to Evaluation of Effects of Postulated Pipe Failures Outside Containment for McGuire Nuclear StationML20063N585 |
Person / Time |
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Site: |
McGuire, Mcguire |
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Issue date: |
10/01/1982 |
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From: |
DUKE POWER CO. |
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To: |
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Shared Package |
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ML20063N577 |
List: |
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References |
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MDS-PDG-77-1, NUDOCS 8210040279 |
Download: ML20063N585 (3) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20117J0491996-05-0808 May 1996 At&T Round Cell Nuclear Util User'S Council Charter ML20094N0751995-10-31031 October 1995 Validation of Crest, Interim Rept ML20094N0641995-07-31031 July 1995 Computer Program for Coupled Response Spectrum Analysis of Secondary Sys ML20098A4511995-04-30030 April 1995 Stations Replacement SG Topical Rept ML20077S6091994-12-31031 December 1994 1994 Annual Insp of Snsw Dam & Wwcb Dikes ML20071A9291994-01-25025 January 1994 Nonproprietary McGuire Units 1 & 2 Kinetic Sleeve Evaluation ML20059J2771994-01-18018 January 1994 Non-proprietary Document 51-1228707-01, Evaluation of Bwnt Kinetic Sleeving Process ML20126A0671992-12-0909 December 1992 Snubber Elimination at McGuire Nuclear Station Using Limit Stops, Interim Rept ML20101F1811991-11-18018 November 1991 Rev 0 to Overtemp Delta Temp Scaling,Westinghouse NSSS Process Control Sys ML20079N4011991-11-11011 November 1991 Mixed Waste Characterization & Processing ML20011E2531989-07-31031 July 1989 Arrotta Validation & Verification - Std Benchmarks Set. ML20246A6791989-06-30030 June 1989 Description of Additions to & Deviations from Generic Emergency Response Guidelines ML20246J3571989-05-31031 May 1989 Evaluation of Degradation of Tube R18C25 & Justification for Return to Power ML20244B3341989-05-12012 May 1989 Rev 3 to Final Design Description of ATWS Mitigation Sys Actuation Circuitry ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20196L6281988-05-20020 May 1988 Rev 2 to ATWS Mitigation Sys Actuation Circuitry (Amsac) ML20196L6421988-05-0606 May 1988 ATWS Mitigation Sys Actuation Circuitry Response to Unit Transients ML20210C9641987-01-28028 January 1987 Rev 0 to Analysis of Fire Exposure to Steel Supports Penetrating Fire Barriers ML20212K1201987-01-23023 January 1987 Final Design Description,Atws Mitigation Sys Actuation Circuitry ML20210C9061986-11-12012 November 1986 Rev 0 to Evaluation of Need for Fire Protection of Steel Penetrating Fire Barrier Walls ML20205T6031986-06-30030 June 1986 Comparison of Std Westinghouse PWR & McGuire Nuclear Station After Deletion of Upper-Head Injection Sys Re Expected Results of Large Break Loca ML20215J8011986-06-10010 June 1986 Rev 1 to MCSD-2211.00-35, Equipment Staging Bldg Heating Ventilating & Air Conditioning Sys - Vk/Yk ML20011E2551986-04-30030 April 1986 Draft Arrotta:Advanced Rapid Reactor Operational Transient Analysis Computer Code Documentation Package,Vol 1:Theory & Numerical Analysis. ML20207S9751986-04-16016 April 1986 Rev 1 to McGuire Nuclear Station Unit 1 Electrical Controls Sys Description,Electrical Penetration Circuits - Eza Sys ML20207S9771986-04-16016 April 1986 Rev 1 to McGuire Nuclear Station Unit 2 Electrical Controls Description,Electrical Penetration Circuits - Eza Sys ML20210E5111986-03-25025 March 1986 Rev 13 to Pages from Analysis of Hydrogen Control Measures at McGuire Nuclear Station, Responding to Questions Transmitted by Youngblood ML20138Q9471985-10-31031 October 1985 Analysis of Electray Hanger Rods in Unit 2 Auxiliary Feedwater Pump Room at McGuire Nuclear Station ML20151S1671985-10-30030 October 1985 Analysis of Coolant at Reduction Observed at McGuire Unit 2 ML20205H3901985-10-29029 October 1985 Nonproprietary Resistance Temp Detector Bypass Elimination Licensing Rept for McGuire Units 1 & 2 ML20133D2261985-09-30030 September 1985 Safety Analysis for Upper Head Injection Elimination ML20138Q9361985-09-20020 September 1985 Rev 1 to Analysis of Electray Hanger Rods in Unit 1 Mechanical Pipe Chase at McGuire Nuclear Station ML20215C4221985-08-31031 August 1985 Rod Swap Methodology Rept for Startup Physics Testing ML20216A8521985-08-0101 August 1985 Steam Line Break Qualification Evaluation ML20127L7191985-05-31031 May 1985 Evaluation of Main Steam Line Break in Doghouse ML20128F7011985-05-31031 May 1985 Corrected Evaluation of Main Steam Line Break in Doghouse. Rept Redistributed Due to Copying Error ML20090G6731984-04-30030 April 1984 Nuclear Physics Methodology for Reload Design ML20087M4171984-03-23023 March 1984 Nonproprietary Info Reflecting Use of Rosemount Resistance Temp Detector ML20080U4541984-02-29029 February 1984 Rev 10 to Analysis of Hydrogen Control Measures at McGuire Nuclear Station ML20080N7231984-02-16016 February 1984 Rev 2 to Response to Suppl 1 to NUREG-0737 ML20082D6571983-11-14014 November 1983 Safety Evaluation for McGuire Units 1 & 2 Transition to Westinghouse 17x17 Optimized Fuel Assemblies ML20082L8571983-09-23023 September 1983 Surveillance Requirements for Emergency Diesel Fuel Oil Sys in Nuclear Power Plants, Prepared for Snupps ML20087F8901983-06-30030 June 1983 Steam Pressure Suppression