IR 05000220/2019002
ML19225B640 | |
Person / Time | |
---|---|
Site: | Nine Mile Point ![]() |
Issue date: | 08/12/2019 |
From: | Erin Carfang Division of Nuclear Materials Safety I |
To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
References | |
IR 2019002 | |
Download: ML19225B640 (36) | |
Text
August 12, 2019
SUBJECT:
NINE MILE POINT NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000220/2019002 AND 05000410/2019002
Dear Mr. Hanson:
On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station. On July 31, 2019, the NRC inspectors 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.
The NRC inspectors documented one finding of very low safety significance (Green) in this report. The finding did not involve a violation of NRC requirements.
If you disagree with a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; and the NRC Resident Inspector at Nine Mile Point.
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/
Erin E. Carfang, Chief Reactor Projects Branch 1
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:
05000220/2019002 and 05000410/2019002
Enterprise Identifier: I-2019-002-0037
Licensee:
Exelon Generation Company, LLC
Facility:
Nine Mile Point Nuclear Station
Location:
Oswego, NY
Inspection Dates:
April 01, 2019 to June 30, 2019
Inspectors:
J. Steward, Acting Senior Resident Inspector
E. Miller, Senior Resident Inspector
J. Dolecki, Resident Inspector
B. Sienel, Resident Inspector
C. Bickett, Senior Reactor Inspector
J. Brand, Reactor Inspector
T. Dunn, Operations Engineer
C. Hobbs, Reactor Inspector
J. Kulp, Senior Reactor Inspector
M. Orr, Reactor Inspector
S. Pindale, Senior Reactor Inspector
J. Rady, Reactor Inspector
R. Rolph, Resident Inspector
A. Rosebrook, Senior Project Engineer
A. Turilin, Reactor Inspector
S. Wilson, Health Physicist
Approved By:
Erin E. Carfang, Chief
Reactor Projects Branch 1
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Nine Mile Point Nuclear Station 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. NRC identified and self-revealed findings, violations, and additional items are summarized in the table below.
List of Findings and Violations
Failure to Address and Disposition Turbine Stop Valve 13 Issues Resulted in Reactor Scram Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000220/2019002-01 Open None (NPP)71153 A self-revealed Green finding (FIN) of PI-AA-125, Corrective Action Program Procedure, was identified when Exelon failed to address and disposition issues for the main steam system turbine stop valve (TSV) 13. Specifically, after issues were identified in April 2015 with the configuration of TSV 13 mechanical hydraulic control (MHC) system components and controlling TSV 13 stroke time, Exelon failed to implement procedure changes for controlling the TSV stroke time or precaution that a reactor scram may result if the stroke time is too fast (i.e., open-to-close or close-to-open). As a result, Exelon personnel did not ensure the appropriate configuration of the TSV 13 MHC system components prior to stroke time testing, which led to a fast closure of the TSVs and a subsequent automatic scram due to high reactor pressure on April 14, 2019.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period shut down for planned refueling outage N1R25. On April 12, 2019, operators performed a reactor startup from the refueling outage. On April 14, 2019, at 21 percent power, Unit 1 experienced a reactor scram due to high reactor pressure. Later that day, operators commenced a reactor startup following the reactor scram.
On April 15, 2019, Unit 1 synchronized to the grid, ending refueling outage N1R25. On April 16, 2019, operators performed a reactor shutdown from 21 percent power due to inadequate lube oil supply to the feedwater pump 13 clutch assembly. On April 26, 2019, following repairs to the feedwater pump 13 clutch assembly, operators commenced a reactor startup. On April 27, 2019, Unit 1 synchronized to the grid. On April 29, 2019, operators inserted a manual reactor scram from approximately 83 percent power, due to reactor power and pressure oscillations. Following repairs to the turbine pressure control system, operators commenced a reactor startup and synchronized to the grid on May 5, 2019. On May 7, 2019, Unit 1 reached 100 percent power. Unit 1 remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at 75 percent power. On April 2, 2019, operators commenced power ascension following repairs to the stator water cooling system. On April 3, 2019, operators reduced reactor power from 93 to 84 percent due to electro-hydraulic control system vibrations. On April 4, 2019, Unit 2 reached 100 percent following repairs to the electro-hydraulic control system. On May 17, 2019, operators performed a planned power reduction to 65 percent to conduct quarterly turbine valve testing and a rod pattern adjustment.
On May 19, 2019, Unit 2 was restored to 100 percent power. Unit 2 remained at or near rated thermal power for the remainder of the inspection period.
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 performed plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot temperatures for the 102 and 103 emergency diesel generators and the 11 and 12 125 volts direct current batteries.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 emergency diesel generator 103 on April 4, 2019
- (2) Unit 1 shutdown cooling system on April 16, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configuration during a complete walkdown of the Unit 1 11 emergency service water system on June 4, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Unit 2 Division I battery room, fire area 4, on June 6, 2019
- (2) Unit 2 Division II battery room, fire area 5, on June 6, 2019
- (3) Unit 2 Division III battery room, fire area 13, on June 6, 2019
- (4) Unit 1 emergency condenser make-up water tanks, fire area 5, on June 13, 2019
- (5) Unit 2 600 volt switchgear room, fire area 3, on June 14, 2019
71111.07A - Heat Sink Performance
Annual Review (IP Section 02.01) (1 Sample)
The inspectors evaluated readiness and performance of the Unit 2 'B' residual heat removal heat exchanger room unit cooler 2HVR*UC401A.
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01)
- (1) The inspectors verified that the Unit 1 reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities at Unit 1 from March 25 to March 29, 2019:
03.01.a - Nondestructive Examination and Welding Activities.
1. Manual ultrasonic testing of core spray weld 40-WD-008.
2. Manual ultrasonic testing of bottom head meridional weld RV-WD-158.
3. Manual encoded phased array ultrasonic testing of reactor recirculation outlet
nozzle (N1A) to safe end dissimilar metal weld 32-WD-002.
4. Manual encoded ultrasonic testing of control rod drive housing penetrations
roll expansion repairs and stub-tube-to-housing J-Groove welds on control rod drive 34-31, 34-15, 34-07 and 10-15, in accordance with American Society of Mechanical Engineers code case N-730.
5. Manual encoded phased array ultrasonic testing of core spray nozzle (N6B) to
inner safe end dissimilar metal weld 40-WD-080.
