ML20071M081
| ML20071M081 | |
| Person / Time | |
|---|---|
| Site: | Hatch, 05003660  |
| Issue date: | 05/26/1983 |
| From: | Beckham J GEORGIA POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20071M062 | List: |
| References | |
| REF-SSINS-6820, RTR-NUREG-0313, RTR-NUREG-313 IEB-83-02, IEB-83-2, NED-83-324, TAC-51407, NUDOCS 8305310084 | |
| Download: ML20071M081 (39) | |
Text
.
ATTACHMENT 1 3 p dm A Atlanta, Geena 30M Tc'ephone 404 52GJC20 Maang Adress Post of*co Ben M M A:ama Georia 252 ga Georgia Power J. T. Beckham. Jr.
tre southem e'ectrc system v.co pres,cer t a ia o.,re n.: uar a;cr NED-83-324 Nuc' ear G3rera.on May 26, 1983 U. S. Nuclear Regulatory Commission
'REFEREtCE:
Office of Inspection and Enfo'rcement RII: JP0 Region II - Suite 2900 50-366 101 Marietta Street, NW I&E Bulletin Atlanta, Georgia 30303 83-02 ATTENTION: Mr. James P. O'Reilly GENTLEEN:
Georgia Power Company (GPC) hereby submits the following information concerning inservice inspection activities at Plant Hatch Unit 2 in response to NRC I&E Bulletin 83-02.
The subject bulletin pertains to stress corrosion cracking in large-diameter stainicss steel recirculation system piping at BWR plants.
Item 1 (as applicable to Plant Hatch Unit 2)
Some of the licensees listed in Table 1 (of the subject bulletin) have completed efforts to validate the UT detection capability to be used to perform plant inspections in accordance with the requirements of Action l
Item 1 of I&E Bulletin 82-03, Revision 1.
These licensees need not repeat this effort in accordance with Action Item 1 of this bulletin provided that:
the previous validated inspection group performs the new plant examination using identical UT procedures, standards, make and model of UT instrument, and the same make and model transducers that were used to complete the previous validation effort.
In addition, the UT personnel employed in the new examination must be the same; or those having appropriate training (documented) in IGSCC inspection using cracked thick-wall pipe specimens, and are under direct supervision of the Level II/III UT operators who successfully complete the performance demonstration tests.
l Resoonse ung 8o Validation of the UT procedures was performed under NRC I&E Bulletin
'O 82-03, Rev. 1 for the examination of large-diameter stainless steel L
piping at Plant Hatch Unit 1 during the Fall 1982 maintenance / refueling og outage.
Pursuant to I&E Bulletin 83-02, the licensee need not repeat O.a the validation process.
Similar procedures, equipment, and transducers g4 were used at Plant Hatch Unit 2.
In addition, each Level II UT og y. technician was satisfactorily tested after receiving training in IGSCC Ma.eg'Jedetection 2
using cracked thick-wall pipe specimens under the direct &.
4 stpervision of a Level III who had performed the qualification for I&E g:E
. u,,Bulletin 82-03, Revision 1.
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i Georgia Power n U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II - Suite 2900 May 26, 1983 Page Two Item 2 (as applicable to Plant Hatch Unit 2)
Before resuming power operations licensees are to augment their ISI programs to include an ultrasonic examination of the following minimum number of recirculation system welds:
Ten welds in recirculation piping of 20-inch diameter, or larger.
a.
b.
Ten welds of the jet pumps inlet riser piping and associated safe-ends, c.
Two sweepolet-to-header (manifold) welds of jet pump risers nearest the end caps, if applicable to the design.
If flaws indicative of cracking are found in the above examination, additional inspection is to be conducted in accordance with IWB-2430 of ASE Code Section XI.
Response
The ISI program was augmented to include the minimum number of welds required by this particular item of the bulletin.
As a result of observing unacceptable flaw-like indications, the original scope of examinations was increased in accordance with the guidance of ASE Section XI, IWB-2430.
Ultimately, a 100% examination of the Class 1 Recirculation System welds (ASE Category B-J welds only) was performed.
