IR 05000424/2014007
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| ML14205A176 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/22/2014 |
| From: | Nease R L NRC/RGN-II/DRS/EB1 |
| To: | Tynan T E Southern Nuclear Operating Co |
| References | |
| IR-14-007 | |
| Download: ML14205A176 (14) | |
Text
July 22, 2014
Mr. Tom Vice President - Vogtle Southern Nuclear Operating Company, Inc.
Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830
SUBJECT: VOGTLE ELECTRIC GENERATING PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000424/2014007 AND 05000425/2014007
Dear Mr. Tynan:
On June 27, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Vogtle Electric Generating Plant, Units 1 and 2, and discussed the results of this inspection with Mr. J. Thomas and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.
The NRC inspectors did not identify any findings or violations of more than minor significance.
In accordance with Title 10 of the Code of Federal Regulations 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if any, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA: Shakur A. Walker for/ Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety
Docket Nos.: 05000424, 05000425 License Nos.: NPF-68 and NPF-81
Enclosure:
Inspection Report 05000424/2014007 and 05000425/2014007
w/Attachment:
Supplementary Information
cc: Distribution via Listserv July 22, 2014 Mr. Tom
SUMMARY
Inspection Report (IR) 05000424/2014007, 05000425/2014007; 06/09/2014-06/27/2014; Vogtle Electric Generating Plant, Units 1 and 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.
This report covers a two-week, on-site inspection by three regional inspectors. No findings or violations were identified. The Nuclear Regulatory Commission's (NRC's) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R17 Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications
a. Inspection Scope
Evaluations of Changes, Tests, and Experiments: The team reviewed six safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, "Changes, tests, and experiments," to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 19 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:
- the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
- the safety issues requiring the changes, tests or experiments were resolved;
- the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
- the design and licensing basis documentation used to support the change was updated to reflect the change. The team used, in part, Nuclear Energy Institute (NEI) 96-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000.
This inspection constituted six samples of evaluations and 19 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04. Permanent Plant Modifications: The team reviewed 10 permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below:
- Design Change Package (DCP) 1060336501, 480-Volt (V) Breakers and 4160/480V Transformer Replacement, Ver. 4.0
- DCP 1081089101, Replacement/Modification of Motor Operators HV8811A/B, Ver. 6.0
- DCP 1102491801, Penetration through Auxiliary Building Roof, Ver. 2.0
- DCP SNC466754, High Efficiency Purge Unit, Ver. 1.0
- Equivalency Determination (ED) SNC366192, Replace G700 Main Steam Isolation Valve (MSIV) packing with Argo 524, Ver. 1.0
- ED SNC438360, Westinghouse 2D82820G02 5-V Direct Current Power Supply, Ver. 2.0
- ED SNC491984, Emergency Diesel Generator Jacket Water Gasket Binder Change from Nitrile Butadiene Rubber (NBR) to Styrol Butadiene Rubber (SBR), Ver. 1.0
- ED SNC128991, Reserve Auxiliary Transformer and Generator Step-up Transformer Lighting Arresters, Ver. 1.0 The modifications were selected based upon risk significance, safety significance, and complexity. The team reviewed the modifications selected to determine if:
- the supporting design and licensing basis documentation was updated;
- the changes were in accordance with the specified design requirements;
- the procedures and training plans affected by the modification had been adequately updated;
- the test documentation as required by the applicable test programs had been updated; and
- post-modification testing adequately verified system operability and/or functionality. The team also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications. Documents reviewed are listed in the Attachment.
