IR 05000220/2020010

Design Basis Assurance Inspection (Teams) Inspection Report 05000220/2020010 and 05000410/2020010

ML20329A040
Person / Time
Site:	Nine Mile Point
Issue date:	11/24/2020
From:	Mel Gray Engineering Region 1 Branch 1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Gray M
References
IR 2020010
Download: ML20329A040 (12)

Text

November 24, 2020

SUBJECT:

NINE MILE POINT NUCLEAR STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000220/2020010 AND 05000410/2020010

Dear Mr. Hanson:

On November 5, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station and discussed the results of this inspection with Mr. Peter Orphanos, Site Vice President, 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, X /RA/

Signed by: Melvin K. Gray Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000220 and 05000410 License Nos. DPR-63 and NPF-69

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000220 and 05000410 License Numbers: DPR-63 and NPF-69 Report Numbers: 05000220/2020010 and 05000410/2020010 Enterprise Identifier: I-2020-010-0027 Licensee: Exelon Generation Company, LLC Facility: Nine Mile Point Nuclear Station, Units 1 and 2 Location: Oswego, NY Inspection Dates: October 19, 2020 to November 5, 2020 Inspectors: E. Andrews, Health Physicist J. Brand, Reactor Inspector L. Dumont, Reactor Inspector J. Lilliendahl, Senior Emergency Response Coordinator B. Pinson, Reactor Inspector J. Schoppy, Senior Reactor Inspector J. Schussler, Senior Resident Inspector Approved By: Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Nine Mile Point Nuclear Station, 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)

=

(1) Unit 2 Reactor Core Isolation Cooling Pump and Turbine (2ICS*P1)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Equipment/environmental controls and qualification

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• System and component level performance monitoring

• Equipment protection from fire, flood, and water intrusion or spray

• Heat removal cooling water and ventilation The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(2) Unit 2 4 KV Division I Emergency Bus (2ENS*SWG101)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Control logic

• Protective relaying and coordination

• Design calculations

• Surveillance testing and recent test results

• Environmental conditions

• Contactor and fuse ratings; component adequacy for minimum voltage

• Equipment protection from fire, flood, and water intrusion or spray

• Heat removal cooling water and ventilation The team used Appendix B guidance for Instrumentation, Circuit Breakers and Fuses, Cables, Electric Loads, and Motor Control Centers (MCCs).

(3) Unit 1 Battery Board 11 (PB-BB11)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Control logic

• Design calculations

• Surveillance testing and recent test results

• Environmental conditions

• Contactor and fuse ratings; component adequacy for minimum voltage

• Protection coordination; load in-rush and full load current

• Range, accuracy, and setpoint of installed instrumentation

• 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).

(4) Unit 2 125 Vdc Battery 2A (2BYS*BAT2A)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Control logic

• Design calculations

• Surveillance testing and recent test results

• Equipment protection (sealing of cable and conduits)

• Environmental conditions

• Contactor and fuse ratings; component adequacy for minimum voltage

• Protection coordination; load in-rush and full load current

• Range, accuracy, and setpoint of installed instrumentation

• 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 As-Built System.

(5) Unit 2 Reactor Core Isolation Cooling Injection Valve (2ICS*MOV126)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Equipment/environmental controls and qualification

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• Equipment protection (sealing of cable and conduits)

• Equipment protection from fire, flood, and water intrusion or spray The team used Appendix B guidance for Valves, Instrumentation, and As-Built System.

Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)

(1) Unit 1 Suppression Chamber

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Heat removal

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• Process medium (water level and temperature)

• Component degradation The team used Appendix B guidance for Instrumentation and As-Built System.

Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)

(1) 00251528, Emergency Diesel Generators, Mobilgard' 410NC Lubricating Oil

(2) ECP-16-000514, Replace the Unit 2 Div. I & II Emergency Diesel Generator Starting Air System Air Dryers with New Membrane Air Dryers

(3) ECP-16-000799, Removal of Excessive Engine Vibration Trip Circuitry (2EGS-WEV113 & 2EGS-WEV213) for 2EGS*EG1 and 2EGS*EG3 and Associated Annunciators

(4) ECP-18-000187, Harden SFC Function by Removing Remote Manual Function of 2SFC*HV6A, HV6B, HV37A, HV37B

(5) ECP-18-000259, Remove Division 1 and Division 2 Synchronous Motor Pull-Out Relay

(6) ECP-19-000522, U1 EDG 102/103 Fuel Oil Storage Level Indicating System and Oil Spill Prevention System Upgrade

Review of Operating Experience Issues (IP Section 02.06) (3 Samples)

(1) NRC Information Notice 2018-07: Pump/Turbine Bearing Oil Sight Glass Problems

