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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GEORGIA 30303-8931
{{#Wiki_filter:UNITED STATES
  April 14, 2010  
                                NUCLEAR REGULATORY COMMISSION
                                                REGION II
Mr. Thomas D. Gatlin  
                                  SAM NUNN ATLANTA FEDERAL CENTER
Vice President - Nuclear Operations  
                                  61 FORSYTH STREET, SW, SUITE 23T85
South Carolina Electric & Gas Company  
                                      ATLANTA, GEORGIA 30303-8931
Virgil C. Summer Nuclear Station  
                                              April 14, 2010
P.O. Box 88  
Mr. Thomas D. Gatlin
Jenkinsville, SC 29065  
Vice President - Nuclear Operations
South Carolina Electric & Gas Company
SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION- NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION WHILE TRANSITION TO 10 CFR PART 50.48(c) IS IN PROGRESS (NRC INSPECTION REPORT NO. 05000395/2010008)
Virgil C. Summer Nuclear Station
P.O. Box 88
Dear Mr. Gatlin:  
Jenkinsville, SC 29065
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. Summer Nuclear Station, in June and July 2010. The inspection team will be led by Mr. Necota Staples,  
SUBJECT:       VIRGIL C. SUMMER NUCLEAR STATION- NOTIFICATION OF CONDUCT OF
NRC 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 71111.05TTP, the NRC's 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  
                A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION WHILE
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.
                TRANSITION TO 10 CFR PART 50.48(c) IS IN PROGRESS (NRC INSPECTION
                REPORT NO. 05000395/2010008)
On March 03, 2010, during a telephone conversation between Mr. Arnie Cribb (Summer Licensing Supervisor) of your staff, and Mr. Staples, 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:
Dear Mr. Gatlin:
* Information gathering visit: May 25 - 27, 2010
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
* Week 1 of onsite inspection: June 14 -18, 2010
Region II staff will conduct a triennial fire protection baseline inspection at Virgil C. Summer
* Week 2 of onsite inspection: June 28 - July 02, 2010
Nuclear Station, in June and July 2010. The inspection team will be led by Mr. Necota Staples,
The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the Summer Nuclear Station fire  
NRC Reactor Inspector, of the Region II Office. The team will be composed of personnel from
protection programs, fire protection features, post-fire safe shutdown capabilities, plant layout, and mitigating strategies to address Section B.5.b of the Interim Compensatory Measures Order, EA-02-026, of February 25, 2002/10 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. Staples prior to preparing copies of the materials listed in the Enclosures.  
the NRC Region II Office. The inspection will be conducted in accordance with Inspection
SCE&G 2  The inspection team will try to minimize your administrative burden by specifically identifying those documents required for inspection preparation. 
Procedure 71111.05TTP, the NRCs baseline fire protection inspection procedure for plants in
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 their office space; arrangements for unescorted site access (including radiation protection training,
the process of implementing 10 CFR 50.48(c) and National Fire Protection Association
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. 
Standard (NFPA) 805. The inspection guidance is different from the regular triennial
We request that during the inspection weeks you ensure that copies of analyses, evaluations or
inspections in that the inspectors will concentrate on the fire protection program infrastructure
documentation regarding the implementation and maintenance of the Summer 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
and the adequacy of compensatory measures implemented for identified departures from code
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 Summer fire protection program and its implementation. 
requirements. Inspection of circuit analysis is not included in the inspection procedure;
however, electrical topics will be addressed by the team.
On March 03, 2010, during a telephone conversation between Mr. Arnie Cribb (Summer
Licensing Supervisor) of your staff, and Mr. Staples, 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: May 25 - 27, 2010
    *   Week 1 of onsite inspection: June 14 -18, 2010
    *   Week 2 of onsite inspection: June 28 - July 02, 2010
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, to become familiar with the Summer Nuclear Station fire
protection programs, fire protection features, post-fire safe shutdown capabilities, plant layout,
and mitigating strategies to address Section B.5.b of the Interim Compensatory Measures
Order, EA-02-026, of February 25, 2002/10 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. Staples prior to preparing copies of the materials listed in the Enclosures.


