IR 05000220/2020001

Integrated Inspection Report 05000220/2020001 and 05000410/2020001 and Independent Spent Fuel Storage Installation Inspection Report 07201036/2020001

ML20122A200
Person / Time
Site:	Nine Mile Point, 07201036
Issue date:	05/04/2020
From:	Erin Carfang Division Reactor Projects I
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2020001
Download: ML20122A200 (22)

Text

May 4, 2020

SUBJECT:

NINE MILE POINT NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000220/2020001 AND 05000410/2020001 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07201036/2020001

Dear Mr. Hanson:

On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station. On April 22, 2020, 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.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Nine Mile Point Nuclear Station.

If you disagree with a cross-cutting aspect assignment 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 Nuclear Station. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, X /RA/

Signed by: Erin E. Carfang Erin E. Carfang, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 05000220 and 05000410 License Nos. DPR-63 and NPF-69

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000220, 05000410, and 07201036 License Numbers: DPR-63 and NPF-69 Report Numbers: 05000220/2020001, 05000410/2020001, and 07201036/2020001 Enterprise Identifier: I-2020-001-0039 I-2020-001-0134 Licensee: Exelon Generation Company, LLC Facility: Nine Mile Point Nuclear Station Location: Oswego, NY Inspection Dates: January 1, 2020 to March 31, 2020 Inspectors: G. Stock, Senior Resident Inspector J. Dolecki, Resident Inspector B. Sienel, Resident Inspector J. Brand, Reactor Inspector J. Kulp, Senior Reactor Inspector E. Love, Transportation and Storage Safety Inspector J. Nicholson, Senior Health Physicist R. Rolph, Health Physicist J. Schoppy, Senior Reactor Inspector Approved By: Erin E. Carfang, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure

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.

List of Findings and Violations

Failure to Replace Degraded Direct Current (DC) Motor Brushes on Safety-Related Motor-Operated Valve (MOV) Led to Failure to Close Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.14] - 71152 NCV 05000220/2020001-01 Conservative Closed Bias A self-revealed Green Finding and associated NCV of Title 10 of the Code of Federal Regulations (CFR) Part 50, Appendix B, Criterion XVI, Corrective Action, was identified when Exelon failed to correct a condition adverse to quality in 2017 which led to the failure of Unit 1 emergency cooling (EC) steam isolation valve IV-39-08R to close when called upon for system isolation.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 remained at or near rated thermal power throughout the inspection period.

Unit 2 began the inspection period at rated thermal power. On January 17, 2020, reactor power was reduced to 80 percent to perform a rod pattern adjustment. Operators restored power to 100 percent on January 18, 2020. On January 24, 2020, Unit 2 began end of cycle coastdown which continued until March 4, 2020. On March 4, 2020, Unit 2 operators inserted a manual scram due to a significant electro-hydraulic control system leak and entered their planned refueling outage, which had been scheduled to begin March 9, 2020. Unit 2 remained shut down 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/readingrm/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. From January 1 - March 19, 2020, 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week during which they conducted plant status activities as described in IMC 2515, Appendix D, and observed risk significant activities when warranted. In addition, resident and regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In the cases where it was determined the objectives and requirements could not be performed remotely, management elected to reschedule the inspection to a later date.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated readiness for impending adverse weather for a blizzard warning on February 27, 2020.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 1 containment spray 121 on January 13, 2020

(2) Unit 2 instrument air system on February 10, 2020

(3) Unit 2 Division II shutdown cooling on March 9, 2020

(4) Unit 2 spent fuel pool cooling on March 11, 2020

(5) Unit 2 Division II emergency diesel generator on March 27, 2020

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Unit 2 turbine building, condenser, fire area 50, on March 10, 2020

(2) Unit 2 turbine building, feedwater heater bays, fire area 50, on March 10, 2020

(3) Unit 2 normal switchgear building, east switchgear room, fire area 79, on March 18, 2020

(4) Unit 2 control building, remote shutdown room 'A', fire area 17, on March 18, 2020

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated onsite fire brigade training and performance during an unannounced fire drill on February 18, 2020.

