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) | |
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Martin, Robert ~f' Howe. Allen; Croteau, Rick; Jones. William; Kulesa. Gloria; Glitter. Joseoh; Wilson, George Khanna. Meena; Williamson, Edward; McCoy. Gerald RE: Discussion with North Anna regarding the SSE Thursday, August 25, 2011 6:30:24 PM 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 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 E
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A. INTRODUCTION Paragraph IV(aX3) of Appendix S, "Earthquake Engineering Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," requires shutdown of the nuclear power plant if 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 contintied 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 lRegulatory Guide 1.166, "Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions," provides cri-teria 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 instrumentation 2 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 al-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.
21Regulatory Guide 1.12, Revision 2, "Nuclear Pow.er Plant Instrumen-tation for Earthquakes," describes seismic instrumentation acceptable to the NRC staff.
3EPRI reports may be obtained from the Electric Power Research Insti-tute, EPRI Distribution Center, 207 Coggins Dr., P.O. Box 23205, Pleasant Hill, CA 94523.
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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-fied 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 Para-graph IV(a)(3) of Appendix S to 10 CFR Part 50.
- 1. EXCEPTIONS TO SECTION 63.4.1 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 Limits 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 Reactor 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.
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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.
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-Federal Recycling Program
-I 1.167-3
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555-0001 FIRST CLASS MAIL POSTAGE AND FEES PAID USNRC PERMIT NO. G47 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300