IR 05000220/2020004
ML21041A342 | |
Person / Time | |
---|---|
Site: | Nine Mile Point ![]() |
Issue date: | 02/11/2021 |
From: | Ed Miller Reactor Projects Branch 1 |
To: | Rhoades D Exelon Generation Co, Exelon Nuclear |
References | |
IR 2020004 | |
Download: ML21041A342 (21) | |
Text
February 11, 2021
SUBJECT:
NINE MILE POINT NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000220/2020004 AND 05000410/2020004 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07201036/2020002
Dear Mr. Rhoades:
On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station. On January 26, 2021, the NRC inspectors discussed the results of this inspection with Mr. Pete Orphanos, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, X /RA/
Signed by: Eric D. Miller
Eric D. Miller, Acting Chief Projects Branch 1 Division of Reactor Projects
Docket Nos. 05000220, 05000410 and 07201036 License Nos. DPR-63 and NPF-69
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000220, 05000410 and 07201036
License Numbers:
Report Numbers:
05000220/2020004 and 05000410/2020004
07201036/2020002
Enterprise Identifier: I-2020-004-0020
I-2020-002-0013
Licensee:
Exelon Nuclear
Facility:
Nine Mile Point Nuclear Station
Location:
Oswego, NY
Inspection Dates:
October 1, 2020 to December 31, 2020
Inspectors:
G. Stock, Senior Resident Inspector
J. Dolecki, Resident Inspector
B. Sienel, Resident Inspector
T. Fish, Senior Operations Engineer
T. Hedigan, Operations Engineer
C. Lally, Acting Branch Chief
J. Nicholson, Senior Health Physicist
P. Ott, Operations Engineer
S. Wilson, Senior Health Physicist
Approved By:
Eric D. Miller, Acting Chief
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.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000410/2020-002-00 LER 2020-002-00 for Nine Mile Point Nuclear Station,
Unit 2, Failure to Meet Technical Specification MSIV Stroke Times 71153 Closed LER 05000410/2020-002-01 LER 2020-002-01 for Nine Mile Point Nuclear Station,
Unit 2, Failure to Meet Technical Specification MSIV Stroke Times 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On October 9, 2020, the unit was downpowered to approximately 70 percent to perform a control rod pattern adjustment. The unit was returned to rated thermal power on October 10, 2020. On November 29, 2020, the unit was downpowered to approximately 72 percent to perform a control rod pattern adjustment and remove the 15 recirculation motor generator set from service for maintenance. The unit was returned to rated thermal power on November 30, 2020. On December 18, 2020, the unit was downpowered to approximately 70 percent to perform a control rod pattern adjustment and restore the 15 recirculation motor generator set to service. The unit was returned to rated thermal power on December 19, 2020 and remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power. On October 23, 2020, the unit was downpowered to approximately 75 percent to perform a control rod pattern adjustment and control rod scram timing. The unit was returned to rated thermal power on October 24, 2020 and 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 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 and during that time conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. 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 some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures on December 18, 2020.
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather associated with high winds on November 2, 2020.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 'B' residual heat removal system on October 13, 2020
- (2) Unit 2 low pressure core spray system on October 20, 2020
- (3) Unit 2 Division I emergency diesel generator on October 29-30, 2020
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 emergency diesel generators on November 18, 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 1 screenhouse, fire area 13, on November 2, 2020
- (2) Unit 1 turbine building 261', diesel generator 103 room, fire area 19, on November 12, 2020
- (3) Unit 1 turbine building 261', diesel generator 102 room, fire area 22, on November 12, 2020
- (4) Unit 1 turbine building 250', cable spreading room, fire area 10, on November 23, 2020
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 1 torus room
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (2 Samples)
- (1) The inspectors reviewed and evaluated the Unit 1 licensed operator annual requalification results for the annual operating exam administered October - November 2020.
- (2) The inspectors reviewed and evaluated the Unit 2 licensed operator annual requalification results for the annual operating exam on November 24, 2020.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations
The inspectors evaluated the quality of the Unit 1 licensed operator biennial requalification written examinations administered October - November 2020.
Annual Requalification Operating Tests
The inspectors evaluated the adequacy of Exelon's annual requalification operating test.
