IR 05000298/2022010
| ML22165A319 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/16/2022 |
| From: | Nick Taylor NRC/RGN-IV/DORS |
| To: | Dent J Nebraska Public Power District (NPPD) |
| References | |
| IR 2022010 | |
| Download: ML22165A319 (14) | |
Text
June 16, 2022
SUBJECT:
COOPER NUCLEAR STATION - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000298/2022010
Dear Mr. Dent:
On April 22, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On April 28, 2022, the NRC inspectors discussed the results of this inspection with Khalil Dia, General Manager of Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, 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 Operating Reactor Safety Docket No. 05000298 License No. DPR-46 Enclosure:
Inspection Report 05000298/2022010 Distribution via Listserv Signed by Taylor, Nicholas on 06/16/22
ML22165A319 X SUNSI Review By: GAP ADAMS:
X Yes No Sensitive X Non-Sensitive Non-Publicly Available X Publicly Available Keyword NRC-002 OFFICE RIV/EB2 DORS/EB2 DORS/EB2 EB2/BC PBC/BC EB2/BC NAME GPick NOkonkwo MChisolm NTaylor JJosey NTaylor SIGNATURE
/RA/
/RA/
/RA/
/RA/
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DATE 6/14/2022 6/14/2022 6/15/2022 6/15/2022 6/15/2022 6/16/2022
Enclosure U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
05000298
License Number:
Report Number:
Enterprise Identifier:
I-2022-010-0008
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
Brownville, NE
Inspection Dates:
April 4 to 28, 2022
Inspectors:
G. Pick, Senior Reactor Inspector, Team Lead
M. Chisolm, Reactor Inspector
N. Okonkwo, Reactor Inspector
Approved By:
Nicholas H. Taylor, Chief
Engineering Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial fire protection inspection at Cooper Nuclear Station, 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
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) Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)
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 in the safe shutdown analysis.
- (1) Operator actions can be accomplished as assumed in the licensees fire probabilistic risk assessment analysis and safe shutdown analysis for Fire Area CB-D for a control room evacuation.
- (2) Ensure that post maintenance tests and/or surveillance activities are performed as scheduled for the underground fire loop, fire pumps, and sprinkler system in the cable spreading room and halon gas system for the computer room.
- (3) Walked down the sprinkler system and fire pumps to identify equipment alignment discrepancies. Inspect for deficient conditions such as corrosion, missing fasteners, cracks, and degraded insulation.
- (4) Ensured that fire protection components are being managed for aging (e.g., loss of material, cracking, reduction of heat transfer) in accordance with appropriate aging management programs. Verify that the licensees aging management program activities associated with fire protection equipment are being implemented.
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) Hot work, fire impairment, and combustible control programs.
- (2) Fire probabilistic safety assessment monitoring for classic fire protection activities.
Fire Protection Program Changes/Modifications (IP Section 03.03) (1 Sample)
The inspectors verified the following, as applicable:
a.
Changes to the approved fire protection program do not constitute an adverse effect on the ability to safely shutdown.
b.
The adequacy of the design modification.
c.
Assumptions and performance capability stated in the safe shutdown analysis have not been degraded through changes or modifications.
d.
The fire protection program documents, such as the Updated Final Safety Analysis Report, fire protection report, fire hazards analysis, and safe shutdown analysis were updated consistent with the fire protection program for design change.
e.
Post-fire safe shutdown operating procedures, such as abnormal operating procedures, affected by the modification were updated.
