ML063200015
| ML063200015 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/14/2006 |
| From: | Payne D NRC/RGN-II/DRS/EB2 |
| To: | Archie J South Carolina Electric & Gas Co |
| References | |
| IR-07-006 | |
| Download: ML063200015 (8) | |
See also: IR 05000395/2007006
Text
November 14, 2006
South Carolina Electric & Gas Company
ATTN: Mr. Jeffrey B. Archie
Vice President, Nuclear Operations
Virgil C. Summer Nuclear Station
P. O. Box 88
Jenkinsville, SC 29065
SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
WHILE TRANSITION TO 10 CFR PART 50.48(c) IS IN PROGRESS
(INSPECTION REPORT NO. 05000395/2007006)
Dear Mr. Archie:
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 the Virgil C. Summer
Nuclear Station. Mr. Gerald Wiseman, NRC Senior Reactor Inspector, of the Region II Office
will lead the inspection team, which will be composed of personnel from the NRC Region II
Office. 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. The
inspectors will not routinely inspect for or evaluate circuit related issues.
On November 14, 2006, during a telephone conversation between Mr. Arnie Cribb Jr., Licensing
Supervisor, and Mr. Paul Fillion, Fire Protection Team Leader, 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: February 20 - 22, 2007
- Week 1 of onsite inspection: March 19 - 23, 2007
- Week 2 of onsite inspection: April 2 - 6, 2007
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, and to become familiar with the Virgil C. Summer Nuclear
Station 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.
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Please contact Mr. Wiseman 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.
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 Virgil C. Summer Nuclear
Station 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 Virgil C. Summer Nuclear Station 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.Wiseman (404) 562-4542, 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 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/
D. Charles Payne, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-395
License No. NPF-12
cc w/encl: (See page 3)
Enclosure: Triennial Fire Protection Inspection Support Documentation
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cc w/encl:
R. J. White
Nuclear Coordinator Mail Code 802
S.C. Public Service Authority
Virgil C. Summer Nuclear Station
Electronic Mail Distribution
Kathryn M. Sutton, Esq.
Electronic Mail Distribution
Henry J. Porter, Director
Div. of Radioactive Waste Mgmt.
Dept. of Health and Environmental
Control
Electronic Mail Distribution
R. Mike Gandy
Division of Radioactive Waste Mgmt.
S. C. Department of Health and
Environmental Control
Electronic Mail Distribution
Robert G. Sweet, Manager
Nuclear Licensing (Mail Code 830)
South Carolina Electric & Gas Company
Virgil C. Summer Nuclear Station
Electronic Mail Distribution
Robert M. Fowlkes, General Manager
Engineering Services
South Carolina Electric & Gas Company
Virgil C. Summer Nuclear Station
Electronic Mail Distribution
Thomas D. Gatlin, General Manager
Nuclear Plant Operations (Mail Code 303)
South Carolina Electric & Gas Company
Virgil C. Summer Nuclear Station
Electronic Mail Distribution
David A. Lavigne, General Manager
Organization Development
South Carolina Electric & Gas Company
Vigil C. Summer Nuclear Station
Electronic Mail Distribution
_________________________
OFFICE RII:DRS RII:DRS RII:DRP
SIGNATURE /RA/ /RA/ /RA/
NAME C. Payne P.Fillion G. Guthrie
DATE 11/14/2006 11/14/2006 11/14/2006 11/ /2006 11/ /2006 11/ /2006 11/ /2006
E-MAIL COPY? YES NO NO NO YES NO YES NO YES NO YES NO
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SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
WHILE TRANSITION TO 10 CFR PART 50.48(c) IS IN PROGRESS
INSPECTION REPORT NO. 05000395/2007006)
DATE:
Distribution w/encl:
R. Martin, NRR
C. Evans (Part 72 Only)
L. Slack, RII EICS
OE Mail (email address if applicable)
RIDSNRRDIRS
PUBLIC
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.
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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.
Enclosure
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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.
Enclosure