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| | 1 I OUISIANA 342 OeunoNoe srneer POWER & LIGHT P O BOX 6008 |
| | * NEW ORLEANS. LOUISIANA 70174 * (5041 366-2345 UTiuS$EsNU April 5, 1984 W3K84- 0814 Q-3-A35.07.99 Mr. John T. Collins Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 |
| | |
| | ==REFERENCE:== |
| | LP&L letter W3K84-0433 dated February 29, 1984 |
| | |
| | ==Dear Mr. Collins:== |
| | |
| | gg |
| | |
| | ==SUBJECT:== |
| | Waterford SES Unit No. 3 / |
| | Docket No. 50-382 gl3g Significant Construction Deficiency No. 99 |
| | " Safety Injection Tank (SIT) Isolation Valve" , p Second Interim Report The above referenced letter indicated submittal of an Interim or Final Report to the USNRC on April 6, 1984. |
| | At the present time, we are awaiting vendor response to his inspection conducted on March 27, 1984. This response is scheduled for mid April 1984. |
| | The Final Report will be submitted to the USNRC on April 27, 1984. |
| | Very truly yours, V |
| | T. F. errets Corporate Quality Assurance Manager TFG:CNH:VBR cc: Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 8404190111 840405 PDR ADOCK 05MMB2 m y{Ofl 8__. m p |
| | |
| | e d, % |
| | I Mr. John T. Collins April 5, 1984 W3K84-0814 Page 2 |
| | -cc: Director Office of Management |
| | -Information and Program Control U._S.. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. E. L. Blake Shaw, Pittman,'Potts & Trowbridge 1800 M Street, N.W. |
| | Washington, D.C. 20036 Mr. W. M. Stevenson Monroe & Lemann 1424. Whitney Building New Orleans, Louisiana 70130. |
| | Mr. W. A. Cross 7910 Woodmont Avenue Suite-1200 Bethasda, Maryland 20814 v |
| | ) |
| | w |
| | : s. . |
| | {''.}} |
Latest revision as of 20:59, 13 May 2020
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|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20207M9231999-03-12012 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
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML18065B1351998-01-0606 January 1998
Part 21 Rept Re Use of Deltstrat Code for RCS Flow Rate Determination.Code Corrects for Temps to Determine Hot Leg Bulk Coolant Temp
ML20203J2521997-12-0101 December 1997
Deficiency Rept Re Failed Mdr Relays at Entergy Operations Inc,Waterford 3 Nuclear Generation Station.Caused by Contaminated Grease.Housekeeping Procedures Formalized & Added Enclosed Booth Isolating Mdr Final Assembly
LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997
Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201
LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997
Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys
LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997
Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004
ML20140A9661997-05-29029 May 1997
Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum
ML18065B0111996-10-18018 October 1996
Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology
ML20117K9731996-09-10010 September 1996
Follow-up Part 21 Rept of Re Failures of Waterford 3 Dedication Testing Process of Seven Commercial Grade Barksdale Pressure Switches
ML20116C7031996-07-29029 July 1996
Part 21 Rept Re Failures Identified by Waterford 3 Dedication Testing Process of 7 Commercial Grade Barksdale Pressure Switches
ML20117G4641996-05-14014 May 1996
Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs
LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996
Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power
ML20077D3431994-11-29029 November 1994
Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods
ML20078G3051994-11-0909 November 1994
Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept
LD-94-019, Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info1994-03-16016 March 1994
Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info
LD-93-177, Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested1993-12-23023 December 1993
Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested
LD-93-003, Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared1993-01-13013 January 1993
Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared
ML20126J5961992-12-31031 December 1992
Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl
ML20125C7161992-12-0707 December 1992
Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl
ML20127M5201992-11-24024 November 1992
Final Part 21 Rept Re Reject Lot Serial Numbers of Defective Fuel Nozzle Tips,Consisting of Corrected Page 6 of 921102 Rept Re Reject Lots for Fuel Injector Assembly
ML20127P5861992-11-23023 November 1992
Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl
ML20115D6331992-10-15015 October 1992
Part 21 Rept Re Nuclear Logistics Inc 10CFR21 Notification for Gnb Industrial Battery Co Batteries.Util Will Obtain Replacement Batteries from C&D Power Sys,Inc & Alarm Features to Be Tested by End of Refuel 5
ML20118B4391992-09-11011 September 1992
Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option
ML20101Q9311992-07-0808 July 1992
Part 21 Rept Re Failure to Comply w/1 Minute Rating of NCX-17 Cells Mfg by Gnb Battery Co (Formally Gould).Addl Testing of Cell Sizes & End Voltages Scheduled to Begin on 920713 & Be Completed on 920815
