ML20117C526

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Forwards Proposed Task Interface Agreement Re Lack of Annunciation/Indication of Motor Operated Valve Inoperability Due to Thermal Overload Bypass Circuit Design. Potential for Generic Problem W/Design Noted
ML20117C526
Person / Time
Site: 05000000, Susquehanna
Issue date: 10/20/1983
From: Starostecki R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Eisenhut D, Jordan J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation
Shared Package
ML20114F930 List:
References
FOIA-84-616 NUDOCS 8505090450
Download: ML20117C526 (2)
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UNITED STATES S.

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NUCLEAR RESULATORY COMMISSION 5

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OCT 2 01983

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MEMORANDUM FOR:

Darrell G. Eisenhut, Director, Division of Licensing, NRR Edward L. Jordan, Director, Division of Engineering and Quality Assurance, IE FROM:

Richard W. Starostecki, Director, Division of Project and Resident Programs, Region I

SUBJECT:

DESIGN PROBLEM IN MOTOR-OPERATED-VALVE THERMAL OVERLOAD BYPASS CIRCUITRY AT SUSQUEHANNA UNIT 1 This forwards the proposed Task Interface Agreement (TIA) we discussed regard-ing potential lack-of annunciation / indication of MOV inoperability at Susque-hanna Unit I due to thermal overload bypass circuit design.

The TIA requests IE and NRR to jointly assess the generic significance of this prablem and to make the appropriate notifications to other Commission Offices, and to reactor applicants and licensees.

As reported in PP&L's LER No. 50-387/83-129, a MOV with a burned-out motor (whose thermal overloads have actuated) would not be annunciated or indicated as inoperable as long as the bypass is in effect in accordance with Regulatory Guide 1.106. The Region I resident inspector reviewed this problem with the licensee.

Results indicate a potential for a generic problem exists for those facilities using the bypass circuit design involved.

The primary contacts in Region I for this issue are E. McCabe (488-1231) and E. Kelly (488-1132).

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s Richard W. Starostecki, Director Division of Project and Resident Programs

Enclosures:

1.

Task Interfac'e Agreement 2.

10/19/83 Kelly to Greenman memo with attachments cc w/encls:

V. Benoraya, NRR J. Taylor, IE R. Lewis, RII C. Norelius, RIII J. Gagliardo, RIV T. Bishop, RV T. Martin, RI C. Heltemes, AE0D 8505090450 841002 PDR FOIA BARFIEL84-616 PDR

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TASK INTERFACE AGREEMENT TASK No.

DATE:

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PROBLEM:

Design Problem in MOV Thermal Overload Bypass Circuitry -

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Annunciator Operability Status at Susquehanna Unit 1 LEAD OFFICE:

IE D NRR REGION

@ JOINT NOTIFICATION:

REFERENCES:

(1) NRC Region I Inspection Report 50-387/83-21; (2) LER 50-387/83-129 dated 10/7/83; (3) Regulatory Guide 1.106, Rev.1 March 1977; (4) LER 50-387/83-111 dated 9/2/83; (5) Memo Kelly to Greenman dated 10/13/83.

ACTION PLAN:

Determine if annunciator circuitry problem applies to all other MOV's at Susquehanna 1.

Unit 1 (currently operating at 100% power); Unit 2 (under construction); and whether this is generic to other BWR's or PWR's with MOV thermal overload bypass circuits in accordance with Reg. Guide 1.106. (IE, NRR, Region )

2.

Review design modifications (NRR) 3.

Issue generic correspondence (IE)

Assess operability status of affected ESF Systems at Unit 1 (Region) 4.

NRR: Designate Lead Project Manager to assign TACS and coordinate meetings, reports and correspondence.

OFFICE COORDINATOR,:

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APPROVED:

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I NRR REGIONLI cc:

V. ftello, ROGR J. Sniezek, IE H. Thompson, NRR G. Holahan, NRR Regional Admin.

R. DeYoung, IE D. Eisenhut NRR NRR Project Manager J. Taylor IE F. Miraglia, NRR R. Vollmer NRR R. Purple NRR C. Heltemes, AEOD H. Denton, NRR G. Lainas, NRR R. Wessman, NRR E. Jordan, IE E. Case, NRR R. Baer, IE R. Mattson, NRR T. Novak, NRR W. Mills, IE J. Kramer, NRR T. Ippolito, NRR

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Octcber 7,1983 Dr. Thomas E. Murley Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 83-129/01P-0 ER 100450 FILE 841-23 Docket No.

