ML20210T555
| ML20210T555 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 09/10/1997 |
| From: | Hubbard B VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20210T552 | List: |
| References | |
| YAEC-1941, NUDOCS 9709150198 | |
| Download: ML20210T555 (200) | |
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3 $ ADDITIONAL BENCllMARKING OF llOILING WATER REACTORS USING CASMO-3/ SIMULATE-3 July 1997 PrincipalInvestigators: B. Hubbard . P. Delmolino A. Fyfe G. Lam R. Paulson Prepared By: - 2/!f7
' B. Y. Hubbard, Sr. Nuclear Engineer (Date) '
Reactor Physics Group
= Appmved By:
7/>-//97 _ . Cacciapou ager- '(Date) ctor Physic oup
' ApprovedBy: {WC &A [/N/97 J/R. Chap Director #
'(Date) ,
Nucleare gineeringDepanment
-Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740-1398
be e .3 ) DISCLAIMER nis document was prepared by Yankee Atomic Electric Company for its own use. The use of infomaation cortained in this document by anyone other than Yankee Atomic Electric Company is nct authoriad and in regard to unauthorized use neither Yankee Atomic Electric Compar.y or any of its officers, directors, agents or employees assumes any obligation, responsibility or liability, or makes any warranty or representation, with respect to the contents of this document, or its accuracy or completeness. 8 11
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. e ., s AI3STRACT The MICBURN 3/CASMO-3frABLES-3/ SIMULATE 3 code package is applied to the ten most recent cycles of Vermont Yankee and three cycles of Pilgrim Nuclear Power Station, both General Electric DWRs. The purpose of this benchmark is to demonstrate the suitability of these codes for DWR operational support and reload licensing using advanced fuel types such as the Gell and GE13. Cold critical startup, hot steady-state full power operation and low power operation are modeled. Steady, consistent eigenvalues close to unity are exhibited. Extensive 3-D comparisons are made between the model calculated and plant-measured detector responses. The comparisons demonstrate that the code package reproduces the power distributions with reasonable accuracy, iii
i be ., 6 TABLE OF CONTENTS Disclaimer...........................................................................................................................n** Abstract.........................................................................................................................iii L i s t o f Tabl es .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . Li st o f Fi g u re s . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . ..
. . .. .... .. ... .... vii A c kn o wl e d g m e n ts . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. .. . . . .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. . . ... . . . . . . . . .
1.0 INTRODUCTION
AND S UMMARY................................................................. ........ I 2.0 GENERAL CODE PACKAGE DESCRIPTION .... ................................................... 3 2.1MICDURN-3....................................................................................................3
CASMO-3.........................................................................................................3 2.3 TABLES-3........................................................................................................4 2.4 S I M U LATE-3 . . .. . .. .. . . . . . . . . .. . . . .. . . . . . . . . . . . . . .. . .. . . . . .. .. .. . . .. . . . . ... . . . . . . .. . . . . . . . . . . . .
3.0 VERMONT YANKEE OPERATING CHARACTERISTICS................................... 5 3.1 Core D escription .. ... ...... . . ...... .. ....... . .... ......... .. ... .... . ........ . ..... ..... . .. ..... ...... ..... . .. .. 5 3.2 Description of Cycles Modeled ........................................................................ 6 3 .3 Fuel Descript io n .. ....... ... .... ........... .... . . . .... .. ... .... .... .. ..... ... ... ..... ..... . .. .. ....... ......... 6 4.0 VERMONT YANKEE SPECIFIC MODEL .............................................................14 4.1 MICD URN-3 Model Description .. ................................................................. I 4 4.2 CASMO-3 Model Description........................................................................ 14 4.2.1 CAS MO-3 Depletion Cases ............................................................ 14 4.3 TA B LES-3 Constmetion ......... ...... ..... ... .. .. .... ....... ... . ...... ... .. . ....... ... .... .......... . .. I 5 4.4 SIM ULATE-3 Model Description .................................................................. I 5 4.4.1 SIMULATE-3 Hot Model ........................................................... ..... I 5 4.4.2 S IMULATE-3 Cold Model ...... ........................... ............ ................ ! 6 5.0 VERMONT YANKEE PHYSICS MODEL RESULTS ............................................I 8 5.1 Hot Mod el Eigenval ues.... . ..... ....... ...... . . ... . ..... . . .. ........... .. ..... .. .......... . ... ...... .. .. I 8 5.1.1 Full Power / Full Flow Conditions......... ...........................................I 8 5.1.2 Low Power / Low Flow Conditions......................... .......................19 5.2 Cold M odel Eigenval ues .. .. ... ........... ... . .. .. ... .. ......... . . .. .. . .. . . . . .. . ... . .. ....... .... .... ... 19 5.3 Hot Model l>etector Comparisons .................................................................. 20 5.4 Rad ial Comparisons ....... .. ..... . . ..... .... .... ... . . .... . ..... .. . .... . . . . . . . . .. . ....... ..... .. ... .. . . .. . 21 5.5 Axial Average Comparisons ............................... ........................................... 21 iv
3 a # #t b l l 6.0
SUMMARY
AND DESCRIPTION OF TIIE PILGRIM MODEL . ... ............. . .... 36 6.1 Summary of Cycles Modeled . . .... ................. .......... .. .... .. .. . .. ...... . .... 3 6 6.2 Pilgrim Physics Model Results....... . . .... .............. . .... ........... ... ......, .. .. 3 7 6.2.1 liot Model Eigenval ues ..... ... ......... ................................................ 3 7 6.2.2 Cold Model Eigenvalues ... ......................... ... ....... ........ . .... ....... 3 7 6.2.31 lot Model Detector Comparisons ................. ..... .................. ..... 3 8 6.2.4 Radial Comparisons .............. . ......................................... ..... ........ 3 8 6.2.5 Axial Average Comparisons ............................................. ..... ...... 39 7.0 CO N C LU S I ON S . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .. . . . . . . . 8.0 REFE REN C ES . ... . . .. . . . . .. .. . . .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . .. . . . . .. . . .... . . . .. . . . . .. . . . . ... . . . . . .. . . . . . . . . . ... ... APPENDIX A Vermont Yankee Hot Depletion Statepoints ......................................... A-1 APPENDIX B Vermont Yankee Cold Critical Statepoints............................................ B-1 APPENDIX C Vermont Yankee Hot Model-to-Plant Detector Comparisons .............. C-1 APPENDIX D Pilgrim Hot Depletion Statepoints ....................................... ............. ... D-1 APPENDIX E Pilgrim Cold Critical Statepoints.............................................................E-1 APPENDIX F Pilgrim Hot Model-to-Plant Detector Comparisons ...............................F-1 m V
- h. # .t 6 LIST OF TABLES Number Title 3.1 Vermont Yankee Rated Operating Characteristics.......................................... 7 3.2 Vermont Yankee General Core Description.................................................... 8 3.3 Summary of Vermont Yankec Cycles Modeled................ .............. ..............,9 5.1 VY SiMULA TE-3 Cycle Average Hot Eigenvalues .......................... ......... 22 5.2 VY SIMULATE 3 Beginning of Cycle llot Eigenvalues............................. 23 5.3 VY SIMULATE-3 End of Full Power Life Hot Eigenvalues.... .................. 24 5.4 VY Cold Critical Case Conditions and SIMULATE-3 Results.................... 25 5.5 VY SIMULATE-3 Nodal TIP Reading RMS Errors ..... .............................. 27 5.6 VY Total Uncertainties at Beginning of Cycle ............................................. 28 6.1 Pilgrim Rated Operating Characteristics....................................................... 4 0 6.2 Pilgrim General Core Description............................................. ................... 41 6.3 Summary of Pilgrim Cycles Modeled ........................................................... 4 2 6.4 Pilgrim SIMULATE-3 Cycle Average Hot Eigenvalues.............................. 43 6.5 Pilgrim SIMULATE-3 Beginning of Cycle Hot Eigenvalues....................... 43 6.6 Pilgrim SIMULATE-3 End of Full Power Life Hot Eigenvalues................. 43 6.7 Pilgrim Cold Critical Case Cond.itions and SIMULATE-3 Results.............. 44 6.8 Pilgrim SIMULATE-3 Nodal TIP Reading RMS Errors.............................. 45 6.9 Pilgrim Total TIP Uncertainties at First Eighth Core Symmetric ................ 45 vi
LIST Ol< FIGURES Number Title - 3.1 - Radial Map of Vermont Yankee Core..... ..................................................... 1 1 3.2 Axial Relationship of Fuel, Control Rods and Incore Detectors...................12 3.3 Detail of Fuel, Control Rod and Incore Instmment Tube ...... ......................13 5.1 VY Cycles 10-19 Depletion K-effective Exposure....................................... 29 5.2 VY Low Power / Low Flow Benchmark Power and Flow Versus Time....... 30 5.3 VY Low Power / Low Flow Benchmark Rod Position Versus Time............ 31 5.4-VY Low Power / Low Flow Benchmark K-effective Versus Time..... .......... 32 5.5 VY Cold Eigenvalue Versus Cycle Exposure............................................... 33 5.6 VY & Quad Cities Unit 1 Cold Eigenvalue Versus Cycle Exposure............ 34 5.7 VY Cycles 10-19 Averaged TIP Integral Errors, Standard Deviations an d RM S Erro rs . . .. . . . . . . . . . .. . . .. . . . . . . . . ... . .. .. . . . . . .. . .. . ...... . .. .. .. . . . . .. . . . . . . . . . . . . . . . 6.1 Radial Map of Pilgrim Core ........ ................................................................ .. 4 6 6.2 Pilgrim Cycles 9-11 Depletion K-effective Versus Exposure....................... 47 6.3 Pilgrim Cycles 911 Averaged TIP Integral Errors, Standard Deviations ' and RM S Erro rs .. .. . .. . . . . . . . . . .. . . .. ... . . . .. .. . . .. ... . . . . .. . ... . . . .. . . . . . . .. . . .. . . . . . . . .. . . . . ... A.1 Reload Design of VY Cycle 10................................................................... A-2 A.2 Power History of VY Cycle 10 Showing TIP Statepoints .......................... A-3 - A.3 Control Rod Inventory of VY Cycle 10 Showing TIP Statepoints............. A-4 A.4 Reactor Conditions for VY Cycle 10 Depletion Steps................................ A-5 A~5
. Reload Design of VY Cycle 1 1....................................... .......................... A-7 A.6 Power History of VY Cycle 11 Showing TIP Statepoints .......................... A 8 A.7 Control Rod Inventory of VY Cycle 11 Showing TIP Statepoints............. A-9 A.8 Reactor Conditions for VY Cycle 11 Depletion Steps.............................. A-10 A.9 Reload Design of VY Cycle 12................................................................. A- 12 A.10 _ Power History of VY Cycle 12 Showing TIP Statepoints ........................ A-13 A.11 - Control Rod Inventory of VY Cycle 12 Showing TIP Statepoints ........... A-14
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A.12 Reactor Conditions for VY Cycle 12 Depletion Steps...................... ...... A-15 A.13 Reload Design of VY Cycle 13................................................................. A-17 A.14 Power History of VY Cycle 13 Showing TIP Statepoints ........................ A A.15- _ Control Rod Inventory of VY Cycle 13 Showing TIP Statepoints........... A-19 ' A.16 Reactor Conditions for VY. Cycle 13 Depletion Steps.............................. A-20 A.17_ . _ Reload Design of VY Cycle 14................................................................. A-22 A.18 Power History of VY Cycle 14 Showing TIP Statepoints ........................ A-23
'A.19- Control Rod Inventory of VY Cycle 14 Showing TIP Statepoints........... A-24 '
A.20 ' Reactor Conditions for VY Cycle 14 Depletion Steps.............................. A-25 A.21' - Raload Design of VY Cycle 15.................................................... . ........... A-2 7 A.22 Power History of VY_ Cycle 15 Showing TIP Statepoints ................... ....~A-28 A.23 Control Rod Inventory of VY Cycle 15 Showing TIP Statepoints........... A-29 A.24 Reactor Conditions for VY Cycle 15 Depletion Steps.............................. A-30
' A.25 Reload Design of VY Cycle 16........................ ....................................... A-3 2 A.26 - Power History of VY. Cycle 16 Showing TIP Statepoints ........................ A-33 A.27 - Control Rod Inventory of VY Cycle 16 Showing TIP Statepoints........... A-34 A~.28 Reactor Conditions for VY Cycle 16 Depletion Steps.............................. A-35
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1 a a a o j 1 i l I l LIST OF FIGURES Number Title A.29 Reloa,i Design o f VY Cycle 17.......... ............................................ ......... A-3 8 A.30 Power Ilistory of VY Cycle 17 Showing TIP Statepoints........................ A-39 A.31 Control Rod Inventory of VY Cycle 17 Showing TIP Statepoints........... A-40 , A.32 Reactor Conditions for VY Cycle 17 Depletion Steps.............................. A-41 1 < A.33 Reload Design of VY Cycle 18................................................................. A 44 A.34 Power History of VY Cycle 18 Showing TIP Statepoints ........................ A-45 A.35 Control Rod Inventory of VY Cycle 18 Showing TIP Statepoints........... A-46 A.36 Reactor Conditions for VY Cycle 18 Depletion Steps.............................. A-47 A.37 Reload Design of VY Cycle 19................................................................. A-5 0 A.38 Power History of VY Cycle 19 Showing TIP Statepoints ........................ A-51 A.39 Control Rod Inventory of VY Cycle 19 Showing TIP Statepoints........... A-52 A.40 Reactor Conditions for VY Cycle 19 Depletion Steps.............................. A-53 B.1 VY Cycle 10 Cold Critical Pattems .............. ..............................................B-2 B.2 V Y Cycle 11 Cold Critical Patterns .......................... . ................................B-4 B.3 VY Cycle 12 Cold Critical Pattems .............................................................B-5 B.4 VY Cycle 13 Cold Critical Patterns .............................................................B-6 B5 V Y Cycle 14 Cold Critical Pattems .............................. .............................B-8 B.6 VY Cycle 15 Cold Critical Pattems .............................................................B-9 , B.7 VY Cyc!c 16 Cold Critical Pattems ...........................................................B-11 B.8 VY Cycle 17 Cold Critical Patterns ...........................................................B-12 B.9 VY Cycle 18 Cold Critical Patterns ........................-...................................B-13 B.10 VY Cycle 19 Cold Critical Pattems ...........................................................B-14 C.1 VY Cycle 10 Averaged TIP Integral Errors, Standard Deviations, an d RM S Errors . . . . . .. .. . . ... . ... . ... . . .. . .. . . ... .. . . . . . .. . . . . . . . . . ... .. . . . . .. .. . . . . . . .. . . . . . .. . . . . . .. .. . .. C-2 C.2 VY Cycle 10 Core Average Axial TIP Comparisons by TIP Set ................C-3 C.3 VY Cycle 11 Averaged TIP Integral Errors, Standard Deviations, an d RM S Erro rs . . . . .. . ... . . . . ... .... . . . . . . . .... ... . .. . . . . . . . . .. . . . .. . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . .. . .. C- 8 C.4 VY Cycle 11 Core Average Axial TIP Comparisons by TIP Set ...... .........C-9 C5 VY Cycle 12 Averaged TIP Integral Errors, Standard Deviations, an d RM S Erro rs . . . . . . . . . .. . . . . . . . . . . .. . . . . .. . . .. . . . . . .. . . . . . . . . . . . . . .. . . .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . C- 14 C.6 VY Cycle 12 Core Average Axial TIP Comparisons by TIP Set ..............C-15 C 7- VY Cycle 13 Averaged TIP Integral Errors, Standard Deviations, and RM S Eno rs . . .. . . ... . .. ... . ... . . . .. . .. . . . .. .. . .. . . . . . . . .. . . . . . . . . . . . . . . . .. . . . .. . . . . .... . . . . . . ... .. . C-2 0 C.8 VY Cycle 13 Core Average Axial TIP Comparisons by TIP Set ..............C-21 C.9 VY Cycle 14 Averaged TIP Integral Errors, Standard Deviations, and RM S Erro rs . . . . . . . . . . . . . . .. . . . .. . . . .. ... . .. . . . .. . . . . . . ... .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. C-2 7 C.10 VY Cycle 14 Core Average Axial TIP Comparisons by TIP Set ..............C-28 C.11 VY Cycle 15 Averaged TIP Integral Errors, Standard Deviations, an d RM S Erro rs . . . . . . .. . . . . . . . . . . .. . . .. .. . .. . . . .. .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-3 2 C.12 VY Cycle 15 Core Average Axial TIP Comparisons by TIP Set ..............C-33 C.13 VY Cycle 16 Averaged TIP Integral Errors, Standard Deviations, and RM S Errors ... . ... ... ... ... .. . .. . .. .. .. ... .. .. . .. .... . . . .. .. .. . . .. . .... . .. .. . . ... . . . .. . .. . .. . . . C-3 7 vili
. . _- . - =- .- . .- . , i e e LIST OF FIGURES Number Title C.14 VY Cycle 16 Core Average Axial TIP Comparisons by TIP Set ..............C 38 C.15 VY Cycle 17 Averaged TIP Integral Errors, Standard Deviations, and RM S Eno rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
C.16 VY Cycle 17 Core Average Axial TIP Comparisons by TIP Set ..............C-40 C.17 VY Cycle 18 Averaged TIP Integral EtTors, Standard Deviations, an d R M S Erro rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C.18 VY Cycle 18 Core Average Axial TIP Comparisons by TIP Set ..............C-43 C.19 VY Cycle 19 Averaged TIP Integral Errors, Standard Deviations, an d RM S Erro rs . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . C.20 VY Cycle 19 Core Average Axial TIP Comparisons by TIP Set ..............C-47 D.1 PILGRIM Reload Design of Cycle 9 .......................................................... D-2 D.2 PILGRIM Station Cycle 9 Daily Average Thermal Power......................... D-3 D.3 _ PILGRIM Cycle 9 Control Rod Inventory Curve....................................... D-4 D.4 PILGRIM Reload Design of Cycle 10................. ....... .............................. D-5 D.5 PILGRIM Station Cycle 10 Daily Average Thermal Power....................... D 6 D.6 PILGRIM Station Cycle 10 Control Rod Inventory Curve... ........... ......... D-7 D.7 PILG RIM Reload Design o f Cycle 1 1........................................................ D.8 D.8 PILGRIM Station Cycle 11 Daily Average Thermal Power....................... D-9 D.9 PILGRIM Station Cycle 11 Control Rod Inventory Curve....................... D-10 E.1 PILGRIM Station Cycle 9 Cold Critical Pattem..........................................E-2 E.2 PILGRIM Station Cycle 10 Cold Critical Pattern........................................E-3 E.3 PILGRIM Station Cycle 11 Cold Critical Pattern........................................E-4 F.1 _ ILGRIM Station Cycle 9 Averaged TIP Integral Errors, Standard D eviations, and RM S Errors . .......... .............................. .............................. F-2 F.2 PILGRIM Station Cycle 9 Core Average Axial TIP Comparisons by TIP Set................................................................................................................F-3 F.3 PILGRIM Station Cycle 10 Averaged TIP Integral Errors, Standard Deviations, and RMS Errors ................................. ....................................... F 6 F.4 . PILGRIM Station Cycle 10 Core Average Axial TIP Comparisons by TIP Set...............................................................................................................F-7 F.5 PILGRIM Station Cycle 11 Averaged TIP Integral Errors, Standard Deviatio ns, and RMS Errors ..................... ............................ . ..................... F-9 F.6 PILGRIM Station Cycle 11 Core Average Axial TIP Comparisons by TIP Set............................................................................................................F-10 4 ix w
,. , i,. ACKNOWLEDGMENTS ] The authors wish to acknowledge contributions by C. Chiu, J. N. Neyman and D. J. Morin who have collected the VY data as part of their core follow efforts and by R. A. Wochlke for his assistance in editing this manuscript. We also wish to thank B. W, llagemeier of Boston Edison Company for his assistance in the gathering of the Pilgrim data. i X
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1.0 INTRODUCTION
AND
SUMMARY
Yankee Atomic Electric Company prepared a topical report (Reference 1) and obtained approval to use the hi!CDURN-3/CAShiO-3/FABl.ES-3/SIhfULATE-3 system of codes for Vermont Yankee Nuclear Power Plant in 1989. The original topical report benchmarks Cycles 9 through 13 of Vermont Yankee and describes in detail the codes and the plant specific models. Relative to that report, the model used and the conditions evaluated in this benchmark are very similar; however, this benclunark includes additional evaluations of new fuel types and low power / low flow conditions to expand the applicability of the modcl. This report benchmarks the hilCDURN-3/CAShiO 3/ FABLES-3/SihiULATE-? code package against ten recent cycles of Vermont Yankee operating data. 'Ihe models are used to calculate eigenvalues and detector response data at numerous steady-state exposure points. These calculations are compared to plant measurements; i.e., criticality and gamma Transversing Incore Probe (TIP) data. The consistency and accuracy of the comparisons validate these codes for reload design, steady state licensing and plant support applications. Several recent cycles of Pilgrim Nuclear Power Station are also modeled and benchmarked. The modeling of Pilgrim provides the opportunity to benchmark the code package against more advanced fuel designs, it also demonstrates the accuracy of the model versus neutron TIP systems. Section 2 provides a brief overview of the code package, hilCBURN-3/CAShiO-3ffABLES-3/ SIMULATE-3. Section 3 describes the Vermont Yankee cores and fuel types covered by the benchmark. Section 4 describes the construction of the Vermont Yankee model. Section 5 provides the detailed results of the model-to-plant comparisons of the Vermont Yankee model. Briefly, the average hot eigenvalue for the ten cycles is 0.9999 with a standard deviation of *0.0012. The cold eigenvalue is 0.9971 with a standard deviation of *0.0022. The model produces nodal instrument readings which are compared to the plant for 302 sets of TIP measurements. For lese comparisons, the RMS differences in nodal TIP readings using the plant gamma detectors are 2.0%. Section 6 provides a summary of the Pilgrim Nuclear Power Station comparisons. Briefly, the hot eigenvalue for the three cycles is 0.9997 with a standard deviation of
*0.0021. The cold eigenvalue is 1.0026 with a standard deviation of *0.0025. The model produces nodal instrument readings which are compared to the plant for 54 sets of TIP measurements. For these comparisons, the RMS ditTerences in nodal TIP readings using the plant neutron detectors are 5.1%.
