IR 05000220/2021003
ML21309A651 | |
Person / Time | |
---|---|
Site: | Nine Mile Point ![]() |
Issue date: | 11/09/2021 |
From: | Erin Carfang NRC/RGN-I/DORS |
To: | Rhoades D Exelon Generation Co LLC, Exelon Nuclear |
References | |
IR 2021001, IR 2021003 | |
Download: ML21309A651 (21) | |
Text
November 9, 2021
SUBJECT:
NINE MILE POINT NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000220/2021003 AND 05000410/2021003 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07201036/2021001
Dear Mr. Rhoades:
On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station. On November 5, 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, Erin E. Carfang, Chief Projects Branch 1 Division of Operating Reactor Safety 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:
05000220/2021003, 05000410/2021003 and 07201036/2021001
Enterprise Identifier: I-2021-003-0037
I-2021-001-0059
Licensee:
Exelon Nuclear
Facility:
Nine Mile Point Nuclear Station
Location:
Oswego, NY
Inspection Dates:
July 01, 2021 to September 30, 2021
Inspectors:
G. Stock, Senior Resident Inspector
J. Dolecki, Senior Resident Inspector
C. Kline, Resident Inspector
B. Sienel, Resident Inspector
E. Andrews, Health Physicist
M. Henrion, Health Physicist
O. Masnyk Bailey, Health Physicist
B. Pinson, Reactor Inspector
S. Veunephachan, Health Physicist
S. Wilson, Senior Health Physicist
Approved By:
Erin E. Carfang, Chief
Projects Branch 1
Division of Operating Reactor Safety
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
None.
PLANT STATUS
Unit 1 operated at or near rated thermal power throughout the inspection period.
Unit 2 operated at or near rated thermal power throughout 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 and regional 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, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; conducted routine reviews using IP 71152, Problem Identification and Resolution; 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 a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - 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 hot temperatures for the following systems:
- Unit 1 11 and 12 125-volt (V) batteries on August 18, 2021
- Unit 2 115-kilovolt (kV) electrical distribution system on August 18, 2021
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 Division II emergency diesel generator on July 12, 2021
- (2) Unit 2 Division I emergency diesel generator on August 2, 2021
- (3) Unit 1 11 high pressure coolant injection function of feedwater system on August 3, 2021
- (4) Unit 2 'A' residual heat removal system on September 2, 2021
Complete Walkdown Sample (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 containment spray system on September 13, 2021.
- (2) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 reactor core isolation cooling system on September 30, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 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 reactor building 175, fire areas 34 and 35, on September 10, 2021
- (2) Unit 2 normal switchgear building 237', fire areas 51 and 52, on September 10, 2021
- (3) Unit 1 power board 102 room 261', fire area 23, on September 13, 2021
- (4) Unit 1 reactor building east 237', fire area 1, on September 13, 2021
- (5) Unit 1 screenhouse, fire area 13, on September 15, 2021
- (6) Unit 2 Division II emergency switchgear room, fire area 19, on September 20, 2021
- (7) Unit 2 Division III emergency switchgear room, fire area 21, on September 20, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (3 Samples)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 1 turbine building elevation 250', emergency diesel generator and powerboard rooms, on August 20, 2021
- (2) Unit 2 reactor building elevation 175' on September 9, 2021
- (3) Unit 1 turbine building condensate pump room on September 10, 2021
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 2 service water bay 'A' unit cooler 2HVY*UC2C on July 22, 2021
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 2 operations personnel response following a fault on 120V alternating current (AC) distribution panel 2SCI-PNLB101 on July 29, 2021, and scavenging steam restoration activities at 98 percent power on August 2, 2021.
- (2) The inspectors observed Unit 1 operations personnel respond to a loss of reactor protection system 11 and restoration on September 25, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed a Unit 2 simulator evaluation that included a single rod scram, the loss of an electrical bus, reactor fuel failure, and an unisolable loss of coolant into secondary containment on August 5, 2021.
- (2) The inspectors observed a Unit 1 simulator evaluation that included a tornado, loss of offsite power, large break loss of coolant accident, and an unisolable emergency condenser steam leak on August 17, 2021.
