ML20127C657
| ML20127C657 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 07/31/1992 |
| From: | Chicots J, Meyer T, Munoz Frances Ramirez WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20127C650 | List: |
| References | |
| WCAP-13406, NUDOCS 9209100011 | |
| Download: ML20127C657 (61) | |
Text
{{#Wiki_filter:.. - ... . - . .. . 7 WESTINGHOUSE' PROPRIETARY-CLASS 3 WCAP-13406 HEATUP AND COOLDOWN LIMIT CURVES FOR NORMAL OPERATION FOR ZION UNITS ) & 2 M. A. Ramirez J. M. Chicots
-July 1992 Work Performed Under Shop Order CVPP-139 Prepared by Westinghouse Electric Corporation for the Commonwealth Edison Company i
Approved by: Mm 6) I i T. A. Mey;er, Manager Structural Reliability-& Plant Life Optimization WESTINGHOUSE-ELECTRIC CORPORATION Nublear and-Advanced Technology Division P.O. Box 355 Pittsburgh, Pennsylvania = 15230-0355
- 1992 W'estinghouse Electric Corporatior-All' Rights Reserved 9209100011 920901 PDR ADOCK 05000295 p- PDR
, _ _ . , _ . . . _ _ _..._..--, ..~ _.._._ .-._._..u;.-.-,-,..--.__,
t i 1 4 TABLE OFtCONTENTS I 4
- Section 11111 3 f391
- List of Tables 11-
) a List of Figures-i :- .iii :
- 1. Introduction
- 1
- 1. 2.
i Location and Identification of Beltline Region 1 Materials
- 3. Definition and Source of Material Properties for All Vessel Locations -
4~ i i 4. Fracture-Toughness Properties 4- !
- 5.
i- Criteria for Allowable Pressure-Temperature ' Relationships . 7 _6. Heatup and Cooldown Pressure-Temperature l'mit Curves i '10 s
- 7. Calculation of Adjusted Reference Temperatures 4 11 4
- ~
- 8. References t
40 i.
- 9. Appendix A : Data Points for Heatup.and Cooldown-o, Curves i
i-l i-i < i 5 g i t I' i l-
.. . . . . ~ . . . .. - _-- . - . -
LIST OF TABLES Iable lille P_Lqt
- 1. Materials Data From B&W Integrated Surveillance 5 Capsule Program Used In Developing Zion Units 1 and 2 Heatup and Cooldown Curves
- 2. Zion Unit 1 Reactor Vessel Toughness Table 6 (Unirradiated)
- 3. Zion Unit 2 Reactor Vessel Toughness Table 7 (Unirradiated)
- 4. Summary of Adjusted Reference Temperatures at 1/4T and 3/4T Locations of Zion Unit 1 Seltline 4
Region Materials for 14, 20, 25, and 32 EFPY 14
- 5. Summary of Adjusted Reference Temperatures at 4
1/4T and 3/4T Locations of Zion Unit 2 Beltline Region Materials for 14, 20, 25, and 32 EFPY 15
- 6. Calculation of Adjusted Reference Temperatures for the Limiting Reactor Vessel Material Bounding Zion Units 1 & 2 - Cire. Weld WF for 14 EFPY 16
- 7. Calculation of Adjusted Reference Temperatures for the Limiting Reactor Vessel Material Bounding Zion Units 1 & 2 - Cire. Weld WF for 20 EFPY 17
- 8. Calculation of Adjusted Reference Temperatures for the Limiting Reactor Vessel Material Bounding Zion Units 1 & 2 - Circ. weld WF for 25 EFPY 18
- 9. Calculation of Adjusted Reference Temperatures for the Limiting Reactor Vessel Material Bounding Zion Units 1 & 2 - Circ. Weld WF for 32 EFFY 19 11
LIST OF FIGURES Fiaure lilla, LLat
- 1. Location and Identification of Materials Used in the Fabrication of Zion Unit 1 Reactor Pressure Vessel 2
, 2. Location and Identification of Materials Used in the Fabrication of Zion Unit 2 Reactor Pressure Vessel 3
- 3. Reactor Coolant System Heatup Limitations (Heatup Rates up to 20*F/hr) Applicable to Zion Units 1 & 2 for the First 14 EFPY 20
- 4. Reactor Coolant System Heatup Limitations (Heatup Rates up to 40*F/hr) Applicable to Zion i
Units 1 & 2 for the First 14 EFPY 21
- 5. Reactor Coolant System Heatup Limitations (Heatup Rates up to 60*F/hr) Applicable to Zion Units 1 & 2 for the First 14 EFPY 22
!~
- 6. Reactor Coolant System Heatup Limitations (Heatup Rates up to-100*F/hr) Applicable to-Zion Units 1 & 2 for the First 14 EFPY- 23
- 7. Reactor Coolant System Heatup Limitations (Heatup Rates up to 20*F/hr) Applicable to Zion Units 1 & 2 for the First 20 EFPY 24 B. Reactor Coolant System Heatup Limitations (Heatup Rates up to 40*F/hr) Applicable to Zion Units 1 & 2 for the First 20 EFPY 25
- 9. . Reactor Coolant System Heatup Limitations-(Heatup Rates up to 60*F/hr) Applicable to Zion Units 1 & 2 for the First 20 EFPY 26
- 10. Reactor Coolant System Heatup Limitations (Heatup Rates up to 100*F/hr) Applicable to Zion Units 1 & 2 for the First 20 EFPY 27-
- 11. Reactor Coolant System Heatuo Limitations (Heatup Rates up to 20*F/hr) Applicable to Zion Units 1 & 2 for the First 25 EFPY 28
- 12. Reactor Coolant System Heatup Limitations (Heatup Rates up to 40*F/hr) Applicable to Zion Units 1 & 2 for the First'25 EFPY. 29
- 13. Reactor Coolant System Heatup Limitations (Heatuo Rates up to 60*F/hr) Applicable to Zion Units 1 & 2 for the First 25 EFPY 30 iii
LIST OF FIGURES (CON'T) Fiaure Title Etag
- 14. Reactor Coolant System lleatup Limitations '
(Heatup Rates up to 100*F/hr) Applicable to Zion Units 1 & 2 for the First 25 EFPY 31
- 15. Reactor Coolant System Heatup Limitations (Heatup Rates up to 20*F/hr) Applicable to Zion Units 1 & 2 for the First 32 EFPY 32
- 16. Reactor Coolant System Heatup Limitations (Heatup Rates up to 40*F/hr) Applicable to Zion Units 1 A 2 for the first 32 EFPY 33
- 17. Reactor Coolant System Heatup Limitations (Heatup Rates up to 60*F/hr) Applicable to Zion Units 1 & 2 for the First 32 EFPY 34
- 18. Reactor Coolant System Heatup Limitations (Heatup Rates up to 100'F/hr) Applicable to Zion Units 1 & 2 for the First 32 EFPY 35
- 19. Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100*F/hr)
Applicable to ,on Units 1 & 2 for the First 14 EFPY 36 20, Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100'F/hr) Applicable to Zion Units 1 & 2 for the First 20 EFPY 37
- 21. Reactor Coolant System Cooldown Limitaitons (Cooldown Rates up to 100*F/hr)
Applicable to Zion Units 1 & 2 for the First 25 EFPY 38
- 22. Reactor Coolant System Cooldown Limitations (Cooldown Rates up.to 100'F/hr)
Applicable to Zion Units 1 & 2 for the First 32 EFPY 39 iv
- 1. INTRODUCTION
' Heatup and cooldown limit curves are calculated using the most limiting value of RT NDT (reference nil-ductility temperature) for the reactor vessel. The most limiting RTNDT of the material in the core region of the reactor vessel I is determined by using the preservice reactor vessel material fracture toughness properties and estimating the radiation-induced ART NDT-RT NDT 1s designated ss the higher of either the drop weight nil-ductility transition temperature (NDTT) or the .emperature at which the material exhibits at least 50 ft-lb of impact snergy and 35-mil lateral expansion (normal to the major working direction) minus 60*F. RT NDT increases as the material is exposed to fast-neutron radiation. Therefore, to find the most limtting RTNDT at any time period in the reactor's life, ART NDT due to the radiation exposure associated with that time period must be added to the original unirradiated RT The extent of NDT. the shift in RT NDT is enhanced by certain chemical elements (such as copper and nickel) present in reactor vessel steels. The Nuclear Regulatory Commission (NRC) has published a method for predicting radiation embrittlement in Regulatory Guide 1.99 Rev. 2 (P.adiation Embrittlement of Reactor Vessel Materials){ll. Regulatory Guide 1.99, Revision 2 is used for the calculation of RT NDT values at 1/4T and 3/4T locations (T is the thickness of the vessel at the beltline region). Recently, new materials data has been obtained from the Babcock and Wilcox (B&W) Integrated Surveillance Capsule Program applicable to both Zion Units 1 and 2. Thus, a new evaluation using this data to determine the most limiting material in the beltline region and the corresponding RTNDT values at 1/4T and 3/4T has been performed. This report summarizes the results of this evaluation and presents the new heatup and cooldown curves generated based on i the results of this evaluation. LOCATION AND IDENTIFICATION OF BELTLINE REGION MATERIALS The beltline region is defined to be "the region of the reactor vessel (shell material including welds, heat-affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron irradiation damage"[2]. Figures 1 and 2 identify the location of all beltline region materials for Zion Units 1 and 2, respectively. 1 w-4 (1004) o* 87805-5 g
% -I l 2W- -+- ._ w JJ a
I f w-154 (Inner IE%)
- _ /[(SA-I?se (Ouser 18%)
BTEk5-1 carss-2
/W Shen [(C3795-2 180*
'W-4 (Ouser 6I%)
c I w -4 ,W-8 meer 39%) tw-e m(Ouser eer3es) st%) Inter. Sheet
=
*/ ','r -(core udsene) s w-< ocas) o' N
W-70(1005)
=
- w-enom ooos) 87823-t
/*"'"(bM e
' "hj -
w-ts4 0aos: zw . - __+- w W -8(1005) _ W -6(toDE) l C3799-2 tw tower shog I Figure 1. Location and Identification of Materials Used in the Fab of Zion Unit 1 Reactor Pressure Vessel
-)
l i ! .I i l h l 4 W-70 (100%) - o' 88006-1 1 i l "% , ('
% .I av + w
/ 'i i
4 ,s , D l ,
.L
~
y, w-200 (m) Beoe-1 -
]
I
% g,,, Be006-t w-70 t toom i
/ 88040-1 .,,,,
Inter.Shes. g_g g g3 (caeukspennei
. : ,, w-mitoon) n.
