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| number = ML101310501 | | number = ML101310501 | ||
| issue date = 05/11/2010 | | issue date = 05/11/2010 | ||
| title = | | title = Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000313-10-006; 05000368-10-006) and Request for Information | ||
| author name = O'Keefe N | | author name = O'Keefe N | ||
| author affiliation = NRC/RGN-IV/DRS/EB-2 | | author affiliation = NRC/RGN-IV/DRS/EB-2 | ||
| addressee name = Walsh K | | addressee name = Walsh K | ||
Line 14: | Line 14: | ||
| page count = 9 | | page count = 9 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000313/2010006]] | ||
=Text= | =Text= | ||
{{#Wiki_filter:May 11, 2010 | {{#Wiki_filter:UNITED STATES | ||
NUC LE AR RE G UL AT O RY C O M M I S S I O N | |||
Arkansas Nuclear One | R E GI ON I V | ||
612 EAST LAMAR BLVD , SU I TE 400 | |||
AR LI N GTON , TEXAS 76011-4125 | |||
May 11, 2010 | |||
Region IV staff will conduct a triennial fire protection baseline inspection at your Arkansas Nuclear One, Units 1 and 2 in August, 2010. | Kevin Walsh, Vice President, Operations | ||
Entergy Operations, Inc. | |||
Arkansas Nuclear One | |||
1448 S.R. 333 | |||
Russellville, AR 72802 | |||
SUBJECT: ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - NOTIFICATION OF AN NRC | |||
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION | |||
REPORT 05000313/2010006; 05000368/2010006) AND REQUEST FOR | |||
INFORMATION | |||
Dear Mr. Walsh: | |||
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC), | |||
Region IV staff will conduct a triennial fire protection baseline inspection at your Arkansas | |||
Nuclear One, Units 1 and 2 in August, 2010. The inspection team will be comprised of reactor | |||
inspectors from the NRC Region IV office. The team will conduct the inspection in accordance | |||
with the baseline Inspection Procedure 71111.05TTP, "Fire Protection-NFPA 805 Transition | |||
Period (Triennial)." | |||
The schedule for the inspection is as follows: | |||
* Information gathering visit: July 27-29, 2010 | |||
* Onsite inspection: August 9-13, 2010 | |||
August 23-27, 2010 | |||
The purposes of the information gathering visit are to obtain information and documentation | |||
needed to support the inspection, to become familiar with the fire protection programs, fire | |||
protection features, post-fire safe shutdown capabilities and plant layout, 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). Four inspectors will participate in the information gathering visit | |||
to select the fire areas for evaluation, identify additional documents needed to support the | |||
inspection, obtain unescorted access, and meet with the key personnel who will support the | |||
inspection. The fire area selection will require a walkdown of candidate fire areas in company | |||
with key personnel from your staff. The enclosure to this letter provides an initial list of the | |||
documents the team will need for their review. We request that your staff transmit copies of the | |||
documents listed in the enclosure to the NRC Region IV office for team use in preparation for | |||
the inspection. Please send this information so that it will arrive in our office in Arlington, Texas, | |||
by the dates listed in the enclosure. | |||
Entergy Operations, Inc. -2- | |||
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; 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 fire | |||
protection program, including post-fire safe shutdown capability, be readily accessible to the | |||
Entergy Operations, Inc. | team for their review. Of specific interest for the fire protection portion of the inspection are | ||
those documents that establish that your fire protection program satisfies the NRC regulatory | |||
requirements and conforms to applicable NRC and industry fire protection guidance. For the | |||
team for their review. | 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, please ensure the availability of appropriate personnel knowledgeable of: (1) plant | |||
systems required to achieve and maintain safe shutdown conditions from inside and outside the | |||
control room, (2) the electrical aspects of the post-fire safe shutdown analyses, (3) reactor plant fire protection systems, and (4) the fire protection program and its implementation. | control room, (2) the electrical aspects of the post-fire safe shutdown analyses, (3) reactor plant | ||
fire protection systems, and (4) the fire protection program and its implementation. | |||