1
%. . so e The results of the MICBURN-3/CASMO-3frABLES-3/ SIMULATE-3 benchmark l demonstrates that this code package is suitable for all applications approved in Reference
- 1. Also by virtue of this benchmark, the model application is expar:ded to handle more
)
advanced fuel designs and to cover low power and low flow operations. i 9 L 2 o
e e a e 2.0 GENERAL CODE PACKAGE DESCRIPTION i The code package benchnwked in this report is the current version of the physics codes of MICBURN-3, CASMO 3, TABLES 3, and SIMULATE-3. %refore, it is very similar to the approved code package used in reload licensing for Vermont Yankee Cycles 9-19. A brief general description of the codes is given below for completeness. 2.1 MICBURN-3 The MICBURN 3 code is 4 scribed in detail in References 2 and 3. It calculates the bumup in a fuel pin containing an initially homogenous distribution of the burnable absorber, gadolinium. The code supplies CASMO-3 with effective abso.ption cross sections for the gadolinium, homogenized over the fuel pin. 2.2 CASMO-3 CASMO-3 (alc.o referred to as CASMO-3P) is described in detail in Reference 4. Both the generic benchmark of the code and the Safety Evaluation Report are provided in Reference 3. CASMO-3 performs bumup calculations on an entire fuel assembly. The code handles geometry consisting of cylindrical fuel rods of varying composition in a square pitch array. It allows for fuel rods loaded with bumable poison, water gaps, water holes, boron steel curtains, channels and cruciform control rods. CASMO-3 uses multi-group transport theory to calculate the 2-D space / energy distribution of flux within the bundle. It performs the depletion calculation and produces two-group cross sections, homogenized over the assembly, for input into SIMULATE-3. CASMO-3 generates discontinuity factors for use in SIMULATE-3. The raodel uses 40 neutron energy groups. The nuclear library uses the standard ENDF/B-IV cross section set with some ENDF/B V fission spectrum updates. It can calculate both gamma and neutron detector responses. CASMO-3 can handle baflie/ reflector regions, hafnium control blades, water cross and large water hole assembly designs. The current version of CASMO-3 has been updated to model today's more complicated fuel and control rod designs. 3
2.3 TABLES-3 The TABLES 3 code (also referred to as TABLES-3P) is described in detail in References 5 and 6. It is a linking code between CASMO 3 and SIMULATE-3. TABLES-3 processes CASMO-3 two-group cross sections into two and three dimensional tables. SIMULATE-3 reads these tables and, according to the local conditions, SIMULATE-3 can reconstruct the appropriate homogenized two-group cross sections for each node. TABLES-3 can handle discontinuity factors, gamma or neutron detector response data and other data SIMULATE-3 requires. 2.4 SIMULATE-3 The SIMULATE-3 code (also called SIMULATE-3P) is described in detail in References 6 and 7. Reference 8 provides the generic benchmark and the Safety Evaluation Report. SIMULATE-3 is a three dimensional nodal analysis code. It models the steady state neutronics and thermal-hydraulic behavior of the core. It provides power, exposure, and i void distributions, bumup, fission product and reactivity effects. SIMULATE-3 is a true two-group nodal code, it uses the QPANDA model which solves the three-dimensional, two-group neutron diffusion equation. The QPANDA rnethodology also assumes that the flux distribution is comprised of two pieces: global shapes (homogeneous smooth flux distribution) and local shapes (heterogeneous assembly flux distributions). This assumption allows assembly discontinuity factors ADFs to be edited from the same CASMO-3 calculations that produce two-group cross sections. When used in the QPANDA model, the ADFs alter the neutron currents between nodes, effectively eliminating spatial homogenization errors. The ADF concept is also applied in modeling homogenized bafDe/ reflector nodes. Relative to Reference 1, SIMULATE-3 has been upgraded to handle the thermal-hydraulics and weight averaging of fuel assemblies with non-uniform axial geometry such as part length fuelrods. 4
. . is . 3.0 VERMONT YANKEE OPERATING CHARACTERISTICS Vermont Yankee (VY) is a General Electric BWR-3 which began commercial operation in 1972. Vermont Yankee began a transition to axially zoned fuel assemblies with a longer active fuel length in Cycle 6 (1978) 'Ihus, starting with Cycle 6, all VY cores have been zoned. Also, from Cycles 6 to 9, VY had cores that possessed uneven active i fuel at tne top. Beginning with Cycle 9 (1981), VY made the tmnsition to longer cycles. This required larger reload batches, and later, higher ewichments with more bumable absorber. There have also been several minor changes in the design of the fuel and water rods in the past ten years. All of these changes can be accommodated by the modeling capabilities of the MICBURN 3/CASMO-3/ FABLES-3/ SIMULATE-3 code package. 3.1 Core Description VY is a D-lattice plant with a small diameter, high power density core. The rated operating characteristics are provided in Table 3.1. The core description is summarized in Table 3.2. A radial map of the VY core is shown in Figure 3.1. All 368 cha:meled fuel . assemblics are orificed to control flow. The cross hatched assemblies, shown in Figure 3.1, have smaller orifices to maintain a flow balance between the higher powered core interior and the lower powered edge. The intersections of the dashed lines show the centers of the control blades. Figure 3.1 also shows the locations of the various incore detectors. The benchmarking effort presents comparisons in the 20 instrumentation locations containing both the Traversing Incore Probes (TIPS) and the local power mnge monitors (LPRMs). The LPRMs are fixed neutron detectors arranged at fou: axial levels as shown in Figure 3.2. The LPRMs are calibrated frequently: that is, normalized to their adjacent TIPS. The three TIP machines (A, B, and C) are, in turn, normalized to each other by use of a common core location shown in Figure 3.1. Thus, the TIP readings are the single most important measure of the accuracy of the model. All other measures of power distribution, including those at the plant, ere either derived or inferred from the TIP readings. Comparisons between the model-calculated gamma-TIP readings and the plant 4 measured gamma-TIP readings provide the most direct and accurate test of the ability of the model to reproduce the plant power distributions. Toward the end of Cycle 8(1981), the TIPS were converted from neutron detectors to gamma sensing detectors. The Vemiont Yankee benchmark will only compare to masurements made with the gamma TIP detectors, s n
L. . in . t I 3.2 Description of cycles Modeled l As discussed, Vermont Yankee converted to gamma TIPS toward the end of Cycle 8, i Thus, Cycle 9 was the first full cycle to use gamma /DPs and the first transition cycle to longer cycle lengths. Cycles I through 8 have little application to future plant operation ! and will not be presented here. Cycle 9 was modeled but was considered a transition cycle and therefore not included in the results. Thus, the benchmarking will examine Cycle 10 through the completed Cycle 18. In addition, the recently loaded Cycle 19 will be examined through part of the cycle. A summary of the operation of Cycles 10-19 is provided in Table 3.3. More detail of Cycle 10 through 19 is provided in Appendix A, which includes ins reload design of each of the cycles, As shown in Appendix A, Vermont Yankee employs a conventional core loading scheme, resulting in twice burned fuel assemblies alternating with fresh fuel assemblies. He loading schemes are also low leakage; i.e., oldest fuel loaded on the core periphery. In addition to low leakage, VY also demonstrates Idgh power density in a small core, resulting in steep, rapidly varying flux gradients, ne low leakage and high power density core behavior can be handled by the modeling capabilities
. of the code pact: age. -
3.3 Fuel Description Table 3.3 lists the vendor designation of each fuel type modeled in the Vermont Yankee benchmarking. Detailed descriptions of the fuel are propriettry to the vendor and can be found in Reference 9. However, as a general description of the fuel, the fuel types modeled are all D-lattice GE 8x8 arrays as shown in Figure 3.3. They include several different enrichments, gadolinium loadings, water rod designs, and active fuel lengths. Most of the fuel is zoned axially, creating several lattices per fuel type. A lattice consists of any unique pin distribution of enrichment or gadolinium in an axial slice of an assembly. Each lattice is explicitly modeled. In addition the model requires that the reflector regions of the core be represented. Therefore, explicit axial and radial reflectors (cross sections) for the 8x8 fuel are modeled. 6
as .
- TA13I E 3.1 i
Mennont Yankee Rated Operating Charneteristics
]
Rated Power (MWth) 1593.0 Average Power Density (kW/l) 49(1) Number ofAssemblies 368 Equivalent Core Diameter (inches) 129.9 l Total Core Rated Flow (Mlb/hr) 48.0 Core Bypass Flow (Mlb/hr) 5.2(2) l Steam Flow Rate (Mlb/hr) 6.43 Feedwater Flow Rate (Mlb/hr) 6,40 Feedwater Temperature (*F) 372
~
Nominal Steam Dome Pressure (ps!a) 1025 , Nominal Core Average Pressure (psia) 1040 CoreInlet Enthalpy(Btu /lbm) 520 CoreInlet Subcooling (Btu /lbm) 27 Core Exit Quality (% steam) 13.3 Notes; (1) Varies with active length of fuel. A full core of 150 inch fuel equals 48,92 kW/1. (2) Varies slightly from cycle to cycle. It depends on the number of assemblies with drilled lower tie pl tes and the number of water rods per assembly. Most later cycles
- have about 5.2 Mlb/hr of bypass flow at rated total core flow.
7 m
1 . on . TABI E 3.2 Vermont Yankee General Core Descrintion Number of Assemblies 368 Cold Assembly Pitch (inches) 6.0 Active Fuel Height (inches) 144-150 Fuel Rod Array , 8x8 Lattice Type D Fuel Pellet Material Sintered UO 2 Fuel Clad Material Zr-2 Channel Material Zr-4 , Channel Thickness (mils) 80 Spacer Material Zr-4 and Inconel l Number of Spacers 7 l Movable Control Rods Number of Rods 89 Shape Cmeiform Cold Control Rod Pitch (inches) 12.0 Contro! Material Height (inches) 143 Control Material Compacted B4C in S.S. tubes and sheath, or . Hafnium equivalent. Incore Instrumentation Source Range Monitors 4 Intermediate Range Monitors 6
~
Power Range Detector Locations 20 LPRMs (4 per Location) 80 TIP Machines 3 8 i
,ee as e TABLE 3.3 Summary of Vermont Yankee Cycle 3 Modeled 1/2 Cycle 10 1 Cycle 11 Cycle 12 Cycle 13 Cycle 14 , Operation Dates: BOC 6/17/83 8/6/84 4/30/86 10/2/87 4/8/89 EOC- 6/15/84 9/20/85 8/7/87 2/11/89 8/31/90 As-Loaded Core Weight (Short Tons): Initial H.M. 74.13 74.25 74.44 74.82 73.94 Core Average Bumups(Mwd /St): BOC 10,463 10,418 9,820 8,613 9,195 EOFPL 17,185 16,733 16,358 16,901 18,343 EOC 17,806 18,283 17,949 18,307 19,642 Thermal Capacity Factor While Operating: CF(%) 93.6 89.2 94.3 91.4 95.1 l Number and Type of Fuel Assemblies Loaded: Fresh 108 104 120 136 88&48 Identification P8DPB289 P8DPB289 P8DPB289 BP8DRB299 BD326B & BD324B 1 Cycle . 120 108 104 120 136
~
Identification P8DPB289 P8DPB289 P8DPC289 P8DPB289 BP8DPB299 2 Cycle 80 120 108 104 96 Identification - P8DPB289 P8DPB289 P8DPB289 P8DPB289 P8DPB289 3 Cycle 60 36 36 8 N/A Identification P8DPB289 P8DPB289 P8DPB289 P8DPB289 N/A s.. 9
- m
>e-e is . Table 3.3 Summary of Vennont Yankee Cveles Modeled l i 2n Cycle 15 Cycle 16 Cycle 17 Cycle 18 Cycle 19 Opention Dates: BOC 10/15/90 4/19/92 10/24/93 5/2/95 10/30/96 EOC 3/7/92 8/28/93 3/17/95 9/6/96
- As-Loaded Core Weight (Short Tons):
Initial li.M. 72.95 72.06 72.02 72.12 72.21 Core Average Burnups (Mwd /St): BOC '0809 1 II417 11547 12316 12,662 EOFPL 20046 21103 21603 22024
- EOCf 21082 21878 22156 22 % 5
- Thermal Capacity Factor While Operating:
CF(%) 92.5 95.5 94.1 97.8
- Number and Type of Fuel Assernblics Loaded:
Fresh 60 A64 &4 40 & 88 % A32 88 &32 - 120 Identification & BP8DWB31110GZ, BP8DWB311 10GZ, BP8DWB335-10GZ, BPSDWB335-10GZ, DP8DWB3$4120Z Type hP8DWB313 IIGZ. BP8DWB311 ilGZ BP8DWB335-IIGZ BPSDWB335 IlGZ GE-9 ANFIX 3.04B EGZ GE-9 GE-9 GE-9 GE-9 AANF-WAs 1 Cycle 88 & 48 60 &64 A4 40 & 88 96 &32 88 A32 Identification & BD326B & BD3248 BP8DWB311 10GZ, BP8DWB311 10GZ, BP8DWB335100Z, BPSDWB33510GZ, Type-- GE8 BP8DWB311 1IGZ, BP8DWB311 1IGZ BP8DWB335 IlGZ BPSDWB335-llGZ ANFIX-3.04B-EGZ GE-9 GE-9 GE-9 GE-9 & ANF-QA 2 Cycle 104 72 & 40 52 & 60 40 & 88 96 A32 Identification & P8DPB299 BD326B & BD324B BP8DWB311 10GZ, BP8DWB311 IXIZ, BP8DWB33510GZ,
'Type GE-7 GE-8 BP8DWB311 IlGZ, - FP8DWB3ll llGZ BP8DWB235-IIGZ GE-9 GE-9 GE-9 '
3 Cycle N/A N/A N/A N/A N/A Identification & N/A N/A N/A N/A N/A Type
- EOC Cycle 19 had not occurred at the time of this benchmark.
10
Figure 3.1 Radial Map of Vermont Yankee Core 44 42
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$ Common TIP Location b SRM Location '
O TIP Location (Three Machines: A, B, C)
- Source Location
@ IRH Location Tightly Orificed Assemblies 11
Es e ss < Figure 3.2 Axial Relationship of Fuel, Control Rod and Incore Detectors 1 Top of Channel 164" - PLLNUtt Tcp of Control l Blade 145" ;- IOP ZONE 4 Top of Active Fuel 150" Tcp of B4C 143" y ' Spacer --> d Top of TIP Trace 144" pg 0 139.85" D 0 126" Spacer 4 0 119.69" Spacer 4 0 99.54" LPM C 0 90" Spacer 4 - 0 79,39 HIDDLE ZONE 8 n. Spacer ---> d p 9 59.24" g - LPKM O B e 54" Spacer ---@ 0 39.09" Spacer 4 LPRM 6 gg,94 - A 0 18" Top of Zone Bottom of. ; M OE Activ3 Fuel 0.0" Bottom of Active Fuel 0.0" 12
. . . o . Figure 3.3 Detail of Fuel, Control Rod and Incore Instrument Tube W ') W ')
% r- O r, G 00000000 0 0 0 0 0 0 0 0.O 00000000 -
00000000 00000000 00000000 l 00000000 00000000 l 00000000 00000000 00000000 00000000 00000000 00000000 OOOOOOOO 0000000O e o .c yg o
- c. . .<'
(. . i i )uwe cie n r, Bfc >0 00000000 O rust oa utrea 00000000 OOOOOOOO OOOOOOOO h %.',"yls""y',,*" OOOOOOOO 00000000 OOOOOOOO c c o e 000000001+ NARROW GAP-13
lo e w e 1 4.0 VERMONT YANKEE SPECIFIC MODEL 4.1 MICBURN 3 Model Descrintion The MICBURN-3 code microscopier.lly oepletes the gadolinium in the burnable absorber pin. For the fuel types modeled in this benchmark, MICBURN-3 cases were run for each bumabic absorber pin that contained a different weight percent gadolinium. The primary output of MICBURN-3 consists of effective gadolinium microscopic absorption crovs sections for the bumable absorber pin (gad pin) at a function of the absorber number density, N BA, for USC in CASMO-3. The details on the MICBURN-3 model and se* a are stated in Reference 1. 4.2 CASMO-3 Model Description The CASMO-3 code (also called CASMO-30) is used to calculate the bumup and .'-D flux and energy distributions within each of the lattices required by the benchmark. 4.2,1 CASMO-3 Depletion Cases Each lattice in the benchmark required eight separate depletion cases. Four were uncontrolled; one each, at 0%,40%,70% and 85% voids. These are called the void history depletions, ne other four cases were controlled: one each, at 0%,40%,70% and 85% voids, nese are called the control history depletions. The output edited from each of the depletion steps includes: two-group cross sections and k-infinity, aaembly power distribution, conversion ratios, kinetics data, fission product yields, and assembly discontinuity factort These are processed by TABLES-3 for input into SIMULATE-3. The instantaneous effects are generated by means of branch cases run from various restart exposure points in the void history or control history depletion cases. Essentially, for each void history depletion, branch cases are run to each of the other void levels not covered by the deliletion. In addition, fuel temperature branch cases are run, and a rodded branch case is run. From the control rod history depletion, an unrodded branch case is run. In order to model the cold lattice, two uncontrolled and two controlled branch cases were run from each of the 0%,40%,70% and 85% void history depletions. The modermor for the cold cases is set to zero voids. The moderator and fuel temperatures are set equal to each other, ne controlled and uncontrolled cases are run at cold branch temperatures. 14 l
.. o ,
l For more details on the CASMO 3 rnodel and setup, refer to Reference 1, The major . change in the CASMO-3 model is the additional 85% void history depletion. His i depletion was included to provide additional accuracy at the top of the core. In keeping with the SER of Reference 1, the VY model continues to assume an appropriate amount ofchannel bow in the modeling of the CASMO-3 lattices. l 4.3 TABLES-3 Construction TABLES-3 (also called TABLES-3P) reads user specified CASMO-3 punch files and creates tables of parameterized input for SIMULATE-3. Separate TABLES-3 cases are run for each lattice type used in the benchmark. Because the VY model is segregated into a hot model and a cold model, separate sets of TABLES-3 cases are run for each condition. However, the outputs from both models are compiled into a single library that SIMULATE-3 can access. Reference 1 provides more details about the TABLES-3 construction. De only significant change relative to Reference 1 is that the base of the TABLES-3 hot model construction was changed from the 0% void depletion to the 40% void depletion. Making the base of the interpolation tables at 40% void fraction better represents the average }' reactor conditions at full power, 4.4 SIMULATE-3 Model Description The SIMULATE-3 model of VY is developed in two parts. These are the het and the cold model. hey differ in the temperature range at which the cross sections were generated, and in the thermal-hydraulics of the core. In both cases, the geometry and fuel specifications of the reactor are identical. 4.4.1 SIMULATE-3 Hot Model ne hot model performs thermal-hydraulics calculations. The SIMULATE-3 internal heat balance is input by means of interpolation tables of various reactor w~ater flows, temperatures, pressure drops, etc. The heat balance for the VY model was largely derived from fits to actual plant measurements. Some of the values, such as cany-under fraction, were inferred. The fraction of bypass flow and several other pressure drop parameters were calculated by FIBWR[10,11). Based on this heat balance, the SIMULATE-3 model calculates inlet subcooling. As an altemative, the subcooling calculated by the plent process computer can be input directly. 15
- - - . . _- - .. - - - -- _= -
b.. ,e . l For the calculatim. of volds up the channel, the VY model uses the standard EPRI Void correlation [12) Fu fuel temperatures, the VY model uses fuel temperatures generated with FRC SSTEY[13,14, IS). nese fuel temperatures were input to SIMULATE 3 as a function c.f exposure c n the assembly. Each cycle moMd in this benchmark was depleted in steps of one to two weeks l duration. In the early cycles, TIP calibrations were perfonned by VY on a one to two l week frequency, allowing the depletion to progress from TIP to TIP. Af er VY implemented the 3D Monicore* core monitoring system in 1990, the need for frequent TIP ca!ibrations was reduced, in later cycles, 'llP calibrations were perfonned approximately rnonthly. Between TIPS, the model was depleted in roughly weekly steps using the plant conditions and rod pattern at the end of each interval. Appendix A contains a summary of the condlions of each depletion step as well as descriptions of core condit a for each cycle. All of the TIP sets modeled are gamma TIP measurements and ns . L .dl are at equilibrium conditions. The input to SIMULATE 3 for each depletion step includes: core average exposure, power, flow rate, inlet subcooling, steam dome pressure, and control rod positions. SIMULATE 3 deplet:s to where a TIP set was taken and calculates a corresponding detector response. This response ca.a then be compared to the plant measured data. He SIMULATE-3 model setup is essentially unchenged from that described in Reference
- 1. In keeping with the SER, the use of the spacer void option was re-evaluated. The best results were achieved by retalning the spacer void option in the VY model. The SER in Reference 1 also restricted use of the model to the range of operating conditions existing in the benclunark of Cycles 913. Therefore, in addition to modeling plant conditions near full power / full flow conditions, the hot model in this benclunark models f lant conditions at low power / low flow conditions to further expand the applicability of the model.
4.4.2 SIMULATE-3 Cold Model The test of the T* cold model consists of comparisons to plant measured cold criticals. Each cold bencWrk is done as a branel, SIMULATE 3 case following the hot model depletion to the appropriate exposure point in the cycle. A fission product depletion s;ep always precedes the cold case, to account for the shutdown period before the critical was measured. This is necessary to account for the right fission product concentrations. Each cold benchmark case is modeled at the plant measured conditions of: core average exposure, reactor average teraperature (fuel and moderator are at the same temperature), and control rod positions. Reactor pressure is usually atmospheric; however, some of the criticals required a higher saturation pressure because they took place above 212'F. The reactor period, recorded at the time of the critical, is converted to worth via the in hour equation and used to correct the eigenvalue. 16
e e ., , l 1 A total of 33 cold criticals occurred at VY during the ten cycles nuxleled in the benclun tk. Every one of them was modeled. Appendix B gives the details of each cold critical. The accuracy of the model in the cold benclunark is determined by a steady consistent eigenvalue among all the cold critical cases. Section 5.2 of this report presents the SIMULATE-3 model results for all the cold benchmarks. d l - 'I l e e 17
(.. 5.0 VERMONT YANKEE PlWSICS MODEL RESULIS The evaluation of the entire code package is based upon the pcrformance of the SIMULATE 3 code. SIMULATE-3 is benclunarked against hot and cold critical statepoints from Cycles 1019. He model isjudged on two main figures of merit: Eigenvalues - rnust be reasonably close to 1.0. They must be steady, with smsll standard deviations. Any trends exidbited must be gradually varying. TIP Traces - generated by the model must compare closely to the plant TIP traces, both radially and axially. He errors must be small and steady. Any trend exidbited in the enors must be gradually varying. A model that meets both these figures of merit is suitable for making predictions. The applications of the model can be short range, as in plant operational support; or, long range, as in reload licensing. 5.1 Ilot Model Eigenvalues 5.1.1 EDll Power / Full Flow Conditions ne benclunark was initiated with the end of Cycle 8 (EOC8) CASMO-2/ SIMULATE-E exposure and void anays (References 16-19). As such, the EOC8 history arrays loaded into SIMULATE-3 were somewhat inconsistent with the new CASMO-3 cross sections. Also, the SIMULATE-E model for Cycle 8 did not employ a centrol rod Idstory,
%erefore, Cycle 9 was depleted to produce a set of exposure, void and control Idstory arrays consistent with the CASMO-3 cross sections. The results for Cycle 9 were discarded as a transitional cycle. Therefore, the benclunark is based upon Cycles 10-18 and part ofCycle 19.
Figure 5.1 shows the eigenvalues for the ten cycles of the benchmark. The data is consistent. There is a slight sinusoidal behavior to the eigenvalues. Ilowever, tids drift meets the criterion that any trends be slowly varying. It will not affect the ability to make critical predictions as long as the drift is considered during predictions. Table 5.1 shows the average hot eigenvalue for each cycle widi the standard deviation. The average hot eigenvalue for all cycles is 0.9999 i 0.0012. This meets the figure of merit of being reasonably close to unity. The overall standard deviation is small and consistent within the individual cycles. The standard deviations, for each cycle, primarily reflect the small amount of drift in the eigenvalue over each cycle. Within a given cycle, the eigenvalue is very well behaved. It varies gradually with exposure as the presions example in Figure 5.1 illustrates. Herefore, tids model is suitable for hot critical predictions during plant operation. 18
e s w e . Table 5.2 shows the hot startup eigenvalue at the beginning of each cycle, his was derived by veraging the first five equilibrium statepoints of each cycle. He average of the DOC hot eigenvalues is 1.0000 for all the cycles, with a standard deviation of 10.0014. his small standard deviation indicates good consistency among the cycles. In reload licensing applications, this provides a high level of confidence in the calculation of DOC hot excess reactivity Mus, predictions of startup control rod pattems will be quite accurate, Table 5.3 shows the hot eigenvalue at end of full power life (EOFPL)in each cycle. his was the eigenvalue of the depletion statepoint nearest to the start of coastdown. As with the BOC eigenvalues, the EOFPL values are consistent among all the cycles. The average of all the EOFPL hot eigenvalues is 1.0022 with a standard deviation of 0.0013. Consistency in these eigenvalues is important for predicting the EOFPL exposure when l performing reload licensing analysis. The results ofcertain licensing transients, especially l the pressurization translents, are sensitive to the EOFPL condition. 5.1.2 Low Power / Low Flow Conditions The benchmark for low power / low flow consists of modeling the VY Cycle 19 startup. He reactor was modeled from cold critical to hot full power. Figure 5.2 shows the power and flow conditions venus time for this benchmark. Figure 5.3 shows the rod insertion versus time, nese figures show that a large range of power / flow / rod insertion cases were modeled. Figure 5.4 shows the eigenvalue venus time. As shown, the eigenvalue beyond the 25 hour point is steady. His coincides with powers above 15% core thermal power (CTP). The average eigenvalue above 15% CTP for this benchmark is 1.0000 for core thermal power greater than 15% with a standard deviation ofi 0.0023. nus, the model can be used to predict low power / low flow conditions. 5.2 Cold Model Eigenvalues The cold model is based on the in-sequence cold critical statepoints that occurred at the l plaat during Cycles 10 through 19. No local (few rod) criticals were ' demonstrated during these cycles. The results of the cold critical benclunark are presented in Table 5.4. The actus! control rod patterns for the criticals are given in Appendix B. The cold critical eigenvalue for the SIMULATE-3 model is 0.9971 with a standard deviation of* 0.0022. The cold eJgenvalue is plotted against cycle exposure in Figure 5.5. From this figure, it can be seen aat the data exhibits a trend with exposure. This trend can be fitted with a 19
e s *
- stmight line as shown in Figure 5.5. 'this linear regression represents the best estimate cold critical eigenvalue versus exposure. 'lhe residual k effective using this bumup correction has a standard deviation of 10.0013. 'lhete are no other obvious trends exhibited by the cold critical eigenvalues with regard to moderator temperature, etc.
Even though the VY benchmark does not include any local (few rods) cold critical statepoints, it has been shown by Northem States Power in Reference 20, that the CAShio 3/SihiULATE 3 code package demonstrates no k-effective bias between the local criticals and in sequence criticals demonstrated at hionticello. The hionticello core design and local criticals are diflicult to obtain; however, the core design of Quad Cities Urdt 1, Cycle 1, is in the public domain (Reference 21). Quad Cities performed 10 local criticals (Reference 22) at 110Cl. These were modeled with CAShiO 3/ SIMULATE 3 and the results am compared to the VY results in Figure 5.6. As shown, the Quad Cities local critical results am reasonably close to the VY in sequence critical results at zero cycle exposure. Iloth Monticello (Reference 20) and the Quad Cities to VY companson (Figure 5.6), show that there are no significant differences between the ability of the model to calculate local and in sequence criticals. 4 In conclusion, the cold eigenvalue benchmark demonstmtions modeled for Cycles 10-19 are suflicient to demonstrate cycle to cycle eigenvalue consistency with a small standard deviation, provided one accounts for the exposure dependence in the application of the . eigenvalue (See Figure 5.5).
- 5. 3 Hothiodel Detector Comparisons All plant meesurements of power distribution ultimately depend on the TIP taces.
