Summary of Plant-Specific Crane Data, Revision 1 to App B Suppl,Supplied for Facility Auxiliary Bldg Crane ModML19305E864 |
Person / Time |
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Site: |
Fort Calhoun ![Omaha Public Power District icon.png](/w/images/6/6a/Omaha_Public_Power_District_icon.png) |
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Issue date: |
02/19/1980 |
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From: |
Clark C EDERER, INC. |
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To: |
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Shared Package |
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ML19305E842 |
List: |
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References |
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EDR-1-APP-B, EDR-1-APP-B-R1, NUDOCS 8005200545 |
Download: ML19305E864 (8) |
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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20199L9181997-12-31031 December 1997 Rev 0 to Final Rept CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Tech Specs LIC-93-0270, Evaluation of Upper Shelf Energy for Combustion Enginering Nuclear Steam Supply Systems Reactor Pressure for Sept 19931993-09-30030 September 1993 Evaluation of Upper Shelf Energy for Combustion Enginering Nuclear Steam Supply Systems Reactor Pressure for Sept 1993 ML20138D3181993-01-31031 January 1993 Nonproprietary OPPD Nuclear Analysis,Reload Core Analysis Methodology,Neutronics Design Methods & Verification ML20138D3351993-01-31031 January 1993 Nonproprietary OPPD Nuclear Analysis Reload Core Analysis, Methodology Transient & Accident Methods & Verification ML20092H9731992-01-13013 January 1992 Westinghouse ECCS Evaluation Model for Analysis of CE-NSSS & Results of Large & Small Break LOCA Analyses for Fort Calhoun Unit 1 ML20091C7541991-07-31031 July 1991 Nonproprietary, Westinghouse ECCS Evaluation Model for Analysis of C-E NSSS, Topical Rept ML20077K0651991-06-30030 June 1991 Nonproprietary Augmentation Factor Elimination for Westinghouse Fuel in Fort Calhoun ML20082E9561991-06-30030 June 1991 Nonproprietary Westinghouse Reload Fuel Mechanical Design Evaluation for Fort Calhoun Station Unit 1 ML20073H2411991-04-11011 April 1991 Control Element Assembly Ejection Accident Methodology Summary Rept ML20073H2271991-03-31031 March 1991 Nonproprietary Westinghouse Reload Fuel Mechanical Design for Fort Calhoun Station,Unit 1 ML20073H2441991-02-28028 February 1991 Rept on Analysis Methods & Evaluation Models to Be Employed in Large Break & Small Break LOCA Analyses for Fort Calhoun, Unit 1 ML20135A9301985-08-31031 August 1985 Nonproprietary Suppl 1 to Statistical Combination of Uncertainties, Parts 1-3 ML20077L7511983-05-31031 May 1983 Evaluation of Impact of Thermal Shield Support Sys Failure in Ft Calhoun Reactor ML20050E1231982-03-31031 March 1982 Effects of Vessel Head Voiding During Transients & Accidents in C-E Nsss. ML20039F8581981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Fort Calhoun Reactor Vessel. ML19345E9811980-08-28028 August 1980 Evaluation of Irradiated Capsule W-225,Reactor Vessel Matls Irradiation Surveillance Program, Revision 1 ML19338E9491980-07-18018 July 1980 to Exxon Nuclear Co Setpoint Methodology for C-E Reactors. ML19305E8641980-02-19019 February 1980 Summary of Plant-Specific Crane Data, Revision 1 to App B Suppl,Supplied for Facility Auxiliary Bldg Crane Mod ML19305E8741980-02-11011 February 1980 Summary of Regulatory Positions to Be Addressed by Applicant, App C Suppl Submitted for Auxiliary Bldg Refueling Area Crane ML19296B4481980-01-31031 January 1980 Revised Limiting Large Break LOCA Analyses for Fort Calhoun Using ENC WREM-IIA PWR ECCS Evaluation Model, Supplement 1 ML19246B7941979-06-25025 June 1979 Exxon Nuclear Co Setpoint Methodology for C-E Reactors. ML19246B7881979-05-29029 May 1979 LOCA Analyses at 1,500 MW Using Exxon Nuclear Co WREM-IIA PWR ECCS Evaluation Model,Large Break Example Problem. 1999-05-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 LIC-98-0136, Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With ML20155G4261998-09-30030 September 1998 Performance Indicators for Sept 1998 ML20154A1251998-08-31031 August 1998 Performance Indicators, Rept for Aug 1998 LIC-98-0122, Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With ML20238F7231998-08-17017 August 1998 Owner'S Rept for Isis ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 1999-09-30
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s P. O. BOX 24708, SEATTLE. WA 98124 k '] 2331 FIRST AVE. S., SEATTLE, WA 98134 e 206 4224421 5200 8 l______.-- _, -.y&} SUBSIDIAR Y OF FORMAC INTERNATIONAL., INC.
DESIGNERS AND MANUFACTURERS OF CRANES AND HEAVY MACHINERY SINCE 1901 O
APPENDlX B SUPPLEMENT TO GENERIC LICENSING TOPICAL REPORT .
EDR-1
SUMMARY
OF PLANT SPECIFIC CRANE DATA SUPPLIED BY EDERER INCORPORATED FOR OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION AUXILIARY BUILDING CRANE MODIFICATION
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REVISION 1 2/19/80 Approved j, C. W. Clark, Jr. / 1 Engineering Manager ,
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Revision 1 2/19/80 EDR-l APPENDIX B SUPPLEMENT ,
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SUMMARY
OF PLANT SPECIFIC CRANE DATA SUPPLIED BY EDERER FOR FORT CALHOUN STATION AUXILIARY BUILDING CRANE MODIFICATION TABLE OF CONTENTS AND REVISION STATUS I
Description Pope No. Revision Title Page i 1 2/19/80 1 Table of Contents and Revision Status ii 1 2/19/80
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Topical Report Section Ill.C(C. I .a) 1 0 2/15/80 lli.C(C.I.b) I
!!!.C(C.2.b) & Ill.E.4 l Ill.C(C.3.e) 2 1 2/19/80
.,. Ill.C(C.3.h) 2 lil.C(C.3.i) 3 _ _ _ ._
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Ill.C(C.3.j) 3 .
Ill.D. I 4 1 2/19/80 l Ill.D.2 5 1 2/19/80 lil.D.3 5 Ill.D.5 5 Ill.D.6 5 lil.F. I ,
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Revision 0 .2/IS/80 -
Page I of 6 EDR-l APPENDIX B SUPPLEMENT ,-
SUMMARY
OF PLANT SPECIFIC CRANE DATA SUPPLIED BY EDERER -
FOR FORT CALHOUN STATION AUXILIARY BUILDING CRANE MODIFICATION Regulatory Topical
- Posit,on Report Information to be Provided Specific Crane Dato i
Section C. I .o Ill.C (C.I.a) 1. The octual crone duty classifi- 1. The crane will have o Class A-1 cation of the crone specified by crone duty classification in accor-
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the applicant. dance with CMAA Specification //70.
C.I.b lil.C(C.I.b) 1. The minimum operating tem- 1. The rainimum operating temperature perature of the crane specified fc- We crone is S0 degrees F.
by the opplicant. -
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C.2.b lil.C (C.2.b) 1. The maximum extent of load I. The crane will be designed such that Ill.E.4 motion and the peak kinetic the maximum load motion following o energy of the load fol.'nwing a drive train failure is less than i foot drive train failure. and the maximum kinetic energy of the load is less than that resulting from I inch of free fall of the maxi-mum critical load.
- 2. Provisions for actuating the 2. Provisions for automatically actuat-Emergency Drum Broke prior to ing the Emergency Drum Broke prior traversing with the load, when to traversing with the load are not required to accomodate the load required since the maximum amount
, motion following a drive train. of load motion and kinetic energy con
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failure. be accommodated by the facility design.
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R: vision i 2/19/80 .'
Paga 2 of 6 EDR-1 APPENDIX B SUPPLEMENT .
SUMMARY
OF PLANT SPECIFIC CRANE DATA SUPPLIED BY EDERER FOR FORT CALHOUN STATION AUXILIARY BUILDING CRANE MODIFICATION Topical otory Report Information to be Provided Specific Crone Data Section C.3.e Ill.C (C.3.e) 1. The maximum cable loading fol- 1. The maximum cable loading following
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lowing c oire rope failure in a wire rope failure will be less than terms of the acceptance criteria the maximum allowed by the accept-established in Section Ill.C once criterio established in Section (C.3.e.) lil.C (C.3.e). In addition, the lead line stress with all ropes intact does not exceed 10% of the published breal<ing strength of the rope while hoisting the maximum critical load. ,
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C.3.h lil.C (C.3.h) 1. The maximum extent of motion I. The crane will be designed such that
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lil.E.1 I and peak kinetic energy of the the maximum load motion following a load following a single wire rope single wire rope failure is less than failure. one foot end the maximum kinetic energy of the load is less than that resulting from one inch of free fall of the maximum critical load.
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Revision i 2/19/80 - -
Page 3 of 6 EDR-1 APPENDIX B SUPPLEMENT *
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SUMMARY
OF PLANT SPECIFIC CRANE DATA SUPPLIED BY EDERER FOR FORT CALHOUN STATION AUXILIARY BUILDING CRANE MODIFICATION Topicci Specific Crane Data
'Y Report Information to be Provided h,*,9"I
Section The type of load control system I. GE Maxspeed 320 using silicon con-C.3.i Ill.C (C.3.i) 1.
trolled rectifiers with provisions to specified by the applicant.