6. Containment coating and moisture barrier general visual inspections.
7. Visual examination of the reactor vessel internals during in-vessel visual
inspection activities in accordance with BWRVIP-03 including core shroud repair assemblies, steam dryer and vertical welds per BWRVIP-76a and core shroud off-axis cracking inspections per BWRVIP guidance letter 2016-030.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated Unit 1 operations personnel during a planned reactor startup following refueling outage N1R25 on April 12, 2019
- (2) The inspectors observed and evaluated Unit 2 operations personnel during a planned power reduction to 65 percent for control rod exercising and a feedwater pump swap on May 17, 2019
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated Unit 1 operator actions for just-in-time training for a new digital feedwater modification on April 2, 2019
- (2) The inspectors observed and evaluated a Unit 2 simulator evaluation that involved severe weather, loss of offsite power, and a reactor scram on May 24, 2019
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Unit 1 emergency condenser system on June 16, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Unit 1 elevated risk during reactor cavity drain down on April 4, 2019
- (2) Unit 1 unplanned maintenance associated with the feedwater pump 13 clutch assembly on April 16, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (7 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Unit 1 liquid poison 11 discharge relief valve failed bench test on March 27, 2019
- (2) Unit 2 step change in jet pump 6 flow indication on April 16, 2019
- (3) Unit 1 shutdown cooling system vibration on April 17, 2019
- (4) Unit 1 average power range monitor 15-18 alarm failed to clear when power was above the reset point on May 5, 2019
- (5) Unit 1 minimum critical power ratio with the mechanial pressure regulator out of service on May 9, 2019
- (6) Unit 2 high pressure core spray diesel generator fuel injector failure on May 16, 2019
- (7) Unit 1 core spray topping pump 111 discharge relief valve failed local leak rate test on May 22, 2019
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from April 22 through April 25, 2019:
- (1) Evaluation 2016-02, 10 CFR 50 Appendix J, Local Leak Rate Testing Scope Reduction
- (2) Evaluation 2017-01, Unit 2 Digital Electro-Hydraulic Control System Upgrade
- (3) Evaluation 2017-02, TRACG-LOCA Implementation
- (4) Evaluation 2018-01, Operability Evaluation 4148579: Bypass Reactor Recirculation Cavitation Protection Interlock
- (5) Evaluation 2018-02, Unit 1 Feedwater Level Control System Upgrade (6)5059-2016-571, ECP-16-000752, Replace Actuator Motor for 2RCS*MOV18A (7)5059-2016-621, ECP-16-000799, Unit 2 Division I and II Emergency Diesel Generator Vibration Switch Bypass (8)5059-2017-050, ECP-17-00048, Technical Evaluation for PSV-01-102 (9)5059-2017-108, ECP-16-000739, Replacing Manual Globe Valves with Manual Gate Valves in the Main Steam System and Select Emergency Core Cooling Systems (10)5059-2017-109, ECP-16-000744, Change Package for the Electro-Hydraulic Control System Throttle Pressure Transmitter Replacement (11)5059-2017-112, ECP-17-000126, Change to Emergency Diesel Generator Field Ground Alarm Permissive Contact (12)5059-2017-162, C93049636, Work Order to Correct Safety Relief Valve Indications (13)5059-2017-180, ECP-16-000514 Replace the Division I & II Emergency Diesel Generator Starting Air System Dryers with New Membrane Air Dryers (14)5059-2017-259, ECP-17-000423, Temporary Modification for Reactor Protection System Limit Switch for Turbine Stop Valve (15)5059-2017-283, ECP-17-000395, Evaluation to Upgrade to Digital Voltage Regulator Recommended by Original Equipment Manufacturer (16)5059-2017-298, Revision to Procedure N1-EOP-1 (17)5059-2017-460, Revision to N2-EOP-HC (18)5059-2018-075, ECP-18-00098, Surveillance Procedure Extension (19)5059-2018-243, ECP-18-000348, Retirement of 2EGT*H1 Division III Diesel Generator Space Heater (20)5059-2018-245, Revise Technical Specification Bases for 2.1.1 Fuel Cladding Safety Limit to Add Clarification Reference Associated with GE SIL 516 S2 (21)5059-2019-005, ECP-18-000120, Unit 1 Rod Worth Minimizer Software Patch (22)5059-2019-013, ECP-18-000635, Unit 2 Data Diode Refresh Project
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Permanent Modification: ECP-18-000407, Unit 1 MSIV [main steam isolation valve] 01-01 Stuffing Box Machining
- (2) Permanent Modification: ECP-18-000035, Unit 1 Digital Feedwater Level Control System Upgrade
71111.19 - Post-Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) Unit 1 electromatic relief valve tail pipe temperature element installation on April 3, 2019
- (2) Unit 1 main steam isolation valve, IV-01-01, following maintenance on April 3, 2019
- (3) Unit 1 reactor pressure vessel and ASME Class 1 system leakage test on April 5, 2019
- (4) Unit 1 digital feedwater level control modification testing during initial reactor startup on April 13, 2019
- (5) Unit 1 turbine stop valve 13 stroke time testing following turbine stop valve 13 bypass mechanical hydraulic control system components maintenance on April 16, 2019
- (6) Unit 1 feedwater pump 13 clutch assembly repairs on April 22, 2019
- (7) Unit 1 digital feedwater level control modification testing at 60 percent power on April 27, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (3 Samples)
- (1) The inspectors evaluated Unit 1 refueling outage (N1R25) from March 18 through April 15, 2019
- (2) The inspectors evaluated Unit 1 forced outage (1F1901) from April 16 through April 27, 2019
- (3) The inspectors evaluated Unit 1 forced outage (1F1902) from April 29 through May 5, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Inservice Testing (IP Section 03.01)
- (1) N1-ISP-001-018, Electromatic Relief Valve Pressure Switch Calibration, on April 17, 2019
Surveillance Tests (other) (IP Section 03.01) (6 Samples)
- (1) N1-ESP-001-130, Main Steam Isolation Valve Limit Switch Test, on April 5, 2019
- (2) N1-ST-R12, Initiation of Emergency Condensers From Remote Shutdown Panel 11 and 12 Operability Test, on April 7, 2019
- (3) N1-ST-C3, High Pressure Coolant Injection Automatic Initiation Test, on April 12, 2019
- (4) N2-RSP-RMS-R103, Channel Calibration Test of the Standby Gas Treatment System Exhaust Process Radiation Monitor, on April 17, 2019
- (5) N2-OSP-EGS-M@001, Division I Emergency Diesel Generator Monthly Run, on June 27, 2019
- (6) N2-OSPCSL-Q@002, Low Pressure Core Spray Pump Valve Operability Test, on June 28, 2019
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) A Unit 1 simulator scenario that involved a feedwater master controller failure, a loss of power board 102, a loss of 115 kilovolt with power board 102 unavailable, and a loss of all reliable level indication requiring entry into the emergency operating procedure for reactor pressure vessel flooding on June 18,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)
- (1) The inspectors reviewed the procedures and evaluated controls for high radiation areas, locked high radiation areas, very high radiation areas, and radiological transient areas in the plant.
Instructions to Workers (IP Section 02.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas:
Radiation work packages
- NM-1-19-0050 Drywell Scaffold
- NM-1-19-0051 Drywell In Service Inspection
- NM-1-19-0090 Reactor Disassembly/Reassembly
- NM-1-19-00510 Drywell Insulation
- NM-1-19-00610 Reactor Water Clean Up
Electronic alarming dosimeter alarms
The inspectors observed labeling of containers in the drywell and the reactor building during facility walkdowns.
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)
- (1) The inspectors evaluated radiation worker performance and radiation protection technician proficiency.
Radiological Hazard Assessment (IP Section 02.01) (1 Sample)
The inspectors evaluated radiological hazards assessments and controls.