requirements were approved by the Office of Management and Budget, control number 3150-0011. | 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 | |||
In accordance with 10 CFR 2.390 of the | 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. | |||
In accordance with 10 CFR 2.390 of the NRCs 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 | |||
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading- | |||
rm/adams.html (the Public Electronic Reading Room). | |||
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 Sam Graves, the team lead inspector, in the Region IV office at (817) 860-8102, or by | |||
email, samuel.graves@nrc.gov. | |||
Sincerely, | |||
/RA/ | |||
N. OKeefe, Chief | |||
Engineering Branch 2 | |||
Division of Reactor Safety | |||
Docket: 50-313 | |||
50-368 | |||
Entergy Operations, Inc. -3- | |||
License: DPR-51 | |||
NPF-6 | |||
Enclosure: Triennial Fire Protection | |||
Inspection Documentation Request List | |||
Senior Vice President | |||
& Chief Operating Officer | |||
Entergy Operations, Inc. | |||
P.O. Box 31995 | |||
Jackson, MS 39286-1995 | |||
Thomas Palmisano | |||
Vice President, Oversight | |||
Entergy Operations, Inc. | |||
P.O. Box 31995 | |||
Jackson, MS 39286-1995 | |||
David Bice | |||
Acting Manager, Licensing | |||
Arkansas Nuclear One | |||
1448 SR 333 | |||
Russellville, AR 72802 | |||
Joseph A. Aluise | |||
Associate General Counsel - Nuclear | |||
Entergy Services, Inc | |||
639 Loyola Avenue | |||
New Orleans, LA 70113 | |||
Senior Manager, Nuclear Safety & Licensing | |||
Entergy Nuclear Operations | |||
P.O. Box 31995 | |||
Jackson, MS 39286-1995 | |||
Chief, Radiation Control Section | |||
Arkansas Department of Health | |||
4815 West Markham Street, Slot 30 | |||
Little Rock, AR 72205-3867 | |||
Jim E. Gibson | |||
County Judge of Pope County | |||
100 West Main Street | |||
Russellville, AR 72801 | |||
Entergy Operations, Inc. -4- | |||
Arkansas Department of Health | |||
Radiation Control Section | |||
4815 West Markham Street, Slot 30 | |||
Little Rock, AR 72205-3867 | |||
David E. Maxwell, Director | |||
Arkansas Department of Emergency | |||
Management, Bldg. 9501 | |||
Camp Joseph T. Robinson | |||
North Little Rock, AR 72199 | |||
Chief, Technological Hazards | |||
Branch | |||
FEMA Region VI | |||
800 North Loop 288 | |||
Federal Regional Center | |||
Denton, TX 76209 | |||
Entergy Operations, Inc. -5- | |||
Electronic distribution by RIV: | |||
Regional Administrator (Elmo.Collins@nrc.gov) | |||
Deputy Regional Administrator (Chuck.Casto@nrc.gov) | |||
DRP Director (Dwight.Chamberlain@nrc.gov) | |||
DRP Deputy Director (Anton.Vegel@nrc.gov) | |||
DRS Director (Roy.Caniano@nrc.gov) | |||
DRS Deputy Director (Troy.Pruett@nrc.gov) | |||
Senior Resident Inspector (Alfred.Sanchez@nrc.gov) | |||
Resident Inspector (Jeffrey.Josey@nrc.gov) | |||
Resident Inspector (Jeff.Rotton@nrc.gov) | |||
Branch Chief, DRP/E (Jeff.Clark@nrc.gov) | |||
Senior Project Engineer, DRP/E (Ray.Azua@nrc.gov) | |||
ANO Administrative Assistant (Vicki.High@nrc.gov) | |||
Public Affairs Officer (Victor.Dricks@nrc.gov) | |||
Public Affairs Officer (Lara.Uselding@nrc.gov) | |||
Project Manager (Kaly.Kalyanam@nrc.gov) | |||
Branch Chief, DRS/TSB (Michael.Hay@nrc.gov) | |||
RITS Coordinator (Marisa.Herrera@nrc.gov) | |||
Regional Counsel (Karla.Fuller@nrc.gov) | |||
Congressional Affairs Officer (Jenny.Weil@nrc.gov) | |||
OEMail Resource | |||
File located: R:\REACTORS\ANO2010006 RFI - STG MLXX | |||
SUNSI Rev Compl. ;Yes No ADAMS ;Yes No Reviewer Initials STG | |||
Publicly Avail Yes ;No Sensitive Yes ; No Sens. Type Initials STG | |||
RIV:DRS/EB2 C:DRS/ EB 2 | |||
SGraves NOkeefe/GAP for | |||
/RA/ /RA/ | |||
05/10/2010 05/11/2010 | |||
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax | |||
ENCLOSURE | |||
Triennial Fire Protection Inspection Documentation Request | |||
Please provide the following documentation (items 1 - 4) prior to the onsite | |||
information-gathering visit, preferably no later than July 19, 2010. Where practical, please | |||
provide copies electronically. | |||
1. The current version of your fire protection program and fire hazards analysis. | |||
2. Post-fire safe shutdown analysis and the supporting calculations that demonstrate | |||
acceptable plant response. | |||
3. Copies of the licensing basis documents for fire protection (safety evaluation reports, | |||
pertinent sections of the final safety analysis report, exemptions, deviations, letters | |||
