ML20211N989
| ML20211N989 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 08/31/1986 |
| From: | Gong H, Palusamy S WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20211N947 | List: |
| References | |
| WCAP-11247, NUDOCS 8612180365 | |
| Download: ML20211N989 (53) | |
Text
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WCAP-11247 WESTINCHOUSE CLASS 3 CUSTOMER DESIGNATED DISTRIBUTION BEATUP AND COOLDOWN LIMIT CURVES FOR THE COMMONWEALTH EDISON COMPANY ZION UNITS 1 AND 2 REACTOR VESSEL R. Gons Reviewed:
C. C. Heinecke August 1986 Approved:.-
Iaw ?
,M
- //
/
S. S. p lusamy, Manager Structural Materials Engineering Frepared by Westinghouse for the Comonwealth Edf son Company i
Work performed under Shop Order CEZJ-135-Although information contained in this report is nonproprietary, no distribution shall be ande outside Westinghouse or its licensees without the customer's approval.
Westinghouse Electric Corporation Nuclear Energy Systema F.O. Box 355 Pittsburgh, Pennsylvania 15230 8612180365 06120S PDR ADOCK 05000295 PDR P
1.
INTRODUCTION Heatup and cooldown limit curves are calculated using the most limiting value of RTNDT (reference nil-ductility temperature). The most limiting RTNDT of the material in the core region of the reactor vessel is determined by using the preservice reactor vessel material properties and estimating the radiation-induced ARTNOT. RTNDT is designated as the higher of either the drop weight nil-ductility transition temperature (TNOT) or the temperature at which the material exhibits at least 50 ft -lb of impact energy and 35-mil lateral expansion (normal to the major working direction) minus i
60*F.
RTNOT increases as the material is exposed to fast-nautron radiation. Thus, to find the most limiting RTNDT at any time period in the reactor's life, ARTNOT due to the radiation exposure associated with that time period must be added to the original unirradiated RTNOT. The extent of the shift in RTNDT is enhanced by certain chemical elements (such as copper, nickel and phosphorus) present in reactor vessel steels. Westinghouse, other NSSS vendors, the U.S. Nuclear Regulatory Commission and others have developed trend curves for predicting adjustment cf RTNDT as a function of fluence and copper, nickel and/or phosphorus content. The Nuclear Regulatory commission (NRC) trend curve is published in Regulatory Guide 1.99 (Effects of Residual Elements on Predicting Radiation Damage to Reactor Vessel Materials)(1).
Regulatory Guide 1.99 was originally published in July 1975 with a Revision 1 being issued in April 1977. Currently, a Revision 2 to Regulatory Guide 1.99 is under consideration within the NRC. The chemistry factor, "CF" (in*F),
a function of copper and nickel content identified in Regulatory Guide 1.99, Revision 2 is given in Table I for welds and Table 11 for base metals (plates and forgings). Interpolation is permitted. The value, "f", given in Figure 1 is the calculated value of the neutron fluence at the location of interest (inner surface, 1/4T, or 3/4T) in the vessel at the location of the postulated 19 The fluence factor is l
defect, in n/cm2 (E > 1 MeV) divided by 10 determined from Figure 1.
1 1
mu so-o.eeo,
Given the copper and nickel contents of the most. limiting material, the radiation induced ARTNOT can be estimated from Tables I and II and Figure 1.
The maximum fast-neutron fluence (E > 1 MeV) at the inner surface, 1/4 T (wall thickness), and 3/4 T (wall thickness) vessel locations are given as a function of full-power service years in Figures 2 and 3 for the vessel core regions of Zion Units 1 and 2. respectively. The data for all other ferritic materials in the reactor coolant pressure boundary are examined to insure that no other component will be limiting with respect to RTNOT-Ti.e current plant heatup and cooldown curves for the Zion Units 1 and 2 plants were generated in 1979 for 8 effective full power years (EFPY) of operation.
Presently the Zion plants have exceeded 7 EFPY of operation necessitating the generation of a new set of curves. The adjusted reference nil-ductility temperatures used will be based on the February 1986 proposed version of Regulatory Guide 1.99 Revision 2.(2) The original 8 EFPY curves were done to Regulatory Guide 1.99 Revision 1.
A comparison of RTNDT (reference nil-ductility temperature) vs. EFPY when degulatory Guides 1.99 Revisions 1 and 2 (with and without surveillance capsule data) are used are given in i
i Figures 4-7 for Zion Units 1 and 2 at the 1/4T and 3/4T locations of the most limiting material. Note that the 8 EFPY cooldown curves using revision 1, i
with a 1/4T adjusted reference temperature of 206*F is limiting when compared to the 16 EFPY cooldown curves using revision 2 with surveillance i
capsule data (in which the 1/4T adjusted reference temperature would be 196* F). As a result the original 8 EFPY cooldown curves done to revision 1 are now applicable for up to 16 EFPY since the criteria is now revision 2.
In any event the cooldown curves will be presented to be complete; in addition, use of the cooldown curves based on revision 2 would be less limiting in terms of plant operatic s.
2.
FRACTURE TOUGHNESS PROPERTIES i
l The preirradiation fracture-toughness properties of the Zion Units 1 and 2 reactor vessel materials are presented in Ta:
s III and IV respectively. The fracture-toughness properties of the ferritic material in the reactor coolant pressure boundary are determined in accordance with the NRC Regulatory Standard Review Plan.[3] The postirradiation fracture-toughness properties l
..n i. -
2
]
1 of the reactor vessel beltline material were obtained directly from the Zion Units 1 and 2 Vessel Material Surveillance Programs.
3.
CRITERIA FCR ALLOWABLE PRESSURE-TEMPERATURE RELATIONSH PS The ASME approach for calculating the allowable limit curves for various heatup and cooldown rates specifies that the total stress intensity factor, Kg, for the combined thermal and pressure 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 fracture toughness curve, defined in Appendix G of the ASME Code.E43 The KIR curve is given by the equation:
KIR = 26.78 + 1.223 exp [0.0145 (T-RTNDT + 160)}
(1) where KIR is the reference stress intensity factor as a function of the metal temperature T and the metal reference nil-ductility temperature RTNDT. Thus, the governing equation for the heatup-cooldown analysis is defined in Appendix G of the ASME CodeE43 as follows-CKIM + kit < KIR (2) where KIM is the stress intensity factor caused by membrane (pressure) stress kit is the stress intensity factor caused by the thermal gradients KIR is a 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 conditions during which the reactor core is not critical ion.io. oso.
3
At any time during the heatup or cooldown transient, KIR is determined by the metal temperature at the tip of the postulated flaw, the appropriate value for RTNOT, and the reference fracture toughness curve. The thermal Stresses resulting from 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, from these, the allowable pressures are calculated.
For the calculation of the allowable pressure-versus-coolant temperature during cooldown, the Code reference flaw is assumed 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 measurement of reactor coolant temperature, whereas 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 ID. This condition, of course, is not true for the steady-state situation.
It follows that, at any given reactor coolant temperature, the AT developed during cooldown results in a higher value of l
KIR at the 1/4 T location for finite cooldown rates than for steady-state l
operation. Furthermore, if conditions exist such that the increase in KIR exceeds Kit, the calculated allowable pressure during cooldown will be greater than the steady-state value.
l l
The above procedures are needed because there is no direct control on j
temperature at the 1/4 T location and, therefore, allowable pressures may l
unknowingly be violated if the rate of cooling is decreased at various
~
intervals along a cooldown ramp. The use of the composite curve eliminates 1923s 10 860404 4
this problem and. insures conservative operation of the system for the entire cooldown period.
Three separate calculations are required to determine the limit curves for finite heatup rates. As is done in the cooldown analysis, allowable pressure-temperature relationships are developed for steady-state conditions as well as finite heatup rate conditions assuming the presence of a 1/4 T defect at the inside of the vessel wall. The thermal gradients during heatup produce compressive stresses at the inside of the wall that alleviate the tensile stresses produced by internal pressure. The metal temperature at the crack tip lags the coolant temperature; therefore, the KIR for the 1/4 T crack during heatup is lower than the KIR for the 1/4 T crack during steady-state conditions at the same coolant temperature. During heatup, especially at the end of the transient, conditions may exist such that the effects of compressive thermal stresses and lower KIR's do not offset each other, and the pressure-temperature curve based on steady-state conditions no longer represents a lower bound of all similar curves for finite heatup rates when the 1/4 T flaw is considered. Therefore, both cases have to be analyzed in order to insure that at any coolant temperature the lower value of the allowable pressure calculated for steady-state and finite heatup rates is obtained.
The second portion of the heatup analysis concerns the calculation of pressure-temperature limitations for the case in which a 1/4 T deep outside surface flaw is assumed. Unlike the situation at the vessel inside surface, the thermal gradients established at the outside surface during heatup produce stresses which are tensile in nature and thus tend to reinforce 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 tensile and increase with increasing heatup rates, each heatup rate must be analyzed on an individual basis.
Following the generation of pressure-temperature curves for both the steady-state and finite heatup rate situations, the final limit curves are produced by constructing a composite curve based on a point-by-point comparison of the steady-state and finite heatup rate data. At any given l
l 1923s 10-400404 5
o temperature, the allowable pressure is taken to be the lesser of the values taken from the curves under consideration. The use of the composite curve is necessary to set conservative heatup limitations because it is possible for conditions to exist wherein, over the course of the heatup ramp, the controlling condition switches from the inside to the outside and the pressure limit must at all times be based on analysis of the most critical criterion.
