ML12348A111
| ML12348A111 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/11/2012 |
| From: | Mark King NRC/RGN-II/DRS/EB2 |
| To: | Henderson K Duke Energy Corp |
| References | |
| IR-13-007 | |
| Download: ML12348A111 (10) | |
See also: IR 05000413/2013007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
December 11, 2012
Mr. Kelvin Henderson
Site Vice President
Duke Energy Corporation
Catawba Nuclear Station
4800 Concord Road
York, SC 29745-9635
SUBJECT: CATAWBA NUCLEAR PLANT - NOTIFICATION OF CONDUCT OF A
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION
REPORT NO. 05000413/2013007 AND 05000414/2013007)
Dear Mr. Henderson:
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 Catawba Nuclear
Plant in April and May 2013. The inspection team will be led by Mr. David Jones, NRC Senior
Reactor Inspector, of the Region II office. The team will be composed of personnel from the
NRC Region II office. The inspection will be conducted in accordance with Inspection
Procedure 71111.05T, the NRCs baseline fire protection inspection procedure dated January 1,
2012.
On November 29, 2012, during a conversation between Ms. A. Driver of your staff and Mr.
Jones, 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: April 2 - 4, 2013
- Week 1 of onsite inspection: April 22 - April 26, 2013
- Week 2 of onsite inspection: May 6 - 10, 2013
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, to become familiar with the Catawba Nuclear Plant fire
protection program, fire protection features, and post-fire safe shutdown capabilities and plant
layout, mitigating strategies to address Section B.5.b of NRC Order EA-02-026, Order for
Interim Safeguards and Security Compensatory Measures, dated February 25, 2002, and Title
10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2). The types of documents the
team will be interested in reviewing, and possibly obtaining, are listed in Enclosures 1 and 2.
Please contact Mr. Jones 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.
K. Henderson 2
During the information gathering visit, Mr. Jones will 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 radiation protection training,
security, safety and fitness for duty requirements); and the availability of knowledgeable plant
engineering, operations 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 Catawba 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. For the B.5.b 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 that 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 Catawba 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, 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.
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. Jones at (404) 997-4631, or me at (404) 997-4511.
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
K. Henderson 3
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html http://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading
Room).
Sincerely,
/RA/
Michael F. King, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No.: 50-413 & 414
License No.: NPF-35 & 52
Enclosures:
1. Triennial Fire Protection Program Supporting Documentation
2. Mitigating Strategies Supporting Documentation
cc: (See page 4)
_________________________ xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED
OFFICE RII:DRS RII;:DRS
NAME JONES KING
DATE 12/11 /2012 12/ 11 /2012
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
K. Henderson 4
cc: Lara S. Nichols
Scott L. Batson Deputy General Counsel
Plant Manager Duke Energy Corporation
Catawba Nuclear Station Electronic Mail Distribution
Duke Energy Corporation
Electronic Mail Distribution David A. Cummings
Associate General Counsel
William M. Suslick General Office
Design Engineering Manager Duke Energy Corporation
Catawba Nuclear Station Electronic Mail Distribution
Duke Energy Corporation
Electronic Mail Distribution Beth J. Horsley
Wholesale Customer Relations
Steven B. Putnam Duke Energy Corporation
Organizational Effectiveness Manager Electronic Mail Distribution
Catawba Nuclear Station
Duke Energy Corporation Sandra Threatt, Manager
Electronic Mail Distribution Nuclear Response and Emergency
Environmental Surveillance
Randall D. Hart Bureau of Land and Waste Management
Regulatory Compliance Manager Department of Health and Environmental
Catawba Nuclear Station Control
Duke Energy Corporation Electronic Mail Distribution
Electronic Mail Distribution
Division of Radiological Health
Joseph Michael Frisco, Jr. TN Dept. of Environment & Conservation
Vice President, Nuclear Design Engineering 401 Church Street
General Office Nashville, TN 37243-1532
Duke Energy Corporation
Electronic Mail Distribution Senior Resident Inspector
U.S. Nuclear Regulatory Commission
M. Christopher Nolan Catawba Nuclear Station
Director - Regulatory Affairs U.S. NRC
General Office 4830 Concord Road
Duke Energy Corporation York, SC 29745
Electronic Mail Distribution
David A. Repka
David A. Cummings (acting) Winston Strawn LLP
Fleet Regulatory Compliance & Licensing Electronic Mail Distribution
Manager
General Office County Manager of York County
Duke Energy Corporation York County Courthouse
Electronic Mail Distribution P. O. Box 66
York, SC 29745-0066
Alicia Richardson
Licensing Administrative Assistant Piedmont Municipal Power Agency
General Office Electronic Mail Distribution
Duke Energy Corporation
Electronic Mail Distribution
(cc contd - See page 5)
K. Henderson 5
(cc contd)
Vanessa Quinn
Federal Emergency Management Agency
Radiological Emergency Preparedness
Program
1800 S. Bell Street
Arlington, VA 20598-3025
Letter to Kelvin Henderson from Michael F. King dated December 11, 2012
SUBJECT: CATAWBA NUCLEAR PLANT- NOTIFICATION OF CONDUCT OF A
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION
REPORT NO. 05000413/203007 AND 05000414/2013007)
Distribution:
RIDSNRRDIRS
PUBLIC
RidsNrrPMCatawba Resource
Triennial Fire Protection Program Supporting 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. Electronic media is
preferred, if readily available. (The preferred file format on CD-ROM or DVDROM is .pdf).
