Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits
PLA-2357, Forwards Rev 1 to Inservice Insp Program Plan & Response to 840912 Request for Addl Info on Program.Rev to Program Is Result of Addl Relief Requests Identified & Editorial Changes Deemed Necessary.Fee Paid
PLA-1698, Forwards Supplemental Response to SER Open Item 3.10.1(3). Fatigue Cycling Effects on NSSS Equipment Due to Safety Relief Loads (License Condition 23(a)) Discussed
MNS-14-058, Inservice Inspection Report, End of Cycle 22 Refueling Outage
LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic
LR-N13-0172, Enclosure 1 - Salem Nuclear Generating Station Unit 1 Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic
NOC-AE-12002879, Foreign Ownership, Control, or Influence (FOCI)
NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5
U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval
L-08-240, Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations
NRC 2008-0081, Point Beach, Unit 1, Cycle 32 (U1C32) Core Operating Limits Report.
PLA-6169, Submittal of Proposed License Amendments Re Arts/Mellla Implementation - Supplement
PLA-5888, Proposed Amendment Nos. 274 and 243 to License Nos. NPF-14 and NPF-22, Application for Technical Specification Improvement to Revise Technical Specifications to Eliminate Requirements for Monthly Operating Reports
NLS2005007, License Amendment Request to Adopt Generic Changes to Standard Technical Specifications
DCL-05-023, Inservice Testing (IST) Program - Third Ten-Year Interval and IST Relief Requests
05000315/LER-1981-016-03, /03L-0:on 810601,procedure Review Revealed That Selected Valves Were Not Cycled at Frequency & in Operating Modes Required by Tech Specs.Caused by Personnel Error. Procedures Revised
ET 17-0024, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term
BYRON 2004-0120, Issuance of Reactor Coolant System Pressure and Temperature Limits Reports
DCL-18-105, Submittal of the Fourth Ten-Year Interval Inservice Testing (1ST) Program Plan, Revision 1
DCL-04-002, Inservice Testing (IST) Program Plan, Revision 20
PLA-5542, Proposed Amendment No. 251 to License NPF-14 & Proposed Amendment No. 216 to License NPF-22: Adoption of NRC Approved Generic Changes to Improved Standard Technical Specifications (Intermittent Opening of Isolated Flow Paths & Tip Isolation
DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19
DCL-02-061, Inservice Testing (IST) Program Plan, Revision 18
NRC-91-0049, Monthly Operating Rept for Mar 1991 for Fermi 2
NRC-92-0101, Monthly Operating Rept for Aug 1992 for Fermi 2
NRC-91-0089, Monthly Operating Rept for June 1991 for Fermi 2
NRC-91-0097, Monthly Operating Rept for Jul 1991 for Fermi 2
NRC-89-0122, Monthly Operating Rept for May 1989 for Fermi Unit 2
05000353/LER-1998-007, Forwards LER 98-007-00,reporting Condition Prohibited by TS, in That Remote Shutdown Panel Instrument Calibr Was Not within Required Frequency & Required Actions Were Not Taken. Event Occurred Due to Administrative Error
NRC-87-0119, Monthly Operating Rept for Jul 1987
NRC-87-0228, Monthly Operating Rept for Nov 1987
NRC-89-0179, Monthly Operating Rept for Aug 1989 for Fermi 2
NRC-89-0129, Monthly Operating Rept for June 1989 for Fermi 2
IA-89-244, Final Response to FOIA Request for Records.App a & B Records Available in Pdr.App B Records Encl
NRC-89-0137, Monthly Operating Rept for Jul 1989 for Fermi 2
05000353/LER-1998-004, Forwards LER 98-004-00,reporting Manual Actions Taken in Response to Plant Conditions,To Perform Secondary Containment Isolation,Sgts Initiation & RERS Initiation
NRC-87-0222, Monthly Operating Rept for Oct 1987