L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl1991-01-0404 January 1991
Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl
ML17223A7451990-01-26026 January 1990
Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N
ML20246P7111989-07-17017 July 1989
Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available
ML20247P7991989-04-0404 April 1989
Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area
ML20234C7351987-06-23023 June 1987
Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station
ML20211P7211987-02-23023 February 1987
Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly
ML20215G6801986-10-10010 October 1986
Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing
ML20215G5351986-10-10010 October 1986
Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing
ML20153D8861986-02-17017 February 1986
Part 21 Rept Re Failure of Penetration & Conduit Seal Configurations During Fire Tests.Initially Reported on 860214.Evaluation of Number & Location of Defective Seals in Progress.Nrc Assistance Requested
ML20140A5281985-12-19019 December 1985
Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl
ML20135E1161985-09-0505 September 1985
Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl
W3P85-1442, Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e)1985-08-0101 August 1985
Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e)
ML20133G9741985-07-31031 July 1985
Part 21 Rept Re Anchor/Darling Valve Co Swing Check Valves W/Loose Set Screws &/Or Missing Lock Welds,Reported by Palo Verde Nuclear Generating Station.All Customers W/Similar Valves Notified.Ltr Re Waterford 3 Valves Encl
W3P85-1420, Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Submittal of Written Rept on Deficiency Rescheduled for 8508011985-06-27027 June 1985
Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Submittal of Written Rept on Deficiency Rescheduled for 850801
W3P85-1400, Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time Needed to Evaluate Deficiency. Next Rept Will Be Submitted by 8507011985-05-29029 May 1985
Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time Needed to Evaluate Deficiency. Next Rept Will Be Submitted by 850701
ML20128G5101985-05-24024 May 1985
Part 21 Rept Re Heat Numbers to Be Added & Deleted from Sublist Sheet A,Based on Review of NRC
W3P85-1240, Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Written Rept Submittal Date Extended Until 8505311985-04-29029 April 1985
Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Written Rept Submittal Date Extended Until 850531
W3P85-0785, Interim Deficiency Rept 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Required. Submittal of Written Rept Rescheduled for 8504301985-03-25025 March 1985
Interim Deficiency Rept 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Required. Submittal of Written Rept Rescheduled for 850430
W3P85-0551, Significant Const Deficiency Rept 93 Re Charging & Letdown Containment Isolation Valve.Potential Exists for Valve to Stick Open Due to Thermal Contraction.Testing Under Temp Conditions Being Performed1985-03-0606 March 1985
Significant Const Deficiency Rept 93 Re Charging & Letdown Containment Isolation Valve.Potential Exists for Valve to Stick Open Due to Thermal Contraction.Testing Under Temp Conditions Being Performed
W3P85-0544, Supplemental Final Significant Const Deficiency 93 Re Failure of Containment Isolation Valve CVC-103 to Close After Plant Cooldown.Details Will Be Provided on Valve Failure When Info Obtained1985-02-27027 February 1985
Supplemental Final Significant Const Deficiency 93 Re Failure of Containment Isolation Valve CVC-103 to Close After Plant Cooldown.Details Will Be Provided on Valve Failure When Info Obtained
W3P85-0509, Interim Rept of Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Needed.Next Rept Delayed Until 8503291985-02-26026 February 1985
Interim Rept of Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Needed.Next Rept Delayed Until 850329
W3P85-0337, Final Significant Const Deficiency Rept SCD-80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply shut-off Valves.Pneumatic Operators for Valves 2MS-V611A & V612 Replaced w/D-C Motors1985-02-22022 February 1985
Final Significant Const Deficiency Rept SCD-80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply shut-off Valves.Pneumatic Operators for Valves 2MS-V611A & V612 Replaced w/D-C Motors
W3P85-0339, Final Significant Const Deficiency Rept SCD-93 Re Charging & Letdown Containment Isolation Valve Deficiency.Vendor Repaired Valve W/New Seats Sized for Max Interference Fit1985-02-21021 February 1985
Final Significant Const Deficiency Rept SCD-93 Re Charging & Letdown Containment Isolation Valve Deficiency.Vendor Repaired Valve W/New Seats Sized for Max Interference Fit
W3P85-0338, Final Part 21 & Const Deficiency Rept SCD-37 Re Unreliable Temp Signals from Resistance Temp Detectors (Rtd).Initially Reported on 810710.Safety-related RTDs Replaced or Environmentally Sealed.Design Change Notice Issued1985-02-21021 February 1985