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  
SCE&G                                          2
request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.  
The inspection team will try to minimize your administrative burden by specifically identifying
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. Staples at (404) 997-4644, or me at (404) 997-4530.  
those documents required for inspection preparation.
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  
During the information gathering visit, the team will also discuss the following inspection support
SCE&G 3  (ADAMS).  ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html  (the Public Electronic Reading Room).
administrative details: office space; specific documents to be made available to the team in their
Sincerely,  /RA/  Rebecca L. Nease, Chief Engineering Branch 2 Division of Reactor Safety 
office space; arrangements for unescorted site access (including radiation protection training,
Docket No.: 50-395 License No.: NPF-12
security, safety and fitness for duty requirements); and the availability of knowledgeable plant
Enclosures: 1. Triennial Fire Protection Inspection Support Documentation    2. Mitigating Strategies Support Documentation
engineering and licensing organization personnel to serve as points of contact during the
inspection.
cc w/encl.  (See page 4)
We request that during the inspection weeks you ensure that copies of analyses, evaluations or
SCE&G 4  cc w/encl:
documentation regarding the implementation and maintenance of the Summer fire protection
R. J. White Nuclear Coordinator S.C. Public Service Authority Mail Code 802 Electronic Mail Distribution
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 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 Summer 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. Staples at (404) 997-4644, or me at (404) 997-4530.
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


Kathryn M. Sutton, Esq. Morgan, Lewis & Bockius LLP Electronic Mail Distribution
SCE&G                                        3
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
Susan E. Jenkins Director, Division of Waste Management Bureau of Land and Waste Management S.C. Department of Health and Environmental Control Electronic Mail Distribution
rm/adams.html (the Public Electronic Reading Room).
                                            Sincerely,
R. Mike Gandy Division of Radioactive Waste Mgmt. S.C. Department of Health and Environmental Control Electronic Mail Distribution
                                            /RA/
                                            Rebecca L. Nease, Chief
                                            Engineering Branch 2
                                            Division of Reactor Safety
Docket No.: 50-395
License No.: NPF-12
Enclosures:  1. Triennial Fire Protection Inspection Support Documentation
              2. Mitigating Strategies Support Documentation
cc w/encl. (See page 4)


Andy T.  Barbee Director Nuclear Training South Carolina Electric & Gas Company
SCE&G                                      4
Electronic Mail Distribution
cc w/encl:
Bruce L. Thompson Manager Nuclear Licensing (Mail Code 830)
R. J. White                                  Robert M. Fowlkes
South Carolina Electric & Gas Company Electronic Mail Distribution
Nuclear Coordinator                          General Manager
 
S.C. Public Service Authority Mail Code 802  Engineering Services
  Robert M. Fowlkes General Manager Engineering Services South Carolina Electric & Gas Company  
Electronic Mail Distribution                South Carolina Electric & Gas Company
Electronic Mail Distribution  
                                            Electronic Mail Distribution
David A. Lavigne General Manager Operational Readiness  
Kathryn M. Sutton, Esq.
South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P.O. Box 88 Jenkinsville, SC   29065  
Morgan, Lewis & Bockius LLP                  David A. Lavigne
Senior Resident Inspector Virgil C. Summer Nuclear Station  
Electronic Mail Distribution                General Manager
U.S. NRC 576 Stairway Road Jenkinsville, SC   29065  
                                            Operational Readiness
Robin R. Haselden  
Susan E. Jenkins                            South Carolina Electric & Gas Company
General Manager Organizational Development & Effectiveness South Carolina Electric & Gas Company Electronic Mail Distribution  
Director, Division of Waste Management      Virgil C. Summer Nuclear Station
Bureau of Land and Waste Management          P.O. Box 88
S.C. Department of Health and                Jenkinsville, SC 29065
Environmental Control
Electronic Mail Distribution                Senior Resident Inspector
                                            Virgil C. Summer Nuclear Station
R. Mike Gandy                                U.S. NRC
Division of Radioactive Waste Mgmt.          576 Stairway Road
S.C. Department of Health and                Jenkinsville, SC 29065
Environmental Control
Electronic Mail Distribution                Robin R. Haselden
                                            General Manager
Andy T. Barbee                              Organizational Development &
Director                                    Effectiveness
Nuclear Training                            South Carolina Electric & Gas Company
South Carolina Electric & Gas Company       Electronic Mail Distribution
Electronic Mail Distribution
                                            George A. Lippard, III
Bruce L. Thompson                            General Manager
Manager                                      Nuclear Plant Operations
Nuclear Licensing (Mail Code 830)            South Carolina Electric & Gas Company
South Carolina Electric & Gas Company        Electronic Mail Distribution
Electronic Mail Distribution
                                            Robert L. Justice
                                            Manager
                                            Nuclear Operations
                                            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
Robert L. Justice Manager Nuclear Operations
South Carolina Electric & Gas Company Electronic Mail Distribution
 


_________________________
_________________________                     G SUNSI REVIEW COMPLETE
G   SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS RII:DRP RII:DRS   SIGNATURE RA RA RA RA   NAME STAPLES WALKER MCCOY NEASE   DATE 3/8/2010 4/8/2010 3/16/2010 4/14/2010   E-MAIL COPY?     YES NO   YES NO   YES NO   YES NO   YES NO   YES NO  YES NO
OFFICE             RII:DRS         RII:DRS         RII:DRP         RII:DRS
  Enclosure 1 Triennial Fire Protection Inspection Support Documentation
SIGNATURE         RA             RA             RA               RA
  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 DVD-
NAME               STAPLES         WALKER         MCCOY           NEASE
ROM 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  
DATE                   3/8/2010       4/8/2010       3/16/2010       4/14/2010
documents or electronic information.
E-MAIL COPY?         YES       NO YES         NO YES         NO YES         NO YES     NO YES     NO  YES NO
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).  
                Triennial Fire Protection Inspection Support Documentation
    Note: This is a broad list of the documents the NRC inspection team may be interested
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).  
    in reviewing, and possibly obtaining, during the information gathering site visit. The
4. The post-fire safe shutdown analysis, including system and separation analyses.  
    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 DVD-
5. The alternative shutdown analysis.  
    ROM is .pdf). The CD/DVD-ROM should be indexed, hyperlinked, readable, and
6.  Piping and instrumentation (flow) diagrams for the fire suppression systems.  
    searchable to facilitate ease of use. Please provide 5 copies of each CD/DVD-ROM
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.  
    submitted). Information in lists should contain enough information to be easily
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  
    understood by someone who has knowledge of the technology. The lead inspector will
alternative or dedicated shutdown capability.  
    discuss specific information needs with the licensee staff and may request additional
9. Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment.  
    documents or electronic information.
1.   The Fire Protection Program document and the Fire Hazards Analysis.
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).  
2.   The Fire Protection Program implementing procedures (e.g., administrative controls,
11. Plant layout drawings which identify the general location of the post-fire emergency lighting units.  
    surveillance testing, fire brigade).
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.  
3.   The fire brigade training program document and the pre-fire plans for the selected fire
Enclosure 1 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).  
    areas/zones (to be determined during information gathering visit).
14. Maintenance and surveillance testing procedures for alternative shutdown capability (including Appendix R emergency lights and communication systems) fire barriers,  
4.   The post-fire safe shutdown analysis, including system and separation analyses.
detectors, fire pumps and fire suppression systems.  
5.   The alternative shutdown analysis.
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  
6.  Piping and instrumentation (flow) diagrams for the fire suppression systems.
maintenance procedures used to routinely verify fuse/breaker coordination in accordance with the post-fire safe shutdown coordination analysis.  
7.   Piping and instrumentation (flow) diagrams for the systems and components used to
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.  
    achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from
    the control room.
17. A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R, Section Ill.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 Ill.G.2.a), 20-foot separation along with detection and suppression (Section IIl.G.2.b), 1-hour rated fire barriers with detection and suppression  
8.   Piping and instrumentation (flow) diagrams for the systems and components used to
(Section lII.G.2.c), or alternative shutdown capability (Section lll.G.3) is used for the selected fire areas/zones.  
    achieve and maintain hot standby, and cold shutdown, for fires in areas requiring
18. Procedures or instructions that govern the implementation of plant modifications, temporary modifications, maintenance, and special operations, and their impact on fire  
    alternative or dedicated shutdown capability.
protection.  
9.   Plant layout and equipment drawings which identify the physical plant locations of hot
19. Organization chart(s) of site personnel down to the level of the fire protection staff.  
    standby and cold shutdown equipment.
20. Procedures or instructions that control the configuration of the fire protection program, features, and post-fire safe shutdown methodology and system design.  
10. Plant layout drawings which identify plant fire area and/or fire zone delineation, areas
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)).  
    protected by automatic fire suppression and detection, and the locations of fire
22. The three most recent fire protection QA audits and/or fire protection self-assessments.  
    protection equipment for the selected fire areas/zones (to be determined during
23. A list of open and closed fire protection problem identification and resolution reports [also known as action reports/condition reports/problem investigation reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the past three years.
    information gathering visit).
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 facility's post-fire safe shutdown configuration).
11. Plant layout drawings which identify the general location of the post-fire emergency
    lighting units.
25. A list of fire protection or Appendix R calculations,  
12. Plant operating procedures used to, and describing shutdown from inside the control
Enclosure 1 26. A list of fire impairments identified during the previous year.
    room with a postulated fire occurring in any plant area outside the control room.
27. A list of abbreviations/designators for plant systems.  
                                                                                    Enclosure 1
  Enclosure 2 Mitigating Strategies 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 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  
                                            2
".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.  
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
1.   A list of all modifications to regulatory commitments made to meet the requirements of Section B.5.b of the ICM Order, EA-02-026, dated February 25, 2002, the subsequently imposed license conditions, and 10 CFR 50.54(hh)(2).  
    other alternative shutdown area).
2.   Copies 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  
14. Maintenance and surveillance testing procedures for alternative shutdown capability
(EOPs), abnormal operating procedures (AOPs), etc.
    (including Appendix R emergency lights and communication systems) fire barriers,
3.  A matrix that shows the correlation between the mitigation strategies identified in Nuclear Energy Institute 06-12 and the site-specific procedures or guidelines that are used to implement each strategy.  
    detectors, fire pumps and fire suppression systems.
4.  Engineering evaluations/calculations that were used to verify engineering bases for the mitigation strategies.
15. Calculations and/or justifications that verify fuse/breaker coordination for the selected
5.  Piping and instrumentation diagram (P&ID) or simplified flow diagrams for systems relied upon in the mitigation strategies. These could be the type used for training.
    fire areas/zones (to be determined during information gathering visit) that are fed off the
6.  A modification package or simplified drawings/descriptions of modifications that were made to plant systems to implement the mitigation strategies.
    same electrical buses as components in the protected train. Also, a list of the
    maintenance procedures used to routinely verify fuse/breaker coordination in
7.  Copies of procedures used to inventory equipment (hoses, fittings, pumps, etc.) required to be used to implement the mitigation strategies.  
    accordance with the post-fire safe shutdown coordination analysis.
8.  A list of B.5.b strategies, if any, which have implementing details that differ from that documented in the submittals and the safety evaluation report.
16. A list of the significant fire protection and post-fire safe shutdown design change
9.  A copy of site general arrangement drawing(s) that show the majority of buildings/areas referenced in B.5.b documents.  
    descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter
10. Training records/training matrix/lesson plans related to B.5.b.  
    (GL) 86-10 evaluations.
11. Copies of Memoranda of Understanding (MOUs) (e.g., with local fire departments) required to implement any mitigating strategies.
17. A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R,
    Section Ill.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 Ill.G.2.a), 20-foot separation along with detection and
    suppression (Section IIl.G.2.b), 1-hour rated fire barriers with detection and suppression
    (Section lII.G.2.c), or alternative shutdown capability (Section lll.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 investigation
    reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the
    past three years.
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,
                                                                                      Enclosure 1
 
