L-17-052, Supplemental Request Associated with the License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3
NLS2017033, Technical Specification Bases Changes
L-16-348, Response to a Request for Additional Information Regarding a License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3
L-16-298, Response to a Request for Additional Information Regarding a License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
L-16-083, License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3
NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function
NG-12-0034, Supplemental Information to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
L-2011-237, Supplemental Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Containment and Ventilation Issues
TSTF-17-16, Technical Specifications Task Force - Transmittal of TSTF-568, Clarify Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
2CAN061002, Request for Additional Information Technical Specification Changes and Analyses Relating to Use of Alternative Source Term
RS-09-147, Response to Request for Additional Information Regarding Generic Letter 2008-01
PLA-6561, Amendment Request No. 296 to Unit 1 and Amendment Request No. 266 to Unit 2 Re Emergency Core Cooling System Instrumentation - Technical Specification (TS) Table 3.3.5.1-1 and Editorial Change to TS 3.10.8.F, Response to RAI
RC-09-0072, Calculation DC00040-066, Rev 2., Spray and Sump Ph with Delta-75 Sgs
2CAN100703, Unit 2 License Amendment Request for Technical Specification Change Associated with Replacement of Containment Sump Buffer
RA-19-0007, License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications
1CAN022001, License Amendment Request: Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate
LR-N04-0417, LCR S03-05, Implementation of Alternate Source Term Request for Additional Information (TAC Nos. MC3094 & MC3095)
W3F1-2004-0028, License Amendment Request NPF-38-254, Reactor Coolant System Leakage Detection
U-603640, Transmittal of Revision 8 to the Technical Specification Bases
L-03-135, Withdrawal of the Containment Conversion Portion (Phase 2) of License Amendment Request Nos. 300 and 172
RS-03-157, Additional Information Regarding Inservice Testing Program Relief Requests
RS-03-066, Additional Information Supporting License Amendment Request to Revise Suppression Pool Water Level Upper Containment Pool Water Level Requirements in Mode 3
RS-02-163, Additional Information Supporting License Amendment Request to Revise Suppression Pool Water Level & Upper Containment Pool Water Level Requirements in Mode 3
GNRO-2002/00083, Technical Specification Bases Update to NRC for Period Dated September 12, 2002
GNRO-2002/00072, Supplement to Amendment Request, Response to Request for Additional Information Concerning New Special Operations Limiting Condition for Operation Suppression Pool Makeup-Mode 3
GNRO-2002/00011, Request for License Amendment to Add Limiting Condition for Operation
LR-N20-0015, License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling
1CAN072001, Supplemental Information Related to License Amendment Request to Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate
RBG-25278, Application for Amend to License NPF-47,revising Surveillance Requirement Interval for Drywell Bypass Leakage Testing.Amend Requested Prior to 870425 to Avoid Shutdown.Fee Paid
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
AECM-87-0019, Forwards Summary Rept of Safety Evaluations Conducted as Result of Updated FSAR Change Notice Review Program,Per Util 860410 Response to Violation 50-416/86-02-01
RC-95-0192, Forwards Response to NRC Ltr Re Violations Noted in Insp Rept 50-395/95-09.Corrective Actions Addressed in Attached Ler.W/O LER
ST-HL-AE-3791, Requests Withdrawal of Proposed Tech Spec Changes Based on STPEGS PRA
3F0691-04, Application for Amend to License DPR-72,consisting of TS Change Request 186,replacing TS 3.6.2.2 for Spray Additive Sys W/Ts 3.6.2.2 for Containment Emergency Sump Ph Control Sys
W3P88-1213, Requests Temporary Waiver of Compliance W/Tech Spec 3.6.2.2 Re Containment Cooling Fans Which Need to Be Operable in Modes 1-4.Tech Spec Change Request Revises Tech Spec 3.6.2.2 to Allow Only Two Fans to Be Operable During Modes 1-4
W3P88-1212, Application for Amend to License NPF-38,consisting of Tech Spec Change Request NPF-38-81,revising Number of Fans Which Must Be Operable in Tech Spec 3.6.2.2, Containment Cooling Sys. Fee Paid
PY-CEI-NRR-2216, Forwards Supplemental Response to NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs. Updated Info to NRC on Several Design Approaches Which Have Been Revised During Final Design Process,Provided
U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval
CNL-14-103, Response to Request for Additional Information 2 Regarding Ultimate Heat Sink License Amendment Request
JAFP-20-0012, License Amendment Request - Application to Adopt Technical Specification Task Force Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line.
