ML19325E175
| ML19325E175 | |
| Person / Time | |
|---|---|
| Issue date: | 10/24/1989 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | Miraglia F, Murley T, Sniezek J NRC |
| References | |
| IEB-79-14, NUDOCS 8911020173 | |
| Download: ML19325E175 (2) | |
Text
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1
'N OCT 2 41989 1
9 MEMORANDUM FOR:
T. Murley G. Holahan J..Zwolinski J. Sniezek C. Rossi A. Thadani i
F. Miraglia J. Roe C. Miller J. Partlow F. Congel D. Crutchfield J. Richardson S. Varga FROM:
Ledyard B. Marsh, Chief-Mechanical Engineering Branch i
Division of Engineering Technology s
SUBJECT:
FORTHCOMING MEETING WITH BECHTEL RE: IE BULLETIN 79 14
-l AND RELATED ISSUES DATE & TIME:
Tuesday, October 31, 1989 at 9:30 a.m.
LOCATION:
One'While Flint North Room 10 B 13 1
11555 Rockville Pike Rockville, Maryland 20852 PURPOSE:
NRC and Bechtel will discuss the status of closure of IE Bulletin 79 14 and related issues such as' local stress evaluation at welded attachments and current-NRC position of Independent support Motion and Code Case N-411 PARTICIPANTS
- NRC Bechtel j
L. B. Marsh B. Meyers j
F. T. Kuo R. Jackson W. Lanning R. Pa re kh.
R. Parkhill S. Kalajar G. Bagchi M. Khlafaliah.
EMEB Members S. Be sen Ledyard Marsh, Chief Mechanical Engineering Branch Division of Engineering Technology
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy,"
.i 43 Federal Register 28058,6/28/78.
n Distribution:
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DATE
- 10/20/89
- 10/23/89
- 10/.
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OCT % '89 13:14 BCCHTCL G42THCRSBUM, MD p,3 i
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1 A4Ub4 NRC = BECHTEL MEETING OCTOBER 31, 1989 AccKVILLE, Mb A.
NRC IE Bulletin 79-14 i
1 o
Status of closure of IE3 79-14 by the NRC Acceptance / closure basis for ongoing 79-14 inspection e
o Generic plan and/or specific areas of NRC concern i
o A/E role in assisting utilities 3.
Local Stress Evaluation at Welded Attachments o
Attschments on fittings (elbows, toes ---)
o shapes of attachments Historical perspective for older plants (60's and L
o early 70's) o SIF approach WRC-107 approach for locai stress evaluation l
o o
Use of CMTR data for code compliance l
'I o
operability evaluation Faulted (primary) aC 2 Sy Upset (Prim + Sec) - use of Mark 1's fatigue data-l 1
C.
Application of Code Case N-411 to Clder Plants l
D.
EPRI NP-6153 Report and Current NRC Position of ISM and Code Case N=411 l
f PD100126.RVP 10/13/89
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