IR 05000220/2023001

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Integrated Inspection Report 05000220/2023001 and 05000410/2023001
ML23125A005
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 05/05/2023
From: Erin Carfang
NRC/RGN-I/DORS
To: Rhoades D
Constellation Energy Generation, Constellation Nuclear
References
IR 2023001
Download: ML23125A005 (1)


Text

May 5, 2023

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000220/2023001 AND 05000410/2023001

Dear David Rhoades:

On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station. On April 20, 2023, 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 NRC-identified or self-revealing findings were identified during this inspection.

A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)

consistent with Section 2.3.2 of the Enforcement Policy.

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

Document Control Desk, Washington, D.C. 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Nine Mile Point Nuclear Station. 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 (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Erin E. Carfang, Chief Projects 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:

05000220/2023001 and 05000410/2023001

Enterprise Identifier: I-2023-001-0045

Licensee:

Constellation Energy Generation, LLC

Facility:

Nine Mile Point Nuclear Station

Location:

Oswego, NY

Inspection Dates:

January 1, 2023 to March 31, 2023

Inspectors:

G. Stock, Senior Resident Inspector

C. Kline, Resident Inspector

B. Sienel, Resident Inspector

J. Kulp, Senior Reactor Inspector

S. Veunephachan, 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. A licensee-identified NCV is documented in report section 71111.1

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period at rated thermal power. On January 7, 2023, the unit was downpowered to 88 percent for a control rod pattern adjustment and returned to rated thermal power on January 8, 2023. On January 17, 2023, the unit was downpowered to 93 percent to perform suppression testing following the identification of a leaking fuel assembly. On January 18, 2023, power was raised to 95 percent and the unit began end of cycle coastdown.

On March 12, 2023, the unit was downpowered to enter the Unit 1 refueling outage and the unit was shut down March 13, 2023. The unit remained shut down for the remainder of the inspection period.

Unit 2 began the inspection period at rated thermal power. On January 6, 2023, the unit was downpowered to 65 percent for a reactor feedwater pump swap and was returned to rated thermal power on the same day. On March 4, 2023, the unit was downpowered to 62 percent for a reactor feedwater pump swap, scram time testing, turbine valve testing, and a control rod pattern adjustment. The unit was returned to rated thermal power on March 6, 2023 and remained at or near rated thermal power for the remainder of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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

71111.01 - Adverse Weather Protection

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

(1) The inspectors evaluated readiness for impending adverse weather for a wind chill warning on February 3, 2023.

71111.04 - Equipment Alignment

Partial Walkdown (IP Section 03.01) (7 Samples)

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

(1) Unit 2 'B' residual heat removal system on January 10, 2023
(2) Unit 2 high pressure core spray system on February 8, 2023
(3) Unit 2 reactor core isolation cooling (RCIC) on February 21, 2023
(4) Unit 1 core spray train 121 on March 15, 2023
(5) Unit 1 shutdown cooling 12 on March 16, 2023
(6) Unit 1 emergency diesel generator 103 on March 17, 2023
(7) Unit 1 spent fuel pool cooling 11 on March 28, 2023

71111.05 - Fire Protection

Fire Area Walkdown and Inspection (IP Section 03.01) (9 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' north, fire area 1, on January 4, 2023
(2) Unit 1 emergency diesel generator 103 room, fire area 19, on January 13, 2023
(3) Unit 1 emergency diesel generator 102 room, fire area 22, on January 19, 2023
(4) Unit 1 turbine building 291' north, fire area 5, on February 14, 2023
(5) Unit 2 diesel fire pump room, screenwell 261', fire area 71, on February 15, 2023
(6) Unit 1 main steam line room, fire area T1A, on March 13, 2023
(7) Unit 1 condenser bay, fire area 5, on March 14, 2023
(8) Unit 1 heater bay, fire area 5, on March 14, 2023
(9) Unit 1 drywell, fire area 3, on March 16, 2023

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 1 reactor building closed loop cooling 12 heat exchanger

71111.08G - Inservice Inspection Activities (BWR)

BWR Inservice Inspection Activities - Nondestructive Examination and Welding Activities

(IP Section 03.01)

(1) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from May 14, 2023 to April 17, 2023:
  • ECP-21-000197-CN-001, Flaw Evaluation of the Unit 1 Recirculation Nozzles (N1C

