ML20155E368

Submits Results of Feedwater Nozzle Exams.No Recordable Indications Found on Safe Ends & Nozzle Inside Radii,Per NUREG-0619, BWR Feedwater Nozzle & CRD Return Line Nozzle Cracking

ML20155E368
Person / Time
Site:	Hope Creek
Issue date:	10/04/1988
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-NUREG-0619, RTR-NUREG-619 NLR-N88158, NUDOCS 8810120267
Download: ML20155E368 (4)

Text

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Punc Service Electric and Gas Company Steven E. Mittenberger Putbc Serv:co Electric and Gas Company P.O. Box 236 Hancocks Brdge, NJ 08038 609 339-4199 we nn nen ra c e va*v ouer  ;

l October 4, 1988 NLR-N88158 United States Nuclear Regulatory Commission  :

Document Control Desk t Washington, DC 20555 '

Gentlemen RESULTS OF FEEDWATER N0ZZLE EXAMINATIONS HOPE CREEK GENERATING STATION ,

DOCKET NO. 50-354 i

. Pursuant to NUREG-0619 "BWR Feedwater Nozzle and Control Rod Drive (CRD) Return Line Nozzle Cracking," Public Service i

Electric end Gas Company (PSE&G) has committed to perform the ,

1 examinations specified for the nozzle configuration that exists .

I at Hope Creek Generating Station. Since the Hope Creek Reactor  !

Vessel design does not include a CRD return line nozzle, only the six (6) feedwater nozzles, N4A through N4F, were cxamined.

i i The Hope Creek Reactor Pressure Vessel Feedwater Nozzles have the l triple slaave design with two (2) sister ring seals, with the i cladding removed. This design requires an ultrasonic exam every

) two refueling outages, a visual inspection of the feedwater

. spargers every four refueling outages, and "Routine pts" of the nozzle bore every nine (9) refueling outages or 135 shutdown /startup. cycles.  !

The exeaination of the safe ends and the nozzle inside radij were I performed on the six (6) feedwater nozzles during the Preservice Inspection (PSI). No recordable 4.ndications were found. t l

During the First Refueling Outage at Hope Creek Generating  !

) Station, PSE&G contracted Southwest Research Instituted (SWRI)  !

I for the performance of ultrasonic (UT) examinations of the six .

(6) nozzle inner bore areas, and General Electric Co. for the  ;

performance of visual examinations (VT) of the feedwater sparger  ;

flow holes, welds in the sparger arms and sparger tees. No i recordable indications were found. 8 Two (2) areas with limitations were identified by SWRI on nozzles '

N4B and N4D. The limitations were caused by permanently welded i thermocouple pads while scanning from the nozzle boss. The limitation area on nozzles N4B was from 7-9 o' clock, and on 7q t

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Document Control Desk 2 10-04-88 l 2  ;

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nozzle N4D from 8:30-9 o' clock, as viewed facing the reactor pressure vessel.  ;

copies of examination procedures, field examination data, and  !

video tapes have been retained and are available at the site for review.

1 Should you have any further questions with regard to these f

, examination results. please do not hesitate to contact us. j t

l Sincerely, .

i l jfj ~ >1 L hlawb khN+

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l C Mr. G. W. Rivenbark i Licensing Project Manager i Mr. G. W. Meyer  !

Senior Resident Inspcctor j i

Mr. W. T. Russell, Administrator l Region I l Ms. J. Moon, Interim Chief Bureau of Nuclear Engineering Department of Environmental Protection  !

380 Scotch Road ,

Trenton, NJ 08628 i F

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PubtCServce oectr.c and Gas cwcry Steven E. Miltenberger Pet c Se v ce E ecmc and Gas Company P O Sci 236. Haacccas Br c;;e. NJ C8033 603-339-4W sarm : m e s c c o . y e:e.

October 4, 1988 NLR-N86158 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

RESULTS OF FEEDWATER N0ZZLE EXAMINATIONS HOPE CREEK GENERATING STATION DOCKET No. 50-354 Pursuant to NUREG-0619 "BWR Feedwater Nozzle and Control Rod Driva (CRD) Return Line Nozzle Cracking," Public Service Electric and Gas Company (PSE&G) has committed to perform the examinations specified for the nozzle configuration that exists at Hope Creek Generating Station. Since the Hope Creek Reactor Vessel design does not include a CRD return line nozzle, only the six (6) feedwater nozzlts, N4A through N4F, were examined.

The Hope Creek Reactor Pressure Vessel Feedwater Nozzles have the triple sleeve design with two (2) siator ring seals, with the cladding removed. This design requires an ultrasonic exam every two refueling outages, a visual inspection of the feedwater spargers overy four refueling outages, and "Routine pts" of the nozzla bore overy nine (9) refueling outages or 135 shutdown /startup cycles.

The examination of the safe ends and the nozzle inside radii were performed on the six (6) foodwater nozzles during the Preservice Inspection (PSI). No recordable indications were found.

During the First Refueling Outage at Hope Creek Generating Station, PSE&G contracted Southwest Research Instituted (SWRI) for the performance of ultrasonic (UT) examinations of the six (6) nozzle inner bore areas, and Generel Electric Co. for the performance of visual examinations (VT) of the feedwater sparger flow holes, welds in the aparger arms and sparger tees. No

! recordable indications were found.

Two (2) areas with limitations were identified by SWRI on nozzles N4B and N4D. The limitations were caused by permanently welded thermocouple pads while scanning from the nozzle boss. The limitation area on nozzles N4B was from 7-9 o' clock, and on

Document Control Desk 2 10-04-88 nozzle N4D from 8:30-9 o' clock, as viewod facing the reactor pressure vessel.

Copies of examination procedures, field examintition data, and video tapes have been retained and are available at the site for review.

Should you have any further questions with regard to these examination results, please do not hesitate to contact us.

Sincerely, fj , ,i

. kd h k(* tb C Mr. G. W. Rivenbark Licensing Project Manager Mr. G. W. Heyer Senior Resident Inspector Mr. W. T. Russell, Administrator Region I Hs. J. Moon, Interim Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 L