ML17194B666

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Notification of 830809 Meeting W/Util in Bethesda,Md for Presentation of Recommendation & Concerns Re Proposed Acceleration of Insps of Large Diameter BWR Pipe Welds. Agenda Encl
ML17194B666
Person / Time
Site: Dresden, Quad Cities  
Issue date: 08/01/1983
From: Holahan G
Office of Nuclear Reactor Regulation
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NUDOCS 8308050134
Download: ML17194B666 (2)


Text

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ment coritroi ORAB Reading Docket No. 50-249 50-265 AUGUST 1

1983 MEMORANDUM FOR:

Darrell G. Eisenhut, Director Division of Licensing THRU:

Frank J. Miraglia, Assistant Director for Safety Assessment Division of Licensing FROM:

.Gary M. Ho.lahan, Chief Operating Reactors Assessment Branch Division of Licensing NRC PDR L PDR PRC System JZwolinsk.i TAlexion GHolahan

SUBJECT:

FORTHCOMING MEETING WITH THE C01"U'10NHEAL TH EDISON COMPANY (Dresden 3 and Quad Cities 2)

Date & Time:

August 9, 1983 9:00am - 12 noon Location:

Room P-422 Phillips Building

Purpose:

Participants:

To have 1 icensees present to the staff recommendati ans.

and concerns regarding the proposed acceleration of inspections of large diameter BWR pipe welds (Agenda attached)

NRC H. Denton, E. Case, D. Eisenhut, R. Vollmer, E. Jordan, R. Purple, G. Lainas, F, Miraglia, W. Johnston, D. Vassallo, D. Crutchfield, G. *Holahan, B.D. Liaw, J. Zwolinski, T. Alexion, P. Matthews, R. Bevan, R. Gilb.ert CE Co D. Farrar, et al p4 0 It\\ t, *r \\"11 (',\\I '*; : *} /: ~,"ififil'

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T AGENDA I.

NRC Opening Remarks IT.

Licensee Presentation. on:

  • A. Justification for continued operation of the facility prior to completing the* inspections described in Attachment A to the S0.54(f) letter. Describe any unique safety related feature, infonnation or action that would justify not.

accelerating your current test and inspection schedule.

B.

Sunnnary of weld inspections completed which the licensee believes conform to the intent of IE Bulletin 83-02:

inspection results:, dates, system location inspection method crack detection sensitivity disposition of crack. indications C.

Description of any special surveillance measures i:n effect or proposed for primary system leak detection that supplement current plant Technical Specifications.

D.

Costs and impacts on other safety related activities of conducting the inspections in Attachment A to the S0.54{f) letter:

a.

on a conmitted realistic accelerated schedule

b.

30, 60, or 90 days from August 15, 1983 c*.. during the next refueling outage E.

Discussion of availability of qualified inspection personnel to perfonn inspections.

III. Licensee discussion of changes in information or* positions as a result of EPRI UT information from 08/04/83 meetings.