Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20195C3041999-05-28028 May 1999
Annual Rept on ABB CE ECCS Performance Evaluation Models
ML20204H1401999-03-23023 March 1999
Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3
ML20204H2451999-03-22022 March 1999
Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3
ML20204H1231999-03-22022 March 1999
Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping
ML20198H3911998-07-14014 July 1998
Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool
ML20248E7781998-06-0101 June 1998
Annual Rept on ABB CE ECCS Performance Evaluation Models
ML20198H4681998-05-20020 May 1998
Non-proprietary Rev 1 to HI-981942, Independent Review of Waterford Unit 3 Spent Fuel Pool Cfd Model
ML20247A3891998-05-0101 May 1998
SG Eddy Current Examination (8th Refueling Outage)
ML20199F5831998-01-29029 January 1998
Errata Change Pages for Rept HI-971628,for Section 8.6.1.2 & Table 8.1.Change Pages Submitted to Assure Consistency Between LAR & Calculations Performed for SFP Structural Analysis
ML20198H4641998-01-28028 January 1998
Non-proprietary Rev 1 to HI-91700, Dynarack Validation Manual
ML20141G7081997-07-0505 July 1997
To Rept on Vortexing in Condensate Storage Pool
ML20140F1491997-04-16016 April 1997
Rev 3 to 10CFR50.59 Safety Evaluation
ML20137G2141997-03-27027 March 1997
Non-proprietary Version of Licensing Rept for Reracking of Waterford 3 Sfps
ML20094H4141995-11-0303 November 1995
Thermo-Lag Installed to Tested Fire Barrier Evaluation (GL 86-10 Evaluation)
ML20086T3561995-07-31031 July 1995
Individual Plant Exam for External Events
ML20094H4001995-05-30030 May 1995
Pyrolysis Gas Chromatography Analysis of 3 Thermo-Lag Fire Barrier Samples
ML20078F1001995-01-31031 January 1995
Summary of Waterford 3 Criticality Safety Analysis for Fuel Enrichments Above 4.1 W/O U-235 Taking Credit for Fixed Burnable Poisons
ML20078Q2951994-11-0909 November 1994
3 Ses Tsc/Osc Tabletop 4,941109
ML20078Q3111994-11-0707 November 1994
3 Ses EOF Tabletop 4,941107
ML20078Q2851994-10-12012 October 1994
3 Ses Tsc/Osc Tabletop 3,941012
ML20078Q3051994-10-10010 October 1994
3 Ses EOF Tabletop 3,941010
ML20078Q2741994-09-20020 September 1994
3 Ses Tsc/Osc Tabletop 2,940920
ML20078Q3021994-08-15015 August 1994
3 Ses EOF Tabletop 2,940815
ML20078Q2731994-05-25025 May 1994
3 Ses Tsc/Osc Tabletop 1,940525
ML20078Q3001994-05-23023 May 1994
3 Ses EOF Tabletop 1,940523
ML20062M1441993-12-29029 December 1993
Section 6.0 of Development of RCS Pts...& Recommended Surveillance Withdrawal Schedule for Waterford Unit 3
ML20059D3971993-10-31031 October 1993
Rev 0 to Development of RCS Pressure Temp Limits for 20 EFPYs (Fluence = 2.29 X 10(19) n/cm(2)) & Recommended Surveillance Withdrawal Schedule for Waterford Unit 3, Final Rept
ML20198H3711991-11-12012 November 1991
Non-proprietary HI-91700, Dynarack Validation Manual
ML20086C4241991-09-0505 September 1991
Design Engineering Program Assessment Executive Summary
ML20073K8451991-03-31031 March 1991
Entergy Nuclear Performance Rept,Mar 1991
ML20199F5531991-03-31031 March 1991
Chin Shan Analyses Show Advantages of Whole Pool Multi-Rack Approach, from Nuclear Engineering International,Mar 1991
ML20072R2261991-03-20020 March 1991
3 Plant Ref Simulator Certification Package
ML20056A7301990-06-30030 June 1990
Basemat Monitoring Program Special Rept 3
ML20246P2561989-07-31031 July 1989
Compliance W/10CFR50.62 Reduction of Risk from ATWS Events
ML20245J5071989-07-31031 July 1989
Unit 3 Control Element Assembly Drop Time Tech Spec Change Justification
ML20155E1311988-10-31031 October 1988
Compliance W/10CFR50.62,Reduction of Risk from ATWS Events
ML20207L2881988-09-30030 September 1988
Basemat Monitoring Program,Special Rept 2, from Inception to Aug 1988
ML20155B7181988-09-0909 September 1988
Rev 1 to Louisiana Power & Light Co Response to US-NRC Bulletin 88-005
ML20154D0571988-09-0909 September 1988
Actions Completed by Louisiana Power & Light Co
ML20151F1771988-06-30030 June 1988
1987 SALP Progress Rept Updated June 1988
ML20195G8941988-06-20020 June 1988
MSIV Guide Rail Failure Final Rept
ML20151B7901988-03-31031 March 1988
1987 SALP Progress Rept
W3P87-1746, Emergency Preparedness Exercise1987-10-14014 October 1987
Emergency Preparedness Exercise
ML20234C1501987-07-31031 July 1987
Basemat Summary Rept
ML20214M5571987-05-27027 May 1987
Draft Waterford 3 Nuclear Plant Island Structure Basemat Summary Rept. W/Two Oversize Figures
ML20198H4061987-04-30030 April 1987
Non-proprietary HI-87113, Evaluation of Fluid Flow for In- Phase & Out-of-Phase Rack Motions
ML20198H4421987-04-0707 April 1987
Non-proprietary HI-87112, Fluid Flow in Narrow Channels Surrounding Moving Rigid Bodies
ML20198H4121987-04-0707 April 1987
Non-proprietary HI-87114, Estimated Effects of Vertical Flow Between Racks & Between Fuel Cell Assemblies
ML20198H4371987-01-14014 January 1987
Non-proprietary HI-87102, Study of Non-Linear Coupling Effects
ML20215N4601986-10-0101 October 1986
Program to Perform Confirmatory Analyses,Nuclear Plant Island Structure Basemat:Results of Analyses
1999-05-28
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999
Drill 99-08 Emergency Preparedness Exercise on 991013
05000382/LER-1999-014, :on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B1999-10-12012 October 1999
- on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B
ML20217G7211999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with
05000382/LER-1999-013, :on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included1999-09-23023 September 1999
- on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included
