ML20210E777
| ML20210E777 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 09/10/1986 |
| From: | Rooney V Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8609250088 | |
| Download: ML20210E777 (67) | |
Text
{{#Wiki_filter:-- September 10, 1986 Docket No. 50-271-LICENSEE: VERMONT YANKEE NUCLEAR POWER CORPORATION FACILITY: VERMONT YANKEE ATOMIC POWER STATION
SUBJECT:
JULY 29, 1986 MEETING WITH VERMONT YANKEE NUCLEAR POWER CORPORATION (VYNPC) TO DISCUSS REVIEW 0F THE RELAP SYA CODE On July 29, 1986, a meeting was held at the NRC Headquarters at Bethesda, Maryland to discuss the review of the RELAP SYA computer code for LOCA analysis at Vermont Yankee. Enclosure 1 is the list of the individuals that attended the meeting. Enclosure 2 is the proposed meeting agenda offered by the licensee. Enclosure 3 is a handout of the slides presented by the licensee at the meeting. The following is a summary of significant items discussed:
- 1. VY LOCA Licensing Analysis Method
- 2. VY LOCA Sample Problems
- 3. NRC-EG&E Technical Review Questions
- 4. Acceptance of R5YA EM Heat Transfer
- 5. Method for Quantifying Margin of Conservatism (Appendix K, Item II.5)
Original signed by Vernon L. Rooney, Project Manager BWR Project Directorate #2 Division of BWR Licensing i l
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f BWR#2 i VRooney;eh
- 9 / 3 /86 l 8609250088 860910 DR p ADOCK 05000271 PDR i.
Mr. R. W. Capstick Vemont Yankee Nuclear Power Corporation Vermont Yankee Nuclear Power Station - cc: Mr. J. G. Weigand W. P. Murphy, Vice President & President & Chief. Executive Officer Manager of Operations Vermont Yankee Nuclear Power Corp. Vemont Yankee Nuclear Pcwer Corp. R. D. 5, Box 169 R. D. 5, Box 169 Ferry Road Ferry Road Brattleboro, Vemont 05301 Brattleboro, Vemont 05301 Mr. Donald Hunter, Vice President Mr. Gerald Tarrant , Connissioner Vermont Yankee Nuclear Power Corp. Vermont Department of Public, Service 1671 Worcester Road 120 State Street Framingham, Massachusetts 01701 Montpelier, Vemont 05602 New England Coalition en Nuclear Pollution Hill and Dale Fam Public Service Board R. D. 2, Box 223 State of Vermont Putney, Yemont 05346 120 State Street Montpelier, Vermont 05602 Mr. Walter Zaluzny Chairman, Board of Selectman Yemont Yankee Decommissionirg Post Office Box 116 -Alliance Vernon, Vemont 05345 Box 53 Montpelier, Vermont 05602-0053 J. P. Pelletier, Plant Manager Vemont Yankee Nuclear Power Corp. Post Office Box 157 Resident Inspector Vernon, Vemont 05354 U. S. Nuclear Regulatory Commission Post Office Box 176 Raymond N. McCandless Vernon, Verrcnt 05354 Vemont Division of Occupational
& Radiological Health Yemont Public Interest Administration Building Research Group, Inc.
10 Baldwin Street 43 State Street Montpelier, Vemont 05602 Montpelier, Vermont 05602 i Honorable John J. Easton Thomas A. Murley Attorney General Regional Administrator State of Vermont Region I Office 109 State Street U. S. Muclear Regulatory Corrission Montpelier, Vemont 05602 631 Park Avenue King of Prussia, Pennsylvania 19406 John A. P.itscher, Esquire Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 I
MEETING SUP91ARY DISTRIBUTION Licensee: Yankee Atomic Electric Company
- Copies also sent to those people on service (cc) list for subject plant (s).
