IR 05000317/2019011
| ML19284A518 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/10/2019 |
| From: | Glenn Dentel Engineering Region 1 Branch 2 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Dentel G | |
| References | |
| IR 2019011 | |
| Download: ML19284A518 (13) | |
Text
October 10, 2019
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000317/2019011 AND 05000318/2019011
Dear Mr. Hanson:
On September 26, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Calvert Cliffs Nuclear Power Plant, Units 1 and 2 and discussed the results of this inspection with Mr. Mark Flaherty and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety
Docket Nos. 05000317 and 05000318 License Nos. DPR-53 and DPR-69
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000317 and 05000318
License Numbers:
Report Numbers:
05000317/2019011 and 05000318/2019011
Enterprise Identifier: I-2019-011-0015
Licensee:
Exelon Generation Company, LLC
Facility:
Calvert Cliffs Nuclear Power Plant, Units 1 and 2
Location:
Lusby, MD
Inspection Dates:
September 9, 2019 to September 26, 2019
Inspectors:
E. DiPaolo, Senior Reactor Inspector (Team Lead)
C. Bickett, Senior Reactor Inspector
P. Finney, Senior Project Engineer
S. Graves, Senior Reactor Inspector
Approved By:
Glenn T. Dentel, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial fire protection inspection at Calvert Cliffs Nuclear Power Plant, Units 1 and 2 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
71111.05XT - Fire Protection - NFPA 805 Fire Protection Inspection Requirements (IP Section 02.01a)
The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones, including analyzed electrical circuits:
- (1) Fire Area 16 - Unit 1 Cable Spreading Room and 1C Cable Chase
- (2) Fire Area 18 - Unit 2 27' Switchgear Room
- (3) Fire Area 25 - Unit 2 45' Switchgear Room
- (4) Fire Area 32 - Unit 1 45' West Electrical Penetration Room
Analyzed Circuits:
1-CV-4030OP, Main Steam Isolation Valve Circuit
1-ERV-402, Power Operated Relief Valve
1-HC-3987B, 11 Auxiliary Feedwater Pump Controller
2-CV-4070, AFW Pump Steam Admission Valve
2-HC-4056A, 21 Atmospheric Dump Valve Controller
B.5.b Inspection Activities (IP Section 02.03) (2 Samples)
The inspectors evaluated the following B.5.b Mitigating Strategies:
- (1) Makeup to Condensate Storage Tank using the B.5.b Pump
- (2) Manually Depressurize Steam Generator and Use Portable Pump
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On September 26, 2019, the inspectors presented the triennial fire protection inspection results to Mr. Mark Flaherty and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.05XT Corrective Action
Documents
20773
21559
2742586
4046035
4067297
248214
248382
256424
257102
267663
268815
275593
Corrective Action
Documents
Resulting from
Inspection
267663-05, -06,
-07
274804
276645
277875
278033
278046
278073
278075
278079
278324
278327
278683
278741
278790
278853
279004
280273
280796
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
281526
281807
281862
281997
282024
282071
282114
282386
Drawings
263-0003
Halon 1301 Fire Suppression System
2E-198, Sheet
28
Connection Diagram Junction Box 2J571
60616B, Sheet 57 Logic Diagram Pressurizer Solenoid Operated Relief
Valves-1ERV402 & 404
60714, Sheet 3
Plant Fire Protection System Turbine, Service Bldgs. &
Intake Structure
60722, Sheet 3
Auxiliary Building Ventilation System
60723, Sheet 4
Ventilation Systems Control Room and Cable Spreading
Room HVAC
60729, Sheet 1
60929, Sheet 1
Loop Diagram 11 AFW Pump Turbine Speed Control
1HC3987A & B
61-199-B, Sheet
9A
Electrical Penetration Assembly Termination 1ZEC1
61001, Sheet 1
Electrical Main Single Line Diagram Final Safety Analysis
Report (FSAR) Fig. No. 8-1
61005
Meter and Relay Diagram 4KV System Unit Buses 11 and
FSAR Fig. No. 8-4
61017
Single Line Diagram Reactor 480V MCC 114R
and 43
61035