Then, composite curves for the heatup rate data.and the cooldown rate data are adjusted for possible errors in the pressure and temperature sensing instruments by 60 psig and 10*F respectively.
Finally, the new 10CFR50(5] rule which addresses the metal temperature of the closure head flange and vessel flange regions is considered. This 10CFR50 rule states that the metal temperature of the closure flange regions must i
exceed the material RTNOT by at least 120*F for normal operation when the pressure exceeds 20 percent of the preservice hydrostatic test pressure (621 psig for Zion Units 1 and 2). Tables III and IV indicate that the limiting RTNDT of 60*F occurs in the vessel flange of Zion Unit 2; therefore, the minimum allowable temperature of this region is 180*F at pressures greater than 621 psig.
4.
ADJUSTED REFERENCE TEMPERATURE This section determines the most limiting material in the Zion Units 1 and 2 core beltline regions based on the adjusted reference temperatures (ART) of the materials. Regulatory Guide 1.99 Revision 2E23 will be used. From Regulatory Guide 1.99 Rev. 2 the ART for each material in the beltline is given by the following expression:
ART = Initial RTNOT + ARTNOT + Margin (3)
The initial RTNOT 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 RTNOT for the material in question are not available, generic mean values for that class of material may be used if there are sufficient test results to establish a mean and standard deviation for the class.
im iee==>
6
ARTNDT is the mean value of the adjustment in reference temperature caused by irradiation and should be calculated as follows:
aRTNOT surface = (CFif(0.28-0.10 log f)
(4)
To calculate ARTNDT at any depth (e.g., at 1/4T or 3/4T), the following attenuation formula is used:
ARTNOT = [aRTNOT surface]e-0.067x (5) where x (in inches) is the depth into the vessel wall measured from the vessel inner (wetted) surface.
CF (*F) is the chemistry factor, a function of copper and nickel content.
CF is given in Table I for welds and in Table II for base metals (plates and forgings). Linear interpolation is permitted.
In Tables I and II
" weight-percent copper" and " weight-percent nickel" are the best-estimate e
values for the material, which will normally be the mean of the measured values for a plate or forging or for weld samples made with the weld wire heat number that matches the critical vessel weld.
l Finally, Margin = 2 /oI2 g62',
(6) standard deviation of the initial RTNOT; if a measured where 01
=
value of initial RTNOT is used a1 = 0.
If a generic value of initial RTNDT is used, og should be obtained from the same set of data, standard deviation of the shift in RTNDT ca
=
l (ARTNDT); for welds, ca = 28'F and l
for base metals, og = 17'F.
ca need not exceed 0.5 times the mean value of ARTNDT surface however. Also, if surveillance data is
.available, og may be cut in half.
i ART's will be calculated for 9.5 EFPY for which the surface fluence = 6.4 x 18 2
I 10 n/cm for Zion 1 (see Figure 2) and the surface fluence = 6.2 x ion, io.
o.o.
7 i
~
18 2
10 n/cm for Zion 2 (see Figure 3). For Zion 1 it is realized that based upon the material properties (5 Cu, 1Ni and RTNDT) given in Table III the limiting base metal material would be the lower shell plate 9-144-2 (heat no. C3799-2). The ART will also be computed for the intermediate shell plate 8-144-1 (heat no.87835-1) since surveillance capsule data exits for that plate.
Baseplate Initial Surface (b)1/4T(c) 3/4T(c)
I Number RT ECu ")
1Ni(a) CF(d) ART ARg ART NOT g
g 8-144-1 5'F 0.12 0.49 80.8 70.69 61.37 46.25 9-144-2 20*F 0.15 0.50 104.5 91.43 79.38 59.82 (a) See Table III (b) See Equation (4); values are calculated for 9.5 EFPY (c) See Equation (5); values are calculated for 9.5 EFPY (d) From Table II e
Since the initial RTNOT values are measured, og = 0 to calculate the margin. Also, oo = 17'F for the base metal. Therefore, margin
= 2 /or
,32 2
= 2 /0 + 172 = 34*F I
Baseplate 9.5 EFPY ')
9.5EFPY(*)
Number Margin 1/4T ART 3/4T ART 8-144-1 34*F 100.37' 85.25' 9-144-2 34*F 133.38*
113.82*
(e)Seeequation(3).
Fcr the Zion 1 weld metal, it is seen that the limiting weld metal based upon the material properties (% Cu, %Ni, RTNDT) given in Table III would be the circumferential intermediate to lower shell weld WF-70 (heat 72105).
Surveillance data is available for this weld metal, ion. io-o 8
For the limiting weld metal, from Table III, %Cu = 0.32, %Ni = 0.56, Initial RTNDT = 0*F From Table I, CF = 196.6, and from equations (4) and (3),
ARTNOT surface = 172.01*F 1/4TARTNDT = 149.3*F 3/4TARTNOT = 112.55'F For the margin, since the initial RTNOT is not measured but is a generic mean value defined by the PTS rule (6), the standard deviation of the initial RTNDT is also obtained from the PTS rule, at = 17*F. Also, ca = 28'F for welds (note that 1/2 RTNDT surface is greater i
than 28'F so that 28'F is used for oa). Therefore, margin =
2 /172 + 282 = 65.5'F
~
Then using equation (3), the 9.5 EFPY 1/4T ART = 214.8'F and the 9.5 EFPY 3/4 ART = 178.05'F for the Zion 1 limiting weld metal.
For Zion 2, based upon the material properties (%Cu, 1Ni, RTNDT) given in Table IV the limiting base metal material could be either the intermediate shell plate 8-152-2 (heat no. C4007-1), the lower shell plate 9-152-1 (heat no. 8800o-1), or the lower shell plate 9-152-2 (heat no. 88040-1). Note that surveillance data exists for intermediate shell plate 8-152-2.
Baseplate Initial Surface (c)1/4T(d) 3/4T(d)
Number RT
%Cu(a) %Ni(a) cp(b) ART ARbOT ART NDT NOT NDT 8-152-2 22*F
.12
.53 81.6 70.67 61.35 46.24 9-152-1 10*F
.12
.54 81.8 70.85 61.51 46.36 9-152-2 2*F
.14
.52 96.4 83.49 72.48 54.63 (a) See Table IV.
(b) From Table II.
(c) See equation (4); values are calculated for 9.5 EFPY.
(d) See equation (5); values are calculated for 9.5 EFPY.
m 2..-
9
As before, since the initial RTNOT values are measured, og = 0 to calculate the margin, and og = 17'F for the base metal (note that 1/2RTNOT surface is greater than 17'F so that 17'F is used for og). Therefore, from equation (6), margin = 34*F.
Baseplate 9.5EFPY(*)
9.5 EFPY ')
I Number Margin 1/4T ART 3/4T ART 8-152-2 34*F 117.35' 102.24' 9-152-1 34*F 105.51' 90.36' 9-152-2 34*F 108.48' 90.63' (e) see equation (3).
For the Zion 2 weld metal it is seen that the limiting weld metal based upon the material properties (%Cu, %Ni, RTNDT) given in Table IV would be the longitudinal lower shell weld WF-70, heat 72105. Surveillance data is available for this weld. The material properties for this weld are:
5 Cu = 0.32
% Ni u 0.56 Initial RTNDT = 0'F The properties are identical with those for the weld considered for Zion Unit 1.
As a result the Zion 2 limiting weld ART's can be taken to be the same as the Zion 1 limiting weld ART's:
9.5 EFPY 1/4T ART = 214.8'F 9.5 EFPY 3/4T ART = 178.05'F Note that the Zion 1 9.5 EFPY fluences are slightly greater than the Zion 2 9.5 EFPY fluences making the above ART's slightly conservative for Unit 2.
= = io.
10
ART's Using Surveillance Data:
For Zion Unit 1. capsule T data is taken from references [7] and [8], Capsule U data from reference [8]. and Capsule X data from reference [9]. The surveillance data is summarized below:
Capsule T Capsule U Capsule X Material ARTNOT/ Fluence ARTNDT/ Fluence ARTHDT/ Fluence 18 Base Plate 87835-1 60/2.89 x 10 85/8.92 x 1018 19 100/1.2 x 10 (longitudinal) 19 18 19 Base Plate 87835-1 25/2.69 x 10 60/8.92 x 10 80/1.5 x 10 (transverse) 18 Weld Metal 101/2.89 x 10 188/8.92 x 1018 19 195/1.5 x 10 (Heat 72105) 2 Units of ARTNDT are 'F and of fluence are n/cm.
For Zion Unit 2, Capsule U data is taken from references (7) and (10] and Capsule T data is taken from reference (10). The surveillance data is summarized below:
Capsule U Capsule T Material ARTNOT/ Fluence ARTNDT/ Fluence 18 18 Base Plate C4007-1 38/2.85 x 10 75/8.7 x 10 (Longitudinal) 18 19 Base Plate C4007-1 49/3.6x10 90/1.1 x 10 (Transverse) 18 19 Weld Metal (Heat 72105) 128/3.6 x 10 175/1.1 x 10 2
Units of ARTNOT are 'F and of fluence are n/cm,
(
ForZionUnit1, Plate 8-144-1(HeatNo.B7835-1):
l i.n...
11
Measured Fluence (*)
'ARTNOT Fluenge Factor Surface n/cm FF ARTNOT X FF Capsule T (Long.)
60*F 2.89 x 1018
.6607 39.M CapsuleT(Trans.)
25'F 2.89 x 1018
.6607 16.52 Capsule U (Long.)
85'F 8.92 x 1018
.968 82.28 CapsuleU(Trans.)
60*F 8.92 x 1018
.968 58.08 Capsule X (Long.)
