ML20147B163

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

ML20147B163
Person / Time
Site:	05000363
Issue date:	11/24/1978
From:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
References
NUDOCS 7812150160
Download: ML20147B163 (1)

Text

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Docket No. 50-363 2 4 NOV 1973 Jersey Central Power & Light Company ATTN: Mr. I. R. Finfrock, Jr.

Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 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'tM s Bulletin or the actions required by you, please contact this office.

Sincerely,

/9- 5/$ h l$b W s Boyce H. Grier Efirector

Enclosures:

1. IE Bulletin 78-12A

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

M. K. Pastor, Project Manager 7812156 (30

. . UNITED STATES NUCLEAR REGULATORY COMMISS10N OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 IE Bulletin No.78-12A Date: November 24, 1978 Page 1 of 2 ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS 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 weld wire that failed to meet all specified chemical properties in welds of twelve identified reactor pressure vessels. Use of the atypical weld material in vessel weldments causes them to have higher than normal nil-ductility transition tempera-ture characteristics which in turn requires more conservative pressure /

temperature operating limits.

Bulletin 78-12 was issued for the purpose of verifying that similar atypical weld 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 corsuming, and to assure that responses provided are meaningful, the requirements of Bulletin 78-12 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 weld materiall:

1. Provide all information available on weld materialg used for each reactor vessel primary boundary ferritic weldment.' (Items 1c,ld, 2a, 2b, first sentence of 2c, 3 and 4 of Bulletin 78-12.) This in-formation may be provided to NRC through the vessel manufacturers or suppliers as appropriate to prevent duplication of data.

1 The twelve nuclear units identified as having possible atypical pressure vessel weldments 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. 4 and Zion Unit Nos. 1 and 2.

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

IE Bulletin No.78-12A Date: November.24, 1978 Page 2 of 2

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 weld materials information provided to the NRC 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 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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IE Bulletin No.78-12A November 24,1978 Page 1 of 2

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LISTING 0F 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 Operating License (0L) or Construction Permit (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 Gas Mixture Accumula- Reactor Facilities tions Associated with with an OL or CP BWR Offgas System Oper.ations 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 Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR105X 1 78-06 Defective Cutler- 5/31/78

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All Power Reactor l 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 Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees l i

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IE Bulletin No.78-12A November 24, 1978 Page 2 of 2 LISTING 0F IE BULLETINS

. ISSUED IN 1978 Bulletin ' Subject Date Issued Issued To No.

78-08 Radiation Levels from 6/12/78 All Power, Test', and Fuel Element Transfer Research Reactor Tubes Facilities with.an OL having Fuel Element Transfer Tubes.

78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell withanOL(foraction)

Closures or CP (for information).

78-10 Bergen-Paterson 6/27/78 'All 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 with an OL Welds for action: Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vermont Yankee. All other BWR Power Reactor Facilities with an OL for information.

78-12 Atypical Weld Material in S/29/78 All Power Reactor Reactor Pressure Vessel Facilities with an OL or Welds CP 78-13 Failures in Source Heads 10/27/78 All General and Specific of Kay-Ray, Inc. Gauges Licensees with the l Models 7050, 7050B, 7051, Subject Kay-Ray, Inc.

7051B, 7060, 7060B , 7061 Gauges and 7061B i

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