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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20211M2981999-08-0606 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 ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 ML20198Q7181997-10-24024 October 1997 Rev 5 to ER-ME-067, Evaluation of Thermo-Lag Fire Barrier Systems ML20137D3601997-03-20020 March 1997 Engineering Self-Assessment Rept ML20129F6991996-10-25025 October 1996 Justification for SPC 1986 LBLOCA Evaluation Model W/Interim Adjustment for Non-Physical Behavior ML20100F2761996-02-13013 February 1996 Rev 0 of Engineering Rept, Resolution of NRC GL 95-07 'Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves.' ML20116M4021996-02-0101 February 1996 Commitment Matl Change Evaluation Rept 0001 for 941101- 960201 ML20095K5411995-12-18018 December 1995 Nonproprietary Small Break LOCA Analysis Methodology ML20094P7971995-11-22022 November 1995 Rev 0 to CPSES Risk-Based IST Program Risk Ranking Determination Study ML20094P7821995-11-22022 November 1995 CPSES Risk-Based IST Program Risk Ranking Determination Study Summary Rept ML20094P4231995-09-29029 September 1995 Pyrolysis Gas Chromatography Analysis of 10 Thermo-Lag Fire Barrier Samples ML20085N2911995-06-21021 June 1995 Individual Plant Exam of External Events for Severe Accident Vulnerabilities TXX-9432, Rev 0 to CPSES Fuel Storage Licensing Rept,Cpses Expansion of Spent Fuel Storage Capacity1994-12-0909 December 1994 Rev 0 to CPSES Fuel Storage Licensing Rept,Cpses Expansion of Spent Fuel Storage Capacity ML20097A3821994-08-19019 August 1994 Individual Plant Exam of External Events,Seismic,Cpses ML20069M8761994-06-10010 June 1994 Engineering Rept Evaluation of Unit 1 & Unit 2 Thermo-Lag Configurations ML20064M6081994-03-21021 March 1994 Engineering Rept Evaluation of Thermo-Lag Fire Barrier Sys ML20059F5431993-10-0505 October 1993 Engineering Rept, Evaluation of Fir Endurance Test Results Related to Cable Functionality in 1-1/2 & 2 Inch Conduits ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20127K8121993-01-19019 January 1993 Rev 0,to Evaluation of Unit 2 Thermo-Lag Configurations ML20126G2121992-12-23023 December 1992 Rev 2 to ER-ME-067, Evaluation of Thermo-Lag Fire Barrier Systems ML20126C0421992-12-18018 December 1992 Suppl 6 to Human Factors Control Room Design Review of Comanche Peak Steam Electric Station ML20126A3621992-12-15015 December 1992 Rev 3 to Receipt,Dispensing,Quality & Insp Requirements for Thermo-Lag Fire Barrier Matls ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20116C9511992-10-27027 October 1992 Individual Plant Exam Submittal:Comanche Peak Steam Electric Station Vol II:Back-End Analysis ML20115D2241992-09-29029 September 1992 Rev 1 to HI-92880, Criticality SE of Comanche Peak Fuel Storage Facilities W/Fuel of 5% Enrichment ML20127C8291992-09-0808 September 1992 Rev 1 to Interim Engineering Rept, Evaluation of Thermo-Lag Fire Barrier Sys ML20114B8051992-09-0101 September 1992 Suppl 5 to Human Factors Control Room Design Review of Comanche Peak Steam Electric Station ML20114C6101992-08-31031 August 1992 Individual Plant Exam Comanche Peak Steam Electric Station Vol 1:Front-End Analysis ML20105A7821992-08-14014 August 1992 Engineering Rept on Thermo-Lag 330-1 Fireproofing Coating Thicknesses Required for 1 & 2 Hour Fire Ratings for Various Structural Steel Members Used by Texas Utils Svcs,Inc ML20105A8471992-08-0606 August 1992 Rev 0 to Comanche Peak Steam Electric Station Unit 2 Engineering Bwip Check Valve 2AF-0083 Failure Investigation ML20116C9621992-07-16016 July 1992 Review of IPE Level 2 Draft Repts for Cpses ML20078H1581992-06-19019 