ML19343A749
| ML19343A749 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/15/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-03-10.A, TASK-3-10.A, TASK-RR NUDOCS 8011210154 | |
| Download: ML19343A749 (6) | |
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' NUCLEAR REGULATORY COMMISSION E
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. h i) g Mr. James A. Kay
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Dear Mr. Kay:
RE: SEP TOPIC III-10.A. THERMAL-0VERLOAD PROT'CTION FOR MOTORS OF MOTOR-OPERATED VALVES (Yankee-Rowe)
Enclosed is a copy of our evaluation of Systematic Evaluation Program Tcpic III-10. A, Thermal-0verloac Protection for Motors of Motor-Operated Valves.
This assessment compares your facility, as described in Docket No. 50 29, with the criteria currently used by the regulatcry staff for licensing new facilities.
Please infcrm us if your as-built facility differs from tne licensing basis assumed in our assessment within 60 days cf receipt of this letter.
This evaluation will be a basic input to the integrated safety assessment fer your facility unless you identify changes needed tc reflect the as-built ccnditions at your facility.
This tcpic assessment may be revised in the future if your facility design is changed or if MRC criteria relating to this tcpic is modified befcre the integrated assessment is completed.
- Sirereiy, i
ennis k. Crutchfield, Ch :f Operating Reactors Sranch #5 Divisicc of Licensing
Enclosure:
Comoleted SEP Tcpic_III-lC.A cc w/ enclosure:
See next page D**D *DfYM UM ib %
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Mr. James A. Kay' September 15, 1980 9
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- Mr. James E. Tribble, President -
Yankee Atomic Eler*.ric Coapany e
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-Westborough, Massachusetts 01581 I
' G reenfi e' Community College i
1 College Drive Greenfield, Massachusetts 01301.
Chairman Board of Selectmen 2
Town of Rowe Rowe, Massachusetts 01367
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Energy Facilities Siting Council
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14th Floor One Ashburton Place Bcston, Massachusetts 02108 Director, Technical Assessment Division Office of Radiation Progrars
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(AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
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U. S. Environmental Protection Agency Region I Office ATTN: EIS COORDINATOR JFK Federal Building Besten, Massachusetts 02203 Resident Inspector Yankee Rowe Nuclear Power Station -
c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350 I
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SEP TECHNICAL EVALUATION TOPIC III-10.A THERMAL-0VERLOAD PROTECTION FOR MOTORS OF MOTOR-OPERATED VALVES YANKEE ROWF, Docket No. 50-29 April 1980
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4-9-80
SEP TEC'dNICAL EVALUATION TOPIC III-10.A THERMAL-0VERLOAD PROTECTION FOR MOTORS OF MOTOR-0PERATED VALVES YANKEE ROWE TOPIC?III-10.A Thermal-Overload protection for Motors of Motor-Operated Valves The objective of this review is to provide assurance that the appli-cation of thermal-ove:.aad protection devices to motors associated with safety-related motor-operated valves do not result in needless hindrance of the~ 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-Overload 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 jeopardized or that other safety systems are not degraded, (a) the thermal-overload protection devices should be continuously bypassed and temporarily placed k-in force only.when the valve motors are undergoing periodic or maintenance testing, or (b) those thermal-overload protection devices that are normally in force during plant operation should be bypassed under acci-
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-dent conditions.
(2) The trip setpoint of the thermal-overload protection devices should be established with all uncertainties resolved in favor of completing.che safety-related
. action. With respect to those uncertainties,. consider-ation should be-given to (a) variations ia the ambient temperature at the installed-location of the overload
protection devices and the valve motors, (b) inaccura-cies in motor heating data and tr overload protection device trip characteristics and catching of these t.
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 addition, the current licensing criteria require that:
(3)
In MOV designs that use a torque switch to limit the opening or closing of the valve, the automatic opening or closing signal should be used in conjunction with a corresponding limit switch.
DISCUSSION Review of Yankee Rowe drawings show 20 motor-operated valves which are
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supplied power from ESF buses.
Plant Technical Specifications require that power be removed frca all but one bf these valves prior to plant oper-ation at full power.0 Of the 16 valves for which elementary diagrams are available, all have thermal-overload devices which are not bypassed; there is no docketed information to indicate that TOL trip setpoints have been set to comply with Criterion 2, above. Additionally, two automatic com-mands are terminated by linic switches, but five are terminated by torque switches.
EVALUATION Thermal-overload protection for motors of motor-operated valves at Yankee Rowe does not meet current licensing criteria. Thermal-overload devices are not bypassed, no information is available to support adequacy of trip setpoints, and torque switches rather than limit swiches are used to terminate valve cravel for five of seven automatic commands.
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REFE RENCES.
1.
IEEE Standard 179-1971, " Criteria.for Protection Systems for Nuclear Power Generating Stations."
2.
3 ranch Technical Position EICSB-27, " Design ' Criteria for Thermal Over-load Protection.for Motors of Motor-Operated Valves."
3.
Regulatory Guide 1.106, " Thermal 0verload Protection for Electric Motors on Motor-Operated valves."
4.
Yankee Rowe drawing ESK-6AA, Revision 5, dated 1-23-76.
5.
Yankee Rowe drawing ESK-6AD, No Revision, dated 11-10-77.
6.
Yankee Rowe drawing 9699-FE-lJ, Revision 8, dated 5-2-78.
7.
Yankee Rowe drawing 9699-FE-5A, Revision LA, dated 1-26-76.
8.
" Yankee Nuclear Power Station, Technical S,pecifications," para-graph 4.5.2.b.
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