Characteristics of Water-Soluble Plastic Membrane Shielded Ice for Ice Condenser Containment Nuclear Power Plants. Supporting Documentation Encl ML20079Q9121983-06-15015 June 1983 Summary Rept of Radiological Aspects of Mod of McGuire Nuclear Station,Unit 1 Steam Generator ML20073P4431983-04-22022 April 1983 Rev 8 to Analysis of Hydrogen Control Measures at McGuire Nuclear Station, Insertion Instructions,Vol 3 ML20072B7961983-02-15015 February 1983 Control Room Review Plan for Oconee,Mcguire & Catawba Nuclear Stations,Duke Power Co ML20028G6181983-02-15015 February 1983 Rev 6 to Analysis of Hydrogen Control Measures at McGuire Nuclear Station. ML20063N5851982-10-0101 October 1982 to Evaluation of Effects of Postulated Pipe Failures Outside Containment for McGuire Nuclear Station 1999-05-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20199E0301998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20198D7561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199E0491998-11-30030 November 1998 Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20196G0581998-11-0606 November 1998 Rev 17 to COLR Cycle 13 for McGuire Unit 1 ML20196G0761998-11-0606 November 1998 Rev 15 to COLR Cycle 12 for McGuire Unit 2 ML20198D7771998-10-31031 October 1998 Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E5961998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154L6251998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E6021998-09-30030 September 1998 Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154B4131998-09-22022 September 1998 Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20154L6321998-08-31031 August 1998 Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1 ML20153B3741998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20237B2381998-07-31031 July 1998 Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2 ML20153B3931998-07-31031 July 1998 Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days 1999-09-30
[Table view] |
Text
O EVALUATION OF THE EFFECTS OF POSTULATED PIPE FAILURES OUTSIDE CONTAINMENT FOR MCCUIRE NUCLEAR STATION May 2, 1977 h)
REPORT NO. MDS/PDG-77-1 Revision 1 8-15-77 Revision 2 10-06-73 Revision 3 11-05-80 Revision 4 1-26-81 Revision 1 2
?
ffR DO O O PDR g K
f' f, 2) For purposes of evaluating the mechanical integrity
(
v ef fects of the impact of a whipping pipe or jet on piping compone*ts (i.e., pumps, valves, flanges, etc.), piping component pressure boundaries are con-sidered to be pipe of the same size and wall thick-ness as the main process piping to which the compo-nents are attached. Bodies of valves (including check valves) are assumed not to f ail upon impact by a smaller whippf ng pipe or jet from a smaller pipe.
- 3) An active component is assumed to be incapable of per-forming its active function following impact by a whipping pipe or jet, unless pro., etherwise by detailed impact analysis. External valve operators are assumed to be incapable of performing their intended function following impact by a whipping pipe or jet.
- 4) Cables and electrical equipment imp.cted by pipe
-~
[ 's whip or jet impingement will be assumed to fail along 6
('%ss with the final actuated devices the cables and equip-j ment support. Only the consecuences of failure of these final devices (e.g., MOVs, transmitters, etc.) !
will be considered in the Electrical analysis. Further- l j more, the failure mode will al ays - be nonnechanistically assumed to be the position associated with loss of power to the device.
- 5) If pipe supports are damaged by whipping pipes or jets, the target pipe supported by t he hangers is assumed to remain supported upon the loss of one hanger.
b) Environmental Interactions
- 1) Structures are assumed f ailed if their design pressure is exceeded, unless integrity can be demonstrated.
,--~s 43 Revision 6
( \
V -
musus
- 2) The final actuated devices that cables and electrical
(s equipment support are assumed incapable of performing their function upon exceeding the environmental qualifica-6 tion parameters (temperature, pressure, relative humidity) of the cabling or electrical equipment.
c) An active component is assumed incapable of performing its active function upon experiencing environmental conditions exceeding the environmental qualifications of the active canponent.
4.2.2 Pipina Systems Enclosed Within Structures For the purpose of assuring compliance with the requirements of Section 4.1 for piping systems within enclosures, breaks are postulated in accordance with Section 3.2, and it is demonstrated by analysis that such enclosure is adequately
'~s designed to prevent damage to essential structures and
'"# equipment from the effects of pipe whip, Jet impingement, pressurization of the enclosure compartment, environmental conditions, and flooding associated with the escape of the contained fluid. Piping restraints within the enclosure may by accounted for in limiting the effects of the postulated pipe rupture.
4.2.3 Other High-Eneroy Pipina Systems For the purpose of assuring compliance with the requirements of Section 4.1 for piping systems neither physically separated i
from essential structures and equipment nor enclosed, breaks I are postulated in accordance with Section 3.2; and it is demon-l l strated by analysis that the effects of pipe whip, jet impinge-ment, compartment pressurization, environmental conditions, and N
! 44 Revision 6
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