IR 05000317/2018010

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Design Bases Assurance Inspection (Teams) Report 05000317/2018010 and 05000318/2018010
ML18292A579
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 10/19/2018
From: Mel Gray
Division of Reactor Safety I
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
References
IR 2018010
Download: ML18292A579 (13)


Text

October 19, 2018

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT - DESIGN BASES ASSURANCE INSPECTION (TEAMS) REPORT 05000317/2018010 AND 05000318/2018010

Dear Mr. Hanson:

On October 5, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2. The NRC inspectors discussed the results of this inspection with Mr. Todd Tierney, Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any findings or more-than-minor violations.

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 the NRCs Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety

Docket Nos.

50-317 and 50-318 License Nos. DPR-53 and DPR-69

Enclosure:

Inspection Report 05000317/2018010 and 05000318/2018010

Inspection Report

Docket Numbers:

50-317 and 50-318

License Numbers:

DPR-53 and DPR-69

Report Numbers:

05000317/2018010 and 05000318/2018010

Enterprise Identifier:

I-2018-010-0013

Licensee:

Exelon Generation Company, LLC

Facility:

Calvert Cliffs Nuclear Power Plant, Units 1 and 2

Location:

Lusby, MD

Inspection Dates:

September 17, 2018, through October 5, 2018

Inspectors:

J. Schoppy, Senior Reactor Inspector, Division of Reactor Safety

(DRS), Team Leader

J. Lilliendahl, Senior Emergency Response Coordinator, DRS

M. Orr, Reactor Inspector, DRS

S. Pindale, Senior Reactor Inspector, DRS

C. Baron, NRC Mechanical Contractor

S. Kobylarz, NRC Electrical Contractor

Approved By:

M. Gray, Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at

Calvert Cliffs Nuclear Power Plant Units 1 and 2 by conducting a design bases assurance inspection 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.

No findings or more-than-minor violations were identified.

INSPECTION SCOPES

This inspection was conducted using the appropriate portions of the inspection procedure in effect at the beginning of the inspection unless otherwise noted. Currently approved inspection procedures 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 inspection procedure requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program - Operations Phase. The team 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

===71111.21M - Design Bases Assurance Inspection (Teams)

The team evaluated the following components, permanent modifications, and operating experience during the weeks of September 17, 2018, and October 1, 2018.

For the components, the team reviewed the attributes listed in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations. Specific documents reviewed are listed in the Documents Reviewed section.

Components===

  • Unit 2 No. 21 High Pressure Safety Injection Pump o Material condition and installed configuration (e.g., visual inspection/walkdown)o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o System health report, maintenance effectiveness and records, and corrective action history o Equipment/environmental controls and qualification o Design calculations o Surveillance testing and recent test results o System and component level performance monitoring o Equipment protection from fire, flood, and water intrusion or spray o Heat removal cooling water and ventilation

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

  • Unit 1 No. 11 125 Vdc Battery o Material condition and installed configuration (e.g., visual inspection/walkdown)o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o System health report, maintenance effectiveness and records, and corrective action history o Operator actions o Design calculations o Surveillance testing and recent test results o Environmental conditions o Contactor and fuse ratings; Component adequacy for minimum voltage o Equipment protection from fire, flood, and water intrusion or spray o Heat removal cooling water and ventilation

The team used Appendix B guidance for Instrumentation, Circuit Breakers and Fuses, Cables, Electric Loads, and As-Built System.

  • Unit 1 No. 14 4160V Bus

o Material condition and installed configuration (e.g., visual inspection/walkdown)o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o System health report, maintenance effectiveness and records, and corrective action history o Control logic o Design calculations o Surveillance testing and recent test results o Equipment protection (sealing of cable and conduits)o Environmental conditions o Protection coordination; Load in-rush and full load current o Range, accuracy, and setpoint of installed relays o Equipment protection from fire, flood, and water intrusion or spray

The team used Appendix B guidance for Instrumentation, Circuit Breakers and Fuses, Cables, Electric Loads, and Motor Control Centers (MCCs).

  • Unit 1 Containment Sump Recirculation Valve 1-MOV-4144

o Material condition and installed configuration (e.g., visual inspection/walkdown)o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o System health report, maintenance effectiveness and records, and corrective action history o Equipment/environmental controls and qualification o Operator actions o Design calculations o Surveillance testing and recent test results o Equipment protection (sealing of cable and conduits)o Equipment protection from fire, flood, and water intrusion or spray The team used Appendix B guidance for Valves, Instrumentation, Cables, Electric Loads, and As-Built System.