Fifty percent (50%) of the ASE Category B-F welds in the Recirculation System were examined with no unacceptable indications observed; therefore, the scope of examinations for this particular category weld was not increased.
In addition to the examination of Recirculation System welds, a 100% examination of the stainless steel welds in the RHR System was performed pursuant to NRC NUREG-0313, Revision 1 guidance.
Five welds in the RWCU System were examined with no unacceptable flaw-like indications observed; therefore, the scope of examinations for RWCU was not increased.
Item 3 Before resuming power operations following the outage, the licensee is to report the results of the Item 2 inspection and any corrective actions (in the event cracking is identified).
This report should also include the susceptibility matrix used as a basis for welds selected for examination (e.g.,
stress rule index, carbon content, high stress location, repair history) and their values for each weld examined.
700775
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Georgia Power n\\
'U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II - Suite 2900 May 26, 1983 Page Three
Response
The welds in the original scope of examination and the initial increased scope of examination for the Recirculation System were chosen based on
~
high stress rule index (SRI) number and carbon content.
As a result of observing unacceptable flaw-like indications in the original scope and then' the initial increased scope of examinations, all remaining Recirculation System welds (i.e., ASE Category B-J welds only) were then examined. As noted above,100% of the stainless steel welds of the RHR System were examined, thereby precluding the necessity of weld selection criteria (i.e.,
susceptibility matrix) as discussed in bulletin item 3.
High SRI number and carbon content served as the basis for the selection criteria of the five RWCU System welds examined.
Attachment I lists the Recirculation, RHR, and RWCU system welds examined, their SRI number, carbon content, and examination results. lists those welds for which corrective action in the form of repairs, analysis, or replacement is being conducted. Details of the analyses, repairs, ard replacement will be submitted to NRC NRR under separate cover.
A copy of that submittal will be provided to NRC Region II.
Please refer to Attachment 3
for isometric drawings of the Recirculation, RHR, and RWCU system piping.
ASE Category B-F and B-J welds examined during the 1983 inservice inspection are denoted by circled weld numbers.
l l
Item 4 The NRC has an on-going program to evaluate possible additional longer-term requirements relative to the IGSCC problem in the BWR recirculation system piping.
The NRC may need additional information as part of this program.
Therefore, licensees are requested to retain the records and data developed pursuant to the inspections performed in l
accordance with Item 2.
Response
The inservice inspection records and data developed pursuant to the inspections performed in accordance with bulletin item 2 will be retained.
The subject records and data will be incorporated into the l
inservice inspection report to be issued by the ISI contractor.
Inservice inspection reports are required by Technical Specification l
6.10.2h to be retained for the life of the plant.
rxns t
Georgia Power A U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II - Suite 2900 May 26, 1983 Page Four Should you have any questions in this regard, please contact this office.
J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.
GEORGIA POWER COWANY By:
J. T. Becknam, Ar.
Sworn to an subscribe befor me this 26th day of May, 1983.
.///
Notary Public, Geof91, State at Large b/
[/IM My Commission ExDires Sect. 20.19R i Notary Public 7,7 JAE/mb
- 4. '
Enclosure l
xc:
H. C. Nix, Jr.
Senior Resident Inspector I
J. P. O'Reilly, (NRC-Region II)
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e ATTACHE NT 1 WELD EXAMINATION LISTING
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STAINLESS STEEL PIPING UT EXAMINATION RESULTS WELD SIGNIFICANT WELD NO.
WELD TYPE FAB.
