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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20210C2971997-12-31031 December 1997 WCAP-15010, CP Unit 1 Evaluation for Tube Vibration Induced Fatigue ML20154C9211997-12-31031 December 1997 Non-proprietary Rept WCAP-15005, F* Tube Plugging Criterion for Tubes with Degradation in Tubesheet Region of Comanche Peak Unit 1 Sgs ML20097H7121996-01-31031 January 1996 Nonproprietary Bypass Test Instrumentation for Comanche Peak Units 1 & 2 ML20092J1031995-07-31031 July 1995 Non-proprietary WCAP-14315, Analysis of Capsule U from Tx Utils Electric Co Comanche Peak Steam Electric Station Unit 2 Reactor Vessel Radiation Surveillance Program ML20092J1191995-07-31031 July 1995 Non-proprietary WCAP-14345, Evaluation of Pressurized Thermal Shock for Comanche Peak Steam Electric Station (CPSES) Unit 2 ML20127G3861992-12-31031 December 1992 Nonproprietary WCAP-13571, Pressurizer Surge Line Leak- Before-Break for Comanche Peak Unit 2,Presentation Matls ML20116C9701992-07-31031 July 1992 Analysis of Capsule U from Texas Util Electric Company Comanche Peak Unit 1 Reactor Vessel Radiation Surveillance Program ML20116C9821992-07-31031 July 1992 Evaluation of Pressurized Thermal Shock for Comanche Peak Unit 1 TXX-9207, Nonproprietary Evaluation of Thermal Stratification for Comanche Peak,Unit 2,Pressurizer Surge Line1992-02-29029 February 1992 Nonproprietary Evaluation of Thermal Stratification for Comanche Peak,Unit 2,Pressurizer Surge Line ML20094F7101992-02-29029 February 1992 Nonproprietary Evaluation of Thermal Stratification from Postulated Valve Leakage for Comanche Peak Unit 2 RHR Lines ML20092L8561992-02-12012 February 1992 Nonproprietary NRC Bulletin 88-008 Evaluation of Auxiliary Piping for Comanche Peak,Unit 2 ML20092J3571992-01-31031 January 1992 Nonproprietary Technical Justification for Eliminating 10 Inch Accumulator Lines Rupture as Structural Design Basis for Comanche Peak Nuclear Plant Unit 2 ML20092H8741991-12-31031 December 1991 Nonproprietary Technical Justification for Eliminating RHR Lines Rupture as Structural Design Basis for Comanche Peak Nuclear Power Plant - Unit 2 ML20092H8451991-12-31031 December 1991 Nonproprietary Technical Justification for Eliminating Pressurizer Surge Line Rupture from Structural Design Basis for Comanche Peak Unit 2 ML20070G9241990-09-30030 September 1990 Nonproprietary Evaluation of Effect of Surveillance Frequencies & Out of Svc Times on Unavailability of N-16 Reactor Trips & Refueling Water Storage Tank Switchover Function ML20043G3321990-06-30030 June 1990 Nonproprietary Suppl 3 to WCAP-12247, Supplementary Assessment of Leak-Before-Break for Pressurizer Surge Lines of Unit 1. ML19325E7561989-10-31031 October 1989 Nonproprietary Suppl 2 to Addl Info in Support of Evaluation of Thermal Stratification for Comanche Peak Unit 1 Pressurizer Surge Line. TXX-8907, Nonproprietary Suppl 1 to Addl Info in Support of Evaluation of Thermal Stratification for Comanche Peak Unit 1 Pressurizer Surge Line1989-09-30030 September 1989 Nonproprietary Suppl 1 to Addl Info in Support of Evaluation of Thermal Stratification for Comanche Peak Unit 1 Pressurizer Surge Line ML20245J8751989-08-31031 August 1989 Suppl 2 to Evaluation of Thermal Stratification for Comanche Peak Unit 1 RHR Lines ML20246B1161989-06-30030 June 1989 VIPRE-01 Core Thermal-Hydraulic Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications ML20246K1781989-05-31031 May 1989 Technical Bases for Eliminating Rupture of Accumulator Injection Nozzles as Structural Design Basis for Comanche Peak Unit 1 ML20247A4501989-04-30030 April 1989 Nonproprietary Rev 2 to Westinghouse Methodology for Protection Sys,Comanche Peak Unit 1,Rev 1 ML20246E7991989-04-30030 April 1989 Nonproprietary Evaluation of Thermal Stratification for Comanche Peak Unit 1 RHR Lines ML20245G0881989-04-30030 April 1989 Evaluation of Thermal Stratification for Comanche