ML20062E139

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

ML20062E139
Person / Time
Site:	Summer
Issue date:	11/24/1978
From:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Mary Johnson SOUTH CAROLINA ELECTRIC & GAS CO.
References
NUDOCS 7812040318
Download: ML20062E139 (1)

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..770 In Reply Refer To:

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,y South Carolina Electric and Gas Company Attn: Mr. M. C. Johnson, Vice President

~I and Group Executive - Special Services and Purchasing P. O. Box 764 Columbia, South Carolina 29218 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 facility (ies) 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, g f.c%10-mes P. O'Reilly D rector G ..

Enclosures:

l. IE Bulletin 78-12A

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

H. I. Donnelly, Jr.

Quality Assurance P. O. Box 8 Jenkinsville, South Carolina 29065 T. B. Conners, Jr.

Conners, Moore and Corber 1747 Pennsylvania Avenue, N. W.

Washington, D. C. 20006

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UNITED STATES NUCLEAR REGULATORY COMMISSION N. OFFICE OF INSPECTION AND ENFORCEMENT

,h WASHINGTON, D.C. 20555 November 2h, 1978

. ?h IE Bulletin No.78-12A a.

F '., ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS 32

'fa 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 veld 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 them to have higher than normal nil-ductility transition temperature characteristics which in turn requires more conservative pressure / tempera-

.. 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 to assure that responses provided are meaningful, the requirements of Bulletin 7%12 are being modified.

Action To Be Taken By Licensees and Permit Holders:

For all power reactor facilities with an operating license or a construction permit, except those already identified as possibly having atypical veld materia 11:

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1 The 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 Nuclear 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. h and Zion Unit Nos. I and 2.

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IE Bulletin No.78-12A November 2h, 1978 4

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%; , 1. Provide all information available on veld materials used for each

. ,, reactor vessel primary boundary ferritic weldment,.2 (Items 1c, ld,

- - ' 2a, 2b, first sentence of 2c, 3 and b of Bulletin 78-12. ) This information may be provided to IEC through the vessel manufacturers

- , - or suppliers as appropriate to prevent duplication of data.

7. p ' 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 IEC 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 0 120 d vs of the date of this nu11etin urr1ement. Report be submitted to the Director of the appropriate NRC Regional hou1d Office and a copy should be forwarded to the U.S. Nuclear Regulatory Caramission, 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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Weld =aterial information submitted vill be evaluated by NRC. Requests f4 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 2h, 1978 c .;

>d a~ LISTING OF IE BULLETIUS

' 4 ISSUED IN 1978 7..

- i Bulletin Subject Date Issued Issued To f; 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 b'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 Operations t

78-Oh Environmental Quali- 2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit OL er CP Switches Inside Reactor Containment 78-05 Malfunctioning of h/1h/78 All Power Reactor Circuit Breaker Facilities with an j Auxiliary Cuntact OL or CP 14echanism-General Model CR105X 78-06 Defective cutler- 5/31/78 All Power Reactor Hammer, Type M Relays Facilities vith an With DC Coils OL or CP 78-07 Protection afforded 6/12/78 All Power Resctor 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 i

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, 6 IE Bulletin No. 78 12A Date: November 2k, 1978 LISTING OF IE BULLETINS ISSUED In 1978

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1 Bulletin Subject Date Issued Issued To

' No.

,. 78-08 Radiation Levels from 6/12/78 All Power and Fuel Element Transfer Research T'eactor Tubes Facilitio Lth a Fuel Eleme...

transfer tu'oe and an OL.

BWR Dryvell Leakage 6/lk/78 All BWR Power 78-09 Paths Associated with Reactor Facilities Inadequate Dryvell -

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 Examination of Mark I 7/21/78 BWR Power Reactor 4l 78-21 Facilities for

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Containment Torus Welds action: Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-I cello and Vermont

' Yankee O 7 12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an yessel Welds OL or CP 8-13 Failures in Source Heads 10/27/78 All General and of Yg -Ray, Inc., Gauges - Specific Licensees Models 7050, 7050B, 7051 with Kay-Ray Gauges 7051B, 7060, 7060B, 7061 and 7061B Enclosure '.

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