2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
2CAN081001, Request for Additional Information, Technical Specification Changes and Analyses Relating to Use of Alternative Source Term
05000338/LER-1989-016-01, :on 890826,recirculation Spray HX Svc Water a Supply Header Isolation Motor Operated Valves Deenergized in Closed Position.Caused by Miscommunication Between Shift Supervisor & Other Personnel.Power Reinstated
05000339/LER-1989-008-02, :on 890806,ESF Valve 2-RS-MOV-201B Inadvertently Closed During on-line Slave Relay Testing. Caused by Incorrect Interlock Identification for Valve.Valve Opened Following Testing of Slave Relay K645
05000368/LER-1998-005-01, :on 980722,discovered That Surveillance Test of Sodium Hydroxide Addition Pump Was Not Performed as Required by Ts.Caused by Deficiencies in Test Procedure.Procedure Revised
05000454/LER-1987-016-03, :on 870526,during Mode 3,both Trains of Containment Spray Additive Sys Discovered Inoperable.Caused by Two Locked Open Isolation Valves Mispositioned Due to Procedural Deficiency.Valve Repositioned
05000382/LER-1997-025, :on 971017,gag for Valve CC-835B Was Partially Engaged Restricting Valve to Approx 80% Open.Caused by Inadequate Work Instructions.Gag Was Completely Disengaged on Valve CC-835B
05000338/LER-1988-025-01, :on 881101,Tech Spec 3.6.2.2 Violated.Caused by One Recirculation Spray Subsystem W/One Casing Cooling Subsystem Inoperable.Functional Testing on Casing Cooling Tank Level Transmitters Stopped
05000338/LER-1998-007-01, :on 981015,3B Casing Cooling Pump Failed to Develop Discharge Pressure & Recirculation.Caused by Air Binding.Subject Pump Was Vented of Air,Started & Tested Satisfactorily.With
05000335/LER-1986-003-03, :on 860214,iodine Removal Sys Out of Svc Greater than 72 H.Caused by Combination of Leaking Check Valves & Cognitive Personnel Error.Valves Repaired & Training Requirements Under Evaluation
05000316/LER-1985-028-01, :on 850915,spray Additive Tank Vol Exceeded Tech Spec 3.6.2.2.Caused by Procedural Deficiencies.Tank Drained to Meet Specs & Returned to Operable Status
05000338/LER-1992-016-01, :on 921203,two Conditions Outside of TS 3.3.1.1,Table 3.3-1 Action 2.(a) & 3.6.2.2 Occurred.Caused by Inadequate Initial Development of Test Procedures.Change to TS Initiated
05000395/LER-1995-003, :on 950421,vol in Na Hydroxide Storage Tank Was Above TS Limits Due to Inadequate Procedural Guidance. Operations Personnel Drained Approx 60 Gallons from Tank to Restore Level to Middle of Specified Range
05000362/LER-1983-054-03, /03L-0:on 831111,low Level Alarm for Containment Spray Chemical Storage Tank 3T-105 Received.Caused by Failure of Manway Cover Gasket.Gasket Replaced & Leak Tested on 831116
05000361/LER-1983-120-03, /03L-0:on 830829 & 31,flow Control Valve 2FV-0318 for Iodine Removal Sys Failed to Open & Declared Inoperable.Caused by Cracked O-ring Allowing High Pressure Oil to Leak to Low Pressure Side
05000366/LER-1983-084-03, /03L-0:on 830817,during RHR Shutdown Cooling Mode, Procedure HNP-2-1114 on Loop a of Rhr,Loop a HX Outlet Valve 2E11-F003A Failed to Open,In Violation of Tech Spec 3.6.2.2. Caused by Component Failure
05000412/LER-1994-009, :on 940812,unit 2 at 100% Power a RSS Pump Was Inoperable.Caused by Scaling of Flow Transmitters/ Indicators Were Not Matched to Characteristics of Flow Elements
05000334/LER-1994-001, :on 940109,required Plant Shutdown Occurred Due to Inoperable Train of Recirculation Spray Hxs.Caused by Inaccurate Indications.Unit Was Shutdown & a Train Heat Exchangers Cleaned
JSP-719-90, Application for Amend to License DPF-62,revising Tech Spec 3/4.6.5, Drywell Post-LOCA Vacuum Relief Valves