Equipment Layout Cable Spreading Room Aux. Bldg. Area
EL.27'-0
61075, Sheet 53
Reactor Auxiliaries Pressurizer Relief 1ERV402
61076, Sheet
2H
Schematic Diagram Reactor Safeguards S.G. 11 Main
Steam Isolation 1CV4043
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
61086, Sheet 1
Schematic Diagram 4KV Bus 11 & 17 Tie Breaker 152-
1103
61086, Sheet 3
Schematic Diagram 4KV Bus 14 Diesel Generator 1B
Feeder Breaker 152-1403
61101, Sheet 43A Connection Panel Isolation Panel 1C43A
61101, Sheet
43D
Wiring and Connection Diagram Aux Feed Water Control
Panel 1C43
2-632-C, Sheet
Loop Diagram Alternate Shut-Down Related Circuits Unit
No. 2 AFW System Throttle, and Miscellaneous Control
Valves
2153, Sheet 33
Barrier Segment Drawing for Plant Elevation 69
2583, Sheet 1
AFW System (Steam)
and 63
2633, Sheet 1
Loop Diagram 21 & 22 Main Steam Line Atmos Dump and
Turbine Bypass 2PT4056 & 2 HIC4056
2730, Sheet 1
Chemical and Volume Control System
63069
Schematic Diagram Turbine Steam Dump and Bypass
Controls
63079, Sheet 55A Schematic Diagram AFW Pumps 21 & 22 Isolation Valves
2CV4070 & 2CV4070A
and 3
63196, Sheet 120
Connection Diagram for 2I/P3938 and 2I/P3939
63196, Sheet 7W
Connection Diagram Solenoid Valves 2SV4070,
2SV4070A, 2SV4071 & 2SV4071A
66065, Sheet 1
Instrument Installation Detail for 2CV3938 & 2CV3939
203, Sheet 4
Electrical Wiring Diagram Panel 1C03 Condensate &
Feedwater Control Board
87303, Sheet 9
Electrical Wiring Diagram Panel 2C03 Condensate &
Feedwater Control Board
M-162
Heating & Ventilation System Auxiliary Building Unit 1 Plan
at Elevation 45'
Engineering
Changes
ECP 14-000070
Protection of Secondary Side Transformers with Excessive
Thermal Overload or Short Circuit Design Issues (NFPA
805 Compliance LAR #15)
ECP-16-000335
Replace Fire Protection Valves
04/26/2016
ECP-17-000653
NSB Modular Building Installation
11/17/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Evaluations
1-ERV402 Cable Selection Worksheets
03/31/2011
1-HC-3987B 11 AFW Pump Controller Cable Selection
Worksheets
06/29/2011
2-CV-4070
AFW Pump Steam Admission Valve Cable Selection
Worksheets
2/22/2011
C0-FRE-F001
Fire Risk Evaluation Report
CA04007
Appendix R Analysis of Inadvertent Lifting of Both
Pressurizer PORVs
CA05974
CFR 50 Appendix R Fire Protection Abnormal Operating
Procedure 9 Simulations
CA07803
Minimum Allowable Reactor Coolant System Temperature
to Support NFPA 805 Transition
ECP-13-000303-
015-6-01
Equivalent Change Technical Evaluation for Acceptability of
The Following 1.5-Hour Fire Doors Installed In 3-Hour Fire
Barriers
ECP-13-000325-
015-6-01
Equivalent Change Technical Evaluation for Acceptability of
Issues Related to Fire Dampers Installed in Fire Barriers
ES199901141
Engineering Evaluation to Summarize Appendix R
Communications Issue
10/14/1999
FP00002
Fire Hazards Analysis Summary Report
NFPA 805-00006
Nuclear Safety Capability Assessment Report (NSCA)
NFPA 805-
00006A
NSCA Analysis Result
and 1
NFPA-805-
00006A
NFPA 805 Transition Project Attachments
and 1
NFPA-805-00008
Non-Power Operation Modes Transition Review
R2215-003-001
NFPA 805 Radioactive Release Review
R2215-021-001
NFPA 805 Chapter 3 Fundamental Fire Protection Program
and Design Elements Review
R2215-022-001
NFPA Code Conformance Review
R2215-043-001
NFPA 805 Effects of Fire Suppression Activities Review
Report
R2215-048-001
Fire Area Review Report (Table B-3 Report)
and 1
R2215-049-001
Recovery Action Feasibility Assessment
and 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Fire Plans
Fire Fighting
Strategy
Unit 1 Cable Spreading Room 306
00300
Fire Fighting
Strategy
Unit 1 West Electrical Penetration Room 423
00400
Fire Fighting
Strategy
Unit 2 Switchgear Room 311
00300
Fire Fighting
Strategy
Unit 2 Switchgear Room 430
00600
Miscellaneous
2019 Annual Fire Fighting Training
Calvert Cliffs Fire Protection Program Health Report
1P2019
