ML20147E480

Forwards IE Bulletin 78-12 Atypical Weld Matl in Reactor Pressure Vessel Welds Requesting Action in 60 Days.List Bulletins Issued in 1978 Encl

ML20147E480
Person / Time
Site:	Seabrook
Issue date:	09/29/1978
From:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Tallman W PUBLIC SERVICE CO. OF NEW HAMPSHIRE
References
IEB-78-12, NUDOCS 7810160257
Download: ML20147E480 (6)

Text

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W pa n'Puq UNITED STATES g, g NUCLEAR REGULATORY COMMISSION REGION I f-'3

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September 29, 1978

. Docket Nos. 50-443 50-444 ,

Public Service Company of New Hampshire ATTN: Mr. W.-C. Tallman President 1000 Elm Street Manchester, New Hampshire 03105 Gentlemen:

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Enclosed is 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, with specified exceptions.

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

Sincerely, hff oyce H. Grier

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Director -

Enclosures:

1. IE Bulletin No. 78-12 '

2. List of IE Bulletins -

Issued in 1978 cc w/encis:

John D. Haseltine, Project Manager 3

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. UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 IE Bulletin No. 78-12 Date: September 29, 1978 Page 1 of 3 ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:

On August 4,1978, the NRC was informed by the Duke Power Company and the Babcock and Wilcox Company (B&W) that the weld wire used in some of the reactor vessel welds in Oconee Unit No. 3 may have differed from that specified. A chemical analysis of one sample of archive material by B&W disclosed that the nickel content was measured to be 0.1 percent (versus 0.45 to 0.8 percent nominal specified) and the silicon content was measured to be 1.0 percent (versus 0.3 to 0.6 percent nominal specified).

The heat of weld metal in question was supplied by the Page Company, a Division of the American Chain & Cable Co., Bowling Green, Kentucky to B&W, the manufacturer of the Oconee Unit No. 3 vessel. Further checks by B&W of its records have identified eleven additional vessels in which the incorrect weld material may have been used. Owners of these vessels have been notified.

The NRC staff has made a determination of the possible effects on reactor vessel integrity of the use, or possible use, of the improper weld ma terial . Weldments containing the atypical material are likely to have higher than normal nil-ductility transition temperature characteristics.

Therefore to maintain reactor vessel safety margins, implementation of new conservative pressure / temperature operating limits may be required.

While the specific problem has been identified as possibly affecting twelve vessels manufactured by B&W, it is not possible to conclude in the absence of specific information that similar atypical weld material was not also supplied to other vessel manufacturers and used in reactor pressure vessel fabrication.

Action To Be Taken By Licensees and Permit Holders: "

For all power reactor facilities with an operating license or a construction permit, eycept those already identified as possibly having atypical weld materiali:

1 The twelve nuclear units identified as having possible atypical pressure vessel weldments are: Three Mile Island Unit Nos. 7 and 2, Crystal River Unit No. 3, Arkansas Nuclear One Unit No.1, Oconee Unit No. 3. Rancho Seco Unit No.1, Midiand 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.

IE Bulletin No. 78-12 September 29, 1978 Page 2 of 3

1. Conduct a record search 2 of all primary reactor pressure vessel weldments (excluding partial penetration welds) and submit the following information4:

a. The principal vessel manufacturer. If other manufacturers were utilized, identify those companies and the weldments completed by those firms.

b. The type and form of weld materials and the identifying heat ,

and lot numbers used in each weldment.

c. The weld material manufacturer (s) and the types and form of materials supplied.

d. The specified properties of the weld materials and the completed weldments (Chemistry, tensile and impact properties, as appropriate).

2. Describe the procedures utilized during fabrication to verify conformance to the specifications. Specifically provide the following:

a. Describe the type, number and dates of tests performed on welding materials to satisfy the material conformance testing requirements for each heat, lot or combination of heat and batch, etc., of welding materials used in the construction or repair of the reactor pressure vessel in your facility. Indicate whether each heat, lot or batch subdivision (coil or spool) was tested and the extent of such testing, i.e., were both ends of a coil or spool of wire tested for each sub-arc flux-wire combination or heat-flux batch combination.

b. Describe the type, number and dates of other tests such as procedure qualification, welder performance tests, in-process checks on post-weld tests which were performed.

n 4 The record search may be performed by the vessel manufacturer and the requested information reviewed as appropriate by each licensee prior to forwarding to the NRC. It is not the intent of this Bulletin to require each licensee to individually examine manufacturing records of a generic

, nature. Records of nonconforming conditions that may be identified by the manufacturer and are uniauely applicable to a specific vessel should however be carefully examined by the owner.

3 Some of the information requested by this Bulletin may have been f

previously supplied to the NRC under the Surveillance Program.

Information previously submitted may be referenced in lieu of resubmittal.

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w_________ ._

IE Bulletin No. 78-12 September 29, 1978 Page 3 of 3

c. For each of the tests described in 2(a) and 2(b) above, describe the parameters of each test and provide the results obtained. Identify the applicability to specific weldments by correlation of heat, lot or batch as appropriate.

3. Identify those cases of weld filler material which did not meet procurement specifications based on verification tests, i.e.

mechanical or chemical properties. Describe the disposition action taken or the acceptance basis for utilization in vessel fabrication. In such cases, discuss the effect that the atypical weld composition has on the fracture toughness of the weld metal.

4. Provide information on the availability of archive weld materials which might be used for verification purposes.

5. Please provide your response in writing within 60 days. 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 //31/80. Approval was given under a blanket clearance specifically for identified generic probl ems ,

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IE Bulletin No. 78-12 l

September 29, 1978 Page 1 of 2 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 -

-0L 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 i

BWR Offgas System Operations 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 78-06 Defective Cutler- 5/31/78 All Power Reactor Facilities with an

~

Hammer, Type M Relays 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

IE Bulletin No. 78-12 September 29, 1978 Page 2 of 2 LISTING OF 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 with an OL (for action)

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 Facilitics with an OL for information.

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