The inspectors reviewed the following as one sample:
Design Change 5229496, EOP PTM 97-100 Review - revises control logic for RHR MOVs 27A and spares
Engineering Change 6039780, Emergency Station Service Transformer (ESST)
Replacement
Engineering Evaluation 10-055, Fire Protection Evaluation of Conduit Internal Seals, Revision 1
Engineering Evaluation 01-009, Revise EE 01-009 to remove references to Kennedy FP, Revision 5
Engineering Evaluation 20-012, Evaluation of ClearView Shielding as Temporary Shielding Material
Engineering Evaluation 01-009, Revise EE 01-009 to replace Water Pressure and CO2 fire extinguishers with ABC fire extinguishers, Revision 6
Design Change 5357188, Replace Heat Activated Devices for Fire Protection Systems 9, 10, 12, & 13
Design Engineering Change 5246597, Relocates Hydrant #3 inside the protected area
Design Engineering Change 5343757, Replaces Computer Room Halon control and peripherals
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 28, 2022, the inspectors presented the triennial fire protection inspection results to Khalil Dia, General Manager of Plant Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CNS-PSA-007
PRA Deterministic Calculation Notebook
NEDC 11-088
(Calc-17-031)
Fire Safety Analysis for Fire Area CB-0
NEDC 11-095
Fire Safety Analysis for Fire Area RB-DJ EPM Report RI-
1906-008-RBD-1
NEDC 14-056
Essential Control building Ventilation Desired Thermostat
Setpoints and Hydrogen Concentration Calculation
Calculations
NEDC-10-081
Task 8, Fire Risk Evaluation Area CB-A
Corrective Action
Documents
CR-CNS-
2008-01460, 2008-01576, 2008-02027, 2014-06146,
2016-03315, 2016-06698, 2016-07185, 2016-09062,
2017-04000, 2018-03118, 2019-00745, 2019-02049,
2019-02295, 2019-03165, 2019-05491, 2019-05576,
20-01859, 2020-04487, 2020-04670, 2020-05288,
20-05701, 2021-01477, 2021-01583, 2021-01787,
21-01858, 2021-02419, 2021-02467, 2021-03321,
21-03791, 2021-03793, 2021-04960, 2021-05266,
22-00362
Corrective Action
Documents
Resulting from
Inspection
CR-CNS-
22-01468, 2022-01470, 2022-01473, 2022-01474,
22-01492, 2022-01494, 2022-01497, 2022-01515,
22-01519, 2022-01770, 2022-01794
2016, Sheet 1B
Flow Diagram, Fire Protection, Cont., RW, ARDW Bldg
2016, Sheet 4
Halon and Cardox System Flow Diagram
2018
Flow Diagram Turbine Generator Bldg. & Control Bldg.
Heating & Ventilating
25
HVAC Control Bldg., Plan El 877-6 & El. 903-6 &
Section
3009 Sheet 1
Cooper Nuclear Station One Line Switching Diagram 12.5
kV Ring Bus System
3009 Sheet 4
Cooper Nuclear Station Fire Protection Pump "E"/Panel
DPTC1 Heat Trace Feeder Auxiliary One Line Diagram
71111.21N.05
Drawings
3036 Sheet 5
Control Elementary Diagrams
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
3101
Turbine Generator Bldg, Basement & Mezzanine
Grounding Plans
257 Sheet 65
Cooper Nuclear Station Alternate Shutdown HPCI Panel
Internal Connections
257 Sheet 66
Cooper Nuclear Station Alternate Shutdown HPCI Panel
Internal Connections
257 Sheet 67
Cooper Nuclear Station Alternate Shutdown HPCI Panel
External Connections
2242808
Fire Protection Pre-Fire-Plan, Reactor Building Southwest
Quadrant Elevation 881-9 and 859-9
2242809
Fire Protection Pre-Fire-Plan, Reactor Building First Floor
Elevation 903-6
2242819
Fire Protection Pre-Fire-Plan, Control Building Auxiliary
Relay Room, Elevation 903-6
2242823
Fire Protection Pre-Fire-Plan, Control Building Cable
Spreading Room Elevation 918-0
2242824
Fire Protection Pre-Fire-Plan, Con. Bldg Control Rm and
Comp Rm Elevation 932-6
2242828
Fire Protection Pre-Fire-Plan, Office Building Cable
Expansion Room Elevation 918-6
454003604
Flow Diagram, Fire Protection, Turbine Generator Building