Peak Unit 1 Pressurizer Surge Line ML20247L3111989-03-31031 March 1989 Nonproprietary Rev 1 to WCAP-12230, Westinghouse Setpoint Methodology for Protection Sys ML20236E2381989-03-31031 March 1989 Nonproprietary Evaluation of Thermal Stratification of Surge Line & RHR Lines for Comanche Peak Unit 1 - Presentation Overheads for 890221 TU Electric/Nrc Meeting ML20207M7061988-09-30030 September 1988 Surge Line Stratification Presentation Overheads - 880907 Texas Util Electric/Nrc Meeting ML20154J9831988-04-30030 April 1988 RCS Flow Anomaly Investigation Rept ML20235V8601987-07-16016 July 1987 Response Team Results Rept Rev 1 for Issue Specific Action Plan VII.a.4 Audit Program & Auditor Qualifications ML20235U7521987-07-16016 July 1987 Response Team Results Rept Rev 1 for Issue Specific Action Plan Isap I.d.2 Guidelines for Administration of QC Inspector Tests, Technical Evaluation Rept ML20210E0511986-07-31031 July 1986 Nonproprietary Row 1 & Row 2 Heat Treatment for Comanche Peak Unit 1 ML20214J9321986-05-31031 May 1986 Nonproprietary Shotpeening Licensing Rept for Comanche Peak Unit 1 ML20092H4651984-05-31031 May 1984 Nonproprietary Westinghouse Setpoint Methodology for Protection Sys,Comanche Peak Station. W/Two Oversize Tables.Aperture Cards Available in PDR ML20084A6801984-04-30030 April 1984 Nonproprietary Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Comanche Peak,Units 1 & 2 ML20081E8151983-10-31031 October 1983 Nonproprietary Version of Technical Bases for Eliminating Large Primary Loop Pipe Ruptures as Structural Design Basis for Comanche Peak Units 1 & 2 ML20081A4841983-06-30030 June 1983 Nonproprietary Version of Counterflow Preheat Steam Generator Tube Vibration Summary Rept ML20081A4761983-06-30030 June 1983 Nonproprietary Version of Counterflow Preheat Steam Generator Tube Expansion Rept ML20090D2541983-02-28028 February 1983 Rev 1 to Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internals Lift Rig,Load Cell & Load Cell Linkage to Requirements of NUREG-0612 for Texas Util Generating Co,Comanche Peak,Units 1 & 2 1997-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E8021999-10-0707 October 1999 CPSES Unit 1 Cycle 8 Colr ML20217G4151999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Cpses,Units 1 & 2 ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20216J5701999-09-16016 September 1999 Rev 2 to CPSES Unit 2 Cycle 5 Colr TXX-9920, Monthly Operating Repts for Aug 1999 for Cpses.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Cpses.With ML20211M2981999-08-0606 August 1999 Rev 1 to CPSES Fuel Storage Licensing Rept, CPSES Credit for Soluble Boron & Expansion of Spent Fuel Storage Capacity, Consisting of Revised Title Page and 4-1 ML20210U4081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Cpses,Units 1 & 2 ML20210D8321999-07-23023 July 1999 Safety Evaluation Accepting Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20209H7661999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209H2721999-07-0909 July 1999 2RF04 Containment ISI Summary Rept First Interval,First Period,First Outage ML20209H2631999-07-0909 July 1999 2RF04 ISI Summary Rept First Interval,Second Period,Second Outage ML20209G7501999-07-0808 July 1999 SER Finding That Licensee Individual Plant Exam of External Events Complete with Regard to Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given Design, Operation & History of Comanche Peak Steam Electric Station ML20196L0191999-07-0808 July 1999 Safety Evaluation Granting Request Relief B-6 (Rev 2),B-7 (Rev2),B-12,B-13,B-14 & C-9,pursuant to 10CFR50.55a(g)(6)(i).Technical Ltr Rept Also Encl ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20209G0801999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Cpses,Units 1 & 2 ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively ML20195G5141999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Comanche Peak Steam Electric Station,Units 1 & 2.With