ML19273B192
| ML19273B192 | |
| Person / Time | |
|---|---|
| Site: | 05000484 |
| Issue date: | 03/19/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dienhart A NORTHERN STATES POWER CO. |
| References | |
| NUDOCS 7904030071 | |
| Download: ML19273B192 (1) | |
Text
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Docket No. 50-484 Northern States Power Company ATTN:
Mr. A. V. Diechart Vice President - Tyrone Energy Park 100 North Barstow Street Eau Claire, WI 54701 Gentlemen:
Enclosed is a supplement (IE Bulletin No.78-12B) to IE Bulletin No. 78-12 and 12A which requires action by you with regard to your power reactor facility with an operating license or a construction permit.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, bY James G. Kepp er Director
Enclosures:
1.
List of IE Bulletins Issued in Last Twelve Months cc w/encls:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC vTIC Regions I & IV 4
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U.S. NUCLEAR RFOULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III March 19, 1979 IE Bulletin No.78-12B ATYPICAL WELI) MATERIAL IN REACTOR PRESSURE 7ESSEL WELDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletins 78-12 and 12A and all three documents must be collectively considered to provide an adequate response to the bulletins.
Following the issuance of IE Bulletin 78-12A, members of the Office of Inspection and Enforcement staff met with representatives from the reactor vessel manufacturers and suppliers to discuss the requirements of the bulletins. During these meetings, detailed interpretation of the data requirements was provided based on the manufacturer's respective pethods of fabrication and record systems.
Recognizing that the scope of the record review is extensive, additional time to respond to the bulletins is provided by this supplement.
Action to be Taken by Licensees and Permit Holders:
This bulletin applies to all power reactor facilities with an operating license or a construction permit, except those already identified as possibly having atypical veld material.
Responses to the requirements in Bulletins 78-12 and 12A shall be submitted in writing in accordance with the following schedule:
1.
Generic reports from each reactor vessel manufacturer shall
_he submitted to the NRC by May 1,1979.
2.
The licensee responses shall be submitted by May 29, 1979. The licensee's response shall include all of the specific vessel information required by the bulletins which is not covered by the vessel manufaqturers generic report and shall indicate that the licensee is satisfied that the generic report adequately represents data for the specific vessels covered by the licensee's report.
Approved by GAO, 3180225 (R0072); clearance expirep 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.
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1 IE Bulletin No.78-12B March 19, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MORIHS Bulletin "ubject Date Issued Issued To No.
78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Eechanism-General Model CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type E Relays Facilities with an 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 1 Material Licensees 78-08 Radiation Levels from 6/12/78 All Power and Tuel Element Transfer Research Reactor Tubes Facilities with a Fuel Element transfer tube and an OL.
78-09 BWR Drywell Leakage 6/14/79 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL or CP Closures 78-10 Bergen-Paterson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an OL or CP Spring Coils i
Page 1 of 2
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- s IE Bulletin No.78-12B March 19, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
78-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Facilities for Welds action: Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Tessel 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 of Kay-Ray, Inc., Gauges specific licensees Models 7050, 7050B, 7051, with the subject 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B gauges 78-14 Deterioration of Buna-N 12/19/78 All GE BWR facilities Cc=ponents In ASCO with an OL or CP Solenoids 79-01 Environmental Qualifica-2/8/79 All Power Reactor tion of Class IE Equipment Facilities with an OL or CP 75-02 Pipe Support Base Plate 3/2/79 All Power Reactor Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or CP 79-03 Longitudinal Weld Defects 3/12/79 All Power Reactor in ASME SA-312 Type 304 Facilitiec and an Stainless Steel Pipe OL or CP Spools Eanufactured by Youngstown Welding and Engineering Company Page 2 of 2
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