ML20148G371
| ML20148G371 | |
| Person / Time | |
|---|---|
| Site: | Black Fox |
| Issue date: | 10/31/1978 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Ewing T PUBLIC SERVICE CO. OF OKLAHOMA |
| References | |
| NUDOCS 7811130055 | |
| Download: ML20148G371 (3) | |
Text
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4 UNITED STATES NUCLEAR REGULATORY COMISS10fl 0FFICE OF INSPECTION AtID ENFORCEMENT WASHINGTON, D.C.
20555 flovember 24, 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 September 29, 1978, and the two documents should be considered together.
Bulletin 78-12 described the use of weld wire that failed to meet all specified chemical properties in welds of twelve identified reactor pressure vessels.
Use of the atypical weld material in vessel weldments 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 weld material was not also supplied to other vessel manufacturers and used in reactor pressure vessel fabrication.
Recognizing that the i
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, eycept those already identified as possibly having atypical weld material :
uy I The twelve nuclear units identified as having possible atypical pressure vessel weldments are:
Three Mile Island Unit Nos.1 and 2, Crystal River Unit No. 3, Arkansas Nuclear One Unit No.1, Oconee Unit No. 3, Rancho Seco Unit flo.1, Midland Unit No.1, Quad Cities Unit No. 2, Browns Ferry Unit No.1, Turkey Point Unit No. 4 and Zion Unit Nos. 1 and 2.
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V IE Bulletin No.78-12A November 24, 1978 1.
Provide all information available on weld materialg used for each reactor vessel primary boundary ferritic weldment.
(Items 1c, id, 2a, 2b, first sentence of 2c, 3 and 4 of Bulletin 78-12.) This information may be provided to NRC through the vessel manufacturers or suppliers 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.
(Lastsentence of Item 2c,Bulletin 78-12.) However, each licensee is required to verify that the weld materials information provided to the NRC under Item 1 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 NRC 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 i
was given under a blanket clearance specifically for identified generic problems.
.+
2 Weld material information submitted will be evaluated by NRC.
Requests for further information will be dependent upon results of these evalua-tions. Additional requests or instructions will be issued following these evaluations.
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IE Bulletin No.78-12A Date: November 24, 1978 LISTING 0F 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 i
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 Offgas System Operations 78-04 Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit OL or CP Switches Inside Reactor Containment 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 cr 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 Page 1 of 2
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