ML20216E0711999-05-21021 May 1999 1999 Graded Exercise - Comanche Peak Steam Electric Station ML20206Q0091999-05-14014 May 1999 Safety Evaluation Accepting GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Electric Station,Unit 1 ML20206H2061999-05-0606 May 1999 SER Accepting Exemption to App K Re Leading Edge Flowmeter for Plant,Units 1 & 2 ML20196L2241999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Cpses,Units 1 & 2 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205J7831999-04-0101 April 1999 Rev 0 to ERX-99-001, CPSES Unit 2 Cycle 5 Colr ML20205N3101999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Cpses,Units 1 & 2 ML20204H6371999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Comanche Peak Units 1 & 2 ML20205N1481999-02-28028 February 1999 Corrected Monthly Operating Rept for Feb 1999 for CPSES, Units 1 & 2 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 ML20210J9201999-02-0101 February 1999 CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802- 990201 ML20202D0101999-01-27027 January 1999 Safety Evaluation Supporting First 10-yr Interval ISI Program Plan Requests for Relief B-9,B-10 & B-11 for CPSES, Unit 1 ML20199E9961998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Cpses,Units 1 & 2 ML20207D6091998-12-31031 December 1998 1998 Annual Operating Rept for Cpses,Units 1 & 2. with ML20197K2371998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Cpses,Units 1 & 2 ML20195F3161998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Cpses,Units 1 & 2 ML20154M8841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Cpses,Units 1 & 2 ML20154B5741998-09-30030 September 1998 Safety Evaluation Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves. Licensee Has Established Acceptable Program ML20151W0361998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Cpses,Units 1 & 2. with ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20237C6721998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Cpses,Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236R0711998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Cpses,Units 1 & 2 ML20249B2581998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Cpses,Units 1 & 2 ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20247G3241998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Cpses,Units 1 & 2 ML20216B8661998-04-0101 April 1998 Rev 0 to ERX-98-001, CPSES Unit 1 Cycle 7 Colr ML20216J3061998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Cpses,Units 1 & 2 ML20216J1861998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Comanche Peak Steam Electric Station ML20197A6951998-02-24024 February 1998 Inservice Insp Summary Rept,First Interval,Second Period, First Outage ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 1999-09-30
[Table view] |
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. WESTINGHOUSE CLASS 3 (Non Proprietary) ;
I WCAP 13571 ,
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PRESSURIZER SURGE LINE LEAK-BEFORE BREAK ,
FOR COMANCHE PEAK UNIT 2 r
PRESENTATION MATERIALS ,
December 1992
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Westinghouse Electric Corporation Nuclear and Advanced Technology Division P.O. Box 355 '
Pittsburgh, PA 15230
- 1992 Westinghouse Electric Corporation All Rights Reserved -
! '9301210243 930113'.
PDR- ADOCK 0S000446
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1 M. PDR
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i ENCLOSURE 2 WCAP 13571, PRESSURIZER SURGE LINE LEAK BEFORE BREAK '
FOR COMANCHE PEAK UNIT 2. PRESENTATI0H HATERIALS (NON PROPRIETARY VERSION) v i
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I-A meeting was held on November 2,1992, between TU Electric, Westinghouse, and the i NRC Staff to discuss additional information concerning the application of leak-before break
! technology to the pressurizer surge line for Comanche Peak Unit 2.
1-The presentation materials are included within.
