ML20154J891
| ML20154J891 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/19/1988 |
| From: | Malloy M NRC OFFICE OF SPECIAL PROJECTS |
| To: | NRC OFFICE OF SPECIAL PROJECTS |
| Shared Package | |
| ML19297G995 | List: |
| References | |
| NUDOCS 8809230170 | |
| Download: ML20154J891 (56) | |
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#g3** %9'o., UNITED STATES
[l 'g NUCLEAR REGULATORY COMMISSION g ...t WASHINGT*N, O. C. 20655
%.....! SEP 191988 Docket Nos. 50-445 and 50-446 APPLICANT: Texas Utilities Electric Company (TV Electric)
FACILITY: Comanche Peak Steam Electric Station (CPSES), Units 1 and 2
SUBJECT:
SUMMARY
OF MEETING ON SEPTEMBER 7, 1988 - BOUNDING ANALYSIS FOR STRESS CONDITION OF THE PRESSURIZER SURGE LINE At a meeting held on August 18, 1988 in Rockville, Maryland between NRC staff and representatives of TV Electric concerning the proposed application of advanced fracture mechanics analyses (also referred to as "leak-before-break methodology") to the pressurizer surge line at CPSES.* It was decided at that meeting that a follow-up mee. ting should be held within about two weeks to discuss (1) what specific thermal stratification data are available and l why they characterize the pressurizer surge line at Comanche Peak; (2) what instrumentation TU Electric would install to collect Comanche Peak-specific data and how those data compare to other available data; and (3) what opera-tional method (start-up) is planned for the Coinanche Peak pressurizer. These discussions were planned to provide the NRC staff with a basis for deciding whether the data collection and analysis approach proposed by the applicant is appropriate and whether the staff could give further consideration to applying leak-before-break (LBB) methodology to the pressurizer surge line. The follow-up meeting was held on September 7,1988 in Rockville, Maryland. The meeting notice and the list of attendees are provided as Enclosures 1 and 2. The presentation slides are provided as Enclosures 3 and 4. A portion of tne meeting concerned discussions of proprietary data. Presentation slides for j that portion of the meeting are likewise proprietary and have been excluded from this meeting sumary. l T Data from instrumented pressurizer surge lines at the Trojan Nuclear Plant and the Beaver Valley Power Station Unit 2 was discussed together with the applicability ; of these data to the CPSES. The proposed instrumentation for the CPSES Unit 1 ! pressurizer surge line was discussed as well as the schedule for conduct of hot functional testing. In addition, the operational methods for start-up and ' shutdown and their influence on thermal stratification in the CPSES pressurizer surge line were discussed.
- See sumary of Meeting on August 18, 1988 - Application of Leak-Before-Break (LBB) Nethodology to the Pressurizer Surge Line dated August 31, 1988. l i
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r . Sunnary of 9/7/88 meeting l The applicant discussed with the staff in more detail the proposal presented at the meeting on August 18, 1956 to instrument the Unit 1 surge line and
- analyze the effects of thermal stratification on the piping. The applicant feels that the proposed analysis methodology is likely to result in conser- ,
vatively bounding the stress condition in the pressurizer surge line at CPSES and establishing the surge line's integrity for approximately 5 to 10 years, i for a long-term resolution, the applicant proposes to supplement the bounding , analysis with a plant-specific analysis using data obtained during hot functional testing from the instrumented CPSES Unit 1 pressurizer surge line and with the results of the Westinghouse Owners Group surge line stratification program. The staff indicated that the applicant's plans for analyzing the effects of ; thermal stratification in the surge line was proceeding in a technically sound , manner. The decision as to whether to permit application of leak-before-creak methodology to the pressurizer surge line in the event that the applicant's analyses demonstrate a service life less than 40 years will be further evaluated by the staff. The staff recognizes that not allowing the application of LBB methodology to the pressurizer surge line will likely result in a significant impact on the CPSES licensing schedule while plant modifications are made. The staff indicated that : it would provide additional feedback to t applicant in oximately a week.
}{
Melinda Malloy, Project Man r
! Comanche Peak Project Divis n Office of Special Projects -
Enclosures:
! 1. Meeting Notice
- 2. List of Attendees ;
- 3. TV Electric Presentation Slides
i
- 4. Duquesne Light Presentation Slides l
- 5. Proprietary Presentation Slides ;
(NRC Docket File copy only) . cc: See next page l l l l 1 l 1 i
September 19, 1988 r . Sumary of 9/7/88 meeting The applicant discussed with the staff in more detail the proposal presented at the meeting on August 18, 1988 to instrument the Unit 1 surge line and analyze the effects of thermal stratification on the piping. The applicant feels that the proposed analysis methodology is likely to result in conser-vatively bounding the stress condition in the pressurizer surge line at CPSES and establishing the surge line's integrity for approximately 5 to 10 years. ; For a long-term resolution, the applicant proposes to supplement the bounding analysis with a plant-specific analysis using data obtained during hot functional testing from the instrumented CPSES Unit 1 pressurizer surge line and with the results of the Westinghouse Owners Group surge line stratification program. The staff indicated that the applicant's plans for analyzing the effects of thermal stratification in the surge line was proceeding in a technically sound manner. , 1 The decision as to whether to permit application of leak-before-break methodology l to the pressurizer surge line in the event that the applicant's analyses demonstrate l a service life less than 40 years will be further evaluated by the staff. The staff recognizes that not allowing the application of LBB methodology to the pressurizer surge line will likely result in a significant impact on the CPSES ' licensing schedule while plant modifications are made. The staff indicated that it would provide additional feedback to the applicant in approximately a week. qMainst simped W.s Melinda Malloy, Project Manager Comanche Peak Project Division Office of Special Projects