i N SA-t79 (1004) 8805-1 w-29 Bolh (1004)
/= **("s.J" L
** 'h j ,
270*f t : W-t w-a i toom -./ w-a tioom f C4007-1
- 1W Lower Sheu a
Figure 2. Location and identification of Materials Used in the Fabrication
- of Zion Unit 2 Reactor Pressure Vessel.
i-3. DEFINITION AND SOURCE OF MATERIAL--PROPERTIES FOR ALL VESSEL LOCATIONS Fast neutron irradiation-induced changes in the-tension, fracture, and I impact properties of reactor vessel materials are largely dependent 'on , chemical composition, particularly in-the copper concentration. The ! variability in irradiation-tra. ed~ property changes, which. exists in ! general,-is compounded by the variabilitv of copper concentration within. the weldmc sts. In order to address the variation in chemistry,. Babcock and Wilcox has given. Commonwealth Edison new materials data for Zion Units 1 and 2. The 3 new material data applicable to Zion Units 1 and 2 is shown -in Table 1 and was transmitted to Westinghouse via letter dated May 21. 1992, writtca by Commonwealth Edison Materials Groupl33 This new material data was used to determine the limiting beltline material bounding-both Zion'Unitsil and 2 and was consequently used to generate the heatup and cooldown limit curves bounding both plants. 4
- 4. FRACTURE TOUGHNESS PROPERTIES The fracture-toughness properties of the ferritic material in -the reactor coolant = pressure boundary are determined'in accordance~with the NRC kegulatory -Standard. Review Plane 43. The_ pre-irradiation fracture I
toughness properties for the' Zion Units 1 and 2 reactor-vessel materials are presented ~in Tables 2 and 3, respectively. t 1 h l: , .4--
- -,_,,,_..a
.. .. . - . . . ..~ ,.,.m. __ . . _ _ _ . , . _ _ . - - - - - . - - . . - _ . - . , _ . . . .. ._._.-.._ .-._. _.m.._m. -~ _ _._ _ . . _ . - . . --.4 - -. .
t 6-YABLE 1 ' MATERIALS DATA FReal BW INTEGRATED SURVEILLA8tCE CAPSULE PROGRAMI33 USED IN DEVELOPING Zl0N UNIIS I AND '2 NEATUP AND COOLDOWN CURWE5
. Weld Metal Initla g gg * ' Chemistry Factor - Copper- Nickel
{ :(*F) WF-70 .+18(2) 20 (2) 14' [ 174 (2) .35 (2) .59 (2) 2.- M -200 - 5 (1), 20 (1) .14 162 (3) ;.24 (I)- .63 (1) ?.
- a. ,
i F SA-1769 - 5 (1) 20(1)' '14
.: 19S (3) .26 (1) .61 (1)
?
(l)-
- WF-154 . 20.(1) 14 116 (3) .31 (1) .59 (1)
- l i ,
i
-(l). 8AW-1803. Rev.
~ 1,:" Correlations for Predicting the Effects of Neutron Radi4 tion an Linde 80 submerged Arc Welds"..May 1991. *
(2)1 R.J. Tamminga et .s t 'to T.J. .:Kovech. " Zion Station Units I and 2 Revised initial Ri gy and RTpg$ Values for Reactor Pressure Vessel Listing Weld Metal .WF-10", Chron #185582 May 11.1992.- i (3) T.L. Baldstn' to A.G. Panagos, " Task.145. Report of RTMDT. Values for Zion Units.I' and 2 for 15 EFPY", Babcock and Welcox letter . ESC-421. May 14. 1992.
- Per Reg. Guide 1.99. Revc .2 ' Position'2, the 28*F GA value may be divided by 2 'because credible surveillance data e ists.
4' f
- u. v e ga. .4- --+>=.=4 % a.- 44 m. - ,.44
. m E .ac. & .M+s masA4 .A a 4 4 u4 4.- w4 TABLE 2 ZION UNIT I REACTOR VESSEL TOUGHNESS DATA (UNIIRADIATED)
MRTERIAL Ce Rt P MOT
~
I L 5 N C090E NT- NOT MAT 30. ITPE (I) (I) (I) (*f) T (,(*F) (*F) g y g,t g) CLO5URE MAS SM 09094-2 A533. CL. I .I4 .55 .012 20 90 30 17 CLO5URE MAS SES. C5086-1 * *
.09 .54 .014 to 32 CLO5pBE M AS 355.
- 10 103 88793 3 *
.09 .52 .012 10 53 10 96' CL95MRE LEAS RME 123W323 A500. CL. 2 -
.69 .010 55I *I 26 55 96 VE55EL RANEE *
- 3239236 .06 .68 .004 FI *I -2 7 131 IEETIID2RE *
- 213600-1 .12 .68 .009 60I *I 27 60 79 IEET NOIRE * . "
IT360s-2 .11 .67 .009 60I *I 41 60 s2 IEET N0lRE 2T3592-1 * *
.10 .66 .011 60I *I 103 60 77 IEET N0ZRE ZT3592-2 * *
.11 .67 .010 60I *)
i 51 60 62 60I
- I SUTLET N022LE 213592-3 *
.II .64 .010 - 60 60
- 86 46I *I 0UTLET NBZRE
- 2T3592-4 .11 .68 .009 16 46 85 CUILET E0ZRE ID600-3 .10 .57 .011 60I *I $2 60 62 60I *I OtiTLET Nel2LE 2T3600-4 *
.11 .68 ' .011 46 60 >63
/n UPPER N0ZZLE $NELL 123v426' * *
.06 .75 .005 10 43 to 115 LOWER Nel2LE DGELL- IV3300 .06 .83 .008 20 72 20 87 INTER. $NELL C3795-2 A53M . CL. 1 .12 .49 .010 -10 70 10 85 INTER. SHELL *
- 87835-1 .12 .49 .010 -20 65(Actual) 5 115 (Actual)
LSER SELL 87823-1 .13 .48 013 -20 56(Actual) -4 115.5 (Actual) liber SELL *
- C3799-2 .15 .50 010 -20 80(Actual) 20 !!6 (Actual) I
'SSTTON IEAS TilAA$.
ties IT3779 A508. CL. 2 .09 .71 010 10
. 60 to 92 30TTqui sEAg sigt 37777-I A53B, CL. I .62
. 015 -30 33 -21 84 INTER. TO LOWER SIELL i
EIRTil WLS SEAN E78 IbI SAW .32 .56 017 0(a) 0 - ) INTER. SHELL LIBE. , WL5 SEAR W4I 'I SAW .29 .55 .013 0g ,} - 0 - INTER. 5MELL LIBE. IELS 5051 W8ggg SAW .29 0g*g
.55 . 013 -
0 - LOWER $NELL LIBI6 MELS SEAfl WS IdI 5AW - .29 .55 013 OI *I 0 . 2 (a) ESTifulTES UsinG METN005 0F 18.5.181C altsmE6-oe00. BRANCH TECHNICAL POSITION MTER 5-2. Jutt.1981 (b) WLS WIM HEAT NO. 72105 AND LINDE 80 TLUI LOT No. 8669 (c) WLS WIRE petAT NO.' Sil862 AsE LilI0E 80 ELUE LOT NO. 4597 (4) WELO WIRE HEAT NO. 8T1762 ANO LitIDE 80 FLUI LOT NO. 8632
TABLE 3 - ZION UNIT 2 REACTOR VESSEL TOUGHNESS DATA (UNIRRADIATED) T RT "A"5 NRTERIAL Ce NI P m0T W
#* FTp, 35 m m0T ESMBENT MAT NO. TfPE (1) (1) (1) -(*F) h,gg j
(*r ) (*F) CLO5URE LEAS SIDE 89094 1 A5338.CL. 1 .14 .55 .012 -20 71 11 ' 72 ELO5URE MAS 588. C4787-IA .13 .62 .006 0 30 0 88 CLO5URE NEAS SES. C5086-2 .09 .54 .014 30 45 30 88' CLO5URE NEAS FLAME 12468600 A508. EL. 2 .08 .70 .010 12I *I -13 12 los VE5SEL FLANEE 2V-965 * *
.12 .74 .010 - 60I
- 33 60 79 g,
IE LT 5022LE 2T4007-2 '*
.11 .70 .009 12 48 378 i IEET NO22LE 2T3ee5-1 '*
.11 .58 .012 48(a) 60 43 60 82 INLET N022LE *
- 2T3005 .11 .56 .011 43 31 43 1s , _
IE ET N022LE *
- 2T3085 .11 .56 .012 60 48 60 >se GITLET NO22LE *
- Zv3930 .12 .66 .010 58 20 58 93 OUTLET N022LE 2V3930 .11 .65 .011 15 CUTLET IIO22LE 2V39M * *
.12 .67 .011 48((a) 55 a) 28 48 55
>so
- 84 GUTLET N022LE 2T3 ABS-4 .11 .57 .013 60(a) 41 60 7 61 h UPPER N022LE $NELL 293940 A500. CL. 2
.07 .62 .000 10 65 to 106 LGhER N022LE SELL 2V3055 -* .09 .66 .008 to 70 10 eso INTER. $NELL 90029 1 A5338. CL.1 .12 .51 .010 -10 - 82 22 81 INTEd. 5NELL C4007 1 .12 .53 .010 to 82(Actual) 22 94(Actual) liber 5 ELL 80006 1 * *
.12 .54 .010 10 68 to 89 LOWER $NELL 88040 1 .14 .52 .000 -10 62 2 92 00 TION IIEAS TR4115.
