ML17250B183: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:ACCELERATED DIS ii~UTION DEMONSTIWTION SYSTEM REGULATORY INFORMATION DXSTRXBUTXON SYSTEM (RIDS)ACCESSION NBR:9006110336 DOC.DATE: 90/05/31 NOTARIZED:
{{#Wiki_filter:ii ACCELERATED DIS
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.
UTION DEMONSTIWTION SYSTEM REGULATORY INFORMATION DXSTRXBUTXON SYSTEM (RIDS)
Office of Nuclear Reactor Regulation, Director (Post 870411  
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:==
==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: TITLE: Part 21 Rept (50 DKT)NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
Part 21 rept re potential matl defect of SMA type torque switches supplied by Limitorque during late 1960s.
D 8 05000244/RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: AEOD/DOA IRM TECH ADV NRR VARGA,S NRR/DOEA/OGCB11 NRR/DST 8E2 RES/DSIR/EIB RGN2 RGN4 EXTERNAL: INPO RECORD CTR NRC PDR COPIES LTTR ENCL 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DSP/TPAB NRR CRUTCHFIELD NRR/DLPQ/LPEB10 DRIS/RVIB9D RE 01 RGB.RGN3 RGN5 LPDR'S I C S I LVER g E COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS:
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
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 22 A D D
                                                                                                  /
<(IIZZus qi'ZZZuZ'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:
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
Dr.Thomas E.Murley Office of Nuclear Reactor Regulation Washington, D.C.20555  
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
A D
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
 
    <( IIZZus qi'ZZZuZ
  '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:==
==Subject:==
Notification of 10CFR, Part 21 R.E.Ginna Nuclear Power Station Docket No.50-244 Licensee No.DPR-18  
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
 
  'l A,
 
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
 
( ~
C
 
~ 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


==Dear Dr.Murley:==
Attachment   I (continued)
Rochester Gas and Electric is submitting the attached 10CFR, Part 21 Evaluation and Notification.
Time to Complete Action:
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.
All   loose bolting has been   tightened or replaced during refurbishment.
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.
Advice Related to Defect:
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.
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.}}
9006li03 6 900531 PDR ADOCK 05000244 PDC
'l A, 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
(~C
~Li Attachment.
I Name: Title: Facility: Docket No.: Robert E.Smith Senior Vice President,'roduction
&Engineering R.E.Ginna Nuclear Power Plant 50-244 Basic Component:
Supplier: Safety Related Motor Operated Valve (MOV)Actuators Limitorque Corporation Nature of Defect: 11 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: Corrective Action: Fourteen safety related MOV actuators (five were non-safety related).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.}}

Revision as of 19:46, 29 October 2019

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)
v • d • e


Text

ii ACCELERATED DIS

~

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

/

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

A D

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

<( IIZZus qi'ZZZuZ

'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

'l A,

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

( ~

C

~ 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.

Retrieved from "https://kanterella.com/w/index.php?title=ML17250B183&oldid=2000572"