Enclosures:
1
- 1. Meeting Hotice
- 2. List of Attendees
- 3. TU Electric Presentation Slides
- 4. Duquesne Light Presentation Slides
- 5. Proprietary Presentation Slides (NRC Docket file copy only) cc: See next page Distribution .#/o Enclosure 5: Distribution w/ Enclosure 5:
NRC PDR RWarnick K. WichN n Docket F11e <L Local POR JWiebe Slee OSP Reading MHalloy THarsh CPPD Reading Dierao PKuo JPartlow 0GC SNHou CGrimes DCrutchfield GDick FMcKee EJordan PTam JHWilson BGrimes Tchan JLyons CCheng ACRS(10) MNalloy CPPD:05 DTerao AD:C JHWi . h 09/d/88 09/p/88 09/d/ f
0 0 W. G. Counsil Comanche Peak Steam Electric Stacion Texas Utilities Electric Company Units 1 and 2 cc: Jack R. Newman, Esq. Asst. Director for Inspec. Programs Newman & Holtzinger, P.C. Comanche Peak Project Division Suite 1000 U.S. Nuclear Regulatory Commission 1615 L Street, N.W. P. O. Box 1029 Washington, D.C. 20036 Granbury, Texas 76048 Robert A. Wnoldridge, Esq. Regional Administrator, Region IV Worsham, Forsythe, Sampels & U.S. Nuclear Regulatory Commission Wooldridge 611 Ryan Plaza Drive Suite 1000 2001 Bryan Tower, Suite 2500 Arlington, Texas 76011 Dallas, Texas 75201 Lanny A. Sinkin Mr. Homer C. Schmidt Christic Institute Director of Nuclear Services 1324 North Capitol Street Texas Utilities Electric Company Washington, D.C. 20002 Skyway Towar 400 North Olive Street, L.B. 81 Ms. Billie Pirner Garde, Esq. Dallas, Texas 75201 Government Accountability Project Midwest Office Mr. R. W. Ackley 104 East Wisconsin Avenue Stone & Webster Appleton, Wisconsin 54911 Comanche Peak Steam Electric Station P. O. Box 1002 David R. Pigott, Esq. Glen Rose, Texar, 76043 Orrick, Herrington & Sutcliffe 600 Montgomery Street Mr. J. L. Vota San Francisco, California 94111 Westinghouse Electric Corporation P. O. Box 355 Anthony Z. Roisman, Esq. Pittsburgh, Pennsylvania 15230 Suite 600 1401 New York Avenue, NW Susan h. Tneisen Washington, D.C. 20005 Assistant Attorney General , Environmental Protection Division Robert Jablon P. O. Box 12548, Capitol Station Bonnie S. Blair Austin, Texas 78711-1548 Spiegel & McDiarmid 1350 New York Avenue, NW Mrs. Juanita Ellis, President Washington, D.C. 20005-4798 Citizens Association for Sound Energy 1426 South Polk George A. Parker, Chairman Dallas, Texas 75224 Public Utility Committee Senior Citizens Alliance Of Ms. Nancy H. Williams Tarrant County, Inc. CYGNA Energy Services 6048 Wonder Drive 2121 N. California Blvd., Suite 390 Fort Worth, Texas 76133 Walnut Creek, CA 94595
W. G. Counsil Comanche Peak Electric Station Texas Utilities Electric Company Units 1 and 2
'CC:
Joseph F. Fulbright Fulbright & Jaworski 1301 McKinney Street Houston, Texas 77010 Roger D. Walker Manager, Nuclear Licensing Texas Utilities Electric Company Skyway Tower 400 North Olive Street, L.B. 81 Dallas, Texas 75201 Texas Utilities Electric Company c/o Bethesda Licensing . 3 Netro Center Suite 610 Bethesda, Maryland 20814 William A. Burchette, Esq. Counsel for Tex-La Electric Cooperative of Texas Heron, Burchette, Ruckert & Rothwell Suite 700 1025 Thomas Jefferson Street, NW Washington, D.C. 20007 l GDS ASSOCIATES INC. Suite 720 1850 Parkway Place Marietta, Georgia 30067-8237
O ENCLOSURE 1 .
/ga at%,*S, UNITED STATES , .i ,t .
1 NUCLEAR REGULATORY COMMISSION 4 wassiNoToN.,0. c. zosss 3, , i--f, (j .2.. .. hA,/1 /C,d. N / pg[ 30) $$ Uccket Nos. 50-445 and 50-446 MEMORAHOUM FOR: Christopher I. Grimes, Director Comanche Peak Project Division Office of Special Projects FROM: James H. Wilson, Assistant 91 rector for Projects Comanche Peak Project Division Office of Special Projects
SUBJECT:
FORTHCOMING MEETING WITH TU ELECTRIC Date and Time: N , .m , N _ym ., ;;; Md,adgesdag , 7, /93$ 9:00 am ':M pr "3 : 80 pm (/ Location: One White Flint North 11555 Rockville Pike Rockville, MD 20855 Room Vo. 88-11
Purpose:
Review of Comanche Peak pressurizer surge line stratification
Participants:
- NRC TU Electric Westinghouse R. L. Clou,d C. Grimes R. Walker G. Anta(i W. Server J. Lyons J. tiuffett D. Pearty R. Beaudoin J. H. Wilson D. Rencher R. Carlson D. Terao H. Marvray R. Brice-Nash ,
C. Cheng R. Flores R. Coffield K. W1cnman S, Swamy li. Hodges B. Maurer L. flarsh o . s . .. I)Q Yh James'.. Wilscn, Assistant Director forTrojects Comanche Peak Project Division Office of Special Projects
Enclosure:
Proposed agenda cc: See rext page
- ceetings between NRC tectinical staff and applicants fur licenses are open for interested members of the public, petitioners, intervenors, or otner parties to attena as coservers pursuant to "Open Meettngs ard Statement of hKC Staf f Felicy," 43 Federal Register .'6058, 6/28,76. nowever, portions cf this meeting will be closeo to tne gereral public due to the presentatler, arc discussion of proprietary intorri.ation.
_.sg e 4&l M O SPF
=
EtiCLOSURE e .
