ML12053A403
| ML12053A403 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/14/2011 |
| From: | Seung Min Division of License Renewal |
| To: | James Medoff, Bo Pham, On Yee, Ching Ng Division of License Renewal |
| References | |
| FOIA/PA-2011-0357 RG-1.167 | |
| Download: ML12053A403 (7) | |
Text
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Craver, Patti From:
Mi Seung Sent:
Wednesday, September 14, 2011 12:29 PM To:
Pham, Bo; Medoff, James; Yee, On; Ng, Ching
Subject:
RE: Questions/Issues related to North Anna Seismic Event Attachments:
RG 1.167 ML003740093.pdf Good Afternoon, RG 1.167, Regulatory Position 1.2 addresses fatigue analysis for ASME Code Class 1 components and systems. I am wondering if activities per this position have been completed.
- Thanks, Seung Min C. REGULATORY POSrlION After a phas bnm sWd at d ywsb m
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OCX ad fth 1 45m evaluatl ta t are specified in Section 63, with sh excqiospec d bow, a cepftable to e NRC stafffssfygthe reqime ns Is PM-puph wV(Ix3) of Appeodi S to 10 CFR Put 50.
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OF DII NP-4M9 LI Item (1) dsel ted&-
If the cWallated stresme frm the ac seis-mIckxobSh cnmdiioas e he udms de alow-able for emacy coadntokm (*4., ASME Code Levl C Sevce Umits or eqivale) or adgima design buss, the item Ib cnsdere pt pvid the reauts otfpeciom ad tet (8eo1n S3&2) drow so dam e.
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ss a toe adtU of the item Tho evaduios shosul addrs a&l to.
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- 2. LONG-TEM EVALUATONS Concdetwith tae longerm e~vaato, the
-1 should be restoreiid to its curent liening basi.
fcptiom to d. mu be ap*poved by th Dircto, Office of Nuclea Rackir Rgaal.
From: Pham, Bo Sent: Wednesday,'September 14, 2011 12:20 PM To: Medoff, James; Fu, Bart; Homiack, Matthew; Sakai, Stacie; Brittner, Donald; Kalikian, Roger; Yee, On; Ng, Ching; Min, Seung
Subject:
Fw: Questions/Issues related to North Anna Seismic Event Importance: High
- RARB, While the event at North Anna may seem to be only affecting the structural aspexts of the facility, please let Jim know today if there are other technical concerns within our purview that should be considered.
NRR is responsible for the decision to let NA restart post-earthquake. We need to do our best to inform NRR of all relevant issues that should be vetted before allowing them to start back up.
Thanks.
Sent from NRC blackberry Bo Pham From: Khanna, Meena To: Mendiola, Anthony; L.~es, Anthony; Casto, Greg; Dennig, Robert; Bailey, Stewart; Taylor, Robert; Lupold, Timothy; Mitchell, Matthew; McMurtray, Anthony; Wilson, George; Murphy, Martin; Mathew, Roy; Tate, Travis; Martin, Robert; Harrison, Donnie; Circle, Jeff; Klein, Alex; Pham, Bo; Auluck, Rajender; Pelton, David; Kulesa, Gloria; Manoly, Kamal; Miranda, Samuel; Mitman, Jeffrey; Karipineni, Nageswara; Rahn, David; McConnell, Matthew; Goel, Vijay; Sahay, Prem; Som, Swagata; Scales, Kerby; Matharu, Gurcharan; Laur, Steven; Snodderly, Michael; Sheikh, Abdul; Bedi, Gurjendra; Lin, Bruce; Franke, Mark; McCoy, Gerald; Boyle, Patrick; Martin, Robert; Kulesa, Gloria Cc: Hiland, Patrick; Howe, Allen; Galloway, Melanie; Lubinski, John; Wilson, George; Lee, Samson; Evans, Michele; Giitter, Joseph; Farzam, Farhad Sent: Wed Sep 14 12:13:55 2011
Subject:
Questions/Issues related to North Anna Seismic Event
- All, PIs note that the licensee has indicated that they plan to submit their restart document to us this Friday.
Having said that, we'd like to request that all technical BCs, as applicable, identify any high priority questions, e.g., related to fuel, etc. be submitted to Bob Martin and myself by 2:30 pm today. The plan is for us to share these questions with the licensee by COB, today, and provide them with an opportunity to hold conference calls with us tomorrow to discuss, as needed. We would like to send whatever high priority questions we have today, so that at least they can consider them prior to issuing their document. PIs. note that this is by no means intended to be an all inclusive list.
2
In going forward, we will discuss a "systematic" approach in issuing the questions to the licensee at the 1:30 pm meeting today.
Thanks so much for all of the support and we'll see you at 1:30.
Meena Khanna, Branch Chief Mechanical and Civil Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation (301)415-2150 meena.khanna@nrc.qov 3
U.S. NUCLEAR REGULATORY COMMISSION March 1997 REGULATORY GUIl OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.167 (Draft was DG-103')
RESTART OF A NUCLEAR POWER PLANT SHUT DOWN BY A SEISMIC EVENT E.
A. INTRODUCTION Paragraph IV(aX3) of Appendix S, "Earthqake Engineering Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Ucensing of Production and Utilization Facilities," requires shutdown of the nuclear power plant Uf vibratory ground motion exceed-ing that of the operating basis earthquake ground mo-tion (OBE) occurs or if significant plant damage oc-curs. 1 Prior to resuming operations, the licensee must demonstrate to the NRC that no functional damage has occurred to those features necessary for continded op-eration without undue risk to the health and safety of the public.
