ML19260D050
| ML19260D050 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/01/1980 |
| From: | Groce R Maine Yankee |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| WMY-80-18, NUDOCS 8002070299 | |
| Download: ML19260D050 (2) | |
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MAIRE O HARHEE 7
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TURNPIKE ROAD (RT. 9)
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$.71
/j ENGINEERING OF FICE WESTBORO, MASSACHUSETTS 01581
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617-366-9011
%~% w p 9 WMY 80 18 B.3.2.1 February 1, 1980 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention: Office of Nuclear Reactor Regulation Mr. Robert W. Reid, Chief
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) USNRC Letter to MYAPC dated August 18,1978 (Amendment No.
40)
(c) USNRC Letter to MYAPC dated September 24, '979
Dear Sir:
Subject:
EOC-4 Fuel and CEA Inspection Program In Reference (b), you requested information regarding Maine Yankee's planned inspection program for both fuel and control element assemblies to be conducted during the next refueling outage which is presently scheduled to begin in January 1980. The following is in response to this request:
A.
A minimum of four assemblies that were sleeved in the irradiated condr'on and are scheduled for re-insertion in Cycle 5 in a CEA or instrument location, will be inspected to, evaluate them for the adequacy of the crimp and for CEA wear.
In the event that the crimp does not meet our acceptance criteria, the sleeves shall be recrimped. The acceptance criteria for the crimp is basically that-the sleeve shall have sufficient crimp to assure that the sleeve will remain in its proper position throughout the life of the fuel assembly.
Combustion Engineering has developed a value for the minimum crimp required to meet this criteria. The specific value is proprietary to Combustion Engineering. The crimp will be evaluated by either a mechanical guage or by eddy current inspection. The eddy current inspection, if used, will generate data which will be compared with standards prepared to assure that the minimum required crimp has been met.
B.
A representative afample of up to six CEAs will be inspected to establish tisat no significant wear has occurred.
Significant wear is that value which has been judged sufficient to compromise the integrity of the CEA during the next operating cycle of the reactor. The specific value has been developed by and is considered proprietary to Combustion Engineering.
1938 103 so o e o7 0 AM f
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Office of Nuclear Reactor Regulation December 11, 1979 Attention:
Mr. Fobert W. Reed, Chief Page 2 C.
Assemblies will be examined to evaluate the effectiveness of design changes made to eliminate CEA guide tube wear.
D.
Selected fuel assemblies will be sipped and/or visually inspected to characterize general performance.
E.
Acceptance criteria will be similar to criteria used at other similar power plants.
We trust this information is acceptable to you, however, should you have any questions please feel free to contact us.
Very truly yours, Robert H. Groce
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"* "E RHG/nj 1938 104
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