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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20202J7991998-09-30030 September 1998 Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept ML20247G7011998-05-31031 May 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2 ML20248M0561998-05-31031 May 1998 Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique ML20216D0971998-02-28028 February 1998 Rev 3 to WCAP-14780, Prairie Island,Unit 1 Heatup & Cooldown Limit Curves for Normal Operation ML20216D1101998-02-28028 February 1998 Rev 2 to WCAP-14637, Prairie Island,Unit 2,Heatup & Cooldown Limit Curves for Normal Operation ML20199A6231997-10-31031 October 1997 Non-proprietary Rev 4 to CEN-620-NP, Series 44 & 51 Design Tube Repair Using Tube Rerolling Technique, Final Rept ML20217M8691997-08-31031 August 1997 Nonproprietary Rev 1 to Addendum 1 to Repair of W Series 44 & 51 SG Tubes Using Leak Tight Sleeves, Final Rept ML20141D6391997-04-30030 April 1997 Non-proprietary Analysis of Capsule P from Northern States Power Co Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, Rev 1 ML20141D6241997-04-30030 April 1997 Non-proprietary Evaluation of Pressurized Thermal Shock for Prairie Island Unit 2, Rev 1 ML20141D5971997-04-30030 April 1997 Non-proprietary Analysis of Capsule from Northern States Power Co Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Rev 1 ML20141D5221997-04-30030 April 1997 Non-proprietary Rev 1 to Evaluation of Pressurized Thermal Shock for Prairie Island,Unit 1 ML20134A8791997-01-31031 January 1997 Analysis of Capsule from Northern States Power Comp Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program ML20134A7821997-01-31031 January 1997 Rev 3 to Series 44 & 51 Design SG Tube Repair Using Tube Re-Rolling Technique, Final Rept ML20134A7741997-01-31031 January 1997 Rev 2 to Series 44 & 51 Design SG Tube Repair Using Tube Re-Rolling Technique, Final Rept ML20135A8311996-11-30030 November 1996 Rev 1 to Final Rept, Repair of W Series 44 & 51 SG Tubes Using Leak Tight Sleeves ML20129E2741996-09-30030 September 1996 Nonproprietary F* & Elevated F* Tube Plugging Criteria for Tubes W/Degradation in Tubesheet Region of Prairie Island Sgs ML20116E9031996-07-31031 July 1996 Analysis of Capsule P from NSP Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program ML20116E8881996-07-31031 July 1996 Evaluation of PTS for Prairie Island Unit 2 ML20116J5981996-03-31031 March 1996 Non-proprietary Verification of Structural Integrity of Abb Ceno SG Welded Sleeve ML20087H4641995-03-31031 March 1995 Nonproprietary Handbook on Flaw Evaluation Prairie Island Units 1 & 2 SGs Upper Shell to Dome Weld Region ML20078H4531995-01-31031 January 1995 Nonproprietary Handbook on Flaw Evaluation for Prairie Island Units 1 & 2 SGs & Pressurizer ML20077N0731994-12-31031 December 1994 Non-proprietay WCAP-14226, F* & L* Tube Plugging Criteria for Tubes W/Degradation in Tubesheet Roll Expansion Region of Praire Island Units 1 & 2 Steam Generators ML20081K3531991-03-31031 March 1991 Nonproprietary Technical Jusitification for Eliminating Pressurizer Surge Line Rupture as Structural Design Basis for Praire Island Unit 1 ML20236A3131989-01-19019 January 1989 Discussion of Torsion Effects on Limit Moment Theory & Piping Code Criteria. Technical Rept ML20154L6501988-09-30030 September 1988 Nonproprietary, Advanced Digital Feedwater Control Sys Median Signal Selector for Northern States Power Prairie Island Units 1 & 2 ML20151K6861988-03-31031 March 1988 Evaluation for Tube Vibration Induced Fatigue ML20214P8501986-07-31031 July 1986 Rev 1 to Toughness Criteria for Thermally Aged Cast Stainless Steel ML20214P8691986-07-31031 July 1986 Rev 1 to Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Prairie Island Unit 2 ML20154K4141986-02-12012 February 1986 Reactor Vessel Upper Internals Replacement Safety Evaluation ML20140A7471986-01-31031 January 1986 Demonstration of Conformance of Prairie Island Units to App K & 10CFR50.46 for Large Break Locas ML20140A7751985-12-31031 December 1985 Demonstration of Conformance of Prairie Island Units W/Exxon Fuel Assemblies to App K & 10CFR50.46 for Small Break Locas ML20140A7511985-10-31031 October 1985 Demonstration of Conformance of Prairie Island Units to App K & 10CFR50.46 for Small Break Locas ML20205G7101985-09-30030 September 1985 Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Prairie Island Unit 2 ML20205G7241985-09-30030 September 1985 Toughness