WLW5kU?? NRC PDR L PDR BBD-2 Rdg DMu11er HAbelson OGC-MNBB 9604 EJordan BGrimes ACRS-10 PWheatly WHodges TCollins CGraves VRooney 1 i I
1 Enclosure 1 List of Meeting Attendees July 29, 1986 Name Organization T. Fernandez Yankee Atomic Electric Co. H. Da Silva Yankee Atomic Electric Co. K. St. John Yankee Atomic Electric Co. 2 A. Husain Yankee Atomic' Electric Co. W. Hodges- NRC/ DBL /RSB T. Collins NRC/ DBL /RSB C. Graves NRC/ DBL /RSB H. Ableson NRC/ DBL /BWR#2 P. Wheatly EG&G/NRC Consultant J. Jones EG&G/NRC Consultant 1 J ,l i k I i I I l t
/-
Enclosure 2 AGENDA 115E TOPIC , 8:45- 8:50 MEETING OBJECTIVES & AGENDA RTF VY LOCA LICENSING ANALYSIS METHOD 8:50- 9:00 o OVERVIEW RTF RTF 9:00- 9:20 o RELAP5YA~ CODE & ASSESSMENT 9:20-10:00 o TLTA LBLOCA TEST 6425/R2 HCDS 10:00-11:00 VY NSSS MODEL RTF 11:00-11:15 VY HC MODEL RTF 11:15-11:45 VY EM HEAT IRANSFER RTF LUNCH LBLOCA SAMPLE PROBLEMS RTF 1:00-1:40 o CASE EA 1:40-1:50 o CASE EB 1:50-2:20 o CASE BA 2:20-3:00 SBLOCA SAMPLE PROBLEM HCDS 3:00-4:00 METHOD FOR QUANTIFYING CONSERVATIVE MARGIN 4:00-4:30 MEETING
SUMMARY
ALL RTF-2 7/29/86
Enclosure 3 ( VY LOCA LICENSING ANALYSIS PLAN 5 GOALS
' 1.
OBTAIN SER ON BWR LOCA LICENSING ANALYSIS METHOD BY DECEMBER 1986.
- 2. APPLY METHOD FOR VY HIGH ENERGY BUNDLE PROGRAM TO OBTAIN SER FOR CYCLE 14 (STARTUP 11/1/88).
MAJOR MILESTONES
- 1. COMPLETE RESPONSE TO 197 NRC QUESTIONS ON RELAPSYA CODE BY SEPTEMBER 30, 1985.
k
- 2. COMPLETE RESPONSE TO 39 ADDITIONAL NRC QUESTIONS ON RELAPSYA CODE BY DECEMBER 31,1985.
- 3. OBTAIN SER ON RELAP5YA CODE BY MARCH 31, 1986.
- 4. SUBMIT VY LOCA SAMPLE PROBLEMS TO NRC BY JUNE 30, 1986.
- 5. OBTAIN SER ON BWR LOCA METHOD FROM NRC BY DECEMBER 31, 1986.
- 6. SUBMIT VY LOCA LICENSING ANALYSIS BY DECEMBER 31, 1987.
- 7. OBTAIN SER ON VY LOCA ANALYSIS FROM NRC PRIOR TO STARTUP OF CYCLE 14 (NOVEMBER 1988).
( R7'F
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W LOCA LICENSING ANALYSIS SCHEDULE 1986 1987 1988 1985 4Q IQ 2Q 3Q 4Q 1Q 2Q 3Q 4Q IQ 2Q 3Q 4Q TASK 1Q 2Q 3Q j I. RELAP5YA QUESTIONS / ANSWERS
! a. General Questions (197) -
2
- b. Additional Questions (39) i l 3
- c. NRC Review 4
l 2. W LOCA SAMPLE PROBLDiS i
- a. YAEC Perform 0
i b. NRC Review
- 3. W LOCA ANALYSES
^
a
- a. YAEC Perform l 7
- b. NRC Review 1
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.W PROJECTED OPERATION:
1 TB i ax 4 l 4 O
( BWR LOCA LICENSING ANALYSIS METHOD
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OBJECTIVE: PROVIDE CYCLE INDEPENDENT LOCA ANALYSES THAT COMPLY WITH 10 CFR 50.46 AND APPENDIX K. INPUT DATA e PLANT DRAWINGS, TECHNICAL SPECIFICATIONS, PERFORMANCE DATA e SIMULATE CODE - CORE AXIAL & RADIAL POWER DISTRIBUTIONS MODERATOR, FUEL AND SCRAM REACTIVITY TABLES e FIBWR CODE - INITIAL CORE AND BYPASS FLOW DISTRIBUTION e CASMO CODE
- R0D POWER DISTRIBUTION WITHIN PEAK BUNDLE e FROSSTEY CODE - INITIAL FUEL ROD PARAMETERS e ACTIVATE APPENDIX K EVALUATION MODEL OPTIONS STEADY STATE INITIALIZATION - RELAP5YA CODE e NSSS EM INITIALIZATION MODEL - ACCELERATED STARTUP TRANSIENT FROM HOT STAGNANT CONDITIONS TO STEADY STATE i
ACCIDENT ANALYSES - RELAPSYA CODE e LOCA EM SYSTEM MODEL - INTEGRAL ANALYSIS OF ENTIRE ACCIDENT e LOCA EM HOT CHANNEL MODEL - RUN FOR MORE DETAILED ANALYSIS (WHEN NECESSARY) USING SYSTEM TRANSIENT RESULTS AS BOUNDARY CONDITIONS ACROSS BUNDLE ( 2rf - 3 7/n/tco i
- - - - - ,n .. . . . . . - . - - -
( BWR LOCA LICENSING ANALYSIS METHOD OUTPUT DATA FOR REPORTS
- 1. GRAPHS o DBA STEAM DOME PRESSURE HISTORY e DBA WIDE RANGE (" INNER SHROUD") LEVEL HISTORY, OR e DBA VESSEL MASS INVENTORY HISTORY e DBA CORE FLOW HISTORY e DBA ECCS FLOW HISTORIES
( o DBA PIAK CLADDING TEMPERATURE HISTORY e DBA HEAT TRANSFER COEFFICIENT HISTORY
- 2.