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) Unit 2 Divisions I and II emergency diesel generators on July 8, 2021
- (2) Unit 1 containment spray to core spray cross-tie check valve, CHK-93-58, on September 30, 2021
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) The commercial grade dedication of movable contacts installed in a Unit 1 safety related 600V feeder breaker on September 20, 2021
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (7 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 emergent work on Division II emergency diesel generator, 2EGS*EG3, following unplanned inoperability due to a degraded start time, on July 7, 2021
- (2) Unit 2 elevated risk during planned Division II emergency diesel generator air start valve replacements on August 2, 2021
- (3) Unit 1 elevated risk during planned 12 feedwater pump seal replacement on August 3, 2021
- (4) Unit 1 elevated risk during planned emergency diesel generator 103 maintenance on September 13, 2021
- (5) Unit 2 elevated risk during planned Division I emergency diesel generator maintenance on September 20, 2021
- (6) Unit 2 elevated risk during planned Division I residual heat removal pressure maintenance pump maintenance on September 22, 2021
- (7) Unit 1 elevated risk during planned emergency diesel generator 102 maintenance on September 30, 2021
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 1 121 containment spray raw water due to reverse flow testing failure of check valve 93-62 on July 1, 2021
- (2) Unit 1 hardened containment vent system after several battery cell resistance readings exceeded criteria on July 7, 2021
- (3) Unit 2 Division I emergency diesel generator due to degraded start time to reach rated output voltage on July 21, 2021
- (4) Unit 2 Division I emergency diesel generator exhaust damper, 2HVP*MOD1C, due to failure to open on August 25, 2021
- (5) Unit 2 control rods 02-43 and 18-59 following identification of elevated friction results during testing on September 20, 2021
- (6) Unit 1 control room emergency ventilation system failure to actuate on loss of reactor protection system 11 on September 25, 2021
- (7) Unit 2 Division III diesel generator due to an air leak on air start compressor, 2EGA-C4, on September 27, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Permanent Modification: Field Change Notice G9MI2-40506, Unit 2 Digital Electro-hydraulic Control Filtration Activation
Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)
- (1) Units 1 and 2 Revision to Severe Accident Management Guidelines
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (9 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 1 111 containment spray raw water pump discharge check valve inspection on July 1, 2021
- (2) Unit 2 Division II emergency diesel generator following unplanned inoperability and corrective maintenance on July 7, 2021
- (3) FLEX pump vacuum test following annual maintenance on July 20, 2021
- (4) Unit 2 Division II emergency diesel generator air start pressure control valve replacements on August 4, 2021
- (5) Unit 1 12 high pressure coolant injection pump inboard seal replacement on August 5, 2021
- (6) Unit 2 'A' instrument air compressor 3-year preventive maintenance on August 23, 2021
- (7) Unit 2 'C' residual heat removal pump motor inspection and testing on September 2, 2021
- (8) Unit 1 emergency diesel generator 103 following 6-year preventive maintenance on September 17, 2021
- (9) Unit 1 emergency diesel generator 103 cooling water following check valve preventive maintenance on September 17, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) N2-OSP-SLS-Q001, Standby Liquid Control Pump, Check Valve, Relief Valve Operability Test and ASME XI Pressure Test, on August 17, 2021
- (2) N2-OSP-RDS-@002, Channel Interference Testing, on September 18, 2021
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) S-PM-003, FLEX 450 kilowatt (kW) Portable Diesel Generator Test, on August 31, 2021
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) A Unit 2 simulator evaluation which included nuclear fuel failure, a loss of coolant accident, and the declaration of a Site Area Emergency and General Emergency on August 3,
RADIATION SAFETY
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (2 Samples)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Unit 2 standby gas treatment system
- (2) Unit 1 reactor building emergency ventilation system
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
- (1) No temporary ventilation systems were in use at the time of this inspection.
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose.
Internal Dosimetry (IP Section 03.03) (2 Samples)
The inspectors evaluated the internal dosimetry program implementation.
- (1) Dose assessment through in-vivo bioassay monitoring of a worker who alarmed contamination monitors after working in Unit 2 drywell during N2R17.
