ML061570440: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(One intermediate revision by the same user not shown)
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:June 6, 2006Mr. William LevisSenior Vice President and Chief Nuclear Officer PSEG Nuclear LCC - N09
{{#Wiki_filter:June 6, 2006 Mr. William Levis Senior Vice President and Chief Nuclear Officer PSEG Nuclear LCC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
 
P.O. Box 236 Hancocks Bridge, NJ 08038


==SUBJECT:==
==SUBJECT:==
HOPE CREEK NUCLEAR GENERATING STATION - NOTIFICATION OFCONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
HOPE CREEK NUCLEAR GENERATING STATION - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION


==Dear Mr. Levis:==
==Dear Mr. Levis:==
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region I staff will conduct a triennial fire protection baseline inspection at your Hope Creek Nuclear Generating Station beginning in March 2006. The inspection team will be led by Mr.
Leonard Cheung from the NRC Region I Office. The team will be composed of personnel from NRC Region I. The inspection will be conducted in accordance with IP 71111.05, the NRCs baseline fire protection inspection procedure.
The schedule for the inspection is as follows:
Information gathering visit - August 15 - 17, 2006 Weeks of onsite inspection - August 28 - September 1, 2006, and September 11 - 15, 2006.
The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the Hope Creek Nuclear Generating Station fire protection programs, fire protection features, and post-fire safe shutdown capabilities and plant layout, and, as necessary, obtain plant specific site access training and badging for unescorted site access. A list of the types of documents the team is interested in reviewing, and possibly obtaining, are listed in the enclosure. Some of the listed documents apply only to the fire areas selected for the inspection. The team leader will notify your staff of the selected fire areas approximately three weeks before the site visit.
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 their 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 Hope Creek Nuclear Generating Station fire protection program including post-fire safe shutdown


The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)Region I staff will conduct a triennial fire protection baseline inspection at your Hope CreekNuclear Generating Station beginning in March 2006. The inspection team will be led by Mr.Leonard Cheung from the NRC Region I Office. The team will be composed of personnel fromNRC Region I. The inspection will be conducted in accordance with IP 71111.05, the NRC'sbaseline fire protection inspection procedure.The schedule for the inspection is as follows:
Mr. Christopher M. Crane 2
    *Information gathering visit - August 15 - 17, 2006
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 Hope Creek Nuclear Generating Station fire protection program and its implementation.
    *Weeks of onsite inspection - August 28 - September 1, 2006, and September 11 - 15, 2006.The purposes of the information gathering visit are to obtain information and documentationneeded to support the inspection, to become familiar with the Hope Creek Nuclear GeneratingStation fire protection programs, fire protection features, and post-fire safe shutdown capabilities and plant layout, and, as necessary, obtain plant specific site access training andbadging for unescorted site access. A list of the types of documents the team is interested in reviewing, and possibly obtaining, are listed in the enclosure. Some of the listed documentsapply only to the fire areas selected for the inspection. The team leader will notify your staff ofthe selected fire areas approximately three weeks before the site visit.During the information gathering visit, the team will also discuss the following inspection supportadministrative details:  office space size and location; specific documents requested to be made available to the team in their 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 aspoints 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 HopeCreek Nuclear Generating Station fire protection program including post-fire safe shutdown Mr. Christopher M. Crane2capability, be readily accessible to the team for their review. Of specific interest, are thosedocuments which establish that your fire protection program satisfies NRC regulatoryrequirements 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 frominside 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 HopeCreek Nuclear Generating Station fire protection program and its implementation.Your cooperation and support during this inspection will be appreciated. If you have questionsconcerning this inspection, or the inspection team's information or logistical needs, please contact Leonard Cheung, the team leader, in the Region I Office at (610) 337-5296.Sincerely,/RA/
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 Leonard Cheung, the team leader, in the Region I Office at (610) 337-5296.
John F. Rogge, ChiefEngineering Branch 3 Division of Reactor SafetyDocket No.50-354License No.NPF-57
Sincerely,
/RA/
John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No.
50-354 License No.
NPF-57


