ML17249A826
| ML17249A826 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/05/2017 |
| From: | Alan Dahbur Engineering Branch 3 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2017010 | |
| Download: ML17249A826 (10) | |
See also: IR 05000373/2017010
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, IL 60532-4352
September 5, 2017
Mr. Bryan C. Hanson
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2NOTIFICATION OF NRC
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR
INFORMATION 05000373/2017010; 05000374/2017010
Dear Mr. Hanson:
On October 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) will begin a Triennial
Fire Protection Baseline Inspection at your LaSalle County Station, Units 1 and 2. This
inspection will be performed in accordance with Inspection Procedure (IP) 71111.05T,
the NRCs Baseline Fire Protection IP.
Changes were made to the IP 71111.05T which now requires the Fire Protection Inspection
to review your actions to mitigate postulated events that could potentially cause loss of large
areas of power reactor facilities due to explosions or fires. This requirement was implemented
by the issuance of the Interim Compensatory Measures Order EA-02-026, Section B.5.b,
and the subsequent requirements of Title 10 of the Code of Federal Regulations (CFR),
Part 50.54(hh)(2), which are collectively referred to as B.5.b requirements. During this
inspection, the B.5.b requirements review will be performed during the first onsite week of
the inspection starting on November 1, 2017.
The schedule for the onsite inspection activity is as follows:
Information Gathering Visit: October 30, 2017;
B.5.b Requirements: November 1-3, 2017; and
Fire Protection Inspection: November 13-17, 2017, and
November 27-December 1, 2017.
The purpose of the information gathering visit is: (1) to obtain information and documentation
needed to support the inspection; (2) to become familiar with the LaSalle Fire Protection
Programs, fire protection features, post-fire safe shutdown capabilities, and plant layout; and
(3) to arrange administrative details, such as office space, availability of knowledgeable office
personnel and to ensure unescorted site access privileges.
B. Hanson -2-
Experience has shown that the Baseline Fire Protection Inspections are extremely resource
intensive both for the NRC inspectors and the licensee staff. In order to minimize the inspection
impact on the site and to ensure a productive inspection for both organizations, we have
enclosed a request for documents needed for the inspection. These documents have been
divided into four groups.
The first group lists information necessary to aid the inspection team in
choosing specific focus areas for the inspection. It is requested that this
information be provided to the lead inspector via mail or electronically no
later than October 20, 2017.
The second group also lists information and areas for discussion necessary to
aid the inspection team in choosing specific fire protection focus areas for the
inspection and to ensure that the inspection team is adequately prepared for the
inspection. It is requested this information be available during the information
gathering visit on October 30, 2017.
The third group of requested documents consists of those items that the
team will review, or need access to, during the inspection. Please have this
information available by the first day of the second onsite inspection week of
November 13, 2017.
The fourth group lists the information necessary to aid the inspection team in
tracking issues identified as a result of the inspection. It is requested that this
information be provided to the lead inspector as the information is generated
during the inspection.
It is important that all of these documents are up to date and complete in order to minimize the
number of additional documents requested during the preparation and/or the onsite portions of
the inspection.
The lead inspector for this inspection is Mr. Alan Dahbur. We understand that our
regulatory contact for this inspection is Mr. Terry Lanc of your organization. If there are
and questions about the inspection or the material requested, please contact the lead
inspector at 630-829-9810, or via e-mail at Alan.Dahbur@nrc.gov.
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.
B. Hanson -3-
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.
Sincerely,
/RA/
Alan Dahbur, Senior Reactor Inspector
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50-373; 50-374
Enclosure:
Triennial Fire Protection Baseline
Inspection Document Request
cc: Distribution via LISTSERV
B. Hanson -4-
Letter to Bryan C. Hanson from Alan Dahbur dated September 5, 2017
SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2NOTIFICATION OF NRC
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR
INFORMATION 05000373/2017010; 05000374/2017010
DISTRIBUTION:
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Cynthia Pederson
DRPIII
DRSIII
ADAMS Accession Number ML17249A826
OFFICE RIII RIII RIII RIII
NAME ADahbur:cl
DATE 09/05/17
OFFICIAL RECORD COPY
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
Inspection Report: 05000373/2017010 AND 05000374/2017010
Onsite Inspection Dates: October 30, 2017 (Information Gathering Visit)
November 1-3, 2017 (B.5.b Requirements)
November 13-17, 2017 (Fire Protection Inspection)
November 27-December 1, 2017 (Fire Protection Inspection)
Inspection Procedures: IP 71111.05T, Fire Protection (Triennial)
IP 71152, Identification and Resolution of Problems
Inspectors: Alan Dahbur
Senior Reactor Inspector (Lead)
630-829-9810
Alan.Dahbur@nrc.gov
Senior Reactor Inspector Reactor Inspector
630-829-9824 630-829-9831
Atif.Shaikh@nrc.gov Jasmine.Gilliam@nrc.gov
I. Information Requested Prior To the Information Gathering Visit:
The following information is requested by October 20, 2017. If you have any
questions regarding this request, please call the lead inspector as soon as possible. All
information should be sent to Mr. Alan Dahbur (e-mail address Alan.Dahbur@nrc.gov).