- Proposed Agenda
- 1. Introduction and Agenda
- 2. Background
?. Description
- a. Systems Operation
- b. Stratification in Pressuri:er Surge Line
- 4. Engineering Evalaation
- a. Monitoring Program
- b. Definition of Transients
- c. Heat Transfer
- d. Piping Global Effects
- e. Piping Local Effects
- f. Piping System and Compartment Qualification
- 5. Leak-Befdre-Break
- 6. Summary O
O , e 4
Mic4, M / 3
.1 -
Aseht F De WT (' 'C. !. Gr' ices Forthcoming meetirg with 70 Electric en September 1, 1988 to review of the i Comanche Peak pressurizer surge line stratification DISTRIBUTION Docket File - NRC POR
, Local POR OSP Reading 4 CPPD Reading J. Partlow
., C. Grimes P. McKee J. H. Wilson ! J. Lyons
- R. Warnick B. Zalcman F. Miraglia <
M. Malloy '
- D. Terao W. Lanning ,
4 OGC E. Jordaa
- 6. Grimes Receptionist (WF) hRC Participants ACRS(10)
GPA/PA J. Sutton J. Gilliland RIV/PA S. Matthews J. Bradfute T. Cher. , SHERRY t AO:CFP0: , JHWilson C8//f/ 88 i b i l t i i
- - - , - . . . . . . ~ _ _ _ . . - . _ . .
W. G. Counsil Comanche Peak Steam Electric Station Texas Utilities Electric Company Units 1 and 2 cC' Jack H. Newman, Esq. Asst. Director for Inspec. Programs Newman & Holtzinger, P.C. Comanche Peak Project Division . Suite 1000 U.S. Nuclear Regulatory Commission 1615 L Street, N.W. F. O. Box 1029 Washington, D.C. 20036 Granbury. Texas 76048 i Robert A. Wooldridge, Esq. Regional Administrator, Region IV ' Worsham, Forsythe, Sampels & U.S. Nuclear Regulatory Commission Wooldridge 611 Ryan Plaza Drive, Suite ICCO 2001 Bryan Tower, Suite 2500 Arlington, Texas '5011 Dallas, Texas 75201 Lanny A. Sinkin Mr. homer C. Schmidt Christic Institute Director or Nuclear Ser/ ices 1324 North Capitol Street T(xas Utilities Electric Company Washington 0.C. 20CC2 Skyway Tower 400 North Olive Street, L b. 81 Ms. Billie Pirner Garde. Esq. , Dallas, Texas 75201 Government Accountability Project Midwest Office Mr. R. W. Ackley 104 East Wisconsin Avenue Stor.e & Webster Appleton, Wisconsin 54911 Comanche Peak Steam Electric Station P. O. Box 1002 David R. Pigott, Esq. Glen Rose, Texas 76043 Orrick, Herrington & Sutcliffe ECO Montgomery Street Mr. J. L. Vota San Francisco, California 94111 Westinghouse Electric Corporation P. O. Box 355 Anthony Z. Roisnan, Esq. Pittsburgh, Pennsylvania 15230 Suite 600 1401 New York Avenue, NW Susan M. Theisen Washington, D.C. 2CC05 Assistant Attorney General Environmental Protection Division Robert Jablon P. 9. box 12548, Capitol Staticn Bonnie S. Stair Austin, Texas 78711-1548 Spiegol & McDiarmid 1350 New York Avenue, NW Mrs. Juanita Ellis, President Washington, D.C. 20005-4798 Citizens Association for Sound Energy 1426 South Polk George A. Farkar, C1' rman Dallas, Texas 752:4 Public Utili ty Cemn: . tee Senior Citizens Alliance Of Ms. Nancy H. Williams Tarrant County, Inc. CYGNA Energy Services 6048 Wonder Drive 2121 N. California Blvd., Suite 390 Fort Worth, Texas 7613; Walnut Creek, CA 94596 I
E Comanche Fetk T'ectric Station W. G. Counsil Texas btilities Electric Company Units 1 ar.c ? cc: Joseph F. Fulbright Tulbright & Jawerski 1301 McKinney Street Houston, Texas 77010 Roger D. Walker Manager,tiuclear Licensing Texas Utilities Electric Company Skyway Tower 400 horth Olive Street, L.C. bl Dallas, Texas 75201 Texas Utilities Electric Company c/o Bethesda Licensing 3 Metro Center, Suite 610 Bethesda, Maryland 20814 4 William A. Burchette. Esq. Counsel for Tex-La Electric Cooperative ,' of Texas Peron, Burchette, Ruckert b Rothwell Suite 700-1025 Thomas Jefferson Street,liW Wasilington, D.C. 20007 GOS ASSOCI A'IES, Ific. 4 Suite 720 1850 Parkway Place Marietta, Georgia 30067-8237
/ -
ENCLOSURE 2 LIST OF ATTENDEES AT MEETING HELD IN ROCKVILLE, MD ON SEPTEMBER 7, 1988 - PRESSURIZER SURGE LINE NRC WESTINGHOUSE
'PT McKee "G. Antaki
'J. Lyons 'D. Roarty
*J. Wilson *E. Johnson
'J. Wiebe 'R. Brice-Nash
'M. Malloy 'S. Swamy
'd. Moore *H. Barlow C. Cheng 'G. Ellis
'A. Wichman 'B. Maurer S. Lee *C. Benton
*L. Marsh 'H. Sandner
'S, Hou 'J. Vota
'G Dick *R. Carlson
*P. Tam 'R. Coffield *
'T. Chan
*P. T. Kuo BNL DUQUESNE LIGHT
*S. Mukherjee
'UT DeGrassi
'M. Te ta
'G Kammerdeiner
'N. Tonet TV ELECTRIC HOUSTON LIGHTING AND POWER "R. Walker "A. Harrison
'J. Muffett 'd. Bailey
'J. Redding
'A. Marvray
'R Flores
*D. Rencher STONE & WEBSTER
'S. Greer w m-- - , .--,,-_w, - - - - , _ ,e e
ENCLOSURE 3 ( ' mummmmemummume mummer assem um-mm. ====== TU ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION l [ 1 PRESSURIZER SURGE LINE STRATIFICATION LEAK - BEFORE - BREAK i PRESENTATION TO THE NUCLEAR REGULATORY COMMISSION ROCKVILLE, MD SEPTEMBER 7,1988 1 . .. . - .-__ . - _.-.. - .
