ML20265A042
| ML20265A042 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/21/2020 |
| From: | Nick Taylor NRC/RGN-IV/DRS/EB-2 |
| To: | Peters K Vistra Operations Company |
| References | |
| IR 2020011 | |
| Download: ML20265A042 (17) | |
See also: IR 05000445/2020011
Text
September 21, 2020
Mr. Ken Peters
Senior Vice President and Chief Nuclear Officer
Vistra Operations Company LLC
P.O. Box 1002
Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT - TRIENNIAL FIRE
PROTECTION INSPECTION REPORT 05000445/2020011 AND
05000446/2020011 AND NOTICE OF VIOLATION
Dear Mr. Peters:
On August 27, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at Comanche Peak Nuclear Power Plant and discussed the results of this inspection with
Mr. T. McCool, Site Vice President, and other members of your staff. The results of this
inspection are documented in the enclosed report.
Enclosure 2 discusses a violation associated with a finding of very low safety significance
(Green). The NRC evaluated this violation in accordance Section 2.3.2 of the NRC
Enforcement Policy, which can be found at http://www.nrc.gov/about-
nrc/regulatory/enforcement/enforce-pol.html. We determined that this violation did not meet the
criteria to be treated as a non-cited violation because your staff did not restore compliance
within a reasonable period of time after a violation was previously identified by the NRC as
NCV 05000445/2017008-01; 05000446/2017008-01.
The NRC has concluded that information regarding: (1) the reason for the violations; (2) the
corrective actions that have been taken and the results achieved; and (3) the date when full
compliance was achieved is already adequately addressed on the docket in the inspection
report (Enclosure 2). Therefore, you are not required to respond to this letter unless the record
does not accurately reflect your corrective actions or your position. In that case, or if you
choose to provide additional information, you should follow the instructions specified in the
Notice of Violation (Enclosure 1).
If you contest the violation or the significance or severity of the violation documented in this
inspection report, you should provide a response within 30 days of the date of this inspection
report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional
Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector
at Comanche Peak Nuclear Power Plant.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a
response within 30 days of the date of this inspection report, with the basis for your
K. Peters
2
disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk,
Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the
NRC Resident Inspector at Comanche Peak Nuclear Power Plant.
This letter, its enclosures, and your response (if any) 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 2.390, Public
Inspections, Exemptions, Requests for Withholding.
Sincerely,
Nicholas H. Taylor, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 05000445 and 05000446
License Nos. NPF-87 and NPF-89
Enclosures:
2. Inspection Report
cc w/ encl: Distribution via LISTSERV
Nicholas
H. Taylor
Digitally signed by
Nicholas H. Taylor
Date: 2020.09.21
08:19:02 -05'00'
X
SUNSI Review
X
Non-Sensitive
Sensitive
X
Publicly Available
Non-Publicly Available
OFFICE
SRI:EB2
SRI:EB2
RI:EB2
C:PBB
TL:ACES
D:DRA
C:EB2
NAME
JMateychick
JDrake
SAlferink
NOKeefe
JGroom
RLantz
NTaylor
SIGNATURE
/RA/
/RA/
/RA/
/RA/
/RA/
/RA/
/RA/
DATE
9/11/2020
9/13/2020
9/14/2020
9/8/2020
9/8/2020
9/17/2020
9/21/2020
Enclosure 1
Vistra Operations Company LLC
Comanche Peak Nuclear Power Plant,
Units 1 and 2
Docket Nos.: 05000445 and 05000446
License Nos.: NPF-87 and NPF-89
During an NRC inspection completed on August 27, 2020, a violation of NRC requirements was
identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
License Condition 2.G for Unit 1 requires, in part, that the licensee implement and
maintain in effect all provisions of the approved fire protection program as described in
the Final Safety Analysis Report through Amendment 78 and as approved in the Safety
Evaluation Report and its supplements through Supplement 24.
License Condition 2.G for Unit 2 requires, in part, that the licensee implement and
maintain in effect all provisions of the approved fire protection program as described in
the Final Safety Analysis Report through Amendment 87 and as approved in the Safety
Evaluation Report and its supplements through Supplement 27.
