ML20050A473

Forwards Draft Responses to Concerns Identified in Matl & Qualification Engineering Branch Draft Ser.Responses Will Be Incorporated in Subsequent Amend to FSAR

ML20050A473
Person / Time
Site:	Perry
Issue date:	03/25/1982
From:	Davidson D CLEVELAND ELECTRIC ILLUMINATING CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8204010329
Download: ML20050A473 (4)

Text

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. 'T . { a ,, jif ,. $i ,, i P o Box 5000 e CLEVELAND, OHIO 44101 e TELEPHONE (216) 622-9800 e ILLUMINATING BLDG e 55 PUBLICSQUARE Dalwyn R. Davidson ing e Best L mi n in the etion VICE PHESIDENT Sv$7E M ENGINE EHiNG AND CONSTRUCTION March 25, 1982 Mr. A. Schwencer Chief, Licensing Branch No. 2 Division of Licensing U. O. IMclear Regulatory Commission j Washington, D. C. 20555 Perry IMelear Power Plant Docket Nos. 50-440; 50-441 Response to Draft SER Materials & Qualifications Engineering Branch

Dear Mr. Schwencer:

This letter and its attachment is submitted to provide draft responses to the concerns identified in the Draft SER for Materials & Qualifications Engineering Branch.

It is our intention to incorporate these responses in a subsequent amendment to our Final Safety Analysis Report.

Very Truly Yours, v? W Dalwyn . Davidson Vice President System Engineering and Construction PRD: mlb W A cc: Jay Silberg p g John Stefano Max Gildner p :C30D E' u}fil$

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k 123.1 'Ib demonstrate compliance with Paragraph III. B. 3, '

l- certify that the calibration schedule for temperature L instruments, drop weight, and Charpy V-notch machines connply with the requirements of Paragraph NB-2360 of the ASME Code. If they are not in compliance, indicate the schedule used and provide a basis for

.- granting an exemption to the exact requirements of NB-2360 of the ASME Code.

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Response

Calibretion of temperature instruments, and Charpy V-notch impact test machines used in impact testing was required in accordance ,

with the requirements of paragraph NB-2360 of the ASME Code.

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123 2 To demonstrate compliance with the requirements of Paragraph IV.A.3 of Appendix G,10 CFR Part 50, certify that all ferritic materials used for reactor coolant pressure boundary piping and valves which are in balance of plant and the nuclear steam supply system meet the requirements of NB-2300 of -

the ASME Code.

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Response

All ferritic materials in the reactor coolant pressure boundary piping and valves in balance of plant and nuclear. steam supply system are Safety Class 1 and are procured in accordance with the material requirements of ASME Section III, Subsection NB-2300. Fracture test data, as applicable, is available and auditable if required.

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7 123 3 To demonstrate the surveillance capsule program complies with Paragraphs II.B' and II.C of Appendir H.

(a) Provide a sketch showing the azilmithal location of each material surveillance capsule.

1. (b) Identify each plate specimen in each capsule

, by heat number and chemical composition, es-pecially copper and phosphorus.

(c) Identify each weld specimen in each capsule by weld wire type and heat, **: .rr type, lot identification, and chemical . 4

[*; ion, especially copper and phosphort 7 (d) Identify the lead factor for each surveillance capsule.

Response

The chemical analyses for the beltline materials are provided in Table 5 3-1. The surveillance specimens were taken from the RPV belglineareaandthesamplecapsulesarelocatedat30, 1 77 and 183 By symmetry the lead factor for each capsule is expected to be the same with respect to the vessel. These values will be-provided in a later amendment.

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