SUMMARY
TABLES e DBA SIGNIFICANT EVENT TIMES 1 e PEAK CLADDING TEMPERATURE VS BREAK SPECTRUM e HAPLHGR, PCT, % OXIDATION, %H RELEASE VS BURNUP 2 l l l I RrF - 4 l 7/29/1V 1
( REIAP5 CODE
SUMMARY
AD_yA_NCED HYDRODYNAMIC _MODEL e Two-fluid, Nonhomogeneous, Nonequilibrium e ID with Multi-D Approximations e Noncondensible Gas & Dissolved Boron Allowed e 8 Governing Differential Equations l 4 CONT; 2 MOMENTA: 1 Mix ENERGY, 1 Mix State e 8 Primary Variables (p,, p B, X,, ,V g ..V p _ U,g.P.) e Constitutive and Process Models rg, C r, FI, W, K, GCRIT' S s i i RrF -S W19/16
i t RELAP5 CODE
SUMMARY
COM3ONENib e INTERNAL VOLUMES AND JUNCTIONS
- SNGLVOL, SNGLJUN, BRANCH, PIPE, ANNULUS e ACCUMULATOR *-
e SEPARATOR e CENTRIFUGAL PUMP e JET PUMP
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o VALVES (Trip, Check, Inertial, Motor, Servo) e Generalized TRIP and CONTROL SYSTEM e FUEL BEHAVIOR
- Boundary Conditions: TMDPVOL, TMDPJUN e
1
- Heat strucAures Rif-s 7/29/?4
I 1 J I REI.APSYA Model Developrnent Tasks t Hydrodynamic Models Analysis Requirement A.
- 1. Interphase Drag .BI, EM
- 2. Moody Two-Phase Critical Flow _
EM
- 3. Jet Pump BE, EM
& B. Heat Trans'er Models
- 1. Forced Convective Boiling BE, EM
- 2. Critical Heat Flux BE, EM
- 3. Rewet and Quench BE, EM
- 4. Multi-Surface Radiation Ls;.. EP
- 5. Heat Transfer Logic Options EM C. Fuel Behavior Models
- 1. Internal Gas Pressure BE, EM s*
A- 2. Rod Deformation and Rupture BE, EM
- 3. Transient Cap Conductance BE, EM y
k 4. Zircaloy-Water Reactions EH E 1 E. , E. R. N R TF- 7 (^ 7/z9/ra
Separate Effect Tests for RELAPSYA Model Assessment Assessment Cases Hydrodynamic Models 4 Frigg Loop Tests. interphase Drag 1 GE Level Swell Test i 7 Parametric calculations Two-Phase Critical Flow 1 Marviken Test i 233 1/6 Scale EG&G SS Tests Jet Pump 1/6 Scale Blowdown Tests
' 2 VY Jet Pump M-N Curve' 1 Maine Yankee Test Accumulator 1 LOFT L3-1 Test i Heat Transfer Moocis Forced Convective Boiling 3 Bennett Tests 5 Columbia Tests critical Heat Flux 4 CE Nine Rod Tests 3 ORNL THTF Tests 1
2 Analytical Solutions Radiation 4 Parametric Calculations i Parametric Calculations 9 EM Logic Options Fuel Behavior M.: is 1 Analytical Solution Metal-Water Reaction 1 T00DEE2-EM Run All Models I I I I E 1 RTF- o 7/2 9/AG,
Integral Tests for RELAPSYA Code Assessment ( Reference Thermal-Hydraulle Test Facility (ORNL-NRC) , , 1-4 3 Steady-State Film Boiling Tests 1-4 1 Transient Film Boiling Test f 1-4 1 1 Quasi Steady-State Boiloff Test 1-4 2 Reflood Tests Two Loop Test Apparatus (GE-EPRI-NRC) 1-4, 1-10 Large Break With ECCS, Test 6425/2 Large Break Without ECCS, Test 6426/1 1-4 1-4, 1-10 Small Break With Degraded ECCS, Test 6323/1 1-4 System Bolloff With Recovery Test 6441/6 LOFT (EC&G-NRC) *
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k Small Break With Pumps On, Test L3-6 1-4, 1-9 Severe Core Transient With Pumps Tripped Test L8-1 1-4 Small Break With Pumps Off Test L3-1 1-9 Semiscale Test Facility (EG&G-NRC) l Single-Phase Two-Phase, and Reflux Modes of 1-9 f Natural Circulation. Test Series S-NC-2 Yankee Plant (YAEC) Reactor Coolant Pump Trip Test 1-7 frF- 9 7/z9/8