SIMULATE-3 produces a set of ganuna based detector responses at specific instmment locations. 'Ihese responses can be compared with the plant measured gamma TIP traces, at the same locations. The simplest comparison is a one-for-one comparison, or nodal comparison. Each of the 20 plant TIP traces has 24 readings, spaced evenly over the 144 inches of the TIP tube, giving one reading for every six inch node. One-for one comparisons were made between the SIMULATE-3 TIP readings and the plant TIP readings at each of the 480 nodal (24x20) locations. 'Ihe 480 comparisons provide an RMS enor for each exposure statepoint where TIP readings were taken (called a TIP set). The nodal RMS crrors wem statistically summed for each cycle and for all ten cycles. 'Ihe results am given in Table 5.5. During Cycle 16, TIP machine "A" malfunctioned and it was not repaired until late in the cycle: This significantly reduced the number of valid TIP comparisons available in Cycle 16.at equilibrium xenon conditions. Ilowever, given the ten cycle span of the benchmark, the lack of data for Cycle 16 is not an issue. For the ten cycles the total RMS nodal error is 1.98%. 20
.c . ._. . - -- . _ - _ _ _ _ - - ..-
.. , + , i f Die TIP instnunentation error can be characterized by calculating the TIP asymmetry associated widi cach cycle. To calculate the TIP asymmetry, the nodal plant calculated . TIP traces are compared for % differences at symmetric locations across the core at the I beginning of each cycle. The case chosen must be eighth core syrnmetric. This value for each cycle is shoven in Table 5.6. Cycles 10 and 11 are not included because they did not startup in eighth core symmetric pattems. The overall TIP asymmetry is 1.97%, Thus, instmment uncertainty as characterized by TIP asymmetry, is of the same magnitude as die RMS error (l.98%). 5.4 Rndial Comparisons : Integrated TIP readings were created at each of the 20 instrument locations by adding up the 24 normalized nodal readings for each individual string. 'the resulting integral reading for the given string is proportional to the relative reactor power in the four adjacent assemblies.13y comparing the SIMULATE-3 integrated TIP readings to the plant integrated TIP readings, a map may be constmeted showing the radial differences. The integral TIP differences at each TIP location for each TIP set have been averaged and mapped for each cycle. These radial maps can be found in Appendix C. The differences at each location can '.dso be averaged for all ten cycles as shown in Figure 5.7. The radial comparisons show excellent agreement between the model and the plant. , 5.5 Axial Average comparisons in a manner similar to the creation ofintegrated TIP readings, the TIP readings may be integrated for axial planes cf the core. The resulting reading is proportional to the relative power in the given plane of the core. The SIMULATE-3 core average (planar) TIP readings may then be compared to the plant core average (planar) TIP readings. Appendix C provides axial average comparisons for all TIP sets in the benchmark. The axial average comparisons, given in Appendix C, show excellent ovemil agreement between the model and the plant. 21
i 4 e . . 4 f ! TABLE S.I i -l j VY SIMULATE-3 Cycle Averagcjkdigem alure a .I i Cycle Number of Average
- Standard .
Statepoints' Eigenvalue Deviation ! Modeled 10 46 1.00046 0.00166 j 11 41 1.00171 0.00143 4 12 44 1.00190 0.00097 1 13 52 1.00088 0.00140 4 14 39 1.00002 0.00096 15 41 0.99916 0.00111 i
- 16 G7 0.99913 0.00066 i 17 69 0.99811 0.00194 i 18 67 0.99905 0.00085
{- 19 27 0.99919 0.00123 4 , 10 Cycles 0.99994 0.00123 !
- Statepoints modeled include TIP cases and equilibrium cases
, between TIPS. i 0 t i 4 d F s f 22
oe
- e i
TAllLE 5.2 VY SIMUL ATE-3 Beginning of Cycle 1101 Rigenvalues Cycle Nurnber of Average
- Standard IlOC Eigenvalue Deviation ;
Statepoints ; 10 $ 1.00001 0.00011 11 5 1.00002 0.00148 12 5 1.00186 0.00023 13 5 1.00068 0.00024 14 _ 5 1.00041 0.00029 15 5 0.99952 0.00046 16 5 0.99906 0.00052 17 5 0.99767 0.00121 18 5 0.99887 0.00079 19 5 1.00213 0.00073' 10 Cycles 1.00002 0.00135 23 l
. e se .
TABLE 5.3 l 1 VY SIMULATE-3 End of Full l'ower Life 110t Eigenvalues Cycle Number of Average Statepoints Eigenvalue 10 1 1.00337 11 1 1.00334 12 1 1.00394 13 1 1.00247 i 14 1 1.00201 15 1 1.00170 16 1 1.00065 17 1 1.00198
~
I 18 1 1.00020 19 N/A N/A 10 Cycles 1.00218 i0.00125
- Cycle 19 data does not include an EOFPL statepoint 24
ee .* e TABLE 5.4 VY Cold Critical Case Conditions and SIMUL ATE-3 Results Date Cycle Cycle ControlRod Recirc. Reactor K effective Number Exposure Sequence Temperature Period Adjusted (mwd'St) ('F) (Sec) for Period 5/28/83 10 0 Al 103 223 0.99696 6/17/83 10 0 Al 189 75 0.99824 1/US4 10 4,085 Al 225 120 0.99642 6/19/84 10 7,343 A2 126 100 0.99334 6/19/84 10 7,343 D1 127 200 0.99457 7/27/84 11 0 A1 94 160 0.99728 l 8/6/84 11 0 Al 161 197 0.99758 9/29/84 11 633 AI 227 120 0.99722 6/5/86 12 0 A2 83 185 0.99854 6/30/86 12 0 B2 158 87 0.99825 7/02/86 12 0 B2 165 118 0.99872 8/27/87 13 0 A2 87 55 0.99792 10/02/87 13 0 A2 197 72 0.99686 7/2/88 13 5,386 B2 209 70 0.99275 8/26/88 13 6,329 Al 228 142 0.99433 8/28/88 13 6,329 Al 234 96 0.99424 3/02/89 14 0 A2 84 55 0.99810 4/08/89 14 0 A2 195 121 0.99788 . 3/21/90 14 7,210 Al 226 185 0.99416 25
. e ** a TABLE 5.4 (con't) VY Coldfritical Case Conditions and SIMULA~lT -3 Results Date Cycle Cycle Control Rod Recirc. Reactor K effective Numtw Exposure Sequence Temperature Period AcDusted j (mwd'St) ('F) (Sec) for Period I
~
10/10SO 15 0 A2 116 75 1.00179
~
10/1460 15 0 A2 201 192 0.99932 3/17/91 15 3.111 Al 224 95 0.99646 3/1861 15 3.111 Al 245 111 0.99634 4/30S1 15 3,892 Al 206 242 0.99647 6/20S 1 15 4,884 A2 236 167 0.99595 9/14S1 15 6,624 B2 191 500 0.99517 4/19 S 2 16 0 A2 162 77 0.99858 4/16/93 16 7,603 D2 220 134 0.9938E 10/24/93 17 0 A2 158 275 1.00027 12/12/93 17 915 A2 198 120 0.99873 12/20/93 17 915 A2 200 267 0.99839 5/02 S 5 18 0 A2 136 80 1.00023 10/30S6 19 0 A2 151 165 0.99907 Average 0.99713 Standard *0.00216 Deviation 26
.O o &
TABLE 5.5 VY SIMULATE-3 Nodal TIP Reading NMS Enors Cycle Number of Pais Error TIP Set 10 45 2.2452 11 39 1.9231 i 12 43 1.9193
~
13 51 2.1896 14 34 1.8296 15 36 2.0330 16' 8' 2.2053 17 18 1.4123 18 20 1.6251 19 8 1.6508 10 Cycles 1.9810
- An inoperable "A" TIP machine resulted in Cycle 16 having only 8 complete TIP sets.
27
\e b
- b TAI 3LE 5.6 i
VY Total TIP Uncertainties at 13eginning of Cvele Cycle Piet TIP Uncertainty (%) 10
- 11
- 12 1.9274
=
13 2.0418 l l 14 2.6021 15 2.5593' : 16 1.8724 17 1.5599 18 1.5551
-19 1.6549 8 Cycles 1.9716 i
- No BOC eighth core symmetric case exist e
20 (
- , . . . . , , _ . . . - ~ . . , . - - . . .-- - -, - -
o D ** 6 FIGURE 5.1 VERMONT YANKEE CYCLES 1019 DEPLETION K EFFECTIVE VS. EXPOSURE 1.010 0 Cycle 10 1.009 6 Cycle 11 . O Cycle 12 1.008 - v Cycle 13 ..
- Cycle 14 e Cycle 15 1.007 - a Cycle to 4 Cycle 17 1.000 -
- Cycle 18 -
Y Cycle 19 1.005 - 1.004 - 6 - 1.003 - 0 80 4'h7W v
~
97 0 1.002 - o *M 0 j aA 00 y8 , *V V g - l ,,og, _ .. . 4 .% ,......gg.e.^. g p .% . g.9...v,,...*.*..>.....**4 A . _ u 1.000 - * - ****+** * - 5 *'l': ,, 0.997 - Nkh}'khh$f
.. A A
A A Ai A, 0.996 - Aa '"' # A A A 'a ' ' - A 0.995 - - 0.994 - - 0.993 - - 0.092 - - -
- Average K off = 0.99994 0.991 - . . Avg K-eff + Std Dev = 1.00117
-- Avg K off . Std Dov = 0.99871 0.990 i ,
i , i , O 1 2 3 4 5 6 7 8 9 10 11 CYCLE EXPOSURE (GWd/St) 29
...a .. . I a J 2 4 } Figure 5.2 s j Low Power / Low Flow 13cnclunark , Power and Flow Versus Time 4 I 4 I 100 i g*, $
,# 9
- g, j / ,'
t a ! 80 = - % %r '
. . % Fbw ;
i / ','
. ); . a
- - 70 '
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60 =' .
.E : /-
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, . . . . . ......- .,,. ,y.
s I -- 30 . 20 ',
/
10 - ~ 0' ,,, , , , ,,. ,,, ,, , , , , ,,, , , , , , , 0 20 40 00 80 100 120- 140 160 180 Time (hrs) 30 . 1
- . o se i J
I 1 Figure 5.3 Low 1 ower Low Flow Denclunark Rod Position versus Time k 3500
. s h
i 3000- " a E ( 1 .: e 1500-3 1000
- X /t 1 S
. \
m q y Q y & Q Q l l $ l N h
.0 20 40 00 80 100 120 140 160 180 Time (hrs) -
31-
- 1
. o i. 6 :
J d 1 i FIGURE 5.4
- Low Power Low Flow Denchmark ,
., Keft vs. Time ' s i 1.04000 i i ! t 1.03000 = ; O e 1.02000 - E x 1.01000 l 1.00000 - i I Y % ; N [J 4 4 I I I I 1 3 4 I 1 4 4 E 4 5 4 I E 5 I E V I I 5 4 $ 0 20 40 60 80 100 120 140 160 180 Time (hrs) 32 , . .- - - . - -. ._ , . - . . , .
i . o is 6 6 4 i k i 1 4 t FIGURE 5.5 . Cold Eigenvalue vs Cycle Exposure 1 ! 1.01
- LINEAR REGRESSION
- - STANDARD DEVIATION OF THE RESIDUALS j f
r I i e i 1.005 - k i 4 I lu J 1.0 - o L ' 4 s
\
4 ...
\\ ... .
V 7...e....... 4.............
... 44 %
4
........... 4 4
.......... g 4 ...
4
.........4 I
. . . .. 5 m
4 I T 5 t U 1 1 ] T ] V T 1 4 4 i 1 1 1 4 5 I I E 3 1 4 I g1 0 1 2 3 4 5 6 7 8 9 10 CYCLE EXPOSURE (GWd/St) d _ . . . . _ ..,33 . ... _ ... _ - _ _ . . - _ ._-, _ _ . - _ _ . .
.o i. e FIGURE 5.6 Vermont Yankee and Quad Cities Unit 1 Cold Eigenvalue vs Cycle Exposure 1.01 o Adjusted K effectives: Oued Cities Unit 1 BOC 1
- Adjusted K effectives: W Cycles 1019 LINEAR REGRESSION FOR W COLD CRITICAL 8 l , - STANDARD DEVIATION OF THE RESIDUALS FOR W COLD CRITICALS I
I 1,005 - O II e e \\ t, k s.o :,........ e e k \ . t vg...&....... ............ Q.9 4 4 9 0 ..... 0.99 ,,,,, ,, 0 1 2 3 4 5 6 7 8 9 10 CYCLE EXPOSURE (GWd/St) 34
.. 6 9 . FIGURE 5,7 Vermont Yankco Cyclos 1019 Averaged I'IP Integral Errors, Standard Dovlations, and RMS Errors l I 1 KEY (in %): Avorogo Difference J l l l Standard Deviation
~ ..,p.. ...t... ...l... , RMS Differonco 1 m -a w ar r a - j
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I t 1 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 M
6.0 fiUMMAllY AND DESCRIPTION OF Tile ElLORIM MODEL ne Pilgrim core was modeled to demonstrate the capability of the code system to model the more advanced llWit fuel types, it also demonstrates the ability of the code to model neutron TIpplants. 6,1 Summary of Cycles Modeled Pilgrim Station is a 1998 MWth power plant with 580 fuel assemblics and 145 cruc! form shaped movable control rods in its core. De nited operating characteristics are provided in Table 6.1 We core description is summarized in Table 6.2. A radial map of the Pilgrim core is shown in Figure 6.1. Included in this map are the locations of the various incore detectors, ne intersections of the dashed lines in Figure 6.1 show the centers of the control blades. Pilgrim employs a Control Cell Core
- loading scheme. The loading schemes used are low leakage; i.e., oldest fuel loaded on the core periphery, ne benclunark examines Cycle 9 through, Cycle 11. The previous seven cycles have little ap-lication to future plant operation and were not inch'ded in the benchmark. A summaty of the operation of Cycles 911 is provided in Table 6.3. More detail of each cycle is provided in Appendix D including the reload design of each of the cycles.
Table 6.3 lists the vendor designation of each fuel type modeled in the benchmarking effort. As a general description of the l'uel, the fuel types modeled in Cycle 9 are D-lattice,8 x 8 arrays (GE-7 and GE-8). The Cycle 10 fuel type is also in a 8 x 8 array; however, it is a GE-10 fuel type which has an offset channel intended to make the D-lattice plant more closely resemble a C-lattice plant. The Cycle 11 fuel type (GE-II) is a 9 x 9 array with the same offset channel used in the Cycle 10 design. The fuel types in these cycles include several different enrichments, gadolinium loadings and active fuel lengths. In addition, the GE-11 possesses part length fuel rods. That requires the model to handle differing thermal hydraulle axial zones. Some of the fuel is zoned axially, creating several lattice arrays per fuel type. A lattice array consists of any unique pin distribution of carichment or gadolinium in an axial slice of an assembly. Each lattice artuy is explicitly modeled. For the remainder of tids section, the term lattice will be used to mean lattice array. 36
c 0 ** 6 6.2 Pilgrim Physics Model ltesults 6.2,1 Hot Model Egenvalues ne Pilgrim benchmark was initiated by obtaining a set of exposure and void history arrays from the beginning of Cycle 8 (BOC8). The latter were part of a CASMO. 2/ SIMULATE-E model of Pilgrim. As such, it s end of Cycle 7(EOC) history arrays loaded into SIMULATE 3 were inconsistent with the new CASMO-3 cross sections. The old cross section history effects disappear during the depletion of Cycle 8. Ilowever, all of the Cycle 8 results were discarded to climinate any bias that may have occurred due to the effects ofinconsistent histories. Since the use of the spacer correction option must be evaluated on a plant by plant basis, the option was tested for the Pilgrim plant but was not employed because the model to plant comparisons were better with the option tumed oft. Figure 6.2 shows the eigenvalues for the three cycles of the benchmark. The data is fairly consistent, exhibiting a drift similar to that exhibited by the VY model. The eigenvalue tends to drop through the first half of the cycle, and drin back up in the . second half. However, the drining is slowly varying. The drin will not affect the-ability of the model to make critical predictions as long as it is considered during predictions. Table 6.4. shows the average hot eigenvalue for each cycle with the standard deviation. The average hot eigenvalue for all cycles is 0.9997*0.0021. He overall standard deviation is acceptable and consistent within the individual cycles. Within a given cycle, the eigenvalue varies gradually with exposure. Therefore, tids model is suitable for hot critical predictions during plant operation. Table 6.5 shows the hot startup eigenvalue at the beginning of each cycle. The hot startup eigenvalue was derived by averaging the first equilibrium statepoints of each cycle. %e average of the BOC hot eigenvalues is 1.0002 for all cycles. The standard deviation is 10.0023. This standard deviation indicates good consistency among cycles. Table 6.6 shows the hot eigenvalue at end of full power life (EOFPL) in each cycle. This was the eigenvalue of the depletion statepoint nearest to EOFPL. As with the DOC eigenvalues, the EOFPL values are consistent among all the cycles. The average of all the EOFPL hot eigenvalues is 1.0025 with a standard deviation of *0.0004. 6.2.2 Cold Model Eigenvalues ne results of the cold critical benclunark are presented in Table 6.7. The actual control
- tod pattems for the criticals are given in Appendix 2. He cold critical eigenvalue for the SIMULATE 3 modelis 1.00261 with a standard deviation of *0.0025. It must be noted 37
. . .= .
that only BOC cold criticals were evaluated. Since the initiating cycle was Cycle 8, the jj HOC 8 statepoint is not included. The low number of cold critical statepoints makes the ) statistics questionable. 6.2.3110t Model Detector comparisons l All plant measurements of power distribution ultimately depend on the TIP traces. At Pilgrim Station the TIPS employ a neutron detector, not a ganuna detector. S1hiULATE. 3 uses CAShiO 3 data to produce a set of neutron based detector responses at specific instrument locations. These can be compared with the plant measured neutron-TIP traces, at the same locations. The simplest comparison is a one for-one comparison, or nodal comparison. Each of the l 30 plant TIP traces has 24 readings, spaced evenly over the 144 inches of the TIP tube, giving one reading for every six inch node. One for one comparisons were made between the SlhiULATE-3 TIP readings and the plant TIP readings at each of the 720 nodal (24x30) locations. nc 720 comparisons provide an RhtS crror for each exposure statepoint where TIP readings were taken. The nodal RhiS errors were statistically summed for each cycle and for all four cycles. The results are given in Table 6.8. For the three cycles the total RhiS nodal error is 5.12%. A large portion of the error can be attributed to the inaccuracies of the neutron TIP instrumentation. Relative to gamma TIPS, neutron TIPS are :.. ore sensitive to the I geometric location of the TIP-tube within the water gap that exists between the channels. The instrumentation error can be approximated by calculating the TIP asymmetry associated with each cycle. To calculate the TIP asymmetry, the nodal plant TIP trace measurements are compared for symmetdc locations across the core. The case chosen must be eighth core symmetdc. This value for each cycle is shown in Table 6.9. The overall TIP asynunetry is 5.00% with most of tids enor being found in Cycle 9. A comparison of RhtS errors in Table 6.8 and the TIP asymmetry in Table 6.9 shows that the code RhiS error goes up and down with the TIP asymmetry. Because of the sensitivity of neutron T1Ps to geometrical positioning within the water gap, the neutron TIPS in general exhibit more instrument uncertainty than gamma TIPS. This is assumed to be the reason why the Pilgrim model exhibits an RhiS error larger than the VY mode!. 6.2,4_Itndial Comparisons Integrated TIP readings were created at each of the 30 instnunent locations by adding up the 24 nomialized nodal readings for each individual string. The resulting integral reading for the given string is proportional to the relative reactor power in the four 38 s
- adjacent assemblies. Ily comparing the SIMULATS3 integrated TIP results to the plant J integrated TIP results, a snap may be constructed showing the radial citor.
He integral TIP differences at each TIP location for each TIP set have been averaged and mapped for each cycle. %csc radial maps can be found in Appendix F. %e differences at cach location can also be averaged for all four cycles as shown in Figure 6.3. The radial comparisons show good overall agreement between the model and the plant. 6.2.5 Axial.,Avernse comparisons in a manner similar to the creation ofintegrated TIP readings, the TIP readings may be integrated for axial planes of the core. He resulting reading is almost prolcrtional to the relative powcr in the given plane of the core. He SIMULATE 3 core average (planar)
' TIP readings may then be compared to the plant core average (planar) TIP readings.
Appendix F provides axial average comparisons for all TIP sets in the benclunark. De axial average cornparisons, given in Appendix F, show good overall ag reement between the model and the plant. 39
e e <* s TAllLE 6.1 ISlgrim Rated Opergting Charactedstics Operational Data Rated Power (MWth) 1998 l- . TotalCore Rated Flow (MIMA) 69 l Core Bypass Flow (MIMv) 7.01 l Steam Flow Rate (Mlb/hr) 7.98 l Feedwater Flow Rate (Mlb/hr) 7.92 Feedwater Temperature ('F) Normal 365 Final Feedwater Reduction 290 Nominal Steam Dome Pressure (psla) 1034.6-. Core inlet Enthalpy(Btu /lbm) 534.65 '
- Core Inlet Subcooling(Btu /lbm) 23,31 '
?
40
e a s* s TABLE 6.2 Pilgrim General Core Description Eucl Number of Assemblics $80 Cold Assembly Pitch (inches) 6.0 Active FuelIleight(inches) 145.24,141.24 Fuel Rod Array - 8x8,9x9 Lattice Type D Fuel Pellet Material SinterUO 2 FuelClad Material Zr 2 Channel Material Zr 3 ChannelTidekness(mils) 80,65 SpacerMaterial Zr-4 and Inconel NumberofSpacers 7 Movable Control Rods Number ofRods 145 Shape Crucifonn Cold Control Rod Pitch (inches) 1,2.0 ' Control Materiallieight(inches) 143 Control Material Compacted in B4 C in S.S. tubes & sheath Incore Instmmentation Source Range Monitors 4 Intennediate Range Monitors 8 Power Range Detectorlocations LPRMs(4 perLocation) 120 TIP Machines 4 41 _____ J
e o
- s , ,
l i TAlli E 63 i Summary ofl'ilgrim cveles Modeled Cycle 9 Cycle 10 l C)tle 11 Operation Dates: i 1100 8/14/91 S'30/93 6/01/95 ! EOC 4/03/91 3/25/95 * ' Core Average Dumups(Mwd'St): BOC 10,$31 12,832 13,336 EOFPL i EOC 19,24$ 21,977
- t Number and lype of fuel Anemblies Loaded:
Tresh 168 140 136 ldentincation & BP8DQB323 BP81tXil333 BI911UB378 Type Obl0 ODII 1" Cycle 192 168 140
)
Identincation A BP6DRB300 BP8DQB323 BP8ttXB335 Type ODIO 2" Cycle 192 192 168 Identification P8DRB282 BPSDRB300 BPSDQB323 3dCycle 8 &20 80 136 IdemlGcation P8DRB282 & P8DRB282 BPIDRB300 PIDRB263 i
- EOC Not Available T
r 42
e o + _s TABLE 6.4 Pilgrim SIMULATE 3 Cycle Average 110t Eigenvalues a Cycle Number of TIP Set Average Eigenvalue i Standard Deviation 9 19 0.99985 0.00130 10 18 0.99813 0.00212
~
11 17 1.00117 0.00185 l 3 Cycles 0.99969 0.002I l TABLE 6.5 l l- Eilcrim SIMULATE 3 Beginning of Cycle llot Eigenvalues 1 l Cycle Number of TIP Set Average Eigenvalue 9 4 0.99855 10 4 0.99925 11 4 1.00288 3 Cycles 1.00023
*0.0023
- TABLE 6.6 Pilgrim SIMULATE-3 End of Full Power Life Hot Eigenvalues Cycle Number of TIP Set . Average Eigenvalue
~
9 1 1.00288 10 1 1.00201 11 1- 1.00266 3 Cycles 1.00252 v 10.00045 43
TABLE 6.7 Pilgrirn Cold Critical Car >e Conditions and SIMULATE-3 Results Cycle Cycle Control Recirc, React K effective Nember Exposure Rod Temperature or Adjusted (MW4St) Sequence (*F) Period for Period (Sec) 9 0 A2 180 137-- 1.00184 10 0 A2 185 102 1.00060
~
11 0 A2 150 209 1.00539 Average 1.00261 S*andard ggy49 Deviation l l
-e 44-
e e o . } TABLE 6.8 Ellgrim SIMULATE-3 Nodal TIP Reading RMS Errors Cycle Number of TIP RMS Error Sets 9 19 6.232 10 18 4.129 11 17 4.671 3 Cycles 5.120 TABLE 6.9 Eilgrim Total TIP Uncertainties at First Eighth Core Symmetric Cycle Number ofTIP Total TIP Uncertainty Sets _ from Plant Traces Only 9 1 6.001 10 1- 4.132 11 4 4.865 3 Cychs 4.999 45
FIGURE 6.1 Radial Map of Pilgrim Core - .. I i i l I i I i l i l I i I e
~~~~ 1 I I i 1- 1 i l i I I I I I I i 1 l I I I I i 1 1 1 I I I I I i i i I I I I I l l lslI-1-
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'O I I I I I I I I I I i 1 1 1 I I i i i I I I l
-@ I- 1 I I I i @ i l-1 I I i i I l- 1 I I l- l~ -1 I l ' I I I l lcl i lu; lc; 1-I I 1 1 1 I I I I I i 1 I I 1 i l i 1
- 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 i
$ Common TIP Location @ IRM Location O _ TIP Location (4 Machines: A,B,C D) A - SRM Location 46
i e' o 4 . FIGURE 6.2 PILGRIM CYCLE 9-11 DEPLETION K EFFECTIVE VS. E)'POSURE j 1.010 j' v Cycle 9 1.009 -
- Cycle 10 -
O Cycle 11 1.008 - - 1.007 - - 1.006 - - 1.005 - - 1.004 - g_ ~ O O O 1.003 - + 0 0 y - 1.002 -
.........g ........................................v..........*...... -
$ 1.001 v 0 v+ -
b 'O h 7
- W , ,, v 0, -
. @ 1.000 - v V O " '
y0.999- 4 7 VV v 0 0 v - Y
.0.998 - + , , O -
.y..................................................................