RING 3V-433 A500. CL. 2 .09 .76 .010 0 43 0 87 30TTON NEAS gupE C4007 2 A533B , CL. 1 .12 .53 .010 -20 60 0 72 INTER.- 10 LetER SELL SIRIN E LS SEAfd $A1769(b) 5Alf .26 .50 .019 0(a) - 0 - INTSR. SNELL LS E.. g NELS SEAN5 W 29 ,g SAW .23 .63 .019 OI ,I - 0 - LatER 5NELL Laus, WLS SEANS W70g,I 5AW .32 .56 .017 OI ,I .- 0 - (a) ESTINnTEs 951Ns ETN00 0F u.5.Nac Nutts.0e00 sRANCH TEClellCAL POSITION NIEB 5-2, JULY.1981 3 (n) ute ulRE HEAT NO. 71249 ANO LINDE 80 FLUX LOT NO. 8738 i (c) WLO WIRE HEAT NO. 72102 AND LIMOE 80 FLliZ LOT NO. 8650 (4) WLS WIRE IIEAT 100. 72105 ANO LINDE 80 FLUE LOT NO. 8669
R I- 5. CRITERIA'FOR ALLOWABLE PRESSURE-TEMPERATURE RELATIONSHIPS l _The ASME approach for calculating the allowable limit curves for various heatup l and cooldown rates specifies tht the total stress intensity _ factor, Kg, for I the combined thermal and pressu.e. stresses at any time during heatup-or [ cooldown cannot be greater than the reference stress intensity factor, KIR' { for the metal temperature at that time, KIR is obtained from the reference-i fracture toughness curve, defined in Appendix.G to the ASME Code [5). The Kgg curve is given by'the following equation:. l ' j- KIR = 26.78 + 1.223 exp [0.0145 (T-RTNOT.+ 160)) p (1) V where L l~ KIR = reference stress intensity factor as a-function of the metal-I temperature T and the metal reference nil-ductility temperature }- RTNDT ' 7 Therefore, the governing equation for the heatup-cooldown analysis is defined i ir. Appendix G of the ASME Code [5] as follows: 1
- - C*Kgg + KIT I KIR (2) l' where t-KIM = stress intensity factor Lcaused by membrane -(pressure) _ stress i
f l KIT = stress intensity factor caused by the thermal gradients 4 KIR = function'of temperature relative to-the RTNDT of the material C = 2.0 for level A and Level-B: service limits C -= 1.5.for hydrostatic and leak' test con'ditions during_which the e reactor core is not critical 4 6-
- i. e
_. . . . _ . , - . _ . ....-..-.m.,- ,.__.,-__.-.....~-.-.,._..,-,-..,m.,- -
At any time during the heatup or cooldown transient, Kyg is determined by the metal temperature at the 7 of the postulated flaw, the appropriate value for RTNDT, and the reference fracture toughness curve. The thermal stresses resulting from the temperature gradients through the vessel wall are calculated and then the corresponding (thermal) stress intensity factors, KIT, for the reference flaw are computed. From equation 2, the pressure stress intensity factors are obtained and frora these the allowable pressures are calculated. For the calculation of the allowable pressure'versus coolant temperatur:. during cooldown, the reference flaw of Appendix G to the ASME Code is assus;ed to exist at the inside of the vessel wall. During cooldown,.the~ controlling location of the flaw is always at the inside of the wall because the thermal gradients produce tensile stresses at.the inside, which increase with increasing cooldown- > rates. Allowable pressure-temperature relations are generated for both steady-state and finite.cooldown rate situations. From these relations, composite limit curves are constructed for each cooldown rate of interest. The use of the composite curve in the cooldown analysis -is necessary-because control of the cooldown procedure is based. on the measurement of reactor coolant temperature, whreas the limiting pressure'is actually dependent on the material temperature at -the tip of the assumed flaw. During cooldown, the 1/4 T vessel location is at a higher temperature than the fluid adjacent to the vessel 10. This condition, of course, is.not true for the steady-stato situation. It--follows.that, at any given reactor coolant temperature, the AT developed during cooldown results-in a higher value of l K IR at the 1/4 T location for finite cooldown rates than for steady-state operation. Furthermore, if conditions exist so that the increase in K IR exceeds KIT, the calculated allowable pressure during cooldown will. be-greater than the steady-state value. The above procedures are needed because there is no direct control on i temperature at the 1/4 T location and, therefore, allowable pressures may_ unknowingly be vio' lated if the rate of cooling is decreased at various intervals along a cooldown ramp. The use of the composite curve eliminates ~ this problem and ensures conservative operation of the system for the er.tbe cooldown period. 9- { . _ _ _ . . -. -- .- - - - - - - - ' ~ ~ ~~~'~
4
- Three separate calculations are requircd to determine the lictit curves for j- finite heatup rates. As is done in the cooldown analysis, allowable pressure-j temperature relationships are developed for steady-state conditions as well as finite heatup rate conditions assuming tha presence of a 1/4 T defect at the ,
inside of the wall that alleviate the tensile stresses produced by internal i } pressure. The metal temperature at the crack tip lags the coolant temperature; j therefore, the Kgg for the 1/4 T crack during heatup is lower than the K IR j for the 1/4 T crack during steady-state conditions at the same coolant ! temperature. During heatup, especially at the end of the *ransient, conditions i may exist so that the effects of compressive thermal strestes and lower KIR's , do not offset each other, and the pressure temperature curve based on j steady-state conditions no longer represents a lower bound of all similar j curves for finite heatup rates when the 1/4 T flaw is considered. Therefore, 4 both cases have to be analyzed in order to ensure that at any coolant-3 temperature the lower value of the allowable pressure calculated for { steady-state and finito heatup rates is obtained. 4 4 The second portion of the heatup analysis concerns the calculation of the pressure-temperature limitations for the case in which a 1/4 T deep outside j surface flaw is assumed. Unlike the situation at the vessel inside surface, 2 the thermal gradients established at the outside surface during heatup produce stresses which are tensile in nature and therefore tend to re'inforce any , pressure stresses present. These thermal stresses are dependent on both the rate of heatup and the time (or coolant temperature) along the heatup ramp. ! Since the thermal stresses at the outside are t,nsile and increase with increasing heatup rates, each heatup rate must be analy*/d on-an-individual basis. 4 i
- Following the generation of pressure-temperature cu ees for both the s-state and finite heatup rate situations, the final limit curves are proout.d by constructing a composite curve based on a point-by-point comparison'of the j steady-state and finite heatup rate data. At any giver erperature, the allowable pressure is taken to be the lesser of the thn" values' taken from the l,
curves under consideration. -The use of the composite. curve is necessary to set . conservative heatup limitations because it is possible for cenditions to exist wherein, over the course of the heatup ramp, the controlling condition switches f from the inside to ib outside, and the pressure limit must at all times be based on analysis of tae most critical ce terion. i 1
, . . , , - +
, ,e. , , . . - , , , .
..m , --.---c_,_ ,.-, , , , - . . ,-.m, , , ~ . - ~ ~ , , ,.- .,_<.m _ _ _ ,
i t 4 Finally,the1983Amendmentto10CFR50AppendixG[2]hasarulewhich ' addresses the metal temperature of the closure head flange and vessel flange regions. This rule states that the metal temperature of the closure flange j regions must exceed the material RT NOT by at least 120'F for normal operation when the pressure exceeds 20 percent of the preservice hydrostatic l test pressure (621 psig for Zion Units I and 2). ' The minimum allowable temperature is based upon the limiting initial RT NOT h the vessel and closure flange regions of Zion Units 1 and 2. Table 2 indicates ' that the initial RTNOT of 55'F and 7'F occurs in the closure head flange and vessel flange, respectively, of Zion Unit I reactor vessel. Table 3 4 indicates that the, initial RTNOT of 12*F and 60*F occurs in the closure head flange and vessel flange, respectively, of Zion Unit 2 reactor vessel. Therefore, using the most limiting initial RTNDT value of 60*F, , bounding Zion Units 1 and 2, the minimum allowable temperature of this region s determined to be 180*F at pressures greater than 621 psig. These limits are less restrictive than the limits shown in Figures 3 through 22. 4 6. HEATUP AND COOLDOWN PRESSURE-TEMPERATURE LIMIT CURVES I i Pressure-temperature limit curves for normal heatup and cooldown of the Reactor - Coolant System have been calculated using the methods discussed in Section 5. ' Figures 3 through 18 contain the heatup curves for 20,-40, 60 and 100 'F/hr for 14, 20, 25 and 32 EFPY, respectively, applicable to both Zion' Units 1 and 2. Figures 19 through 22 contain.the cooldown curves up to 100*F/hr for 14, 20, 25 and 32 EFPY, respectively, applicable to both Zion Units.1 and 2. Margins of 10 *F and 60 p.sig are included in these- figures _t'o' allow for
- possible instrumentation errors.
Allowable combinationsiof temperature and pressure for specifin temperature change rates are below'and to the right of thel 11mit lines-shown in Figures _3 through 22. This is in addition to other criterialwhich must'be met before the reactor-is made critical.
--I1
, . ~ . - . . . . ..__...-.--___.m.. . . . _ _ . . _.
.,_ . _ _ , _ _ -,_ _.- 4-.m. , , , . . . . .