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 2 residual heat removal heat exchanger 2RHS*E1A

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 reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities during the Nine Mile Point Unit 2 N2R17 refueling outage from March 10, 2020, to March 15, 2020:

03.01.a - Nondestructive Examination and Welding Activities.

• Automated phased array of the N2A recirculation nozzle to pipe dissimilar metal weld (2R17-APR-01)

• Manual ultrasonic test of the N2E recirculation nozzle inner radius 2RPV-ACX (R-08)

• Manual ultrasonic test of the N2E recirculation nozzle to reactor vessel shell weld 2RPV-KA-07 (R-11)

• Magnetic particle test of reactor core isolation cooling piping integral attachment 21-CS-57-08-FW302 (ISI-MT-20-004)

• IWE/IWL inspection (VT3) of suppression chamber exterior concrete wall on 215 level (ISI-VT-20-188)

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 main turbine emergency governor trip testing and reactor building emergency ventilation initiation testing on March 2, 2020.

(2) The inspectors observed and evaluated Unit 2 licensed operator performance in the control room during a manual reactor scram on March 4, 2020.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)

(1) The inspectors observed and evaluated a Unit 1 simulator evaluation that included an electrical fault on a safety related power board, a reactor building closed loop cooling system leak inside the drywell, and a failure to scram with an unisolable reactor water cleanup system leak on January 28, 2020.

(2) The inspectors observed and evaluated Unit 2 simulator training on a new digital feedwater level control modification on February 11, 2020.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Maintenance Rule Periodic Assessment, October 1, 2017 - September 30, 2019, reviewed on February 7, 2020

(2) Unit 1 emergency diesel generator 103 air start system on March 2, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Unit 1 elevated risk during a 115-kilovolt Line 1 outage to support an emergent grid repair on January 14, 2020

(2) Unit 1 elevated risk during an emergent main turbine electro-hydraulic pressure regulator filter replacement and pressure regulator swap on January 29, 2020

(3) Unit 2 emergent work on the 'C' instrument air compressor on February 10, 2020

(4) Unit 2 elevated risk during a planned reactor cavity flood up on March 8, 2020

(5) Unit 2 elevated risk during planned control rod drive mechanism replacements on March 13, 2020

(6) Unit 2 elevated risk during planned reactor cavity draindown on March 24, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 2 recirculation flow control valve 'A' due to a blown fuse on a hydraulic pressure unit on January 2, 2020

(2) Unit 2 standby gas treatment system due to air leaks identified during pneumatic supply and accumulator leak rate testing on January 13, 2020

(3) Unit 1 station battery 11 due to a ground on February 6, 2020

(4) Unit 1 core spray check valves due to elevated temperatures on February 20, 2020

(5) Unit 2 'A' spent fuel pool cooling pump due to decreasing oil level on February 24, 2020

(6) Unit 2 'B' residual heat removal pump following loss of shutdown cooling on March 9, 2020

(7) Unit 2 jet pumps 1 and 5 due to degradation caused by foreign material lodged in the inlet mixer nozzles on March 23, 2020

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

(3 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) Permanent Modification: Unit 2 Engineering Change Package ECP-18-000691, Remove Unit 2 Reactor Recirculation Pump Auto Trip Low Speed Transfer on Differential Temperature

(2) Permanent Modification: Unit 2 Engineering Change Package ECP-19-000301, Upgrade Unit 2 MSIV [main steam isolation valve] Internals

(3) Permanent Modification: Unit 2 Engineering Change Package ECP-18-000373, Diesel Generator Governor Replacement

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:

(1) Unit 2 'C' instrument air compressor following motor replacement on March 1, 2020

(2) Unit 2 'E' service water strainer following maintenance on March 3, 2020

(3) Unit 2 'A' source range detector following replacement on March 9, 2020

(4) Unit 1 control room ventilation system following system maintenance on March 24, 2020

