ML20141C161

Discusses Completion of Licensing Action for GL 95-03, Circumferential Cracking of SG Tubes, Dtd 950428,for Plant,Unit 1

ML20141C161
Person / Time
Site:	Three Mile Island
Issue date:	05/14/1997
From:	Buckley B NRC (Affiliation Not Assigned)
To:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
References
GL-95-03, GL-95-3, TAC-M92283, NUDOCS 9705160168
Download: ML20141C161 (4)

Text

-_. . - . __ .. _.

t

@ U%y (D - 2 Q}

p 4 UNITED STATES j

g NUCLEAR REGULATORY COMMISSION o t WASHINGTON, D.C. 20066 0001

% p* May 14, 1997 l Mr. James W. Langenbach, Vice President and Director, TMI-1 GPU Nuclear Corporation ,

P.O. Box 480 Middletown, PA 17057 l

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTEF % 03, l

"CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES, DATED APRIL 28, 1995, FOR THREE MILE ISLAND, UNIT 1 (TAC NO. M92283)

Dear Mr. Langenbach:

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:

i (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.

l Require that all addressees submit to the NRC a written response (3)  !

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 l 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 Item (1) above, as well as past inspection scope and results, susceptibility to circumferential l

l' cracking, threshold of detection, expected or inferred crack growth \

9 f1 rates, and other relevant factors, develop a safety assessment justifying' continued operation until the next scheduled steam generator '

tube inspections.

tV

' \

1. *n 9705160168 970514

• NRC HLE CENTER COPY PDR ADOCK 05000289 P PDR

.- _ ._ . _ . - ~ . . ____.._ _ _ _ _ _ _ _ _. _ _

i

! ~

4 Mr. J. Langenbach May 14, 1997 (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).

i 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, you provided letters dated June 20, September 26, October 30, and November 21, 1995, and August 1, 1996, for Three Mile Island, Unit 1. These submittals provided the information requested by GL 95-03; therefore TAC No. M92283 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 Bart Buckley at 301-415-1483. 1 C.  %

Bart C. Buckley, Sr. Project anager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Regulations Docket No. 50-289 cc: See next page DISTRIBUTION i Docket File PUBLIC PDI-3 Rdg.

SVarga 0GC ACRS PEselgroth, RI KKarwoski SDembek )

DOCUMENT NAME: G:\G:\BUCKLEY\M40718.MPA Ta ,sielve a copy of this document,indcate in the box: "C" = Copy without attachment / enclosure "E* = Copy with attachment / enclosure *N* = No copy 0FFICE PDI 3/PM M/*d lC P0lla1/LA lC (A)D\PDI 33 a 3 l l NAME BBuckley EDunnington MD PMIlano yu' DATE 05//f/97 05//V/97 05/ M /97 OFFICIAL RECORD COPY

l Mr. J. Langenbach (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: l l

L (1) A safety assessment justifying continued operation, predicated on the i evaluation performed in accordance with requested actions 1 and 2  !

!- (above).

l (2) A summary of the inspection plans developed in accordance with requested i action 3 (above) and a schedule for the.next planned inspection.

l In response to GL 95-03, you provided letters dated June 20, September 26, October 30, and November 21, 1995, and August 1,1996, for Three Mile Island, '

Unit 1. These submittals provided the information requested by GL 95-03;

! therefore TAC No. M92283 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' Bart Buckley at 301-415-1483.

Sincerely, h (a LM %

Bart C. Buckley, Sr. Project Manager Project Directorate I-3 ,

! Division of Reactor Projects - I/II Office of Nuclear Regulations j Docket No. 50-289 ,

l cc: See next page.

l' i

1 l

Three Mile Island Nuclear Station, Unit No. 1 i .

, cc:  !

.' Michael Ross Robert B. Borsum Director, O&M, TMI B&W Nuclear Technologies  ;

GPU Nuclear Corporation Suite 525 '

P.O. Box 480 1700 Rockville Pike  !

j Middletown, PA 17057 Rockville, MD 20852 l l

John C. Fornicola William Dornsife, Acting Director i

, Director, Planning and Bureau of Radiation Protection J j Regulatory Affairs Pennsylvania Department of

GPU Nuclear Corporation Environmental Resources '

100 Interpace Parkway P.O. Box 2063 '

i Parsippany, NJ 07054 Harrisburg, PA 17120  :

Jack S. Wetmore Dr. Judith Johnsrud

Manager, TMI Regulatory Affairs National Energy Committee i i GPU Nuclear Corporation Sierra Club l P.O. Box 480 433 Orlando Avenue

! Middletown, PA 17057 State College, PA 16803 i .

j Ernest L. Blake, Jr., Esquire l i Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.

j Washington, DC 20037

. Chairman l Board of County Commissioners j of Dauphin County i Dauphin County Courthouse  ;

i Harrisburg, PA 17120 )

l

Chairman

{ Board of Supervisors 3

of Lo.ndonderry Township

R.D. #1, Geyers Church Road j Middletown, PA 17057 i Michele G. Evans '

- Senior Resident Inspector (TMI-1)

{ U.S. Nuclear Regulatory Commission i P.O. Box 311 i- Middletown, PA 17057 l Regional Administrator, Region I

U.S. Nuclear Regulatory Commission j 475 Allendale Road

{ King of Prussia, PA 19406 i

l 1

1 1