The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease
of use. Please provide 5 copies of each CD/DVD-ROM submitted. Information in lists should
contain enough information to be easily understood by someone who has knowledge of the
technology. The lead inspector will discuss specific information needs with the licensee staff
and may request additional documents or electronic information.
1. The current version of the fire protection program and fire hazards analysis.
2. Corrective action closeouts as part of operator manual actions corrective actions.
3. List of identified fire induced circuit failure configurations for the selected fire
areas/zones (to be determined during information gathering visit).
4. Corrective actions for fire-induced circuit failures, both single and multiple spurious
actuations for the selected fire areas/zones (to be determined during information
gathering visit).
5. Cable routing for components and equipment credited for safe shutdown for the selected
fire areas/zones (to be determined during information gathering visit).
6. List of protected safe shutdown train equipment for the selected fire areas/zones (to be
determined during information gathering visit).
7. Current versions of the fire protection program implementing procedures (e.g.,
administrative controls, surveillance testing, fire brigade).
8. Fire brigade training program and pre-fire plans.
9. Post-fire safe shutdown systems and separation analysis.
10. Post-fire alternative shutdown analysis.
11. Piping and instrumentation diagrams showing the components used to achieve and
maintain hot standby and cold shutdown for fires outside the control room and those
components used for those areas requiring alternative shutdown capability.
12. Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment.
13. Plant layout drawings which identify plant fire area delineation, areas protected by
automatic fire suppression and detection, and the locations of fire protection equipment.
14. Plant layout drawings which identify the general location of the post-fire emergency
lighting.
Enclosure 1
2
15. Plant operating procedures which would be used and describe shutdown from inside
the control room with a postulated fire occurring in any plant area outside the control
room, procedures which would be used to implement alternative shutdown capability in
the event of a fire in the control or cable spreading room.
16. Maintenance and surveillance testing procedures for alternative shutdown capability
and fire barriers, detectors, pumps and suppression systems.
17. Maintenance procedures that routinely verify fuse breaker coordination in accordance
with the post-fire safe shutdown coordination analysis.
18. A list of significant fire protection and post-fire safe shutdown related design change
packages and evaluations according to Generic Letter 86-10, Implementation of Fire
Protection Requirements.
19. The reactor plant's Individual Plant Examination for External Events (IPEEE), results of
any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in
response to IPEEE information.
21. Organization charts of site personnel (including fire protection staff personnel).
22. If applicable, drawings of potential reactor coolant/recirculation pump lube oil system
leakage points and associated lube oil collection systems.
23. Licensing basis documents for fire protection (safety evaluation reports, pertinent
sections of the final safety analysis report, exemptions, deviations, letters to/from the
NRC regarding fire protection/fire safe shutdown, etc.).
24. Procedures/instructions that control the configuration of the plant's fire protection
program, features, and post-fire safe shutdown methodology, and system design.
25. A list of applicable codes and standards related to the design of plant fire protection
features and evaluations of code deviations.
26. Procedures/instructions that govern the implementation of plant modifications,
maintenance, special operations, and their impact on fire protection.
27. Internal and external self-assessments, audits, peer-assessments or similar reviews
related to post-fire safe shutdown capability or the fire protection program completed
since the previous NRC fire protection triennial inspection.
28. Recent quality assurance surveillances of fire protection activities.
29. A listing of open and closed fire protection condition reports (problem reports/nuclear
condition reports/event analysis reports/problem identification, and resolution reports)
since the last triennial inspection.
Enclosure 1
Mitigating Strategies Supporting 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 on CD-ROM or DVDROM is .pdf).
The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease
of use. Please provide 5 copies of each CD/DVD-ROM submitted. The lead inspector will
discuss specific information needs with the licensee staff and may request additional documents
or electronic information.
1. A list of all modifications to regulatory commitments made to meet the requirements of
Section B.5.b of NRC Order, EA-02-026, Order for NRC Interim Safeguards and
Security Compensatory Measures, dated February 25, 2002, the subsequently
imposed license conditions, and Title 10 of the Code of Federal Regulations (10 CFR)
50.54(hh)(2).
2. Lists of procedures/guidelines that were revised or generated to implement the
mitigation strategies. These could be extensive damage mitigation guidelines
(EDMGs), severe accident management guidelines (SAMGs), emergency operating
procedures (EOPs), abnormal operating procedures (AOPs), etc.
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 used to
implement each strategy.
4. Engineering evaluations/calculations that were used to verify engineering bases for the
mitigation strategies.
5. Piping and instrumentation diagram for systems relied upon in the mitigation strategies.
These could be of the type used for training.
6. A list of modification packages or simplified drawings or descriptions of modifications
that were made to plant systems to implement the mitigation strategies.
7. Copies of procedures used to inventory equipment (hoses, fittings, pumps, etc.)
required to implement the mitigation strategies.
8. A list of B.5.b strategies, if any, that have implementing details that differ from those
documented in the submittals and the safety evaluation report.
9. A copy of site general arrangement drawing(s) that show the majority of buildings/areas
referenced in B.5.b documents.
10. Training records, training matrix, and lesson plans related to B.5.b.
11. Copies of Memoranda of Understanding (MOUs) (e.g., with local fire departments)
required to implement any mitigating strategies.
Enclosure 2