Revised Comparison Between CMAA-70 & EOCI-61ML20069G638 |
Person / Time |
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Site: |
North Anna |
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Issue date: |
03/01/1983 |
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From: |
BECHTEL GROUP, INC. |
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To: |
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Shared Package |
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ML20069G628 |
List: |
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References |
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REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8303280110 |
Download: ML20069G638 (4) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20249C0011997-11-30030 November 1997 Reactor Vessel Fluence Analysis Methodology ML20148E7091997-05-31031 May 1997 Vols 1 & 2 to Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Ors,Usi A-46, Per GL 87-02 ML18151A7101996-09-30030 September 1996 Supplemental Info for VA Power Nomad Code & Model. ML20249C4051996-05-16016 May 1996 Rev 0 to CE-0082, Review of Augmented ISI Frequency for Pressurizer Spray Lines ML20249C4031996-04-23023 April 1996 Rev 0 to CE-0081, Review of Augmented ISI Frequency for Reactor Coolant Bypass Lines ML20092A2611995-08-31031 August 1995 EDG Preventive Maint Insp Outage Probabilistic Safety Assessment for August 1995 ML20078P9261994-09-26026 September 1994 Service Water System Operational Performance Assessment 940711-29 ML18153B4221993-07-31031 July 1993 Rev 11 to Engineering Evaluation 25, Evaluation of Existing Fire Enclosure Around Ventilation Duct,North Anna Power Station. ML18153B4211993-07-31031 July 1993 Rev 11 to Engineering Evaluation 24, Evaluation of Radiant Energy Shields,North Anna Power Station. ML20046D1581993-02-28028 February 1993 Virginia Power Sys Transient Analysis Using Version 1 of North Anna Retran Model. ML18152A0711993-02-0101 February 1993 NFPA Heat & Flame Evaluation of MSA Custom 4500 SCBA Using Enriched O2 Breathing Air for VA Power,Final Rept. ML20116A2901992-09-23023 September 1992 Conceptual Engineering Final Rept NP-2653, RG 1.97 Isolation Devices Type 2,North Anna Power Station. W/One Oversize Encl ML20101B0331992-04-30030 April 1992 Suppl to Update of Settlement Monitoring Points & Graphs NAPS - Supplement to Technical Rept CE-0019,North Anna Settlement Data Oct 1989 - Apr 1992 ML20077A6601991-05-0707 May 1991 Summary Rept on Exam of Steam Generator Tube R11-C14,North Anna Power Station,Unit 1 ML18153C3111990-07-26026 July 1990 Decommisioning Financial Assurance Certification Rept for Surry Power Station & North Anna Power Station. ML20011F6221990-02-26026 February 1990 Analysis of Small Steamline Break Performance W/O Low Pressurizer Pressure Safety Injection North Anna Units 1 & 2. ML20248E8641989-09-19019 September 1989 Rev 0 to Evaluation of Settlement Monitoring Program for Main Plant Structures in Support of Proposed Changes to Tech Spec 3/4.7.12. W/One Oversize Figure ML20246J1391989-08-17017 August 1989 Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding EP-2 ML20246J1581989-08-0909 August 1989 Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding MC-1 ML20246J1261989-07-20020 July 1989 Rev 0 to Coordination of Load Ctr Circuit Breakers,EP-1 ML20246J1191989-07-20020 July 1989 Rev 0 to Response to SSOMI Item IC-8 of NRC ML20246J0991989-07-18018 July 1989 Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-2 ML20246J1071989-07-18018 July 1989 Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-7 ML20246J1481989-06-30030 June 1989 RCS Leakage Detection Sys ML20246K3461989-05-0505 May 1989 Technical Evaluation & Safety Analysis:Solid State Protection Sys Slave Relay Testing REA-88-51 ML20245K7311989-04-26026 April 1989 Rev 0 to 890225 Steam Generator Leak Event Rept ML20056A0341989-04-18018 April 1989 Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement ML18151A9661989-04-18018 April 1989 Nuclear Decommissioning Trust Agreement. ML20245A5311988-09-13013 September 1988 Simulator Certification Submittal ML20148J6311988-03-16016 March 1988 Generator Tube Fatigue Evaluation & Remedial Actions Rept ML20147F5621988-03-0202 March 1988 Safety Evaluation in Support of Containment Temp Increase for North Anna Power Station ML20196J2901988-02-24024 February 1988 Rev 1 to Civil Engineering Technical Rept 0005, Differential Settlement Between Svc Bldg & Unit 2 Main Steam Valve House ML20148J6401988-02-12012 February 1988 Rev 2 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept ML20091L7041987-10-19019 October 1987 Generator Row 9 Column 51 Tube Failure Analysis ML20235G2441987-09-25025 September 1987 Steam Generator Downcomer Mods Safety Evaluation for North Anna Units 1 & 2 ML20238F6161987-09-15015 September 1987 Rev 1 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept ML18151A1351987-08-28028 August 1987 Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. ML20235U6701987-08-0707 