                                          3
26. A list of fire impairments identified during the previous year.
27. A list of abbreviations/designators for plant systems.
                                                                    Enclosure 1
 
                        Mitigating Strategies 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 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 the ICM Order, EA-02-026, dated February 25, 2002, the subsequently
    imposed license conditions, and 10 CFR 50.54(hh)(2).
2. Copies 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 and the site-specific procedures or guidelines that are
    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 (P&ID) or simplified flow diagrams for systems relied
    upon in the mitigation strategies. These could be the type used for training.
6.  A modification package or simplified drawings/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 be used to implement the mitigation strategies.
8.  A list of B.5.b strategies, if any, which have implementing details that differ from that
    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/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
}}
}}

Latest revision as of 20:47, 13 November 2019

Notification of Conduct of Triennial Fire Protection Baseline Inspection While Transition to 10 CFR Part 50.48(c) Is in Progress (IR 05000395-10-008)
ML101060442
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 04/14/2010
From: Nease R
NRC/RGN-II/DRS/EB2
To: Gatlin T
South Carolina Electric & Gas Co
References
IR-10-008
Download: ML101060442 (9)


See also: IR 05000395/2010008

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

SAM NUNN ATLANTA FEDERAL CENTER

61 FORSYTH STREET, SW, SUITE 23T85

ATLANTA, GEORGIA 30303-8931

April 14, 2010

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- NOTIFICATION OF CONDUCT OF

A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION WHILE

TRANSITION TO 10 CFR PART 50.48(c) IS IN PROGRESS (NRC INSPECTION

REPORT NO. 05000395/2010008)