100'F 1.2 x 1019 1.0509 105.09 Capsule X (Trans.)
80*F 1.5 x 1019 i
1.1123 88.98 i
SUM = 390.59 i
(a) FF = f(0.28 - 0.1 log f) where f = fluence /10 19 (7)
Sum of the squares of the fluence factors = 5.0887 CF =
= 76.76 l
The 9.5 EFPY Zion 1 surface fluence = 6.4 x 1018 n/cm2(Figure 2);using equations (4) and (5),
ARTNOT surface = 67.16'F 1/4TARTNOT = 58.3*F 3/4TARTNOT = 43.94*F For the margin, since surveillance data is used, og = 17'F/2 =
8.5'F for base metals (note that 1/2 RTNOT surface is greater than 17'F). ot = 0 since the initial RTNOT for this material is a measured value. Then using equation (6), margin = 17'F.
Since the intial RTNOT = 5'F for plate 8-144-1, using equation (3), the following 9.5 EFPY ART's are obtained:
1/4T ART = 80.3*F 3/4T ART = 65.94*F
= = ie-e 12
For the Zion Unit I weld metal, heat 72105:
Measured Fluence (b)
ARTN3T F'Ler"e fact:r 2
Surface n/cm FF ARTNOT X FF Capsule T 101*F 2.89x1018
.6607 66.73 Capsule U 188'F 8.92x1018
.968 181.96 Capsule X 195'F 1.5x1019 1.1123 216.89 SUM = 465.58 (b) See equation (7).
Sum of the squares of the fluence factors = 2.6108 CF =
= 178.3 Using the same Zion 1 surface fluence as before and equations (4) and (5),
ARTNDT surface = 156'F 1/4TARTNDT = 135.4*F 3/4TARTNOT = 102.1*F For the margin, since survie11ance data is used ca = 28'F/2 =
14*F for welds (note that 1/2 RTNOT surface is greater than 28'F).
For og, as before, since a generic value of the initial RThDT is used, og = 17'F. Then using equation (6), margin = 44.05'F.
I Since the initial RTNDT of the weld (heat 72105) = 0*F using equation (3) the following 9.5 EFPY ART's are obtained:
1/4T ART = 179.45'F 3/4T ART = 146.15'F For Zion Unit 2, Plate 8-152-2 (Heat No. C4007-1):
mme-13
...,, -. - -.., - - - - -.. -, -.,. - -.. - -. ~..
0.
Measured Fluence (a)
ARTNDT Fluenge Factor Surface n/cm FF ARTNDT X FF 18 Capsule U (long.)
38'F 2.85x10
.6571 24.97 Capsule U (Trans.)
49'F 3.6x1018
.7179 35.18 18 Capsule T (Long.)
75'F 8.7x10
.9609 72.07 Capsule T (Trans.)
90'F 1.1x1019 1.0266 92.4 SUM = 224.62 (a)seeequation(7)
Sum of the squares of the fluence factors = 2.924.
224 CF = g.62 = 76.82 The 9.5 EFPY Zion 2 surface fluence = 6.2 x 1018 n/cm2 (Figure 3); using equations (4) and (S),
ARTNDT surface = 66.5'F 1/4T RTNDT = 57.7'F 3/4T RTNDT = 43.5'F As before for the margin, og = 17'F/2 = 8.5'F for base metals (note that 1/2 RTNOT surface is greater than 17'F), and c1 = 0 since the initial l
RTNDT for this material is a measured value; hence, margin = 17'F (using equation (6)).
Since the RTNOT initial = 22*F for plate 8-152-2, using equation (3),
the following 9.5 EFPY ART's are obtained:
1/4T ART = 96.7'F 3/4T ART = 82.5'F.
i
..n.io-o.o.
14
For the Zion Unit'2 weld metal, heat 72105:
Measured Fluence (b)
ARTNOT Fluenge Factor Surface n/cm FF ARTNDT X FF Capsule U 128'F 3.6 x 1018
.71792 91.89 Capsule T 175'F 1.1 x 1019 1.0266 179.66 SUM = 271.55 (b) see equation (7)
Sum of the squares of the fluence factors = 1.5693 CF =
= 173.04 Using the same Zion 2 surface fluence as before and equations (4) and (5),
ARTNOT surface = 149.86*F
~
1/4TARTNDT = 130.1*F 3/4TARTNDT = 98.06*F For the margin, as before, oA = 28'F/2 = 14*F for welds (note that 1/2RTNDT surface is greater than 28'F), and as before, since a generic value of the initial RTNDT is used, c1 = 17'F. Then using equation (6), margin = 44.05'F.
Since the initial RTNOT of the weld (heat 72105) = 0*F, using equation (3) the following 9.5 EFPY ART's are obtained:
1/4T ART = 174.2*F 3/4T ART = 142.1'F.
l ion, io-een o.
15 l
l...
.-------~. --
A summary of the adjusted reference temperatures for 9.5 EFPY are given below:
Zion 1 Material 1/4T RTNDT 3/4T RTNOT Intemediate Shell Pl. 8-144-1 100.37'/80.3'*
85.25'/65.94'*
l Lower Shell Pl. 9-144-2 133.4*
113.8*
Intermediate to lower Shell 214.8'/179.45'*
178.05'/146.15'*
Circumf. Weld (heat 72105)
Zion 2 Material 1/4T RTNDT 3/4T RTNOT Intermediate Shell Pl. 8-152-2 117.35'/96.7'*
102.24*/82.5 **
Lower Shell P1 9-152-1 105.51' 90.36' Lower Shell P1 9-152-2 108.5*
90.63*
Lower Shell Longitudinal Weld 214.8'/174.2'*
178.05'/142.1**
i (heat 72105)
- 8ased on surveillance capsule data.
Note that regulatory guide 1.99 rev. 2 indicates that if the ART determined using surveillance capsule data is higher than the ART determined otherwise, l
-the surveillance capsule ART should be used.
If the surveillance capsule ART is less, than either value may be used. Hence, referring to the sumary of the ART's, for Zion Units 1 and 2 the most limiting material is the weld metal, heat 72105(specificallytheZion1intermeidatetolowershell circumferentialweld),withmaterialproperties:
= = ie-een 16 i
+.. _,, -. -..,,. - _. _
e L
'O.32% Cu m
0.56%(Ni '
0*F initial RTNOT The 9.5 EFPY. ART's for this limiting material is:
I 1/4T RTNOT = 179.45*F 3/4T RTHDT
- 146 IS*F The heatup and cooloown limit curves will be based on the material properties for this limiting material.
The 15, 16, and 32 EFPY heatup and cooldown curves are based on the same diMting weld metal material. The ART's for these EFPY's are noted on their respective heatup and cooldown curves.
5.
HEATUP AND COOLDOWN LIMIT CURVES Limit curves for normal heatup and cooldown of the Primary Reactor Coolant
, System have been calculated using the methods discussed in Section 3.
The s
j derNation,ofthelimitcurvesispresentedintheNRCRegulatoryStandard
- Revfew Plan.[3]
s Transition temoerature shifts occurring in the pressure vessel materials due
~
to radiation exposu're have been obtained directly from the reactor pressure vessel surveillance program.
The heatup and cooldown curves to be presented are applicable to both units 1 and 2 even though the.fluences for the two units are slightly different. This is possible because the maximum fluence of the two units is used in developing the curves. This of course results in a very slight conservatism in the curves for the unit 1with slightly lower fluences.
9.5 EFPY heatup curve:s for 20* F/hr, 40* F/hr, 50 F/hr, and
-\\
100*F/hN are given in Figures 8 to 11, re.spectively. The 9.5 EFPY l
' m. io-mm 17 i
i
cooldown curves for cooldown rates of 0 *, 20 *, 40 *, 60* and
~
~
100*F/hr are given in Figure 12.
16 EFPY neatap curves for 20'F/hr, 40*F/hr, 60'F/hr, and 100*F/hr are given in Figures 13 to 16 respectivelf. The 16 EFPY cooldown curves.are given in Figure 17.
32 EFPY heatup curves for 20*F/hr, 40*F/hr, 60*F/hr ~ and 100*F/hr dhe given in Figures 18 to 21 respectively. The 32 EFPY cooldown i
curses are given in Figure 22.
i 15 EFPY heatup curves for 20*F/hr., and 60*F/hr. are given in Figures 23.and 24, respectively. The 15 EFPY cooldown curves are given in Figure 25.
These curves were later specifically requested'by Commonwealth Edison.
Allowable combinations of temperature and pressure for specific temperature
' change rates are below'and to the right of the limit lines shown on the heatup
$ndcooldowncurves. The reactor must not he'made critical until 5
pressure-temperature combinations are to the right of the criticality limit line shown on the heatup curves. This is in addition to other criteria which must be met before the reactor is made critical.
The leak test limit curve shown on the heatup curves represent minimum temperature requirements'at the leak test pressure specified by applicable codes (3,4].
The heatup and cooldown curves presented define limits for insuring prevention of nonductile' failure.
im,io w m 18
.w,
,w m-
TABLE I CHEMISTRY FACTOR FOR WELOS, 'F Copper.