The Fire Protection Report was included as part of the licensees approved fire
protection program for both units. Section I-2.4 states, in part, that administrative control
of the fire protection program is provided through station procedures to ensure that the
fire protection systems and equipment are operable and properly maintained and
operational at all times. Section IV-2.1.c.1 requires, in part, that the required fire rated
assemblies and penetration sealing devices are confirmed operable by visually
inspecting the exposed surfaces using a site approved sampling plan every 18 months.
Contrary to this requirement, from 2009 to June 25, 2020, the licensee failed to ensure
that fire protection program procedures used to establish inspection criteria for
penetration sealing devices appropriately captured all required penetration sealing
devices for visual inspection using a site approved sampling plan every 18 months.
Specifically, Procedure FIR-310, Penetration Seal Inspection, revised in response to
NCV 05000445/2017008-01; 05000446/2017008-01, Failure to Implement and Maintain
Adequate Inspection Procedures for Penetration Sealing Devices, did not ensure that all
required penetration sealing devices would be inspected within the licensees sampling
plan interval. Consequently, the licensee failed to restore compliance to the previous
NCV since the revised procedure did not ensure the fire rated penetration seals in the
auxiliary building were included in the maintenance list so they would be scheduled for
inspection.
This violation is associated with a Green SDP finding.
2
The NRC has concluded that information regarding the reason for the violation, the corrective
actions taken to correct the violation and prevent recurrence and the date when full compliance
was achieved is already adequately addressed in the enclosed inspection report (Enclosure 2).
However, you are required to submit a written statement or explanation pursuant to
10 CFR 2.201 if the description therein does not accurately reflect your corrective actions or
your position. In that case, or if you choose to respond, clearly mark your response as a "Reply
to a Notice of Violation," and send it to the U.S. Nuclear Regulatory Commission,
ATTN: Document Control Desk, Washington, DC 20555-0001 with a copy to the Regional
Administrator, U.S. Nuclear Regulatory Commission, Region IV, 1600 East Lamar Blvd.,
Arlington, Texas 760114511, and a copy to the NRC Resident Inspector at the Comanche
Peak Nuclear Power Plant that is the subject of this Notice, within 30 days of the date of the
letter transmitting this Notice of Violation (Notice).
If you choose to respond, your response will be made available electronically for public
inspection in the NRC Public Document Room or from the NRCs document system (ADAMS),
accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. Therefore, to
the extent possible, the response should not include any personal privacy or proprietary
information so that it can be made available to the public without redaction.
In accordance with 10 CFR 19.11, you may be required to post this Notice within two working
days of receipt.
Dated this 21st day of September 2021
Enclosure 2
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Numbers:
05000445 and 05000446
License Numbers:
Report Numbers:
05000445/2020011 and 05000446/2020011
Enterprise Identifier: I-2020-011-0039
Licensee:
Vistra Operations Company LLC
Facility:
Comanche Peak Nuclear Power Plant
Location:
Glen Rose, Texas
Inspection Dates:
June 08, 2020 to August 27, 2020
Inspectors:
S. Alferink, Reactor Inspector
J. Drake, Senior Reactor Inspector
J. Mateychick, Senior Reactor Inspector
Approved By:
Nicholas H. Taylor, Chief
Engineering Branch 2
Division of Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting a triennial fire protection inspection at Comanche Peak Nuclear
Power Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight
Process is the NRCs program for overseeing the safe operation of commercial nuclear power
reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
Failure to Implement and Maintain Adequate Inspection Procedures for Penetration Sealing
Devices
Cornerstone
Significance
Cross-Cutting
Aspect
Report
Section
Mitigating
Systems
Green
NOV 05000445;05000446/2020011-01
Opened/Closed
H.8 - Procedure
Adherence
05
The team identified a Green violation of License Condition 2.G for the licensees failure to
maintain adequate procedures for the inspection of penetration sealing devices as required by
the licensees Fire Protection Report, Section IV-2.1.c.1. Specifically, the licensee
implemented a revision to Fire Protection Procedure FIR-310, Penetration Seal Inspection,
in 2020 to provide corrective actions for an NCV issued in 2017 due to the procedure not
ensuring that all penetrations seals would be inspected during the required 15-year cycle.