50-387 License No. NPF-14 PLA-1898

Dear Dr. Murley:

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This transmission confirms the verbal report of October 7,1983, by L.A. Kuczynski to C.G. Rhoads of your staff, in that it has been determined that the present thermal overload bypass circuit design for certain motor operated valves (MOV) could prevent Control Room indication of thermal overload actuation.

On September 27, 1983, operations personnel attempted to operate BV-156F059 from the Control Room following a preventive maintenance activity on the HPC1 turbine exhaust pressure switches. When EV-156F059 would not operate, an investigation commenced which yielded the following conclusions:

1) The torque switch spring pack failed to open at the specified This caused the valve operating motor to burn up on torque.

over-torque with a locked rotor. This will be discussed further in LER 83-140/03L-0.

2) The thermal overload bypass circuit desigh could give erroneous indication of valve electrical operability'in the Control Room.

This indication would arise if a valve's MOV test / bypass switch were to be returned to the normal ' bypass' position prior to actuation of the thermal overload heater coils.

An inspection to verify the integrity of other DC MOV thermal overload heater coils was immediately performed. All checked coils were in satisfactory condition. Plans have been made to check the coils on the appropriate AC valve motors. Shif t supervision have been notified through the Night Orders book that MOV test switches should remain in the ' test' position for at least thirty seconds following a valve closing operation prior to the MOV test switch being placed back to the normal

' bypass' position. This action would assure Control Room indication if the overload relays actuate to protect the MOV motor against a thermal

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overload condition. An engineering evaluation of the thermal overload bypass circuit design is underway.

This condition is considered reportable in accordance with Technical Specification 6.9.1.8.I, and additional information regarding circumstances of the incident and corrective actions to be taken will be provided in the fourteen day follow-up report.

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B.W. Kat er Superint.ndent of Plant-Susquehanna IAK:p.ig cc:

G.G. Rhoads Residant Inspector U.S. Nuclear Regulatory Conunission P.O. Box 52 Shickshinny, PA 18655 Document Control Desk U.S. Nuclear Regulatory Conuniasion Washington, DC 20555 5

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Pennsylvania Power & Light Company Two North Nmth Street = Allentown, PA 18101

  • 21517745151 September 2, 1983 1

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Dr. Thomas E. Murley Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 83-111/03L-0 ER 100450 FILE 841-23 Docket No.

50-387 PLA-1825 License No. NPF-14

Dear Dr. Murley:

Attached is Licensee Event Report No. 83-111/03L-0. This event was determined to be reportable per Technical Specification 6.9.1.9.b, in that the breaker which controls the electrical operation of one of the valves in the High Pressure Coolant Injection (HPCI) system tripped and would not stay reset.

(The valve controls cooling water flow to the HPCI system lube oil cooler and barometric condenser.) This resulted in entry into Limiting Condition for operation 3.5.1.

It was determined that valve motor insulation break-down caused burned field windings which disabled the valve's electrical operation. The motor was replaced, the valve stroked electrically and the system returned to service.

H.W. Keiser Superintendent of Plant-Susquehanna LAK/pjg cc:

C.G. Rhoads Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 52 Shickshinny, PA 18655 Document Control Desk U.S. Nuclear Regulatory Cor=ission Washington, DC 20555 C '2 -

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LICENSEE EVENT REPORT siso-sosi c

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(PLEASE PRINT OR TYPE ALL REoulRED INFORMATsONI F5TTl Iy l A l S l E l S l 1 l@l0 10 l-l 0 l 0 l 0 l 0l Ol -l 0 l 0 l@l4 l1 l1 l1 l1 l@l l

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@ I meh the unit in steady state operation at 100% power. it was found that the valvel r.m lwhich controls cooling water flow to the HPCl lube oil cooler and barometric con-l idenser would not cycle electrically. It was immediately determined that the valve l o e oa lstroked freely when operated manually. Since the valve could have been operated l

oe l==nually and the remainian ECCS systems were available during the time period in l

o7 I auestion. there were no adverse effects to public health and safety.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1 0 l Valve electrical inoperability was caused by valve motor insulation breakdown l

1 1 l vhich led to burned field windings. A replacement motor was installed. The valve l l was stroked electrically and the LCO cleared. The inoperable motor was shipped l

t 2 t 3 l off-site for re-vinding and cleaning. No further actions are required.

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lllllllllllll NAME OF PREPARER L. A. Kuczynski puoNE. (717)542-2181

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