IR 05000220/2023011

Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011

ML23289A017
Person / Time
Site:	Nine Mile Point   (DRP-063, NPF-069)
Issue date:	10/16/2023
From:	Mel Gray Division of Operating Reactors
To:	Rhoades D Constellation Energy Generation, Constellation Nuclear
References
IR 2023011
Download: ML23289A017 (1)

Text

October 16, 2023

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - COMPREHENSIVE ENGINEERING TEAM INSPECTION REPORT 05000220/2023011 AND 05000410/2023011

Dear David Rhoades:

On September 29, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station, Units 1 and 2. The NRC inspectors discussed the results of this inspection with Peter 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety

Docket Nos. 05000220 and 05000410 License Nos. DPR-63 and NPF-69

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000220 and 05000410

License Numbers:

DPR-63 and NPF-69

Report Numbers:

05000220/2023011 and 05000410/2023011

Licensee:

Constellation Energy Generation, LLC

Facility:

Nine Mile Point Nuclear Station

Location:

Oswego, NY

Inspection Dates:

September 11, 2023 to September 29, 2023

Inspectors:

P. Cataldo, Senior Reactor Inspector

N. Floyd, Senior Reactor Inspector

D. Kern, Senior Reactor Inspector

J. Kulp, Senior Reactor Inspector

N. Mentzer, Reactor Inspector

E. Miller, Reactor Inspector

J. Schoppy, Senior Reactor Inspector

A. Turilin, Reactor Inspector

Approved By:

Mel Gray, Chief

Engineering Branch 1

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a comprehensive engineering team 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.

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.

REACTOR SAFETY

===71111.21M - Comprehensive Engineering Team Inspection

The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Structures, Systems, and Components (SSCs) (IP section 03.01)===

For each component sample listed below, the team reviewed licensing and design basis documents and a sampling of applicable operator actions, periodic testing results, corrective action program documents, internal and external operating experience, preventive and corrective maintenance work orders, modifications, and aging management programs.

Additionally, the team performed walkdowns of the component or procedure and conducted interviews with licensee personnel.

The team used the attributes contained in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below as guidance. Specifically, the team evaluated these attributes in the course of applying 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations.

(1) Unit 1 Loss of Main Feedwater Initiating Event

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(2) Unit 1 High Pressure Coolant Injection Pump No. 12 (PMP-29-03)

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(3) Unit 1 Electromatic Relief Valve 123

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

The team used Appendix B guidance for Valves, Instrumentation, and As-Built System.

(4) Unit 1 Emergency Condenser Loop 11

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(5) Unit 2 Loss of 4 KV Division II Emergency Bus (2ENS*SWG103) Initiating Event

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Instrumentation, Circuit Breakers and Fuses, Cables, Electrical Loads, Motor Control Centers, and As-Built System.

(6) Unit 2 A Residual Heat Removal Heat Exchanger Service Water Supply Isolation Valve (2SWP*MOV90A)

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(7) Unit 2 A Residual Heat Removal Pump (2RHS*P1A)

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(8) Unit 2 A Residual Heat Removal Pump Motor

• Energy sources (electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Instrumentation, Circuit Breakers and Fuses, Cables, Electrical Loads, Motor Control Centers, and As-Built System.

(9) Unit 2 Suppression Pool Purge Nitrogen Supply Outboard Outlet Isolation Valve (2CPS*AOV111)

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

Modifications (IP section 03.02) (5 Samples)

(1) ECP-16-000339: Replace the EDG 102 and EDG103 Timing Relays

(2) ECP-18-000398: Add Redundant Valve in Series with 2EGS*AOV2011A /

2EGS*AOV2011B (Post Lube Pilot Valves)

(3) ECP-20-000570: NMP1 Emergency Diesel Generator Tank Cathodic Protection System Modification

(4) ECP-21-000361: Modify NMP2 Service Water Pump Interlock Logic

(5) ECP-22-000282: Replace PT Fuses for DIV I & II located in 2EGS*PNL11 and 2EGS*PNL31 10 CFR 50.59 Evaluations/Screening (IP section 03.03) (17 Samples)

