ML19319A925

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Responds to 770125 Memo & Summarizes Available Info Re Steam Generator Tube Leak Incidents.Tube Diagram & Table Encl
ML19319A925
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 01/28/1977
From: Shao L
Office of Nuclear Reactor Regulation
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NUDOCS 7912300196
Download: ML19319A925 (4)


Text

_ _ _ _

.g JAN 2 81977

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D. Eisenhut, Assistaot Director for Operational MEMORANDUM FOR:

Technology, Division of Operating Reactors t.. Chao, Chief. Engineering Branch. Division of FROM:

Operating Reactors OCONEE UNITS 1, 2 & 3 STEAM GENERATOR TUBE 1.EAK i

SUBJECT:

INCIDEilTS i

25, 1977, and as a follow-This is to respond to your note of Jannary 16,1976, regarding the subject up to my note to you dated DecemberWe have been in constant cont follow the progress of B&W's investigation into the cause of theseF matter.

Following is a su::

reported tube fatiures.

y to us to date:

Attached Figure 1 and Table 1 give the locations of all failed

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tubes that either caused leaks already or were found 1.

cracked.

tube sheets or at support plates.

direction and near the uppi a

Information obtained from two informal sources 2.

The top steam outlet side cracks caused by flow induced vibration.

was the region where the maximum steam' cross flow velocity w lfsthis failure mechanism were to be confimed by the licensee or their HSSS. It would be serious because it could indi in;;dequacy of the support system.

j Prior to the tube leal !ncidents at Units 1 & 2 on 12/4/76 12/9/76, respectively, the licensee had infomed us that the crack 3.

could be attributed to random manufacturing defects.

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Thera is only one tube that was renoved la steasa generator 28T t

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(unit 2 SG B; for laboratory examination.

reported the results of the laboratory examination to us.

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We have requested through Don Neighbors that the licensee elaborate ontheun-confirmedreports-(Item (2)). We have also requested

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that D.' Neighbors arrange a meeting with the licensee on the subject.

L.-Shao, Chief l

Engineering Branch Division of Operating Reactors i

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Enclosures:

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As stated DISTRIBUTION:

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OTSG TUBE IDENTIFICATION PLAN-VIEW

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. TABLE'l' OCONEE OTSG TUBE EXPCRIENCE STEAM GE OR,._

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TUBE ELEVATIO3 DATE LANC TUDE CONDITION DESIGNATION.

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-77 17 lubcsheet 11/76 Yes Yes Crack 1-B 114 109 14thPiate 12/76 No Yes No Visual inspecticn 1-B 113 -

110 14th Plate 12/76 Nc No Similar to 114/109 1-B 75 18 Tubtsheet 12/76 Yes.

No 300* Crack 2-B 77 23.

Tubeshoot 12/76 Yes Yes 270* Crack, llole.

2-8 77 27 15th Plate 12/76 Yes yo Wear Appear-2, ance 2-8 124 42 12th Plate' 12/76 No No Eddy Current

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