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 And 2 -
Issuance of Amendments Regarding Transition to A Risk
Informed, Performance-Based Fire Protection Program in
Accordance With 10 CFR 50.48(c) (CAC NOS. MF2993
AND MF2994)
08/30/2016
Fire Brigade Drill records from 4th quarter 2016 through
2nd quarter 2019
Plant Barrier Impairment Log as of Plant Barrier Impairment
- 19-8-3
Updated Final Safety Analysis Report, Chapter 9.9, Fire
Protection Program Report
U.S. NRC License Amendment and Safety Evaluation
Report
8/30/2016
19-04-006, 19-08-
005, and 19-05-
2
Hot Work Permits
2686762-04
NRC Information Notice 2016-08: Inadequate Work
Practices Resulting in Faulted Circuit Breaker Connections
Safe Shutdown due to a Severe Fire
Fire Protection Codes and Standards
Standard for the Installation of Centrifugal Fire Pumps
1969
Standard on Industrial Fire Brigades
2000
Fire Protection Rule (45 FR 76602, November 19, 1980)
2/20/1981
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Clarification Letter, Fire Protection Rule - Appendix R
03/22/1982
OE-2009-003518
Response to NRC Information Notice 2009-29, Potential
Failure of Fire Water Supply Pumps to Automatically Start
Due To A Fire
2/17/2009
OPEX 4163523
NRC Information Notice 2018-009, Electrical Arc Flash
Caused by Foreign Material Damages Fire Door
11/13/2018
PCR-13-02102
PCR-13-02104
PCR-13-02122
PCR-13-02123
PCR-13-02124
Project No.03-
5980-003
Fire Stop Penetration Tests on Fire Protection System, Slab
No.2
08/15/1980
SA-1-105
Fire Brigade Training,
01100
VTD-D243-1014
Instructions for Installation and Maintenance Consoli
Electromatic Relief Valve Type 31533VX-30 with Bellows,
09/04/1990
Procedures
Calvert Cliffs Nuclear Power Plant Fire Systems Alarm
Manual, Unit One and Two
Control Room Evacuation and Safe Shutdown due to a
Severe Control Room Fire
Safe Shutdown due to a Severe Cable Spreading Room
Fire
Configuration Change Control for Permanent Physical Plant
Changes
Fire Protection Program Configuration Change Review
EDMG-1
Large Area Loss
NFPA 805 Monitoring Program
FM-FP-W-1
Transient Combustible Walkdown/Weekly Fire Marshall
Tour/Weekly B.5.b Checks
Regulatory Review of Proposed Changes to the Approved
NFPA 805 Fire Protection Program
Quality Assurance Topical Report (QATR)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OI-22H
Control Room and Cable Spreading Rooms Ventilation
03000
OI-22H
Switchgear Ventilation and Air Conditioning
2500
OI-27D-2
Station Power 480V System Breaker Lineup
200
Locked Equipment Program
OP-AA-108-105-
1001
MCR and RWCR Equipment Deficiency Management and
Performance Indicator Screening
Fire Drill Performance
OP-AA-201-010-
1001
B.5.b Mitigating Strategies Equipment Expectations
OP-CA-102-106
Operator Response Time Program at Calvert Cliffs
OP-CA-108-3.0
Immediate Actions
00400
OP-CA-201-012-
1001
On-Line Fire Risk Management
201
OP-CA-TRM-100
CCNPP Technical Requirements Manual
PE 1-102-10-O-R
Remote Shutdown Panel Operation Verification
00503
Preventive
Maintenance
Task 01022041
Inspect, Inventory, and Test Run Portable B.5.b Diesel
Pump
08/19/2008
SAG-3
Technical Support Center Severe Accident Guideline:
Inject into Steam Generators
STP O-63-1
Remote Shutdown and Post Accident Monitoring Instrument
Channel Check
STP-F-592-2
Penetration Fire Barrier Inspection
01400
STP-M-499-2
and 45 Switchgear Rooms Halon System Fire
Detection Instruments Functional Test
00301
STP-M-699-2
Functional Test of Halon System for Switchgear Rooms
00800
Emergency Services Training Programs
Technical Support Guideline: Site Capabilities
Self-Assessments
Functional Area Self-Assessment of Fire Protection
Program
08/06/2019
NOSA-CAL-18-
Fire Protection Audit Report
09/14/2018
Work Orders
C93231444
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
C93374514
C93374514
C93589599
C93589599
C93645538
C93645538
C93661670
C93661670
C93677938
C93683576
C93683576
M-80-9333