IR 05000220/2021003

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Integrated Inspection Report 05000220/2021003 and 05000410/2021003 and Independent Spent Fuel Storage Installation Report 07201036/2021001
ML21309A651
Person / Time
Site: Nine Mile Point  Constellation icon.png
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:

DPR-63 and NPF-69

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-STORM FW FSAR

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

71111.01

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

71111.04

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

SDBD-203

Containment Spray System

71111.05

Fire Plans

N1-PFP-0101

Unit 1 Pre-Fire Plans

00700

N2-FPI-PFP-0201

Unit 2 Pre-Fire Plans

71111.06

Corrective Action

Documents

04443084

04444041

04444168

Miscellaneous

Nine Mile Point Nuclear Station - Unit 1, Individual Plant

Examination

07/1993

Unit 2 USAR

71111.07A

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

71111.12

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

71111.13

Corrective Action

Documents

04433671

04434222

Drawings

0001040209048

Control Diagram Shutdown System, Sheet 2

Procedures

N2-OP-31

Residual Heat Removal System

03600

OP-AA-108-117

Protected Equipment Program

OP-NM-108-117

Protected Equipment Program at Nine Mile Point

00500

71111.15

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

71111.18

Corrective Action

Documents

04381891

04387312

04426934

Miscellaneous

Reactor Oversight Process Changes to Address Severe

Accident Management Guidelines

2/23/2016

(ML16032A029)

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

NEI 14-01

Emergency Response Procedures and Guidelines for

Beyond Design Basis Events and Severe Accidents

(ML16224A619)

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

71111.19

Corrective Action

Documents

04040891

04428736

04428910

04428924

04433439

04434443

Miscellaneous

10CFR21-0127

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

71111.22

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

NEI 99-02

Regulatory Assessment Performance Indicator Guideline

71152

Corrective Action

Documents

04305757

04311965

04355747

Corrective Action Performance Evaluation

08/13/2020

04388983

Procedures

N2-OP-29

Reactor Recirculation System

03300