Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210D8951999-07-23023 July 1999
Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020
ML20196J3081999-06-29029 June 1999
Safety Evaluation Supporting Amend 153 to License NPF-38
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
ML20195D5491999-06-0303 June 1999
Safety Evaluation Supporting Amend 151 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
ML20206A9641999-04-21021 April 1999
Safety Evaluation Supporting Amend 150 to License NPF-38
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
ML20203H8591999-02-17017 February 1999
Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3
ML20203H8151999-02-17017 February 1999
Safety Evaluation Supporting Amend 149 to License NPF-38
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
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
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
ML20154Q4831998-10-19019 October 1998
Safety Evaluation Supporting Amend 146 to License NPF-38
ML20153H3501998-09-24024 September 1998
Safety Evaluation Supporting Amend 145 to License NPF-38
ML20237C5661998-08-17017 August 1998
Safety Evaluation Accepting Licensee Request for Exemption from Section Iii.O of Appendix R to 10CFR50
ML20236S9031998-07-22022 July 1998
SER Accepting Rev 19 to Quality Assurance Program for Waterford Steam Electric Station,Unit 3
ML20236M9781998-07-10010 July 1998
Safety Evaluation Supporting Amend 144 to License NPF-38
ML20236K6371998-07-0202 July 1998
Safety Evaluation Supporting Amend 143 to License NPF-38
ML20217Q4671998-04-0808 April 1998
Safety Evaluation Supporting Amend 141 to License NPF-38
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)
ML20217H8531998-04-0101 April 1998
Safety Evaluation Supporting Amend 140 to License NPF-38
ML20217C0791998-02-23023 February 1998
Safety Evaluation Supporting Amend 139 to License NPF-38
ML20198R3921998-01-15015 January 1998
Safety Evaluation Supporting Amend 138 to License NPF-38
ML20198B3601997-12-18018 December 1997
Safety Evaluation Supporting Amend 137 to License NPF-38
ML20203E9371997-12-0909 December 1997
Safety Evaluation Granting Relief Request,Per 10CFR50.55a(g) (I)
ML20199J3291997-11-20020 November 1997
Safety Evaluation Supporting Amend 136 to License NPF-38
ML20199H3711997-11-19019 November 1997
SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50
ML20199D5701997-11-14014 November 1997
Safety Evaluation Supporting Amend 135 to License NPF-38
ML20216E9921997-09-0404 September 1997
Safety Evaluation Accepting 970623 Request for Relief Re Authorization for Use of ASME Code Case N-416-1 & N-532,ISI Program for Listed Plants
ML20217M7541997-08-19019 August 1997
Safety Evaluation Supporting Amend 133 to License NPF-38
ML20141H8411997-07-30030 July 1997
Safety Evaluation Accepting Use of Code Case N-508-1 for All Four Plants for Rotation of Serviced Snubbers & Pressure Relief Valves for Purpose of Testing in Lieu of ASME Code
ML20149E1611997-07-11011 July 1997
Safety Evaluation Supporting Amend 132 to License NPF-38
ML20148T8071997-07-0303 July 1997
Safety Evaluation Supporting Amend 131 to License NPF-38
ML20141F3881997-06-30030 June 1997
Safety Evaluation Authorizing Licensee Request for Extension of First ISI Interval to 970924
ML20140F8151997-06-11011 June 1997
Safety Evaluation Supporting Amend 130 to License NPF-38
ML20148H1271997-06-0505 June 1997
Supplemental Safety Evaluation Re Conformance to Reg Guide 1.97,Entergy Operations,Inc,Waterford Steam Electric Station Unit 3
ML20148D9891997-05-29029 May 1997
Safety Evaluation Supporting Amend 129 to License NPF-38
ML20141G4851997-05-20020 May 1997
Safety Evaluation Supporting Amend 128 to License NPF-38
ML20137Z4561997-04-21021 April 1997
Safety Evaluation Supporting Amend 126 to License NPF-38
ML20137U2451997-04-11011 April 1997
Safety Evaluation Supporting Amend 125 to License NPF-38
ML20137R9391997-04-10010 April 1997
Safety Evaluation Supporting Amend 124 to License NPF-38
ML20147E0951997-02-13013 February 1997
Safety Evaluation Supporting Amend 123 to License NPF-38
ML20134K9321997-02-12012 February 1997
Safety Evaluation Supporting Amend 122 to License NPF-38
ML20149M4221996-12-12012 December 1996
Safety Evaluation Supporting Update Insvc Insp Programs to 1992 & Portions of 1993 ASME Boiler & Pressure Vessel Code, Sect XI for Licenses DPR-51,NPF-6,NPF-38,NPF-29 & NPF-47. Technical Ltr Rept Encl
ML20129E7661996-09-27027 September 1996
Safety Evaluation Supporting Amend 121 to License NPF-38
ML20112G5131996-06-0505 June 1996
Safety Evaluation Supporting Amend 119 to License NPF-38
ML20107F5611996-04-17017 April 1996
Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request
1999-07-23
[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
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
ML20211Q2141999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With
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
ML20210S0581999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Waterford 3.With
ML20210Q6361999-07-31031 July 1999
Corrected Monthly Operating Rept for July 1999 for Waterford 3
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
ML20210D8951999-07-23023 July 1999
Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020
05000382/LER-1999-007-01, :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
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
ML20196J3081999-06-29029 June 1999
Safety Evaluation Supporting Amend 153 to License NPF-38
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
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
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
ML20203H8151999-02-17017 February 1999
Safety Evaluation Supporting Amend 149 to License NPF-38
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
1999-09-30
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