ML20141G563

Informs of Completion of Licensing Action for GL 95-03, Circumferential Cracking of SG Tubes, for Plant,Units 1 & 2

ML20141G563
Person / Time
Site:	Beaver Valley
Issue date:	05/16/1997
From:	Brinkman D NRC (Affiliation Not Assigned)
To:	Cross J DUQUESNE LIGHT CO.
References
GL-95-03, GL-95-3, TAC-M92222, TAC-M92223, NUDOCS 9705220416
Download: ML20141G563 (4)

Text

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g rs%-j UNITED STATE 8 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30e86-coM May 16,1997 Mr.-J. E. Cross '

President-Generation Group l' Duquesne Light Company Post Office Box 4 i Shippingport, PA 15077 .

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03.

"CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES." DATED APRIL 28, 1995, FOR BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 l (TAC NOS. M92222 AND M92223)  !

Dear Mr. Cross:

On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic l Letter (GL) 95-03. "Circumferential Cracking of Steam Generator Tubes " to all  !

holders of o>erating licenses or construction permits for pressurized-water i reactors. T1e NRC issued GL 95-03 for three principal reasons: l (1) Notify addressees about the safety significance of the recent steam generator tube inspection findings at Maine Yankee Atomic Power Station.

(2) Request that i.41 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 l Appendix B to Title 10. Part 50, of the Code of Federal Regulations (10 CFR

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Part 50).

In GL 95-03, the NRC staff also requested that licensees take the following actions: if U

(1) Evaluate recent operating experience with respect to the detection and sizing of circumferential indications to determine the applicability to y their plants. I (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

• just:'ving continued operation until the next scheduled steam generator y tube mspections.

,, .m m NRC RE CENTECOPY 9705220416 970516 "'

PDR ADOCK 05000334 P PDR  ;,

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J. Cross .

(3) Develop plans for the next steam generator tube inspections as they pertain to the detection of circumferential cracking. The inspection plans shoula 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). l (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. Duquesne Light Company provided letters dated  !

June 23. 1995, and Januar.y 10, 1996, for Beaver Valley Power Station, Unit  ;

Nos. 1 and 2. These submittals provided the information requested by GL 95- l 03: therefore, TAC Nos. M92222 and M92223 are closed. For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Gene'rator Tubes."

If you have any questions regarding this matter, please contact me at (301)-415-1409.

Sincerely, Donald S. Brinkman, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation '

Docket Nos. 50-334 and 50-412 l cc: See next page i

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F J. Cross May 16, 1997 i (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, Duquesne Light Company provided letters dated June 23. 1995. and January 10. 1996. for Beaver Valley Power Station, Unit Nos. 1 and 2. These submittals provided the information requested by GL 95-03: therefore. TAC Nos. M92222 and M92223 are 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)-415-1409.

Sincerely.

(Original Signed By)

Donald S. Brinkman, Senior Project Manager Project Directorate I-2 Division of Reactor Projeci.s - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 cc: See next page DISTRIBUTION:

Docket File PUBLIC PDI-2 r/f SVarga JStolz M0'Brien DBrinkman OGC. 0-15B18 ACRS. TWF PEselgroth, RI KKarwoski, 0-7D4 SDembek 0FFICE PDI-2/PMhd PpidM_ MDI-2/D NAME DBrinkman:cw hiIken 3Shh DATE f//4 /97 6// h97 $/k/97 0FFICIAL RECORD COPY DOCUMENT NAME: BV92222.CL0

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9 J. E. Cross Beaver Valley Power Station Duquesne Light Company Units 1 & 2 cc:

Jay E. Silberg. Esquire Bureau of Radiation Protection  :

Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of 2300 N Street. NW. Environmental Resources Washington. DC 20037 ATTN: Michael P. Murphy Post Office Box 2063 Director-Safety and Licensing Harrisburg. PA 17120 Department (BV-A)

Duquesne Light Company Mayor of the Borrough of Beaver Valley Power Station Shippingport PO Box 4 Post Office Box 3 Shippingport. PA 15077 Shippingport, PA 15077 Commissioner Roy M. Smith Regional Administrator, Region I West Virginia Department of Labor U.S. Nuclear Regulatory Commission j Building 3. Room 319 475 Allendale Road j Capitol Complex King of Prussia, PA 19406  !

Charleston. WVA 25305 l Resident Inspector l Director. Utilities Department U.S. Nuclear Regulatory Commission l Public Utilities Commission -

Post Office Box 298 180 East Broad Street Shippingport. PA 15077 Columbus OH 43266-0573 Director, Pennsylvania Emergency Duquesne Light Company Management Agency Beaver Valley Power Station Post Office Box 3321 PO Box 4 Harrisburg, PA 17105-3321 Shippingport, PA 15077 i ATTN: S. C. Jain Vice President  ;

Ohio EPA-DERR Nuclear Services (BV-A) l ATTN: Zack A. Clayton i Post Office Box 1049  !

Columbus, OH 43266-0149 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue i State College, PA 16803 Duquesne Light Company Beaver Valley Power Station PO Box 4 Shi3pingport. PA 15077 ATTi: R. L. Grand. Division Vice  !

President. Nuclear Operations Group l and Plant Manager (BV-SOSB-7)