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
ber 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: DPR-53 and DPR-69 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 Enclosure
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 Type Designation Description or Title Revision or
Procedure Date
71111.05XT Corrective Action 2720773
Documents 2721559
2742586
4046035
4067297
248214
248382
256424
257102
267663
268815
275593
Corrective Action 4267663-05, -06,
Documents -07
Resulting from 4274804
Inspection 4276645
277875
278033
278046
278073
278075
278079
278324
278327
278683
278741
278790
278853
279004
280273
280796
Inspection Type Designation Description or Title Revision or
Procedure Date
281526
281807
281862
281997
282024
282071
282114
282386
Drawings 12263-0003 Halon 1301 Fire Suppression System 11
2E-198, Sheet Connection Diagram Junction Box 2J571 0
28
60616B, Sheet 57 Logic Diagram Pressurizer Solenoid Operated Relief 4
Valves-1ERV402 & 404
60714, Sheet 3 Plant Fire Protection System Turbine, Service Bldgs. & 36
Intake Structure
60722, Sheet 3 Auxiliary Building Ventilation System 18
60723, Sheet 4 Ventilation Systems Control Room and Cable Spreading 55
Room HVAC
60729, Sheet 1 Reactor Coolant System 78
60929, Sheet 1 Loop Diagram 11 AFW Pump Turbine Speed Control 5
1HC3987A & B
61-199-B, Sheet Electrical Penetration Assembly Termination 1ZEC1 2
9A
61001, Sheet 1 Electrical Main Single Line Diagram Final Safety Analysis 50
Report (FSAR) Fig. No. 8-1
61005 Meter and Relay Diagram 4KV System Unit Buses 11 and 36
FSAR Fig. No. 8-4
61017 Single Line Diagram Reactor 480V MCC 114R 42 and 43
61035 Equipment Layout Cable Spreading Room Aux. Bldg. Area 33
EL.27'-0
61075, Sheet 53 Reactor Auxiliaries Pressurizer Relief 1ERV402 22
61076, Sheet Schematic Diagram Reactor Safeguards S.G. 11 Main 11
2H Steam Isolation 1CV4043
Inspection Type Designation Description or Title Revision or
Procedure Date
61086, Sheet 1 Schematic Diagram 4KV Bus 11 & 17 Tie Breaker 152- 26
1103
61086, Sheet 3 Schematic Diagram 4KV Bus 14 Diesel Generator 1B 28
Feeder Breaker 152-1403
61101, Sheet 43A Connection Panel Isolation Panel 1C43A 9
61101, Sheet Wiring and Connection Diagram Aux Feed Water Control 3
43D Panel 1C43
2-632-C, Sheet Loop Diagram Alternate Shut-Down Related Circuits Unit 0
No. 2 AFW System Throttle, and Miscellaneous Control
Valves
2153, Sheet 33 Barrier Segment Drawing for Plant Elevation 69 0
2583, Sheet 1 AFW System (Steam) 57 and 63
2633, Sheet 1 Loop Diagram 21 & 22 Main Steam Line Atmos Dump and 14
Turbine Bypass 2PT4056 & 2 HIC4056
2730, Sheet 1 Chemical and Volume Control System 82
63069 Schematic Diagram Turbine Steam Dump and Bypass 20
Controls
63079, Sheet 55A Schematic Diagram AFW Pumps 21 & 22 Isolation Valves 1 and 3
2CV4070 & 2CV4070A
63196, Sheet 120 Connection Diagram for 2I/P3938 and 2I/P3939 0
63196, Sheet 7W Connection Diagram Solenoid Valves 2SV4070, 2
2SV4070A, 2SV4071 & 2SV4071A
66065, Sheet 1 Instrument Installation Detail for 2CV3938 & 2CV3939 2
203, Sheet 4 Electrical Wiring Diagram Panel 1C03 Condensate & 31
Feedwater Control Board
87303, Sheet 9 Electrical Wiring Diagram Panel 2C03 Condensate & 11
Feedwater Control Board
