ML21286A713
| ML21286A713 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/15/2021 |
| From: | Sam Graves Division of Reactor Safety IV |
| To: | Dinelli J Entergy Operations |
| References | |
| IR 2022010 | |
| Download: ML21286A713 (10) | |
See also: IR 05000313/2022010
Text
Mr. John Dinelli, Site Vice President
Arkansas Nuclear One
Entergy Operations, Inc.
N-TSB-58
1448 S.R. 333
Russellville, AR 72802-0967
SUBJECT:
ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - NOTIFICATION OF AN NRC
FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT
05000313/2022010 AND 05000368/2022010) AND REQUEST FOR
INFORMATION
Dear Mr. Dinelli:
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 Arkansas Nuclear
One, Units 1 and 2, in January and February 2022. The inspection team will be comprised of
three reactor inspectors from the NRC Region IV office. The inspection will be conducted in
accordance with Inspection Procedure 71111.21N.05, Fire Protection Team Inspection (FPTI),
the NRCs baseline fire protection inspection procedure. The schedule for the inspection is as
follows:
Remote Inspection Planning Meetings:
January 11 - 12, 2022
Onsite inspection:
January 31 - February 4, 2022, and
February 14 - 18, 2022
The team lead will review the initial set of documents requested in the enclosure to select the
scope of structures, systems, and components for evaluation and identify additional documents
needed to support the inspection. The enclosure to this letter provides an initial list of the
documents the team lead will need for 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 the NRC Region IV office by
the dates listed in the enclosure.
During the remote inspection planning meeting(s), the team lead will also discuss the following
inspection support administrative details: (1) office space size and location; (2) specific
documents requested to be made available to the team in their office spaces; (3) arrangements
for reactor site access (including radiation protection training, security, safety, and fitness for
duty requirements); and (4) the availability of knowledgeable plant staff and licensing
organization personnel to serve as points of contact during the inspection.
October 15, 2021
J. Dinelli
2
We request that during the on-site inspection weeks you ensure that copies of analyses,
evaluations, or documentation regarding the implementation and maintenance of the station fire
protection program, including the success path necessary to achieve and maintain the nuclear
safety performance criteria, 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 (i.e., fire protection compliance assessment
documents). Also, personnel should be available at the site during the inspection who are
knowledgeable regarding those plant systems required to achieve and maintain safe and stable
plant conditions, including the electrical aspects of the nuclear safety capability assessment,
reactor plant fire protection systems and features, and the station fire protection program and its
implementation.
PAPERWORK REDUCTION ACT STATEMENT
This letter contains mandatory information collections that are subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)
approved these information collections (approval number 3150-0011). Send comments
regarding this information collection to the Information Services Branch, Office of the Chief
Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office
of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and
Budget, Washington, DC 20503.
PUBLIC PROTECTION NOTIFICATION
The NRC may not conduct nor 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 OMB control number.
This letter and its enclosure will be made available for public inspection and copying at
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
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 me, the team lead inspector, in the Region IV office at (817) 200-1102 or
samuel.graves@nrc.gov.
Sincerely,
Samuel Graves, Senior Reactor Inspector
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-313 and 50-368
Signed by Graves, Samuel
on 10/15/21
SUNSI Review
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By: STG
Yes No
Publicly Available
Sensitive
OFFICE
SRI: EB2
NAME
S. Graves
SIGNATURE
/RA/
DATE
10/15/2021
A1-1
Enclosure 1
Fire Protection Baseline Inspection Document Request
The documents and information requested below should generally be made available to the
inspection team prior to the inspection. Electronic format is the preferred format, except where
specifically noted. If electronic files are made available via a secure document management
service, then the remote document access must allow inspectors to download, save, and print
the documents.
If a secure document management service is utilized, it is recommended that a separate folder
be used corresponding to each item listed below. It is recommended that multiple documents
within each folder be individually entered and combined into a compressed (ZIP) file which is
uploaded into the same folder. Documents should be identified by both document number and
noun name. Electronic media on compact disc or paper records (hard copy) are also
acceptable.
Where ANSI C-size paper drawings are requested, please prepare two copies. Retain one copy
on site for the Teams use during the inspection weeks. Send one copy to the team leader at
the NRC Region IV office.
To allow review before the on-site information gathering visit, the documents requested in items
A.1 thru A.13 should be made available to the team no later than December 10, 2021.
Based on review of the documentation, the team leader will identify the scope for the inspection
prior to the end of the on-site information gathering visit or in-office review of the information
obtained.
This document request is based on typical documents that a generic plant might have. As such,
this generic document request is not meant to imply that any specific plant is required to have all
the listed documents. It is recognized that some documents listed below may not be available
for your plant. In addition, the document titles listed below are based on typical industry
document names; your plant-specific document titles may vary.
