ML18025B992
| ML18025B992 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/01/1983 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8308080499 | |
| Download: ML18025B992 (4) | |
Text
Docket No. 50-296 AUGUST 1
1983 DISTR cu-ment Contro GRAB ea ing JZwolinski TAlexion GHolahan NRC PDR L PDR PRC System MEMORANDUM FOR:
Darrell. G. Eisenhut, Director Division of Licensing THRU:
FROM:
SUBJECT:
Frank J. Miragli,a, Assistant Director for Safety Assessment Division of Licensing Gary M. Holahan, Chief Operating Reactors Assessment Branch Division of Licensing FORTHCOMING MEETING WITH THE TENNESSEE VALLEY AUTHORITY ( Browns Ferry 3)
Date 8 Time:
Location:
Purpose:
Parti ci pants:
August 9, 1983 1:00 pm - 4:00 pm Room P-422 Phillips Building To have licensees present to the staff recommendations 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. Clark TVA J.
- Green, L. Mills, J.
Domer, et.al grig'mal S>Rned 8 8308080499 83080i
'DR ADQCK 05000296
, 6, PDR
Enclosure:
Agenda Gary M.. Holahan, Chief Operating Reactors Assess nt Division of Li nsing DL TACAN)
JZwo inski olahan 08/ / /83 08/,i /83 08/
y /83 Branch D
SA OL:
Fl glia DEisenhut 08// /83 08/
/83
AGENOA I.
NRC Opening Remarks II.
Licensee Pre'sentation on:
A.
B.
Justification for continued operation of the facility prior to completing the inspections described in Attachment A to the 50.54(f) letter.
Describe any unique safety related
- feature, information or action that would justify not accelerating your current test and inspection schedule.
Summary 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 disposit'ion of crack indications C.
Description of any special. surveillance measures in 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 50.54(f) letter:
I a.
on a committed realistic accelerated schedule b.
30, 60, or 90 days from August 15, 1983
- c. 'uring the next refueling outage E.
Discussion of availability of qualified inspection personnel to perform inspections.
III.
Licensee discussion of changes in information or positions as a
result of EPRI UT information from 08/04/83 meetings.
~e ~
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