Administration of an Annual Requalification Operating Test
The inspectors evaluated the effectiveness of Exelon in administering requalification operating tests required by Title10 of the Code of Federal Regulations (10 CFR)55.59(a)(2) to ensure that Exelon is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security
The inspectors evaluated the ability of Exelon to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations
The inspectors evaluated the effectiveness of remedial training conducted by Exelon, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions
The inspectors evaluated Exelon's program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator
The inspectors evaluated the adequacy of Exelon's control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution
The inspectors evaluated Exelon's ability to identify and resolve problems associated with licensed operator performance.
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 Unit 1 operations personnel during a planned downpower to 75 percent for a control rod sequence exchange on October 9, 2020.
- (2) The inspectors observed Unit 2 operations personnel during a planned downpower to 75 percent for a control rod sequence exchange and scram time testing on October 23, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed Unit 1 simulator annual requalification examination scenarios that included an unplanned main steam isolation valve closure, a steam leak in the drywell, an emergency condenser tube leak, and a failure to scram, on November 3, 2020.
- (2) The inspectors observed Unit 2 simulator annual requalification operating test scenarios, including
- (1) a scenario involving trip of a spent fuel pool cooling pump, trip of an air compressor, steam leak in the reactor core isolation cooling room with a failure to auto isolate, a trip of the electro-hydraulic control pumps, a manual reactor scram, and a steam leak in containment leading to the operators performing a reactor pressure vessel blowdown using safety relief valves; and
- (2) a scenario involving a loss of one line of 115-kilovolt off-site power, a trip of an control rod drive pump, degraded main condenser vacuum, an unisolable steam leak in the reactor core isolation cooling room, a manual reactor scram, and operators performing a reactor pressure vessel blowdown using safety relief valves on November 3, 2020.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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) Unit 1 core spray system
- (2) Unit 1 intermediate range monitors
- (3) Unit 2 instrument air system
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 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 2 elevated risk during planned Division I residual heat removal system preventive maintenance on October 13, 2020
- (2) Unit 2 elevated risk during planned high pressure core spray system maintenance on October 20, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1 high pressure coolant injection due to slow opening stroke times of flow control valves, FCV-29-141 and FCV-29-137, on October 16, 2020
- (2) Unit 1 scram discharge volume due to high volume level reading during surveillance testing on October 16, 2020
- (3) Unit 2 Division III diesel generator following unexpected isolation of service water inlet valve, 2SWP*MOV95B, on October 27, 2020
- (4) Unit 2 Division III diesel generator service water inlet check valve, 2SWP*V260, following unsatisfactory reverse flow exercise test on October 29, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 2 Division I residual heat removal pump following motor preventive maintenance on October 13, 2020
- (2) Unit 1 high pressure coolant injection 11 following maintenance on October 15, 2020
- (3) Unit 2 Division II emergency diesel generator following 2-year preventive maintenance on October 30,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how Exelon identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials, and how Exelon assesses radiological hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) The inspectors observed radiation protection technicians survey potentially contaminated material leaving the radiation control area.
- (2) The inspectors observed workers exiting the radiation control area at Unit 1 and Unit 2 control points.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors observed radiation workers conducting repair of contaminated parts in the hot machine shop and decontamination area.
- (2) The inspectors observed pre-job meetings and radiation protection technicians performing locked high radiation area controls for personnel entries into the Unit 1 condenser bay.
- (3) The inspectors observed pre-job meetings and radiation protection technicians performing locked high radiation area controls for personnel entries into the Unit 1 steam isolation valve room.
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements. Observations included radiation protection technician-controlled entries into the Unit 1 steam isolation valve room (posted locked high radiation area); a radiation protection technician surveying a solid waste high integrity container in a high radiation area; and a radiation worker performance during repair of contaminated equipment in the hot machine shop.