to/from the NRC regarding fire protection/fire safe shutdown, etc.). | |||
4. The fire probabilistic risk assessment or portions of the plants individual plant | |||
examination for external events report addressing fire events. | |||
Please provide the following documentation (items 5 - 46) during the information-gathering | |||
visit or by July 29, 2010, in order to support inspection preparation. Whenever practical, | |||
please provide copies electronically. However, drawings should be provided as paper | |||
copies of sufficient size that all details are legible. | |||
5. Plant layout and equipment drawings for the selected fire areas (these areas will be | |||
selected during the information gathering trip) that identify: (a) the physical plant | |||
locations of major hot standby and cold shutdown equipment; (b) plant fire area and/or | |||
fire zone delineation; and (c) the locations of fire protection equipment, such as | |||
detection, suppression, and post-fire emergency lighting units; and (d) fire area | |||
boundaries. | |||
6. Fire protection program implementing procedures (e.g., administrative controls, operator | |||
response procedures for fires, fire fighting procedures, etc.). | |||
7. Operating procedures used for achieving and maintaining hot and cold shutdown | |||
conditions from the control room in the event of a fire outside the control room (III.G.2 | |||
areas). | |||
8. Operating procedure(s) used to implement an alternative shutdown (III.G.3 areas) | |||
capability with or without control room evacuation. | |||
9. Pre-fire plans for the selected fire areas (areas to be selected by the team during the | |||
information-gathering trip). | |||
-1- Enclosure | |||
10. A list of equipment used to achieve and maintain hot standby and cold shutdowns in the | |||
event of a fire (safe shutdown equipment lists). | |||
11. Piping and instrumentation (flow) diagrams showing the components used to achieve | |||
and maintain hot standby and cold shutdown for normal and alternate shutdown. Please | |||
provide one copy of the piping and instrumentation (flow) diagrams for these systems of | |||
a size sufficient to read all details. These should include the systems used for reactor | |||
coolant system (RCS) makeup, RCS pressure control, decay heat removal, and | |||
reactivity control, including the essential support systems. | |||
12. A listing, with descriptions, of design change packages which were determined to impact | |||
fire protection and post-fire safe shutdowns, performed in the last 3 years. | |||
13. Copies of Generic Letter 86-10 evaluations performed in the last 3 years. | |||
14. A listing of open and closed Condition Reports initiated in the last 3 years, which relate | |||
to the fire protection program or equipment. Include Corrective Action Process | |||
document number, date, and subject. | |||
15. A listing of the applicable codes and standards (with the versions) related to the design | |||
of plant fire protection features and evaluations of any code deviations. Copies of these | |||
codes should be available for review. | |||
16. Drawings of the portions of the emergency lighting system which support fire response. | |||
17. Procedures used to remove smoke from safety-related areas and the engineering | |||
studies or calculations which support the design basis. | |||
18. Drawings of communication systems credited in the license basis for firefighting and | |||
plant operations during fires where control room is occupied and/or evacuated. | |||
19. Piping and instrumentation (flow) diagrams for the fire water and sprinkler systems. | |||
20. A listing of maintenance and surveillance testing procedures for alternative shutdown | |||
capability and fire barriers, detectors, pumps and suppression systems. | |||
21. Maintenance rule performance criteria and a summary of the last 3 years performance | |||
history for fire protection program systems or functions monitored within the | |||
maintenance rule program. | |||
22. A copy of fire protection program requirements (e.g., limiting conditions for operation, | |||
surveillance test requirements) covered by technical specifications, technical | |||
requirements manual, updated final safety analysis report, or similar documents. | |||
23. Copies of internal and external self-assessments, audits, peer-assessments or similar | |||
reviews related to post-fire safe shutdown capability or the fire protection program | |||