August 1987 Loss of Inventory Event 870617-21 ML20235Q0661987-08-0505 August 1987 Metallurgical Svcs Rept FAL-00050 ML20237G9791987-07-29029 July 1987 Rev 0 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept. W/Pages from Facility Updated FSAR ML20235U3431987-07-20020 July 1987 Rev 0 to Chronology Steam Generator Tube Rupture Event North Anna Power Station Unit 1 870715. Related Info Encl ML20238E1611987-07-15015 July 1987 Rept of Emergency Preparedness Events Re Unit 1 Steam Generator Tube Rupture ML20215G5471987-06-17017 June 1987 Safety Evaluation for Change in Methodology & Supporting Analyses ML20235Q0551987-05-21021 May 1987 Investigation Rept FAL-00024, Emergency Diesel Generator Floating Busing Failure ML20206D6721987-03-31031 March 1987 Engineering Analysis Svc & Maint North Anna Power Station Fairbanks-Morse 38 TD8-1/8 Diesel Engines Phase II ML20207B5231986-11-30030 November 1986 Reactor Vessel Fluence & Rt/Pts Evaluations Suppl to WCAP 11016 ML20213D7771986-10-31031 October 1986 RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices ML20213D7601986-10-31031 October 1986 RCS Loads & Component Support Margins Evaluation for Elimination of Rcs,Main Loop Pipe Break Protective Devices ML20210F6821986-10-17017 October 1986 Reactor Protection Sys Trip Setpoint Drift Characterization 1999-10-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08
[Table view] |
Text
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3 nevision 3-1-83 i
. COMPARISON BETWEEN CMAA-70 AND EOCI-61 The draft Technical Evaluation Report for the North Anna plants asks for an evaluation of 14 issues regarding the recommendations of CMAA-70 and EOCI-61 which was the design basis for North Anna cranes.
of comparison are addressed as follows: The 14 issues ik _ Impact Allowance v
CMAA-70, Article 3.3.2.1.1.3 requires that crane design calculations minute of hoisting speed but not less than 15 percent. include an EOCI-61 specifies only a minimum allowance of 15 percent. Therefore, for cranes with hoist speeds in excess of 30 feet per minute, it is possible that the impact allowance applied under E0CI-61 will be less than that required by CMAA-70.
The containment polar cranes hoist speeds are below 30 fpm, and thereby, comply with the above article.
- 2. Torsional Forces CMAA-70, Article 3.3.2.1.3 requires that twisting moments due to overhanging loads and lateral forces acting eccentric to the horizontal neutral axis of a girder be calculated on the basis of the distance between the center of gravity of the load or force center line, and the girder shear center measured normal to the force vector .
EOCI-61 to the girder states centerthat such moments are to be calculated with reference of gravity. For girder sections symmetrical about each principal central axis, such as box sections or I-beam girders, used in these cranes, the shear center coincides with the centroid of the girder section and there is no difference between the two requirements.
The containment polar cranes are constructed with symmetrical box section girders, thereby complying with the above article.
- 3. Longitudinal stiffeners QF1AA-70, Article 3J3.3.1 specifies (1) the maximum allowable web depth / thickness (h/t) ratio for box girders using longitudinal stiffeners.and (2) requirements concerning the location and minimum moment of inertia for such stiffeners. EOCI-61 allows the use of longitudinal stiffeners but provides no similar guidance.
There box are two longitudinal stiffeners on the containment polar crane girder.
The web depth / thickness ratio h/t is calculated to be 219, which is within the allowable h/t specified~in CMAA-70:
8303280110 830323 PDR ADOCK 05000338 P PDR
. _ , -- y __
- Revision 3-1-83 allowable h/t = C(k + 1) 17 6 =
2C = 2 x 243 = 486 a
or h/t = M = 564
. where s
- j. C = 243 for 2 longitudinal stiffeners (k + 1) 17.6 =
2 which is the smallest value based on the fe most conservative approach used for a synenetrical girder, where the maximum stresses are assumed to equal the basic allowable stresses.
M = 564 for 2 longitudinal stiffeners Therefore the design complies with the CMAA-70 article.
- 4. Allowable Compressive Stress CMAA-70, Article 3.3.3.1.3 identifies allowable compressive stresses to be approximately 50 percent of yield strength of the recommended structural material (A-36) for girders, where the ratio of the distance between web plates to th'e thickness of the top cover plate (b/c ratio) is less than or equal to 38. Allowable compressive stresses decrease linearly for b/c ratios in excess of 38. EOCI-61 provides a similar method for calculating allowable compressive stresses except that the allowable stress decreases from approximately 50 percent of yield only after the b/c ratio exceeds 41. Consequently, structural members with b/c ratios in the general range of 38 to 52 designed under EOCI-61 will allow a slightly higher compressive stress '
than those designed under CHAA-70.