However, the revised procedure incorrectly excluded from the inspection schedule all
penetration seals in the auxiliary building.
Additional Tracking Items
None
3
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors reviewed selected procedures and records,
observed activities, and interviewed personnel to assess licensee performance and compliance
with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.21N.05 - Fire Protection Team Inspection (FPTI)
SSC Credited for Fire Prevention, Detection, Suppression, or Post-Fire SSD Review
(IP Section 03.01) (4 Completed Samples and 2 Partial Samples)
The inspectors verified that components and/or systems will function as required to support
the credited functions stated for each sample. Additional inspection considerations are
located in the fire hazards analysis (FHA) or safe shutdown analysis (SSA).
(1)
The auxiliary feedwater system and the steam generator power-operated relief
valves.
(2)
The fire water system including the fire water tanks, fire pumps, and yard loop
distribution piping system.
(3)
The fire detection systems and fire suppression systems installed in Fire Area EN,
Unit 1 Cable Spreading Room.
(4)
The fire detection systems and fire suppression systems installed in Fire Area EM,
Unit 2 Cable Spreading Room.
(5)
(Partial Sample)
Subsection b states, Verify that operator actions can be accomplished as assumed
in the licensees FHA, or as assumed in the licensees fire probabilistic risk
assessment (FPRA) analysis and SSA. Due to conditions related to COVID-19 in
the area of the plant, onsite inspector walkdowns of procedures with licensee
operations personnel could not be performed at this time. An inspector will visit the
licensees site to perform this activity later as conditions permit. The results of the
additional inspection will be documented in a resident inspectors quarterly report.
(6)
(Partial Sample)
Subsection e states, Perform a walkdown inspection to identify equipment alignment
discrepancies. Inspect for deficient conditions such as corrosion, missing fasteners,
cracks, and degraded insulation. Due to conditions related to COVID-19 in the area
of the plant, onsite inspector walkdowns of fire protection systems with licensee fire
protection personnel could not be performed at this time. An inspector will visit the
licensees site to perform this activity later as conditions permit. The results of the
additional inspection will be documented in a resident inspectors quarterly report.
4
Fire Protection Program Administrative Controls (IP Section 03.02) (2 Samples)
The inspectors verified that the selected control or process is implemented in accordance
with the licensees current licensing basis. If applicable, ensure that the licensees fire
protection program contains adequate procedures to implement the selected administrative
control. Verify that the selected administrative control meets the requirements of all
committed industry standards.
(1)
The inspectors reviewed the licensees administrative controls of hot work, transient
combustibles, and fire impairments.
(2)
The inspectors reviewed the licensees fire brigade training program.
Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)
(1)
The inspectors reviewed changes to the approved fire protection program concerning
the inspection of fire rated penetration sealing devices.
(2)
The inspectors reviewed the changes to the approved fire protection program
incorporated into the Comanche Peak Nuclear Power Plant Fire Protection Report
Units 1 and 2, Revision 33.
INSPECTION RESULTS
Failure to Implement and Maintain Adequate Inspection Procedures for Penetration Sealing
Devices
Cornerstone
Significance
Cross-Cutting
Aspect
Report
Section
Mitigating
Systems
Green
NOV 05000445; 05000446/2020011-
01
Opened/Closed
H.8 - Procedure
Adherence
5
The team identified a Green violation of License Condition 2.G for the licensees failure to
maintain adequate procedures for the inspection of penetration sealing devices as required
by the licensees Fire Protection Report, Section IV-2.1.c.1. Specifically, the licensee
implemented a revision to Fire Protection Procedure FIR-310, Penetration Seal Inspection,
in 2020 to provide corrective actions for an NCV issued in 2017 due to the procedure not
ensuring that all penetrations seals would be inspected during the required 15-year cycle.
However, the revised procedure incorrectly excluded from the inspection schedule all
penetration seal devices in the auxiliary building.
Description: During the 2017 triennial fire protection inspection, the NRC identified a Green
non-cited violation for the failure to maintain adequate procedures for the inspection of fire
penetration seals. As part of this violation, the NRC noted that the licensee used an
automated random sampling process for selection of penetration seals for inspection and this
process failed to ensure that all required penetration seals were inspected within their 15-year
sampling plan interval.