PRESSURIZER SURGE LINE STRATIFICATION - AGENDA SEPTEMBER 7, 1988 9 10:00 A.M. ' l l
- 1. INTRODUCTION AND AGENDA R. WALKER (TU ELECTRIC)
- 2. BACKGROUND J. MUFFETT (TU ELECTRIC)
G. ANTAKI (W)
- 3. DESCRIPTION A. SYSTEMS OPERATION R. CARLSON (W) i B. STRATIFICATION IN PRESSURIZER D. ROARTY (W)
SURGE LINE C. UTILITY EXPERIENCE
- 4. ENGINEERING EVALUATION (CPSES SPECIFIC)
A. MONITORING PROGRAM R. FLORES (TU ELECTRIC) i D. ROARTY (W) D. RENCHER (TU ELECTRIC) i B. DEFINITION OF TRANSIENTS D. R0 ARTY (W) 1 C. HEAT TRANSFER D. RGARTf (W) D. P1 PING GLOBAL EFFECTS G. ANTAKI (W) E. PIPING LOCAL EFFECTS 0. R0 ARTY (Ws 4 F. PIPING SYSTEM AND COMPONENT G. ANTAKI (W) QUALIFICATION '
- 5. LEAK-BEFORE-BREAK (CPSES SPECIFIC) 5. SWAMY (W)
- 6.
SUMMARY
J. MUFFETT (TU ELECTRIC) l
e
\
TU ELECTRIC COMANCHE PEAK GTEAM ELECTRIC SThTION . LEAK - BEFORE - BREAK
'ACKGROUND B i APRIL 15,1988: CPSES WHIPJET REPORT ON LEAK-BEFORE-BREAK SUBMITTED TO NRC JUNE 22,19 88: CONFERENCE CALL WITH NRC, TU ELECTRIC, AND CONSULTANTS.TO DISCUSS WHIPJET REPORT JUNE 22,19 88: IE BULLETIN HO. 8 8-0 8 ISSUED JUNE 24,19 88: IE BULLETIN HO. 88-08 SUPPLEMENT 1 ISSUED JULY 2 0,1988: CONFERENCE CALL WITH NRC, TU ELECTRIC, AND CONSULTANTS TO DISCUSS THE PRESSURIZER SURGE LINE 1
AUGUST 4,1988: IE BULLETIN NO. 88-08 SUPPLEMENT 2 ISSUED f AUGUST 18,1988: NRC/TU ELECTRIC MEETING TO DISCUSS LEAK-BEFORE-BREAK , t
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ n
l l
SUMMARY
RCL-PRESSURIZER AT OCCUR DURING CERTAIN MODES OF OPERATION, WHICH CAN RESULT IN STRATIFICATION OF FLOW IN SURGER LINE. EXTENSIVE DATA FROM REFERENCE PLANT AND LABORATORY TESTS l ALLOW US TO UNDERSTAND STRATIFICATION. STRATIFICATION CAN BE PREDICTED AND ANALYZED. l DESIGN TRANSIENTS WILL BE ADJUSTED TO INCORPORATE j STRATIFICATION. STRESS ANALYSIS (ASME QUALIFICATION AND LBB) WILL INCORPORATE SilRGE LINE STRATIFICATION TRANSIENTS. i - PROGRESS REPORTS WILL BE PROVIDED TO NRC. A FINAL REPORT (WCAP) WILL BE SUBMITTED. l
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9 CPSES Pressurizer Surge Line Stratification - ASME Ill anc LBB Qualification Prgcram SES Curren CPSC.S Cursens CPSES sa' - oa~ - uorm e i
,e,e.e_a g. n, oe s.g.,1r aes.,,, oe s., A,,a,, . .,
- Weigh"
- Pressure Stra tJacehon Heat Transles Fkso Mechare;$ Analysis Seismic
, pg A g l - Thurmal Upda ed Design Tsansents for Staat t.cas.on l
Surge Line Stress Analpas l ASME la Ovakfication of Sys,em & Componerats I , LBD Ouuktscateun i HFT Morutosing (18 Not Cos>Istned) Po cr ASME Stress Monitosing Repos a (11 hos Contamea) , 1340 026914 016 #** '"
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O e l i i 1 RCS Pressurizer-I l i l Aux. Spray
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{ PRESSURIZER i l PnOVIDES A POINT IN THE RCS WHERE LIQUID AND VAPOR CAN l BE MAINTAINED IN EQUILIBRIUM UNDER SATURATED
) CONDITIONS FOR PRESSURE CONTROL PURPOSES.
FUNCTIONS: i
- 0 TO PROVIDE A MEANS FOR ATTAINING l OPERATING PRESSURE DURING PLANT HEATUP.