The b/c ratio of the containment polar crane girder is calculated to be 25, therefore complying with the CMAA-70 article. 1
- 5. Fatigue Considerations CMAA-70, Article, 3.3.3.1.3 provides substantial guidance with respect 2
to fatigue failure by indicating allowable stress ranges for various structural members in joints under repeated loads. EOCI-61 does not 4
address fatigue failure. )
The requirements of CMAA-70 are not considered to be of consequence !
for the containment polar cranes because these cranes are not generally subjected to frequent loads at or near design conditions l 1
(CMAA-70 provides allowable stress ranges for loading cycles in excess I of 20,000) and are not generally subjected to stress reversal (CMAA-70 allowable stress range is reduced to below the basic allowable stress for only a limited number of joint configurations). Therefore, fatigue failure is unlikely.
l
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r+---wt-=wa-- er N--
- Revicisu 3-1-83 1 ' 6. Hoist Rope Requirements CHAA-70, Article 4.2.1 requires that the capacity load plus the bottom block divided by the number of parts of rope not exceed 20 percent of the published rope breaking strength. EOCI-61 requires that the rated
, .,. capacity load divided by the number of parts of rope not exceed 20 percent of the published rope breaking strength. The effect on crane safety margins of this variation depends on the ratio of the weights
- of the load block and the rated load.
e- There are 12 parts of rope for the containment polar crane main hoists, therefore complying with the requirements of OdAA-70.
- 7. Drum Design OdAA-70, Article 4.4.1 requires that the drum be designed to withstand combined crushing and bending loads. EOCI-61 requires only that the drum be designed to withstand maximum load bending and crushing loads with no stipulation that these loads be combined.
The containment polar crane drums are designed to withstand combined crushing and bending loads, therefore complying with the requirements of CMAA-70.
- 8. Drum Design OdAA-70, Article 4.4.3 provides recommended drum groove depth and pitch. EOCI-61 provides no similar guidance.
The CMAA-70 article represents a codification of the same good engineering practice that would have been used in the cranes built to EOCI-61 specifications.
- 9. Gear Design CMAA-70, Article 4.5 requires that gearing horsepower ratings be based on certain American Gear Manufacturers Association Standards and provides a method for determining allowable horsepower. EOCI-61 provides no similar guidance.
American Gear Manufacturers Association Standards were used in the design of containment polar crane, therefore complying with the requirements of CMAA-70.
$ 10. Bridge Brake Design CHAA-70, Article 4.7.2.2 requires that bridge brakes, for cranes with cab control and the cab on the trolley, be rated at least 75 percent of bridge motor torque. EOCI-61 requires a brake rating of 50 percent of bridge motor torque for similar configurations.
The containment polar cranes are controlled from cabs mounted on the bridges.
, . , . - - y---- -- --
mavicien 3-1-83
- 11. Hoist Brake Design CMAA-70, Article 4.7.4.2 requires that hoist holding brakes, when used with a method of control braking other than mechanical, have torque ratings no less than 125 percent of the hoist motor torque.
EOCI-61 requires a hoist holding brake torque rating of no less than 100 percent of the hoist motor torque without regard to the
. type of control brake employed.
5 The containment polar crane main and auxiliary hoist motors are equipped with two DC magnetic brakes, each rated at 150% of full l motor torque. The bridge motors have an electric hydraulic foot brake rated at 150% of the full motor torque. The designs comply with,the CMAA-70 article.
- 12. Bumpers and Stops CMAA-70, Article 4.12 provides substantial guidance for the design and installation of bridge and trolley bumpers and stops for cranes which operate near the ends of bridge and trolley travel. No l similar guidance is provided in EOCI-61.
l
! The following bumpers are provided for the containment polar cranes.
Bridge Bumpers Trolley Bumpers Polar Crane None provided, crane Spring operates on circular runway
- 13. Static Control Systems CMAA-70, Article 5.4.6 provides substantial guidance for the use of static control systems. EOCI-61 provides guidance for magnetic control systems only.
The containment polar cranes are equipped with magnetic-type motor controls, so this article is not applicable.
- 14. Restart Protection CMAA-70, Article 5.6.2 requires that cranes not equipped with spring-return controllers or momentary-contact push buttons be -
provided with a device that will disconnect all motors upon power failure and will not permit any motor to be restarted until the controller handle is brought to the OFF position. No similar guidance is provided in EOCI-61.
The containment polar cranes were designed with motor controllers of the " dead-man" type with spring returns to the "0FF" position.
Therefore, this article is not applicable.
_ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ .