ML20148T518

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

ML20148T518
Person / Time
Site:	Perry
Issue date:	11/24/1978
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Davidson D CLEVELAND ELECTRIC ILLUMINATING CO.
References
NUDOCS 7812050325
Download: ML20148T518 (1)

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c4gm MC 4 O UNITED STATES yo 'g NUCLEAR REGULATORY COMMISSION j g nectoN ill

• 'C 799 ROOSEVELT ROAD

$, OLEN E LLYN, ILLINolS 60137 NOV 2 4 .378 Docket No. 50-440 Docket No. 50-441 The Cleveland Electric Illuminating Company ATTN: Mr. Dalwyn R. Davidson Vice President - Engineering P. O. Box 5000 Cleveland, OH 44101 Gentlemen:

Enclosed is a supplement (IE Bulletin No.78-12A) to lE Bulletin No. 78-12 which requires action by you with regard to your power

[ reactor facilities 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, bY ames G. Kep ler '

Director

Enclosures:

1. IE Bulletin 78-12A

2. List of IE Bulletins

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Issued in 1978 cc w/encls:

Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC  ;

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' U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT l

REGION III November 24, 1978 IE Bulletin No.78-12A ATYPICAL WELD F'"' 'EACTOR PRESSURE VESSEL WELDS Description of Circums.  :

This Bulletin is a supplement to IE Bulletin 78-12, issued on September 29, 1978, and the two documents should be considered toEether. ,

Bulletin 78-12 described the use of veld wire that failed to meet all specified chemical properties in velds of twelve identifief, reactor pressure vessels. Use of the atypical veld material in vessel veldments causes them to have higher than normal nil-ductility transition temperature characteristics which in turn requires more conservative pressure /teepera-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 2

to assure that responses provided are meaningful, the requirements of Bulletin 78-12 are being modified.

- Action To Be Taken By Licensees and Permit Eolders:

• Tor all power reactor facilities with an operating license or a construction permit, except those already identified as possibly having

- ptypical veld material.3/

• I be h twelve nuclear units identified as having possible atypical pressure vessel veldments are:

Three Mile Island Unit Nos. 1 and 2,

' -- Crystal River Unit No. 3, Arkansas Fuelear 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. 4 and a

Zion Unit Nos. I and 2. *

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

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1. Provide all information available on weld materials used for each reactor vessel primary boundary ferritic weldment// (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.

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2. Correlation of specific heat, lot or batch to specific weldments j

in specific vessels is not required at this time. (Last sentence of Item 2c, Bulletin 78-12.) However, each licensee is required J

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.

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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 was given under a blanket clearance specifically for identified generic problems.

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'1/ Weld material information submitted will be evaluated by NRC

. . Eequests for further information will be dependent upon results of these evalus-tions. Additional requests or instructions vill be issued following i 'hese evaluations.

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IE Bulletin No.78-12A Date: November 24, 1978 e

LISTING OF IE BULLETINS ISSUED IN 1978 i

Bulletin Subj ect 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

'( 76-03 Potential Explosive 2/8/78 All BWR Power Gas Mixture Accumula- Reactor Facilities tions Associated with with an OL or CP l BWR Offgas System i Operations )

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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 l 78-05 Malfunctioning of 4/14/78 All Power Reactor ,

Circuit Breaker Facilities with an Auxiliary Contact )

OL or CP '

Mechanisc-General I Model CR1051 I

78-06 Defective Cutler- 5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils OL or 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 l 4

Research Reactors with l an OL, all Fuel Cycle Facilities with an OL, and all Priority' 1 )

l Material Licensees l Enclosure 1 Page' 1 of 2 s

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L IE Bulletin No.78-12A Date: November 24, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 i l

Bulletin Subj ect Date Issued Issued To No.

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

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

, 78-10 Bergen-Paterson 6/27/78 All BVR 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 Kay-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 g -sp' e19 = %e *-