^
.~..,-,,,;,,..-,,,,_..,-_._,,
The leak limit curves shown in Figures 3 through 22 represent the minimum temperature requirements at the leak test pressure 3pecified by applicable codes [4,5). The leak test limit curve was determined by methods described I in 10CFR50 Appendix GI23 and the Standard Review Plani 4}. ) l The criticality limit curves shown in Figures 3 through 22, specify pressure- ! temperature limits for critical core operation to provide additional margin
- during actual power production as specified in 10CFR50 Appendix GI23 The pressure- temperature limits for core operation (except for low power physics tests) are that the reactor vessei must be at a temperature equal to or higher
., than the minimum temperature required for the inservice hydrostatic test, and i at least 40'F higher than the minimum pressure-temperature curve for heatup and cooldown calculated as described in Section 3. The maximum temperature for the inservice hydrostatic leak test bounding Zion Units 1 and 2 reactor vessels i is 352'F, 367'F, 377'F and 389'F for 14, 20, 25 and 32 EFPY, a respectively. A vertical line at these temperatures on the pressure-temperature curve for 14, 20, 25 and 32 EFPY, respectively, intersecting a curve 40*F higher than the pressure-temperature limit curve, constitutes the limit for core operation for the reactor vessel. Figures 3 through 22 define limits for ensuring prevention of nonductite l failure for Zion Units 1 and 2 reactor vessels. l
- 7. CALCULATION OF ADJUSTED REFERENCE TEMPERATURE 1
From Regulatory Guide 1.99 Rev. 2III, the adjusted reference temperature (ART) for each material in the beltlino is given by the following expression: ART = Initial RTNOT + ARTNOT + Margin (3) mitial RTNDT is the reference temperature for the unirradiated material as defined in paragraph NB-2331 of Section III of the ASME Boiler and Pressure Vessel Code. If measured values of initial RT NDT for the material in questicn are not available,. generic mean values for that class of material may be esed if there are sufficient test results to establish a mean and standard deviation for.the class. ARTNOT is the mean value of the adjustment in reference temperature caused by irradiation and should be calculated as follows: ARTNDT - [CF)f(0.28-0.10 log f) (4) To calculate ARTNDT at any depth (e.g., at 1/4T or 3/4T), the following formula must first be used to attenuate the fluence at the specific depth. f(depth X) " fsurface(8 ) (5) where x (in inches) is the depth into the vessel wall measured from the vessel clad / base metal interface. The resultant fluence is then put into equation (4) to calculate ARTNDT at the specific depth. CF (*F) is the chemistry factor, a function of Copper and Nickel content. Chemistry factor values for the welds were obtained from the B&W Integrated Surveillance Capsule Program per letter from Commonwealth EdisonI33. These values are shown in Table 1. Chemistry factor values for the base metals (plates and forgings) were obtained from Table 2 in Regulatory Guide 1.99, Revision 2[II, using the corresponding Copper and Nickel content for each l material. Applying the methodology described in Regulatory Guide 1.99, Revision 2Ill to determine the Adju'ted s Reference Temperature (ART) for each beltline regien material, it was found that the circumferential weld seam WF-70 in Zion Unit 1, between the vessel intermediate and lower shell, was the limiting material bounding both Zion Units 1 and 2. ART values for the circumferential weld WF-70 were evaluated at 1/4T and 3/4T locations using chemistry factor values l provided by Commonwealth Edison from the B&W Reactor Vessel Integrated i Surveillance Capsule ProgramI33 The results of the ART values at 1/4T and 3/4T for all materials in the beltline region of Zion Units 1 and 2 are presented in Tables 4 and 5 respectively. Note the ART values shown in Tables 4 and 5 were obtained using ' chemistry factors from the Regulatory Guide 1.99, Revision 2, tables. The ART values using the new B&W materials data from their Integrated Surveillance Capsule Program are shown in Tables 4 and 5 with an
- as a footnote. Sample calculat: ens of adjusted reference temperatures are shown in Tables 6 through 9.
IABLE 4
$UMMARY OF ADJUSTED REFERENCE TEMPERATURES Ai I/41 AND 3/4T LOCATIONS OF ZION UNIT I BELTLINE REGION MATE FOR 14, 20, 25 AND 32 EFPY v
14 EFPY 20 EFPY 25 EFPY 32 EFPY RT RI # AT RT NOT ND'i AT Ri Af AT Concorent 1/4T (*F) 3/4T f*F) 1/4T [*F1 3/4T (*F1 1/47 f*F) 3/47 (*FI !!4T f*F) J/47 f*F) C h c.- Weld W -154/5A-1769
- 167 125 183 137 193 la6 204 156 (Upper to Inter.)
Inter. Shell B7835-1 64 64 91 70 96 14 101 79 In*er. Shell C3795-2 123 102 130 108 135 112 140 IIT i 4 Long. Veld WF-4 9 0* 165 121 179 138 189 146 201 155 4 tm Weld VF-4/WF-8 165 127 119 138 189 146 201 155 9 180* Cire. Weld VF-70
- 206 161 222 175 232 184 243 194 (Inter. to Lower) iover Shell 87823-1 1D0 77 108 84 Ill 89 118 94 tower Shell C3199-2 138 Ill 147 119 153 124 160 130 Long. Weld VF-8 9 90* 165 127 180 138 189 146 201 155 tong. Veld W-8 9 270* 165 127 180 138 189 146 201 155 RT NDT values calculated using new materials data from the B&W Integre, ' 3arveillame Capsule Program
1 iA8tE 5 SlMMARY OF ADJUSTED REFERENCE TEMPERAllSES AT 1/4T AND 3/4T LOCAi!ONS OF 2!0N latti 2 BELTLINE REGI FOR 14. 20. 25 AND 32 EFPY 14 EFPY 20 EFFY 75 EFPf 32 EFPY RT A Ri # NDT RT AT RT AT NDT AT Component 1/4T (*F1 3/4T (*F) 1/4T (*F) 3/4T f*F) 1/4T (*F] 3/4T (*F) 1/4T (*Fl 3f 47 ( *s-) Circ. Weld W-200
- 161 121 175 133 184 141 195 150 (Upper to Inter.) '
Inter. Shell B8006-1 123 102 130 108 135 112 140 117 Inter. Shell B8040-1 127 102 135 109 141 114 147 120 g Long. Veld W-10 0 0* 158 123 112 133 ist 141 m 192 150 8 Long. Weld VF-10 9180 158 123 172 133 181 141 192 150 Cire. Weld SA-1769
- 199 149 216 164 228 174 240 186 linter. to Lower)
Lower Shell C4007-1 109 86 117 93 122 98 12S 103 Lower Shell E8029-1 135 114 142 120 146 124 152 129 Long. Weld WF-29 9 90* 157 122 171 133 181 140 191 149 L wg. Weld WF-29 9 27D* 157 122 171 133 181 140 191 149 RT MDT values calculated us tog new materials date from the BfN Integrated Surveillance Capsule Program.
{ TABLE 6 4 j CALCULATION OF ADJUSTED REFERENCE TEMPERATURES FOR THE LIMITING REACTOR VESSEL MATERIAL BOUNDING ZION UNITS 1 & 2 - CIRC. WELD WF FOR 14 EFPY t 4 Reaulatory Guide 1.99 - Revision 2 14 EFPY j Parameter . 1/4 T., 3/4 T ! Chemistry Factor, CF (*F)(a) 374 374 {. Fluence, f (1019 n/cm2 )(b) 0.492 0.179 1 t Fluence Foctor, ff 0.802 0.543 i j ARTNDT CF x ff (*F) 139_ 94 i j Initial RTNDT, I (*F) 18 18 Margin, M (*F) (C) 48.8 48.8
- . Revision 2 to Regul. tory Guida 1.99 I
i Adjusted Reference Temperature, 206 161 i ART = Initial RTNDT + ARTNDT_+ Margin 4 1 (a) Chemistry Factor value was provided by Commonwealth Edison from the B&W l Surveillance Capsule ProgramI33. See lable 1. 4 7 (b) Fluence, f, is based upon fsurf (10 19 n/cm2 , E>l Mev) = 0.8166 at 14 EFPY, The Zion Unit I reactor vessel wall thickness is 8.441 inches at J- the beltline region. ' L ' (c) Margin is calculated ~as -M = 2 [og2+c_ a ) ' 5. . The standard deviation for the initial RTNDT margin term (og) is 20'F. This value was provided by Commonwealth Edison from.the B&W L integrated Surveillance Capsule Program (3), also shownfin Table l. The standard deviation for ARTNDT' .(8 A ) is: 14*F for weld metal, since credibleisurveillance data exists from the B&W Integrated. Surveillance Capsule Program. 16-
% -,9=. o. + ma ,v,repr-.,.7,-- v,--r-.g.m-w.--ve--- .=r -ry-=-.me-n 3-+--,e- --y-w ,gw .-v--+y-rwy-vvcev.--v-v--y--- v'<e., www,9=,,-' r-r'f v s'WW -mm r' s wer e tue m * -ew'gr
- N- r - h '
TABLE 7 i i CALCULATION OF ADJUSTED REFERENCE TEMPERATURES FOR THE LIMITING REAC VESSEL MATERIAL BOUNDING ZION UNITS 1 & 2 - CIRC. WELD WF-70 -FOR 20 EFPY Reculatory Guide 1.99 - Revision 2 20 EFPY Parameter 1/4 T 3/4 T Chemistry Factor, CF (*F)(a) }74 174 Fluence, f (1019 n/cm2 )(b) 0.676 0.24S Fluence-Factor, ff 0.890 0.619 ARTNDT CF x ff-(*F) 155 108 Initial RTNDT, I ('F) 18 18 Margin, M ('F) (C) 48.8 48.8 Revision 2 to Regulatory Guide 1.99 Adjusted Reference Temperature, 222 175 ART = Initial RTNDT + ARTNDT_+ Margin (a) Chemistry Factor value was provided by Commonwealth Edison from the B&W Surveillance Capsule ProgramI33 see' Table 1. (b) Fluence, f, is based upon-fsurf (10 19 n/cm2 ,-E>l Mev) _1.121 at 20 tFPY. The Zion Unit I reactor vessel n11 thickness is- 8.441 inches at the beltline region.- (c) Margin is calculated as, M = 2 [og2+y 230.5. The-standard deviation for the. initial RTNDT margin term (og) is 20*F. This value was provided by Commonwcalth Edison frem the B&W Integrated Surveillance Capsule ProgramI3I, also shown in Table 1. _The standard deviation for ARTNDT' (8A ) is 14*F for weld metal, since credible surveillance data' exists from the B&W Integrated Surveillance Capsule Program.
2 1
- TABLE 8 j CALCULATION OF ADJUSTED REFERENCE TEMPERATURES FOR THE LIMITING REACTO i
YESSEL MATERIAL BOUNDING ZION UNITS 1 & 2 - CIRC. WELD WF FOR 25 EFPY j i
- Reaulatory Guide 1.99 - Revision 2 ,
25 EFPY l Partmeter 1/4 T 3/4 T j i j Chemistry Factor, CF ('F)(a) 374 374 ! Fluence,f(10l9 n/cm)(b) 2 0.829 0.301
- Fluence Factor, ff 0.947 0.671 l ARTNDT - Cl x ff (*F) 165 117 p Initial RTNDT, I (*F) 18 18 Margin, M (*F) (C) 48.8 48.8
- { ******************************************************************************* -
! Revision 2 to Regulatory Guide 1.99 ' l jt Adjusted Reference Temperature, 232 184 j ART Initial RTNDT + ARTNDT + Margir.. i (a) Chemistry Factor value was provided by Commonwealth Edison from=the B&W s
~
Surveillance Capsule ProgramI3}. See' Table 1. ! (b) Fluence, f, is based upon fsurf(10 19 n/cm 2 E>l Mev) - 1.376 at 25
- EFPY[6).
