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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20199G1991997-11-19019 November 1997 Corrected Page 4-12 to WCAP-14723, Farley Nuclear Plant Units 1 & 2 Power Uprate Project NSSS Licensing Rept ML20148M7841997-06-30030 June 1997 Non-proprietary Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for AL Power Farley Nuclear Plant Units 1 & 2, Rev 1 ML20212D2621997-04-30030 April 1997 Rev 1 to WCAP-14689, Farley,Units 1 & 2,Heatup & Cooldown Limit Curves for Normal Operation & PTLR Support Documentation ML20135C9731997-01-31031 January 1997 Non-proprietary Version of WCAP-14723, Farley Nuclear Plant Units 1 & 2 Power Uprate Project NSSS Licensing Rept ML20133G6011997-01-31031 January 1997 Specific Application of Laser Welded Sleeves for Farley Units 1 & 2 Sg ML20133G5901997-01-31031 January 1997 Rev 4 to W Series 44 & 51 SG Generic Sleeving Rept,Laser Welded Sleeves ML20149L9111996-11-0606 November 1996 Nonproprietary Class 3 SG Sleeving Integration Rept for Jm Farley Units 1 & 2 ML20128M5411996-10-0808 October 1996 L* Tube Plugging Criteria for Tubes W/Degradation in Tubesheet Roll Expansion Region of Farley Unit 2 Sg ML20135B8261996-09-30030 September 1996 RCS Flow Verification Using Elbow Taps at Westinghouse 3- Loop Pwrs ML20212D2551996-06-30030 June 1996 Jm Farley,Units 1 & 2,Radiation Analysis & Neutron Dosimetry Evaluation ML20087E8311995-08-31031 August 1995 Elimination of Pressure Sensor Response Time Testing Requirements,Wog Program MUHP-3040 Rev 1 ML20069K2921994-03-31031 March 1994 Nonproprietary Steam Generator Lower Level Tap Relocation Assessment for Jm Farley Nuclear Plant Units 1 & 2 ML20072F3661993-12-31031 December 1993 Elimination of Pressure Sensor Response Time Testing Requirements ML20114B5011992-08-31031 August 1992 Nonproprietary Response to NRC Questions on Farley SG Tube Alternate Plugging Criteria Presentation Matls ML20114B5131992-08-31031 August 1992 Nonproprietary PWR SG Tube Repair Limits:Technical Support Document for Outside Diameter Stress Corrosion Cracking at Tube Support Plates Final Rept ML20101G2901992-03-31031 March 1992 Nonproprietary Preliminary Data on Voltage/Burst/Leakage of 3/4 Inch Diameter Tubing for ODSCC at Tsps ML20092M9471992-02-29029 February 1992 Steam Generator Tube Alternate Plugging Criteria Presentation Matls ML20094J9681992-02-29029 February 1992 Nonproprietary Jm Farley Units 1 & 2 SG Tube Plugging Criteria for Outer Diameter Stress Corrosion Cracking at Tube Support Plates ML20090B9511992-02-28028 February 1992 Nonproprietary Rev 2 to RTD Bypass Elimination for Licensing Rept for Jm Farley Nuclear Plant,Units 1 & 2, Table 2.1-1 (Replacement Page 15) ML20092J1281991-12-31031 December 1991 Nonproprietary WCAP-13139, Steam Generator Tube Support Plate Alternate Plugging Criteria Summary ML20086A0421991-10-31031 October 1991 Nonproprietary Addl Info Supporting SG TSP Criteria for Jm Farley,Units 1 & 2 ML20086A0611991-10-31031 October 1991 Rev 1 to WCAP-12872, Jm Farley Units 1 & 2 SG Tube Plugging Criteria for ODSCC at Tsp ML20082T4381991-09-30030 September 1991 Nonproprietary Addl Info in Support of Eliminating Pressurizer Surge Line Rupture from Structural Design Basis for Jm Farley Plant Units 1 & 2 ML20082S7461991-08-31031 August 1991 Nonproprietary Jm Farley Nuclear Plant Units 1 & 2 Response to NRC Request for Addl Info on Steam Generator Flow Area Reduction Due to