Nickel. Wt. %
Wt. %
0 0.20 0.40 0.60 0.80 1.00 1.20 0
20 20 20 20 20 20 20 0.01 20 20 20 20 20 20 20 0.02 21 26 27 27 27 27 27 0.03 22 35 41 41 41 41 41 0.04 24 43 54 54 54 54 54 0.05 26 49 67 68 68 68 68 0.06 29 52 77 82 82 82 82 0.07 32 55 85 95 95 95 95 0.08 36 58 90 106 108 108 108 0.09 40 61 94 115 122 122 122 0.10 44 65 97 122 133 135 135 0.11 49 68 101 130 144 148 148 0.12 52 72 103 135 153 161 161 0.13 58 76 106 139 162 172 176 0.14 61 79 109 142 168 182 188 0.15 66 84 112 146 175 191 200 0.16 70 88 115 149 178 199 211 0.17 75 92 119 151 184 207 221
~
0.18 79 95 122 154 187 214 230 0.19 83 100 126 157 191 220 238 0.20 88 104 129 160 194 223 245 0.21 92 108 133 164 197 229 252 0.22 97 112 137 167 200 232 257 0.23 101 117 140 169 203 236 263 0.24 105 121 M4 173 206 239 268 0.25 110 126 148 176 209 243 272 i
0.26 113 130 151 iB0 212 246 276 0.27 119 134 155 184 216 249 280 0.28 122 138 160 187 218 251 284 0.29 128 142 164 191 222 254 287 0.30 131 146 167 194 225 257 290 0.31 136 151 172 198 228 260 293 0.32 140 155 175 202 231 263 296 0.37 144 160 180 205 234 266 299 0.34 149 164 184 209 238 269 302 i
0.35 153 168 187 212 241 272 305 0.36 158 172 191 216 245 275 308 0.37 162 177 196 220 248 278 311 0.38 166 182 200 223 250 281 314 t
0.39 171 185 203 227 254 285 317 0.40 175 189 207 231 257 288 320 i
l 19
TA8LE !!
CHEMISTRY FACTOR FOR 8ASE METAL, 'F
Wt. %
0 0.20 0.40 0.60 0.80 1.00 1.20 0
20 20
'20 20 20 20 20 0.01 20 20 20 20 20 20 20 0.02 20 20 20 20 20 20 20 0.03 20 20 20 20 20 20 20 0.04 22 26 26 26 26 26 26 0.05 25 31 31 31 31 31 31 0.06 28 37 37 37 37 37 37 0.07 31 43 44 44 44 44 44
+
O.08 34 48 51 51 51 51 51 0.09 37 53 58 58 58 58 58 0.10 41 58 65 65 67 67 67 0.11 45 62 72 74 77 77 77 0.12 49 67 79 83 86 86 86 0.13 53 71 85 91 96 96 96 0.14 57 75 91 100 105 106 106 0.15 61 80 99 110 115 117 117-0.16 65 84 104 118 123 125 125 0.17 69 88 110 127 132 135 135 0.18 73 92 115 134 141 144 144 0.19 78 97 120 142 150 154 154 O.20 82 102 125 149 159 164 165 0.21 86 107 129 155 167 172 174 0.22 91 112 134 161 176 181 184 0.23 95 117 138 167 184 190 194 0.24 100 121 143 172 191 199 204 0.25 104 126 148 176 199 208 214 0.25 109 130 151 180 205 216 221 0.27 114 134 155 184 211 225 230 l
0.28 119 138 160 187 216 233 239 0.29 124 142 164 191 221 241 248 0.30 129 146 167 194 225 249 257 0.31 134 151 172 198 228 255 266 0.32 139 155 175 202 231 260 274 l
0.33 144 160 180 205 234 264 282 0.34 149 164 184 209 238 268 290 0.35 153 168 187 212 241 272 298 0.36 158 173 191 216 245 275 303 i
0.37 162 177 196 220 248 278 308
~
0.38 166 162 200 223 250 281 313 0.39 171 185 203 227 254 285 317 0.40 175 189 207 231 257 288 320 20
TABLE Ill ZION UNIT 1 REACTOR VESSEL TOUGHNESS DATA MATERIAL Cu Ni P
MOT NOT T
CIDFONENT HEAT NO.
TYPE (1)
(1)
(1)
("F)
("F)
(*F)
QT-t B )_
CLOSURE HEAD 00E 89094-2 A5338. CL.1
.14
.55
.012 20 90 30 77 CLOSURE HEAD SEG.
C5086-1
.09
.54
.014 10 32 10 103 CLOSUREHEA5SEG.
38793-3
.09
.52
.012 10 53 10 96 I8I 26 55 96
.69
.010 55 CLOSURE HEAD FLANGE 123W323 A508. CL. 2 I8I
-2 7
131 VESSEL FLANGE 123V236
.06
.68
.004 7
I8I 27 60 19 IEET N0ZZLE ZT3600-1
.12
.68
.009 60 I8I 41 60 82 IE ET N0ZZLE ZT3600-2
.11
.67
.009 60 I8) 103 60 77 IE ET N0ZZLE ZT3592-1
.10
.66
.011 60 IEET H0ZZLE ZT3592-2
.11
.67
.010 60(a) 51 60 62 60 *I 60 60 86 I
l OUTLET N0ZZLE ZT3592-3
.11
.68
.010 0UTLET N0ZZLE ZT3592-4
.11
.68
.009 46(a) 16 46 85 OUTLET N0ZZLE ZT3600-3
.10
.67
.011 60(a) 52 60 82 I
60 *I 46 60
>63 OUTLET N0ZZLE Z13600-4
.11
.68
.011 UPPER N0ZZLE SHELL 123V426
.06
.75
.005 10 43 10 115 N
LOWER N0ZZLE SHELL ZV3300
.06
.83
.008 20 72 20 87 INTER. SHELL C3795-2 A5338. CL. 1
.12 49
.010
-10 70 10 85 INTER. SHELL 37835-1
.12
.49
.010
-20 65(Actual) 5 115(Actual)
LOWER SHELL 37823-1
.13 48
.013
-20 56 (Actual)
-4 115.5 (Actual)
LOWER $ HELL C3799-2
.15
.50
.010
-20 80 (Actual) 20 116 (Actual)
BOTTOM HEAD TRANS.
RING ZV3779 A508. CL. 2
.09
.71
.010 10 60 10 92 BOTTOM HEAD 00E 87777-1 A5338. CL. 1
.62
.015
-30 33
-27 84 INTER. TO LOKR SHELL GIRTH WELD SEAM W70(b)
SAW
.32
.56
.017 0(a) 0 INTER. SHElL LONG.
0,)
0 g
WELD SEAM W4(C)
SAW
.29
.55
.013 INTER. SHELL LONG.
IO 'I 0
WLD SEAM W8(d)
SAW
.29
.55
.013 LOWER SHELL LONG.
WELO SEAM W8(d)
SAW
.29
.55
.013 0(a) 0 (a) ESTIMATED USING METH005 0F U.S.NRC NUREG-0800 BRANCH TECleIICAL POSITION MTES 5-2. JULY.1981 (b) WELO WIRE HEAT NO. 72105 AhD LINDE 80 FLUX LOT NO. 8669 (c) WELD WIRE HEAT NO. 8Tl?62 AND LINDE 80 FLUX LOT NO. 8597 (d) WELO WIRE HEAT NO. 8T1762 AND LINDE 80 FLUX LOT NO. 8632
TABLE IV ZION UNIT 2 REACTOR VESSEL TOUGHNESS DATA RT "I
g(35 MIL T
NOT MATERIAL Cu Ni P
NDT "F)
(*f)
(rt.L8)
CIN OMENT HEAT NO.
TYPE (1)
(1)
(1)
("F)
CLOSURE HEAD DOME 89094-1 A5338. CL.1.14
.55
.012
-20 71 11 72 CLOSURE HEAD SEG.
C4787-IA
.13
.62
.008 0
30 0
88 CLOSURE HEAD SEG.
C5086-2
.09
.54
.014 30 45 30 88 CLO5URE HEAD FLANGE 124W609 A508. CL. 2
.08
.70
.010 12(a)
-13 12 105 I
.12
.74
.010 60
- 33 60 19 32 48
>78 48(a)
.11
.70
.009 IKET N0ZZLE ZT3885-1
.11
.58
.012 60 43 60 82 IK ET N0ZZLE ZT3885
.11
.56
.011 43 31 43 78 48 60
>84 60(a)
IEET N0ZZLE ZT3885
.11
.56
.012 OUTLET N0ZZLE ZV3930
.12
.66
.010 58 20 58 93 OUTLET N0ZZLE Zv3930
.11
.65
.011 48 15 48
>80 28 55 84 55(a' OUTLET N0ZZLE ZV3930
.12
.57
.011 OUTLET N0ZZLE ZT3885-4
.11
.57
.013 60 41 60
> 61 y
UPPER N0ZZLE SHELL 2D3940 A508. CL. 2
.07
.62
.008 10 65 10 106 LOWER N0ZZLE SHELL Zv3855
.09
.66
.008 10 70 10
>80 INTER. SHELL 88029-1 A5338. CL.1.12
.51
.010
-10 82 22 81 INTER. SHELL C4007-1
.12
.53
.010 10 82 (Actual) 22 94 (Actual)
LOWER SHELL B8006-1
.12
.54
.010 10 68 10 89 LOWfR SHELL 88040-1
.14
.52
.008
-10 62 2
92 BOTTOM HEAD TRANS.
RING 3V-433 A508. CL. 2
.09
.76
.010 0
43 0
87 BOTTOM llEAD DOME C4007-2 A5338. CL. 1.12
.53
.010
-20 60 0
72 l
INTER. TO LOWER SHELL O 'I 0
I GIRTH WELD SEAM SA1769(b)
SAW
.26
.60
.019 INTER. SHELL LONG.
SAW
.23
.63
.019 0(a) 0 ICI WELD SEAMS WF29 LOWER SHELL LONG.
