ML17256A953

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Responds to NRC Questions on Eddy Current Insp Program Re Steam Generator Evaluation
ML17256A953
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/18/1982
From: Maier J
ROCHESTER GAS & ELECTRIC CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
NUDOCS 8205240469
Download: ML17256A953 (6)


Text

REGULA'TORY FORMATION DISTRIBUTION SY M ('RIDS)

'AGCESSION NBR;8205240469 DOC ~ DA'TE: 82/05/18 NOTARIZED:,,NO DOCKET FACIL;.50 244 Robert Emmet Ginna Nuclear Plant>

Uni,t ii <<Rochester G

05000244

'AUTH,NAME AUTHOR AFFILIATION MA'IERRJ ~ ED Rochester Gas 8 Electric Corp ~

RHC IP 9 NAME, RECIPIENT AF F IL'lbTION QRUTCHF IELD P D ~

Operating Reactors Br anch 5

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SUBJECT:

Responds to NRC auestions on eddy cur rent insp program re steam generator evaluations

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DISTRIBUTION CODE! 'A001S

.COPIES RECEIVEDoLTR., 3 -ENCL SIZEj

'TITLE:

General Distribution for after Issuance of.Operating License NOTES:NRR/DL/SEP icy, 05000244 REC IP IENT ID "CODE/NAME ORB ¹5 "BC 01

.'COPIES LTTR ENCL RECIPIENT ID 'CODE/NAME COPIES LT<<TR ENCL INT<<ERNAL: ELD/HDS4 NRR/DL OIR NRR/DS I/RAB RGN1 NRR/DHFS DEPY08 1

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EXTERNAL: ACRS NRC PDR NTIS NOT>ES:

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Q lTOTAL.NUMBER OF COPIES 'REQUIRED:

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ti IIIIIIIIII IIIIIIIIIIII Zlà I III/g/III ROCHESTER GAS AND ELECTRIC CORPORATION

~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAILER Vice Preeident TKI.EPHONE AREA cooK Tie 546-2700 May 18, 1982 Director of Nuclear Reactor Regulation Attention:

Mrs Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Washington, D.C, 20555

Subject:

Eddy Current Inspection Program Steam Generator Evaluation R.

E. Ginna Nuclear Power Plant Docket No. 50-244 Dear Mr. Crutchfield-.

This letter is in response to questions from members of the NRC Staff.

Question 1

Provide a full breakdown of eddy current examination sampling.

Answer 1

"A" Steam Generator Examination Program The eddy current inspection included:

a) b)

c) d)

99.96% of inlet tubes to the first support plate, ill inlet tubes over the U bends, 415 outlet tubes to the first support plate, ill outlet tubes to the sixth support plate.

(These are the same tubes identified in item b above.)

"B" Steam Generator Examination Program The eddy current inspection included:

a) b)c) d)

99.96$ of inlet tubes to the first support plate, 251 inlet tubes over the U-bends, 415 outlet tubes to the first support plate, ill outlet tubes to the sixth support plate.

(These tubes were included in the number of tubes: inspected in item b above.)

82052404'20518 PDR ADQCK'05000244, goo<

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ROCHESTER GAS AND ELECTRIC CORP.

DATE May 18, 1982 TO Mr. Dennis M

Crutchfield SHEET NO.

2 Question 2

Confirm that all tubes within two rows of the periphery on the cold leg side of both steam generators were examined.

Answer 2

Two rows of tubes were examined around the periphery of both steam generator's outlet (cold leg).

Question 3

Were periphery tubes examined for their full length or partial length?'nswer 3

All periphery tubes were examined to the first support plate.

Additionally, all periphery tubes in the "B"

Steam Generator inlet were re-examined after repairs to the sixth support plate, with 140 of these tubes being examined over the U-bends.

Question 4

What was the axial length of the indications found in tube R32 C15 at the time of plugging?

Was the examination absolute or differential?

Answer 4

In April 1976, utilizing a differential eddy current technique, R32 C15 had a dent signal at the first support plate, a localized ID signal 3.5 inches above the top of the tube sheet and a distorted tube sheet entry signal (much less than 20% O.D. signal).

In April 1980, utilizing differential and absolute techniques, R32 C16 had a localized 36% outside diameter signal approximately one inch above the top of the tube sheet Very truly yours, Jo E.

aier

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