ML20031F102
| ML20031F102 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/22/1977 |
| From: | Stuart R Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13319A640 | List:
|
| References | |
| FOIA-81-313 NUDOCS 8110190185 | |
| Download: ML20031F102 (1) | |
Text
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gf UNITED STATES 3 '-
NUCLEAR REGULATORY COMMISSION
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t FEB 2 21277 MEMORANDUM FOR:
D. Eisenhut, Assistant Director for Operational Technology, Division of Operating Reactors THRU:
L. Shao, Chief, Engineering Branch, f 7
Division of Operating Reactors M
FROM:
R. Stuart, Leader, Section B, Engineering Branch, Division of Operating Reactors
SUBJECT:
TRIP REPORT - WESTINGHOUSE, TAMPA DIVISION On February 17, 1977 Dr. B. D. Liaw, Dr. F. Almeter and Dr. R. J. Stuart met with the staff of the Westinghouse, Tampa Division to discuss steam generator strain calculations for dented tubec and cracked support plates and representatives from VEPCO to discuss the recent Surry Unit 2 steam generator tube leaks. Followin;; these discussions there was a short tour of the manufacturing facility. Attached are the meeting agenda, a list of significant participants and a schematic of t'n plant layout.
The following is a su= mary of the outcome of the isst.es discussed.
Westinghouse Analytical Effort - The short term analytical effort (45 days) is summarized in the following steps:
l 1.
Change the shear modulus (or Poisson's ratio) on the current support l
plate expansion model and by trial and error attempt. to correlate the l
results with the known radial growth of the plate periphery. Previcusly this parameter was not accurately predicted.
2.
Recalculate the plate strains using this refined model for unblocked, blocked and closed flow slots.
3.
Conduct bi-axial compression tests of tube cross-sections and determine corresponding strains in the tube. The results will plot maximum tensile strains in the tube vs. the mea. of the major and minor axis deformation for a family of curves with varying biaxiality ratios (ratio of major to minor axis applied deformations).
4.
Utilizing the results of 2 and 3 plot contour lines of tube strain (equivalent, hoop and strain rate) on the support plate layout for blocked, unblocked and closed flow slots.
l l
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C.
Correlate these contours with previous tube leaks and/or published NY-5 5.
Intergranular Stress Corrosion Cracking data for various tube strains.
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6.
Establish the plugging criteria accordingly.
/
The long term analytical effort was also discussed. It was agreed that '
several reffaements to the above scenario could be made in the future, and possibly new ECT methods could be available soon. Westinghouse, Tampa personnel agreed to attempt to provide a short summary of thext long term analytical program within 45-60 days. This summary could serve as an agenda for a future working session to discuss such a f
prograta.
The following is a summary of the data reported regarding Surry Unit 2 -
five steam generator tube leaks (total operating leakage = 1 GPM) recently discovered (locations attached):
1.
Stear Generator Row Column Support Cor nents
~
A 6
40 3 or 4 weeping-outside
.hardspot plugging pattern B
2 14' 4 or 5
~within hardspot plugging
'. same tube plugged in A B
2 81 4 or 5 within hnrdspot plugging B
4 30 4
tube outside periphery of
/
listdspot plugging pattern C
3 10 2
plugged in A weeping Lower support plate hourglassing previously greater in S.G.-A than 2.
B and C.
Top support plate inspection port previously installed in S.G.-A 3.
r after large U-bend leak..
4.
Delay in startup time until February 28, 1977 to perform'the following:
extensive eddy current probing at and around S.G.-A-6'--40; a.
reopen top plate inspection port on S.G.-A and measure plate
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b.
periphery radial deformation; J
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D. Eisenhut.g u.
c.
measure denting in tube B-4-30;
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d.
pull tube B-4-30; and
'e.
attenpt to determine the degree of flow-slot hourglassing in the second and third support plates.
5.
Report ECT and hourglassing results to NRC.
WD 3. %d l
R. J. Stuart, Leader, Section B Engineering Branch Division of Operating Reactors
Enclosures:
As stated cc v/ encl:
V. Stello, OR L Shao, OR W. Hazelton, OR K. Colic.r, OR M. Fairtile, OR F. Almeter, OR B. Liaw, OR J. Weeks J. Strosnider, OR R. Camble, OR R. LaGrange, OR D. Dilanni, OR C. Cheng, OR e
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s ATTENDEES - 2/17/77
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Westinghouse NRC
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Utilities
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D. Marburger R. Stuart R. Sylvia, VEFCO L.'Conway F. Almeter W. Daly, VEPCO P. Smith-B. Liaw B. Acosta, FPL s
M. Shulman D. Ford N. George s
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AGENDA
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WTD/NRC MEETING ON DENTING STRESS ANALYSIS PP.0 GRAMS Date: February 17-18, 1977 Location: Westinghouse. Tampa Division Tampa, Florida l
Thursday, 9:00 a.m. - 4:30 p.m.
1.
INTRODUCTION 2.
NRC ORDERS TO VEPCO (SURRY 1) AND FP&L (TURKEY POINI 4)
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3.
W PLUGGING CRITERIA DEVELOPMENT PROGRAMS 4.
WTD STRESS ANALTSIS PROGRAMS Tube and Support Plate Crush Tests i
Small Radius U-bend Deformation Tests Support Plate Expansion Models Tube Strain Estimates 5.
U-BEND REfIDUAL STRESSES Friday, 9:00 a.m. - 12:00 Noon 1.
WRAP-UP SESSIGH Review of Technical Information Discussed Additional Information Needed by NRC 2.
TOUR OF OFFICE BUILDING AND MANUFACTURING FACILITY ll:
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STEAM GENERATOR INFORMATION DISTRIBUTION ENGINEERING BRANCH DIVISION OF OPERATING REACTORS L. Shao Klecker Section B Section A
. Hazelton R. Stuart F Almeter D. Liaw
. Y. Cheng
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