Combined LOCA & SSE Loads ML20092L1911991-07-31031 July 1991 Rev 2 to Handbook on Flaw Evaluation for Joseph Farley Units 1 & 2 Steam Generators & Pressurizers ML20073P1261991-05-31031 May 1991 Allowable Outage Time Study for RHR Valves for Farley Nuclear Plant,Units 1 & 2 ML20079D6031991-05-31031 May 1991 Westinghouse Revised Thermal Design Procedure Instrument Uncertainity Methodology for Alpr,Farley Nuclear Plant,Units 1 & 2 (for RTD Bypass Loops) ML20079D6071991-05-31031 May 1991 Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Alpr,Farley Nuclear Plant,Units 1 & 2 (for RTD Bypass Loop Elimination) ML20073J9891991-04-30030 April 1991 Nonproprietary Technical Justification for Eliminating Pressurizer Surge Line Rupture from Structural Design Basis for Farley Units 1 & 2 ML20066J5661991-01-31031 January 1991 Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Jm Farley Units 1 & 2 Nuclear Power Plants ML20066L0501991-01-31031 January 1991 Nonproprietary Rev 2 to WCAP 12614, RTD Bypass Elimination Licensing Rept for Jm Farley Nuclear Plant Units 1 & 2 ML20066L3171991-01-31031 January 1991 Nonproprietary WCAP-12856, Structural Evaluation of Farley Units 1 & 2 Pressurizer Surge Lines,Considering Effects of Thermal Stratification ML20066E5091990-12-31031 December 1990 Nonproprietary Steam Generator Tube Plugging Limits Presentation Matls ML20197H6651990-11-30030 November 1990 Nonproprietary WCAP-12764, Steam Generator Tube Collapse Considerations Presentation Matls ML20058E3851990-10-26026 October 1990 Rev 1 to RTD Bypass Elimination Licensing Rept for Jm Farley Nuclear Plant Units 1 & 2 ML20058E3551990-08-31031 August 1990 Rev 0 to Alabama Power Jm Farley Unit 1 Increased Steam Generator Tube Plugging & Reduced Thermal Design Flow Licensing Rept ML20059D4851990-08-16016 August 1990 Steam Generator Sleeving Rept Laser Welded Sleeves Jm Farley Units 1& 2 ML20058E3661990-07-31031 July 1990 Median Signal Selector for Westinghouse 7300 Series Process Instrumentation - Application to Westinghouse Three Loop Plants Employing RTD Bypass Elimination,Alabama Light Co, Jm Farley Unit 1 ML20059D4371990-07-31031 July 1990 Alabama Power Jm Farley Unit 2 Increased Steam Generator Tube Plugging & Reduced Thermal Design Flow Licensing Rept ML20062F9781990-07-31031 July 1990 Rev 1 to WCAP-12213, Handbook on Flaw Evaluation for J Farley Units 1 & 2 Steam Generators & Pressurizers ML20062F9761989-09-30030 September 1989 Nonproprietary WCAP-12447, Background & Technical Basis: Handbook on Flaw Evaluation for Farley Units 1 & 2 Main Coolant Sys & Components ML20247N0321989-07-31031 July 1989 Nonproprietary Jm Farley Unit 2 Engineering Evaluation of Weld Joint Crack in 6-Inch Safety Injection & RHR Piping ML20058N8181988-12-31031 December 1988 Safety Evaluation Supporting More Negative Eol Moderator Temp Coefficient Tech Spec for Jm Farley Nuclear Plant Units 1 & 2 ML20153D7051988-07-31031 July 1988 Joseph Farley Unit 1 & 2 Evaluation for Tube Vibration Induced Fatigue ML20153D6621988-04-30030 April 1988 Background & Technical Basis for Handbook on Flaw Evaluation for Jm Farley Nuclear Plant Units 1 & 2 Reactor Vessel Beltline & Nozzle to Shell Welds ML20210D2831987-04-30030 April 1987 Rev 1 to Jm Farley Units 1 & 2 Steam Generator Sleeving Rept (Mechanical Sleeves) ML20210D3041987-04-30030 April 1987 Rev 2 to Tubesheet Region Plugging Criterion for Alabama Power Co Farley Nuclear Station Unit 2 Steam Generators