IR 05000369/2023004
| ML24029A040 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  (NPF-009, NPF-017) |
| Issue date: | 01/31/2024 |
| From: | Eric Stamm Division Reactor Projects II |
| To: | Pigott E Duke Energy Carolinas |
| References | |
| IR 2023004 | |
| Download: ML24029A040 (18) | |
Text
SUBJECT:
MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2023004 AND 05000370/2023004
Dear Edward Pigott:
On December 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On January 25, 2024, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. 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, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at McGuire Nuclear Station.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at McGuire Nuclear Station.
January 31, 2024 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, Eric J. Stamm, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 05000369 and 05000370 License Nos. NPF-9 and NPF-17
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000369 and 05000370
License Numbers:
Report Numbers:
05000369/2023004 and 05000370/2023004
Enterprise Identifier:
I-2023-004-0019
Licensee:
Duke Energy Carolinas, LLC
Facility:
McGuire Nuclear Station
Location:
Huntersville, North Carolina
Inspection Dates:
October 01, 2023, to December 31, 2023
Inspectors:
C. Safouri, Senior Resident Inspector
F. Young, Resident Inspector
A. Price, Resident Inspector
M. Schwieg, Senior Reactor Inspector
Approved By:
Eric J. Stamm, Chief
Reactor Projects Branch 1
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at McGuire 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
Failure to Resolve Electromagnetic Interference Affecting Unit 1 Source Range Nuclear Instruments Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000369/2023004-01 Open/Closed
[H.5] - Work Management 71152A A self-revealing green finding and associated non-cited violation (NCV) of Title 10 Code of Federal Regulations Part 50, Appendix B, Criterion XVI was identified when the licensee failed to correct deficient conditions associated with intermittent power spikes of Unit 1 source range nuclear instruments 1N31 and 1N32.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period in defueled mode as part of refueling outage M1R29. The unit was returned to 100 percent rated thermal power (RTP) on October 27, 2023, and remained at or near 100 percent RTP for the remainder of the inspection period.
Unit 2 operated at or near 100 percent RTP for the entire 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
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions on November 2, 2023, prior to the onset of seasonal cold temperatures for the following systems:
Main feedwater Auxiliary feedwater Fire protection
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 train A/B residual heat removal system prior to reactor coolant system lowered inventory, on October 13, 2023
- (2) Unit 1 train A emergency diesel generator (D/G) auxiliary systems including diesel fuel oil, D/G room ventilation, and D/G cooling water, on December 18, 2023
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Unit 1 upper containment prior to containment closeout, on October 21, 2023
- (2) Unit 1 lower containment prior to containment closeout, on October 21, 2023
- (3) Auxiliary building 733 ft elevation shared equipment area, on December 13, 2023
- (4) Safe shutdown facility, on December 15, 2023
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the: Auxiliary building at the 695 ft elevation, on November 14, 2023
===71111.08P - Inservice Inspection Activities (PWR) 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 October 2, 2023, to October 6, 2023.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic Examination
- Reactor vessel closure head penetrations Magnetic Particle Examination
- Flange RN-486-7 Liquid Penetrant Examination
- Accumulator injection line weld Welding Activities
- Nuclear service water (RN) flange PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
- (1) Reactor vessel closure head penetrations PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
(1)
- Nuclear condition report (NCR) 02466821, seal table boric active evaluation
- Threaded connection associated with core exit thermocouple (CET) plug
- Containment and auxiliary building walkdowns, on October 4-5, 2023
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." The inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, and the crew simulator operating examinations in accordance with inspection procedure (IP) 71111.11, "Licensed Operator Requalification Program and Licensed Operator Performance." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP
===71111.11.
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on June 21, 2023.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
=
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 reactor coolant system lowered inventory for refueling outage operation, on October 14, 2023, and Unit 1 train A main feedwater pump startup and power ascension, on October 25, 2023.