IO *I 0
WELD SCAMS WF70(d)
SAW
.32
.56
.017
[
f-(a) ESTIMATED USING METHOD OF U.S.NRC NUREG-0800 BRANCH TECHNICAL POSITION MTE8 5-2. JULY 1981 (b) WELD WIRE HEAT NO. 71249 AND LINDE 80 FLUX LOT NO. 8738 (c) WELD WIRE HEAT NO. 72102 AND LINDE 80 FLUX LOT NO 8650 l
(d) WELD WIRE HEAT NO. 72105 AND LINDE 80 FLUX LOT NO. 8669
,Y
. N I$
l
2.C k
1.0 I
i t.s i,,,,,,,,,,,,,,uiu 7
,e i
I
-g
.3 cii
.7
,,iiin
q
,g
.is'
.'I a
o 5
e O
4 e
i 11 m
p:
'i 0
3 jji c 3 e
W
',i\\
l l l\\
2 w
w l
u
,\\
y 8
I '
s s
I p
i
,8 t
p l
6 l
v' l*
.1 i
1 2
3 4
5 6 7891 2
3 4
5 6 7891 2
3 4
5 8 7 891 l
git gie ges gae 8
Fluence, n/cm (E > 1 MeVI FIGURE 1 FLUENCF. FACTOR FOR USE IN THE EXPftESSION FOR ORT8s07
e*
9 N
'-:t C } --ha
_7pgai L5 i T.;3==.c'--==r=-
.1-._=. L._..
=-- %
._...: h, _2_L ^=_: i :.-E : z _- _
-fitfitr_-nti-' -
4_ __ _ _
g-
_;=
7_____
.-_e__
p
.,_._9 p __
6'*
w S...
4..
3..
2...
SURFACE.,,,,,,
l l
l
- J ' ---
, 1 I
1
. I T
. 1 I
y I
p I
i I t t i I i i i.
t I
, 1 a I
, i 1 i1 - p i
y 3
'I i
it 1 I i i l I ' i l 1 i e l l,
- i I
.' i i l 8 1l l 6 i i i
- I e i i
{ # j.,
,l
[
i,
.e.
. i,... i i
i 1/4T -
i i i i i i :
_+$_.-
S..
_____.-j y- -
6..
u
__- ~
^
2, --1_EE 3lllE :l IE!M
---'- = m +-Me e +s =-J k--E2
- + =s=- M E
=
g W
E 3..
~
d l
3._
J' 3/4T s-
- D W
m s
I I
I I
1 E
I I
I I
I W
I I
I
- I '
I i I
I T # 1 I
I
- i. A i
~ i
. l n I
f L
l J
- I I
i 1
- 1 I il l
I I
I J il
- i+
i i f14 i i liei-
- 1
- I'
' I t
i e i 4 +
4 9 e l't i l I5i 6 #1 ia l*
1
? I I
l
,g i F e16 l4J. e 6 y 6iIie l- - {.* i-4 - t l g_ J J g, _:F '{ 8.
- --*_~?
Q---------- J ':= 7. 4. _.y- -i 5' I. _ j =.. _- w-u-__== ;--q- : M..%.-_= - l=+m_ _-- =_ __ W y G. l _ _.^2 4 ~ 3. l I l l 2. I 1 Y I. 2 1 . 1 I .I I., a.... 1 a i I I I I l l 5 ) I I I 3 3 A j 50 3 I I I 3 3 3 5 5 5 I l l jI E I no IFIGURE 2 FAST NEUTRON FLUENCE (E.1 Mey) AS A FUNCTION OF FULL POWER SERVICE' LIFE (EFPY) FOR ZION UNIT 1 a ~ ' ' ' ' ' - ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' 10 0 5 to 15 20 25 30 35 EFPY 24
1 .a j o I. ~ re-r=-- r- . aw .-7;ngr e ; g--- . :1 _; __x. .m r= z= 1 ' = a _yg ,, ;.;.,_ ; :._.w.-
- m,=_ y
.gp= , w. y,,, l= '- i.___~L' _.L..i : - . t ~ ~~ k.+ii+.___--kk------- 6... .__.-.--..._g.. m -_.- ~ ~- r - = = 1 5... 4... 3... l 1 2... SURFACE l 1/4T 19.e.. S.. 7.. 6.. 5 S-1 4.. ~ w W y s.. i 3/4T k w 4 j m.? e. 7 s. I S. I 4 I. 4 I i 2. IGURE 3 FAST NEUTRON FLUENCE (E>1 MeV) A5 A FUNCTION OF FULL POWER SERVICE LIFE (EFPY) FOR ZION UNIT 2 ~ IE 0 5 1 1 0 5 30 35 EFPY 25
I i i .{ _ l F.q l _.p.-4.. . _ _.. _ l._.q_ _l__l_..l.4_. q. .. J... . 9 ._. 4.. . y_ p. y MGEW$1I $W/ ,/ / o ~ .o,. j . _g q ...k. _._... ... /Q O "j~'~% mLArsn+1 I I. t i 4 g I
- q. q_
_i... 7 w i i g 6J n -- g (.*1~1j~ T '~~ ~ f ' 2. '~?"T ' 'i' ~ ... C_ _... ' '"i
- * " ' " c'*"' "i t '
.T '. t'. "" 'l t i .. i - .,i t ._.. _.7 7.. j. .j 7 .. j j.. .p..]. .. l.
- p.. j..4
'_".? oa i of .lk ..i 25 m . W N_)"{. ? M&M! FIGURE 4 RTNDT versus EFPY at the 1/4 Thickness Wall Location of Zion Unit 1 ?6
J ---{- l 1 l 1l'lt j l. l-i jl j. il "i i M . i ;. {. j. ,i _ i i .{ . 4 .j..!. l .I 1.l .[ 4 E 4" T'Jed,ar>ik { _-/lM,W 3 m- -o l I p-. i i k'.- . -~t .o'jy# ' l. e.3-
- ,.a I
J... ,h / (9 ____ um___. ~ ~ ~ ' 6 .l.. -f f y -4W5 'Af 4 ..I <as l ..~ S-...._'/ h,,, s pl l A 'ed w c f l . t.. -i-. i ..f. .. _g <p..I. a s paio_. r / 99 #1s ir. / a .cy... ..... _ '..Md.f f ~ 4 k _ _l. I _.q_ ....q_. _ _ .__.p ~ _ _ -. l_ I a r m. .. ifs be. fer>- A.. q......_ 3a..... -.K.- L lao.. ~ t l I t i1 r i FIGURE 5 RTNDT versus EFPY at the 3/4 Thickness Wall Location of Zion Unit 1 27
_[. l ...._ {. q_ . _...._q . _.____j MC L. .1_. l ^^ . L' _.. 7 / w... Arn Lw ree ke/. ) ./ ..._-f. ,o f ,9. _. e $L ..b .....l /A ./ 1 l .- Q~'7.. \\-Am.fe wec.;,91.# RWA d l_ 1 i L x I Z.- r l.. ."g.. i . ~.. s m . j.._t .j. .n 7 .. y.. p. . _1. i .. _g i ge o p , g. l. .g I. - . Jro,Gbac, /.of ;AWA .h g %m' ..1 .a l I i i ~ i 7 4 l l !. .j. /10 i .. j. ..... ]. l;. i. .l j._l l.. lll. .l l l . _.i l.. j E ' '.'." J~. to. /r l. i ui E . t 30, 1 Jf. l +1mr d I !\\i i n i i i i ,,,iii i i I i i i FIGURE 6 RTNDT versus EFPY at the 1/4 Thickness Wall Location of Zion Unit 2 28
e..... I i l l I l l d 4 I I i I l y Ad'A G8' 1.09 Arg i i \\ l -(F M i \\ ,s,,---"'- s,--' ,s tgg h 4o) s m-nme __Au /* r \\ _,y ^
- n~~
,, []C,/r ~ t-.n i ik ,s a '~ /" L ,/" o f s l h ".$Jr-S*.T !~ 'W A* V y i,- l i a: I 3 la - nr.. frr>A-.- 1r.._ >Q. ss l Ja-rrer q r l I iI ! I I i i FIGURE 7 RTNDT versus EFPY at the 3/4 Thickness Wall Location of Zion Unit 2 e 29
PlTEP'Al PRSPEFTY KACIS : Cor. trolling Material
- Weld Metal (Heat 72105)
Cepper Centent
- 0.32 WTt Nickel Content
- 0.56 WTt Init:s; FT
- 0*F g7 RT After 9.5 EFPY
- 1/4T, 180*F NDT
- 3/4T, 146'F Curve appli::stle for heatup rates up to 20*F/hr*for the service period up to 9.5EFFY ond contains margins of 10 F and 60 psig for possible instrwent errors A
I II III I I IIII i ,1 a I II III II I I i3 f f LEAK TEST LIMIT j ttso i l l J A 1 2000 l / UNACCEPTABLE. / / ~ OPERATION a R ) l E r r I 1500 / / IIN r r HEATUPPTESUT ACCEPTABLE'---- 4 TO 20 F/iR N / OPERATION ::::: I g/ l 1000 e. k ~~ CRITICALITY LIMIT / 750 / BASED ON INSERVICE l / NYDR0 STATIC TEST l TEMPERAnlRE (325 F) l 500 FOR THE SERVICE PERIOD i UP 10 9.5 EFPY 190 0 SO 100 150 200 250 300 350 400 450 500 INDICATED TEMPERARTRE (DEC. F) I I FIGURE 8 Zion 1 and 2 Reactor Coolant System Heatup limitations Applicable for up to 9.5 EFPY and Heatup Rates up to 20*F/HR 30
Pl? EPI A!_ PPSPEm MSIS : I Cor.trelling Paterial : Weld Metal (Heat 72105) Copper Centent
- 0.32 WT; Nickel Cor. tent
- 0.56 WT; Ir.:::a1F.3, 0*F RT After 9.5 EFPY : 1/4T, 180*F N0t
- 3/4T,146 'F Curve applicat3e for heatup rates up to 40*F/hr*F and 60 psig for for the service period up to 9.5EF7Y and contains rargins of 10 possible instrwent errors l
l 1I I I I II I II I I s Ii i, I I I II II I II I I I J 11 [ I' i LEAK TEST LIMITS 1890 ~ l } } l l 2000 l i S UNACCEPTABLE / f g OPERATION J J i 1750 / / f f 1 I i 1500 MEATUPgATESUP ACCEPTABLE. - 1 TO 40"F/HR OPERATION 's e r -u 2 ~1 I F 1890 5 f H / i 1000 l CRITICALIA LIF.IT 730 BASED ON INSERVICE r HYDROSTATIC TEST r TEMPERATURE (325 F) ii e Soo FOR THE SERVICE PERIOD ~ UP 10 9.5 EFPY 250 'o so too isc 200 aso soo sso soo 45o soo 'l i INDICATED TEMPERATURE UIED. F) i FIGURE 9 Zion 1 and 2 Reactor Coolant System Heatup Limitations Applicable for up to 9.5 EFPY and Meetup Rates up to 40*F/HR I 31
PlTEP* Al PM PERTY RACIS Cor.trollirg Materia; : Weld Metal (Heat 72105) Copper Center.t
