IR 05000324/2024010
| ML24248A206 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/10/2024 |
| From: | James Baptist NRC/RGN-II/DRS/EB1 |
| To: | Krakuszeski J Duke Energy Progress |
| References | |
| IR 2024010 | |
| Download: ML24248A206 (1) | |
Text
SUBJECT:
BRUNSWICK UNITS 1 & 2 - FOCUSED ENGINEERING INSPECTION COMMERCIAL GRADE DEDICATION REPORT 05000324/2024010 AND 05000325/2024010
Dear John A. Krakuszeski:
On August 28, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Units 1 & 2 and 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.
Two findings of very low safety significance (Green) are documented in this report. Two of these findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or the significance or severity of the violations 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 Brunswick Units 1 & 2.
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 Brunswick Units 1 & 2.
September 10, 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, James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000324 and 05000325 License Nos. DPR-62 and DPR-71
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000324 and 05000325
License Numbers:
Report Numbers:
05000324/2024010 and 05000325/2024010
Enterprise Identifier:
I-2024-010-0047
Licensee:
Duke Energy Progress, LLC
Facility:
Brunswick Units 1 & 2
Location:
Southport, N.C.
Inspection Dates:
August 05, 2024 to August 28, 2024
Inspectors:
S. Egli, Sr. Construction Inspector
T. Fanelli, Senior Reactor Inspector
T. Su, Reactor Inspector
Approved By:
James B. Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Focused Engineering Inspection Commercial Grade Dedication at Brunswick Units 1 & 2, 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 Maintain the Quality of Lubricants Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000325,05000324/2024010-01 Open/Closed
[H.3] - Change Management 71111.21N.
The NRC identified two examples of a Green non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion III for the failure to provide objective evidence of shelf life and ensure the quality assurance requirements for lubricants prior to their installation in their final locations.
Failure to Maintain Qualification of Relays Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000325,05000324/2024010-02 Open/Closed
[H.5] - Work Management 71111.21N.
The NRC identified a Green non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion III for the failure to install safety related relays in the configuration that maintained their qualification.
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
71111.21N.03 - Commercial Grade Dedication Commercial Grade Dedication
- (1) Capacitors, CATID 9220128040
- (3) Current Transformer/Diode, CATID 9230036476
- (4) Breakers: (MCCBs), CATID 73751653
- (5) Relay Timing, CATID 9230032214
- (6) Grout/Cement, CATID 9220093400
- (7) Lubricants, Super-O-Lube CATID 73991622
- (8) Lubricants, CATID 9220201439
- (9) Gasket, CATID 69911352
- (10) Thrust Bearing, CATID 73878852
- (11) Pump, CATID
INSPECTION RESULTS
Failure to Maintain the Quality of Lubricants Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000325,05000324/2024010-01 Open/Closed
[H.3] - Change Management 71111.21N.0 The NRC identified two examples of a Green non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion III for the failure to provide objective evidence of shelf life and ensure the quality assurance requirements for lubricants prior to their installation in their final locations.
Description:
The inspection sampled two lubricants for which the manufacturer specified a five-year shelf life if stored at 68°F to 74°F & relative humidity 40-44% (MOV long life and Mobil grease XHP). Brunswick shelf life for lubricants (oils and greases) specified that shelf life was not applicable to any lubricants other than lube oil while stored in American National Standard Institute (ANSI) level B conditions (up to 140°F). The Brunswick Quality Assurance Program (QAP) is based on the criteria developed in ANSI N45.2, Quality Assurance Program Requirements for Nuclear Power Plants, and its criteria sub standards. For the control of purchase material equipment, and services, the QAP requires objective evidence of quality be furnished for purchased items. This required verifiable evidence, verifiable by the inspector. Standard N45.2.2, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants. The General requirements of section 6.1, stated, in part, that levels and methods of storage necessary are defined to minimize the possibility of damage or lowering of quality due to corrosion, contamination, deterioration or physical damage from the time an item is stored upon receipt until the time the item is removed from storage and placed in its final location.
Example 1: Duke Energy performed a corporate shelf-life evaluation. It is documented in Engineering Change (EC) 400765, Generic Shelf-Life Program, Revision 4. The EC specified that the quality of lubricants was not affected by degradation mechanisms prior to placement in its final location. The EC stated, DEPs historical practice of assigning lubricant shelf life per the guidance provided by Tables 1 and 2 below, combined with a lack of failures attributed to lubricant degradation in storage provides reasonable assurance that the current DEP practice is acceptable and shall continue as the acceptable practice for shelf life of lubricants. The table stated in part, No shelf life applicable (except as noted in TABLE 2 below). Table 2 excepted lube oil. The EC did not perform any technical evaluation of the degradation mechanisms (e.g., oxidation, moisture, temperature, and contaminants) to demonstrate that they are not in effect at Duke sites.