Electronic media is preferred. The preferred file format is a searchable pdf file on a
compact disk (CD). The CD should be indexed and hyper-linked to facilitate ease of
use, if possible. Please provide four copies of each CD submitted (one for each
inspector).
1. The most risk-significant fire areas as determined by probabilistic risk analyses, if
available. Otherwise, the reactor plant's Individual Plant Examination for External
Events for fire and results of any post-Individual Plant Examination for External
Events reviews for fire.
2. A copy of the current version of the Fire Protection Program, fire hazards
analysis, safe shutdown analysis, Updated Safety Analysis Report, technical
specifications, license (including the fire protection license condition), and
technical requirements manual or equivalent for fire protection structures,
systems, and components.
3. A list of fire areas requiring alternative shutdown capability, (i.e., those areas for
which Title 10 of the Code of Federal Regulations (CFR), Part 50, Appendix R,
Section III G, requirements are satisfied under Section III.G.3), or where both
safe shutdown trains can be affected.
Enclosure
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
4. Plant operating procedures which would be used and describe shutdown for a
postulated fire (for both areas requiring alternative shutdown and areas which do
not require alternative shutdown). Only those procedures with actions specific to
shutdown in the event of a fire need be included. In addition, please include
those procedures which operators would use for initial response to a fire, such as
annunciator or alarm response procedures, the procedure used for activating the
fire brigade, and the procedure which directs operators to the applicable safe
shutdown procedure.
5. Analysis performed in support of plant evaluation regarding multiple spurious
operation (MSO), which includes the following:
a. List of identified multiple spurious fire-induced circuit failure configurations.
b. List of the generic and plant specific MSOs.
c. Results of expert panel process and associated review/evaluation of the
generic and plant specific MSOs and existing safe shutdown analysis.
d. Evaluations and corrective actions taken for resolution of MSO issues.
II. Information Requested During the Information Gathering Visit (October 30, 2017):
The following information is requested to be provided to the inspection team during the
onsite information gathering visit. Except for Item 8, it is requested that the following
information be provided on four sets of CDs (searchable, if possible) with the B.5.b
Mitigating Strategies information (Items 8.a through 8.h) provided on one separate CD.
In addition, one set of hard copy drawings are requested for Items 4.a. through 4.d.
1. One set of hard-copy documents for facility layout drawings which identify plant
fire area delineation; areas protected by automatic fire suppression and
detection; and locations of fire protection equipment.
2. Licensing Information:
a. All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)
applicable to fire protection (specifically including those SERs referenced by
the plant fire protection license condition) and all licensing correspondence
referenced by the SERs;
b. All licensing correspondence associated with the comparison to Standard
Review Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing
purposes;
c. Exemptions from 10 CFR 50.48 and 10 CFR Part 50, Appendix R, and
associated licensing correspondence;
d. All licensing correspondence associated with those sections of
10 CFR Part 50, Appendix R, that are not applicable to the plant under
10 CFR 50.48(b)(1). Specifically, the licensing correspondence associated
with those fire protection features proposed or implemented by the licensee
that have been accepted by the NRC staff as satisfying the provisions of
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TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
Appendix A to Branch Technical Position APCSB 9.5-1 reflected in
the NRC fire protection SERs issued before February 19, 1981,
(10 CFR 50.48(b)(1)(i)); or those fire protection features, which were
accepted by the NRC staff in comprehensive fire protection SERs issued
before Appendix A to Branch Technical Position APCSB 9.5-1 was published
in August 1976 (10 CFR 50.48(b)(1)(ii)); and
e. The Final Safety Analysis Report sections applicable to fire protection, fire
hazards analysis, and safe shutdown analysis in effect at the time of original
licensing.
3. Fire Protection Program:
a. A listing of changes made to the Fire Protection Program since the last
Triennial Fire Protection Inspection;
b. A listing of the protection methodologies identified under 10 CFR Part 50,
Appendix R,Section III.G used to achieve compliance for selected fire
zones/areas (to be determined during information gathering visit). That is,
please specify whether 3-hour rated fire barriers; (Section III.G.2.a), 20 foot
separation along with detection and suppression; (Section III.G.2.b), 1-hour
rated fire barriers with detection and suppression; (Section III.G.2.c), or
alternative shutdown capability; (Section III.G.3) is used as a strategy for
each selected fire zone/area;
c. A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe-
shutdown evaluations);
d. A list of applicable codes and standards related to the design of plant fire
protection features. The list should include National Fire Protection
Association code versions committed to (i.e., the National Fire Protection
Association Codes of Record); and
e. List of plant deviations from code commitments and associated evaluations.
4. Facility Information:
a. Piping and instrumentation (flow) diagrams showing the components used to
achieve and maintain hot standby and cold shutdown for fires outside the
control room, those components used for those areas requiring alternative
shutdown capability, and systems relied upon for B.5.b mitigation strategies.