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1) The inspectors evaluated Unit 2 Refueling Outage N2R17 activities from March 4, 2020 through March 31, 2020.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) N2-OSP-EGS-M@001, Diesel Generator and Diesel Air Start Valve Operability Test Division II, on February 13, 2020

(2) N2-OSP-EGS-R007, Operating Cycle Diesel Generator Simulated Loss of Offsite Power Division III, on February 26, 2020

(3) N2-OSP-RMC-R001, Mode Switch Shutdown Position Rod Block Channel Functional

Test, on March 12, 2020 Inservice Testing (IP Section 03.01) (2 Samples)

(1) N1-ST-Q8A, Liquid Poison Pump 11 and Check Valve Operability Test, on January 13, 2020

(2) N2-OSP-SLS-R001, Standby Liquid Control Manual Initiate Actuation and ASME XI Pressure Test, on March 16, 2020

Containment Isolation Valve Testing (IP Section 03.01) (2 Samples)

(1) N2-OSP-MSS-003, Main Steam Isolation Valve Leak Rate Test (Inboard Static Head of Water), on March 9, 2020

(2) N2-OSP-CNT-008, Local Leak Rate Testing of Drywell to Suppression Chamber Vacuum Breaker, on March 19, 2020

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

(1 Sample)

(1) The inspectors evaluated the conduct of a routine Exelon emergency preparedness drill on February 11, 2020.

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) A Unit 1 simulator evaluation which included a reactor building closed loop cooling system leak inside the drywell, a failure to scram with an unisolable reactor water cleanup system leak, and ultimately the declaration of a Site Area Emergency on January 28,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated radiological protection-related instructions to plant workers.

Radiological Hazards Control and Work Coverage (IP Section 03.04) (1 Sample)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

(1) Undervessel control rod drive maintenance. Dose gradient from head to chest.

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (1 Sample)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1)

• Unit 2 north drywell entrance

• Unit 2 traversing incore probe (TIP) room (Very High Radiation Area)

• Unit 2 'A' reactor water cleanup pump room

• Unit 2 'B' reactor water cleanup pump room

• Unit 2 drywell equipment drain tank pump room

• Unit 2 drywell floor drain tank pump room

• Unit 2 reactor building drain pump room

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

(1) Unit 1 (January 1, 2019 - December 31, 2019)

(2) Unit 2 (January 1, 2019 - December 31, 2019)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)

(2 Samples)

(1) Unit 1 (January 1, 2019 - December 31, 2019)

(2) Unit 2 (January 1, 2019 - December 31, 2019)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (January 1, 2019 - December 31, 2019)

(2) Unit 2 (January 1, 2019 - December 31, 2019)

71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)

(1) The inspectors evaluated the licensees response to a Unit 2 manual reactor scram following a turbine electro-hydraulic control fluid leak on March 4, 2020.

(2) The inspectors evaluated the licensees response to a Unit 2 loss of shutdown cooling on March 5,

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60854.1 - Preoperational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants Preoperational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants

(1) The inspectors evaluated Exelons performance during NRC-observed pre-operational dry run activities that were performed in order to fulfill requirements in the Certificate of Compliance (CoC) No. 1032, Amendment 1, Condition 9. The inspectors observed dry run activities on March 16-17, 2020. Specifically, the inspectors observed or reviewed the following activities:

• Closure welding of a multipurpose canister mock-up including lid to shell, port covers, and closure ring

• Non-destructive weld evaluations including visual and penetrant testing

• Simulated radiological field surveys and radiation protection coverage of welding activities

• A recording of PCI Energy Services LLC welding personnel cutting open a welded canister mock-up, removing the port covers and lid, that was witnessed by NRC personnel

INSPECTION RESULTS

Failure to Replace Degraded Direct Current (DC) Motor Brushes on Safety-Related Motor-Operated Valve (MOV) Led to Failure to Close Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.14] - 71152 NCV 05000220/2020001-01 Conservative Closed Bias A self-revealed Green Finding and associated non-cited violation (NCV) of Title 10 of the Code of Federal Regulations (CFR) Part 50, Appendix B, Criterion XVI, Corrective Action, was identified when Exelon failed to correct a condition adverse to quality in 2017 which led to the failure of Unit 1 emergency cooling (EC) steam isolation valve IV-39-08R to close when called upon for system isolation.

