ML20137J507
| ML20137J507 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1997 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| FRN-61FR65157, TASK-*****, TASK-RE AD93-2-014, AD93-2-14, REGGD-01.167, REGGD-1.167, NUDOCS 9704040045 | |
| Download: ML20137J507 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION March 1997
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f g***** ),REGULATORY GU DE 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(a)(3) 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 shutdowra of the Data from seismic instrumentation 2 and a nuclear power plant if viuratory ground moiion exceed-l walkdown of the rmclear power plMi are med to make ing that of the operating basis earthquake ground mo-the initial determination of whether the plant saust be tion (OBE) occurs or if significant plant damage oc-shut down after an carthquake, 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 ictitute has devel-
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- 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-2Regulatory 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.
tRegulatory Guide 1.166, " Pre-Earthquake Planning and Immediate JEPRI reports may be obtained from the Electric Power Research Insti.
Nuclear Power Plant Operator Postcarthquake Actions," provides cri-tute, EPRI Distribution Center, 207 Coggms Dr., PO. Box 23205, teria for plant shutdown.
Pleasant Hill, CA 94523.
1 USNRC RLGULATORY GUIDL5 The guides are issued in the following ten broad dmssons
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Regulatory Gades are issued to desenbe and make evelable to the pubke suchinforma tion as methods acceptatWe to the NRC staff for implementing specif c parts of the Com.
1 Power Reactors 6 Products mission a regulations. techniques used by the staff sievaluatmg specific problems or pos-2 Research and Test Reactors 7 Transportation tulated accidents. and data needed by the fWRC staff in as review of apphcations for per.
3 Fuels and Materials Facilities e Occupational Healtn p
mais and kcenses Regulatory gudes are not substitutes for regulations. end comphance 4 Environmental and Siting 9 Antitrust and Financial Heview with them a not required Methods and solutions different kom those set outin the gusoes 6 Materials and Plant Protection
- 10. General will ts acceptable if they provide a base for theimdings reqwsste to the muuance or con.
T de was er derr on of monts received from the pubhc Com.
i eton A Ds son and a Senn S'
egulatory
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D ADM. U S Naciear Regulatory Commisseon, Wasnington, DC 205%-0001 lasued gwdes may also be purchased from the National Tect' scal Information Sennce on wntten commanis rnay be submitted to the Rules Review and Direttives Branch. DFIPS, e standmg order base Detads on tnis servsce may be obtened by wnting NTIS. 5205 Port Royal Road. Spnngfield. VA 22161 9704040045 970331 PDR REGGD lllll]ll]lEllll[llll]l[l-01.167 R PDR
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 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 e,aluations, 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-I). IMPLCMENTATION er plant equipmeat 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 th6 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 the evaluation of applications for constmetion permits, 1.
EXCEITIONS TO SECTION 6.3.4.1 OF perating licenses, combmed licenses, or demgn 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 Iloiders 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-acceptable, provided the results ofinspections 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 and Immediate Nuclear Power Plant Operator Post-should read:
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. Tais evaluation should address all lo-staff on a case-by-case basis.
1.167 - 2
REGUIATORY ANALYSIS A separate regulatory analysis was not prepared for benefits of the rule as implemented by the guide. A l
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. (1xwer Level), Washington, tory basis for this guide and examines the costs and DC, as Attachment 7 to SECY-96-118.
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