- (2) Dose assessment of two workers who received facial contamination after performing welding work for residual heat removal valving in the drywell.
Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situation:
- (1) Licensees implementation of requirements to manage radiation protection of three declared pregnant workers.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 - July 1, 2020 through June 30, 2021
- (2) Unit 2 - July 1, 2020 through June 30, 2021
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 - July 1, 2020 through June 30, 2021
- (2) Unit 2 - July 1, 2020 through June 30, 2021
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 - July 1, 2020 through June 30, 2021
- (2) Unit 2 - July 1, 2020 through June 30, 2021
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) April 1, 2020 through June 30, 2021
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) October 1, 2020 through June 30, 2021
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) Issue Reports (IRs) 04305757 and 04388983 - Review of Issue Evaluations and Corrective Actions for Reactor Recirculation Hydraulic Power Unit Issues
- (2) IR 4355747 - Radiation Protection Training Records Not Complete, Accurate, Authenticated, or Retrievable and No Formal Investigation Completed
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855 - Operation of an ISFSI Operation of an ISFSI
(1)
===60855 - Operation of an Independent Spent Fuel Storage Installation
The inspectors evaluated Nine Mile Point's independent spent fuel storage installation cask loadings on June 28-July 2, 2021. Specifically, the inspectors observed the following activities:
- Fuel selection and fuel loading
- Heavy load movement of the transfer cask and loaded dry storage canister
- Decontamination of cask
- Drying and backfill evolutions
- Closure welding and non-destructive weld evaluations
- Transfer and transport evolutions
- Radiological field surveys
60856 - Review of 10 CFR 72.212(b) Evaluations
Review of 10 CFR 72.212(b) Evaluations===
- (1) NRC staff evaluated Independent Spent Fuel Storage Installation (ISFSI) concrete storage pad 4 to determine if it has sufficient capacity to withstand the static and dynamic loads of the HI-STORM FW XL casks that will be stored there, such that the casks can maintain their structural integrity, and that the addition of the HI-STORM FW casks will not negatively impact the existing NUHOM horizontal storage modules (HSMs). In addition, a site-specific tip-over analysis of the HI-STORM FW XL was performed.
The staff reviewed applicable documentation supporting Exelons assumptions and overall methodology demonstrating compliance with 10 CFR Part 72.212(b)(5)(ii)requirements and verified that the analysis and design methodology used for the HI-STORM FW casks on the Nine Mile Point ISFSI pad was consistent with the HI-STORM FW FSAR as well as applicable guidance in ACI 318-02, ACI-349-06, NUREG-1536 and NUREG-0800. The staff concluded that Exelon's overall approach was reasonable, satisfies the requirements of 10 CFR Part 72.212(b)(5)(ii), and therefore provides a reasonable assurance of safety.
INSPECTION RESULTS
Observation: Evaluation of Corrective Actions and Extent of Condition for IR 04355747 71152 In September 2019, the licensee conducted a maintenance and technical training self-assessment. During the self-assessment several gaps were identified in the documentation and record management associated with the radiation protection and chemistry technician training programs. The issue included training documentation and records retention requirements not being completed in accordance with training procedures and licensee processes and records management procedures. The licensee determined that many of the identified issues were repetitive and occurred over several years without being detected and corrected in a timely manner. The licensee determined that the identified issues did not impact the qualification of personnel. Subsequent to the self-assessment, additional focused program reviews and evaluations were completed and comprehensive corrective actions were implemented. An extent of condition review revealed that the majority of the records identified as missing from the records management system in the self-assessment were from the radiation protection training program. The missing records were located or recreated from course materials and test records that were retained in paper form. The inspectors found that the licensee followed their process for identifying and correcting the administrative inconsistencies associated with this issue. The inspectors reviewed the licensees self-assessment, relevant IRs and associated corrective actions, and discussed the inconsistent management of radiation protection training records with the training manager. Inspectors determined that Exelon appropriately classified and evaluated the inconsistencies in training document retention and prioritized corrective actions commensurate with the safety significance. No performance deficiencies were identified.