==Enclosure:==
==Enclosure:==
List of Reactor Fire Protection Program Supporting Documents cc w/encl:G. Barnes, Site Vice President D. Winchester, Vice President - Nuclear Assessments W. F. Sperry, Director - Business Support D. Benyak, Director - Regulatory Assurance M. Massaro, Hope Creek Plant Manager J. J. Keenan, Esquire M. Wetterhahn, Esquire Consumer Advocate, Office of Consumer Advocate F. Pompper, Chief of Police and Emergency Management Coordinator P. Baldauf, Assistant Director of Radiation Protection and Release Prevention, State of   New Jersey K. Tosch, Chief, Bureau of Nuclear Engineering, NJ Dept. of Environmental Protection H. Otto, Ph.D., DNREC Division of Water Resources, State of Delaware N. Cohen, Coordinator - Unplug Salem Campaign W. Costanzo, Technical Advisor - Jersey Shore Nuclear Watch E. Zobian, Coordinator - Jersey Shore Anti Nuclear Alliance Mr. Christopher M. Crane3Distribution w/encl:S. Collins, RA M. Dapas, DRA A. Blough, DRS M. Gray, DRP B. Welling, DRP G. Malone, DRP, Senior Resident Inspector T. Wingfield, DRP, Resident Inspector K. Venuto, DRP, Resident OA B. Sosa, RI OEDO D. Roberts, NRR D. Collins, NRR S. Bailey, PM, NRR Region I Docket Room (with concurrences)SUNSI Review Complete:         JFR                 (Reviewer's Initials
List of Reactor Fire Protection Program Supporting Documents cc w/encl:
)DOCUMENT NAME: E:\Filenet\ML061570440.wpdAfter declaring this document "An Official Agency Record" it will/will not be released to the Public.To receive a copy of this document, indicate in the box:
G. Barnes, Site Vice President D. Winchester, Vice President - Nuclear Assessments W. F. Sperry, Director - Business Support D. Benyak, Director - Regulatory Assurance M. Massaro, Hope Creek Plant Manager J. J. Keenan, Esquire M. Wetterhahn, Esquire Consumer Advocate, Office of Consumer Advocate F. Pompper, Chief of Police and Emergency Management Coordinator P. Baldauf, Assistant Director of Radiation Protection and Release Prevention, State of New Jersey K. Tosch, Chief, Bureau of Nuclear Engineering, NJ Dept. of Environmental Protection H. Otto, Ph.D., DNREC Division of Water Resources, State of Delaware N. Cohen, Coordinator - Unplug Salem Campaign W. Costanzo, Technical Advisor - Jersey Shore Nuclear Watch E. Zobian, Coordinator - Jersey Shore Anti Nuclear Alliance
" C" = Copy without attachment/enclosure   " E" = Copy with attachment/enclosure   " N" = No copyOFFICERI/DRSRI/DRSNAMELSCheung/LSCJFRogge/JFRDATE06/02/0606/02/06OFFICENAMEDATEOFFICIAL RECORD COPY ENCLOSUREReactor Fire Protection Program Supporting Documentation[Note: This is a broad list of the documents the NRC inspection team is interested in reviewing,and possibly obtaining, during the information gathering site visit. The team leader will notifythe licensee of the fire areas selected for the inspection approximately three weeks before the site visit.]1.The current version of the Fire Protection Program and Fire Hazards Analysis for theselected fire areas.2.Current versions of the fire protection program implementing procedures (e.g.,administrative controls, surveillance testing, fire brigade). 3.Fire brigade training program.
 