Criteria for Thermally Aged Cast Stainless Steel ML20128N1971985-03-31031 March 1985 Steam Generator Sleeving Rept (Brazed Sleeves) ML20128N1561985-01-31031 January 1985 Steam Generator Sleeving Rept (Mechanical Sleeves) ML20116K3641984-12-31031 December 1984 Background & Technical Basis for Handbook on Flaw Evaluation for Prairie Island Units 1 & 2 Reactor Vessels ML20116K3591984-12-31031 December 1984 Handbook on Flaw Evaluation for Prairie Island Units 1 & 2 Reactor Vessels ML20106J5261984-09-30030 September 1984 Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Prairie Island Unit 1 ML20090E9171984-02-28028 February 1984 Limiting Break LOCA-ECCS Analysis W/Increased Enthalpy Rise Factor ML20024A9011983-05-27027 May 1983 Limiting Break LOCA-ECCS Analysis Using Exem/Pwr. ML20069H2221982-05-31031 May 1982 Analysis of Capsule P from Northern States Power Co Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program ML19347F3761981-03-31031 March 1981 Analysis of Capsule T from Northern States Power Co Prairie Island 2 Reactor Vessel Radiation Surveillance Program, Mar 1981 ML19323C3671980-04-11011 April 1980 Exposure Sensitivity Study for ENC XN-1 Reload Fuel at Prairie Island Unit 1 Using ENC WREM-IIA PWR Evaluation Model, Revision 1,nonproprietary Version ML19263C4111979-01-31031 January 1979 Generic Analysis of Control Rod Ejection Transient for Pwrs. ML19270F0731978-11-30030 November 1978 Generic Mechanical & Thermal Hydraulic Design for Exxon Nuclear 14X14 Reload Fuel Assemblies W/Zircaloy Guide Tubes for Westinghouse 2-Loop Pressurized Water Reactors. Studies Design Criteria,Analyses & Test Results ML19276D7081978-11-30030 November 1978 Plant Transient Analysis. ML19276D7111978-11-30030 November 1978 Cycle 5 Sar. ML19276D7091978-11-22022 November 1978 ECCS Large Break Spectrum Analysis Using ENC WREM-11A PWR Evaluation Model. ML19250C0151978-08-28028 August 1978 Cycle 5 Sar. 1998-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20205N1081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 ML20207J6951999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant ML20202J7711999-02-0404 February 1999 Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept ML20202G3761999-01-31031 January 1999 Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units ML20207L2811999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2 ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety ML20206P7861998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198J6441998-12-17017 December 1998 Rev 0 to PINGP COLR Unit 2-Cycle 19 ML20206N2731998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20155K6301998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20154H4061998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With ML20202J7991998-09-30030 September 1998 Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept ML20198P0571998-09-0303 September 1998 Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator ML20153B0761998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With ML20237A3961998-08-11011 August 1998 Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20236X8531998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant ML20236R6481998-07-15015 July 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept ML20236R0771998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant ML20249A5751998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant ML20247G7011998-05-31031 May 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2 ML20248M0561998-05-31031 May 1998 Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique ML20247E2671998-05-0505 May 1998 Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy) ML20247G2921998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20216C6361998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2 ML20216H0341998-03-31031 March 1998 Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept ML20217D2041998-03-13013 March 1998 Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn ML20236P9801998-03-12012 March 1998 Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys ML20248L3931998-03-10010 March 1998 ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212 ML20216D0911998-03-0606 March 1998 Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept 1999-09-30
[Table view] |
Text
. _ _ . _ __ __ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _
C NON PROPRIETARY CEN 629 NP Addemdum 1, Rev. 01 COMBUSTION ENGINEERING, INC.