ML20210T5711986-06-30030 June 1986 Rev 2 to Heatup & Cooldown Limit Curves for Alabama Power Co,Joseph M Farley Unit 1 Reactor Vessel ML20155A3231986-02-28028 February 1986 Rev 1 to Heatup & Cooldown Limit Curves for Jm Farley Unit 2 Reactor Vessel ML20137K8181986-01-31031 January 1986 Jm Farley Units 1 & 2 Reactor Vessel Fluence & Ref Temp for Pressurized Thermal Shock Evaluations 1997-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P0761999-10-0606 October 1999 Non-proprietary, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217G0361999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20212E7451999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Hcgs,Unit 1.With Summary of Changes,Tests & Experiments Implemented During Aug 1999.With ML20216E4941999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Jmfnp.With ML20210T2161999-08-0606 August 1999 Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant ML20211B2011999-08-0404 August 1999 Informs Commission About Results of NRC Staff Review of Kaowool Fire Barriers at Farley Nuclear Plant,Units 1 & 2 & Staff Plans to Address Technical Issues with Kaowool & FP-60 Barriers ML20210R6031999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20196J3791999-06-30030 June 1999 Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable ML20209G0661999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-267, Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-023, Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with ML20206G7471999-05-0404 May 1999 Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07 L-99-020, Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C9461999-04-30030 April 1999 1:Final Cycle 16 Freespan ODSCC Operational Assessment L-99-161, Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20205N0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20204D7271999-03-15015 March 1999 ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jm Farley Nuclear Generating Plant,Unit 1 ML20207M6421999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20203A2651999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20199D8611999-01-12012 January 1999 SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199E6591998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C8081998-12-31031 December 1998 Alabama Power 1998 Annual Rept ML20198K4091998-12-18018 December 1998 COLR for Jm Farley,Unit 1 Cycle 16 ML20198B2561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20195E2281998-11-16016 November 1998 Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1 ML20195C9681998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20155E0271998-10-29029 October 1998 SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04 ML20154B6121998-10-0101 October 1998 Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1 ML20151V8341998-09-30030 September 1998 Non-proprietary Rev 2 to NSA-SSO-96-525, Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change ML20154H6001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) ML20197C8991998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20237C5471998-08-20020 August 1998 Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only ML20236Y1121998-07-31031 July 1998 Voltage-Based Repair Criteria 90-Day Rept ML20237B1891998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20237A2181998-07-24024 July 1998 Jm Farley Unit 2 ISI Rept Interval 2,Period 3 Outage 1, Refueling Outage 12 