure.
The inspection team will try to minimize your administrative burden by specifically identifying
those documents required for inspection preparation.
2
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 its
office space; arrangements for reactor site access (including 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 inspection weeks you ensure that copies of analyses, evaluations or
documentation regarding the implementation and maintenance of the Crystal River Unit 3 fire
protection program, including post-fire safe shutdown capability, be readily accessible to the
team for its review. Of specific interest are those documents which establish that your fire
protection program satisfies NRC regulatory requirements and conforms to applicable NRC and
industry fire protection guidance. 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 Crystal River Unit 3 fire protection program and its
implementation.
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. Thomas at (404) 562-4673, or me at (404) 562-4669.
In accordance with 10 CFR 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 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).
Sincerely,
/RA/
D. Charles Payne, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No.: 50-302
License No.: DPR-72
Enclosure:
Triennial Fire Protection Inspection Support Documentation
cc w/encl: (See page 3)
3
cc w/encl:
Jon A. Franke
Director Site Operations
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Michael J. Annacone
Plant General Manager
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Phyllis Dixon
Manager, Nuclear Assessment
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Stephen J. Cahill
Engineering Manager
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Daniel L. Roderick
Vice President, Nuclear Projects and Construction
Crystal River Nuclear Plant
Electronic Mail Distribution
David M. Varner
Manager, Support Services - Nuclear
Crystal River Nuclear Plant
Electronic Mail Distribution
R. Alexander Glenn
Associate General Counsel (MAC - BT15A)
Florida Power Corporation
Electronic Mail Distribution
Steven R. Carr
Associate General Counsel - Legal Dept.
Progress Energy Service Company, LLC
Electronic Mail Distribution
Attorney General
Department of Legal Affairs
The Capitol PL-01
Tallahassee, FL 32399-1050
(cc w/encl contd - See page 4)
4
(cc w/encl contd)
William A. Passetti
Bureau of Radiation Control
Department of Health
Electronic Mail Distribution
Craig Fugate, Director
Division of Emergency Preparedness
Department of Community Affairs
Electronic Mail Distribution
Chairman
Board of County Commissioners
Citrus County
110 N. Apopka Avenue
Inverness, FL 36250
Jim Mallay
Framatome Technologies
Electronic Mail Distribution
Distribution w/encl:
S. Bailey, NRR
RIDSNRRDIRS
PUBLIC
_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRS
SIGNATURE
NAME
MTHOMAS
SWALKER
SVIAS
DATE
9/ /2007
9/ /2007
9/ /2007
9/ /2007
9/ /2007
9/ /2007
9/ /2007
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
Triennial Fire Protection Inspection Support Documentation
Note: This is a broad list of the documents the NRC inspection team may be interested
in reviewing, and possibly obtaining, during the information gathering site visit. The
current version of these documents is expected unless specified otherwise. Electronic
media is preferred, if readily available. (The preferred file format is searchable .pdf
files on CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of
use. Please provide 5 copies of each CDROM submitted.) Information in lists should
contain enough information to be easily understood by someone who has a knowledge
of the technology. The lead inspector will discuss specific information needs with the
licensee staff and may request additional documents.
1.
The Fire Protection Program document and the Fire Hazards Analysis.
2.
The fire protection program implementing procedures (e.g., administrative controls,
surveillance testing, fire brigade).
3.
The fire brigade training program document and the pre-fire plans for the selected fire
areas/zones (to be determined during information gathering visit).
4.
The post-fire safe shutdown analysis, including system and separation analyses.
5.
The alternative shutdown analysis.
6.
Piping and instrumentation (flow) diagrams for the fire suppression systems.
7.
Piping and instrumentation (flow) diagrams for the systems and components used to
achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from
the control room.
8.
Piping and instrumentation (flow) diagrams for the systems and components used to
achieve and maintain hot standby, and cold shutdown, for fires in areas requiring
alternative or dedicated shutdown capability.
9.
Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment.
10.
Plant layout drawings which identify plant fire area and/or fire zone delineation, areas
protected by automatic fire suppression and detection, and the locations of fire
protection equipment for the selected fire areas/zones (to be determined during
information gathering visit).
11.
Plant layout drawings which identify the general location of the post-fire emergency
lighting units.
12.
Plant operating procedures used to, and describing, shutdown from inside the control
room with a postulated fire occurring in any plant area outside the control room.
2
Enclosure
13.
Plant operating procedures used to implement the alternative shutdown capability from
outside the control room with a fire in either the control or cable spreading room (or any
other alternative shutdown area).
14.
Maintenance and surveillance testing procedures for alternative shutdown capability
(including Appendix R emergency lights and communication systems) and fire barriers,
detectors, fire pumps and fire suppression systems.
15.
Calculations and/or justifications that verify fuse/breaker coordination for the selected
fire areas/zones (to be determined during information gathering visit) that are fed off the
same electrical buses as components in the protected train. Also, a list of the
maintenance procedures used to routinely verify fuse/breaker coordination in
accordance with the post-fire safe shutdown coordination analysis.
16.
A list of the significant fire protection and post-fire safe shutdown design change
descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter (GL) 86-10 evaluations.
17.
A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R,
Section III.G) used to achieve regulatory compliance for the selected fire areas/zones
(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 for the
selected fire areas/zones.
18.
Procedures or instructions that govern the implementation of plant modifications,
temporary modifications, maintenance, and special operations, and their impact on fire
protection.
19.
Organization chart(s) of site personnel down to the level of the fire protection staff.
20.
Procedures or instructions that control the configuration of the fire protection program,
features, and post-fire safe shutdown methodology and system design.
21.
A list of applicable codes and standards related to the design of plant fire protection
features and evaluations of code deviations (i.e., a listing of the NFPA code editions
committed to (Code of Record)).
22.
The three most recent fire protection QA audits and/or fire protection self-assessments.
23.
A list of open and closed fire protection problem identification and resolution reports
[also known as action reports/condition reports/problem reports/problem investigation
reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the
past three years.
3
Enclosure
Enclosure
24.
A list of plant fire protection licensing basis documents (i.e., a list of the SERs and
change evaluations which form the licensing basis for the facilitys post-fire safe
shutdown configuration).
25.
A list of fire protection or Appendix R calculations.
26.
A list of fire impairments identified during the previous year.
27.
A list of abbreviations/designators for plant systems.