ML20141E858
| ML20141E858 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/15/1997 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | Jeffery Wood CENTERIOR ENERGY, TOLEDO EDISON CO. |
| References | |
| GL-95-03, GL-95-3, TAC-M92238, NUDOCS 9705210134 | |
| Download: ML20141E858 (4) | |
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NUCLEAR REGULATORY COMMISSION
' WASHINGTON, D.C. 30006 0001 y*****f May 15, 1997
' Mr. John K. ' Wood Vice President - Nuclear, Davis-Besse i
'Centerior Service Company
.c/o Toledo Edison Company
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Davis-Besse Nuclear Power Station 5501' North State Route 2
' Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 - COMPLETION OF LICENSING ACTION FOR GENERIC LETTER.95-03, "CIRCUMFERENTIAL CRACKING 0F STEAM GENERATOR TUBES," DATED APRIL 28, 1995 (TAC NO. M92238)
Dear Mr. Wood:
[
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 principa,1 reasons:
'(1) Notify addressees about the safety significance of the recent steam generator tube inspection findings at Maine Yankee Atomic Power Station; i
'(2)
Request that all addressees. implement the actions' described within the i
generic letter; and (3)
Require that all addressees submit to the NRC'a written response regarding implementation of the requested actions.
1
.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 tnat the performance of steam generator tube exa:r.inations 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 re<.ent operating experience with respect to the detection and
' ' sizing of circumferential indications to determine the applicability to ff their plants; jlf
-(2) On the basis of the evaluation in Item (1) above, as well as past j) l inspection scope and results, susceptibility to circumferential cracking, i V
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; and 9705210134L970515
'PDR ADOCK 05000346 i
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J. Wood (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 aCressees 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; and (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, you provided letters dated June 23, 1995, February 1, 1996, and June 3, 1996, for Davis-Besse.
These submittals provided the information requested by GL 95-03. Therefore, TAC No. M92238 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) 415-1390.
Sincerely, Original signed by:
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-346 cc:
See next page D11TRIBUTION:
Docket File JRoe OGC PD3-3 R/F EAdensam (EGAl)
ACRS PUBLIC GMarcus GGrant, RIII l
KKarwoski, EMCB SDembek, SP0-L l
i DOCUMENT NAME:
G:\\DAVISBES\\DB92238.LTR Ta receive a copy of this document. Indicate in the box: 'C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy 1
0FFICE LA:PD3-3
/C PM:PD3-3
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NAME CBoyl.e UW AHansen # O DATE 05/l5/97 0
05//r97" 0FFICIAL RECORD COPY
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,3 J. Wood.
(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:
5 (1) A safety assessment justifying continued operation, predicated on the evaluation performed in accordance with requested Actions 1 and 2 above; and (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, you provided letters dated June 23, 1995, February 1, 1996, and June 3, 1996, for Davis-Besse. These submittals provided the information requested by GL 95-03.
Therefore, TAC No. M92238 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) 415-1390.
Sincerely, Original signed by:
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-346
)
cc:
See next page 4
DISTRIBUTION:
Docket File JRoe OGC PD3-3 R/F EAdensam (EGA1)
ACRS PUBLIC GMarcus GGrant, RIII KKarwoski, EMCB SDembek, SPO-L
~
DOCUMENT NAME: G:\\DAVISBES\\DB92238.LTR Ta receive a copy of this document, Bruscate in the box: "C" = Copy without enclosures *E* = Copy with enclosures "N" = No copy 0FFICE LA:PD3-3
/C PM:PD3-3
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NAME CBoyl_e CW AHansen # J DATE 05/15/97 0
05//f97' OFFICIAL RECORD COPY
O John K. Wood Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. I cc:
Mary E. O'Reilly Robert E. Owen, Chief Centerior Energy Corporation Bureau of Radiological Health 300 Madison Avenue Service
. Toledo, Ohio 43652 Ohio Department of Health P. O. Box 118 James L. Freels Columbus, Ohio 43266-0118 Manager - Regulatory Affairs Toledo Edison Company James R. Williams Davis-Besse Nuclear Power Station Chief of Staff 5501 North State - Route 2 Ohio Emergency Management Agency Oak Harbor, Ohio 43449-9760 2855 West Dublin Granville Road Columbus, Ohio 43235-2206 Gerald Charnoff, Esq.
Shaw, Pittman, Potts Roy P. Lessy, Jr., Esq.
and Trowbridge Andrew G. Berg, Esq.
2300 N Street, N.W.
Akin, Gump, Strauss, Hauer Washington, D.C.
20037
& Feld, L.L.P.
1333 New Hampshire Ave., NW, Ste. 400 Regional Administrator Washington, D.C.
20036 U.S. NRC, Region III 801 Warrenville Road Ohio Environmental Protection Agency Lisle, Illinois 60523-4351 DERR--Compliance Unit ATTN:
Zack A. Clayton 1
Robert B. Borsum P. O. Box 1049 Babcock & Wilcox Columbus, Ohio 43266-0149 Nuclear Power Generation Division 4
1700 Rockville Pike, Suite 525 State of Ohio i
Rockville, Maryland 20852 Public Utilities Commission 180 East Broad Street Resident Inspector Columbus, Ohio 43266-0573 U. S. Nuclear Regul' tory Commission 5503 North State Route 2 Attorney General Oak Harbor, Ohio 43449 Department of Attorney 30 East Broad Street James H. Lash, Plant Manager Columbus, Ohio 43216 Toledo Edison Company Davis-Besse Nuclear Power Station President, Board of County 5501 North State Route 2 Commissioner of Ottawa County 4
Oak Harbor, Ohio 43449-9760 Port Clinton, Ohio 43252 Donna Owens, Director Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations and Maintenance 6606 Tussing Road P.O. Box 4009 Reynoldsburg, Ohio 43068-9009 l
.