i { O TO MAINTAIN THE REQUIRED RCS PRESSURE { DURING STEADY STATE OPERATION. ! O TO LIMIT PRESSURE CHANGES DURING NORMAL f PLANT OPERATION TO WITHIN AN ALLOWABLE ! RANGE. me ! O TO PREVENT Te RCS PRESSURE FROM I EXCEEDING ITS DESIGN VALUE. ? l
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- Aux. Spray Pressurizer
- - - - = - - a a gg gg y Pzr Heaters t1 Spray Spray
\/
RCS g Decay Heat (t , / Loop _ i / Volume -
'RHRS 1
Surge Line ! a m l Charging RCP Seal in
. Leakage, ,
Letdown D013 D?6914 022 l }
A ! Steam Bubble Mode Heatup ~ Temperature ( F) 700 l H6 653 F 1 600 - H5 u f H4 l H1 H2 500 - H3 "
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) 425 F ~ ,
' A '
l 325 Psia 400 - 1 TPres l 300 --
=
TRcs l l120F ' 200 - i , l y ; 100 a I I I
! 0 2 4 6 8 10 12 14 16 1
18 20 ! Time (Hours) i D013 D26914 025 I
l l STEAM BUBBLE MODE HEATUP .' i i j ORIGIN OF LARGE PZR - HOT LEG TEMPERATURE DIFFERENTIAL l l THE LARGE DIFFERENTIAL TEMPERATURE RESULTS FROM THE ! REQUIREMENT THAT A STEAM BUBBLE BE PRESENT IN THE il PRESSURIZER BEFORE THE RCP'S ARE STARTED. - i l PROCEDURE: O THE RCS IS PRESSURIZED TO 325 PSIA, THE j PRESSURE REQUIRED FOR RCP OPERATION. i l 0 THE PRESSURIZER COOLANT IS THEN HEATED WITH i PRESSURIZER HEATERS TO 4250F, THE SATURATION TEMPERATURE, AND A STEAM BUBBLE DRAWN. O THE RCP'S ARE THEN STARTED TO BEGIN HEATING UP THE RCS COOLANT. AT THIS TIME THE PZR - HOT LEG TEMPERATURE DIFFERENTIAL IS
- APPROXIMATELY 3200F.
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l i Steam Bubble Mode Cooldown Temperature ( F) 4 700 i C1 g 653*F
~
600 550*F 500 - k C4 Cs I I ' 425T 1 400 - ' 325 Psia C7 300 - TRes ' 300 F ,, 67 Psia i ! 200 - 1 1 120*F ) 39g I I I i , , 1 j 0 2 4 6 8 10 12 14 16 18 li Time (Hours)
- Do t3 D26914 023 l
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C00LDOWN - i ACCOMPLISHED IN TWO PHASES, USING STEAM SYSTEM DOWN TO i 3500F AND 400 PSIG AND THEN RHRS. . FOR BOTH STEAM BUBBLE AND WATER SOLID MODES, PZR IS 1 . COOLED DOWN TO 4250F WITH PRESSURE AT 325 PSIA. i STEAM 8UBBLE MODE F i O WHEN RCS REACHES 1600F, OPERATING RCP IS SHUTOFF. O SHUTDOWN STEAM BUBBLE CONDITIONS ACHIEVED WITH AUXILI.".RY SPRAY. WATER SOLID MODE O CHARGING FLOW IS INCREASED AND PRESSURIZER ) SPRAY OPERATED TO FILL PRESSURIZER AND COLLAPSE BUBBLE. t i
l i i i 3A.
SUMMARY
- SYSTEM OPERATION MAXIMUM oT OF 3200F FOR CPSES i -
SIGNIFICANT OT ONLY OCCURS DURING CERTAIN MODES OF OPERATION i . DURING POWER OPERATION DT LESS THAN 500F OPERATIONS OF CPSES AND REFERENCE PLANT ARE VERY SIMILAR t ] 4 o
+ -
Outline
- Criterion to estaalisri stratification
- Spatial variations in stratified flow i
- Thermal striaing 30tential associated with l stratification i
1340 D25914.002
/ 9EACTOR HYDRODYNAMICS TABLE 4-11 '
IMPORTANT DIMENSIONLESS GROUPS FOR SIMILITUDE IN HYDRODYNAMIC TESTING Parameter Symbol Definition Significance
' / OAP/2pV2L Weisbach frcton, Pressure forcelinertia force factor
- 2. Cavitation nuinoer b (P, -P,)/p V # Pressure efference/mertia force
- 3. Reynolds number Re pVD/g ineftia force /vtscous force
- 4. Strounal numoer Sr @/V Vortex shedong frecuencyl inertia force
- 5. Weber number We pOV8 /o inertia force / surface-tenson force 2
- 6. Froude number Fr V /g O Inertia force /gravrty force 3
- 7. Rchardson number Ri ApgD/pV Buoyancy force /merte force (Modshed Froude number)
- 8. Euler number Eu AP/pV' Pressure force /inerte force
- 9. Prandtl number Pr gC/k Momentum diffustvitylthermal diffusrvrty
- 10. Peclet number Pe pVOC/k Convectrve heat transfert (Re x Pr) conductive heat transfer
- 11. Grashof number Gr L'p agsAT/g 8 Buoyancy force /vs:ous force
- 12. Raylegh number Ra L3p'CgsAT/pk (Gr x Pr)
NOMENCLATURE: lC = specihc heat g = acceleraten of gravity p = density P = pressure u = surface tenson P, = state flud pressura k = thermal conductrvrty P, = flud vapor pressure
#- = volumetre expansion coefficient LO = charactenstc dimensons
! AT = flud temperature change V = flud velocrty ( ,. " ,ortex shedding frequency = viscosrty
Stratification Potential Based on Richardson Number
. Stratification potential exists if R1 > 1
. Example: 90 GPM in 14" schedule 140 pipe with 300 F hot-to-cold temperature difference gives ApgD g 3aTD ~
Ri - -
- 60 V2 V 2 l OR if ~ 700 GPM
! Ri = 1 - 1 i OR if AT ~ 5 F l R1 = 1 1340 D26914.003
j . SPATIAL VARIATIONS IN STRATIFIED FLOW O LIMITED HEAT EXCHANGE BETWEEN HOT AND COLD FLUID LAYERS; EARLIER EXAMPLE WOULD ONLY ATTEdUATE A T BY 10% AFTER 70 FEET (USING STANDARD SEMI-INIFINITE BODY SOLUTION),
! O STRATIFIED FLOW COULD PERSIST IN THE STRATIFIED STATE FOR LONG PERIODS AFTER FLOW STOPS.
i O BASEDONOBSERVATIONSFROMSMAgLANDLARGEDIAMETER WESTINGHOUSE TESTS, FLOW IN 90 ELBOW WOULD BE EXPECTED TO HAVE PATTERN SHOWN BY ATTACHED FIGURE. l [ O HOT-TO-COLD INTERFACE CAN BE STEEP AS SHOWN BY ATTACHED
, DATA FROM WESTINGHOUSE TESTS.