Description:

Safety-related MOVs control fluid flow in plant systems and licensees rely on the operability of certain MOVs to satisfy technical specification requirements. Degraded DC motor brush-to-commutator contact can affect the ability of safety-related MOVs to perform their safety function. Specifically, inadequate contact between the brushes and commutator can result in excessively high resistance that can prevent the actuator from moving the valve (i.e., perform the safety function).

The Unit 1 emergency cooling system safety-related MOVs close, to isolate the line, in the event of a steam line break to maintain barrier integrity. In April 2017, Exelon generated IR 03993689 due to the failure of the emergency cooling system steam outlet isolation valve, IV-39-08R, to close while performing a surveillance test. Investigation of IV-39-08R determined the failure was a result of the DC motor brushes' inadequate contact with the commutator due to corrosion buildup on the brush holders, which prevented the brushes from maintaining contact as they continued to wear. The brush holders were cleaned and the existing brushes were reinstalled. In October 2019, IV-39-08R failed to close after a fault in the analog trip system resulted in a system isolation signal, which closes steam isolation valves IV-39-08R and IV-39-10R. Valve IV-39-10R successfully isolated, however IV-39-08R failed to close as required. Exelon generated IR 04292465 to document the failure. Investigation into the 2019 failure to isolate found excessive carbon dust buildup on the brush holders which restricted brush movement and limited brush contact. Excessive carbon dust buildup is indicative of uneven wear on the motor brushes. Exelon determined that the failure in 2017 had hardened the contact surface of the brushes. The existing brushes were reused after the 2017 failure and the hardened contact surface led to uneven wear and the excessive carbon dust buildup.

Corrective Actions: Exelon generated IR 04292465 in October 2019 when IV-39-08R failed to close during the isolation of emergency condenser loop 12. Corrective actions included replacing the motor brushes with new brushes and cleaning the commutator and brush holders. Other actions included performing an extent of condition review and creating work orders to replace the DC motor and brush holders on safety-related valves based on observed conditions in the next 2 years or next outage.

Corrective Action References: IRs 03993689, 04292465, 04292868, and 04301820

Performance Assessment:

Performance Deficiency: The inspectors determined that in April 2017, Exelon failed to replace defective DC motor brushes for a safety-related MOV, contrary to 10 CFR Part 50 Appendix B, Criterion XVI, Corrective Action, that was reasonably within Exelons ability to foresee and correct and therefore a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Configuration Control attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the licensees failure to replace defective DC motor brushes for IV-39-08R in emergency condenser loop 12 resulted in the valve not being able to close (safety function) in October 2019 when called upon for a system isolation.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors utilized IMC 0609, Appendix A, Exhibit 3, Barrier Integrity Screening Questions. As a result, the inspectors determined the finding was of very low safety significance (Green) because the finding did not represent an actual open pathway in the physical integrity of reactor containment (valves, airlocks, etc.), containment isolation system (logic and instrumentation),and heat removal components.

Cross-Cutting Aspect: H.14 - Conservative Bias: Individuals use decision making-practices that emphasize prudent choices over those that are simply allowable. A proposed action is determined to be safe in order to proceed, rather than unsafe in order to stop. A failure on IV 39-08R in April 2017 led to uneven brush wear and hardening of the brush contact surface in the DC motor. An inspection was done on the brushes and commutator after the failure which did not identify significant degradation, however failures such as the one in April 2017 are known to lead to degraded brush condition. The decision was made to reuse the existing brushes and in October 2019, IV-39-08R failed to close due to inadequate brush contact which was the result of reusing the degraded brushes.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Actions requires that, in part, measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.

Contrary to the above, Exelon failed to establish measures that assure conditions adverse to quality are corrected when the defective DC motor brushes on IV-39-08R, a safety-related MOV, were reused following the failure to isolate during surveillance testing in April 2017.

