ML18018A528

Forwards Response to Draft SER Open Item 59 Re Containment Sys.Reactor Cavity Subcompartment Analysis Conservative

ML18018A528
Person / Time
Site:	Harris
Issue date:	05/11/1983
From:	Mcduffie M CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
LAP-830135, NUDOCS 8305160017
Download: ML18018A528 (5)

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@MD, Carolina Power & Light Company MAY 11 1983 SERIAL:

LAP 83-135 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS ~

1 AND 2 DOCKET NOS. 50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSES CONTAINMENT SYSTEMS BRANCH

Dear Mr. Denton:

Carolina Power

& Light Company hereby transmits one original and forty copies of the response to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER)

Open Item No. 59.

Carolina Power @Light Company will be providing responses to other Open Items in the DSER shortly.

Yours very truly, PS/kj r (6729PSA)

Attachment M. A. McDuffie Senior Vice President Engineering

& Construction CC:

Mr. Yun-Seng Huang (NRC-CSB)

Mr. N. Prasad Kadambi (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Mr. J.

P. O'Reilly (NRC-RII)

Mr. Travis Payne (KUDZU)

Mr. Daniel F.

Read (CHANGE/ELP)

Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Ms. Patricia T. Newman Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB)

Dr. J.

H. Carpenter (ASLB)

Mr. J. L. Kelley (ASLB) 8305ihOOi7 8305ii PDR ADDCK 05000400 E

PDR goo'11 Fayettevllle Street o P. O. Box 1551 I Raleigh, N. C. 27602

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OPEN ITEM 059:

Acceptance of the design-basis pipe break for the reactor cavity subcompartment analysis is contingent on acceptance of the mechanically constrained limit on the postulated cold leg or hot leg pipe rupture size and flow area (150 in. ).

(SEC:

6.2.1.2)

RESPONSE

TO OPEN ITEM 059:

Westinghouse assumed a

150 in.

rupture area when analyzing for asymmetric 2

loads in the reactor cavity.

Using this area as the maximum allowable break

area, Ebasco designed the reactor vessel hot and cold leg restraints.

Westinghouse,

then, using geometric parameters from the restraints calculated the actual rupture areas of approximately 32 in.

for the hot leg and 90 2

2 in.

for the cold leg.

Since these areas are enveloped by the assumed 150 2

in.

break area the reactor cavity subcompartment analysis is conservative.