completed since December 3, 2007. | |||
-2- Enclosure | |||
24. A list of manual actions taken outside the control room which are credited to mitigate the | |||
consequences of fires in III.G.2 areas (non-alternative shutdown areas). The list should | |||
group actions by the initiating fire area or zone and indicate where the action must take | |||
place. | |||
25. Electronic copies of operator study guides (i.e., lesson plan text and graphics) or design | |||
basis documents that describe the purpose/function/operating characteristics of the safe | |||
shutdown systems (RCS makeup, RCS pressure control, decay heat removal, and | |||
reactivity control, including the essential support systems). | |||
26. Two copies of one-line diagrams of the electrical distribution system. These should | |||
depict how power gets from the switchyard to the engineered safety feature loads (480V | |||
and 4160V). Also, include the vital DC distribution system one-line diagrams. | |||
27. A list of automatic and manually initiated gaseous fire suppression systems in the plant, | |||
giving location and the key equipment being protected. | |||
28. A list of repairs (and the procedure that controls the actions) needed to: a) reach and/or | |||
maintain hot shutdown and b) reach and/or maintain cold shutdown. | |||
29. A list of high to low pressure interface valves. | |||
30. A copy of procedures governing the training and operation of the fire brigade. | |||
31. Organization charts of site personnel down to the level of fire protection staff personnel. | |||
32. A contact list of key site personnel who will be supporting this inspection, giving location | |||
of their office and phone number onsite. | |||
33. The team would like to observe an unannounced fire brigade drill in the plant, if possible, | |||
during the week of August 23, 2010. Please put us in contact, during the onsite | |||
information gathering trip, with the appropriate personnel for planning drills. | |||
34. The team would like to perform a walkthrough of the procedure for control room | |||
evacuation due to fire with qualified operators in the plant during the week of August 9, | |||
2010. Please put us in contact, during the onsite information gathering trip, with the | |||
appropriate personnel for planning the walkthrough. | |||
The following documents involve B.5.b mitigating strategies. | |||
35. A copy of the license condition that incorporated the requirements issued to address the | |||
requirements of Section B.5.b of the ICM Order, EA-02-026, dated February 25, 2002, | |||
and 10 CFR 50.54(hh)(2). | |||
36. 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). | |||
-3- Enclosure | |||
37. A list of procedures/guidelines which 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. | |||
38. 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. | |||
39. A list of engineering evaluations/calculations that were used to verify engineering bases | |||
for the mitigation strategies. | |||
40. Copies of 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. | |||
41. A list of modification packages and simplified drawings/descriptions of modifications that | |||
were made to plant systems to implement the mitigation strategies. | |||
42. Copies of procedure(s) used to inventory equipment (hoses, fittings, pumps, etc.) | |||
required to be used to implement the mitigation strategies. | |||
43. A list of B.5.b strategies, if any, which have implementing details that differ from that | |||
documented in the submittals to the NRC and the safety evaluation report. | |||
44. A copy of site general arrangement drawing(s) that show the majority of buildings/areas | |||
referenced in B.5.b documents. | |||
45. Training records/ training matrix/ lesson plans related to B.5.b. | |||
46. Copies of Memoranda of Understanding (MOUs) (e.g., with local fire departments) | |||
required to implement any mitigating strategies. | |||
-4- Enclosure | |||
}} | }} |
Latest revision as of 18:26, 13 November 2019
ML101310501 | |
Person / Time | |
---|---|
Site: | Arkansas Nuclear |
Issue date: | 05/11/2010 |
From: | O'Keefe N NRC/RGN-IV/DRS/EB-2 |
To: | Walsh K Entergy Operations |
References | |
IR-10-006 | |
Download: ML101310501 (9) | |
See also: IR 05000313/2010006
Text
UNITED STATES
NUC LE AR RE G UL AT O RY C O M M I S S I O N
R E GI ON I V
612 EAST LAMAR BLVD , SU I TE 400
AR LI N GTON , TEXAS 76011-4125
May 11, 2010
Kevin Walsh, Vice President, Operations
Entergy Operations, Inc.
