ML20141H708
| ML20141H708 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/20/1997 |
| From: | Stone J NRC (Affiliation Not Assigned) |
| To: | Maynard O WOLF CREEK NUCLEAR OPERATING CORP. |
| References | |
| GL-95-03, GL-95-3, TAC-M92289, NUDOCS 9705270089 | |
| Download: ML20141H708 (4) | |
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UNITED STATES l,
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NUCLEAR REGULATORY COMMISSION j
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WASHINGTON, D.C. 30eeH001 k
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May 20, 1997 i
Mr. Otto L. Maynard President and Chief Executive Officer l
Wolf Creek Nuclear Operating Corporation Post Office Box 411 i
Burlington, Kansas 66839 i
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SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES," DATED j
APRIL 28, 1995, FOR WOLF CREEK GENERATING STATION (TAC NO. M92289) l
Dear Mr. Maynard:
f-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 operating licenses or construction permits for pressurized-water reactors. The 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.
(3)
Require that all. addressees submit to the NRC a written response regarding implementation of the requested actions.
In addition, 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 Regulatfons (10 CFR l
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.
4 (2)
On the' basis of the evaluation in Item (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.
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230039 9705270089 970520 DR ADOCK 050004 2
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Mr. Otto L. Maynard
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May 20, 1997
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(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).
1 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, Wolf Creek Nuclear Operating Corporation provided letters dated June 23, 1995 and January-9,1996, for the Wolf Creek Generating Station.
These submittals provided the information requested by GL 95-03; therefore TAC No. M92289 is closed.
For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."
1 If you have any questions regarding this matter, please contact me at (301) 415-3063.
Sincerely, Original Signed By James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION:
. Docket File cc:
See next page PUBLIC S. Dembek PDIV-2 Reading K. Karwoski J. Roe J. Strosnider EGA1 ACRS W. Bateman P. Gwynn, RIV J. Stone W. Johnson, RIV E. Peyton DOCUMENT NAME:
GL9503CL.WC 0FC PDIV-2/Pf0(/t,PDIV-2/LA NAME JStone:yef EYeytN DATE l 5/2d97 5/R/97 0FFICIAL RECORD COPY
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- Mr. Otto L.-Maynard
- May 20, 1997
,.,iI (3)~
Develop plans for the next steam generator tube inspections as they.
t pertain to the detection of circumferential cracking.
The inspection 2
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 i
(above).
(2)-
A summary of the inspection plans developed in accordance with requested actiu,3 (above) and a schedule for the next planned inspection.
In response to GL 95-03, Wolf Creek Nuclear Operating Corporation provided
~ letters dated June 23,,1995 and January 9,1996, for the Wolf Creek Generating-Station. 'These submittals provided the information requested by GL 95-03; therefore TAC No. M92289 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) 415-3063.
Sincerely,
$1 d.4&+
ames C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-482 cc: See next page i
+
Mr. Otto L. Maynard May 20, 1997 cc:
Jay Silberg, Esq.
Chief Operating Officer Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation L
2300 N Street, NW P. O. Box 411 Washington, D.C.
20037 Burlington, Kansas 66839 Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Comission Wolf Creek Nuclear Operating Corporation 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 Burlington, Kansas 66839 i
Senior Resident Inspector U.S. Nuclear Regulatory Comission U.S. Nuclear Regulatory Comission Resident inspectors Office l
P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Utilities Division Kansas Corporation Comission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027 4
Office of the Governor State of Kansas Topeka, Kansas 66612 1
Attorney General Judicial Center 301 S.W. 10th 2nd Floor 4
Topeka, Kansas 66612 County Clerk Coffey County Courthouse Burlington, Kansas 66839 Vick L. Cooper, Chief I.
Radiation Control Program Kansas Department of Health and Environment Bureau of Air and Radiation Forbes Field Building 283 Topeka, Kansas 66620
.