454250005
Main Power Transformer Fire Protection, Fire Alarm
Control Panel Mechanical Outline
454250006
Main Power Transformer Fire Protection, Fire Alarm
Control Panel Interconnection Diagram
454250007
Main Power Transformer Fire Protection, Fire Alarm &
Detection System, Detection Layout & Valve Station
Layout
B
454250008
Main Power Transformer Fire Protection, Fire Alarm &
Detection System, Wiring Detail
D
64929D, Sheet 1
Fire Protection System Detection Layout Systems 9 & 10
Reactor Feed Pump 1A and 1B
C
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
64929M
Fire Protection System Mechanical Outline - ACI Model
A888-M1638
B
791E271,
Sheet 1A
Cooper Nuclear Station Elem Diagram HPCI System
CNS-FP-214
Fire Protection Pre-Fire Plan Reactor Building Southwest
Quadrant Elevations 881'-9" and 859'-9"
CNS-FP-215
Fire Protection Pre-Fire Plan Reactor Building First Floor
Elevation 903'-6"
CNS-FP-225
Fire Protection Pre-Fire Plan Control Building Auxiliary
Relay Room Elevation 903'-6"
CNS-FP-229
Fire Protection Pre-Fire Plan Control Building Cable
Spreading Room Elevation 918'-6"
CNS-FP-230
Fire Protection Pre-Fire Plan Control Building Control
Room and Computer Room Elevation 932'-6"
CNS-FP-234
Fire Protection Pre-Fire Plan Office Building Cable
Expansion Room Elevation 918'-6"
IN 08-1232
Equipment Layout Halon, 1301 System, NPPD Computer
Room
DC5229496
EOP PTM 97-100 Switches
DEC-5343757
Computer Room Halon System Control Upgrade
Emergency Station Service Transformer Replacement
EE-01-006
Disposition of NFPA Code Compliance Deviations
(Systems in Fire Zones Requiring an IPEEE Phase 2
Screening)
EE-01-009
Review of NFPA 10, 14, & 24 Code Conformance for
Power Block Buildings
EE-01-009
Review of NFPA 10, 14, & 24 Code Conformance for
Power Block Buildings
Engineering
Changes
TCC 5396378
TCC repowers various electrical equipment that would
normally be de-energized during a 4160V Bus G outage.
EE 10-055
Fire Protection Evaluation of Conduit Internal Seals
EE 20-12
Evaluation of ClearView Shielding as Temporary Shielding
Material
Engineering
Evaluations
ER 2015-002
NFPA 805 Fire Protection Monitoring Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NEDC 10-041
Recovery Action Feasibility Assessment Report Review
EPM Report R1906-004-005
NEDC 11-088
Fire Safety Analysis for Fire Area CB-D
NEDC-10-085
Scientech Calculation 17712-018-04, Task 8 Fire Risk
Evaluation Area CB-D
2.3-FP-5
Fire Protection - Annunciator 5
3002018285
Results of Accelerated Aging for Sprinklers Used in
Nuclear Power Plants: Fire Sprinkler Head Testing
11/2020
Time Response Design Criteria for Safety-related
Operator Action
1994
ANSIANS-59.2
Safety criteria for HVAC systems located outside Primary
Containment
1985
CED 6017100
Battery Room Heating Evaluation
2/19/05
CNS System
Health
FP System Health Report 21-10
10/2021
CNS System
Health
FP System Health Report 21-07
7/2021
Construction
Standard
U12S3C3 Dwg
NC34572
2KV-SW-Duct-3PH-Pad-SWGR 09/10/11/12
EE 01-006
Disposition of NFPA Code Compliance Deviations
(Systems in Fire Zones Requiring an IPEEE Phase 2
Screening)
FAQ (Frequently
Asked Question)
07-0030
Establishing Recovery Actions
FAQ 10-0059
NFPA (National Fire Protection Association) 805
Monitoring
Digital Evaluation of Fire Protection Panel for Transformer
Deluge Systems
2/04/2012
Miscellaneous
Crediting of Operator Actions in Place of Automatic
Actions and Modifications of Operator Actions, Including
Response Times
10/23/1997
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Instruction Sheet
2-505
Manual PMH Pad-Mounted Gear Outdoor Distribution
(14.4kV AND 25kV)
3/9/2020
NC33070
KV-SW-Duct-3PH-Pad, SWGR 03/04 Conn. Diag.
