ML19319B034
| ML19319B034 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/14/1977 |
| From: | Neighbors D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001060055 | |
| Download: ML19319B034 (10) | |
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Duke Power Comparty c
FACILITY:.
Oconee Huclear Station i
StM1ARY OF MEETING HELD ON MAY
. 13, 1977. TO DISCUSS THE STEAM GENERATOR ~
TUBE PROBLEM AT OCONEE NUCLEAR STATION u
On May 13.1977.- representatives of Duke Power Company (DPC) arid Babcock i
and Wilcox (BW) met with the NRC staff to discuss the subject topic.L
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A list of attendees is attached.
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f Duke Power Co. and BW wers told that the purpose of the meeting was to
.I discuss the status of the S-G tube leak problems at Oconee and the plans that Duke and B W have for resolving these problems.
I Mr. Hooker of BW made a presentation which included an overview of the tube failure problem which included a history of tube leaks and accomplish-j ments since the previous NRC meeting on February 15,.1977. Mr. Hooker's presentation is attached. The data in the attached presentation do not include the tube leak which occurred on May 7.1977..
At the present time. Duke Power' Co. and 89 have not determined the cause of the surface defects where cracking of the tubes initiates and then propagates due to flow induced vibration.
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Investigations are continuing to determine the cause of the S-G tube problem. One potential cause has been identified which cculd aggravate W.
the tube cracking problem. The testing of steam stop and control valves-at Oconee have been tested at a frequency 'of daily and weekly, mspectively.
Recent tests have confirmed that the cycling of the components induces.
system pressure transients which may prwpagate to the steam generators; The frequency of this testing ~has been changed to' monthly and additional-analyses are planned of the possibility of this being the causeMR2 C
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- -. NRC Form 318 (2 76) NRCM 02040
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LAt our request, Duke Power Company has comitted to do the follow
-1.
_ Provide documentation for the basis for safe continued operation of the Oconee steam generators. _ This docmentation will include analyses of the probabilities of the failure of the tubes under several failure mechanisms.
This will be provided within 60 days.
2.-
Previde'~us with Duke Power Company's and B&W plans and schedul investigating the possible resolution of this problem.
be provided within about 60 days also.
This will
. 3. -
Inform HRC of its proposed course of action before any tube is plugged and before the facility is returned to operation in the -
event that the facility is shutdown to investigate or to' plug a staan generator. tube or to otherwise correct steam generator tube leakage.
4..
coolant steam generator leakage rate of 1 gpm an limits er the reactor and secondary coolants by June 5,1977.
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Don Neig rs, Project Manager Operating Reactors Branch fl Division of Operating Reactors
Enclosures:
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1.ist of Attendees-0 2.
Presentation by Mr. Hooker. B&W
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ATTENDEES AT~
HRC MEETING WITH 1
DUKE POWER CDKPAllY AND BABC0CK AND WILCOX MAY 13,1977 NRC L
I J. Reese K. Goller A. Schwencer L. dhao J. Scinto-R. Stuart
- F. Almeter
- 8. D. Llaw
-J. Strosntder R.-La Grange J. Guibert G. Millman L. Frank G. Zwetzig L.'Barrett D. Neighbors DPC M. Tucks.an H. Tucker K. Canady C. Sansburg B&W G. Geissler W. Keyworth N. Hooker F. Burke D"*
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'-*3-D. Hitti R. Coad r
JUN 141977
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DAO Form N RC-3 3 8 (7.75) NRCM 0240 fr v..
nove.=uswr e.,uvi=a orrics Ms.so.ees
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1.
OTSG TUBE LEAKS 1
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"HISTORi l.
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! JULY.1976 FIRST LEAKING TUBE (3-B).
j l NOVEMBER.1976 SECOND LEAKING TUBE-(1-A).
NOVEMBER 1976 B&W INITIATED EVALUATION / CORRECTION PROGRAM:
l INSPECTION CAPABILITY.
TUBE SAMPLE REMOVAL CAPABILITY.
TUBE STABILIZER DEVELOPED.
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DECEMBER 1976 LEAKS SIMULTANEOUSLY IN OCONEE 182.
g THOROUGH INSPECTION OF BOTH UNITS.
-TUBE SAMPLES (2). REMOVED FOR LABORATORY EXAMINATION.
1-JANUARY-MARCH ADDITIONAL LEAKS IN OCONEE 183.
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. 1977 FEBRUARY'1977 DUKE POWER IDENTIFIED TURBINE STOP VALVE TESTING.
MARCH 1977 ADDITIONAL TUBE SAMPLE OBTAINED FROM OCONEE 1-B.
MARCH 1977 B&W RECOMMENDED ACTIONG TO PREVENT REPEATED SHUTDOWNS.
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iUBJECT 3@ - CATALOG NO.
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-t ACCOMPLISHMENTS SINCE PREVIOUS'
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NRC MEETIllG (2/9/77)
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REMOVAL AND EVALUATION OF ADDITIONAL TUBE SAMPLE (77/25, OCONEE 1-B) i EVALUATION- 0F IURBINE STOP VALVE IESTS AT Oc0 NEE AND TMI-1.
