IR 05000220/2019002

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Integrated Inspection Report 05000220/2019002 and 05000410/2019002
ML19225B640
Person / Time
Site: Nine Mile Point  Constellation icon.png
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:

DPR-63 and NPF-69

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

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

Temporary Ventilation System Setups

  • Unit 2 dry cask storage campaign temporary ventilation system
  • Unit 2 equipment pit temporary ventilation

Portable or Installed 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

71111.01

Corrective Action

Documents

2702620

71111.01

Corrective Action

Documents

04157336

71111.01

Corrective Action

Documents

04171068

71111.01

Corrective Action

Documents

04190212

71111.01

Procedures

N1-OP-26

Turbine Building Ventilation System

200

71111.01

Procedures

N1-OP-45

Emergency Diesel Generators

04800

71111.01

Procedures

N1-OP-47A

25 VDC Power System

200

71111.01

Procedures

N1-OP-64

Meteorological Monitoring

01900

71111.01

Procedures

N2-OP-102

Meteorological Monitoring

2600

71111.01

Work Orders

C93658067

71111.01

Work Orders

C93660309

71111.04

Drawings

C-18018-C

Reactor Shutdown Cooling P&I Diagram

71111.04

Procedures

N1-OP-4

Shutdown Cooling System

04800

71111.04

Procedures

N1-OP-45

Emergency Diesel Generators

04700

71111.04S

Corrective Action

Documents

04038003

71111.04S

Corrective Action

Documents

04044383

71111.04S

Drawings

C-18022-C, Sheet 1

Service Water, Reactor and Turbine Buildings P&I

Diagram

71111.04S

Miscellaneous

SDBD-502

Service Water System Design Basis Document

71111.04S

Procedures

N1-OP-18

Service Water System

04400

71111.04S

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

71111.07A

Corrective Action

Documents

04196392

71111.07A

Miscellaneous

NMPNS-HX-001

Generic Letter 89-13 Heat Exchanger Program Plan

71111.07A

Procedures

GAP-HSC-02

System Aging Inspection and Cleanness Controls

2000

71111.07A

Procedures

N2-PM-HVR-401

Performance Evaluation Test for Unit Cooler

2HVR*UC401A, B, C, D, E, and F

00100

71111.07A

Procedures

S-TDP-REL-0103

GL 89-13 Service Water System Problems Affecting

Safety-Related Equipment Program Plan

71111.07A

Work Orders

C92972141

71111.08G Miscellaneous

Field Deviation

Disposition Request

(FFDR) 005N2487

NMP1 Shroud Tie Rod

71111.08G NDE Reports

INR N1R25 IVVI 19

Tie Rod Clevis Pin and Nut - Indication Notification

Report for Clevis Pin 090 - 089 side

04/01/2019

71111.08G NDE Reports

INR N1R25 IVVI 19

166 TR Clevis Pin and Nut Post Torque - Indication

Notification Report for Clevis Pin 166 - 165 side

04/01/2019

71111.12

Corrective Action

Documents

03988865

71111.12

Corrective Action

Documents

03990258

71111.12

Corrective Action

Documents

04122437

71111.12

Corrective Action

Documents

230591

71111.12

Corrective Action

Documents

232357

71111.12

Corrective Action

Documents

232473

71111.12

Corrective Action

232618

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

71111.12

Procedures

ER-AA-320

Maintenance Rule Implementation Per NEI 18-10

71111.12

Procedures

ER-AA-320-1003

Maintenance Rule 18-10 - Failure Definition

71111.12

Procedures

ER-AA-320-1004

Maintenance Rule 18-10 - Performance Monitoring and

Dispositioning Between (a)(1) and (a)(2)