To allow review before the on-site inspection weeks, all requested documents should be made
available to the team no later than January 24, 2022.
A1-2
Enclosure 1
A.
DESIGN AND LICENSING BASIS DOCUMENTS
A.1
Post-fire Nuclear Safety Capability, Systems, and Separation Analysis
A.2
Fire Hazards Analysis and/or NFPA 805 Design Basis Document
A.3
Fire Probabilistic Risk Assessment (PRA) Summary Document or full PRA
Document
A.4
NFPA 805 Transition Report, developed in accordance with NEI 04-02
A.5
Fire Risk Evaluations (i.e., NFPA 805 Section 2.4.3)
A.6
Plant Change Evaluations (i.e., NFPA 805 Section 2.4.4)
A.7
Facility Operating License.
A.8
Technical Specifications (electronic format only).
A.9
Updated Final Safety Analysis Report (electronic format only).
A.10
A list of the ten most risk significant plant systems for core damage frequency
from the fire protection probabilistic risk assessment.
A.11
A list of the ten most risk significant plant systems for large early release
frequency from the fire protection probabilistic risk assessment.
A.12
Plant layout drawings which identify: (electronic format and C-size paper
drawings)
Plant fire area boundaries
Combustible control zone drawings
Areas protected by automatic fire suppression and detection
A.13
For recovery actions, provide the following:
Manual Action Feasibility Study
Operator Time Critical Action Program
Timelines for time-critical manual actions
Timeline validations
A1-3
Enclosure 1
B.
GENERAL PLANT DESIGN DOCUMENTS
B.1
Piping and instrumentation diagrams (P&IDs) and legend list for components
used to achieve and maintain post-fire safe shutdown for the sample systems or
fire areas selected (electronic format and C-size paper drawings).
B.2
Piping and instrumentation diagrams and legend list for fire protection systems,
including the fire water supply; water suppression sprinklers; and deluge,
gaseous suppression systems for the sample systems or fire areas selected
(electronic format and C-size paper drawings).
B.3
AC and DC electrical system single line diagrams, from off-site power down to
the highest safety-related bus level (typically 4kV, EDG bus) (electronic format
and C-size paper drawings).
B.4
Single line diagrams for motor control centers (MCCs) that supply post-fire
nuclear safety component loads for the sample systems or fire areas selected
(electronic format and C-size paper drawings).
B.5
Equipment location drawings which identify the physical plant locations of post-
fire safety shutdown equipment for the sample systems or fire areas selected
(electronic format and C-size paper drawings).
C.
CLASSIC FIRE PROTECTION
C.1
Copy of fire protection program implementing procedures (e.g., administrative
controls, surveillance testing, and fire brigade).
C.2
List, with descriptions, of calculations and engineering analyses, studies, or
evaluations for the fire protection system, including the fire water system.
C.3
Last two completed surveillances of fire protection features for the sample
systems or features within the fire areas selected (detection, suppression,
damper inspections, damper tests, penetration inspections, barrier inspections,
etc.).
C.4
List, with descriptions, of routine tests, surveillances, and preventive
maintenance on fire pumps, including pump controllers and batteries.
C.5
Last two completed annual fire pump pressure and flow tests with a complete
copy of the test procedure.
C.6
Last two completed monthly and/or quarterly fire pump tests with a complete
copy of the test procedure.
C.7
Last two completed fire water system flow tests and flushes with a complete copy
of the test procedure.
C.8
For Fire Brigade Drills, provide the following:
Last five fire brigade drill critiques
A1-4
Enclosure 1
Last drill critique for a drill with off-site fire department support
Last unannounced drill critique
Last back-shift drill critique
Dates, shifts, and locations of unannounced drills for last three years
Summary of any unsatisfactory drill performance items for last three years
Last unannounced drill critique by a qualified individual independent of the
licensees staff
C.9
For fire brigade equipment provide the following:
Procedure for inventory and inspection
Most recent inspection and inventory results
C.10
Fire Brigade Qualifications, including self-contained breathing apparatus, (SCBA)
and training lesson plans.
C.11
Copy of the evaluation or analysis of the effects of fire suppression activities on
the ability to achieve the nuclear safety performance criteria for the sample
systems or fire areas selected demonstrating:
The automatic or manually actuation of a suppression system, due to a fire in
a single location, will not indirectly cause damage to the success path
The inadvertent actuation or rupture of a suppression system will not
indirectly cause damage to the success path
Adequate drainage for areas protected by water suppression systems
The hydrostatic rating of any floor penetration seals installed within the fire
areas that are credited with keeping water from leaking into fire areas below
C.12
Pre-fire plans for all fire areas.
C.13
Impairment Log (at start of inspection) for fire protection features that are out of
service.
C.14
List of penetration seal work, re-work, or installation activities, in the last three
years.