4.Pre-fire plans for the selected fire areas.
Mr. Christopher M. Crane 3
5.Post-fire safe shutdown systems and separation analysis for the selected fire areas. 6.Post-fire alternative shutdown analysis for the selected fire areas.
Distribution w/encl:
7.Piping and instrumentation (flow) diagrams showing the components used to achieveand maintain hot standby and cold shutdown for fires outside the control room and thosecomponents used for those areas requiring alternative shutdown capability. 8.Plant layout and equipment drawings which identify the physical plant locations of hotstandby and cold shutdown equipment for a fire in the selected fire areas. 9.Plant layout drawings which identify plant fire area delineation, areas protected byautomatic fire suppression and detection, and the locations of fire protection equipment. 10.Plant layout drawings which identify the general location of the post-fire emergencylighting units.11.Plant operating procedures which would be used and describe shutdown from inside thecontrol 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 theevent of a fire in either the control or cable spreading room. 12.Maintenance and surveillance testing procedures for alternative shutdown capability andfire barriers, detectors, pumps and suppression systems.13.Latest two test results of the Alternate Shutdown Panel surveillances (Note: this itemmay be combined with item 12 if the procedure is included in the test results).14.Latest two test results of fire pump pressure and flow tests (Note: this item may becombined with item 12 if the procedure is included in the test results).
S. Collins, RA M. Dapas, DRA A. Blough, DRS M. Gray, DRP B. Welling, DRP G. Malone, DRP, Senior Resident Inspector T. Wingfield, DRP, Resident Inspector K. Venuto, DRP, Resident OA B. Sosa, RI OEDO D. Roberts, NRR D. Collins, NRR S. Bailey, PM, NRR Region I Docket Room (with concurrences)
215.Maintenance procedures which routinely verify fuse/breaker coordination in accordancewith the post-fire safe shutdown coordination analysis. 16.A sample of significant fire protection and post-fire safe shutdown related design changepackages and Generic Letter 86-10 evaluations.17.The reactor plant's IPEEE, results of any post-IPEEE reviews, and listings of actionstaken/plant modifications conducted in response to IPEEE information.18.Temporary modification procedures.
SUNSI Review Complete: JFR (Reviewers Initials)
: 19. Organization charts of site personnel down to the level of fire protection staff personnel.
DOCUMENT NAME: E:\\Filenet\\ML061570440.wpd After declaring this document An Official Agency Record it will/will not be released to the Public.
20.If applicable, layout/arrangement drawings of potential reactor coolant/recirculationpump lube oil system leakage points and associated lube oil collection systems.21.A listing of the SERs which form the licensing basis for the reactor plant's post-fire safeshutdown configuration.22.Procedures/instructions that control the configuration of the reactor plant's fire protectionprogram, features, and post-fire safe shutdown methodology and system design.23.A list of applicable codes and standards related to the design of plant fire protectionfeatures and evaluations of code deviations.24.Procedures/instructions that govern the implementation of plant modifications,maintenance, and special operations, and their impact on fire protection.25.The three most recent fire protection Quality Assurance (QA) audits and/or fireprotection self-assessments.26.Recent QA surveillances of fire protection activities.
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RI/DRS RI/DRS NAME LSCheung/LSC JFRogge/JFR DATE 06/02/06 06/02/06 OFFICE NAME DATE OFFICIAL RECORD COPY
27.A listing of open and closed fire protection condition reports (problemreports/NCRs/EARs/problem identification and resolution reports) for the past threeyears.28.Listing of plant fire protection licensing basis documents.
 
29.A listing of the NFPA code versions committed to (NFPA codes of record).
ENCLOSURE Reactor Fire Protection Program Supporting Documentation
30.A listing of plant deviations from code commitments.
[Note: This is a broad list of the documents the NRC inspection team is interested in reviewing, and possibly obtaining, during the information gathering site visit. The team leader will notify the licensee of the fire areas selected for the inspection approximately three weeks before the site visit.]
31.Actual copies of Generic Letter 86-10 evaluations.
1.
32.Latest five hot work permits completed during power operation.
The current version of the Fire Protection Program and Fire Hazards Analysis for the selected fire areas.
33.Latest five transient combustible permits.
2.
334.Latest two test results of main loop flow tests.35.Latest five fire drill critiques (include fire drill(s) for the selected fire areas if applicable).36.Layout drawings and equipment listing of the Alternate Shutdown Panel(s).
Current versions of the fire protection program implementing procedures (e.g.,
37.Appendix R circuit breaker coordination analysis (if dedicated analysis is available).
administrative controls, surveillance testing, fire brigade).
38.Electrical one-line diagrams for 4160 Vac, 480 Vac, 120 Vac (vital buses) and 125 Vdcsystems.39.Fire fighting communication plan (if available) for fires in the selected fire areas.
3.
40.Latest two inventory results of post-fire cold shutdown equipment.
Fire brigade training program.
41.Fire Protection System health reports.}}
4.
Pre-fire plans for the selected fire areas.
5.
Post-fire safe shutdown systems and separation analysis for the selected fire areas.
6.
Post-fire alternative shutdown analysis for the selected fire areas.
7.
Piping and instrumentation (flow) 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.
8.
Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment for a fire in the selected fire areas.
9.
Plant layout drawings which identify plant fire area delineation, areas protected by automatic fire suppression and detection, and the locations of fire protection equipment.
10.
Plant layout drawings which identify the general location of the post-fire emergency lighting units.
11.
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.
12.
Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps and suppression systems.
13.
Latest two test results of the Alternate Shutdown Panel surveillances (Note: this item may be combined with item 12 if the procedure is included in the test results).
14.
Latest two test results of fire pump pressure and flow tests (Note: this item may be combined with item 12 if the procedure is included in the test results).
 