- (1) The inspectors evaluated radiological hazards assessments and controls. The inspectors reviewed the following:
Radiological surveys
- 2019-037575 drywell 225' March 18, 2019 at 0349
- 2019-037575 drywell 225' under vessel March 18, 2019 at 0349
- 2019-037675 drywell 225' March 18, 2019 at 1200
- 2019-037695 drywell 259' March 18, 2019 at 1518
- 2019-037746 drywell 305' March 18, 2019 at 2214
- 2019-038752 reactor building 261' reactor water cleanup heat exchanger room March 23, 2019 at 1654
Risk significant radiological work activities
- drywell scaffold
- drywell inservice inspection
- reactor disassembly/reassembly
Air sample survey records
- 2019-037575
- 2019-037845
- 2019-038541
- 2019-038887
Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walkdowns and observation of radiological work activities. The inspectors assessed whether posted surveys, radiation work permits, worker radiological briefings and radiation protection job coverage, the use of continuous air monitoring, air sampling and engineering controls, and dosimetry monitoring were consistent with the present conditions. The inspectors examined the control of highly activated or contaminated materials stored within the spent fuel pools.
71124.02 - Occupational ALARA Planning and Controls
Radiation Worker Performance (IP Section 02.04) (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician performance during:
- (1) The inspectors evaluated radiation worker and radiation protection technician performance during drywell activities, refuel floor activities, and turbine building activities. The inspectors also observed a simulation of Unit 1 and Unit 2 drywell high range radiation monitor calibrations.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Engineering Controls (IP Section 02.01) (1 Sample)
The inspectors evaluated airborne controls and radioactive monitoring.
- (1) The inspectors evaluated airborne controls and radioactive monitoring. The inspectors reviewed the following:
Installed Ventilation Systems
- Control room envelope ventilation system
- Reactor building ventilation system
Temporary Ventilation System Setups
- Unit 2 dry cask storage campaign temporary ventilation system
- Unit 2 equipment pit temporary ventilation
Portable or Installed Monitoring Systems
- Unit 1 reactor building ventilation particulate, iodine and noble gas monitoring systems
- Unit 2 reactor building ventilation particulate, iodine and noble gas monitoring systems
Self-Contained Breathing Apparatus for Emergency Use (IP Section 02.03) (1 Sample)
- (1) The inspectors evaluated self-contained breathing apparatus (SCBA) program implementation. The inspectors reviewed the following:
Status and Surveillance Records for SCBA
- Status and surveillance records for five SCBA units
- Monthly surveillance records (functional checks) for five SCBA units
SCBA Fit for On-Shift Operators
- Three on-shift operators (fire brigade) SCBA fit
SCBA Maintenance Check
- Status maintenance records for the previous 24 months for five SCBA units
Use of Respiratory Protection Devices (IP Section 02.02) (1 Sample)
The inspectors evaluated the licensees use of respiratory protection devices by:
- (1) The inspectors evaluated respiratory protection. The inspectors reviewed the following:
Evaluations for the Use of Respiratory Protection
- (3) Respiratory Protection Use During Work Activities
- No activities were available for observation
- Documentation of respirator use during reactor cavity decontamination
Medical Fitness for Use of Respiratory Protection Devices
- Medical fitness of three health physics personnel and four fire brigade members
Observation of Donning, Doffing and Functional Test
- Three health physics personnel donning and doffing respirators for fit tests
- Four fire brigade members donning and doffing and functional testing SCBA units staged for fire brigade
Respiratory Protection Device Evaluation
- Physical condition and records of periodic inspection for 10 respiratory protection devices staged adjacent to the Unit 1 control room
71124.04 - Occupational Dose Assessment
Internal Dosimetry (IP Section 02.03) (1 Sample)
The inspectors evaluated the internal dosimetry program implementation.
- (1) The inspectors reviewed internal dosimetry procedures, whole body counter measurement sensitivity and use, adequacy of the program for whole body count monitoring of plant radionuclides or other bioassay technique, adequacy of the program for dose assessments based on air sample monitoring and the use of respiratory protection, and internal dose assessments for any actual internal exposure.
Source Term Categorization (IP Section 02.01) (1 Sample)
- (1) The inspectors evaluated the licensees characterization of the source term and use of scaling factors for the use of hard-to-detect radionuclide activity.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1, January 1, 2018 - March 31, 2019
- (2) Unit 2, January 1, 2018 - March 31, 2019
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1, January 1, 2018 - March 31, 2019
- (2) Unit 2, January 1, 2018 - March 31, 2019
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) IR 04179494, Spent Fuel Pool Boraflex Coupon Failed Test Results
- (2) IR 04201192, Aggregate Review of Significant 2018 Station Events
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors evaluated a sample of issues and events that occurred over the course of the first and second quarters of 2019 to determine whether issues were appropriately considered as emerging or adverse trends.
71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors evaluated a Unit 2 power reduction due to electro-hydraulic control system vibrations on April 3, 2019
- (2) The inspectors evaluated a Unit 1 automatic reactor scram due to high reactor pressure on April 14, 2019
- (3) The inspectors evaluated a Unit 1 manual reactor scram due to reactor pressure oscillations on April 29,
INSPECTION RESULTS
Minor Violation 71152 Minor Violation: Degradation of Boraflex spent fuel pool neutron absorbing material is a known industry issue that has been identified in NRC Generic Letters 1996-04 and 2016-01.
In 2004, Nine Mile Point Unit 1 completed replacing all but two Boraflex racks in the spent fuel pool with Boral racks. Boral is not subject to the same degradation mechanisms as Boraflex. As part of the license renewal process, Nine Mile Point Unit 1 committed to an Aging Management Program that included monitoring Boraflex degradation in the two remaining Boraflex racks in the Unit 1 spent fuel pool (SFP) through the period of extended operation. The period of extended operation for Nine Mile Point Unit 1 began in 2009 and will end in 2029. The Boraflex aging management program consists of three components as described in Appendix C.1.5 of the Unit 1 UFSAR: 1) inspection of test coupons removed from the SFP to measure material loss of Boraflex in the samples; 2) correlation of measured levels of silica in the spent fuel pool with analysis using a predictive computer code (RACKLIFE), to estimate boron loss from Boraflex panels; and 3) periodic neutron attenuation testing to directly measure the boron areal density of the Boraflex racks in the SFP (BADGER testing).
BADGER testing was performed once at the end of 2008, and showed satisfactory results for the 45 panels tested with average boron areal density measured at 0.0263 grams B-10/cm2.
The minimum boron areal density specified in the Criticality Analysis of Record (CAOR) is 0.0217 grams B-10/cm2. Boraflex coupon samples have been removed from the Boraflex racks every 2 years since entering the period of extended operation. Until 2016, all samples passed the inspection criteria specified in the program. The last two samples removed from the pool did not pass several inspection criteria, but did pass the thickness criteria specified in the CAOR. The recommended corrective action for the 2016 Boraflex coupon test failure was to perform BADGER testing in 2016, in accordance with the 8-year frequency specified in NMP-AMP-BFX01, Nine Mile Point Unit 1 Program Plan for Spent Fuel Rack Boraflex Degradation Monitoring Program, Section 10. The inspectors determined that this testing was not completed as required.