0.997 - ,
+ +
0.996 - + -
'O.995 - ,+ -
0.994 - - 0.993 - - 0.992 - -
- Average K-eff 0.99969 0.991 - -- Avg K-eff + Std Dev- 1.00179 -
-- Avg K-eff Std Dev 0.99759 0.990 ,
0 1 2 3 4 5 6 7 8 9 10 CYCLE EXPOSURE (GWd/St) i
e e v . FIGURE 6.3 Pilgrim Station Cycle 0911 Averaged TIP Integral Errors, Standard Deviations, and RMS Errors KEY (in %): Average Difference I I i I - i i Standard Deviation
.-_1_._
.. fi .- _ .ll I 1_._ I- l. _ ___1_.-_f__
I I i RMS Difference
- 1. I I I I I I I I I i 1 1 I -1 1 1 I i 1 1 I I I i 1
-l i I i , 1 1 1 I 1 I l.. I ! I l l l I l:
i i i i la i i
!.!Ei i
i i Iif i. i i i i i i l i 1 1 -i l- 1 I i 1 I i l i l i i l i l i I I I f I I I I I I I I I I I i i I I I' i 1 I I i l i ! 1 i l i i i l i I i I l i i i i ld i i
---il i
i i
~~~
i i l i i i l i I I I I I I I i 1 1 I I I I I i 1 l l 1 1 I I I I I i 1 i i l i i l I I i i __ I fgj____4 hi____j h4____j fgI _} ghi____Ijh4___ _I__ l i i i i i i I i l I i i l i i i i< l 1 i l i l I i l 1 I I i i i i i l l I I I I I I I I i l 1 1 I I I i i I 1 1 ,, w i I I I I I i 1 i k$ ---lkxh---h lIll - l Et---- 1 -i i -i i i lM$h--l !$! ----i-i i i i i i -i i i i i i i i i l __j ____y__ __ __ __4____y 4___ 4____1____1____j____1____.p____j_. i i i i i s i i x i l, i i i i i i i i l i iYi i 9s i __4____4j gj .___4 g 4___ j g .1____1 gp____1 g:gy__ l l I I I I I i i 1 1 1 1 -i i i i i- I
. 1 I I I I I i 1 I I I -l i I I I i 1 1 I i w I 1 x i I'fw l_ l i I I I I I Y l ,
I lQ.gI 1 Q. j i 1 -g:.g7 I I l l 6.765 l l 5.1 3 l 4 985 l 01 03 05 07 09 11 13 15 17- 19 21 23 25 27 29 31 33 35 37 39 41 43 45. 47 49 51 I 48
, a. o .
7.0 CONCLUSION
S The purpose of this benchmark was to show that the MICBURN 3/CASMO 3/ FABLES-3/ SIMULATE-3 code package is suitable for all applications approved in Reference 1, for applications involving new fuel designs and for applications involving low power and low flow conditions. The VY model has an overall hot eigenvalue of 0.9999 with a standard deviation of 10.0012. The cold eigenvalue is 0.9971 with a standard deviation of i0.0022. The eigenvalue for the low power and low flow conditions is 1.0000 i0.0023. The VY model produces nodal instrument readings which have an RMS error of 2.0%. The Pilgrim mc. del has an overall hot eigenvalue of 0.9997 with a standard deviation of i0.0021. The cold eigenvalue is 1.0026 with a standard deviation of i0.0025. The Pilgrim model produces nodal instrument readings which have an RMS error of 5.1%. These results show that the model has good overall agreement compared to the plant and is suitable for use for all applications approved in Reference 1, for applications involving new fuel designs and for applications involving low power and low flow conditions. 4 49
e e o .
8.0 REFERENCES
- 1. Wochlke, R. A., et al., MICBURN-3/CASMO-3rrABLES-3/ SIMULATE-3 Duchmarking of Vermont Yankee Cveles 9 through 13, YAEC 1683-A, March, 1989.
- 2. Ahlin, A., et al., hilCBURN Microscopic Burnun in Burnable Absorber Rods.
Studsvik/NFA/26, dated November,1986. (Proprietary)
- 3. DiGiovine, A. S., et al., CASMO-3G Validation, YAEC-1363-A, April,1988.
- 4. Edentius, M., et al., CASMO-3. A Fuel Assembly Purnup Program. Studsvik/NFA-86/7, dated November 1986. (Proprietary) 5 ' VerPlanck, D. M., et al., TABLES-3P Library Preparation Code for SIMULATE-3P, Studsvik/SOA-88/02, dated February,1988. (Proprietary)
- 6. DiGiovine, A. S., et al., McGuire Unit 2 SIMULATE-3 Benchmark Analvsis Cveles 1 throuch 3. YAEC-1608, dated October 1987.
- 7. VerPlanck, D. M., et al., SIMULATE-3P Advanced Three. Dimensional Two-Grcup Reactor Analysis Code. Studsvik/SOA - 88/01, dated February,1988.
- 8. DiGiovine, A. S., et al., SIMULATE-3 Validation and Verification, YAEC-1659-A, dated September 1988.
- 9. _Geeral Electric Standard Application for Reactor Fuel (GESTARII), NEDE-24011-P-A-9, GE Proprietary, February 1988, as amended.
- 10. Ansari, A. A. F., Methods for the Analysis ofl] oiling Water Reatters Steady-State Core Flow Distribution Code (FIBWRt YAEC-1234, December 1980,
- 11. Ansari, A. A. F., et al., FIBWR* A Steady-State Core Flow Distribution Code for Boiling Water Reactors - Code Verification <nd Oualification Reoort, EPRI NP-1923, Project 1754-1 Final Report, July 1981.
- 12. Lellouche, G. S. and Zolotar, B. A., Mechanistic Model for Predicting Two-Phase Void Fraction for Water in Vertical Tubes Channels. and Rod Bundles, EPRI NP-2246-SR, February,1982.
- 13. Schultz, S. P. and St. John, K. E., Methods for the Analysis of Oxide Fuel Rod Steady-State Thermal Effects (FROSSTEYT Code /Model Descrintion Manual.
YAEC-1249P, April 1981. 50
. ~ -- -.-. - - .- -.- - -.-..- -.__- - - . . - - . . *o . e I
- 14. Schultz, S. P. and St. John, K. R., Methods for the Analysis of Oxide Fuel Steadv-State Thermal Effects (FROSSTEY) Code Oualification and Anplication, YAEC-1265P, June 1981.
- 15. Letter and SER, USNRC to R. W. Capstick, " Approval of Use of Fuel Performance Code FROSSTEY." NVY 85 205, September 27,1985.
- 16. Sironen, M. A., et al., Vermont Yankee Ovele 8 Summary Report, YAEC-1305, August 1982.
- 17. VerPlanck, D. M., Methods for the Analysis of Boiling Water Reactors Steady State
! Core Physics, YAEC-1238, March 1981.
- 18. Pilat, E. E., Methods for the Analysis of Boiling Water Reactors Lattice Physiss, ,
YAEC-1232, December 1980, i
- 19. USNRC Letter to J. B. Sinclair, SER, " Acceptance for Referencing in Licensing Actions for the Vermont Yankee Plant of Reports: YAEC-1232, YAEC-1238, YAEC-1239P, YAEC-1299P, and YAEC-1234," NVY 82-157, September 15,1982.
f .
- 20. Dean, D. W., et al., Oualification of Reactor Physics Methods for Application to j Monticello, NSP-NAD-8609-A, Rev. 3, October 1995.
l 21. Larsen, N.H., et al., Core Design and Ooerating Data for Cycles 1 and 2 of Ouad Cites 1.EPRI NP-240, November 1976.
- 22. Tennessee Valley Authority, Verification of TVA Steady-State BWR Physics
] Methods, TVA-TR79-01, January 1979. J l i i i \ 51
. . O e APPENDIX A 110T DEPLETION STATEPOINTS Figure A.1 shows the reload design for the beginning of Cycle 10. The map is shown in color as well as with a numeric value. The oldest fuel is represented by the number 1 '
and the newest fuel is represented by the highest number. Figure A.2 shows the plant power versus exposure for Cycle 10. The statepoints where TIP data set comparisons were made are indicated. The plant ran close to full capacity at all times, so most -4 statepoints are near full power, except during coastdown. Figure A-3 shows the rod inventory for the cycle with the modeled statepoints indicated. The statepoints are evenly distributed among A and B sequences. Finally, Figure A.4 provides the reactor conditions at the comparison statepoints. Also shown are the additional depletion steps where no comparisons to TIP data (LPRM Calibrations) were made. Figures A.5-A.8 provide similar information for Cycle 11. Figures A 9-A.12 for Cycle 12, Figures A.13-A.16 for Cycle B, Figures A.17-A.20 for Cycle 14, Figures A.21-A.24 for Cycle 15, Figures A.25-A.28 for Cycle 16, Figures A.19-A.22 for Cycle 17, Figures A.23- A.26 for Cycle 18, and Figures A.27-A.30 for Cycle 19. 9 A-1
)
Figure A.1 g Reload Design of Vermont Yankee Cycle 10
/ North l
f l l ia i !M i M M as I" !~ l to l .. l sa la I j ,. h H l
.4
! 1 l*- i
.1 es M et es it i3 14 17 se at 33 at 27 29 31 33 as 37 se 41 43 Key S8%I O '-
' - " ~
L e .. . a _ .. m- . a - ,. . # A2 L ._ _ _ _ _ _ _ _ . . . . . _ . - _ _ _ . - _ - - _ - . - . _ . _ . - - _ - - _ _ _ _ _ _ . _ - . _ . - - - . - . - - . -- .---- . - - - - - - - - - - - .
VERMONT YfNKEE CYCLE 10 DAILY AVE CORE THERNAL POWER VS.~DATE AND EXPOSURE 3,
+a LPMt CfLIBlWitIONS 11 SED IN SI!1ULATC 1600 - p, pppg gg 1 ;, y p. , ;;;
pg e, p -;,; h [ + V 'P'k 1500 - , li 1400 - - 5 4 1300 - -
}
1200 - I , ( 1100 - - 5
~
S 1000 - - 2
< m 5 n- .
& 5
> e n- -
5 E w y z m o a-700 - [ y 600 - - ra 500 - d a- . - y w 300 - g
. . g n_ .
g-ts x 100 - . 0- . . .. . . . . . . '. . . . . . . . . . . . . . . . . . . 1 is 28 8 iS 2f to 24 f 21 - 8 19 2 le 20 14 28 11 28 8 22 1 21 4 le 2 to 33 "13 2r JUN JUL AUG SEP OCT NOV DEC J8N FEB MP.R APR t1AY JLN 1983 1984 0 1000 20b0 3000 40'0 0 5000 6000 7000 7342 800 - JUN 17, 1983 CYCLE EXPOSURE (MHD/ST) E00 - JUN 15, 1984
o e #1 o FIGURE A.3
.ConitolEod Inventory of Cvele 10 Showinn TIP Statepoints
.h ~h
+
.g "h
+
' + ? *
- E .
.+ -
+ -
'. l 3
. E g * -
.g o
-8 . g
-3
.i .
. U + - ' ++ 2
~
+ E
+ '.g
, . .g
+ . .
+ .
- EE E -- 4 .
+
. . h Gi 'g . .Q. ~
+
+ !WW
- g..
- gg E -h
+ 8
+
n - _ g
, b . .@
. E G
+ ;::
006 o'r oIr ($1 0 .@ 03183SNI S3H310N 008 1081NO3 A-4
. . v .
FIGURE A.4 Reactor Conditions for Cvele 10 Depletion Skpl Step flP No. Date Itod l'attern l'owerlMWTh] FlowlMlbs/hr] ExposurelGWd/STl 1 777 06/29/83 Al-1, Deep @ 18 1590 46.7 .139 2 785 07/12/83 Al-1, Deep @ 18 1591 47.8 .387 3 786 07/26/83 Al-1, Deep @ l8 1592 46.9 .687 4 788 08/02/83 Al-1, Deep @ 18 1591 46.5 .841
, 5 789 08/l1/83 A1-1, Deep @ 16 1592 47.3 1.033 6 793 08/16/83 B2-1, D:ep @ 12 1591 44.5 1.129 7 794 08/24/83 B2-1, Deep @ 10 1592 46.6 1.302 8 803 09/06/83 B2-1, Deep @ 08 1590 46.0 1.539 9 804 09/14/83 B2-1, Deep @ 08 1588 46.5 1.707 10 805 09/21/83' B2-1, Deep @ 08 1590 46.0 1.857 I1 806 09/29/83 B2-1, Deep @ 06 1590 46.3 2.027 12 810 10/04/83 A2-1, Deep @ 04 1591 47.1 2.111 13 812 10/05/83 A2-1, Deep @ 04 1589 46.6 2.152 14 813 10/14/83 A2-1, Deep @ 04 1591 46.5 2.343 15 814 10/18/83 A2-1, Deep @ 08 1592 46,6 7.427 16 815 10/25/83 A2-1, Deep @ 04 1590 46.9 2.577 17 817 11/01/83 A2-1, Deep @ 00 1590 46.6 2.728 18 821 11/09/83 B1-1, Deep @ 10 1591 46.4 2.891 19 822 11/17/83 Bl-1, Deep @ 08 1591 47.2 3.062 20 823 11/22/83 B1-1, Deep @ 08 1591 47.0 3.168 21 824 12/05/83 B1-1, Deep @ 06 1591 46.9 3.451 22 826 12/08/83 B1-1, Deep @ 06 1591 46.8 3.539 23 827 12/12/83 B1-1, Deep @ 06 '592 46.6 3.601 24 831 12/20/83 A1-2, Deep @ 10 1590 46.9 3.759 25 832 12/28/83 Al-2, Deep @ 10 1593 47.3 3.931 26 834 01/04/84 Al-2, Deep @ 10 1590 47.4 4.085 A-5
, .. 4 .
FIGURE A.4 (Continued) Reactor Conditions for Cvele 10 Depletion Steps Step TIP No. Date Rod Pattern Power lMWThl Flow l Mibs /hr) Exposure lGWd/STl 27 840 01/10/84 Al-2, Deep @ 10 1587 45.5 4.163 28 841 01/19/84 Al-2, Deep @ 10 1588 46.0 4.359 29 849 02/03/84 B2-2, Deep @ 06 1591 46.1 4.585 30 851 02/07/84 B2-2, Deep @ 06 1592 46.6 4h69 31 853 02/14/84 B2-2, Deep @ 08 1588 46.0 4.819 32 855 02/28/84 B2 2, Deep @ 10 1593 45.8 5.117 33 859 03/06/84 A2-2, Deep @ 06 1588 47.2 5.239 34 861 03/15/84 A2-2, Deep @ 06 1591 46.5 5.446 35 863 03/28/84 A2-2, Deep @ 10 1592 46.4 5.704 36 864 04/04/84 A2-2, Deep @ 12 1591 46.8 5.871 . 37 866 04/10/84 A2-2, Deep @ 14 1592 46.7 6.003 38 872 04/24/84 B1-2, Deep @ 12 1591 46.7 6.259 39 874 05/01/84 B1-2, Deep @ l8 1590 46.2 6.407 40 875 05/04/84 B1-2, Deep @ 18 1588 46.9 6.473 41 877 05/08/84 B1-2, Deep @ 24 1590 46.2 6.553
'42 879 05/15/84 B1-2, Deep @ 30 1587 47.2 6.678 43 881 05/23/84 Bl-2, Deep @ 42 1573 48.0 6.870 44 882 05/30/84 B1-2, Deep @ 42 1538 47.7 7.015 45 884 06/06/84 ARO 1502 47.7 7.160 46 NoTIP 06/15/84 ARO to EOC 1457 48.0 7.343 A-6 1
w.m. mmm m m mmem,qm mm- - - - - - - - -- - = = = =
- l. o .
Reload Design of ermont Yankee Cycle 11 l / North i
~
I es 40 .. M M M D 10 I at H i a a is 10 . 14 13 19 et H H 68 1 1 b ** O "~
- - ~ ~ -
3 - e - .. .. . a- - e ---
FIGURE A.6 Power llistory of Cvele 11 Showing TIP Statepoints m )
. . . . . . . . . . . . . . ,, . m
.g .w mm m
- ' -=g w &
- ..g -
- ..=g a m
-x '8b
~ m
~
b
~
~"a i o - - .n g d- E '
88
- 2-- .
-=E
-. 8
- I w 8
= ay- c=
~
<w -nhot 8 ;;
w se -e 8R d -- a -=% > . E3 $- B f- -n -
-nl .8 a
~
~
g- -@ -
~
, g 2
-o -
7 -n m e 0- -u o
>;- n.
y C - by r
- o
~
-R , .8 Y h .
-Ek O3 g -
e<E -a $3 c
- g. +u .,
-,g ,
,8 - -=
"y to
+ -x +
c - ,. 3 m
'" ,8 3 d-c-
-x U ,8 o ,
c -
. -so- - e o
.e -R g
- r
-ch @
- 1
,.e -n s
'% .c8 o C ,o O-
- _ m
. . . . . . . . . . . . . . . . . i e 8
n a_e: 8 8 R_ a_ = 8 a_ a ~ a 8 a a 8 Ra8" - - (1MW) 83M0d A-8
o s # . f FIGURE A.7 ,i
- Control Rod inventGy of Cvele 11 Showing TIP Statepoints 4
W
$I.a
. . . .g
. .g
.H
-. ~ . ~ .... ............. ... . ... _ .... . .... 4 ; .
+ ~. 8
+ n .E 'g i
- h '
eo
+
M 4
> .- .T
. N N - h gb *
.f
+ .e
" + ',.
g
+ . y 'R E
+
_ _ _ _+ _
+ -g
+ g
- h
+ a a g;a 4 4 -
g a
+ , gI'g .N .
.g O tt **
- 6
;. . gaa 3 g.
;g a + s
- m. .
]
~ . + , .-
+ 1 g
* .R e *
- 2
?!
- E 0
"D
- 006 00C (XE 001 03183SNI S3H310N 008 1081N00 A.9
o . < . FIGURE A.8 Reactor Conditions for Cvele 11 DeplclwAS.ltp_s Step TIP No. Date Ibd Pattern Power lMWThl l' low lMlbs/htl l'xposurelGWd/STl 1 894 08/23/84 Power Ascent 1274 44.1 .174 2 895 09/04/84 Power Ascent 1272 44.3 .361 3 897 09/04/84 Power Ascent 1381 33.3 .413 4 898 09/14/84 Al-1, Deep @ 14 1519 46.8 .547 5 No TIP 09/18/94 Al-1, Deep @ 14 1519 46.8 .633 6 904 10/09/84 Al-1, Deep @ 14 1593 46.8 .773 7 907 10/18/84 Al-1, Deep @ 14 1590 46.6 .960 8 917 10/29/84 B2-1, Deep @ 06 1584 44.0 1.158 9 918 11/02/84 B2-1, Deep @ 06 1591 46.7 1.223 10 920 11/07/84 B2-1, Deep @ 06 1592 46.5 1.355 11 921 11/15/84 B2-1, Deep @ 04 1590 47.2 1.524 12 922 11/26/84 B21, Deep @ 04 1591 46.2 1.758 13 924 12/04/84 B2-1, Deep @ 00 1592 46.8 1.930 14 925 12/13/84 B2-1, Deep @ 00 1591 46.2 2.122 15 927 12/21/84 A2-1, Deep @ 04 1591 47.7 2.306 16 929 01/03/85 A2-1, Deep @ 06 1592 47.0 2.559 17 931 01/23/85 A2-1, Deep @ 04 1593 46.4 2.984 18 932 01/29/85 A2-1, Deep @ 04 1592 47.1 3.112 19 937 07/05/85 B1-1, Deep @ 10 1590 46.4 3.263 20 943 02/12/85 B1-1, Deep @ 10 1589 46.2 3.381 21 944 02/26/85 B1-1, Deep @ 10 1590 46.4 3.683 22 947 03/07/85 B1-1, Deep @ 10 1591 46.4 3.876 23 948 03/19/85 B1-1, Deep @ 10 1592 46.7 4.133 24 951 03/26/85 Al-2, Deep @ 12 1593 46.2 4.273 25 952 04/04/85 Al-2, Deep @ 12 1593 46.9 4.466 26 955 04/15/85 A1-2, Deep @ 12 1585 45.5 4.700 A-10
o , i FIGURE A.8 (Continued) Reactor Conditions for Cvele 11 Depletion StepJi Step TIP No. Date llod l'attern l'owerlMWTh] Flow lMlbs/hr] Exposure lGWd/STj 27 956 04/18/85 Al-2, Deep @ 12 1593 46.9 4.761 i 28 957 04/23/85 Al-2. Deep @ 14 1590 45.6 4.870 29 959 05/07/85 Al-2, Deep @ 16 1590 46.0 5.170 30 960 05/14/85 Al-2, Deep @ 18 1590 45.5 5.313 31 963 05/21/85 B2 2, Deep @ 10 1590 44.9 5.453 32 956 06/06/85 B2-2, Deep @ 14 1590 46.5 5.792 33 968 06/12/85 B2-2, Deep @ 24 389 44.4 5.920 34 971 06/19/85 B2-2, Deep @ 32 1592 45.4 6.063 35 974 07/02/85 ARO*, Deep @ 46 1583 47.6 6.342 36 975 07/17/85 ARO*, Deep @ 46 1529 47.7 6.650 37 976 08/08/85 ARO*, Deep @ 46 1430 47.7 7.104 38 978 08/21/85 ARO*, Deep @ 46 1372 47.6 7.279 39 980 09/03/85 ARO*, Deep @ 46 1326 47.8 7.571 40 981 09/19/85 ARO+, Deep @ 46 1261 47.7 7.842 41 No TIP 09/21/85 l ARO* to EOC 1260 48.0 7.865
'In Cycle 11, VY had a single rod " impeded" at 46; that is, it gave no settle indication at 48. The mirror symmetric rods were also driven to 46. Therefore, during coastdown, the model was nearly ARO.
A-11
I, s s .
\
I Figure A.9 - Reload Design of Vermont Yankee Cycle 12
- North L .. _
I u l H M N N u M It t9 - 14 1R 19 H ea M 0. I
., n . .7 ii ,, i. i7 .. n n a 7 a n n = n = a u l O
- " ~ ~
oi . o - ,. .. m - ,, . .... E - ,.. - # A 12 l i- - .. --. . . - _ _ . _ _ _ . . _ _ _ _ _ _
. . . - .. \
VERMONT YANKEE CYCLE 12 DAILY AVE CORE THERMAL P0HER VS. DATE AND EXPOSURE 3799 _,
+-trsift OfL18 RATIONS USED IN SIMULATE 1600 - , ; f,-s
,qt--c,;,-,',,y,,;.- :: ,
ea , - 1500 - - m
~. 9 1400- .
1300 - ,
- E m
3 o ' 1200 - 5 6 7 - 7 1100 - 9 - C 1000 - 2 - O2 21 c) 2 E 900 - j , g $ 800- , p 5 a_ 700 - 3 g L o i
~
600 -
- a
' N d. !
S00 - . cn 400 - E , 4 r 8 300 - - y
. ;;;- t 200 -
g 100 - - 1 0 , , , , . . . . ,, . . . . . . , . . . . . . . . . . . . . .,. , i IS 29 33 27 10 21 7 21 $ it 2 IS 30 14 28 Il 25 8 22 8 22 S 30 3 17 32 34 28 12 25 9 23 i JUN OUL AUG SEP OCT NOV DEC JAN FEB M8R f1PR HRY JUN JUL AUG 198S 1987
'O 1000 2000 3000 40hD .50'00 60b0 70'0 0 80b0 9000 !
BOC - JUN 30, 1986 CYCLE EXPOSURE (MHD/ST) E00 - AUG 31, 1987 l k
eo d e \ l FIGURE A.11 l 1 Control Rod Inventory of Cvele 12 Showing TIP Statenoints i l
<rr3
,-g .a f
ll.. -
....... ....... ._. . .. ................_........ 3..-
4
. 7 .g :
n -..... , M 6 :g .g . t
+ .
. ;g e .a 6
9 g y
. :p- = .R**-
+ -
~
- I d ._ .. :g
+ .
. i.. i i
* -us d
. ,.t._ , -- __ ; .g
.o .
.g
*W
+
b k
+ .
. .o "k 001 0 004 00C 00t -
03183SNI S3H310N 008 ~1081N00 I A-14
- o .
FIGl)Ri! A.12 Reactor Conditions for Cycle 12 Denletion Stens Step TIP No. Date Rod Pattern l'on er[MWThl Flow l Mibs /hrl ExposurelGWd/ST) 1 995 07/15/86 A2-1, Deep @ 12 1588 46.1 .163 2 996 07/24/86 A2-1, Deep @ 14 1581 45.6 .350 3 997 07/31/86 A21, Deep @ 12 1594 46.9 .500 4 999 08/12/86 A2-1, Deep @ l2 1590 45.6 .760 5 1002 09/05/86 A2-1, Deep @ 12 1591 45.2 1.262 6 1005 09/09/86 Bl 1, Deep @ 10 1589 46.4 1.342 7 1006 09/16/86 B1-1, Deep @ 10 1590 46.0 1.487 8 1007 09/17/86 B1-1, Deep @ 10 1592 46.0 1.521 9 1008 09/30/86 B1-1, Deep @ 10 1592 45.9 1.786 10 1017 10/10/86 Bl-1, Deep @ 10 1591 45.4 1.931 11 1018 10/16/86 BI-1, Deep @ 10 1590 45.0 2.055 12 1020 10/21/86 B1-1, Deep @ 10 1589 46.2 2.163 13 1021 10/39/86 B1-1, Deep @ 10 1588 47.0 2.352 14 1024 11/05/86 Al-1, Deep @ 12 1593 46.1 2.478 15 1026 11/13/86 Al-1, Deep @ 12 1593 46.8 2.645 16 1027 11/25/86 Al-1, Deep @ 12 1593 46.2 2.901 17 1029 12/04/86 Al-1, Deep @ 12 1592 46.7 3.096 18 1030 12/18/86 Al-1, Deep @ 12 1593 45.6 3.393 19 1033 12/23/86 B2-1, Deep @ 06 1589 46 ? 3.492 20 1034 01/02/87 B2-1, Deep @ 06 1592 45.7 3.705 21 1036 01/06/87 B2-1, Deep @ 04 1591 47.1 3.795 22 1037 01/20/87 B2-1, Deep @ 04 1591 46.8 4.094 23 1038 02/04/87 B2-1, Deep @ 04 1593 46.8 4.410 24 1043 02/10/87 A2-2, Deep @ 06 1591 45.9 4.538 25 1044 02/24/87 A2-2, Deep @ 06 1593 47.2 4.833 26 1046 03/03/87 A2-2, Deep @ 06 1591 45.6 4.984 A-15
lilGUIW A.12 (Continued) Reactor Conditions for Cycle 12 Depletion Stepj Step TII' No. l Date Rod l'attern l'owerlMWThl I'lowlMlbs/hr) Exposure lGWd/ST) 27 1047 03/11/87 A2 2, Deep @ 06 1592 46.7 5.150 28 1048- 03/17/87 A2 2, Deep @ 08 1591 46.9 5.278 29 1050 03/25/87 A2 2, Deep @ 08 1591 45.7 5.447 30 1052 04/01/87 A2 2, Deep @ 08 1591 46.8 5.601
'31 1063 04/14/87 B1-2, Deep @ 10 1593 46.8 5.850 32 1064 04/21/87 B1-2, Deep @ 14 1590 46.4 5.998 33 1066 04/28/87 B1-2, Deep @ 18 1591 46.1 6.150 34 1068 05/06/87 B1-2, Deep @ 24 1594 46.4 6.317
! 35 1072 05/13/87 Bl-2, Deep @ 40 1590 46.7 6.453 ! 36 1073 05/19/87 B1-2, Deep @ 40 1583 47.4 6.582 37 1074 05/26/87 B1-2, Deep @ 40 1557 47.4 6.735 38 1076 06/04/87 ARO 1526 48.0 6.920 , 39 1078 06/18/87 ARO l 1473 47.6 7.201 40 1079 07/01/87 ARO 1430 47.8 7.445 41 1081 07/09/87 ARO 1398 48.0 7.606 42 1082 07/28/87 ARO 1324 47.8 7.943 43 1083 08/06/87 ARO 1285 47.7 8.106 44 No TIP 08/07/87 ARO to EOC 1280 48.0 8.129 A-16 s
Figure A 13 Reload Design of Vermont Yankee Cycle 13
/ North a .-
43 H M M M i et M 38 r te !M as to la le 14 il 14 98 OG
- e. ..