2 15.
Maintenance procedures which routinely verify fuse/breaker coordination in accordance with the post-fire safe shutdown coordination analysis.
16.
A sample of significant fire protection and post-fire safe shutdown related design change packages and Generic Letter 86-10 evaluations.
17.
The reactor plant's IPEEE, results of any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in response to IPEEE information.
18.
Temporary modification procedures.
: 19.
Organization charts of site personnel down to the level of fire protection staff personnel.
20.
If applicable, layout/arrangement drawings of potential reactor coolant/recirculation pump lube oil system leakage points and associated lube oil collection systems.
21.
A listing of the SERs which form the licensing basis for the reactor plant's post-fire safe shutdown configuration.
22.
Procedures/instructions that control the configuration of the reactor plant's fire protection program, features, and post-fire safe shutdown methodology and system design.
23.
A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations.
24.
Procedures/instructions that govern the implementation of plant modifications, maintenance, and special operations, and their impact on fire protection.
25.
The three most recent fire protection Quality Assurance (QA) audits and/or fire protection self-assessments.
26.
Recent QA surveillances of fire protection activities.
27.
A listing of open and closed fire protection condition reports (problem reports/NCRs/EARs/problem identification and resolution reports) for the past three years.
28.
Listing of plant fire protection licensing basis documents.
29.
A listing of the NFPA code versions committed to (NFPA codes of record).
30.
A listing of plant deviations from code commitments.
31.
Actual copies of Generic Letter 86-10 evaluations.
32.
Latest five hot work permits completed during power operation.
33.
Latest five transient combustible permits.
 
3 34.
Latest two test results of main loop flow tests.
35.
Latest five fire drill critiques (include fire drill(s) for the selected fire areas if applicable).
36.
Layout drawings and equipment listing of the Alternate Shutdown Panel(s).
37.
Appendix R circuit breaker coordination analysis (if dedicated analysis is available).
38.
Electrical one-line diagrams for 4160 Vac, 480 Vac, 120 Vac (vital buses) and 125 Vdc systems.
39.
Fire fighting communication plan (if available) for fires in the selected fire areas.
40.
Latest two inventory results of post-fire cold shutdown equipment.
41.
Fire Protection System health reports.}}

Latest revision as of 08:34, 15 January 2025

Notification of Conduct of a Triennial Fire Protection Baseline Inspection
ML061570440
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/06/2006
From: Rogge J
Engineering Region 1 Branch 3
To: Levis W
Public Service Enterprise Group
References
Download: ML061570440 (6)
v • d • e


Text

June 6, 2006 Mr. William Levis Senior Vice President and Chief Nuclear Officer PSEG Nuclear LCC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK NUCLEAR GENERATING STATION - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

Dear Mr. Levis:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region I staff will conduct a triennial fire protection baseline inspection at your Hope Creek Nuclear Generating Station beginning in March 2006. The inspection team will be led by Mr.

Leonard Cheung from the NRC Region I Office. The team will be composed of personnel from NRC Region I. The inspection will be conducted in accordance with IP 71111.05, the NRCs baseline fire protection inspection procedure.

The schedule for the inspection is as follows:

Information gathering visit - August 15 - 17, 2006 Weeks of onsite inspection - August 28 - September 1, 2006, and September 11 - 15, 2006.

The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the Hope Creek Nuclear Generating Station fire protection programs, fire protection features, and post-fire safe shutdown capabilities and plant layout, and, as necessary, obtain plant specific site access training and badging for unescorted site access. A list of the types of documents the team is interested in reviewing, and possibly obtaining, are listed in the enclosure. Some of the listed documents apply only to the fire areas selected for the inspection. The team leader will notify your staff of the selected fire areas approximately three weeks before the site visit.

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 their 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 Hope Creek Nuclear Generating Station fire protection program including post-fire safe shutdown

Mr. Christopher M. Crane 2

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 Hope Creek Nuclear Generating Station fire protection program and its implementation.

Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection, or the inspection team's information or logistical needs, please contact Leonard Cheung, the team leader, in the Region I Office at (610) 337-5296.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No.

50-354 License No.

NPF-57

Enclosure:

List of Reactor Fire Protection Program Supporting Documents cc w/encl:

G. Barnes, Site Vice President D. Winchester, Vice President - Nuclear Assessments W. F. Sperry, Director - Business Support D. Benyak, Director - Regulatory Assurance M. Massaro, Hope Creek Plant Manager J. J. Keenan, Esquire M. Wetterhahn, Esquire Consumer Advocate, Office of Consumer Advocate F. Pompper, Chief of Police and Emergency Management Coordinator P. Baldauf, Assistant Director of Radiation Protection and Release Prevention, State of New Jersey K. Tosch, Chief, Bureau of Nuclear Engineering, NJ Dept. of Environmental Protection H. Otto, Ph.D., DNREC Division of Water Resources, State of Delaware N. Cohen, Coordinator - Unplug Salem Campaign W. Costanzo, Technical Advisor - Jersey Shore Nuclear Watch E. Zobian, Coordinator - Jersey Shore Anti Nuclear Alliance