August,1997 -
Repair cf Westinghouse Series 44 and 51 Steam Generator Tubes Using Leak Tight Sleeves FINAL REPORT Combustion Engineering, Inc.
Nuclear Operations Windsor, Connecticut 9708250344 970815 .
PDR ADOCK 05000282)
P PM o
LEGAL NOTICE Tills REPORT WAS PREPARED AS AN ACCOUNT OF WORK SPONSORED BY ABB COMBUSTION ENGINEERING. NEITilER ABB COMBUSTION ENGINEERING NOR ANY PERSON ACTING ON ITS BEllALF:
A. MAKES ANY WARRANTY OR REPRESENTATION, EXPRESS OR IMPLIED INCLUDING TliB WARRANTIES OF FITNESS FOR A PARTICULAR
' PURPOSE OR MERCilANTABILITY, WIT 11 RESPECT TO TI1E ACCURACY, COMPLETENESS, OR USEFULNESS OF Ti1E INFORMATION CONTAINED IN T111S REPORT, OR PROCESS DISCLOSED IN Tills REPORT MAY NOT INFRlNGE PRIVATELY OWNED RIGliTS; OR B.
ASSUMES .iNY LIABILITIES WIT 11 RESPECT TO TiiE USE OR FOR DAMAGES RESULTING FROM Tile USE OF, ANY INFORMATION, APPARATUS, MET 110D OR PROCESS DISCLOSED IN TlilS REPORT.
U 4
4 ABSTRACT This addendum details the assessment of steam generator tube sleeves operating under conditions outside of the bounding values originally used to assess the adequacy of this repair for installation in Westinghouse designed Series 44 and 55 steam generators.
The assessment contained herein verifles that the sleeves described in the original repoet remains an acceptable repair technique for these steam generator tubes.
1
TAlll .E OF CONTENTS SECTION TITI.E PAGE
- 1. INTRODUCTION 1 1.1 PURPOSE 1
1.2 BACKGROUND
1
1.3 REFERENCES
1
- 2.
SUMMARY
AND CONCLUSIONS 1
- 3. ACCEPTANCE CRITERIA 2
- 4. DESIGN DESCRIPTION OF SLEEVES AND INSTALLATION 2 EQUIPMENT
~
- 5. SLEEVE EXAMINATION 2 5.1 ULTRASONIC EXAMINATION 2 5.2 EDDY CURRENT EXAMINATION 2
- 6. SLEEVE TUBE CORROSION TEST PROGRAM 3
- 7. MECHANICAL TESTS OF SLEEVED STEAM GENERATOR 3 TUDES .
- 8. STRUCTURAL ANALYSIS 3 8.1
SUMMARY
AND CONCLUSIONS 3
8.2 LOADINGS CONSIDERED 6 8.3 EVALUATION FOR ALLOWABLF SLEEVE WALL 7 DEGRADATION USING REGULATORY GUIDE 1.121 8.4 EFFECT OF TUBE LOCK-UP ON SLEEVE LOADING 8 8.5 SLEEVED TUBE VIBRATION CONSIDERATIONS 9 4
~
11
4 TABLE OF CONTENTS (cont.)
SECTION TITLE PAGE 8.6 STRUCTURAL ANALYSIS FOR NORMAL OPERATION 10 9.- SLEEVE INSTALLATION VERIFICATION 13
- 10. EFFECT OF SLEEVING ON OPERATION 13 e
e
- l. INTRODUCTION 1.1 PURPOSB The purpose of this addendum is to provide additional infonnation to support a tecimical specification change allowing installation of repair sleeves in Westinghouse designed Series 44 and 51 steam generators that have made changes in their operating parameters beyond those specified in Reference 1.3.1.
1.2 BACKGROUND
As steam generators age, increased plugging limits result in opemting parameters outside the bounds of the inp'at pammeters utilized in Reference 1.3.1.
Additionally, changes in industry requirements that alter input parameters, specifically MSLB conditions, have been incorporated. This addendum addresses these changes and the resulting differences in sleeve loadings and stress levels associated with the sleeve / tube assembly.