The Zion Unit I reactor vessel wall thickness is 8.441 inches , 4 at the beltline region. (c) Margin is calculated as, M = 2 (o;2 + , 2 30.5 -The ! standard deviation-for-the initial RTNDT margin-term (ag) is - 20'F. This_value was provided by Commonwealth Edison from.the-B&W-Integrated Surveillance Capsule ProgramI33, also shown in Table 1. The-standard deviation for ARTNDT'- (8 4 ) is 14'F for weld metal, since credible < surveillance data exists from the B&W' Integrated Surveillance Capsule Program. v +- ec,,,rn-, , w-, 9,- ,, -r+e v er+ w 9e -e et e , e w*v wv'-= r v - t'w+< we +=*-vv- '*w*c -fqb - '*a'v+ --ew% e - w"a-- W ' e
- TABLE 9 CALCULATION OF ADJUSTED REFERENCE TEMPE VESSEL MATERIAL BOUNDING ZION UNITS 1 & 2 Reoulatory Guide 1.99 - Revision 2 Parameter ___ 32 EFPY
_1/4 T_ 3 /4 T___ Chemistry Factor, CF ('F)(a) Fluence, f (10I9 n/cm2 )(b) 174 j74
},o44 o,379_
Fluence Factor, ff 0.732
...*****.*********************.**********************1.012 **************************
ART NDT - CF x ff (*F) 176 127 Initial RTNDT. 1 (*F) 10 Margin, M (*F) (c) 18 >
- 4. ..**** 48,8 48.8
...........**......**...***v....
Revision 2 to Regulatory Guide 1.99 Adjusted Reference Temperature, 243 194 ART - Initial RTNDT + ARTNDT + Margin (a) *** *******************************......**... *** Chemistry Factor value was provided by Commonwealth Edison fro Surveillance Capsule ProgramI33 See -Table 1. (b) Fluence, f, is based upon-f EFPYt6' surf (10 19 n/cm2 , E>l Mev) = 1.732 at 32 Theregion. at the beltline 7h n Unit I reactor vessel wall thickness is 8.441 (c) Margin is calculated as,-M = 2 (0 2 # , 2 30.5 The 1 standard deviation for the initial RT NDT margin term (cy) is 20*F. This value was provided by Commonwealth Edison from the B&W Integrated Surveillance Capsule Program (33, also:shown The in Table 1 standard deviation for ART . NDT* ('A) is 14*F for weld metal, since credible surveillance data exists-from the B&W Integrat Surveillance Capsule Program.' 1 9 4 l 4 RATERIAL PROPERTY BASIS CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70 1 { INITIAL RTNDT: 18'F j ART AT 14 EFPY: 1/4T = 206*F 4 3/4T = 161*F !
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l 0 ' ' ' ' O 50 100 150 200 .250 300 350 i 400 450 500 lNDicATED TEWPERATURE (DEG.F) l Figure 3. , Reactor Coolant System Heatup Limitations (Heatup rates up to 20*F/hr) Applicable to Zion Units 1 and 2 for the First 14 EFPY (With Margins of 10*F~and 60 psig For Instrumentation Errors) i=
MATERIAL PROPERTY BASIS $ CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70 INITIAL RTNDT: 18'F ART AT 14 EFPY: 1/4T - 206'F 3/4T = 161'F 2500 w e i3 i, i , , . _, , , ,! , , ii, i ,, , i i ti i-> if i ! i i !! ! i 11 11 ! ii! i
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_ . ~ .. . ._ _ _ _ . _ - . _ _ _ - _ _ . _ _ - _ i MTERIAL PROPERTY BASIS k CONTROLLING MATERIAL: C]RCUMFERENTIAL WELD WF-70 ] INITIAL RTNDT: 18'T i i AR1 AT 14 EFPY: 1/4T - 206*F
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Figure 5. . -Reactor Coolant System Heatup~ Limitations-(Heatup rat'es up to-60*F/hr) Applic21e to Zion Units L1 'and 2 for the-First 14 EFPY. (With Margins of 10*F and 60 psig For Instrumentation. Errors) 22 ! ~.
*-p % .< -- - g -e ,-s- ,.sp- t--- &t-y-te,--r+'7 tm,
MATERIAL PROPERTY BASIS 4 CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70 INITIAL RTNDT: 18'F ART AT 14 EFPY: 1/4T - 206*F 3/4T = 161*F 2500: 7 m.m , i , , i a;;i ,iir i i i i i i i j [v . , , . i + i i ! i i i i ! i i I i l i ! i i r i , i i , ; _i ! i ! I ,! t i i ih iiIt i i ' 1 s , e i e ii ii i *bii 4 i / i i 4
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i i i ! MATERIAL PROPERTY BASIS 4 4 CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70
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-2 A ..
MATERIAL PROPERTY BASIS CONTROLLING MATERIAL: CIRCUHFERENTIAL WELD WF-70 l 18'F i INITIAL RTNDT: ART AT 20 EFPY: 1/4T - 222'F 3/4T - 175'F ! 2500 g i y,2 3 i j , , , 4
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r MATERIAL PROPERTY BAS 15 CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70 INITIAL RTNDT: 18'F
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MATERIAL PROPERTY BASIS CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70 INITIAL RTNOT: 18'F ART AT 32 EFPY: 1/4T 243*F 3/4T 194*F a 25co m y,w
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MATERIAL PROPERTY BASIS CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70 INITIAL RTNDT: 18'F ART AT 32 EFPY: 1/4T = 243*F ' 3/4T = 194*F 2500 3 ; gwp , , ! ; i , , ; ; i ! i i i ii ' 3 i,, ,, , ,,,, 1 I i I i
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! ' 1 f i i 0' ' '
i i O 50 100 150 200 250 300 350 400 450 500 INDICATED TEWPERATURE (DEG.F) Figure 17. Reactor Coolant System Heatup Limitations (Heatup rates up to 60*F/hr) Applicable to Zion Units 1 and 2 for the First 32 EFPY (With Margins of 10*F and 60 psig For Instrumentation irrors) MATERIAL PROPERTY BASIS CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70 IN!TIAL RTNDT: 18'I ART AT 32 EFPY: 1/4T = 243*F 3/4T = 194*F 2500 7 py,m, 3 ij; i , , , i ; i i i; i i i .ii i f i 1 , 1 , ; ,
. . ,, . .i! ! ! ! ! ! ! i I ii f i 'ii e i ii i
!/ ! f i il,,!,
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i i , i, i i i . . l t ii . i Il! , ' .j(/j i_ y4j !j i!
/i i, iy ~ ,i 1
'*O
; i i !i lI i i i LEAK TEST LlHIT ii !J vii i i ;i ! ! I i/ 4 : i Ii i 4 iii 4 1 ' iir ! .
>! 1 I I 1
I! t
! t li
+i il I _ I
'IT~ Ii iI6 i > 11 i,
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4 ii e it i i 4 i i i i f ' L'l I i i/ii i, e000 -
, iih i 1 li h J !
,. i 'i ,f Ai1 T
- i
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.~ i,1 i
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, i
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i i
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- i
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i,i; ,,,i .,; i - - 4 i i OPERATION i . -
- y !
i - i i, > i i! < zi' + it i
! i
^
! il l l i l l l ll ll l/ l / ACCEPTABLE o 1500 ,, ,! i ,! ,' ,',',' : ,! .'
! ! ! h'!
i ,' if i/
! . if'
+/ OPERATION G i! i ! i i ! ! i i i ! ' '
i*! A i : ii i i i ii l i ei i/ '/
~ e i l i g 1250 ll'l ii i
i
!' i
.HEATUP RATES l
'/ / lj -
i ! UP T0 i
/ /- i i S
U y ! ll i l i l'l i i
- 100'F/HR i!
i
/ /' ,
l,',
/ / i i i4 .
E 1000 e l i lll i i
/! /
l l l t-w i i 4
/ ii !
- 4
/ i i . < ii I , i; / i i i 750 L>
o
,/ ; ! l, z i i !
y I , i ! f. 500 ii j / ' CRITICAllTY LlHIT BASED ON INSERVICE
/
HYDROSTATIC TEST l ! ./ ~" TEMPERATURE (389'F)
,5 ' ' '
"0 i '
FOR THE SERVICE
, l l , j, , PERIOD UP TO 32 EFPY
, i t ! I ' '
I I i
! I i !
- i i 0 50 100 150 200 250 300 350 400 450 500 INDICATED TEWPERATURE (DEG.F)
Figure 18. Reactor Coolant System Heatup Limitations (Heatup rates up to 100*F/hr) Applicable to Zion Units 1 and 2 for the First 32 EFPY (With Margins of 10*F and 60 psig For Instrumentation t Errors) t
=- ._ . _ - .- --. _. - .- - . _ . . _ _ . - . _ . - _ - _ . _ - _ _ - _ _ _
i i 1
, MATERIAL PROPERTY BASIS 4
4 CONTROLLING MATERIAL: i CIRCUMFERENTIAL WELD WF-70 INITIAL RTNOT: 18'F ART AT 14 EFPY: 1/4T = 206*F i 3/4T - 161*F i l i 2500-7,ga n ,i, , i , i , , , i i i l i i i i i . 3 , i
! i + ! l ! i !I f I i iI i
,i,3 i i . i i ! i 4
5! is i t > i! !i i i i i ! . ! i e i ! ! i ' i if i i ! i i
! I f i 8 ! ! I ! !! i iI i If f i ! ! ! I i I '
s } i i }
'.250 i 4
i i i i 1 6 i l ! t ! f 4 i i !
- i i i I i i I i ii i , , 1 i ! i I t i ! ' ' ' ~.] i I i e ! I I# # l f
- I 8 i * ! i 8
) ; ;! i l' i ! ! 2000 I ' f 4 ; i l l i . , , ,
!j l i .
,' { / l l 1 l' '
, , 11 , 4 . . ,
j ii.i i i ;i - i + i , i UNACCEPTABLE
- 1750
',, ' : OPERATION '
i
/'
- i i !iii 1i ! e i ,
.I i iii
- i8 i ii '
i ! i ! -
! !! (__ ! i '
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g, 4 ! i ; i i i i i ,' i * , ii. ,
'1 i
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! '! +
! i a ! i ii /. i , , i<
i ie i ( i f
- y 1250 l !j -
i i ii i 3 , , i i [ j 'jj; ! $ l' i E ACCEPTABLE lli;
- a. 1000 OPERATION ii,.
i b ,7 O
, , i i 4
w Y b b E
, . i i i r <
u ll ; j_ , - 750 .
