ML20204C966

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

ML20204C966
Person / Time
Site:	Marble Hill
Issue date:	11/24/1978
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Coughlin J PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA
References
NUDOCS 7812050305
Download: ML20204C966 (1)

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Docket No. 50-546 NOV I4 .378 Docket No. 50-547 Public Service of Indiana ATTN: Dr. James Coughlin Vice President, Nuclear 1000 East Main Street Plainfield, IN 46168 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 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, James G. Kep er Director

Enclosures:

1. IE Bulletin 78-12A

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

R. M. Brown, Construction Project Engineer Central Files Director, hTR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC LeBoeuf, Lamb, Leiby & MacRae 78120503sf (Q

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U.S. NUCLEAR REGULATORY COMMISSION A

OFFICE OF INSPECTION AND ENFORCEKENT REGION III November 24, 1978 i

IE Bulletin No.78-12A ,

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ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS

- Description of Circumstances:

This Bulletic 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 chemdeal properties in velds of twelve identified 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 / tempera-ture operating limits.

Bu11etin 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 coneucing, and to assure that responses provided are meaningful, the requirements of Bulletin 78-12 are being modified.

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Action To Be Taken By Licensees and Permit Bolders:

Tor all power reactor facilities with an operatf 'icense or a

- .: construction permit, except those already ident . as possibly having ptypical veld material.1/

. The twelve nuclear units identified as having possible atypical

. .. pressure vessel veldsents are: Three Mile Island Unit Nos. 3 and 2, Crystal River Unit No. 3, Arkansas Nuclear One Unit No. 1. Oconee Unit No. 3. Rancho Seco Unit No.1. Midland Unit No.1. Quad Cities Unit No. 2. Browns Terry Unit No.1, Turkey Point Unit No. 4 and

, Zion Unit Nos. I and 2.

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IE Bulletin No.78-12A November $4, 1978

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1. Provide all information available on veld materials used for each reactor vessel primary boundary ferritic weldmentd/ (Items Ic, Id, 2s, 2b, fsret sentence of 2c, 3 and 4 of Bulletin 78-12.) This infortation 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 vesscis is not required at this time. (Last sentence of Item 2c,Bulletin 78-12.) However, each id:ensee 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 Ifeensee 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 was given under a blanket clearance specifically for identified generic problems.

'1/ Weld naterial information submitted vill 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 these evaluations.

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i 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 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 i 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 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 78-05 Malfunctioning of 4/14/78 -All Power Reactor

. Circuit Breaker ascilities with an Auxiliary Contact OL or CP

, Mechanism-General Model CR105X 78-06 Defective Cutler- 5/31/78 All Power Reactor

- Eammer, Type M Relays Facilities with an With DC Coils OL or CP

78-07 Protection afforded 6/12/78 All Power Reactor

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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 A eg ww e4, m-We**Am=.e.*A 5 e'M a.-r 6 - as >+m 4 ' " * * * *' " * * *

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

-LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subj ect Date Issued Issued To No.

78-08 Radiation Levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor Tubes Facilities with a Fuel Element 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 Closures

, 78-10 Bergen-Paterson 6/27/78 All BWR Power i Hydraulic Shock Reactor Facil10,es Suppressor Accumulator with an OL or CI' Spring Coils i 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 z Yankee 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure

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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 9

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