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PRESSURIZER St[RGE LINE l LEAK BEFORE BREAK FOR
, COMANCHE PEAK UNIT 2
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CHRONOLOGY FEBRUARY 1992 ANALYSIS OF PRESSURIZER SURGE LINE LBB SUBMITTED BY TU ELECTRIC I JULY 1992 NRR REQUEST FOR ADDITIONAL INFORMATION j
ON DETERMINATION OF LEAK FLAW SIZE AND DETERMINATION GOVERNING LOCATIONS AUGUST 1992 TU ELECTRIC RESPONSE TO JULY RAI l
- NOVEMBER 1992 MEETING TO RESOLVE CONCERNS REGARDING CODE USED IN LBB ANALYSIS OF UNIT 2 SURGE 4
LINE
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NODE LOCATION 1920-m 4
I HI6IEST STIESSED 1020 mi LE6 WLDL.0CAil0N -
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l Conservatisms in the LBB Methodology
- o Algebraic Sum of Loads for Leakage
) o Absolute Sum of Loads for Stability l 0 Factor of 10 on Leak Rate
! o Factor of 2 on Leakage Flaw i
i Standard Review Plan 3.6.3 1
2 Conservatisms in the Analysis o Average Material Properties for Leakage j o Minimum Material Properties for Stabllity 4
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LOW PROBABILITY OF - A, o, e OCCURRENCE OF LOAD CASE 1
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o As indicated in the surge line report, is judged to be
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a low probability event. It would Fequir the maximum heatup/cooldown stratification case to occur simultaneously 4
with the safe shutdown earthquake (SSE) event following leakage detection at 100% power.
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WESTINGHOUSE AND PICEP RESULTS FOR CASE ~'"A" LEAK RATE o Westinghouse method uses two programs. They are:
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. W, % e This program calculates the crack opening ares
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' This program calculates the leak from tg crack opening area obtained by[ ]Ttwo phase nuld conditons).
o To correspond with the 10 gpm leakage margin, ,c,e Westinghouse estimates a leakage naw size of[ ]
- inches. -
i o The PICEP program calculates both the crack opening area and the leak from that area.
o To correspond with the 10 gpm leakage margin, PICEP estimates a leakage naw size of 5.0 inches.
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l PICEP OVER FREDICTION OF LEAKAGE SIZE FLAW o Crack Opening Area Predictions, o PICEP over predicts the leakage size naw by under-predicting the crack opening areas.
o The next overhead, which shows experimental data ,c,e from a four point bend test, indicates that the[
(Westinghouse method) shows excellent agreement
]
with the test data, while for crack opening areas greater than 0.01 in', PICEP under predicts the opening area. For a 0.02 in' opening area PICEP under-predicts this area by about 40%
o Flow rate predictions. s o Limited test data at 2.7 GPM shows that PICEP under predicted the now by 18 24% while the Westinghouse method [ ]Ii'nd'er predicted the now by only 1-2% This is shown in the overhead with the table. .
- s,c.e o Based on . the limited experiments, _ _
predicts the test data better than PICEP. .
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! COMPARISON OF EXPERIMENTALLY l
DETERMINED LEAK RATES l AND ANALYTICAL PREDICTIONS w,c,e l
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l i CONCLUSION i o Following are the reasons why Westinghouse is convinced that the 5.0 inch leakage flaw size calculated _"by',PICEP
! does not challenge the LBB integrity of the Comanche Feak Unit 2 surge line:
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The conservatisms in the LBB methodology.
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- The low probability of occurrence of the load case a.,c,4
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The excellent agreement of the results with experimental data. _
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The tendency of PICEP to under prbict leak rates by 18 24% compared against the same data.
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NORMAL LOAD (CASE B) AND FAULTED LOAD (CASE G)
Normal Faulted Normal Faulted Normal Faulted Fx lb. FXlb. My(in. My(in. Mz (in- Mz (In.
Ib) lb) Ib) Ib)
Pressurt 219,721 41,781 0 0 0 0 DW 2,690 2,690 - 83,520 83,520 178,260 178,260
. i _ _2A6 SSE 9,080 1,887,220 589,390 ap,e TOTAL
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Normal Faulted
. .%c,e Fx (Ib)
Mb (in lb) 11
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