- 0.32 WT%
Ni:kel Centent
- 0.56 WT Ir.itisi PT;,7
- 0*F RT After 9.5 EFPY 1/4T, 180*F NDT
- 3/4T,146'F Curve applicable for heatup rates up to 60*F/hr*for the service period up to 9.5EFFY and contains margir.s of 10 F and 60 psis f:r possible instrrent errors 2500 iiiiiiiiiiii i
i II I I I I I i i I i5 I 1 1 LEAK TEST LIMIT- / l l , m 2250 l l l l J I 1 r r [ UNACCEPTAB:.E / / OPERATION 1750 / / m g i r r Q l l ,ga r r l NEATUPpTESUP / l ACCEPTABI.E< - 10 60 F/HR N / OPERATION I l 1250 f / i i b 1000 g E / 750 / -CRITICALITY LIMIT / SASED ON INSERVICE / HYDROSTATIC TEST 900 / TEMPERATURE (325 F) FOR THE SERVICE PERIOD UP 10.. 9. 5 EFPY Io S0 100 150 too 250 300 350 400 450 500 l INDICATED TEMPERATURE (DEG. F) FIGURE 10 Zion 1 and 2 Reactor Coolant System Heatup Limitations Applicable for up to B.5 EFPY and Heatup Rates up to 60*F/HR l 32 l l
PrEn Al PRSDE m RLCIS : Cor.trellirg Material : Weld Metal (Heat 72105) Cepper Center.t
- 0.32 WTL Nickel Cor. tent
- 0.56 WT; Ir.;t:a; ?! g 0*F RT After 9.5 EFPY : 1/4T. 180*F NDT
- 3/4T. 146'F Curve applicat3e for heatup rates up to 100' F/pr for the service period up to 9.5Ern and contains margins of 10 F and 60 psig for possible instrwent errors iI I I I I I II II I s
1. ,1 I i i i i i i i i i ii 1 n LEAK TEST LIMITN / l l1 2250 NJ ) i I [ [ l l i 2000 I I UNACCEMABLE_ l / j 1750 OPERATION I 1 l P.! r r 'M .HEATUP RATES UP TO 100'F/HR \\ / / I1250 1 I h/ / ACCEPTAB:.E OPERATION j j l h 1000 / / g e 1 -CRITICALITY LIyJT SASED ON INSERVICE r / HYDROSTATIC TEST g f TEMPERATURE (325 F) ~ FOR THE EERVICE PERIOD UP 70 9.5 EFPY 250 0 SO 100 150 200 250 300 350 400 450 SOC INDICATED TDfERATURE (DED. F) I; FIGURE 11 Zion 1 and 2 Reactor Coolant System Heatup Limitations Applicable For up to 9.5 EFPY and Heatup Rates up to 100 F/HR 33
l MATEP'Af PROPESTY RACIS ; Cor. trolling Material : Weld Metal (Heat 72105) Cepper Centent
- 0.32 WT*.
Nickel Centent
- 0.56 WT*
Init:a1 P.T
- 0*F g7 RT After 9.5 EFPY : 1/4T,180*F NDT
- 3/4T,146'F Curves applicable for cooldown rates up to 100'[/hr for the service period up to 9.5EFM and contains margins of 107 and 60 psig for possible instrunent errors 2500 i
f I 2250 r 2000 r i I UNACCEPTABLE 1750 OPERATION _a / b / ACCEPTABLE 1500 w --__.0PERATION, I ac f' 1250 j t h 1000 / M Jr g r C00gDOWNRATES . eE m 750 F/HR
- y
--~ 500 -- 0x fffy __ 20 ~ n -- 40 --- -' ](( 250 :: 60< --100-l 0 50 100 150 200 250 300 350 400 450 500 INDICATED TEMPERATURE (DEG. F) FIGURE 12 Zion 1 and 2 Reactor Coolant System cooldown Limitations Applicable For up to 9.5 EFPY and cocidown rates up to 100 F/hr i 34 i l l1___.,,____.._.__.
MATEDTai PROPERTY RAtIS : -Controlling Materisi Weld Metal (Heat 72105) Copper Content
- 0.32 bmi Nickel content
- 0.56 nrT*.
Initial PT
- 0*F g
RT After 16 EFPY
- 1/47,198 E g
- 3/4T,160 *F Curve applicable for heatup rates up to 20 F/hr"F and 60 psig for for the service period up to 16 EFPY and contains margins of 10 possible instrtment errors
.I.I I.I.I I..II.I.I I I r LEAK TEST LIMIT-l l ggg n>I I I f I I l r' r Q mo i UNACCEPTABLE l / OPERATION f l ,7g I I / / / / ACCEPTABLE: g i OPERATION < 12M W VP pTC) UP j l r r I g T lth T/m A m I 1000 1 }' 7M CRIE, CALM LIMIT BASED ON INSERVICE / HYDROSTATIC TEST l 300 j TEMPERATURE (344 F) e i FOR THE SERVICE PERIOD UP 70,16 EFPY 250 0 Sc 100 150 200 350 ace 350 soc esc Soo INDICATID TEMPERATURE (DED. F) FIGURE 13 Zion 1 and 2 Reactor Coolant System Heatup limitations Applicable i f,or up to 16 EFPY and Heatup Rates up to 20*F/HR 1 35 i 7.-_._,_
9 MATERTAf~ PROPERTY RARIS : Controlling Material : Weld Metal (Heat 72105) Copper Content
- 0.32 WTi Nickel Content
- 0.56 Wit Initial RT
- 0*F NDT 1/4T, I?8}F RT After 16 EFPY g
3/4T,160 Curve applicable for heatup rates up to 40*F/hr for the service period up to 16 EFPY arid contains margins of 10 F and 60 psig for possible instnment errors I I I I II I I I II I i s s I I I I I I I I I II I r 1 1 LEAX TEST LIMIT _ j j t290 ~ i '*l n I J f f I J J 2000 l l UNACCEPTABLE r r j OPERATION / ) E 17S0 r' r' ,g ACCEPTABLE" HEATUPRATESUP ( f -OPERATION - 70 40"F/HR w nj j I g1250 / r' 6 ~ E'1000 2 CRITICALITY LIMIT 780 BASED ON INSERVICE / NYDR0 STATIC TEST TEMPERATURE (344 F) See FOR THE SERVICE PERIOD UP TO 16 EFPY 150 0 90 100 1H 200 250 NO 3H 400 450 S00 INDICATED TIMPERATURE (DEG. F) FIGURE 14 Zion 1 and 2 Reactor Coelant System Heatup Limitations Applicable for up to 16 EFPY and Heatup Rates up to 40*F/NR 36
MATERTAL PR3PERTY RARIS : Weld Metal (Heat 72105) -Controlling Material : Copper Content
- 0.32 WTi Nickel Content
- 0.56 WTi Initial RT
- 0*F g7 RT After 16 EFPY
- 1/4T, 198 g
- 3/4T,160 F Curve applicable for heatup rates up to 60 F/hr for the service 4
period up to 16 EFPY and contains margins of 10 F and 60 psig for l possible instrument errors i I I I i iI I II I i
- I i
i i1i LEAK TEST LIMIT- / ~ f l i t w r 2250 l l I I n l i I 2000 ) UNACCEPTABLE / / OPERATION 17S0 j f l i G i y i j l 1500 2 w j l 12M i { J J ACCEPTABLE-- HEATUP GATES UP / OPERATION :: 10 607/rfR v I F 1000 7 6 l ~ 2 mx l 7S0 N hITICALITYLIMIT BASED ON INSERVICE HYDROSTATIC TEST,F) 500 TEMPERATURE (344 FOR THE SERVICE PERIOD UP TO 16 EFPY 250 1 ,i i i, i i g 0 50 100 150 200 250 300 350 400 450 SOC INDICATED TEMPERATURE (DED. F) FIGURE 15 Zion 1 and 2 Reactor Coolant System Heatup Limitations Applicable for up to 16 EFPY and Heatup Rates up to 60*F/HR 37
MATEFIAL PROPERTY MASIS : Weld Metal (Heat 72105) Controlling Material : Copper Content
- 0.32 WTi Nickel Content
- 0.56 WT; Initial RT
- 0*F g
1/4T,198'E RT After 16 EFPY
- 3/4T,160"F Curve applicable for heatup rates up to 100* F/pr for the service period up to 16 EFPY and contains umrgins of 10 F and 60 psig for possible instrunent errors l I I I I I l 1 1 1 1 i
1l l l I I iI I I I I I I l r l 1 [ LEAK TEST LIMI1L l l ttso %l l l i I i 2000 l UNACCEPTABLE I / gyg OPERATION l R E i i 1 isoo HEATUP RATES UP r r i, ~ TO 100*F/HR \\ j ) ACCEPTABLE. s / OPERATION ' isso / / g l l 5 1*** / / m i j ~ 1s0 j x f 'N I 2RITICALITYLIMIT s 500 f BASED ON INSERVICE HYDROSTATIC TEST TEMPERATURE (344*F) 25e FOR THE SERVICE PERIOD UP TO 16 EFPY I I O 50 100 150 200 250 300 350 400 450 500 INDICATED TEMPERATURE (DEC. F) FIGURE 16 Zion 1 and 2 Reactor Coolant System Heatup Limitations Applicable For up to 16 EFPY and Heatup Rates up to 100"F/HR 38
x .m. a. ...as u MATERIAL PROPEftTY BASIS : ' Controlling Material : Weld Metal (Mest 72105) Copper Content