Final Part 21 & Const Deficiency Rept SCD-37 Re Unreliable Temp Signals from Resistance Temp Detectors (Rtd).Initially Reported on 810710.Safety-related RTDs Replaced or Environmentally Sealed.Design Change Notice Issued
W3P85-0083, Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Safety-related & Environmentally Qualified Equipment Manuals to Be Reviewed.Next Rept Anticipated by 8502281985-01-14014 January 1985
Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Safety-related & Environmentally Qualified Equipment Manuals to Be Reviewed.Next Rept Anticipated by 850228
1999-03-12
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999
Drill 99-08 Emergency Preparedness Exercise on 991013
ML20217G7211999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with
ML20211Q2141999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With
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
ML20210D8951999-07-23023 July 1999
Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020
ML20209H3781999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Waterford 3 Ses. with
ML20195J8951999-06-17017 June 1999
Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii)
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
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
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
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
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
ML20203H8591999-02-17017 February 1999
Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3
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
ML20199C9101998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Waterford 3.With
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
ML20195E5161998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Waterford 3.With
ML20155C1351998-10-26026 October 1998
Rev B to Entergy QA Program Manual
ML20154K0801998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Waterford 3 Ses. with
ML20151W8331998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Waterford,Unit 3. with
ML20237B6831998-08-17017 August 1998
LER 98-S01-00:on 980723,discovered That Waterford 3 Physical Security Plan,Safeguards Document Was Not Under Positive Control of Authorized Person at All Times.Caused by Human Error/Inappropriate Action.Counseled Employee Involved
ML20237C5661998-08-17017 August 1998
Safety Evaluation Accepting Licensee Request for Exemption from Section Iii.O of Appendix R to 10CFR50
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML20237B5261998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Waterford 3
ML20236S9031998-07-22022 July 1998
SER Accepting Rev 19 to Quality Assurance Program for Waterford Steam Electric Station,Unit 3
ML20198H3911998-07-14014 July 1998
Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool
ML20236N4181998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Waterford,Unit 3
ML20248E7781998-06-0101 June 1998
Annual Rept on Abb CE ECCS Performance Evaluation Models
ML20249A4711998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Waterford 3 Ses
ML20196A4051998-05-31031 May 1998
Rept of Facility Changes,Tests & Experiments,Per 10CFR50.59 for 970601-980531. with
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)
ML20247F6761998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Waterford,Unit 3.W/
ML20217M8951998-04-30030 April 1998
QA Program Manual
ML20217P8281998-04-0707 April 1998
Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i)
ML20216B1751998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Waterford 3 Ses
ML20217M1411998-03-0303 March 1998
Rev 2 of Waterford 3 Cycle 9 Colr
1999-09-30
[Table view] |
Text
,
1 I OUISIANA 342 OeunoNoe srneer POWER & LIGHT P O BOX 6008
- NEW ORLEANS. LOUISIANA 70174 * (5041 366-2345 UTiuS$EsNU April 5, 1984 W3K84- 0814 Q-3-A35.07.99 Mr. John T. Collins Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
REFERENCE:
LP&L letter W3K84-0433 dated February 29, 1984
Dear Mr. Collins:
gg
SUBJECT:
Waterford SES Unit No. 3 /
Docket No. 50-382 gl3g Significant Construction Deficiency No. 99
" Safety Injection Tank (SIT) Isolation Valve" , p Second Interim Report The above referenced letter indicated submittal of an Interim or Final Report to the USNRC on April 6, 1984.
At the present time, we are awaiting vendor response to his inspection conducted on March 27, 1984. This response is scheduled for mid April 1984.
The Final Report will be submitted to the USNRC on April 27, 1984.
Very truly yours, V
T. F. errets Corporate Quality Assurance Manager TFG:CNH:VBR cc: Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 8404190111 840405 PDR ADOCK 05MMB2 m y{Ofl 8__. m p
e d, %
I Mr. John T. Collins April 5, 1984 W3K84-0814 Page 2
-cc: Director Office of Management
-Information and Program Control U._S.. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. E. L. Blake Shaw, Pittman,'Potts & Trowbridge 1800 M Street, N.W.
Washington, D.C. 20036 Mr. W. M. Stevenson Monroe & Lemann 1424. Whitney Building New Orleans, Louisiana 70130.
Mr. W. A. Cross 7910 Woodmont Avenue Suite-1200 Bethasda, Maryland 20814 v
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