This guide provides guidance acceptable to the NRC staff for performing inspections and tests of nu-clear power plant equipment and structures prior to re-start of a plant that has been shut down by a seismic event.
The information collections contained in this regu-latory guide are covered by the requirements of 10 CFR Part 50, which were approved by the Office of Manage-ment and Budget, approval number 3150-0011. The tRegubtacy Guide 1.166, OPW.Ertshae Planning and Immediate Nuclear Pwer Plant Operator ftstsarthquake Admin." provides en-tori. for plant shutdown.
NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information un-less it displays a currently valid OMB control number.
B. DISCUSSION Data from seismic instrumentation2 and a walkdown of the nuclear power plant1 are used to make the initial determination of whether the plant must be shut down after an earthquake, if the plant has not Il-ready shut down from operational perturbations result-ing from the seismic event.
The Electric Power Research Institute has devel-oped guidelines that will enable licensees to quickly identify and assess earthquake effects on nuclear power plants in EPRI NP-6695, "Guidelines for Nuclear Plant Response to an Earthquake," December 1989.3 This regulatory guide addresses sections of EPRI NP-6695 that relate to postshutdown inspection and tests, inspection criteria, inspection personnel, docu-mentation, and long-term evaluations.
R*j a Gutde 1.12, Revision 2, nNudene Poe Plant Instrumen-fEa"rakes describes seimic istrumentation acceptable to the NRC aat 3EPRJ rpWmaybe Obtained from the iectre Power Rcasareb Insti-
- tute, M Dtribution Center, 207 CM*
Dr., P.O. Box 23205, Pleasant Hill, CA 94523.
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bawd hay Use b.pWdUuId tan VuNdand Todiniad h*eindan Swwlaaan anus suItes may be abbened byawshig N~3, inePat VA 3161.
EPRI NP-6695 has been supplemented to add in-spections and tests as a basis for acceptance of stresses in excess of Service Level C and to recommend that en-gineering evaluations of components with calculated stresses in excess of service Level D focus on areas of high stress and include fatigue analyses.
C. REGULATORY POSITION After a plant has been shut down by an earthquake, the guidelines for inspections and tests of nuclear pow-er plant equipment and structures that are in EPRI NP-6695, depicted in Figure 3-2 and specified in Sec-tions 5.3.2, 5.3.3, and 5.3.4; the documentation speci-fled in Section in 5.3.5 to be submitted to the NRC; and the long-term evaluations that are specified in Section 6.3, with the exceptions specified below, are acceptable to the NRC staff for satisfying the requirements in Pama-graph IV(aX3) of Appendix S to 10 CFR Part 50.
- 1. EXCEPTIONS TO SECTION 6.341 OF EPRI NP-6695 1.1 Item (1) should read:
If the calculated stresses from the actual seis-mic loading conditions are less than the allow-ables for emergency conditions (e.g., ASME Code Level C Service iUmits or equivalent) or original design bases, the item is considered acceptable, provided the results of inspections and tests (Section 5.3.2) show no damage.
1.2 The second dashed statement of Item (3) should read:
-An engineering evaluation of the effects of the calculated stresses on the functionality of the item. This evaluation should address all lo-cations where stresses exceed faulted allow-ables and should include fatigue analysis for ASME Code Class 1 components and systems.
- 2. LONG-TERM EVALUATIONS Coincident with the long-term evaluations, the plant should be restored to its current licensing basis.
Exceptions to this must be approved by the Director, Office of Nuclear React&r Regulation.
D. IMPLEMENTATION The purpose of this section is to provide guidance to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.
Except in those cases in which the applicant pro-poses an acceptable alternative method for complying with the specified portions of the Commission's regula-tions, the method described in this guide will be used in the evaluation of applications for construction permits, operating licenses, combined licenses, or design certi-fication submitted after January 10, 1997. This guide will not be used in the evaluation of an application for an operating license submitted after January 10, 1997, if the construction permit was issued prior to that date.
Holders of an operating license or construction per-mit Issued prior to January 10, 1997, may voluntarily implement the methods described in this guide in com-bination with the methods in Regulatory Guides 1.12, Revision 2, "Nuclear Power Plant Instrumentation for Earthquakes," and 1.166, "Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Post-earthquake Actions." Other implementation strategies, such as voluntary implementation of portions of the cited regulatory guides, will be evaluated by the NRC staff on a case-by-case basis.
K 1.167-2
REGULATORY ANALYSIS A separate regulatory analysis was not prepared for this regulatory guide. The regulatory analysis, "Revi-sion of 10 CFR Part 100 and 10 CFR Part 50," was pre-pared for these amendments, and it provides the regula-tory basis for this guide and examines the costs and benefits of the rule as implemented by the guide. A copy of the regulatory analysis is available for inspec-tion and copying for a fee at the NRC Public Document Room, 2120 L Street NW. (Lower Level), Washington, DC, as Attachment 7 to SECY-96-118.
Federal Recyclng Program
,1.167-3
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555.0001 PENALTY FOR PRIVATE UWSE $300 RMS cL4S$ MAIL POSTAGE AND FEES PAID PERMIT NO. G67