05000325/LER-1982-079-03, /03L-0:on 820702,RHR Svc Water Pump 1D Tripped During Suppression Pool Cooling.Cause Not Determined. Troubleshooting of Electrical Protective Devices Revealed No Irregularities.Pump Tested & Returned to Svc
05000302/LER-1982-026-03, /03L-0:on 820326,during Procedural Review, Procedure Identified for Security Sodium Hydroxide Spray in Mode 4 Prior to Entry Into Mode 5,contrary to Tech Specs. Caused by Procedural Error.Procedure Rewritten
05000311/LER-1981-113, Forwards LER 81-113/03L-0.Detailed Event Analysis Encl
3F0593-05, Advises That Containment Emergency Sump Ph Control Sys, Using Trisodium Phosphate Dodecahydrate,Operable Prior to Entering Mode 4.Cycle 9 mid-cycle Outage Completed on 930426
05000334/LER-1981-092-03, /03L-0:on 811005,w/reactor Power at 98%,declared Outside Recirculation Spray Pump Inoperable Due to Apparent Seal Problem.Caused by Iron Particle Deposits Between Seal Surfaces.Carbon Steel Fittings to Be Replaced
05000339/LER-1990-001-02, :on 900215,inadvertent Partial Train a ESF Actuation of Containment Depressurization Sys Occurred. Caused by Human Error.Evaluation to Be Performed to Determine If Test Points Can Be Moved
05000339/LER-1981-030-03, /03L-0:on 810316,casing Cooling Subsys B Was Removed from Svc During Mode 1,contrary to Tech Spec 3.6.2.2.Caused by Need to Prevent Pressurization of Sys While Performing Maint on Valve MOV-RS-201B
05000302/LER-1980-050-03, /03L-0:on 801119,found That Level Indication for Sodium Hydroxide Tank BST-2 Was Erratic & Displaying Incorrect Indication.Caused by Water in Sensing Lines. Engineering Investigation Is Being Conducted
JAFP-20-0030, Response to Request for Additional Information in Support of License Amendment Request - Proposed Changes to the Technical Specifications to Primary Containment Hydrodynamic Loads
05000382/LER-1989-020, :on 891031,containment Fan Cooler C Motor Ran in Reverse Direction Reducing Air Flow & Cooling Capacity. Caused by Personnel Not Performing Surveillance Testing. Motor Rewired for Correct Slow Speed Operation
CNRO-2007-00042, Entergy Operations, Inc. - Relief Requests for 10 Year Updates to the 120 Month Inservice Testing Intervals
05000368/LER-1980-007-03, /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits
05000302/LER-1979-096-01, /01T-0:on 790780,vol of Sodium Hydroxide Tank Exceeded Tech Spec,But Not Reported.Caused by Inadequate Design.Daily Operating Surveillance Procedure SP-300 Revised to Include Operating Band Requirement
05000346/LER-1979-084-01, /01T-0 on 790806:containment Air Coolers Svc Outlet Valves,Automatically Regulated by Inlet Air Temp, Failed to Meet Response Time.Caused by Design Error in Actuator Air Opening Size.Valves Will Be Redesigned
05000272/LER-1992-018, :on 920731,discovered That Valves 11 & 12 CS20 & CS6 Found to Be in Closed Position.Caused by Personnel Error Attributed to Poor Work Practice.Individuals Involved Received Appropriate Discipline
05000400/LER-1988-004-01, :on 880125,resultant Level Indication Revealed That Actual Tank Level Was Less than That Required by Tech Spec 3.6.2.2.Caused by Air Trapped in Sensing Lines of Level Transmitters.Sensing Line Vented
L-90-251, Documents Written & Verbal Request of Region II Personnel for Temporary Waiver of Compliance of Tech Spec 3.4.2.b.1 Re Allowable Out of Svc Time for One Emergency Containment Cooler from 24 H to 72 Hr W/Addl Reasons
05000316/LER-1981-005, Describes 810331 Incident Reported in LER 81-005/01T-0 Re Spray Additive Tank Level
05000335/LER-1999-001-01, :on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With
L-88-168, Forwards Addl Info on Proposed License Amend Re Boric Acid Concentration Reduction,Per NRC 880310 Telcon Request
L-94-260, Application for Amends to Licenses DPR-67 & NPF-16,upgrading TS 3/4.6.2.1 & 3/4.6.2.3 by Adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants
