ML20011B254
| ML20011B254 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/24/1981 |
| From: | Beckham J GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-07811, TAC-08019, TAC-7811, TAC-8019, NUDOCS 8112080256 | |
| Download: ML20011B254 (11) | |
Text
Geyg a Pcwer Company 333 P.cdment Asenne At'anta, Georg;a 30308 Te echene 404 526-7020 t
t/a:wg Acmess Pet Of re Bo< 4545 AraNa. Gecrya 20302 Georgia Power J. T. Beckham, Jr.
$Na7$$$rEn d M' 34" November 24, 1981
@Q Director of NtJclear Reactor Regulation i
OEC7 Jgg7, R U. S. Nuclear Regulatory Commission m,,,%,*
Washington, D. C.
20555
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/j NRC DOCKET 50-321 0 / U \\
OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 LIMITATIONS EXPERIENCED DURING 1981 CLASS 1 INSERVICE EXAMINATIONS Centlemen:
Georgia Power Company wishes to advise you of Class 1 inservice examinations which did not receive. a full-code examination during the 1981 maintenance / refueling outage on Hatch 1.
The examinations were performed in accordance with the requirements of the 1974 edition of the ASE Section XI Code with addenda through Summer 1975.
Enclosed as Attachment 1 is the listing of Class 1 examination areas not receiving a full-code examination.
These areas included lugs, Reactor Recirculation System vessel nozzles, piping butt welds, and recirculation pump studs. is a summary of the limitations encountered.
Also included as part of Attachment 2 are figures to pictorially describe limitations encountered during the mechanized examination of Reactor Recirculation System nozzle-to-vessel welds.
If you have any questions in this regard, please contact this office.
Sincerely yours, J
J. T. Beckham, Jr.
l#
h04l Attachments J
I xc:
M. Manry R. F. Rogers, III Director - Region II 8112080256 811124 PDR ADOCK 05000321 P-PDR
ATTACHMENT 1 Edwin I. Hatch Nuclear Plant, Unit 1 1981 Inservice Examination Class 1 Examination Areas Not: Receiving A Full-Code Examination The following lugs.did not have 2T (2 times thickness) of base material on the lugs examined.
The lug welds, however, were ultrasonically examined and found to be acceptable.
Main Steam System 1821-1MS-24A-8PS-D-2 (Pipe Support)
Feedwater System IB21-lFW-18A-llHL-2 (Hanger Lug)'
1821-lFW-188-6RL-4 (Restraint Lug) 1821-lFW-188-9H.-2 (Hanger Lug)
IB21-lFW-12AB-lPS-B (Pipe Support)
Reactor Recirculation System 1831-lRC-288-15HL-3 (Hanger Lug)
IB31-lRC-22BM-lHL-B-2 (Hanger Lug)
High Pressure Coolant Injection System lE41-lHPCI-10-D-7HL-A-8
-(Hanger Lug)
Core Spray System lE21-lCS-10A-3PL-l*
lE21-lCS-10A-3PL-2*
i lE21-lCS-10A-3PL-3*
lE21-lCS-10A-3PL-4*
(Pipe Lugs) lE21-lCS-108-4PL-l*
lE21-lCS-108-4PL-2*
lE21-lCS-108-4PL-3*
lE21-lCS-108-4PL-4*
(Pipe Lugs)
- Augmented examinations requested by Georgia Power Cvmpany' personnel for support of NRC I&E Bulletin 79-14 walkdowns.
2-4 The following - coverage was obtained on the Reactor Recirculation System suction nozzle 1N1B nozzle-to-vessel weld examination:
00 parallel exam 100% coverage
=
450 parallel exam 100% coverage
=
600 parallel exam 100% coverage 4
=
450 transverse exam =
0% coverage 600 transverse exam =
0% coverage The following coverage was obtained on the Reactor Recirculation System inlet nozzle 1N2 (B,E,H,K) nozzle-to-vessel weld examinations:
00 parallel exam 97.8% coverage
=
450 parallel exam 99.8% coverage
=
600 parallel exam 99.9% coverage
=-
450 transverse exam =
0% coverage 600 transverse exam =
0% coverage The following pipe butt welds had physical limitations as noted:
Residual Heat Removal System 1
lEll-lRHR-24A-R-6 No examination from w=0" to w=2" for L=25" to ' L=28" on the upstream side due to a welded pipe support.
