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Category:ARCHIVE RECORDS
MONTHYEARML20217K7641999-09-27027 September 1999 Rev 0 to DCR 990247, Containment Overpressure Duration Requirement (Addendum to Calculation QDC-1000-M-0781) ML20217K7441999-04-23023 April 1999 Rev 1 to QDC-0010-M-0396, Quad Cities Station Unit 2:ECCS Strainer Head Loss Estimates ML20155A6741998-09-29029 September 1998 Rev 1 to Calculation QDC-1000-M-0454, Short Term Rhr/Core Spray Pump NPSH Analysis - Design Basic Loca ML20155B5221998-09-29029 September 1998 Rev 1 to QDC-1000-M-0535, Long-Term Rhr/Core Spray Pump NPSH Analysis - Design Basis Loca IA-97-451, Plant Issues Matrix1997-12-0909 December 1997 Plant Issues Matrix ML20203J7501997-12-0909 December 1997 Plant Issues Matrix ML20135B8021996-12-0606 December 1996 Press Release III-96-073, Quad Cities Nuclear Plant Rated 'Good' in Two Areas, 'Acceptable' in Two Areas in NRC Performance Assessment ML20199K6041996-12-0303 December 1996 Rev 1 to 93C2806.3-C002, Cable Tray & Conduit Raceway Limited Analytical Review (LAR) for USI A-46 at Quad Cities Nuclear Station. Page 71 of 98 of Incoming Submittal Not Included ML20101Q7541996-04-0808 April 1996 Rev 3 to Calculation 9200-E0-S,demonstrating That Reduction of Torsional Loads from Auxiliary Steel Will Significantly Reduce IC Values for Beam & Connections ML20106J7921996-04-0404 April 1996 Calculation for Checking Functional Status of Beam B4 & Cheek Plate Connection at Right End of Beam B10 in Quad Cities,Unit 1 Southeast,Rhr Corner Room ML20101Q0581996-03-30030 March 1996 Flaw Evaluation for 02BS-F14 Weld in Quad Cities Unit 1 Loop B Recirculation Sys ML20101Q0481996-03-19019 March 1996 Flaw Evaluation for 02AS-S4 Weld in Quad Cities Unit 1 Loop a Recirculation Sys ML20101Q0271996-03-18018 March 1996 Flaw Evaluation for 02AS-F2 Weld in Quad Cities Unit 1 Loop a Recirulation Sys ML20101Q0361996-03-11011 March 1996 Flaw Evaluation for 02AD-F12 Weld in Quad Cities Unit 1 Loop a Recirculation Sys ML20086E0891995-07-0303 July 1995 Shroud Head Contact on Upper Support ML20091G3461995-06-15015 June 1995 Rev 0 to Shroud Repair Program for Quad Cities Unit 2, Shroud Head Contact on Upper Support ML20091G3561995-06-15015 June 1995 Rev 0 to Shroud Repair Program for Quad Cities Unit 2, Shroud Head Contact on Upper Support ML20101E8161993-11-22022 November 1993 Power Recovery Probabilities for Quad Cities Ipe ML20126G1021992-12-17017 December 1992 Rev 0 to RSA-D-92-07, LPCI Room Temperature Response Due to Loss of Room Cooler at Dresden Station ML20058M1641992-11-18018 November 1992 Quad-Cities 2/I Safety-Related Continuous Load Running/ Starting Voltages ML20058M1451992-07-31031 July 1992 Quad-Cities 1/I Safety-Related Continuous Load Running/ Starting Voltages ML20101Q7661992-06-16016 June 1992 RHR Pump 1C/1D Discharge Line 1-1008B-18 ML20058M1711992-05-20020 May 1992 Second-Level Undervoltage Relay Setpoint ML20058M1581992-05-0404 May 1992 Quad-Cities 1/II Safety-Related Continuous Load Running/ Starting Voltages ML20058M1541992-04-20020 April 1992 Evaluation of Toshiba Dgcwp Starting Voltage ML20058M1671992-04-15015 April 1992 Quad-Cities 2/II Safety-Related Continuous Load Running/ Starting Voltages ML20058M1491992-04-15015 April 1992 Evaluation of 460-Volt Diesel Generator Cooling Pump Min Starting Voltage ML20058M1741992-04-0303 April 1992 Evaluation of DG 2 Cooling Water Pump Cooler Fan a & B Min Starting Voltage ML20065S8691990-11-16016 November 1990 Draft Setpoint Calculation for RPS Turbine Control Valve Fast Closure Trip Function ML20247R3711989-09-18018 September 1989 Package of Three FOIA Requests ML20247M2831988-01-11011 January 1988 Rev 1 to Quad Cities,Control Room Dose Analysis,Plot of Dose as Function of Standby Gas Treatment Sys Effluent ML20247M3191987-09-24024 September 1987 Control Room Dose Analysis, (Suppl to Dose Calculation 546Y-M-07) ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20247M2891987-04-0101 April 1987 Infiltration Analysis ML20212P1571987-02-28028 February 1987 News Release Informing That Util Selected Wastechem Corp as Prime Contractor for Processing & Disposal of 55 Control Rod Blades from Facilities Spent Fuel Pools.Responsibilities Include Radiation Monitoring & Waste Disposal ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML19316A8861980-03-25025 March 1980 Slide Presentation Entitled, Barrier Fuel Program. ML20084L6921967-05-0505 May 1967 Wire Svc Press Release Re Wall Collapsing on 670505. Undetermined Number of Men Injured & Trapped Under Debris 1999-09-27
[Table view] Category:PHOTOGRAPHS & SLIDES
MONTHYEARML19316A8861980-03-25025 March 1980 Slide Presentation Entitled, Barrier Fuel Program. 1980-03-25
[Table view] |
Text
. ._ __ - - . - _ _ . _ _ __ . - . -. . _.. . .-
.e ,-
BARRIER FUEL PROGRAM i
DEVELOP FUEL MORE RESISTANT TO PCI DOE SPONSORED PROGRAM BEGINNING IN 1977 i -
EXTENSIVE PREVIOUS RESEARCH TWO POTENTIAL DESIGNS IDENTIFIED o COPPER BARRIER i
I o ZIRCONIUM LINER l
i e
JC:sLx/1327 3/25/80 8005280 89 %
PROGRAM STATUS EXTENSIVE TESTS TO VERIFY PCI RESISTANCE HAVE BEEN PERFORMED.
