ML17309A136

Requests Summary of History of motor-operated Valve Performance at Facility for NRC Review of SEP Topic III-10.A Re thermal-overload Protection for Motors of motor-operated Valves

ML17309A136
Person / Time
Site:	Ginna
Issue date:	03/18/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Maier J ROCHESTER GAS & ELECTRIC CORP.
References
TASK-03-10.A, TASK-3-10.A, TASK-RR LSO5-81-03-039, LSO5-81-3-39, NUDOCS 8103230666
Download: ML17309A136 (7)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 18, 1981 Docket No. 50-244 LS05-81-03-039 Mr. John E. Maier, Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

SEP TOPIC III-10.A, THERMAL-OVERLOAD PROTECTION FOR MOTORS OF MOTOR OPERATED VALVES (R. E. GINNA)

Comments provided in Enclosure 1 of your January 8, 1981 letter will be considered along with the valve operating history when the integrated safety assessment is prepared for your plant-Although the Regulatory Guide publishing Criterion 3 has not yet been issued, operating plant experience with spurious torque switch actuation has shown that it is prudent to bypass torque switches over the first 10% of valve travel.

The purpose of this bypass is to permit the motor and valve parts to come to operating speed and generate breakaway torque above the normal running torque.

You should provide within 30 days of receipt of this letter a

summary of the history of motor operated valve performance at your plant to enable the staff to reach a determination regarding spurious torque switch actuation at your faci 1 ity.

Sincerely, Dennis M. Crutchfield, C ref Operating Reactors Branch No.

5 Division of Licensing s Eo(

i/i D5R RAG 47)

. Mr. Join" E. Maier 2

R.

E.

GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 CC w/enclosure:

Harry H. Voigt, Esquire

LeBoeuf, Lamb, Leiby and MacRae 1333 New Haaqshire

Avenue, N.

W.

Suite 1100 Mashington, D. C.

20036 Mr. Michael Slade 12 Trai lwood Circle Rochester, New York 14618 Rochester Committee for Scientific Information Robert E. Lee, Ph.D.

P. 0. Box 5236 River Campus Station Rochester, New York 14627 J effrey Cohen New York State Energy Office Swan Street Bui 1 di ng Core 1, Second Floor Enqire State Plaza

Albany, Hew York 12223 Director, Technical Development Programs State of New York 'Energy Office Agency Building 2 Esquire State Plaza

Albany, Hew York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road Mest

Ontario, New York 14519 Resident Inspector R. E. Ginna Plant

.c/o U. S.

NRC 1503 Lake Road

Ontario, Hew York 14519 Richard E. Schaffstal1, Executive Director for SEP Owners Group 1747 Pennsylvania

Avenue, HW Washington, D.C.

20006 Director, Technical Assessment Division Office of Radiation Programs (AM-459)

U. S. Environmental Protection Agency Crystal Mall f2 Arlington, Virginia 20460 U. S. Environmental Protection Agency Region II Office ATTN:

E IS COORD IHATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.

20555 r

Dr. Richard F. Cole Atomic Safety and Licensing Board U.

S. Nuclear Regulatory Comnission Mashington, D. C.

20555 Dr.

Emneth A. Luebke Atomic Saf ety and Licens ing Board U. S. Nuclear Regulatory Comnission Mashington, D. C.

20555 Mr. Thomas B. Cochran Natural Resources Defense Council, Inc.

1725 I Street, N.

M.

Suite 600 Mashington,-D.

C.

20006 r

Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of-Law 2 World Trade Center New York, New York 10047

~PS RED'+*++

UNITEDSTATES NUCLEAR REGULATORY COMMlSSlON WASHINGTON, O. C. 2D555 August 20, 1980 Docket No. 50-244 Mr. leon D. White, Jr.

