ML20129C981
| ML20129C981 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 10/21/1996 |
| From: | Dan Dorman NRC (Affiliation Not Assigned) |
| To: | Frizzle C Maine Yankee |
| References | |
| GL-95-03, GL-95-3, TAC-M92250, NUDOCS 9610240172 | |
| Download: ML20129C981 (3) | |
Text
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October 21, 1996 Mr. Charles D. Frizzle, President Maine Yankee Atomic Power Company 329 Bath Road Brunswick, ME 04011
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TC GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING 0F STEAM GENERAiOR TUBES" -
MAINE YANKEE ATOMIC POWER STATION (TAC N0. M92250)
Dear Mr. Frizzle:
On April 28, 1995, the NRC staff issued the subject Generic Letter (GL) requesting licensees to develop plans for the next steam generator tube inspections pertaining to the detection of circumferential cracking. Maine Yankee Atomic P:)wer Company (MYAPC) responded to GL 95-03 by letter dated June 1
27, 1995 (MN-95-73).
The staff has reviewed the information provided by MYAPC and determined that additional information is required to assess the adequacy of the licensee's inspection plans.
Accordingly, the staff requests that you provide the information specified in the enclosed request for additional information within 30 days of receipt of this letter.
If you have any questions regarding this matter, please call me at (301) 415-1429.
Sincerely, (Original Signed By)
Daniel H. Dorman, Project Manager Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-309
Enclosure:
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Maine Yankee Atomic Power Station Maine Yankee Atomic Power Company cc:
Mr. Christopher R. Shaw Mr. Charles B. Brinkman Plant Manager Manager - Washington Nuclear Maine Yankee Atomic Power Station Operations P.O. Box 408 AB8 Combustion Engineering Wiscasset, ME 04578 12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 Mr. G. D. Whittier, Vice President Licensing and Engineering Thomas G. Dignan, Jr., Esquire Maine Yankee Atomic Power Company Ropes & Gray 329 Bath Road One International Place Brunswick, ME 04011 Boston, MA 02110-2624 Mr. Patrick J. Dostie Mr. Uldis Vanags State of Maine Nuclear Safety State Nuclear Safety Advisor Inspector State Planning Office Maine Yankee Atomic Power Station State House Station #38 P.O. Box 408 Augusta, ME 04333 Wiscasset, ME 04578 Mr. P. L. Anderson, Project Manager Mr. Graham M. Leitch Yankee Atomic Electric Company Vice President, Operations 580 Main Street Maine Yankee Atomic Power Station Bolton, MA 01740-1398 P.O. Box 408 Wiscasset, ME 04578 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mary Ann Lynch, Esquire 475 Allendale Road Maine Yankee Atomic Power Company King of Prussia, PA 19406 329 Bath Road Brunswick, ME 04578 First Selectman of Wiscasset Municipal Building Mr. Jonathan M. Block U.S. Route 1 Attorney at Law Wiscasset, ME 04578 P.O. Box 566 Putney, VT 05346-0566 Mr. J. T. Yerokun Senior Resident Inspector Maine Yankee Atomic Power Station U.S. Nuclear Regulatory Commission P.O. Box E Wiscasset, ME 04578 Mr. James R. Hebert, Manager Nuclear Engineering and Licensing Maine Yankee Atomic Power Company 329 Bath Road Brunswick, NE 04011 Friends of the Coast P.O. Box 98 Edgecomb, ME 04556
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MAINE. YANKEE ATOMIC POWER COMPANY e
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MAINE YANKEE ATOMIC POWER STATION l
DOCKET NO. 50-309 REQUEST FOR ADDIT 0NAL INFORMATION GENERIC LETTER 95-03. "CIRCUMFERENTIAL t
l CRACKING OF STEAM GE81EAATOR TUBES" 1.
The following areas have exhibited circumferential cracking:
i a.
Expansion transition circumferential cracking 2
b.
U-bend circumferential cracking Dented location (including dented TSP) circumferential cracking c
j d.
Sleeve joint circcaferential cracking In your response to Generic Letter (GL) 95-03, the susceptib'.ity of the i
U-bends and dented locations in your steam generators to circumferential i
cracking was not addressed.
If these areas are susceptible to circumferential cracking, please submit the information requested in GL i
95-03 per the guidance contained in the GL for these areas and any other j
area susceptible to circumferential cracking. The above response should clarify the inspections performed at these locations during the prior j
tube inspection outage and should clarify the inspections to be perfonned during the next scheduled steam generator tube inspection.
i For dented locations, if applicable, the criteria for determining which dents are/were examined should be provided.
If a dent voltage threshold i
is used for such a determination, the calibration procedure used (i.e.,
4.0 volts on 4-20 percent through-wall ASME holes at 550/130 mix) should j
be provided.
l 2.
In your GL 95-03 response, it was indicated that a 20 percent sample of the sleeves installed during the present outage (i.e.,1995 outage) l would be examined in the next outage and that 20 percent of the cold leg i
expansion transition region just above the top of the tubesheet would be examined with techniques suitable to detect circumferential cracking i
(e.g., plus point and Cecco 5).
In addition, it was indicated that a j
submittal would be made which addresses the expansion criteria.
Please i
specify the expansion criteria to be used during the next scheduled steam generator tube inspection for these regions (i.e., cold leg j
expansion transitions and all installed sleeves).
3.
Discuss whether terrain plots will be used to analyze the RPC eddy j
current data at locations susceptible to circumferential cracking during i
your next steam generator tube inspection (i.e., the next inspection per your Generic Letter 95-03 response).
i 1
k 5
d Enclosure
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