I )l i I 1 I 4 1
a
} N .
- Thermal Striping Associated l with Stratification
! . Hot-to-cold interf acial sur"ace oscillation in ) range of 0.1 to 10 hertz (Westinghouse tests + i~ Japanese tests}. .i Hea : transfer coefficient, BTU / HR-FT 2 _ F, in l range (for earlier exam 3le?. c , 263 s; HMAx < 1052 / l Based on boundary layer development arguments-l (ful y developec, classical entrance region.or J limited Bergies data for vibrating plates}.
+0 D26914.006
Estimate of Flow Stratification Pattern in Elbow Under Pressurizer Hot Flow from Pressurizer Thot = 425 F r
~
m A > ~ l i I . e Velocity = 0.3 fps i I I i/ t t i t i i i i i i i i I
" ~
Velocity 0.6 fps i \' * /
\ (\_ ____. / ____
[) - I - N~ n ,-
~ Stagnant Cold Fluid Tcold = 125 F j j' 1340 026914.008
~
1 i ] i 'I 1 3a.
SUMMARY
- STRATIFICAT. ION l-i -
STRATIFICATION CAN EE PREDICTED THERMAL HYDRAULIC PARAMETERS (oT, D A!40 v)
- SIMILAR FOR CPSES AND REFERENCE PLANT.
i - EXISTING. TEST DATA GENERALLY APPLICABLE TO SURGE ! LINE. } l f 1 l ) __ _ _. _ _ _ . . . _ . ~ _ . _ ,_ . _ .
. \
TU ELECTRIC l IPO-OO1 A/IPO-OO5A HEATUP/COOLDOWN PROCEDURES . P 4 I ! COMANCHE PEAK i STEpM ELECTRIC ' STATION j I RALPH FL_ ORES -
l i IPC-001A PLANT HEATUP PROCEDURE HAJOR E'iP*.UTIONS PERfAINT'.C TO HEATUP INITIAL CONDITION' o RCS T1* '"9'F. 170*F o RCS PL t' ' 5 PSIG o- PRZR TEl. 20'F. 170'F PROCEDURAI. GUIDANCE o START NO 1 AND 4 REACTOR COOLANT PUMPS INITIATING PLANT HEATUP. (ONLY IF RCS TEMPS.;30*F) o INITI.\TE PP.ESSURIZER !!EATUP. o DRAW PR8SS'JRIZER BUBBLE. t Cl!EMISTRY PAP.AliETERS IN SPEC. o START N0 1 AND 4 REACTOP. COOLANT PUMPS TO INTTIATE RCS HEATUP. IF NOT PREVIOUSLY DONE. o RHR OUT OF SERVICE. o START NO 2 AND 3 REACTOR C00LAhT PtPfPS TO ASSIAT IN RCS llFATUP. o INITIATE PRESSURIZER HEATUF AND PP. ESSURE INCREASE. o START REMAINING REACT 0h C00LAN* IF NCT PREVIOUSELY DONE. s _x -__. . , , , ._ - -
Drawr Start 2 Start l WT Par H/Ul Pzr .... RCP's - - - - . 1 or 2 Remai. in9 --------------- a inc ) -- lStart 4th I,, ' Bubble RCSM/U RCP's Press RCP j h - P , , . - J . . 657"F .l e \ m _y_ 440*F
- Max: 50'F/hr l p .
- =
(*F) - . C S Max: 50 F/hr 3f.p 340*F g , l T 557'F .
$ Final Cond:
p T-Pzr = 657 F _ 3:
/ T-RCS - 557 F I
1701
- 305 [y, ( P-RCS - 2235 j {
1 . n "
^
C ' Ps/g > 605#' g .
" anti + / "
{rcs s 1970#j 22., 3# . P ' r l l e S l ' s 325 # : (psig) l P _ m____-m_ _ _ - _ - - _ _ _ _ . _ _ _ _ _ . _
~,
, i Start l Draw
~
Start 2 Resume 1 ar 2 Prr H/U my RCP's -- Pzr RCSil/U . &Inc Start 4th Reraaining ------- .. .. , RCS H/U Bubble ggg.s Press RCP . g e l , l z l l l 657"F i
- y\ l e ; =
m 440*F = Max: 50 F/hr l p --->--- - a
=
(4) . l
. ,' =
=
a n :Eccs: I C * -
/*
S Max: 50 F/hr 3g6.g M07 , T 557*F Final Cond- . Max: 50*F/nr p I g T-Pzr = 657 F +.