ML20236U6141998-07-23023 July 1998 Safety Evaluation Authorizing Use of Alternative Alloy 690 Welds (Inco 52 & 152) as Substitute for Other Weld Metal ML20236R8671998-07-0909 July 1998 Safety Evaluation Concluding That Southern Nuclear Operating Co USI A-46 Implementation Program Has Met Purpose & Intent of Criteria in GIP-2 & Staff SSER-2 on GIP-2 for Resolution of USI A-46 ML20236M5981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20154H0461998-06-30030 June 1998 Technical Evaluation Rept on Review of Farley Nuclear Plant IPEEE Submittal on High Winds,Flood & Other External Events (Hfo) ML20248M3121998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20247F3631998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20217D2591998-04-21021 April 1998 Safety Evaluation Accepting Licensee Proposed Alternative Re Augmented Exam of Reactor Vessel Shell Welds for Plant ML20247E8851998-03-31031 March 1998 FNP Unit 2 Cycle 13 Colr ML20217H3191998-03-31031 March 1998 Safety Evaluation Accepting Proposed Changes to Plant Matl Surveillance Programs ML20216D5941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20217D4081998-03-24024 March 1998 Safety Evaluation Accepting Proposed Changes to Maintain Calibration Info Required by ANSI N45.2.4-1972 ML20216H6731998-03-17017 March 1998 SER Accepting Quality Assurance Program Description Change for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20216J6851998-03-16016 March 1998 Revised Pages 58 & 59 to Fnp,Units 1 & 2,Power Uprate Project BOP Licensing Rept ML20216D9811998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Jm Farley Nuclear Plant,Units 1 & 2 1999-09-30
[Table view] |
Text
- _ _ _ _ _
WEST!NGHOUSE CLASS 3 WCAP-12764 Steam Generator Tube Collapse Considerations Presentation Materials Preparea by Gary Whiteman November 1990 Westinghouse Electric Corporation Pittsburgh, PA 01990 Westinghouse Electric Corporation. All Rights Reserved 9011200036 901158 PDR ADOCK 05000364 P PDC /
N
A meeting was held on November 8,1990, between the Alabama Power Company, Westinghouse, and the NRR to discuss stcam generator tube collapse considerations using seismic /LOCA loading combinations.
1 The following topics were discussed:
l~ 1) Analysis methodology
- 2) Load combinations
- 3) Effect on LOCA peak clad temperature
- 4) Farley-specific results E
E
l PRESENTATION OVERVIEW l
l e
ANALYSIS METN000 LOGY FOR CALCULATING PLATE LOADS e DETAILED PLANT SPECIFIC ANALYSIS e SCOPING ANALYSIS FOR FLOW AREA REDUCTION ESTIMATE e Discussion OF LIMITING LOCA CONDITION e PEAK CLAD TEMPERATURE VERSUS '
max STEAM GENERATOR LOADS e REVIEW oF PLATE CRULd tests e CALCULATION OF FL0w AREA REDUCTION e IN-LEAKAGE CONSIDERATIONS FOLLOWING LOCA 1
ANALYSIS METHODOLOGY FOR CALCULATING PLATE LOADS DETAILED PLANT SPECIFIC ANALYSIS ,
l o TSP LOADS RESULT FnoM THREE LOADING MECHANISMS
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ANALYSIS METHODOLOGY 1
! SEISMIC ANALYSIS t
e NON-LINEAR FINITE ELEMENT ANAL 0VERALL STEAM GENERATOR L
L o
TSP / WRAPPER / a,c SHELL GAPS M0cELE -
l e
ACCELERATION r
TIME HISTORY LOAoING
, a,c e
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N00ELEo j
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ANALYSIS OUTPUT IN TERMS OF TUR PLATE IMPACT FORCE TIME HISTORIES 3
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P TYPICAL SEISMIC MODEL MODEL F STEAM GENERATOR 4
L_________________._.______..______.__.-_.______._..._ , _..-.
