LIC-17-0041, Independent Spent Fuel Storage Installation - Revision to Emergency Plan Update
L-2017-058, License Amendment Request to Revise the National Fire Protection Association Standard 805 Modifications
NRC 2013-0080, License Amendment Request 252 Technical Specification 5.6.5. Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) Response to Request for Additional Information
DCL-12-050, Attachment 2 to DCL-12-050, Final Safety Analysis Report Changes for Process Protection System Replacement
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 1 of 9
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8
RS-14-029, Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 2009
DCL-11-104, Attachment 8: Revision 4 to Diablo Canyon Power Plant Units 1 & 2, Process Protection System (PPS) Replacement Interface Requirements Specification, Nuclear Safety-Related.
BW090068, Fourteenth Refueling Outage Steam Generator Inservice Inspection Summary Report
NLS2009100, Response to Request for Additional Information for the Review of Cooper Nuclear Station License Renewal Application
LR-N09-0164, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items
NRC-2009-0046, Annual Monitoring Report, Cover Letter Through Part D, Groundwater Monitoring
L-PI-09-007, Responses to NRC Requests for Additional Information Dated December 24, 2008 Regarding Application for Renewed Operating Licenses
NRC 2008-0098, 2007 Annual Monitoring Report (Revised)
HNP-03-145, 5 to PEP-310, Notifications and Communications
GNRO-2003/00020, Changes to Emergency Plan Implementing Procedures - March 17, 2003, Rev. 37 to 10-S-01-06, Rev. 10 to 01-S-10-3, Rev. 17 to 10-S-01-11 and Rev. 2 to TQ-110
NTD-16-051, Draft Outlines (Facility Letter Dtd. - 9/12/2016 (Folder 2)
NL-05-0960, Response to Request for Additional Information Related to Requests for Exemption/Amendment from Fire Protection Requirements
L-18-249, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805
NRC 2003-0051, Response to Request for Additional Information (RAI) Regarding Request for Exemptions to 10 CFR 50.61, Appendices G & H to 10 CFR 50, and Approval of PTS Application for Pbnp Unit 2 and Proposed Heatup and Cooldown Limit Curves
RBG-31324, Forwards Updated Info Re Util Licensing Activities.Effect of Drywell Temp Increase on Suppression Pool Hydrodynamics Can Be Addressed by Evaluating Effects on Peak Drywell Pressure
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
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
NSD-NRC-97-5231, Forwards Formal Transmittal of Correspondence Previously Sent Over Period 970515-970605.W/index
B16348, Forwards Annual Low-Level Radwaste Rept for Millstone Site for 1996, by Ltr
NRC-84-0071, Forwards Addl Info Re Comparison of Snupps ECCS Evaluation Model to Recent 1981 Evaluation Model,In Connection w/840417 Ltr on Proposed Rev of Emergency Diesel Generator Start Time from 10 to 12
W3P89-1582, Forwards Rev 10,Change 2 to Physical Security Plan.Encl Withheld (Ref 10CFR73.21)
TXX-4780, Interim Significant Deficiency Rept CP-86-22 Re Adequacy of Fan Cooler Design in Safeguards Area.Initially Reported on 860402.Ebasco Svcs,Inc Performing Evaluation.Next Rept Will Be Submitted by 860714
L-2022-143, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response
ULNRC-06702, Enclosureplacement Version of Attachment 3 to ULNRC-06688, Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505
NLS8900379, Forwards Info Re Sims for Plant,Per Project Manager Request
05000336/LER-1989-001-02, :on 890202,inoperability of Two Fire Barrier Cable Penetration Seals Which Had Been Permanently Resealed Determined.Caused by Personnel Error.Roving Hourly Fire Watch Initiated
NSD-NRC-97-5133, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period 970416-0502,including Draft of SSAR Markup for LOOP Issue & Open Item Status
05000327/LER-1992-024, :on 921212,discovered That Continuous Fire Watch Had Not Been Established within Required Timeframe Due to Inattention to Detail by Fire Operator.Individuals Were Counseled on Importance of Attention to Detail
05000397/LER-1985-034, :on 850525,inadvertent ESF Injection to Reactor Pressure Vessel Occurred During Cold Shutdown.Caused by Faulty Logic seal-in Lamp Indication.Procedural Changes Made to Identify Logic Status More Positively
05000328/LER-1993-004-01, :on 930323,discovered That Surveillance Interval Specified in TS 4.6.5.1 Exceeded.Caused by Ineffective Communication Between Chemistry Personnel. Procedure Revised
05000029/LER-1979-002-03, /03L-0 on 790122:following Plant Trip,Control Room Operator Found Rod 22 Failed to Drop Into Core from 87 Inches on the Scram & All Rods in Group Were Not within Plus/Minus 8 Inches.Caused by Crud Buildup After Refueling
RA-18-0015, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating
05000255/LER-1980-021-01, /01X-1:on 800725,during Valve Inservice Insp, Operator Opened Containment Sump Valve CV-3030.Valve Stayed Open 36-h.Caused by Operator Error.Valve Closed,Operator Counseled & Shift Turnover Checklist Revised
05000296/LER-1979-028-03, /03L-0:on 791218,while Performing SI,PS-3-74A & B & PS-68-95 (Reactor Pressure) Did Not Actuate at Correct Setpont.Caused by Drifting of Barton Model 288 & Barksdale B2T-M12SS.Switches Readjusted
L-98-152, Forwards Assessment of Best Estimate of Risk Re Operation of Commercial Airport at Homestead Air Force Site W/Regard to to Safety at Turkey Points 3 & 4
05000237/LER-1975-049, Regarding Failure of Channel a Floor Radiation Monitor Downscale
LIC-17-0063, EP-FC-1001, Rev. 2, Post-Shutdown Radiological Emergency Response Plan
RA15-028, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
ULNRC-05737, Completion Time Extensions for TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Functions, TAC No. ME2822 (LDCN 09-0039 Supplement)
RBG-46479, Supplement to Amendment Request Corrections to Loss of Power Instrumentation Requirements
E900-05-023, Calculation E900-05-023, Rev 1, Miscellaneous Chain Link Fences MA9 - Survey Design
ULNRC-04929, Common Stars License Amendment Regarding Implementation of WCAP-14333 and WCAP-15379, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
NG-11-0123, 2011 Duane Arnold Energy Center Initial Examination Outline Submittal
ULNRC-05731, Completion Time Extensions for TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Functions (LDCN 09-0039 Supplement)
DCL-24-111, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3.1 and 3.3.2
NLS8400220, Submits Info Demonstrating Ability to Obtain Funds for Payment of Deferred Premiums within 3-month Period.Annual Rept to Securities & Exchange Commission for 1983 & Uniform Forecast Form for Security Analysts Encl
L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ
05000382/LER-1987-018, :on 870716,containment Pressure Transmitter CB-IPT-6702 Smd Found Isolated.Caused by Failure of Technicians to Properly Restore Transmitter Following Calibr on 861220.Technician Counseled & Disciplined
05000328/LER-1988-033, :on 880730,plant Found in Noncompliance W/Tech Specs.Caused by Inadequate Surveillance Instruction Used for Calibr of Upper Head Injection Sys.Surveillance Instruction Manual Changed