The team documented this violation as NCV 05000445/2017008-01; 05000446/2017008-01,
Failure to Implement and Maintain Adequate Inspection Procedures for Penetration Sealing
Devices, on July 31, 2017. The licensee documented this issue in the corrective action
program in Condition Report CR-2017-007746.
5
In response to this violation, the licensee generated a list of over 16,000 fire penetration seals
that required inspection. The licensee divided this list into different groups based on the
penetration seal location. The licensee associated these groups with 15 repetitive preventive
maintenance tasks. The licensee then updated Procedure FIR-310, Penetration Seal
Inspection, to require the inspection of penetration seals using one of these 15 preventive
maintenance tasks each year over a 15-year period, thereby ensuring that each penetration
seal would be inspected once during the 15-year period. The licensee revised this procedure
on February 6, 2020.
During the current inspection, the team reviewed the revised inspection procedure and the
repetitive preventive maintenance tasks. The team identified that the fire penetration seal
group associated with the auxiliary building was not included in any of the 15 repetitive
preventive maintenance tasks. This group contained 1,956 penetration seals. Since this
group was not included in any of the 15 preventive maintenance tasks, the team determined
that these 1,956 penetration seals were not scheduled to be inspected during the current
15-year period.
In response to the teams questions, the licensee reviewed the previous fire penetration seal
inspections for the penetration seals associated with the auxiliary building. The licensee
identified that 1,192 of the penetration seals were inspected and 764 of the penetration seals
were not inspected during the previous 15-year period. Of the penetration seals that were
inspected, the licensee determined that only two of them failed the inspection.
Corrective Actions: There was no immediate safety concern since the licensee had observed
a very low failure rate of penetration seals during the previous 15-year cycle. The licensee
entered this issue into the corrective action program for resolution and incorporated the
auxiliary building penetration seals into eight of the preventive maintenance tasks required by
procedure FIR-310. The licensee restored compliance with the approved fire protection
program on June 25, 2020, and performed an Organizational Effectiveness Investigation to
determine the cause of the violation. The licensee identified a lack of attention to detail and
verbatim compliance with procedure STA-422, Corrective Action Program, as causes. The
verification of the lists of penetration seals to be inspected was not completed and was
transferred to future actions. This was not in compliance with procedure STA-442, Section
6.6, Condition Report Closure to Future Actions, which states that when the condition report
documents a Licensing Basis Deviation the condition report may not close to future actions.
The licensee provided coaching for the personnel involved.
Corrective Action References: Condition Report CR-2020-004473
Performance Assessment:
Performance Deficiency: The failure to ensure that fire protection program procedures used
to establish inspection criteria for penetration sealing devices appropriately captured all
required penetration sealing devices for visual inspection using a site approved sampling plan
was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor
because it was associated with the Protection Against External Factors attribute of the
Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure
the availability, reliability, and capability of systems that respond to initiating events to prevent
undesirable consequences.
6
Significance: The inspectors assessed the significance of the finding using Appendix F, Fire
Protection and Post - Fire Safe Shutdown SDP. The team assigned the fire confinement
category to the finding since it involved fire rated penetration seals. The team noted that the
licensee observed a very low failure rate of the auxiliary building penetration seals during the
past 15 years.
The team discussed the finding with a senior reactor analyst because the finding involved
multiple fire areas. In consultation with the senior reactor analyst, the team assigned a low
degradation rating to the finding because of the very low failure rate and the fact that a
majority of the auxiliary building penetration seals have been previously inspected.
The team determined the finding was of very low risk significance (Green) in Step 1.3 since
the finding was assigned a low degradation rating.
H.8 - Procedure Adherence: Individuals follow processes, procedures, and work instructions.
Specifically, the licensee failed to complete required verifications of corrective actions to
assure adequacy.
Enforcement:
Violation: License Condition 2.G for Unit 1 requires, in part, that the licensee implement and
maintain in effect all provisions of the approved fire protection program as described in the
Final Safety Analysis Report through Amendment 78 and as approved in the Safety
Evaluation Report and its supplements through Supplement 24.
