ML20128F074
| ML20128F074 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/02/1992 |
| From: | Shiraki C Office of Nuclear Reactor Regulation |
| To: | Kovach T COMMONWEALTH EDISON CO. |
| References | |
| TAC-M84546, TAC-M84547, NUDOCS 9212080247 | |
| Download: ML20128F074 (12) | |
Text
_ _ _...
ctM 4A pog'o Q \\ %K.
=
UNITED STATES
!" g m #,%
NUCLE AR REGULATO% COMMISSION 1
WASmNoTON, D. C. 20555
/
%, *... *f s
/
December 2, 1 W L aet Nos. 50-295 l
and 50-304 Mr. Thomas J. Kovach Nuclear Licensing Manager Commonwealth Edis.n Company-Suite 300 OPUS West 111 1400 OPUS Place Downers Grove, Illinois 60515
Dear Mr. Kovach:
SUBJECT:
ZION STATION, UNITS 1 AND 2, FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESdVRIZED THERMAL SHOCK EVENTS,10 CFR 50.61 i
(TAC NOS. M84546 AND MB4547) in a letter dated May 22, 1992, you provided the staff an assessment of the pressurized thermal shock reference temperature (RTns) values for the reactor l
vessels of Zion Station, Units 1 and 2, which are Westinghouse designed reactors.
In your analysis, the unirradiated reference temperature value for the limiting weld metal (weld metal f abricated from Linde 80 flux and heat number 72v5 weld wire) was determined from the mean value of all heat number 72105 weld metal data with stress relief times of less than 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />.
Data with stress relief times greater than 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> were not included in your evaluation, The increase in reference temperature resulting from neutron irradiatko was determined from the analysis of surveillance data from welds fabricated from Linde 80 flux and heat number 72105 weld wire.
Data were available from both Westinghouse and Babcock and Wilcox designed reactor vessels.
The staff's consult nt, Oak Ridge National Laboratory (ORNL), performed an analysis of Linde 80 weld, base metal and standard reference materials irradiated in Westinghouse and Babcock and Wilcox designed reactor vessels using the Power Reactor Embrittlement Data Base.
The enclosed data indicate that for the same material and neutron fluence, reactor vessels designed by Westinghouse will have greater neutron embrittlement than reactor vessels uesigned by Babcock and Wilcox.
This could be attributed to lower operating temperatu'es of the Westinghouse designed reactors or to a difference in neutron sp.ctra.
Hence, based on this data, the increase in reference temperature resulting from neutron irradiation should be determined from welds fabricated from Linde 80 flux and heat number 72105 weld wire, which were irradiated in surveillance capsules in Westinghouse designed reactor vessels.
Although Zion 1 and 2 have Westinghouse designed reactor vessels, your conclusions for the increase in reference temperature for Zion weld metal were based on data from surveillance capsules irradiated in Babcock and Wilcox designed reactor vessels, 070014 9212080247 921202 i
PDR ADOCK 0500 5
p
~ 4.1 wggyy g
.e
4 Mr. Thomas J. Kovach December 2, 1992 We request that you provide, within 60 days of the date of this letter, the basis (mechanistic and statistical) for not including in your analvris-unirradiated data with stress relief times greater than 35 hourt m the basis
- d. 'd' metal for concluding that the increase in reference tem p ature for Z',
mry be determined from surveillance data irradiated in Babcock o *
.cox designed reactor vessels.
Plant specific irradiation temperature;.ad spectra should be included in your evaluation of the effect of neutron irradiation on the increase in reference temperature.
In addition, the surveillance data in Table 2 of your analysis are different than the data in previous surveillance reports.
You should provide the Charpy impact data and curves that were used to determine the increase in'the 30 f t-lb transition temperature and identify the neutron transport code, the scattering cross-sections and quadrature approximations used in determining-the neutron fluences of the capsules, if you have any questions, please contact me.
