ML20204C949

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

ML20204C949
Person / Time
Site:	Zimmer
Issue date:	11/24/1978
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Borgmann E CINCINNATI GAS & ELECTRIC CO.
References
NUDOCS 7812050300
Download: ML20204C949 (1)

Text

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-Docket No. 50-358 Cincinnati Gas and Electric Company ATTN: Mr. Earl A. Burgmann Vice Preside".it Engineering Serviaes and Electric Production 139 East 4th Street Cincinnati, ' 0B 45201 Gentlemen:

4- 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 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, l

James G. Keppler Director

Enclosures:

1. IE Bulletin 78-12A ,

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

Mr. J. R. Schott, Plant Superintendent Central Files -

l Director, NRR/DPM l Director, NRR/ DOR PDR l' ' Local PDR NSIC l TIC U. Young Park, Power Siting Commission I

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I U.S. NUCLEAR REGULATORY COMMISSION 5

OFFICE OF INSPECTION AND ENFORCEMENT 1 REGION III November 24, 1978 i

, IE Bulletin No.78-12A ,

ATYPICALWELDMATEk1ALINREACTORPRESSUREVESSELWELDS

, 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 transitisn temperature chcracteristics 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 By Licensees and Permit Bolders:

Tor all power reactor facilities with an operating license or a

- *. construction permit, except those already identified as possibly having stypical weld material.1/

JNhhe twelve nuclear units identified as having possible atypical

.. pressure vessel weldsents are: Three Mile IsIcod Unit Nos. I and 2,

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Crystal River Unit No. 3 Arkansas Nuclear One Unit Wo.1, Oconee

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. Unit No. 3, Rancho Seco Unit No.1. Midland Unit No.1, Quad Cities Unit No. 2, Browns Perry Unit No.1, Turkey Point Unit No. 4 and

, Zion Unit Nos. I and 2.

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a IE Bulletin No.78-12A -

2- November f4, 197G

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1. Provide all information available on veld materials used for each reactor vessel primary boundary ferritic weldmentM (Items Ic, 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. (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 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 shou 1G be forwarded to the U.S. Fuelear 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 blanket clearance specifically for identified generic problens.

1/ Weld caterial information submitted will be evaluated by NRC. Requests for further infornation 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 24, 1978 i

t LISTING OF IE BULLETINS I ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.

Flammable Contact - 1/16/78 All Power Reactor 78-01 Facilities with an Arm Retainers in G.E.

CR120A Reisys OL or CP Terminal Block 1/30/78 All Power Reactor 78-02 Facilities with an Qualification a

OL or CP Potential Explosive' .1/8/78 All BWR Power 4 78-03 Gas Mixture Accumula- Reactor Facilities tions' Associated with with an OL or CF BWR Offgas System i Operations I

! 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 Mechanisc-General Model CR105X Defective Cutler-- 5/31/78 All Power Reactor q 78-06 Facilities with an Hammer, Type M Relays  !

OL or CP With DC Coils All Power Reactor

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78-07 Protection afforded 6/12/78 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 j Facilities with an OL, and all Priority' 1

• Material Licensees

'd Enclosure' 1 Page' 1 of 2 l

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IE Bulletin No.78-12A Date: November 24, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.

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

09 BWR Drywell Leakage 6/14/78 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 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 Ray-Ray, Inc., Gauges Specific Licensees Models 7050, 7050B, 7051 with Kay-Ray Gauges 7051B, 7060, 7060B, 7061 and 7061B Enclosure' 1 Page 2 of 2

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