43 l l A- BtM
*~
O n -,. a - ,, .. E - ,. o ._ , . ... # -"- A 17
-_. o VERMONT YANKEE CYCLE 13 DAILY RVE CORE THERMAL POWER VS. DATE AND EXPOSURE .
1700
+- tfftM CFLIBR8TIONS t! SED IN SIMULRTC
+ e^^** -
r (m 1600 - . , _ . . . . . . . ., r - - -
.j,
- m
- o 1500 -
( , 1400 - ( l - g 1300 -
- 6 1200 - 2 o
m 1100 -
$1 m5 H 1000 - o 3 - -
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=
o > o 700 - 5. A 0-2 . 600 - - O s00 - P p 400 - - 5 300 -
. 8 5.'
200 - 100 - 0 . , , . . . . . . . . 3 is a 22 m to 24 7 21 4 se 2 17 st 34 as 12 as e 2s 7 21 4 se 1 is an is sr so me a 22 s is 2 ss OCT NOV DEC JAN FEB MR P.PR 1988 MY JUN JUL BUG SEP OCT NOV DEC JRN FEB 1989 1987 , EOC - FEB 10, 1989 800 - OCT 2, 1987 CYCLE EXPOSURE (MWD /ST)
- . # . l l
FIGURE A.15 l Control Rod Inventory of Cycle 13 Showing TIP Statepoints i 3
.h
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.__________________________________________+. .
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s a a a 0 00S 00+ 000 003 001 0 03183SNI S3H010N 008 'lO81N00
- A
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FIGURE A.16 Reactor Conditions for Cycle 13 Depletion Steps Step TIP No. Date Rod Pattern Power lMWTh] FlowlMlb/hr] ExposurelGWd/ST) 1 1103 10/21/87 A2-1, Deep @ 18 1592 47.6 .284 2 1104 10/28/87 A2-1, Deep @ l8 1590 47.5 .434 3 1105 11/04/87 A2-1, Deep @ l8 1591 46.8 .582 4 1116 11/17/87 A21, Deep @ 16 1592 45.8 .793 5 1118 12/02/87 A21, Deep @ l6 1592 45.2 1.112 6 1123 12/09/87 B1-1, Deep @ 12 1591 45.7 1.253 7 1127 12/29/87 Bl-1, Deep @ 10 1591 45.9 1.675 8 1130 01/06/88 D1-1, Deep @ 08 1591 46.3 1.850 9 1131 01/12/88 B1-1, Deep @ 08 1593 45.8 1.975 10 1132 01/19/88 B1-1, Deep @ 08 1590 46.3 2.124 11 1134 01/28/88 B1-1, Deep @ 08 1589 44.9 2.316 12 1138 02/04/88 Al-1, Deep @ 12 1592 46.2 2.455 13 1140 02/09/88 Al-1, Deep @ 12 1592 45.4 2.560 14 1142 02/25/88 Al-1, Deep @ 10 1593 46.3 2.901 15 1144 03/08/88 Al-1, Deep @ 10 1592 46.6 3.159 16 1146 03/18/88 Al-1, Deep @ 10 1593 45.6 3.367 17 1151 03/25/88 B2-1, Deep @ 06 1592 46.4 3.505 18 1153 04/06/88 B2-1, Deep @ 04 1593 46.8 3.757 19 1155 04/19/88 B2-1, Deep @ 04 1592 46.0 4.036 20 1156 04/26/88 B2-1, Deep @ 00 1591 46.9 4.183 21 1161 05/10/88 A2-2, Deep @ l0 1593 46.6 4'.472 22 1163 05/13/88 A2-2, Deep @ 10 1591 46.5 4.541 23 1164 05/20/88 A2-2, Deep @ 10 1591 46.2 4.686 24 1165 05/26/88 A2-2, Deep @ 10 1593 46.1 4.812 3 1166 06/03/88 A2-2, Deep @ 10 1592 46.6 4.983 26 1174 06/23/88 A2-2, Deep @ 10 1590 46.0 5.386 A-20
__ _ _ _ _ . _ _ . _ - . . _ _ _ . _ _ _ _ _ _ . _ _ _ . ___.__m _ . _ _ _ _ . _ _ _ __ _ _ _ __ e e
' e 1
FIGURl! A.16 ' (Contitued) Reactor Conditions for Cycle 13 lhpletion Stepj Step Til' No. Date Itod !'atttrn l'owerlh1W1hl 110wl A11b/hrl bposurelGWd/STl 27 1193 07/22/88 B12, Deep @ 04 1592 46.7 5.655 28 1194 05/26/88 B12, Deep @ 06 1591 46.9 5.802 29 1197 08/02/88 B12, Deep @ 06 1586 46.0 S.868 30 1198 08/05/88 Bl.2, Deep @ 06 1595 46.6 5.951 31 1201 08/17/88 B12. Deep @ 08 1592 46.1 6.201 32 1202 08/23/88 Bl.2, Deep @ 08 1592 46.5 6.329 33 1213 09/02/88 A12, Deep @ 08 1589 45.9 6.441 34 1219 09/19/88 Al 2, Deep @ 10 1595 46.1 6.800 35 1220 09/27/88 Al-2, Deep @ 12 1590 45.4 6.965 36 1223 10/07/88 Al.2, Deep @ l2 1592 47.4 7.174
~
37 1225 10/11/88 Al-2, Deep @ l4 1591 46.3 7.258 38 1227 10/18/88 Al 2, Deep @ 16 1590 46 3 7.407 39 1228 10/25/88 Al-2, Deep @ 18 1591 45.9 7.556 40 1232 11/02/88 B2-2, Deep @ 16 1591 47.5 7J14 41 1234 11/08/88 B2 2, Deep @ l8 1590 46.3 7.841
~
42 1237 I1/15/88 B2 2, Deep @ 24 1591 46.1 7.989 43 1239 11/22/88 B2 2, Deep @ 38 1592 46.4 8.135 44 1240 11/29/88 B2 2, Deep @ 38 1584 48.0 8.285 45 1241 12/06/88 B2 2, Deep @ 40 1554 47.8 8.432 46 1242 12/13/88 B2-2, Deep @ 40 1525 47.8 8.574 47 1244 01/03/F9 B2-2, Deep @ 40 1442 - 47.8 8.993 48 1247 01/10/89 ARO 1413 47.8 9.126 49 1248 01/24/89 ARO 1362 47.6 9.386 50 1249 02/06/89 ARO 1315 47.7 9.618 51 1250 02/10/89 ARO 1299 47.6 9.688 52 No TIP 02/10/89 ARO to EOC 1299 47.6 9.694 A-21
., e .
Figure A 17 Reload Design of Vortnont Yankee Cycle 14
/ North = -
u . l N - l ._ - l w I L
~
e ' t. i
,8 m .. i M
N - m 08
- 6. -
0 '~ O
~~~
Q .. .. a .. _ m .. . E .. .~.. # A 22 L. .
y VERMONTYANKEE CYCLE 14 DAILY AVETHERMAL POWER vs DATE AND EXPOSURE s 1700 o= LPRM Cautradons Usedin SE4ULATE3 ~ 1600 - . p 6 e f. f. .: :. e,. : e +w :- : e. ::.- . 5-e > g 1500 - 1 = 1400 - c
- 3 4 1300 - .
s - o tt u 1200 - 12 g
^
d 7 g 1100 - ri
*I e 1000 -
l 9 --: 3 i 3 s E 900 - ^ 1, _C > c 2 M
!E 800 4 m h
" g y 6 l .5 E G- 700 - 8.
=
a 600 - , . q 500 - E2 400 - B 5. 300 - . = 5' 200 - 100 - . a e i & 4 4 4 4 4 4 4 .* 4 e 4 O &6444444i644444444444464 4 1 152913271024 8 22 5 19 2 1630143281125 9 23 6 20 3 17 3 173114281226 9 23 7 21 4 18 1 1529 APR MAY JUN JUL AUG SEP~ dCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP
' 1990 1989 b ib 2b 3b- 4b Sb 6000 7b 8 9 10 00 EOC- August 31,1990 BOC- Apdl8,1989 Cycle Exposure (MWD /ST)
+ o *.
1:1GU1111 A.19 Control Redlnyrntory of Cvele 14 Showing Til' Statepoints 8 O. v T"
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> . ** o I:lGUlt!! A.20 lleactor Conditions for Cycle 14 Deplclien,Sicp.s Step Til' No. Date Itod l'attern l'oneslMWIhl flow lMlbs/hrl EsposurelGWd/STl 1 1261 04/19/89 A21, Deep @ 20 1589 46.9 .175 2 1262 04/26/89 A21, Deep @ 20 1590 46.7 .326 , 3 1263 05/03/89 A21, Deep @ 20 1593 46.2 .476 4 1265 05/15/89 A21, Deep @ 18 1593 46.7 .738 5 1266 05/30/89 A2-1, Deep @ 16 1589 46.7 1.055 6 1271 06/08/89 B1-1, Deep @ 18 1473 38.5 l 1.253 l 7 1273 07/07/89 B1 1, Deep @ 16 1591 45.7 1.865 8 1279 07/13/89 B1-1, Deep @ 14 1594 46.3 1.983 9_ 1280 07/18/89 B1-1, Deep @ 14 1590 46.5 2.089 10 1281 07/?'/89 B1 1, Deep @ 14 1593 46.8 2.240 I1 1285 08/02/89 Al-1, Deep @ 12 1591 47.0 2.412 12 1286 08/15/89 Al-1, Deep @ 12 1593 45.7 2.687 13 1287 08/22/89 Al-1, Deep @ l2 1592 45.8 2.838 14 1288 09/05/89 A1-1, Deep @ 10 1592 46.2 3.142 15 1290 09/20/89 A1-1, Deep @ 10 1590 46.5 3.460 16 1293 09/26/89 B2-1, Deep @ 10 1592 46.6 3.582 17 1295 10/11/89 B21, Deep @ 08 1591 46.4 3.909 18 1296 10/31/89 B21, Deep @ 06 1591 47.0 4.333 19 1297 11/14/89 B21, Deep @ 06 1593 46.8 4.639 20 1305 11/29/89 A2-2, Deep @ 08 1593 46.9 4.936 21 1310- 12/13/89 A2-2, Deep @ 08 1592 44.3 5.231 22 1312 12/19/89 A2-2, Deep @ 08 1592 44.3 5.358 23 1314 01/03/90 A2-2, Deep @ 08 1590 44.2 5.678 24 1317 01/10/90 B1-2, Deep @ 04 1592 45.7 5.819 25 1320 01/30/90 B12, Deep @ 00 1588 45.0 6.250 26 1321 02/13/90 B1-2, Deep @ 00 1593 46.0 6.545 A-25
l I 1lGUltli A.20 (Continued) ' Itenetor Conditions for Cvele 14 Depletion Stepj Step Til' No. Date Rod !'attern l'ow erlMWThl Flow l Mibs /hri EsposurelGWd/STl { 27 1323 02/28/90 B12, Deep @ 04 1589 45.8 6.864 28 1325 03/07/90 B12, Deep @ 04 1591 46.5 7.016 29 No TIP 03/16/90 Al 2, Deep @ 06 1591 46.2 7.210 30 1330 04/04/90 Al 2, Deep @ 06 1591 46.2 7.416 31 1332 04/19/90 A12, Deep @ 10 1589 45.6 7,738
-32 1334 05/01/90 Al-2, Deep @ 12 1593 45.2-7.994 33 1335 05/15/90 Al 2, Deep @ 14 1592 45.8 8.291 34 1339 05/23/90 B2 2, Deep @ 12 1592 44.8 8.458 35 1345 06/20/90 B2 2, Deep @ 26 1590 45.7 9.005 36 No TlP 07/11/90 A2-3, Deep @ 36 1544 47.7 9.449 .
37 No TIP 07/25/90 A2-3, Deep @ 42 1491 47.6 9.730 38 No TIP 08/14/90 A2-3, Deep @ 42 1421 47.5 10.144 39 No TIP 08/31/90 A2-3, Deep @ 42 1410 48.0 10.448 A.26
I,, e . Figure A.21 , Reload Design of Vermont Yankee Cycle 15
/ North
,.. i i l" i 'N
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is t 1 l 1, 19 M N l l t a.- 1 O N Rossed ,. .DQba.e O 4efoed 4 30QRu. 3 Remed 14 .DQSM4 0 i. ow.3,i 9 Commien fr Chave A 27
VERMONTYANKEE CYCLE 15 DAILY AVETHERMAL POWER vs DATE AND EXPOSURE so 1700 o- LPFN CaRwallons Used in SIMtA. ATE-3 , 1600 - pp ge._ e e: e :e e - w ,
- : :: f ^e : : _
1500 - 3 a . 5 'O 15 1400 - 1300 - 13 2 12 6 1200 - '
=
1100 - , n o
^ 1000 - j b 2 4
m g
- 6 . 900 - .
c- n ~
> y 800 - [ h h .o 0- '
z
- 700 - -
I ? 600 - 1
=
3 m 500 - _.: Y 400 - m 16 @ o 300 -
- b 200 - g 100 - -
1 8 a 7 9 1 1? 0 4 6 # 4 4 4 e i 4 6 4 e e e i 6 4 4 4 t.4 4 6 6 6 6 6 4 4 6 4 4 4 4 6 4 4 1 152912261024 7 21 4 18 4 18 1 152913271024 8 22 5 19 2 163014281125 9 23 6 20 3 17 2 1630 OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR 1990 1991 1992 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 BOC - October 15,1990 Cycle Exposure (MWD /ST) EOC- March 7,1992 I
' * ' ' ' ' ' ' ' -' - " - ' - - - ' ' - - - ' ' ' - ' ' - - ' ' - ' ^ ' - ' - ' ' - ' ' - - ' - - ' ' ' ' '
oe # FIGUlm A.23
, Control llod Inventory of Cvele U Shnwing TII' Statepeinta 8
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> . o . FIGUIW A.24 Reactor Conditions for Cycle 15 Depletion Stens Step TIP No. Date Itod i'attern PowerlMWThl riowl Mibs /htl riposurelGWd/STl 1 1362 10/24/90 A21, Deep @ l2 1587 47.8 .130 2 1365 10/31/90 A21, Deep @ 18 1590 46 9 .281 3 1369 11/14/90 A21, Deep @ 16 1588 45.6 .553 4 1370 11/19/90 A21, Deep @ 12 1592 46.3 .658 5 1372 12/13/90 A21, Deep @ 10 1590 45.8 1.179 6 1375 12/20/90 Bl.), Deep @ 10 1586 45.3 1.308 7 1376 12/26/90 Bl 1, Deep @ 10 1588 45.4 1.437 8 1377 12/27/90 Bl.1, Deep @ 10 1589 45.3 1.462 9 1378 01/04/91 Bl.1, Deep @ l0 1591 46.1 1.633 10 1379 01/17/91 Bl.1, Deep @ 06 1594 46.5 1.920 11 1380 01/24/91 Bl 1, Deep @ 06 1591 45.1 2.067 12 1383 02/04/91 B21, Deep @ 08 1595 47.2 2.293 13 1385 02/20/91, B21, Deep @ 06 1593 46.1 2.642 14 1387 02/25/91 D21, Deep @ 08 1593 46.1 2.752 15 1388 03/04/91 D21, Deep @ 06 1592 46.3 2.910 16 No TIP 03/09/91 A1 1, Deep @ 06 1592 46.3 3.111 17 1394 03/28/91 Al-1, Deep @ 10 1591 47.3 3.324 18 1395 04/08/91 Al 1, Deep @ 10 1592 46.1 3.562 19 No TIP 04/23/91 Al 1, Deep @ 10 1592 46.1 3.892 20 1400 05/07/91 Al-1, Deep @ 08 1591 45.6 4.041 21 1404 05/22/91 A2 2, Deep @ 08 1592 45.3 4.355 22 1405 06/05/91 A2 2, Deep @ 06 1592 46,0 4.664 23 No TIP 06/15/91 A2 2, Deep @ 06 1592 46.0 4.884 24 1411 06/26/91 A2-2, Deep @ 06 1592 46.6 5.005 25 1412 07/10/91 A2-2, Deep @ 06 1589 47.2 5.310 26 1415 07/23/91 Dl-2, Deep @ 04 1593 46.8 5.591 A-30
8 > . o FIGURl! A.24 (Continued) Reagier Conditions for Cvele 15 Depletion Steps Step TIP No. Date Itod i'attern l'ow erlMWThl l~ low lMlbs/hrl 13posurelGWd/STl 27 1416 08/02/91 Bl-2, Deep @ 06 1592 45.6 5.807 28 1417 08/08/91 BI 2, Deep @ 06 1592 45.7 5.945 29 1421 09/04/91 B12, Deep @ 10 1590 46.6 6.525 (Center @00)* 30 No TIP 09/15/91 B1-2, Deep @ 10 1590 46.6 6.624 (Center @00)* 31 1424 09/18/91 B2-2, Deep @ 06 1595 45.9 6.685 32 1425 09/24/91 B2 2, Deep @ 06 1592 46.3 6.812 l 33 1428 10/11/91 B2 2, Deep @ 00 1593 46.9 7,184 l 34 1429 10/28/91 B2-2, Deep @ 04 1589 46.4 7.558 35 1431 11/01/91 B2-2, Deep @ 04 1589 46.5 8.073 36 1432 12/05/91 Al 2, Deep @ 12 1586 46.1 8.376 37 1435 01/14/92 Al-2, Deep @ 30 1591 47.8 9.243 (Center @00)* 38 1436 01/22/92 A12, Deep @ 30 1549 47.4 9.396 (Center @00)* ' 39 1437 02/04/92 A1-2, Deep @ 30 1486 47.5 9.665 (Center @00)* 40 1439 03/02/92 A1-2, Deep @ 30 1369 47.5 10.196 (Center @00)* 41 No TIP 03/06/92 A12, Deep @ 30 1353 47.7 10.273 (Center @00)* O Center rod inseded to reduce off gas from leaker. A 31
I, , s . Figure A.25 fieload Design of Vermont Yankee Cycle 16
/ North l
!= , W f. \- - t. ,1 i. M
~ .L l
l l 1 4 .. a .. : ! O ~ t. o v~
. _ , . . _ . m _ ,.. _ . g _ ,.. _ , m _ ,.. _ , e -' -
l
. 32 i
VERMONTYANKEE CYCLE 16 DAILY AVE THERMAL POWER vs DATE AND 2XPOSURE o 110 o= LPRM CaRwations Used in SIMULATE-3 . . 100 - 'e00 00t100 00 0 0' 0,'y 000 7 - - - - - - - - - 3 -1 m---- 3-3 8 > 5 12 13 g 7 90 - , , e 1 - o E ec - . 2 I _.
- o 70 - -
$ Q 1 o, l
-g 60 -
O m a 1 > e- 5 1- - C M Y '8 50 - m m a w c _ D 40 - 4 ' 6 =, N
$ im d
30 - m
- e 2 20 - +3 0
a 10 - to 14281226 9 23 7 21 4 18 1 152913271024 8 22 5 19 2 16 2 163013271125 8 22 6 20 3 1731 APR MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG 1992 1993 I I I I I I I I i f f 1doO 2doo 3doo 4dm 5doo odoo 7dm ed@ 9dM 108 @ 6 soc- A;$ril19,1992 Cycle Exposure (MWD /ST) EOC - August 28,1993
d . F10Ulm A.27 Canimi Rod Inventory of Cy!e 16 l'howing TIP Statenoints l 8 O e-T*
^
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FIGUllE A.28 3
- jigactor Conditions for Cycle 16 Denletion Sigp3 I
i Step TIP No. Date Rod Pattern Power lMWThl Flow lMlbs/hr) ExposurelGWd/STl
- 1 1444 04/28/92 A21, Deep @ 10 1590 46.9 .124
- 2 NoTIP 05/01/92 A21, Deep @ l0 1591 46.4 .188 l 3 No TIP 05/08/92 A21, Deep @ 10 -
1592 45.8 .343 4 1 4 1446 05/13/92 A21, Deep @ 10 1592 45.6 .457
- 5 No TIP 05/22/92 A21, Deep @ 08 1592 45.8 .652 6 No TIP 05/29/92 A21, Deep @ 10 1593 46.0 .807 i 7 No TIP 06/05/92 A21, Deep @ 08 1591 46.5 .961 8 No TlP 06/12/92 A21, Deep @ 06 1593 45.8 1.123 i
j 9 No TIP 06/18/92- B21, Deep @ 14 1592 45.5 1.239 ! 10 1448* 06/23/92 B21, Deep @ 12 1591 46.0 1.356 s L 11 No T!P 07/03/92 B2-1, Deep @ 10 1593 46.0 1.570 i j 12 1449' 07/09/92 B2-1 Deep @ 08 1593 46.3 1.710 j 13 No TIP 07/17/92 B21, Deep @ 10 1594 46.4 1.880 14 1450* 07/22/92 B2-1, Deep @ 08 1590 46.8 1.992 15 1452* 07/31/92 B21, Deep @ 08 1593 45.4 2.195 16 No TIP 08/07/92 B2-1, Deep @ 10 1593 45.5 2.344 l j 17 1453' 08/19/92 Al 1, Deep @ 10 1589 46,0 2.612 , 18 No TIP 08/28/92 Al 1, Deep @ 12 1588 46.0 2.804 1 19 No TIP 09/11/92 Al-1, Der.p @ 12 1595 45.0 3.113 20 No TIP 09/18/92 Al-1. Deep @ 10 1594 45.5 3.268 21 1455' 09/22/92 A'.-1, Deep'@ 10 1592 46.2 3.362 22 No TIP 10/02/92 A1-1, Deep @ 10 1594 46.2 3.584 23 NoTIP .10/14/92 Al-1, Deep @03 1593 45.8 3.849 24 1461* 10/22/92 B1-1, Deep @ 10 1591 45.2 3.998 25 No TIP 10/30/92 Bl-1, Deep @ 10 1590 46.3 4.176
*TIP machine "A" was inoperative.
A 35
,.--c-- - - . _ , . , - . - . . - - ,., , ..w,,..,r,., ,, -.y-,,m. , . . . . -,,r. . , -, , , , _ , _ - - . . , - - ~ ~ , - -
c ,-- -- -,
3 e o . FIGUltli A.28 (Continued) Ileactor Conditions for Cvele 16 Depletion Steps Step TIP No. Date Itod Pattern Power lMWThl FlowjMlbS/hr) 1:1posurelGWd/STl 26 No TIP 11/06/92 B1-1, Deep @ 10 1592 45.9 4.327 27 No TlP 11/20/92 Bl 1, Deep @ 10 1595 45.8 4.569 28 1462* 11/23/92 B1 1, Deep @ 10 1591 47.0 4.638 29 No TIP 12/04/92 B1-1, Deep @ 10 1593 46.1 4.879 30 No TlP 12/11/92 A2-2, Deep @ 08 1595 45.3 5.032 31 No TIP 12/18/92 A2 2, Deep @ 06 1592 46.2 5.187 32 1465* 12/22/92 A2 2, Deep @ 06 1590 45.7 5.277 33 1466* 12/24/92 A2-2, Deep @ 06 1591 45.7 5.323 34 1468* 12/30/92 A2-2, Deep @ 06 1593 46.0 5.456 35 No TIP 01/08/93 A2-2, Deep @ 04 1593 46.1 5.654 36 No TIP 01/15/93 A2 2, Deep @ 04 1592 45.8 5.813 37 1469* 01/26/93 A2-2, Deep @ 04 1592 45.9 6.050 38 , No TlP 02/08/93 A2-2, Deep @ 04 1591 47.3 6.335 39 1471* 02/12/93 B2-2, Deep @ 06 1592 46.9 6.423 40 No TIP 02/26/93 B2 2, Deep @ 06 1591 46.2 6.731 41 1412' 03/03/93 B2-2, Deep @ 06 1591 45.9 6.847 42 No TIP 03/12/93 B2 2, Deep @ 06 1593 46.4 7.040 43 No TlP 03/19/93 B2-2, Deep @ 06 1589 46.0 7.198 44 No TIP 03/26/93 B2-2, Deep @ 06 1593 46.8 7.349 45 1474* 03/29/93 B2-2, Deep @ 06 1593 46.0 7.418 46 No TIP 04/05/93 B2-2, Deep Q 06 1592 46.9 7.570 47 No TIP 04/07/93 B2-2, Deep @ 06 1592 46.9 7.6d3 48 1476 04/21/93 Al-2, Deep @ 10 1589 45.6 7.689 49 No TIP 04/30/93 Al-2, Deep @ 10 1590 47.6 7.885 50 No TIP 05/07/93 A1-2, Deep @ 12 1590 46.3 8.040 51 1477 05/11/93 Al-2, Deep @ l2 1591 45.4 8.132
*TlP machine "A" was inoperative.