In order to demonstrate sufficient margin to the criticality limits specified in the current CAOR, Exelon performed RACKLIFE calculations in both 2016 and again in 2018. The 2018 RACKLIFE calculation is documented in Technical Evaluation ECP-18-000696, and shows that the maximum Boron loss from the Boraflex panels is expected to be 2.73 percent as of December 31, 2019, and 3.53 percent as of March 16, 2029. The CAOR specifies a maximum Boron loss of 4.00 percent in order to ensure sufficient margin to the Technical Specification 5.5 limit of an effective neutron multiplication factor of 0.95 or less in the Boraflex racks. The RACKLIFE predicted results are based on measured levels of silica in the SFP. It is known that degradation of Boraflex will result in higher measured levels of silica in the SFP. The measured silica levels in the Nine Mile Point Unit 1 SFP have been relatively low and consistent at 0.5 ppm or less at the end of each refueling outage since 2004. In addition, no new fuel discharged from the reactor has been placed in the Boraflex racks since 2003, thus resulting in an integrated gamma dose to the Boraflex panels that is less than if fresh fuel assemblies from the reactor were discharged into the Boraflex racks on a consistent basis since 2003.
Exelon submitted License Amendment No. 234 in February 2018 to remove credit for the Boraflex racks from the CAOR. The License Amendment was approved by the Office of Nuclear Reactor Regulation in January 2019. However, it is contingent upon moving the fuel in the Boraflex racks into a checkerboard pattern in which 1 out of every 2x2 block of fuel assemblies is empty, and cell blockers are installed in the empty fuel locations to prevent accidental insertion of a fuel assembly. Exelon has planned fuel movement in the Boraflex racks into the checkerboard pattern described in the issued License Amendment in Work Order C93681986, scheduled for the week of August 5, 2019. The inspectors noted that non-compliance with the Boraflex Aging Management Program as specified in NMP-AMP-BFX01, still exists until the License Amendment is implemented by moving the fuel in the SFP, which will remove credit for Boraflex in the SFP.
Screening: The inspectors determined the performance deficiency was minor. The inspectors determined the failure to perform BADGER testing on 8-year frequency specified in NMP-AMP-BFX01 was a performance deficiency, and evaluated the performance deficiency for significance in accordance with the guidance in Inspection Manual Chapter (IMC) 0612, Appendix B, Issue Screening, dated January 1, 2018, and Appendix E, Examples of Minor Issues, dated October 1, 2018. RACKLIFE simulation, has demonstrated that significant margin exists to the limits specified in the Criticality Analysis of Record for the Boraflex racks in the Unit 1 spent fuel pool through December 31, 2019. In addition, a License Amendment is in place to remove credit for the Boraflex racks as a neutron absorber in the U1 SFP.
Movement of fuel assemblies is scheduled for August 2019, which will implement the License Amendment and remove Boraflex credit. With Boraflex credit no longer required, the Boraflex Aging Management Program will no longer be necessary, and compliance will be restored.
This performance deficiency is similar to IMC 0612, Appendix E, example 3d.
Enforcement:
Nine Mile Point Unit 1, License Condition 1.C of Renewed Facility Operating License No. DPR-63, requires in part that, actions have been identified and will be taken with respect to managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1). Nine Mile Point Nuclear Station Unit 1 Updated Final Safety Analysis Report, Appendix C.1.5, Boraflex Monitoring Program, states in part that, the Boraflex Monitoring Program for Unit 1 will be enhanced to perform periodic in-situ neutron attenuation testing and measurement of boron areal density for those Boraflex racks that remain in use during the period of extended operation. The NMP-AMP-BFX01, Nine Mile Point Unit 1 Program Plan for Spent Fuel Rack Boraflex Degradation Monitoring Program, Section 10, specifies that neutron attenuation will be performed initially prior to the period of extended operation, and every 8 years thereafter through the period of extended operation to confirm the correlation and conditions of test coupons to those of the Boraflex spent fuel racks.
Contrary to the above, in-situ neutron attenuation measurements on the Boraflex racks in the Unit 1 spent fuel pool was performed once in 2008 prior to the period of extended operation, and not re-performed again in 2016. Thus, non-compliance with the Boraflex Aging Management Program has existed since November 2016. Failure to perform periodic in-situ neutron attenuation measurements on the Boraflex racks in the Unit 1 spent fuel pool is a minor violation of Nine Mile Point Unit 1 License Condition 1.C. Exelon has noted the deficiencies in the Boraflex Aging Management Program in ARs 2608609, 4094907, 4179494, and 4192187. Exelon plans to eliminate the Boraflex Aging Management Program through implementation of License Amendment No. 234 in August 2019. Movement of fuel in the spent fuel pool into the checkerboard pattern specified in the License Amendment will restore compliance. This minor violation is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Observation: Human Performance Observations 71152 The inspectors reviewed several causal evaluations associated with human performance events in 2018 and their respective corrective actions. Further, inspectors performed in-field inspections in June 2019. Based on the documents reviewed and observed licensed operator execution of surveillance and operating procedures, the inspectors observed no issues with operations department compliance with procedures and use of Human Performance Tools. The inspectors reviewed corrective actions and training documents and evaluated the effectiveness of licensee human performance improvement measures during the period of June 3, 2019, to June 5, 2019. The inspectors also observed several main control room equipment manipulations, communications, stop work execution and in-field safety related activities. However, based on the following safety related functional testing observations in the field, and lack of operator aid controls, corrective actions related to human performance and human performance error prevention techniques are not yet fully effective.
Specifically:
- IR 04254594. The inspectors observed a technician not following prescribed electrical safety precautions while performing electrical panel activities.
- IR 04256316. The inspectors identified a potential vulnerability with respect to the human performance error prevention technique of place-keeping due to the use of tablet devices in the field. Although this observation was discussed with maintenance department management on June 4, 2019, the observation was not accurately captured in the corrective action program until June 17, 2019.
- IR 04253737. The inspectors observed that operator aids in the main control room were not being controlled as required by station procedures. Specifically, some of these operator aids contained out-of-date information.
The inspectors reviewed the above issues using NRC Inspection Manual Chapter 0612, Appendix B, Issue Screening, and determined they were of minor risk significance. In conclusion, low level gaps still exist in human performance at this site, as evidenced by inspector observations. Gaps also exist in the initiation and written communication of identified deficiencies as evidenced by the timing and level of detail contained in IR 04256316, issued June 12, 2019.
Observation: Semi-Annual Trend Review 71152 The inspectors identified a continuation of the adverse trend associated with procedure quality and adherence issues identified in the past two semi-annual trend reviews (NRC inspection reports 05000220/2018002, 05000410/2018002, 05000220/2018004 and 05000410/2018004). Exelon generated IR 04157970 for the second quarter of 2018 trend and IR 04217844 for the fourth quarter of 2018 trend. Exelon performed work group evaluations in response to these IRs and determined, in general, the cause to be lack of questioning attitude by the operators and lack of precise control of plant evolutions. Exelon has implemented some corrective actions, namely changes through clarification of procedures; however, some corrective actions remain in progress. Since documentation of these trend IRs, inspectors have identified additional issues demonstrating a weakness in procedure quality and adherence that impacted equipment reliability.