Arkansas Nuclear One
1448 S.R. 333
Russellville, AR 72802
SUBJECT: ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - NOTIFICATION OF AN NRC
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION
REPORT 05000313/2010006; 05000368/2010006) AND REQUEST FOR
INFORMATION
Dear Mr. Walsh:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),
Region IV staff will conduct a triennial fire protection baseline inspection at your Arkansas
Nuclear One, Units 1 and 2 in August, 2010. The inspection team will be comprised of reactor
inspectors from the NRC Region IV office. The team will conduct the inspection in accordance
with the baseline Inspection Procedure 71111.05TTP, "Fire Protection-NFPA 805 Transition
Period (Triennial)."
The schedule for the inspection is as follows:
- Information gathering visit: July 27-29, 2010
- Onsite inspection: August 9-13, 2010
August 23-27, 2010
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, to become familiar with the fire protection programs, fire
protection features, post-fire safe shutdown capabilities and plant layout, 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). Four inspectors will participate in the information gathering visit
to select the fire areas for evaluation, identify additional documents needed to support the
inspection, obtain unescorted access, and meet with the key personnel who will support the
inspection. The fire area selection will require a walkdown of candidate fire areas in company
with key personnel from your staff. The enclosure to this letter provides an initial list of the
documents the team will need for their review. We request that your staff transmit copies of the
documents listed in the enclosure to the NRC Region IV office for team use in preparation for
the inspection. Please send this information so that it will arrive in our office in Arlington, Texas,
by the dates listed in the enclosure.
Entergy Operations, Inc. -2-
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; 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 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 that establish that your fire protection program satisfies the 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, please ensure the availability of appropriate personnel knowledgeable of: (1) plant
systems required to achieve and maintain safe shutdown conditions from inside and outside the
control room, (2) the electrical aspects of the post-fire safe shutdown analyses, (3) reactor plant
fire protection systems, and (4) the 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.
In accordance with 10 CFR 2.390 of the NRCs 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
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
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 Sam Graves, the team lead inspector, in the Region IV office at (817) 860-8102, or by
email, samuel.graves@nrc.gov.
Sincerely,
/RA/
N. OKeefe, Chief
Engineering Branch 2
Division of Reactor Safety
Docket: 50-313
50-368
Entergy Operations, Inc. -3-
License: DPR-51
Enclosure: Triennial Fire Protection
Inspection Documentation Request List
Senior Vice President
& Chief Operating Officer
Entergy Operations, Inc.
P.O. Box 31995
Jackson, MS 39286-1995
Vice President, Oversight
Entergy Operations, Inc.