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (9 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) ThermoFisher-Scientific Model AMS-4 continuous air monitor at Unit 1 Turbine Building 300' Reheater area (SN1748/1745)
- (2) ThermoFisher-Scientific Model AMS-4 continuous air monitor at Unit 2 Reactor Building 353' elevation (SN1745/1746-9)
- (3) Portable ion chambers stored ready for use at Unit 2 control point access Eberline RO2A SN2995
- (4) Eberline RO2A SN6443-05
- (5) Eberline RO2A SN3007
- (6) Eberline RO20 SN 078042
- (7) Eberline RO2 SN6054
- (8) Portable Geiger-Müller tube instruments at Unit 2 control point access Merlin Gerin Telepole SN079827
- (9) Merlin Gerin Telepole SN025992
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Eberline RO2A, SN3007
- (2) Eberline RO2A, SN6443-05
- (3) Eberline RO2A, SN2995
- (4) Eberline RO20 SN4428
- (5) Ludlum Model 3, SN12093
- (6) Merlin Gerin Telepole SN6610-057
- (7) Merlin Gerin Telepole SN079827
- (8) Eberline SAC 4, SN1037 (2019)
- (9) Bicron BC4, SN745
- (10) RadEye, SN0022641
- (11) Canberra 5AB, SN1012-317, at Unit 2 RCA exit
- (12) ThermoFisher Small Article Monitor 11, SN544
- (13) Eberline SAC 4, SN1037 (2020)
Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 1 Stack Gas Process Radiation Monitor RAM RN10A Channel Calibration records dated June 21, 2017
- (2) Unit 1 Stack Gas Process Radiation Monitor RAM RN10A Channel Calibration records dated March 24,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) Unit 1 October 1, 2019 through September 30, 2020
- (2) Unit 2 October 1, 2019 through September 30, 2020
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 October 1, 2019 through September 30, 2020
- (2) Unit 2 October 1, 2019 through September 30, 2020
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 October 1, 2019 through September 30, 2020
- (2) Unit 2 October 1, 2019 through September 30, 2020
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) Units 1 and 2, July 1, 2019 through September 30, 2020
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed Exelons corrective action program for trends that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) IRs 03993689 and 04292465 - Review of Corrective Actions for Direct-Current Motor-Operated Valve Copper-Clad Steel Brush Holders
71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000410/2020-002-00 & -01, Failure to Meet Technical Specification MSIV
[Main Steam Isolation Valve] Stroke Times, ADAMS Accession Nos. ML20129J906 and ML20255A078. The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. The inspectors reviewed the original and updated LER submittals. These LERs are closed.
Personnel Performance (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensee's response to a Unit 2 unplanned power change following the 'A' reactor recirculation flow control valve drifting open on December 10,
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 Exelon's 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 3. The inspectors observed dry run activities on August 3-5, 2020. Specifically, the inspectors observed or reviewed the following activities:
- Hydrostatic testing of the closure weld
- Blowdown and vacuum drying of the canister
- Simulated radiological field surveys and radiation protection coverage of canister processing activities
- Helium backfilling of the canister
92709 - Licensee Strike Contingency Plans Licensee Strike Contingency Plans
- (1) On October 30, 2020, the contract between Exelon and IBEW Local 97 was set to expire. In preparation for a potential strike, the NRC inspectors evaluated the adequacy of Exelon's contingency plan. The inspectors assessed the adequacy of the plan's post-strike staffing levels, staff qualifications, safety conscious working environment, and site access in meeting operational and security requirements. The contract was ratified October 20,
INSPECTION RESULTS
Observation: Review of Corrective Actions on Direct Current Motor-Operated Valve Copper-Clad Steel Brush Holders 71152 The inspectors reviewed Exelons evaluation and corrective actions following the identification of an issue with the copper-clad steel brush holders in the motors of direct current (DC)motor-operated valves (MOVs). In April 2017, a safety-related isolation MOV in the Unit 1 emergency condenser system, IV-39-08R, failed in mid-position during a surveillance test. Exelon generated issue report (IR) 03993689 to document the failure. The station conducted a causal evaluation and concluded that corrosion buildup from the DC MOV steel brush holder led to inadequate electrical contact between the brushes and commutator.
Corrosion from the brush holders can prevent the brushes from sliding freely to maintain contact with the commutator. Issue Report 03993689 stated that a new DC motor was installed in April 2015 and the brush holder had corroded in only two years of normal service life. Exelon identified a list of safety-related MOVs susceptible to the same condition.
Additionally, in October 2019, DC MOV IV-39-08R failed in its mid-position due to a different issue. Exelon generated IR 04292465 to address the issue and included corrective actions to address the deficient copper-clad steel brush holders.
As actions within IR 04282465, Exelon generated a list of 17 DC MOVs and associated work orders to inspect the brush holders using S-EPM-GEN-067, Limitorque MOV Actuator P.M.,
Revision 01100, within two years or next outage (Unit 2 refueling outage in 2022 was the latest date, due to replacement part lead time). As stated in the IR, brass brush holders and spare DC motors shall be available to replace the current steel brush holders and motors (as a contingency). In accordance with S-EPM-GEN-067, if operators identify signs of cracking, pitting, or corrosion in the brush holder area, the brush holders or motor is to be replaced with solid brass brush holders.