Component, Large Early Release Frequency (1 Sample)

o Material condition and installed configuration (e.g., visual inspection/walkdown)o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o Maintenance effectiveness and records, and corrective action history o Operator actions o Design calculations o Surveillance testing and recent test results o Environmental conditions o Equipment protection from fire, flood, and water intrusion or spray o Heat removal cooling water and ventilation

The team used Appendix B guidance for Instrumentation, Motor Control Centers (MCCs),and As-Built System.

Permanent Modifications (5 Samples)

  • ECP-14-000064; ESR-13-000829 - 4kV Normal Incoming Supply Feeder Breaker Modification
  • ECP-14-000159: AFW Emergency Ventilation System Upgrade
  • ECP-15-000727: ESR-15-002466 - Provide Engineering to Raise RAS Setpoint
  • ECP-16-000353: ESR-16-000050 - Enable RWT Outlet MOVs 4142 and 4143 to Close Automatically on a RAS
  • ECP-16-000462: Update Fairbanks Morse Trip Circuit Design

Operating Experience (3 Samples)

  • Prairie Island 2 10CFR21 (2017-45-00), EDG High Crankcase Pressure Switch Mounting Bracket Fastener System Failure, dated September 14, 2017

INSPECTION RESULTS

No findings or more-than-minor violations were identified.

EXIT MEETINGS AND DEBRIEFS

The team verified no proprietary information was retained or documented in this report.

  • On October 5, 2018, the team presented the Design Bases Assurance Inspection (Teams)results to Mr. Todd Tierney, Plant Manager, and other members of Exelon staff.

DOCUMENTS REVIEWED

71111.21M - DESIGN BASES ASSURANCE INSPECTION (TEAMS)

Audits and Self-Assessments

04058864, Readiness Review for 2018 NRC Design Bases Assurance Inspection Self

Assessment, dated 6/1/18

Calculations

95-0188, Seismic II/I Evaluation of ILRT Piping to Containment Penetration #50, Revision 0

A01080.F02-002, Pressure Locking Thrust Calculation, Revision 1

CA0772, AC Load Flow Study, Revision 2

CA04079, Comparison of Available and Required NPSH for the Safety Injection and

Containment Spray Pumps during Post-RAS Operation, Revision 0

CA04691, Circulating Water Flooding in the Turbine Building through a Ruptured Expansion

Joint, Revision 0

CA07773, AFW Pump Room Cooler Sizing, Revision 0

CA10206, Refueling Water Tank Level RAS Setpoint Determination, Revision 0

E-85-010, 125VDC Battery 01, 11, 12, 21 and 22 Fault Current Calculation, Revision 2

E-87-009, 125VDC System Short-Circuit Review, Revision 1

E-89-005, SBO & LOCA Battery Duty Cycle - Bus 11, Revision 4

E-89-042, Voltage Drop in DC Systems, Revision 4

E-90-033, Master Fault Calculation, Revision 4

E-90-038, MOV Minimum Voltages Lasting More than 5 Seconds, Revision 11

E-90-071, 4kV Bus 14 Protective Devices, Revision 6

I-94-003, Refueling Water Tank Level(s) and Capacity, Revision 4

M-91-044, MOV Weak Link Analysis, Revision 2

M-90-193, Flood Heights Resulting from a Pipe Break in the Turbine Building, Revision 0

M-91-197, Maximum Line and Differential Pressure Valves 1 & 2-MOV-4144 & 4145 May

Experience During Operation, Revision 0

Completed Surveillance, Performance, and Functional Tests

2013-29, Unit 2 Integrated Leakage Rate Test Report, dated 5/8/13

OP-6, PreStartup Checkoff, performed 3/15/18

STP-M-152-1, 11 Station Battery Weekly Check, performed 8/30/18

STP-M-352-1, 11 Station Battery Quarterly Check, performed 6/23/16, 9/22/16, 12/21/16,

3/23/17, 6/22/17, 9/21/17, 12/19/17, 3/22/18, and 6/21/18

STP M544A-2, #21 Penetration Room Exhaust Filter Test, performed 4/6/18

STP M5445-2, #22 Penetration Room Exhaust Filter Test, performed 5/8/18

STP-M-552-1, 11 Station Battery Service Test, performed 11/5/13, 4/1/16, and 4/9/18

STP M-651A-2A, SIAS B-10 Trip Bypass for 2A Diesel Generator, performed 7/31/18

STP M-651A-2B, SIAS B-10 Trip Bypass for 2B Diesel Generator, performed 1/16/15 and