Observation: IRs 04305757 and 04388983 - Review of Issue Evaluations and Corrective Actions for Reactor Recirculation Hydraulic Power Unit Issues 71152 The inspectors reviewed Exelons evaluations and corrective actions associated with failures of the Unit 2 reactor recirculation system flow control valve hydraulic power units.
Specifically, IR 04305757 and IR 04388983 documented unexpected flow control valve A openings following issues associated with the system hydraulic power units. Issue report 04305757 was written on December 23, 2019, after both A hydraulic power unit pumps failed to operate following a blown fuse in the associated power system, which led to the A flow control valve slowly drifting closed. Issue report 04388983 was written on December 8, 2020 after the A flow control valve unexpectedly opened approximately five percent following a planned hydraulic power unit subloop swap.
Following the December 2019 incident, Exelon performed a work group evaluation and identified a failed pressure switch seal that allowed oil to leak into a hydraulic power unit power supply housing. This caused an electrical short, leading to a blown fuse which prevented operation of both associated hydraulic power unit pumps. Exelon performed inspections and replacement of pressure seals in the system and identified a power supply vulnerability that affects both subloops in cases of high inductance electrical failures. A work order was generated to implement a modification in the upcoming Unit 2 refueling outage (N2R18) to address the power supply vulnerability. Following the December 2020 incident, Exelon performed a work group evaluation and concluded that high acidity in the hydraulic oil had likely led to varnishing of some small tolerance components within the system and caused sticking of an associated servo valve. The high acidity of the hydraulic oil had been previously identified (IR 04311965), and mitigating measures such as more frequent filter changes and oil sampling were in place. Exelon identified additional corrective actions following the December 2020 incident including a full system flush and chemical cleaning during the next outage, more frequent oil sampling and filter changes, and installation of an additional filtration system to maintain oil acidity level.
In addition to the actions described above, there were numerous changes to the frequencies of system filter changes dating back to 2018. In some cases, the frequency was decreased as a result of satisfactory system performance. In other cases, most notably following the identification of high oil acidity, the frequency was increased in order to address the high acidity. The inspectors did not identify any issues of concern with the modifications to the filter changeout frequencies.
The inspectors reviewed the work group evaluations, relevant IRs and associated corrective actions, and discussed the failures with site engineers. Inspectors determined that Exelon appropriately classified and evaluated the failures in the hydraulic power units and prioritized corrective actions commensurate with the safety significance. No performance deficiencies were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 5, 2021, the inspectors presented the integrated inspection results to Mr. Pete Orphanos, Site Vice President, and other members of the licensee staff.
- On August 16, 2021, the inspectors presented the independent spent fuel storage installation loading campaign inspection results to Mr. Pete Orphanos, Site Vice President, and other members of the licensee staff.
- On September 30, 2021, the inspectors presented the airborne, dosimetry, and performance indicator verification inspection results to Mr. Pete Orphanos, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60856
