05000400/LER-2010-001, Unit 1 Regarding Clearance Error Results in Required Equipment Becoming Inoperable
NOC-AE-13003011, Report of Changes Made to the Technical Specification Bases Covering the Period from June 16, 2011 to June 16, 2013
L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases
L-2011-438, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System
L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08
NOC-AE-08002354, Request to Defer Part of Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
NOC-AE-08002351, Revision 2 to Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
NOC-AE-08002319, Response to RAI Revision to Proposed Amendment to TS 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
NOC-AE-07002234, Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007
RC-07-0025, License Amendment Request - LAR 05-3594 Steam Generator Tube Integrity
L-2007-003, Reply to Request for Additional Information, Steam Generator Tube Integrity Amendment Request
L-2006-229, Response to Request for Additional Information - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
L-06-149, Improved Technical Specification (ITS) Conversion License Amendment Request
HNP-06-116, Response to Request for Additional Information Regarding License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
HNP-06-060, License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
L-2006-094, Proposed License Amendment Steam Generator Tube Integrity Pursuant to 10 CFR 50.90
L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
W3F1-2006-0016, To Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
W3F1-2006-0007, Supplement to Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
05000272/LER-1996-008-02, :on 960613,failure to Meet TS Requirements While in Mode 5 for Natural Circulation Was Noted.Caused by Insufficient Technical Input for Development of Controls. Revised Plant Operating Logs for Mode 5
05000272/LER-1989-019-01, :on 890520,both Loops of RHR Sys Were Declared Inoperable Due to Gas Binding of RHR Pumps.Caused by Personnel Error.Use of Test Procedure Discontinued Until Completion of Review.Procedure Revised
NOC-AE-05001921, License Amendment Request - Proposed Amendment to Technical Specifications to Incorporate Best Estimate Analyzer for Core Operations - Nuclear
W3F1-2003-0075, Ses, Unit 3, License Amendment Request NPF-38-250, Revision to Pressure/Temperature and Low Temperature Overpressure Protection Limits for 32 Effective Full Power Years
05000395/LER-1982-004, Forwards LER 82-004/03L-0.Detailed Event Analysis Encl
W3F1-2002-0095, License Amendment Request NPF-38-243 Reactivity/Boron Concentration Changes
05000395/LER-1983-034, Forwards LER 83-034/03L-0.Detailed Event Analysis Encl
05000395/LER-1983-031, Forwards LER 83-031/03L-0.Detailed Event Analysis Encl
1CAN068908, Application for Amend to License DPR-51,revising Tech Spec 3.4.1.4 to Clarify Ambiguity in Interpretation of Relationship of Limiting Condition for Operation to Associated Surveillance Requirement
B16845, Responds to 971028 RAI Re Util 970829 Amend to License NPF-49 to Revise TS to Resolve Inconsistencies Re Cold Overpressure Protection Sys Enabling Temperature & Eccs/ Charging Sys Mode 3 Requirements
AECM-86-0092, Application for Amend to License NPF-29,changing Tech Specs to Increase Neutron Flux Noise Surveillance Per Rev 1 to GE Svc Info Ltr 380 & to Permit Operation W/One Recirculation Loop Out of Svc.Fee Paid
B15902, Requests That Util Modifies Certain Commitments to Perform Testing at Plant Per NRC Request in Response to NRC Bulletin 96-001
AECM-84-0229, Forwards Program Completion Rept Re Conclusion of Tech Spec Review Program.Rept Documents That Thorough & in-depth Engineering,Operations & Licensing Review of Tech Specs Conducted Per Programmatic Commitments
B14803, Application for Amend to License NPF-49,proposing Changes to Ts,Addressing Shutdown Margins,Reactor Trip Sys & Heat Flux Hot Channel Factor
ST-HL-AE-3642, Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for PORV & Block Valves
TXX-9636, Forwards Response to Violations Noted in Insp Repts 50-445/96-04 & 50-446/96-04.Corrective Actions:Rhr Pump 2-01 Started & Flow Restored to Normal
NOC-AE-05001847, Technical Specification Bases Change
L-2006-212, Reply to Request for Additional Information Steam Generator Tube Integrity Amendment Request