June 1992 CPSES Thermo-Lag Barrier Applications Thermo-Lag Fire Test Conduit & J-Box Test Assemblies. Preliminary Test Results ML20095H2411992-04-13013 April 1992 Validation Efforts for Comanche Peak Steam Electric Station Unit 2 ML20094P3371992-03-26026 March 1992 Control Room Simulator 10CFR55 Certification Initial Rept TXX-9200, RHR Line Summary Rept1992-03-23023 March 1992 RHR Line Summary Rept ML20086E3861991-10-31031 October 1991 Pressurizer Surge Line Transient Justification ML20079D0481991-06-21021 June 1991 Engineering Rept, Testing & Analysis of Commercial-Grade Swing Arms in Borg-Warner Check Valves, June 1991 ML20077E0271991-05-31031 May 1991 Methodology for Reactor Core Response to Steamline Break Events ML20217C4601991-05-31031 May 1991 Reactivity Anomaly Events Methodology ML20073Q8291991-05-17017 May 1991 Small Break LOCA Analysis Methodology ML20084V1401991-03-31031 March 1991 Safety Evaluation for Operation of Comanche Peak Unit 1 W/ Positive Moderator Temp Coefficient ML20079D0571991-03-31031 March 1991 Final Rept on Analysis of Check Valve Swing Arms, Mar 1991 ML20066F4331991-01-31031 January 1991 Draft Analysis of Flow Stratification in Surge Line of Comanche Peak Reactor ML20066L0691990-12-31031 December 1990 Large Break LOCA Analysis Methodology ML20066B2391990-12-31031 December 1990 Control Rod Worth Analysis ML20067B1291990-12-24024 December 1990 Suppl 1 to TUE-1 DNB Correlation ML20062D9041990-11-12012 November 1990 Unit One Loose Parts Monitoring Sys Special Rept 1999-08-06
[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] |
Text
_ _ . _ _ . _ _ - .
l COMANCHE PEAK UNIT 1 PREESURIZER SURGE LINE TRANSIENT JUSTIFIC ATION October 1991 S.Tandon Ventied by: -
P. L. Strauch Venfied by: T h.
T.H.Liu WESTINGHOUSE ELECTRIC CORPORATION Nuclear and Ach/anced Technology Division P.O. Box 2728 Pittsburgh, Pennsylvania 15230 2728
@1991 Westinghouse Electric Corp.
FM073710/8SI:101
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EXECUTIVE
SUMMARY
In Apnl 1980, Westinghouse completed WCAP 12248 to resolve NRC Bulletin 8811 which addressed the issue of thermal stratification in the Pressurizer Surgo Line for Comancho Peak Unit 1. Subsequent to this report, the NRC required Texas Utilities (T.U.) Electnc to continue monitonng of the surge line for one additional fuel cycle to ensure that the analysis was conservative. T.U. E:ectnc contracted Westinghouse to review the data from the fuel cycle and eva!uate whether the onginal analysis was conservative.
Based on this review it is concluded that the onginal analysis was very conservative. It is estimated that approximately one seventh as many stratification cycles are expected to occur dunng the life of the plant as assumed in the original analysis Consequently, no further monitoring of this line is necessary.
FM073710491:10-2
^
1.0 INTRODUCTION
in Apnl 1989, Westinghouse completed WCAP 12248 (1) to resolve NRC Bulletin 8811 for Comanche Peak Unit 1. This bulletin addressed the issue of thermal stratification in the pressurizer surge line. It required that the surge line meet the stress and fatigue critena defined by Section lli of the ASME Boiler and Pressure Vessel Code considering the effects of thermal stratification. Per the WCAP 12248 analysis, all Section ill criteria
{
was met for Comanche Peak Unit 1 (1). J h
When the original fatigue analysis was performed in WCAP 12248, stratification j transients were developed to simulate thermal cycling effects on the line. These .
transients were developed for normal, upset and heatup/cooldown conditions using:
(1) - The most recent systems standard design transients.