- 0.32 WTL Nickel Centent
- 0.56 W';
- n;t:al RT
- 0*F ET 1/4T,198'[F RT After 16 EFPY g
3/4T,160 Curvesapplicableforcooldownratesupto100{Fand60psigfor /hr for the service period up to 16 EFPY and contains margins of 10 possible instrunent errors 2500 i j i i I i 2250 [ l I i I l 2000 / I 1 UNACCEPTABl.E 1750 OPERATION / G ~ E 1500 / w A / - ACCEPTAB;.E---- 1250 OPERATION " ) 1000 l r M J g' i M 750 J f %DOWN RATES . z r, i F/HR l / s%% J ~"
- Lf//
) ( SH
- o-
< n, -u s - 20.-- -v s
- 40-
'~ / ~~ 250
- 60 100
~ T l l 00 SO 100 150 200 250 300 350 400 450 S00 i INDICATED TEMPERATURE (DEG. F) FIGURE 17 Zion 1 and 2 Reactor Coolant Systen cooldown Limitations Applicable For up to 16 EFPY and cooldown rates up to 100 F/hr 39
Pl?EFIAL PEOPEFTY KACIS : Cor.trollir.g Material : Weld Metal (Heat 72105) Cepper Centent
- 0.32 WT%
Nickel Cor. tent
- 0.56 WTt Initial PT
- O'F g-FT After 32 EFPY
- 1/47, 224 'F g7
- 3/4T,180 *F Curve sp;1icable for heatup rates up to 20*F/hr*for the service period up to 32 EFFY and contains margins of 10 F and 60 psic fer possible instreent errors I I I I I I I II a
1 i 1 I I I I I II I 1 I I ~ LEAK TEST LIMIR I l 2250 N T I l i l 2000 i l I G 1750 UNACCEPIABLE j i g OPERATION / / j i I 1500 / / I I [ HEA"UP tea WP / / ACCEMABLL "D M N OPERATION,l 1250 h [ , a $ 1000 i E H -CRITICALITY LIMIT 750 BASED ON INSERVICE HYDROSTATIC TEST TEMPERA 11)RE (370 F) FDR THE SERVICE PERIOD 500 s ' UP 70 32 EFPY I 250 'o so too 150 200 250 soo no 400 45o soo INDICATED TEMPERATURE (DEL. F) FIGURE 18 Zion 1 and 2 Reactor Coolant System Heatup Limitations Applicable for up to 32 EFPY and Heatup Rates up to 20*F/HR 40
P;TE:1 Af PF2PECTV WIS _: Cor.trellir.g Material
- Weld Metal (Heat 72105)
Cep;er Cc.9ter.t
- 0.32 WTt Nicke: C:r.ter t
- 0.56 WTL Ir. t:a1 P!g_
- 0*r FT7~' After 32 EFPY
- 1/4T, 224 'F i
i
- 3/4T, loo'r i
Curve ap;11 cat 3e for heatup rates up to 40*F/hr*for the senice period up to 32 EFFT and contains r.srgins of 10 F and 60 psig for possible instrwent errors i i I I II I I I I. I. ,1 I I I I 1 1 ,1 i o i LEAK TEST LIMIT. 'N m. iI 2250 w I 4 r r I 1 ; I ii a 2000 I UNACCEPTABLE / 1 o OPERATION i i j 0S0 i i l w 1 i i y l l 1500 / / MI %IU UP / / ACCEPTABLE 4 12M ,/ j OPERATION i s i m 9 1000 m I CRITICALITY LIMIT i N BASED ON INSERVICE HYDROSTATIC TEST / TEMPERATURE (370*F) j l 300 FOR THE SERVICE PERIOD UP TO 32 EFPY l 250 O i 0 SO 100 150 200 250 300 350 400 450 500 INDICATED TDfERATURE (DEG. F) I FIGURE 19 Zion 1 and 2 Reactor Coolant System Heatup Limitations Applicable 0 for up to 32 EFPY and Meetup Rates up to 40 F/NR 41 ~.-. -
..e W EPIAL PS?PELTv M IS : Cor.trellir.g Materia! : Weld Metal (Heat 72105) Cc;;er Centent
- 0.32 WTi
!!!c W Cor. tent
- 0.56 WTL Ir.it:a1 PT coF g_
FT After 32 EFPY
- 1/4T, 224 'F g7
- 3/4T,180
- F Curve ap;11 cat 2e for heatup rates up to 60'T/hr*for the service period up to 32 EFFY and contains margir.s of 10 F and 6C ps:E f:
possitIe instrsent errors iI I I I I II I I I I i r
- r i! I I I 1 1 i i I ai I I I I 1
I 'I LEAK TEST' LIMIT / / / -/ j j 22M I ( { l I f J J 2000 / / UNACCEPTABLE OPERATION [ / h 1750 2 r i w I { W h ggo HEATUPgATESUP [ [ TO 60 F/HR N J ACCEPTABLE D OPERATION t -w ,gge l f h '"- CRITICALITY LI C m 3 i M 1000 BASED ON INSERVICE E HYDROSTATIC TEST TEMPERAnlRE (370 F) 750 FDR THE SERVICE PERIOD UP 10 32 EFPY 500 / 250 i 0 SO 100 150 200 250 300 350 400 450 S00 INDICATED TEMPERATURE (DEG. F) FIGURE 20 Zion 1 and 2 Reactor Coolant System Neatup Limitations Applicable for up to 32 EFPY and Heatup Rates up to 60*F/HR 42
PJTD' Af PROPUT! KACTS ; ~ Controlling Material : We d Metal (Heat 72105) Cc;;tr Center.t
- 0.32 WTt Nickel Centent
- 0.56 WTt
!r.;t:a; F! g 7 0*F RT After 32 EFPY
- 1/47, 224 'F GT
- 3/47,180 'F Curve applicable for heatup rates up to 100' F/pr for the service period up to 32 Ef7Y and contains margins of 10 F and 60 psig f:r possible instraent errors I I III II I I I II I I I a
i.!, 3 I I I I I I i 1 I I I I I 1 f I LEAK TEST LIMIT s / 2250 d l l i f J J i 2000 1l 1 a j g i r b' i UNACCEPTABLE OPERATION i i I1500 I I / / HEATUP M1ES L? / / TO 100*F fMR N 8 1230 N/ / ACCEPTABLE Fh OPERATION I t >g I f i E 1000 .~ / / - CRITICAL M LIV.:T / BASED OK INSERVICE / 750 h7DROSTATIC TEST TEMPERATURE (370'F) FDR ThE SERVICE PERICD UP TO 32 EFPY / 250 00 50 100 150 200 250 300 350 400 450 500 INDICATED TEMPERATJRE (DED. F) FIGURE 21 Zion 1 and 2 Reactor Coolant System Heatup Limitations Applicable For up to 32 IFPY and Heatup Rates up to 100"F/HR 43
1 plTEPIAf PROPEFTY RACTS : Cor. trolling Material : Weld Metal (Heat 72105) Copper content
- 0.32 WT%
Kickel Content
- 0.56 WT Initial PT
- 0*F g7 ET After 32 EFPY
- 1/47, 224 'F CT
- 3/47, Iso *r Curves applicable for cooldown rates up to 100*[F and 60 psig for
/hr for the service period up to 32 EFPY and contains sergins of 10 possible instriment errors 2500 ) I A 2290 i 20o0 l n a r 2 i 175g UNACCEPTABLE 1' 8d OPERATION l 1500 / 1 ACCEPTABLE: ~- ~ g / OPERATION - 1250 m i E 1000 f n a V f 7 C00gDOWNRATES F/HR ,) sn. l 500 om q [W 20 4: ];;OZ 40 - s 250 60 - 100-1III OO SO 100 150 200 250 300 3S0 400 450 500 1 INDICATED TEMPERATURE (DED. F) 1 I FIGURE 22 Iion 1 and 2 Reactor Coolant System cooldown Limitations Applicable For up to 32 EFPY and cocidown rates up to 100 F/hr i 44 1
4 .y i .g \\ l wTEptif PROPEPTY RatIS : 3 s b 1 N Controlling Material Weld Metal (Heat 72105) Copper Cer. tent
- 0.32 WT%
s Nickel Content
- 0.56 WT:
p "g Initial RTET
- 0'F NDT' Af teb 15 EFPY
- 1/4T. 195'F RT
- 3/4T. 158'F Curve applicat$e for heatup rates up to 20 F/hr*F and for the service period up to 15 EFPY and contains margins of 10 pos.sible instr 1 ment errors
~l I I I I II I t, ,,a! e r l J Il 1iAr I 6 'l e i i i 1 l 2m LEAKTESTI,IMIT,- / / ); 1 ~- i a 2000 UNACCEPTABLE ~~'~~ / / OPERATION l l r r 1750 l l R f f f HEAWPpTESUP -~ / i 1500 TO 2C F/Hri / f XCEPTABLE Il m OP RATION r ~1 i 1250 I t l 1000 / sh f I H i M CRITICAL 1'IY LIMIT f j / r BA3ED ON INSERVICE / HYDROSTATIC TEST 500 / '~~~" TEMPERATURE (341 F) ~ ~ FOR THE SERVICE PERIOD j UP 1015 EFH 25o i 0 50 100 150 200 250 300 350 400 450 S00 INDICATED TEMPERATURE (DEG. F) Figure 23: Zion 1 and 2 Reactor Coolant System Haagup Limitations Applicable for up to 15 EFFY and Heatup Rates up to 20 F/Hr without Pressurizer Bubble (Bubble defined as Pressuriser Level less than 501). 4 45 4 y ..____--.._.._..,..1.. ,_.___.,,,,-.__.-__.,..,...__________,m--,.