L-2017-006, Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b
HNP-16-076, Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the a Emergency Service Water Pump Replacement
HNP-16-068, Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the a Emergency Service Water Pump Replacement
HNP-16-056, Response to Second Request for Additional Information Regarding License Amendment Request for Temporary Changes to Technical Specifications for the a Emergency Service Water Pump Replacement
HNP-16-072, Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the a Emergency Service Water Pump Replacement
05000272/LER-2015-005, Regarding Low Containment Spray Additive Tank Sodium Hydroxide Concentration
05000251/LER-2014-003, Regarding Emergency Containment Cooler Safety Function Impacted During Breaker Replacement
05000296/LER-2013-003, Regarding Automatic Reactor Shutdown Due to an Actuation of the Reactor Protection System from a Turbine Trip
NG-13-0084, NextEra Energy Duane Arnold, Llcs, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12
05000410/LER-2012-003, Regarding Suppression Pool Level Below Technical Specification Limit During Mode Change
05000400/LER-2008-001, Regarding Containment Spray Additive System Eductor Test Flow Outside of Technical Specification Limits
RS-10-044, Response to Request for Additional Information Related to Request for Approval of Relief Requests for Third Inservice Testing Interval
05000251/LER-2005-004, Re Foreign Material Causes Inoperability of One Emergency Containment Cooler
05000389/LER-2005-002, Valve Mispositioning Led to Inoperable Iodine Removal System Train
05000335/LER-2003-004, Re Improper Sampling Techniques Led to Operation of Naoh Tank Outside Tech Spec Limits
05000346/LER-2002-008, For Davis-Besse Unit 1 Re Containment Air Coolers Collective Significance of Degraded Conditions
05000272/LER-2002-002, Re Containment Spray Additive Tank Exceeded Technical Specification Limit Allowable Outage Time
05000412/LER-2002-001, Re Service Water Conditions for Recirculation Spray System Lead to Technical Specification Noncompliance
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
RS-03-053, Additional Information Supporting the Request for License Amendment Related to Application of Alternatives Source Term
CNL-18-056, Completion of Required Action for NRC Order Number EA-12-049, Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
GNRO-2017/00017, Three Relief Requests for Jockey Pumps for the Third 10-year Inservice Testing Interval
U-603859, Transmittal of Revision 11 to the Clinton Power Station Technical Specification Bases
JAFP-17-0083, Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
RBG-34-592, Application for Amend to License NPF-47,changing Tech Spec 3.6.2.3, Drywell Air Locks & Associated Bases to Permit Entry Into Drywell W/One Air Lock Door Inoperable
05000339/LER-1989-008-01, :on 890806,ESF Valve 2-RS-MOV-201B Closed Inadvertently During Initial Performance of 2-PT-36.5.3A. Caused by Misidentification of Interlock for 2-RS-MOV-201B. Tech Spec 3.0.3 Entered & Deviation Rept Done
NLS2016070, Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events
05000250/LER-2016-001, Regarding Loose Breaker Control Power Fuse Caused the 3B Emergency Containment Cooler to Be Inoperable Longer than Allowed
05000423/LER-1995-016-02, :on 950911,A Train Quench Spray Pump Discharge Valve Exceeded TS Surveillence Periodicity Limit.Caused by Programmatic Error.Surveillance Tracking Procedure Revised
05000302/LER-1983-024-03, /03L-0:on 830624,procedures Governing Lab Determination of Sodium Hydroxide Concentration Erroneously Equated 1.0 Mg Per Liter w/1.0 Ppm Causing Concentration Error.Caused by Procedure Inadequacy
L-09-218, Submittal of Technical Specification Bases, Revision 7