M-162 Heating & Ventilation System Auxiliary Building Unit 1 Plan 15
at Elevation 45'
Engineering ECP 14-000070 Protection of Secondary Side Transformers with Excessive 0
Changes 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 12 NSB Modular Building Installation 11/17/2017
Inspection Type Designation Description or Title Revision or
Procedure Date
Engineering 1-ERV402 Cable Selection Worksheets 03/31/2011
Evaluations 1-HC-3987B 11 AFW Pump Controller Cable Selection 06/29/2011
Worksheets
2-CV-4070 AFW Pump Steam Admission Valve Cable Selection 02/22/2011
Worksheets
C0-FRE-F001 Fire Risk Evaluation Report 2
CA04007 Appendix R Analysis of Inadvertent Lifting of Both 0
Pressurizer PORVs
CA05974 10 CFR 50 Appendix R Fire Protection Abnormal Operating 0
Procedure 9 Simulations
CA07803 Minimum Allowable Reactor Coolant System Temperature 0
to Support NFPA 805 Transition
ECP-13-000303- Equivalent Change Technical Evaluation for Acceptability of 0
015-6-01 The Following 1.5-Hour Fire Doors Installed In 3-Hour Fire
Barriers
ECP-13-000325- Equivalent Change Technical Evaluation for Acceptability of 0
015-6-01 Issues Related to Fire Dampers Installed in Fire Barriers
ES199901141 Engineering Evaluation to Summarize Appendix R 10/14/1999
Communications Issue
FP00002 Fire Hazards Analysis Summary Report 2
NFPA 805-00006 Nuclear Safety Capability Assessment Report (NSCA) 1
NFPA 805- NSCA Analysis Result 0 and 1
00006A
NFPA-805- NFPA 805 Transition Project Attachments 0 and 1
00006A
NFPA-805-00008 Non-Power Operation Modes Transition Review 2
R2215-003-001 NFPA 805 Radioactive Release Review 2
R2215-021-001 NFPA 805 Chapter 3 Fundamental Fire Protection Program 2
and Design Elements Review
R2215-022-001 NFPA Code Conformance Review 1
R2215-043-001 NFPA 805 Effects of Fire Suppression Activities Review 1
Report
R2215-048-001 Fire Area Review Report (Table B-3 Report) 0 and 1
R2215-049-001 Recovery Action Feasibility Assessment 0 and 2
Inspection Type Designation Description or Title Revision or
Procedure Date
Fire Plans Fire Fighting Unit 1 Cable Spreading Room 306 00300
Strategy
Fire Fighting Unit 1 West Electrical Penetration Room 423 00400
Strategy
Fire Fighting Unit 2 Switchgear Room 311 00300
Strategy
Fire Fighting Unit 2 Switchgear Room 430 00600
Strategy
Miscellaneous 2019 Annual Fire Fighting Training
Calvert Cliffs Fire Protection Program Health Report 1P2019
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 And 2 - 08/30/2016
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)
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 50
Protection Program Report
U.S. NRC License Amendment and Safety Evaluation 8/30/2016
Report
19-04-006, 19-08- Hot Work Permits
005, and 19-05-
2
2686762-04 NRC Information Notice 2016-08: Inadequate Work
Practices Resulting in Faulted Circuit Breaker Connections
AOP-9X-2 Safe Shutdown due to a Severe Fire 1
ES-056 Fire Protection Codes and Standards 3
NFPA-20 Standard for the Installation of Centrifugal Fire Pumps 1969
NFPA-600 Standard on Industrial Fire Brigades 2000
NRC Generic Fire Protection Rule (45 FR 76602, November 19, 1980) 02/20/1981
Letter 81-12
Inspection Type Designation Description or Title Revision or
Procedure Date