A-36
3 , o e FIGlJilB A.28 (Continued) Reactor Conditions for Cyclg 16 Depletion Steps Step Til' No. Date Rod l'altern l'ow erlMWThl Flow lMlbs/hr) EsposurelGWd/STl I 52 No TIP 05/14/93 A12, Deep @ 12 1592 46.5 8.195 53 No TIP 05/21/93 Al 2, Deep @ 12 1592 46.4 8.349
$4 No TIP 05/28/93 Al 2, Deep @ 12 1591 46.9 8.504 55 1479 06/01/93 A12, Deep @ 12 1591 46.5 8.596 56 No TIP 06/04/93 A12, Deep @ 12 1592 47.4 8.658 57 1480 06/09/93 B12, Deep @ 10 1592 46.4 8.768 58 No TIP 06/18/93 B12, Deep @ 10 1591 45.9 8.965 59 No TIP 06/25/93 B1-2, Deep @ 10 1582 47.4 9.119 60 No TIP 07/02/93 B12, Deep @ 16 1592 45.0 9.272 61 No TIP 07/09/93 bl-2, Deep @ 16 1591 47.4 9.427 62 1484 07/15/93 B1-2, thep @ 32 1593 45.4 9.561 63 No TIP 07/23/93 Bl 2, Deep @ 32 1573 47.6 9.734 64 1485 08/02/93 B12, Deep @ 40 1524 47.4 9.952 65 No TIP 08/13/93 B12, Deep @ 40 1464 46.6 10.176 66 No TIP 08/27/93 Bl-2, Deep @ 40 1399 47.3 10.458 67 No TIP 08/28/93 B12, Deep @ 40 1399 47.3 10.461 *TIP machine "A" was inoperative.
A-37
je . I Figure A.20 Reload Design of Vermont Yankee Cycle 17 North i f as 4
.4 8 .I N
N N i- 1 l l l i.
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l 4 i 1. I i i a ._ i o-O -
*~~" ~
o-., e - ,. ._ Q ._. ,, .. . # ' A 38
9 y . VERMONTYANKEE CYCLE 17 0 DAILY AVE THERMAL. POWER vs DATE AND EXPOSURE . 1.1 1.0 -
;'s r : % -
i 1-
' I.
p, , T. I 0.9 i 14 15 y e 4 0 0.8i ) 10 h 3 3 E 5 0.7 : 5 13 m l 4 3 3 0.6 .: 8 2. O g il 1 C
# 3 4 5 0 .1 0.s 4 2 ; s ss O -
i 3 8 g 0.4 i
- i 9 d i . T i -
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. l 5 0.1 2
- LPRMCAUBRATIONS I
5 ti t2 0.0 ,, ,, . , , , , , , , , , , , , . , , . . , , , t . . . . . . . . . . . 1 152912261024 7 21 4 18 4 18 1 152913271024 8 22.%19 2 1630142S1125 9 23 6 20 3 173 17 oct Nov Dec Jan Feb Mar Apr Wy Jun Jul Aug Sep Oct Not Dec Jan Feb Mar 1993 1994 1995 0 1000 2000 3.00 4000 50G3 8000 7000 8000 9000 10000 BOC- October 24,1993 Cycle Espostme (MWWSt) EOC- March 17,1995
e , * * \ I!GUlm A.31 1 Control Rod Inventory of Cycle 17 Showing Til! Statep.cints a
-~
e
. ok 8 fi
.s 8 -8 -
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .R 2
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9 a S R R ' 03183SNI S3HO10N COU 70U1NOO A-40
o ., o . IlGUlm A.32 Reactor Conditions for Cyde 17 Deplclinn.Slcra Step *llP No. Date Hod l'attern Power [MWThl Flow [ Mibs /htl Esposure[GWd/STl 1 1491 11/02/93 A21, Deep @ 18 1591 47.3 .154 2 No TIP 11/15/93 A21, Deep @ l8 1593 46.8 .438 3 No TIP 11/19/93 A21, Deep @ 18 1591 46.5 .527 4 No TIP 11/26/93 A21, Deep @ l8 1592 46.6 .682 5 1492 12/01/93 A21, Deep @ l8 1591 46.7 .795 l 6 No TIP 12/06/93 A21, Deep @ l8 1591 46.3 .902 7 No TIP 12/06/93 A21, Deep @ 18 1591 46.3 .915 8 No TIP 12/31/93 A21, Deep @ 12 1592 45.7 1.162 9 1495 01/06/94 A2-1, Deep @ 10 1590 46.9 1.298 10 1496 01/t8/94 B2-1, Deep @ l6 1593 46.0 1.561 11 No TIP 01/28/94 B21, Deep @ 14 1592 45.9 1.779 12 No TIP 02/04/94 B21, Deep @ 12 1593 46.0 1.934 13 1498 02/16/94 B21, Deep @ 12 1591 46.6 2.190 14 No TIP 03/04/94 B2-1, Deep @ 10 1591 45.8 2.542 15 No TIP 03/11/94 B2-1, Deep @ 08 1590 45.8 2.696 16 1500 03/14/94 B2-1, Deep @ 06 1590 76.2 2.769 17 1501 03/21/94 Al-1, Deep @ 14 1590 46.7 2.914 18 No TIP 04/0lN4 Al-1. Deep @ 14 1594 45.6 3.151 19 No TIP 04/08/94 Al-1, Deep @ 14 1591 46.5 3.305 20 No TIP 04/15/94 A1-1, Deep @ 14 1594 46.4 3.408 21 No TIP 04/22/94 A1-1, Deep @ 14 1592
~
45.5 3.561 22 1504 05/03/94 A1-1, Deep @ 14 1593 45.9 3.812 23 No TIP 05/06/94 Al-1, Deep @ 14 1593 45.7 3.872-24 No TIP 05/16/94 A1-1, Deep @ 14 1594 46.1 4.094 25 No TIP 05/27/94 B1-1, Deep @ i0 1593 45.9 4.336 26 1505 05/31/94 B1-1, Deep @ 10 1591 46.4 4.431 A-41
i' l FIGURE A.32 i (Continued) Reactor Conditions for Cycle 17 Denletion Stens l Step Til' No. Date Itod i'attern l'ower[MWThl l'lonlMlbvhrl EsimurelGWd/STl ] l 27 No TIP 06/03/94 Bl 1, Deep @ 10 1589 45.9 4.494 l 28 No TIP 06/10/94 B1 1 Deep @ 10 1591 46.3 4.645 29 NoT1P 06/24/94 B1 1, Deep @ 10 1591 45.8 4.955 30 1507 06/28/94 B1-1, Deep @ 10 1592 46.9 5.046 ~ 31 No TIP 07/08/94 B1-1, Deep @ 10 1591 46.2 5.264 32 No TIP 07/18/94 B1-1, Deep @ 10 1592 46.4 5.485 33 No TIP 07/27/94 A2 2, Deep @ 08 1591 46.6 5.694 I 34 No TIP 07/29/94 A2 2, Deep @ 08 1431 36.9 5.723 35 No TIP 08/05/94 A2 2, Deep @ 08 1590 46.0 5.855 36 No TIP 08/08/94 A2-2, Deep @ 04 1592 46.4 5.921 37 1509 08/09/94 A2 2, Deep @ 04 l592 46.5 5.946 l 38 No TIP 08/26/94 A2 2, Deep @ 04 1591 46.5 6.319 4 39 No TIP 09/09/94 A2-2, Deep @ 04 1591 46.4 6.582
- 40 1511 09/13/94 A2-2, Deep @ 04 1589 46.5 6.677 41 No TIP 09/16/94 A2-2, Deep @ 04 1593 46.5 6.736 42 No TIP 09/23/94 A2-2, Deep @ 04 . 1590 47.0 6.891 l
9 No TIP 09/16/94 A2-2, Deep @ 08 1592 46.6 7.107 44 No TIP 10/25/94 B2-2, Deep @ 06 1591 46.0 7.273 i 45 '513 10/25/94 B2-2, Deep @ 08 1591 46.2 7.495 ;
- .s .
46 i No TIP 11/04/94 B2-2, Deep @ 10 1591 46.4 7.697 47 No TIP 11/09/94 B2 2, Deep @ 10 1592 46.1 7.807 48 No TIP 11/18/94 B2-2, Deep @ 10 1593 46.0 8.006 49 No TIP 11/25/94 B2-2, Deep @ 10 1592 46.9 8.161 50 1516 11/29/94 B2-2, Deep @ 12 1591 46.7 8.251 51 1519 12/05/94 A1-2, Deep @ 10 1593 45.6 8.387 52 No TlP 12/09/94 A1-2, Deep @ l0 1595 46.7 8.469 , A-42
3 ~ 0 . FIGUllE A.32 (Continued) lleactor Conditions for Cvele 17 Depletion Steps Step Tir No. Date Rod Pattern l'owerlMWThl Flow lMlbs/hrl Exposuse[GWd/ST) 53 No TIP 12/16/94 A12, Deep @ 10 1591 47.3 8.624 54 No TIP 12/23/94 Al 2, Deep @ 12 1592 46.2 8.778 55 No TIP 12/30/94 Al 2, Deep @ 12 1591 46.5 8.933 56 1520 01/03/95 Al 2, Deep @ 14 1592 45.5 9.028 57 No TIP 01/06/95 A1-2, Deep @ 14 1592 46.4 9.087 58 No TIP 01/13/95 Al-2, Deep @ 14 1593 47.5 9.242 59 No TIP 01/20/95 Al-2, Deep @ 16 1593 47.0 9.397 60 No TIP 01/27/95 Bl.2, Deep @ 12 1588 47.5 9.550 61 No TIP 02/03/95 B1-2, Deco @ 16 1590 46.8 9.705 62 No TIP 02/10/95 Bl-2, Deep @ 22 1593 46,4 9.859 63 1523 02/13/95 B1-2, Deep @ 28 1589 45.8 9.933 64 No TIP 02/17/95 Bl-2, Deep @ 28 1592 47.2 10.014 65 No TIP 02/22/95 B12, Deep @ 36 1566 47.4 10.167 66 No TIP 03/03/95 B12, Deep @ 44 1533 47.4 10.318 67 1525 03/06/95 ARO 1517 47.6 10.387 68 No TIP 03/13/95 ARO 1483 47.4 10.527 69 No TIP 03/17/95 ARO to EOC 1464 47.5 10.613 k A-43
^
[, ., Figure A.33 Reload Design of Vermont Yankee Cycle 18 j / North l l" l M
' .8 B.
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6 0 VERMONTYANKEE CYCLE 18
' DidLY AVE THERMAL POWER vs DATE AND EXPOSURE '
i.10 _ 1.00 :
- ,- 0:-
7 p; ., 3 4 '# T 0.90 h 8 s 2 s 7 , y a 0.80 ~ , _
=:
? 3
- :l is 2
IO 0.70 4: 22 j - a : o w@ 0.60 j a p' h
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0.40 i
- LPRMCALIBRATIONS 3 La
$ i 5.
- i 5
0.30 4 d
^
W 0.20 i G ' Di E *s i _. 0.10 4 = 5 0.00 ' , , ,. , , , , , , , , , , , , , , , , , , ,. , , , , , , , , , , , , , 2 163013271125 8 22 5 19 3 173114281226 9 23 6 20 5 19 2 163014281125 9 23 6 20 3 MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUGSEP 1995 1996 h 1000 2000 3h00 4h00 Sh00 Sh00 7000 8000 9000 10h00 BOC-May 2,1995 Cycle Exposure (MWD /ST) EOC- S6ptoiTher 6,1996
3 . 0 . FIOURE A.35 Control flod Inventory of Cycle 18 Showing Tll' Statenoluit a
> i. si := a er a >> 33 = 27 se si 42 1
Key' SFN r 0 - \ o---- D - - - g _ .,. . g ._ ,, .. e A-50
l l ! l 4 l i 1.1l. - - o &RM Calibrations 1.0 i m# 0 00 0 i Ii 1.0 I 0.9 i m j. t 5 4 0.8 I
~~
- g o
2 80.74 3 : o m - O : O : E E '< T c E 0.6 i 1 o 5; C
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W i 0.3 h ,g y i ' S. }
- 52.
i 0.24 E 0.1 '-E ! E 0.0 - ' 1 15 29 13 27 10 24 7 21 7 21 4 18 2 163013271125 8 22 5 19 3 173114281226 9 23 6 20 620 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 1996 1997 1998 i t 0 974 2005 3108 3568 BOC - 11/01/96 Cycle Exposure (mwd /St) Expected EOC -3/21/93 f
. - - - - _ . . . . . . _ - - . - . - - ~ . - - - _ - . . _ . - _ - . _ . - . - - - ~ . _ . . -
$ , 0 , FIGURE A 39 i Control Rod Inventory of Cycle 19 S}iowine TIP Statenoints , h b8 s a M . i!li g &
.g S -g g .: )6 Oh
< b b G :
o . W *o 02 %
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, o : h o 4 o . o ' .......,.........,,,,,,,,,,,,,,,,,,,,I,,,,,, ,I''''I''''3'' 'i''''gi . . . $ O o o o g a : 8 8 g g g g g g g G3183SNI S3HO10N 0081081NOO A-52 i
FIGURE A.40 Reactor Conditions for Cycle 19 Depletion Steps Step TIP No. Date Rod Pattern Power lMWTh] Exposure lGWd/ST) Flow lMlbs/hr] 1 No TIP 11/07/96 A2-1, Deep @ 12 1588 47.3 .072 2 1567 11/08/96 A2-1, Deep @ 12 1593 46.9 .100 3 No TIP 11/14/96 A2-1, Deep @ 14 1591 45.9 .230 4 1568 11/19/96 A21, Deep @ 14 1589 45.9 .344 5 1569 11/20/96 A2-1, Deep @ 14 1589 46.2 .368 6 No TIP 11/30/96 A2-1, Deep @ l4 1592 45.6 .597 7 No TIP 12/09/96 A2-1, Deep @ 12 1592 45.8 .773 8 No TIP 12/13/96 A2-1, Deep @ 12 1593 45.2 .861 9 1571 12/18/96 A2-1, Deep @ 12 '1591 46.2 .974 10 No TIP 12/27/96 A2-1, Deep @ 10 1592 46.2 1.169 11 No TIP 01/06/97 A2-1, Deep @ l0 1593 45.1 1.390
=
12 No TIP 01/09/97 B2-1, Deep @ 12 1592 45.5 1.455 13 , No TIP 01/14/97 B2-1, Deep @ 12 1590 45.4 1.565 14 1572 01/14/97 B2-1, Deep @ 12 1592 45.6 1.572 15 1574 01/23/97 B2-1, Deep @ 10 1592 45.9 1.768 16 No TIP 02/03/97 B2-1, Deep @ 10 1590 45.1 2.005 17 No TIP 02/10/97 B2-1, Deep @ 10 1591 45.3 2.159 18 No TIP 02/13/97 B2-1, Deep @ 10 1592 46.0 2.225 19 No TIP 02/17/97 B2-1, Deep @ 10 1592 45.6 2.314 20 No TIP 03/03/97 B2-1, Deep @ 08 1592 45.6 2.622 21 1577 03/05/97 B2-1, Deep @ 06 1592 46.2 2.671 22 No TIP 03/10/97 B2-1, Deep @ 06 1591 45.7 2.776 23 No TIP _ 03/14/97 A2-2, Deep @ 04 1592 47.3 2.863 24 1578 03/25/97 A2-2, Deep @ 04 1591 46.5 3.108 25 No TIP 03/31/97 A2-2, Deep @ 04 1593 45.9 3.238 26 No TIP 04/07/97 A2-2, Deep @ 04 1592 45.3 3.398 27 No TIP 04/15/97 A2-2, Deep @ 04 1591 45.4 3.568 A-53
- .- -. _.. - - - . . ~ .~.. - . . ... - , - _ . -. . - . , - _ ~ . ~ - - . . - . - -
1 APPENDIX B COLD CRITICAL STATEPOINTS 1 The following figures give the control rod pattems for the cold criticals performed at - V.Y during the period of the benchmark. Figure B.1 provides the cold critical patterns
-for Cycle 10. - _ Figures B.2 B.10 provides the same for Cycles 11 through 19, respectively. . Also provided are the reactor period, the temperature and the approximate hours of xenon, also lodine, promethium and samarium depletion at zero
. power which preceded the cold critical. In some instances, the time between scram and i
recovery was sufficiently short that failure to model the xenon depletion shifts the
- eigenvalue significantly.
i'
^
i 1 1 a 1 4 4 1 B-1
h,o :, FIGURE B.1 Vermont Yankee CvCle 10 Cold Critical Patterns
. CRITICAL PATTERN CRITICAL PATTERN 43 43 04 39 48 48 48 48 39 48 48 48 48 35 35 04 04 31 48 12 48 48 31 48 48 48 48 27 27 04 08 04 -23 48 48 48 48 48 48 23 48 48 48 48 48 48 19 18 04 04 04 15 48 48 48 15 48 48 48 48 11 11 04 04 07 48 48 48 48 07 48 48 48 48 m M g 02 06 10 14 18 22 26 30 34 38 42 02 06 10- 14 18 22 26 30 34 38 42 DATE: 5/2843 PERIOD:_ 2?ts_ees TEMP: 103 T XEN: 2018 hrs DATE: W1743 PERIOO: 75 eece TEMP: 189 V XEN: 2496 hrs CRITICAL PATTERN CRITICA:. PATTERN 43 10 43 39 48 48 48 48 39 48 48 48 48 33 10 10 35 31 48 48 48 48 31 48 12 48 48 27 10 12 10 27 23 48 48 48 48 48 48 23 48 48 48 48 48 48 19 10 10 12 18 15 48 48 48 48 15 48 48 48 -
11 11 10 10 07 43 43 43 43 07 43 48 48 43 03 12 03 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE: 1KGB4 PERIOO 120 sacs TEMP: 225Y XEN- 32 brs ' DATE: 6/19/84 PERIOO 100 secs TEMP: 126 T XEN: 75 hrs Notr A Blar* Dox Denotes Hod Posnion 00 B-2
(, o , FIGURE B.1 (Continued) Vermont Yankee Cvele 10 Cold Critical Patterns CRITICAL PATTERN CRITICAL PATTERN 43 43 l 39 48 48 48 39 35 04 35 31 43 43 43 43 43 31 27 04 27 23 48 48 48 48 48 23 19 g4 19 15 48 48 48 48 48 15 11 11 07 48 48 48 07 03 03 1 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE: MiW84 PERIOD 200 secs TEMP: 127Y XEN: 75 hrs DATE* PERIOO- nece TEMP
- T XEN hrs CRITICAL PATTERN CRITICAL PATTERN 43 43 39 39 35 35 31 31 27 27 23 23 19 19
. ' 15 15 11 11 07 07 03 03 02 06- 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE: PEnlOO- secs TEMP- T XEN: has DATER PERIOD- seca TEMP: T XEN- hrs Note: A Diar
- Box Derdes Rod Position oo B-3
l 1 FIGURE B.2 '
. Vermont Yankee Cvele 11 Cold Critical Pattems CRmCAL PATTERN CRmCAL PATTERN 43 43 39 48 48 48 48 39 48 48 48 48 35 35 31 48 48 31 48 1S 06 48 48 27 27 23 48 48 48 48 48 48 23 48 48 48 48 48 48 19 19 15 48 48 15 48 48 48 11 11
-07' 48 48 48 48 07 48 48 48 48 03 03
. i 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30. 34 38 42 DATE: 74744 PERIOD 160 sece TEMP: 94 Y XEN: 1008 hrs DATE: 806/84 PERIOD: 197sece TEMP: 161 Y XEN: 1248 tre CRmCAL PATTERN CRmCAL PATTERN 43 43 39 48 48 48 48 39 04 04 35 31 48 48 48 48 31 27 04 27 23 48 48 48 48 48 48 23 19 04 04 19 15 48 48 48 48 15 11 11 04 04 07 ' 48 48 48 48 07 M g M 02 06 10 14. 18 _22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE: 9GWB4 PERIOD 120 secs TEMP; 2277 XEN: 252 hrs DATE: PERIOO- seca TEMP: Y XEN: hrs Note: A DarA Su Denotes Rod Position 00 0-4
k.*. FIGURE B.3 Vermont Yankee CvCle 12 Cold Critical Patterns q CRITICAL PATTERN CRITICAL PATTERN 43 43 39 48 48 48 48 39 48 48 48 35 35 31 48 22 48 31 48 48 48 48 48 27 27 23 48 48 48 48 48 48 23 48 48 48 48 48 19 19 15 48 48 15 48 48 08 48 48 11 11 07 48 48 48 48 07 48 48 48 03 03 02 06 10 14 18 22 20 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE: 845m8 PERIOD: 185 sees TEMP: 83 Y XEN: 8168 hrs DATE: 6/3048 PERICO: 87 sece TEMP; 158Y XEN: 6768 hre CRITICAL PATTERN CRITICAL PATTERN 43 43
- 39 48 48 48 39 35 35 31 48 48 48 48 48 31
~27 27 23 48 48 48 48 48 23 19 19 15' 48 48 12 48 48 15 11 11 07 48 43 43 07 03 Da 02 06 10 14 18 22. 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE: 702/06 PERIOD: 118 secs TEMP: 165 T XEN: 6816 brs DATE: PERIOD: seca TEMP- T XEN: hra Nota: A DiarA Bor Denotes Rod Poslw oo B-5 i'
(,4 - FIGURE B,4 Vermont Yankee CvCle 13 Cold Critical Patterr 1 4 CRITICAL PATTERN CRITICAL PATTERN 43 43 39 48 48 48 48 39 48 48 48 48 35 35 31 48 48 31 48 10 48 27 27 23 48 48 48 12 48 23 48 48 48 48 48 48 19 19 15 48 48 15 48 48 11 11 07 48 48 48 48 07 48 48 48 48 m M e 2 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30: 34 38 42
- - DATE
- M727 PERIOO- 55 67 TEMP: 87 7 XEN: 480 two DATE:1_QO2/5_7 PERIOO: 72 eecs TEMP: 197 T XEN: 1344 hrs CRITICAL PATTERN CRITICAL PATTERN
- 43 ~ 43 39 48 48 48 39 48 48 48 48 l 33 35 31 48 48 48 31 48 08 48 48 48 27 27 23 48 48 14 48 23 48 48 48 48 48 48
, 19 19
- 15 48 48 48 48 15 48 48 48 11 11 07 ' 43 43 43 07 43 48 48 48 03 03 06 10 14 18 22 26 30 - 34 38 42 02- 06 to 14 18 22 26 30 34 38 42 DATE: 7/02/88 PERIOO- 70 secs.. TEMP
- 209 Y XEN 182 hrs DATE: 8/2fVB8 PERIOD: 142 secs TEMP: 228T XEN: 61 hrs _
Nott A Blar* Dox Denotes nod Posman 00 B-6
- b. * .
FIGURE B.4 (Continued) Vermont Yankee CvCle 13 Cold Critical Patterns CRITICAL PATTERN CRITICAL PATTERN
~43 43 39 48 48 48 48 39 35 35 31' 48 48 48 31 27 27 23 48 48 48 48 48 48 23-19 19 15 48 28 48 15 11 11 07- 48 48 48 48 07 03 03 02 06 10 14 18 22 26 30 34 38-42 02 06 10 14 18 22 26 30 34 38 42 -
DATE: a/2848 PERICO: 96 sara TEMP: 234 7 XEN: 100 hrs DATK- PERIOD- mece TEMP- T XEN: hre CRITICAL PATTERN CRlhlCAL PATTERN
. 43 ' 43 39 39 35 , 35 31 31 27 27
( 23 23 19 19 15 15 11 11
' 07 07 03 03 02 06 10 14 18 22 26 30 34 38 42 02 03 10 14 18 22 26 30 34 38 42
~ DATE: PERIOct secs TEMP: Y XEN: hrs DATE: _ PERIOO- secs TEMP: 7 XEN: hrs
- Note: A Blard Sox Denotes Rod Posmon 00 O*7
1 1 s q l FIGURE B.5 Vermont Yankee CvCle 14 Cold Critical Pattems j l l CRmCAL PATTEf 4N - CRmCAL PATTERN 3 43 43 I. 8 39 48 48 48 48 39 48 48 48 48 35 35 04 04 31 48 20 48 31 48 48 48 48 27 27 04 23 48 48 48 48 48 48 23 48- 48 48 48 48 48 19 19 04 04 15 48 48 15 48 48 48 48 i 11 11 04 i 1 07 48 48 48 48 07 48 48 48 48 m m g 02 06 -10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE: $U2/80 PERICO: 55 sece TEMP: 84 Y XEN. 456 hrs DATE: 40840 PERIOD 121 sece TEMP: 195T XEN: 1344 hrs CRmCAL PATTERN CRmCAL PATTERN 43 43 39 48 48 48 48 39 35 35 31 48 24 48 31
~ 27 27' 23 48 48 48 48 48 48 23 19 19 15 48 48 15 i 11 11 07 48 48 48 48 07 03 03 02 06 10 '14 18 22 26 30. 34 38 42 02 06 10 14 18 22 26 30 34 38- 42 DATE: lM21/90 PERIOD 185 sees TEMP: 226 Y XEN: 104 hrs DATE: PERIOD: secs TEMP: Y XEN: tus Note O Btar* Box Denotes Hod Position 00 6-8
. ~9 .
i l FIGURE B.6 l yermont Yankee CvCle 15 Cold CritlCal Pattems
- CRITICAL PATTERN CRITICAL PATTERN
- q. 43 12 43 12 39 48 48 48 48 39 48 48 48 48 35 12 12 35 12 12 l 31 - 48 48 48 48 31 48 48 48 48
$ 27 12 12 12 27 12 20 12 23 48 48 48 48 48 48 23 48 48 48 48 48 48 18 12 12 12 18 12 12 12 1 j 15 48 48 48 48 15 48 48 48 48 11 11 j 12 12 12 12 07 43 43 43 43 07 48 48 48 48 03 12 03 12 4 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42
! DATE:1&1040 PERIOD: 7$ secs TEMP: 1167 XEN: 000 hrs DATE:10r14s0 PERIOCk 192 seca TEMP: 20t T XEN: 1058 hrs l.