Calculations
W-1-131
Design of ISFSI HSM Pads and Approach Slabs
W-1-132
Seismic Soil Structure Interaction Analysis of ISFSI Pad
Miscellaneous
HI-2114830
HI-2188770
Non-Mechanistic Tip-Over Analysis of the HI2 Storm FW XL
Cask on ISFSI Pad
HI-2200583
ISFSI Soil Structure Interaction Analysis for Nine Mile Point
HI-2200876
Structural Evaluation of Nine Mile Point ISFSI Pad
LR No. 721004-
1071
TN 10 CFR 72.48 Applicability and 10 CFR 71 Review
04/2012
Corrective Action
Documents
04157336
Corrective Action
Documents
Resulting from
Inspection
04432692
Procedures
N1-OP-26
Turbine Building Ventilation System
03300
N1-OP-47A
25 VDC Power System
200
N1-OP-64
Meteorological Monitoring
2000
N2-OP-102
Meteorological Monitoring
2800
N2-OP-70
Station Electrical Feed and 115KV Switchyard
2700
Work Orders
C93744831
C93745032
Corrective Action
Documents
218850
04424083
04437275
Drawings
0001040209048
Control Diagram Shutdown System, Sheet 2
C-18005-C, Sheet
Feed Water Flow High Pressure P & I Diagram
C-18005-C, Sheet
Feed Water Flow High Pressure P & I Diagram
C-18012-C, Sheet
Reactor Containment Spray Raw Water System P&I
Diagram
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
C-18012-C, Sheet
Reactor Containment Spray System P&I Diagram
PID-104A
Piping and Instrumentation Diagram Standby Diesel Gen
System
PID-104B
Piping and Instrumentation Diagram Standby Diesel Gen
System
PID-104F
Piping and Instrumentation Diagram Fuel Oil Schematic
Standby Diesel Generator System
PID-35A
Piping and Instrumentation Diagram Reactor Core Isolation
Cooling
PID-35B
Piping and Instrumentation Diagram Reactor Core Isolation
Cooling
PID-35C
Piping and Instrumentation Diagram Reactor Core Isolation
Cooling
PID-35D
Piping and Instrumentation Diagram Reactor Core Isolation
Cooling
Procedures
N2-OP-100A
Standby Diesel Generators
03100
N2-OP-100A -
LINEUPS
Standby Diesel Generators - LINEUPS
00500
N2-OP-31-
LINEUPS
Residual Heat Removal System - LINEUPS
00300
N2-OP-35
Reactor Core Isolation Cooling
01600
N2-OP-35-
LINEUPS
Reactor Core Isolation Cooling - LINEUPS
00100
Containment Spray System
Fire Plans
N1-PFP-0101
Unit 1 Pre-Fire Plans
00700
N2-FPI-PFP-0201
Unit 2 Pre-Fire Plans
Corrective Action
Documents
04443084
04444041
04444168
Miscellaneous
Nine Mile Point Nuclear Station - Unit 1, Individual Plant
Examination
07/1993
Unit 2 USAR
Corrective Action
04386503
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
04426305
04440437
Procedures
N2-TTP-HVY-
@102
Performance Evaluation Test for Unit Cooler 2HVY*UC2A,
B, C, and D
00500
Work Orders
C93773435
71111.11Q Corrective Action
Documents
04448532
Procedures
N1-OP-40
Reactor Protection and ATWS Systems
03000
N1-SOP-40.1
Loss of RPS
00300
N2-OP-2
Moisture Separator Reheater System
01400
Corrective Action
Documents
240544
04357553,
04359704,
04364396,
04366448,
04428910,
04428924,
04428736,
04433243,
04433671
04432219
04432356
04432670
Drawings
C-18012-C
Reactor Containment Spray Raw Water System P&I
Diagram, Sheet 1
Miscellaneous
Purchase Order
804496
Procedures
N1-ST-Q28
Containment Spray Raw Water Inter Tie Check Valve
01400
N2-MSP-EGS-
6Y001
Diesel Generator 6 Year Inspection Division 1 and 2
01300
N2-MSP-EGS-
R001
Diesel Generator Inspection Division 1 and 2
2400
Shipping Records
103585
Quality Receipt Inspection Package
Work Orders
C93713932
C93761578
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
04433671
04434222
Drawings
0001040209048
Control Diagram Shutdown System, Sheet 2
Procedures
N2-OP-31
Residual Heat Removal System
03600
Protected Equipment Program
OP-NM-108-117
Protected Equipment Program at Nine Mile Point
00500
Corrective Action
Documents
04394076
04407035
04407416
04415646
04420648
04420677
04424910
04430237
04431538