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limit the maximum speed, when carrying critical loods, to 5 feet per minute.
- 2. Whether interlocks are recom- 2. The crane will not be used to lif t fuel mended by Regulatory Guide elements from the reactor core or 1.13 to prevent trolley and spent fuel rocks. Therefore, inter-bridge movements while fuel locks to prevent trolley and bridge elements are being lifted and movements while hoisting are not whether they are provided for provided.
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this application.
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- 1. The maximum calculated machinery lli.C (C.3.j) 1. The maximum cable and mo-C.3.J chinery loading that would result loading that would result in the event in the event of a high speed two of a two blocking at the hoist's maxi-blocking, assuming a control sys- mum speed (3 times the 5 foot /
minute maximum critical load speed),
tem malfunction that would allow the full breakdown torque assuming a control system malfunc-of the motor to be applied to the tion that would allow the full break-
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drive motor shaf t.
down torque of the motor to be applied to the drive motor shaft, will not exceed 3 times the design rated loading. In addition, the EATL design prevents the maximum cable loading during the above described two-blocking from exceeding the accept-
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once criterio established in Section
~ lli.C (C.3.e) of the Topical Report.
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Page 4 cf 6 EDR-l APPENDIX B SUPPLEMENT - -
SUMMARY
OF PLANT SPECIFIC CRANE DATA SUPPLimD BY EDERER ,
- FOR FORT CALHOUN STATION AUXILIARY BUILDING CRANE MODIFICATION Reg atory Topical Report Information to be Provided Specific Crone Data Section
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Ill.D.I 1. The type of Emergency Drum 1. A single pneumatically released bond Broke used, including type of broke will be used.
release mechanism.
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- 2. The relative location of the 2. The Emergency Drum Brake will en-Emergency Drum Broke. gage the wire rope drum.
- 3. Emergency Drum Broke Copa- 3. The Emergency Drum Broke will have city. a minimum capacity of 130% of that required to hold the design rated load.
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Ill.D.2 1. Number of friction surfaces in i. The EATL will have between 17 and EATL. 21 friction surfaces.
- 2. EATL Torque Setting. 2. The EATL torque setting will be at approximately 130% of the design rated load.
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EDR-1 APPENDIX B SUPPLEMENT ,
- SUMMAP.Y OF F LANT SPECIFIC CRANE DATA SUPPLIED BY EDERER FOR FORT CALHOUr'siATION AUXILIARY BUILDING CRANE MODIFICATION Regul ory Topical
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Report 1:1 formation to be Provided Specific Crane Dato Section
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Ill.D.3 1. Type of Foilu e Detection Sys- 1. An electro-mechanical Failure tem. Detection System will be provided.
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Ill.D.5 1. Type of Hydraulic Load Equali- 1. The Hydraulic Lood Equalization zotion System. System will include both features described in this section.
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lil.D.6 1. Type of hook. 1. A dual load path hook will be used.
- 2. Hook design load. 2. The hook design load will be 75 tons with a 5:1 factor of safety on ulti-mate (3:1 on 10% of yield) on each
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lo ad path.
- 3. Hook test load. 3. T1e test lood for each hook load path v ill be 150 tons.
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Ill.F.I 1. Design rated food. 1. 75 Tons
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- 2. Maximum critical load rating. 2. 75 Tons
- 3. Trolley weight (net). 3. Less than 90,000 !br.(! :h; ding hook)
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Rcvision i 12/19/80 - -
Page 6 ef 6 EDR-I APPENDIX B SUPPLEMENT , ,
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SUMMARY
OF PLANT SPECIFIC CRANE DATA SUPPLIED BY EDERER .. .
FOR FORT CALHOUN STATION AUXILIARY BUILDING CRANE MODIFICATION *
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Topical Regulatory Position Report Information to be Provided Specific Crone Data Section ,
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Ill.F. I 4. Trolley weight (with food). 4. 240,000 lbs.
, S. Hook lif t. 5. 60' 6"
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- 6. Number of wire rope drums. 6. I
- 7. Number of ports of wire rope. 7. 2 ropes with 8 parts each
- 8. Drum size (pitch diameter). 8. 56.5" ,
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- 9. Wire rope diemeter. 9. i 04"
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- 10. Wire rope type. 10. 6x37 class IWRC ll. Wire rope material. I 1. Stainless steel.
- 12. Wire rope breaking strength. 12. 117,000 pounds
- 13. Wire rope yield strength. 13. 70,200 pounds
- 14. Wire rope reserve strength. 14. o minimum of 60%
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- 15. No. wire ropes. 15. 2
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