ML20062H095
| ML20062H095 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 03/19/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Wofford A LONG ISLAND LIGHTING CO. |
| References | |
| NUDOCS 7904240181 | |
| Download: ML20062H095 (1) | |
Text
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.. pa asoog[o UNITED STATES y
g NUCLEAR REGULATORY COMMISSION i
S REGION I 3
i sai eman avenus f
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I March 19, 1979 Docket No. 50-322
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Long Island Lighting Company 1
ATTN: Mr. Andrew W. Wofford Vice President i
d 175 East Old Country Road
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Hicksville, New York 11801
. h Gentlemen:
l Enclosed is a supplement (IE Bulletin No.78-128) to IE Bulletin Nos.
.i 78-12 and 12A, which requires action by you with regard to your power j
reactor facility (ies) with an operating license or a construction permit.
A written response is required.
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Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely,
/C(,
GW Boyce H. Grier Director i
Enclosures:
1.
IE Bulletin 72-128 2.
List of IE Bulletins Issued i
in Last Twelve Months cc w/encls: -
J. P. Novarro, Project Manager
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Edward M. Barrett, Esquire
_. 1 Edward J. Walsh, Esquire I
I T. F. Gerecke, Manager, Engineering QA Department i
l 7 9042401Sl Q
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UNITED STATES NUCLEAR REGULATORY C0PfiISSION 0FFICE OF INSPECTION AND ENFORCEMENT t
WASHINGTON, D.C.
20555
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Date: March 19, 1979
.f?j Page 1 of 1
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j ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:
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This bulletin is a supplement to IE Bulletins 78-12 and 12A and all three documents must be collectively considered to provide an adequate
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response to the bulletins.
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Following the issuance of IE Bulletin 78-12A, members of the Office of Inspection and Enforcement staff met with representatives from the
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reactor vessel manufacturers and suppliers to discuss the requirements of the bulletins.
During these meetingr., detailed interpretation of the data requirements was provided based on the manufacturer's respective i
methods of fabrication and record systems.
Rec::gnizing that the scope of the record review is extensive, additional time to respond to the bulletins is provided by this supplement.
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i Action to be Taken by Licensees and Permit Holders:
This bulletin applies to all power reactor facilities with an operating license or a construction pennit, except those already identified as i
possibly having atypical weld material.
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Q Responses to the requirements in Bulletins 78-12 and 12A shall be submitted
_ l in writing in accordance with the following schedule:
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1.
Generic reports from each reactor vessel manufacturer shall
-j be submitted to the NRC by May 1,1979.
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2.
The licensee responses shall be submitted by May 29, 1979. The licensee's response shall include all of the specific vessel infonnation required by the bulletins which is not covered by the vessel manufacturers generic report and shall indicate that the licensee is satisfied that the generic report adequately represents data for the specific vessels ccvered by the licensee's report.
Approved by GAO, ?l80225 (R0072); clearance expires 7/31/80. Approval t
was given under a blanket clearance specifically for identified generic I
problems.
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1 IE Bulletin No.78-128 Date: March 19, 1979 a
Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
.j j
78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an
,j Auxiliary Contact Operating License i
Mechanism - General (OL) or Construction j
Electric Model CR105X Permit (CP) 78-06 Defective Cutler-5/31/78 All Power Reactor Hamer, Type M Relays Facilities with an
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With DC Coils OL or CP 78-07 Protection afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority I Material Licensees 78-08 Radiation Levels from 6/12/78 All Power. Test and Fuel Element Transfer Research Reacter Tubes Facilities with an OL having Fuel Element Transfer Tubes b'
78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities j
Inadequate Drywell with an OL (for action) j Closures or CP (for information) 78-10 Bergen-Paterson 6/27/78 All BWR Power Reactor Hydraulic Shock Facilities with Suppressor Accumulator an OL or CP 4
Spring Coils l-l l
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IE Bulletin No.78-12B Date: March 19, 1979 Page 2 of 3 I
LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED)
Bulletin Subject Date Issued Issued To
,j No.
.s g
78-11 Examination of Mark I 7/24/78 BWR Power Reactor Containment Torus Facilities with an OL Welds for action: Peach j
Bottom 2 and 3, Ouad Cities 1 and 2, Hatch 1, Monti-lj cello and Vennont Yankee. All other l
BWR Power Reactor Facilities with an i
O
' ' " '"' r"**'
a 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-13 Failures In Source Heads 10/27/78 All General and i
of Kay-Ray, Inc., Gauges Soer.ific Licensees Models 7050, 70508, 7051, with the subject 70518, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B Gauges 4
(m 78-14 Deterioration of Buna-N 12/19/78 All BWR Power Reactor ul Components In ASCO Facilities with an OL Solenoids (foraction),andall other Power Reactor 1
Facilities with an OL j
orCP(forinformation) 79-01 Environmental Qualifica-2/8/79 All Power Reactor j
tion of Class IE Equipment Facilities with an j
OL, except the 11 Systematic Evaluation
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i Program Plants (for action), and all l
other Power Reactor Facilities with an OL or CP (for in-formation) l
,7 IE Bulletin No.78-12B Date: March 19,1979 Page 3 of 3
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LISTING OF IE BULLETINS
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ISSUED IN LAST TWELVE MONTHS (CONTINUED)
- 4 Bulletin Subject Date Issued Issued to l... ;.
No.
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79-02 Pipe Support Base Plate 3/8/79 All Power Reactor
~j Design Using Concrete Facilities with Expansion Anchor Bolts an OL or CP 79-03 Longitudinal Weld Defects 3/12/79 All Power Reactor in ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe OL or CP 1
Spools Manufactured by Youngstown Welding and l
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Engineering Company
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