CRmCAL PATTERN CRITICAL PATTERN 43 08 43 10 39 48 48 48 48 39 48 49 48 48 35 10 10 35 10 10 31 48 48 48 48 31 48 48 48 48 27 08 10 08 27 10 10 10 23 48 48 48 48 48 48 23 48 48 48 49 48 48 18 08 10 18 10 10 10 10 15 48 48 48 48 15 48 48 48 48 11 11 08 08 10 10 07 48 48 48 48 07 48 48 48 48 03 10 03 jo
. l 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE: 3/17!91 PEritOO 95 secs TEMP: 224 T._ XEN- 78 hrs DATE: 3/18/91. PERIOCt 111 sees TEMP: 245Y XEN: 100 hrs Notr A Blar* Ebx Denotes Rod Posamn oo B-9
ks * -.- FIGURE B.6 (Continued) Vermont Yankee Ovele 15 Cold Critical Patterns CRmCAL PATTERN g CRITICAL PATTERN 43 06 43 06
-39 48 48 48 48 39 48 48 48 48 35 08 08 35 06 06 31 48 48 48 48 31 48 48 48 48 27 06 08 06 27 06 06 04 23 48 48 48 48 48 48 23 48 48 48 48 48 48 19 08 06 08 19 06 04 06 15 48 48 48 48 15 48 48 48 48 11 11 06 06 06 06 07 48 48 48 48 07 48 48 48 48 M- g M M 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 20 30 34 38 42 DATE: 4/XW91 PERIOD _242 eecs TEMP: 206V XEN: 156 hrs DATE: 8/HW91 PERIOD- 187 secs TEMP: 236V XEN: 112 hrs CRmCAL PATTERN CRmCAL FATTERN 43 04 04 43 39 48 48 48 39 35 04 04 35 31 48 40 48 48 48 31 27 04 04 08 04 27 23 48 48 48 48 48 23 10 04 04 04 04 19 15 - 48 48 48 48 48 15 11 11 04 04' 07 48 48 48 07 03 04 04 M 02 06 10 14- 18 22 26 30 34 38 42 - 02 06 10 14 18 22 26 30 34 38 42 DATE: 9/1441 PERIOD 500 secs TEMP: 101 T XEN; 144 hrs DATE: PERIOD- secs TEMP: T XEN: hrs
, Not3:A Diank Dox Demtes Rott Position oo G-10
FIGURE B.7 Vermont Yankee OvCle 16 Cold Critical Patterns CRITICAL PATTERN CRITICAL PATTERN 43 10 43 06 06 39 48 48 48 48 39 43 48 48 j 35 12 12 35 06 06 31 48 48 48 48 31 48 48 48 48 48 i ' 27 10 12 10 27 06 04 06 06 23 48 48 48 48 48 48 23 48 48 48 48 48 19-- 12 10 12 19 06 06 04 06
-15 48 48 48 48 15 48 48 48 48 48 11 l 11 10 10 06 06 5
4 07 48 48 48 48 07 48 48 48 03 12 03 06 06 02_ 06 10 14 18 22 26 30 34 38 42 02 06 to 14 18 22 26 30 34 38 42 _ DATE: #1692 PENOD:_77 secs TEMP: 162 V XEN: 1032 hrs DATE: #1643 PERICO: 134 secs TEMP: 220T XEN: 220 hrs CRmCAL PATTERN CRITICAL PATTERN 43 43 39 39 I 35 35
. 31 31 27 27 23 23 19 19 15 15 11 11 07 07 03 03
~
02 06 -10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE! PEROO- secs .TEMR Y XEN- hrs DATE! PERIOO: secs TEMP- T XEN: hrs Note: A Blank Dox Denotes Rod Posinon 00 6 11
N,
- s l l
l FIGURE B.8 Vermont Yankee CvCle 17 Cold Critical Patterns CRITICAL PATTERN CRITICAL PATTERN 43 43 08 39 48 48 48 48 39 48 48 48 48 35 35 08 08 31 48 48 48 31 48 48 48 48 27 27 08 10 08 23 48 48 48 48 48 48 23 48 48 48 48 48 48 19 18 08 08 10 15 48 28 48 15 48 48 48 48 , 11 11 - 08 08 07 48 48 48 48 07 48 48 48 48 03 M og 02 06 10 14 18 22 26 30 34 38 42 02 06 to 14 18 22 20 30 34 38 42 DATE:167441 PERIOD: 275 sees TEMPL158 Y XEN: 13r:a hrs, DATE:12/12M3 PERIOD: 120 sees TEMP: 198 Y XEN:__1_36 hrs CRITICAL PATTERN CRITICAL PATTERN 43 08 43 39 48 48 48 48 30 4 33 08 08 35 31 48 48 48 48 31 27 08 10 08 27 - 23_ _ 48 as 48 48 48 48 23 19 08 08 08 19
-15 48 40 48 48 15 11 'l 09 08 07 43 48 48 43 07 03 08 03 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 CATE:12!?0/93 PERIOO 207 secs TEMPQ001 XEN: 316 brs DATE: _ PERIOD- secs TEMP- T XEN: hrs
- Note: A Blar* Bou Denotes Rod Posite 00 0-12
..__...._m.. _._._. _ - _ _.__.- _ _ _ -
FIGURE B 9 Vermont Yankee Cvele 18 Cold Critical Pattems ! I CRmCAL PATTERN CRmCAL PATTER 4 43 43 39 48 48 48 48 39' I , 35 35 31 48 18 48 48 31 27 27 1 23 48 48 48 48 48 48 23 19 19 I 15 48 48 48 15 11 11 07 /,8 48 48 48 07
'03 03 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE: SAMUD6 PERIOD: 80 eece TEMP: 136 V XEN: ItN twa DATE: PERIOD- sece TEMP: 7 XEN- hre CRmCAL PATTERN CRmCAL PATTERN -43 43 39 39 35 35 31 31 '
- 27 27.,j 23 23
-19 19 15' 33 11 11- - 07 07 03 03 02 06 10 14 -18. 22 26 30 34 38 d2 02 06 10 14 18 22 26 30 34 38 42 DATE:- PERIO0e secs TEMP: Y XEN: tus DATE _ PERIOD- secs TEMP: T XEN- hrs Not3:A Blank Dox Denotes Rod Position oo B-13
FIGURE B 10 Vermont Yankee Cvele 19 Cold Critical Pattems CRITICAL PATTERN CRITICAL PATTERN 43 43 1 39 48 48 48 48 39 , 35 35 31 48 16 48 48 31 i 27 27 _ 23 48 48 48 48 48 48 23 19 19 . 15 48 48 48 15
~
- .11 11 07 48 48 48 48 07 j 03 03
- ' 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 DATE
- WJW96 PERIOD: 165 sece TEM *: 151 Y XC 4: 1298 two DATE! PERIOD- esco TE R 7 XEN: hre i .
- . CRITICAL PATTERN CRITICAL PATTERN I
s
. 43 43 l ,
39' 39 35 35 31 31 27 27 23 '- 23 19 19 15 15
~
11 11
'07 07 03 03 I
l I 02 06 10 - 18 22 26 -30 34 38 42 02 06 10 14 18 22 26 30 34 42 DATE L PERIOO- secs TEMP: Y XEN: tws DATE: PERIOO- secs TEMP- *
.F XEN: hrs
~ Nott: d Diari Box Denotes Rod Position oo B-14 1
C . 1 4 APPENDIX C HOT MODEL-TO-PLANT DETECTOR COMPARISONS Integrated TIP readings were created at each of the 20 instrument locations by adding up the 24 normalized nodal readings for each individual string. The resulting integral reading for the given string is proportional to the relative reactor power in the four adjacent assemblies. By comparing the SIMULATE-3 integrated TIP readings to the plant integrated TIP readings, maps present the radial differences by cycle. Similarly, the TIP readings may be integrated for axial planes of the core. The resulting reading is proportional to the relative power in the given plane of the core. The SIMULATE-3 core average (planar) TIP readings are then compared to the plant core average (planar)TIP readings.
"Ihis appendix presents the plant to model comparisons for each cycle. For Cycle 10, Figure C.1 shows the average error and standard deviation in the TIP integrals at each location. Note: percent error is ahvays defined as 100* ((Model Plant)/ Plant). Figure C. I also shows the RMS error in the TIP integrals at each location. Figure C.2 shows the core average axial TIPS for the model (lines) compared to the plant (A). The axially averaged TIPS are rhown for each TIP set modeled in the Cycle 10 depletior.. The order of the TIP sets can be identified by either the TIP set number or the cycle exposure.
Figums C.3 and C.4 present similar information for Cycle 11. Figures C.5 and C.6 for Cycle 12. Figures C.7 and C.8 for Cycle 13. Figures C.9 and C.10 for Cycle 14. Figures C.ll and C.12 for Cycle 15. Figures C,13 and C.14 for Cycle 16. Figures C.15 and C.16 : for Cycle 17. Figures C.17 and C.18 for Cycle 18. Figures C.19 and C.20 for Cycle 19. It should be noted that the "A" TIP machine was broken for much of Cycle 16, therefore, only a few TIP comparisons ate provided. C-1 i i I
( ,
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N,' . j 1 FIGURE C.3 Vermont Yankee Cycle 11 Averaged TIP Integral Errors, Standard Deviations, and RMS Errors i KEY (in %): Average Difference 44 l l l Standard Deviation
...i.. ...l... ...l... RMS Difference 42 - l l l 40 l , , .
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e _
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. *o nGURE C.
SIMULA1E 31{,ojoraces Avor ed Axiaj ' P Plarit 1racgca .ored Traces iparg
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FIG RE Cote Avor Axiz '4TIP Tracce i SIMULATE 3 TIP Tracea mparo bp Plant floasuredTraces 1 ago 30 o 1 1 i j j
~:[3 u :_ . ,
= l n 3:-:... . .
r-1cf : /!3 ('.; h L l :( ; 3 i $
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4 > . e FIGURE C SIMULATE 3 TII'oto 1 races Aver ed AsiPlant rnpara . IP Measured Traces Traces age 4 of pg. ( ,.a, r - s.mm 4,. o, [:![:.
>.<e 5 S i d- Ed B[.::E_- : ::} ><=l m ~ :
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p f"' y y e g e al C 12
) 4 . obihil Trac SIMULATE.311kIio racos Avorko i pg3rgp go [)lant f}casured Traces e w i 1
-e o
e e w o I"
.'4 m
e 9* w 4 x 8
~
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=Ma -+= L.= .
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p ,
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. p .. ...
g . - e al C-13
N . FIGURE C.5 Vermont Yankee Cycle 12 Averaged TIP Integral Errors, Standard Dovlations, and RMS Errors KEY (in %): ! Average Difference
- : : Standard Deviation
. . . l. . . . . . l. . . . . . l. . . RMS Difference i ,-
i ,i , ,i , . .i l
. i i i i i ,
-@ l l
- l l a l l @ l 4 i . i i i , , , ,
b!$!, i
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i i i
. . . :. . . . . . :. . . . . . :. . . . . . l. . .
I st I I t t i i l i i i 1 g e i i i i .i . . . i. . i , , ,
...l... ...:... . . . :. . . . . . :. . ...:... ...:... . . . :. . .
,! N ,! ! $d !
. . . l. . . . . . l. . . . . . :. . . . . . :. . . . . . :. . . . . . l. . . . . . :. . . . . . . . . . . . . . .
. . i
, i, , i, i, i, i
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. i i i i i i i i l @ l l = l l
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. . .:. . . . . . l. . . ......
- $'$ !i i i ! 'N .
i -!. ' NE. i i i i i i i i i 1 1 1 4 , 4 i 1
..:... ...l...
i i i i i I 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 C.14
v .
,o p<e3 m-QCpmE O S_
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- _ e10 0 0 riI 7 ci' ny 900 giiW Ii 60 1- - 4 lp 1 IiI?.
yMI .
- n. 91 1 M_
n910 - - - 21 i e _ _ - - - - D !L ,N rF 4 2 s 2 9 0 0 1 0 0 9 1 1 .. 9 ' e .. a lc y P Y C W I T W i e e k n . a Y t n e o m r
- e e
V i a t s d S t ,N t ,3
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H 9 9 1 - N H1 e
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i cO cp i 7 5 5 9 9 9 9 9 9 i P W I T W a i e T N Ae Lm i Ps A-QaO'
( % FIGURE C > C ed Axial P Traces SIMULATE 3'lil'1racos ore Avernpared Plarit ideasured Traces ago 2 of Q gb id g (:]' .d n- - _ M 8sg gb d ang 9h] al q- .- : 4
.a .
n- ~ m=
. . A u- -
p y.em . p ....... .
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+5x+ -
b) $T"i ! 9 l - 5'r ,!=>k! .! ' !m - S$g
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u 5- +r , +s . m4+ s.s BE4c>:d' ga! a -
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l
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b g# r 0 "Ii gF re-r g 6 g'r.--.65t i- i a j'yrj'r,. ] P/q-e "m < m :1_' gg E -rm -= a' i i 1 ss. a 4 I; gg. 3'- 's <Ij
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giirj i fji _ _ g.t. _
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- a. =', 5
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=
6
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<l C-10
FIGURE C. > Coro Avor ed Axia P Traces SIMULAT E 3 Tile itaces npare Plant rdoasured Traces ago 30
$a '
[fIJ -
~
]
))g m;* g [._)
C y ~: C- $j~ n r-a- > - 7 lxil IEu 8
~
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23 1B 3-e I i
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. . .; r n-14;1.Y . a-a q. u- -
6 5 . a k .. k ..
. k ..
e k -
<l C
FIGU' Core Avera ed A'E C 6xial11P f racce SIMULATE 3 TIP 1 races mpared to Plant floasured Traces
>ago 4 of 6 f -_:: :
g .-, g .,7 5 : 1 3- 8E:: ..:1. 1 2- g 7 -
- . b5 5E EtE.1~]
w a-] .OE: :z-- o: E] d eE:LLi: .] a_ - ._ .. sc ul. - y p ys',- -
~
f- fl h
./
h se WD
, g g g . .. g., g __s g -
s.a
-l- g:
a i- : ag
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. z
=:
. i au V:
af
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g.
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gk-t "~t'd ad gl - - -
-l sl es gI 44i gl as e: .
; =
; : sa- a .
3 , as ;
; : sa. -
Li' _i Li' _
! ! A- !
k / n b [ O e IR -
<l C-18
- a FIGUI o Averac od i . Trac SIMULA1E 311 racos pare )lant casured Traces 5o N E 4 g 5 .. _
- r. :.]
b_.._4 $l s : ss 2 #- - Eigqq _ E
~
p
.e 4
4 9
- 9 se Aquwied El's MI'S A--
3~~~ 5 Se $ - ~ l m El i 2l SS
#- E!
! 51 -
5 E!
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, G I p -
k 3C . u - b 6 sus msg gum
, , 22 , , $s 5, ,
g: : gg g: ; g ge- ----- -a g 2l- _ k . p -
=
28 -
<l C-19 -. . . ,- .. . .
FIGURE C.7 Vermont Yankoo Cycle 13 Averaged TIP Integral Errors, Standard Deviations, and RMS Errors KEY (in %): Average Ditforonce ) : : l Standard Deviation
. . l. . . ..8... . . . l. . . RMS Differenco
) : -~)Nl
, l 'al$ ! l l
)
. . . l. . .
i i i i i , i
@ l l
- l l = l l @ l
) i i i i i i i i t
. . . :. . . ...l... . . . :. . . . . . :. . . . . . :. . . ...:... . . . :. . .
) !'2$$"!.
! 'h$$i !
I
!si i
i i i k! i
!i 1
...l...1
. . . :. . . .........l...
1 1 I i 4 i I 4 l et t t
.t -
.t .t .I .i .t .t
- i i .
I i i i e i 4 1 i i I
. . . l. . . . . . :. . . . . .:. : . . . . . . .
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l i
, $[! , ! e3 !
I i !M! i , ! 'h$$ ! i i
. . . :. . . .........l... . . . :. . . . . . :. . .
i i i i i i I ,i i 1 I 1 i t t I s( l
* @N 1 1 e i . . . l .t .~, I .
1 I i i i i i i l i I
!d!
i i
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i i
,i .. ..
! 'M !
i i
! d6 !
i
...i... . . . . . . . ......
i
!N i
i i i i i , i i l i l I i i i I l @ l l 3 l l
- l l @ l l 4 I I i i l i I 4
$$ ! i
! IN! !
i i
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i i 1 1
.. .. ...l... ...l... ...l... . . .l. . . . .l. . . . . .l. . .
4 I i 1 4 4 i ; 1 i l 4 I i 1 - I l t I i 9 l 4 6 4 1 1 i
-...l... ...f... . . .l. . .
I t i I i i t i 1 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 C-20
) , FIGURE C.8 Coro Avera ed Axia TIP Traces SIMULATE 3 TIP 1 races npar to Plant rdcasured Traces age 1 0 3j r 4-4 %8
$ i b-M i' j. P g 7 :. g, g i : 1
- g. -
.'g E4: o :
- ] B3 E-g[j- = 3
-'] m
=g 6E~.
' '2 l S$-
4 gj . f; f>t. E
- . - 8:
_jg_ _ s- a B j, -
,<#y _
E h
/p n
? g y g -. __ g g g J J 2~ g_ =;: :#: 2 g- . . J g - gl . , q .
] e ug 91__1, s
e u.j gl .. .
+ 1 mg
_j 4.4.c4 '
.t 1
- u. -
= .: _ " h g .
f ..
& 6 & / 6 e E
x 1 \ : e
~
g , g rT , g rT g - -
,! 2 g, .! .;-,-l,.-
2 g ! - - gb m_._ 7.3 mg u- 3. : =.m :
; 3 gj g F.!,+,r1 2l g
_:..:,p - u- - - i
' ~
f
~
p.Ils 9 hi - aI C-21
* -e FIGURE C.
SIMULATE 3 TIgogo Aver d Axial _ tacos i pgrg ' plant P Tracgcasured Traces r Ir r 5 "R-tu : p i o r-deg_ g-v g-a Q 4 tu. g .. bpqcc -
, .: . . i ap:F - - ' >
#u 4_ .
8 8L: 2
' A+,5-4 i i km% 2 gg e< . . ! ..'i_j i 1 -
- (' g 1'
~
- t'gt- g _
_l's j-m a v l
', b 3 d "- S ,o E g, E
- n. ,: -
I___ra._ - [____ __..w-+ p g__ .- 4 - d,_ al " sv
- 8
;; s -
$-l -
m ij l
-> g ll 1 -
. " .i.-
saI - c ___
= t" _,
a '4' e s
} "
& b b &
s __:4_ j --
%-- " le . .-- .,-
. pg m
j .:
. s ;
el ; :c chi J J u- . .
-1
- a. . .
m ad a : al a . i
..g;;__ _
_j i 1- ______.T e F l *
- h _
al
- o2P g _ _ _ _ ,
- e FIGURE Coro Aver Axl . P Traces SIMULATE.3 TIP Traces pgrg Plant Measured Traces er ee :_
_- ,vm 1 .' 1 g 4._ .;,1 gl ,, .! . gl g ,
;jg gl as -
ge r - - -
; g g : __u-_ga t a gtr s .ru. a. u , r f,,;py , sa -
xg. ~ ~"~ s f --y 1 E E E
> S S . .
lgL... 27--
. . . 65.
E 57 gp u: :u g
. . 2.
8 . 7 j y _j gs , . . . j:: ,L g ..-
.-. .x x _
m 8 8 9
- a. n. . a. s _
l . . . _. . l
, .'9-l__4mm . . ., :
3
=. *, -
; e g
g! g! ;.;: : :! ! gl g gi :-: : :'.:g gl g
-; ; ;-t, ! _
n La.; . . nt__ ., . . E. R R g 6 . g - S S em I II - al C-23 -
,- 1 FIGunE i C i SIMULATE 3Tlf' ore Aver ltaces ed AxlPlant npare ' P Tracos MeasurodTraces 1 ago 4o 0 i
~
- . - 7 .
E 1- - -(( .. l
~:::Et3: $
- C g : ': C .1 ; t
- ce : 09s c :ce >n r -. . .: .
Pin 6,.:; i Q ll
- ty:r,: 5 o
{ h:;:- Ctcc .i . .
.l . i gg 4:3;p
- 'g:- -113:r .
B B 5 - 6 [. . - n S 4
?
_ i [ e m, e - - - e :::__
,i 1-t ....-.: g, g, :- :- :- .
, oh !, . . .
5,
.,. - .- --.- r 9 .:
my u g g .
...m_3 ag u -
.- p -
_3 a g a n , c -
& b & -
R _ ; [ g,
. . . . g -.i . . . . .
e ,l. yt. 5:
- eg ga g
y gg . .
- >=Q E
m
- a. . ,
7 x _ ' E- P - I
~
.. 9 .g S S 6 ,-.
W i .
/ -
h - i C
..-..-24' .- ..., - . .. . - . . , . . ,, - .. - ,- . - ... - . . _ , . -_..
4 # 1 I FIGURE ' Coro Avor SIMULATE 3 TIP 1 races >d Axi ipare . Plarit P 'Iracodeasured Traces ago $c, 0
$_ ]: @ c--
~
!).:; .
fill4;Ni] j f- N!!!N !] b el -
!, E !b'ij 4:13 Nj
~
h h e
- /"~'
[k - [ 3 4 4 4 HD GD psruiu a- =- im=
!. i 3 i 5 RI : .1 li i u
>)k u-iL--;4;-l >k u- RIIN~l >5],
2
. ~ : - - -,.+.. u- -
;i-- -i :i* -,
D B
~ B~
B f
~
f 8
~ ] / -
mpumaw gamm em D i . .. . . i hg a 5, . . . . , bg h o r-d d
! d
,' b M
bg - ~ gi
- - .r .:H .
,i ,n.
ng a-q: : .
..-.._--_+>
. :a ml u-g:
~
.i a ra,
=
.r1
.r, al u- -
--- --- aa ,
, ~< .
Ann 1sD h - al C-25 - . - - - . . . - - .
a e i IGURE C H Core Avet d /wia llP Traces SIMULAT E 3 llP leacos npare to Plant tjeasurod Traces 0 00 0 w op
=ad 4
- 1 l
~
1 "4 4.m qqq M a , e Ng g- ^ Ng h *
.E- -i g -
mg a-ge._
. x:--=:
._j_ mg n.
g[ j e s - l
.._ ~~::: -~ -
- ~- ,
M C $
~ ~
~ n
~
B
. f% h l
6 . e a 2 1
'h \
m.eM EMM'4 i , 2e Ir-q . .
! , 8, . . , 2- -
5: at_. 2l m n s: ca i mg . H . mg a
=m<.,,..
n- . : I a- ; I n -
""" w.. .,,,,.
2 - U V y 3 3 wum h .
\
C-26
FIGURE C.9 Vermont Yankee Cycle 14 Averaged TIP Integral Errors, Standard Deviations, and RMS Errors KEY (in 7.): Avorage Difference
; ; l Standard Deviation
. . .p . . ...t...
. . . l. . . RMS Difference i I l i
i i idI i tid ! l i i i i
. . . l. . . .........p..
i
...p.....p.. ...p.. ...l...
i i i . . .
--@ l l
- l l .". l l @- l ,
f i 1 l i i i l
...p.. ...p..
1
...p.. . . . l. . . . . . l. . . . . . l. . . ...p.. ...l... . . .p . .
l d! I i
$! l
...p........ . . . l. . . . . . p . . ...p......
!- 3 !
i i
! dN ! ~
l I
...p........ . . . l. . .
l I i i l i l i i 1 1 Jt i i t i i i i ~~ i i i I i i i\ l l 6 l 1 1 1 1 i i l i l i
...p..
1
. . . l. . . . . .p . . ...p.. . . .p . . ...p.. . . . l. . . ...p.. . . .p . . ...p.. ...p..
~
1 1 8 1 1 2 4 i i 4 1 i 83 l .'
. . . l. . . . . .p . . ......
...p.... p.. .........l... . . .p . . . . .p . . . . . l. . . . . . l. . .
i l i l 1 i l i i l i i 1 i i t t I ; I i
* @ i, >
4 . t i i I i 1 .I . 1 I i 1 i l i l 1 i 1
. . .p . . . . .p . . . . . l. . . ...... . . .p . . ...p.. . . .p . . . . . l. . . l. . .. .. ..l... . ...p..
id !
...p..
!i '1M i! !llll!
i
...p..
i
! [hh i i
. . .p . . .. p..
! l6 '
i
. . . l. . . . . . :. . . . . . l. . . . . . l. . . ...p..
l l i i , i i i i l @ l l b l l
- l l @ l l '
I i l i I I i l 1
. . . ;. . . ...... ...p.. . . .p . . . . . l. . . ...p.. ...... . . .p . . . . .p . .
Id ! i i
!-l$! i b M-!
i i
! !$b!
i i
. .p . . . . . l. . . . . . l. . . ...p.. .. . . l. . . ...p.. ...p..
i i i i i i i i i i 1 i l i i i l I
...t... . . , l. . .