C.15
List of fire wrap work, re-work, or installation activities, in the last three years.
C.16
Fire protection system health reports for the two most recent quarters.
C.17
Fire protection program health reports for the two most recent quarters.
C.18
Licensee evaluations of industry operating experience concerning fire protection
issues completed in the last three years.
C.19
List of fire event analysis reports for the last three years.
A1-5
Enclosure 1
C.20
Fire protection program requirements (e.g., limiting conditions for operation,
surveillance test requirements) covered by technical specifications, the technical
requirements manual, the updated final safety analysis report, procedures, or
similar documents.
C.21
Fire Protection System(s) Design Basis Document.
C.22
List of applicable NFPA codes and standards and issuance dates (i.e., codes of
record).
C.23
A list or document identifying any deviations from the NFPA codes of record.
C.24
Organization charts of site personnel down to the level of fire protection staff
personnel.
C.25
A contact list of key site personnel who will be supporting this inspection, giving
the office location and phone number.
C.26
The team would like to perform a walkdown of the sample fire protection systems
and/or fire areas with fire protection personnel in the plant during the week of
January 31, 2022. Please put us in contact with the appropriate personnel for
planning the walkdowns during the remote inspection planning meetings.
D.
ELECTRICAL
D.1
Electrical system health reports for the two most recent quarters.
D.2
Surveillance procedures and last surveillance demonstrating operability of
components required for alternative shutdown.
E.
OPERATIONS
E.1
The team would like to perform a walkthrough of a sample of post-fire safe
shutdown procedures with qualified operators in the plant during the week of
January 31, 2022. Please put us in contact with the appropriate personnel for
planning the walkthroughs during the remote inspection planning meetings.
E.2
List, with descriptions, of licensed operator Job Performance Measures (JPMs)
for operator actions required to achieve and maintain post-fire safe shutdown.
E.3
List, with descriptions, of non-licensed operator training associated with non-
licensed operator actions to achieve and maintain post-fire nuclear safe
shutdown (including JPMs, in-field training walkdowns, simulations, or initial
qualification).
E.4
Lesson plans for post-fire safe shutdown training for licensed and non-licensed
operators.
E.5
Thermal hydraulic calculation or analysis that determines the time requirements
for time-critical manual operator actions.
A1-6
Enclosure 1
E.6
Operating procedures to achieve and maintain post-fire safe shutdown from the
control room and requiring a control room evacuation.
E.7
For safe shutdown equipment and tools, provide the following:
Procedure for inventory and inspection
Most recent inspection and inventory results
E.8
List, with descriptions, of procedures that implement cold shutdown repairs.
E.9
For cold shutdown repairs, if required, provide the following:
Procedure for inventory and inspection (i.e., needed tools, material, etc.)
Most recent inspection and inventory results
F.
ADMINISTRATIVE CONTROL, OVERSIGHT, AND CORRECTIVE ACTION
PROGRAMS
F.1
Copies of procedures that control the configuration of the fire protection program,
features, and post-fire safe shutdown methodology and system design. Also,
copies of procedures that govern the implementation of plant modifications,
maintenance, and special operations and their impact on fire protection.
F.2
List of open and closed condition reports for the fire protection systems for the
last three years.
F.3
List of open and closed condition reports associated with the post-fire safe
shutdown analysis for the last three years.
F.4
List of open and closed condition reports associated with operator actions to
achieve and maintain post-fire safe shutdown for the last three years.
F.5
List of open and closed condition reports associated with the fire protection
program including plant change evaluations, post-fire operating procedures
and/or training, timeline evaluations for operator actions, and supporting
engineering evaluations, analysis, or calculations for the last three years.
F.6
List of open and closed condition reports for emergency lighting units for the last
three years.
F.7
Self-assessments, peer assessments, and audits of fire protection activities for
the last three years.
F.8
Self-assessments, peer assessments, and audits of post-fire nuclear safety
capability methodology for the last three years.
F.9
Provide administrative procedures that control temporary modifications,
permanent plant changes, design changes, procedure changes, aging
management changes, equivalency evaluations, suitability analyses,
A1-7
Enclosure 1
calculations, commercial grade dedication, safety-security interface, and repairs.
F.10
Provide procedures that control the following: combustible controls, hot work,
monitoring, compensatory measures, and work-arounds.
F.11
Last five hot work permits (at power).
F.12
Last five transient combustible permits (at power).
G.
Aging Management Program
G.1
Copies of the aging management programs applicable to fire protection including
but not limited to the following:
Fire Protection
Fire Water System
Aboveground Metallic Tanks
Buried and Underground Piping and Tanks
G.2
Copies of procedures, work orders, preventive maintenance tasks, or other
documents which implement the commitments made as part of the license
extension related to fire protection.
G.3
List of aging management activities related to fire protection performed to date.