& N1D) Nozzle to Safe End Axial Indications, Revision 0

  • Encoded Phased Array Ultrasonic Examination of the N2D Nozzle to Safe End Weld, (NMP1-ISI-VE-22)
  • Encoded Phased Array Ultrasonic Examination of the N2E Nozzle to Safe End Weld, (NMP1-ISI-VE-019)
  • Encoded Phased Array Ultrasonic Examination of the N2E Nozzle to Safe End Weld Overlay, (N2ENMPU1ND1)
  • In-vessel Visual Examination of Core Spray Sparger Nozzles (N1R27 CSS-S3a-A-23A)
  • In-vessel Visual Examination of Tie Rod 166W (N1R27 SHD TR 166 W Dimension 165)
  • Manual Ultrasonic Examination of Emergency Condenser Steam Inlet Line Pipe to Elbow Weld (1R27-ISI-UT-033)
  • Visual Examination (VT2) on N13B RPV Instrumentation Nozzle, (NMP1-VT-23-014)
  • Visual Examination (VT2) on N14B RPV Instrumentation Nozzle, (NMP1-VT-23-017)
  • Visual Examination (VT2) on N15B RPV Instrumentation Nozzle, (NMP1-VT-23-018)
  • Visual Examination (VT2) on N16B RPV Instrumentation Nozzle, (NMP1-VT-23-019)
  • Visual Examination (VT2) on N17B RPV Instrumentation Nozzle, (NMP1-VT-23-020)

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 during a reactor downpower to 62 percent and control rod scram time testing on March 4, 2023.
(2) The inspectors observed Unit 1 operations personnel during the reactor shutdown for refueling outage N1R27.

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

(1) The inspectors observed a Unit 2 simulator evaluation that included a reactor coolant leak culminating in the declaration of a Site Area Emergency on January 31, 2023.
(2) The inspectors observed a Unit 1 simulator evaluation that included a 13 feedwater flow control valve failure, a loss of power board 102, a loss of condenser vacuum, and a large break loss-of-coolant accident with loss of level indication on February 14, 2023.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

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

(1) Unit 1 emergency diesel generator 103

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management (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 Division I air conditioning (A/C) fan failure on January 27, 2023
(2) Unit 1 elevated risk during 12 reactor building closed loop cooling heat exchanger maintenance on February 6, 2022
(3) Unit 2 elevated risk during RCIC system outage on February 6, 2023
(4) Unit 2 elevated risk during emergent work on RCIC keep fill pump discharge line on February 13, 2023
(5) Unit 1 elevated risk during emergent maintenance on the diesel fire pump on February 15, 2023
(6) Unit 1 elevated risk during planned reactor cavity floodup on March 14, 2023
(7) Unit 1 elevated risk during planned reactor cavity draindown on March 28, 2023

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

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

(1) Unit 1 diesel driven fire pump due to coolant leak on January 24, 2023
(2) Unit 2 high pressure core spray due to surveillance test below specification recirculating flow on January 26, 2023
(3) Unit 1 emergency diesel generator 103 fuel oil normal level switch degraded identified during surveillance testing on February 27, 2023
(4) Unit 2 Division II standby diesel generator due to exhaust fan trip after automatic start during a surveillance on March 6, 2023
(5) Unit 1 diesel generator 103 due to loss of power board 171A on March 10, 2023
(6) Unit 1 diesel generator 102 due to output breaker failure to close during testing on March 23, 2023

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) Temporary Modification: ECP-23-000038, Division I Control Room A/C Fan Motor Replacement
(2) Permanent Modification: ECP-22-000042, Replace Obsolete GEMAC Steam Flow Indication with NUS Module
(3) Permanent Modification: ECP-22-000396, Unit 1 Suppression Chamber (Torus)

Minimum Wall Thickness Optimization

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated Unit 1 refueling outage N1R27 activities from March 13 through 31, 2023.

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (IP Section 03.01) (2 Samples)

(1) Control room emergency filtration system following A/C fan motor replacement on January 29, 2023
(2) Unit 1 power board 102 following loss of voltage relay replacement on March 23, 2023

Surveillance Testing (IP Section 03.01) (5 Samples)

(1) N1-ST-M4A, Emergency Diesel Generator 102 and power board (PB) 102 Operability Test, on January 23, 2023
(2) N1-ST-M4B, Emergency Diesel Generator 103 and PB 103 Operability Test, on February 13, 2022
(3) N1-ST-V8, Main steam, feedwater/high pressure coolant injection, shutdown cooling, emergency cooling, Reactor Head Vent Valve Cold Shutdown Operability Test, on March 13, 2023
(4) N1-ST-R9A, Core Spray Loop 11 Operability Test Using Demineralized Water, on March 15, 2023
(5) N1-ST-C1A, Liquid Poison Functional Test Using Demineralized Water with Squib Valve Plugs Removed, on March 20, 2023

Inservice Testing (IST) (IP Section 03.01) (2 Samples)

(1) N2-OSP-SWP-Q005, Division III Service Water Operability Test, on January 23, 2023
(2) N2-OSP-ICS-Q@002, RCIC Pump and Valve Operability Test and System Integrity Test, on February 9, 2023

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) N1-ST-TYC-001, Main steam isolation valve Type C Leak Rate Tests, Attachment 16, on March 13, 2023

71114.06 - Drill Evaluation

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

The inspectors evaluated:

(1) The inspectors evaluated a Unit 1 simulator scenario that included a large break loss-of-coolant accident with loss of level indication requiring a Site Area Emergency declaration on February 14,

RADIATION SAFETY

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials, and how the licensee assesses radiological hazards.

