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{{Adams | |||
| number = ML023470222 | |||
| issue date = 12/12/2002 | |||
| title = Notification of Triennial Fire Protection Baseline Inspection (NRC Inspection Report Nos. 50-335/03-02 and 50-389/03-02) | |||
| author name = Ogle C | |||
| author affiliation = NRC/RGN-II/DRS | |||
| addressee name = Stall J | |||
| addressee affiliation = Florida Power & Light Co | |||
| docket = 05000335, 05000389 | |||
| license number = DPR-067, NPF-016 | |||
| contact person = | |||
| case reference number = IR-03-002 | |||
| document type = Inspection Plan, Letter | |||
| page count = 7 | |||
}} | |||
See also: [[see also::IR 05000335/2003002]] | |||
=Text= | |||
{{#Wiki_filter:December 12, 2002 | |||
Florida Power and Light Company | |||
ATTN: Mr. J. A. Stall, Senior Vice President | |||
Nuclear and Chief Nuclear Officer | |||
P. O. Box 14000 | |||
Juno Beach, FL 33408-0420 | |||
SUBJECT: | |||
NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION, | |||
(NRC INSPECTION REPORT NOS. 50-335/03-02 and 50-389/03-02) | |||
Dear Mr. Stall: | |||
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 St. Lucie Nuclear | |||
Plant in February and March 2003. The inspection team will be led by Mr. M. Thomas, Senior | |||
Reactor Inspector, of the Region II Office. The team will be composed of personnel from the | |||
NRC Region II Office and conducted in accordance with the NRCs baseline fire protection | |||
inspection procedure 71111.05. | |||
The inspection objective will be to evaluate your fire protection program implementation with | |||
emphasis on post-fire safe shutdown capability and the fire protection features provided to | |||
ensure at least one post-fire safe shutdown success path is maintained free of fire damage. | |||
The inspection team will focus their review on the separation of systems and equipment | |||
necessary to achieve and maintain safe shutdown and fire protection features of selected fire | |||
areas. | |||
On December 12, 2002, during a telephone conversation with Mr. Kelly Korth, Licensing | |||
Manager, 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 onsite visit - February 25-27, 2003 | |||
Week 1 of onsite inspection - March 10-14, 2003 | |||
Week 2 of onsite inspection - March 24-28, 2003 | |||
The purposes of the information gathering visit are to obtain information and documentation | |||
needed to support the inspection; to become familiar with the St. Lucie fire protection program, | |||
fire protection features, post-fire safe shutdown capabilities and plant layout; and, as | |||
necessary, to obtain plant specific site access training and badging for unescorted site access. | |||
The types of documents the team will be interested in reviewing, and possibly obtaining, are | |||
listed in the Enclosure. Please contact Mr. Thomas prior to preparing copies of the materials | |||
listed in the Enclosure. The inspection team will try to minimize your administrative burden by | |||
specifically identifying those documents required for inspection preparation. | |||
During the information gathering visit, the team will also discuss the following inspection support | |||
administrative details: office space; specific documents requested to be made available to the | |||
team in their office spaces; arrangements for reactor site access (including radiation protection | |||
FP&L | |||
2 | |||
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 St. Lucie Nuclear Plant | |||
fire protection program, including post-fire safe shutdown capability, be readily accessible to the | |||
team for their 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 St. Lucie 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 teams information or logistical needs, please | |||
contact Mr. Thomas at (404) 562-4673, or me at (404) 562-4605. | |||
Sincerely, | |||
/RA: Walter Rogers for:/ | |||
Charles R. Ogle, Chief | |||
Engineering Branch 1 | |||
Division of Reactor Safety | |||
Docket Nos. 50-335, 50-389 | |||
License Nos. DPR-67, NPF-16 | |||
Enclosure: | |||
Triennial Fire Protection Inspection | |||
Support Documentation | |||
cc w/encl: | |||
D. E. Jernigan | |||
Site Vice President | |||
St. Lucie Nuclear Plant | |||
Florida Power & Light Company | |||
Electronic Mail Distribution | |||
R. E. Rose | |||
Plant General Manager | |||