. 37o r p. T-RCS - 557 F I, I "
./ i3rfp J -
y P-RCS = 2235 y
=
H . C (Ps/g > 605#' l S g -> . p {'scs s 1970aj 2235u r l 0 s : s 325 # l (psio) - l a
=
. f r
1 ^ I IPO-001A PLANT HEATUP PROCEDURE INITIAL BUBBLE RCP START PRZR H/U FINAL ;
, CONDITIONS $0'F/HR 50'F/HR 50'F/HR CONDITION RCS TEMP BETWEEN BETWEEN* HEATUP HEATUP 130-170 130-170 130-300 300-557 TIME DURATION N/A N/A 4 HRS 6 HRS 557 i PRESSUR12ER BETWEEN HEATUP *
, 130-170 130 co 440 440 440 to 657 TIME DURATION N/A 7 HRS N/A 5 HRS 657 i PRESSURIZER PRESSURIZE PRESSURE 325 325 325 325 to 2235 ! TIME DURATION N/A 7 HRS N/A 5 HRS 2235 i DELTA T 0 0 to 310 310 to 140 140 to 100 I i (PRZR.RCS) i [ TIME DURATION 7 HRS 4 HRS 6 HRS l I l 5 i l l e r I e i i
]
I ,, )
P IPO-005A PLANT C001.DOWN PROCEDURE MAJOR EVOLUTIONS PERTAINING TO COOLDOWN l INITIAL CONDITIONS , o RCS TE !P 557'T I o RCS PRESS 2235 PSIC o PRZR TEMP 657'F PROCEDURAL CUIDANCE o STOP NO. 2 AND 3 REACTOR COOLANT PUMPS TO INITIATE RCS C00LDOWN. o INITIATE RCS DEPRESSURIZATION AND P.'.ESSURIZER C00LDOWN. o INITIATE RHR C00LINC. o STOP NO. 1 AND 4 RF. ACTOR COOLANT PUMPS. o FILL C00LDOWN AND DEPRESSURIZE PRESSURIZER. o CONTINUE PRESSURIZER C00 WN. 1
Place RHR Stop 2 Begin Begin RCS Stop in S/D Fill, C/D Pzr HCP's RCS Depress & RCP's
. ..... .....==== Cooling ...... ,
& . Continue - -
(pref 2 & 3) Cooldown Pzr C/D Mode 1&4 Depressurize Pzr C/D P \ r Max: 100 F/hr
- 650 F ~ 630 F g T l ,
$ l 440 F N
l 2 (* F) l Max: 100 F/hr
,' I Final Cond: '
n h . C \ T-Pzr - 140 F S 557"F l Max: 50 F/hr T-RCS - 140 F P-RCS - Atmosj T e l m 5525 to 2500 F l P (ie: Psg < 605#) l 140 F (* F) f f R . C l 2235 r s1960# to 21910# l e s (ie: less than P-11) l ~ 325 # Jpsig)
- o. .
IPO-005A PLANT C00LD0kW PROCEDURE INITIAL BEGIN RCS BEGIN RCS RHR IN FILL.C/D FINAL CONDITIONS C00LDOWN DEPRESS & SERVICE PRZR & CONDITIONS 50*F/HR 100*F/HR DEPRESSURIZE RCS TEMP C00LD0kW C00LDOW C00LD0kW COOLDOWN 557 557 to 53G 530 to 500 500 te 300 300 to 140 TIME DURATION N/A 1 HR 1 HR 5 HRS 4 HRS 140 PRESSURIZER C00LD0hH C00LD0kW C00LD0kW TEMP 657 657 657 to 630 h30 to 440 440 to 140 TIME DURATION N/A N/A 1 H'R 3 HRS 4 HRS 140 PRESSURIZER , DEPRESSURIZE DEPRESSURIZE DEPRESSURIZE 2235 2235 2235 to 1960 1960 to 350 325 to 50 TIME DURATION N/A N/A 1 HR 3 HRS 4 HRS ATMOS. DELTA T 100 127 130 130 300 to O (PRZR. RCS) TIME DURATION 1 HR 1 IIR 5 HRS 'O HRS b
e PROCEDURAL CONTROLS FOR TEMPERATURE AND PRESSURE LIMITS
- o PROCEDURAL STEP SEQUENCING (BUBBLE CHARTS) o PRECAUTIONS SUBC00 LING MINIMUM 320 DELTA T LIMIT COOLDOW/HEATUP LIMITS (ADMINISTRATIVE)
SUBC00 LING DELTA T LIMIT (RCS, PRZR) LeccING TEMPERATURES TECH SPEC CURVES t P f
~
N 1
'*N PRESSURIZER SURteE LINE -
r PRESSURIZER MONITORING LOCAT10NS I TBX-RCPCPR-Ol I ( l A
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PRESSURIZNR SURGE LINE MONITORING PARAMETERS LOCATIONS / DIRECTIONS 9 LOCATIONS D1 THROUGH D4 AND T1 THROUGH T4 (+6") O LATERAL AND VERTICAL READINGS AT ALL LOCATIONS RECORDING INTERVALS S EVER Y 10 MINUTES DURING HEATUP-S EVERY 60 MINUTES AT EACH TEMPERATURE PLATEAU RECORDING SYSTEM CAPABILITIES G ) 10 SECOND INTERVALS FOR A PERIOD OF 10 MINUTES O PROVIDE LABELED PLOTS OF TEMPERATURES AND DISPLACEMENTS AS A FUNCTION OF TIME G AVERAGE ALL TEMPERATURE READINGS AT EACH ; MEASUREMENT TIME l l l
ENCLOSURE 4 1 r DUQUESNE LIGHT COMPANY BEKVER VALLEY UNIT 2 . ) , !. PRESSURIZER SURGE LINE . l STRATIFICATION i ! I l l I ! S. K. MUKHERJEE l NUCLEAR ENGINEERING ; \ DEPARTMENT l l i
. BACKCROUND o ORIGINAL CONFIGURATION OF SURGY. LINE (PRE HFT)
TANDFM 6 KIP MECH. SNUBBERS INSTALLED WHIP RESTRAINTS REMOVED PER WHIPJET PROGRAM 2 VARIABLE SPRING BANGERS INSTALLED 1 PERMANENT RTD INSTALLED
- OPERATING LIMITS - MAX TEMP, DIFF. 300 0 r <
e STRATIFICATION FIRST BECAUSE APPARENT DURING RFT
- UNUSUAL MOVEMENT OF SNUBBERS NOTED i
- ADDITIONAL INSTRUMENTATION INSTALLED TO REMOTELY MONITOR DISPLACEMENT DURING FUTURE TESTING i
