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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements ML20205P6291999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Battery Requirements ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20205P6931999-04-0909 April 1999 Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2 ML20207C0631999-02-25025 February 1999 Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable ML20207M7561999-02-24024 February 1999 Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999 ML20198K1341998-12-17017 December 1998 Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6 ML20198A3661998-12-0808 December 1998 Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb ML20196B4381998-11-24024 November 1998 Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153D8491998-09-17017 September 1998 Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20236Y5081998-08-0606 August 1998 Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits ML20236Y5951998-08-0606 August 1998 Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys ML20236Y5251998-08-0606 August 1998 Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels ML20236Q2781998-07-13013 July 1998 Proposed Tech Specs Re Safety Limits & Limiting Safety Settings ML20236G6921998-06-29029 June 1998 Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection ML20236G5631998-06-29029 June 1998 Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values ML20236G5421998-06-29029 June 1998 Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys ML20236G4911998-06-29029 June 1998 Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20217N6141998-04-30030 April 1998 Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt ML20217M2621998-04-30030 April 1998 Proposed Tech Specs Re DG Load Rejection Testing ML20217M4871998-04-28028 April 1998 Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle ML20217P8141998-04-0101 April 1998 Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15 ML20216J7841998-03-17017 March 1998 Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing ML20203D1061998-02-18018 February 1998 Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys ML20202G9771998-02-0909 February 1998 Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs 1999-09-07
[Table view] Category:TEST REPORT
MONTHYEARML20216G6371997-09-23023 September 1997 ANO Unit 1 SG Tube Exam ML20216H9461997-09-0808 September 1997 Cycle 13 Startup Rept ML20101H8201992-04-30030 April 1992 Reactor Containment Bldg Integrated Leakage Rate Test Rept, for Apr 1992 ML20086J0771991-11-0707 November 1991 Simulator Performance Testing Rept ML20077G9801991-04-30030 April 1991 One,Unit II Reactor Containment Bldg Integrated Leakage Rate Test ML20059E7901990-01-22022 January 1990 ASTM E-72 Load Testing of 2-h Solid Stud Wall ML20247E8271988-11-30030 November 1988 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20155D4931988-05-20020 May 1988 Rev 1 to Reactor Containment Bldg Integrated Leak Rate Test,880501 ML20214K3641986-11-24024 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `B' Pump Case-Surface Flaw ML20214K3951986-11-24024 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `A' Pump Case - Supplementary Topics ML20214K3291986-11-18018 November 1986 Rev 0 to Arkansas Nuclear One,Unit 1 Pump Case - Crack Growth Due to Transients ML20213F4731986-11-0707 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One-1 a Pump Case Indication ML20213F4791986-11-0707 November 1986 Rev 1 to Arkansas Nuclear One-1 Pump Case Stresses ML20214K3161986-11-0707 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `B' Pump Case Indication ML20206T3181986-01-31031 January 1986 Vols I-III of IEEE 634-1978 Std Cable Penetration Fire Stop Qualification Test:Arkansas Nuclear Units 1 & 2, Russellville,Ar - Site Specific,Arkansas Power & Light Co Spec APL-2434, Final Rept ML20203A2311985-10-23023 October 1985 Corrosion Test of Mechanically Sleeved Unit 1 Once-Through Steam Generator Tube ML20099M3031985-01-31031 January 1985 Rev 1 to Nonproprietary Phase I of Arkansas Power & Light Inadequate Core Cooling Monitoring Sys Program Test Series Summary Rept ML20215B4391985-01-14014 January 1985 Rev 0 to Pistar Computer Program Verification Document Program Version 3.3.1 ML20112F7681984-12-31031 December 