The inspectors observed that lubricants stored in the warehouse were degrading. For example, the oils in grease were leaching out and soaking into the containers they were stored in and onto the shelving. This degradation was contrary to the EC as stated above. In addition, the corrective action program (CAP) documented examples of degraded conditions that could be attributed to lubricant degradation and thus it could not be ruled out. Based on the inspector observations and CAP results the EC statement about lubricant degradation in storage was unsubstantiated. The inspectors determined that degraded lubricants could have been used for maintenance because the replacement frequencies were shorter than the specified life of the lubricants.
Example 2: The inspectors noted that, once lubricants were issued from the warehouse to the maintenance department, the quality of the storage conditions were not maintained to ensure the life of the lubricants were not degraded. The maintenance rooms did not have storage locations that were controlled by N45.2.2.
The manufactures of MOV long life and Mobil Grease specified that the established life was approximately five years dependent on if the containers were unopened and stored at around 68°F to 74°F. The inspectors noted that the storage and handling conditions in the maintenance areas were such that the lubricants could degrade further than allowed for by the lubricant specifications. The maintenance personnel did not have guidance to maintain the quality of the lubricants.
The Inspectors found the grease used for safety related components were checked out from the warehouse and stored in other areas of the plant unsealed without proper environmental controls before placement in their final locations i.e. in the components that required their application. Based on the observed degradation and recent degraded equipment examples in the CAP, the inspectors determined this was current licensee performance.
Corrective Actions: The licensee entered the issue into the corrective action program to restore compliance Corrective Action References: CR02526383
Performance Assessment:
Performance Deficiency: The failure to provide objective evidence of shelf life and ensure the quality assurance requirements for lubricants prior to their installation in their final locations was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control 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 engineering changes that failed to evaluate objective evidence of the properties of lubricants (oils and greases) adversely affected the designed reliability of systems that respond to initiating events.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Exhibit 2, A.1, If the finding is a deficiency affecting the design or qualification of a mitigating SSC, does the SSC maintain its operability or PRA functionality? - YES --> GREEN Cross-Cutting Aspect: H.3 - Change Management: Leaders use a systematic process for evaluating and implementing change so that nuclear safety remains the overriding priority.
Leaders did not use a systematic process for evaluating the quality of lubricants over time with objective evidence and implementing that change so that nuclear safety remained the overriding priority.
Enforcement:
Violation: 10 CFR 50 Appendix B, to 10 CFR Part 50, Criterion III, Design Control, requires, in part, that measures shall be established to assure that applicable regulatory requirements and the design basis, as defined in § 50.2 and as specified in the license application, for those structures, systems, and components to which this appendix applies are correctly translated into specifications, drawings, procedures, and instructions. These measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled.
Contrary to the above, since 1995, the site did not provide design control measures to include provisions to assure that appropriate quality standards were specified and included in design documents for evaluating the quality of lubricants and that deviations from such standards for quality lubricants were controlled.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Failure to Maintain Qualification of Relays Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000325,05000324/2024010-02
[H.5] - Work Management 71111.21N.0
Open/Closed The NRC identified a Green non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion III for the failure to install safety related relays in the configuration that maintained their qualification.
Description:
The inspection sampled Allen Bradley 700-RTC relays that were commercial grade dedicated (CGD) by Nuclear Logistics Incorporated (NLI) for the site. The licensing basis required the relays to be qualified to the range of voltage, frequency, load, electromagnetic interference, and other electrical characteristics in accordance with IEEE 323-1974, IEEE Standard-for Qualifying Class 1E Equipment for Nuclear Power Generating Stations. To meet the electromagnetic interference requirement, the CGD used the tests and acceptance criteria in MIL-STD-461G, Requirements for The Control of Electromagnetic Interference Characteristics of Subsystems and Equipment.
Relay qualification report QR-700RTC-1, Rev. 1, identified electromagnetic interference (EMI)during MIL-STD-461G test for conducted susceptibility (test CS114) in the frequency range from 10 kHz - 30 MHz. Specifically, the degraded condition appeared in the range 2.6MHz to 20.3MHz and required the installation of a ferrite bead to mitigate the condition. This made the ferrite bead a required addition to the installed components in the emergency diesel generators (EDGs). The qualification report documents that the relay was successfully retested with input power lines wrapped three turns through a ferrite bead (Fair Rite P/N 0475176451).
