ML20205F271
From kanterella
| ML20205F271 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, 05000000 |
| Issue date: | 08/31/1985 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20205F242 | List: |
| References | |
| NEDO-24146A-ERR, NEDO-24146A-ERR-14, NUDOCS 8511050275 | |
| Download: ML20205F271 (11) | |
Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20198R2331997-04-30030 April 1997
[Table view]Rev 2 to Quad Cities Unit 2 Cycle 145 Reload Analysis ML20198T3251997-04-18018 April 1997 Non-proprietary Rev 1 to EMF-96-180, Quad Cities Unit 2 Cycle 15 Plant Transient Analysis ML20078E5171995-01-25025 January 1995 Correction to Encl 3, Equivalent Margin Analysis Plant Applicability Verification Form of Topical Rept NEDO-32205-A,Rev 1 ML20078D8611995-01-0505 January 1995 Shroud Repair Seismic Analysis ML20078A7451994-06-30030 June 1994 Evaluation of Indications Found at H5 Weld Location in Quad Cities Unit 1 Shroud ML17187A8051993-01-31031 January 1993 Suppl 1 to GENE-770-26-1092, Long Term Containment Response to DBA-LOCA w/65 Fdegrees F Svc Water Temperature,80 Degrees F Initial Pool Temperature & Initiation of Containment Cooling at 1800 Seconds. ML17252A7531992-11-30030 November 1992 Lpci/Containment Cooling Sys Evaluation. ML20065Q8531990-11-30030 November 1990 Rev 0 to, Comm Ed Topical Benchmark of BWR Nuclear Design Methods ML20006A8231990-01-10010 January 1990 Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 ML19332E4071989-10-16016 October 1989 Errata & Addendum 1 to, Safety Evaluation to Justify Operation W/Loss of Jet Pump Flow Indication for Quad Cities 1 & 2. ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML19325C9131989-03-31031 March 1989 Safety Evaluation to Justify Operation W/Loss of Jet Pump Flow Indication for Quad Cities,Units 1 & 2. ML20235M9111989-02-20020 February 1989 Nonproprietary Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue ML20207L7781988-10-0606 October 1988 Nonproprietary WCAP 11936, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue ML20154M2421988-09-30030 September 1988 Simulate-3 Validation & Verification ML20207L9261988-09-30030 September 1988 Nonproprietary Addendum 2 to COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment (Response to NRC Questions) ML20154A4131988-07-13013 July 1988 Extended Operating Domain/Equipment Out-of-Svc Analysis for Dresden Units 2 & 3 ML20154J9831988-04-30030 April 1988 RCS Flow Anomaly Investigation Rept ML20147F4101988-02-0909 February 1988 Rev 49 to CE-1-A, QA Program for Nuclear Generating Stations ML20237C4091987-11-30030 November 1987 Nonproprietary Rev 2 to Byron/Braidwood T-Hot Reduction Final Licensing Rept ML20154A4021987-09-28028 September 1987 LOCA-ECCS Analysis for Dresden Units During Single Loop Operation W/Advanced Nuclear Fuels Corp Fuel ML20235C4871987-07-31031 July 1987 Extended Operating Domain & Equipment Out-of-Svc for Quad Cities Nuclear Power Station Units 1 & 2. B Wolfe Affidavit Also Encl ML20235C4331987-06-30030 June 1987 Rev 0 to Suppl Reload Licensing Submittal for Quad Cities Nuclear Power Station Unit 1,Reload 9 ML18149A5121986-11-30030 November 1986 Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code. ML20207H9761986-11-30030 November 1986 Nonproprietary Resistance Temp Detector Bypass Elimination Licensing Rept for Byron 1 & 2 & Braidwood 1 & 2 ML20210A6051986-09-0505 September 1986 Addendum a to Vol II of Nusco 140-2, Nusco Thermal Hydraulic Model Qualification ML20155J4911986-05-31031 May 1986 Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block ML20155J5231986-05-31031 May 1986 Rev 1 to Functional Design Requirement for Core Protection Calculator ML20155J5051986-05-31031 May 1986 Rev 1 to Functional Design Requirements for Control Element Assembly Calculator ML20203G5481986-03-31031 March 1986 Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs ML20151Z0641986-01-31031 January 1986 Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines ML20151Z0521986-01-31031 January 1986 Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure ML20140A6821985-12-31031 December 1985 Reactor Vessel Fluence & Ref Temp for Pressurized Thermal Shock Evaluations ML20138M4211985-09-30030 September 1985 Justification for Raising Setpoint for Reactor Trip on High Pressure, Transient Assessment Program ML20135H9491985-08-31031 August 1985 Rev 1 to Reload Nuclear Design Methodology ML20135A5571985-08-31031 August 1985 B&W Owners Group Cavity Dosimetry Program ML20205F2711985-08-31031 August 1985 Errata & Addenda Sheet 14,replacing Pages v/vi,3-2,4-3,4-10, 4-15 & 4-16 to, LOCA Analysis Rept for Dresden Units 2,3 & Quad Cities 1,2 Nuclear Power Stations ML20134N3021985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Core Protection Calculator ML20134N2941985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Control Element Assembly Calculator ML17346B1711985-07-31031 July 1985 Retran Code Transient Analysis Model Qualification. ML20133H3591985-07-31031 July 1985 Statistical DNBR Evaluation Methodology ML20138P1541985-07-0202 July 1985 Rev 1 to TMI-1 Nuclear Generating Station Natural Circulation Cooldown Analysis W/O Reactor Vessel Upper Head Void Formation, Topical Rept ML20127K1381985-06-30030 June 1985 Nuclear Physics Methodology for Reload Design ML20128Q2751985-05-31031 May 1985 Revised Nomad Code & Model ML20129E9881985-05-30030 May 1985 VEPCO Reactor Sys Transient Analysis Using Retran Computer Code ML20106A6481985-01-31031 January 1985 Errata & Addenda Sheet 13,replacing Pages v/vi,3-2,4-3, 4-15 & 4-16 to, LOCA Anaysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations ML20111C1171985-01-31031 January 1985 Rev 1 to Comprehensive Vibration Assessment Program for Palo Verde Nuclear Generating Station Unit 1 (Sys 80 Prototype),Evaluation of Predictions & Pre-Core Hot Functional Measurement & Insp Programs ML20137F0331985-01-15015 January 1985 Rev 1 to Criticality Safety Analysis,Dresden 2,3 Spent Fuels Storage Pool W/Exxon Nuclear Co,Inc 9x9 Reload Fuel ML18142A1531984-12-31031 December 1984 Nonproprietary Version of Revised VEPCO Evaluation of Control Rod Ejection Transient. ML17298B5401984-11-30030 November 1984 Summary Rept on Operability of Shutdown Cooling Sys Relief Valves for Palo Verde Units 1,2 & 3. 1997-04-30 Category:TEXT-SAFETY REPORT MONTHYEARML20217A9931999-09-30030 September 1999
[Table view]NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data SVP-99-204, Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With SVP-99-155, Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety ML20195G6381999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With SVP-99-123, Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206N2821999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with1999-04-30030 April 1999 Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with SVP-99-104, Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20207D2341999-03-0101 March 1999 Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205 ML20207M6921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With1999-01-31031 January 1999 Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199D3261998-12-31031 December 1998 10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.With ML20199C8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20197G8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 ML20196C8731998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station ML20196C8391998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 SVP-98-364, Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With1998-10-31031 October 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With ML20195D2861998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.With 1999-09-30 |
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