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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:OPERATIONS SUPPORT-CALCULATIONS
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 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 ML20058M1491992-04-15015 April 1992 Evaluation of 460-Volt Diesel Generator Cooling Pump Min Starting Voltage ML20058M1671992-04-15015 April 1992 Quad-Cities 2/II Safety-Related Continuous Load Running/ Starting Voltages 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 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) ML20247M2891987-04-0101 April 1987 Infiltration Analysis 1999-09-27
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SNitOUD REPAIR PROGRAM FOR b.
QU AD CITIES UNIT'2 Shroud Head Contact on Upper Support GENE-7711110695 REV. O
{ DRP# B13-01740 Back-sip Calculations for FDDR# EE2-0505 June 15,1995 Propssed By: 1d-
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.EEERIEGE
- 1. 718E816 Rev. 6 GE Shroud Head and Seperstors D'rawing
- 2. 112D6541 Rev. 4 GE Upper SupportLong Drawing
- 3. GENB 771-681094 Quad Cities Shroud and Repair REV.O Hartiware Stress Analysis 4 919D611P001 Rav. 4 Quad Cities GE Shroud Hand Bolt Drawing
- 5. 112D5487 Rev. 6 Quad Cities GE Reactor, Modl6 cation A le==He%
. Drawing
- 6. GENE-77169-1094 Basimp Calculations for Quad Cities Shroud Repair REV.1 Shroud Stress Raport DESCRIPTION During inarmilatian of the shroud head and separstors assen:bly at Quad Cities Unit 2, two of the !!fting rod estensions contacted two of the upper supports that are part of the shroud
=~IL9 cation assemblies. The purpose of this analysis is tojustify the a%uacy of the long upper support design to withstand the contact load from the shroud head and separators assembly.
} ANALYMS According to the sketch provided (Figure 1), the (3"x3.5") cross sectional area of the i support bears the highest stresses (banding and shear) due to the contact load (P).
! According to the refbrances 1 and 4 drawings, the shroud head and separators assembly i plus the 48 shroud head bolts weigh ((126.90 + (48) (0.312)] = 141.9 kips dry. In this
! calculation, it is assumed tbst half of the total dry weight of the assernbly (141.9/2) = 71 l kips, contacted one of the long upper supps at 103' and 283' azimuth loacations.
i Note that conservatively the eSiset of buoyw; is not considered.
5 According to the reference 2 drawing and the Figure 1 AUTOCAD sketch:
j MOMENT ARM = 1.70 in (distance fkorn rasctive fbrce) 2 SHEAR AREA = (3.0) (3.5) = 10.5 in i
! I(MOM. OF IN.) = (bh'/12) = [(3.5) (3.3)*]/12 = 7.88 in'
! C (TO N A) = (h/2) = (3.0/2) = 1.5 in i
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! GENE-771-111-0695 REV O j Thersibm, I
i SHEAR STRESS = (71.0y(10.5) = 6.8 kai .65m - (.6)(47.5)
= 28.5 losi 4
{ BENDING STRESS = [(71.0) (1.7) (1.5)y(7.9) = 22.9 kai 1.5.Sm ,
j =71.3kal
) The upper support matenalis X-750 (refersace 2) and the value of Sm = 47.5 kai is the
- minimum value of Sm at 550 4 per paragraph 3.3 of the reference 3 analysis. This is a j conservative -=y.k-5 since the actual value of Sm is higher The 1.5Sm limit is also
! from paragraph 5 of the reference 3 analysis. The .6Sm limit is from ASME Section III, i Subsection NO 3227.2,1989 Edition j Since this calculation shows the maximum stresses to be below their allowables, it is l mehuled that the actualloads om the two supports did not damage the cornponents.
J Note that tiue to the nature af the shroud modification design (idor .ee 5), the shroud j head and sapsrators assernbly load on the top of the long upper support could not be
- transferred dew z2o the lower components of the assembly (i.e. tie rod, yoke,....) causing .
{ axial compresave b% The shroud head load was reacted by the shroud fknge. l
} Note also that the airoud bearing strees of((71.0y(3.4 x 3.5)] = 6.0 kai is lower than the * ~
l
- allowable of Sy = 30 J kai at 1007. The beanns stress allowable is from ASME Section l l III Subsection NG4227.1,1989 Edition, and the value of Sy fbr 304 stainless xcel is from i Appendix I of the same ASME code. The dimensions for the bearing area are from the l reference 5 drawleg. '
i
- Furthermors, this compressive fbres on the shroud d!d rm cause an overstress condition in
! the top guide support piste. According to pages 17 and 18 of the reference 6 report, a j compresolve load of165.5 kips by the long upper supports creates a rnaximum Normal +
l Upset (OBE) stress of 22.0 kai. Thersfbre, the 71.0 kips compressive load on the shroud j created a lower stress in the top pide support plats and thus this loading is acceptable
- The lifting rod / lug assembly does not need to be svahmied since its designed fbaction is to j bear the contact loads each time it is used.
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FIGURE 1 I