NOC-AE-08002363, Supplement to Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation
L-2006-089, Proposed License Amendment Steam Generator Tube Integrity
05000369/LER-1982-024, Forwards LER 82-024/03L-0.Detailed Event Analysis Encl
L-2007-071, Reply to Request for Additional Information Re Steam Generator Tube Integrity Amendment Request
05000272/LER-1982-015, Forwards LER 82-015/03L-0.Detailed Event Analysis Encl
L-2008-149, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
RC-06-0084, License Amendment Request - LAR 05-3594, Steam Generator Tube Integrity
L-2019-076, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
LR-N16-0055, Response to Request for Additional Information Regarding Chilled Water System Modifications
05000327/LER-1987-041, :on 870804,momentary Loss of RHR Flow Occurred When Valve 1-FCV-74-2 Inadvertently Closed,Isolating RHR Pump 1A-A Suction from RCS Loop 4 Hot Leg.Caused by Personnel Error.Student Assistant Counseled
05000352/LER-1987-049, :on 870919,Tech Spec 3.4.1.4 Surveillance Test ST-6-043-390-1 Re RCS Temp Missed.Caused by Operator Not Performing Applicable Steps.Procedure Revised
05000313/LER-1987-001-01, :on 740521,four Seismic Supports Not Installed During Initial Const.Caused by Inadequate Coordination Between Design & Installation Groups.Supports Installed During Latest Refueling Outage
05000323/LER-1986-002-01, :on 860117,instrument Ac Panel Py 2-1 Inadvertently Transferred to Backup Power.Caused by Unlicensed Operator Error.Operator Counseled & Procedures Revised
05000275/LER-1986-012-01, :on 860908,while Installing Mod in Solid State Protection Sys Cabinet,Both RHR Trains Became Inoperable & Event Not Reported within Time Required.Caused by Personnel Error.Personnel to Be Retrained & Event Reviewed
05000334/LER-1997-041, :on 971215,failed to Remove Power from Isolated RCS Loop Isolation Valve Operators within One Hour as Required by Ts.Caused by Inadequate Actions Taken to Control & Implement Change.Revised Procedures
L-2003-199, Proposed License Amendments Regarding Control Room Ventilation System and Miscellaneous Minor Changes
05000327/LER-1988-021-01, :on 880523,loss of Operating Train of RHR Sys Occurred.Caused by Opening of Manual Isolation Valve.Train B RHR Pump Stopped by Placing in put-to-lock Condition
05000328/LER-1988-001-01, :on 880111,ltr Received from S&W Revealing That Lower Support Frame of Containment Spray HXs 2A & 2B Could Be Overstressed During Design Basis Seismic Event.Caused by Design Deficiency.Frames Modified
05000323/LER-1986-002, :on 860117,RHR Valve 8702 Closed & RHR Pump 2-1 Secured in Response to Ensuing loss-of-flow Alarm.Caused by Unlicensed Operator Error.Valve Reopened.Pump Restarted, Observed for Seal Damage & Declared Operable
05000327/LER-1985-040, :on 851009,trains Became Inoperable Due to Air Injection Into Suction of Pumps During Swap Over from Train B to a Rhr.Caused by Procedure Inadequacy.Pumps Shutoff & Vented.Rcs Level Increased.Valves Verified
05000213/LER-1996-024, :on 960901,B RHR Pump Was Found Inoperable in Mode 5.Caused by Original Mfg Defects Along W/Marginal Pump Design.Replaced Pump Rotating Element
05000413/LER-1985-028, :on 850422,both RHR Trains Inoperable & RCS Draining Began While Train a Inoperable Due to Maint.Caused by Personnel Error.Centrifugal Charging Pump a Started to Restore PCS Sys Level
05000311/LER-1984-002-01, :on 840209,RHR Common Suction Valve 2RH1 Inadvertently Shut,Resulting in Loss of RHR Flow Through Rcs.Caused by Bezel Covers Not Removed to Reflect Release of Breaker Tags
05000370/LER-1984-001-02, :on 831231,RHR Np Pump B Observed to Have Zero Discharge Flow.On 840109,computer Alarm for Np Pump a Dischange Pressure Received.Caused by Procedural Deficiencies Due to Inadequate Guidelines
05000370/LER-1984-002, :on 840115,both Nd Trains Declared Inoperable When Breakers for Valves 2ND-1B & 2NB-2A Closed.Caused by Personnel Error.Procedures Revised & Personnel Counseled
05000499/LER-1995-001-01, :on 950119,potential Slight Degradation of Decay Heat Removal Capacity Via Natural Circulation Occurred.Caused by Failure to Fully Evaluate Thermodymanic TS Bases for Using Sg.Operators Briefed
NRC-98-0003, Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS
05000328/LER-1990-013-02, :on 900911,loss of RHR Shutdown Cooling Due to Inadvertent Deenergization Occurred.Caused by Oversight During Impact Evaluation.Event Reviewed W/Personnel
