ML21020A068
| ML21020A068 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/20/2021 |
| From: | Scott Shaeffer NRC/RGN-II/DRS/EB2 |
| To: | Teresa Ray Duke Energy Carolinas |
| References | |
| IR 2021011 | |
| Download: ML21020A068 (6) | |
See also: IR 05000369/2021011
Text
January 20, 2021
Mr. Tom Ray
Site Vice President
Duke Energy Carolinas, LLC
McGuire Nuclear Station
12700 Hagers Ferry Road
Huntersville, NC 28078-8985
SUBJECT: MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - NOTIFICATION OF AN NRC
FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT
05000369/2021011 and 05000370/2021011) AND REQUEST FOR INFORMATION (RFI)
Dear Mr. Ray:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),
Region II staff will conduct a fire protection team inspection at the McGuire Nuclear Station,
Units 1 and 2, in March 2021. The inspection team will be led by Mr. Philipp Braaten, a Senior
Reactor Inspector from the NRC Region II Office. The inspection team will be comprised of four
inspectors from the NRC Region II office. The inspection will be conducted in accordance with
Inspection Procedure 71111, Attachment 21N.05, Fire Protection Team Inspection, the NRCs
baseline fire protection inspection procedure.
On January 12, 2021, during a telephone conversation between Joseph Hussey of your staff
and Mr. Braaten, our respective staffs confirmed arrangements for a two-week inspection. The
schedule for the inspection is as follows:
Week 1 of inspection: March 22 - 26, 2021
Week 2 of inspection: April 05 - 09, 2021
Given the ever changing and dynamic situation surrounding the COVID-19 pandemic, the NRC
staff and licensee staff will need to remain flexible regarding the conduct of the inspection. The
NRCs goal is to complete the baseline inspections in a smart and safe manner. The NRC staff
intends to use a mixture of remote inspection activities and limited and focused on-site
inspection activities. The exact details of onsite times will remain in flux until a period closer to
the inspection to ensure the activities are completed in a safe and efficient manner for all
parties.
The team lead and senior reactor analyst will work with your staff prior to the start of the
inspection to select the scope of structures, systems, and components for evaluation; identify
additional documents needed to support the inspection; and obtain unescorted access.
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 II office for team use in preparation for the inspection. Please send this
information so that it will arrive in the NRC Region II office by the dates listed in the enclosure
T. Ray
3
During the weeks leading up to the inspection, the team leader will discuss with your staff 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; (5) the
details for COVID-19 precautions and site policies for COVID-19 (masks, social distancing,
temperature checks, etc.).
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.
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 under 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.
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 Philipp Braaten, the team lead inspector, in the Region II office at (404) 997-4651 or
philipp.braaten@nrc.gov or me at (404) 997-4521.
Sincerely,
/RA/
Scott Shaeffer, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-369 & 50-370
Enclosures:
Fire Protection Team Inspection
Document Request
cc w/enclosure: via ListServ
OFFICE
RII:DRS/EB2
RII:DRS/EB2
NAME
P. Braaten
S. Shaeffer
DATE
1/20/2021
1/20/2021
Fire Protection Team Inspection Document Request
Enclosure
The initial request for information (i.e., first RFI) concentrates on providing the inspection team
with the general information necessary to select appropriate samples to develop a site-specific
inspection plan. The first RFIs requested information is specified below in items A.1 thru A.22,
and is requested to be provided by February 15, 2021, or sooner, to facilitate the selection of
the specific items that will be reviewed during the onsite inspection weeks.
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 in the NRCs regional office.
If a secure document management service is utilized, it is recommended that a separate folder
be used corresponding to each item listed below. Documents should be identified by both
document number and name. Electronic media on compact disc or paper records (hard copy)
are also acceptable.
The inspection team will examine the returned documentation from the first RFI and
identify/select specific samples to provide a more focused follow-up request to develop the
second RFI. The inspection team will submit the specific selected samples to your staff by
February 24, 2021. We request that the additional information provided from the second RFI be
made available by March 12, 2021.
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
of 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.
A.
DESIGN AND LICENSING BASIS DOCUMENTS
A.1
The current version of the Fire Protection Program and Fire Hazards
Analysis
A.2
Post-fire safe shutdown analysis (or Post-fire Nuclear Safety Capability,
Systems, and Separation Analysis Fire if NFPA 805 licensing basis) and the
supporting calculations that demonstrate acceptable plant response.
A.3
(If NFPA 805 licensing basis) Fire PRA Summary Report, and list of Fire
PRA calculations
(If Appendix R licensing basis) Portions of the plants individual plant examination
for external events (IPEEE) report addressing fire events. Also, include the
results of any post-IPEEE reviews and listings of actions taken/plant
modifications conducted in response to IPEEE information that relate to fire risk
A.4
(If NFPA 805 licensing basis) NFPA 805 Transition Report, developed in
accordance with NEI 04-02
2
(If Appendix R licensing basis) 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.)
A.5
List of post-fire safe shutdown systems and components (i.e., safe
shutdown equipment list).
A.6
List of fire areas with automatic fire suppression systems
A.7
List, with descriptions, of design change packages performed since the
last fire protection team inspection associated with fire protection or post-fire safe
shutdown systems.
A.8
List, with descriptions, of any fire protection program changes and
evaluations (not limited to Generic Letter 86-10 evaluations) performed since the
last fire protection team inspection
A.9
Fire Protection System(s) Design Basis Document.
A.10
List of applicable NFPA codes and standards and issuance dates (i.e.,
codes of record).
A.11
A list or document identifying any deviations from the NFPA codes of
record.
A.12
Facility Operating License.
A.13
Technical Specifications (electronic format only).
A.14
Updated Final Safety Analysis Report (electronic format only).
A.15
COPY of NRC Safety Evaluation Reports that form the licensing basis for:
- Post-fire Nuclear Safety Capability.
A.16
COPY of NRC approved exemptions for plant fire protection and post-fire
nuclear safety capability features.
A.17
COPY of exemption requests submitted but not yet approved for plant fire
protection and post-fire nuclear safety capability features.
A.18
LIST of nuclear safety capability design changes completed in the last
three years (including their associated 10 CFR 50.59 and NFPA 805 plant change
evaluations).
A.19
List of the top 25 highest fire CDF scenarios for each unit
A.20
List of the top 25 highest fire LERF scenarios for each unit
3
A.21
From your most recent PRA including external events and fires:
a.
Two risk rankings of components from your site-specific PRA: one sorted
by Risk Achievement Worth (RAW), and the other sorted by Birnbaum
Importance
b.
A list of the top 500 cut-sets
A.22
Copy of the Quality Assurance Program Manual (including specific fire
protection QA manual, if applicable)