5/16/17

STP M-651C-1B, SIAS B-10 Trip Bypass for 1B Diesel Generator, performed 12/6/16

STP O-4B-1, B Train Integrated Engineered Safety Features Test, performed 3/17/18

STP O-5A21-2, 21 Auxiliary Feedwater Pump Quarterly Surveillance Test, performed 7/25/18

STP O-7A-1, "A" Train Engineered Safety Features Logic Test, performed 5/1/18

STP O-7B-2, B Train Engineered Safety Features Logic Test, performed 10/20/17

STP O-7C-2, A Train Engineered Safety Features Logic Test, performed 5/3/18

STP O-14A-2, A Train Safety Injection, Containment Spray, and SDC Gas Accumulation Test,

performed 7/5/18

STP O-55-2, Unit 2 Containment Integrity Verification Mode 1-4, performed 7/30/18

STP O-70-2, Monthly Test of "A" Train Containment Cooling Units, Iodine Removal Units, &

Penetration Room Exhaust Filter, performed 5/22/18

STP O-71-2, Monthly Test of "B" Train Containment Cooling Units, Iodine Removal Units, &

Penetration Room Exhaust Filter, performed 6/4/18

STP O-73G-2, HPSI Pump Large Flow Test, performed 2/19/17

STP O-731A-2, A-Train HPSI Pump and Check Valve Operability Test, performed 8/1/18

STP XM-503-1 Calibration Check of #14 4KV Bus LOCI and Shutdown Sequencer, performed

3/15/16

TURB-04, AFW Turbine Overspeed Trip Adjustment, performed 3/17/18

Completed Preventive Maintenance, Calibrations, and Inspections

1-44-2-O-Q, Condensate Level Switch, performed 4/3/18

2-44-2-O-Q, Condensate Level Switch, performed 2/22/18

Initial Scoping Report 0027, Aging Related Degradation Inspection Check List for Identification

of Aging Effects, Unit 2 5 Fan Room, dated 1/4/11

Corrective Action Issue Reports (IRs)

4-024-386

2009-6043

2009-6251

2009-6252

2014-0396

1700131

1700348

1786965

1803213

1803587

1803588

1803624

1803831

1851368

1852812

1855691

1856563

1856715

1856779

1857138

2010203

2402107

2409006

2454706

2464168

2482579

2494780

2497552

2498947

28973

2552315

2552673

2554032

2555303

2574382

2574385

2580916

2581489

2581500

2589648

2595124

2633221

2639867

2644934

2668740

2676847

2682276

2689863

2703487

2714272

3980419

4007684

25294

29406

4033503

4054408

4056915

4058864

4063744

4064642

4065747

4090677

4106197

4111139

4113435

4113450

4113717

4114625

4116170

4130071

4144777

4149542

4154234

4155119

4161927

4170441*

4175196*

4175295*

4177713*

4178917*

4179072*

4179914*

4179941*

4180135*

4180558*

4180563*

4180608*

  • IR written as a result of this inspection

Drawings

61-076-B, Schematic Diagram High Pressure Safety Injection Pump 13, Revision 6

2083-34, Terry Steam Turbine, Revision 1

2103-0001, High Pressure Safety Injection Pump Outline Dimension, Revision 4

2103-0014, Piping-Bearing and Stuffing Box w/Seal Circulation, Revision 5

33810, High Pressure Safety Injection Pump Performance Curve, dated 12/19/69

60307, Area & Equipment Drains Containment & Aux. Bldg. Unit 1 Plan at El 27, Revision 8