1.3 REFERENCES
1.3.1 CEN 629-P, Revision 01, Renair of Westinnhouse Series 44 and 51 Steam Generator Tubes Using f_nk Tinht Sleeves, Combustion Engineering Inc.,
November 1996, 1.3.2 WCAP-14790, Zion Increased Steam Generator Tube Pluzeing and Themial Design Reduction Analysis Progtmn
- 2.
SUMMARY
AND CONCLUSIONS The changes in operating parameters described in this addendum have only a minimal effect on the loads and stresses experienced by any of the sleeve or sleeve plug designs described in Reference 1.3.1. As such the safety factors descrilxx!
therein as described in the analysis and verified by the testing performed, still provide more than adequate margin against operating and faulted conditions.
- 1 of 13
- 3. ACCEITANCE CRITERIA The conditions evaluated in conjunction with the design criteria contained in Reference 1.3.1 are as follows:
Primary Side: 596* F (operating) 2235 psig (operating) 650' F (design) 2500 psig (design)
Secondary Side 495' F (operating) 638 psig (operating) 550* F (design) 1085 psig (design)
Of the parameters described in Section 3.0 of Reference 1.3.1, only the operating conditions have been inodified, Although included here for completeness, design parameters remain as described in the referenced report.
- 4. DESIGN DESCRIITION OF SLEEVES AND INSTALLATION EQUIPMENT The changes in operating parameters described in Section 3 have no affect on the contents of this section of Reference 1.3.1,
- 5. SLEEVE EXAMINATION PROGRAM 5.1 ULTRASONIC INSPECTION The changes in operating parameters described in Section 3 have no affect on the contents of this section of Reference 1.3.1.
5.2 EDDY CURRENT EXAMINATIOF Based on the revised calculations performed in Section 8 for R.G.1,121 analysis, the eddy current testing acceptance criteria given in Section 5.2 of Reference 1,3,1 provides an adequate margin of 11.5 % (vs 12%) with respect to growth and ECT uncertainty, 2 of 13 --
O
- 6. SLE3VE TURE CORROSION TFET PROGRAh!
The changes in operating parameters described in Section 3 have no affect on the contents of this section of Reference 1.3.1.
- 7. AfECilANICAL TESTS OF SLEEVED STEAh! GENERATOR TUHES The changes in operating pammeters described in Section 3 have no affect on the contents of this section of Reference 1.3.1.
- 8. STRUCTURAL ANALYSIS OF SLEEVE-TUBE ASSEhiHIX 8.1 SUhfMARY AND CONCLUSIONS Based on '.he analytical evaluation contained in this section and the mechanical test data contained in Reference 1.3.1, Section 7.0, it is concluded that the Full Depth Tubesheet (FDTS) and the Tube Support (TS) sleeves described meet all the requirements stipulated m Section 3.0 and 8.0 with substantial margins. This addendum highlights the calculations affected by the operating and faulted condition parameter changes found in Section 3. of this Addendum. Calculations involving design conditions remain as described in Reference 1.3.1 Section 8.0.
Only the [ 30 ) inch sleeve in the " worst" case envelopment which is not locked in the tube support will be discussed since it provided the most conservative results in Reference 1.3.1. As such the calculations in this addendum are more conservative or the same as those which would results from a complete analysis as presented in F
Reference 1.3.1 Section 8.0.
8.1.1 Design Sizing The changes in operating parameters described in Section 3 have no affect on the contents of this section of Reference 1.3.1.
8.1.2 Detailed Analysis Summary A summary of the detail analysis changes brought about by the changes in operating parameters and htSLB conditions is as described below and in Tables 81 and 8-2.
3 of 13 4
i . .. . . .
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~
]
4 4
4 l
FORMULAS FOR GENERAL MEMBRANE STRESSES SUMMARIZED IN TABLE 8-1 (Note: All Si equations below are a derivation of the formula in Par. NB.3324.1.)
i
- 1. GENERAL PRIMARY MEMBRANE STRESS (DESIGN TUBESHEET DELTA l PRESSURE) ne changes in operating parameters described in Section 3 have no affect on the contents of this section of Reference 1.3.1.
- 2. MAIN STEAM LINE BREAK J
- 3. PRIMARY PIPE BREAK (LOCA)
The changes in opemting parameters described in Section 3 have no affect on the contents of this section of Reference 1.3.1.