i ANALYSIS METHODOLOGY LOCA RAREFACTION WAVE ANALYSIS e LINEAR DYNAMIC ANALYSIS OF THREE TusE RADII e FINITE ELEMENT MoDEL CONSIDERS TUsE U-BEND DOWN TO SECONO TusE SUPPORT PLATE BELOW U-BEND e PRESSURE WAVE GENERATED FROM TRANSIENT l- THERMAL-HYDRAULIC ANALYSIS
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6
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l-e LOADS APPLIED TO STEAM GENERATOR IN FORM '
f 0F DrsPLACEMENT TIME HrsTORrts AT SUPPORT LOCATIONS e DrsPLACEMENT TIME HrsTORIEs OBTAINED As FOLLOWS:
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ANALYSIS METH0DOLOGY CONBINED PLATE LOADS l
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INEARLY e CoMsINED LOCA AND SEISMIC' loads USING SQUARE Ro0T OF THE SUM 0F THE SouAREs l
G 8
___.____ _ _______ _ __ __ _ _ _ ._______________________J_
DISCUSSION 0F LIMITING LOCA LOADS PEAK CLAD TEMPERATURE VERSUS MAX STEAM GENERATOR L0 ADS I
e PEAK CLAD TEMPERATURE LIMITING LOCA LOADS l e BREAK LOCATION - PUMP OUTLET e REsULTING STEAM GENERATOR LOADS SMALL e IMPACT ON FLOW AREA REDUCTION MINIMAL L
e max STEAM GENERATOR LOADS e- BREAK LOCATION - STEAM GENERATOR OUTLET e IMPACT ON PCT NOT As SEVERE As PUMP OUTLET BREAK o FL0u AREA REDUCTION CONCERN Is IMPACT ON PCT L
e- FLOW AREA REDUCTION BASED ON LOCA LOADS FROM LIMITINe LOCA FOR PCT e TSP LOADS REDUCE TO SEISMIC LOADS ONLY 1
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DEVELOP RELATIONSHIP sETWEEN PLATE LOAD AND LOSS IN FL0w AREA ACCOUNTING F0n' COLLAPSED L
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CALCULATION OF FLOW AREA REDUCTION
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O CALCULATE 0 CALCULATE Ass 0CIATED Flow AREA I. EDUCTION 0 _ CALCULATE TOTAL Flow AREA REDUOTION BY a,c 15
ANALYSIS METHODOLOGY FOR. SCOPING ANALY FLOW' AREA REDUCTION ESTIMATE 0.
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FVX AREA REDUCTION RESULTS FOR FARLEY
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a (MooEL D) UsED AS A BASIS
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FL0w o' ARF.A REDUCTION PER STEAM GENERATO e SERIES 51 -[ C"A" FARLEY - 0.44 %
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4 IUBE-COLLAPSE CONSIDERATIONS WCAP-9659 LOCA IN-LEAKAGE ROUND OR OVALIZED TUsES 8 m IN-LEAKAGE IS LESS THAN NORMAL OPERATION LEAKAGE PRESSURE DIFFERENTIAL IS LESS THAN NORMAL PRIMARY TO SECONDARY: AP SECONDARY TO PRIMARY?tiP-CAUSES LESS-
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TUBE COLLAPSE CONSIDERATIONS WCAP-8429 COLLAPSE CAPABILITY ROUNo TUsES WITH"THROUGH WALL EDN StoTS
_ _ my e .-COLLAPSE PRESSURES EXCEED _ _
EVEN WITH 10 PARALLEL 1.5 INCH THROUGH WALL SLOTS WITH: PART'THROUGH WALL EDN SLOTS e-
, _ ,y COLLAPSE PRESSURES EXCEED FOR PARTIAs. PENETRATIONS'EXCEEE .MG L1.25 INCH LENGTHS T i
i i~,
27
_=__ uni---n- im m mei iii um .. isi -- . i. ..
1 j1 6
- TABLE 51 TUBE COLLAPSE TESTS (PART AND THROUGH WALL FLAWS)
/
.. s i i
- ('
~
l*W W A87" 00 by 0.048" Well)
T
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w g-e 1 d= =
m , -h d .:
w 5 k
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____ _.,-----.-.--.w Tues COLLAPSE-CONSIDERATI0W-WCAP-8429 COLLAPSE CAPABILITY OvaLIzEn TusES
+
PARTIAL PENETRATION EDM SLITS IN TUBES OVALIZED
- d.,b,C TO _ ; HAVE LITTLE EFFECT ON COLLAPSE PRESSURE.
l 30 '
a:
~
^ ' '
,, ..u . . .
