ML20062K563

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Submits Addl Info Requested in Re Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports.Mill Test Repts on Grade of ASTM A-283 Used for Lugs Not Available
ML20062K563
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/16/1980
From: Trimble D
ARKANSAS POWER & LIGHT CO.
To: Novak T
Office of Nuclear Reactor Regulation
References
2-120-19, NUDOCS 8012230200
Download: ML20062K563 (7)
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ARKANSAS POWER & LIGHT COMPANY

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POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 L..

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December 16, 1980 M

E to 2-120-19 Mr Thomas H. Novak Assistant Director for Operating Reactors Division of Licensing U. S. Nuclear Regulatory Comm.

Washington, D.C.

20555

SUBJECT:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Fracture Toughness of the Steam Generator and Reactor Coolant Pump Supports (File: 2-1510)

Gentlemen:

As committed in our letter of August 19, 1980, the following infonnation is provided to respond to item 1 subtopics 1, 2, 3 and 4 and item 3, subtopic C, of your letter of August 5,1980.

To address item 1 General Electric Co. (GE), the RCP motor manufacturer was contacted and asked to respond to subtopics 1, 2 and 3.

The following, which incorporates GE input, is provided 'as our response to Item 1.

ITEM 1 SUBTOPIC 1)

Identify the grade of the ASTM A-283 used for these lugs.

Provide the mill test report for these members.

Indicate supplementary material requirements (if any) specified for these members. Provide any other available data that may be indicative of fracture toughness.

RESPONSE

To date we have been unable to obtain any additional information beyond that which is already available to the Franklin Research Center (FRC) and which further identifies the grade of ASTM A-283 steel used. The mill test reports were not available to f~

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Mr. Thomas H. Novak December 16, 1980 GE and to date have not been found in AP&L's, or CE's, files.

We will continue to search for this information and will inform the NRC of any additional information identified.

ITEM 1 SUBTOPIC 2)

Indicate how the final rolling dir'ection of the plate from which the lugs were cut is related to the direction of principal stress imposed by the snubber mechanism.

RESPONSE

This information is not available.

i.

ITEM 1 SUBTOPIC 3)

Provide geometric details of the seismic lug and of the welding attachment of the RCP motor case.

RESPONSE

This information is available in GE drawings pertaining to the RCP motor. We are in the process of obtaining these drawings and will forward them to you as soon as they are available. We anticipate submittal within approximately 3 to 4 weeks.

In GE's response to this question, they stated that there were no welds., A further explanation of this will be provided by the drawings.

ITEM 1 SUBTOPIC 4)

Provide a fracture-toughness evaluation of the lug most highly stressed in tension under the most severe loading any lug experiences.

RESPONSE

)

To date we have not obtained sufficient information on the RCP motor lug material to perform an adequate fracture i

toughness evaluation. We will continue to research this matter and will provide the NRC with updates of our progress as appropriate.

To address item 3 subtopic C, Byron Jackson, the RCP manufacturer,.was contacted and requested to respond to subtopic C.

The following, which incorporates Byron Jackson's input, is provided as our response l

- to item 3 subtopic C.

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Mr. Thomas H. Novak December 16, 1980 ITEM 3 SUBTOPIC C)

Byron Jackson Dwg. ZF-1442, Revision 6 (Vertical Reactor Coolant Pump) welds joining lugs 1, 2, 3, 4 on pump Nos.

2P32A and 2P32D.

Also joining of seismic lugs on RCP (details on drawings provided unfortunately were not clear).

Please furnish the following information:

a) Welding process (es) used for these joints.

b) Electrode types, diameters, or other con-sumable welding materials (such as fluxes, if applicable) used.

c) Welding conditions used.

d) The sequences of welding passes used.

e) Were any of the weldments given a post-weld heat treatment?

If so, what were the time and temperatures used? How were the tempera-tures monitored?

f) Were the welds inspected during fabrication?

^

What techniques were used? Have subsequent weld inspections been made? When and with what results?

RESPONSE

Attached is Byron Jackson's response which is-currently all of the infonnation available to us. We feel this information should be adequate for the purpose of your evaluation.

However, should additional information pertaining to the RCP lugs become available we will provide it to you.

Very truly yours, David C. Trimble Manager, Licensing DCT:DEJ:1p r

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