NRC-87-0184, Monthly Operating Rept for Sept 1987
NRC-87-0093, Monthly Operating Rept for June 1987
NRC-89-0019, Monthly Operating Rept for Jan 1989 for Fermi 2
NRC-87-0154, Monthly Operating Rept for Aug 1987
NRC-87-0083, Monthly Operating Rept for May 1987
JAFP-89-0666, Monthly Operating Rept for Aug 1989 for Ja Fitzpatrick Nuclear Power Plant
BECO-89-101, Monthly Operating Rept for June 1989 for Pilgrim Nuclear Power Station
JAFP-89-0502, Monthly Operating Rept for June 1989 for Ja FitzPatrick Nuclear Power Plant
JAFP-89-0449, Monthly Operating Repts for May 1989 for James a Fitzpatrick Nuclear Power Plant
JAFP-87-0713, Monthly Operating Rept for Aug 1987
JAFP-87-0633, Monthly Operating Rept for Jul 1987
JAFP-87-0975, Monthly Operating Rept for Nov 1987
JAFP-87-0800, Monthly Operating Rept for Sept 1987
JAFP-87-0545, Monthly Operating Rept for June 1987
GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With
NSD-NRC-97-5329, Forwards Markup of AP600 Ssar,Reflecting Design of Containment Spray Sys.Addl Fire Protection Sys Changes Will Not Affect Representation of Containment Spray Sys
A04929, Forwards Addl Info Re Crdr Implementation Plan,Per Suppl 1 to NUREG-0737 in Response to NRC 850523 & 860624 Concerns. Human Factors Consultant & Other Consultants Identified & Roles Discussed
JAFP-86-0296, Monthly Operating Rept for Mar 1986
0CAN028806, Forwards Written Rept Describing Approach to Each Action Items from IE Bulletin 85-003 & Summary of Data for Each motor-operated Valve Compiled in Response to Bulletin.Rept Completes Response to IE Bulletin 85-003
SNRC-1552, Forwards Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Engineering Study Verified That Instrument Air Receivers & Accumulators Designed Per ANSI & ASME Codes
RBG-20487, Final Deficiency Rept DR-271 Re RTD Splices in Electrical Penetrations Supplied by Conax Corp.Initially Reported on 850320.Nonconformance & Disposition & Engineering & Design Coordination Repts Required Repairs Using New Butt Splices
NRC-92-0082, Monthly Operating Rept for Jul 1992 for Fermi Unit 2.W/
JAFP-84-0471, Monthly Operating Rept for Apr 1984
B11025, Advises That 7,896 Operating Hours Spent at Hot Standby Through Cycle 5,per NRC Request
NG-94-1445, Requests Schedule Extension to Complete GL 89-10, Safety Related Motor Operated Valve Testing & Surveillance, Activities for 51 Motor-Operated Valves in Ies Utilities Inc GL 89-10 Program
JSP-062-94, Responds to 931227 RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers
BECO-93-135, Responds to GL 89-10,Suppl 5, Inaccuracy of MOV Diagnostic Equipment
W3P87-2375, Forwards Response to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Submittal Provides Sufficient Info to Close Open Issues from Insp Rept 50-382/87-05
TXX-4828, Forwards Addl Info Re Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events, in Response to NRC 851205 Request.Info Addresses Program for post-trip Review & Maint Program for Trip Breakers
JPN-87-035, Forwards Insp Summary of Igscc,Per Util 861028 Commitment. Welds Classified According to NUREG-0313,Rev 2.Specific Insp Plans Will Be Addressed Prior to Next Scheduled Refueling Outage.Two Oversize Drawings Encl
05000333/LER-1997-008-01, :on 970806,both Trains of SGTS Were Declared Inoperable Due to Flow Restriction in Discharge Line. Developed Periodic Surveillance That Can Adequately Detect Blockage in Drain Line
05000456/LER-1997-007-05, :on 971027,excessive Operator Response Times Were Noted.Caused by Inadequate Analysis Implementation. BwEP-3 Was Revised to Suspend Transition to BwFR-P.1 During Depressurization Portion of BwEP-3
