ML13333A327
| ML13333A327 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/24/1978 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Southern California Edison Co |
| References | |
| TASK-03-06, TASK-08-03.A, TASK-3-6, TASK-8-3.A, TASK-RR NUDOCS 7812130156 | |
| Download: ML13333A327 (7) | |
Text
F NOV 2 4 1978 N RL Local PDR ORB#2 RDG Docket No. 50-206 VStello DEisenhut BGrimes Southern California Edison Company DLZiemann ATTN:
Mir. James H. Drake ABurger Vice President HSmith 2244 Walnut Grove Avenue OELD Post Office Box 800 OI&E(3)
Rosemead, California 91770 TERA JRBuchanan Gentlemen:
ACRS(16)
DDavis Enclosed are copies of our draft evaluation of two Systematic Evaluation Program (SEP) topics. You are requested to examine the facts upon which the staff has based its evaluation and respond either by confirming that the facts are correct, or by identifying any error. If in error, please supply corrected information for the docket.
We encourage you to supply for the docket any other waterial related to these topics that might affect the staff's evaluation.
It would be most helpful if your comments were received within 30 days of the date you receive this letter..
Sincerely, Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Enclosures:
Topics III-lO.A VIII-3.A cc w/enclosures:
See next page
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November 24, 1978 cc Rollin E. Woodbury, Vice President and General Counsel Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David R. Pigott Samuel B. Casey Chickering & Gregory Three Embarcadero Center Twenty-Third Floor San Francisco, California 94111 David W. Gilman Robert G. Lacy San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 U. S. Nuclear Regulatory Commission ATTN:
Robert J. Pate Post Office Box 4167 San Clemente, California 92672 K M C Inc.
ATTN:
Mr. Jack McEwen 1747 Pennsylvania Avenue, N. W.
Suite 1050 Washington, D. C. 20006
SYSTEMATIC EVALUATION PROGRAM THERMAL-OVERLOAD PROTECTION FOR MOTORS OF MOTOR-OPERATED VALVES SAN ONOFRE UNIT NUMBER 1 Topic III-10.A Thermal-Overload Protection for Motors of Motor Operated Valves The objective of this review is to provide assurance that the application; of thermal overload protection devices to the motors associated with safety-related motor operated valves do not result in needless hindrance of these valves to perform their safety functions.
In accordance with this objective, the application of either one of the two recommendations contained in Regulatory Guide 1.106, "Thermal Over load Protection for Electric Motors on Motor-Operated Valves" is ade quate.
These recommendations are as follows:
- 1. Provided that the completion of the safety function is not jeopardiz2d' or that other safety systems are not degraded, (a) the thennal over load protection devices should be continuously bypassed and tempo rarily placed in force only when the valve motors are undergoing periodic or maintenance testing or (b) those thermal overload pro tection devices that are normally in force during plant operation should be bypassed under accident conditions.
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- 2. The trip setpoint of the thermal overload protection devices should be established with all uncertainties resolved in favor of completing the safety-related action.
With respect to those uncertainties, consideration should be given to (a) variations in the ambient temperature at the installed location of the over load protection.devices and the valve motors, (b) inaccuracies in motor heating data and the overload protection device trip charac teristics and the matching of these two items, and (c) setpoint drift. In order to ensure continued functional reliability and the accuracy of the trip point, the thermal overload protection device should be periodically tested.
In general, the thermal overload devices associated with the safety-related motor operated valves are bypassed permanently at the San Onofre Unit Number 1 Nuclear Plant. However, during the course of the review for this topic four safety-related motor operated valves have been identified as having thermal overload devices on their motors which are not bypassed. Two of these valves (MOVs 720A and 720B) are associated with the Component Cooling Water System. The.remainin two valves (MOVs 813 and 814) are associated with the Residual Heat Removal System. For MOVs 720A and 7OB the licensee has committed to bypass the thermal overload protection devices, which are associated with these motor operated valves. Concerning MOVs 813 and 814 it is not necessary to bypzss the thermal devices associated with these
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vlves since these valves are not required to change states within a relative short period of time during or folloring acci-.
dent conditions (Further, the Residual Heat Removal System itself is not actuated automatically by an accident signal).
Accordingly, we conclude that the San Onofre Unit Numbcr N
Plant design does satisfy current licensing requiremenlts for thr Mal overload protection devices which are associated with safety related motor operated valves subject to the final insta1lation of the bypasses for the two valves indicated above.
X
SYSTEMATIC EVALUATION PROGRAM BATTERY CAPACITY TESTS SAN ONOFRE DOCKET NO: 50-206 Topic VIII-3.A Station Battery Test Requirements The objective of this review is to assure that the onsite Class IE battery capacity to supply all safety related D-C loads is verified by periodic testing.
The testing should be in accordance with IEEE Standard 450-1975, IEEE Standard 308-1974, BTP EICSB 6 and the "Standard Technical Specifications for Westinghouse Pressurized Water Reactors" (NUREG-0452). The required tests are as follows:
- 1. At least once per 18 months, during shutdown, a battery service test should be performed to verify that the battery capacity is adequate to supply and maintain in operable status all of the actual emergency loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 2.
At least once per 60 months, during shutdown, a battery discharge test should be performed to verify that the battery capacity is at least 80' of the manufacturer's rating.
The technical specifications for the San Onofre Nuclear Station include in Section 4.4 D the required battery service and discharge tests at the required intervals.
Therefore, the San Onofre Nuclear Station battery tests comply with current licensing requirements. No additional SEP action is necessary.
References
- 1.
"San Onofre Technical Specifications",Southern California Edison Company.
- 2.
Standard Review Plan, Appendix 7-A, BTP EICSB 6, "Capacity Test Requirements of Station Ba-ftteries. - Technical Specifications", U. S.
Nuclear Regulatory Commission.
- 3. "IEEE Standard Criteria for Class IE Power Systems for Nuclear Power Generating Stations", Std. No. 308-1974, The Institute of Electrical and Electronics Engineers, Inc.
- 4.
"IEEE Recommended Practice for Maintenance, Testing and Replacement of Large Lead Storage Batteries for Std. No. 450-1975, The Institute of Electrical and Electronics Engineers, Inc.
- 5. "Standard Technical Specifications for Westinghouse Pressurized Water Reactors",
NUREG-0452, U. S. Nuclear Regulatory Commission.