Sincerely, Original signed by:
Clyde Y. Shiraki, Senior Project Manager Project Directorate III-2 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Enclosure:
ORNL Data Analysis for the Evaluation of the Irradiation Temperature Effects cc w/ enclosure:
see next page DISTRIBUTION l
Docket File NRC & Local PDRs PDill-2 r/f BElliott OCC ACRS(10)
TKing JStrosnider CMoore
.CShiraki PDIll-2 p/f BClayton, Rill JRoe JDyer O
LN ' 11-2 PM/PDIII-2 D/PDIII-$p oor CShiraki JDyer U
l'-/ l /92 y/(/92 jv/p/92
Mr. Thomas J. Kovach:
Zion Nuclear Power Station-Commonwealth Edison Company Unit Nos. 1 and 2 CC:
Michael 1. Miller, Esquire Fidley and Austin One First National Plaza Chicago, Illinois 60690 Dr. Cecil Lue-Hing l
Director of Research and Devu s..ien t i
Metropolitan Sanitary District of Greater Chicago 100 East Erie Street Chicago, Illinois 60611 Phillip Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Mayor of Zion Zion, Illinois 60099 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 U. S. Nuclear Regulatory Commission Resident inspectors Office 105 Shiloh Blvd.
Zion, Illinois 60099 l
Regional Administrator,-Region 111 U.-S. Nuclear Regulatory Commission 799. Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 l
Robert Neumann L
Office of Public Counsel State of Illinois Center 100 W. Randolph Suite-11-300-Chicago,.Illinc 60601 l
l-i
-- - ~
i!
ENCLOSURE Sub}ect: Additionel Data Analysis for Eve' etion of irradiation Temperature Effects The folkrwing study is the continua!!on of the residual studes for the irradiation temperature effects, dated April 8,1992. The atattstical Analysis will ra include the data whose absolute residual value is greater than 100*F. however, the data point will be retaired in the plot.
Two categories of data anaYsis were canied out in this study, the deta!!ed anaysis for sach category is sta:od as below:
- 1. Wastinghouse's surventance data whose materials are from B&W suppliedossets.
In this category, only the wdd materials are available from PR-ELS A residual plot was generated for this catogory, the mean tosiduai value ( 1.6'F) and two sigma bounds (52,48'F) were also marked in the p ot, see Figure 1. The residual plot couid be interpreted to show a fluence dependence effect. At talathe low fluences, say below 10rwt. Reg. Guide 199 underpredicted the shift value, and at fluences grsaf er than 1.0x10%'t, Reg Guide 199 overpredicted the shift value.
- 11. Standard reference materials for Westinghouse and B&W plants.
- In this category, only the surveillance data of the standard reference materia!, SHSS02 (HSST02), is available for both Wasunghouse and B&W plants from PR-EDB Two residual plots, figure 2 3. were generated for Westinghoae and B&W respectNely. The corresponding maan residual and two sigma bounds are listed below:
Vendor Mean t Two Sigma Westlnghouse
-3.90 :t 34'F Babcock & Wilcox 44.18 2 39'F Two addttiona! plots for B&W's base and weld materiats are also included with this report. Both base and weld materials have 23*F mean residual, ses figure 4 5. The Charpy specimens o' different materials are dtstributed evenly within the B&W's surveillance capsule.
Subject:
Data Selection Procedures Used in the Radiation Embrittlement Study in ofder to carry out the rad;ation embrlttlement studies more efficiently, a processed file, SHIFT,PR.dbf.
Das generated from PR EDB data base. The criteria of dats selectbn processes are defined as below:
Charpy shift data; The reported shift data, DTT30, is chosen it found. If DTT30 data is not listed cr can not be determined by subtraction of the untrradiated from the irradiated data, then DTT30 is detrarm!ned from F.W. Statimann's TANH fit program.
Fluence cata:
if there are two or more reported fluences for one capsule, then the vendors value is chosen.
Chemistry data:
Manufacturer's data are chosen if available. If the manufacturers data is not eval!able, then the specimen data are used.
P ei of 1 siduaL vs. Iuence le d a;erials)
~
68 a
48 m
~'
b m"
o 28 o0 0
0
.m-mw 0
d o
g o
0 m
v i
'o Westinghouse 0
m
-28 B&WSupplier ~
0 M
- Mean Residual -1.8'F o
o H
0 s
o A
Two Signa 52.48'F O
-48 0 0 0
g(
=
f f
t a
17.8 17.5 18.8 18.5 19.0 19.5 n/en*, log.