Specifically, the inspectors identified procedure quality issues that impacted equipment reliability, such as the inoperability of a diesel generator, a reactor scram, and an inconsistency between acceptance criteria and technical specification surveillance requirements. The reactor scram is detailed in this report as Green finding 2019002-01.
The inconsistency between the acceptance criteria and technical specification surveillance requirements is detailed in the 2019 first quarter integrated inspection report (ADAMS Accession Number ML19128A291) Green finding and associated non-cited violation 2019001-01.
In addition, the inspectors identified deficiencies in the licensees procedural adherence.
These deficiencies impacted equipment reliability, such as significant damage to the bearings of a feedwater pump, unprotected equipment, an inadvertent trip of the reactor building emergency ventilation, inability to open a bypass valve, unplanned inoperability of standby gas treatment, inadvertently initiating a half-scram, and a reactor building crane trip.
The examples above demonstrate an adverse trend with regards to procedure quality and adherence. Exelon generated IR 04263226 to address those deficiencies. The inspectors independently evaluated the deficiencies for significance in accordance with the guidance in IMC 0612, Appendix B, Issue Screening, and Appendix E, Examples of Minor Issues. The inspectors determined that these conditions, except as noted, were deficiencies of minor significance and, therefore, are not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Failure to Address and Disposition Turbine Stop Valve 13 Issues Resulted in Reactor Scram Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events
Green FIN 05000220/2019002-01 Open None (NPP)71153 A self-revealed Green finding (FIN) of PI-AA-125, Corrective Action Program Procedure, was identified when Exelon failed to address and disposition issues for the main steam system turbine stop valve (TSV) 13. Specifically, after issues were identified in April 2015 with the configuration of TSV 13 mechanical hydraulic control (MHC) system components and controlling TSV 13 stroke time, Exelon failed to implement procedure changes for controlling the TSV stroke time or precaution that a reactor scram may result if the stroke time is too fast (i.e., open-to-close or close-to-open). As a result, Exelon personnel did not ensure the appropriate configuration of the TSV 13 MHC system components prior to stroke time testing, which resulted in a fast closure of the TSVs and a subsequent automatic scram due to high reactor pressure on April 14, 2019.
Description:
The Nine Mile Point Unit 1 main steam system has four TSVs and nine main turbine bypass valves (TBVs). The positioning of these valves is controlled by the MHC system. Unique to TSV 13 is an internal bypass valve, which is opened to permit steam at a lower flow rate to both equalize the pressure across the TSV 13 main disk to permit the main disk to be opened and to provide main turbine steam chest warming prior to fully opening all four of the TSVs during a startup. The TSV 13 bypass valve positioning and the TSV 13 stroke time are controlled by a pilot valve and associated MHC system components. These components include an Open End Rigid Stop and Closed End Rigid Stop and the restoring arm breakdown (RAB). The Open and Closed End Rigid Stop control the TSV 13 opening and closing stroke time, respectively. The RAB provides fine motion control of the TSV 13 bypass valve. The RAB is not used during TSV 13 main disk maneuvers.
In April 2015, two IRs were generated to capture issues related to TSV 13 MHC system components, one IR related to the RAB and one IR related to the Open End Rigid Stop.
Issue Report 02476630 was generated after the RAB was discovered to be out of the normal operating position during performance of work under C92295646 to correct TSV 13 bypass handwheel motor position indication issues. To address the issue, the RAB was reinstalled under the existing work order C92295646 (note it was later determined that the RAB was incorrectly reinstalled). Issue Report 02476630 detailed that vibration during the operating cycle likely resulted in the RAB being out of position; however, IR 02476630 did not include a corrective action to change the procedure or include a maintenance strategy to ensure proper position of the RAB prior to utilizing the TSV 13 MHC system. Issue Report 02481818 was generated after the TSV 13 unexpectedly failed closed during close-to-open full stroke time testing in accordance with N1-ISP-001-008, Turbine Stop Valve 10% Closure Instrument Channel Test/Calibration. To address the issue, an investigation into the proper positioning of the Open End Rigid Stop was performed, as shown in IR 02481818. As determined in IR 02481818, the Open End Rigid Stop should be set at no greater than 0.030 open end over-travel in order to meet the close-to-open stroke time acceptance criteria and avoid the TSV 13 from opening too fast then tripping. Issue Report 02481818 detailed that the MHC system components can become misadjusted after time due to wear or vibration and station personnel lacked detailed working knowledge on the MHC system components; however, IR 02481818 did not include a corrective action to change the procedure to ensure the Open End Rigid Stop was set at no greater than 0.030 open end over-travel prior to performance of the TSV 13 full stroke time testing. Overall, corrective actions were not generated to revise procedures to verify positioning of the RAB and Open End Rigid Stop prior to controlling the TSV 13 as a result of IR 02476630 or IR 02481818. Furthermore, the inspectors determined a caution was communicated in General Electric (GE)-supplied information in April 2005 (GE PAC 20050425-0057) that if TSV stroke test times are not within specific times stated, then a reactor scram may result. This caution had not been incorporated into procedures.
Procedure PI-AA-125, Corrective Action Program (CAP) Procedure, Section 4.3.1 states, in part, to address and disposition any issues generated by the IR originator, reviewers, screeners, station ownership committee, or management review committee. Contrary to this, the inspectors determined Exelon did not address and disposition the two issues identified in April 2015 with the configuration of TSV 13 MHC system components and controlling TSV 13 stroke time and, as a result, did not implement corrective actions to revise applicable TSV 13 procedures to ensure the TSV stroke time testing is performed without a reactor scram occurring.
Due to Exelon's failure to implement corrective actions to revise TSV 13 stroke time testing procedures following issues identified in April 2015, an automatic reactor scram occurred on April 2019 during performance of TSV 13 full stroke time testing. Specifically, on April 14 2019 at 12:03 AM, Unit 1 was at approximately 21 percent thermal power while operators were performing full stroke time testing on the TSV 13 for post-maintenance testing in accordance with N1-ST-Q29, Quarterly Turbine Valve Log, when an automatic reactor scram occurred due to high reactor pressure.
Corrective Actions: Exelon generated IR 04239350 to capture the scram and to initiate a root cause evaluation. Detailed in the root cause evaluation, planned corrective actions include revising main turbine start-up and TSV stroke time testing procedures, and developing a comprehensive maintenance strategy. Further, Exelon plans to ensure qualified applicable station personnel are proficient in the TSV internal bypass and procedures.
Corrective Action Reference: 04239350
Performance Assessment:
Performance Deficiency: The inspectors determined that Exelons failure to address and disposition issues identified in April 2015 with the configuration of TSV 13 MHC system components and controlling TSV 13 stroke time was contrary to the Exelons PI-AA-125 Corrective Action Program Procedure and was a performance deficiency that was reasonably within Exelons ability to foresee and correct and should have been prevented.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Initiating Events cornerstone. It adversely affected the cornerstone objective attribute to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations.
Significance: The inspectors assessed the significance of the finding using IMC 0609, 4, Initial Characterization of Findings, dated October 7, 2016, and IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, dated June 19, 2012. The inspectors performed a Phase 1 SDP review of this finding using the guidance provided in IMC 0609, Appendix A, Exhibit 1, Initiating Events Screening Questions, and determined this finding is of very low safety significance (Green) because the transient did not involve the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition.
Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance. The performance deficiency was associated with decisions made greater than three years ago and is not indicative of current plant performance.
Enforcement:
Inspectors did not identify a violation of regulatory requirements associated with this finding.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 31, 2019, the inspectors presented the integrated inspection results to Mr. Peter Orphanos, Site Vice President, and other members of the licensee staff.
- On March 29, 2019, the inspectors presented the NMP1 ISI inspection to Mr. Peter Orphanos, Site Vice President, and other members of the licensee staff.
- On April 25, 2019, the inspectors presented the results of the evaluations of changes, tests, and experiments inspection to Mr. Peter Orphanos, Site Vice President, and other members of the licensee staff.
- On May 14, 2019, the inspectors presented the results of the Unit 1 spent fuel pool Boraflex coupon sample failed test results inspection to James Tusar, Senior Manager, Nuclear Fuels, and other members of the licensee staff.
- On June 5, 2019, the inspectors presented the Human Performance Observations to Denise Wolniak, Acting Regulatory Assurance Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2702620
Corrective Action
Documents
04157336
Corrective Action
Documents
04171068
Corrective Action
Documents
04190212
Procedures
N1-OP-26
Turbine Building Ventilation System
200
Procedures
N1-OP-45
04800
Procedures
N1-OP-47A
25 VDC Power System
200
Procedures
N1-OP-64
Meteorological Monitoring
01900
Procedures
N2-OP-102
Meteorological Monitoring
2600
Work Orders
C93658067
Work Orders
C93660309
Drawings
C-18018-C
Reactor Shutdown Cooling P&I Diagram
Procedures
N1-OP-4
Shutdown Cooling System
04800
Procedures
N1-OP-45
04700
Corrective Action
Documents
04038003
Corrective Action
Documents
04044383
Drawings
C-18022-C, Sheet 1
Service Water, Reactor and Turbine Buildings P&I
Diagram
Miscellaneous
Service Water System Design Basis Document
Procedures
N1-OP-18
Service Water System
04400
Procedures
N1-SOP-18.1
Service Water Failure/Low Intake Level
00600
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.05Q Procedures
N1-PFP-0101
Unit 1 Pre-Fire Plans
00500
71111.05Q Procedures
N2-FPI-PFP-0201
Unit 2 Pre-Fire Plans
Corrective Action
Documents
04196392
Miscellaneous
NMPNS-HX-001
Generic Letter 89-13 Heat Exchanger Program Plan
Procedures
GAP-HSC-02
System Aging Inspection and Cleanness Controls
2000
Procedures
N2-PM-HVR-401
Performance Evaluation Test for Unit Cooler
2HVR*UC401A, B, C, D, E, and F
00100
Procedures
S-TDP-REL-0103
GL 89-13 Service Water System Problems Affecting
Safety-Related Equipment Program Plan
Work Orders
C92972141
71111.08G Miscellaneous
Field Deviation
Disposition Request
(FFDR) 005N2487
NMP1 Shroud Tie Rod
INR N1R25 IVVI 19
Tie Rod Clevis Pin and Nut - Indication Notification
Report for Clevis Pin 090 - 089 side
04/01/2019
INR N1R25 IVVI 19
166 TR Clevis Pin and Nut Post Torque - Indication
Notification Report for Clevis Pin 166 - 165 side
04/01/2019
Corrective Action
Documents
03988865
Corrective Action
Documents
03990258
Corrective Action
Documents
04122437
Corrective Action
Documents
230591
Corrective Action
Documents
232357
Corrective Action
Documents
232473
Corrective Action
232618
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Procedures
Maintenance Rule Implementation Per NEI 18-10
Procedures
Maintenance Rule 18-10 - Failure Definition
Procedures
Maintenance Rule 18-10 - Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
Procedures
N1-MMP-GEN-901
Reactor Reassembly
2700
Procedures
N1-OP-34
Refueling Procedure
03900
Procedures
N1-PM-34
Reactor Cavity Flood up and Drain Down
00900
Work Orders
C93620400
Corrective Action
Documents
229798
Corrective Action
Documents
231873
Corrective Action
Documents
233329
Corrective Action
Documents
238289
Corrective Action
Documents
240207
Corrective Action
Documents
240629
Corrective Action
Documents
240815
Corrective Action
Documents
246485
Corrective Action
Documents
248297
Corrective Action
Documents
249623
Corrective Action
Documents
249690
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
C-18007-C
Sheet 1, Reactor Core Spray P&I Diagram
Drawings
C-18018-C
Reactor Shutdown Cooling
Miscellaneous
Core Operating Limits Report Nine Mile Point 1
Miscellaneous
ACMP, Degraded Flow on Jet Pump #6
Miscellaneous
N1P020500PUMP002 Instructions for Installing, Operating, and Maintaining
Pacific Pumps Type HVC
Procedures
N1-ARP-F3
Control Room Panel F3
00900
Procedures
N1-ARP-K3
Control Room Panel K3
00900
Procedures
N1-MSP-GEN-251
ASME OM Code Pressure Relief Valve Removal, Bench
Testing, and Installation
01300
Procedures
N1-OP-31
Tandem Compound Reheat Turbine
05100
Procedures
N1-OP-38C
Local Power Range Monitors (LPRM) Average Power
Range Monitors (APRM)
2900
Procedures
N1-OP-4
Shutdown Cooling System
04800
Procedures
N1-OP-43A
Plant Startup
04801
Procedures
N1-ST-Q1A
CS 111 Pump, Valve ad SDC Water Seal Check Valve
Operability Test
01800
Procedures
N1-ST-R9
Core Spray Operability Test Using Demineralized (CST)
Water
01300
Procedures
N2-MPM-EGS-508
General Motors Diesel (DIV III) Lube Oil Preventative
Maintenance Sampling
00000
Work Orders
C93622411
Work Orders
C93705978
Work Orders
C93706436
Work Orders
C93706442
Calculations
EC-83
Overload Heater Selection for Normal and Emergency
600 Volts AC and 125 Volts DC Motor Control Centers
Calculations
S20.7RVV002
Drywell Ambient Temperature Effect on Reactor Head
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Safety Valve Setpoint
Corrective Action
Documents
2715685
Corrective Action
Documents
2715901
Corrective Action
Documents
2721034
Corrective Action
Documents
2721963
Corrective Action
Documents
03994179
Corrective Action
Documents
226374
Corrective Action
Documents
226377
Corrective Action
Documents
226730
Corrective Action
Documents
226801
Corrective Action
Documents
227857
Corrective Action
Documents
227873
Corrective Action
Documents
Resulting from
Inspection
243234*
Corrective Action
Documents
Resulting from
Inspection
243411*
Corrective Action
Documents
Resulting from
243421*
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Drawings