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) NCR 02476511, Unit 1/2 standby shutdown facility diesel generator cylinder 8L fuel injector pushrod failure, on November 27, 2023
- (2) NCR 02477616, Unit 1 channel 2 reactor protection system reverted to test condition during maintenance, on December 13, 2023
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Unit 1 large early release frequency yellow risk due to Unit 1 train A motor driven auxiliary feedwater flow balance surveillance and power range low power current calibrations, on October 25, 2023
- (2) Unit 1 elevated risk during pressurizer level channel III calibration, on November 30, 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) NCR 02489684, Unit 2 residual heat removal to refueling water storage tank high point vent, 2ND-88, gas detection during emergency core cooling system venting, on October 9, 2023
- (2) Work request (WR) 20257008, Unit 2 train A RN unreliable strainer differential pressure indication, on October 17, 2023
- (3) NCR 2491358, Unit 1 source range nuclear instrument, 1NI-31, erratic indication, on October 24, 2023
- (4) WR 20257346, Unit 2 RN auxiliary building non-essential header return isolation valve, 2RN-64A, failure to close, on October 26, 2023
- (5) NCR 02492962, Unit 2 loop B steam generator (SG) power operated relief valve (PORV), 2SV-7AB, indication failure led to a failed valve stroke time test, on November 6, 2023
- (6) NCR 02495695, Unit 1 pressurizer level channel III incorrect calibration methodology and associated re-calibration, on November 30, 2023
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering change (EC) 423224, Unit 1 loop D SG PORV, 1SV-1AB, boring of sleeve to use larger size packing, on October 23, 2023
- (2) EC 420632, Unit 2 train B D/G starting air distributor filter from Fisher Type 254F to Fisher Type 252, on December 18, 2023
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Unit 1 refueling outage, M1R29, activities from October 1, 2023, to October 25, 2023. The inspectors completed inspection procedure Sections 03.01.c through 03.01.e.
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 (PMT) (IP Section 03.01) (8 Samples)
- (1) MP/0/A/7600/282, Unit 1 train A RN flow control valve to component cooling water (KC) heat exchanger, 1RN-89A, air operated valve diagnostic testing following replacement, on September 29, 2023
- (2) Work order (WO) 20545352, Unit 1 train A KC pump #2 power cable, 1*KC622, repair and tan delta testing, on October 4, 2023
- (3) WO 20574407, Unit 1 train A D/G load sequencer relay replacement, on October 5, 2023
- (4) PT/1/A/4209/012, Unit 1 train A centrifugal charging pump head curve performance test following pump mechanical seal replacement, on October 7, 2023
- (5) PT/1/A/4255/004 B, Unit 1 loop D SG PORV quarterly valve stroke timing following packing repairs, on October 12, 2023
- (6) WO 20552195, Unit 2 train B D/G Struthers-Dunn relay retaining clips installation, on November 28, 2023
- (7) WO 20607829, Unit 1 train B KC motor electrical inspection, cleaning, and testing, on November 28, 2023
- (8) WO 20581715, Unit 1 train A residual head removal pump motor inspection, on December 19, 2023
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) PT/1/A/4200/009A, Engineered Safety Features Actuation Periodic Test Train A, Section 12.3, Unit 1 train A D/G load testing and engineered safety features valve stroking upon safety injection, phase A isolation, phase B isolation, and blackout signals, on September 17, 2023
- (2) PT/1/A/4200/009A, Engineered Safety Features Actuation Periodic Test Train A, Section 12.3, Unit 1 train A D/G response testing with offsite power available upon safety injection signal, on September 17, 2023
- (3) PT/1/A/4200/001A, "Containment Integrated Leak Rate Test," for Unit 1, on October 18, 2023
- (4) SM/0/A/8510/006, "Ice Condenser Intermediate Deck Doors Inspection and Corrective Maintenance," for Unit 1, on November 8, 2023
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) PT/1/A/4200/001C, Enclosure 13.26, Unit 1 Penetration M-331 annulus ventilation valves, 1VE-10A, 1VE-11, and 1VE-12, on October 10, 2023
Ice Condenser Testing (IP Section 03.01) (1 Sample)
- (1) PT/0/A/4700/096, "NF Ice Bin and PCMT Surveillance," on November 3,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1 (October 1, 2022, through September 30, 2023)
- (2) Unit 2 (October 1, 2022, through September 30, 2023)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (October 1, 2022, through September 30, 2023)
- (2) Unit 2 (October 1, 2022, through September 30, 2023)
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) NCR 02487303, Unit 1 source range channel 1N32 malfunction, and NCR 02491358, Unit 1 source range channel 1N31 erratic indication, on December 18, 2023
- (2) NCR 02473627, Part 21 for Curtis Wright electrical connectors, on December 21, 2023
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in emergency supplemental power source that might be indicative of a more significant safety issue.
