ML20134J841

Notifies NRC of Completion of mid-cycle SG Eddy Current Insp Prior to 961015 as Committed to in 960524 Ltr Re SG Tube & in Situ Testing

ML20134J841
Person / Time
Site:	Braidwood
Issue date:	01/31/1997
From:	Stanley H COMMONWEALTH EDISON CO.
To:	NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9702120359
Download: ML20134J841 (2)

Text

-o i G,mmonwealth I.diwn unnpany liraidwood Generating Station Houte al, llos H s liraceville, II. 60 #059619

.TclHl41 W 2801 January 31,1997 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn.: Document Control Desk

Subject:

Braidwood Station Unit 1 NRC Docket Number: 50-456 Steam Generator Tube Removal and Insitu Testing

References:

1. Comed letter to Office of Nuclear Reactor Regulatory, Braidwood Station Unit 1, NRC Docket Number: 50-456, Operating Interval l Between Eddy Curtent Inspections for Circumferential Indications in the Braidwood Unit 1 Steam Generators, dated May 24,1996 i

2. D. Lynch letter to D. Farrar transmitting Extension of*the Operatmg Interval Between Eddy Current Inspections for Circumferential Indications in the Braidwood Unit 1 Steam Generator Tubes, dated May 22,1996 In Reference 1, Comed committed to perfonn a mid-cycle Steam Generator eddy current inspection at Braidwood Unit 1 prior to October 15, 1996. The staff approved plant operation up to October 15,1996 subject to the acceptance of four conditions. These conditions were to:

1. Plug or sleeve all steam generator tubes with circumferential indications found in the Braidwood Unit 1 Fall 1996 outage; j

2. Use an eddy current inspection methodology during the Braidwood Unit 1 Fall 1996 "9 ,

outage which is equivalent to, or better than that used in the Byron Unit 1 Spring 1996 l refueling outage; J

3. Remove and destructively analyze tubes with circumferential indications in the roll '

/ M 'g i

transition zone during the Braidwood Unit 1 Spring 1997 refueling outage; and

4. Conduct in-situ pressure tests of selected steam generator tubes in the Braidwood Unit 1 Fall 1996 outage.

9702120359 970131 PDR ADOCK 05000456 G PDR c:Vonfid site $corres' 1997'970064x A l'mcom G>mpany

_. . _ =

Document Control Desk Page 2 01/31/97 Comed performed a mid-cycle eddy current inspection of the Braidwood Unit I steam generator's hot-leg top-of-tubesheet roll transition regions during an outage that started -

October 12, 1996. All circumferential indications found were plugged or sleeved. The -

eddy current inspection methodology used was equivalent to or better than that used in the Byron Unit 1 Spring 1996 refueling outage. In-situ pressure tests were performed on twenty-three steam generator tubes to verify adequate structural integrity of the more severe circumferential indications detected. This satisfies conditions 1,2, and 4.

During the Fall 1996 mid-cycle outage, four tubes with circumferential indications in the roll transition region were removed from the Braidwood Unit I steam generators for destructive analysis to determine the morphology of the circumferential indications.

Therefore, condition 3 was satisfied during the Fall 1996 mid-cycle outage. Comed does not intend to remove additional tubes with circumferential indications in the roll transition region during the Braidwood Unit 1 Spring 1997 refueling outage Please direct any questions regarding these commitments to Douglas S. Huston, Braidwood Licensing Supervisor, (815) 458-2801, extension 2511.

l l

l Sincerely,

, ' ,r// , .,l-l fl. Gene' Stanley Site Vice Presiden Braidwood Station cc: D. Lynch, Senior Project Manager - NRR )

R. Assa, Braidwood Project Manager - NRR C. Phillips, Senior Resident Inspector - Braidwood A. B. Beach, Regional Administrator - RIII Oflice of Nuclear Safety - IDNS onconfid aitevp\corre( 199797006. doc