=-
~
= ;
c CCJillit100$ CRACK '
9 i j k lgl 7.50" I
C8ACKE9 $ECTfell . M U U V
..~ 1 y ...- =; ,0.00,.
h -
fffff ) ) ~,
CROSS SECilen 5800milIG LOCAT1001 0F C8 ACES TUDE INSIDE WAR
'CSACE
- Figure 5 27 Diagram Showmg the Conimuous Ceached Tube Specimen Seuausi orid in toca.o..
._,,..aJ.L4 . 'd' r ?
TABLE 510 STRAIGHT OVAL FULL WALL TUBES COLLAPSE DATA t=0.043",{ _] % *, c.
o,. *
- j f
-i t
- I i
- 1. _.j
.\
1 32
-F
~ ' K , 6, C.
1 Figure 6 28. (R Collapaa Pressure venus Ovality hw Straight Ovellaed Tubes m=0.378", a 41,600 y pel, t=0.063")
33
TUsE COLLAPSE CONSIDERATIONS ~
WCAP-8429 COLLAPSE CAPABILITY DENTED TUBES o
PLATE DEFORMATION UPON CONTACT WITN TH CAUSES TUBE OVALIZATION AND-REDUCES THE COLLAPSE PRESSURE VS ROUND TUBES e
PRESENCE OF PLATE ENHANCES COLLAPSE PR 4 OF UVALIZED TUBES-e COLLAPSE PRESSURES WITH COLLARS EXCEED LOAD WITH DIAMETRAL DEFORMATION EQUAL TO r a, b, c.
e h y 34 ii
jl:) l TABLE 512
_ DENTED TUBE 8 MECHANICAL TEST PLAN o ,C f:
e N
i 35
TABLE 513 (Con't.)
DENTED TUBES MECHANICAL TEST PLAN
~
ct,c' n.
a
=mm Ef
=
- i i
(
4 36 1
1
t TABLgig.13 DENTED TUBES MECHIANICAL 7337 RESULTS
- cA. , b, C.
I N
37
7 i
t E
1 L
.a A , C.
=.
=
_ 2
?
' 's
-i M
Figure 6 37 Effeet of Denting on Collapse Pressure 38
[
TUBE. COLLAPSE CONSIDERATIONS
+
3 LOCA IN-LEAKAGE
[ MULTIPLE AND LONG , 900GN WALL CRACKS DO NOT LOWER COLLAPSE CAPABIL'ITIES TO MARGINAL LEVELS (NIGN CAPABILITY)
~
WITHOUT COLLAPSE SECONDARY TO: PRIMARY PRESSURE
=
FOLLOWING LOCA RESULTS IN LOWER LEAKAGE THAN
_ DURING= NORMAL. OPERATION
_ -INE PRESENCE OF-PARTIAL PENETRATION CRACKS DO NOT t
SIGNIFICANTLY AFFECT COLLAPSE PRESSURES
, , , SIGNIFICANT CRACK EXTENSION OR PENETRATION IS NOT F
EXPECTED Td OCCUR AS A RESULT OF TUBE COLLAP!it t;i
~
I
- o. ,b, c.
TO CREATE THE POTENTIAL FOR TUBE COLLAPSE i
/
39
- TUBE COLLAPSE-CONSIDERATIONS FARLEY 2 j< LOCA IN-LEAKAGE
] - IN-LEAKAGE-IS .'XPECTED TO BE LESS THAN NORMAL OPERATION LEAKAGE IN THE POSTULATED EVENT OF A LOCA 0 ' PLATE DEFORMATION'IS EXPECTED TO BE LESS THAN THAT REQUIRED TO INDUCE TUBE COLLAPSE a.,s ,c.
i 10 . TUBE LEAKAGE IS REDUCED IF COLLAPSE DOES NOT. OCCUR-
- - - a. ,c, c.
2 Ea m
E e
40 m.