ML17261A854
| ML17261A854 | |
| Person / Time | |
|---|---|
| Site: | Point Beach, Ginna, 05000000 |
| Issue date: | 01/13/1989 |
| From: | Gieske J SANDIA NATIONAL LABORATORIES |
| To: | Hum M Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17261A853 | List: |
| References | |
| NUDOCS 8902280553 | |
| Download: ML17261A854 (6) | |
Text
ENCLO-ORE Sandia National Laboratories Albuquerque. New Mexicv 87185 January 13, 1989 Mr. M. R.
Hum U. S. Nuclear Regulatory Commission Materials Engineering Branch Washington, DC 20555
Subject:
Nozzle Sizing Study Meeting January 10-11, 1989
Dear Mr. Hum:
The Nozzle Sizing Study performed by Southwest Research Institute, Rochester Gas 6 Electric, Wisconsin Electric Power, and Electric Pover Research Institute shows that any flaw sizing done by amplitude measurements vill alvays be an approximation to the true size of the flaw.
In most cases it will oversize the flaw due to beam spread.
Using focused transducers reduces the beam spread contribution but does not eliminate it entirely.
Using beam spread corrections reduces the measured size of the flaw, and it is only justified when the amplitude and metal path data of the reflected signal versus transducer travel are consis-tent vith that of a single flaw of a given size at the location of the flav in the vessel wall thickness.
A presentation of this data must be required along with the beam spread correction data.
In my opinion sizing by 50% or 20%
DAC with beam spread correc-tion will only yield a conservative size of the true flaw size for very few flaw sizes, and for small flavs sizes it will underestimate the flaw size in most cases.
The db drop method (independent of DAC calibration amplitudes) using focused transducers for flaw sizing is the most preferable since it can be used so that the most accurate yet conservative flaw size is obtained for large and small flaws in most cases.
From the data presented at the meeting, the most accurate sizing is accomplished by collecting data of edge diffracted waves from the geometric extremities of the flav.
Flav size as computed f
th time of.flight measurements of the edge diffracted waves rom e
is independent of amplitude and yields a sample geometric
~
~
con-struct of the flaw extremities as measured from known positions and angles of the transducer.
The method is only applicable when automated UT data acquisition systems are being used; i.e.,
where the waveforms of the flaw echo and transducer positions are digitized at small incremental steps of the transducer over the entire area of the flaw.
These data will be available at the 8902280553 8902$.4 PDR ADQCK 05000244 O
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Ginna and Point Beach Reactor Vessel examinations since the SWRI Enhanced Data Acquisition System (EDAS) will be used.
- However, the edge diffracted signals are not always able to be detected so that it is not applicable to all flaws detected.
Every attempt should be made in the examinations at Ginna and Point Beach to obtain the edge diffracted signals.
I am pleased to see that the utilities are taking the initiative to develop techniques above minimum ASME Code requirements which allow a comprehensive flaw sizing calculation to be made using all of the ultrasonic information available through state-of-the-art techniques.
Sincerely, ohn H. Gieske JHG: jk Copy to:
NRC Harold Polk 6442 D. S. Horschel 7552 W.
W. Shurtleff
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FEB o8
>98g Distribution:
Q Docket 50-244 PD I-3 Reading M. Rushbrook C. Stahle DOCKET NO(S).
50-244 Dr. Robert C. Hecredy, General
- hfanager, Nuclear Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649
SUBJECT:
R. E. Ginna Nuclear Power Plant The following documents concerning our review of the subject facility are transmitted for your information.
Noti ce of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No.
dated Environmental Assessment and Finding of No. Si gnificant Impact, dated Notice of Consideration of Issuance of Facility Operating License or Amendment to
= Facility Operating License, dated
~ Bi-Weekly Notice; Applications and Amendments to Operating Licenses Involving No if' d
id i
d d2~ISB I
(3]
5175 Exemption, dated Construction Permit No.
CPPR-
, Amendment No.
dated Facility Operating License No.,
Amendment No.
dated Order Extending Construction Completion Date, dated f<onthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by letter dated En cl osures:
As stated Office of Nuclear Reactor Regulation with enclosure See Attached Sheet OFFICE/
SURNAME/
OAVED N
/RP...I( LI HRu 2/ /
PD.L 3""".I".
HRC FORM 318 1IO/80 NRCM 0240 OFFICIAL RECORD COPY
Dr. Robert C. Mecredy Rochester Gas and Electric Corporation R.
E. Ginna Nuclear Power Plant CC:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby-and MacRae 1333 New Hampshire
- Avenue, N.W.
Suite 1100 Washington, D.C.
20036 4 Ezra Bialik As s is tant Attorney Gener a 1 Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Mr. Bruce A. Snow, Superientendent Nuclear Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, N.Y. 14649-0001 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Resident Inspector R.E.
Ginna Plant c/o U.S.
NRC 1503 Lake Road
- Ontario, New York 14519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road
- Ontario, New York 14519 Ms.
Donna Ross Division of Policy Analysis 8 Planning New York State Energy Office Agency Building 2, Empire State Plaza
- Albany, New York 12223