ML070530567
| ML070530567 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 11/07/2006 |
| From: | Becker L State of VT |
| To: | James Shea Plant Licensing Branch III-2 |
| References | |
| Download: ML070530567 (6) | |
Text
I James Shea - Seismic and Flood Questions from ANR Page 11 1I Page I James Shea Seismic and Flood Questions from ANR From: "Becker, Laurence" <Laurence.Becker@state.vt.us>
To: "James Shea" <JJS@nrc.gov>
Date: 11/0712006 3:31:06 PM
Subject:
Seismic and Flood Questions from ANR To: James Shea - Please see attached two separate memos that contain questions concerning Seismic and Flood issues at Vermont Yankee.
Thank you for following up and your attention to these matters.
Looking forward to your reply.
Sincerely, Larry Becker Please note new e-mail - laurence.becker@state.vt.us Laurence R. Becker Vermont State Geologist and Director Vermont Geological Survey/Division of Geology and Mineral Resources Vt. Dept. of Environmental Conservation 103 South Main Street Waterbury, VT 05671-2420 Phone - (802) 241-3496 Fax - (802) 241-4585 Web - http:/Awww.anr.state.vt.us/dec/geo/vgs.htm
--- Original Message---
From: James Shea [1]
Sent: Monday, October 23, 2006 4:18 PM To: Becker, Laurence Cc: David Pelton; Hosung Ahn; Richard Laufer; Raymond Powell; Richard Emch; Rebecca Karas; Tracy Walker
Subject:
Your questions concerning VY Seismic design and flooding Laurence R. Becker, State Geologist & Director Division of Geology & Mineral Resources, VT Geological Survey and Radioative Waste Management Program State of Vermont.
Larry, As we discussed today on the phone please send me your questions concerning the VY Seismic and Flooding Design and we will get answers back to you as soon as we can. Thanks!
James Shea, PM NRRIDORL/LPLI-1 U.S. Nuclear Regulatory Commission Mail Stop #: O-8C2 Phone #: 301-415-1388 E-Mail jjs@nrc.gov CC: "David Pelton" <DLP1@nrc.gov>, "Hosung Ahn" <HXA1@nrc.gov>, "Richard Laufer"
<RJL@nrc.gov>, "Raymond Powell" <RJP@nrc.gov>, "Richard Emch" <RLE@nrc.gov>, "Rebecca Karas"
<RLK@nrc.gov>, "Tracy Walker" <TEW@nrc.gov>, "Gjessing, Catherine"
<Catherine.Gjessing@state.vt.us>, "Cahoon, Barry" <Barry.Cahoon@state.vt.us>
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Subject:
Seismic and Flood Questions from ANR Creation Date 11/07/2006 3:30:31 PM From: "Becker, Laurence" <Laurence.Beckerastate.vt.us>
Created By: Laurence.Becker(&state.vt.us Recipients nrc.gov TWGWPO02.HQGWDOO1 JJS (James Shea) nrc.gov kplpo.KP -DO DLP1 CC (David Pelton)
RJP CC (Raymond Powell)
TEW CC (Tracy Walker) nrc.gov OWGWPOO2.HQGWDOO1 HXA1 CC (Hosung Ahn)
RLE CC (Richard Emch) nrc.gov TWGWPOOI .HQGWDOO1 RJL CC (Richard Laufer) nrc.gov OWGWPO04.HQGWDO01 RLK CC (Rebecca Karas) state.vt.us Barry.Cahoon CC (Barry Cahoon)
Catherine.Gjessing CC (Catherine Gjessing)
Post Office Route TWGWPO02.HQGWDO01 nrc.gov kpl_po.KPDO nrc.gov OWGWPO02.HQGWDOO01 nrc.gov TWGWPOO1.HQGWDOO1 nrc.gov OWGWPO04.HQGWDO01 nrc.gov state.vt.us
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..... emp\GW }OO Files Size Date & Time MESSAGE 1397 11/07/2006 3:30:31 PM NRC Questions (4) Flood.doc 24576 NRC Questions Seismic.doc 28672 Mime.822 77023 Options Expiration Date: None Priority: Standard ReplyRequested: No Return Notification: None Concealed
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Page 1 James Shea - NRC Questions (4)
James -
Flood.doc (4)Flood.doc; Page 11 Agency of Natural Resources Department of Environmental Conservation MEMORANDUM Date: November 8, 2006
Subject:
Entergy-Vermont Yankee - Flood Questions The purpose of this memorandum is to set forth a brief outline of ANR questions regarding flood issues and the Entergy Vermont Yankee Nuclear Power Plant.
" The Design Basis for External Events (DB) relating to floods is a Probable Maximum Flood (PMF) of 480,100 cfs. How was this PMF calculated? What assumptions were made to calculate the PMF for this plant? What NRC standards and/or methodologies were used to arrive at this PMF?
- Does the DB analysis for External Events consider the impacts of inundation related to changes in the river channel including sedimentation, debris deposition and catastrophic erosion potential? If not, why not?
" What is the proper standard of design basis protection for extending the license of a nuclear power plant?
" Has NRC evaluated whether the age and current physical condition of the facility make it any more susceptible to External Events, including Design Basis External Events, such as, Flood and Earthquake?
I James Shea - NRC Questions Seismic.doc Page I I Agency of Natural Resources Department of Environmental Conservation MEMORANDUM Date: November 8, 2006
Subject:
Entergy-Vermont Yankee - Seismic Questions The purpose of this memorandum is to set forth a brief outline of ANR questions regarding seismic issues and the Entergy Vermont Yankee Nuclear Power Plant.
VY received a license to operate in 1972 and is designed for operation to conform to Atomic Energy Commission requirements of April 1968. The maximum ground accelerations at the site are specified as a 0. 14g (14% of the acceleration of gravity) Safe Shutdown Earthquake (SSE) and a 0.07g (7% of the acceleration of gravity) Operating Basis Earthquake (OBE).
- What return interval, spectra, and accelerations were employed to predict shaking at the site?
- How were these calculations used to determine accelerations as a percent of gravity for an Operating Basis Earthquake (OBE) and the Safe Shutdown Earthquake (SSE)? Please show the calculations for both the OBE and SSE determinations. From the above calculations how were the OBE and SSE established for the design basis? Please be specific about the NRC criteria used to establish these design basis parameters.
- In the late 1990's, the core shroud repair design utilized a USNRC Regulatory Guide 1.60 rev. 1 (1973) response spectrum input for the repair seismic analysis. How does the overall 1973 guidance compare with the late 1960's design basis criteria? If there is a difference, please be specific about the difference? If there is a difference are the 1973 criteria going to be applied to the design basis analysis for re-licensing?
0 On June 28, 1991, NRC issued Generic Letter 88-20, Supplement 4, "Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities, 10 CFR 50.54(f), and NUREG-1407, "Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities. A Seismic Margins Assessment (SMA) was conducted at Vermont Yankee subsequent to these NRC releases also in conjunction with document EPRI NP-6041 guidance. ANR understands that the guidance employed a 0.30g review level earthquake for the plant examination. How does this 0.30g review level compare to the 0.14g SSE level? If this is a higher standard is it going to be employed in the design basis review for re-licensing?
- What is the proper standard of design basis protection for extending the license of a nuclear power plant?
9 Has NRC evaluated whether the age and current physical condition of the facility make it any more susceptible to External Events, including Design Basis External Events, such
I James Shea - NRC Questions Seismic.doc Page 2 1 as, Earthquake and Flood?