This inspection constituted 10 permanent plant modification samples as defined in IP 71111.17-04.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On June 27, 2014, the team presented inspection results to Mr. J. Thomas and other members of the licensee's staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- L. Mansfield, Fleet Design Director
- G. Gunn, Licensing Supervisor
- K. Walden, Licensing Engineer
- J. Wade, Site Design Manager
NRC personnel
- M. Cain, Senior Resident Inspector, Vogtle
- W. Pursley, Resident Inspector (Acting), Vogtle
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Opened
None
Closed
- None
Discussed
None Updated
None
LIST OF DOCUMENTS REVIEWED
10
- CFR 50.59 Evaluations
- C101640301-01, Evaluation to Support Start of Core Offloading in Less Than 100 Hours After Shutdown, Ver. 1.0
- DCP 1060336501, 480-Volt Breakers and 4160/480-Volt Transformer Replacement, Ver. 1.0
- DCP SNC142974, Spent Fuel Cask Bridge Crane Replacement, Ver. 3.0
- DCP SNC466754, High Efficiency Purge Unit, Ver. 1.0 DCP SNC517148, Replacement of Seal Injection Filter System with Sub-micron Filter System, Ver. 3.0
- 10
- CFR 50.59 Screenings Design Change Package (DCP)
- 1051971501, Replace Reactor Coolant System Wide Range Pressure and Reactor Vessel Level Instrumentation System Barton Transmitters with Rosemount, Ver. 3.0
- DCP 1061091101, Loop 1 Residual Heat Removal Bypass Tie-back Support and Check Valve Modification, Ver. 1.0
- DCP 1062305601, Class 1E Battery Charger Repl. 1AD1CA, 1AD1CB, 1CD1CA & 1CD1CB, Ver. 2.0
- DCP 1070199801, Inverter 1CD1I5, 1DD1I6 & 1ND3I4 Replace, Ver. 1.0
- DCP 1070970501, Rotor 4 Limit Switch Setpoint Increase for 1HV3548, Ver. 1.0
- DCP 1081089101, Replacement/Modification of Motor Operators HV8811A/B, Ver. 1.0
- DCP 1101017401, Reduce Reactor Coolant System Full Load Average Temperature, Ver. 1.0
- DCP 1102491801, Penetration Through Auxiliary Building Roof, Ver. 2.0
- DCP 2019002201, Removal of Portions of the Post-Accident Sampling System, Ver. 3.0
- DCP 2051767701, Electrical Penetration Assembly Circuit Breaker Replacement, Ver. 2.0 DCP
- C029000201, Upgrade Fire Detection, Ver. 1.0 DCP
- C100867701, Aux./Fuel Handling Bldg. Design Interface Analysis & Modifications, Ver. 4.0 Licensing Design Change Request (LDCR)
- 2012015, Diesel Generator and Engineered Safety Features Actuation Systems Test Surveillance Interval, Ver. 1.0 Minor Design Change (MDC) SNC127126, Pipe Break Room Protection 1FT15212A, Ver. 1.0
- MDC SNC331429, Change MSIV Nitrogen Pressure Switch (1PSH3026B & 1PSHH3026B), Ver. 1.0 MDC SNC342049, Nuclear Service Cooling Water Motor Cooler Line Modification, Ver. 1.0
- MDC 2081617501, Molded Case Circuit Breaker Replacement for 2ABA, Ver. 1.0
- Licensing Bases Documents Commitment SNC3365 (2002360917), High Energy Line Break Isolation Sensors Surveillance Frequency Control Program, Surveillance Test Interval List, Rev. 3
- Surveillance Frequency Control Program, Surveillance Test Interval List Bases, Rev. 3
- Technical Requirements Manual, Current Technical Specifications and Bases, Current Updated Final Safety Analysis, Current
Calculations
- AX6AA06-20029, Summary of Weak Link and Seismic Evaluations of the Westinghouse 14GM74FEH at Vogtle Units 1 and 2, Ver. 1.0
- Attachment
- MC-V-07-0048, Life for Rosemount Pressure Transmitters (X4AJ07 and X5AD04), Rev. 8