NRC Generic Clarification Letter, Fire Protection Rule - Appendix R 03/22/1982
Letter 81-12
OE-2009-003518 Response to NRC Information Notice 2009-29 , Potential 12/17/2009
Failure of Fire Water Supply Pumps to Automatically Start
Due To A Fire
OPEX 4163523 NRC Information Notice 2018-009, Electrical Arc Flash 11/13/2018
Caused by Foreign Material Damages Fire Door
PCR-13-02102
PCR-13-02104
PCR-13-02122
PCR-13-02123
PCR-13-02124
Project No .03- Fire Stop Penetration Tests on Fire Protection System, Slab 08/15/1980
5980-003 No.2
SA-1-105 Fire Brigade Training, 01100
VTD-D243-1014 Instructions for Installation and Maintenance Consoli 09/04/1990
Electromatic Relief Valve Type 31533VX-30 with Bellows,
Procedures 1C24B-ALM Calvert Cliffs Nuclear Power Plant Fire Systems Alarm 46
Manual, Unit One and Two
AOP-9A-1 Control Room Evacuation and Safe Shutdown due to a 19
Severe Control Room Fire
AOP-9B-1 Safe Shutdown due to a Severe Cable Spreading Room 23
Fire
CC-AA-103 Configuration Change Control for Permanent Physical Plant 31
Changes
CC-AA-209 Fire Protection Program Configuration Change Review 6
CC-AA-211 Fire Protection Program 8
EDMG-1 Large Area Loss 0
ER-AA-610-1003 NFPA 805 Monitoring Program 0
FM-FP-W-1 Transient Combustible Walkdown/Weekly Fire Marshall 3
Tour/Weekly B.5.b Checks
LS-AA-128-101 Regulatory Review of Proposed Changes to the Approved 1
NFPA 805 Fire Protection Program
NO-AA-10 Quality Assurance Topical Report (QATR) 94
Inspection Type Designation Description or Title Revision or
Procedure Date
OI-22H Control Room and Cable Spreading Rooms Ventilation 03000
OI-22H Switchgear Ventilation and Air Conditioning 02500
OI-27D-2 Station Power 480V System Breaker Lineup 02200
OP-AA-108-103 Locked Equipment Program 2
OP-AA-108-105- MCR and RWCR Equipment Deficiency Management and 6
1001 Performance Indicator Screening
OP-AA-201-003 Fire Drill Performance 17
OP-AA-201-010- B.5.b Mitigating Strategies Equipment Expectations 3
1001
OP-CA-102-106 Operator Response Time Program at Calvert Cliffs 7
OP-CA-108-3.0 Immediate Actions 00400
OP-CA-201-012- On-Line Fire Risk Management 00201
1001
OP-CA-TRM-100 CCNPP Technical Requirements Manual 3
PE 1-102-10-O-R Remote Shutdown Panel Operation Verification 00503
Preventive Inspect, Inventory, and Test Run Portable B.5.b Diesel 08/19/2008
Maintenance Pump
Task 01022041
SAG-3 Technical Support Center Severe Accident Guideline: 0
Inject into Steam Generators
STP O-63-1 Remote Shutdown and Post Accident Monitoring Instrument 35
Channel Check
STP-F-592-2 Penetration Fire Barrier Inspection 01400
STP-M-499-2 27 and 45 Switchgear Rooms Halon System Fire 00301
Detection Instruments Functional Test
STP-M-699-2 Functional Test of Halon System for Switchgear Rooms 00800
TQ-AA-173 Emergency Services Training Programs 3
TSG-3 Technical Support Guideline: Site Capabilities 0
Self-Assessments Functional Area Self-Assessment of Fire Protection 08/06/2019
Program
NOSA-CAL-18- Fire Protection Audit Report 09/14/2018
Work Orders C93231444
Inspection Type Designation Description or Title Revision or
Procedure Date
C93374514
C93374514
C93589599
C93589599
C93645538
C93645538
C93661670
C93661670
C93677938
C93683576
C93683576
M-80-9333
11