SCH16-003, Discharge Monitoring Report December 2015
PLA-2756, Forwards Postulated Pipe Rupture Calculations M-MSS-010 & M-MSS-006,per NRC 861112 Telcon Request
L-PI-14-043, Independent Spent Fuel Storage Installation, 2013 Annual Radiological Environmental Monitoring Program (REMP) Report
L-12-399, Submittal of Contractor Root Cause Assessment Report
NL-11-2032, D. R. Madison Ltr. Edwin I. Hatch, Appeal to the Executive Director of Operations: Backfit and Applicability of Compliance Backfit Exception
NL-11-0449, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))
NL-11-0255, Outage Inservice Inspection Summary Report
ULNRC-05893, Callaway, Unit 1, Enclosure 21 to ULNRC-05893 - Callaway 2008 Air Emission Report
L-2009-227, Request to Renew Industrial Wastewater Facility Permit
ULNRC-06455, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00334
SCH07-004, New Jersey Pollutant Discharge Elimination System Discharge Monitoring Report
BVY 07-003, Email: (PA-LR) Vermont Yankee Nuclear Power Station License Renewal Commitment List, Rev. 5
L-PI-06-037, Annual Radiological Environment Environmental Monitoring Program (REMP) Report
L-2006-131, Wastewater Permit Number FL0001562, Request for Minor Revision Notification
L-PI-05-012, Request for Relief No. 17, Revision 0, for the Plant 3rd 10-year Interval Inservice Inspection Program
LR-N04-0361, Response to Second Request for Additional Information for LCR-H03-07 Request for Change to Technical Specifications Emergency Diesel Generator (EDG) Surveillance Testing
NRC 2003-0025, Supplement to Generic Letter 96-06 Resolution
NSD-NRC-97-5285, Forwards W Revised Response to NRC RAI Re AP600 Shutdown PRA & Surge Line Flooding
B12002, Forwards Probabilistic risk-based Fire Analysis of internally-initiated Events.Fire Analysis Documented as Chapter 6 of Probabilistic Safety Study.W/Nine Oversize Encls
2CAN039204, Application for Amend to License NPF-6,revising TS 4.4.5 to Allow Installation of Tube Sleeves as Alternative to Plugging Defective SG Tubes.Encl Rept 51-1212539-00 Withheld
BYRON 2023-0002, Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements
CY-98-044, Provides Info on Beyond Design Basis Event of Loss of Water from Spent Fuel Pool at Plant Per NRC RAI
NG-98-0531, Forwards Comments on NRC Draft SE for DAEC Conversion to Improved TS Based Upon NUREG-1433.Draft SE Contains Util Markups & Typed Inserts
05000295/LER-1986-041, :on 861118,portable Particulate/Iodine Continuous Air Sampler Found Inoperable.Caused by Personnel Error.Sampler Relocated to Locked Caged Area in Turbine Bldg
05000373/LER-1986-036-01, :on 860521,snubber Functional Tests Confirmed 104 safety-related Snubbers Failed to Meet Test Acceptance Limits.Cause of Each Failure Determined & Listed.Corrective Actions Implemented from 860521-0829
NRC-89-3448, Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS
05000295/LER-1987-002-04, :on 870112,eddy Current Field Rept Revealed That Steam Generator 1D Classified as Category C-3 in Tech Spec Due to 38 Tubes Being Defective.Caused by Intergranular Attack & Antivibration Bar Wear.Tubes Sleeved
05000414/LER-1988-010-01, :on 880203,during NRC Equipment Qualification Insp,Damaged RHR Sys Rotork Electric Motor Operated Valve Actuator Discovered.Caused by Improper Installation of Motor to Actuator on Valve 2ND2A.Valve Repaired
05000278/LER-1985-019-02, :on 851116,RWCU Sys Isolated on Unexpected High Temp Signal.Caused by Instrument Technicians Troubleshooting Wrong Temp Element on RWCU sys.TE-3-12-98 Leads Reconnected & RWCU Reset
NSD-NRC-97-5079, Forwards AP600 SSAR Markups That Identify Changes Required to Implement Isolation Requirements for Normal Residual Heat Removal Sys
05000341/LER-1985-007, :on 850423,24 & 25,Tech Spec 3.3.7.11.b Violated Due to Grab Samples Not Taken within Required 8 H Period When Radiation Monitor Inoperable.Caused by Personnel Error.Personnel Counseled.Procedure Written
05000364/LER-1984-006-01, :on 840519,diesel Generator 2B Tripped on High Jacket Water Temp.Review Revealed Generator Output Breaker Would Not Open If Trip Followed Nonemergency Test Start. Design Implemented to Correct Condition
05000366/LER-1983-062-03, /03L-0:on 830720 & 25,core Max Fraction of Limiting Power Density Exceeded Fraction of Rated Thermal Power.Caused by Peaks in Core Flux.Average Power Range Monitor Adjusted
05000280/LER-1978-028-03, /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled
05000366/LER-1982-073-03, /03L-0:on 820716,core Max Fraction of Limiting Powder Density Found Greater than Fraction of Rated Thermal Power.Caused by Rod Withdrawals in Areas of Low Xenon Concentration.Average Power Range Monitor Adjusted
