ML20099F268
| ML20099F268 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/20/1984 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8411260352 | |
| Download: ML20099F268 (2) | |
Text
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y SOUTH CAROLINA NECTRIC & GAS COMPANY k-Asr oprics 7 4 l1
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COLUMelA, SOUTH CAROLINA 29218 g'
20,.1984 w
November
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VICE PRESIDENT I'
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Mr. Harold R. Denton, Director-Office of Nuclear Reaq. tor Regulation f '
s U.S. Nuclear Regulatory 1Commis,sion 7,
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Washington, D.C.
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Subject:
- 'Virgl'lhC. Summer }iuclear Station Docke t'- No. 50/395 Operating License No. NPF-12 i
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\\.i, Steam '3enerator Tube Plugging
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Dear Mr. Dentot s
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i In response to Staff interest in any ster 3 n gen'erator row 1 tubes plugged at the Virgil C. Summer Nuclear Station as a result of U-ben'd area degradation er leakage, the following information 1s provided.
s During "Ita present.refuc,1.ing outage, South Carolina Electric and Gas Cor@Sny ('SCEryu). conducted standerd eddy current inspec'tlons 'of all'unpitlgged row 1 stehm generator tubes in each of the three-(3) oceam generators at'the Station.
Of the 340' row 1 tubes ' inspected,1 tube within the B steam generator was identified as leaking in the U-bend area and was subsequently plugg~ed.
The location of that leak was determined to be.in Column 107,' 2.4 inchos above the 14th support plate on the inlet side of the steam generator.
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Earlie^r this year, during July 198k, ~ ~ ne other tub'e, also in 0
the,B steam generator, had through wall leakage in the U-bend area and was plugged.. The location of that leak wac determined t.o be in Coltimn lol, 2.4 inches abov3 tho 14th support plate on the hot leg, side.
No other row 1 tubes indicate any degradation withiri rfte U-bend area.
s A G'ecial Re< art JSPR 84-016 dated November 14, 1934) was p
forwarded ty Tiegion II ident,tjying all tubes plugged as a result of eddy curent inspections in accordance with Technical Spepifications 4.4.5.2 and 4.4.5.5(a).
SCE&G expects to continue with its eddy current testing program in accordance
'wl,th the inspection frequency' outlined in Technical Specification 4.4.5.3.
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- o Mr. Harold R.'Denton, Director.
Steam Generator Tube Plugging November' 20, 1984 Page #2 In order to remain sensitive to steam generator issues, an in-house Steam Generator Committee for the purposes of collecting and evaluating-information available on design, operation, maintenance and inspection of steam generators has been established.
This Committee will make appropriate recommendations pertaining to enhanced steam generator maintenance and operation.
Furthermore, SCE&G is now a member of the Electric Power Research Institute (EPRI) Steam Generator Owners Group and will continue investigating and pursuing resolution of generic steam generator concerns.
Should. you have any questions, please contact us at your convenience.
Very truly yours,
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O. W Di
, Jr.
MDB/OWD/gj
Attachment:
cca V. C.
Summer C. A. Price T. C.
Nichols, Jr./O. W. Dixon, Jr.
C.
L. Ligon (NSRC)
E.
H. Crews, Jr.
K.
E. Nodland E.
C. Roberts R. A.
Stough W. A. Williams, Jr.
G.
Percival D. A.
Nauman C. W.
Hehl J.
P.
O' Reilly J.
B.
Knotts, Jr.
Group Managers NPCF O.
S.
Bradham File