71111.13

Procedures

N1-MMP-GEN-901

Reactor Reassembly

2700

71111.13

Procedures

N1-OP-34

Refueling Procedure

03900

71111.13

Procedures

N1-PM-34

Reactor Cavity Flood up and Drain Down

00900

71111.13

Work Orders

C93620400

71111.15

Corrective Action

Documents

229798

71111.15

Corrective Action

Documents

231873

71111.15

Corrective Action

Documents

233329

71111.15

Corrective Action

Documents

238289

71111.15

Corrective Action

Documents

240207

71111.15

Corrective Action

Documents

240629

71111.15

Corrective Action

Documents

240815

71111.15

Corrective Action

Documents

246485

71111.15

Corrective Action

Documents

248297

71111.15

Corrective Action

Documents

249623

71111.15

Corrective Action

Documents

249690

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.15

Drawings

C-18007-C

Sheet 1, Reactor Core Spray P&I Diagram

71111.15

Drawings

C-18018-C

Reactor Shutdown Cooling

71111.15

Miscellaneous

Core Operating Limits Report Nine Mile Point 1

71111.15

Miscellaneous

ACMP, Degraded Flow on Jet Pump #6

71111.15

Miscellaneous

N1P020500PUMP002 Instructions for Installing, Operating, and Maintaining

Pacific Pumps Type HVC

71111.15

Procedures

N1-ARP-F3

Control Room Panel F3

00900

71111.15

Procedures

N1-ARP-K3

Control Room Panel K3

00900

71111.15

Procedures

N1-MSP-GEN-251

ASME OM Code Pressure Relief Valve Removal, Bench

Testing, and Installation

01300

71111.15

Procedures

N1-OP-31

Tandem Compound Reheat Turbine

05100

71111.15

Procedures

N1-OP-38C

Local Power Range Monitors (LPRM) Average Power

Range Monitors (APRM)

2900

71111.15

Procedures

N1-OP-4

Shutdown Cooling System

04800

71111.15

Procedures

N1-OP-43A

Plant Startup

04801

71111.15

Procedures

N1-ST-Q1A

CS 111 Pump, Valve ad SDC Water Seal Check Valve

Operability Test

01800

71111.15

Procedures

N1-ST-R9

Core Spray Operability Test Using Demineralized (CST)