P.O. Box 31995
Jackson, MS 39286-1995
Acting Manager, Licensing
Arkansas Nuclear One
1448 SR 333
Russellville, AR 72802
Joseph A. Aluise
Associate General Counsel - Nuclear
Entergy Services, Inc
639 Loyola Avenue
New Orleans, LA 70113
Senior Manager, Nuclear Safety & Licensing
Entergy Nuclear Operations
P.O. Box 31995
Jackson, MS 39286-1995
Chief, Radiation Control Section
4815 West Markham Street, Slot 30
Little Rock, AR 72205-3867
Jim E. Gibson
County Judge of Pope County
100 West Main Street
Russellville, AR 72801
Entergy Operations, Inc. -4-
Radiation Control Section
4815 West Markham Street, Slot 30
Little Rock, AR 72205-3867
David E. Maxwell, Director
Arkansas Department of Emergency
Management, Bldg. 9501
Camp Joseph T. Robinson
North Little Rock, AR 72199
Chief, Technological Hazards
Branch
FEMA Region VI
800 North Loop 288
Federal Regional Center
Denton, TX 76209
Entergy Operations, Inc. -5-
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov)
Deputy Regional Administrator (Chuck.Casto@nrc.gov)
DRP Director (Dwight.Chamberlain@nrc.gov)
DRP Deputy Director (Anton.Vegel@nrc.gov)
DRS Director (Roy.Caniano@nrc.gov)
DRS Deputy Director (Troy.Pruett@nrc.gov)
Senior Resident Inspector (Alfred.Sanchez@nrc.gov)
Resident Inspector (Jeffrey.Josey@nrc.gov)
Resident Inspector (Jeff.Rotton@nrc.gov)
Branch Chief, DRP/E (Jeff.Clark@nrc.gov)
Senior Project Engineer, DRP/E (Ray.Azua@nrc.gov)
ANO Administrative Assistant (Vicki.High@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Public Affairs Officer (Lara.Uselding@nrc.gov)
Project Manager (Kaly.Kalyanam@nrc.gov)
Branch Chief, DRS/TSB (Michael.Hay@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
OEMail Resource
File located: R:\REACTORS\ANO2010006 RFI - STG MLXX
SUNSI Rev Compl. ;Yes No ADAMS ;Yes No Reviewer Initials STG
Publicly Avail Yes ;No Sensitive Yes ; No Sens. Type Initials STG
RIV:DRS/EB2 C:DRS/ EB 2
SGraves NOkeefe/GAP for
/RA/ /RA/
05/10/2010 05/11/2010
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
ENCLOSURE
Triennial Fire Protection Inspection Documentation Request
Please provide the following documentation (items 1 - 4) prior to the onsite
information-gathering visit, preferably no later than July 19, 2010. Where practical, please
provide copies electronically.
1. The current version of your fire protection program and fire hazards analysis.
2. Post-fire safe shutdown analysis and the supporting calculations that demonstrate
acceptable plant response.
3. Copies of the licensing basis documents for fire protection (safety evaluation reports,
pertinent sections of the final safety analysis report, exemptions, deviations, letters
to/from the NRC regarding fire protection/fire safe shutdown, etc.).
4. The fire probabilistic risk assessment or portions of the plants individual plant
examination for external events report addressing fire events.
Please provide the following documentation (items 5 - 46) during the information-gathering
visit or by July 29, 2010, in order to support inspection preparation. Whenever practical,
please provide copies electronically. However, drawings should be provided as paper
copies of sufficient size that all details are legible.
5. Plant layout and equipment drawings for the selected fire areas (these areas will be
selected during the information gathering trip) that identify: (a) the physical plant
locations of major hot standby and cold shutdown equipment; (b) plant fire area and/or
fire zone delineation; and (c) the locations of fire protection equipment, such as
detection, suppression, and post-fire emergency lighting units; and (d) fire area
boundaries.
6. Fire protection program implementing procedures (e.g., administrative controls, operator
response procedures for fires, fire fighting procedures, etc.).
7. Operating procedures used for achieving and maintaining hot and cold shutdown
conditions from the control room in the event of a fire outside the control room (III.G.2
areas).
8. Operating procedure(s) used to implement an alternative shutdown (III.G.3 areas)
capability with or without control room evacuation.
9. Pre-fire plans for the selected fire areas (areas to be selected by the team during the
information-gathering trip).
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10. A list of equipment used to achieve and maintain hot standby and cold shutdowns in the
event of a fire (safe shutdown equipment lists).
11. Piping and instrumentation (flow) diagrams showing the components used to achieve
and maintain hot standby and cold shutdown for normal and alternate shutdown. Please
provide one copy of the piping and instrumentation (flow) diagrams for these systems of
a size sufficient to read all details. These should include the systems used for reactor
coolant system (RCS) makeup, RCS pressure control, decay heat removal, and
reactivity control, including the essential support systems.
12. A listing, with descriptions, of design change packages which were determined to impact
fire protection and post-fire safe shutdowns, performed in the last 3 years.