$g ,
mym
- e i ,. ,. :
3 z .. 4 i ,
- m. .
i i
.COOLDOWN RATEL w/
500 ,' i
'F/HR-i i 0 m- --o o "w" .-
/
*lIi i i ! !
t i gn + sv , . 14 ,
-- _ .-r-- , ,,
,50 -~
40 i f j <. 60' 1' , i
-- 100 l L- ' ' ' ' '
j_ l i ie i i 0 i 1 0 50 100 150 200 I i 250 300 350 400 450 i 500-INDICATED TEMPERATURE-(CEG.F)~ Figure 19. Reactor Coolant System Cooldown Limitations (Cooldown rates up to i 100'F/hr) Applicable to Zion Units 1 and 2 for the First 14 EFPY (With Margins of 10'F and 60 psig For Instrumentation Errors) e
., -- ,, . ._...~.,m_ . . - . _ . , , , , . . . , . - . , , ., , ,. . . . _ , . , , _ . , .
MATERIAL PROPERTY lLAILS CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70 INITIAL RTNDT: 18'F ART AT 20 EFPY: 1/4T 222'F 3/4T - 175'F 2500 gym i ; i , ; , -
! I i , ,
i 1 , ; ; , , , i i ! t i i f _I i i l i i i
<I i i ! ! ! i i i I i ! i
! 6i i ! . ! i i i i ! I i jj . 4 i e i i ii e i t i ! i '
I i t i4 i i !! I thi -
! 1 i
' ' ' i !!
2250 l I f l i l' i i
! ll !j# !;' ll ,
i , ,, , a 8i f i I! ! ! i
! i 1 , t
< # i , ,
! i ! t i i ii il i 4 2000 l ,
l l ' i l l !j# _ ll , i + 1 i ! < t i 1 / ! i i i
! t i / t e
~ i ! I i 1750 : .
- UNACCEPTABLE l'i !, !' .
' OPERATION l !'!1/'/ !i ! ,; ,' l
! 1 ii ii i i !
s i i j ii I e ! l 4 e t
^ ' ' ' / i l l l i .
o 1500 . . , i i' i i '
~
g *
! . i i
s'i . i i ! ! ! !
- 1. , ,l .' , t !
i I
/! ' i i 4 ' 'i j i4 ! i i i i
/ ! ii y 1250 l , l '
j D t i i lll
/
$ ' i
>> ACCEP,ABLE '
- E i
- o. 1000 , , / OPERATION i o .
i f, - w i i J . i s 2r , Q ! E' . i i . u
- 750 '
! i 1 it i '
O fa i s si i ff/>{ i i 5 s om
, . i
> t ! >
i ! i _COOLDOWN RATES ' own 500 .-
.*F/HR 3
i . 0.1 e
! i e
m-s"w e e
/
i i ii !
!4 20 ' ---
"-Y ' '
'5 "0
4-- 40 v i i . s 6 , 60 ' ! i
' i+
100 ' i l l
' [!
0 ' ' ' O 50 100 150 200 250 300 350 400 450 500 INDICATED--TEWPERATURE (DEG,F) Figure 20. Reactor Coolant System Cooldown Limitations (Cooldown rates up to 100*F/hr) Applicable to Zion Units 1 and 2 for the First 20 EFPY (With Margins of 10*F and 60 psig For Instrumentation Errors)
. . _ . . . _ . -~ - . . -
4
. MATERtAL PROPERTY BASH
. CONTROLLING MATERIAL: CIRCUMFERENTIAL WELD WF-70
- 18'F INITIAL RTNDT
j ART AT 25 EFPY: 1/4T - 232*F 3/4T- = 184*F i 2500 7,o m g , ! , , , ; , j , 1 i i i f i i i ; 1 , , , , , , , , , ' i i i i i i i i i i i ! I j i i4 e
. e Jl i i i i ,
! , i i t i e i , i
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! 6 i i i i i i 6 i i '
i A " O ' ' i ' ' l if i !I i i i ! !
-- ' I ' ' '
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4 i i ! i i i I' I i
, , i
! ! i i
. , i , ! i , t . , .
4 ij ,,. i, 1 ii i , i !I ei i i i , i r
, 1 i i e i iii if; ii! i > >d 4000 , , ;; i i 1 i i if i i i ! , ,i 1 ,I
, ; i , ,, _ ,
i , i i i ,; , ; , ; i f i,,i , , , i i , , ,, 4
, ,i .
iiti i i, i i ! e
- ' '! ' ! if i is ,i si'! UNACCEPTABL" ! ! ' !
- 1750 ; , ; ll ; ll, lll OPEPATION l
!I
/, il ll, f
, i , . s .. iyi . i + i ! i,,
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i ii! i i! ! i ,', i i 1 i
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, ,i,
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, ; , , ,; ,,j i ! i4 , i i f i i ,,,i
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, e i; i ,,i i i i,i,
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- .i , i i i ,. w 1250 ' ' ' ' l 5 ,
' ' ' 1-.
E '! t i / ACCEPTABLE b
- y i ii = ! '! !
/
/
OPERATION E i E 1000 l' ,' ll' l t
,'/
o i i , ! , , l l ; i LJ f I i ! I i i i . ,,
*- 2 Fi
' ! i i i , ii E'. 0-
- 750 ,' ,' 4
,' d '
. i
. O 1 om .' , ,! ,' 5 : iil l l l ' fj% ( i i
. i ,
.,0 0 C00LDOWN RATES
, *F/HR , , i wm m "n7 '
y i i i 20 0 g i ' ' ' w s""w y A* f
/
^
, , i ,' i .'
i E ~1m @ W--p"'- 6t> , -[ l !!'! , . 100 T D P"P , i ,
! ;i t-4 ii , T, . ,
i ! i , i , i ; . ri ,
, , , i , , ,,;
i Ob1.' 50 100 150-
' ' ' I D, ' ,C ,
' 'I i 200 250 -300 350 4 ')0 - - 450 500 1.
INDICATED TEWPERATURE'(DEG.F)
- Figure 21.
Reactor Coolant System Cooldown Limitations (Cooldown-rates up to 100*F/hr) Applicable to Zion Units 1 and 2-for the First 25 EFPY (Witt Margins of 10*F and 60 psig For instrumentation-4 -Errors)
, - , , , v , - , e-a,,,,n-. , - - , . , , , - , - , - , - , , , - , - - - , , - , - - , , -a,s-~.--- , , n---..,o
< MATERIAL PROPERTY BASIS CONTROLLING l%TERIAL:
CIRCUMFERENTIAL WELD WF-70 INITIAL RTNDT 18'I ART AT 32 EFPY: 1/4T - 243*F 3/4T - 194*F 2500r, g n , , i . i 4 i , ,, 4 i iii i! i-, i ii i i i ! ' t i 4 * * *i iI e i
!44 -,iii,ii3 , ,i, t i i i i i i ! i i i i >
iii i ,i t i i ! i i f i i 1 <
'**0 ! ' ' ' ' '
i t : i - iieff i .
, , i
' - ' 4 ' ' '
! I i 'h ' ' '
t ! I t ! i i t i l1 i I j ! Il i
' i ' '
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, i i i ! i j i ,
i i i1 i i 1i i i ! ! ! i i
! I!1 ii ! i i i 6 i i i l
i , i , 46 . , f, , , , i i ! ' I i , 2000 > i t ,! , ! i i '
!i' ' ' ' ' ' ' ' i 4 ! If 8 1 i 4
) !
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.' ii
_' t l If Il l l lt i , , 1 ; i i , i ,, ! 4 diI ! ! ! j t i 1 - i i , 1750 , . i . .. UNACCEPTABLE if, i i J i i , i
- 1. U ' i +ii i ; i i , ~,
- i i i a > -
i OPERATION i , s >
,!1_,' ,'
- ~~
d, ![ _I i I l ' i i ,! ! ' , T
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{! I l f'II ! ! ' i i i i i , , i f f j !/' i j ! } } l 1 i Ii g .$g ! i
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. 1 4 i i i i i i i lii ! i i
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) ) i l i i ! / i i i
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' ' i i e
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a 1250 i i iii i
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)
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- f. i e iii t i
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' . i y l lli! ! !
4 , - ii ACCEPTABLE ~ ~ y ! f t 8 ;/ l OPERATION E 1000 l 'lll 1/i i i ;ie i o W !
! !ii
' '4
' +
r
/ j ll'H i
; i i i - ! ,
i g _ i
, i 4
ii i
. 7=*
a i , i i /*
)~
i i ! a i I
. gyr'.
i i' i ; i> t
/M/ t t ji 500 (C00LDOWNRATES
,*F/HR
/ww -
,- ff '
lll 0-M' _.,___ , 2 0
.sAr
's/^e y, <
, i ii 11
- f i f , ,
W 40 ' / ' i i ;i 250 ' 60 i_ j, , j ' ' ' i ,i
--- , ll 100 h.
i i t 0 ' ' ' ' i
, ei O 50 100 150 200
! i !
250 300 350 400 450 500 IN0iCATED TEWPERATURE (DEG.F) Figure 22. Reactor Coolant System Cooldown Limitations (Cooldown rates up to 100*F/hr) Applicable to Zion Units 1 and 2 for the First 32 EFPY (With Margins of 10*F and 60 psig For Instrumentation Errors) p _ _ _ _ _ _ _ _ - -- - -- -- -
- 8. REFERENCES
- 1. Regulatory Guide 1.99, Revision 2 " Radiation Embrittlement of Reactor Vessel Materials", U.S. Nuclear Regulatory Comission, May,1988.
- 2. Code of Federal Regulations, 20CFR50, Appendix G, " fracture Toughness Requirements", U.S. Nuclear Regualtory Comission, Washington, D.C.,
Federal Register, Vol. 48 No. 104, May 27, 1983.
- 3. Comonwealth Edison Letter, " Materials Data for Use in Developing Revised Zion Units 1 and 2 Reactor Pressure Vessel Heatup and Cooldown Limit Curves", by Thomas D. Spry, et al., dated May 21, 1992.
- 4. " Fracture Toughness Requirements", Branch Technical Position MTEB 5-2, Chapter 5.3.2 in Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Editle., NUREG-0800, 1981.
