ML20148Q543

Forwards IE Bulletin 78-12A,suppl to IE Bulletin 78-12. W/Encl ANO:7811300055

ML20148Q543
Person / Time
Site:	Rancho Seco
Issue date:	11/24/1978
From:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT
References
NUDOCS 7811300092
Download: ML20148Q543 (1)

Text

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l Docket flo. 50-312 Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Attention: Mr. John J. Mattimoe Assistant Gueral Manager Gentlemen:

Enciased is a supplement (IE Bulletin No.78-12A) to IE Bulletin flo.

78-12 which may be of interest to you with regard to your power reactor facility (ies).

Should you have questions regarding this Bulletin, please contact this office. ,

Sincerely, O. .

IN h /

R. H. Engel ken Director

Enclosures:

1. IE Bulletin 78-12A

2. List of IE Bulletins Issued in 1978 cc w/ enclosures:

R. J. Rodriguez, SMUD L. G. Schwieger, SMUD  ;

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UllITED STATES

, fiUCLEAR REGULATORY COMMISSI0ft 0FFICE OF IllSPECTI0ft Afl0 EflFORCEMEtlT WASHIllGT0ft, D.C. 20555 flovember 24, 1978 IE Bulletin flo.78-12A ATYPICAL WELD MATERIAL Ifl REACTOR PRES 50RE VESSEL WELOS 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 l causes them to have higher than normal nil-ductility transition temperature l 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 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 Ey 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 naterial :

I The twelve nuclear units identified as having possible atypical pressure vessel weldments are: Three Mile Island Unit flos.1 and 2, Crystal River Unit flo. 3, Arkansas fluclear One Unit flo.1, Oconee Unit flo. 3, Rancho Seco Unit fio.1, Midland linit flo.1, Quad Cities Unit flo. 2, Browns Ferry Unit flo.1, Turkey Point Unit f40. 4 and *2 Zion Unit flos.1 and 2.

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IE Bulletin No.78-12A November 24, 1978 p-

1. Provide all information available on weld materialg used for each reactor vessel primary boundary ferritic weldment. (Itemslc,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. , 4

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 k-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 under a blar.ket clearance specifically for identified generic problems.

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Weld material information submitted will be evaluated by NRC. Requests -

for further informacion will be dependent upon results of these evalua- i tions. Additional < equests or instructions will be issued following $

these evaluations.

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IE Bulletin flo.78-12A Datet flovember 24, 1978 LISTING OF IE BULLETIflS 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 Offgas System Operations 78-04 Environmental Quali- 2/ 21 / 7 8 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 Pcwer 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 l With DC Coils OL or CP l

78-07 Protection afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities with an l 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 E.nclosure 2 Page 1 of 2 l

IE Bulletin No.78-12A

. Date: November 24, 1978 j LISTING OF IE BULLETINS I ISSUED IN 1978 l Bulletin Subject Date Issued Issued To No.

78-08 Radiation Levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor 1 Tubes Facilities with a 0 Fuel Element transfer tube and an OL. ,

l 78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL or CP

' Closures l 78-10 Bergen-Paterson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities i

Suppressor Accumulator with an OL or CP Spring Coils 1

78-11 Examination of Mark I 7/ 21 /78 BWR Power Reactor i Containment Torus Facilities for l Welds action: Peach Bottom 2 and 3, i Quad Cities 1 and 1 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 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 Kay-Ray Gauges 7051B, 7060, 70608, 7061 and 70618 4

Enclosure 2 Page 2 of 2 l

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