- MC-V-07-0051, Containment Minimum Flood Level Due to a LOCA, Ver. 2.0
- MC-V-07-0251, Refueling Water Storage Tank Volume, Setpoints, and Operator Time Requirements for ECCS Pump Suction, Ver. 2.0
- MC-V-08-0049, Emergency Core Cooling Pumps Suction Line Losses and NPSH, Ver. 1.0MC-V-09-0037, Control Building - Category 1 Equipment Supports - Level B, Ver. 2.0
- MC-V-10-0147, PAS Monitoring System 2702, Ver. 1.0
- MC-V-10-0148, Hydrogen Recombiner and Monitoring System, Ver. 1.0
- MC-V-11-0038, Auxiliary Building Analysis for Tornado, Ver. 1.0
- MC-V-11-0039, Auxiliary Building Level '4' Roof Slab, Ver. 1.0
- X2CK04.08.41, CVCS Seal Injection Filter Chamber Load Drop Evaluation, Ver. 1.0
- X4C1204V01, Emergency Core Cooling Pumps Suction Line Losses and NPSH, Ver. 7.0
- X4C1592S00F1, Failure Modes and Effects Analysis, Rev. 3 X4CPS-0030, Evaluation of Tie-Back Pipe Supports for 4", 6", & 8" Clamps, Rev. 3 X5CP01310, RVLIS Instrument Uncertainty, Ver. 1
- X6JH.27, Reactor Vessel Level Instrumentation Transmitter Panel Doses, Rev. 2
- Corrective Action Documents Technical Evaluation (TE)
- TE285547, NSCW motor cooling piping specification and classification drawing clarification
- TE824523, Implement LDCR
- 2014012 Ver. 1.0 per DCP SNC517148
Condition Report (CR)
- 2006112975, 1HV3548 failed stroke time due to dual light indication for greater than 20 seconds
- CR 350827, NSCW motor cooling piping specification and classification drawing clarification CR13797 -
- 2009105986, Found plastic cover for EMAX Breaker 1AB15-01 to be damaged at upper mounting screws
- CR2006101340, Leakage found on 2HV8701B bypass line welds
- CR2006103407, Pressure boundary leakage identified from bypass line around 2HV8701B
- CR2006109758, Leak on NSCW discharge bypass line around vent valve
- 1-1202-X4-A16
- CR2008101980,
- NRC-Identified finding for inadequate differential pressure assumption for the containment sump motor operated valves 1/2HV8811A/B
- CR165654
- CR166207
- CR355814
- CR395556
- CR494415
- CR496282
- CR526498
- CR726723
Procedures
- 12004-C, Power Operation (Mode 1), Ver. 109
- 213-1, Backflushable Filter System, Ver. 42.1
- 20003-C, Control of Erecting, Modifying, and Disassembling Scaffolding, Rev. 34.1 28480-C, 480V "EMAX" Breaker Maintenance, Ver. 30.1 93713-C, MPC Fuel Loading Operations, Ver. 4.0
- NMP-AD-008, Applicability Determinations, Ver. 17.1
- NMP-AD-010, 10
- CFR 50.59 Screenings and Evaluations, Ver. 13.0
- NMP-AD-012, Operability Determinations and Functionality Assessments, Ver. 12.3
- NMP-ES-034, Equivalency Determinations, Ver. 15.0
- NMP-ES-041, Minor Design Change Packages, Ver. 11.0
- NMP-ES-044, Preparation of Design Change Packages (DCPs), Ver. 13.0
- NMP-MA-014, Post Maintenance Testing, Ver. 1.1
- Attachment Completed Procedures: 14850-2, Cold Shutdown Valve Inservice Test, Rev. 45 completed 3/10/13 and Rev. 46 completed 3/29/13
- 14880-1, Cold Shutdown Valve Inservice Test, Rev. 54.1 completed 3/16/14 and completed 4/2/14
- Design Criteria (DC) Documents
- DC-1007, Environment - Interdiscipline, Ver. 34
- DC-1202, Nuclear Service Cooling Water (NSCW) System, Ver. 13
- DC-1213, Spent Fuel Pool and Purification System, Ver. 6.0
- DC-1806, Class 1E DC System, Ver. 13
Drawings