1984 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20128K3561984-12-17017 December 1984 Change Notice 1 to Primary Reactor Containment Integrated Leak Rate Test,Final Rept ML20215B5081984-11-0909 November 1984 Rev 1 to Gensap Program Verification Document Program Version 4.0 ML20096D8011984-08-31031 August 1984 Nonproprietary Final Rept of Arkansas Power & Light Inadequate Core Cooling Monitoring Sys Confirmatory Test Program ML20203A1971984-08-0909 August 1984 Rept of Once-Through Steam Generator Mechanical Sleeve 40% Wall Reduction Test 2CAN068408, Unit Two Cycle Four Startup Rept, for Period Ending 8403151984-03-15015 March 1984 Unit Two Cycle Four Startup Rept, for Period Ending 840315 ML20215B5681983-11-19019 November 1983 Computer Program Verification - Stardyne -3 DEC01/82A H Level Ncsi Cyber 730 ML20080T8391983-06-10010 June 1983 Exam of Once-Through Steam Generator Tubes B73-8 & B112-19 from ANO-1, Final Rept ML20071G1921983-05-12012 May 1983 Station,Unit 2,Cycle Three Startup Rept, for Period Ending 830104 ML20072P8111983-03-17017 March 1983 Cycle 2 Refueling Outage Fuel Exam Results ML20215B5451982-11-24024 November 1982 Suppl a to Rev 0 to Gensap Verification. Baseplate II Verification Rept Encl ML20215B5301982-10-23023 October 1982 Rev 0 to Gensap Program Verification ML19350F1251981-06-30030 June 1981 Nonproprietary Version of Reactor Vessel Open Core Flow Model Test Rept. ML19277A0681981-06-16016 June 1981 Nonproprietary Version of Cpc/Ceac Sys Phase II Software Verification Test Rept. ML20009G3181981-06-12012 June 1981 Inservice Testing AND-Unit 1,Check Valve Reliability Analysis. ML20079F9071981-06-0202 June 1981 Nonproprietary ANO-2 Cycle 1 Refueling Outage Fuel Exam Results ML20004C5111981-05-31031 May 1981 B&W Post-Test Evaluation of Loft Test L3-1. ML20004C5161981-05-20020 May 1981 B&W Post-Test Analysis for Semiscale Test S-07-10D. ML20126K9701981-02-25025 February 1981 Primary Reactor Containment Integrated Leakage Rate Test ML20053E9161980-12-12012 December 1980 Rept on Floor & Wall Penetration Fire Stops. ML20003E6161980-10-31031 October 1980 Cesec Simulation of NSSS Transients Tests at AR Nuclear One-Unit 2. ML20151A3841980-07-28028 July 1980 Revision a to Electrical Wire & Cable Isolation Barrier Matls Test for Susquehanna Steam Electric Station,Units 1 & 2 for Bechtel Power Corp ML19323H2841980-04-30030 April 1980 AR Nuclear 1 Steam Electric Station,Unit 2,Startup Rept, Suppl 3 for Period Ending 800430 ML19318C3421980-04-30030 April 1980 Rept on Wall Penetration Fire Stops. ML19344D2581980-01-29029 January 1980 Startup Rept,Suppl 2 for Period Ending 800129. ML19260C3601979-12-17017 December 1979 Pages S1-47,S1-48,S1-A1 & S1-A2 to 791211 Suppl to Startup Rept ML19256G5611979-12-17017 December 1979 Four Pages Omitted from 791211 Submittal of Suppl 1 to 790913 Startup Rept ML19210E2641979-11-29029 November 1979 Revised Pages to Startup Rept Cycle 4 Correcting Error in Moderator Coefficient Extrapolated to 95% Full Power & Indicating Location of in-core Instrumentation Used to Determine Core Power Distribution ML19211A2891979-10-31031 October 1979 Suppl 1 to Startup Rept for Period Ending 791031 ML19209A5141979-09-25025 September 1979 Cycle 4 Startup Rept for Period Ending 790704 ML19208A9361979-07-31031 July 1979 Startup Rept. ML19344A6631979-05-14014 May 1979 Class IE Prequalification Tests for Itt Barton Pressure Differential Switch,Model 580. 1997-09-08
[Table view] |
Text
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- u. J. THEUS l
est* file is.LR:76:2341-74:1 er hf.
obj. COLLAPSE TESTS ON INTENTIONALLY DAMAGED ALLOY 600 Sets OTSG TUBING APRIL 20,1976 g.~.....-...-.-, ,
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SUP94ARY A test progmm on the effect of a lose of coolant accident (LDCA) on D inte ::ic'ully d2uged Alloy FCC steam generator tubing was carried out at the {
Q A Miance cesearch Center. *he progrcr- consisted of a serice of ocllapse tests
'o i r. refrechel OTsa :uality va:er at 600'T ard pressures betveen 2000 and i
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Distribution (COMPANY LIMITED) This infonnation is freely available to all Company personnel. Written approval by sponsoring unit's R&D coordinator is required only if release outside of the Company is requested.