3/1/2020
NEDC 09-085
Section 7.44 Incipient Detection Excerpt from NEDC 09-
085 Rev. 4 Fire Risk Quantification
NEDC 09-085,
Sec.7.4.4
Incipient Detection Excerpt from Fire Risk Quantification
NFPA 12A
Halon 1301 Fire Extinguishing Systems
2/1980
NLS2012006
License Amendment Request to Revise the Fire
Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)
4/24/2012
Procedure 7.0.7
rev 12 screen
Scaffolding Construction and Control rev 12 screen
Procedure 7.0.7
rev 16 screen
Scaffolding Construction and Control rev 16 screen
Procedure 7.0.7
rev 25 screen
Scaffolding Construction and Control rev 25 screen
Purchase Order
5404944
AFFF Foam Chemical Analysis Summary
2/14/2022
RT 5368430
20 Scaffold Inspection
10/25/2020
TRM T3.11
Technical Requirements Manual - Fire Protection Systems
10/17/2016
TSP 5209096
2018 Scaffold Inspection
4/30/2018
U12S3C4B
S-Switch Underground
3/10/2020
NDE Reports
Condensate
Storage Tank -
Wall & Floor
4/11/2011
0-CNS-LI-102
Corrective Action Process
0.23
CNS Fire Protection Plan
0.39
Hot Work
0.39.1
Fire Watches and Fire Impairments
0.39.1
Fire Watches and Fire Impairments
0.39.2
Ignition Source Procedure
Procedures
0.7.1
Control of Combustibles
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
11.CS-Dedicated
Media
Dedicated Use of Media
15.FP.307
Halon 1301 Computer Room Fire Suppression
Surveillance Checks
15.FP.309
Fire Protection Manual Pull Station Functional Test.
15.FP.647
Non-TRM Required Fire Fighting Equipment Examination
15.FP.650
Fire Locker and Hazardous Material Response Inventory
2.0.4
Relief Personnel and Shift Turnover
2.2.18.3.DIV1
4160V DIV 1 Distribution Support
2.2.38
System Operating Procedure, HVAC Control Building
3-CNS-DC-357
NFPA 805 Monitoring Program
3-EN-DC-115
Engineering Change Process
5.3SBO
Station Blackout
5.4FIRE-S/D
Fire Induced Shutdown From Outside Control Room
5.4Post -Fire-
Reactor
Reactor Building Post-Fire Operational Information
5.4Post-Fire-
Control
Control Building Post-Fire Operational Information
5.4Post-Fire-
Turbine
Turbine Building/Outside Areas Post-Fire Operational
Information
6.1FP.301
Diesel Generator C02 Operability Test (DIV 1)
6.1FP.302
Fire Detection System Examination (DIV 1)
6.FP.101
Fire Pump Operability Test
6.FP.102
Station Fire Pump Surveillance Testing
6.FP.102
Station Fire Pump Surveillance Testing
6.FP.203
Fire Damper Assembly Examination (Fire Protection
System 24 Months Examination)
6.FP.204
Fire Door Examination
6.FP.314
Panel 9-32 and 9-33 Incipient Smoke Detector Testing
6.FP.601
Fire Protection System 31 Day Examination
6.FP.606
Fire Barrier/Penetration Seal Visual Examination
6.FP.610
Yard Hydrant Flow Check & Fire Protection System Flow
Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
7.0.7
Scaffolding Construction and Control
7.3.17.4
4160V Vacuum Bottle Breaker Maintenance
IP-ENG-001
Standard Design Process
Work Orders
4744842, 4880243, 5028698, 5067194, 5137136,
5181059, 5200420, 5201372, 5203385, 5205851,
205859, 5209006, 5209740, 5210849, 5211381,
211483, 5211484, 5211485, 5211486, 5303589,
5303593, 5303594, 5337669, 5344017, 5368430,
5395381, 5397980