FLUEiiCL > 1 NeV at Capsule Center Figure 1. Plot of Residual versus Fluence for Westinghouse with B&W Supplier
.0i O! 36SNildi YS, Ill8DC0
[8/8822da$8PiaLSJ' L
40 r 30 ;-----~~-~~~~~~~~~--~~~-------0-~~-------~~----
a o Ucstinghouse M
o o
20 SHSS02 Materials Pa
- Mean Residual -3.9'F 0
o o
Two Signa 34.4*F m
10 m
o w
o o
c5 0
.v cax v
1
-10 o
O o
o o
O G
O l
o m
o s
-20 o"
o o
o o
o
~38 i-o g...........,...-.......,............,........._......._....;
17.5 18.0 18.5 19.0 19.5 20.0 2
n/cm, log.
FLUENCE > 1 MeV at Capsule Center Figure 2. Plot of Residual versus Fluence for Westinghouse SHSSO2 Material
W hdResihai vs. Lience GISS82 liateria s)
^
186 o Babcock 8 UiIcox a,
SHSS82 Materials 3-m g-58 Mean Residual -44*F
______ h Sim 39'F
.m m.
8 g
d w
O o
o a:
o
-58 o 0o-0 0
a p
E
-108.___________________________________________.o____o i
i,.
C
--150 17.5' 118.8-
'18.5.
19.8 19.S.
.28.8 n/cn*, log.
FLIENCE > 1 NeU at Capsule Center A
t
, e Figure 3. Plot of Residual versus Fluence for B&W SHSSO2 Material o.
i
'I W
ry'-
g p*
,1.cm-.
e b
Y T
b
'+44
'W
"'-T'Y
- Tt 4
9-T
''M*4 6r Y-'T'W--
"-W'*
[.0" 02 38SidlaI. YS, I(181108 $0? 2dSB dE8 Pia.'S 108
=
m m
50 s
+
g o
.t g
+
T 8
U-
+-
1
++
g s
c 3
d 4+
+
+
4++A w
+
m
+
+
+ 4+T+ +W 2
-50'
+-
~
+
+
+
+
S J
+
______p__________p__+r________________________
A
-108
+ Babcock & Wilcox
- Mean Residual -23 AF
Two Sigma 59'F 4
-150 17.5.
18.8 18.5 19.8-19.5 28,8 n/cn*, log.
FLUENCE > 1 fleV at Capsule Center Figure 4. Plot of Residual versus Fluence for B&W Base Materials
7aM 3esifua. vs. 7uence for Vel keria:s 100 ',r I
e m
58
+
s 5
+
+
mm 8
+
w T4 T g
+
+
++
-se
+
+
+
+
+
+
++
c
+
o)
+
s A
188
+ Babcock & Wilcox
. -- Mean: Residual -23.4F
+
- Two Sigma 64*F
~158
^
2 17.5 18.8 18.5 19.8 19.5 28.8 w'cn* s log.
FIDENCE > 1 Me.V at Capsule Center Figure 5. Plot of Residual versus Fluence for B&W Weld Materials l
t.:
n -
4 >
Sosteset Fue cf Westinghouse teAW 1gspiler):
' Pope 1 Yes : PLASTJS - CAPSULE WE4f,19.
SPEC,0RI CSPf1
__ CAP,Tylm Cr.P,T.fWLt 97U0 ATTR.ettr m e.
n.w REf_tB Os 31" OIDIJS
.U.
Jial V.
1ee101
' TL -
6.580E+1a RESIDLAL
_.a w:=
.W tte a
wee 01
'TL 7.600E.te
+
579 to 12
-22 sual-06-8976 0.030 e.500 mor-8957 W'
SIN.
'T:
Elmel TL
.1.750e+19 Si?
- N 165 131 16 saw-1803
-W-
' Glu Y
=WEtut1 TL 4.900E*18 154 188 c.230 9.540 ucap-10006 W
PS)
R' WPt101 7L 2.220E+19 579 165 181
-16 WCAP-9357 3s tcap.10006
$79 140 131 9
FP-4A 1 4.230 4.3e0 scaP-380es
. U ' Pet s
WP8101 TL 7.050E *14 0.230 9.340 WCap-19056 W
Pat-T WPS101
- it 2.110E*19 579
-165 135 30 WCAP-8739 9.180 9.575 1 CAP-19736
.U-PS1.
V-579 100 179 1
etar-19736 t ~ W ' Ps2 E ~
1eS101 ft 3.580E*t8 579 590 110 107 3
es3 0673 4.180. 0.5M. weaP-1er36 WP5201 TL 2.010E+19 -
0.100 9.579 1 cap-19736 '
W:.Ps2
.T WPS201 TL 9.450E+18 579 235 208 2T sau-tso3 0.190 '9.579 4 CAP-19734
..W-f Ps2
.V WPS201 TL 4.760E+18 579 590 165 138 27 sur-0675 0.250. 8.590 1 cap-9331 579 145 1 72
-27 wtar-9331 0.250 0.599 nCar-9331 1r sut.