%C INDICATIONS
% THRU-WALL (MAX)
RECIRCULATION SYSTEM 2B31-lRC-12AR-F-1 BC-P FW l.11
.065 None
-2 P-E SW 1.44
.065 360* Inter., Pipe-Side 25%
-3 E-P SW _
l.53'
.065 360* Inter., Pipe Side 10%
-4 P-SE FW 1.30
.065 None
-2B31-lRC-12AR-G-1 BC-P FW l.11
.075 None
-2 P-E SW l.46
.075 360* Inter., Pipe Side 14%
-3 E-P SW 1.56
.075 360* Inter., Pipe Side 15%
-4 P-SE FW l.33
.075 None
~2B31-lRC-12AR-H-1 Red-P FW-1.15
.075 None
-2 P-E SW' 1.55
.075 360* Inter., Pipe Side 10%
-3 E-P SW 1.65
.060 360* Inter., Pipe Side 30%
-4 P-SE FW l.46
.060 None
-5 SE-N SW Not Examined 2B31-lRC-12AR-J-l BC-P FW l.07
.065 None
-2 P-E SW l.45
.065 360* Inter., Pipe Side 23%
-3 E-P SW l.56
.065 360* Inter., Pipe Side 20%
-4 P-SE FW l.30
.065 360* Inter., Pipe Side 28%
-5 SE-N SW Not Examined 2B31-lRC-12AR-K-1 BC-P FW 1.05
.070 None
-2 P-E SW l.45
.070 360* Inter., Pipe Side 19%
-3 E-P SW l.45
.070 360* Inter., Elbow Side 6%
-4 P-SE FW l.27
.070 None
-5 SE-N
.SW Not Examined
WELD TYPE FAB.
%C INDICATIONS
% THRU-WALL (MAX)
RECIRCULATION SYSTEM (Continued) 2B31-1RC-12BR-A-1 BC-P FW l.04
.060 None
-2 P-E SW 1.40
.060 None
-3 E-P SW l.44
.060 360* Inter., Pipe Side 25%
-4 P-SE FW l.21
.060 None
-5 SE-N SW None 2B31-lRC-12BR-B-1 BC-P FW l.06
.070 None
-2 P-E SW l.44
.070 360* Inter., Pipe Side 26%
-3 E-P SW l.51
.070 360* Inter., Pipe / Elbow 22%
Sides
-4 P-SE FW l.26
.070 360* Inter., Pipe Side 23%
-5 SE-N SW None 2B31-lRC-12BR-C-1 Red-P FW l.15
.065 None
-2 P-E SW l.53
.065 360* Inter., Pipe Side 28%
-3 E-P SW 1.60
.060 360* Inter., Pipe Side 30%
-4 P-SE FW l.38
.055 360* Inter., Pipe Side 32%
-5 SE-N SW None 2B31-1RC-12BR-D-1 BC-P FW l.10
.060 None l
-2 P-E SW 1.44
.060 360* Inter., Pipe Side 14%
l
-3 E-P SW l.53
.060 360* Inter., Pipe Side
-17%
l
-4 P-SE FW l.31
.060 None
(
2B31-lRC-12BR-E-1 BC-P FW 1.11
.060 None
-2 P-E
'SW l.43
.060 None l
-3 E-P SW 1.49
.060 360* Inter., Pipe / Elbow 22%.
Sides
-3A P-P FW Not Calc. --
360* Inter., Pipe Side 21%-
I i-
{
4
o UELD SIGNIFICANT WELD NO.
WELD TYPE FAB.
%C INDICATIONS
% THRU-WALL (MAX)
RECIRCULATION SYSTEM (Continued)
-4 P-SE FW l.29
.055 360* Inter., Pipe Side 18%
1
-5 SE-N SW None 2B31-lRC-22AM-1 C-P SW l.16
.048 Parallel to weld C-42%
Cap 53"L & 7 1/2"L P-14%
Pipe 25 1/2"L & 9"L
-2 P-CR SW l.13
.056 Shallow indications in the HAZ called inside geometry. GPC to re-examine next refueling outage.
-3 CR-P SW l.07
.056 Shallow indications in the HAZ called inside geometry.
GPC to re-examine next refueling outage.
-4 P-C SW 0.96 054 Parallel to weld, Pipe 19%
60"L.
2B31-1RC-22BM-1 C-P SW 0.96 048 Parallel to weld, Cap C-16%
25 l!2"L & 5 1/2"L, Pipe P-40%
27"L.
I 2
P-CR SW l.13
.056 Shallow indications in the RAZ called inside geometry. GPC to re-examine next refueling outage.
l
-3 CR-P SW 1.10
.056 Shallow indications in the HAZ called inside geometry.
GPC to re-examine next refueling outage.
l
-4 P-C SW 0.96
.048 360* Inter., Pipe / Cap P-37%
Sides C-30%
l 2B31-lRC-22AM-1BC-1 P-BC SW 0.98
.060 Shallow indications 2
outside the HAZ.
