ML20085E328
| ML20085E328 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/26/1983 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8308010283 | |
| Download: ML20085E328 (4) | |
Text
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DUKE POWER COMPANY P.O. IBOX 33189.
CHARLOTTE, N.C. 28242 HALB. TUCKER TELEPHONE (704) 373-4531 VDCE,BEGIDENT July 26, 1983
,,mo...om, Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
.Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
Section 4.4.3.1 of the Catawba Safety Evaluation Report provides a discussion of Confirmatory Item 9, Loose Parts Monitoring Systems. Attached are revised Catawba FSAR pages which respond to this item.
Very truly yours, Bf
/gy Hal B. Tucker ROS/php Attachment cc:
Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.
' Attorney-at-Law P. O. Box 12097 Charleston, South _ Carolina 29412 Palmetto Alliance 2135 Devine Street
- l Columbia,_ South Carolina 29205 1
i i
Mr. Jesse L._Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 8308010283 830726 PDR ADOCK 05000413 E
CNS of the Engineered Safety Feature devices of the control board is designed to minimize the time required for the operator to evaluate system performance under accident conditions.
7.8.7 OCCUPANCY Safe occupancy of the control room during abnormal conditions is provided for in the design of the Auxiliary Building.
Adequate shielding is used to main-tain tolerable radiation levels in the control rooms for maximum hypothetical accident conditions.
Each control room ventilation system is provided with radiation detectors and appropriate alarms.
Provisions are made for the control room air to be recirculated through absolute and charcoal filters.
Emergency lighting is provided.
7.8.8 LOOSE PARTS MONITORING SYSTEM The following design considerations form the basis for the Loose Parts Monitor-ing System (LPMS) installed at Catawba.
- 1. ) The LPMS is designed to detect and record signals resulting from loose-part impacts occurring within the Reactor Coolant System.
2.) Channel separation is addressed in response to Q492.1.
3.) The Primary Coolant System in its entirety is designed to withstand seismic events, therefore, loose parts are not anticipated result' ants from seismic events.
l
- 4. ) Seismic qualification of the LPMS is addressed in response to Q492.1.
5.) Complexity and demand en operators time is held at a minimum while providing reliable indications.
Twelve transducers are located in the areas where loose parts are most likely to become entrapped.
These are:
two on the reactor vessel lower head, diametrically opposed.
two on the reactor vessel upper head, diametrically opposed.
l two on the lower head of each steam generator, diametrically l
I opposed.
Experience has shown that the exact location of these transducers is not critical since the acoustic wave that results from an impact propagates throughout the entire head.
The transducers are piezoelectric accelerometers.
These accelerometers are individually tested and calibrated.
7.8-3 Rev. 8
CNS quake requirements of the Regulatory Guide 1.133, and therefore no seismic test reports for this system are available.
The in-containment portion of the Catawba LPMS consists of accelero-meters, preamplifiers and interconnection cables. We have re-viewed these components for seismic capability and have deter-mined that:
(
i) The design of accelerometers inherently provides some seismic capability.
The accelerometer design at Catawba is similar to designs used in systems that have been seismically tested and qualified.
( ii) The preamplifers used are solid state, light weight devices similar to other type amplifers which have been seismically tested and qualified in safety re-lated systems.
(iii) The cables used for LPMS are high quality, low noise cables protected by an overall armor.
These cables inside co..Lc..'3 ment are installed in seismically qualified cable support systems.
5.
Personnel who are required to perform checks, calibrations and tests of the LPMS will be qualified by training and experience appropriate to their responsibilities.
Personnel who perform the qualitative channel checks will receive general fam.iliariza-tion training on recognition of abnormal audio signals and basic operation of the LPMS.
Personnel who perform monthly channel checks or who perform maintenance on the LPMS hardware will be qualified instrument and controls technicians and will perform this work under approved procedures.
Personnel who analyze the LPMS signals and perform evaluations of the spectra and other plant parameters during normal surveil-lance or alarm investigation will be qualified by education and experience in frequency analysis and interpretation, and will be knowledgable through experience with respect to Reactor Cool-ant System componets structures and operations.
In addition, these personnel will receive specialized training on the de-tection and analysis of loose parts events.
6.
Duke Power will install four additional channels of LPM, one per steam generator.
These new channels, i.e., sensors, preamplifiers, cables and penetrations will be physically separated from the existing steam generator LPM channels.
Redundant channels associated with the other natural collection regions will also meet the same separation criteria.
490-1c Rev. 8
o.
CNS 7.
A final design report will be provided on the same schedule as the Startup Report (Technical Specification 6.9.1.3) and will contain a description of the system, a description of applicable station procedures (including results of startup tests) and an evaluation of the LPMS for corJormance to Regulatory Guide 1.133.
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