L-2015-218, Inservice Inspection Plan Fourth Ten-Year Interval Unit 1 Relief Request No. 10, Revision 0
RC-12-0142, License Amendment Request - LAR-06-00055, License Amendment Request to Adopt NFPA 805, Response to Request for Additional Information
SBK-L-11066, License Amendment Request 11-01, Application to Revise the Technical Specifications for Reactor Coolant System Leakage Detection Instrumentation
L-2007-003, Reply to Request for Additional Information, Steam Generator Tube Integrity 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
LR-N06-0248, Technical Specification 6.9.1.5 Annual Reports
L-2006-094, Proposed License Amendment Steam Generator Tube Integrity Pursuant to 10 CFR 50.90
2CAN050601, Response to NRC Request for Additional Information on ANO-2 Steam Generator Tube Inservice Inspection Program
L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
RC-18-0067, (Vcsns), Unit 1 - License Amendment Request - LAR-16-00644 - Revise Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2
05000311/LER-1988-019-01, :on 881005,several Tubes Found Degraded in Steam Generator Tubes 22 & 24.Caused by Steam Generator Design.Emergency License Amend Issued to Modify Steam Generator Tube Sampling Method
05000272/LER-1981-040, Forwards LER 81-040/03L-0.Detailed Event Analysis Encl
NOC-AE-04001794, License Amendment Request Revision to Proposed Amendment to Technical Specifications for Steam Generators
NOC-AE-04001765, License Amendment Request - Proposed Amendment to Technical Specifications for Steam Generators
PLA-4055, Forwards Proposed Amend 117 to License NPF-22 Re Power Uprate W/Increased Flow
RC-02-0091, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity.
3F0585-24, Submits Second Revised Response to Violations Noted in Insp Rept 50-302/83-27.Corrective Actions:Automated Surveillance Tracking Program Developed as Backup to Manual Sys.Computer Terminal Will Be Located Outside Control Room
NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval
3F1287-32, Forwards Updated ASME Section XI Pump & Valve Program Inservice Insp, Vols I & Ii.Revised Relief Requests & Recommended Schedule for Issuance of NRC Approval Also Encl
2CAN068702, Informs That Temp Monitoring of Reactor Head Flange Leakoff Line Will Not Be Performed Until Remote Instrumentation Operable,Per 870605 Telcon.Listed Actions & RCS Leak Rate Calculations Will Identify Significant Pathway Leaks
B17764, Application for Amend to License NPF-49,deleting Reference to ASME Code Paragraph Iwv 3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger Contained in TS 4.4.6.2.2.e
B16555, Advises NRC of Six Discrepancies in Unit 3 SER (NUREG-1031) Identified During Our Configuration Mgt Program Review. Commitments,Encl
CLI-85-18, Notifies That Encl Kelley,Kline & Bright & Order CLI-85-18 Re Leak Rate Data Falsification Forwarded to Encl List of Individuals for Second Time During 860127-0213
3F0184-03, Responds to NRC Re Violations Noted in IE Insp Rept 50-302/83-27.Corrective Actions:Rcs Leakage Determination Satisfactorily Completed & Automated Tracking Program for Control Rod 3 Initiated
2CAN099402, Forwards Comparison of RCS Leak Detection to Reg Guide 1.45 in Support of Permanent Reactor Pressure Vessel Seal Plate Installation
ST-HL-AE-3628, Requests Waiver from Tech Spec 4.4.6.2.2d,extending 24 H Time Requirement to 72 H for Pressure Isolation Valve Leak Testing
B13615, Requests That 900705 Request for Amend to License DPR-61 Be Approved on Emergency Basis & That Temporary Waiver of Compliance from Tech Spec 4.4.6.2.1.g Be Given Until NRC Acts on Emergency Amend
L-2006-212, Reply to Request for Additional Information Steam Generator Tube Integrity Amendment Request
L-2006-089, Proposed License Amendment Steam Generator Tube Integrity
05000338/LER-1999-001-01, :on 990106,RCS Leak Rate Missed Surveillance Was Noted.Caused by Computer Malfunction.Computer Malfunction Affecting VCT & Pzr Level Inputs Was Corrected. with
05000454/LER-1985-083, :on 850820,RCS Water Inventory Surveillance Not Performed within Required Time Interval.Caused by Inadequate Review of Surveillances Listed on Surveillance Schedule. Shift Engineers Reprimanded.Event Reviewed
05000457/LER-1996-008-07, :on 960802,determined Containment Atmospheric Radiation Monitor Inoperable.Caused by Leak in Air Dryer. Removed Dryer from Service & Initiated Action Request for Troubleshooting and Repair
05000454/LER-1996-013-02, :on 960815,determined Atmospheric Radiation Monitor Alarm Setpoint Did Not Meet Design Criteria.Cause Unknown.Setpoint Changes Were Completed
05000498/LER-1990-017, :on 900706,determined That Personnel Failed to Adequately Perform Tech Spec Required Surveillance on Reactor Coolant Pressure Isolation Valves.Caused by Misinterpretation.Addl Training Provided
05000370/LER-1989-011-04, :on 890914,operations Personnel Logged Into Tech Spec 3.0.3 to Allow Leak Rate Testing of ECCS Check Valves.No Cause Assigned Since Station Voluntarily Entered Tech Spec.Personnel Aware of Sys Alignment
05000400/LER-1990-011-01, :on 900405,tech Spec Violation Occurred Due to Missed Leakage Tests on Valve.Caused by Procedural Deficiency.Appropriate Procedure Revised & Personnel Trained
05000400/LER-1998-005, :on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim Manner
HNP-99-149, Application for Amend to License NPF-63,implementing Selected Improvements Described in GL 93-05
05000400/LER-1990-011, :on 900405,Tech Spec Violation Occurred Due to Missed Tests on Valve.Caused by Procedural Deficiencies. Procedures Revised & Plant Personnel Trained
L-95-277, Forwards Third 10-Yr ISI Interval Inservice Testing Program for Pumps & Valves
05000389/LER-1993-002-02, :on 921201,missed Surveillance on RCS Pressure Isolation Check Valves Due to Procedural Deficiency. Deficiencies in SR Corrected to Include Precautions in Procedure
L-92-133, Forwards Addl Info on Anomaly 8 Re Relief Request VR-10,in Response to Request Made in Transmitting Safety Evaluation for Rev 2 of Facility IST Program
L-94-212, Frowards Rev 1 to JNS-PSL-204, Second Ten-Yr ISI Interval IST Program for Pumps & Valves,St Lucie Nuclear Power Plant Unit 2. Response to Open Items Noted in 930823 SE of IST Program Also Encl
B18732, Additional Information Technical Specification Change Request 3-11-01 Reactor Coolant System Operational Leakage
L-2021-231, Relief Request Number 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety
DCL-86-238, Forwards Rev 4 to Diablo Canyon Unit 1 Inservice Insp & Testing Program Plan & Rev 1 to Diablo Canyon Unit 2 Inservice Insp & Testing Program Plan. Response to Sser 31 & Justification for Changes Also Encl
A06401, Forwards Responses to Questions on Pumps & Valves Inservice Testing Program,Per 870602 & 03 Meetings
05000272/LER-1979-015-03, /03L-0 on 790212:during Normal Operation,Noted Required Surveillance to Be Performed Every 78-h Had Not Been Done on 790210 When Scheduled.Caused by Personnel Error.Entry Made in Log Instructing Supervisor