Mr. Christopher M. Crane 3

Distribution w/encl:

S. Collins, RA M. Dapas, DRA A. Blough, DRS M. Gray, DRP B. Welling, DRP G. Malone, DRP, Senior Resident Inspector T. Wingfield, DRP, Resident Inspector K. Venuto, DRP, Resident OA B. Sosa, RI OEDO D. Roberts, NRR D. Collins, NRR S. Bailey, PM, NRR Region I Docket Room (with concurrences)

SUNSI Review Complete: JFR (Reviewers Initials)

DOCUMENT NAME: E:\\Filenet\\ML061570440.wpd After declaring this document An Official Agency Record it will/will not be released to the Public.

To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RI/DRS RI/DRS NAME LSCheung/LSC JFRogge/JFR DATE 06/02/06 06/02/06 OFFICE NAME DATE OFFICIAL RECORD COPY

ENCLOSURE Reactor Fire Protection Program Supporting Documentation

[Note: This is a broad list of the documents the NRC inspection team is interested in reviewing, and possibly obtaining, during the information gathering site visit. The team leader will notify the licensee of the fire areas selected for the inspection approximately three weeks before the site visit.]

1.

The current version of the Fire Protection Program and Fire Hazards Analysis for the selected fire areas.

2.

Current versions of the fire protection program implementing procedures (e.g.,

administrative controls, surveillance testing, fire brigade).

3.

Fire brigade training program.

4.

Pre-fire plans for the selected fire areas.

5.

Post-fire safe shutdown systems and separation analysis for the selected fire areas.

6.

Post-fire alternative shutdown analysis for the selected fire areas.

7.

Piping and instrumentation (flow) 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.

8.

Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment for a fire in the selected fire areas.

9.

Plant layout drawings which identify plant fire area delineation, areas protected by automatic fire suppression and detection, and the locations of fire protection equipment.

10.

Plant layout drawings which identify the general location of the post-fire emergency lighting units.

11.

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.

12.

Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps and suppression systems.

13.

Latest two test results of the Alternate Shutdown Panel surveillances (Note: this item may be combined with item 12 if the procedure is included in the test results).

14.

Latest two test results of fire pump pressure and flow tests (Note: this item may be combined with item 12 if the procedure is included in the test results).

2 15.

Maintenance procedures which routinely verify fuse/breaker coordination in accordance with the post-fire safe shutdown coordination analysis.

16.

A sample of significant fire protection and post-fire safe shutdown related design change packages and Generic Letter 86-10 evaluations.

17.

The reactor plant's IPEEE, results of any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in response to IPEEE information.

18.

Temporary modification procedures.

19.

Organization charts of site personnel down to the level of fire protection staff personnel.

20.

If applicable, layout/arrangement drawings of potential reactor coolant/recirculation pump lube oil system leakage points and associated lube oil collection systems.

21.

A listing of the SERs which form the licensing basis for the reactor plant's post-fire safe shutdown configuration.

22.

Procedures/instructions that control the configuration of the reactor plant's fire protection program, features, and post-fire safe shutdown methodology and system design.

23.

A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations.

24.

Procedures/instructions that govern the implementation of plant modifications, maintenance, and special operations, and their impact on fire protection.

25.

The three most recent fire protection Quality Assurance (QA) audits and/or fire protection self-assessments.

26.

Recent QA surveillances of fire protection activities.

27.

A listing of open and closed fire protection condition reports (problem reports/NCRs/EARs/problem identification and resolution reports) for the past three years.

28.

Listing of plant fire protection licensing basis documents.

29.

A listing of the NFPA code versions committed to (NFPA codes of record).

30.

A listing of plant deviations from code commitments.

31.

Actual copies of Generic Letter 86-10 evaluations.

32.

Latest five hot work permits completed during power operation.

33.

Latest five transient combustible permits.

3 34.

Latest two test results of main loop flow tests.

35.

Latest five fire drill critiques (include fire drill(s) for the selected fire areas if applicable).

36.

Layout drawings and equipment listing of the Alternate Shutdown Panel(s).

37.

Appendix R circuit breaker coordination analysis (if dedicated analysis is available).

38.

Electrical one-line diagrams for 4160 Vac, 480 Vac, 120 Vac (vital buses) and 125 Vdc systems.

39.

Fire fighting communication plan (if available) for fires in the selected fire areas.

40.

Latest two inventory results of post-fire cold shutdown equipment.

41.

Fire Protection System health reports.

Retrieved from "https://kanterella.com/w/index.php?title=ML061570440&oldid=5363329"