This resulted in emergency condenser steam isolation valve, IV-39-08R, failing to close in October 2019.

Enforcement Action: This violation is being treated as an NCV, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On April 22, 2020, the inspectors presented the integrated inspection results to Mr. Peter Orphanos, Site Vice President, and other members of the licensee staff.

• On March 14, 2020, the inspectors presented the Inservice Inspection inspection results to Mr. Michael Faivus, Senior Manager of Engineering Programs, and other members of the licensee staff.

• On March 17, 2020, the inspectors presented the Independent Spent Fuel Storage Installation inspection results to Mr. Michael Cazzolli, Senior Manager Dry Cask Storage, and other members of the licensee staff.

• On March 17, 2020, the inspectors presented the Radiation Hazards and Exposure Control inspection results to Mr. Michael Gray, Radiation Protection Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

60854.1 Miscellaneous Certificate of HI-STORM Flood/Wind (FW) Multipurpose Canister (MPC) Amendment

Compliance Storage System 1

(CoC) No. 1032

Procedures PI-CNSTR-OP- Closure Welding of Holtec Multi-Purpose Canisters-HI- Rev 4

HLTC-H-01 STORM 100, HI-STAR100, HI-STORM FW & UMAX

Systems

71111.01 Miscellaneous OP-AA-108-111- Severe Weather and Natural Disaster Guidelines 017

1001

Procedures N1-OP-64 Meteorological Monitoring 01900

N2-OP-102 Meteorological Monitoring 02500

N2-SOP-90 Natural Events 00800

71111.04 Corrective Action 03950231

Documents 04059302

288111

04325279

04325282

Drawings 019-001 Piping & Instrumentation Diagram Instrument & Service Air 01.00

Fundamental

C-18012-C Reactor Containment Spray System P&I Diagram 2

PID 104A Piping and Instruction Diagram Standby Diesel Generator 31

System

PID 104C Piping and Instruction Diagram Standby Diesel Generator 9

System

PID 104D Piping and Instruction Diagram Jacket Water Standby Diesel 7

Generator System

PID 104E Piping and Instruction Diagram Lube Oil Standby Diesel 8

Generator System

PID 104F Piping and Instruction Diagram Fuel Oil Standby Diesel 5

Generator System

PID-31A, E, and F Residual Heat Removal System Piping & Instrumentation 26, 21, & 16

Diagram

PID-38A and C Fuel Pool Cooling & Clean Up Piping & Instrumentation 16 & 15

Inspection Type Designation Description or Title Revision or

Procedure Date

Diagram

Miscellaneous NRC Information Degradation of Shutdown Cooling System Performance June 16,

Notice 93-45 1993

NRC Information Inadequate Control of Reactor Coolant System during December 8,

Notice 93-93 Shutdown 1993

NRC Information Partial Bypass of Shutdown Cooling Flow from the Reactor January 18,

Notice 96-05 Vessel 1996

Procedures N2-OP-100A Standby Diesel Generators 02800

N2-OP-19 Instrument and Service Air System 02800

71111.05 Fire Plans N2-FPI-PFP-0201 Unit 2 Pre-Fire Plans 06

Miscellaneous OP-AA-201-003 Attachment 3, Fire Drill Scenario, Unit 2 Turbine Building February 18,

Elevation 277' West Switchgear Room 2020

OP-AA-201-003 Attachment 3, Fire Drill Scenario, Unit 1 Turbine Building February 19,

Elevation 261' PB 152C 2020

Procedures N2-FPI-PFP-0201 Unit 2 Pre-Fire Plans 06

OP-AA-201-003 Fire Drill Performance 17

TQ-AA-224-F020 Course Attendance Sheet 05

71111.07A Miscellaneous 2RHS*E1A Heat Exchanger Inspection Report March 16,

20

Procedures ER-AA-340 GL [Generic Letter] 89-13 Program Implementing Procedure 9

ER-AA-340-1002 Service Water Heat Exchanger Inspection Guide 9

Work Orders C93672353

71111.08G Corrective Action 4326616

Documents

Resulting from

Inspection

71111.11Q Procedures N1-OP-10 Reactor Building Heating, Cooling, and Ventilation System 03000