Vice President Electric and Steam Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York

Dear Mr. White:

RE:

SEP TOPICS III-lO.A, V-ll.A, VI<<7.C.l, VI-7.F AND'III-3.B (GINNA)

Enclosed are copies of our current evaluations of Systematic Evaluation Program Topics III-lO.A, Thermal-Overload Protec tors of Motor-Operated Valves;

- ~,

ec r, ns rumentation and Control Features f il d

<<;VI.7.C.1,1 d

of Redundant Onsite Power System; V1-7.F, AccuIIUlator Isolation Valves Power and Control System Design; andI III-3.B, D.C. Power System Bus Voltage Monitoring and Annunciation.

These assessments compare your facility, as described in Docket No. 50-244, with the criteria currently used by the regulatory staff for licensing new facilities.

Please inform us if your as-built facility differs from the licensing basis assumed in our assessments within 45 days of receipt of this letter.

You are also requested to submit a proposed technical specification change which would prevent the transfer of all four instrument buses to the same source.

These evaluations will be basic inputs to the integrated safety assessments for your facility unless you identify changes needed to reflect the as-built conditions at your facility.

These topic assess ants may be revised in the future if'your facility design is changed or if NRC criteria relating to these topics are modified before the integrated assessments are completed.

Sin erely,

@l4' Dennis M. Crutchfield, ief Operating Reactors Branch f5 Division of Operating Reactors E ncl osure:

Completed SEP Topics III-lO.A, V-11.A, VI-7.C.1, VI-7.F and III-3-B cc w/enclosures:

See next page

SYSTEMATIC EVALUATION PROGRAM TOPIC III-10.A THER.LQ -OVERLOAD PROTECTION FOR MOTORS OF ~OTORW~cP~T-0 VALV"S Robert Emmett Ginna, Unit No.

1

TOPIC III-10.A Thermal&verload 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 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 objectve, the application of either one of the two recommendations contai.ned in Regulatory Guide 1.106, "ThermalWverload Protection for Electric Motors on MotorWperated Valves," is adequate.

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 tempor-arily placed in force only when the valve motors are undergoing peri.odic or maintenance

testing, or (b) those thermal-overload protection devices that are normally in force during plant operation should be bypassed under acci.dent conditions.

(2)

The trip setpoint or the thermal-overload protec-tion devices should be established with all uncer-tainties resolved in favor of completing the safety"related action.

With respect to those uncertainties, considerati.on should be given to (a) variations in the ambient temperature at the installed location of the overload protection

devices and the valve motors, (b) inaccuracies in motor heating data and the overload protection device trip characteristics 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 addition, the requirements for TOLs as outlined in R.G.

1.106, the current licensing criteria, require that:

(3)

In MOV designs that use a torque s~itch to limit the opening or closing of the valve, the automatic opening or closing signal should be used in con-junction (series) with a corresponding limit s~itch.

DISCUSSION A review of the dockets and the plant safety-related motor-operated valve (MOV) schematics did not disclose any thermal-overload (TOL) bypasses for the MOVs.

There was no information in the NRC docket indicating that the trip point settings of the safety-related MOVs were established in favor of completing the safety function.

The MOV schematics indicate that, on all automat'cally-or manually-operated MOVs, a limit switch is in series with a torque switch in the opening circuitry of the valves'hese switches open the opening cir-cuit when the valve is in the full-open position.

However, on valves that are automatically-closed, only a torque switch is used to stop the closing of the valve when it is fully closed.

EVALUATION Accordingly, we concluded that the R. E. Ginna Unit No.

1 Nuclear Plant does not satisfy current licensing requirements for (a) bypassing

or establishing that the TOL trip setpoints are set in favor of com-pleting the safety"related function and (b) use of a limit switch in conjunction with the torque s~itch to limit the automatic closure of

,valves.

REFERENCES 1.. Rochester Gas and Electric Corp.

Dwg. No.

10905, "MotorWperated Valve E 1emen tary Wiring Diagrams."

2.

EEEE Standard 179-1971, "Criteria for Protection Systems for Nuc-lear Power Generating Stations."

3.

Branch Technical Position ETCSB-27, "Design Criteria for Thermal Overload Protection for Motors of MotorWperated Valves."

4.

Regulatory Guide 1.106, "Thermal Overload Protection for Electric Motors on MotorWperated Valves."