The inspectors reviewed Exelons corrective actions at Unit 1 and Unit 2 associated with deficient steel brush holders contained within IRs 03993689 and 04292465. The inspectors reviewed the extent of condition list of DC MOVs to ensure all potentially affected MOVs had been identified, and reviewed the status of Exelons actions, including a review of work order status. The inspectors also reviewed Exelons readiness with replacement parts, or the ability to procure them, if they are needed.
As a result of the inspectors' review, Exelon generated IR 04388354 to document improvements that can be made to scheduling work activities and to revise the Unit 1 refuel outage work schedule.
Observation: Semi-Annual Trend Review 71152 The inspectors identified a trend associated with degraded conditions which have existed for a long period of time and impact plant operations. Following the identification of the individual issues, Exelon generated IRs in their corrective actions program to address the issues and define corrective actions. However, the inspectors identified that multiple issues that require additional actions by operators have existed for an extended period of time due to delayed corrective actions.
Specifically, the inspectors identified outstanding issues on a number of systems, the most significant of which are the Unit 1 mechanical hydraulic control (MHC) system identified in IRs 02485219 and 04244521; the Unit 1 fire protection system identified in IRs 04347881 and 04385984; and the Unit 2 service water system identified in IRs 02535772 and 04277608.
The issue on the MHC system is discussed in the Inspection Results Section of Inspection Report 05000220/2019010 and 05000410/2019010. The issue on the fire protection system was reviewed during this inspection period, as documented in section 71111.15. The issue on the service water system is discussed in the Inspection Results Section of Inspection Report 05000220/2020003 and 05000410/2020003.
In each of the above referenced issues, additional actions are/were required by operators to operate the plant or respond to events. The corrective actions for these conditions have been extended for various reasons. Specifically, the Unit 1 MHC system issue (power instability region due to inadequate lead-lag testing) was initially scheduled with a due date of November 8, 2019 and is now delayed to the Spring 2021 refueling outage. The Unit 2 service water issue (valve 2SWP*MOV21B failed in mid-position) has existed since September 9, 2020 and has been extended to the Spring 2022 refueling outage. The Unit 1 local fire panel issues (e.g. fire damper failed to open, leading to trouble alarms on a local fire panel) have existed since at least May 28, 2020.
As a result of these outstanding degraded conditions, Unit 1 has an Operator Burden to address pressure oscillations due to the MHC issue, Unit 1 has had nuisance alarms affecting operators ability to interface with the local fire panels due to the fire protection system issues, and Unit 2 has revised an Abnormal Operating Procedure to include opening an additional valve due to the service water valve issue.
The examples above demonstrate a trend. The inspectors determined the trend is not an additional performance deficiency.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 26, 2021, the inspectors presented the integrated inspection results to Mr. Pete Orphanos, Site Vice President, and other members of the licensee staff.
- On December 16, 2020, the inspectors presented the independent spent fuel storage installation inspection results to Mr. Joseph Dougherty, Senior Program Manager, Dry Cask Storage, and other members of the licensee staff.
- On December 17, 2020, the inspectors presented the radiation protection inspection results to Mr. Michael Gray, Radiation Protection Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60854.1
Miscellaneous
Certificate of
Compliance
(CoC) No. 1032
HI-STORM Flood/Wind (FW) Multipurpose Canister (MPC)
Storage System
Amendment
RRTI No. 2847-
006-R2
Response to Request for Technical Information, Holtec
International, Holtec Project No.2847
November
24, 2020
Procedures
HPP-2847-300
MPC Sealing, Drying, and Backfilling
Work Orders
WO C93736388
ISFSI Campaign Dry Run Phases 1 and 2 Cask Sealing,
Drying, and Backfilling
Procedures
N1-OP-64