St. Lucie Nuclear Plant | |||
Electronic Mail Distribution | |||
(cc w/encl contd - See page 3) | |||
FP&L | |||
3 | |||
(cc w/encl contd) | |||
Kelly J. Korth | |||
Licensing Manager | |||
St. Lucie Nuclear Plant | |||
Electronic Mail Distribution | |||
Don Mothena, Manager | |||
Nuclear Plant Support Services | |||
Florida Power & Light Company | |||
Electronic Mail Distribution | |||
Mark Dryden | |||
Administrative Support & Special Projects | |||
Florida Power & Light Company | |||
Electronic Mail Distribution | |||
Rajiv S. Kundalkar | |||
Vice President - Nuclear Engineering | |||
Florida Power & Light Company | |||
Electronic Mail Distribution | |||
M. S. Ross, Attorney | |||
Florida Power & Light Company | |||
Electronic Mail Distribution | |||
William A. Passetti | |||
Bureau of Radiation Control | |||
Department of Health | |||
Electronic Mail Distribution | |||
Craig Fugate, Director | |||
Division of Emergency Preparedness | |||
Department of Community Affairs | |||
Electronic Mail Distribution | |||
J. Kammel | |||
Radiological Emergency | |||
Planning Administrator | |||
Department of Public Safety | |||
Electronic Mail Distribution | |||
Douglas Anderson | |||
County Administrator | |||
St. Lucie County | |||
2300 Virginia Avenue | |||
Ft. Pierce, FL 34982 | |||
Distribution w/encl: See page 4 | |||
FP&L | |||
4 | |||
Distribution w/encl: | |||
B. Moroney, NRR | |||
RIDSNRRDIPMLIPB | |||
PUBLIC | |||
OFFICE | |||
RII:DRS | |||
RII:DRS | |||
RII:DRP | |||
RII:DRS | |||
SIGNATURE | |||
THOMAS | |||
ROGERS FOR | |||
WERT | |||
NAME | |||
MThomas | |||
CPayne | |||
LWert | |||
COgle | |||
DATE | |||
12/12/2002 | |||
12/12/2002 | |||
12/12/2002 | |||
12/ /2002 | |||
12/ /2002 | |||
12/ /2002 | |||
12/ /2002 | |||
E-MAIL COPY? | |||
YES | |||
NO YES | |||
NO YES | |||
NO YES | |||
NO YES | |||
NO YES | |||
NO YES | |||
NO | |||
OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML023470222.wpd | |||
Enclosure | |||
Triennial Fire Protection Inspection Support Documentation | |||
[Note: This is a broad list of the documents the NRC inspection team may be interested | |||
in reviewing, and possibly obtaining, during the information gathering site visit. The | |||
current version of these documents is expected unless specified otherwise. Electronic | |||
media is preferred if readily available (i.e., on CD-ROM or computer disc). If electronic | |||
media is offered, we request that an index of files or a simple menu be provided.] | |||
1. | |||
The Fire Protection Program 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 and pre-fire plans. | |||
4. | |||
Post-fire safe shutdown systems and separation analysis. | |||
5. | |||
Post-fire alternative shutdown analysis. | |||
6. | |||
Piping and instrumentation (flow) diagrams showing those systems and 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. | |||
7. | |||
Plant layout and equipment drawings which identify the physical plant locations of hot | |||
standby and cold shutdown equipment. | |||
8. | |||
Plant layout drawings which identify plant fire area delineation, areas protected by | |||
automatic fire suppression and detection, and the locations of fire protection equipment. | |||
9. | |||
Plant layout drawings which identify the general location of the post-fire emergency | |||
lighting units. | |||
10. | |||
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 either the control or cable spreading room. | |||
11. | |||
Maintenance and surveillance testing procedures for alternative shutdown capability and | |||
fire barriers, detectors, pumps and suppression systems. | |||
12. | |||
Maintenance procedures which routinely verify fuse breaker coordination in accordance | |||
with the post-fire safe shutdown coordination analysis. | |||
13. | |||
A sample of significant fire protection and post-fire safe shutdown related design change | |||
packages and Generic Letter 86-10 evaluations. | |||
2 | |||
Enclosure | |||
14. | |||
The reactor plants IPEEE, results of any post-IPEEE reviews, and a list of actions taken | |||
or plant modifications conducted in response to IPEEE information. | |||
15. | |||
Temporary modification procedure(s). | |||
16. | |||
Organization charts of site personnel down to the level of fire protection staff personnel. | |||
17. | |||