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~ 1nitial Parameter Data SS Initiation at 2 MW Conditions ndle Power (MW) 5.05 10.03 2.0 5.06 3' team Dome Pressure (psi) 1044 15 1043.8 1044.2.
Lower Plenum Enthalpy 528 15 521 526.1 (Stu/lbm) Initial Water Level (inches) 73 16 76 77.6 Feedwater Enthalpy 41 12 42.9 42.9 (Btu /lbm) Bundle Pressure Drop (psid) 17 12 11.0 16.3 Steam Flow (Ibm /s) 6 il 1.88 5.7 Feedwater Flow (Ibm /s) 1.4 10.3 1.84 1.4 Intact Loop Pump Flow (Ibm) 9.1 11 8.73 8.8 Broken Loop Pump Flow (Ibm) 8.4 il 8.3 8.4 Intact Loop Jet Pump (Ibm) 22 12 18.1 20.0 Broken Loop Jet Pump (Ibm) 20 12 16.4 18.4 Bundle Inlet Flow (Ibm) 39 15 31.1 34.1 Lower Plenum Pressure (psi) 1071 15 1061.5 1070.1 l l
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b, (iii iiii,....,4' iii VV Figure 1.2-1: Vermont Yankee Reactor Vessel t i i
TABLE 1.2.1 Vermont Yankee Operatina Conditions Rated Design Core Power (MWt) 1,593 1,664 Vessel Pressure (psia) 1,020 - 1,035 Vessel Water Level (inches)* 512 512 Fe'edwater Temperature (OF) 372 376 Feedwater Flow (MLBM/hr)b 6.40 6.72 Recirculation Loop Flow (MLBM/hr) 12.3 12.3 (each of two loops) Control Rod Drive Flow (MLBM/hr) 0.03 0.03 Core Flow (MLBM/hr) 48.0 48.0 Main Steam Line Flow (MLBM/hr) 6.43 6.75 (four combined lines) NOTES:
- a. Inches above the top of the lower reactor vessel invert.
- b. Million pounds mass per hour.
661 l 559 659 l 557 240 657 l 555
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- o sit sto 360 is2>+3 W us V h sse Figure 2.1-1
- Veermotit Yatikee NSSS Nodalization Diagram
TABLE 2.1.1 Ver1mont Yankee WSSS Wodalization Sununary . Region Nodalization Ihnaber of Number of Number of or Diagram Volumes Junctions- Heat Striactures System Numbers Active TMDPVOL Active TMDPJUN Active Passive Reactor Pressure Vessel Lower Plenum 002 to 012 6 0 10 0 0 6 Control Rod Guide Tubes 022 to 024-5 6 0 6 0 0 6 Core Bypass 100 to 102-9 10 0 10 0 0 10 Core Fuel Assemblies 116 Peripheral Low Power 120 to 122-9 10 0 11 0 9 10 248 Central Average Power 140 to 142-9 10 0 11 0 9 10 4 Central High Power 160 to 162-9 10 0 11 0 9 10 Upper Plenum 206 to 208 2 0 2 0 0 2 Standpipes and Separators 210 to 228 3 3 5 2 0 3 Interinediate Steam 232 1 0 2 0 0 0 Steam Dryer Assembly 234 1 0 1 0 0 1
- Steam Dome 240 1 0 1 0 0 1 Downconer 250 to 290 15 0 14 0 0 13 Other Systems Recirculation Loop A 302 to 338-1 12 0 12 0 0 12 Jet Pump Bank A 340 to 342-3 4 0 6 0 0 4 Recirculation Loop B 352 to 388-1 12 0 12 0 0 12 Jet Pump Bank B 390 to 392-3 4 0 6 0 0 4 Feedwater Lines 400 to 402-3 3 1 3 1 0 0 Main Steam Lines 540 to 550 6 1 7 0 0 5 Steam Relief and Supply 551 to 571 0 1 6 1 0 ,O Conta1rument 614 to 663 0 8 0 0 0 0 ECCS 700 to 763 2 4 2 4 0 , 0 -
D8C Break 801 to 802 0 0 2 0 0 0 TOTALS 118 18 140 8 27 109 p-
~ - . _ .
