ML20062E229

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

ML20062E229
Person / Time
Site:	Bailly
Issue date:	11/24/1978
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Shorb E NORTHERN INDIANA PUBLIC SERVICE CO.
References
NUDOCS 7812050338
Download: ML20062E229 (1)

Text

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NOV 2.4 .378 Docket No. 50-367 Northern Indiana Public Service Company ATIN: Mr. Eugene M. Shorb Senior Vice President 5265 Hohman Avenue Hammond, IN 46325 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 fccility 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, James G. Kep SY r Director

Enclosures:

1. lE Bulletin 78-12A

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

Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General

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1 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III November 24, 1978 U. Bulletin No.78-12A ,

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ATYPICAL WELD MATEk1AL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:

This Bulletic is a supplement to IE Bulletin 78-12, issued on Septenber 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 velds of twelve identified reactor pressure vessels. Use of the atypical weld material in vessel veldments causes then to have higher than normal nil-ductility transition temperature characteristics which in turn requires more conservative pressure /tenpera-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 coneuzing, and to assure that responses provided are meaningful, the requirements of Bulletin 78-12 are being modified.

Action To Be Taken By Licensees and Pertit Eolders: ,

Tor all power reactor facilities with an operating license or a

. construction permit, except those already identified as possibly having 7 typical weld material.3/

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- he twelve nuclear units identified as having possible atypical

.. pressure vessel veldnents are: Three Mile Island Unit Nos. I and 2, Crystal River Unit No. 3 Arkansas Nuclear One Unit No.1. Oconee ,

. r - . Unit No. 3, Rancho Seco Unit No.1, Midland Unit No.1. Quad Cities Unit No. 2, Brovns Terry Unit No.1 Turkey Point Unit No. 4 and

, Zion Unit Nos. I and 2.

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, i ol IE Bulletin No.78-12A -

2- November 24, 1976 i a

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.

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 Ite: 1 does in fact cover each reactor vessel for which tne  !

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 Com=ission, Office of Inspection and Enforcement, Division of ,

Reactor Construction Inspection, Washington, D.C. 20555. .

I Approved by GAO, B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic 1 problems.

WWeld material information submitted will be evaluated by NRC. Requests for further information vill be dependent upon results of these evalua-tions. Additional requests or instructions will be issued following

'hese t evaluations.

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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.

78-01 Flammable Contact - 1/16/78 All Power Reactor Arc Retainers in C.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 Cas Mixture Accumula- Reactor Facilities tions Associated with with an OL or CP BWR Offges System Operations 78-04 Environmental Quali- 2/21/78 All Power Reactor fication of certain Facilities with an Stec 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-Ceneral Model CR105I 78-06 Defective Cutler- 5/31/78 All Power Reactor Eaccer, Type H Relays Faci'ities 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 Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1

. Material Licensees Enclosure 1 Page 1 of 2

2 IE Bulletin No.78-12A Date: November 24, 1978 LISTING OF IE MULLETINS ISSUED IN 1978 Bulletin Subj ect Date Issued Issuec To No.

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

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

, 78-10 Bergen-Paterson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an OL or CP ,

Spring Coils l 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, 70508, 7051 with Kay-Ray Gauges 7051B, 7060, 7060B, 7061 and 7061B Enclosure 1 Page 2 of 2 g , e.m a - m+ '

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