- 1K3-1205-003-01, Residual Heat Removal - Fab. Isometric - Aux. Bldg Area 3E & 3G Lvl D, Rev 33 1K5-1202-512-01, Nuclear Service Water System (NSCW) Fabrication Isometric - Tower and Pumphouse Building Area 7E, Ver. 11.0 1K5-1202-516-01, NSCW Fabrication Isometric - Tower and Pumphouse Building Area 7F, Ver. 12.0 1K7-1205-027-01, Residual Heat Removal - Fabrication Isometric - Fuel Handling Building Area 3D Level C, Rev 15 1X1D08H029, Auxiliary Building Level 4 Architectural Penetration Seal Floor El. 288'-2", Ver. 1.0 1X3D-BD-E03F, Elementary Diagram - Residual Heat Removal System 1HV-8811A, Rev. 9 1X4AN06-00016, Seal Water Injection Backflushable Filter, 3/7/1984 1X4AR17-00196 - 00198, Main Steam Isolated Valves, List of Material, Rev. 6, dated 1/23/13
- 1X4DB122, P&ID - Residual Heat Removal (System No. 1205), Ver. 51.0
- 1X4DB122, P&ID - Residual Heat Removal System (System No. 1205), Ver. 51.0
- 1X4DB133-1(2), P&ID - Nuclear Service Cooling Water System (System No. 1202), Ver. 54.0(64.0) 1X4DB148-3, Pipe and Instrumentation Diagram (P&ID) - Seal Water Injection Cartridge Filter (System No. 1208), Ver. 2.0 1X4DB148-4, P&ID - Seal Water Injection Cartridge Filter (System No. 1208), Ver. 1.0
- 1X4DE323, Auxiliary Building Unit 1 Equipment Layout Level B, Ver. 23
- 1X4DK 001-087, Safety-related MOV setpoint data sheet for 1HV 3548, Rev. 9.0
- 1X4DK001-199, Safety-related MOV setpoint data sheet for 1HV8811A, Rev. 6.0 1X4DK001-201, Safety-related MOV setpoint data sheet for 1HV8811B, Rev. 6.0 1X6AA06-20031-1(2), Motor Operated Gate Valve Mod 14002GM84FEH010
- SB-2-60-Actuator, Ver. 1.0(2.0) 2X4DB133-1(2), P&ID - Nuclear Service Cooling Water System (System No. 1202), Ver. 54.0(53.0) 2X4DK 001-088, Safety-related MOV setpoint data sheet for 2HV 3548, Rev. 6.0 2XDB110, P&I Diagram Post Accident Sampling System, Ver. 24
- AX2D08A150, Auxiliary Building Area B1, B2, C1, C2 Roof Plan El. 288' -2", Ver. 5.0
- AX2D08F133, Auxiliary Building Area 3B2, 3B1, 3C2, 3C1 Steel Framing Plan at El. 288' -2", Ver. 2.0 AX4DE501, Spent Fuel Cask Bridge Crane Clearance and Hook Travel Envelope Plan View, Ver. 1.0 SNC517148M013, Seal Injection Housing Filter, Ver. 3.0
- V1-1202-512-H603, Pipe Support Assembly, Ver. 1.0
- V1-1202-516-H603, Pipe Support Assembly, Ver. 1.0
- Attachment Miscellaneous Documents 2X4AW05A-20019, Containment Sump Passive Strainer Sys. S0100 Hydraulic Sizing Report, Ver. 1.0 2X4AW05A-20020, Summary Report for Impact of Chemical Effects for Vogtle 2, Ver. 1.0 American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, 1974 edition,Section III, Subsection
- NC-7000, "Protection Against Overpressure" ASM Handbook, Volume 1, Properties and Selection: Irons, Steels, and High-Performance Alloys
- AX3AC02B-20015, Seismic and Environmental Qualification Test Report ABB RMAX Low Voltage Power Replacement Circuit Breakers with ABB/SACE Digital Protective Relay PR112/P-A, Ver. 1.0 AX3AC02B-20017, ANSI Qualification Report - ABB RMAX Circuit Breaker, Ver. 1.0 AX3AC02B-20021, Qualification of the ABB PR112 Digital Overcurrent Trip Device for Use on the Southern Nuclear Company EMAX Low Voltage Breakers, Ver. 1.0 AX3AC02B-20023, PR112/P SW Quality Document, Ver. 1.0 AX3AC02B-20032, Westinghouse Test Report
- WCAP-16531-P January 2006, Ver. 1.0
- AX4AL03A-00024, Spent Fuel Cask Bridge Crane 125/15 Ton Top Running SFP Trolley NUREG 0554/0612 Compliance Safety Analysis Report, Ver. 1.0 AX5AD04-00061, Qualification Report for Rosemount 1153 Pressure Transmitters, Ver. 7.0