GPC to re-examine next refueling outage.
-1BC-2 P-BC SW 0.98
.060 Shallow indications outside the RAZ.
GPC to re-examine next refueling outage.
.. ~. -.,
n...
WELD TYPE FAB.
%C INDICATIONS
% THRU-WALL (MAX)
RECIRCULATION SYSTEM (Continued) 2B31-lRC-22AM-3BC-1 P-BC SW l.01
.060 Shallow indications
'outside the HAZ. GPC to re-examine next-refueling outage.
.060 Shallou indications outside the HAZ.
CPC to re-examine next refueling outage.
l
[
2331-lRC-22BM-1BC-1 P-BC SW l.01
.060 Shallow indications outside the HAZ.
GPC to re-examine next 1
refueling outage.
l-IBC-2 P-BC SW l.06
.060 None i
2B31-lRC-22BM-3BC-1 P-BC SW l.03
.060 Shallow indications outside the HAZ. GPC to re-examine next refueling outage, i
3BC-2 P-BC SW 1.02 060 Shallow indications I
outside the HAZ.
GPC to re-examine next refueling outage.
2B31-lRC-28A-1 N-SE SW None 2
.045 None
-3 P-E
'SW l.46
.060 Parallel to weld, Elbow 12%
Side 5 1/4"L.
4 E-P SW l.35
.060 360* Inter., Elbow Side 17%
.062 None
-6 T-P SW 0.92
.062 Shallow indications in the RAZ called inside geometry. GPC to re-examine next refueling outage.
l
-7 P-E SW l.30
.057 360* Inter., Pipe / Elbow P-8%
Sides E-4%
-8 E-V FW 1.03
.057 None l
-9 V-P FW l.01
.045 None 1
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WELD TYPE FAB.
%C INDICATIONS
% THRU-WALL (MAX)
RECIRCULATION SYSTEM (Continued) 2B31-lRC-28A-10 P-E SW l.46
.056 Parallel to weld, Pipe 10%
Side - 1 1/4"L
-11 E-Pu FW l.03
.056 None
-12 Pu-P FW 1.13
.041 None
-13 P-V FW 1.03
.041 None
-14 V-E FW l.07
.058 None
-15 E-P SW 1.40
.058 Shallow indications in the RAZ called inside' geometry. GPC to re-examine next refueling outage.
.062 Shallow indications in the HAZ called inside geometry.
GPC to re-examine next refueling outage.
-17 T-C SW l.09
.062 None
-18 CR-Red SW 1.04
.063 None 2B31-lRC-28B-1 N-SE SW Not Examined 2
P-E SW l.28
.060 360* Inter., Pipe Side 15%
-4 E-P SW l.21
.060 Shallow indications in the HA7. called inside geometry.
GPC to re-examine next refueling outage.
-5 P-P FW 0.91
.045 None
-7 P-E SW 1.29
.057 360* Inter., Pipe Side 18%
-8 E-V FW l.37
.057 360* Inter., Elbow Side 7%
-9 V-P FW 1.01
.045 None
-10 P-E SW l.41
.056 360* Inter., Pipe / Elbow P-19%
Sides E-20%
WELD TYPE FAB.
%C INDICATIONS
%'THRU-WALL (MAX)
RECIRCULATION SYSTEM (Continued)
-11 E-Pu FW 1.02
.036 None
-12 Pu-P FW l.13
.041 None
-13 P-V FW 1.03
.C41 Shallow indications in the HAZ called inside geometry.
GPC to re-examine next refueling outage.
-14 V-E FW l.05
.056 None
-15 E-P SW l.32
.056 360* Inter., Elbow Side 23%
.062 Shallow indications in the HAZ called inside geometry. GPC to re-examine next refueling outage.