C22004C-003, Sheet
Interconnection Wiring Diagram for Feedwater
Instrumentation System
Miscellaneous
Memorandum, from Constellation Energy to U.S Nuclear
Regulatory Commission, License Amendment Request to
Remove Position Indication for Safety Relief Valves and
Safety Valves from Technical Specifications
07/02/2009
Miscellaneous
Nine Mile Point Nuclear Station Units 1 and 2 10 CFR 50.46 Annual Report
01/25/2019
Miscellaneous
Nine Mile Point Unit 1 Core Operating Limits Report,
Cycle 23
Miscellaneous
Final Safety Evaluation Related to General Electric-
Hitachi Licensing Topical Report NEDE-33005P and
NEDO-33005, TRACG Application for Emergency Core
Cooling Systems/Loss-of-Coolant Accident Analyses for
BWR/2-6
2/22/2017
Miscellaneous
2N3714
Nine Mile Point Nuclear Station Unit 1 TRACG-LOCA
Loss of Coolant Analysis for GNF2
03/16/2017
Miscellaneous
Amendment 205,
Nine Mile Point
Nuclear Station, Unit
Issuance of Amendment Regarding Removal of Position
Indication for Relief Valves and Safety Valves from
Technical Specifications (TAC no. ME1719)
06/29/2010
Miscellaneous
EE-00435
Equivalency Evaluation to Identify Equivalent
Replacements for Existing Reactor Vessel Skin and
Flange Temperature Thermocouples
Miscellaneous
NMP-2018-209
TRR Details, Implement ECP-18-000388 New
Recirculation Sub-cooling Indication and Alarm
09/18/2018
Miscellaneous
NMP2L2693
Submittal of Revision 23 to the Nine Mile Point Unit 2
Updated Safety Analysis Report (USAR) and References
Figures, 10 CFR 50.59 Evaluation Summary Report,
Technical Specifications bases, Technical Requirements
Manual Changes, and 10 CRR 54.37(b) Aging
Management Review
10/24/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
NMPNS-IST-001
In-service Testing (IST) Program Plan, Units 1 and 2 10-
Year Interval 1/1/2019 - 12/31/2028
03/19/2019
Miscellaneous
Technical
Specifications
Nine Mile Point Nuclear Station Unit 1
Miscellaneous
Technical
Specifications
Nine Mile Point Nuclear Station Unit 2
Miscellaneous
UFSAR Change 2-17-
CRF-008
Unit 2 Division I and II Emergency Diesel Generator
Vibration Switch Bypass
Miscellaneous
Updated Final Safety
Analysis Report
Nine Mile Point Nuclear Station Unit 1
Miscellaneous
Updated Final Safety
Analysis Report
Nine Mile Point Nuclear Station Unit 2
Miscellaneous
WNA-AR-00206-GEN
Software Failure Analysis of Ovation Platform
Miscellaneous
WNA-AR-00593-
G9MI2
Turbine Control and Protection Failure Modes and
Effects Analysis
Procedures
Technical Task Risk/Rigor Assessment, Pre-Job Brief,
Independent Third-Party Review, and Post-Job Review
Procedures
Exelon 50.59 Review Process
Procedures
Exelon 50.59 Resource Manual
Procedures
N1-ISP-029-005
Feedwater System Reactor Level
Work Orders
C92793067
Work Orders
C93469632
Work Orders
C93620416
Work Orders
C93694290
Corrective Action
Documents
233517
Engineering
Changes
ECP-18-000035
Unit 1 Feedwater Level Control System Upgrade
001
Engineering
Changes
ECP-18-000407
Unit 1 MSIV 01-01 Stuffing Box Machining
and 1
Procedures
Exelon 50.59 Review Process
011
Procedures
50.59 Evaluation Form
007
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
C93668585
Work Orders
C93669858
Corrective Action
Documents
2481818
Corrective Action
Documents
03993927
Corrective Action
Documents
233517
Corrective Action
Documents
234415
Corrective Action
Documents
235965
Corrective Action
Documents
236212
Corrective Action
Documents
236278
Corrective Action
Documents
239350
Procedures
Conduct of Troubleshooting
Procedures
N1-ISP-001-008
Turbine Stop Valve 10% Closure Instrument Channel
Test/Calibration
00900
Procedures
N1-MFT-136
Digital Feedwater Level Control Site Acceptance Testing
Procedures
N1-ST-Q29
Quarterly Turbine Valve Log
00900
Procedures
N1-ST-R30
Reactor Pressure Vessel and ASME Class 1 System
Leakage Test
01600
Procedures
N1-ST-TYC-001
200
Work Orders
C93619202
Work Orders
C93620311
Work Orders
C93620385
Work Orders
C93621648
Work Orders
C93683030
Work Orders
C93705851
Corrective Action
235425
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
239884
Corrective Action
Documents
243772
Corrective Action
Documents
243966
Corrective Action
Documents
244521
Corrective Action
Documents
Resulting from
Inspection
244980
Miscellaneous
Shutdown Safety
Management Plan for
N1R25
Procedures
Fatigue Management and Work Hour Limits
Procedures
N1-EOP-2
RPV Control - Flowchart
01600
Procedures
N1-OP-16
Feedwater System Booster Pump to Reactor
06700
Procedures
N1-OP-31
Tandem Compound Reheat Turbine
05100
Procedures
N1-OP-4
Shutdown Cooling System
04800
Procedures
N1-OP-43A
Plant Startup
04801
Procedures
N1-OP-43C
Plant Shutdown
2600
Procedures
N1-SOP-1
Reactor Scram
2600
Procedures
Core Verification Guideline
Procedures
Unit Restart Review
Procedures
Post Transient Review
Procedures
OU-NM-103-101
Shutdown Safety Management Program
200
Procedures
OU-NM-4001
Refueling Operations
00601
Procedures
S-MMP-FHP-100
Receiving, Inspection, and Storage of New Fuel
01400
Work Orders
C93621570
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
239043
Corrective Action
Documents
Resulting from
Inspection
243823
Miscellaneous
PCR-19-01581
Miscellaneous
PCR-19-01592
Miscellaneous
PCR-19-01609
Channel Calibration Test of the Standby Gas Treatment
System Exhaust Process
Procedures
N1-ESP-001-130
Main Steam Isolation Valve 7% and 10% Limit Switch
Test
00300
Procedures
N1-ISP-001-018
Electromatic Relief Valve Pressure Switch Calibration
00400
Procedures
N1-ST-C3
HPCI Automatic Initiation Test
01400
Procedures
N1-ST-R12
Initiation of Emergency Condensers from Remote
Shutdown Panel 11 and 12 Operability Test
01000
Procedures
N2-OSP-CSL-Q@002 LPCS Pump and Valve Operability and System Integrity
Test
01400
Procedures
N2-OSP-EGS-
M@001
Diesel Generator and Diesel Air Start Valve Operability
Test, Division I and II
01900
Procedures
N2-RSP-RMS-R103
Channel Calibration Test of the Standby Gas Treatment
System Exhaust Process Radiation Monitor
007T2
Work Orders
C93615244
Work Orders
C93619977
Work Orders
C93620072
Work Orders
C93621713
Procedures
Addendum 3, Appendix 1, NMP Unit 1 EAL Wallboard
Procedures
N1-EOP-4
Primary Containment Control
01700
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
N1-ARP-A4