60710 Sh.1, Component Cooling System, Revision 46

60722 Sh. 2, Auxiliary Building Ventilation System, Revision 48

60722 Sh. 3, Auxiliary Building Ventilation System, Revision 17

60723 Sh. 2, Ventilation Systems Containment Turbine and Penetration Rooms, Revision 38

60731 Sh. 1, Safety Injection and Containment Spray Systems, Revision 94

60733 Sh. 3, Miscellaneous Drain & Sump Piping Turbine & Diesel Bldg. and Yard, Revision 64

61001 Sh. 1, Electrical Main Single Line Diagram, Revision 48

61005, Meter and Relay Diagram 4KV System Unit Buses 11 and 14, Revision 36

61022 Sh. 1, Single Line Diagram 120VAC Vital System, Revision 57

61024 Sh. 1, Single Line Diagram 125VDC Vital System Bus 11, Revision 57

61024 Sh. 2, Single Line Diagram 125VDC Vital System Bus 14, Revision 3

61024 Sh. 3, Single Line Diagram 125VDC Vital System Bus 15, Revision 3

61071 Sh. 7, Schematic Diagram 4KV Bus 14 Feeder Breaker 152-1401, Revision 19

61071 Sh. 8, Schematic Diagram 4KV Bus 14 Feeder Breaker 152-1414, Revision 20

61076 Sh. 4, Schematic Diagram High Pressure Safety Injection Pump 12, Revision 18

61076 Sh. 7, Schematic Diagram High Pressure Safety Injection Pump 13, Revision 17

61076 Sh. 30B, Schematic Diagram Reactor Safeguards Containment Sump Discharge Valve

1MOV4144, Revision 4

61076 Sh. 31, Schematic Diagram Reactor Safeguards CS & SI Pumps Recirc Valve

1MOV659, Revision 18

61740 Sh. 1, Containment Liner Plan, Elevation and Penetrations, Revision 22

61740 Sh. 2, Containment Structure Penetrations, Revision 8

2151 Sh. 1, Appendix R Separation Requirements Aux. Bldg. & Containment Structure Floor

Plan at El. 27, Revision 10

2731 Sh. 1, Safety Injection and Containment Spray Systems, Revision 84

63076 Sh. 31, Reactor Safeguards CS and SI Pumps, Recirc Valves 2MOV659, Revision 14

63076 Sh. 31A, Reactor Safeguards CS and SI Pumps, Recirc Valves 2MOV660, Revision 2

64311, Simplified System Drawing - Safety Injection and Containment Spray, Revision 14

64316, Containment and Penetration Room Ventilation SL-065A, Revision 12

84311, Safety Injection and Containment Spray System, Revision 15

ECP-16-0462-CN-001, Update Fairbanks Morse EDG Trip Circuit Design, Revision 0

ECP-16-0462-CN-006, Update Fairbanks Morse EDG Trip Circuit Design, Revision 0

ECP-16-0462-PCN-1002-CN-005, Update Fairbanks Morse EDG Trip Circuit Design, Revision 0

N2010-FCU-4-FAB Sh. 5, Auxiliary Feedwater Pump Room Emergency Cooler/Fan Coil Unit

Fabrication Drawing, Revision 1

Engineering Evaluations

1MOV4144, MIDACALC Results - AC Motor Operated GL96-05 Gate Valve, Revision 2

Comments on Calculation CA07773, AFW Pump Room SR Ventilation Gothic Evaluation and

Unit Sizing, dated 4/27/12

ECP-12-000318, AFW Pump Room Emergency Ventilation System, Revision 0

ECP-14-000064 Form 7 and 7A, Design Change Technical Evaluation, Revision 3

ECP-14-000064 Form 9, Installation Testing Instructions, Revision 4

ECP-14-000159-015-7-01, Form 7, Design Change Technical Evaluation, Revision 3

ECP-14-000159-015-7A-01, Form 7A, Design Change Technical Evaluation Continuation,

Revision 8

ECP-14-000159-5059-01, AFW Pump Room Emergency Ventilation System Upgrade 50.59

Screen, Revision 9

ECP-15-000023, Technical Evaluation for Connection Resistance Methodology, Revision 0

ECP-15-000727, Raise RAS Setpoint, Revision 2

ECP-16-000353, Enable RWT Outlet MOVs 4142 and 4143 to Close Automatically on a RAS,

Revision 0

ECP-16-000462, Update Fairbanks Morse Trip Circuit Design, Revision 0

ECP-17-000523, Vortexing in the Refueling Water Tank Technical Evaluation, Revision 0

ES-001, Flooding, Revision 5

ES-034, Electrical Device Settings, Revision 1

ES199801327, MOV Pressure Locking Evaluation, Revision 0

Operability Evaluation 17-002, 2CV5171: 21 ECCS Cooler Outlet Control Valve, Revision 0

Project No. 11562-061, AFW Pump Room Elevated Temperature Issue - NRC Comment

Resolution, Revision 0

QL00847, Barrier Function Table, Revision 2

SE00558, Automatic Closure of the RWT Outlet Valve MOVs 50.59 Evaluation, Revision 0

Maintenance Work Orders

C12023668

C20072161

C20074962

C20074963

C20083624

C90728304

C90767769

C91408624

C91426157

C91909242

C91910467

C91944763

C91945787

C92413803

C92543727

C92813807

C92935353

C92957877

C92957878

C92957879

C92957880

C92967907

C93110332

C93445185

C93466890

C93476179

C93509570

C93549452

C93609295

C93622647

C93640623

C93644323

C93644324

Miscellaneous

004, 4160 VAC Electrical Power Distribution System Description, Revision 3

2, Auxiliary Building Ventilation System Description, Revision 7

2-1401, CCNPP Protective Relaying Setting Sheet, Revision 3

2-1410/2/SB2, CCNPP Protective Relaying Setting Sheet, Revision 2

2-1414, CCNPP Protective Relaying Setting Sheet, Revision 3

A116, NRR Letter: Request for Additional Information Regarding Generic Letter 2004-02, dated