I e DURING PREOF AND POWER ASCENSION TESTING YURTHER DISPLACEMENT OF A CYCLIC NATURE WERE OBSERVED l
- MAX. RECOl'OED DISPLACEMENT NAS ~ 3. O INCHES VERSUS .4 IN. CALCULATED DISPLACEMENT
- MAX. DISPLAODENT OCCURRED DURING HEAT UP AND COOL DOWN 1
l
= - -_______ _ _ _
- FROM EVALUATI N OF DATA GONCLUDED THAT HIGE DISPLACEMENTS MERE A RESULT OF FLUID
- THERMAL STRATIFICATION DATA COLLECTION e - PIPING DISPLACEMENTS APPEARED TO VARY AS A FUNCTION OF TEMPERATURE DIFFERENTIAL BETWEEN THE PRESSURIZER AND THE RCS HOT LEG e - ADDITIONAL INSTRUMENTATION INSTALLED TO REMOTELY MONITOR TEMPERATURE l e - CONTINUED PLANT TESTING NITH CONTINUOUS MONITORING OF DISPLACEMENTS AND TEMPERATURE ACTIONS t
e - IMPOSED REAT UP/ COOL DONN LIMITATION OF 6T 6 200 F0BETWEEN PRESSURIEER AND RCS HOT LEG e - REMOVED SNUBBER TRAPEZE ON SURGE LINE UTILIZING ASME CODE CASE N-411 e - ANALYSIS CONDUCTED TO QUANTIFY EFFECTS OF STRATIFICATION
SPECI'FIC ANALYSIS . e - SIMPLIFIED 'ANSYS' MODEL OF SURGE LINE GENERATED
- MODEL COMPRISED OF ELASTIC BEAM ELEMENTS l l
- FIRST BENCH MARKED 'ANSYS' HODEL TO ORIGINAL
- 'NUPIPE' MODEL t
.ALL THERMAL CONDITIONS APPLICABLM TO SURGE LIFE '
WERE REVIEWED TO DETERMINE THE PRESENCE OF ' THERMAL STRATIFICATION AND POTENTIAL EFFECTS 4 ON THE EXISTING PIPING ANALYSIS , l 'l
- THESE THERMAL CONDITIONS INCLUDED L o NORMAL POWER OPERATION
] e HEAT UP AND COOL DOWN .i
- . e MAXIMUM STRATIFICATION FOLLOWING PLANT l l EXCURSION / TRIP l
i l l . L t l l \ . l
. e 'ANSYS' MODEL INCORPORATED ACTUAL RECORDED IN-PLANT TEMPERATURE DATA DURING THE ABOVE TRERMAL CONDITIONS TO QUANTIFY THERMAL STRATIFICATION EFFECTS o - RESULTS OF 'ANSYS' MODEL (FORCES, MOMENTS) FOR EACH APPLICABLE THERMAL CONDITION MAS I RE-EVALUATED BY THE ORIGINAL 'NUPIPE' MODEL e - NUPIPE MODEL THEREFORE COMBINED THE EFFECTS OF THERMAL STRATIFICATION WITH ALL OTHER LOADING l CONDITIONS 4
i I , .l 1 l t t-- - - - . ., , - , , , _ , , - . . - - .- - - - , . - - - - - - - - - - - - - - . - - - - - - - . - - - . .--s-----.. , - . . - - - - - - , . , , - - - - - -
WHIPJET REVIEW e EFFECT OF REVISED ANALYSIS ON SURGE LINE EVALUATED l LEAKAGE SIZE FLAW RECALCULATED i i . STABILITY EVALUATION CONDUCTED i FATIGUE CRACK GROWTH RATE ANALYSIS REVIENT.D o MAINTAINED MARGINS PER NUREG 1061 VOL. 3 i I
}
l t l 1 l l f , i l l,
- - - - - - - - - , , n- g- - --- -, , ,,--,,,,, - - - - ,- --.e, -------~ - ,- - , -,-- . -- , - -..---w-, ----.--- ,- - - - .-,
I
~
l BV-1 SURGE LINE REVIEW
)
' e GEOMETRY CLOSELY APPROXIMATES BV-2
- THIS INCLUDES PIPE ROUTING, SIZE, ENTRANCE
*dTO
. HOT LEG AND SLOPE e SUPPORTING ARRANGEMENT SIMILAR TO BV-2 I
NO RUPTURE RESTRAINTS ON SURGE LINE l PIPING SUPPORTED BY TNO VARIABLE SPRING RANGERS ! e OPERATIONAL RESTRICTIONS IMPOSED DUKING HEATUP/ COOLDOWN SIMILAR TO 3V-2 1 i e PIPING LOADS DUE TO STRATIFICATION FROW BV-2 ANALYSIS BEING EVALUATED l 4 i , l 1
.- . - - - - . .-- _. _- ._ ~ .. . _- __ . _ _ _ . .. . - - _ . - _ .
CONCL SIONS e STRkTIFICATION EFFECTS NERE QUALIFIED AND INCORPORATED INTO THE ANALYSIS e ANALYSIS SHOWS THAT CODE ACCEPTABILITY MT.INTAINED UNDER ALL CASES ! a e WHIPJET REANALYSIS OF SURGE L"NE DEMONSTRATES PIPE , LBB CAPABIL.ITY UNDER REVISED LOADING . i i e OPERATIONAL RESTRICTIONS OF dT $ 200 F0 IMPOSED i DURING REATUP AND COOLDOWN ON BOTH BV-1 AND BV-2 e SIMILARITY OF BOTE UNITS SHOWS BV-2 STRATIFICATION EFFECTS / LOADS CAN BE APPLIED TO BV-1 d 1
~ .
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, _ _ - - " - " _ _ , - - ~ ~ _ --
LRNYRRD.RCS 7E01-076P Y- VERTICRL DEFLEC1/DN MbN370RAA o LRNYRRD RCS-7E02-077P L- LRTERRL DEFLEC7 ION MbNITOR LRMYRRD RCS .7E03-078P R - RX)RL DEFLEC7)DN MDN)7&R O # LRNYRRD RCS 7EDy-079P Y- VER7)CRL DEFLEC7)ON NDN! TOR (_ V f]L__ f h th ~ , /N W ' 2RCS 029 7-1 ('C'HOTlE&)
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A SNUBBER PSSPMI DELETED PER EIDCR Ne DCP-)CI5-02
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