Alarm Response Procedure, Control Room Panel A4
01500
Procedures
N1-EOP-1
01800
Procedures
N1-EOP-2
RPV Control
01600
Procedures
N1-EOP-7
RPV Flooding
200
Procedures
N1-EOP-8
RPV Blowdown
200
Procedures
N1-OP-16
Feedwater System Booster Pump to Reactor
06700
Procedures
N1-OP-43B
Normal Power Operations
2500
Procedures
N1-SOP-1
Reactor Scram
2600
Procedures
N1-SOP-1.3
Recirc Pump Trip at Power
00400
Procedures
N1-SOP-33A.1
Loss of 115KV
00800
Procedures
Respiratory Protection Program Description
Work Orders
C92030523
Control Room Outside Air Special Filter Train Functional
Test
March 19,
2015
Work Orders
C93651401
Control Room Envelope Filtration System Operability
Test
February 15,
2019
71151
Corrective Action
Documents
Resulting from
Inspection
256712
71151
Corrective Action
Documents
Resulting from
Inspection
259004
71151
Miscellaneous
Regulatory Assessment Performance Indicator Guideline
71151
Procedures
Dose Equivalent Iodine Determination
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71151
Procedures
Monthly Data Elements for NRC Reactor Coolant System
Specific Activity
71151
Procedures
Monthly Data Elements for NRC Reactor Coolant System
(RCS) Leakage
71151
Procedures
N1-ST-SO
Shift Checks
03000
71151
Procedures
N2-OSP-LOG-S001
Shift Checks - Mode 1
03800
Calculations
ECP-16-000531
Nine Mile Point Unit 1 RACKLIFE Model 2016 Update
Calculations
ECP-18-000696
Nine Mile Point Unit 1 RACKLIFE Model 2018 Update
Calculations
S22.1-XX-G086NF
Nine Mile Point Unit 1 Criticality Analysis for the Spent
Fuel Pool Boraflex Racks
Calibration
Records
NET 28064-006-01
Inspection & Testing of Boraflex Surveillance Coupon
S20 from Nine Mile Point Unit 1
completed
6/21/16
Calibration
Records
NET 28064-017-01
Inspection & Testing of Boraflex Surveillance Coupon
S21 from Nine Mile Point Unit 1
completed
9/10/18
Calibration
Records
NET 307-01
BADGER Test Campaign at Nine Mile Point Unit 1
completed
3/17/09
Corrective Action
Documents
2608609
Corrective Action
Documents
04094907
Corrective Action
Documents
04116759
Corrective Action
Documents
04136339
Corrective Action
Documents
04137255
Corrective Action
Documents
04138851
Corrective Action
Documents
04157970
217844
245508
239884
235724
234115
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
230023
243823
227358
231058
230591
211553
Corrective Action
Documents
04167387
Corrective Action
Documents
04179494
Corrective Action
Documents
04192187
Corrective Action
Documents
Resulting from
Inspection
254594
Corrective Action
Documents
Resulting from
Inspection
254594
Corrective Action
Documents
Resulting from
Inspection
254621
Corrective Action
Documents
Resulting from
Inspection
256316
Corrective Action
Documents
Resulting from
Inspection
263226
Corrective Action
Documents
263766
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Miscellaneous
Nine Mile Point
Nuclear Station Unit 1
Issuance of Amendment No. 234 - Change to Remove
Boraflex Credit from Spent Fuel Racks
January 11,
2019
Miscellaneous
Nine Mile Point Unit 1
Renewed Facility Operating License No. DPR-63
Miscellaneous
Nine Mile Point Unit 1
Updated Final Safety Report
Miscellaneous
Monitoring of Neutron Absorbing Materials in Spent Fuel
Pools
April 7, 2016
Procedures
Human Performance Tools and Verification Practices
Procedures
Procedure Use and Adherence
Procedures
Pre-Job Briefings
Procedures
Conduct of Troubleshooting
Procedures
N1-OP-13
Emergency Cooling System
4300
Procedures
N1-OP-15B
Condensate Transfer System
2400
Procedures
N1-OP-34
Refueling Procedure
03900
Procedures
N1-PM-Q7
Quarterly Main Turbine Testing and Generator Core
Monitor Testing
0500
Procedures
N1-RSP-8Q
Routine Calibration of Refueling Platform High Range
Area Radiation Monitor
00800
Procedures
N1-ST-Q5
Primary Containment Isolation Valves Operability Test
3400
Procedures
N1-ST-R9
Core Spray Operability Test Using Demineralized (CST)
Water
016T1
Procedures
N2-ISP-RDS-@101
Scram Discharge Volume Water Level Instrument
Channel Calibration
2T1
Procedures
N2-OSP-EGS-
M@002
Diesel Generator and Diesel Air Start Valve Operability
Test - Division III
2100
Procedures
N2-RPS-RMS-Q109
Channel Functional Test of the Main Control Room
Ventilation Process Radiation Monitors
0600
Procedures
N2-RSP-RMS-R103
Channel Calibration Test of the Standby Gas Treatment
System Exhaust Process Radiation Monitor
007T2
Procedures
NMP-AMP-BFX01
Nine Mile Point Unit 1, Program Plan for Spent Fuel Rack
Boraflex Degradation Monitoring Program
Procedures
Operating Narrative Logs and Records
Procedures
Operator Aid Postings
2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
OU-NM-103-101
Shutdown Safety management Program
00300
Procedures
Issue Identification and Screening Process
Procedures
SA-NM-129
Electrical Safety
200
Procedures
Surveillance Program Requirements
Work Orders
C93681986
Corrective Action
Documents
236028
Corrective Action
Documents
244521
Corrective Action
Documents
245508
Corrective Action
Documents
Resulting from
Inspection
244980
Corrective Action
Documents
Resulting from
Inspection
263653
Drawings
C-18002-C
Steam Flow Main Steam and High Pressure Turbine
Piping and Instrumentation Diagram, Sheet 1
Drawings
G.E. Drawing
186R999
Turbine Control Diagram
Miscellaneous
Miscellaneous
Vendor Technical
Manual
N1G08000TURBIN001 (N11311)
2.00
Procedures
Conduct of Troubleshooting
Procedures
N1-EOP-2
RPV Control - Flowchart
01600
Procedures
N1-IPM-302-001
Electronic Pressure Regulator (EPR)
01900
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
N1-IPM-302-002
Electronic Pressure Regulator (EPR) PLC Preventive
Maintenance
200
Procedures
N1-ISP-001-008
Turbine Stop Valve 10% Closure Instrument Channel
Test/Calibration
00900
Procedures
N1-OP-31
Tandem Compound Reheat Turbine
05100
Procedures
N1-OP-31
Tandem Compound Reheat Turbine
05000
Procedures
N1-OP-43A
Plant Startup
04800
Procedures
N1-SOP-1
Reactor Scram
2600
Procedures
N1-SOP-31.1
00500
Procedures
N1-SOP-31.2
Pressure Regulator Malfunctions
00500
Procedures
N1-ST-Q29
Quarterly Turbine Valve Log
00900
Procedures
N2-SOP-101D
Rapid Power Reduction
01000
Procedures
Corrective Action Program Procedure
Work Orders
C93620311
Work Orders
C93621648
Work Orders
C93621693
Work Orders
C93626528
Work Orders
C93706420