If applicable, layout/arrangement drawings of potential reactor coolant pump lube oil | |||
system leakage points and associated lube oil collection systems. | |||
18. | |||
A list of the SERs which form the licensing basis for the post-fire safe shutdown | |||
configuration. | |||
19. | |||
Procedures/instructions that control the configuration of the fire protection program, | |||
features, and post-fire safe shutdown methodology and system design. | |||
20. | |||
A list of applicable codes and standards related to the design of plant fire protection | |||
features and evaluations of code deviations. | |||
21. | |||
Procedures/instructions that govern the implementation of plant modifications, | |||
maintenance, and special operations, and their impact on fire protection. | |||
22. | |||
The three most recent fire protection QA audits and/or fire protection self-assessments. | |||
23. | |||
Recent QA surveillances of fire protection activities. | |||
24. | |||
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]. | |||
25. | |||
A list of plant fire protection licensing basis documents. | |||
26. | |||
A list of the NFPA code versions committed to (NFPA codes of record). | |||
27. | |||
A list of plant deviations from code commitments. | |||
}} | |||
Latest revision as of 13:41, 16 January 2025
| ML023470222 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 12/12/2002 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Stall J Florida Power & Light Co |
| References | |
| IR-03-002 | |
| Download: ML023470222 (7) | |
See also: IR 05000335/2003002
Text
December 12, 2002
Florida Power and Light Company
ATTN: Mr. J. A. Stall, Senior Vice President
Nuclear and Chief Nuclear Officer
P. O. Box 14000
Juno Beach, FL 33408-0420
SUBJECT:
NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION,
(NRC INSPECTION REPORT NOS. 50-335/03-02 and 50-389/03-02)
Dear Mr. Stall:
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 St. Lucie Nuclear
Plant in February and March 2003. The inspection team will be led by Mr. M. Thomas, Senior
Reactor Inspector, of the Region II Office. The team will be composed of personnel from the
NRC Region II Office and conducted in accordance with the NRCs baseline fire protection
inspection procedure 71111.05.
The inspection objective will be to evaluate your fire protection program implementation with
emphasis on post-fire safe shutdown capability and the fire protection features provided to
ensure at least one post-fire safe shutdown success path is maintained free of fire damage.
The inspection team will focus their review on the separation of systems and equipment
necessary to achieve and maintain safe shutdown and fire protection features of selected fire
areas.
On December 12, 2002, during a telephone conversation with Mr. Kelly Korth, Licensing
Manager, 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 onsite visit - February 25-27, 2003
Week 1 of onsite inspection - March 10-14, 2003
Week 2 of onsite inspection - March 24-28, 2003
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection; to become familiar with the St. Lucie fire protection program,
fire protection features, post-fire safe shutdown capabilities and plant layout; and, as
necessary, to obtain plant specific site access training and badging for unescorted site access.
The types of documents the team will be interested in reviewing, and possibly obtaining, are
listed in the Enclosure. Please contact Mr. Thomas prior to preparing copies of the materials
listed in the Enclosure. The inspection team will try to minimize your administrative burden by
specifically identifying those documents required for inspection preparation.
During the information gathering visit, the team will also discuss the following inspection support
administrative details: office space; specific documents requested to be made available to the
team in their office spaces; arrangements for reactor site access (including radiation protection
2
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 St. Lucie Nuclear Plant
fire protection program, including post-fire safe shutdown capability, be readily accessible to the
team for their 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 St. Lucie 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 teams information or logistical needs, please
contact Mr. Thomas at (404) 562-4673, or me at (404) 562-4605.