(2) Heatup and cooldown curves, as developed from review of procedures, operational data, and operator experience.
(3) Historical records of characteristic heatup and cooldown temperatures.
Heatups and cooldowns are characterized by the maximum temperature difference between the pressurizer liquid space and the reactor coolar;t loop hot leg during the heatup/cooldown period.
(4) Transients as monitored at five plants (excluding Comanche Peak),
Subsequent to completing this analysis, Bulletin 8811 was addressed on a genenc basis through a program with the Westinghouse Owners Group (WOG)[2]. Monitoring and operational data from 11 plants was utilized in this effort.
Per the reference (3) letter the NRC required T.U. Electric to confirm that the existing design transients utilized in the plant specific evaluation are conservative.
The purpose of this report is to review Comanche Peak monitoring data received for the period of March 1990 to July 1991 to ensure that the WCAP 12248 transients are conservative with respect to: 1. fatigue cycling and 2. tempprature profile loadings in
, the surge line. Based on this analysis, a conclusion will be drawn regarding the l necessity for further monitoring of the line.
FM073710/8/91:10-3
i
' 2.0 METHODOLOGY i'
in order to objectively compare the expected cyclic activity based on plant monitoring data to the WCAP 12248 transients, a transient set is created based solely on the Comanche Peak monitoring data using the WOG program [2] methodology. This Comanche Peak transient set is then compared to the WCAP 12248 analyzed transients to ensure conservatism.
Using the Reference [2] methodology in creating this transient set is beneficial as the analysis approach used in this report has been accepted by the NRC [4).
2.1 Normal and Uoset Transients The normal and upset transient set was created in WCAP 12248 using the latest Westinghouse systems design standard. As this standard had not changed between the -
time that the Comanche Peak 1 report was issued and the time that the WOG Generic Detailed analysis report was issued, this transient set remained unchanged in the Reference [2] analysis.
2.2 Heatuo and Cooldown Transients As desenbed in Reference [2), heatup/cooldown transients are developed using a ,
conservative historical system delta T distnbution (system delta T = pressurizer liquid space temperature reactor coolant loop (rc!) temperature) along with a Relative Strength of Stratification (RSS) distribution per plant operational mode over one heatup where:
TTp r Pipe ~ IBottom of Pipe RSS =
System Delta T (See Figure 1) l The heatup used in the analysis occurred between November 12 to 15,1990. This particular heatup was chosen because it contained the most stratification cycles. ' This is the case because after entering into mode 3, the plant returned to mode 4 during this heatup. As indicated in Reference [2), in general, the most cyclic activity is expected in the higher modes of operation. By comparison to other heatups, this was the case for Comanche Peak. Consequently, using this hectup results in a conservative assumption for the expected number of cycles per heatup in the analysis.
In this comparative analysis, a RSS distribution is created using Comanche Peak ,
monitoring data at the critical location along the line. The critical location is the FM073710/8,91:104
- _ . . . - . . . . _ _ _ . _ . _ _ _ _ . _ _ _ . . _ - _ _ _ _ - , _ . , _ . , ~ , . . , _ . - _ , - _
4 monitoring location with the greatest cyclic activity, and was determined to be location T 1. T 1 is located approximately halfway up the angled riser adjacent to the hot leg noule (see Figure 1). This t distnbution is combined with the historical system delta T distnbution developed in the WOG l analysis. The WOG system delta T distnbution is used because it best predicts the expected system delta T distnbution over the life of the plant, as it encompasses a number of operating practices from l within the industry.
t 3,0 RESULTS in reviewing the Comanche Peak monitored heatup, only seven stratification cycles were discovereo at the criticallocation. This is much less than the 36.5 cycles per heatup assumed in the WCAP.