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

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Licensee surveys of potentially contaminated material leaving the radiologically controlled area
(2) Workers exiting the radiologically controlled area at Unit 1 during refueling outage N1R27

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) RWP-23-00805
(2) VLV-39-50 breach and valve replacement
(3) RWP 23-00513
(4) Torus diving and torus vacuuming

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)

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

(1) Unit 2 reactor water cleanup phase separator aisle, reactor building, 289' elevation
(2) Unit 1 cleanup demineralizer 11, reactor building, 261' elevation
(3) Unit 1 drywell entrance, 237' elevation

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, and

Transportation

Shipment Preparation (IP Section 03.04)

(1) The inspectors observed the preparation and shipment of radioactive waste shipment: 22-2056, LSA-II, Bead Resin Liner. Manifest Number: 1039-C-0068

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

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

(1) Unit 1, January 1, 2022 through December 31, 2022
(2) Unit 2, January 1, 2022 through December 31, 2022

IE03: Unplanned Power Changes per 7000 Critical Hours (IP Section 02.02) (2 Samples)

(1) Unit 1, January 1, 2022 through December 31, 2022
(2) Unit 2, January 1, 2022 through December 31, 2022

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

(1) Unit 1, January 1, 2022 through December 31, 2022
(2) Unit 2, January 1, 2022 through December 31, 2022

===71153 - Follow-up of Events and Notices of Enforcement Discretion

Event Follow-up (IP Section 03.01)===

(1) Unit 2 Division I control room A/C fan failure on January 26,

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71111.12 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation (NCV), consistent with Section 2.3.2 of the Enforcement Policy.

Violation: 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, measures shall be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems and components. The safety-related Nine Mile Point Unit 2 Division I control room chiller is required to maintain control room habitability during an event. On December 8, 2022, the Division I control room chiller tripped on high motor windings temperature due to a degraded relay.

Contrary to above, on December 8, 2022, Constellation failed to establish measures for the selection of parts that are essential to the safety-related functions of the Division I control room chiller. Specifically, a non-safety-related relay was installed following the identification of a degraded high motor temperature trip module relay. The chiller was restored to operable and during work package review Constellation identified that the incorrect relay was installed. The unit was taken out of service and the relay was replaced with a safety-related relay.

Significance/Severity: Green. The inspectors determined this issue to be Green in accordance with IMC 0609 Appendix A, Exhibit 3 because the finding did not represent a degradation to the radiological barrier function provided for the control room or the barrier function of the control room against smoke or a toxic atmosphere.

Corrective Action References: IR

EXIT MEETINGS AND DEBRIEFS

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

  • On March 23, 2023, the inspectors presented the radiation hazard assessment and control inspection results to Joseph Garcia, Radiation Protection Manager, and other members of the licensee staff.
  • On April 20, 2023, the inspectors presented the integrated 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