r1 F.J. Pocock
. P.S. Ayres 0 M.J. Bell - NPGO, Lynchburg M.J. Mravich/W.S. Leedy
%s y R.U. Blaser J.P. Rowe E.E. Coulter - NED, Akron P.E. Sensmeier
' H.F. Cobel - MPGO, Lynchburg T.S. Sprague/L.E. Spry - NED, Barberton p H.4. Domian R.M. Douglass - Mt. Vernon G.J. Theus G.F. Tisinat - Beaver Falls g Chemistry & Corrosion Files (3) g G.N. Ensunuel - Mt. Vernon 0.W. Koch /N.L. Evanchan - NED, Akron Contract Control D J. A. Manzi/E.M. Oorsey B.N. Mcdonald - NPGO, Lynchburg Corporate Information Services Anr tihrarv (3)
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y T.A. McMary NPGD Library (2)~
% R.C. Ritschard/J.V. Monter J d. Musat 8611170248 861031 PDR ADOCK 05000313 P PDR
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l B&W makes no werranty or representation, expressed or implied:
e with respect to the suuracy, completeness, or usefulness of the information contained in this report e that the use of any information, apperatus, method, or process disclosed in this report may not infringe privately owned righti B&W assumes no liat>Isty with respect to the use of, or for damages resulting from the use of.
e any informetion, apparates. method, or process disclosad ir.
this report 1 e experimental apparatus furnished with this report.
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Page 2 Babcock & Wilcox LR:76:2341-74:1 s
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- 1. INTRODUCTION j Abnormal operation of a once-through steam generator (OTSG) may subject its Alloy 600 tubing to a variety of potentially da sging events. Movement between the support plates and tubes my result in thin.!na of the t@e wall due to mechanical wear. Water chemistry upsets may lead to intergranular attack, intergranular stress corrosion cracking, or wastage attack. Should any of these events occur, it could pose a safety related question if a loss of coolant accident (LOCA) were to subsequertly occur. The question would relate to how much damge a tube can endure and still perform satisfactorily in case cf a LOCA.
5hould a LOCA incident occur, the damaged tubes would have to withstand the entire secondary side pressure (approximately 1000 psi) without collapsing.
If tube collapse did occur, the tube wall might rupture and secordary water could enter the primary system and perhaps overload the containment building's pressure capacity. Therefore, there is a need to ascertain how much external pressure a daraged tube can withstand before collapsing and rupturino. In order to determine the extent of " allowable" tube damage, a test program was conducted wherein intentionally damaged Alloy 600 OTSG tubes were subjected to various collapse pressures. The specific objective of the test program was to l determine whether or not tubes damaged to 50% of their wall thickness could I withstand a LOCA incident.
?. TE3T PROGRAM 1
2.1 Material The material used was Alloy 600 OTSG tubing, Heat M5442, manufactured by the Tubular Products Division of the Babcock & t!!!cox Company. All Tubing 1
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W &Wikas s LR:76:2541-74:1 Page 3
' Pas stress relieved, 1150'F/18 hrs, prior to testing. The actual dimensions of this tuMng are 0.d28" 00 x 0.038" wall. The analysis is given in Table 1.
Table 1 Analysis of Heat M5442 v
C .051 Cr 15.81 Fe 8.92 Mn .37 Ni 74.01 Mg .037 5 .0063 Mo .07 Al .28 B .0018 Cu .02 Ti .25
,. Si .13 Co .045 Pb <.005 2.E ' Specimens Duplicate test specimens,18" long, were made of each defect geor etry.
The tubes were sealed at' bc,th ends by welding in a plug of the same material.
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Defects were placed in thi middliof each tubular sr,ecimen, w*th the exception of two undamaged tubes used as comparison spetjmens.
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2.3 Defect Depth The objective of the program is to assure satisfactory tube perforrance in case of a LOCA incident with tubes having incurred damage such that only 50% of their wall ranained. Tubes with a 50% defect depth were not expected to collapse with of.ly' LOC 5 pressures applied, f.e.1000 psi. Therefore, tubes with defect depths greater than 50% of the wall were tested and pressures higher thar.1000 psi were imposed to estaolish tN relationship of defect depth and shape with collapse pressure. Tubes with defect depths less than 50% of the remaining wall w(re also tested to traplete the test array.
The defe:t depths used for each defect gecmetry were:
, 1)' 1001(0.038") of tube wall ree.sining (no defect)
- 2) 75% (0.0285") of tube well retaining P
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Babcock & Wilcom L R:76:2341-74:1 Page 4
- 3) 50% (0.019") of tube wall remaining
- 4) 30%(0.0114") of tube wall remaining.
2.4 Defect Geometry Two specimens of each defect geometry / defect depth combination of interest were tested. The various defect types are described and illustrated below.
e Longitudinal Slit A longitudint,1 groove. 0.010" wide and I" long, was machined in the outside surface of the tube with a milling cutter. This defect simulated a
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longitudinal crack in the tube wall.
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s Circumferential Slit A slit defect groove. 0.010" wide, and extending around 12G' of the circum'erence was machined in the outside surface of the tube with a milling cutter. This defect simulated a circumferential crack in the tube ws11.
e Circumferential Thinning A 360' area of uniform thinning 0.5" long was machiied on the outside surf at e of the tube. Tnis defect simulated an area of uniform t. nning of the tube wall.