License Condition 2.G for Unit 2 requires, in part, that the licensee implement and maintain in
effect all provisions of the approved fire protection program as described in the Final Safety
Analysis Report through Amendment 87 and as approved in the Safety Evaluation Report
and its supplements through Supplement 27.
The Fire Protection Report was included as part of the licensees approved fire protection
program for both units, and states, in part, that administrative control of the fire protection
program is provided through station procedures to assure that the fire protection equipment
and systems are operable and properly maintained. This includes periodic tests and
inspections, compensatory measures concerning items which may be inoperable, and quality
assurance audits. Section IV-2.1.c.1 of the Fire Protection Report required, in part, that the
required fire rated assemblies and penetration sealing devices are confirmed operable by
visually inspecting the exposed surfaces using a site approved sampling plan every 18
months.
Contrary to this requirement, from 2009 to June 25, 2020, the licensee failed to ensure that
fire protection program procedures used to establish inspection criteria for penetration sealing
devices appropriately captured all required penetration sealing devices for visual inspection
using a site approved sampling plan every 18 months. Specifically, Procedure FIR-310,
Penetration Seal Inspection, revised in response to NCV 05000445/2017008-01; 05000446/2017008-01, Failure to Implement and Maintain Adequate Inspection Procedures
for Penetration Sealing Devices, did not ensure that all required penetration sealing devices
would be inspected within the licensees sampling plan interval. Consequently, the licensee
failed to restore compliance to the previous NCV since the revised procedure did not ensure
the fire rated penetration seals in the auxiliary building were included in the maintenance list
so they would be scheduled for inspection.
7
Enforcement Action: This violation is being cited because the licensee failed to restore
compliance after the violation was previously identified consistent with Section 2.3.2 of the
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On June 25, 2020, the inspectors presented the triennial fire protection inspection results
to Mr. T. McCool, Site Vice President, and other members of the licensee staff in a
debrief meeting.
On August 27, 2020, the inspectors presented the triennial fire protection inspection
results to Mr. T. McCool, Site Vice President, and other members of the licensee staff in
an exit meeting.
8
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.05 Calculations
0210-063-0031
Unit 1 and Common Hydraulic Calculation Verification
1
71111.21N.05 Calculations
2-FP-0006
Determination of the Pressure and Flow at the Fire Pump
Discharge
1
71111.21N.05 Calculations
DBD-ME-003
13
71111.21N.05 Calculations
DBD-ME-027
Radiological Accident Analysis
13
71111.21N.05 Corrective Action
Documents
CR-2010-004331 CR-2013-001933 CR-2015-004590
CR-2016-002210 CR-2017-001410 CR-2017-001552
CR-2017-002011 CR-2017-002035 CR-2017-003949
CR-2017-004235 CR-2017-004324 CR-2017-004560
CR-2017-004691 CR-2017-007536 CR-2017-007745
CR-2017-007746 CR-2017-008728 CR-2017-008890
CR-2017-008961 CR-2018-006426 CR-2018-007079
CR-2018-007442 CR-2018-008405 CR-2019-003625
CR-2019-005334 CR-2019-009310 CR-2020-000558
CR-2020-000864 CR-2020-001701 CR-2020-002817
CR-2020-003204 TR-2014-010354 TR-2014-010370
TR-2014-012160 TR-2016-003548 TR-2017-003590