4 of 13
e TAllLE 81 SUSISTARY OF SI,EEVE AND WELD ANALYSIS RESULTS 5 of 13
. - - . , c w
0 j TAHl E 8 2 4
~
1 StiMM ARY OF 1.OWER JOINT (WEl,DED AND ROI,1.ED) DESIGN. ANAINSIS
_ AND TEST REStiLTS
! ~
1 1
i i
8.2 LOADINGS CONSIDEkED
)
j 8.2.1 Upper Sleeve Weld Pullout Load 1
In the event of a main steam line break (MSLB), the pressure differential would be 2560 psi per NRC Generic Lettcr 95-05: " Voltage Based Repair Criteria for Westinghouse
- Steam Generator Tubes AtTected by Outside Diameter Stress Corrosion Cracking", Page 3 of Attachment I as applied to the Westinghouse Plants. Postulating a main steam line break (MSLB) accident, the maximum pullout load would be
7 C
! 8.2.2 Lower Sleeve Rolled or Weld Section Pushout Load i The changes in operating parameters described in Section 3 have no affect on the contents of this section of Reference 1.3.1 I
6 of 13 l
l
e
- k 4
?
8.2.3 Weld FatlFue f
The contents of this pangmph in Reference 1.3.1 do not change.
8.3 EVALUATION FOR ALLOWABLE SLEEVE WALL DEGRADATION !
USING REGULATORY GUIDE 1.121 8.3.1 Normal Opemtion Safety Margin i
l I
8.3.2 Postulated Pipe Rupture Accidents i
i s :
i
- - r L _8.3.3 Avenge Minimum Weld Height Requirements A change in the MSLB AP described in Section' 8.2.1 affects the following
, calculation for minimum weld height i ;
, 7 of 13
1
=
8.4 EFFECT OF TUBE LOCK UP ON SLEEVE LOADING 8.4.1 Sleeved Tube in Operating Steam Generator , Free at Tube Suppon This condition was not reanalyzed.
8.4.2 Sleeved Tube in " Worst" Case Envelopment, Free at Tube Suppon Axial __ Loads at the_ Tube Bundle Peripherv
~
8 of 13
4
.' i i
i t
~
[
p 8,4.3 Sleeved Tube in Operating Steam Generator, Lock up at First Tube Support I This condition was not reanalyzed.
\
8.4.4 Sleeved Tube in " Worst" Case Envelopment, l.ock up at First Tube Support I
- This condition was not manalyzed. '
i.
- 8.4.5 Effect of Tube Prestmss Prior to Sleeving s.
4 The changes in openting parameters described in Section 3 have no affect on the i contents of this section of Reference 1.3.1 8.4.6 Lower Sleeve Rolled or Weld Section Pushout Due to Restrained Thennal
- Expansion
i -
I i :
r Y
l..
1
- 9 of 13
. - . . , , - - - - ~ - - , - - - ~ - - - - - - - - - ~
85 SLEEVED TUl3E VIllRATION RATIONS CONSIDE The changes in operating parameters d 8.6 contents of this section of Reference 131escribed e
STRL'CTURAL AnalysisA pOR NOlt\1 L OPERATION The changes in operating parameters res l i factor in forfactor a usage threegreater of the than four thecases allowed atulyzed hu t n increas 8.6.1 value of 1.0., owever, none of these increases resu Fatigue Evaluation of Upper Sleeve / T b u e Weld l
i I i
\ -
k I
10 of 13
4 t
8.6.2 Evaluation of Lower Sleeve Rolled Section The changes in opemting parameters described in Section 3 have no affect on the contents of this section of Reference 1.3.1 8.6.3 Fatigue Evaluation of Lower Stub Weld For the Lower Sleeve Weld (FDTS) summarized in Table S 1, page 8-4, of Reference 1.3.1 Primary Local Stress:
11 of 13
O s'
h I
l 8.6.4 Fatigue Evaluation of Sleeved Tube Plug Weld 1
12 of 13
o a v' i
- 9. SLEEVE INSTALLATION VERIFICATION The changes in operating pammeters described in Section 3 have no affect on the contents of this section of Reference 1.3.1
- 10. EFFECT OF SLEEVING ON OPERATION The changes in operating parameters described in Section 3 have no affect on the contents of this section of Reference 1.3.1 13 of 13
_= _ _ - =_______ _ _
_