ML15261A718
| ML15261A718 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/15/2015 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Davison K Northern States Power Co |
| References | |
| IR 2016008 | |
| Download: ML15261A718 (10) | |
See also: IR 05000282/2016008
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, IL 60532-4352
September 15, 2015
Mr. Kevin Davison
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company, Minnesota
1717 Wakonade Drive East
Welch, MN 55089
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE
INSPECTION REQUEST FOR INFORMATION 05000282/2016008;
Dear Mr. Davison:
On January 11, 2016, the U.S. Nuclear Regulatory Commission (NRC) will begin a
Triennial Fire Protection Baseline Inspection at your Prairie Island Nuclear Generating
Plant, 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 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
January 13, 2016.
The schedule for the onsite inspection activity is as follows:
Information Gathering Visit: January 11 - 13, 2016;
B.5.b Requirements: January 13 - 15, 2016; and
Fire Protection Inspection: January 25 - 29 and February 8 - 12, 2016.
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 Prairie Island 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.
K. Davison -2-
Experience has shown that the Baseline Fire Protection Inspections are extremely resource
intensive for both 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 December 11, 2015.
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, January 11, 2016.
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 January 25, 2016.
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. Dariusz Szwarc. We understand that our
regulatory contact for this inspection is Ms. Penny Oleson of your organization. If there are
any questions about the inspection or the material requested, please contact the lead inspector
at (630) 829-9803, or via e-mail at Dariusz.Szwarc@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.
K. Davison -3-
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy
of this letter, its enclosure, and your response (if any) will be available electronically for public
inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html
(the Public Electronic Reading Room).
Sincerely,
/RA/
Robert C. Daley, Chief
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50-282, 50-306
Enclosure:
Fire Protection Inspection Document Request
cc w/encl: Distribution via LISTSERV
NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
REQUEST FOR INFORMATION
Inspection Report: 05000282/2016008; 05000306/2016008
Onsite Inspection Dates: January 11 - 13, 2016 (Information Gathering Visit)
January 13 - 15, 2016 (B.5.b Requirements)
January 25 - 29, 2016 (Fire Protection Inspection)
February 8 - 12, 2016 (Fire Protection Inspection)
Inspection Procedures: IP 71111.05T, Fire Protection (Triennial)
IP 71152, "Identification and Resolution of Problems"
Inspectors: Dariusz Szwarc George Hausman
Senior Reactor Inspector (Lead) Senior Reactor Inspector
(630) 829-9803 (630) 829-9743
Dariusz.Szwarc@nrc.gov George.Hausman@nrc.gov
Mark Jeffers Robert Winter
Reactor Inspector Reactor Inspector
(630) 829-9798 (630) 829-9758
Mark.Jeffers@nrc.gov Robert.Winter@nrc.gov
I. Information Requested Prior To the Information Gathering Visit
The following information is requested by December 11, 2015. If you have any
questions regarding this request, please call the lead inspector as soon as possible.
All information should be sent to the lead inspector, Mr. Dariusz Szwarc, via e-mail
address Dariusz.Szwarc@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 (IPEEE) for fire, and results of any post-IPEEE reviews for fire.
2. A copy of the current version of the Fire Protection Program (FPP), Fire Hazards
Analysis (FHA), Safe Shutdown Analysis (SSA), Updated Safety Analysis Report
(USAR), technical specifications, license (including the fire protection license
condition), and Technical Requirements Manual (TRM) 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.
Enclosure
NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
REQUEST FOR INFORMATION
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 (January 11, 2016)
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. For pre-1979 plants, 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
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NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
REQUEST FOR INFORMATION
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 (BTP) 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 BTP APCSB
9.5-1 was published in August 1976 (10 CFR 50.48(b)(1)(ii)); and
e. The final safety analysis report (FSAR) sections applicable to fire protection,
FHA, and SSA in effect at the time of original licensing.
3. Fire Protection Program:
a. A listing of changes made to the FPP 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
(NFPA) code versions committed to (i.e., the NFPA 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 (Vdc) and 125Vdc systems as applicable;
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NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
REQUEST FOR INFORMATION
d. Logic diagrams showing the components used to achieve and maintain hot
standby and cold shutdown; and
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
(EDMGs), severe accident management guidelines (SAMGs), emergency
operating procedures (EOPs), abnormal operating procedures (AOPs), 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;
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NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
REQUEST FOR INFORMATION
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;
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 (MOUs) (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 (May 22, 2012).
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 (January 25, 2016)
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; and
iii. Control of hot work.
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NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
REQUEST FOR INFORMATION
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.
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 (GL) 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 (ac) 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.
6
K. Davison -3-
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy
of this letter, its enclosure, and your response (if any) will be available electronically for public
inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html
(the Public Electronic Reading Room).
Sincerely,
/RA/
Robert C. Daley, Chief
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50-282, 50-306
Enclosure:
Fire Protection Inspection Document Request
cc w/encl: Distribution via LISTSERV
DISTRIBUTION w/encl:
RidsNrrPMPrairieIsland Resource
RidsNrrDorlLpl3-1 Resource
RidsNrrDirsIrib Resource
Cynthia Pederson
DRPIII
DRSIII
ADAMS Accession Number ML15261A718
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To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
OFFICE RIII RIII RIII RIII
NAME DSzwarc:cl RDaley
DATE 09/14/15 09/15/15
OFFICIAL RECORD COPY