ML20141G412

Discusses Completion of Licensing Action for GL 95-03, Circumferential Cracking of Steam Generator Tubes, Dtd 950428,to All Holders of Operating Licenses or Const Permits for pressurized-water Reactors

ML20141G412
Person / Time
Site:	Calvert Cliffs
Issue date:	05/15/1997
From:	Dromerick A NRC (Affiliation Not Assigned)
To:	Cruse C BALTIMORE GAS & ELECTRIC CO.
References
GL-95-03, GL-95-3, TAC-M92229, TAC-M92230, NUDOCS 9705220354
Download: ML20141G412 (5)

Text

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. UNITED STATES '

i, j NUCLEAR REGUL.ATORY COMMISSION ,

WASHINGTON, D.C. 30006 0001 )

-May 15, 1997 l e%*****

Mr. Charles H. Cruse.

L Vice President - Nuclear Energy.

Baltimore Gas and Electric Company-

4. Calvsrt Cliffs Nuclear Power Plant f 1650 Calvert Cliffs Parkway

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fLusby,It) . 20657-4702  ;

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SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03,

-"CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR. TUBES," DATED APRIL 28, 2

1995 -FOR CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 (TAC  :

NOS. M92229 AND M92230) j L

Dear Mr. Cruse:

l -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

,

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 all addressees implement the actions described within the

i. generic letter. 1 I

(3) Require that all addressees submit to the NRC a written response regardir.g implementation of the requested actions. i

! 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 federa7 Regulations (10 CFR ,

l 4 Part 50).

In GL 95-03, the NRC staff also requested that licensees take the following I actions:- [pl (1). Evaluate recent operating experience with respect to the detection and sizing of circumferential indications to determine the applicability to j

. their plants.

~(2)f On the basis of the evaluation-in Item (1) above, as well as past L 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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9705220354 970515 PDR ADOCK 05000317 _

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w l :, 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 .

t expansion criteria, if applicable), methods, equipment, and criteria l (including personnel training and qualification).

To docurent the outcome of these actions, the NRC staff requested that addressees prepare and submit the following: l J

(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 .

action 3 (above) and a schedule for the next planned inspection. l In response to GL 95-03, you provided letters dated June 27, 1995, and October 5,- 1995, for Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2. ,

4 These submittals provided the information requested by GL 95-03; therefore TAC Nos. M92229 and M92230 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- l 3473.  ;

1 Sinceraly, l J

Alexan er W. Dromerick, Senior Project Manager  !

Project Directorate I-I ,

Division of Reactor Projects - I/II  ;

Office of Nuclear Reactor Regulation l Docket'Nos. 50-371 and 50-318  !

! cc: See next page  !

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Mr. Charles H. Cruse Calvert Cliffs Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos. I and 2 Cc:

President Mr. Joseph H. Walter, Chief Engineer Calvert County Board of Public Service Commission of Commissioners Maryland 175 Main Street Engineering Division

- Prince Frederick, MD 20678 6 St. Paul Centre Baltimore, MD 21202-6806 James P. Bennett, Esquire Counsel - Kristen A. Burger, Esquire Baltimore Gas and Electric Company Maryland People's Counsel '

P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21203 Suite 2102 Baltimore, MD 21202-1631 Jay E. Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge Patricia T. Birnie, Esquire 2300 N Street, NW Co-Director Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Thomas N. Prichett, Director Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donate 11 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road Chattanooga, TN 37411-4017  ;

Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685 Mr. Richard I. McLean Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue l Tawes State Office Building, B3 i Annapolis, MD 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission i 475 Allendale Road l King of Prussia, PA 19406 l l

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l (3) Develop plans for the next steam generator tube inspections as they i 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 j 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, you provided letters dated June 27, 1995, and October 5,1995, for Calvert Cliffs Nuclear Power Plant, Unit Nes. I and 2.

These submittals provided the information requested by GL 95-03; therefore '

-TAC Nos. M92229 and M92230 are closed. For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."

i If you have any questions regarding this matter, please contact me at 301-415- l 3473. l l

Sincerely, l

/S/  !

Alexander W. Dromerick, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-371 and 50-318 cc: See next page DOCUMENT NAME: G:\CCl-2\M92229.LTR To receive a copy of this document, indicate in the box: "C" = copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" - No copy office P9p(DI,-if) lE LA:PDI-1ML l DPDI 1 .t 7 Q l l l NAME N :mW SLittI # $8sjwe f7 *' 'A DATE 051/ 5 /97 _ .as/i6 /97 05/ls /97 05/ /97 05/ /97 Official Record Copy