ML20141K347
| ML20141K347 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 05/28/1997 |
| From: | Dan Dorman NRC (Affiliation Not Assigned) |
| To: | Sellman M Maine Yankee |
| References | |
| GL-95-03, GL-95-3, TAC-M92250, NUDOCS 9705290022 | |
| Download: ML20141K347 (3) | |
Text
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i UNITED STATES e
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,j NUCLEAR REGULATORY COMMISSION
~t WASHINGTON. D.C. 20 tie 64001 k*****,/
May 28, 1997 l
W90R i
Mr. Michael B. Sellman President Maine Yankee Atomic Power Company l
329 Bath Road 2
Brunswick. Maine 04011
SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES."
DATED APRIL 28, 1995. FOR MAINE YANKEE ATOMIC POWER STATION l
Dear Mr. Sellman:
On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-03. "Circumferential Cracking of Steam Generator Tubes." to all holders of o)erating licenses or construction permits for pressurized-water reactors.
T1e NRC issued GL 95-03 for three principal reasons:
(1)
Notify addressees about the safety significance of the recent steam generator tube inspection findings at Maine Yankee Atomic Power Station.
(2)
Request that all addressees implement the actions described within the generic letter.
(J)
Require that all addressees submit to the NRC a written response
~
i regarding implementation of the requested actions.
In hddition. GL 95-03 alerted addressees to the importance of performing comprehensive examinations of steam generator tubes using techniques and equipment capable of reliably detecting the types of degradation to which the steam generator tubes may be susceptible. The staff also noted that the performance of steam generator tube examinations is controlled, in part, by Appendix B to Title 10. Part 50, of the Code of Federal Regulations (10 CFR Part 50).
In GL 95-03, the NRC staff also requested that licensees take the following actions:
(1)
Evaluate recent operating experience with respect to the detection and sizing of circumferential indications to determine the applicability to their plants.
(2)
On the basis of the evaluation in requested action (1) above, as well as past inspection scope and results, susceptibility to circumferential cracking, threshold of detection, expected or inferred crack growth rates, and other relevant factors, develop a safety assessment justifying continued operation until the next scheduled steam generator tube inspections.
9705290022 970528 PDR ADOcK 05000309 P
1 Mr. Michael B.'Sellman (3)
Develop plans for the next steam generator tube inspections as they pertain to the detection of circumferential cracking.
The inspection plans should address, but not be limited to. scope (including sample expansion criteria. -if applicable), methods, equipment, and criteria (including personnel training and qualification).
To document the outcome of these actions, the NRC staff requested that addressees prepare and submit the following:
(1)-
A safety assessment justifying continued operation, predicated on the evaluation performed in accordance with requested actions 1 and 2 (above).
(2)
A summary of the inspection plans developed in accordance with requested action 3 (above) and a schedule for the next planned inspection.
In response to GL 95-03. Maine Yankee Atomic Power Company provided letters dated June 27. 1995, and December 3, 1996, for Maine Yankee.
These submittals provided the information requested by GL 95-03: therefore TAC No. H92250 is closed.
For your information, the staff's findings regarding this issue are contained in NUREG-1604. "Circumferential Cracking of Steam Generator Tubes."
If you-have any questions regarding.this matter, please contact me at (301) 415-1429.
Sincerely.
Original signed by Daniel H. Dorman. Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-309 cc:
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- DATE 05/ 2 T/97 05/lr//97 '
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's Mr. Michael B. Sellman ;
d' cc:
Mr. Charles B. Brinkman Mr. Robert W. Blackmore 4
Manager - Washington Nuclear Plant Manager Operations Maine Yankee Atomic Power Station i
ABB Combustion Engineering P.O. Box 408 12300 Twinbrook Parkway, Suite 330 Wiscasset, ME 04578 l
Rockville, MD 20852 Mr. Michael J. Meisner Thomas G. Dignan, Jr., Esquire Vice-President I
Ropes & Gray Licensing and Regulatory Compliance One International Place Maine Yankee Atomic Power Company Boston, MA 02110-2624 329 Bath Road Brunswick, ME 04011 Mr. Uldis Vanags State Nuclear Safety Advisor Mr. Bruce E. Hinkley, Acting i
State Planning Office Vice-President, Engineering State House Station #38 Maine Yankee Atomic Power Company Augusta, ME 04333 329 Bath Road Brunswick, ME 04011 Mr. P. L. Anderson, Project Manager Yankee Atomic Electric Company Mr. Patrick J. Dostie 580 Main Street State of Maine Nuclear Safety Bolton, MA 01740-1398 Inspector Maine Yankee Atomic Power Station Regional Administrator, Region I P.O. Box 408 U.S. Nuclear Regulatory Commission Wiscasset, ME 04578 475 Allendale Road King of Prussia, PA 19406 Mr. Graham M. Leitch Vice President, Operations First Selectman of Wiscasset Maine Yankee Atomic Power Station Municipal Building P.O. Box 408 U.S. Route 1 Wiscasset, ME 04578 Wiscasset, ME 04578 Mary Ann Lynch, Esquire 4
Mr. J. T. Yerokun Maine Yankee Atomic Power Company Senior Resident Inspector 329 Bath Road Maine Yankee Atomic Power Station Brunswick, ME 04578 U.S. Nuclear Regulatory Commission P.O. Box E Mr. Jonathan M. Block Wiscasset, ME 04578 Attorney at Law 4
P.O. Box 566 Mr. James R. Hebert, Manager Putney, VT 05346-0566 Nuclear Engineering and Licensing Maine Yankee Atomic Power Company 329 Bath Road 2
Brunswick, ME 04011 j
Friends of the Coast I.
P.O. Box 98 Edgecomb, ME 04556 i
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