--. _ _______ _ ~- . ..-. . .._ ...
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TLTA DUNOLg CoseTROL ROO CN N L SURFACE RTA CNANNEL l NIAIIN ROOS F FUE L ROOS i
! . t i
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- SUPPORT LOW @
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g Figure 2-5. Flow Paths at inlet Region of a BWR Fuel Bundle and the TLTA Simulation I I 2-13 c -
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3 F' Figure 1. Bottom view of a prototypical 8 X 8 BWR fuel bundle upper tieplate. 0 0
o 6 9 2.4 O Jones [6]. clarinet steam sparger 0 Jones [6], lower tieplate steam sparger 2.0[] O O Naitoh et al. [14] 1.6 - o e c= 1.2 - Og
- O'8 g
* /~ (K )Y' + (K,)Y' = 2.08 .
0.4 - I I I I I I I I o o 0.4 0.8 1.2 1.6 2.0 2.4 2.8 3.2 3.6 (K,)Y' Figure 5. Comparison of data of Jones [6} with data of Naitoh et al. [14] for , flooding at a 8 X 8 tieplate in a simulated BWR fuel bundle.
w Q O-8 J I o o
! I 2.77 in. !
(7.04 cm) 3.25 in. _ F (8.26 cm) 13.75 in. (34.93 cm) l _ Rp tube I 7.34 in. E Flow _ (18.64 cm) l tub <! l
. Orifice
. 0.75 in. (1.91 cm) G o h ce I "'
- 1.88 in.--- -._
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2.00 in. $ D 45* , I . __L. (5.08 cm) -- ' t , 3 il I
- TLTA-1 core inlet geometry TLTA-3 core infet geometry ,
Figure 6. Schematic of TLTA (two-loop test apparatus) core inlet side-entry orifices. (Reference 13) s a b
(Kg)5/f(L*) e Number of Diameter
O l Orifices cm (inches) Symbol 1 6.17 (2.430) 0 1 3.76 (1.480) O 0.8 -
*e 1 3.19 (1.257) Q 1 4.06 (1.600) A 0.6 -
2 2.87 (1.131) V (K g)Y2 (K,)Y2 0.4 - -
+ 0.59 ,
=1
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0.2 - f(L*) = 2.14 - 0.80 X 10 2L* O O 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 (K )h/f(L*) Figure 9. Correlation of flooding data from simulated BWR bottom side-entry orifices.
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Figure II. 1.1. Positive Drive; NormsIIzed l'reneure Difference versus M MM (Suct ion I'lenue to Thront) - I
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STERDY STRTC MODEL HSSCSMENT ' jelllillt 11ll16ll1 111111111 11lllll11 ll111llll lilllillt 14ll11111 11lllllll l l l l 1111_, ;
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Flpure II. 1.2 Of Positive Drive; Norinalized Prgsnure Difference versus M f[/.f[/% (Drive I.tw to Tieront)
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Fly,ure 311 3 Positive Drive; N versus M 5//3/ JN;,
STERDY STRTE MODEL RSSESMENT
= - , . . . . . " '
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-10.0 -9.0 -0.0 -7.0 -e.0 -5.0 -1.0 -3.0 -2.0 -1.0 0.0 1.0 (tMTRLVA4.O87)
Ftr.ure II. 1.4 Negative Drive; Norsializeil Pressure Difference virsus M gfg (Suction Pierwm to Throat) Sh3/PG
A n a e a e i i O
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. Realisfii frestars fictmis sa d f/m}m$'
- s. REtAFry4 yy LBLocA fredo'c films are similar- # 7474.
' ( t, . VY does not use 7 x 7 fuel assemblies-RTF HT- y l 7/zt/!& l
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