. . . l. . .
i i i i i 1 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 C.27
o SIMULATE 3 Tik?i$a^c$,I 'N'"#ideasured ant Traces i e.y
. .1 5,144 ,..x,
,,- i,r '
e
~
~
-g g
2 iase
- 777
~
1 g l'tP . 1"j .. E 6
- 0 p.
e .- . f. _m _.._..4,__ ---7r - i- - i 3 i "i h;, j i i
" " '~' " "
- k . .
l ] ma fl ." - ."i; j ma i' -ti* _i b E E
> k .
'~
g __-; - g -.f;t y g ~7, , 5r-- "- " " "' g; =
=;]
i [.. 5i e
!> 5i "
"! > I!R g; -
=; - ;-
s - - = j $h *1 ; _ _ y;yy,q;; -- n-M 't * .l1' - R
- H E h- -
e 4 e al 4 C-28
e 6 to Ave SIMULATE I3agomparoc Th> 2 of 4 Traces heNxb YtP Traei}cas to Plant M p g n 0 r3: 7 g S ~.: , J3 j r e a! t gljg:r-H y !!i ! $a{.t:{jfsgti i5g$:i gil E E E a ** ** g ... g . . g , gh 6 ;:::-- g) gh _. s-E-4, l { g) j "
,'gem.,'_ ' ';-!_
gg ty l 'i '
"i ! p ' ' '
,,, am.r _e . ug. H,l . . . "i .]
. ,E _
@ ~::{::" 3.'tpIj 2;;"}j _
- e pq e 8
6- a < . 3 .< . 3 .< . j . 8 . ' E . * ' O E . 5 m __T 721 s c .i s . ,
>"U 8,.T}8, Q ~
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'I'; , b5 k<
> i 8( ep., i- r i
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; RS w'-a-if-3-J gg$ g 11
.'i "i gge 4' l a_n 33
'j- 4 7:- :-
ii .. : i
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u-jya 2 _
. ...* E. .,
p .- .
~
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j , C 29
n. SIMULATE 3 TNi$a^c$ I P[arEt f}easuredTraces Wsa 4
%w.4 g.
um Z E: 33, .M~ :! ..: >;,, i[ x z,
] mg a
yF.- a t:~
-i]
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g- 9[_,
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. , , , y
. o *
* =
e a j g eE
-it-
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=
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D Q k p k 3 . s - B
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og g,' , 1, S. ::q:c: U. m ,5%m :ct:c f E.
~~
se , %b;pp~y I s4 g I I I I-K J., k AJ ~ _
=
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a II - al C 30
. e SIMULATE 311hbo bh Avdh[ pare sured $ bracb..
races horn to$'I t Iage 4o 4 T races
~
Q l;4, x;il}d Cn ))l 88- ' a :
-..g. 4::3:
E _ h ..
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e S=a _..LL '.
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si -
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^h '- "i 5th 8g
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N H $ p p p g e e 23 - al C 31 _ , _ . _ . _ _
4 c e FIGURE C.11 - Vermont Yankee Cycle 15 Averaged TIP Integral Errors, Standard Deviations, and RMS Errors l-KEY (in %):
%verage Difference l l l Standard Deviation
. . . j. . . . . .p . . . . . l. . . RMS Difference i
1 i- 4 1 1
! 'ld!
i i i l l . . . :. . . . . . p . . . . .p . . . . .p . . . . .p . . . . .p . . . . . ;. . . i i 8 i i i i 11
@ l i
l l
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l
^ l i
l 1 3- l l l
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l -- l
! is !
$ i
!M!
8 i ! iM ! i
. . .p . . ...p.. . . .p . . . . .p . . . . . p . . . . .p . . . . .p . . . . .p . . . . .p . .
l l i l i 1 i l l l l t it t i l I i i i i i ** i g l 1 0 -l i l i l i 1 1 i i I ( l i l-
.. .p . . . . .p . . . . .p . . . . .p . . . . .p . . . . .p . . . . .p . . . . .p . . . . .p . . . . .p . . . . .p . .
!i ! l@ !
1 l
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1 4
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i l
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1 1
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. . .p . . . . .p . . . . .p . . . . .p . . . . . ;. . . . . .p . . . . .p . . . . .p . . . . .p . . ...p.....;...
l l l- l $ 1 l l' l l l t 1 8 i t i t i et t t i l i i
- i @ i l --
i i 1 i 8 i i
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4 I I l i
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1 4 i i l i i l i i l @ l l = l l
- l l @ l l l l l l l
...j...
4 8 1 1
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. . . l. . . . . .l. . . ... ..
..l...
'Id! l !l@'l i
!"[$ !
i l l I
. . .p . . . . .p . . ....... . . .p . . . . .p . . . . .p . . . . .;. . .
l l l l l + 0 1' I I I t i l 4 i 1 i I
...l... ...l...
i
. . .fi . .
i i i 1 01 03 05 07 09 11 13 15 17~ 19 21 23 25 27 - 29 31- 33 35 37 39 41 43-C 32 I
s e GIMULATEraces 3 Tik)io npared AvefhYkx to Plant afilP Tracf}casured Traces a00 l of 4
$ _- M r; @
I y_ 2hl: hc
$n '29:q'
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p . . /> p .. p .
~
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e 8 E. 2
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} ES a $[
s rl r. rl <_d - E gk x! r rl . l ))f M a I 3 o a. t__
.; ~
2 5 5 .. 5 6 - p .. P V f p p _ b -
? -
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l
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=
=; =;
- n. M =; =; =; g; : -- ;=; =; =; a
_I L1' 'll' - R- . R. R.. - 4 al C-33
-A4 + A. 8-'ha- - 44 4 _,-J4d.A._--.n-u2aa*-> -4_-p _AJ& 4 m-4 .1tm._4. Aam a A-__ <.-.a4. % -he-d h.-- J
--.----l-- h =h- --.--ame.A--m. 4=%__ ===_ e SIMULATE 3 TikkYako$ I" lint IOoasured Traces 1
i a - le 2, ti;E id@a -[lMaH
~
il:
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2 73.q =: .._
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h _ e - e k n h
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- 197 J Tm!
6 Eri:4Jil S ii3l,IiL 1 h9 9 6 r 97.9 959 5
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e21 C0 s a I 411 s n!11Mc --
+
5 r: 260 uOL i1 1 iI3I] 2! .
?0 780 m91 li 1 .1iIi I1 9 ,n! .
s !, 1 siI 991 l1 ,iiii IIi ii1I yII u!' '
;4I I1 2
9 7 s 3 3 3 4 4 1 . .* " 1 : 4 i
- s. 1 .
P P P .* T T T J
. i i
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- 3 Ii2 d : s 4 W e W !:I Nw4l n M94 W !.i.1.I3 W G vW V_
2 i n1 _ I G '- %6 G 1 io I r'1IIF:IlIr "" 4
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I 3 5 _ - .~ . a s 4IIia J1 e11 4 2" TIIl4' t 7 - ri 7 .4.; u 4 e ' s02 7 3 rr g* m-. I _ I" _ lp 9 E1 8 f n916 s . 9 9 1 e - D IEi F' I F. 5 5 2 3 3 1 4 4 3 1 4 l e . *
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1 1 i y c / ' . P P : P C T T T * .
.
- 4 e '
k e - n l a Y t n { o m r 6 e V 4 t I1j S' d _ se t ' t s 3i_ W m. .i n ,M
~
u - e : 4 W W E40 w . . vW - G-14hw4'h. 1 IIgI]14I1J t 4 G . 8 .1 1 o%2 I,:I . 5 5 TII4IeiI%,Ii1L. 9 J0 4 8 4 68 r6.9 9 G 2 1 mW1~ . .
..ig I
4 9 & TC IW af p0 1 c s. s.: ' 7
.p o79 96 W as
[ _
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4 99 I p[ , 1
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P . P P T T T 4 4 4 4 T N As Le 6
*s a-a oc* 3 l 1Il
- e 4
FIGURE C.13 Vorrnont Yankee Cycle 10 Averaged TIP Integral Errors, Standard Deviations: and RMS Errors KEY (in %): Average Difference 44 ,i Standard Deviation l l
...i... ... ..
RMS Difference 48 . . . ,l. . . l l 40 l , , l
. . .p . . . . .p . . . . .p . . . . .p . . . . .p . . . . .p . . . . .p . .
se , , i , , i ,
@ l l -* l l .'s l l @ l se i i i i .
...p.. . . .p . . . . .p . . . . .p . . ...p.. . . .p . . . . .p . . ...l... ...l...
32 - ! 'N l
. . .p . . . . .p . . . . . p . .
l ink! l 2N l l *$ l l 30
. . . l. . . . . .p . . . . .p . . . . .p . . . . .p . . . . .p . .
i i i , , , i et i t i f I 1 i i -- , g-IO i i , , .i ,. . i i i i i , , i i i
. . .p . . . . . l. . . . . .p . . . . . l. . . . . .p . . ...p.. . . .p . . . . .p . . . . .p . . . . .p . . ...l...
- 2 i
!i$!
i i i.3!- i
! l$ !
i i i!N!
. . .p . . ..p.. . . .p . . . . . l. . . . . . p . . . . . l. . . . . . p . . . . . p . . . . . l. . . . . .p . . . . .p . .
i !isd ! i i 22 , , , , , , ,
, i , ,
l l l
- l @ l l l 20 l .
l l l i i i i , i i i i i i
. . .p . . ...p.. . . .p . . ...... . . .p . . . . . l. . . ...p.. . . . l. . . . . .p . . . . .p . . . . .p . .
1 ! '$ !- i i I 10[ ! i i
! l$ !
i i
!M!
i 2 i bN' 14
...l...
i
. . .p . . . . . l. . . . . .p . . . . .;. . . . . .p . .
i i i . .
. . .p .
-i
. . .p . . . . .p . .
i
-i
; @ l 1 "- l l
- l l @ l ;
12 ,
. i i i i i i .
. . . l. . . . . .p . . ...p.. . . .p . . ...p.. . . .p . . . . . l. . . . . .p . . . . .p . .
*8-l 3
l iUIl l *$ l
. .p . . . . .p . . . . .p . . . .p . . . . . l. . . . . . p . . . . . l. . .
lik$hl Os - ,
-, i i i , i f i t i 1 04 .
l -l l 02
... .. ...t... . . .p . __
l l , i e i
' 01 03 05 07 09 11 13 15 ~17 -19 21 23 25 27 29 31 33 35 37 39 41 43 '
C 37
--_..._2_.___.._.- . , _ _ . . _ . _ , . _ , . ~ . _ . _ _ _ . _ . - - . . , . - -
s
- s Co SIMULATE-3 races f ago TIP mpare t o 1 ko Ave hbchxPa YlP Tracidea to Plant g .. : ._
5r: ;.E 8 - i 3 a E$"i$fE)
@h~zT.ZZ
~
f~r" $l tR 88,. 8[: g 6 --. .....
] 8 8g,: -
~.::i:_:- -
r _:__- . 4
\
c o . .! k S 8_ !; 2. : TM g - s aL. 2 xd RFN+H tg4 8{:Ka%*d g g ggE ie d e 4.,_q m** .1 ' ;f a ssh :; :34 a r ga 81 - 1 1 - i1 il '; 'i l-O LJ AL 1; _
$ 9 3
R g e 3 , b *
. b h _
n g . _ E - PO
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5 p :: - 3 5 - R 5 == == , 9. - nt S. . . . = ed -
,m.! :
aam afy . .. . . ses sg - s , , sae s 28 , ,F-a i--- i 'I _
= .
s ,# ' s .
- A e _
=
4 i, - C-38
J
% e s e a
1 FIGURE C.15 b ; Vermont Yankee Cyclo 17 ' _ Averaged TIP Integral Errors, Standard Dev.ations, and RMS Errors 4 4 a KEY (in %): Average Difference 44~ l l- l Standard Deviation '- - ' . . . . . . ' . . . - . .'_ . . RMS Differenw
'42 ,
1 40 . . I 1
> ;$l l 1 1 l '$ l
; 'e l I
i t i
. 38
. . .p . . ......... .. . . .p . . . .p . . . . _ l. . . ___p..
l . se i 3 l i l i
- l l ^l l @ l l- i l i i 1
. . . l. . . . . .p . . . . .p _ _ _ . . p . .. . . .p . . ...p.. . . .p . . . . .p . . . _;. . .
l $$ l
. . .p . . . . .p . . . . .p . .
l lMl I-
. . .p . .
l $ l$!
. . .p . . . . p _ _ . . .p . . . . .p . . . . .p . .
- l l 4 -l l l 4 I s( l i I i i t i s%
0 g .! E0 i i i .i i i 1 1 .I . l I I i i l I i p .
. . .p . . . _... . . .p . . . . .p . . . . .p . . ......
. . . l. . . . . .p . . ......
. . .p . . . . .p . .
!, l 'M !
1 ,
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1
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!l$,!
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. . _ . p . . . . _ l_ .
I l- 4 -l l 1 i l i t i i 1.
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- 20 . i i i i i i i . 1
,'* . . .p . . ......
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-l :.
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I 1'.1p0' I 8 I lb I 8
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i
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.02
. .p . . . . .p . . . . . l. .
I f I I t 4 9 4 - 01 03 .05 07 09' 11 - 13 15 17 -19 21 23 25 27 -29 31 33 35 37 39 41 43 h h i C-39
,, _ _ . . - . - , _ _ . , ._ , _ _ . ~ . -
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I
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FIGURE C,17. Vermont Yankee Cycle 18 Averaged TIP Integral Errors, Standard Deviations, and RMS Errors KEY (in %): Average Difference 44 l l Standard Deviation l 42
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C-42
6 SIMULATE-3 Thore AveTraces xaC1emparei Trac to Plant Neasured Traces Page 1 o 3 g r, a g m, e 3 - i
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efx SIMULATE-3 Tih.oro AveTraces IP Trace pare o Plant PIoasured Traces age 3o e 6 6 4 W e 4 4 a 6 C I *b
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e s 4 FIGURE C 19 ! Vermont Yankee Cycle 19 l Averaged TIP Integral Errors, Standard Deviations, and RMS Errors ! 4 KEY (in %): i Average Difference 44 l l l Standard Deviation , ...L. .._l_.. ..'... RMS Difference ^142
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t e e j eave kip TracNeasured Traces SIMULATE 3 Th Traces par to Plant age l o 1 g # mmm W mpp g: __,_c, . __ gm ._ pr 3'
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1 C-47
. . . , , , . m, ., -. _ . . . , - . -
e APPENDlX D l PILGRIM IIOT DEPLETION STATEPOINTS The TIP traces presented in this Appendix represent the traces where the plant conditions were at or close to equilibrium conditions. What follows is a description of each cycle and the depletion steps used to model it. Generally, the depletion was advanced on a weekly basis. The exception to this was the modeling of significant rod moves that may have occurred at intervals less than a week. The TIP trace conditions was explicitly modeled when the trace was taken. No comparison is made to plant data other than at TIP traces. Figure D.1 show the reload design for the beginning of Cycle 9. The number 1 indicates the oldest fuel. The fresh fuel is indicated by the highest number. Figure D.2 show the plant power versus exposure for Cycle 9. The statepoints where TIP data set comparisons were made are indicated. Figure D.3 shows the rod inventory for the l cycle with the modeled statepoints indicated. l Figures D.4-D.6 provide similar information for Cycle 10 and Figures D.7-D.9 for ! Cycle 11. I l 9 D-1
- i Figure D.1 Pilgrim Station Reload Design of Cycle 09 52 D D aG D D D D D D D D D D 50 -
uM D D D ,0 MM D. u D D M N 4a ' D D E D N M eM D D M D M D D M D.D D D E D E D eD N D D- M D M D E D a 04 D D
- o o o o rM D E N N 'O
.E M D D W D N N M D E M' D D 42 D D W D D D D E NA O M M D N M N O N D M8 0 N 00
@ & G 0 D M M D N D M D D D M D N N u 5 O M D D D E M N D
'48 D M U D M U M M M U M,N O U N M_ U M D M D M p U M D 36
lU o O O 49 @
U D D M N N D M G M D M M, M M .0 M D M D N D E N D D 34 H D M D N M N D E N N N N I D U M N NA O N N N D' M D G Q , Q l 32 B D N OO N D M D M M M M M M M M D E D .. N O M N D D l 30 N DG M D U D toM N M N M N O O N M N N N M D M U $1 0 N 28 e . 40 es.) t D E D N N N N D M N M D N N D E N N O N N N D D M S M N N U N N E N O M N M U N N,0 M N N U N N N N 0M N A - G O 24 5 0 M D 5 .D . M N M N M N D D N M N M N M D M D M'D D 22 B D H H Q N- D M U M M M M p@M M N D MW U N D M N Wp N
=G 20 0 W 0 0 M D U M N,D M N M N N N N M N M D N N N D M .D. FJ 18 N Q N M N N O t) N U D M M M M sM N M D N N N N 88 16 Dyl D D M D E D M D M N D D N N D M D M D M D D D D 14 0 ~N M M U N U $D N U M N N M D N 0M U N U M M N.D 12 - gg -DAO M D G N- @ @ - '
D B M N D M M D D M D D D 'O M D D 10 l D H E E D M S U D M N N N D N N M D E M S
~ B' 08 Q . Q 5 .O M D E D M D D N D M D M D M D D M D M U B U N N D D M B U U 0 8 8 D 04 EEb.D .N M D D *D D 0 M D* D D D U *D 04' -
D D NM D U U N N N N N D D i 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 61 D nonam a nomu A nonamaenonem D asanonem D ananomm (D-2) _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ ._ \
. ~ ~ .
PILGRIM STATION CYCLE 09 DAILY AVE CORE THERMAL POWER VS. DATE AND EXPOSURE 9 1.1 _
.1.04 cl 0 C 0 0 0 -- c 0 0 -
c e.- cr
= c 1 ~ 0.95 0.84 i
y0.7 g- :
-l 0.6 -j 3 C e -
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- i 0.2 -
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0.0 ~ , , , , , , ., , i., , ,, , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , i 1024 7 21 5 19 2 163014281125 8'22 7 21 4.18 2 163013271125 8 22 5 19 3 173114281226 9 23 6 20 6 20 3 k Aug Sep Oct Nov Dec 'Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 'Jan Feb Mar. Apr 1991 1992- ' 1993 i : : : : : : : : : 0 1059. 1901 3107 4121 4998 6053 7004 8077 8690' BOC - 8/14/91 Cycle Exposure (mwd /St) EOC - 4/03/93 i
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~
, , - o i j Figure D.4 Pilgrim Station Reload Design of Cycle 10 [ 62 s0 > 48 46 44 42 l 40 ! 38 36 ( 34 32 30 28 l 26 24 22 i 20 18 16 14 ! 12 10 De 02 l l ! l l } 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 1 E * *omm b useio== E as. o.m D as,w (D-5)
- . . . - . . - . . . - . - . . . - . . . . - . . .- ~.- ~.- . - .... .- .- . .- .. .. . . . -
- PILGRIM STATION CYCLE 10 C DAILY CORE AVE THERMAL POWER VS. DATE AND EXPOSURE- O:I
- . ~8L!
1.1 _ '
- i
^
1.0 'o ) > G- ; -e--- 4 0 ;- 0 -C 0- C 0.9 , ; i ! 5 ] 0.8 - , l b 3 Ei 0.7 E !
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- l b
O.1 i ! E 0.0 ~ , , , , , , , , , ,,,.,,,,_i,,,,,,,,,,,i,,,,,,,,,,,,,,,,,,, 25 8 22 6 20 3 173114281226 9 23 7 21 4 18 1 15 1 152912261024 7 21 5 19 2 163013271125 8 22 6 20 3 173114281428 ! t' MayJun Jul Aug Sep Oct Nov Dec - Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar ' 1993 1994 1995 - 0 954 2208 2954 4056 5019 6082 7061 7986 9011 i BOC - 5/30/93 Cycle Exposure (mwd /St) EOC -3/25/95 l
. . . . - . . . . . . - . ~ . - . .. . . . . . . . . - . - .
3f V'
?
O PILGRIM STATION CYCLE 10 i CONTROL ROD INVENTORY CURVE j 1000 .
? i i
900 -! E i i 800 4 i 0 . O o o w i. , 1 H-T 700 :- W : o o 6 u) : i 2- : ' m 600 w - 0 n l 9 h 5 6 ! N p : C I O 500 : ' m j z o i P o r O : [ 400 - o o J - O i $ o o oCo OC ooooo o . 0% o o oM o o oo *o oo ,oo , Oo 300 _
,o o o O 0 o '
i o
- E 200 i o STATEPOINTSUSEDINSIMULATE-3 i BOC-May 30,1993 oo o o l EOC- March 24,1995 ,0 o ;
g o 100 i o . E l O .. . O 1000 2000 '3000 4000 5000 6000 7000 8000 9000 { EXPOSURE (hAVd/St) ! 3 6/93 7/93 9S3 10/93 11/93 1/94 3/94 5/94 6/94 7/94 8/9412S 4 1/95 2S5 3/95 i
a 3 0 Figure D,7 Pilgrim Station Reload Design of Cycle 11 62 50 48 46 44 _ . 42 40 38 _ 36 3/ 32 30 26 26 24 22 a 18 16 14 12 _ 10 _ 08 _ 06 _ 04 - t 02 _ _ C1 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 <5 47 49 51 e ame.one. D: asse.omm B asi. amm. O asii, ,,uen (D-8)
~
PILGRIM STATION CYCLE 11' j V DAILY AVE CORE THERMAL POWER VS. DATE AND EXPOSl!RE . ; 8 1.1 _ 5 1.0 - 0 0 0- 0 0 0 - 5 0 0 -C 0-- e" O- - M p-0.9 - , E 6 j i I < i 0.8 -- l E - y 0.7 i O : 1 : J 3 t
-e : a ;
g g 0.6 i C b h ! I
- i
-o 30.5i ~
oo i
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b 0.3 i b [ 0.2 i 5 0.1 - - b , 0.0 - , , , , i i_i i i i i i. i i i i i e i i i i i i e i i e i a i i i e i i iiie i e i ! 1 152913271024 7 21 5 19 2 163014281125 8 22 7 21 4 18 2 163013271125 8 22 5 19 3 173114281226 9 23 6 20 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb 1995 1996 1997 l
+
0 976 1992 2965 .4147 4769 5423 6061 6843 7576 8442 9073 BOC - 6/01/95 Cycle Exposure (mwd /St) EOC - 3/01/97
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1: 3_- APPENDIX E COLD CRITICAL STATEPOINTS The following figures give the control rod patterns for the cold criticals modeled for Cycles 9-11. All criticals modeled are at beginning of cycle.
- Figure E,1 provides the cold critical pattern for Cycle 9. Figures E.2-E-3 provide the
- same for Cycles 10-11, respectively. Also provided are the approximate hours of
- shutdown that preceded the critical. This is to determine the need for the modeling of xeno'n depletion at zero power. . For the criticals modeled, no xenon depletion modeling was needed.
I i
\
E-1
.' 4 FIGURE E.1 Pilgrim Station Cycle 9 Cold Critical Pattern l 51 48 48 48 48 47 04 08 04 43 48 48 48 48 48 48 39 04 08 04 04 35 48 48 48 48 48 08 31 04 68 08 27 48 48 48 48 48 48 23 08 06 04 19 48 48 48 48 48 08 15 04 04 08 04 11 48 48 48 48 48 48 07 - 04 04 04 03 48 48 48 48 02 06 10 14 18 22 26 30 34 38 42 46 50 DATE: 08/11/91 PERIOD: 137.00 Sec TEMP: 180 F XE HRS > 1000 E-2
o' a FIGURE E.2 Pilgrim Station Cycle 10 Cold Critical Pattern i 51 48 48 48 48 47 08 08 08 43 48 48 48 48 48 48 39 08 12. 08 08 35 48 48 48 48 48 48 31 08 12 08 l 27 48 48 48 48 48 48 23 12 08 08 l 19 48 48 48 48 48 48 16 08 08 12 08 11 48 48 48 48 48 48 07 08 08 08 03 48 48 48 48 02 06 10 14 18 22 26 30 34 38 42 46 50 DATE: 05/28/93 PERIOD: 102.00 Sec TEMP: 185 F XE HRS > 1000 E-3
,1 9 FIGURE E.3 Pilgrim Station Cycle 11 Cold Critical Pattern l
51' ! 48 12 12 48 l 47 43 48 28 48 48 12 48 39 12 48 48 48 48 12 H 31 27 48 l 48 48 48 48 48 , 23 . 19 12 48 48 48 48 12 18 11 48 12 48 48 12 48 07 03' 48 12 12 48 02- 06 10 14 18 22 26 30- 34 38 42 46 50 DATE: 06/02/95 PERIOD: 208.50 Sec TEMP: 180 F XE HRS > 1000 E-4
) .. g. APPENDIX F PILGRIM HOT MODEL-TO-PLANT DETECTOR COMPARISONS This appendix presents the plant to model comparisons for each cycle. For Cycle 9, Figure F.1 shows the average error and standard deviation in the TIP integral at each location. - Figure F.1 alsa shows the RMS error in the.TIP integral at each location. Figure F.2 shows the core average axial TIPS for the model (lines) compared to the plant (A). The axially average TIPS are shown for each TIP set modeled in the Cycle 9 depletion. The order of the TIP sets can be identified by either the TIP set number or the ; cycle exposure. Figures F.3 and F.4 present similar information for Cycle 10. Figures F.5 and F.6 present the same for Cycle 11. 4 l k F-1
A y FIGURE F-1 Pilgrim Station Cycle 09 Averaged TIP Integral Errors, Standard Deviations, and RMS Errors KEY (in %): Average Difference 52 I I I I I I I
-_1___ _1_ _ ._1_ __ _1_ ___1____1--- _1 - - Standard Deviation RMS Difference i l 1 1 l l l 48 I I I I I I I I I i I i i l i ! I i 40 I I I i ! I I I I I n i I I t 1 I I I 44 1 1 I I l l I i l I i
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$2 i i l l l l l l Standard Deviation g 'l T -- RMS Differonce 48 I i i l l I I I l i I I i i i l I I
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