Regulatory Guide 1.167
| ML003740093 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1997 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| DG-1035 RG-1.167 | |
| Download: ML003740093 (4) | |
U.S. NUCLEAR REGULATORY COMMISSION March 1997 REGULATORY GUIDE
or-I 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 required to respond to, a collection of information un Paragraph IV(aX3) of Appendix S, "Earthquake less it displays a currently valid OMB control number.
Engineering Criteria for Nuclear Power Plants," to
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 continued op eration without undue risk to the health and safety of the The Electric Power Research Institute has devel public. oped guidelines that will enable licensees to quickly identify and assess earthquake effects on nuclear power This guide provides guidance acceptable to the 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 Regulatory Guide 1.12, Revision 2, "Nuclear Power 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., RO. Box 23205, teria for plant shutdown. Pleasant Hill, CA 94523.
USNRC REGULATORY GUIDES The guLides wre Issued Inthe following ten broad divisions:
Regulatory Guides are Wisued to describe ard make available to the public such Informa tIon as methods acceptable to the NRC staff for implementing specific parts of the Corn 1. Power Reactors 6. Products mission's reguiaelone, tedhfques used by the staff in evaluating specific problems or pos 2. Research and Test Reactors 7. Transportation tulated accddents, and data needed by dhe NRC staff In its review of applications for per 3. Fuels and Materials Faclities a. o=upational Health mltsan licenses. Regulatory guides ae not substitutes for regulations, and compliance 4. Environmental msd Siting 9. Antirust nd Financial Review with them Is not required. Methods end solutions different from those set Out in the guides 5. Materials end Plant Protection 10. General will be acceptable 9 they provide a basis for te indings requisite to the Issuance or con.
tinuance of a permit or license by the Commission.
Single copies of regulatory guides may be obtained free of charge by writing the Office of Tha guide was Issued after consideration of comments received from the public. Corn Administration, Attention: Distribution and Mall Services Section, U.S. Nuclear Regulatory merts and suggestions for improvements In these guides we encouraged st all times, and Commission, Washington. DC 20555-0001; or by fax at (301)415-2260.
guides win be revised, as apprpriate, to accommodate comments and to reflect new In fotnnion or eiperlence.
Issued guides may also be purchased from the National Technical Infomation Service on Written comments may be submitted to the Rules Review and Directives Branch, DFIPS, a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port ADM, U.S. Nuclear Regulatorq Commission, Washington, DC 20555-0001. "Royl Road, Springfield, VA 22161.
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 1components and systems.
gineering evaluations of components with calculated stresses in excess of service Level D focus on areas of 2. LONG-TERM EVALUATIONS
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 6.3.4.1 OF the evaluation of applications for construction permits, operating licenses, combined licenses, or design certi EPRI NP-6695 fication submitted after January 10, 199
7. 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 11 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 LStreet NW. (Lower Level), Washington, tory basis for this guide and examines the costs and DC, as Attachment 7 to SECY-96-118.
Federal Recycling Program
1.167-3
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