12248 analysis. The RSS distnbution for the Comanche Peak heatup is as follows:
RSS Ranges (Max Values)
Mode 1 M M M Q10 Q15 Q10 M Q&Q 015 010 QA5 QAQ Q.15 (
5 0 0 0 2 0 0 0 0 0 0 1 0 0 0 4 0 0 0 0 0 0 0 0 0 0 1 0 0 0 3 0 0 0 1 0 0 0 0 0 0 0 0 0 0
~
2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,
(Recall from Reference [2] that the RSS listed is the maximum value of the range. For example. a cycle with an RSS value of 0.67 would be listed under 0.70),
Also, as indicated in Reference [2), it was determined that cooldowns contained less than half tre number of cycles as did heatups. This was confirmed in the review of the Comanche Peak monitoring data. Therefore, the number of cycles in all transients developed for heatups were multiplied by 1.5 to reflect the total for both heatup and cooldown, in order to compare the transients created here with those used in the WCAP 12248 analysis, seven delta T groups are used. All analyzed heatup/cooldown cycles are added into the higher delta T value group. The extrapolated number of cycles for the life of the plant (based on monitoring data) compared to those used in the Reference [1] analysis is depicted on Figure 2 and listed below:
l
- FM073710/8/91
- 10 5
Do!!a 3 Analyzed Predicted 320'F 54 0 300'F 213 0 275'F 569 243 250'F 1262 360 200'F 741 0 175'F 5960 120 150'F 5857 1377 Total 14656 2100 There are approximately (14656/2100) = 7 times as many cycles used in the analysis as predicted based on monitoring data.
Based on the geometry of the surge line, this high level of conservatism is expected.
This line has a 45' entrance angle from the hot leg. Since stratification occurs as a result of insurges or outsurges to the line (see references [1] and [2)), a relatively high amount of fluid mixing is expected in the Comanche Peak surge line. This is due to the change in fluid direction induced by the angled portion of the line. This high amount of mixing tends to reduce the number of stratification cycles in the line. Since the original WCAP 12248 analysis used data from five different lines, the amount of cycling, on average, was greater than expected for Comanche Peak. This results in very conservative transients for Comanche Peak.
Additionally, the axial stratification profile was evaluated at severalinstances at which the high pipe delta T occurred during heatup and cooldown. All observed axial stratification profiles were determined to be less severe ttan the profile used in the original analysis.
4.0 CONCLUSION
S Based on a review of transients developed from monitoring data, the Reference (1)
WCAP 12248 analysis used a very conservative set of transients in calculating the fatigue usage factor for the Comanche Peak surge line. This high level of conservatism is depicted in Figure 2. Approximately seven times as many transients were assumed in the original analysis. Additionally, the axial stratification profile observed in the monitoring data was determined to be less severe than the profile used in the original l analysis.
FM073710,11SI:104 l
l _ __ _
All evaluations in the original WCAP 12248 analysis and conclusions reached remain valid. Based on the results of this comparative analysis, no additional surge line monitoring is necessary for Comanche Peak. This is consistent with the Reference (3) statement that the temperature monitoring program can be terminated at the first refueling outage.
5.0 REFERENCES
- 1. Westinghouse WCAP 12248," Evaluation of Thermal Stratification for the Comanche Peak Unit 1 Surge Line," Dated Apnl 1989.
2.
Westinghouse WCAP 12639, ' Westinghouse Owners Group Pressurizer Surgo Line Thormal Stratification Generic Detailed Analysis Program MUHP 1092 Summary Repor1," Dated June 1990.
3.
T.U. Electric Letter on NRCB 8811 " Comanche Peak Steam Electric Station (CPSES) Docket No s 50 445 and 50 446 NRC Bulletin 8811: Pressurizer Surge Line Thermal Stratification and Leak Before Break AdditionalInformation," Dated 12/12/89.
- 4. Nuclear Regulatory Commission Letter " Audit of Westinghouse on Generic Detailed Analysis of Pressunzer Surgo Line Thermal Stratification (NRC Bulletin 8811),' Shea to Walsh, Dated 8/6/91.
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