Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial RT Ndt ML20236U4751998-07-23023 July 1998 SG Eddy Current Insp Rept Cycle 7 Refueling Outage (B2R07) ML20198J5641998-01-0707 January 1998 Unit 2 Pressure & Temp Limits Rept ML20198J5061998-01-0707 January 1998 Pressure Temp Limits Rept (Ptlr) ML20198J5201998-01-0707 January 1998 Pressure Temp Limits Rept (Ptlr) ML20198J5531998-01-0707 January 1998 Unit 1 Pressure & Temp Limits Rept ML20199E8801997-11-0303 November 1997 Revised Byron Unit 2 Pressure Temperature Limits Rept (PTLR) ML20199E8751997-11-0303 November 1997 Revised Byron Unit 1 Pressure Temperature Limits Rept (Ptlr) ML20217G6171997-07-22022 July 1997 Operability Assessment Process Form ML20141K0241997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0431997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0181997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0371997-05-21021 May 1997 Pressure & Temp Limits Rept ML20148P8811997-05-16016 May 1997 Spent Fuel Rack Criticality Analysis Using Soluble B Credit ML20141F7141997-05-15015 May 1997 Operability Assessment Process Form ML20134M3131996-11-13013 November 1996 Revised SG Tube Rupture Analysis for Byron/Braidwood ML20134N8011996-10-31031 October 1996 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20134N3131996-10-31031 October 1996 Sys Design Description for Containment Spray ML20129F8921996-09-30030 September 1996 Circumferential Indication Summary Rept ML20129G3881996-08-31031 August 1996 Unit-1 EOC 7B Interim Plugging Criteria Rept ML20113B0951996-06-30030 June 1996 Interim Plugging Criteria Return to Power Rept ML20101E7651996-03-31031 March 1996 Unit - 1 EOC 7A Interim Plugging Criteria Rept ML20095G0691995-12-31031 December 1995 Interim Plugging Criteria Return to Power Rept ML20093G7171995-10-12012 October 1995 Rev 0 to PSA-B-95-18, RELAP5M3 Comparison of Model Boiler 2 MSLB from Hzp Test ML20093G8821995-10-11011 October 1995 Rev 0 to PSA-B-95-17, Calculation of Byron 1/Braidwood 1 D4 SG Tube Support Plate Loads w/RELAP5M3 ML20092A9731995-09-0101 September 1995 Independent Verification of Byron/Braidwood D4 SG Tube Support Plate Differential Pressures During Mslb ML20091M8711995-08-25025 August 1995 Rept of Independent Assessment of Calculation of TSP Forces ML20078P1551995-02-0606 February 1995 Probability of Detection by Bobbin Insp ML20078G8351995-01-25025 January 1995 Probability of Detection by Bobbin Insp ML20078F1861995-01-20020 January 1995 Refuel Outage B1R05 RHR HX Nozzles Ultrasonic Indication Summary ML20078G9431995-01-19019 January 1995 EOC 6 Interim Plugging Criteria Rept ML20078R1161994-11-15015 November 1994 Non-proprieatry NFSR-0090, Response to Nuclear Regulatory Staff Request for Addl Info on VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 Fuel ML20149H1591994-06-30030 June 1994 Spent Fuel Rack Criticality Analysis Considering Boraflex Gaps & Shrinkage ML20035G4861993-04-22022 April 1993 Safety Analysis, Responses to NRC RAI on Ceco PWR Transient Analysis Methodology ML20127L0091992-09-0808 September 1992 Rev 0,to VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 Fuel ML20087E0451992-01-0909 January 1992 UHS Design Basis Reconstitution Final Rept ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20082K7641991-08-22022 August 1991 Simulator Initial Certification Rept,Sept 1991 ML20064N8021991-07-27027 July 1991 Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation ML20101F5631991-07-0303 July 1991 Byron/Braidwood Unit 1 Rhr/Safety Injection Piping Water Hammer Acoustic Analysis L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation1990-10-31031 October 1990 Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation ML20042E9131990-03-31031 March 1990 Nonproprietary Rev 1 to Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe 1999-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N3711999-10-13013 October 1999 Safety Evaluation Supporting Amends 111,111,104 & 104 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations 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 ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With 05000454/LER-1998-005, :on 980307,reactor Manually Tripped.Caused by Indeterminate Rod Sequencing Problem.Halted Rod Insertion & Exercised Bank Overlap Thumbwheel Switch to Clean Contacts. with1999-08-20020 August 1999