DESIGNS TESTED UNDER SIMULATED ACCIDENT CONDITIONS, FOUR ASSEMBLIES OPERATING IN QUAD CITIES 1.
DEMONSTRATION NUCLEAR DESIGN COMPLETED, PREPARED TO LICENSE AND MANUFACTURE DEMONSTRATION RELOAD M
JC: JLK/1328 3/25/80 l
MEETING PURPOSE PROVIDE BACKGROUND INFORMATION ON PROGRAM o TEST RESULTS o PLANNED DEMONSTRATION o EDIS0N VIEWPOINT i OBTAIN AGREEMENT ON DEMONSTRATION LICENSING DOCUMENTATION AND SCHEDULE, i
l l
- JC:atx/1329 3/25/80 1
T 7.~.
r BARRIER FUEL PRESENTATION AGENDA l l W
, . INTRODUCTION J. S. CHARNLEY PROGRAM DESCRIPTION AND STATUS H. S. ROSENBAUM EDISON PERSPECTIVE D. R. O'B0YLE CONCLUSION J. S. CHARNLEY SCHEDULE AGREEMENT NRC JC:atK/1330 ~
3/25/80
r i
- DEMONSTRATION FUEL DESIGN ZIRCONIUM LINER SELECTED I
o TWO PURITY LEVELS f
i o SAME AS TWO QUAD CITIES 1 ASSEMBLIES i
COMPARIS0N TO CURRENT P8 x 8R DESIGN o 3 MIL LINER, METALLURGICALLY BONDED l o EXTERIOR DIMENSIONS SAME o INSIDE TUBE DIAMETER SAME o ZIRCONIUM PHYSICAL, CHEMICAL AND NUCLEAR PROPERTIES SIMILAR TO ZIRCALOY o SOME BUNDLES OF SLIGHTLY HIGHER ENRICHMENTS FOR DEMONSTRATION l
MINOR CHANGE IN i FUEL DESIGN JC: JLK/1331 3/25/80 l
l
4 4
LICENSING PERSPECTIVE 7
, MINOR CHANGE IN FUEL DESIGN
q' 3, P0TENTIAL TECH. SPEC CHANGE FOR E0C LOCALIZED POWER RAMPS ph ECCS LIMITS FOR NEW FUEL TYPE ,
'J- NO REVISIONS TO SAFETY ANALYSES METHODOLOGY
JC: JLK/1332 3/25/80
DEMONSTRATION RELOAD LICENSING TWO-PHASE LICENSING o GENERIC PROGRAM DOCUMENT o PLANT / CYCLE UNIQUE LICENSING GENERIC DOCUMENT APPROVAL
< o CONSISTANT WITH QUAD CITIES 2 CYCLE 6 o EDISON DECISION DATE o MANUFACTURING REQUIREMENTS 4
JC: Jtx/1333 3/25/80
MR cTA GENERIC PROGRAM DOCUMENT _ t m . <T ,-> i' N SIMILAR IN SCOPE TO RELOAD LTR INCLUDE DEMONSTRATION DESCRIPTION
~
REFERENCE GENERIC RELOAD LTR WHERE APPLICABLE o SAFETY ANALYSIS METHODOLOGY o APPLICABLE ANALYTICAL RESULTS PROVIDE INFORMATION/ ANALYTICAL RESULTS DIFFERENT FROM THE GENERIC RELOAD LTR w
o INTERNAL FUEL CLADDING GE0 METRY - NO CREDIT FOR LINER STRUCTURAL STRENGTH o STANDARD ENRICHMENT RELATED INFORMATION o LINER MATERIAL PROPERTIES AS REQUIRED o RELEVANT LTA/ TEST INFORMATION o ADDITIONAL MANUFACTURING QUALITY ASSURANCE
~
JC: JLK/1334 3/25/80
SCllEDULE F0il GENERIC APPROVAL NRC SUBMITTAL MAY 1980 3 APPROVAL REQUIRED OCTOBER 1980 l
PLANT / CYCLE UNIQUE SCHEDULE BEGINS NOVEMBER 1980 m
JC:stx/1340 3/25/80 t
w - o a = s m.., e
,. , m - + + - - - - -
, PLANT / CYCLE UNIQUE LICENSING AMEND'ECCS REPORT ECCS/ DEMONSTRATION TECH SPEC, REVISIONS -
STANDARD CYCLE UNIQUE LICENSING e
I JC: JLK/1341 3/25/80 -
i
' - +es - eeew ew = .* eg-e. -e .
-eme eM-- .w- w e - e eem .
- ,, .