71111.01

Procedures

N1-OP-64

Meteorological Monitoring

2100

N2-OP-102

Meteorological Monitoring

2800

OP-AA-108-111-

1001

Severe Weather and Natural Disaster Guidelines

71111.04

Corrective Action

Documents

04562615

Drawings

C-18007-C

Reactor Core Spray P&ID

C-18008-C

Spent Fuel Storage Pool Filtering and Cooling System P & I

Diagram

C-18018-C

Reactor Shutdown Cooling P & I Diagram

PID-31B

Piping & Instrumentation Diagram Residual Heat Removal

PID-31E

Piping & Instrumentation Diagram Residual Heat Removal

PID-31F

Piping & Instrumentation Diagram Residual Heat Removal

PID-33A

Piping & Instrumentation Diagram High Pressure Core Spray

System

PID-33B

Piping & Instrumentation Diagram High Pressure Core Spray

System

Procedures

N1-OP-2

Core Spray System

03900

N1-OP-45

Emergency Diesel Generators

05100

N1-OP-6

Fuel Pool Filtering and Cooling System

03100

N2-OP-31

Residual Heat Removal System - Lineups

03900

N2-OP-31-

Lineups

Residual Heat Removal System - Lineups

00300

N2-OP-33

High Pressure Core Spray System

01900

N2-OP-33-

Lineups

High Pressure Core Spray System - Lineups

00100

N2-OP-35

Reactor Core Isolation Cooling

01800

N2-OP-35-

Lineups

Reactor Core Isolation Cooling - Lineups

200

N2-OSP-RHS-

R@005

RHS Pressure Isolation Valve Leakage Test

00501

71111.05

Fire Plans

N1-PFP-0101

Unit 1 Pre-Fire Plans

00700

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

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

Miscellaneous

DCD-805

Nine Mile Point Unit 1 NFPA 805 Design Criteria

71111.07A

Procedures

ER-AA-340-1002

Service Water Heat Exchanger Inspection Guide

GAP-HSC-02

System Aging Inspection and Cleanliness Controls

2100

Work Orders

C93804532

71111.08G Corrective Action

Documents

04412326

04412423

04565322

04565598

Miscellaneous

Submittal of Emergency Relief Request I5R-11 Concerning

the Installation of a Weld Overlay on Reactor Pressure

Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle

Dissimilar Metal Weld (32-WD-208) (ML23083B991)

Verbal Authorization for NMP1 Proposed Alternative Weld

Overlay N2E Safe End to Nozzle DM Weld (EPID L-2023-

LLR-0011) (ML23090A130)

Verbal Authorization for NMP1 Relief Request I5R-14

Proposed Alternative Associated with N2E Safe End to

Nozzle DM Weld Repair with a Laminar Indication (EPID L-

23-LLR-0017) (ML23104A347)

Work Orders

C93802542

71111.11Q Procedures

N1-OP-43C

Plant Shutdown

030

N2-OSP-RMC-

@001

Control Rod Drive Scram Insertion Time Testing

2700

71111.12

Corrective Action

Documents

04542590

04543095

04544400

04544741

Miscellaneous

Maintenance Rule System Basis Document for Unit 1

Emergency Diesel Generator

01/24/2023

Work Orders

C93765330

C93893496

71111.13

Corrective Action

Documents

04450549

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Procedures

N1-PM-34B

Reactor Cavity Draindown

001

N2-OP-35

Reactor Core Isolation Cooling

01800

OP-AA-108-117

Protected Equipment Program

71111.15

Corrective Action

Documents

04549902

04549997

04557550

04559843

04564239

04564525

Procedures

N1-OP-45

Emergency Diesel Generators

05100

N1-ST-M4A

Emergency Diesel Generator 102 and PB 102 Operability

Test

03100

N2-OP-100A

Standby Diesel Generators

03300

N2-OP-57

Diesel Generator Building Ventilation System

01100

N2-OSP-CSH-

Q@002

HPCS Pump and Valve Operability Test

01100

Work Orders

C93903401

71111.18

Corrective Action

Documents

04550549

04550876

Engineering

Changes

ECP-22-000396

Unit 1 Suppression Chamber (Torus) Minimum Wall

Thickness Optimization

ECP-23-000038

2HVC*ACU1A Motor Replacement

Miscellaneous

NER-1I-003

Nuclear Engineering Report

Work Orders

C93896666

71111.20

Procedures

N1-PM-34A

Reactor Cavity Flood Up

N1-PM-34B

Reactor Cavity Drain Down

OU-NM-103-101

Shutdown Safety Management Program

00800

71111.24

Corrective Action

Documents

04540322

04553684

04561743

Procedures

N1-RCSP-GEN-

334

Operating Cycle Calibration for Loss and Degraded Voltage

Relays on Emergency Switchgear

00700

N1-RCSP-GEN-

Functional Test of 4.16KV Emergency Bus Loss and

00100

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

335

Degraded Voltage Relays

N1-ST-C1A

Liquid Poison Functional Test Using Demineralized Water

with Squib Valve Plugs Removed

N1-ST-M4A

Emergency Diesel Generator 102 and PB 102 Operability

Test

03100

N1-ST-R9A

Core Spray Loop 11 Operability Test Using Demineralized

Water

001

N1-ST-TYC-001

MSIV [main steam isolation valve] Type C Leak Rate Tests

00300

N1-ST-V8

MS, FW/HPCI, SDC,EC, RX Head Vent Valve Cold S/D

Operability Test

200

N1-STM4B

Emergency Diesel Generator 103 and PB 103 Operability

Test

2700

N2-OSP-HVC-

M001

Control Room Emergency Filtration (CREF) System

00500

N2-OSP-ICS-

Q@002

RCIC Pump and Valve Operability Test and System Integrity

Test and ASME XI Functional Test and Analysis

01800

N2-OSP-SWP-

Q005

Division III Service Water Operability Test

00500

Work Orders

C93684058

71151

Miscellaneous

NEI 99-02

Regulatory Assessment Performance Indicator Guideline

71153

Corrective Action

Documents

04550549