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QUALIFICATION OF TUBE STABILIZER (WELDED AND EXPLOSIVE).
I DEVELOPED GENERATOR INETRUMENTATION PROGRAM.
2-FLOW ANALYSIS OF UPPER END OF OTSG.
j EDDY-CURRENT INSPECTION.0F TMI-1.
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.1 SGGRY OF PAJOR OTSG TULE EXPERIENCE AT QC0 HEE
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GDERATOR R0W TUBE El.EVATION DATE LANE _
LEAKER ColmlTION
. DISPOSITICf4 1-B
'114 109 14i auTE 12/76 No YEs No Visual STAS LiztD IMsPECTioN 1-B 113 110 14TH PuTE 12/76 No No Simun To Stasitizen i_
114/109 1-B 75 18 TustsacET 12/76 YEs. PuooAsu 3000 CaACc Stasitizzo l'
1-8 75
~.12 TuatsnEET 1/77 YEs YEs 3450 CaACx STAsitizto i*
1-5 81 128 14TH PLATE 1/77 No No EnDY-CURRENT STAsILizED
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INDICATION, SOS
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No VISUAL STAslW zen '
1-5 32 13 14TH Purt 3/77 No Yt INSPECTloM 1-B ~
33 14 14Tu PuTz 3/77 No No 31-43% EDDY STAsLizan l'
Cu::ntur IxDiCAT:oM
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1-B -
77 25 TustentET
-3/77 Yes No.
ED0Y-CURRENT REMOVED DisTonTioM 1-B 2
7 13TH Purt 3/77 No Ib EcoY-Cu m wT PLuseen INDICAT!oN T
i 1-B 2
5 13Tu PLArt 3/77 No No EDDY-CURRENT Ptuosto 1
INDICATioM O
1-B 101
-4 4TH PuTE 3/77 No No EDDY-CURRENT PLucsto
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1-B 77 3
15TH PuTE 3/77 Yes No EoDY-CURRENT STABILIZED lHDICATIoN 1-B 77 5
15TH PuTe 3/77 Yes No EDDY-CURRENT STAS!LiztD 4
22'PJ INDICATION ba d,
1-B 77 8
15Tu PuTE 3/77 Yes No EDDY-CURRENT SU.31UZED INDICATION-M D,.
1-B 77 -
22 15TH PLATE 3/77 Yes PhoeAsu 450 CaACK STAaruzta o
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1-B 77 29 Tuntsnati 3/77 Yts No Enny-CentMT STAsturts JNDICATIGM 9
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Stft%RY OF MAJOR OISG TUBE EXPERIENCE AT OCONEE 6EERATOR
.R0W TUBE ELEVATION DATE LANE.
LEAKER CONDITION DISPOSITION 1-A '
- 77 17-TusesweeT 11/76 Yt Yr Cancx PLussEn 2-8 77
.23 Tustsatti 12/76 Yes Yrs 270 Cancx, Reevan 0
HOLE s
, 2 77 27 ISTH PuTE 12/76 YEs No WEAR BDOYED
' APPEARANCE 2-5
~124 42 12TH PuTE 12/76 No No EcoY-CuRRear PLussEn
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INoicArion 3-8 77 11 15TH PLATE 7/76 Yes YEs No Visual M-=
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3-5 77 19 15TH PLATE 2/77 YES YE:
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45 CnAcx STAsitizen.
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15TH PLATE 2/77 Yes No EDDY-CURRENT STAS U ZED
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.i COLLUSIONS ljl 1
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TUBE LEAK PROBLEM APPEARS.TO BE RESTRICTED TO OCONEE.
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.0THER' PLANTS HAVE OPERATED PAST TIME OF 3
OCONEE' FAILURES
.- EDDY-CURRENT SIGNALS APPEAR NOT TO.BE INDICATION I
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tl OF IMPENDING LEAKS.
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LEAKS IN LANE TUBES CAUSED BY PROPOGt' ION OF LOCAL DEFECT BY HIGH-CYCLE FATIGUE FROM VIBRATIL...
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LOCAL DEFECTS TO START CRACKS MAY HAVE DIVERSE CAUSES.
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LEAKS 0CCUR PREDOMINANTLY IN LANE TUBES BECAUSE FLOW IS HIGHER.
GREATER POTENTIAL FOR VI',BRATION.
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EXISTS.
l.ARGE AMPLITUDES COULD RESULT FROM TEMPORARY FLOW INCREASES.-
5.. NO EVIDENCE OF INTERGRANULAR STRESS CORROSION.
6.
NO EVIDENCE OF PROBLEMS ASSOCIATED WITH RECIRCULATING STEAM GENERATORS (WASTAGE-AND DENTING)'.
!NO DIRECT EVIDENCE AVAILABLE ON CAUSE OF OFF-LANEfLEAKS.
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