INSPECTION RESULTS
Failure to Resolve Electromagnetic Interference Affecting Unit 1 Source Range Nuclear Instruments Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000369/2023004-01 Open/Closed
[H.5] - Work Management 71152A A self-revealing green finding and associated non-cited violation (NCV) of Title 10 Code of Federal Regulations Part 50, Appendix B, Criterion XVI was identified when the licensee failed to correct deficient conditions associated with intermittent power spikes of Unit 1 source range nuclear instruments 1N31 and 1N32.
Description:
Following installation per engineering change 97370 in 2014, the narrow range source range instruments on Unit 1, 1N31 and 1N32, have experienced repetitive, intermittent power spikes and periods of inoperability during reactor shutdowns with the instruments in the lower decades of their detection range. This condition is evidenced by power indication unexpectedly jumping between one to four decades on a single channel. The licensee identified cause for these spikes is the combination of electromagnetic interference (EMI) and instrument/cabling configuration.
The narrow range source range instruments, 1N31 and 1N32, function for both reactor shutdown monitoring and power level indication for control room operators when reactor power levels are low. Instruments 1N31 and 1N32 also provide input to the source range high neutron flux trip which provides protection during reactor startup and shutdown. Per technical specification (TS) 3.3.1, Reactor Trip System Instrumentation, in modes 3, 4, and 5, with reactor trip breakers (RTBs) closed and the rod control system capable of rod withdrawal, both 1N31 and 1N32 are required to be operable. In modes 3, 4, and 5 with RTBs open and the rod control system not capable of withdrawal, TS 3.3.1 requires one of the two channels to be operable.
Additionally, TS 3.9.3, Nuclear Instrumentation, in mode 6, requires operability of two of the four available source range neutron flux monitors, which includes 1N31, 1N32, or the two additional wide range neutron flux monitors. Prior to October 15, 2023, the intermittent spikes occurred when control rods were not capable of being withdrawn; therefore, the minimum TS required instrumentation were still met with either 1N31 or 1N32 being inoperable.
At the end of a refueling outage in October 2017, the licensee generated an adverse trend nuclear condition report (NCR) 02158084, in which five instances of spikes on 1N32 spanning four years and three instances in 2017 for 1N31 were referenced. NCR 02158084 also identified the jumper connections at each containment penetration as probable sources for EMI coupling for both channels. During refueling outages in 2019, 2022, and 2023, additional power spikes were observed on 1N32. In each instance, the licensee took actions to document the occurrence in the corrective action program and verify the affected instruments operability prior to placing it back into service.
In 2020, vendor troubleshooting was accomplished that supported the previously suspected causes of the unreliable indications. In 2023, the licensee attempted to remove the jumper connections and replace the connections at the penetrations for both instruments with connections that demonstrated improved capability against EMI coupling. The licensee was successful in replacing connections on the annulus side of the penetration, but not the containment side resulting in removal of half of the jumper connections.
On October 15, 2023, operators declared 1N31 inoperable per TS 3.3.1 after observing a power spike during control rod testing in mode 5, when both 1N31 and 1N32 were required to be operable. Following investigation, the licensee identified noisy cabling associated with 1N31 as the source of the power spike. To correct the condition, the licensee swapped the existing cables of 1N31 and 1N35 (the corresponding intermediate range detector) after testing determined it showed less effects of ongoing EMI. After the cable swap, the power spike on 1N31 was not observed and the licensee declared the channel operable.
Corrective Actions: In the short term, the licensee restored operability to 1N31 by swapping the detector cables between 1N31 and 1N35, retested the instrument, and restored operability. The licensee has proposed work orders for modification of detector cabling by eliminating the jumper connections at the containment side of the cable penetration.
