ML19263D992
| ML19263D992 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/19/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 7904240123 | |
| Download: ML19263D992 (1) | |
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g"i 19'Jo re. c at if 0 9:414 tioot t V A v a w ALNur c twr.x, cnt ie ove rain 9: sac f4 arch 19,1979 Docket flo. 50-312 Sacramento fiunicipal Utility District P. O. Box 15830 Sacramento, California 95813 Attention: fir. John J. flattimoe Assistant General flanager Gentlemen:
Enclosed is a supplement (IE Bulletin f;o.78-12B) to IE Bulletin flo. 78-12 and 12A which requires action by you with regard to your power reactor facility (ies) with an operating license or a construc-tion permit.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, Ot L, eel!
R. H. Engelken Director
Enclosures:
1.
List of IE Bulletins Issued in the last 12 months cc w/ enclosures:
R. J. Rodriguez, SMUD L. G. Schwieger, S!4UD 7 0012<10143
e Uf;ITED STATES f:UCLEAR REGULATORY CCMISSION OFFICE OF IliSPECTION AND ENFORCEf1EllT WASHII;GTON, D.C.
20555 flarch 19, 1979 IE Bulletin fio.78-12B ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletins "i8-12 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, nembers of the Office of Inspection and Enforcement staff net with representatives from the reactor vessel manufacturers and suppliers to discuss the requirements of the bulletins.
During these meetinqs, detailed interpretation of the data requirements was provided based on the nanufacturer's respective methcds 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 weld 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 nanufacturer shall be submitted to the f;RC by May 1,1979.
2.
The licensee responses shall be submitted by flay 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 manufacturers 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, B1G0225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.
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pane 1 of 1 79040:20054
IE Bulletin No.78-128 March 19, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWEL'!E MONTHS Bulletin Subject 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 Mechanism-General Model CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils OL or CP
/8-07 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 Fuel 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 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 Enclosure r; c.
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fiarch 19, 1979 LISTIf;G OF IE BULLETIflS ISSUED It' LAST TWELVE !10NTHS Bulletin Subj ect Date Issued Issued To flo.
78-12 Atypical Weld flaterial 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CD 78-12A Atypical Weld liaterial 11/24/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12B Atypical Weld liaterial 3/19/79 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 f4odels 7050, 70508, 7051, with the subject 70518, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B guages 78-14 Deterioration of Buna-fl 12/19/78 All GE BWR facilities Components In ASCO with an OL or CP Solenoids 79-01 Environmental Qualifica-2/08/79 All Power Reactor tion of Class IE Equipment Facilities with an OL or CP 79-02 Pipe Support Base Plate 3/08/79 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 ASi1E SA-312 Type 304 Facilities and an Stainless Steel Pipe OL or CP Spools f4anufactured by Youngstown Welding and Engineering Company Enclosure Page 2 of 2