No examination for all w's for L=25" to L=28" on the downstream side due to the same pipe support.
However, approximately 90% of the weld examination was accomplished.
High Pressure Coolant Injection System lE41-lFPCI-14-R-7 No examination for w=2-3/4" and greater for L=6" to L=16" and L=29-7/8" to L-37-1/8" on the upstream 4
sidc due to a
permanent pipe restraint.
No examination for w=1-7/16" and greater for all L's on i
the downstream side due to the proximity of weld no.
8.
Howeve.,
approximately 80%
of the weld examination was accomplished.
The following bolts were examined from one end in the installed condition:
f IB31-28A Reactor Recirculation Pump-Bolts 11-16 00 examination of studs limited to the 1831-28B top five inches of the stud.
Reactor Recirculation Pump Bolts 1-5 i
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ATTACMENT 2 Summary of Limitations (1) Due to the geometrical configuration, sixteen of the twenty-one category B-K-1 hanger lugs examined ultrasonically did not have the complete 2T (2 times thickness) of the base material of the lugs examined. However, each lug weld, along with the required base material of the pipe, was fully code examined and found to be acceptable.
l (2) Using mechanized equipment for the examination of Reactor Recirculation-System suction nozzle IN18, the examination agency was able to perform a t
full-code examination in accordance with the 1974 edition of ASE Section XI with addenda through Summer 1975 with the exception of the 45-and 60-degree transverse scans.
These scans could not be performed due to nozzle joint configuration.
Figure 1 shows the areas where the transducer module could not be placed.
However, since the scans were performed from both sides of.the nozzle-to-vessel weld, with ultrasonic beams directed toward and away from the nozzle centerline, the examination agency was able to examine the entire volume that the ASME Code requires.
Figure 1-A and 1-B demonstrate that full coverage was achieved at 0, 90, 180, and 270-degree azimuth positions.
(3) For the Reactor Recirculation System inlet 1N2 nozzles, the examination agency was able to perform almost a full-code examination-using mechanized equipment.
Due to the proximity of the insulation support ring to the nozzle-to-vessel weld, it was not possible to examine the entire 1/2 T (1/2 times thickness) base metal adjacent to the weld with 0,
45, and 60-degree parallel scans.
In addition, the 45-and 60-degree transverse scans were not performed due to nozzle joint configuration.
Figure 2 shows the areas where the transducer module could not be placed.
Scans were performed from both sides of the nozzle-to-vessel weld.
Figures 2-A and 2-B identify the small volume that was not' examined.
It-is important to note that the volume that was examined includes the weld, the adjacent base material on the vessel side for a distance of two inches, and all required base material en the nozzle side.
In summary, the following coverage was obtained on these nozzles:
00 parallel exam 97.8% coverage
=
450 parallel exam 99.8% coverage
=
600 parallel exam 99.9% coverage
=
(4) Due to geometrical configurations two of the fifty category B-J butt welds examined experienced some limitations.
However, approximately 80%
of weld 1E41-lHPCI-14-R-7 was examined and approximately 90% of weld lEll-lRHR-24A-R-6 was examined.
(5) The following bolts were examined from one end in the installed condition:
1831-28A Reactor Recirculation Pump Bolts 11-16 00 examination of the studs limited to the top five inches 1831-28B of the stud.
Reactor Recirculation Pumps Bolts 1-5
ATTACl+4ENT 2 (Continued)
Since these examinations are usually performed with the studs in place, the examination agency has recommended that the calibration standard be modified so that. full coverage can be obtained-during examinations with the studs in place. Georgia Power Company is taking this recommendation into consideration.
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