Code Reconciliation
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Code Reconciliation Beaver Valley
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Code Reconciliation Calvert Cliffs
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Code Reconciliation FitzPatrick
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Code Reconciliation Ginna
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Code Reconciliation Hope Creek
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Code Reconciliation Indian Point
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Code Reconciliation Limerick
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Code Reconciliation Millstone
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Code Reconciliation Nine Mile Point
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Code Reconciliation Peach Bottom
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Code Reconciliation Salem
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Code Reconciliation Seabrook
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Code Reconciliation Susquehanna
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NRC Region 1 false
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Code Reconciliation Haddam Neck
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Code Reconciliation Maine Yankee
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Code Reconciliation Oyster Creek
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Code Reconciliation Pilgrim
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Code Reconciliation Saxton
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Code Reconciliation Shoreham
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Code Reconciliation Three Mile Island
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Code Reconciliation Vermont Yankee
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Code Reconciliation Zion
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NRC Region 1 true
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Code Reconciliation Browns Ferry
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Code Reconciliation Brunswick
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Code Reconciliation Catawba
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Code Reconciliation Farley
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Code Reconciliation Harris
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Code Reconciliation Hatch
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Code Reconciliation Lee
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Code Reconciliation McGuire
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Code Reconciliation North Anna
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Code Reconciliation Oconee
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Code Reconciliation Robinson
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Code Reconciliation Saint Lucie
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Code Reconciliation Sequoyah
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Code Reconciliation Summer
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Code Reconciliation Surry
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Code Reconciliation Turkey Point
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Code Reconciliation Vogtle
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Code Reconciliation Watts Bar
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NRC Region 2 false
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Code Reconciliation Crystal River
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NRC Region 2 true
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Code Reconciliation Braidwood
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Code Reconciliation Byron
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Code Reconciliation Clinton
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Code Reconciliation Cook
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Code Reconciliation Davis Besse
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Code Reconciliation Dresden
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Code Reconciliation Duane Arnold
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Code Reconciliation Fermi
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Code Reconciliation LaSalle
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Code Reconciliation Monticello
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Code Reconciliation Palisades
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Code Reconciliation Perry
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Code Reconciliation Point Beach
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Code Reconciliation Prairie Island
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NRC Region 3 false
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Code Reconciliation Kewaunee
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Code Reconciliation La Crosse
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NRC Region 3 true
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Code Reconciliation Arkansas Nuclear
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Code Reconciliation Callaway
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Code Reconciliation Columbia
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Code Reconciliation Comanche Peak
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Code Reconciliation Cooper
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Code Reconciliation Diablo Canyon
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Code Reconciliation Grand Gulf
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Code Reconciliation Palo Verde
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Code Reconciliation Quad Cities
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Code Reconciliation River Bend
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Code Reconciliation Waterford
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Code Reconciliation Wolf Creek
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NRC Region 4 false
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Code Reconciliation Fort Calhoun