(2) Engine Systems Inc. Part 21 Reports: EMD Fuel Injector - Cracked Spray Tip, P/N 5229250 and EMD Fuel Injectors - Seized Plunger and Bushing

(3) GE Hitachi Report made in accordance with 10CFR Part 21 - Nameplate Discrepancy in IAC Time Overcurrent Relays

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On November 5, 2020, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Peter Orphanos, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations 125VDCDISTSYS 125VDC Distribution System Analysis Revision 0

25VDCSYSTEMELAP Battery 11 and 12 Load Shed Coping Time for ELAP Revision 0

Event

A10.1-AD-008 Back-Calculation of Valve Factor from EPRI PPM Revision 0

Calculated Required Thrust

A10.1-H-060 RCIC Pump Performance Test Acceptance Criteria-Lube Revision 0

Oil Cooler Max. Flow Increase

A10.1H4 RCIC Suction Line Size & NPSHa Verification (Suction Revision 0

from Suppression Pool)

EC-032 Diesel Generator Loading Revision 12

EC-042 Verification of Adequacy of Division 1 Battery Revision 11

2BYS*BAT2A and Battery Chargers 2BYS*BAT2A1 &

2A2

EC-129 Plant Emergency Battery Capability for Station Blackout Revision 4

EC-151 Auxiliary System Performance Using ETAP PowerStation Revision 8

EC-154 Starting Voltage Verification for Class 1E MOVs Revision 5

S0-TORUS-M009 NMP-1 Torus Pool Heat Up Analysis Revision 3

Corrective Action 1990689

Documents 1996953

2461835

2608707

2666149

3955525

28779

235565

4340233

4375738

Corrective Action 4377774

Documents 4378021

Resulting from 4378032

Inspection 4378134

4378366

Inspection Type Designation Description or Title Revision or

Procedure Date

4378464

4378465

4378662

4378721

4378750

4378753

4378765

4378901

4378961

4378982

4379033

4379045

4379054

4379583

4379603

4379618

4379848

4380166

4380168

4380193

4380244

4381637

4381737

4382002

4382012

4382415

4382432

4382519

Drawings 1.040-209-065A System Schematic Division I & II Diesel Generator Revision 3

Voltage Regulator

C-19839-C Sh.1 125V DC Control Bus Revision 17

Engineering EC20090078 Alternate Model for Overcurrent Trip Relay UPS172 Revision 0

Changes ECP-16-000514 Replace the Unit 2 DIV I & II Emergency Diesel Generator Revision 0

Starting Air System Air Dryers with New Membrane Air

Inspection Type Designation Description or Title Revision or

Procedure Date

Dryers

ECP-16-000799 Removal of Excessive Engine Vibration Trip Circuitry Revision 0

(2EGS-WEV113 & 2EGS-WEV213) for 2EGS*EG1 and

2EGS*EG3 and Associated Annunciators

ECP-19-000522 NMP1 EDG 102/103 Fuel Oil Storage Level Indicating Revision 0

System and Oil Spill Prevention System Upgrade

Engineering 2EQDP-MOV0003 Motor on Motor Operated Valve Environmental Revision 1

Evaluations Qualification Document Package

90831 Item Equivalency Evaluation for Mobilguard 410 NC Revision 3

ES-139 RCIC Pump-Turbine Room EQ Envelopes Revision 2

MPR Report 1866 Evaluation of Stem Thrust Requirements for dated

2ICS*MOV126 at Nine Mile Point Unit 2 Using the EPRI 11/21/97

MOV Solid and Flexible Wedge Gate Valve Performance

Prediction Methodology

NER-1S-016 Nine Mile Point Unit 1 Torus External Structure Walkdown Revision 11

Results Documentation and 12

Miscellaneous N1C17320BATTRY004 Standby Battery Vented Cell Installation & Operating Revision 5

Instructions

N2-ESP-BYS-R685 Div I/II/III Battery Modified Profile Test performed

2/4/13,

4/18/16, &

3/13/20

N2-OSP-ICS-Q@002 RCIC Pump and Valve Operability Test and System performed

Integrity Test and ASME XI Functional Test and Analysis 2/22/19

N2-OSP-SFC-2Y001 SFC Valve Position Indicator Verification performed

9/11/19

Procedures MA-AA-734-400 Constant Level Oiler and Sight-Glass Maintenance Revision 2

N2-PM-W001 Lubrication of Plant Equipment Revision 22

Work Orders C90651623

C92292614

C92396607

C92562700

C92562702

C93626073

Inspection Type Designation Description or Title Revision or

Procedure Date

C93672565

C93678286

C93698335

C93721801

10