These can be of the type that are used for training;
b. One-line schematic drawings of the electrical distribution system for 4160
Volts alternating current (Vac) down to 480Vac;
c. One-line schematic drawings of the electrical distribution system for 250 Volts
direct current and 125 Volts direct current systems as applicable;
d. Logic diagrams showing the components used to achieve and maintain hot
standby and cold shutdown; and
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TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
e. Safe shutdown cable routing database (requested electronically, such as on
compact disc, if available).
5. Operations Response for Fire Protection:
a. Pre-fire plans for selected fire zones/areas (to be determined during
information gathering visit);
b. Plant operating procedures which specify the initial operations response to a
fire alarm or annunciator; and
c. Procedure for calling out the fire brigade and requesting off-site assistance.
6. Corrective Actions:
a. Listing of open and closed Fire Protection Condition Reports (i.e., problem
identification forms and their resolution reports) since the date of the last
Triennial Fire Protection Inspection; and
b. List of current fire impairments, including duration.
7. General Information:
a. A listing of abbreviations and/or designators for plant systems;
b. Organization charts of site personnel down to the level of fire protection staff
personnel; and
c. A phone list for onsite licensee personnel.
8. B.5.b Mitigating Strategies:
a. 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);
b. Copies of procedures/guidelines that were revised or generated to implement
the mitigation strategies. These could be extensive damage mitigation
guidelines, severe accident management guidelines, emergency operating
procedures, abnormal operating procedures, etc.;
c. 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;
d. A listing of engineering evaluations/calculations that were used to verify
engineering bases for the mitigation strategies;
e. Copies of procedures used to inventory equipment (hoses, fittings, pumps,
etc.) required to be used to implement the mitigation strategies;
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TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
f. A list of B.5.b mitigating strategies, if any, which have implementing details
that differ from that documented in the submittals and the SER;
g. Copies of Memoranda of Understanding (e.g., with local fire departments)
required to implement any mitigating strategies; and
h. A list of changes made to B.5.b mitigating strategies and associated
procedures since the previous NRC inspection of B.5.b mitigating strategies
(June 16, 2014).
9. Onsite Discussions:
In addition, during the information gathering visit, it is requested that licensee
staff be available for the following:
a. Informal discussion on plant procedures operators would use in the event of
fire or explosion (including B.5.b mitigation strategies) and under what
conditions would the plant be shutdown using alternative shutdown
methodology;
b. Informal discussion on the plants safe shutdown cable routing database and
the plant-wide cable routing database, as applicable; and
c. A tour of alternative shutdown and risk-significant fire areas.
d. A discussion of scheduling of fire drills which may occur during the inspection
so that the inspectors may be able to observe a fire drill, if possible.
III. Information Requested to be Available on first Day of the Second Onsite
Inspection Week (November 13, 2017):
The following information is requested to be provided on the first day of inspection. It is
requested that this information be provided on four sets of CDs (searchable, if possible).
1. Program Procedures:
a. Procedures for:
i. Administrative controls (such as allowed out of service times and
compensatory measures) for fire protection systems and components
ii. Control of transient combustibles
iii. Control of hot work
b. List of maintenance and surveillance testing procedures for alternative
shutdown capability and fire barriers, detectors, pumps, and suppression
systems; and
c. List of maintenance procedures which routinely verify fuse breaker
coordination in accordance with the post-fire safe shutdown coordination
analysis.
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TRIENNIAL FIRE PROTECTION BASELINE INSPECTION DOCUMENT REQUEST
2. Design and Equipment Information:
a. Coordination calculations and/or justifications that verify fuse/breaker
coordination for selected fire zones/areas (to be determined during
information gathering visit) that are fed off of the same electrical buses as
components in the protected safe shutdown train;
b. Copies of significant fire protection and post-fire safe shutdown related
design change package descriptions (including their associated 10 CFR
50.59 evaluations) and Generic Letter 86-10 (or adverse to safe shutdown)
evaluations;
c. Gaseous suppression system pre-operational testing, if applicable, for
selected fire zones/areas (to be determined during information gathering
visit);
d. Hydraulic calculations and supporting test data which demonstrate operability
for water suppression systems, if applicable, for selected fire zones/areas (to
be determined during information gathering visit);
e. Alternating current coordination calculations for 4160Vac down to 480Vac
electrical systems; and
f. List of all fire protection or Appendix R calculations.
3. Assessment and Corrective Actions:
The three most recent fire protection Quality Assurance audits and/or fire
protection self-assessments.
IV. Information Requested to Be Provided Throughout the Inspection:
1. Copies of any corrective action documents generated as a result of the
inspection teams questions or queries during this inspection.
2. Copies of the list of questions submitted by the inspection team members and
the status/resolution of the information requested (provided daily during the
inspection to each inspection team member).
If you have questions regarding the information requested, please contact the lead inspector.
6