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Code Reconciliation Fort Saint Vrain
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Code Reconciliation Hallam
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Code Reconciliation Humboldt Bay
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Code Reconciliation Rancho Seco
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Code Reconciliation San Onofre
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Code Reconciliation Trojan
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NRC Region 4 true
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Code Reconciliation Shippingport
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Code Reconciliation Yankee Rowe
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Code Reconciliation Parr
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Code Reconciliation Big Rock Point
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Code Reconciliation Elk River
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Code Reconciliation South Texas
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Code Reconciliation Sundesert
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Code Reconciliation Victoria
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Code Reconciliation 10
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Code Reconciliation Clinch River
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Code Reconciliation Kemmerer
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LIC-13-0164, Integrated Report to Support Restart of Fort Calhoun Station and Post-Restart Commitments for Sustained Improvement
LIC-13-0099, Plan for Sustained Improvement, Revision 0
ULNRC-05998, Response to Request for Additional Information License Amendment Request to Revise the Licensing Basis for Seismic Design as Described in the FSAR-SP Union Electric Company Callaway Plant, Unit 1
RS-12-075, Response to Request for Additional Information Regarding Relief Request 14R-19 and Additional Followup Question on the Flaw Evaluation
3F0412-04, Response to Request for Additional Information to Support NRC Mechanical and Civil Engineering Branch (Emcb) Technical Review of the CR-3 Extended Power Uprate LAR
NL-11-1542, Response to NRC Request for Additional Information, Proposed Alternative FNP-ISI-ALT-11, Version 1.0
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 7, Instrumentation and Controls
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 7, Table of Contents
RS-14-128, LaSalle, Units 1 & 2, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 20
LR-N10-0445, Response to NRC Request for Additional Information Related to 1) the Use of the Westems Program in Metal Fatigue Analysis, and 2) Confirmation of Environmental Fatigue Locations, Associated with License Renewal Application
NRC 2010-0195, License Amendment Request 261 Extended Power Uprate Response to Request for Clarification
NRC 2010-0189, License Amendment Request 261, Extended Power Uprate Response to Request for Clarification
NRC 2010-0186, License Amendment Request 261 Extended Power Uprate, Response to Request for Clarification
NRC 2010-0136, License Amendment Request 261 Extended Response to Request for Additional Information
NRC 2010-0086, License Amendment Request 261 Extended Power Uprate, Response to Request for Additional Information
NRC 2010-0085, License Amendment Request 261 Extended Power Uprate Response to Request for Additional Information
NRC 2010-0069, License Amendment Request 261 Extended Power Uprate Response to Request for Additional Information
M091103, M091103B - Transcript Briefing on Fire Protection Lessons Learned from Shearon Harris
JAFP-07-0019, License Renewal Application, Amendment 9
BSEP 06-0006, Response to Request for Additional Information Regarding Relief Request RR-36, Use of Ultrasonic Examinations in Lieu of Radiographic Non-Destructive Examination
RS-19-098, Submittal of Revision 15 to Updated Final Safety Analysis Report, and Revision 24 to Fire Protection Report
BSEP 05-0100, Relief Request RR-36, Use of Ultrasonic Examinations in Lieu of Radiographic Non-Destructive Examinations
RAIO-0218-58662, LLC Supplemental Response to NRC Request for Additional Information No. 67 (Erai No. 8883) on the NuScale Design Certification Application
L-2004-148, Inservice Inspection Plan Third Ten-Year Interval Relief Requests 6 and 7
LR-N04-0034, Relief Request S1-RR-W02, Proposed Alternative Repair Method for Reactor Vessel Head Penetrations
RS-03-115, Additional Information Regarding Request for License Amendment Related to Heavy Loads Handling
JAFP-03-0065, Summary of Plant Changes, Tests, & Experiments for 2001/2002 as Required by 10 CFR 50.59 & 10 CFR 72.48, & Summary of Commitment Changes for 2001/2002
NRC-97-0006, Forwards Response to Request for Info Per 10CFR50.54(f) Re Adequacy & Availability of Design Bases Info
NL-21-1060, Units 1 and 2, Response to Request for Additional Information Related to License Amendment Request to Allow Elimination of the Encapsulation Vessels Around the First Containment Spray (CS) and Residual Heat Removal .
1CAN109502, Forwards 10CFR50.59 Summary Rept for 1994,containing Brief Description of Changes in Procedures & in Facility as Described in SAR
RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10
L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld
1CAN019010, Forwards Schedule for Completion of Actions in Response to App a & B Items Noted in Insp Rept 50-313/89-200,per NRC Bulletins 79-02 & 79-14
BW190014, Submittal of Inservice Inspection Summary Report
L-97-287, Verifies That Containment Structural Integrity & Containment Leakage Rates Are Acceptable by TS SRs 4.6.1.6 & 4.6.1.2, Respectively.Next Periodic ILRT Is Due Before May 2003. Basis of Util Decision Encl,For Info
W3F1-2010-0019, Request for Amendment to Technical Specification Table 3.4-1 Isolation Valve Addition
RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds
L-25-024, 10 CFR 50.55a Request BV-ISI-2025-01, Quench Spray Pinhole Leak
PNP 2025-003, License Amendment Request to Revise Selected Permanently Defueled Technical Specifications to Support Repairing of Steam Generator Tubes by Sleeving
RA-25-0200, Subsequent License Renewal Application Supplement 1