ML19043A801
| ML19043A801 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/12/2019 |
| From: | John Robbins Engineering Branch 3 |
| To: | Bezilla M FirstEnergy Nuclear Operating Co |
| References | |
| IR 2019011 | |
| Download: ML19043A801 (9) | |
See also: IR 05000346/2019011
Text
February 12, 2019
Mr. Mark Bezilla
Site Vice President
FirstEnergy Nuclear Operating Co.
Davis-Besse Nuclear Power Station
5501 N. State Rte. 2, Mail Stop A-DB-3080
Oak Harbor, OH 43449-9760
SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1NOTIFICATION OF NRC
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR
INFORMATION; INSPECTION REPORT 05000346/2019011
Dear Mr. Bezilla:
On April 1, 2019, the U.S. Nuclear Regulatory Commission (NRC) will begin a Triennial Fire
Protection Baseline Inspection at your Davis-Besse Nuclear Power Station. This inspection will
be performed in accordance with Inspection Procedure 71111.05T, the NRCs Baseline Fire
Protection Inspection Procedure.
Changes were made to the Inspection Procedure 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,
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 April 1, 2019.
The schedule for the onsite inspection activity is as follows:
- Information Gathering Visit and B.5.b Requirements: April 1-5, 2019;
- Fire Protection Inspection: April 15-19, 2019; and
- Fire Protection Inspection: April 29, 2019, through May 3, 2019.
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 Davis-Besse Stations 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.
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.
M. Bezilla -2-
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 March 18, 2019. 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 April 1, 2019. 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 April 29, 2019. 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. John Robbins. We understand that our regulatory
contact for this inspection is Ms. Gwen Ellithorpe of your organization. If there are any
questions about the inspection or the material requested, please contact the lead inspector
at 630-829-9744, or via e-mail at John.Robbins@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.
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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,
Exemptions, Requests for Withholding.
Sincerely,
/RA/
John Robbins, Reactor Inspector
Engineering Branch 3
Division of Reactor Safety
Docket No. 50-346 and 72-014
License No. NPF-3
Enclosure:
Document Request for Triennial Fire
Protection Baseline Inspection
cc: Distribution via LISTSERV
M. Bezilla -3-
Letter to Mark Bezilla from John Robbins dated February 12, 2019.
SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1NOTIFICATION OF NRC
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR
INFORMATION; INSPECTION REPORT 05000346/2019011
DISTRIBUTION:
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ADAMS Accession Number: ML19043A801
OFFICE RIII
NAME JRobbins:cl
DATE 02/12/19
OFFICIAL RECORD COPY
DOCUMENT REQUEST FOR TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
Inspection Report: 05000346/2019011
Onsite Inspection Dates: April 1-5, 2019, Information Gathering Visit and
B.5.b Requirements
April 1519, 2019, Fire Protection Inspection
April 29, 2019 through May 3, 2019, Fire Protection Inspection
Inspection Procedures: 71111.05T, Fire Protection (Triennial)
71152, Identification and Resolution of Problems
Inspectors: John Robbins
Reactor Inspector (Lead)
630-829-9744
John.Robbins@nrc.gov
Senior Reactor Inspector Reactor Inspector
630-829-9824 630-829-9843
Atif.Shaikh@nrc.gov Ijaz.Hafeez@nrc.gov
I. Information Requested Prior To the Information Gathering Visit
The following information is requested by March 18, 2019. If you have any questions
regarding this request, please call the lead inspector as soon as possible. All
information should be sent to Mr. John Robbins (e-mail: John.Robbins@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 three 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, 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. 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).
Enclosure
DOCUMENT REQUEST FOR TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
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.
4. 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 (April 1, 2019)
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 three 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. For pre-1979 plants, all licensing correspondence associated with those
sections of 10 CFR Part50, Appendix R, that are not applicable to the plant
under 10 CFR Part 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 Appendix A to Branch Technical Position APCSB 9.5-1 reflected
in the NRC fire protection SERs issued before February 19, 1981,
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DOCUMENT REQUEST FOR TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
(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
Hazard 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. For pre-1979 plants, 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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DOCUMENT REQUEST FOR TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
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 offsite 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 Interim Compensatory Measures 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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DOCUMENT REQUEST FOR TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
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 safety evaluation
report;
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.
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 (April 29, 2019)
The following information is requested to be provided on the first day of inspection.
It is requested that this information be provided on three 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
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DOCUMENT REQUEST FOR TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
c. List of maintenance procedures which routinely verify fuse breaker
coordination in accordance with the post-fire safe shutdown coordination
analysis.
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:
a. The three most recent fire protection Quality Assurance audits and/or fire
protection self-assessments.
4. Any updates to information previously provided.
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.
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