05000366/LER-1982-111-03, /03L-0:on 820918,shift Technical Advisor Ran P-1 (Periodic Core Performance Log) W/O Benefit of OD-1 (Low Power Range monitor).P-1 Indicated Frtp of 0.627 & Core Max Fraction of Limiting Power Density of 0.653
05000278/LER-1990-008-02, :on 900727,offgas Recombiner Isolation Occurred Causing Main Condenser Vacuum to Begin Decreasing.Caused by Component/Sys Failure in Offgas Recombiner Condensate Sys. Design of Sys Will Be Evaluated for Root Cause
05000413/LER-1989-027, :on 891120,Tech Spec Required Unit Shutdown Due to Inoperable Chemical & Vol Control Centrifugal Pump.W/
PLA-1082, Forwards Amend 46 to OL Application,Including Revision K to Security Plan.Plan Revision Withheld (Ref 10CFR2.790)
05000313/LER-1982-001-03, /03L-0:on 820112,RCS Leak Rate Calculation Indicated Leak Rate of 1.433 Gpm from Flange for Vent Line for Reactor Coolant Pump P32C Seal Cavity Pressure Sensing Line.Caused by Loose Flange Bolts
05000335/LER-1981-055-03, /03L-0:on 811219,during Normal Reactor Startup, Surveillance Requirement to Manually Trip Rx Trip Breakers Not Performed Per Tech Spec Limits.Caused by Personnel Error
05000335/LER-1981-043-03, /03L-0:on 810918,1A Battery Charger Shut Down on High Voltage During Battery Charging Surveillance.Caused by Defective Shutdown Device.Device Replaced
05000366/LER-1982-086-03, /03L-0:on 820814,following Control Rod Pattern Adjustment,Core Max Fraction of Limiting Power Density Found Greater than Tech Spec Limit.Caused by Reduction in Xenon Concentration Due to Increased Burnup
ST-HL-AE-4035, 2RE02 ISI Summary Rept for Repairs & Replacements at South Texas Project Electric Generating Station Unit 2
PY-CEI-NRR-1382, Forwards Semiannual fitness-for-duty Rept for Jan-June 1991. Personnel W/Access to Protected Area in Both Units 1 & 2 Currently Subj to Unit 1 fitness-for-duty Program Since Const of Unit 2 on Hold
05000327/LER-1980-078-03, /03L-0:on 800526,during Mode 4 Operation,Boron Concentration in RWST Measured 2124 Ppm.Caused by Boron Concentration Makeup Being Too High.Boron Diluted to Proper Concentration
05000245/LER-1979-015-03, /03L-0 on 790528:during Refueling,No Control Rod out-block Occurred When Refuel Bridge Was Over Core W/Fuel Assembly Loaded Grapple.Caused by Worn Track Limit Switch. Switch Replaced & Surveillance Procedure Changed
05000324/LER-1979-071-03, /03L-0:on 790808,RHR Sys Pump 2D Vibrated at Level Higher than Allowable Limit During RHR Sys Operational Component Test.Caused by Spring Part Lodged in Vane of Impeller.Part Removed,Pump Inspected & Tested
05000335/LER-2078-011, For St. Lucie Unit 1, When Upper Guide Structure Was Removed (Refueling Shutdown), 3 (of 45) Incore Instrument Thimbles Remained in the Core
L-85-382, Responds to Violations Noted in Insp Repts 50-250/85-26 & 50-251/85-26.Corrective Actions:Revs to Administrative Procedure 0190.19 Will Be Discussed W/Foremen & Supervisors to Ensure Awareness of Work Order Guidelines
L-86-388, Responds to Generic Ltr 86-14 Re Plans for Operator Licensing & Requalification Exams During FY87-90.Schedules Encl
W3F1-2016-0064, Mitigating Strategies Assessment (MSA) Report for Flooding Hazard
L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2
L-13-058, Steam Generator Inspection Report - Technical Specification 5.6.6.2.1
RS-13-002, Response to Request for Additional Information Related to License Amendment Request to Technical Specification 3.7.3, Ultimate Heat Sink
DCL-12-038, Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-072. License Amendment Request 11-06, Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start
CP-201200354, Response to Request for Additional Information, 2RF12 Steam Generator Tube Inservice Inspection Report - TAC No. ME7345
BYRON 2009-0003, Steam Generator Inservice Inspection Summary Report for Refueling Outage 14
ULNRC-05224, Supplement/Revision to License Amendment Request OL-1258 for Revision of Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfivs)
HNP-04-076, One Year Special Report, Steam Generator Tube Inspection Results
L-05-101, Discharge Monitoring Report (NPDES) Permit No. PA0025615
ULNRC-04826, Union Electric Annual Financial Report
1CAN099201, Forwards Inservice Insp Summary Rept Arkansas Nuclear One, Unit 1,Outage:1R10. Forms NIS-2 Re Owners Rept for Repairs or Replacements Also Encl
NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants
HL-5579, Forwards Proprietary & non-proprietary Response to 980210 RAI Re License Amend Request to Increase Authorized Max Power Level to 2,763 Mwt.Topical Rept NEDO-32749 Encl. Proprietary Info Withheld
NSD-NRC-98-5649, Forwards Rev 4 to Section 2.2, Nuclear Safety Sys of AP600 Certified Design Matl,Dtd 980406.Changes Made as Result of W Responses to NRC Questions Re Rev 3 & Include Rais,Fser Open Items & Meeting Open Items from ITAAC Task Group Mee