N1-PM-Q7 Quarterly Main Turbine Testing and Generator Core Monitor 00500

Testing

71111.12 Corrective Action 04061009

Documents 04068720

04085429

04085431

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous Maintenance Rule 18-10 - Periodic (a)(3) Assessment 00

Procedures ER-AA-320 Maintenance Rule Implementation Per NEI 18-10 00

Work Orders C93283487

71111.13 Corrective Action 04313524

Documents

Corrective Action 04310225

Documents

Resulting from

Inspection

Miscellaneous ECP-18-000086, PV Water Inventory Control (RPV WIC) Implementation at 01

TSTF 542 Nine Mile Point Unit 2

N2-FHP-003 Refueling Manual 02000

Procedures N1-OP-31 Tandem Compound Reheat Turbine 05200

N2-OSP-LOG- Daily Checks Log 02500

D001

N2-PM-082 RPV [Reactor Pressure Vessel] Flood Up/Draindown 015T1

N2-PM-082 RPV Flood Up / Draindown 01600

OP-AA-107 Integrated Risk Management 002

OP-AA-107 Integrated Risk Management 002

OP-NM-108-117 Protected Equipment Program at Nine Mile Point 0500

OU-NM-103-101 Shutdown Safety Management Program 00500

WC-AA-101 On-Line Work Control Process 029

71111.15 Corrective Action 02011075

Documents 02017465

291360

299129

299670

04301070

04301071

04305757

04306009

04320370

04324166

Inspection Type Designation Description or Title Revision or

Procedure Date

04328823

Drawings PID-31A Piping and Instrumentation Diagram Residual Heat Removal 26

System

Miscellaneous 125VDCDISTSYS 125VDC Distribution System Analysis 0

Procedures N1-OP-47A 125 VDC Power System 03200

N2-ISP-GTS- Standby Gas Treatment System Pneumatic 00600

R@001 Supply/Accumulator Leak Rate Test

N2-OP-29 Reactor Recirculation System 03000

N2-OP-31 LINEUPS, Residual Heat Removal System - Lineups 00300

N2-OP-61B Standby Gas Treatment System 01700

N2-OSP-RCS- Recirc Flow Control Valve Operability Test 00600

R004

N2-SOP-08 Unplanned Power Changes 013T1

OP-AA-108-115 Operability Determination 022

Work Orders C93479858

C93614049

71111.18 Corrective Action 04148579

Documents 04318072

04327204

04328107

Drawings 20014193 26" MSIV Cover and Internals Rockwell Mod Nine Mile 10

Point, Unit 2

Engineering 18-000373 Emergency Diesel Generator Governor Replacement 1

Changes ECP-18-000691 Remove Unit 2 Reactor Recirculation Pump Auto Trip Low 0

Speed Transfer on Differential Temperature

ECP-19-000301 NMP #2 MSIV Internals Upgrade 0

Procedures 8003015-P1 Governor Modification Installation Procedure 0

LS-AA-104 Exelon 50.59 Review Process 011

LS-AA-104-1004 50.59 Evaluation Form 007

Work Orders C93673566

C93691143

C93696744

71111.19 Corrective Action 04318729

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 04320006

04324847

04325930

Procedures ER-AA-321 Administrative Requirements for Inservice Testing 013

MA-AA-716-004 Conduct of Troubleshooting 17

N1-MPM-210-552 Control Room Ventilation System 00800

N2-IMP-NMS- IRM/SRM Detector/Cable Connector Maintenance and Completed

R008 Testing on March 8,

20

N2-IPM-NMS- Source Range Monitor (SRM) Discriminator Curve Testing Completed

@002 on March 8,

20

N2-ISP-NMS- Source Range Monitor Channel Calibration Completed

Q@108 on March 8,

20

N2-ISP-NMS- Source Range Monitor and Rod Block Trip Channel Completed

