ML20062E223

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

ML20062E223
Person / Time
Site:	Midland
Issue date:	11/24/1978
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 7812050333
Download: ML20062E223 (1)

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.,. *t NUCLEAR REGULATORY COMMISSION REGloN ill f*h M ["" t 799 ROOSEVELT ROAD g .;, . j cten et vn.ittinois sois7 NOV 23 .378 Docket No. 50-329 Docket No. 50-330 Consumers Power Company ATTN: Mr. Stephen H. Howell Vice President 1945 West Parnall Road Jackson, MI 49201 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 pe rmit .

Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.

Sincerely, bf, w James G. Kepp er Director

Enclosures:

1. lE Bulletin 78-12A

2. List of IE Bulletins 1.aued in 1978 cc w/encls:

Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR USIC TIC Ronald Callen, Michigan Public Service Commission Dr. Wayne E. North Myron M. Cherry, Chicago 781205 o 333 e

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

r ATYPICAL VELD MATERIAL IN REACTOR PPISSUPI VESSEL k' ELDS Description of Circumstancest This Bulletin is a supplement to IE Bulletin 78-12, issued on Septecher 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 preperties in velds of twelve identified reactor pressure vessels. Use of the atypical veld material in vessel veldments causes the= to have higher than normal nil-ductility transition tecperature characteristics which in turn requires more censervative pressure / tempera-ture operating limits.

Bulletin 78-12 was issued for the purpose of verifying that similar atypical veld caterial ves not else 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 te assure that responses provided are meaningful, the requirements of Bulletin 78-12 are being codified.

Action Te Be Taken By Licensees and Permit Holders:

,' Tor all power reactor facilities with an operating license or a

. construction permit, except those already identified as possibly having stypical veld caterial.1/

. - The twelve nuclear units identified as having possible atypical

.. pressure vessel veld:ents are: Three Mile Island Unit Nos. I and 2, Crystal River Unit No. 3, Arkans as Nuclear One Unit No.1, Oconee

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

, Zion Unit Nos. I and 2.

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I IE Bulletin No.78-12A , November 24, 1978 1

1. Provide all information available on veld materials,.used for each reactor vessel primary boundary ferritie veldment# (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 i t o'r suppiters as appropriate to prevent duplication of data. ,

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2. _ Correlation of specific heat, lot or s 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

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to verify that the veld materials information provided to the NRC under 7 tem 1 does in fact cover ea'ch 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. R,eports should be submitted to the Director of the appropriate NRC fegional 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 clearancecipecifically for identified generic problems. -

N , s 1/ Weld material 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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IE Bulletin No.78-12A Date: November 24, 1978

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

78-01 Flammable Contact - 1/16/78 All Power Reactor Arn 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 '

r 78-03 Potential Explosive 2/8/78 All BWR Power Gas Mixture Accu =ula- Reactor Facilities tions Associated with with an OL or CP BWR Offgas System g Operations t

78-04 Environcental 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 til Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanis=-General i Model CR105X I

78-06 Defective Cutler- 5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an i With DC Coils- OL or CP 1 h 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 %dth an OL,

• and all Friority 1 .

Material Licensees l

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

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! Bulletin Subj ect Date Issued Issued To No.

78-08 Radiation Levels from 6/12/78 All Power and l

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 i Paths Associated with Reactor Facilities

! Inadequate Drywell with an OL or CP l Closures 78-10 Bergen-Pa tersen 6/27/78 All BWR Power Hydraulic Shock Suppressor Accumulator Reactor Facilities Spring Coils with an OL or CP 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., Cauges Specific Licensees Models 7050, 70503, 7051 with Ray-Ray Gauges 70513, 7060, 70603, 7061 and 7061B Enclosure 1 Page 2 of 2 i

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