7/23/10

Fairbanks Morse Owners Group, Maintenance Guidelines, Voltage Regulator and Excitation

System Maintenance Recommendations, Revision 4

Master Calibration Data Package for 2-PS-4779, dated 2/3/17

Normal and Special (Abnormal) Operations Procedures

1C10-ALM, ESFAS 13 Alarm Manual, Revision 51

1C19-ALM, 13KV & 4KV Essential Feeder Bkrs Contr Board Alarm Manual, Revision 40

1C62/2C62/2C61, 1B/2A/2B Diesel Generator Alarm Manual, Revision 10

AOP-3B, Abnormal Shutdown Cooling Conditions, Revision 30

AOP-71, Loss of 4KV, 480 Volt or 208/120 Volt Instrument Bus Power, Revision 33

EOP-3, Loss of All Feedwater, Revision 23

EOP-5, Loss of Coolant Accident, Revision 30

EOP-8, Functional Recovery Procedure, Revision 41

OI-3A, Safety Injection and Containment Spray, Unit 2, Revision 35

OI-11A, Condensate System, Revision 43

OI-21A, 2A Diesel Generator Operating Instructions, Revision 25

OI-22G, Penetration Room Exhaust System, Revision 6

OI-26A, 125 Volt Vital DC, Revision 21

OI-27C, 4.16 KV System, Revision 28

OI-32A, Auxiliary Feedwater System, Unit 1, Revision 39

OI-32A, Auxiliary Feedwater System, Unit 2, Revision 32

OP-6, PreStartup Checkoff, Revision 53

Operating Experience

NRC Information Notice 2014-03: Turbine-Driven Auxiliary Feedwater Pump Overspeed Trip

Mechanism Issues, dated 2/25/14

Report of Defect per 10CFR21, Basler Electric SBSR Automatic Voltage Regulator Card Solder

Joints, dated 9/21/07

Procedures

BUS-014K, 4 KV Buses 13 and 14 Inspection, Testing and Cleaning, Revision 1

E-10, Testing and Adjustment of Agastat Relays, Revision 5

ER-AA-200-1001, Equipment Classification, Revision 4

ER-CA-450, Structure and System Walkdowns, Revision 0

FTE-59, Periodic Maintenance, Calibration and Functional Testing of Protective Relays,

Revision 8

FTM-11, Rotating Equipment Vibration Monitoring, Revision 3

HVAC-03, Inspection and Replacement of V-Belts, Revision 8

LS-AA-104, Exelon 50.59 Review Process, Revision 10

LS-AA-104-1000, 50.59 Resource Manual, Revision 12

MN-1-209, Predictive Maintenance Program, Revision 7

NSWP-S-06, Core Drilling, Revision 1

OP-CA-102-106, Operator Response Time Program at Calvert Cliffs, Revision 6

TURB-04, AFW Turbine Overspeed Trip Adjustment, Revision 5

Risk and Margin Management

Plant Risk Information e-Book for Calvert Cliffs Nuclear Power Plant, dated 3/1/17

Risk-Informed Inspection Notebook for Calvert Cliffs Nuclear Power Plant Units 1 and 2,

Revision 2.1a

System Health Reports, System Walkdowns, & Trending

HPSI Pump IST Trend Data, dated 1/20/98 - 2/6/18

Auxiliary Feedwater (System 036) System Health Report, dated 7/25/18

High Pressure Injection (System 052) System Health Report, dated 7/23/18

MRFF/MPFF Report Data, 2013 - 2017

Unit 1 and Unit 2 AFW Pump Room Temperature Logs, 7/31/17 - 8/10/18

Vendor Technical Manuals & Specifications

2400-206-1006, GE Magne-Blast Circuit Breaker Instructions GEI-88771D, Revision 0

15138-002-1001, Installation and Operating Instructions for GNB Lead-Calcium Batteries,

Revision 8

ES200800209, Borg-Warner High Pressure Heat Exchanger, dated 11/1/84

Installation, Operation and Maintenance for Bingham Pump Type MSD, dated 11/1/84

VTD 12083-010-1017, Terry Corporation Std Instructions, Section 7, dated 12/9/91