ML12054A684
| ML12054A684 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/23/2012 |
| From: | Reinaldo Rodriguez NRC/RGN-II/DRS/EB2 |
| To: | Gatlin T South Carolina Electric & Gas Co |
| Linda Gruhler x-4614 | |
| References | |
| IR-12-007 | |
| Download: ML12054A684 (8) | |
See also: IR 05000395/2012007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
February 23, 2012
Mr. Thomas D. Gatlin
Vice President - Nuclear Operations
South Carolina Electric & Gas Company
Virgil C. Summer Nuclear Station
P.O. Box 88
Jenkinsville, SC 29065
SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 - NOTIFICATION OF A
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION
REPORT NO. 05000395/2012007)
Dear Mr. Gatlin:
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 Virgil C. (V.C.)
Summer Nuclear Station Unit 1, in May 2012. The inspection team will be lead by Mr. Gerald
Wiseman, NRC Senior Reactor Inspector, of the Region II Office. The team will be composed
of personnel from NRC Region II Office. The inspection will be conducted in accordance with
Inspection Procedure 71111.05T, the NRC=s triennial fire protection baseline inspection
procedure dated October 28, 2011.
On February 22, 2012, during a telephone conversation between Mr. Eric Rumfelt (V.C.
Summer Licensing Supervisor) of your staff, and Mr. Gerald Wiseman, our respective staffs
confirmed arrangements for the following schedule for the inspection:
Information gathering visit: April 24 - 26, 2012
Week 1 of onsite inspection: May 07 -11, 2012
Week 2 of onsite inspection: May 21 - 25, 2012
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, to become familiar with the V.C. Summer Nuclear Station Unit
1 fire protection programs, fire protection features, 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); and, as necessary, obtain plant-
specific site access training and badging for unescorted site access. A list of the types of
documents the team may be interested in reviewing, and possibly obtaining, are listed in
2
SCE&G
Enclosures 1 and 2. Please contact Mr. Wiseman 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 size and location; specific documents requested to be made
available to the team in its office spaces; 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 onsite inspection weeks, you ensure that copies of analyses,
evaluations, or documentation regarding the implementation and maintenance of the V.C.
Summer Nuclear Station 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 the documents that 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, the 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 V.C. Summer Nuclear Station 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 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 teams information or logistical needs, please
contact Mr. Gerald Wiseman, the team leader at (404) 997-4542, or me at (404) 997-4498.
3
SCE&G
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its
enclosures 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 http://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading
Room).
Sincerely,
/RA by Rebecca L. Nease for/
Reinaldo Rodriguez, Acting Chief
Engineering Branch 2
Division of Reactor Safety
Docket No.
50-395
License No.
Enclosures:
1. Triennial Fire Protection Program Supporting Documentation
2. Mitigating Strategies Supporting Documentation
cc w/encl: (See page 4)
_ML# 12054A684______________G SUNSI REVIEW COMPLETE X FORM 665 ATTACHED
OFFICE
RII:DRS
RII:DRP
RII:DRS
SIGNATURE
/RA/
/RA/
/RA R. Nease for/
NAME
G. Wiseman
G. McCoy
R. Rodriguez
DATE
2/22/2012
2/22/2012
2/23/2012
E-MAIL COPY
YES
NO
YES
NO
YES
NO
4
SCE&G
cc w/encl:
J. B. Archie
Senior Vice President
Nuclear Operations and Chief Nuclear
Officer
South Carolina Electric & Gas Company
Electronic Mail Distribution
George A. Lippard, III
General Manager
Nuclear Plant Operations
South Carolina Electric & Gas Company
Electronic Mail Distribution
Andy T. Barbee
Director
Nuclear Training
South Carolina Electric & Gas Company
Electronic Mail Distribution
Wayne D. Stuart
(Acting) General Manager
Engineering Services
South Carolina Electric & Gas Company
Electronic Mail Distribution
Robin R. Haselden
General Manager
Organizational Development &
Effectiveness
South Carolina Electric & Gas Company
Electronic Mail Distribution
Shaun M. Zarandi
General Manager
Nuclear Support Services
South Carolina Electric & Gas Company
Electronic Mail Distribution
Robert L. Justice
Manager
Nuclear Operations
South Carolina Electric & Gas Company
Donna W. Railey
Licensing Technician
Nuclear Licensing
South Carolina Electric & Gas Company
Electronic Mail Distribution
Robin J. White
Nuclear Coordinator
S.C. Public Service Authority Mail Code 802
Electronic Mail Distribution
Susan E. Jenkins
SC Department of Health & Environmental
Control
Bureau of Land and Waste Management
Electronic Mail Distribution
Sandra Threatt, Manager
Nuclear Response and Emergency
Environmental Surveillance
Bureau of Land and Waste Management
Department of Health and Environmental
Control
Electronic Mail Distribution
Kathryn M. Sutton, Esq.
Electronic Mail Distribution
Division of Radiological Health
TN Dept. of Environment & Conservation
401 Church Street
Nashville, TN 37243-1532
Senior Resident Inspector
Virgil C. Summer Nuclear Station
U.S. NRC
576 Stairway Road
Jenkinsville, SC 29065
Bruce L. Thompson
Manager
Nuclear Licensing (Mail Code 830)
South Carolina Electric & Gas Company
Electronic Mail Distribution
Enclosure
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.
15.
Plant operating procedures which would be used and describe shutdown from inside
2
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 2
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.