IR 05000317/2019011

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Triennial Fire Protection Inspection Report 05000317/2019011 and 05000318/2019011
ML19284A518
Person / Time
Site: Calvert Cliffs  Constellation icon.png
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

  1. 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