TR-2017-008741 TR-2017-012520 TR-2018-006427
TR-2019-003269 TR-2020-000040 TR-2020-001999
TR-2020-004586 TR-2917-009888
71111.21N.05 Corrective Action
Documents
Resulting from
Inspection
CR-2020-004397 CR-2020-004473 IR-2020-004760
71111.21N.05 Fire Plans
FPI - 504
Electrical & Control Building Elevation 807'-0"
Unit 2 Cable Spreading Room
1
71111.21N.05 Fire Plans
FPI - 505
Electrical & Control Building
Unit 1 Cable Spreading Room Elevation 807'-0"
3
71111.21N.05 Miscellaneous
Comanche Peak Nuclear Power Plant Fire Protection
Report Unit 1 and Unit 2
32 & 33
71111.21N.05 Miscellaneous
Comanche Peak Fire PRA Summary
1
71111.21N.05 Miscellaneous
AO5407
Response to Fire in the Control Room or Cable Spreading
02/21/03
9
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Room, Perform AO #1 Actions
71111.21N.05 Miscellaneous
20023
Transient Combustible Permit
0
71111.21N.05 Miscellaneous
20060
Transient Combustible Permit
0
71111.21N.05 Miscellaneous
20079
Transient Combustible Permit
0
71111.21N.05 Miscellaneous
20085
Transient Combustible Permit
0
71111.21N.05 Miscellaneous
20088
Transient Combustible Permit
0
71111.21N.05 Miscellaneous
2323-AS-18
Specification Hollow Metal Doors and Frames
1
71111.21N.05 Miscellaneous
5527599
Fire Permit
0
71111.21N.05 Miscellaneous
5563972
Fire Permit
0
71111.21N.05 Miscellaneous
5595567
Fire Permit
0
71111.21N.05 Miscellaneous
5611222
Fire Permit
0
71111.21N.05 Miscellaneous
5832506
Fire Permit
0
71111.21N.05 Miscellaneous
AO6413
Response to fire in Control Room or Cable spreading
room
13
71111.21N.05 Miscellaneous
AO6414
Response to a fire in the Control Room or Cable
Spreading Room opening pressurizer PORV MOV 8000A
12/19/01
71111.21N.05 Miscellaneous
AO6415
Align Alternate Auxiliary Feedwater Supply from Station
71111.21N.05 Miscellaneous
DBD-ME-001
CPSES Fire Protection Program Design Basis Document
12
71111.21N.05 Miscellaneous
DBD-ME-225
Fire Suppression System
27
71111.21N.05 Miscellaneous
FB44.FBR.193
FBR - 2019 Live Fire Requal Training
0
71111.21N.05 Miscellaneous
FB44FBR196
FBR - 2020 Live Fire Requal Training
0
71111.21N.05 Miscellaneous
FBD2FBI103
Portable Fire Extinguishers 1
0
71111.21N.05 Miscellaneous
FBD2FBI107
Fire Hose
0
71111.21N.05 Miscellaneous
FBD2FBI108
Fire Streams and Nozzles
0
71111.21N.05 Miscellaneous
FBD2FBI109
Hoselines and Master Streams
0
71111.21N.05 Miscellaneous
FBD2FBI201
Personal Protective Equipment (Fire Brigade)
0
71111.21N.05 Miscellaneous
FBD2FBI204
Search and Rescue
0
71111.21N.05 Miscellaneous
FBD2FBI207
Handling Hoselines
0
71111.21N.05 Miscellaneous
FBD2FBI208
Foam Operations (Fire Brigade)
0
71111.21N.05 Miscellaneous
FBDSFBI102
Combustion and Fire Behavior
0
71111.21N.05 Miscellaneous
Final Safety
Analysis Report
Emergency Planning
Amendment
No. 109
10
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Section 13.3
71111.21N.05 Miscellaneous
Final Safety
Analysis Report
Section 9.5.1
Amendment
No. 109
71111.21N.05 Miscellaneous
OER-2017-
007276
IER L4-17-6 Fire Event Trend and Causes
06/13/17
71111.21N.05 Miscellaneous
OER-2017-
009751
NRC IN-2917-04 High Energy Arching Faults In Electrical
Equipment Containing Aluminum Components
08/29/17
71111.21N.05 Miscellaneous
OER-2018-
006316
NRC Information Notice 2018-09; Electrical Arc Flash
Caused by Foreign Material Damages Fire Door
09/20/18
71111.21N.05 Miscellaneous
RO4406
Respond To Fire In Control Room Or Cable Spread Room 08/31/08
71111.21N.05 Procedures
ABN-803A
Response To A Fire In The Control Room Or Cable
Spreading Room
13
71111.21N.05 Procedures
ABN-803B
