ML19263D988
| ML19263D988 | |
| Person / Time | |
|---|---|
| Site: | Catawba, Perkins, Cherokee  |
| Issue date: | 03/19/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dail L DUKE POWER CO. |
| References | |
| NUDOCS 7904240062 | |
| Download: ML19263D988 (2) | |
Text
Wy UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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MAR 191979 In Reply Refer To:
RII:JPO 50-413, 50-414 50-488, 50-489 50-490,.50-493 50-4Sf, 50-4p3 Duke Power Company Attn:
Mr. L. C. Dail, Vice President Design Engineering P. O. Box 33189 Charlotte, North Carolina 28242 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 f acility(ies) 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, James P. O'Reilly M
Director
Enclosures:
1.
List of IE Bulletins Issued in Last Twelve Months 7 001210 OG Z.
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MAR 191979 Duke Power Company cc w/ enc 1:
D. G. Beam, Project Manager Catawba Nuclear Station P. O. Box 223 Clover, South Carolina 27910 J. T. Moore, Project Manager Cherokee Nuclear Station P. O. Box 422 Gaffney, South Carolina 29340
5 UNITED STATES NUCLEAR REGULATORY COMISSION OFFICE OF INSPECTION AND ENFORCEMENT k'ASHINGTON, D.C. 20555 March 19, 1979 IE Bulletin No.78-12B ATYPICAL k' ELD MATERIAL IN REACTOR PRESSURE VEfSEL k'ELDC 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 adeouate response to the bulletins.
Following the issuance of IE Bulletin 78-12A, cenbers of the Office of Inspection and Enforcement staff met with representatives fron the reactor vessel manufacturers and suppliers to discuss the requirements of the bulletins. During these neetings, detailed interpretation of the data requirements was provided based on the manufacturer's respective methods of fabrication and record systems.
Recognizing that the scope of the record review is extensive, additional tice to respond to the bulletins is provided by this supplement.
Action to be Taken by Licensees and Permit Eciders:
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 be 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 manufacturers generic report and shall indicate that the licensee is satisfied that the generie report adequately represents data for the specific vessels covered by the licensee's report.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generie preblems.
Page 1 of 1 7904020054 Me
s IE Bulletin ilo.78-12B March 19, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Date Issued Issued To Bulletin Subject No.
78-C5 Malfunctioning of L/1L/78 All Power Reactor Facilities with an Circuit Breaker OL or CP Auxiliary Contact Mechanism-General Model CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Facilities with an Fa-er, Type M Relays OL or CP With DC Coils 78-07 Protection afforded 6/12/78 All Power Reactor Facilities with an by Air-Line Respirators OL, all class E and F and Supplied-Air Hoods Research Beactors 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 Research Reactor Fuel Element Transfer Facilities with a Tubes Fuel Elecent transfer tube and an OL.
78-09 BWR Dryvell Leakage 6/1L/79 All BW Power Reactor Facilities Paths Associated with with an OL or CP Inadeque.te Dryvell Closures 78-10 Bergen-Paterson 6/27/78 All BWR Power Reactor Facilities Hydraulic Shock with an OL or CF Suppressor Accumulator Spring Coils Page 1 of 2
IE Bulletin No.78-12B March 19, 1979 LISTING OF IE BULLETINF ISSUED IN LAST TWELVE M0:U S Date Issued Issued To Bulletin Subject No.
78-11 Examination of Mark I 7/21/78 BWR Power Reactor Facilities for Containment Torus g
action: Peach Welds Botten 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 Facilities with an in Reactor Pressure OL or CP Vessel Welds78-12A Atypical Weld f'.aterial 11/2L/78 All Po/er Reactor Facilities with an in Reactor Pressure OL or CP Vessel Welds 78-13 Failures In Source Heads 10/27/78 All general and of Kay-Ray, Inc., Gauges specific licensees with the subject Models 7050, 70503, 7051, 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B gauges 78-lh Deterioration of Buna-N 12/19/78 All GE BWR facilities vith an OL or CP Components In ASCO Solenoids 79-01 Environmental Qualifica-2/8/79 All Power Reactor Facilities with an tion of Class IE Equipnent OL or CP 79-02 Pipe Support Base Plate 3/2/79 All Power Reactor Facilities with an Designs Using Concrete OL er CF Expansion Anchor Bolts 79-03 Longitudinal Weld Defects 3/12/79 All Power Reactor in ASME SA-312 Type 30h Facilities and ca OL or CP Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Co=pany Page 2 of 2 3
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