- on 980307,reactor Manually Tripped.Caused by Indeterminate Rod Sequencing Problem.Halted Rod Insertion & Exercised Bank Overlap Thumbwheel Switch to Clean Contacts. with
ML20211A8131999-08-10010 August 1999 Safety Evaluation Supporting Amends 110 & 110 to Licenses NPF-37 & NPF-66,respectively ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML17191B4101999-07-27027 July 1999 Safety Evaluation Accepting Alternative to Licenses NPF-72, NPF-77,NPF-37,NPF-66,NPF-19,NPF-25,NPF-11,NPF-18,DPR-29 & DPR-30,respectively ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) 05000454/LER-1999-003-02, :on 990513,automatic Reactor Occurred Due to Human Error During Surveillance Procedure.Appropriate Mgt Action Taken with Instrument Maint Involved & Sp Bsir 3.1.6-200 Revised.With1999-06-11011 June 1999
- on 990513,automatic Reactor Occurred Due to Human Error During Surveillance Procedure.Appropriate Mgt Action Taken with Instrument Maint Involved & Sp Bsir 3.1.6-200 Revised.With
05000454/LER-1999-002-03, :on 990509,missed TS Surveillance Was Noted. Caused by Error in Design Package.Changed Monthly Surveillance Procedure for Containment Isolation Valves1999-06-0808 June 1999
- on 990509,missed TS Surveillance Was Noted. Caused by Error in Design Package.Changed Monthly Surveillance Procedure for Containment Isolation Valves
ML20207E8891999-06-0202 June 1999 Safety Evaluation Supporting Amends 109,109,102 & 102 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station 05000454/LER-1999-001-05, :on 990422,depressing Both Feedwater Isolation Reset Pushbuttons Leads to LCO 3.0.3 Entry.Caused by Implementation Error in Procedure Review for Conversion to Its.Review of Procedures Will Be Conducted1999-05-21021 May 1999
- on 990422,depressing Both Feedwater Isolation Reset Pushbuttons Leads to LCO 3.0.3 Entry.Caused by Implementation Error in Procedure Review for Conversion to Its.Review of Procedures Will Be Conducted
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 ML20206G6031999-05-0303 May 1999 Safety Evaluation Supporting Amends 108,108,101 & 101 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively ML20206R6991999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) ML20206B5531999-04-23023 April 1999 Safety Evaluation Supporting Amends 107,107,100 & 100 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively ML20205N9241999-03-31031 March 1999 Analysis of Capsule X from CE Byron Unit 2 Rv Radiation Surveillance Program ML20205P7001999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20204G3831999-03-19019 March 1999 Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 ML20206A8831999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function1999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function 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 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20204C7671999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With ML20199C9721999-01-31031 January 1999 Non-proprietary Version of Rev 1 to WCAP-15123, Analysis of Capsule W from Commonwealth Edison Co Byron Unit 1 Reactor Vessel Radiation Surveillance Program ML20196K6731998-12-31031 December 1998 10CFR50.59 Summary Rept for 1998 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20202F6021998-12-31031 December 1998 Cycle 9 COLR in ITS Format & W(Z) Function ML20202F6181998-12-31031 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function ML20199E6371998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Byron Station,Units 1 & 2.With ML20199G8271998-12-31031 December 1998 Rev 1 Comm Ed Byron Nuclear Power Station,Unit 1 Cycle 9 Startup Rept ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20198N3831998-12-30030 December 1998 SER Accepting Second 10-yr Interval ISI Program Plan & Associated Request for Relief for Plant,Units 1 & 2 05000454/LER-1998-020-01, :on 981118,analysis Error in Boron Dilution Protection Sys Code Identified.Caused by Personnel Error. Replacement of Bdps Function with Volume Control Tank Level Monitoring & Operator Actions Evaluated1998-12-17017 December 1998
- on 981118,analysis Error in Boron Dilution Protection Sys Code Identified.Caused by Personnel Error. Replacement of Bdps Function with Volume Control Tank Level Monitoring & Operator Actions Evaluated
1999-09-30
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