05000458/LER-1992-027, :on 921125,RCIC Sys Not Placed in Standby Lineup Prior to Rv Pressure Increasing to Above 150 Psig. Caused by Incorrect Interpretation of TS 3.7.3.Training Will Be Initiated for All ROs & SROs
05000414/LER-1996-002-03, :on 960318,TS Violation for Redundant Hydrogen Igniters Inoperable in Same Region Occurred.Caused by No Programmatic Requirements in Place Directing Maint to Perform Communication.Blown Fuse Replaced
05000334/LER-1994-003-01, :on 940404,two Flow Orifices Were Improperly Installed.Caused by Improper Installation of All Accessible Flow Orifices.Personnel Performed Procedure Ost 1.6.4 Correcting Improperly Installed Orifices
05000366/LER-1980-056-03, /03L-0:on 800414,during Cold Shutdown,Reactor Protection Sys Bus/Generator A,2C71-S001A Experienced Logic Power Failure,Causing Reactor Half Scram on Channel A.Caused by Open Circuit on Logic Feeder Breaker 2C71-CB1A
05000244/LER-2075-008, For R. E. Ginna, Control Rod G-5 Lift Coil Open Circuit
05000333/LER-1917-004, Regarding Safety Relief Valves Out of Tolerance
05000250/LER-1994-003-03, :on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced
L-93-161, Forwards Comments on Preliminary Accident Sequence Precurser Analysis (LER 251-92-007) Delineated in NUREG/CR-4674, Precursors to Potential Severe Core Damage Accidents:1992,Status Rept, Per NRC 930602 Request
L-87-263, Forwards Regulatory Rept for June 1987,consisting of Current Integrated Schedule W/Correct Baseline Schedules for Forthcoming Integrated Schedule License Amend.Rept Provided as Update to Rept Transmitted on 870427
L-87-182, Forwards Integrated Schedule,Updating 861219 Application for Amends to Licenses DPR-31 & DPR-41.Issuance of Amends Anticipated within 1 Month
L-88-144, Forwards 6-month Rept of Integrated Schedule for Plant. Schedule Reflects Info as of 880520 Issuance Date.Changes to Schedules Reviewed W/Nrc Per Integrated Schedule Plan
05000316/LER-1995-005-01, :on 950829,RT Occurred on High Negative Rate Resulted from Trip of Both CRD-MG Sets Due to mis-adjusted Voltage Regulators.Replaced CRD-MG Common Bus Overvoltage Relay Body
05000335/LER-1992-001, :on 920117,fuel Handling Bldg Ventilation Stack Radiation Monitor Not in Svc During Routine Check.Caused by Personnel Oversight.Event Reviewed W/Chemistry Personnel.W/
L-80-310, Forwards Response to IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys
L-81-303, Forwards Const/Startup Progress Update for June 1981
05000305/LER-2011-004, For Kewaunee Power Station, Regarding One Offsite AC Electrical Circuit Inoperable Not Performed Until After Discovery
PLA-6112, Revision to Proposed Amendment Nos. 281 and 251, Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67
RS-04-024, Request for Amendment to Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles in Accordance with the Guidance of Generic Letter 91-04
ULNRC-02964, Submits Actions Taken to Comply W/Gl 89-10 Re safety-related motor-operated Valve Testing & Surveillance.Note That Attachment Represents Licensee MOV Program to Date
IA-92-384, Listing of Escalated Actions Contained in NUREG-0940
05000353/LER-1998-008, Forwards LER 98-008-00,reporting Condition Prohibited by Tech Specs & Condition That Alone Could Have Prevented Fulfillment of Safety Function of Sys Designed to Mitigate Release of Radioactive Matl
A07899, Provides Addl Info Re Undervoltage Detection Mods & Related License Amend Request,Per NRC 890320 Request.Actual Wiring Drawings Represent True Indication of Separation & Redundancy & Design Single Failure Proof
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
B13666, Rev 4 to Millstone Nuclear Power Station Unit 1 Inservice Test Pump & Valve Program