2
- 5. ASME Boiler and Pressure Vessel Code, Section III, Division 1 -
Appendixes, " Rules for Construction of Nuclear Power Plant Components, Appendix G, Protection Against Nonductile Failure", pp. 558-563, 1986 4 Edition, American Society of Mechanical Engineers, New York, 1986.
- 6. WCAP-10962, Ravision E, " Zion Units 1 and 2 Reactor Vessel Fluence and RTPTS Evaluations", J.M. Chicots, et al., December 1990.
- 7. WCAP-11247, "Heatup cud Cooldown Limit Curves for the Comonwealth Edison Company Zion Units 1 and 2 Reactor Vessel", H. Gong, et al., August 1986.
h APPENDIX A DATA POINTS FOR HEATUP AND C00LDOWN CURVES 4 (With Margins of 10*F and 60 psig for Instrumentation Errors) 1 5
CWE-COM 20 DEG-F/HR HEATUP RL'G,Gu!DE 1.99.REV.2 WITH MARGIN 05/15/92 THE FOLLOWING DATA WERE CALCutATEDFOR THE INSERVICE HynROSTATIC LEAK TESI MINIMUM INSERVICE LEAK IEST TEMPERATURE ( 14.000 fFPf) PRES $URE (PSI) TEMPERATURE (DEG.F ) 2000 332 2485 352 PRE 55UPE PRESSURE $7RE$$ 1 5 K1M (PSI 3 (PSI) (PSI SO RI.IN.) y, 2000 22234 92837 w 2485 27468 115765 E
- m. ___ __
- . . _ . _ _ . . _. . . _ . _ . . .m.. , _ . _ . . .. . . _ - . m ._ . , , . -, _. .. .. _-. .
I
-CWE.-CON 20DkG-F/HRHEATUPREG. GUIDE1,99.REV.2 WITH MARGIN 05/15/92 COMPOSITE CURVE PLOTTED TOR HEAIUP PROFILE 2 HE ATUP RAIE(5) (OE G. f /NR ) = 20.0
-IRRADIATION PERIOD
- 14'000 EFP YEAR $
! FLAW DEPTH,= (t-AOWIN)T . INDICATED INDIC AT E D ' ' INDICATED INDICATED INOICATED INDICATED , TEMPERATURE- PRESSURE ' TEMPERATURE PRESSURE L IE MPE RA TURE 'PRESSUGE '
.(DEG.F) .(PSI)' (DEG.F)' (PSI) - (OEG F ) (PSI) 1 85.000 424.28 21 185,000 526.04- 41 285.000 958.00 2 90.000! 426.64 22 190.000 .536,06- 42 290.000 1000.16 3 95.000 426.80 23 195.000.' 546 84 43 .295.000 1045.48 4- 100.000 '427.42 -24 200.000 558.42 44 300 000 1094;17 5 105.000 430.74. 25 205.000' '570.73 45 305.000 t144.94 6- 110.000- 434.76 24 210.000 584.12 46 310.000: 1897.11 7 115.000. '439.86 27 215.000 598.51 .47' 385.000 8253.04 8 120.000- 444.88 28 220 000 613.95' 48 320.000 ,1313.00 t- 9 125.000- 448.79 29 225.000- 630.45 49 ~325 000 1377 25
, 30 130.000 453.00 30 ' 230.000 648.34 50 330.000 1446.26 31 835.000 -457.58- . 31 -235.000 667.-38 51 335.000 1520.18
- 12. -140.000,- 462.37 32' 240.000 688.04 52 340.000 1599.38 13 145.000 ~467.59 33 245.000 710.20 53 345.000 1684.26 1 14 150.000 .473.21 34 250.000- 733.93- 54' .350.000 1775.04 i 15 155.000 479.14 '35 255.000 759.37 55 .355.000 1872 25 4 16 160.000 485.63 36 260.000- 786.97 56 360 000 1975.97
- 17. tCS.000 492.60 .37 ; 265.000' 816.37 57 ,365 000 2087s26
.18 170.000 500.I1 38 : 270.0001 848.15- 58 370.000 2205.69 19 175.000- ,508,17- 39 275.000 882.21 59" 375.000 2332 66 4
'20 180.000 516.84- 40 280.000: S18.76, 60 380.000 2467.81 tu
~ 1 4 k
.g 9 -?
I i-i T 1 n em vw . ~ o m < w
.. . _. . . . . ,._ . .m_ m -_ . _ . - . .._m. _ . .._-..,.m. . . ._mm.._.- a _ ._ . .. _ . . . . _ , . . , ._. ._ . .. u.._
CTE-COM 40 DEG-F/ttR HEATUP. REG. GUIDE 1.09.REV.2 CITH MARGIN 05/t5/92 COMPOSITE'. CURVE' PLOTTED'FOR HEATUP PROFILE 2 HE ATUP RATE (S ) ( DE G . F /HR ) = 40.0
- IRRADIATION PERIOD.= 1.14.000 EFP YEARS ~(
FLAW DEPTH + (1-AOWIN)T. INDICAiED INDICATED INDICATED INDICATED INDICATED TEMPERATURE-. PRESSURE INDICATED
-TEMPERATURE PRESSURE T E MPE R.t iURE PRESSURE (DEG.F)J (PSI) (DEG.F ) (PSI) (DEG.F) (PSI)
- . 1 '85.000 't29-"tS'
- .28 '185.000 513.23 41 285.000 2 M 958.00 90.000- .22 -190.000 527.05 42. 290,000 -1000.16 i 3 95.000 *t9-9? 23. 195.000 542.08 43 295.000 4 1045.48 l' 130.000- 486-444 -24 .
. 200.000' C58.24 44 . 300.000 1094.17 5 105.000" 6%/M 25 205.000 570.73 45 305,000 i 6 110.000 404.78 t146.49
-26 210.000 584,92 46- '310.000' 1995.44 7- 115.000 '405.83 . 27 215.000 598.51 47 3t5.000 .1247.45 8 120.000-- 408.07 28 220.000 '
' 630,45 613.95 48 320.000 1303.25 9 125.000 di1.49 29- 225.000' 49 325.000 1363,08
,.to' 130.000, 415 74- 30 230.000 648.34 Ss t t ..
330.000' s427.t1 135.000 420.99 31 235.000 667.38 51- 335 000 1495.74 4 '12 - 140.000 426.76' 32 . 240.000 688.04- . 52 :340.000 1569.33 13 145.000- .433.31' 33 ' 245.000, , 710.20' 53 345.000 1647.88 14 150.000 -440.60' 34- 250.000 733.93 54: 15 - 350.000 1732 50 t
- 155.000 '448.67; 35 . 255.000- - 759.37 55 355 000 . 1822 69 s
16> 160.000~ 457.40 "36u 260.000 786;97 56 360 000 .1919.40 17 165.000- '466.94 . 265.000 57
.37 E16,37 365:000 2022;33 18 '170.000 477,t1- l38 270.000' 848,15 .58 370.000 -2132.79
'19 ' 175.000 488.27 39 275.000 892.28 .59 , 375.000 2250.61 20 . 180.000 500.26 :. 40 .280.000 918.76 GO 330,000 2376.31
. 3:e LJ 4
k' b w 9 g .) y # V t- --m_ ___ -_'uv
. . . . _ . . . . _ _ . _ . . . . _ ._...m _. - - . . _ . . ---m. . . . . . . . m ..
7 r ir ,
~CWE-CD84 60 DEG-F/HR HEATUP REG. GUIDE-f.99 REV.2 WITH 9tARGIN 05/15/92
, cot 4POSITE-CURVE PLOTTED FOR HEATUP PROFILE 2 HEATUP RATEis) (DEG F/NRi
- 60 0
<r IRRADIATION PERIDO =- 84,000 EFP YEARS-FLAW DEP!H =..(t-AOWIN)T
+
INO!CATED - INDICATED-. . INOICATED ItOICATED TE84PERATURE PRESSURE' INDICATED INOICATED (DEG.F ) ; ' T E 84PE R A T URE PRESSURE ' T E 84PE R A IURE PRE S5t#R E
- (PSI)- - (DEG.F ) (PSI) : 10E G . F ) (PSI) 1- 85.000 494-9a 22 .190.000 467.25 42 2 90.000 .290.000 1000_16 3- '95.000-eftt-98 29 l195.000 479.68 '43 '295.000 1045.48 M - . 24 '200.000 493.23 44 100.000 300.000 1094.17 5
4-
?105.000 399-901 999-96 g,A 25 26
'205.000 507.89 45 305.000 t146.49 210.000 523.56 46 310.000' 6 110.000 300-04 . 27 215.000 t197.19 7 540.62 47 315.000 1245 68
. 115.000 999-ts , 28 220.000 558.98. 48 8 120.000 383.66- 29 320.000 1297.61 9 -225.000 578.63 49 325,000 13'53.27 125.000 '383,65 30 230.000 599.98 t to 130.000. 50 330 000 ~ 8 412 . 984 ' 384.72 31 235.000 622.67 11 135.000 386.94- . 3 2 '. 240.000. 647,31
. 5t' 335.000 1476 82 52- 340.000 12 140.000~ 390.04- 33 24S.000 673.63 '.53 1545.37
. 13 145.000' "394.11 34 345 000 1698.64 250.000 702.10 54 350.000 1696.89 14 150.000 -398.96 35 -255.000 732.54~ 15 -155.000 -404.67 36 355 000 1781.08-260.000' 765.21 360.000- 1870.83 16 160.000 419.'13 37: 265.000 800.51 - 57 17 165.000 .418.43 38 365.000 1966.79 270.000 838.29 58 370.000' 2069 26
' 98 170.000 '426.50 39 275.000 19 - 878.85 59 375.000 : 2178.93 175.000 ~435.33 40 280.000' 918.76 *
. 20. -180.000 -445.06 ' 41 60 ' .-380.000 2295.93 285.000-- 958.00: Et- 385.000- 2420.60
, . 21 185.000 '455.71-a Mi s i I. } l' ., , s
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'4 100.000' 999-06 25 .205.000 398.65- 46 310.000 942.24 I 5' '805.000- 383.24 26 210.000 409.13 47 315.000 994.5%
6 -t10.000 373.11- 27: 215.000 420.64 48 7 115.000 ' 364.78 - 28. 320.000 ^ 1050.84
'220.000 433.12 49 325.000 ti11 2S 8 120.000 357.84 .29 l225,000 446.82 50 330 000 1175.91 230.000
+
- 9. 125.000' 352.38 30 461.71 53 335.000 1245.ts 10 130.000 348.1 - 31- -235.000- 477.77- 52- 340 000 1319.40
<ti 135.000 345.07 32 240.000 495_26 53 345 000 1398.79
, 12 140.000 343.06 33' .245.000- 514.19 54 350.000 1483.86 13 145.000 342416. 34' 250.000' 534.51 55 355.000 1574.79 14 150.000 342.12 35 255.000 556.58 56 360.000 -1672.04 15 - 155.000 343,03 .36- 260.000 580.23 57 365 000 1776.03 16' 160.000 344.72 37 '265.000. 605.87' 58 370 000 IB86;e8 17 165.000 : 347:35'- '270.000 633;3t 59 '375 000 2005.42 18 170.000 350.80 .'39l 38- 275 ")OO 662.99- 60 380.000 -2138.77 19 175.000 "355.09- 40 - '280.000 694.82 61 385,000 2266.15 20 180.000. 360.20^ 241 '205.000- ~729.00 62 390.000 2388.95 2: 185.000 .366.16 42 290.000' 765.73 m
- }
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CWE-COM HEATUP CURVES REG. GUIDE t.99.REV.2 WiiH MARGIN 05/15/92 THE FOLLOWING DATA WERE CALCULATEDFOR THE INSERVICE HvDROSIATIL LEAK TEST. MINIMUM INSERVICE LEAK TEST TEMPERATURE ( 20 000 E F PV ) PRE SSL'1E (PSI) TE MPE R A TURE (DEG.F) 2000 341 2485 367 PRES 5URE- PRESSURE STRESS 1.5 K1M (PSI) (PSI) (PSI SQ RI.IN ) 2000 22134 92837 N 2485 2746S 195765 t I
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CWE-COM 20 DEG-F/HR HEATUP REG. GUIDE 1.99,REV.2 WITH MARGIN 05/t5/92 THE FOLLOWING DATA WERE CALCULATEDFOR THE INSERVICE HvDRUSTATIC LEAK it SI . MINIMUM INSERVICE LEAK TESY IEMPERATURE ( 25 000 EfPv) PRESSURE (PSI) IEMPERAIURE (DE G.F ) 2000 357
'2485 377 PRESSURE PRES $URE STRESS 1.5 K1M (PSI) (PSI) (PSI 50 RI.IN.)