W@008 Functional Test on March 9,

20

Work Orders C93664635

C93675612

C93687770

C93691963

71111.22 Procedures ER-AA-321 Administrative Requirements for Inservice Testing 013

N1-ST-Q8A Liquid Poison 11 Pump and Check Valve Operability Test 1500

N2-OSP-CNT-008 Local Leak Rate Testing of Drywell to Suppression Chamber 00000

Vacuum Breaker

N2-OSP-EGS- Diesel Generator and Diesel Air Start Valve Operability Test 02200

M@001 - Division I and II

N2-OSP-EGS- Operating Cycle Diesel Generator Simulated Loss of Offsite 00900

R007 Power Division III

N2-OSP-MSS- Main Steam Isolation Valve Leak Rate Test (Inboard Static 00100

003 Head of Water)

N2-OSP-RMC- Mode Switch Shutdown Position Rod Block Channel 00400

R001 Functional Test

Inspection Type Designation Description or Title Revision or

Procedure Date

N2-OSP-SLS- Standby Liquid Control Manual Initiate Actuation and ASME 00800

R001 XI Pressure Test

WC-AA-111 Surveillance Program Requirements 7

Work Orders C93672632

C93672682

71124.01 Corrective Action 034100009

Documents 04271600

2720052

274185

274187

284643

290635

04304586

043100014

Procedures NISP-RP-004 Posting and Labeling Revision 1

NISP-RP-005 Locked High Radiation Area (LHRA) Key Control Revision 1

NISP-RP-007 Control of Radioactive Material (RAM) Revision 1

RP-AA-376-1001 Radiological Posting, Labeling, and Marking Standard Revision 16

RP-AA-400-001 Very High Radiation Area (VHRA) Controls Revision 6

RP-AA-460 Locked High Radiation Area (LHRA) Key Control Revision 37

RP-AA-503-F-01 Unconditional Release Instructions using the Small Articles Revision 4

Monitor (SAM)

Radiation NMP-2-20-00502 Drywell 261' General Area Air Sample 3/9/2020 @

Surveys 0330

NMP-2-20-00502 Drywell 261' General Area Air Sample 3/9/2020 @

1815

NMP-2-20-00502 Drywell 261' General Area Air Sample 3/10/2020 @

25

NMP-2-20-00502 Drywell 261' South General Area Air 3/9/2020 @

Sample 0345

20-066071 Drywell Under Vessel 3/6/2020 @

1000

20-066177 Drywell 261' General Area Air Sample RWP 503 3/8/2020 @

Inspection Type Designation Description or Title Revision or

Procedure Date

0815

20-067186 Reactor Building 353' Refuel Floor 3/15/2020 @

0717

20-067495 Unit 2 Drywell Under Vessel 3/17/2020 @

2037

20-067550 Reactor Building 353' Refuel Floor 3/18/2020 @

1500

Radiation Work NM-2-20-00506 Drywell Scaffolding Activities 1/1/2020

Permits (RWPs) NM-2-20-00513 Drywell Control Rod Drive (CRD) Exchange 1/1/2020

NM-2-20-00518 Drywell In Service Inspections (ISI) Activities 1/1/2020

NM-2-20-00901 Reactor Disassembly/Reassembly Activities 1/1/2020

NM-2-20-00902 Refuel Floor Support Activities 1/1/2020

NM-2-20-00903 Reactor Cavity Work Platform 1/1/2020

71151 Corrective Action 04233592

Documents 04239884

290993

293947

Miscellaneous NEI 99-02 Regulatory Assessment Performance Indicator Guideline 7

71153 Corrective Action 04323670

Documents 04324166

04324195

04325119

04325198

Drawings PID-23B Turbine Hydraulic Oil System 10

Procedures N2-OP-31 Residual Heat Removal System 03600

N2-SOP-101C Reactor Scram 01400

N2-SOP-101D Rapid Power Reduction 01100

N2-SOP-31 Loss of Shutdown Cooling 00601

19