Neither the ferrite beads or any other device to filter this noise was installed in the EDGs 700-RTC circuits. The 700-RTC relays are not installed in a qualified condition and are susceptible to failures due to conducted high frequency noise.
Corrective Actions: The licensee entered the issue into the corrective action program to restore compliance.
Corrective Action References: CR2526612
Performance Assessment:
Performance Deficiency: The failure to install safety related relays in the configuration that maintained their qualification was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control 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 failure to install the relays in the qualified condition exposed the EDGs to failures due to high frequency noise affecting the reliability.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Exhibit 2, A.1, If the finding is a deficiency affecting the design or qualification of a mitigating SSC, does the SSC maintain its operability or PRA functionality? - YES --> GREEN 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.
The organization did not implement a process of planning, controlling, and executing work activities to install digital relay that were susceptible to high frequency interference such that nuclear safety is the overriding priority. The work process did not include the identification of different mitigation techniques for different kinds of interference and how that may be used to management the risk of using the relays commensurate with the work and the need for coordination with different groups or job activities
Enforcement:
Violation: 10 CFR 50 Appendix B, to 10 CFR Part 50, Criterion III, Design Control, requires, in part, that measures shall be established to assure that applicable regulatory requirements and the design basis, as defined in § 50.2 and as specified in the license application, for those structures, systems, and components to which this appendix applies are correctly translated into specifications, drawings, procedures, and instructions.
Contrary to the above, since April 2016, the site failed to assure that applicable regulatory requirements and the design basis, for 700-RTC relay circuit installations were correctly translated into specifications, drawings, procedures, and instructions used to ensure the circuits were installed correctly.
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 August 28, 2024, the inspectors presented the Focused Engineering Inspection Commercial Grade Dedication results to John A. Krakuszeski and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.03
Calculations
BNP-E-2.006
Unit 1 480V Vital MCC Calculations
Rev. 22
71111.21N.03
Corrective Action
Documents
Diesel Generator #1 Fuel Injection Leakage
10/27/2006
71111.21N.03
Corrective Action
Documents
2-B32-F023A, 2-B32-F031A, 2-B32-F031B Failed Motor
Inspect
03/26/2009
71111.21N.03
Corrective Action
Documents
2C RHR SW Booster Pump Making Very Loud Noise
When Running
08/26/2010
71111.21N.03
Corrective Action
Documents
2C RHRSW Booster Pump Motor Brg has Oil Weepage
06/18/2015
71111.21N.03
Corrective Action
Documents
2C RHR SW Booster Pump Has a Small Packing Leak
03/10/2021
71111.21N.03
Corrective Action
Documents
1-E41-F004-MO Operator Will Not Go Into Manual Mode
09/23/2021
71111.21N.03
Corrective Action
Documents
Minimum Bend Radius Not Achieved for Some FO and LO
Flex Hoses on EDGs
09/28/2023
71111.21N.03
Corrective Action
Documents
Resulting from
Inspection
Discrepancies in Shelf Life Evaluation and Application
08/22/2024
71111.21N.03
Corrective Action
Documents
Resulting from
Inspection
Relay Installation Not in Conformance With Qualification
Report
08/26/2024
71111.21N.03
Drawings
0-FP-5859
Valve Assembly Con-C-Cap Explosive Actuated
Rev. A
71111.21N.03
Drawings
0-FP-84248
8XI3AD Pump Cross Sectional Dwg
Rev. A
71111.21N.03
Drawings
DW-59310109
Fuel Injection Pump
03/21/1972
71111.21N.03
Engineering
Changes
00000067954
B,EE,Q2,Various,Grease,MOBILGREASE XHP 220
Series, EXXON MOBIL, JH/FS
Rev. 0
71111.21N.03
Engineering
Changes
0000073996
