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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
[Table view] |
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RCV BY: CONI ED . U-10-05 . 12:06 . ENC BLDG-. :#25 l , JUN 15 '95 0781GPM GE" NUCLEm EFERGY p.17 i
s SHROUD REPAIR PROGRAM PCR QU AD CITIES UNIT 2 Shroud Head Coatnet on Upper Support GENE-771113-0695 REV. O DRF# B13-01740 Back up Calculations with Impact Factor for FDDR# EE2-0505 Jens 18,1MS M
Prepared By: 7 L- - -
Plant Design Engineer (as yg p 2 .
Veetiled By: /F' F IN MikaFetter Reesear sad Plant Deelen Enginearlag Appened By: L M 8varney Pn@eet Manspor p 4
9507100070 950619 PDR ADOCK 05000254 P PDR
RCV BY:COM ED . 6-19-95 . 12:07 ENC BLDG- :02G
, JUN 15 '95 07:17PM GE NUCLEFA DERGY p,gg GENE-771-113 0695 REV. 0 N CES
- 1. 718B316D + o OE Shroud Head and Separators Drawing
- 2. I 12D6541.._/. 4 OE Upper support Long Drawing
- 3. GENE-771-631094 Quad Chies Shroud and Repair REV.O Hardware Strees Analysis
- 4. 919D611P001 Rev. 4 Quad Cities GE Shmud Head Bok Drawing
- 5. 112D5487 Rev. 6 Quad Cities GE Reactor, ModiScation & Installation Drawing
- 6. GENE-771691094 Backup Calculations fbr Quad Cities Shroud Repair REV.1 Shroud Stress Report QESCRIPI1ON During installation of the shroud head and separators assembly at Quad Cities Unit 2, two of the !!fting rod extenslocs contacted two of the upper suppens that are part of the shroud modification assemblies. The purpose of this analysis is tojustify the adequacy of the long upper support design to withstand the contact load than the shroud head and separators assembly.
ANALYSIS l According to the sketch provided (71gure 1), the (3"x3.5") cross sectional area of the support bears the highest stresses (banding and shest) due to the contact load (P).
According to the refbrances I and 4 J...ir.gs, the shroud head and separators assembly plus the 48 shroud head boks weigh ((126.90 + (48) (0.312)] = 141.9 kips dry. In this calculadon, it is assumed that the total dry weight of the assembly impacted one of the long upper suppens at 103' and 2s3' azimuth locations. Using an impact fhetor of 1.25, the total load on the support is conscrystively assumed to be (141.9 x 1.25) = 177.40 kips.
According to the reference 2 drawing and the Figure 1 AUTOCAD sketch:
MOMENT ARM = 1.70 in (distance from mestive force)
SHEAR AREA = (3.0)(3.5) = 10.5 in' 8
f 1 (MOM. OF IN.) = (bh /12) = [(3.5) (3.0)'j/12 = 7.88 in' C (TO N A) = (h/2) = (3.0/2) = 1.5 in l
RCV BY:C0\1 ED + O-10-95 . 12:08 ENC BLIXi-. :027
, JtN 85 '95 078t"/PM GE NUQ.E M EERGY o,19 GENE-771 113-0695 REV. 0 Therehm, SHEAR STRESS = (177.4y(10,5) = 16.9 kai < .68g = (.6)(47.5)
= 28.5 kai BENDING STRESS = [(177.4) (1.7) (1.5)y(7.9) = 57.3 kpl < l.5 Sm
= 71.3 kai The upper support materialis X-750 (mbranos 2) and the value of Sm = 47.5 kai is the minimum value of Se at 550 *P per paragraph 3.3 of the rebrance 3 analysis. The 1.5Sm limit is alto estreated Som peregraph 5 of the schrence 3 analysis. The .6Sm ilmit is from ASME Section M EM= NB-3227.2,1989 Edition.
Since this conservative calculadora shows the maximum stresses to be below dwir allowables, it is ==4ul=I that the actual loads on tb two supports did not damage the compoesnts.
Note that dos to the nature of the shroud modi 6eedon design (reference 5), the shroud head and separator masambly load on top of the long upper support could not be transfered down into the lower componeasts of the ansamhly 0.e. tie red, yoke.....) causins axial compressive loading. The shroud head load was reacted by the sluoud flange.
Note also that the abroud bearing stress of((177.4y(3.4 x 3.5)) = 14.91 kaiis lower than the bearing allowable of Sy = 30.0 kai at 100*F The bearing stress allowable is from ASME Section M Subasadon NG 3227.1,1989 Edition, and the value of Sy for 304 is tom Appendix I of the same ASME code. The dimensions for the beanng area can be found in the rehrence 5 drawing.
Furthermore, this cornpressive fbrce on the shroud did not cause an overstress condition in the top Suide support plate. AcescOg to pages 17 and 18 of the reference 6 report, a ccsv.eeive load of 165.5 kips by the long upper supports creates a maximum Norrnal +
Upset (OBE) stress of 22.0 kal. Therefbre, the 177.4 kips compressive load on the shroud has crested approsdmately ([(177.4y(165.5)](22.0)) = 23.58 kst stress in the top guide support plass. This vabe is lower than the allowable of 1.55m = (1.5)(20.0) = 30.0 kai and thus it is acceptable. The 5m value of 20.0 kai ibt 304 shroud is kom Appendix I of the ASME Section M, Division 1.
RCV BY:C0\1 ED 6 10-05 : 12:09 ENC BLDG. :#20
, AN 15 '95 07817PM GC ttG.E@ DEPGY P.20 Mwr 771-113-0805 REV.0 s .
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RCV BYiCOM ED' '0 7 10'-US~ + 12:09 .
ENC BLDd-. " #29 Sw N-oos-k Criteria Used to determine Impact fhetor.
References:
- 1. Whiting Crane Handbook. Whiting Corporation,1979.
- 2. Response to Request for Information on the Control ofHeavy Loads, Nov.
1981, Rev 1. Section 2.1.7.c no.13, page 2.1-12. Issued in response to Generic Letter 81-07.
- 3. AISC Code Section 1.3.3 Reference I and 2 providejustification for the use of1/2% impact for each ft per minute of crane speed with a minimum of 15%. The maximum crane speed for the reactor building 125 Ton c.rane ia 5 feet per minute. This would result in an impact factor of !
2.5%. Reference 3 also r=w=nanda the use of25% as the impact factor for traveling I cranes and supports. Hence the use of 25% in the analysis for affect on the core shroud l
repair hardware is conservative as these values provide additional margin above required l
loads.
Prepared by: f Beardsley / /8-Desisn hei- ~
Approved b -
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