13. Copies of Generic Letter 86-10 evaluations performed in the last 3 years.
14. A listing of open and closed Condition Reports initiated in the last 3 years, which relate
to the fire protection program or equipment. Include Corrective Action Process
document number, date, and subject.
15. A listing of the applicable codes and standards (with the versions) related to the design
of plant fire protection features and evaluations of any code deviations. Copies of these
codes should be available for review.
16. Drawings of the portions of the emergency lighting system which support fire response.
17. Procedures used to remove smoke from safety-related areas and the engineering
studies or calculations which support the design basis.
18. Drawings of communication systems credited in the license basis for firefighting and
plant operations during fires where control room is occupied and/or evacuated.
19. Piping and instrumentation (flow) diagrams for the fire water and sprinkler systems.
20. A listing of maintenance and surveillance testing procedures for alternative shutdown
capability and fire barriers, detectors, pumps and suppression systems.
21. Maintenance rule performance criteria and a summary of the last 3 years performance
history for fire protection program systems or functions monitored within the
22. A copy of fire protection program requirements (e.g., limiting conditions for operation,
surveillance test requirements) covered by technical specifications, technical
requirements manual, updated final safety analysis report, or similar documents.
23. Copies of internal and external self-assessments, audits, peer-assessments or similar
reviews related to post-fire safe shutdown capability or the fire protection program
completed since December 3, 2007.
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24. A list of manual actions taken outside the control room which are credited to mitigate the
consequences of fires in III.G.2 areas (non-alternative shutdown areas). The list should
group actions by the initiating fire area or zone and indicate where the action must take
place.
25. Electronic copies of operator study guides (i.e., lesson plan text and graphics) or design
basis documents that describe the purpose/function/operating characteristics of the safe
shutdown systems (RCS makeup, RCS pressure control, decay heat removal, and
reactivity control, including the essential support systems).
26. Two copies of one-line diagrams of the electrical distribution system. These should
depict how power gets from the switchyard to the engineered safety feature loads (480V
and 4160V). Also, include the vital DC distribution system one-line diagrams.
27. A list of automatic and manually initiated gaseous fire suppression systems in the plant,
giving location and the key equipment being protected.
28. A list of repairs (and the procedure that controls the actions) needed to: a) reach and/or
maintain hot shutdown and b) reach and/or maintain cold shutdown.
29. A list of high to low pressure interface valves.
30. A copy of procedures governing the training and operation of the fire brigade.
31. Organization charts of site personnel down to the level of fire protection staff personnel.
32. A contact list of key site personnel who will be supporting this inspection, giving location
of their office and phone number onsite.
33. The team would like to observe an unannounced fire brigade drill in the plant, if possible,
during the week of August 23, 2010. Please put us in contact, during the onsite
information gathering trip, with the appropriate personnel for planning drills.
34. The team would like to perform a walkthrough of the procedure for control room
evacuation due to fire with qualified operators in the plant during the week of August 9,
2010. Please put us in contact, during the onsite information gathering trip, with the
appropriate personnel for planning the walkthrough.
The following documents involve B.5.b mitigating strategies.
35. A copy of the license condition that incorporated the requirements issued to address the
requirements of Section B.5.b of the ICM Order, EA-02-026, dated February 25, 2002,
and 10 CFR 50.54(hh)(2).
36. 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).
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37. A list of procedures/guidelines which 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.
38. 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.
39. A list of engineering evaluations/calculations that were used to verify engineering bases
for the mitigation strategies.
40. Copies of 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.
41. A list of modification packages and simplified drawings/descriptions of modifications that
were made to plant systems to implement the mitigation strategies.
42. Copies of procedure(s) used to inventory equipment (hoses, fittings, pumps, etc.)
required to be used to implement the mitigation strategies.
43. A list of B.5.b strategies, if any, which have implementing details that differ from that
documented in the submittals to the NRC and the safety evaluation report.
44. A copy of site general arrangement drawing(s) that show the majority of buildings/areas
referenced in B.5.b documents.
45. Training records/ training matrix/ lesson plans related to B.5.b.
46. Copies of Memoranda of Understanding (MOUs) (e.g., with local fire departments)
required to implement any mitigating strategies.
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