ML17258A226
| ML17258A226 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/06/1981 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8110140367 | |
| Download: ML17258A226 (11) | |
Text
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P'1 ant'r, Uni t 1 r Roch'ester' 05090244 AUTH~,NAMEl AUTHOR AFF ILIAT'ION MAIER~rJl Ete Roch'ester Gas 8 Electric-Corp>
RECIP" VAN~El RECIIPlKNT'FFILCATIONI CRUTCHF IELO'z D"e Oper ating, R'e'actot s B>anch 5.
SUBJECT":; Provides" pr eel iminar y re'jul ts of Ch'arpy impact te'st specimpns f r oal reactors vessell sur vei 1 1 ance capsul e<
provided. to assist in relic'g of radiation emir itt'le e'f facts'n operating, r eactors; DISTRIBUTION CODEl: A0018'OPIES RECEKVED:LR'R
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ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E.
MAIER V I CE PRES I DENT TCLCPHON ARCA COOC T October 6, 1981 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Preliminary Results of Charpy Impact Test on Specimens from Ginna's Reactor Vessel Surveillance Capsule T
R.
E. Ginna Nuclear Power Plant, Unit No.
1 Docket. No. 50-244
Dear Mr. Crutchfield:
As part of the Ginna Reactor Vessels Surveillance Program Capsule T was removed from the reactor during the Spring 1980 refueling outage.
This shutdown was the completion of fuel cycle 9 core life with approximately 7.1 EFPY operation for the reactor vessel and surveillance capsule.
Based upon this capsules location in the vessel the lead factor of the surveillance specimens to the vessel materials and limiting circumferential weld was 1.94 times the calculated fluence for the vessel.
In early Spring of this year (1981) the capsule was sent to Westinghouse for testing and evaluation.
Presently, the charpy impact test have beep completed.
With preliminary calculated fluence of 1.7 (10) nvt, the transition temperature at the 30 ft-lbs energy level was 150'F which represents essentially no change over capsule R results taken after fuel cycle 3 in the Spring'f 1974, documented in WCAP 8421 Report.
The upper self energy has improved slightly at 55 ft-lbs for the controlling weld.
These weld specimens were fabricated from the same weld wire as the vessel weld, however the Linde 80 neutral flux was from a different lot.
Attached are five figures which show the actual results for these Charpy tests.
Figure (3) presents the results for the limiting weld. It appears that more specimens tested at approximately 200'F would have moved the 50 ft-lbs transition back.
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GH 248 188 0
128 f
PlS TEMPERATURE(F)
IRRADIATED CHARP Y V-NOTCH I HPACT PROPERTIES G I NNA REACTOR VESSEL PLATE P
FIGURE 1
8AHPt E HO.
TEHPERATURE IHPACT E)'-'ERt:Y
- C =(F)
Joules (T"i-jbs) 8-27 b-25 8-22 8-28 8-24 8-23 8-2i 8-26 8-30 8-29
-73 (-i00)
-46
( -50)
-ia
(
0)
-ia
(
0)
-4
(
25) 24
(
75) 66
.( i50)
'79 '( 'i75) i2i' 250) i77
( 350) 3.5
- 36. 5 i06.0 92.0 95.5 76.0 i39.5 i53.0 2i0.0 202.5
(
2.5)
( 27.0)
( 78.0)
( 68.0)
( 70.5)
( 56.0)
(i03.0)
('ii3.'0)
'i55.
0)
(i49.5) 128
>. lIl Qg a8 K
I hl I-Z U.
ld 68 188 0
128 mS
-288 188 8
188 TEMPERATURE(F) 288 388 IRRAOIATEO CHARPY V-NOTCH IMPACT PROPERT IES CINNA REACTOR VESSEL PLATE S
FIGURE 2
~NPLE Ho.
TEYiPEPATURE lYiPi'CT ENERGY
.C (F) 'oules
(~"t-lbs) 8-30 8-.27 4-22 8-28 H-2i LI B
~
8-26 W-24 4-29
-i8 (
0) 24
(
75) 52
( i25) 66
( i50) 99
( 2iO) i2i ( 250) i49
( 300) i77
( 350) 2i8
( 425) 2i8
( 425) 7.0
(
5.0) 30.0
( 22.0) 39.5
( 29.0) 48.0
( 35.5)
'55.5
( 4i.O) 63.0
( 46.5) 68.5
( 50.5) 7i.0
( 52.5) 85;5
( 63.0) 75.0
( 55.5) 128 I RZ TEMPERATURE(F)
IRRADI ATED CHARPY V-NOTCH IMPACT PROPERTIES GINNA REACTOR VESSEL N'ELQ FIGURE 3
SAHPLE No.
TEMPERATURE IHPACT EhERGY C (F)
Joule- (ft-ibm)
H-24 H-2i H-22 H-28 H-23 t-'-25 H-29 H-30 H-27
-73 (-i00)
-5i
( -60)
-46
( -50)
-i8
(
0)
'0
(
50) 24
(
75) 66
( i50) i2i
( 250) f77
( 350).>>':
5.5 i8. 5
- 89. 5 33.0
- 45. 5 i58.0 i73.5 i88.5 i'ie". 5' 4.0)
( i3.5)
( 66.0)
( 24.5)
( 33.5)
(ii6.5)
(i28.0)
(i39.0)
( '86;0) 1S8 128
>. Ol QJ g8 K
I hl l-Z lL td 63
~
1S8 Q
128 Pl N
-288 188 8
188 TEMPERATURE(FO IRRADIATED CHARPY V-NOTCH IMPACT PRCPERTIES GINNA REACTOR VESSEL HEAT AFFECTED ZONE FIGURE 4
SARPi E No.
TEBPERI-'ITURE IHPACT EHER(iY C (F)
Joules
( t-lb')
R-20 R-24 R-22 R-23 R-18 R-ia R-17 R-2i 24
(
75) 38
( i00) 66
( f50) 78
( 175) 88
( 2i0) 121
( 250) k77
( 350) 2iS
( 425)
- 54. 0 26.0 35.5 j0
- 45. 5
- 83. 5
- 85. 5 S0.0
( 40.0)
( i8.0)
( 26.0)
( 30.0)
( 33.5)
( 6i.5)
( 63.0)
( 59.0) 168.
228
>- K 68 I
U.'-
Z Q.
bl 48 40 a8 CrnI 288 388 TEMPERATURE(F)
IRRADIATED CHARPY V-NOTCH IMPACT PROPERTIES GINNA REACTOR VESSEL CORRELATION MONITOR FIGURE 5