(1)5059-2020-168, Disable Moisture Separator High Level Turbine Trip in the Steam Admission Trip Circuit fed from Battery Board 11 (Steam Leak Created Battery Ground), dated September 18, 2020 (2)5059-2020-172, Modification to Install High Point Vents in U1 Control Room Chilled Water Piping, dated September 24, 2020 (3)5059-2020-194, Shielding for the DFR Line From 2DFR*MOV120 to the Containment Penetration, dated November 18, 2020 (4)5059-2020-205, Long Standing Tagout U2X-CCP-0046, dated December 7, 2020 (5)5059-2020-210, Modify Snubbers 2ISC-21PSSP003C1 and 2WCS-PSSP886A1, dated July 12, 2023 (6)5059-2021-016, Control Room Panel F1, dated April 12, 2021 (7)5059-2021-019, NMP1 EOP Support Procedure, dated March 27, 2021 (8)5059-2021-024, Unit 2 Refuel Bridge TRM 3.9.4 Change Evaluation, dated March 11, 2021 (9)5059-2021-043, Install Capacitors on Detector Strings and Fire/Smoke Dampers in Unit 1 Local Fire Panels, dated October 15, 2021 (10)5059-2021-053, Operators Rounds Guide, dated February 25, 2021 (11)5059-2021-059, Change Frequency of N1-IPM-036-017, Reactor Hi Water Level - 13 Feedwater Pump Trip Verification per PMC-20-126425, dated March 4, 2021 (12)5059-2021-065, Main Power Transformer Deluge System Replacement, dated March 18, 2021 (13)5059-2021-068, Add UT as an Inspection Method That Gives Credit to the Top Guide Inspection and Reset Inspection Interval, dated March 16, 2021 (14)5059-2021-110, Residual Heat Removal Reject Line to Reactor Water Cleanup System Cross-tie, dated January 19, 2021 (15)5059-2022-014, NMP1 NERC PRC-026 Compliance: Generator Protection Relays, dated May 16, 2022 (16)5059-2022-105, Standby Diesel Generators, dated September 28, 2022 (17)5059-2022-120, Tech Eval to Defeat Annunciator Input from U1 Refuel Bridge High Range Rad Monitor Input via S-ARP-001, dated October 31, 2022

Operating Experience Samples (IP section 03.04) (3 Samples)

(1) NRC Information Notice 2019-01: Inadequate Evaluation of Temporary Alterations

(2) Part 21 Report - Nonconforming Relay Led to Failures of Battery Chargers (EN 55453)

(3) Part 21 Communication - Failure of Safety-Related Spring Charging Motor (AR 4401753)

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On September 29, 2023, the inspectors presented the Comprehensive Engineering Team Inspection results to Peter Orphanos, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21M Calculations

