ML12044A139
| ML12044A139 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/25/2011 |
| From: | Martin R Plant Licensing Branch II |
| To: | Croteau R, Giitter J, Howe A, William Jones, Kulesa G, George Wilson Steam Generator Tube Integrity and Chemical Engineering Branch, Division of Operating Reactor Licensing, Plant Licensing Branch 1, Division Reactor Projects II, Division Reactor Projects III |
| References | |
| FOIA/PA-2011-0357 | |
| Download: ML12044A139 (5) | |
Text
From: Martin, Robert ~f' To: Howe. Allen; Croteau, Rick; Jones. William; Kulesa. Gloria; Glitter. Joseoh; Wilson, George Cc: Khanna. Meena; Williamson, Edward; McCoy. Gerald
Subject:
RE: Discussion with North Anna regarding the SSE Date: Thursday, August 25, 2011 6:30:24 PM Attachments: NRC 10 CFR Aooendix S to Part 50-Earthquake Enqineerinq Criteria for Nuclear Power Plants.mht RG 1 167 ML003740093r11.odf There is an approach and criteria in RG 1.167 and in our regulations in Part 50, Appendix S, for evaluating such a situation.
From: Howe, Allen Sent: Thursday, AugUst 25, 2011 6:19 PM To: Croteau, Rick; Jones, William; Kulesa, Gloria; Giitter, Joseph; Martin, Robert; Wilson, George Cc: Khanna, Meena
Subject:
Discussion with North Anna regarding the SSE We briefed Jack Grobe on the need to communicate the staff assessment, based on USGS data, that suggests that N. Anna may have exceeded their SSE on Tuesday.
Currently, N. Anna does not have data indicating that the SSE was exceeded, although they were still evaluating the info including the scratch plates.
As an outcome, we will support a Region II call to N. Anna to share our information with the licensee. This differs from the earlier discussion I held with Rick Croteau. I called Bill Jones regarding this direction.
In NRR, Gloria Kulesa is the POC. DE staff including Meena Khanna and Yong Li should be available to support the call.
Thanks - Allen
U.S. NUCLEAR REGULATORY COMMISSION March 1997 REGULATORY GUIE E jr4L OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.167 (Draft was DG-1035)
RESTART OF A NUCLEAR POWER PLANT SHUT DOWN BY A SEISMIC EVENT A. INTRODUCTION NRC may not conduct or sponsor, and a person is not Paragraph IV(aX3) of Appendix S, "Earthquake required to respond to, a collection of information un-Engineering Criteria for Nuclear Power Plants," to less it displays a currently valid OMB control number.
10 CFR Part 50, "Domestic Licensing of Production B. DISCUSSION and Utilization Facilities," requires shutdown of the Data from seismic instrumentation 2 and a nuclear power plant if vibratory ground motion exceed- walkdown of the nuclear power plant1 are used to make ing that of the operating basis earthquake ground mo- the initial determination of whether the plant must be tion (OBE) occurs or if significant plant damage oc- shut down after an earthquake, if the plant has not al-curs. 1 Prior to resuming operations, the licensee must ready shut down from operational perturbations result-demonstrate to the NRC that no functional damage has ing from the seismic event.
occurred to those features necessary for contintied op-eration without undue risk to the health and safety of the The Electric Power Research Institute has devel-oped guidelines that will enable licensees to quickly
) public.
This guide provides guidance acceptable to the identify and assess earthquake effects on nuclear power plants in EPRI NP-6695, "Guidelines for Nuclear NRC staff for performing inspections and tests of nu- Plant Response to an Earthquake," December 1989.3 clear power plant equipment and structures prior to re- This regulatory guide addresses sections of EPRI start of a plant that has been shut down by a seismic NP-6695 that relate to postshutdown inspection and event. tests, inspection criteria, inspection personnel, docu-The information collections contained in this regu- mentation, and long-term evaluations.
latory guide are covered by the requirements of 10 CFR Part 50, which were approved by the Office of Manage- 2 1Regulatory Guide 1.12, Revision 2, "Nuclear Pow.er Plant Instrumen-ment and Budget, approval number 3150-0011. The tation for Earthquakes," describes seismic instrumentation acceptable to the NRC staff.
3 lRegulatory Guide 1.166, "Pre-Earthquake Planning and Immediate EPRI reports may be obtained from the Electric Power Research Insti-Nuclear Power Plant Operator Postearthquake Actions," provides cri- tute, EPRI Distribution Center, 207 Coggins Dr., P.O. Box 23205, teria for plant shutdown. Pleasant Hill, CA 94523.
USN]tC REGULATORY GUIDES The *ideft W-ehued Inte l00 g tnImbd dm s m:.
Regaty QGuides we t*ad to desb and mwe voM" IDe to e putic ush hiforma-nas "me*lodsaceptab to toi NRC u*Wf r brilp flin1 speeffic pat' d do Com- 1. POW od mission'snqiaflrtm- 11tm quesed by Mt inaAeuslng s eciMcproblh er p- 2. Rea.h ard TeReaWto 7. Tr=owteion iated wddewtand datameded by f* NRC stdf nhArew dfappica*in Owper- &.Fues "dMaterds FOiffan. a cn=atiolniHealth mit. md leoe. Regua qoyudeswe not eLftsAea regirronm aWdcomitnce 4. Erson d at g.