Corrective Action References: NCR 02491358
Performance Assessment:
Performance Deficiency: The licensee did not meet 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, when the license failed to correct the deficient condition associated with electromagnetic interference and its' adverse impacts on Unit 1 source range nuclear instrumentation.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the intermittent indicated power spikes for the Unit 1 source range instruments resulted in the inoperability of 1N31 when it was required by TS.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix G, Shutdown Safety SDP. The finding screened to green, as the answers to all questions in Exhibit 3 of Attachment 1 were NO.
Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities.
Enforcement:
Violation: 10 CFR Part 50 Appendix B, Criterion XVI, "Corrective Action," requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, deficiencies, and deviations, are promptly identified and corrected.
Contrary to the above, from October 15, 2017, to October 15, 2023, the licensee failed to correct the condition adverse to quality. Specifically, the known susceptibility of 1N31 to EMI coupling events ultimately led to instrument inoperability during rod testing when channel operability was required by TS.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 6, 2023, the inspectors presented the Unit 1 inservice inspection results to Brent Bare and other members of the licensee staff.
- On January 25, 2024, the inspectors presented the integrated inspection results to Ed Pigott and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Nuclear Condition
Report(s)
2492820, 02492935
Corrective Action
Documents
Resulting from
Inspection
Nuclear Condition
Report(s)
2498473
Drawings
MCFD-1561-
01.00
Flow Diagram of Residual Heat Removal System (ND)
Procedures
OP/1/A/6100/SD-
6A
Placing Train A ND In Service
Calculations
MCC-1206.47-69-
1001
Auxiliary Building Flooding Analysis
Engineering
Evaluations
2465387
Threaded connection with CET Conoseal Plug
Engineering
Evaluations
2466821
Threaded fitting associated with Seal Table
Miscellaneous
NDE Examiner Certification Review
7/23/2023
Miscellaneous
230754
Weld Record: RN 485-7
9/30/2023
Miscellaneous
JL0319
Welder Qualifications
9/01/2022
NDE Reports
180-9348166-000
McGuire Unit-1 (M1R29) RVCH and AHA NDE Final Report
9/27/2023
NDE Reports
291
Magnetic particle examination RN485-7
10/01/2023
NDE Reports
PT-23-002
Liquid Penetrant Examination: Accumulator Injection Line
09/26/2023
Procedures
GTSM0101-01
ASME Section IX Welding Procedure Specification
Drawings
MCFD-1561-
01.00
Flow Diagram of Residual Heat Removal System (ND)
Procedures
OP/1/A/6100/SD-
Draining the NC System
Procedures
OP/1/A/6100/SO-
Maintaining NC System Level
Procedures
OP/1/A/6100/SO-
Draining the Refueling Cavity
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Nuclear Condition
Report(s)
2476511
Engineering
Evaluations
EVAL-2023-MC-
SSF-00002276
(a)(1) Action Plan for standby shutdown facility diesel
generator cylinder 8L fuel injector pushrod failure
Miscellaneous
Maintenance Rule: SSC Summary Sheets - Info Only
Procedures
AD-EG-ALL-1210
Corrective Action
Documents
Nuclear Condition
Report(s)
2492136
Corrective Action
Documents
Resulting from
Inspection
Nuclear Condition
Report(s)
2493895
Drawings
2A1690
Diaphragm Actuated Control Valve
Miscellaneous
Unit 1 eSOMS Narrative Logs
10/25/2023
Miscellaneous
AD-OP-ALL-0210
Operational Risk Mitigation Plan - 1NCLT5170 Calibration
Procedures
AD-WC-ALL-0240
On-line Risk Management Process
Procedures
CSD-WC-MNS-
240-00
McGuire Nuclear Station PRA: ERAT Guidance
Procedures
IP/0/A/3219/016
Setting Throttle Valve Stops
