ML031530413

E-mail from S. Long to W. Cullen, Regarding NRC Questions on Safety Significance Assessment. Partially Deleted

ML031530413
Person / Time
Site:	Davis Besse
Issue date:	05/23/2002
From:	Long S Office of Nuclear Reactor Regulation
To:	Cullen W Office of Nuclear Regulatory Research
References
FOIA/PA-2003-0018
Download: ML031530413 (3)

Text

Re: NRC Questions on Safety Significance Assessment (SSA)

age1 I Steven Long q c-William Cullen f

5/23/02 11:43AM Fwd: Re: NRC Questions on Safety Significance Assessment (SSA)

Ii Bill William H. Cullen, Jr.

Materials Engineering Branch Office of Nuclear Regulatory Research Mail Stop: T-10 E10 Ph: 301 - 415 - 6754 FAX: 301 - 415 - 5151 whc@nrc.gov

>>> Douglas Pickett 05/23/02 09:51AM >>>

Steve Long -

Wally Norris -

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iJ C-5/23102 9:48AM Re: NRC Questions on Safety Significance Assessment (SSA)

Doug-My understanding was the contractor's calculations were not "final" at this stage since there was to be a conference call between us to discuss assumptions, inputs, etc. If it turns out you can send us the calculations by the contractors but these would be made publicly available without appropriate input or assumptions having been used, we will want to discuss this before you release any of these to us. After you find out their availability, please call me and we can discuss.

Thanks.

-Dale Wuokko "Douglas Pickett" To:

<drwuokko@firstenergycorp.com>

<DVP1@nrc.gov>

cc:

<Michael_k._leisure@firstenergycorp.com>

Subject:

Re: NRC Questions on Safety Significance Assessment 0512312002 (SSA) 08:36 AM Dale -

Thanks for your response. I've issued an all-points-bulletin for someone who can respond to item 1 D of the RAI and whether our contractor's calculations can be made available to you (and I assume this means they will be made publicly available).

Doug

>>> <drwuokko@firstenergycorp.com> 05/23/02 08:19AM >>>

Doug-We have two sets of questions from the NRC staff regarding the April 8, 2002 SSA: 1) Five questions that Region IlIl provided under coverletter faxed on May 6, and 2) eight questions that were e-mailed by NRR and Research on May 15, 2002.

We expect to be able to provide a response to the five questions from Region IlIl by June 7, except for "1.d". Question "1.d" requests we provide the estimated areas of exposed clad material that would cause the cladding to fail at normal operating pressure for clad thicknesses of 0.297" and 0.125". The April 8 SSA considered a fixed exposed clad area with cladding thicknesses cases of 0.297" and 0.240" to determine the maximum pressure carrying capability. The 0.240" value was the minimum cladding thickness A)- u-~__t

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In order to respond to NRC question "1.d" we need to obtain from the NRC staff the assumption for the exposed cladding expansion shape; i.e., is it assumed the exposed cladding shape expands uniformly in each direction from the present triangular-like shape, expands in a circular shape, etc. Once this is firmed up with the NRC staff, it will take approximately three weeks to have the results at Davis-Besse.

49-Regarding the questions from NRR and Research, these will be responded to after the above Region IlIl questions have been answered (except for question 1.d). If possible, we would like a copy of the NRC staff contractor's calculations for comparison against our April 8 SSA submittal that included the calculations supporting our SSA.

Thanks.

-Dale Wuokko CC:

<tsswim@firstenergycorp.com>, <dhockwood@firstenergycorp.com>,

<spfrantz@firstenergycorp.com>, <meoreilly@firstenergycorp.com>, <mkeisureefirstenergycorp.com>

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