1701253.301

Structural Integrity Associates, Inc., NMP-1 Top Guide Grid

Beam Flaw Assessment Update

Revision 0

EC-032

Nine Mile Point Unit 2 Diesel Generator Loading

Revision 13

EC-160

25VDC Breakers Coordination

Revision 0

ES-286

RHR Heat Exchanger Performance - K Values used in

Containment Analyses and Recommended HX Performance

Testing Acceptance Criteria

dated 5/6/09

S0-FLOOD-F001

Internal Flooding Hazard Analysis

Revision 1

Corrective Action

Documents

01974089

2429598

2524898

2629695

2664561

04130528

04169109

230952

245321

249798

04327479

04346002

04372692

04401753

04408464

04420027

04428667

04451825

04485431

04486137

04521302

04535217

04668582

04668639

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

04674179

04703564

Corrective Action

Documents

Resulting from

Inspection

4697228

04698169

04701751

04701865

04701902

04701979

04702075

04702077

04702078

04702179

04702247

04702260

04702269

04702502

04702513

04702527

04702530

04702535

04702582

04702791

04702825

04702854

04702855

04703532

04703535

04703554

04704067

04704269

04704311

04704897

04704971

04705153

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

04705291

04705310

04705311

04705312

04705352

04705400

04705408

04705507

04705508

04705539

04705605

04705679

04705696

04705775

04705794

Drawings

B-42346-C, Sh. 6

Unit 1 Fire Barrier Penetration Seal Details for FS-5

Revision 1

C-35970-C, Sh. 1

Unit 1 General Floor Plan Reactor Building El. 237 &

Turbine Building El. 250

Revision 6

Engineering

Evaluations

ADC-11-000685

Minute Operator Action Time for Circulating Water Line

Break

Revision 0

CNF-TGUT-01

Hitachi Ultrasonic Exam Results

dated 4/4/21

ECP-20-000504

Disable Moisture Separator Hight Level Turbine Trip in the

Steam Admission Trip Circuit fed from Battery Board 11

(Steam Leak Created Battery Ground)

Revision 0

ECP-20-000605

NMP1 Reactor Pressure Instrument Channel Surveillance

Frequency Extension from 24 Months to 48 Months

Revision 0

ECP-21-000016

Cross-tie between Residual Heat Removal Reject Line to

Reactor Water Cleanup System Discharge to Condenser

Revision 1

ECP-22-000366

Technical Evaluation to Defeat Annunciator Input from Unit 1

Refuel Bridge High Range Radiation Monitor

Revision 0

N2-MISC-001

Internal Events NMP2 Time Sensitive Operator Actions PRA

Input from the 2019 Model Update

Revision 2

Miscellaneous

Mersen 9F60 Series Potential Transformer Medium Voltage

Fuses

dated 2018

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Shielding Approval Form, 2-SHIELDIN-RB-215-031

dated

9/18/23

Fuse, 0.5E, 5.5KV,

P.T. PR-1 (PO# 01356413, Catalog ID#

0011801524-2, DP# LIM-05495, CG)

Revision 1

N1-EPM-082-801

Emergency Generator Diesel Fuel Storage Buried Tanks

and Piping Cathodic Protection System Potential Survey

performed

9/23/22

N1-EPM-GEN-

24

Electromatic Solenoid Inspection

performed

3/27/23

N1-ISP-066-003

Auto Depressurization System Operability Test

performed

3/26/23

N1-PRA-012

Internal Flooding Analysis Notebook

Revision 3

N1-ST-Q3

High Pressure Coolant Injection Pump and Check Valve

Operability Test

performed

4/22/23

N2-OSP-RHS-

Q@004

RHR System Loop A Pump & Valve Operability Test and

System Integrity Test and ASME XI Pressure Test

performed

7/19/23

N2-RSP-RMS-

M003

Monthly Source Check of DRMS Tech Spec Radiation

Monitors

performed

8/23/23

NRC Information Notice 96-01

Recent Issues Related to the Commercial Grade Dedication

of Allen Bradley 700-RTC Relays

dated

2/17/16

PCR-22-02698

Add Step to Reset Panel to Standby Checks Using Switch to

Reset Logic

dated

9/21/22

S-MMP-SDM-001

Quarterly PM Inspection of Gates and Doors

dated

7/28/23

Procedures

ER-NM-331-1001

Nine Mile Point Unit 1 Reactor Internals Program Basis

Document

Revision 4

N1-EPM-GEN-

150

4.16KV Breaker Inspection P.M.

Revision 20

N2-EOP-6.21

Containment Venting

Revision 7

N2-EPM-GEN-

550

GE 4.16KV Magne-Blast Breaker P.M.

Revision 13

N2-OSP-SWP-

M001

Service Water Valve Position Verification

Revision 5

N2-PM-082

RPV Flood Up/Draindown

Revision 21

N2-SOP-03

Loss of AC Power

Revision 22

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

OP-NM-102-106

Operator Response Time Program at Nine Mile Point

Revision 17

Work Orders

C92180736

C92180870

C92562700

C92562702

C93226857

C93480108

C93718001

C93771790

C93777205

C93777210

C93784028

C93847507

C93886674

06-02118-00

06-02119-00