Sincerely,
/RA: Walter Rogers for:/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-335, 50-389
Enclosure:
Triennial Fire Protection Inspection
Support Documentation
cc w/encl:
D. E. Jernigan
Site Vice President
St. Lucie Nuclear Plant
Florida Power & Light Company
Electronic Mail Distribution
R. E. Rose
Plant General Manager
St. Lucie Nuclear Plant
Electronic Mail Distribution
(cc w/encl contd - See page 3)
3
(cc w/encl contd)
Kelly J. Korth
Licensing Manager
St. Lucie Nuclear Plant
Electronic Mail Distribution
Don Mothena, Manager
Nuclear Plant Support Services
Florida Power & Light Company
Electronic Mail Distribution
Mark Dryden
Administrative Support & Special Projects
Florida Power & Light Company
Electronic Mail Distribution
Rajiv S. Kundalkar
Vice President - Nuclear Engineering
Florida Power & Light Company
Electronic Mail Distribution
M. S. Ross, Attorney
Florida Power & Light Company
Electronic Mail Distribution
William A. Passetti
Bureau of Radiation Control
Department of Health
Electronic Mail Distribution
Craig Fugate, Director
Division of Emergency Preparedness
Department of Community Affairs
Electronic Mail Distribution
J. Kammel
Radiological Emergency
Planning Administrator
Department of Public Safety
Electronic Mail Distribution
Douglas Anderson
County Administrator
St. Lucie County
2300 Virginia Avenue
Ft. Pierce, FL 34982
Distribution w/encl: See page 4
4
Distribution w/encl:
B. Moroney, NRR
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRS
RII:DRP
RII:DRS
SIGNATURE
THOMAS
ROGERS FOR
WERT
NAME
MThomas
CPayne
LWert
COgle
DATE
12/12/2002
12/12/2002
12/12/2002
12/ /2002
12/ /2002
12/ /2002
12/ /2002
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML023470222.wpd
Enclosure
Triennial Fire Protection Inspection Support Documentation
[Note: This is a broad list of the documents the NRC inspection team may be interested
in reviewing, and possibly obtaining, during the information gathering site visit. The
current version of these documents is expected unless specified otherwise. Electronic
media is preferred if readily available (i.e., on CD-ROM or computer disc). If electronic
media is offered, we request that an index of files or a simple menu be provided.]
1.
The Fire Protection Program 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 and pre-fire plans.
4.
Post-fire safe shutdown systems and separation analysis.
5.
Post-fire alternative shutdown analysis.
6.
Piping and instrumentation (flow) diagrams showing those systems and 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.
7.
Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment.
8.
Plant layout drawings which identify plant fire area delineation, areas protected by
automatic fire suppression and detection, and the locations of fire protection equipment.
9.
Plant layout drawings which identify the general location of the post-fire emergency
lighting units.
10.
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 either the control or cable spreading room.
11.
Maintenance and surveillance testing procedures for alternative shutdown capability and
fire barriers, detectors, pumps and suppression systems.
12.
Maintenance procedures which routinely verify fuse breaker coordination in accordance
with the post-fire safe shutdown coordination analysis.
13.
A sample of significant fire protection and post-fire safe shutdown related design change
packages and Generic Letter 86-10 evaluations.
2
Enclosure
14.
The reactor plants IPEEE, results of any post-IPEEE reviews, and a list of actions taken
or plant modifications conducted in response to IPEEE information.
15.
Temporary modification procedure(s).
16.
Organization charts of site personnel down to the level of fire protection staff personnel.
17.
If applicable, layout/arrangement drawings of potential reactor coolant pump lube oil
system leakage points and associated lube oil collection systems.
18.
A list of the SERs which form the licensing basis for the post-fire safe shutdown
configuration.
19.
Procedures/instructions that control the configuration of the fire protection program,
features, and post-fire safe shutdown methodology and system design.
20.
A list of applicable codes and standards related to the design of plant fire protection
features and evaluations of code deviations.
21.
Procedures/instructions that govern the implementation of plant modifications,
maintenance, and special operations, and their impact on fire protection.
22.
The three most recent fire protection QA audits and/or fire protection self-assessments.
23.
Recent QA surveillances of fire protection activities.
24.
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].
25.
A list of plant fire protection licensing basis documents.
26.
A list of the NFPA code versions committed to (NFPA codes of record).
27.
A list of plant deviations from code commitments.