05000334/LER-1993-015, :on 931101,recognized That TS Violation Occurred When Power Restored to Loop Isolation Valves for Isolated Rcl Due to Inadequate Work Organization & Planning. Caution Tags Posted on 480 Volt Ac Breakers
ELV-01675, Responds to Violations Noted in Insp Rept 50-424/90-05 on 900217-0330.Corrective Actions:Locked Valve Procedure Revised to Eliminate Utilization of Hold Tag on Valves Required by Tech Specs to Be Secured in Position
AECM-90-0089, Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant
05000369/LER-1981-185, Forwards LER 81-185/03L-0.Detailed Event Analysis Encl
05000413/LER-1990-020, :on 900324,low Pressure Indication Noted on Cardox Carbon Dioxide Storage Unit & Continuous Fire Watch Not Provided within 1 H.Caused by Personnel Lack of Attention to Detail.Fire Watch Established
05000369/LER-1981-129, Forwards LER 81-129/03L-0.Detailed Event Analysis Encl
05000369/LER-1981-080, Forwards LER 81-080/03L-0.Detailed Event Analysis Encl
05000369/LER-1981-080-03, /03L-0:on 810508,while in Mode 5,initial Fuel Loading,Both Trains of RHR Sys Were Inoperable.Caused by Failure of Personnel to Prevent Entering of Mode 5 W/O RHR Train B Operable.Operating Procedure Will Be Written
05000369/LER-1981-072-03, /03L-0:on 810427,RHR Sys Discovered Isolated from RCS During Mod of Train a Solid State Protection Sys to Include Reactor on Turbine Trip.Caused by de-energized Relay in Logic,Closing Isolation Valve
05000369/LER-1981-073, Forwards LER 81-073/03L-0.Detailed Event Analysis Encl
HNP-12-130, Transmittal of Technical Specifications Bases
HNP-15-046, Transmittal of Technical Specifications Bases
05000311/LER-1989-017-02, :on 890926,motor Operated Valve Found to Have Energized Limit Switch Compartment Space Heater & on 891024, Valve Actuator Found W/Damaged Wiring Insulation.Caused by Personnel Error.Evaluation Underway
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
LR-N970150, Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance
05000272/LER-1996-008-01, :on 960613,failed to Meet Tech Spec Requirement While in Mode 5 for Natural Circulation.Caused by Insufficient Technical Input for Development of Controls. Revised Operating Logs for Mode 5
05000400/LER-1991-007-01, :on 910325,one Emergency Svc Water Pump Inappropriately Removed from Svc for Outage Work.Caused by Personnel/Mgt Error.Info Re Event Disseminated to Personnel & TS Will Be Annotated
05000250/LER-1995-002, :on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4
05000529/LER-1997-007, :on 971006,TS Violation Occurred Due to Inadequate Shutdown Cooling Flow During Modes 5 & 6 Operation.Independent Investigation of Event Was Conducted IAW APS CA Program
RC-13-0047, License Amendment Request - LAR 12-03567, Application to Revise Tech Specs to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement
05000498/LER-2011-001, For South Texas, Unit 1, Regarding Technical Specification Requirement Not Met Regarding Unborated Water Sources
L-2009-099, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
L-02-094, Technical Specifications Bases Change Submittal
ELV-03416, Forwards Response to Oct 1988 Notice of Violation & Civil Penalty.Util Believes Enforcement Action Represents Inappropriate Regulatory Action
ELV-03377, Responds to NRC Forwarding Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000. Corrective Actions:Procedures Revised to Add Precaution Re TS Requirements for Reactor Water Makeup Storage Tank
AECM-83-0565, Forwards marked-up Proposed Changes to Tech Specs Per 821020 Confirmation of Action Ltr.Changes Intended to Enhance Clarity or Provide Consistency W/Plant Design & Operation. Justification for NSHC Encl
RA-21-0282, Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes
B16240, Annual Repts for 10CFR50.59 PORV & SV Challenges Primary Coolant Specific Activity Analysis Occupational Radiation Exposure for 1996
05000328/LER-1981-094-01, /01L-0:on 810806,RHR Pump 2A-A Suction Valve from Containment Sump Started Opening & Normal Suction Valve from Reactor Coolant Loop Started Closing,Creating Flow Path from Reactor Coolant Loop 4 to Containment Sump
05000313/LER-1989-022, :on 890120,RCS Backleakage Occurred Through failed-open Check Valve Resulted in Design Temp of Hpis Piping Being Exceeded.Caused by Failure of Support Designer to Use Correct Load.New Support Replaced