ML20072G986
| ML20072G986 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/23/1994 |
| From: | Marsh W SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9408250171 | |
| Download: ML20072G986 (4) | |
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Southem Califomia Edison Company 23 PARKER STREET IRVINE, CALIFOHNIA 92718 Till PHONE -
WAL TEH C MARSH August 23, 1994
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U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Verification of Data for Generic Letter 92-01, Revision 1 San Onofre Nuclear Generating Station Units 2 and 3
References:
1.
Letter from W. C. Marsh (Edison) to USNRC, dated June 22,1994;
Subject:
Revision to Supplemental Response to Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity,10 CFR 50.54(f) 2.
Letter from Mel B. Fields (USNRC) to Mr. Harold B. Ray (Edison),
dated July 21,1994;
Subject:
Genetic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity Southern California Edison (Edison) provided a final response to Generic Letter ( GL) 92-01, Revision 1, by letter dated June 22,1994 (Reference 1). Reference 2 acknowledged that Edison had provided the information requested by the NRC in GL 92-01, Revision 1, and requested verification that the data in the NRC summary data file was entered accurately.
Edison has compared the NRC summary data file to the data provided in Reference 1. The information in the NRC data file is the same as the data provided in Reference 1, with minor exceptions as provided in the Enclosure. These exceptions should not affect NRC assessments of the Units 2 and 3 reactor vessel beltline materials.
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If you have questions or require further information, please let me know.
Sincerely, l
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4 Enclosure cc:
L. J. Callan, Regional Administrator, NRC Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 M.13. Fields, NRC Project Manager, San Onofre Units 2 and 3
Summary File for Upper Shelf Energy Plant le{ttirse Meat No, Material 1/4T USE at 1/4T Unirrad.
Method of Name Idwit.
Type ECL Neutron USE Determin.
Fluence at Unirred.
EOL USE san Int. shell C 7596-1 a 5338 1 91 2.503E19 119 Direct Onofre 2 C 6404-1 EOL:
Int. shett C 7595-2 A 533B 1 87 2.503E19 113 Direct 10/18/
C-6404 2 2013 Int shell C 7595 1 A 5338 1 76 2.503E19 99 Direct C 6404-3 Lower A 6735 1 A 5338 1 80 2.503E19 104 Direct shell C 6404 4 Lower C-7585 1 A 5338 1 89 2.503E19 118 Direct shett C 6404-5 Lower C 7596-2 A 5338 1 95 2.503E19 124 Direct shett C 6404 6 Int. shell BOLA E 8018, 71 2.503E19 93 10*F data axial SMAW welde 2 203A Int. shalt SOLA E S018, 71 2.503E19 93 10*F data axial SMAW wetde 2 2038 Int. shell BOLA E 8018, 71 2.503E19 93 10*F data axial SMAW welds 2 203C Lower 83637 Linde
-194-2.303E19 136 10*F data sheLL 0091, SAW 103 exist weide 3 203A Lower 83637 Linde 2.503E19 136 10'F data shelt 0091, SAW 103 axlel 6
g 83637 Linde 103 2.503E19 136 10*F data et 0091, SAW antal weide 3 203C Int. to 90130 Linde 107 2.503E19 145 Direct lower 0091, SAW shett cire. weld 9 203
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Summary File for Upper Shelf Energy Plant settline Heat No.
Material 1/4T USE at 1/4T Unirrad.
Method of Name Ident.
Type EOL Weytron USE
- Determin, Fluence at Unirred.
l j
EOL USE San Int, shelt C-9195-2 A 5338 1 42 73 2.503E19 95 Direct onofre 3 C-6802 1 l
EOL:
Int. shett C 9195 1 A 5338 1 te 81 2.503E19 105 Direct 1
10/12/
C 6802-3 r
2013 i
2.503E19 115 Direct l
Int. shett C-9218-2 A 5338 1 84 89 j
C 6802 2 l
2.503E19 118 Direct Lower C-9220 1 A 5338-1
-9G 9
l shell j
C 6802 4 1
Lower C-9218-1 A 5338 1 89 2.503E19 116 Direct shell C 6802 5 j
2.503E19 92 Direct 70 71 Lower 8 3388 1 A 5338-1 shell C 6802 6 Int. shell 83650 Linde
-104-2.503E19 136 20*F data estal 0091, SAW 105 welds 2-203A/C j
2.503E19 161 Ofrect Lower 88114 Linde
-123 122 shell 0091, SAW exist i
welds 3 203A/C j
1 Int. to 90069 Linde 92 2.503E19 123 Direct tower 124, SAW shell i
cire. weld I
0 203 Int. to 90144 Linde 70 2.503E19 91 Direct tower 124, SAW j
I shell cire, weld 9 203 upper to 88118 Linde 115 0.23E18 125 10*F dats shell 0091, SAW ueld il i
p Referencest Cheelest comosition, fluence, and UUSE data are f rom Jme 22, 1994, letter from W. C.
l Marsh (SCE) to USWRC Document Control Desk, subject: Sumtementary response to Generic
)
Letter 92-01, Revision 2, " Reactor vesset Structural Integrity,10 CFR 50.54(f)" San l
l Onofre Wuclear Generating Station Units 2 and 3 1
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