.T Umf101 TL 2.500E*18 U
su1 V
wipiot TL 1.960E+19 590 147 ' 140 27 8AW 1803 0.350 9.400 SAW-1803 0.254 9.590 WtaP-9331-
'O TP3
.T VTP301 TL 5.680E*18 579 260 264
-24 WCAP-11415 U'
TP3 V
WTP301 TL 1.229E+19 579
. 164 140 4
34W-1803 0.35s - s.ese ear-teas W
1P6 T
WTP401.
579 180 201
-21
.. sutt 06-8575 0.319 0.544 ' starf-e6-8575 '
4.850E*18 0.310 'S.548 sutt4b6-4575-U 2m1 T
U2u101 YL.
1.800E+18 579 225 14 7 5e>
SuRI-02-4221 6.346 9.400 tims-et 4221 U-2w1 u
WDs191 TL 8.920E+18 ff2 113
-1 SAW-1603 W
Zul x
wru101 TL 1.500E+19 579 590 195 232
-37 snat-06-7484-001 9.350 9.5M ett-Ss5-4.
579 199 202
-3 SAW-1903 3.354 0.5M ect-Se5-4
' it. Int Y
vzw101 '
TL 1.560E*19-8.350 0.575 scL-585-4 9-2m2 i
WEu291 LT
-1.100E*19 579
. 579 205 234
-29 saw-2982 0. 2W2 U
W2N291 LLT 2.000E+18 590 175 214
-39 stal-e6-4901-001 0.554 9.5 M emnetee3 9.354 9.5M att-385-4
!O 252 T
1R31291 L1 1.4SOE*19 145 119 26 siaw-teos 579 220 251
- 11 WcaP-12396 3.35e e.57s aguetses S.334 9.575' tese7903 4
4-6 3
j.
i t
.U-
-5 y
y
[gl,
medleust File of Westftwhouse sessS2 n+teeleist 1As PtAst Is' CAPsu Pese 1
.lt # EAT,50 SPEC _Ca t CSP,71 cmp _T_ ate CAP f
.._.._. Man...
.n_etc
- E t t toAL.......
...r,t e Of al CuEst 10 01730 DTT30 W ' CK1 1
t#15C2 LT 1.800E*19 579 590 60 73
-10 tir
'O-CK1
.T Setts02 LT T.200E+19 579 590 113 135
-25 V
DC1' SatS02
- LT 2.980E*18 sWI*02 4770
..nn tf 173
.Y saSSO2 LT' 8.050E*18 M
74 sutI-7244-001/1 0.175 0.640 saw-18 %
0.170.0.440 34W-18%
579 ti tut P
579
-s utAP-1tS67 suss02 L1 2.990E*19 140 120 20 WCAP-10300 O
tiaE a
0.150 0.454 WCAP-ItS47-sussc2 11 579 2.070E*19 155 164
-9 WCAP-12C20 9
KWE V
SR5502 LT 5.590E*15 140 153
-13 1 CAP-9675 0.170 0. M 0 34w-1436 579 U
PS2 a
$#5502 Lt 2.010E+19 95 107
-12 utAP-8908 0.17D 0.640 anw-tam 579 U
PS2 7
$N5tal LT 0.173 0.640 saw-1836 579 9.450E+18 151 152
-1 WCAP-9635 0
PS2 V
0.173 0.640 sau-tem SMSsC2 t1 579 105 126
-21 WCAP-9331 W
Pl1.
