ML17250B183

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Part 21 Rept Re Potential Matl Defect of SMA Type Torque Switches Supplied by Limitorque During Late 1960s.Loose Torque Switch Mounting Socket Head Bolts &/Or Wire Termination Bolts Found on 19 of 26 Valve Actuators
ML17250B183
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/31/1990
From: Rich Smith
ROCHESTER GAS & ELECTRIC CORP.
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
REF-PT21-90 NUDOCS 9006110336
Download: ML17250B183 (7)


Text

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UTION DEMONSTIWTION SYSTEM REGULATORY INFORMATION DXSTRXBUTXON SYSTEM (RIDS)

ACCESSION NBR:9006110336 DOC.DATE: 90/05/31 NOTARIZED: NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION SMITH,R.E. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPXENT AFFXLIATXON MURLEY,T.E. Office of Nuclear Reactor Regulation, Director (Post 870411

SUBJECT:

Part 21 rept re potential matl defect of SMA type torque switches supplied by Limitorque during late 1960s.

DISTRIBUTION CODE: IE19D COPIES RECEIVED LTR ENCL SIZE: D TITLE: Part 21 Rept (50 DKT) 8 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244

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RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 0 PD1-3 PD 1 1 D JOHNSON,A 1 1 INTERNAL: AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 D

IRM TECH ADV 1 1 NRR CRUTCHFIELD 1 1 NRR VARGA,S 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OGCB11 1 1 DRIS/RVIB9D 1 1 NRR/DST 8E2 1 1 RE 01 1 1 RES/DSIR/EIB 1 1 RGB. 1 1 RGN2 1 1 RGN3 1 1 RGN4 1 1 RGN5 1 1 EXTERNAL: INPO RECORD CTR 1 1 1 1 NRC PDR 1 1 LPDR'S IC S ILVER E g 1 1 D

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D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 22

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'III Zi ZWiZZ ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TCLEPNDNC AREA CDDK Tle 546-2700 May 31, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Attention: Dr. Thomas E. Murley Office of Nuclear Reactor Regulation Washington, D.C. 20555

Subject:

Notification of 10CFR, Part 21 R.E. Ginna Nuclear Power Station Docket No. 50-244 Licensee No. DPR-18

Dear Dr. Murley:

Rochester Gas and Electric is submitting the attached 10CFR, Part 21 Evaluation and Notification. The notification concerns a potential material defect of SMA type torque switches supplied by Limitorque during the late 1960's.

One hundred seven (107) of one hundred eight (108) motor operated valves (MOV) installed at R.E. Ginna Nuclear Power Plant, actuator wiring configurations were inspected in conjunction with an on-going Electrical Control Configuration Drawing Upgrade Project.

Twenty-six had SMA-type torque switches installed. The SMA-type torque switch is a black fibrous, laminated, phenolic material.

Ten of the twenty-six switches demonstrated loose one-quarter inch socket head mounting screws and nine of the twenty-six demonstrated loose wire termination bolts.

None of the valves with the loose torque switch bolting demon-strated operability problems during operations or testing. The cause of the loose bolting appears to be consolidation or com-pression of the fibrous material and/or vibration.

Specific information regarding failure identification and correc-tive action taken are detailed on the enclosed Attachment 1.

Should further information be required, please contact Mr. Thomas Marlow, Superintendent of Ginna Support Services at 315/524-4446.

9006li03 6 900531 05000244 PDR ADOCK PDC

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Page 2 Dr. Thomas E. Murley May 31, 1990 Very truly yours, Robert E.,Smith Senior'ice President Production 6 Engineering xco Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Ginna Station Senior Resident Inspector

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~ Li Attachment. I Name: Robert E. Smith

Title:

Senior Vice President,'roduction & Engineering Facility: R.E. Ginna Nuclear Power Plant Docket No.: 50-244 Basic Component: Safety Related Motor Operated Valve (MOV)

Actuators Supplier: Limitorque Corporation 11 Nature of Defect: Loose torque switch mounting socket head bolts and/or wire termination bolts associated with SMA-type torque switches found on 19 of 26 valve actuators inspected for wiring configuration. Twenty-six of 107 MOV actuators installed at R.E. Ginna Nuclear Power Plant contained SMA-type torque switches. Torque switch material is a black, fibrous, laminated phenolic material.

Date Obtained: This information was developed during the 1989 and 1990 refueling outage inspections for Electrical Controlled Configuration Drawing Upgrade Project.

Basic Components Affected:

Fourteen safety related MOV actuators (five were non-safety related).

Corrective Action: Immediate corrective action was to tighten the loose bolting. The torque switches are being replaced as scheduled, during a Preven-tive Maintenance Actuator Refurbishment Program. MOV actuators are now on a three year preventive maintenance inspection program for EQ operators, five year preventive maintenance inspection program for safety-related but not EQ and ten year preventive maintenance inspection program for non-safety related actuators.

Responsible Individual for Action:

Thomas A. Marlow, Superintendent Ginna Support Services

Attachment I (continued)

Time to Complete Action:

All loose bolting has been tightened or replaced during refurbishment.

Advice Related to Defect:

Loose bolting had not progressed to a degree that demonstrated an impact on operability at time of defect identification. Torque switch material is a,type supplied with 1967 vintage actuators.