Procedures
IP/0/B/3219/001A
Fisher 3580 and 3582 Valve Positioner Maintenance and
Calibration
Procedures
MCS-1465.00-00-
0015
Design Basis Specification for the Loss of Control Room
System
Work Orders
Work Request(s)
257583, 20257584
Calculations
MCC-1535.00-00-
27
McGuire Unit 1 Pressurizer Level Transmitter Missed
Surveillance
Corrective Action
Documents
Nuclear Condition
Report(s)
2495965, 02496174, 02488969, 1661336, 02482758
Drawings
MCFD-1553-
2.00
Flow Diagram of Reactor Coolant System (NC)
Drawings
MCID-1499-
NC.05
Instrument Detail Pressurizer Level & Pressure (Channels
3&4)
Procedures
IP/1/A/3000/009S
Pressurizer Pressure Protection Calibration Channel III
1NCPT5170
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
IP/1/A/3000/009W
Pressurizer Level Protection Calibration Channel III
1NCLT5170
Work Orders
20636184
Work Orders
Work Request(s)
258193, 20258216
Engineering
Changes
MEVN-1719
Bore and sleeve on packing box on 1SV-1AB
2/20/1989
Corrective Action
Documents
Resulting from
Inspection
Nuclear Condition
Report(s)
2491329
Calculations
MCC-1201.17-00-
0035
Ice Condenser "Error Analysis"
Corrective Action
Documents
Nuclear Condition
Report(s)
2490080
Corrective Action
Documents
Resulting from
Inspection
Nuclear Condition
Report(s)
2498698
Drawings
MC-1753-01.00
Outline & Fabrication Details Diesel Load Sequencing
System Diesel Gen. Load Seq. Pnl. 1DGLSA
Drawings
MC-1753-01.01
Connection Diagram Diesel Load Sequencing System
Diesel Gen. 1A Load Seq. Pnl. 1DGLSA Wiring Section No.
Drawings
MC-1753-01.02
Connection Diagram Diesel Load Sequencing System
Diesel Gen. 1A Load Seq. Pnl. 1DGLSA Wiring Section No.
Drawings
MC-1753-01.03
Connection Diagram Diesel Load Sequencing System
Diesel Gen. 1A Load Seq. Pnl. 1DGLSA Wiring Section No.
& 4
Drawings
MCEE-215-00.21
Elementary Diagram - 4160V Switchgear #2ETB - Diesel
Generator 2B Feeder Breaker (Part 1)
Drawings
MCEE-215-00.36-
Elementary Diagram - 4160 Switchgear #2ETB - Potential
Circuits
Engineering
2777
Document Acceptability of Relay Retaining Clip Installation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
for Struthers-Dunn Series 219 Relays
Miscellaneous
Standards Laboratory Instrument Certification for
MCMNT26545
2/11/2015
Procedures
AD-CP-ALL-0004
Analytical Quality Control Program
Procedures
AD-CP-ALL-0024
Lab Methods
Procedures
IP/0/A/2009/001
Power Cable Inspection and Testing
Procedures
IP/0/A/3090/002
Instrument and Electrical Configuration Control and
Corrective Maintenance
Procedures
IP/0/A/3250/098
Cutler-Hammer Type M Relay and D87 Panel Mount Solid
State Timer Installation
Procedures
LM/M/G236
pH Analysis with Mettler Toledo Seven2Go pro
Procedures
LM/M/P232
Borax Analysis by Mettler T70 Boron Titrator
Procedures
MCM 3.1
Primary Analytical Requirements and Corrective Actions
Procedures
MP/0/A/7600/282
AOV Diagnostic Testing Using Quiklook3 System
Procedures
MP/0/A/7650/261
Component Status Tracking for Equipment Cleared for Work
Procedures
OP/1/A/6350/002
Diesel Generator
138
Procedures
OP/1/A/6450/010
Operation of the Hydrogen Skimmer, Containment Air
Return and Hydrogen Purge Systems
Procedures
PT/0/A/4700/096
NF Ice Bin and PCMT Surveillance
11/03/2023
Procedures
PT/1/A/4350/004A
1A D/G Periodic and Load Sequencer Test
Procedures
PT/1/A/4403/007
RN Train 1A Flow Balance
Procedures
PT/2/A/4350/002B
Diesel Generator 2B Operability Test
20
Work Orders
20552195, 20574849, 20430314, 20540758, 20477522,
20539300, 20545352, 20574695
Corrective Action
Documents
Nuclear Condition
Report(s)
2012438, 2158084, 2254032, 2264595, 2422570, 2424356,
2490811
Engineering
Changes
2311
Removal of Pigtail Jumpers in ENB Channels 1N31/35 &
1N32/36
Work Orders
20084421, 20530026, 20529758