C, EE, Various, Various, Bearing, SKF, JB/JT/LC SKF
Explorer Bearing
Rev. 2
71111.21N.03
Engineering
Changes
0000079457
C, EE, Q2, VARIOUS, GREASE, MOV LONG LIFE,
FORSYTHE/CROMPTON, JT/JB
Rev. 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.03
Engineering
Changes
0000081016
C, CGI, Q2, Various, Lubricants, EXXONMOBIL, WP/MS
Rev. 2
71111.21N.03
Engineering
Changes
0000098353
C, CGI, Various, Bearing, Various Types, MH/JB
Rev. 0
71111.21N.03
Engineering
Changes
400765
Generic Shelf Life Program
Rev. 4
71111.21N.03
Engineering
Changes
C,EE,Q1,9220093400,Masterflow 928 Grout, BASF,
RFH/FS Reduction in Quick Lime Contained in Product
Rev. 0
71111.21N.03
Engineering
Changes
Service Water Intake Structure (SWIS) Repair Project
Rev. 7
71111.21N.03
Engineering
Evaluations
0944 VA20082
Westinghouse Nuclear Parts Audit Package
01/19/2021
71111.21N.03
Engineering
Evaluations
DR-79 EQ
Westinghouse Electric Corporation Report No. 30103-
CCR-4 Environmental Qualification for Nuclear Safety
Related Class 1E Components devices for Replacing
Functionally Equivalent Equipment In the G. E. 7700 Motor
Control Centers,
Rev. 4
71111.21N.03
Engineering
Evaluations
EWR 13462
Use of Loctite PST #580 at Brunswick Nuclear Plant
4/25/1994
71111.21N.03
Engineering
Evaluations
Material
Evaluation
003850.00
09/17/1998
71111.21N.03
Engineering
Evaluations
Material
Evaluation 07646
GREASE, MOV LONG LIFE, Grades 0, 1, 2
07/28/2010
71111.21N.03
Engineering
Evaluations
ME No;
001203.00
Material Evaluation
07/07/1995
71111.21N.03
Engineering
Evaluations
QR-09314565-1
Qualification Report for Time Delay Relays Allen-Bradley
Rev. 1
71111.21N.03
Engineering
Evaluations
QR-700RTC-1
EMI-RFI Qualification Report for Allen-Bradley Relay Mod
Rev. 1
71111.21N.03
Engineering
Evaluations
VVR-700RTC-01
Commercial Grade Dedication Verification and Validation
Report
Rev. 0
71111.21N.03
Miscellaneous
00328626
QC Inspection Report for PO 03083136
2/05/2018
71111.21N.03
Miscellaneous
00333563
QC Inspection Report for PO 03092247
07/17/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.03
Miscellaneous
00338666
QC Inspection Report for PO 03109526
04/07/2020
71111.21N.03
Miscellaneous
00344467
QC Inspection Report for PO 03125422
03/30/2021
71111.21N.03
Miscellaneous
00345522
QC Inspection Report for PO 03126732
05/18/2021
71111.21N.03
Miscellaneous
00346483
QC Inspection Report for PO 03120884
2/01/2021
71111.21N.03
Miscellaneous
238-011
Specification Horizontal Centrifugal Pumps for Service
Water Supply to Residual Heat Removal System
Rev. 7
71111.21N.03
Miscellaneous
27-01-201-1
Specification for Emergency Diesel Generator Sets
Rev. 4
71111.21N.03
Miscellaneous
Design Basis Document for Emergency Diesel Generator
and Supplemental Diesel Generator Systems
2/07/2024
71111.21N.03
Miscellaneous
DBDE-05
Design Basis Document: Standby Liquid Control System
Rev. 16
71111.21N.03
Miscellaneous
EPRI 1019518
Lubrication Guide
Rev. 4
71111.21N.03
Miscellaneous
EPRI NP-6408
Guidelines for Establishing, Maintaining, and Extending the
Shelf Life Capability of Limited Life Items.
Rev. 1
71111.21N.03
Miscellaneous
Technical Manual Valve, Explosive Actuated
Rev. 0
71111.21N.03
Miscellaneous
ME07922R00
Circuit Breakers & Supplementary Protectors Motor Circuit
Protectors
Rev. 0
71111.21N.03
Miscellaneous
Mobile Industrial
Lubricants
Technical Topic
Shelf Life Recommendations for Lubricating Oils and
Greases
2012
71111.21N.03
Miscellaneous
PO 03058272
Grout, Construction, Masterflow 928, Ref. BASF Product
Data Sht Form No 1019303
Rev. 1
71111.21N.03
Miscellaneous
PO 03083136
Lubricant, Grease, MOV Long Life, Grade 1, Tube, 14OZ
11/29/2018
71111.21N.03
Miscellaneous
PO 03092247
Bearing, Trust, 2.7559, 5.90550, 1.3780, Angular Contact,
Ball Bearing
05/09/2019
71111.21N.03
Miscellaneous
PO 03109526
Lubricant, Grease, Mobile Grease XHP 222, TU, 14 OZ
Tubes, 10 Tubes Per Cartoon
03/24/2020
71111.21N.03
Miscellaneous
PO 03110236
Relay, Timing, Solid State (RTC), 0.05-64 Minutes,
20VDC 110/120VAC, 5A, 4
Rev. 1
71111.21N.03
Miscellaneous
PO 03117513
GROUT, CONSTRUCTION, MASTERFLOW 928, REF.