Water

01300

71111.15

Procedures

N2-MPM-EGS-508

General Motors Diesel (DIV III) Lube Oil Preventative

Maintenance Sampling

00000

71111.15

Work Orders

C93622411

71111.15

Work Orders

C93705978

71111.15

Work Orders

C93706436

71111.15

Work Orders

C93706442

71111.17T

Calculations

EC-83

Overload Heater Selection for Normal and Emergency

600 Volts AC and 125 Volts DC Motor Control Centers

71111.17T

Calculations

S20.7RVV002

Drywell Ambient Temperature Effect on Reactor Head

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Safety Valve Setpoint

71111.17T

Corrective Action

Documents

2715685

71111.17T

Corrective Action

Documents

2715901

71111.17T

Corrective Action

Documents

2721034

71111.17T

Corrective Action

Documents

2721963

71111.17T

Corrective Action

Documents

03994179

71111.17T

Corrective Action

Documents

226374

71111.17T

Corrective Action

Documents

226377

71111.17T

Corrective Action

Documents

226730

71111.17T

Corrective Action

Documents

226801

71111.17T

Corrective Action

Documents

227857

71111.17T

Corrective Action

Documents

227873

71111.17T

Corrective Action

Documents

Resulting from

Inspection

243234*

71111.17T

Corrective Action

Documents

Resulting from

Inspection

243411*

71111.17T

Corrective Action

Documents

Resulting from

243421*

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Inspection

71111.17T

Drawings

C22004C-003, Sheet

Interconnection Wiring Diagram for Feedwater

Instrumentation System

71111.17T

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

71111.17T

Miscellaneous

Nine Mile Point Nuclear Station Units 1 and 2 10 CFR 50.46 Annual Report

01/25/2019

71111.17T

Miscellaneous

Nine Mile Point Unit 1 Core Operating Limits Report,

Cycle 23

71111.17T

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

71111.17T

Miscellaneous

2N3714

Nine Mile Point Nuclear Station Unit 1 TRACG-LOCA

Loss of Coolant Analysis for GNF2

03/16/2017

71111.17T

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

71111.17T

Miscellaneous

EE-00435

Equivalency Evaluation to Identify Equivalent

Replacements for Existing Reactor Vessel Skin and

Flange Temperature Thermocouples

71111.17T

Miscellaneous

NMP-2018-209

TRR Details, Implement ECP-18-000388 New

Recirculation Sub-cooling Indication and Alarm

09/18/2018

71111.17T

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

71111.17T

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

71111.17T

Miscellaneous

Technical

Specifications

Nine Mile Point Nuclear Station Unit 1

71111.17T

Miscellaneous

Technical

Specifications

Nine Mile Point Nuclear Station Unit 2

71111.17T

Miscellaneous

UFSAR Change 2-17-

CRF-008

Unit 2 Division I and II Emergency Diesel Generator

Vibration Switch Bypass

71111.17T

Miscellaneous

Updated Final Safety

Analysis Report

Nine Mile Point Nuclear Station Unit 1

71111.17T

Miscellaneous

Updated Final Safety

Analysis Report

Nine Mile Point Nuclear Station Unit 2

71111.17T

Miscellaneous

WNA-AR-00206-GEN

Software Failure Analysis of Ovation Platform

71111.17T

Miscellaneous

WNA-AR-00593-

G9MI2

Turbine Control and Protection Failure Modes and

Effects Analysis

71111.17T

Procedures

HU-AA-1212

Technical Task Risk/Rigor Assessment, Pre-Job Brief,

Independent Third-Party Review, and Post-Job Review

71111.17T

Procedures

LS-AA-104

Exelon 50.59 Review Process

71111.17T

Procedures

LS-AA-104-1000

Exelon 50.59 Resource Manual

71111.17T

Procedures

N1-ISP-029-005

Feedwater System Reactor Level

71111.17T

Work Orders

C92793067

71111.17T

Work Orders

C93469632

71111.17T

Work Orders

C93620416

71111.17T

Work Orders

C93694290

71111.18

Corrective Action

Documents

233517

71111.18

Engineering

Changes

ECP-18-000035

Unit 1 Feedwater Level Control System Upgrade

001

71111.18

Engineering

Changes

ECP-18-000407

Unit 1 MSIV 01-01 Stuffing Box Machining

and 1

71111.18

Procedures

LS-AA-104

Exelon 50.59 Review Process

011

71111.18

Procedures

LS-AA-104-1004

50.59 Evaluation Form

007

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.18

Work Orders

C93668585

71111.18

Work Orders

C93669858

71111.19

Corrective Action

Documents

2481818

71111.19

Corrective Action

Documents

03993927

71111.19

Corrective Action

Documents

233517

71111.19

Corrective Action

Documents

234415

71111.19

Corrective Action

Documents

235965

71111.19

Corrective Action

Documents

236212

71111.19

Corrective Action

Documents

236278

71111.19

Corrective Action

Documents

239350

71111.19

Procedures

MA-AA-716-004

Conduct of Troubleshooting

71111.19

Procedures

N1-ISP-001-008

Turbine Stop Valve 10% Closure Instrument Channel

Test/Calibration

00900

71111.19

Procedures

N1-MFT-136

Digital Feedwater Level Control Site Acceptance Testing

71111.19

Procedures

N1-ST-Q29

Quarterly Turbine Valve Log

00900

71111.19

Procedures

N1-ST-R30

Reactor Pressure Vessel and ASME Class 1 System

Leakage Test

01600

71111.19

Procedures

N1-ST-TYC-001

200