04432219
04432670
04433755
04436288
04441692
04448710
04448774
Drawings
C-18012-C
Reactor Containment Spray Raw Water System P&I
Diagram, Sheet 1
Miscellaneous
[Operations
Standing Order]
SO-2021-002
Control Rod Friction (U2)
5/5/21
ENGDOC-21-
000009
Operability Evaluation
Procedures
N1-OP-49
Control Room Ventilation System
04400
N1-ST-Q28
Containment Spray Raw Water Inter Tie Check Valve
01400
N2-OP-57
Diesel Generator Building Ventilation System
01100
N2-OSP-EGS-
Diesel Generator and Diesel Air Start Valve Operability Test
200
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M@001
- Division I and II
S-EPM-GEN-
VRLA
Valve Regulated Lead Acid Battery Inspections
200T2
Work Orders
C93752846
Corrective Action
Documents
04381891
04387312
04426934
Miscellaneous
Reactor Oversight Process Changes to Address Severe
Accident Management Guidelines
2/23/2016
Exelon Generation Company, LLC Fleet Commitment to
Maintain Severe Accident Management Guidelines
2/04/2015
Field Change
Notice G9MI2-
40506
Nine Mile Point Unit 2 Turbine Control System Modifications
Emergency Response Procedures and Guidelines for
Beyond Design Basis Events and Severe Accidents
Procedures
N1-SAP-1 (1-3)
RPV and Primary Containment Injection for Modes 1-3
00000
N1-SAP-1 (4)
RPV and Primary Containment Injection for Mode 4
00000
N1-SAP-2 (1-3)
RPV, Containment, and Radioactivity Release Control for
Modes 1-3
00000
N1-SAP-2 (4)
Containment and Radioactivity Release Control for Mode 4
00000
N1-SAP-B-
MODES 1-3
NMP1 Severe Accident Procedure Basis Document
00000
N1-SAP-B-RF
(MODE 4)
NMP1 Severe Accident Procedure For Refuel Basis
Document
00000
N1-SAP-PSSAG
NMP1 Plant Specific Severe Accident Guidelines (PSSAG)
00000
N2-SAP-1 (1-4)
RPV and Primary Containment Injection for Modes 1-4
00000
N2-SAP-1 (5)
RPV and Primary Containment Injection for Mode 5
00000
N2-SAP-2 (1-4)
RPV, Containment, and Radioactivity Release Control for
Modes 1-4
00000
N2-SAP-2 (4)
Containment and Radioactivity Release Control for Mode 5
00000
N2-SAP-B-
MODES 1-4
NMP2 Severe Accident Procedure (SAP) Basis Document
00000
N2-SAP-B-RF
NMP2 Severe Accident Procedure (SAP) Basis Document
00000
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(MODE 5)
N2-SAP-PSSAG
NMP2 Plant Specific Severe Accident Guidelines (PSSAG)
00000
Corrective Action
Documents
04040891
04428736
04428910
04428924
04433439
04434443
Miscellaneous
EMD Fuel Injectors - Seized Plunger and Bushing
10/24/2019
Procedures
N1-ST-M4B
Emergency Diesel Generator 103 and PB 103 Operability
Test
2600
N1-ST-Q25
Emergency Diesel Generator Cooling Water Quarterly Test
200
N1-ST-Q3
High Pressure Coolant Injection Pump and Check Valve
Operability Test
01900
N1-ST-Q6A
Containment Spray System Loop 111 Quarterly Operability
Test
2000
N2-MPM-IAS-
V606
Instrument Air Compressor PM 2IAS-C3A, 2IAS-C3B, 2IAS-
C3C
01800
N2-OP-19
Instrument and Service Air System
29T1
N2-OPS-EGS-
M@001
Diesel Generator and Diesel Air Start Valve Operability Test
- Division I and II
200
S-PM-001
Flex 3419MX Water Pump Test
00300
Work Orders
C93641783
C93654944
C93661361
C93751828
C93758738
C93764006
C93766025
C93793313
C93951322
Procedures
N2-OSP-RDS-
@002
Channel Interference Testing
00600
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
N2-OSP-SLS-
Q001
Standby Liquid Control Pump, Check Valve, Relief Valve
Operability Test and ASME XI Pressure Test
2300
S-PM-003
FLEX 450kW Diesel Generator Test
00600
71151
Miscellaneous
N1-MSPI-001
Nine Mile Point 1 MSPI Basis Document
N2-MSPI-001
Nine Mile Point 2 MSPI Basis Document
Regulatory Assessment Performance Indicator Guideline
Corrective Action
Documents
04305757
04311965
04355747
Corrective Action Performance Evaluation
08/13/2020
04388983
Procedures
N2-OP-29
Reactor Recirculation System
03300