Response To A Fire In The Control Room Or Cable
Spreading Room
10
71111.21N.05 Procedures
ABN-804A
Response To Fire In The Safeguards Building
6
71111.21N.05 Procedures
ABN-804B
Response To Fire In The Safeguards Building
4
71111.21N.05 Procedures
ABN-805A
Response To Fire In The Auxiliary Building Or The Fuel
Building
8
71111.21N.05 Procedures
ABN-805B
Response To Fire In The Auxiliary Building Or The Fuel
Building
8
71111.21N.05 Procedures
ABN-806A
Response To Fire In The Electrical And Control Building
8
71111.21N.05 Procedures
ABN-806B
Response To Fire In The Electrical And Control Building
6
71111.21N.05 Procedures
ABN-807A
Response To Fire In The Containment Building
8
71111.21N.05 Procedures
ABN-807B
Response To Fire In The Containment Building
6
71111.21N.05 Procedures
ABN-808A
Response To Fire In Service Water Intake Structure
6
71111.21N.05 Procedures
ABN-808B
Response To Fire In Service Water Intake Structure
4
71111.21N.05 Procedures
ABN-809A
Response To Oil Leak Or Fire In The Turbine Building
8
71111.21N.05 Procedures
ABN-809B
Response To Oil Leak Or Fire In The Turbine Building
5
71111.21N.05 Procedures
ABN-901
Fire Protection System Alarms or Malfunctions
9
71111.21N.05 Procedures
FBD2FBI104
Portable Fire Extinguishers 2
0
71111.21N.05 Procedures
FBD2ICS111
Incident Management
0
71111.21N.05 Procedures
FIR-201
Preparation, Control, Review and Use of Fire Preplan
9
11
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Instructions
71111.21N.05 Procedures
FIR-302
Fire Door Tests and Inspections
8
71111.21N.05 Procedures
FIR-308
Fire Brigade Equipment
4
71111.21N.05 Procedures
FIR-310
Penetration Seal Inspection
4
71111.21N.05 Procedures
FIR-PX-3200
Fire Suppression Loop Flow Test
3
71111.21N.05 Procedures
FIR-PX-3801
Electric Driven Fire Protection Pump CPX-FPAPFP-04
Operability Test
4
71111.21N.05 Procedures
FIR-PX-3802
Diesel Driven Fire Protection Pump CPX-FPAPFP-05
Operability Test
4
71111.21N.05 Procedures
FIR-PX-3803
Diesel Driven Fire Protection Pump CPX-FPAPFP-06
Operability Test
4
71111.21N.05 Procedures
INC-3020
Maintenance and Rework of Plant Doors
2
71111.21N.05 Procedures
OPT-220
Fire Suppression Water System Operability Test
13
71111.21N.05 Procedures
STA-202
Nuclear Generation Procedure Change Process
39
71111.21N.05 Procedures
STA-421
Control of Issue Reports
21
71111.21N.05 Procedures
STA-422
Corrective Action Program
34
71111.21N.05 Procedures
STA-602
Temporary Modifications and Transient Equipment
Placements
20
71111.21N.05 Procedures
STA-716
Modification Process
27
71111.21N.05 Procedures
STA-722
7
71111.21N.05 Procedures
STA-723
Fire Protection Systems/Equipment Requirements
5
71111.21N.05 Procedures
STA-724
Fire Reporting and Response
4
71111.21N.05 Procedures
STA-727
Fire Brigade
6
71111.21N.05 Procedures
STA-729
Control of Transient Combustibles, Ignition Sources and
Fire Watches
12
71111.21N.05 Procedures
STA-738
Fire Protection Systems/Equipment Impairments
7
71111.21N.05 Procedures
STI-422.03
Performing Coaching and Investigations
2
71111.21N.05 Procedures
STI-422.04
Processing of Condition Reports
0
71111.21N.05 Procedures
STI-423.01
Processing Tracking Reports
0
71111.21N.05 Procedures
TRA-104
Fire Protection Training
16
71111.21N.05 Self-
Assessments
EVAL-2018-010
12/15/18
71111.21N.05 Self-
IR-2019-005207
Fire Protection Self-Assessment Report
0
12
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Assessments
71111.21N.05 Work Orders
5209230, 5329355, 5511184, 5557316, 5558257,
5578521, 5655850, 5668385, 5747089, 5749736,
5757975, 5821733, 5840282, 5841173, 5856117,
5861142, 5920545