-17 T-C SW 1.08
.062 None
-18 C-Red SW 1.03
.063 None 2B31-lRC-4AA-1 BC-C FW(?) --
None
-4AB-1 BC-C FW(?) --
None
-4BC-1 BC-C FW(?) --
None
-4 B D-1 BC-C FW(?) --
None 2B31-lRC-6A-1 P-FL FW(?) --
None
-6B-1 P-FL FW(?) --
None RHR SYSTEM 2 Ell-1RHR-20-RS-1 T-P FW l.33
.062 Shallow indications in the HAZ called inside geometry. GPC to re-examine next refueling outage.
-2 P-E FW l.61
.056 360 Inter., Pipe Side 13%
-3 E-P FW 1.56
.056 360* Inter., Elbow Side 14%
2 Ell-lRHR-24A-R-10 P-E FW 2.57
.06Q None
WELD TYPE FAB.
%C INDICATIONS.
% THRU-WALL (MAX)
RHR SYSTEM (Continued) 2 Ell-lRHR-24A-R-ll E-P FW l.69
.062 None
-12 P-E FW l.70
.062 None
-13 E-T FW 1.74
.060 None I
l 2 Ell-lRHR-24B-R-10 P-E FW 2.58
.060 None
-11 E-P FW 1.68
.062 Parallel to weld, Elbow 13%
Side 1-5/8"L, 2-10 9/16"L.
18%
-12 P-E FW l.70
.062 Shallow indications in the HAZ called inside geometry. GPC to re-examine next refueling outage.
-13 E-T FW l.74
.060 None RWCU SYSTEM 2G31-lRWCU-6-D-1 BC-P 1.24
.064 Not Examined
-2 P-E 1.92
.064 None
-3 E-P 1.82
.064 None
-4 P-P 1.22
.064 Not Examined
-5 P-E 1.80
.064 None
-6 E-P 1.98
.064 None
-7 P-V 1.68
.064 None
-8 V-P 1.58
.064 Not Examined
-9 P-E 1.42
.064 Not Examined
-10 E-P 1.40
.064 Not Examined
-11 P-P 1.02
.064 Not Examined
-12 P-E 1.44
.064 Not Examined
-13 E-P 1.46
.064 Not Examined
-14 P-E 1.34
.064 Not Examined
-15 E-P 1.33
.056 Not Examined
WELD TYPE FAB.
%C INDICATIONS
% THRU-WALL (MAX)
RWCU SYSTEM (Continued)
-16 P-V 1.28
.045 Not Examined
-17 V-P 1.31
.063 Not Examined
-17A PX-P 1.30
.063 Not Examined
-18 P-V 1.11
.061 Not Examined KEY FW - Field Weld CR - Cross SW - Shop Weld PX - Penetration P - Pipe N - Nozzle Pu - Pump E - Elbow SE - Safe End FL - Flange T - Tee BC - Branch Connection Red - Reducer C - Cap V - Valve Example: Under " Weld Type" column, P-E is the abbreviation for a pipe-to-elbow weld.
i
o ATTACHbENT 2 CORRECTIVE ACTIONS FOR WELDS HAVING UNACCEPTABLE INDICATIONS l
a Recirculation System RHR System 22AM-18C-1 20-RS-1
-1BC-2 24-B-R-12
-2
-3
-3BC-1
-3BC-2 22BM-18C-1
-2
-3
-3BC-1
-3BC-2 28A-6
-15
-16 288-4
-13
-16 NOTE: As stated previously in this response to NRC I&E Bulletin 83-02, a separate report on the various analyses and repairs will be submitted under separate cover to NRC NRR.
A copy of that report will be submitted to NRC Region II for review, t
i l
a
ATTACHENT 3 ISOMETRIC DRAWINGS FOR RECIRCULATION, RHR, AND RWCU SYSTEMS i
PUMP A SUCTION 2 8 31-IRC - 6 A 2 831-IRC - 2 8 A i-91 RE AC TOR RE CIRCU L A T10N SYS T E M 3 L D-O 2
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CAL. BLOCK: 12-S S - X-l.2 0 H 12 -S S - X -0.6 75 H 2 2 -S S - X - 1.12 5 -4 7 -H REF. P 81 D H - 26003 Figure A-14 LOC ATION : CONTAINMENT 6-N
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ATTACHMENT 2
- s
[
nut'ec?h
.m.%
E N EE m 6833 VIA DEL oRo e SAN JOSE, CALIFORNIA 95119
- PHONE (408) 629-9800
- TELEX 352062
.(m s
May 20, 1983 GPC-07-Oll Mr. J. A. Edwards Georgia Power Company Post Office Box 4545 333 Piedmont Avenue (N.E.)
