ML20077D737
| ML20077D737 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/22/1983 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8307270062 | |
| Download: ML20077D737 (3) | |
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s.
SOUTH CAROLINA ELECTRIC & GAS COMPANY post opric tee CotuustA. SOUTH CAROLINA 29218
- O. W. DixoN, JR.
July 22, 1983 vice m...."'
NUCL. An Op.mAreoMS Mr. Harold.R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12
~
Radiation Dosage During Steam Generator-Modification
Dear Mr. Denton:
In a letter dated May 3, 1983, South Carolina Electric and Gas Company (SCE&G) committed to provide a final report to the NRC concerning radiological dose received during the Steam Generator modification effort.
Attached is a summary of the occupational dose. received by major task and a comparison of estimated versus actual doses received.
The column-labeled, " Estimated Man-Rem," was derived by utilizing the Westinghouse _ generic estimation of doses found in the Westinghouse Preheat Steam Generator D2/D3 Design Modification Final Design Review, and by taking into account the plant specific condition of the Virgil C.
Summer, Nuclear Station Steam Generators.
It is evident that the actual dosas received were much less than estimated.
This can be attributed to SCE&G's overall commitment to maintenance of As Low As Reasonably Achievable (ALARA) doses as manifested by excellent operational conditions as well as good outage planning.
If you have any questions, please contact us.
Very trul
- yours,
/ gf0 O. W. D' on, J
/fje cc:
(See Page #2)
W' t
8307270062 830722 PDR ADOCK 05000395 P
Mr. Harold R.
Denton July 22, 1983 Page 72 cc:
V. C.
Sunmer T.
C.
Nichols, Jr./O. W.
Dixon, Jr.
E.
H.
Crews, Jr.
E. C. Roberts H.
N.
Cyrus J.
P.
O'Reilly Group / General Managers O.
S.
Bradham R.
B.
Clary C. A.
Price A.
R.
Koon C. L. Ligon (NSRC)
G. J. Braddick J. C. Miller J. L.
Skolds J. B.
Knotts, Jr.
NPCF File (Lic./Eng.)
,1 t-L i
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i 1
, -, _, - _, _.... ~... _, _.,,. -. -.. _ - _.., - _ _ _... _ _....., _,.. _ _ _... _. _. -..
Mr. Harold R.
Denton July 22, 1983 Page #3 S/G NOZZLE MODIFICATIONS RADIOLOGICAL DOSE COMPARISONS (RWPs)
Estimated Actual RWP No.
Description of Jo'3 Man-Rem Man-Rem S/G "A"
03-11 Feedwater Nozzle Pipe 5.004 0.866 cut and re-weld S/G "A" 03-14 Removal of F.W. Nozzle 2.080 1.245 Internals and Machine S/G "A"
03-17 Manifold Box & Internals 4.490 0.992 Installation and Final Clean-up and equipment removal S/B "B" 03-12 F.W.
Nozzle pipe cut 5.004 0.674 and re-weld S/B "B"
03-15 Removal of F.W. Nozzle 2.080 0.693 Internals and Machine S/B "B"
03-18 Manifold Box and 4.490 0.953 Internals Installation and Final Clean-up and equipment removal I
S/G "C" 03-16 F.W.
Nozzle Pipe cut 5.004 0.306
(
and re-weld S/G "C"
03-16 Removal of F.W.
Nozzle 2.080 0.984 Internals and Machine S/G "C" 03-19 Manifold Box and 4.490 0.780 Internals Installation and Final Clean-up and equipment removal
-. -.