~ ~ ^ ~ - ~ _ _ FJ.TERIAL PROPERTY RASIS : Controlling Material Weld Metal (Heat 72105) Copper Content
- 0.32 WT%
Nickel Content
- 0.56 WT%
Initial RT
- 0'F NDT RT After 15 EFPY : 1/4T. 195'F NDT
- 3/4T. 158'F Curve applicable for heatup rates up to 60 %/hg for the service period up.to 15 EFFY and contains margins of 10"F and 60 psig for possible instrtment errors i
III II II I I I I I I e __i II1ii iI t i i Iii 1 I I LEAK TEST LIMIT, / m 11s0 ~' ) l I I I I J 2000 UNACCEPTABLE f l l OPERATION r r I i 1750 I I j Q 1 i HEAWP ES UP.. r ~ w g 1500 TO /HR / / [ t 12s0 / l g ACCEPTABLE:: p / OPERATION - - e m / 750 / CRITICALITY LIMIT f ~ BASED ON INSERVICE HYDROSTATIC TEST / TEMPERATURE (341 F) / POR THE SERVICE PERIOD UP TO 15 EFFY 250 00 50 1 150 200 250 300 350 400 450 500 INDICATED TEMPERAWRE (DED. F) Figure 24: Zion 1 and 2 Reactor Coolant System Heatup gimitations Applicable for up to 15 EFPY and Heatup Rates up to 60 F/Hr.with Pressurizer Bubble (Bubble defined as Pressurizer Level less than 50%). 46
FJ.TDIAL PROPDTY BASIS t Controlling Material a Weld Metal (Heat 72105) Copper Content
- 0.32 WT%
Kickel Content
- 0.56 WT%
Initial RT
- 0*F g
RT After 15 EFPY : 1/4T. 195'F NDT
- 3/4T. 158'F Curves applicable for cooldown rates up to 100 period up to 15 EFPY and contains margins of 10[/hr for the service F and 60 psig for possible instrunent errors r
I I i1 i i i i I. i i 2250 l 1 l 2000 l f IN n a E / 1500 I r 1250 / / \\ r 3 1000 / M r k 2 8 m n 1.* C00gDOWNRATES g F/HR ^ /CT/ 880 :: 0 -~~ -1340 -- 20 1;;;[::M/
- 40 25c -- 60
~ 4
- 100 0
50 100 150 200 250 300 350 400 450 SCO INDICATED TEMPERATURE (DED. F) Figure 25: Zion 1 and 2 Reactor Coolant System Cooldown Limitations Applicable for up to 15 ETPY and Cooldown Rates up to 100 F/Hr. 47
REFERENCES (1)RegulatoryGuide1.99, Revision 1."EffectsofResidualElementson j Predicted Radiation Damage to Reactor Vessel Materials," U.S. Nuclear Regulatory Commission April 1977. (2) Regulatory Guide 1.99 Revision 2. " Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials" (Proposed Draft), U.S. Nuclear Regulatory Conmiission, February,1986. (3) " 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 Edition, NUREG-0800, 1981. (4) ASME Boiler and Pressure Vessel Code, Section III Division 1 - Appendices, " Rules for Construction of Nuclear Vessels " Appendix G, " Protection Against Nonductile Failure " pp. 559-564, 1983 Edition, American Society of Mechanical Engineers, New York, 1983. (5) Code of Federal Regulations, 10CFR50, Appendix G " Fracture Toughness Requirements," U.S. Nuclear Regulatory Comission, Washington, D.C., Amended May 17, 1983 (48 Federal Register 24010). (6) Code of Federal Regulations, 10CFR Part 50, " Analysis of Potential Pressurized Thermal Shock Events," U.S. Nuclear Regulatory Commission, Washington, D.C., Vol. 50, No. 141, July 23, 1985. (7) Bate 11eReportNo.BCL-585-4,"ZionNuclearPlantReactorPressureVessel Surveillance Program: Unit No. 1 Capsule T, and Unit No. 2 Capsule U," March 25, 1978. Table 21, pg. 50, and Table 23, pg. 53. (8) Westinghouse WCAP-9890, " Analysis of Capsule U From the Comonwealth Edison Company Zion Nuclear Plant Unit 1 Reactor Vessel Radiation Surveillance Program," March 1981, pgs. 5-20 and 5-21. 1923s 10-000004 48 y. ,,,,,-m, ,.n--,,
i i (9) Southwest Research Institute Report No. SwRI-7484-001/1, " Reactor Vessel j Material Surveillance Program for Zion Unit No. 1 Analysis of Capsule X," March 1984, Table XI, pg. 32. (10) Southwest Research Institute Report No. SwRI 06-6901-001, " Reactor Vessel Material Surveillance Program for Zion Unit No, 2 Analysis of Capsule T," July 1983 Table XI, pg. 36. e l l l i l
r 4 ATTACHMENT 4 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION PROPOSED CHANGES TO ZION TECHNICAL SPECIFICATION APPENDIX A - SECTIONS 3/4.3.2-RCS PRESSURIZATION AND SYSTEM INTEGRITY DESCRIPTION OF AMENDMENT REQUEST An amendment to the Zion Facility Operating License is proposed to revise the current heatup and cooldown limitation curves from the current eight EFPY expiration exposure to 15 EFPY of exposure. BACKGROUND 10 CFR 50.92 states that a proposed amendment will involve a no significant hazards consideration if the proposed amendment does not: (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety. In addition, the Commission has provided guidance in the practical applica-tion of these criteria by publishing eight examples in 48 FR 14870. The discussion below addresses each of these three cr!teria and demonstrates that the proposed amendment involves a no significant hazards consideration. BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Does the proposed amendment (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety?
4 A purely administrative change to technical specifications: for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature. Therefore, since the application for amendment satisfies the criteria specified in 10CFR 50.92 and is similar to examples for which no significant hazards consideration exists, commonwealth Edison Company has made a determination that the application involves no significant hazards consideration. 2431K l l l
o DISCUSSION - Item #1 The purpose of this amendment request is to update the pre-existing heatup and cooldown limitations as the Zion Units accumulate exposure. The purpose of these curves is to ensure that the reactor vessel is not subjected to excessive levels of stress during the heatup and cooldown phases of reactor operation. The revised limitations provide an equivalent level of protection to the previous limitations. The acceptance criteria for the calculations performed have not been significantly altered. Thus, there will be no change in the probability of vessel failure through crack propagation. This amendment will not effect the performance of any Zion's safety systems or structures beyond ensuring the continued integrity of Zion reactor vessels as discussed above. Thus, the consequences of all previously evaluated accidents will be unaltered. DISCUSSION - ITEM #2 The updating of the administrative controls regarding the heatup and cooldown rates allowable at Zion Station has no effect on any of Zion'a systems or structures. In addition, the imposition of a more conservative heatup and cooldown rate will not interact with any other phase of Zion's operation. The analyses contained in the Zion FSAR were examined for any potential alterations. Based upon the lack of system and component interaction discussed above, the specific accident sequences will not be affected. Thus, this revision of the current limitations to include the I. higher levels of exposure will not create the possibility of any new or different kind of accident. DISCUSSION - ITEM #3 WCAP-11247 addressed the criteria for the acceptability of these calculations. The revised heatup and cooldown limitations for Zion Station 3 provide an equivalent level of safety to that which currently exists. The allowable stresses that the reactor vessel could be subjected l } to have not been altered from the currently existing levels. Thus, there will be no change in the margin of safety at Zion Station. l i This proposed amendment updates the exposure limitations for the heatup and cooldown curves at Zion Station from eight EFPY to fifteen EFPY. The mechanical acceptance criteria for the allowable stresses has not been significantly altered. Thus example (i) is applicable in this instance. Example (1) reads as follows: i 4 ~,-,---r -e -+,n,---. v.e-,. ,m -- <, - - -, + - - - - - - ~ r.-...-,
>-m->
e---,w,me.-wew r-w~ -r- =v'-M-- 3 - -v,w}}