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Babcock & Wilcox LR:76:2341-74:1 Page 5 e Flat Defect A flat spot. 0.75" long, was introduced on the tube wall by two techniques -
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machining and by electrochemical (sulfuric acid - glycerine ritture) machining
- of the metal. These defects sirnulated areas thinned by mechanical wear (machined) or by chemical attack (electrocheHcal machining). Chemical attack did not result in significant intergranular penetrations of the tube wall as can be seen in Figure 1.
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Figure 1. Appearance of Tube Surface After Removal l
of Metal by Electrochemical Machining l
2.5 Test Conditions Each test was conductej for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> at 600*F and the pressure was varied, in 500 psi increments, between 2000 psi and 4000 psi. All tests were conducted in a refreshed autoclave using nonel GTSG feedwater (Table 2).
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I Babcock & WNees LR:76:2341-74:1 Peee 6 Table 2. Test Solution
- pH 9 25'C 9.3-9.5(M4) 3 Conductivity 4-10 umhos/cm j 0xygen 0 (i.e. residual hydrazine) l Iron <5 ppb Temperature 600'F(316'C)
Flowrate 0.5 gal /hr (1.9 titers /hr)
Prior to testing, the diameter of each specimen was measured at three points on the circurnference at the site of the defect. After this, the specimens were installeo in a carbon steel holder (Figure 2). The assew6ly was placed in the autoclave and the autoclave was pressurized to the desired level and then heated with water f'owing through it. Pressure was maintained by a mechanical back pressure regulator. Water was supplied to the autoclave by means of a high pressure mechanical pump. After each test, all specimens were remeasured at the same locations on the circunference. If any evidence of flattening was observed, the specimen was removed and regarded as failed. In most cases, failed specimens collapsed and there was little doubt whether failure occurred.
l When measurements were completed, the unfailed tubes were placed back in test.
Failed tubes were testeo for rupture by removing the cap on one end, imersing the tube in water and pressurizing the inside with helium. Bubbles would form at the site of a through-wall failure.
- 3. RESULTS & OISCUSSION Results of the tests are presented by test pressure.
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,4 Figure 2. Collapse Specimen Holder With One Test Specimen Installed
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o Figure 3. Appearance of Fracture in Failed Tube 3000 psi 3500 psi
t Babcock & WHeas LR:76:2341-74:1 Pase 9 I
4000 psi h
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j and Figure 4 suwvnarize the results of the test program, and Figures 5 through fs show tubes after failure.
From the results preser.ted in Table 3 and shown in Figure 4, the follwing surrary staternents can be made:
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Babcock & Wilcos LR:76:2341-74:1 Page 10 Table 3. Summary of Results of Collapse Test. 628" 00 m .038" Wall.
Alloy 600 Tubing Temperature: 600*F. Circulating OTSG Feedwater Time: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> at each pressure. Maximum pressure 4000 psi Type of Defect Circtsferential Slit 120' ,
Longitudinal Slit Circumferential. 360' l Flat (Machined) l L
Flat (Chemical)
No Defect ( As-Rec'd) 1
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FIGURE 4 BAR GRAPH StmaRIZING TEST RESULTS i
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- 4. CONCLUSIONS i The results of collapse tests on intentionally damaged Alloy 600 OTSG tubing allows us to conclude that:
1) 2)
3)
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- 5. REC 0m EN W IONS This test has demonstrated only the effect of pressure (loss of primary coolant) on the collapse properties of intentionally damaged Alloy 600 OT56 tubing. The burst properties of similar tubing were not investigated. In order
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Babceedt & h LR:76:2M1-74:1 Paes 17 1 1
l to complete the study of the behavior of this material under adverse operations, we recommend the initiation of such a progrars. The burst properties of Alley 800 tubing with the same defect geometries as the collapse specimens, at the same pressure and temperature, should be determined. A program to detemine the tensile properties of damaged tubing at room temperature and at 600*F is also recomended.
/ W A ) -}-l R. H. Emanuelson/G. J. Theus J
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"M. & WRces LR:76:2341-74:1 Paae 17 to complete the study of the behavior of this material under adverse operations, we recomend the initiation of such a program. The burst properties et' Alley 400 tubing with the same defect geometries as the collapse speciesns, at the same pressure and terature, should be deteroined. A program to detemine the tensile properties of damaged tubing at room tamperature and at 600*F is also recomended b vm ,
R. H. Emanuelson/G. J. Theus
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