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. Summer

Nuclear Station, in June and July 2010. The inspection team will be led by Mr. Necota Staples,

NRC 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 71111.05TTP, 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 March 03, 2010, during a telephone conversation between Mr. Arnie Cribb (Summer

Licensing Supervisor) of your staff, and Mr. Staples, 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: May 25 - 27, 2010
  • Week 1 of onsite inspection: June 14 -18, 2010
  • Week 2 of onsite inspection: June 28 - July 02, 2010

The purposes of the information gathering visit are to obtain information and documentation

needed to support the inspection, to become familiar with the Summer Nuclear Station fire

protection programs, fire protection features, post-fire safe shutdown capabilities, plant layout,

and mitigating strategies to address Section B.5.b of the Interim Compensatory Measures

Order, EA-02-026, of February 25, 2002/10 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. Staples prior to preparing copies of the materials listed in the Enclosures.

SCE&G 2

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 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 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 Summer 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 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 Summer 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. Staples at (404) 997-4644, or me at (404) 997-4530.

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

SCE&G 3

(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/

Rebecca L. Nease, Chief

Engineering Branch 2

Division of Reactor Safety

Docket No.: 50-395

License No.: NPF-12

Enclosures: 1. Triennial Fire Protection Inspection Support Documentation

2. Mitigating Strategies Support Documentation

cc w/encl. (See page 4)

SCE&G 4

cc w/encl:

R. J. White Robert M. Fowlkes

Nuclear Coordinator General Manager

S.C. Public Service Authority Mail Code 802 Engineering Services

Electronic Mail Distribution South Carolina Electric & Gas Company

Electronic Mail Distribution

Kathryn M. Sutton, Esq.

Morgan, Lewis & Bockius LLP David A. Lavigne

Electronic Mail Distribution General Manager

Operational Readiness

Susan E. Jenkins South Carolina Electric & Gas Company

Director, Division of Waste Management Virgil C. Summer Nuclear Station

Bureau of Land and Waste Management P.O. Box 88

S.C. Department of Health and Jenkinsville, SC 29065

Environmental Control

Electronic Mail Distribution Senior Resident Inspector

Virgil C. Summer Nuclear Station

R. Mike Gandy U.S. NRC

Division of Radioactive Waste Mgmt. 576 Stairway Road

S.C. Department of Health and Jenkinsville, SC 29065

Environmental Control

Electronic Mail Distribution Robin R. Haselden

General Manager

Andy T. Barbee Organizational Development &

Director Effectiveness

Nuclear Training South Carolina Electric & Gas Company

South Carolina Electric & Gas Company Electronic Mail Distribution

Electronic Mail Distribution

George A. Lippard, III

Bruce L. Thompson General Manager

Manager Nuclear Plant Operations

Nuclear Licensing (Mail Code 830) South Carolina Electric & Gas Company

South Carolina Electric & Gas Company Electronic Mail Distribution

Electronic Mail Distribution

Robert L. Justice

Manager

Nuclear Operations

South Carolina Electric & Gas Company

Electronic Mail Distribution

_________________________ G SUNSI REVIEW COMPLETE

OFFICE RII:DRS RII:DRS RII:DRP RII:DRS

SIGNATURE RA RA RA RA

NAME STAPLES WALKER MCCOY NEASE

DATE 3/8/2010 4/8/2010 3/16/2010 4/14/2010

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

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 on CD-ROM or DVD-

ROM 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 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.

Enclosure 1

2

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) 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 Ill.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 Ill.G.2.a), 20-foot separation along with detection and

suppression (Section IIl.G.2.b), 1-hour rated fire barriers with detection and suppression

(Section lII.G.2.c), or alternative shutdown capability (Section lll.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 investigation

reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the

past three years.

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,

Enclosure 1

3

26. A list of fire impairments identified during the previous year.

27. A list of abbreviations/designators for plant systems.

Enclosure 1

Mitigating Strategies 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 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 the ICM Order, EA-02-026, dated February 25, 2002, the subsequently

imposed license conditions, and 10 CFR 50.54(hh)(2).

2. Copies 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 and the site-specific procedures or guidelines that are

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 (P&ID) or simplified flow diagrams for systems relied

upon in the mitigation strategies. These could be the type used for training.

6. A modification package or simplified drawings/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 be used to implement the mitigation strategies.

8. A list of B.5.b strategies, if any, which have implementing details that differ from that

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/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