9 pAWti ara Review wh ties*ns rot mrqulrd MeWtods ad*d rhmodfmM =t dtmesoolegldes & Matials and a A~oPbat 10. Genmn ielI be pwt IEluy wproIde a bes ftreOkm"ng requiteDto We sm orw m-ftuwnce of a pemlot o*rSoea by tio CommnIdision. Shlge lemsof regiaory glides may be mtsln tee of diwe bywilng i*Offie of Rd. iddewas iued after craton d emmat recied hom tie c. cm- Admiritt Aftnf DisDbon wid Mal Se~m Seorn, U.S. uw Re"guaty nn0 and s gesfn fr krnpovwnws I these Wldes wew ecowuged atIdIimes, and Cm sork Wst*lto DO MWS00oco; or by s at (2O)41s-2eo gi9des wiRbe re*sed, as opprcpfat. to sionimodate comment. aid to rdefet new In-fomaOn or iperec. W.Adw may also be bamd -bn Kdo, Tedvo affn'an SAe on V~tei omeb ayb santtdtoli. h..Reiw avd 0Oreclives Orach. OFIPS. a sadin b ore ai.DtisoMdeswloe maybe obtained b wdfti~N718 eSMas ADM. U.S. WueisRer usoyCmisoY~litn DC gcese-Oc0. Royl eed infed VA 2: 1a1.
EPRI NP-6695 has been supplemented to add in- cations where stresses exceed faulted allow-spections and tests as a basis for acceptance of stresses ables and should include fatigue analysis for in excess of Service Level C and to recommend that en- ASME Code Class 1 components and systems.
gineering evaluations of components with calculated
- 2. LONG-TERM EVALUATIONS K
stresses in excess of service Level D focus on areas of high stress and include fatigue analyses. Coincident with the long-term evaluations, the plant should be restored to its current licensing basis.
C. REGULATORY POSITION Exceptions to this must be approved by the Director, After a plant has been shut down by an earthquake, Office of Nuclear Reactor Regulation.
the guidelines for inspections and tests of nuclear pow- D. IMPLEMENTATION er plant equipment and structures that are in EPRI NP-6695, depicted in Figure 3-2 and specified in Sec- The purpose of this section is to provide guidance tions 5.3.2, 5.3.3, and 5.3.4; the documentation speci- to applicants and licensees regarding the NRC staff's fied in Section in 5.3.5 to be submitted to the NRC; and plans for using this regulatory guide.
the long-term evaluations that are specified in Section Except in those cases in which the applicant pro-6.3, with the exceptions specified below, are acceptable poses an acceptable alternative method for complying to the NRC staff for satisfying the requirements in Para- with the specified portions of the Commission's regula-graph IV(a)(3) of Appendix S to 10 CFR Part 50. tions, the method described in this guide will be used in
- 1. EXCEPTIONS TO SECTION 63.4.1 OF the evaluation of applications for construction permits, operating licenses, combined licenses, or design certi-EPRI NP-6695 fication submitted after January 10, 1997. This guide 1.1 Item (1) should read: will not be used in the evaluation of an application for If the calculated stresses from the actual seis- an operating license submitted after January 10, 1997, mic loading conditions are less than the allow- if the construction permit was issued prior to that date.
ables for emergency conditions (e.g., ASME Holders of an operating license or construction per-Code Level C Service Limits or equivalent) or mit issued prior to January 10, 1997, may voluntarily original design bases, the item is considered implement the methods described in this guide in com- K acceptable, provided the results of inspections bination with the methods in Regulatory Guides 1.12, and tests (Section 5.3.2) show no damage. Revision 2, "Nuclear Power Plant Instrumentation for 1.2 The second dashed statement of Item (3) Earthquakes," and 1.166, 'Pre-Earthquake Planning should read: and Immediate Nuclear Power Plant Operator Post-earthquake Actions." Other implementation strategies,
-An engineering evaluation of the effects of such as voluntary implementation of portions of the the calculated stresses on the functionality of cited regulatory guides, will be evaluated by the NRC the item. This evaluation should address all lo- staff on a case-by-case basis.
1.167-2
REGULATORY ANALYSIS A separate regulatory analysis was not prepared for benefits of the rule as implemented by the guide. A this regulatory guide. The regulatory analysis, "Revi- copy of the regulatory analysis is available for inspec-sion of 10 CFR Part 100 and 10 CFR Part 50," was pre- tion and copying for a fee at the NRC Public Document pared for these amendments, and it provides the regula- Room, 2120 L Street NW. (Lower Level), Washington, tory basis for this guide and examines the costs and DC, as Attachment 7 to SECY-96-118.
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-Federal Recycling Program
-I 1.167-3
FIRST CLASS MAIL UNITED STATES POSTAGE AND FEES PAID NUCLEAR REGULATORY COMMISSION USNRC WASHINGTON, DC 20555-0001 PERMIT NO. G47 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300