ML20044D652
| ML20044D652 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 05/14/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9305200113 | |
| Download: ML20044D652 (4) | |
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GE Nuclear Energy 1
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- u.c May 14,1993 Docket No. STN 52-001 l
Chet Poslusny, Senior Project Manager Standardization Project Directorate i
Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated ABWR Review Schedule - Qualification by Experience l
Dear Chet:
Enclosed is a SSAR markup pertaining to qualification by experience. I believe this modification to our recent inclusion of this subject will be acceptable to the NRC based on my telephone conversation with Dave Terao on May 14,1993.
l Please provide a copy of this transmittal to Dave Terao and Jim Brammer.
l Sincerely, M
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Advanced Reactor Programs cc: Dan Rennels (GE)
Bernie Genetti(GE)
Norman Fletcher (DOE) i I
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Standard Plant 3.10 SEISMICQUALIFICATIONOF accomplished by test, analysis, a combination of SEISMIC CATEGORY I test and analysis, or by experience data. -
INSTRUMENTATION AND ELECTRICAL EQUIPMENT (INCLUDING OTHER in general, analysis is used to supplement DYNAMIC LOADS) test data although simple components may lead themselves to dynamic analysis in lieu of full This section is supposed to address only scale testing. The deciding factors for seismic qualification of electrical components choosing between tests or analysis include:
and equipment in accordance with NRC Regulatory j
Guide 1.70 Revision 3. However, recognizing that (1) magnitude and frequency of seismic and other i
dynamic loads due to suppression pool dynamics RBV dynamic loadings; associated with a loss-of-coolant accident (LOCA) and safety / relief valve (SRV) discharge can have (2) environmental conditions (Subsection 3.11.1) a significant vibratory effect on the reactor associated with the dynamic loadings; building, and, hence, on the design of struc-tures, systems, and equipment in the reactor (3) nature of the safety-related function (s);
building, GE has elected to address equipment qualification for both seismic and other reactor (4) size and complexity of the equipment; building vibration (RBV) dynamic loads in this section. The format utilized is consistent with (5) dynamic characteristics of expected failure R.G.1.70, Revision 3; thus, reference to the modes (structural or functional); and operating basis carthquake (OBE) and the safe shutdown earthquake (SSE) in this section include (6) partial test data upon which to base the the combined seismic and other RBV dynamic analysis.
loads. The non-seismic REV dynamic loads are The selection of qualification methods to be described in Table 3.9-2.
used is largely a matter of engineering judge-The mechanical components and equipment and ment; however, tests, and\\or analyses of assem-the electrical components that are integral to blies are preferable to tests or analyses on the mechanical equipment are dynamically separate components (e.g., a motor and a pump, qualified as described in Section 3.9.
including the coupling and other appurtenances should be tested or analyzed as an assembly).
Principal Seismic Category I structures, Qualification by experience is drawn from systems and components are identified in Table previous dynamic qualification or from other 3.2-1. Most of these items Ice safety-related as documented experience such as exposure to explained in Subsection 3.2.1.
The safety-natural seismic disturbance. Qualification by related functions are defined in Section 3.2, and experience is based on dynamic similarity of the include the functions essential to emergency equipment. +- IN s sRT A reactor shutdown, containment isolation, reactor core cooling, reactor protection, contsinment and 3.10.1.2 Input Motion reactor heat removal, and emergency power supply, or otherwise are essential in preventing The input motion for the qualification of significant release of radioactive material to equipment and supports is defined by response the environment.
spectra. The required response spectra (RRS) are generated from the buildings dynamic analy-3.10.1 Seismic Qualification Criteria sis, as described in Section 3.7. They are (Including Other Dynamic leads) grouped by buildings and by elevations. This RRS definition incorporates the contribution and 3.10.1.1 Selection of Qualification Method other RBV dynamic loads as specified by the load combination Table 3.9-2. The response spectra Dynamic qualification of Seismic Category I curves for the SSE and OBE are presented in Ap-i instrumentation and electrical equipment is pendix 3G. When one type of equipment is locat-j f
3 10-1 Amendment 27 1
ABM 23xsioaxe Standard Plant nrv ti by dynamic analysis using appropriate exceeded when the tubing is subjected to the response spectra.
loads specified in Subsection 3.9.2 for Class 2 and 3 piping.
(b) Floor Response Spectra 3.10.4 Operating License Review (Tests and (i) Floor response spectra used are Analyses Results) those generated for the supporting floor. In case supports are See Subsection 3.10.5.2 for COL license attached to the walls or to two information requirements.
different locations, the upper bound envelope spectra obtained by 3.10.5 COL License Information superimposing are used.
3.10.5.1 Equipment Qualification Records (ii) In many cases, to facilitate the design, several floor response The equipment qualification records spectra are combined by an upper including the reports (see Subsections bound envelope obtained by 3.10.2.1.4 and 3.10.2.2.3) shall be maintained superimposing.
in a permanent file and shall be readily available for audit.
3.103.23 Local Instrument Supports 3.10.5.2 Dynamic Qualification Report For field-mounted Seismic Category I instruments, the following is applicable:
A dynamic qualification report (DOR) shall be prepared identifying all Seismic Category I (1) The mounting structures for the instruments instrumentation and electrical parts and have a fundamental frequency above the equipment therein and their supports. The DOR excitation frequency of the RRS.
shall contain the following: (1) A table or file for each system that is identified in (2) The stress lesel in the mounting structure Table 3.2-1 to be safety-related or having does net exceed the material allowable Seismic Category I equipment shall be included stress when the mounting structure is in the DOR containing the MpL item number and subjected to the maximum acceleration level name, the qualification method and the input for its location.
motion for all Seismic Category I equipment and the supporting structure in the system, 3.103.2.4 Instrument Tubing Support and the corresponding qualification summary table or vendor's qualification report. (2)
The following bases are used in the seismic The mode of safety-related operation (i.e.,
and other RBV dynamic loads design and analysis active, manual active or passive) of the of Seismic Category I instrument tubing supports:
instrumentation and equipment along with the manufacturer identification and model numbers (1) The supports are qualified by the response shall also be tabulated in the DOR. The spectrum method; operation al mode id e n tifie s the instrumentation or equipment (a) that performs (2) Dynamic load restraint measures and analysis the safety-related functions automatically, for the supports are based on combined (b) that is use<l by the operators to perform limiting values for static load, span the safety-related functions manually, or (c) length, and computed dynamic response; and whose failure can prevent the satisfactory accomplishment of one or more safety-related (3) The Seismic Category I instrument tubing functions. (See Subsection 3.10.4).
systems are supported so that the allowable stress permitted by Section Ill of ASME A IN WR T 6 Boiler and Pressure Vessel Code are not Amendment 23 3.1G4
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