ML20027A275

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Responds to IE Bulletin 78-12 Re Atypical Weld Matl in Reactor Pressure Vessel Welds.Vessels in Subj Facil Antedate the Atypical Matl,So the Matter Does Not Apply
ML20027A275
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 10/26/1978
From: Burstein S
WISCONSIN ELECTRIC POWER CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 7811070374
Download: ML20027A275 (6)


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Wisconsin Electncmveacower 231 WEST MICHIGAN, MILWAUKEE. WISCONSIN si201 jf October 26. 1978 Mr. J. G. Keppler, Director Office of Inspection and Enfcrcement, Region III U. S. NUCLEAR REGULATORY COMMISSION

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799 Roosevelt Road Glen Ellyn, Illinois 60137

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Dear Mr. Keppler:

DOCKET NOS. 50-266 AND 50-301

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REACTOR VESSEL \\WELDMENT INFORMATION POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Your letter of September 29, 1978, transmitted IE Bulletin No. 78-12 for our information and action.

This bulletin is entitled " Atypical Weld Material In Reactor Pressure Vessel Welds" and requested that we supply certain information concerning the fabrication of the reactor vessel full penetration welds.

As you are aware, the Point Beach reactor vessels are older vessels and 1

were fabricated at a time when the technology in respect to fracture toughness of materials had not been extensively developed.

10 CFR 50, Appendix G and its associated requirements, a fracture taughne tion of the welds in the Point Beach reactor vessels has been perfonned and the results reported to the NRC in my letter of March 4,1977.

In addition, we have periodically advised the NRC of the results of our reactor vessel material wrveillance capsule test program whenever a capsule has been withdrawn and tested.

As no " atypical" weldment information has developed during the course of these programs for the Point Beach reactor vessels, we do not consider all of the actions required by Bulletin 78-12 to be applicable to the Point Beach reactor vessels.

l The attachment to this letter supplies the requested information, to the extent available, which has not been reported previously for the Point Beach reactor vessels.

Please contact us if additional information is required.

Very truly yours, W

1 Sol Burstein

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xe tive Vice Presi en l

Attachment USHRC, Office of Inspection and Enforcement, cc:

Division of Reactor Construction Inspection 4

Washington, D.C.

20555 yT 0 Eis 78110W379 Q

d ATTACHMENT TO LETTER RESPONDING

_TO NRC BULLETIN IE 78-12 POINT BEACH NUCLEAR PLAN'T in the subject bulletin asThe purpose of this attachment is to respond to the informa deemed to apply to the Point Beach reactor J\\ ;'

it is vessels.

The questions have been paraphrased but are kept in the same order as presented in the bulletin.

1.

Conduct a record search and submit information identifying the vessel manufacturer (s), the type and form of weld materials and manufacturers, and the specified properties of the weld materials.

RESPONSE

The Unit 1 reactor vessel and part of the Unit 2 vessel was fabricated by the Babcock & Wilcox Company.

The Unit 2 vessel fabrication was completed by Combustion Engineering, Inc.

Weld materials information is presented in references l'and 2.

In addition to the information contained in these references, the following information is presented for the reactor vessel welds:

Weld Wire Flux Weld Location Type Heat No.

Type Lot No.

Unit 1:

Inter. Shell to Mn-Mo-Ni 71249 LINDE 80 8445 Lower Shell Circle Seam Inter. Shell Mn-Mo-Ni 1P0815 LINDE 80 8350 Long. Seams Mn-Mo-Ni IP0661 LINDE 80 8304

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Lower Shell Mn-Mo-Ni 61782 LINDE 80 8350 Long. Seams Surveillance Weldment Mn-Mo-Ni 72445 LINDE 80 8504 Unit 2:

i Inter to Lower Mn-Mo-Ni 72442 LINDE 80 8579 Shell Circle Seam Surveillance Weld Mn-Mo-Ni -

406L44 LINDE 80 8773 i

2.

the specifications. Describe the procedures utilized during fabrication to ve welding procedure qualification testing, welder performanc

_ RESPONSE:

Both reactor vessels are ASME Class A vessels.Fabrication was (ompleted in 1968 for Unit 1 and 1970 for Unit 2.

The Unit 1 vessel was desi!ned and fabricated to the requirements of the 1965 Edition of Section III of the ASM I

i Code.

The comparable document for the Unit 2 vessel was the 1968 Edition i

with Addenda including the Winter 1968 Addenda.

The procedures and require-ments of these documents would have been applicable to the materials and C) fabrication Processes used durins construction of the reactor ve 3.'

Identify those cases of weld filler material which did not meet procurement specificatior.s based on verification tests, etc.

RESPONSE

t Our records are not known to contain any discrepancies of this nature.

Obviously, if the material nonconformance was identified then the material i

would not have been used.

The subsequent disposal of the material is of j

no concern to the actual reactor vessel weldments.

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Provide information on the availabilit y

might be used for verification purpose.

rchive weld materials which

RESPONSE

i In early 1976, the available PBNP reactor vessel archive material was i

obtained from Westinghouse Electric Corporation and shipped to the Point Beach Nuclear Plant where it now resides.

Figures 1 and 2 attached show the shape and size of the available pieces of material for Units 1 and 2 1

respectively.

The numbers on the sketches relate the material to the X

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respective vessel plate or forging material.

. ith respect to weldments, l

W only one piece for the Unit 2 vessel is available; no pieces exist for Unit 1.

References:

1.

Letter of Mr. S. Burstein to Mr. E. Case, Attn. Mr. G. Lear, " Docket Nos.

50-266 and 50-301, Reactor Vessel Materials Information, Point Beach Nuclear Plant, Units 1 and 2", July 18, 1977.

2.

Letter of Mr. S. Burstein to Mr. B. Rusche, Attn. Mr. G. Lear, " Docket Nos.

50-266 and 50-301, Reactor Vessel Fracture Toughness, Point Beach Nuclear l

Plant, Unit Nos. 1 and 2", March 4, 1977.

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