IR 05000220/2020010
| 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:
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
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)===
- (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
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculations
25VDCDISTSYS
25VDC Distribution System Analysis
Revision 0
25VDCSYSTEMELAP Battery 11 and 12 Load Shed Coping Time for ELAP
Event
Revision 0
A10.1-AD-008
Back-Calculation of Valve Factor from EPRI PPM
Calculated Required Thrust
Revision 0
A10.1-H-060
RCIC Pump Performance Test Acceptance Criteria-Lube
Oil Cooler Max. Flow Increase
Revision 0
A10.1H4
RCIC Suction Line Size & NPSHa Verification (Suction
from Suppression Pool)
Revision 0
Diesel Generator Loading
Revision 12
Verification of Adequacy of Division 1 Battery
2BYS*BAT2A and Battery Chargers 2BYS*BAT2A1 &
2A2
Revision 11
Plant Emergency Battery Capability for Station Blackout
Revision 4
Auxiliary System Performance Using ETAP PowerStation
Revision 8
Starting Voltage Verification for Class 1E MOVs
Revision 5
S0-TORUS-M009
NMP-1 Torus Pool Heat Up Analysis
Revision 3
Corrective Action
Documents
1990689
1996953
2461835
2608707
2666149
3955525
28779
235565
4340233
4375738
Corrective Action
Documents
Resulting from
Inspection
4377774
4378021
4378032
4378134
4378366
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Voltage Regulator
Revision 3
C-19839-C Sh.1
25V DC Control Bus
Revision 17
Engineering
Changes
Alternate Model for Overcurrent Trip Relay UPS172
Revision 0
ECP-16-000514
Replace the Unit 2 DIV I & II Emergency Diesel Generator
Starting Air System Air Dryers with New Membrane Air
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Dryers
ECP-16-000799
Removal of Excessive Engine Vibration Trip Circuitry
(2EGS-WEV113 & 2EGS-WEV213) for 2EGS*EG1 and
2EGS*EG3 and Associated Annunciators
Revision 0
ECP-19-000522
NMP1 EDG 102/103 Fuel Oil Storage Level Indicating
System and Oil Spill Prevention System Upgrade
Revision 0
Engineering
Evaluations
Motor on Motor Operated Valve Environmental
Qualification Document Package
Revision 1
90831
Item Equivalency Evaluation for Mobilguard 410 NC
Revision 3
RCIC Pump-Turbine Room EQ Envelopes
Revision 2
MPR Report 1866
Evaluation of Stem Thrust Requirements for
2ICS*MOV126 at Nine Mile Point Unit 2 Using the EPRI
MOV Solid and Flexible Wedge Gate Valve Performance
Prediction Methodology
dated
11/21/97
NER-1S-016
Nine Mile Point Unit 1 Torus External Structure Walkdown
Results Documentation
Revision 11
and 12
Miscellaneous
N1C17320BATTRY004 Standby Battery Vented Cell Installation & Operating
Instructions
Revision 5
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
Integrity Test and ASME XI Functional Test and Analysis
performed
2/22/19
N2-OSP-SFC-2Y001
SFC Valve Position Indicator Verification
performed
9/11/19
Procedures
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
Procedure
Type
Designation
Description or Title
Revision or
Date
C93672565
C93678286
C93698335
C93721801