05000382/LER-1999-012-01, :on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With1999-09-13013 September 1999
- on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With
ML20211Q2141999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With
05000382/LER-1999-011-01, :on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B1999-08-31031 August 1999
- on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B
05000382/LER-1999-010-01, :on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity1999-08-26026 August 1999
- on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity
05000382/LER-1999-009-01, :on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established1999-08-26026 August 1999
- on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established
ML20210Q6361999-07-31031 July 1999
Corrected Monthly Operating Rept for July 1999 for Waterford 3
ML20210S0581999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Waterford 3.With
05000382/LER-1999-008-01, :on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-021999-07-29029 July 1999
- on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-02
05000382/LER-1999-007-01, :on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff1999-07-23023 July 1999
- on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff
ML20210D8951999-07-23023 July 1999
Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020
05000382/LER-1999-006-01, :on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With1999-07-14014 July 1999
- on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With
ML20209H3781999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Waterford 3 Ses. with
05000382/LER-1999-005-01, :on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested1999-06-24024 June 1999
- on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested
ML20195J8951999-06-17017 June 1999
Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii)
ML20195J9741999-06-16016 June 1999
Safety Evaluation Supporting Amend 152 to License NPF-38
ML20207E8631999-06-0303 June 1999
Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3
ML20195D5491999-06-0303 June 1999
Safety Evaluation Supporting Amend 151 to License NPF-38
ML20195K3391999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Waterford 3 Ses.With
ML20195C3041999-05-28028 May 1999
Annual Rept on ABB CE ECCS Performance Evaluation Models
05000382/LER-1999-004-02, :on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing1999-05-14014 May 1999
- on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing
ML20206S7401999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Waterford 3.With
ML20205T2621999-04-22022 April 1999
LER 99-S02-00:on 990216,contract Employee Inappropriately Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Security Personnel Performed Review of Work & Work Area That Individual Was Involved with
ML20206A9641999-04-21021 April 1999
Safety Evaluation Supporting Amend 150 to License NPF-38
05000382/LER-1999-003-02, :on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With1999-04-0909 April 1999
- on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With
ML20205N9671999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Waterford 3 Ses.With
ML20205E8531999-03-30030 March 1999
Corrected Pages COLR 3/4 1-4 & COLR 3/4 2-6 to Rev 1, Cycle 10, Colr
ML20205A6331999-03-25025 March 1999
SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3
05000382/LER-1999-002-03, :on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired1999-03-25025 March 1999
- on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired
ML20204H1401999-03-23023 March 1999
Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3
ML20204H1231999-03-22022 March 1999
Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping
ML20204H2451999-03-22022 March 1999
Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3
ML20204F0791999-03-17017 March 1999
Rev 1 to Waterford 3 COLR for Cycle 10
ML20207M9231999-03-12012 March 1999
Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results
ML20207F3491999-03-0505 March 1999
LER 99-S01-00:on 990203,contraband Was Discovered in Plant Protected Area.Bottle Was Determined to Have Been There Since Original Plant Construction.Bottle Was Removed & Security Personnel Performed Search of Area.With
ML20204B5141999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Waterford 3.With
ML20203H8151999-02-17017 February 1999
Safety Evaluation Supporting Amend 149 to License NPF-38
ML20203H8591999-02-17017 February 1999
Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3
05000382/LER-1999-001, :on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With1999-02-0404 February 1999
- on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With
ML20202H9161999-02-0202 February 1999
Safety Evaluation Supporting Amend 148 to License NPF-38
ML20199H6261999-01-21021 January 1999
Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change
05000382/LER-1998-020, :on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With1998-12-31031 December 1998
- on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With
ML20199C9101998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Waterford 3.With
ML20198F4691998-12-21021 December 1998
Safety Evaluation Supporting Amend 147 to License NPF-38
ML20196F4911998-12-0101 December 1998
SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2
ML20206N4131998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Waterford 3.With
ML20195C4841998-11-0606 November 1998
SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program
1999-09-30
[Table view] |