71111.19

Work Orders

C93619202

71111.19

Work Orders

C93620311

71111.19

Work Orders

C93620385

71111.19

Work Orders

C93621648

71111.19

Work Orders

C93683030

71111.19

Work Orders

C93705851

71111.20

Corrective Action

235425

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

71111.20

Corrective Action

Documents

239884

71111.20

Corrective Action

Documents

243772

71111.20

Corrective Action

Documents

243966

71111.20

Corrective Action

Documents

244521

71111.20

Corrective Action

Documents

Resulting from

Inspection

244980

71111.20

Miscellaneous

Shutdown Safety

Management Plan for

N1R25

71111.20

Procedures

LS-AA-119

Fatigue Management and Work Hour Limits

71111.20

Procedures

N1-EOP-2

RPV Control - Flowchart

01600

71111.20

Procedures

N1-OP-16

Feedwater System Booster Pump to Reactor

06700

71111.20

Procedures

N1-OP-31

Tandem Compound Reheat Turbine

05100

71111.20

Procedures

N1-OP-4

Shutdown Cooling System

04800

71111.20

Procedures

N1-OP-43A

Plant Startup

04801

71111.20

Procedures

N1-OP-43C

Plant Shutdown

2600

71111.20

Procedures

N1-SOP-1

Reactor Scram

2600

71111.20

Procedures

NF-AA-330-1001

Core Verification Guideline

71111.20

Procedures

OP-AA-101-108

Unit Restart Review

71111.20

Procedures

OP-AA-108-114

Post Transient Review

71111.20

Procedures

OU-NM-103-101

Shutdown Safety Management Program

200

71111.20

Procedures

OU-NM-4001

Refueling Operations

00601

71111.20

Procedures

S-MMP-FHP-100

Receiving, Inspection, and Storage of New Fuel

01400

71111.20

Work Orders

C93621570

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.22

Corrective Action

Documents

239043

71111.22

Corrective Action

Documents

Resulting from

Inspection

243823

71111.22

Miscellaneous

PCR-19-01581

71111.22

Miscellaneous

PCR-19-01592

71111.22

Miscellaneous

PCR-19-01609

Channel Calibration Test of the Standby Gas Treatment

System Exhaust Process

71111.22

Procedures

N1-ESP-001-130

Main Steam Isolation Valve 7% and 10% Limit Switch

Test

00300

71111.22

Procedures

N1-ISP-001-018

Electromatic Relief Valve Pressure Switch Calibration

00400

71111.22

Procedures

N1-ST-C3

HPCI Automatic Initiation Test

01400

71111.22

Procedures

N1-ST-R12

Initiation of Emergency Condensers from Remote

Shutdown Panel 11 and 12 Operability Test

01000

71111.22

Procedures

N2-OSP-CSL-Q@002 LPCS Pump and Valve Operability and System Integrity

Test

01400

71111.22

Procedures

N2-OSP-EGS-

M@001

Diesel Generator and Diesel Air Start Valve Operability

Test, Division I and II

01900

71111.22

Procedures

N2-RSP-RMS-R103

Channel Calibration Test of the Standby Gas Treatment

System Exhaust Process Radiation Monitor

007T2

71111.22

Work Orders

C93615244

71111.22

Work Orders

C93619977

71111.22

Work Orders

C93620072

71111.22

Work Orders

C93621713

71114.06

Procedures

EP-AA-1013

Addendum 3, Appendix 1, NMP Unit 1 EAL Wallboard

71114.06

Procedures

N1-EOP-4

Primary Containment Control

01700

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71114.06

Procedures

N1-ARP-A4

Alarm Response Procedure, Control Room Panel A4

01500

71114.06

Procedures

N1-EOP-1

NMP1 EOP Support Procedure

01800

71114.06

Procedures

N1-EOP-2

RPV Control

01600

71114.06

Procedures

N1-EOP-7

RPV Flooding

200

71114.06

Procedures

N1-EOP-8

RPV Blowdown

200

71114.06

Procedures

N1-OP-16

Feedwater System Booster Pump to Reactor

06700

71114.06

Procedures

N1-OP-43B

Normal Power Operations

2500

71114.06

Procedures

N1-SOP-1

Reactor Scram

2600

71114.06

Procedures

N1-SOP-1.3

Recirc Pump Trip at Power

00400

71114.06

Procedures

N1-SOP-33A.1

Loss of 115KV

00800

71124.03

Procedures

RP-AA-13

Respiratory Protection Program Description

71124.03

Work Orders

C92030523

Control Room Outside Air Special Filter Train Functional

Test

March 19,

2015

71124.03

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

NEI 99-02

Regulatory Assessment Performance Indicator Guideline

71151

Procedures

CY-AA-130-3010

Dose Equivalent Iodine Determination

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71151

Procedures

LS-AA-2090

Monthly Data Elements for NRC Reactor Coolant System

Specific Activity

71151

Procedures

LS-AA-2100

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

71152

Calculations

ECP-16-000531

Nine Mile Point Unit 1 RACKLIFE Model 2016 Update

71152

Calculations

ECP-18-000696

Nine Mile Point Unit 1 RACKLIFE Model 2018 Update

71152

Calculations

S22.1-XX-G086NF

Nine Mile Point Unit 1 Criticality Analysis for the Spent

Fuel Pool Boraflex Racks

71152

Calibration

Records

NET 28064-006-01

Inspection & Testing of Boraflex Surveillance Coupon

S20 from Nine Mile Point Unit 1

completed

6/21/16

71152

Calibration

Records

NET 28064-017-01

Inspection & Testing of Boraflex Surveillance Coupon

S21 from Nine Mile Point Unit 1

completed

9/10/18

71152

Calibration

Records

NET 307-01

BADGER Test Campaign at Nine Mile Point Unit 1

completed

3/17/09

