ML20127J265
| ML20127J265 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 01/14/1993 |
| From: | NORTHEAST UTILITIES SERVICE CO. |
| To: | |
| Shared Package | |
| ML20127J229 | List: |
| References | |
| CY-LOE-266EM, CY-LOE-266EM-R, CY-LOE-266EM-R00, NUDOCS 9301250087 | |
| Download: ML20127J265 (6) | |
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NUSCO CALC. NO. CY-LOE-266EM REVISION 0 l
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HADDAM NECK PLANT i
REACTOR PRESSURE VESSEL END-OF-L2FE UPPER SHELF ENERGY FOR THE NO2ZLE COURSE PLATE MATERIAL 4
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1 NUSCO CALC. NO. CY-LOE-266EM REVISION 0 i
As a result of the issues fientified during the review of GL 92-01, CYAPCo initiated a Charpy impact test program to determine the unirradiated Upper Shelf Energy (USE) of the reactor vessel nozzle course plates. This test program which j
was performed by Westinghouse. included test specimens 1
oriented both in the longitudinal and the trancverse directions machined from excess material from the actual
)
vessel plates. 7he test results indicated that the actual, l
unirradiated, transverse proporties are significantly higher than those predicted using the method described in MTED S-2 l
(i.e. 65% of the longitudinal USE). These results (from Ref.
i
- 1) are summarized in Table I below.
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W9007-1 W9807-8
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USE TEMP.
USE l
TEM P -.
ft-lbs Degrees T ft-lbs i Degrees F ;
Transverse 105.0 320 90,0 150 1
Longitud.
127.0 250
.110.0 320
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m._ -
TABLE I Table II provides the results of the four Haddam Neck capsules analyzed to date (from-Ref. 2). The resulta indicate that the actual measured decrease in USE is significantly less than that predicted by-the method described in paragraph l
C.1.2 of Regulatory Guide 1.99, Rovision 2 (Ref. 3). Since the chemistry of the belt line plates included in the surveillance capsules is similar to the chemistry of the nozzle course plates the end of life USE can be calculated
+
using the plant specific surveillance results as described in i
Reg. Guide 1.99, Revision 2, paragraph C.2.2. Thin methodology requires that the most limiting surveillance i
results be plotted on Figure 2 of the Reg. Guide, and a curve 1
drawn parallel to the existing Reg. Guide curves to obtain the end of life ~ decrease in USE. This method results in an end of life decrease of approximately 18% for a fluence of
'2.22 E19 n/cm"2 at the t/4 location. The end of' life USE for the Nozzle course plates can then be calculated, With the preliminary results provided in Table III. These results demonstrate that the nozzle course plates will remain above 50 f t-lbs through the end of the cur rent, _ vessel design life.
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i NUSCO CALC. No. CY-LOE-266EM REVISION O Since the end of life USE for the remainder of the beltline plates re:nains above 50 f t-lbs, as stated in C/APCo's responce to GL 92-01 (Ref. 2), it is concluded that i
the USE of the Haddam Neck reactor vessel will remain above l
50 ft-lbs through the end of its current design life. CYAPCo will provide the Staff with the final update of the end of i
i life USE values when thu final *.est report is obtained from Westinghouse. The expected completion date of this task is March 1993.
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mm _ _m
. _ s --
Plate #
W9807-2 W9807-4 W9807-7 l
Initial USE 135 126 120
% Cu 0.10 0.12 0.12 e__
o=_-
CAPCULE A Fluence 2.39 E18 2.39 E18 2.39 E10 Measured USB a21 it-lbs N/A N/A l
Actual % Decr.
10.4%
N/A N/A i
l CAPSULE F I
Fluence 4.71 E18 4.71 E18 4.71 E18 l
Measured USE 122.5 ft-]bs 114.3 ft-lbs 108.5 ft-lbs Actual % Decr.
9.3%
9.3%
9.6%
CAPSULE H Fluence 1.58 E19 1.58 E19 1.58 E19 Measured USE 130 ft lbs 122 ft-lbs 117 ft-lbs Actual % Decr.
3.7%
3.2%
2.5%
CAPBULE D i
Fluence 2.22 E19 (2.22 E19 2.22 E19 Messared USE N/A 110 ft-lbs N/A Actual % Decr.
N/A 12.7}
N/A l
f TABLE II i
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NUSCO CALC. NO. CY-LOE-266EH REVISION 0 l
2 UNIRRAD.
1/4T
%USE EOL PLATE #
USE
%Cu FLUENCE DECREASE USE ft-lbs fr-lbs W9807-1 105 0.10 2.22 E19 18%
86.1 W9807-6 64.5 0,11 2.22 E19 18%
52.9 W9807-8 90.0 0,11 2.22 E19 18%
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TABLE III r
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NUSCO CALC. NO. CY-LOE-266EM REVISION O
)
REFERENCES l
- 1. Westinghouse Letter No. CYW-93-903
" Transmittal of CY Upper Shelf Energy Results, Westinghouse G.O.IIR59483;NUSCO 1
P.O.8865413", From R. E.
!!ixson to Nelson Azevedo, Dated January 13, 1993.
j
- 2. Letter from J.
F. Opeka to U. S. Nuclear Regulatory "Haddam Neck Plant, Millstone Nuclear Power Commission,it Nos.
Station, Un 1, 2, cnd 3, Reactor Vessel Structural 1
Integrity, 10CFR50.54(f)", Dated July 6, 1992.
3.
G. S. Nuclear Regulatory Commission, Regulatory Guide 1.99, Revision 2, Dated May 1988.
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