Atlanta, Georgia 30302
Subject:
Evaluation of Welds with UT Indications in the Hatch 2 Large Bore Recirculation System Piping
Dear Mr. Edwards:
The purpose of this letter is to transmit the preliminary results of the NUTECH evaluation of the two largest UT indications in the large bore Recirculation System piping at Plant Hatch Unit 2.
The approach used in this evaluation was to perform a very conservative crack growth analysis based on the flaw characterization provided by Georgia Power Company.
The results are shown in Figures 1 and 2 for the indications in welds 28B-15 and 28B-10, respectively.
Examination of Figures 1 and 2 will show that the as-charac-terized UT indications will not grow to the Code allowable size for at least 26 months.
An alternate way of assessing the margin is that the current allowable crack size is at least 1.25 times the largest actual crack size (28B-15).
Discussion i
j The allowable end of fuel cycle crack size was determined based on Reference 1.
The loads used in the determination of allowable crack size are design pressure, dead weight and i
OBE seismic.
The resulting stresses.at each specific crack location were obtained from the original Stress Report for the Hatch 2 Recirculation System (Reference 2).
The allow-able. crack size is plotted as a dashed line in Figures 1 and 2.
The predicted growth of the existing UT indications requires several inputs:
l 1)
Steady state applied stress 2)
Weld residual stress 3)
Flaw characterization 4)
Crack growth model 5)
Crack growth law
.. +
)
a a
Mr.
J. A.
Edwards May 20, 1983 Georgia Power Company GPC-07-Oll The approach used was to use conservative input for applied stress, residual stress, crack growth model and crack growth law.
Thus, the result of the analysis is a very conservative prediction of crack size versus time.
The steady state loads at each crack location due to operating pressure, dead weight and thermal expansion were obtained from Reference 2.
The steady state stresses were then calculated based on design minimum wall thickness at each specific location.
The weld residual stress was obtained from a set of NUTECH standard residual stress curves (Reference 3).
The residual axial stress curve for large bore piping from Reference 3 is shown in Figure 3.
The flaw sizes were obtained from Reference 4 and are shown in Table 1 for both welds 28B-10 and 28B-15 which contain the largest flaws in the large bore piping.
It was conserva-tively assumed that the crack was full depth for the entire circumference.
The crack growth model is an edge cracked plate.
The growth rate predicted through the use of a cracked cylinder model would be much slower.
Figure 4 uses the same input as Figure 1 except for use of the cracked cylinder model instead of the edge cracked plate.
Figure 4 shows a growth rate less than one tenth of Figure 1.
Figure 4 is not strictly applicable to the Recirculation System piping as the thickness to radius ratio of the Recirculation System piping is slightly less than 0.1.
However, Figure 4 does indicate the magnitude of conservatism in Figures 1 and 2.
The crack growth law is the upper bound law from Reference 5 and is given below:
Qa
-1 4.615 4.116 X 10 K
=
dT da Differential crack size
=
dT Differential time
=
Applied stress intensity factor K
=
Inspection of Figures 1 and 2 will show that crack growth rates of up to 2 X 10-4 inch per hour are predicted in the final month before the allowable crack depth is reached.
The validity of the crack growth law applied to large flaws is based on linear extrapolation of measured crack growth nut _ech m
,wa
+
3 !.,*,
Mr. J. A.
Edwards May 20, 1983 Georgia Power Company GPC-07-Oll rates versus crack tip stress intensity factor.
Such high growth rates (2 X 10-4 inch per hour) have not been observed in realistic laboratory or field situations.
It is likely that a realistic upper bound weld sensitized IGSCC crack growth rate in an operating BWR is less than 2 X 10-4 inch per hour.
The results of the crack growth evaluations are given in Figures 1 and 2 for welds 28B-15 and 28B-10, respectively.
