ML20204C790
| ML20204C790 | |
| Person / Time | |
|---|---|
| Site: | Catawba, Perkins, Cherokee  |
| Issue date: | 11/24/1978 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dail L DUKE POWER CO. |
| References | |
| NUDOCS 7812050230 | |
| Download: ML20204C790 (1) | |
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UNITED ST ATES
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N S4 E In Reply Refer To:
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50-413, 50-414 l
50-488, 50-489 50-490, 50-491
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50-492, 50-493 Duke Power Company Attn:
Mr. L. C. Dail, Vice President Design Engineering P. O. Box 2178 Charlotte, North Carolina 28242 Gentlemen:
Enclosed is a supplement (IE Bulletin No.78-12A) to IE Bulletin No. 78-12 which requires action by you with regard to your power reactor facility (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, f.c M L p
mes P. O'Reilly D rector
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978 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 781205 Ol3 o
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l UNITED STATES NUCLEAR REGULATORY CCMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 2L, 1978 IE Bulletin No.78-12A ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletin 78-12, issued on Septemhr 29, 1978, and the two documents should be considered together.
Bulletin 78-12 described the use of veld wire that failed to meet all specified chemical properties in velds of twelve identified reactor pressure vessels. Use of the atypical veld material in vessel veldrents causes them to have higher than normal nil-ductility transition temperature characteristics which in turn requires more conservative pressure / tempera-ture operating limits.
Bulletin 78-12 was issued for the purpose of verifying that similar atypical veld material was not also supplied to other vessel manufacturers and used in reactor pressure vessel fabrication. Recognizing that the scope of the record review required is extensive and time consuming, and to assure that responses provided are meaningful, the requirements of Bulletin 78-12 are being modified.
Action To Be Taken By Licensees and Permit Holders:
For all power reactor facilities with an operating license or a construction permit, except those already identified as possibly having i
Stypical veld materia 11:
.1 The twelve nuclear units identified as having possible atypical pressure vessel veldments are: Three Mile Island Unit Nos. I and 2, Crratal River Unit No. 3, Arkansas Nuclear One, Unit No.1, Oconee Unit No. 3. Rancho Seco Unit No.1, Midland Unit No.1, Quad Cities Unit No. 2, Browns Ferry Unit No. 1, Turkey Point Unit No. k and Zion Unit Nos. I and 2.
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IE Bulletin No.78-12A November 2h, 1978 1.
Provide all information available on veld materials used for each reactor vessel primary boundary ferritic weldment.2 (Items Ic, Id, 2a, 2b, first sentence of 2c, 3 and h of Bulletin 78-12. ) This information may be provided to NRC through the vessel manufacturers or cuppliers as appropriate to prevent duplication of data.
2.
Correlation of specific heat, lot or batch to specific weldments in specific vessels is not required at this time.
(Last sentence of Item 2c,Bulletin 78-12.) However, each licensee is required to verify that the veld materials information provided to the NRC under Item 2 does in fact cover each reactor vessel for which the licensee is responsible.
3.
Responses to item 1 above shall be submitted in writing within 120 days of the date of this Bulletin supplement. Reports should be submitted to the Director of the appropriate NPC Regional Office and a copy should be forwarded to the U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Reactor Construction Inspection, Washington, D.C.
20555 Approved by GAO, B180225 (R0072); clearance expires 7/31/80. Approval was given unde e a blanket clearance specifically for identified generic
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Weld material information submitted vill be evaluated by NBC. Requests for further information vill be dependent upon results of these evalua-tions. Additional requests or instructions vill be issued following these evaluations.
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IE Bulletin No.78-12A Date: November 2h 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.
78-01 Flammable Contact 1/16/78 All Power Reactor Arm Retainers in G.E.
Facilities with an
'CR120A Relays OL or CP 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with an OL or CP 78-03 Potential Explosive 2/8/78 All BWR Power Gas Mixture Accumula-Reactor Facilities tions Associated with with an OL or CP BWR Offgcc System Operations 7B-Oh Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted LiLit OL or CP Switches Inside Reactor Containment 76-05 Malfunctioning of h/1h/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR105X 7B-06 Defective cutler-5/ 31/7 8 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils OL er CP l
78-07 Protection afforded 6/22/78 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 Page 1 of 2 l
f IE Bulletin No. 78 12A Date: November 2h, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Date Issued Issued To Bulletin Subject No.
78-08 Radiation Levels from 6/12/78 All Power and Research Reactor Fuel Element Transfer Facilities with a Tubes fuel Element transfer tube and an OL.
78-09 BWR Dryvell Leakage 6/lh/78 All BWR Power Reactor Facilities Paths Associated with with an OL or CP Inadequate Dryvell Closures 78-10 Bergen-Paterson 6/27/78 All BWR Power Reactor Facilities Hydraulic Shock with an OL or CP Suppressor Accumulator Spring Coils 78-11 Examination of Mark I 7/21/78 BWR Power Reactor Facilities for Containment Torus action: Peach Welds Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee 7-12 Atypical Weld Material 9/29/78 All Power Reacter Facilities with.an in Reactor Pressure OL or CP yessel Welds B-13 Failures in Source Heads 20/27/78 All General and of Kgy-Ray, Inc., Gauges Specific Licensees Models 7050, 7050B, 7051 with Kay-Ray Gaures 7051B, 7060, 7060s, 7061 and 7061B Page 2 of 2