Meteorological Monitoring
01900
N1-OP-64
Meteorological Monitoring
2000
N1-SOP-64
00300
N2-OP-102
Meteorological Monitoring
2700
N2-OP-102
Meteorological Monitoring
2500
N2-SOP-90
Natural Events
01000
N2-SOP-90
Natural Events
00800
Seasonal Readiness
Corrective Action
Documents
04380768
04380799
Drawings
C-18026-C Sheet
Emergency Diesel Generator 102 Starting Air, Cooling Water,
Lube Oil and Fuel P&I Diagram
C-18026-C Sheet
Emergency Diesel Generator 103 Starting Air, Cooling Water,
Lube Oil and Fuel P&I Diagram
Procedures
N1-OP-45
04900
N2-OP-31-
LINEUPS
Residual Heat Removal System - Lineups
00300
N2-OP-32
Low Pressure Core Spray
200
N2-OP-32-
LINEUPS
Low Pressure Core Spray - LINEUPS
Fire Plans
N1-PFP-0101
Pre-Fire Plans
00500
N1-PFP-0101
Pre-Fire Plans
00600
Corrective Action
CR-2011-003058
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
CR-2012-007568
Drawings
C-18012-C
Reactor Containment Spray System P&I Diagram
C-22300-C
Interconnection Diagram 600 Volt Powerboard
Miscellaneous
Containment System Design Basis Document
71111.11Q Miscellaneous
Reactivity
Maneuver Plan
NM2C18-3-1
NMP2 October 2020 Load Drop
Procedures
N2-OSP-RMC-
@001
Control Rod Drive Scram Insertion Time Testing
2600
Reactivity
Maneuver Plan
NM1C24-7
NMP1 October 2020 Load Drop
Corrective Action
Documents
2011075
2017465
2612418
04060921
04143434
250466
262272
264399
265111
276737
282912
284118
291484
299670
04319061
04351428
04355901
04356128
04365602
04368972
04387314
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
04390645
Miscellaneous
Maintenance Rule
a(1) Action Plan for Unit 1 IRM 15
August 16,
2019
Maintenance Rule
System Basis
Document
Neutron Monitoring, Unit 1
Procedures
Maintenance Rule Functions - Safety Significance
Classifications
Exelon Maintenance Rule Process Map
Maintenance Rule Implementation Per NEI 18-10
Maintenance Rule 18-10 - Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
N1-OP-2
Core Spray System
03900
N1-OP-38B
200
N2-MPM-IAS-
V606
Instrument Air Compressor
- P.M. 2IAS-C3A, 2IAS-C3B and
01700
N2-OP-19
Instrument and Service Air System
2800
Work Orders
C93614049
C93671046
C93681838
C93702322
C93714256
C93715345
C93727465
Procedures
OP-NM-108-117
Protected Equipment Program at Nine Mile Point
006
On-Line Work Control Process
030
Corrective Action
Documents
04001797
04178959
04184175
04197695
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04199197
04372692
04377059
04377164
04378182
04379990
04385984
Procedures
N1-IPM-029-010
Calibration of Feedwater FCV-29-134, FCV-29-137, and FCV-
29-141
01300
N1-IPM-029-010
Calibration of Feedwater FCV-29-134, FCV-29-137, and FCV-
29-141
013T1
N1-ISP-044-005
High Water Level Scram Discharge Volume Instrument
Channel Functional Calibration
00700
N2-OSP-SWP-
Q005
Division 3 Service Water Operability Test
00400
Work Orders
C93028113
C93625581
C93682976
C93684062
C93694459
C93711827
C93769658
Corrective Action
Documents
04376757
Procedures
N1-ST-Q3
High Pressure Coolant Injection Pump and Check Valve
Operability Test
01900
N2-PM-@026
Diesel Generator Start Following Maintenance - Division I and
II
00400
S-EPM-GEN-081
Site 13.8 & 16KV Motor inspection P.M.
200
S-EPM-GEN-
V080
Site AC Motor Predictive Maintenance Testing
01000
Work Orders
C93648661
C93685011
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
C93722157
C93723883
71151
Miscellaneous
Regulatory Assessment Performance Indicator Guideline
Corrective Action
Documents
2485219
2535772
03993689
244521
277608
292465
04301820
04347881
04385984
Miscellaneous
Regulatory Issue
Summary 2001-
015
Performance of DC-Powered Motor-Operated Valve Actuators
August 1,
2001
Procedures
Motor-Operated Valve Program Engineering Procedure
S-EPM-GEN-063
MOV Diagnostic Testing
200
S-EPM-GEN-067
Limitorque MOV Actuator P.M.
01100
S-EPM-GEN-067
Limitorque MOV Actuator P.M.
00900
Work Orders
C90647604
C92393291
C93617215
C93736601
C93736602
C93736603
C93736604
C93736605
C93736606
C93736607
C93736608
C93736609
C93736610
C93736611
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
C93736612
C93736613
C93736614
C93736615
C93736616
C93736617
Corrective Action
Documents
04127385
04324557
04324692
04388983
Procedures
N2-IPM-SOV-
R003
Replacement of Main Steam Solenoid Operated Valves
00500
N2-OSP-MSS-
CS001
Main Steam Isolation Valve Operability Test
00800
N2-SOP-8
Unplanned Power Change
01500