P 4.740E*18 53 593 90 101
-11 SPt-0675 0.173 0.M0 saw-18%
SM15C2 LT t.250E*19 V
Pl1 4
SMS$02 LT 4.C30E*19 154 136 20 VCAP-101C2 8.170 0.440 saw-18%
U Pit v
0.179 0.M0 saw-t m sess02 LT 5.210E+18 186 174 12 UCAP-11006 579 w
satS02 LT 4.420E*19 0.173 0.640 saw-1EM 579 110 105 5
vtAP 39%
u PI2 i
tws502 11 1.050E*19 180 176 4
Ut4P-11343 0.179 0.640 sau-tSM 579 O
Pt2 V
twisC2
-11 5.490E+18 0.170 0.M0 saw-1836 579 160 130 30 WCAP-9877 O
SA1 1
SMis02 Lt 2.56cE+18 0.170 0.440 amW-1836 579 125 107 0.170 0.M0 saw-1836 U
SA)
Y S#S$42 (T
8.910E*18 60 64
-4 wear-9678 0.140 0.680 WCW-11955 579 18 vtaP-9212 42 -
'2 SWSs02 tt 0.179 0.440 saw-1th 579 1.330E*19 125 99 26 WCEP-10694-0 sul T
suss02 11 2.530E*18 579 135 110 25 WCAP-11955 t3 ~ sui y
0.%0 0.600 WCmP-11955 Sassc2 LT 1.940E+19 70 80
-10 occtri 50-200 0.175 0.640 enw-1EM 590 o
sut V
susse2 LT 1.880E*19 9.40 0.600 WCaP-It955 579 145 151
-6 Utar-t1415 w=
sut X
Susss2 LT 3.020E.15 120 150
-3C 9t w-11499 579
'c' Zut T
snSt02 Li
'1.900E*18 0.17e e.440 anw-tsu 590 60 86
-26 e
241 u
SWS$02 11 0.179 0.64e amet-1s M outt-0975/su2 4.920E*18 de 79
-4
- CL-585-4 O
Zut 1
sir $se2 LT 1.400E*19' 579 590 120 140
-20 0.179 0.640 saw faM 579 130 124 0,
2m1' V
6 0.170 0.440 amu-1aN Sas*02 LT 1.540E+tf utAP-9epo tt 2m2 T.
sats82 tt 1.000E+19 579 590 100 128
-28 9.178 s.440 sma-1aM
$79 129 144
-15 4Aw-2082 0.179 0.640 Sar 1EM Swel-D&-7484-001 9.170 9.448 Saw-1536
,O 2N2 u
sutse:
t, 2..ex.i.
'5 Iw?
?
381502 tt -
-1.4a0E*19 50 73 -
-23
.ct.5 5 4 sul-06-ef01-001 8.179 s.444 saw-1sM 579 135 142
-7 utar-t2396 0.17. 0.M0
.m.-1.M 0.17e 0.440 saw-tam
sealent File af Sebeeck'8 tif tcom'sktt02 meteelstes FAG ' PLA#1_O Pope 1 CAPSULE ' NEAT,80 SPEC cel C5P u _..
..J.1 CAP,T,mte cap t
._..,seu ' sit 3e oft 30,stC ' REsteunt..
eff_to O
A41 A
Sa5302 L7 1.030E*19 610 621
'129
-83 sm-1834 CM WI 04E88)#
O Aa1 s
sast02 Li 4.280E+18 - 588 610 53 98 -
-48 saw-169s' S
441 C
S#5502 11 1.460E*19 610 621 6&'
141
- 73 sAW-2375/t1 9.179 0.648 BAw-1836 g.17g 6.640~Saw 1834 s: Ct3 C'
Sust02 11 4.560E*t6 610 621 73 t il -
-43 SAW-1878 e.170 e.6et ase-se36
. 091 A
SWs502 L1 1.290E*19 610 621 106 137
-31 sAW-1S82 0.173 0.640 e4w-tS34 s
- 3-OC1 A
SMt502.
LT' 8.950E+ 18 61C 621 88 124
-36 eau-1837
. 0.170 0.660 anu-1836 0.170'4,6&8 884-1534
.e ett C
SM5532 LT 9.86cE*19 elo 621 68 194
-126 sAv-2050 S
OC2 A
SM5502
~ LT 3.37DE+18 610 621 71 90
-19 sev-1699 a
OC2 E
SM$s02 L7 1.210E*19 621 c.170 9.660 anu-1936 0
.0C3 e
tuss 02 LF 3.120C+18 588 610 39
. 87
-48 SAu-1697 c.173 S.640 anw-1836 95 135
-40 BAw-2051 e
DC3 D
555562 LF 1.450E*19 610 621 119 141
-22 SAW-2128 0.179 9.660 saw-1836-0.179. 0.648 ' anw-1836 a
TR1
.t leS$02 LT 8.660E*16 0.179 9.648 enw-1834 77 123
-46
'GAW-1901 0.17 ' 8.64 - ear-1836 -
D
.5
_...