BASF PRODUCT DATA SHT FORM NO 1019303
Rev. 0
71111.21N.03
Miscellaneous
PO 03118288
Sealant, Pipe, Thread, PST-580,
10/07/2020
71111.21N.03
Miscellaneous
PO 03118457
Transformer, Current, 0.333V Output, Input 5A, Split Core
Rev. 1
71111.21N.03
Miscellaneous
PO 03120884
Pump, Injection, Fuel, Diesel, Repairable
04/20/2021
71111.21N.03
Miscellaneous
PO 03125422
Lubricant, Grease, MOV Long Life, Grade 1, Tube, 14OZ
03/15/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.03
Miscellaneous
PO 03126732
Gasket, Ring, 1-1/2 IN, 304SS
04/20/2021
71111.21N.03
Miscellaneous
PO 03167763
CAPACITOR,.., 7300MFD,150VDC
08/26/2023
71111.21N.03
Miscellaneous
PO 3110236
Receipt Inspection Report
08/21/2020
71111.21N.03
Miscellaneous
PO 3110236
Receipt Inspection Report
08/21/2020
71111.21N.03
Miscellaneous
PO
3114719_UTC
30192602
Receipt Inspection Report
01/13/2021
71111.21N.03
Miscellaneous
PO
3114719_UTC
30198086
Receipt Inspection Report
07/07/2021
71111.21N.03
Miscellaneous
PO03114719
Breaker, Motor Circuit Protector, 3 Amp Continuous
Rating, 9-30 Amp Magnetic Trip Range, 600VAC Max,
65,000 Amp Interrupting Current Rating at 480 VAC
Rev. 2
71111.21N.03
Miscellaneous
Purchase Order
(PO) 03114719
Breaker, Circuit, Thermal Magnetic, 600V, 3A,
65KAIC@480V, Non-Aluminum Terminals, 3P
Rev. 0
71111.21N.03
Procedures
Equipment Lubrication Application Guidance and
Lubrication Listing
Rev. 133
71111.21N.03
Procedures
AC and DC Limitorque Motor Operated Valve Preventive
Maintenance Procedure
Rev. 22
71111.21N.03
Procedures
Mechanical Inspection and Lubrication of Limitorque
Operators
Rev. 48
71111.21N.03
Procedures
AD-EG-ALL-1103
Procurement Engineering Products
Rev. 7
71111.21N.03
Procedures
AD-PI-ALL-0400
Operating Experience Program
Rev. 13
71111.21N.03
Procedures
DUKE-QAPD-
001 -A-
Quality Assurance Program Description Operating Fleet
Amendment
71111.21N.03
Procedures
Valve Operators
05/14/2020
71111.21N.03
Procedures
NSCD-282
Shelf Life
Rev. 6
71111.21N.03
Procedures
NSCD-284
Contract and Acceptance of Services
Rev. 15
71111.21N.03
Procedures
NSCD-285
Procurement Process
Rev. 13
71111.21N.03
Procedures
NSCD-285A
Nuclear Sourcing Purchase Order PSG
Rev. 5
71111.21N.03
Procedures
NSCD-410
Receiving
Rev. 10
71111.21N.03
Procedures
NSCG-R-010
Fraud Detection
Rev. 0
71111.21N.03
Procedures
OE 127237
Degraded equipment voltage setpoints will not ensure ESF
operability
07/24/1992
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.03
Procedures
OPT-06.1
Standby Liquid Control System Operability Test
Rev. 90
71111.21N.03
Procedures
OPT-12.2A
No. 1 Diesel Generator Monthly Load Test
Rev. 124
71111.21N.03
Work Orders
11771487 01
2-DG1-ENG: Replace Fuel Injection Pumps
08/23/2022
71111.21N.03
Work Orders
20397473 02
Unit 2A-1 Battery Removal and Replacement
04/08/2021
71111.21N.03
Work Orders
20409476 32
Reassemble Reactor Vessel and The Associated
Components
2/10/2021
71111.21N.03
Work Orders
20410923 01
2-B32-F031A-MO: OPM-0504 Mechanical and Lube
Inspection
03/21/2021
71111.21N.03
Work Orders
20482448 01
1-C41-F004B, Squib Valve Functional
Testing
03/29/2022
71111.21N.03
Work Orders
20568184 01
1-E41-F004-MO, OPM-O504 Mech. and Lube Inspection
06/26/2023
71111.21N.03
Work Orders
20644838 01
1-E11-F004A-MO Perform OPM-MO009 RHR 1A Supp
Pool Suc
07/25/2024