The initial crack size of 23% of the wall thickness for weld 28B-15 will grow to the allowable size of 63% in approxi-mately 26 months or about one and one half 18 month fuel cycles.
Another way of expressing the same margin is to determine the crack size that would grow to the allowable crack size in the next 18 month fuel cycle.
From Figure 1 for weld 28B-15, a crack size of 29% would grow to the allowable of 63% in 18 months.
Thus, the currently allowable crack size is 29%, which is 1.25 times the largest measured crack size.
Summary Very conservative crack growth evaluations have been performed which show that the UT indications in the large bore Recircu-lation piping at Plant Hatch Unit 2 will not grow to the Code (Reference 1) allowable size for at least 26 months.
Or stated another way, the currently allowable crack size is at least 1.25 times the largest measured crack size.
If you have any questions or comments regarding the infor-mation presented herein, please do not hesitate to contact Jim Charnley.
Very truly yours, J.
E.
- Charnley, P.E.
Project Engineer
}$A%6+
N NI~nny
[
Project Manager JEC:NE/gmm Attachments cc:
H. C. Nix, Jr. (Baxley)
JEC-83-013 NE-83-126 nutech
,3
T O
. o s
REFERENCES 1.
ASME Boiler and Pressure Vessel Code Section XI, Paragraph IWB-3640 (proposed), " Acceptance Criteria for Austenitic Stainless Steel Piping" 2.
General Electric Report 22A4264AA, Revision 0 3.
NUTECH Internal Memo PCR-83-003, March 4, 1983, " Weld Residual Stresses for IGSCC Crack Growth Evaluations" 4.
Indication Notification Forms I83H2015 Rev. 0 (28B-10) April 28, 1983 I83H2016 Rev. 0 (28B-15) April 28, 1983 5.
EPRI-2423-LD, " Stress Corrosion Cracking of Type 304 Stainless Steel in High Purity Water - A Compilation of Crack Growth Rates," June 1982 9
]
+s TABLE 1 UT' CHARACTERIZATION Weld Crack Characterization Maximum Number Orientation-Length Depth 2B31-lRC-28B-10 Circumferential-Essentially 3600 20%
2B31-lRC-28B-15 Circumferential Essentially 3600 23%
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I RFQEKMC 83/05/20 08.23.35 ICSCC CROUTH ANALYSIS (CIR. CRACK)
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RLLOURBLE R/T RT THE END OF FUEL CYCLE N
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' MMKKV 83/05/20 08.09.24 t
-s ICSCC CROUTH ANALYSIS (CIR. CRACK)
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+ 8.1 FGPC83.02 Figure 3 AXIAL RESIDUAL STPISS PIPE DIA!ETER CF 20" TO 28"
ArtisLUt.
83/05/20 l l. 20. W ICSCC CROUTil ANALYSIS ICIR. CRACK)
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0LLOUfl0LE n/T OT Tile END OF FUEL CYCLE L
ATTACHMENT 3 nute p
eass VIA DEL ORo e SAN JOSE,CAUFORNIA 95119 e PHONE (408) 6294800
- TELEX 352062 May 23, 1983 GPC-07-012 Mr.
J. A. Edwards Georgia Power Company Post Office Box 4545 333 Piedmont Avenue (N.E.)
Atlanta, Georgia 30302
Subject:
Stress Intensity as a Function of Crack Depth for Weld 28B15
Reference:
NUTECH Letter GPC-07-011, J. E. Charnley and N. Eng to J. A. Edwards, dated May 20, 1983
Dear Mr. Edwards:
The attached four (4) tables give the stress intensity as a function of crack depth for both applied and. residual stress for Weld 28B15.
The first two (2) tables apply to an edge cracked plate model (Figure 1 of the reference).
The last two (2) tables apply to an I.D. cracked cylinder model (Figure 4 of the reference).
If you have any questions or comments regarding the infor-mation presented herein, please do not hesitate to contact Jim Charnley.
Very truly yours, J. E. Charnley, P.E.
Project Engineer ProjectManager]
N. Eng JEC:NE/gmm l
Attachments cc:
W. Hazelton (NRC)
H. C. Nix, Jr. (Baxley)
JEC-83-014 y:
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