- CAR 209987, Root Cause Analysis for U2 Automatic Reactor Trip on Low Steam Generator Level CX5DT1102-01, EOP Setpoint Document, Ver. 1
- DCP 1062305601, Class 1E Battery Charger Repl. 1AD1CA, 1AD1CB, 1CD1CA & 1CD1CB, Ver. 5.0
- DCP 1102491801, Penetration through Auxiliary Building Roof, Ver. 3.0
- DCP 2051646601, Unit 2 Containment Sump Screen Replacement, Ver. 8.0 Documentation of Engineering Judgment (DOEJ)-VDC1 00867701-M007, Evaluation of the Boron Concentration in Cask Loading Pit after Addition of Demineralized Water for Dry Cask Storage Operations, 6/17/13
- DOE-HTGR-88106, Metal Design Handbook, Rev. 0
- DOEJ-SC-1051971501-001, Seismic Evaluation of Replacement Transmitters for the RVLIS System at Plant Vogtle Unit 1, Ver. 2
- DOEJ-VD1062305601-M001, HVAC/Heat Load Evaluation for Battery Charger Replacement, Ver. 1.0
- DOEJ-VD2019002201-C001, Pipe Support Evaluation for Unit 2 Post-Accident Sampling System (PASS) Removal, Ver. 1.0
- DOEJ-VD2019002201-S001, Pipe Support Evaluation for Unit 2 Post-Accident Sampling System (PASS) Removal, Ver. 1.0
- DOEJ-VD2081089201-M001, Evaluation of Effect on Increased Stroke Time of Containment Sump Suction Valves on Plant Vogtle Required Operator Response Times for DCPs
- 2081089201 and
- 1081089101, Ver. 1.0
- DOEJ-VD-SNC466754-J001, Documentation of Engineering Judgment: EMI/RFI Evaluation of Trane Purge Unit Model PRGCA011BG0B
- DOEJ-VRC101640301, Units 1/2 Spent Fuel Pool Decay Heat Evaluation for 90-Hour Fuel Offload EPRI
- TR-106439, Guideline on Evaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Applications, dated October 1996
- Attachment EQ3489, Change Package for EQDP X5AD07 for changes to 1FT15212A EQ3490, Change Package for EQDP X5AD04 for changes to 1FT15212A
- EQDP X3AC03,
- EQ-3179, 480 Volt Motor Control Centers Qualification Package, Rev. 8 EQDP X3AD02,
- EQ-3183, 125 Volt Motor Control Centers Qualification Package, Rev. 4 EQDP X6AA15, Point Specific Radiation Level for Vogtle Auxiliary Building Mirror Image Rooms: Unit 1 8RB04 and 8RB125
- FMEA-VD-SNC466754-M001, Failure Modes Effects Analysis: High Efficiency Purge Unit Repl. LDCR
- 2010058, Reduction of Decay Time for Core Offload to 90 Hours, Ver. 1.0
- LDCR
- 2011057, Spent Fuel Cask Bridge Crane Replacement, Ver. 2.0
- Letter from Joe Curci, Kingsbury, Inc. Engineering Development Manager, to D'Andre Manigo, Southern Nuclear Co. (Vogtle Plant), Thermal analysis for NSCW motor coolers, dated 8/19/2012 Licensing Document Change Request (LDCR)
- 2014012, Unit 1 Replacement of Seal Injection Filter System with Sub-micron Filter System, Ver. 1.0
- TR-102348, Rev. 1)
- NEI 04-10, Risk-Informed Technical Specifications Initiative 5b - Risk-Informed Method for Control of Surveillance Frequencies (Industry Guidance Document), Rev. 1 (April 2007)
- NL-07-2168, License Amendment Request to Revise Technical Specifications (TS) 3.3.2, "ESFAS Instrumentation," and TS 3.5.4, "Refueling Water Storage Tank (RWST)"
- NUREG-0554, Single-Failure Proof Cranes for Nuclear Power Plants, May 1979
- NUREG-0612,Control of Heavy Loads at Nuclear Power Plants, January 1980
- Reference Manual #00809-0100-4302, "Rosemount 1153 Series B", Rev. BA (January 2008) Report No. 07-MT-009, Root Vent Valve Failure Analysis, February 2007 Report Q1304.2, QualTech NP Fault/Failure Mode Test Report for Trane Purge Unit
- RER
- C101640301-01, Eval. to Support Start of Core Offloading in Less than 100-Hrs After Shutdown RER No.