3> 2000 22234 92837 e 2485 27408 115765 e 6
. . . . . . . . , . . . - . _ ~ . . , _ - , - . .,- .- - . .+. . . .--..w _ - , , . , . . - - sn .._ . . . 4 . .--
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'CWE-COM'20 DEG-F/HR HEAIUP. REG. GUIDE t 99.REV,2 WITH MARGIN 05/15/92 COMPOSITE' CURVE.PLDTIED FOR HEATUP PROFILE 2 Hf.ATUP RATE 45) ( DE G . F /HR ) = 2t L O IRRADIATION PERIOD = 25.000 EFP. YEARS FL AW DEPTH = (t-AOWINIT INOICATED INDICA TE D ' ' INDICATED INDICATED ' INDICATED INOICATED '
1EMPERA1URE PRE $$URE 1ENPERA1URE PRES $URE (OEG, F ) - f(PSI) EtMPERA1URE PRES $URE
' 1DEG. F ) (PSI) . - (DEG. F ) (PSI) 1 '85.000 *te-98 23. 195.000 499.69 45 305.000 2 : 90.000'- M.d 24 916.70
'3 95,000
'4tt-00 200.000 507.72 '46 '3to,000 955.79
*e9-99 205.000 516,36 '47 -395,000 ,
4 100.000 409.15- 26 997.79'
'210.000' 525.52 48 320.000 -1042,92 5 105,000 491.28 27 215.000 535.50 49 6 -110.000 413.90 28 325 000 1091.42
.220.000 546.23 50. 330 000 1142.4i i- :7 115.000 f417.47 29 225.000 >557.77 51 s' -;
8 120.000 421.39 335.000' t194.34 !
'30. 230.000 570 03 52 340.000 8250.03 9 825.000 : 425.87 31' 235.000 58 3.~ 3 7 53
-10 130.000 345.000 '1309.70
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-- 32 597.71 54 350.000 11 135.000 : 435.85 3 3 '.
83'3.53
-245.000 613.09 55 355.000 1442.29 12 140.000- '44%.06
-- 34 250.000' 629.53 56. 360.000 1515.73 I
13 145.000' 444.68 35 255.000 -647 34' 57 365.000 14- 1%94.64 150.000 448.57 36 260.000 666.30' 58 370 000 1679.Or 15 155.000 '452.76 -37 265.000 686.89 59 16 160.000- 457.26' 38 375.000 1769.41 270.300- 708.96 60- 380.000 .t866.13 17: 165.000 462.to 39 275.000 732.60 '69' 385 000 18 170.000 467.30 In9.64 50 280.000 .758.08 -390.000 2080.23 19 - ;175.000- D472,89 41- 62 ~ 285:000. 785.43 63 395.000 2196.29 20 '180.000 478.80 '41 290.000' .814 71 64 400.0001 2344.45 21 185 000 485,26 ' 4'A 295.000- 846.40 65- 405,000 22 190.000 492.21 44 2458.94 300.000 880.30 a 3= e e-* , e a ! t
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' COMPOSITE CURVE PLOTTED FOR HEATUP PROFILE 2 HEATUP RAIE(S) (DEG f/HRI'*
'40.0 IRRADIATION. PERIOD * ~.25.OOO-EfP YEARS +
= F t. AW DE P T H = (t-AOWIN)i' i- . INDICATED : INDICATED.. . INDICATED ]NDiCATED INDICAlf0 ' INDICATED ' TEMPERAIURE- ' PRESSURE- TFMPERATURE PRES $URE T E MPE RA IURE ' : PRE SSURE . (DEG.F ) :tPSI) 3(DEG.F). (PSil ' t DEG F ) (PSI) t '85.000.. *te-98 '23 '195.000 480.60 45 305.000 916.70 2 90.000 400-M]' - 24 '100.000' ; 492.20 46- 310.000 955.79
-4 3 , 95.000
.800.000..
N 39t-91
' g g,125 26' 205.000
- 210.000 "504.78 47 385,000 997.79 518.14. 48 320 000 1042.92 5< '105.000.' W l- .27 :215.000- 532.59 '49 325.000 ,1C91. 4 2 - i
~ 6 110.000 989-9 0 28 220.000 546;23 ' 50 330.000 tt43.53
- 7. ;i15.000 .385.69 29 225.000. 557.77 51 335.000 1193.11 8 .120.000- 386.52- 30 230.000 .570.03 - 52' 340.000?. L1244,90 9 '125.000 388.47- 31- 235.000 583.37. -
53 ;345,000 1300.31' 10 130.000 z 39i.13'- 32' '240.000 597.7t ~ 54 350.000 1359.75' +
-t1- 135.000' 394.55, 33 J245,000- 613.09 . 55 ' 355,000 1423.33' i; 12 't40.000 '398.52. . 34 '250.000 .629.53 56' 360.000- 9491.67 13:
145.000 .403.12 .35 255.000 647.34 57 ' 365.000 1564.75 147 :150.000 408.2e 36 260.000- 666.30 58 370.000' '1643.08-4 . 1 I5 " .155,000 413.89 37- "265.000.. '686.89 59 . 375.000 1726.98 1- 16 '160.000 -420.07 '38m = 270.000 : 708.96 . 60- 380.000 1816.71-i~ 17: .165.000 '426.86 39 - 275,000- 732.60 68 385.000 1912.64
'18 Lt70.000 434.09- 40 .. 280.000- 1758.08 ' 62 390 000 '20t5.31
- I' 19 175.000: 442.06 41 .285.000 785.43 63 395.000: 2124.88 :
!. : 20- 180.000 -.450.63. 42 290.000 814.71 - 64 . 400.000 '2242.04 [~ 28 1985.000a 459,92 43 295.000 846.40 65, 405.000; 2366.93'
- . 22 190.000 469.9i.- 44 '
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- CwE*COM 60'DEG-F/HR HEATUP REG.GulOE 1.99,Riv.2 WITH MARGIN F 05/15/92 i L i.
' COMPOSITE CURVE PL' offed FOR.HEAIUP PROFILE 2 pt ATUP RATE ( 5) (DEG.F/HR) = 60,0 '
LIRRADIATION PERIOD.=al 25 000 EFP YEARS Ft.AW DEPIH = {t-AOWINIT lr j ' INDICATED -INDICAIED P ltKllC AI E D ,INOICAff0 F INDICA TE D INOlCAIED 7 EMPER ATURE _ : PRE SSURF.
' . TEMPERAIURE PRESSURE
' (OEG.F)l -(PSI). -(DfG;F) (PSI);
. TEMP 8RATURE. PRESSURE e ( Dt G '. F ) t PSI 9,
. t '85.000 M 123 195.000
- 2 426.C% 45 305.000- 916i70 90.000' 400-99 200.000 435.59 3 95.000 ~ M '25 - 205 000 46 <310.000
- 955.79 .
446.03 '47 1315,000 997.79
.4- .100.000 Set-t7 '26 '210.000 457.31 5
6
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,M,dl 27 4 215.000 ~469.50 - 49 48 ;320.000 325lO00-l 10424S2'
- 1091.42; 910.000' <
39tH4 28 - '220.000.. ?: '7- 115;O00 - . SethSt 482.53 ' 50 330.000 9i43.53 29 - 225,000 496.70 51
- 8. 120.000 SE P H .30 335.000- t195.42 230.000 511,97 52
- 1. 9 .425.000 869-4rG 31 235.000 528.29
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. IRRADIATION PERIOD = ..f4.000 EFP YEARS FLAW OEPTH = AOWIN.T INDICATED INDICATEC ' INDICATED INDICATED aNDICATED INDICATED TEMPERATURE' PRESSURE ~ T E MPE RA TURE PRESSURE TEMPERAIURE PRESSURE-(DEG.F)- (PS' ) (DEG.F) (PSI) 1DEG.F)~ (PSI) 1 85.000 1291.87 15 155.000 -351.35 ': 29 225.000 532.35-2 90.000 294.14 . 16 '. 160.000 358.80 ~ 30 3 95,000 '296.67 230.000 '554.24
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