71152

Corrective Action

Documents

2608609

71152

Corrective Action

Documents

04094907

71152

Corrective Action

Documents

04116759

71152

Corrective Action

Documents

04136339

71152

Corrective Action

Documents

04137255

71152

Corrective Action

Documents

04138851

71152

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

71152

Corrective Action

Documents

04167387

71152

Corrective Action

Documents

04179494

71152

Corrective Action

Documents

04192187

71152

Corrective Action

Documents

Resulting from

Inspection

254594

71152

Corrective Action

Documents

Resulting from

Inspection

254594

71152

Corrective Action

Documents

Resulting from

Inspection

254621

71152

Corrective Action

Documents

Resulting from

Inspection

256316

71152

Corrective Action

Documents

Resulting from

Inspection

263226

71152

Corrective Action

Documents

263766

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Resulting from

Inspection

71152

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

71152

Miscellaneous

Nine Mile Point Unit 1

Renewed Facility Operating License No. DPR-63

71152

Miscellaneous

Nine Mile Point Unit 1

Updated Final Safety Report

71152

Miscellaneous

NRC Generic Letter 2016-01

Monitoring of Neutron Absorbing Materials in Spent Fuel

Pools

April 7, 2016

71152

Procedures

HU-AA-101

Human Performance Tools and Verification Practices

71152

Procedures

HU-AA-104-101

Procedure Use and Adherence

71152

Procedures

HU-AA-1211

Pre-Job Briefings

71152

Procedures

MA-AA-716-004

Conduct of Troubleshooting

71152

Procedures

N1-OP-13

Emergency Cooling System

4300

71152

Procedures

N1-OP-15B

Condensate Transfer System

2400

71152

Procedures

N1-OP-34

Refueling Procedure

03900

71152

Procedures

N1-PM-Q7

Quarterly Main Turbine Testing and Generator Core

Monitor Testing

0500

71152

Procedures

N1-RSP-8Q

Routine Calibration of Refueling Platform High Range

Area Radiation Monitor

00800

71152

Procedures

N1-ST-Q5

Primary Containment Isolation Valves Operability Test

3400

71152

Procedures

N1-ST-R9

Core Spray Operability Test Using Demineralized (CST)

Water

016T1

71152

Procedures

N2-ISP-RDS-@101

Scram Discharge Volume Water Level Instrument

Channel Calibration

2T1

71152

Procedures

N2-OSP-EGS-

M@002

Diesel Generator and Diesel Air Start Valve Operability

Test - Division III

2100

71152

Procedures

N2-RPS-RMS-Q109

Channel Functional Test of the Main Control Room

Ventilation Process Radiation Monitors

0600

71152

Procedures

N2-RSP-RMS-R103

Channel Calibration Test of the Standby Gas Treatment

System Exhaust Process Radiation Monitor

007T2

71152

Procedures

NMP-AMP-BFX01

Nine Mile Point Unit 1, Program Plan for Spent Fuel Rack

Boraflex Degradation Monitoring Program

71152

Procedures

OP-AA-111-101

Operating Narrative Logs and Records

71152

Procedures

OP-AA-115-101

Operator Aid Postings

2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152

Procedures

OU-NM-103-101

Shutdown Safety management Program

00300

71152

Procedures

PI-AA-120

Issue Identification and Screening Process

71152

Procedures

SA-NM-129

Electrical Safety

200

71152

Procedures

WC-AA-111

Surveillance Program Requirements

71152

Work Orders

C93681986

71153

Corrective Action

Documents

236028

71153

Corrective Action

Documents

244521

71153

Corrective Action

Documents

245508

71153

Corrective Action

Documents

Resulting from

Inspection

244980

71153

Corrective Action

Documents

Resulting from

Inspection

263653

71153

Drawings

C-18002-C

Steam Flow Main Steam and High Pressure Turbine

Piping and Instrumentation Diagram, Sheet 1

71153

Drawings

G.E. Drawing

186R999

Turbine Control Diagram

71153

Miscellaneous

Event Notification#53998

71153

Miscellaneous

Vendor Technical

Manual

N1G08000TURBIN001 (N11311)

2.00

71153

Procedures

MA-AA-716-004

Conduct of Troubleshooting

71153

Procedures

N1-EOP-2

RPV Control - Flowchart

01600

71153

Procedures

N1-IPM-302-001

Electronic Pressure Regulator (EPR)

01900

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71153

Procedures

N1-IPM-302-002

Electronic Pressure Regulator (EPR) PLC Preventive

Maintenance

200

71153

Procedures

N1-ISP-001-008

Turbine Stop Valve 10% Closure Instrument Channel

Test/Calibration

00900

71153

Procedures

N1-OP-31

Tandem Compound Reheat Turbine

05100

71153

Procedures

N1-OP-31

Tandem Compound Reheat Turbine

05000

71153

Procedures

N1-OP-43A

Plant Startup

04800

71153

Procedures

N1-SOP-1

Reactor Scram

2600

71153

Procedures

N1-SOP-31.1

Turbine Trip

00500

71153

Procedures

N1-SOP-31.2

Pressure Regulator Malfunctions

00500

71153

Procedures

N1-ST-Q29

Quarterly Turbine Valve Log

00900

71153

Procedures

N2-SOP-101D

Rapid Power Reduction

01000

71153

Procedures

PI-AA-125

Corrective Action Program Procedure

71153

Work Orders

C93620311

71153

Work Orders

C93621648

71153

Work Orders

C93621693

71153

Work Orders

C93626528

71153

Work Orders

C93706420