- C071256501, Joint Owners Group Periodic Verification (JOG PV) Program - Finalize JOG MOV Calculations for Unit 2 Gate Valves to be modified in 2010, Sequence No.1 Surveillance Test Interval Eval. No.
- 417332, Train A(B) Diesel Generator and ESFAS Test, Rev. 0 Vogtle Unit 1 Cycle 17 Reload Evaluation, Ver. 1.0
- Westinghouse Correspondence
- GP-18009 - "Westinghouse Recommendations for Unit 1 RHR Bypass Line During 1R13", dated September 22, 2006 Westinghouse Correspondence
- GP-18471, Rev. 1 - "Transmittal of RHR Bypass Line and Support Re-Design", dated March 18, 2009 Westinghouse Correspondence
- GP-18952, "Transmittal of Summary of the Hot Full Power and Hot Zero Power Feedwater Malfunction Event Analyses for the Vogtle Units 1 and 2 Digital Feedwater Control System Malfunction and Input to the 50.59," dated August 29, 2012 Westinghouse Correspondence
- GP-19146 - "Transmittal of
- LTR-SEE-III-13-256 'Vogtle Units 1 and 2 Seal Injection Filter Internals Evaluation", dated December 4, 2013 Worksheet 2019002201M018, P&I Diagram Post Accident Sampling System, Ver. 1.0
- Worksheet No.: 1051971501J001, Ver. 7
- X2CK04.00.04.01, Auxiliary Building Roof Steel Hatch Design at El. 288'-2", Ver. 2.0
- X2CK04.57.01, Design of Supporting/Rigging Structure for Cutting Opening at Auxiliary Building Level '4' Roof, Ver. 1.0 X3AD01B, Specification for Battery Chargers - Control Building, Ver. 2.0
- Attachment Work Orders
- 1060336506, 1NB29 Transformer Functional Test
- SNC 322586, Auxiliary Building Functional Test
- SNC 343345, 1AD1CA Output Breaker Test
- SNC 343354, 1AD1CA Calibration Functional Test
- SNC 348077, 1AD1CA / 1AD1CB Load Share Functional Test
- SNC121346, Fabricate/Install tie-back support
- SNC121347, Fabricate/Install tie-back support
- SNC122062, Perform Viper Test on Valve 1HV8811B SNC122063, 1HV8811B Functional Test SNC122989, Cask Crane Functional Test
- SNC127120, 1801-T3ORA-A RAT Lightning Arrestors
- SNC127121, 1802-T3M1A - Replace Lightning Arrestors
- SNC127122, 1802-T3M1B - Replace Lightning Arrestors SNC127123, 1802-T3M1C - Replace Lightning Arrestors SNC127124, 1802-T3M1S - Replace Lightning Arrestors
- SNC137488, 1801-T3ORA-2A RAT Replace Lightning Arrestors
- SNC363461, 1205 1HV8811A Viper Test per DCP SNC122053
- SNC363462, 1205 1HV8811A Functional Test per DCP SNC122053
Condition Reports
generated as a result of the inspection
- CR832290, NRC Mods Inspection Observation