High Temperatures Reduce Limitorque AC Motor Operator TorqueML031070330 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
09/16/1993 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-93-074, NUDOCS 9309100374 |
Download: ML031070330 (11) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
K-/UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 September
16, 1993 NRC INFORMATION
NOTICE 93-74: HIGH TEMPERATURES
REDUCE LIMITORQUE
AC MOTOR OPERATOR TORQUE
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
that high ambient temperatures
can reduce ac motor torque capability
in Limitorque
motor operators.
It is expected that recipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not NRC requiyements;
therefore, no specific action or written response is required.Background
In order to size a motor operator to a given valve, the expected operator torque capable of being developed
under design-basis
conditions
is calculated.
The operator torque output is directly related to the torque output of the operator motor. For dc motor operators, Limitorque
has published
derating factors that are applied to high ambient temperature
applications.
However, until recently, no derating information
was available
for Limitorque
motor operators
equipped with ac motors.DescriDtion
of Circumstances
In response to NRC questions, Limitorque
Corporation
established
a test program to evaluate whether elevated ambient temperatures
could significantly
affect ac motor output torque. In October of 1992, Limitorque
completed testing of five ac motors. This testing indicated
that ac motor stall torque values decreased
significantly
with increasing
ambient temperatures.
The measured torque reductions
ranged from 14 to 25 percent for ambient temperature
increases
from 24°C [75°F] to 169 0 C [336*F]. Limitorque
contracted
with its main motor supplier, Reliance Motor Co., to calculate
the expected stall torque reduction
for all Limitorque/Reliance
ac motor designs.On May 13, 1993, Limitorque
issued a report about a potential
10 CFR Part 21 condition.
The report contained
a tabulation
of motor types and expected torque reductions
for ambient temperature
increases
from 25*C [77 0 F] to 180 0 C 9309100374 x IotNc4 c 2~°>10?- /I.c
IN 93-74'September
16, 1993 [356°F]. This data is given in Attachment
1. Limitorque
has since indicated that the torque reductions
would be applicable
only for motors in ambient conditions
above 40*C [104 0 F] as the motors are designed to deliver full rated torque up to 40C [104'F].Limitorque
has stated that the torque reduction
is linear with respect to temperature.
The Limitorque
table also contains information
on the expected reduction
in locked rotor current at elevated temperatures.
The reduced locked rotor current would provide a slightly higher motor terminal voltage.Although this would improve the calculated
reduced voltage motor performance, it would not compensate
for the torque reduction
resulting
from an elevated temperature.
Limitorque
further stated that motor temperature
rise as a result of prior motor energization
and motor run time (valve stroke time) must be accounted
for.Additional
information
concerning
motor operator performance
can be found in NRC Inspection
Report 99900100/93-01 issued June 28, 1993.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.ast @ A, Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
Jeffrey B. Jacobson, NRR (301) 504-2977 Thomas G. Scarbrough, NRR (301) 504-2794 Attachments:
1. Current/Torque
Changes from 25 to 180 Centigrade
2. List of Recently Issued NRC Information
Notices
-IN 93-74 September
16, 1993 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Orignal signed by Al Chaffee for/Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Jeffrey B. Jacobson, NRR (301) 504-2977 Thomas G. Scarbrough, NRR (301) 504-2794 Attachments:
1. Current/Torque
Changes from 25 to 180 Centigrade
2. List of Recently Issued NRC Information
Notices* r~a Prcovimic~
Cnnrijrr~nrP
OFFICE: *RSIB:DRIL
NAME: JBJacobson
DPNorkin EVImbro CERossi DATE: 08/12/93 08/12/93 08/13/93 08/16/93._ , _ _ ,__ , -, _ _ ., _ ..1 OFFICE: *EMEB:DE *OGCB:DORS
D:DgRW R NAME: TGScarbrough
RJKiessel
DGable GHMarcus BKGrimes DATE: 1 08/23/93 09/01/93 09/01/93 09/08/93 09//193 Document Name: 93-I4.IN
Attacment
1 IN 93-74 September
16, 1993 Curiznt/Torque
Changes from 25 to 180 Centigrade
'a#1 P8 2'#/1800 5'#/1800 5'#/1800 7.5'#J1800
10'#/1800 15'#/1800 25'#/1800 40'#/1800 60'#/1800 60'#/1800 80'#/1800 100'#/1800
200'#/1800
250'#/1800
300'#I1800
2'#/3600 5'#13600 5'#/3600 7.5'#/3600
10'#13600 15'#/3600 25'#13600 40'#/3600 40'#/3600 60'#/3600 80'#/3600 100'#/3600
150'#/3600
200'#/3600
250'#/3600
300'#/3600
400'#/3600
Frame 56 48 56 56 56 56 56 56 58 180 210 210 256 256 326 48 48 56 56 56 56 56 56 180 210 210 256 256 326 326 326 365 Mu2e3#M2735A M2734 M1658 M2925 M1468 M1476 M1480 M1488 M5204 SK-59454 SK-59423 SK-59419A SK-4177 SK-34193 SK-34183 413018-03 M199 M1454 M1457 M1458 M1460 M1463 M4635 SK-59450 SK-59446 SK-59448 SK-34176 SK-34184 SK-34188 SK-34173 SK44171 SK44800-% Current 27.8%29.0%21.8%22.4%26.9%23.7%23.1%21.1%20.8%19.6%16.1%17.0%13.5%11.8%11.7%28.3%27.7%24.7%27.6%23.5%19.2%16.2%27.9%16.2%18.2%18.0%14.1%13.9%10.5%9.3%10.8%8.8%% Torq Loss 20.7%18.6%21.9%5.7%27.7%23.1%23.2%23.4%20.9%18.2%15.8%13.1%9.0%6.9%5.8%16.0%18.5%26.8%16.7%30.8%21.4%24.1%15.9%11.8%16.5%18.3%9.8%10.0%3.4%3.4%2.9%-1.8%'
I n Z b C)*0--:0 0 N m CQ)m C '0 0 Z a o02-I Xn =o (30 (0 o _1 o0c o- 0 V-1 ow z -Attachment
2 IN 93-74 September
16. 1993 Page I of I LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Date of Information
Notice No. Subject 93-73 Criminal Prosecution
of Nuclear Suppliers
for Wrongdoing
93-72 Observations
from Recent Shutdown Risk and Outage Management
Pilot Team Inspections
93-71 Fire at Chernobyl
Unit 2 93-70 Degradation
of Boraflex Neutron Absorber Coupons 93-69 Radiography
Events at Operating
Power Reactors licensees.
93-68 Failure of Pump Shaft Coupling Caused by Temper Embrittlement
during Manufacture
92-16, Loss of Flow from the Supp. 2 ResIdual Heat Removal Pump during Refueling Cavity Oraindown 93-67 Bursting of High Pressure Coolant Injection
Stem Line Rupture Discs Injures Plant Personnel 93-66 Switchover
to Hot-Leg Injection
Following A Loss-of-Coolant
Accident in fres-surized Water Reactors'I L Operat'ng
License CP
Permit Issuance Issued to 09/15/93 All NRC licensees.
09/14/93 All holders of OLs or CPs for nuclear power reactors.09/13/93 All holders of OLs or CPs for nuclear power reactors.09/10/93 All holders of OLs or CPs for nuclear power reactors.09/02/93 All holders of OLs or CPs for nuclear power reactors and all radiography
09/01/93 All holders of OLs or CPs for nuclear power reactors.08/23/93 All holders of OLs or CPs for nuclear power reactors.08/16/93 All holders of OLs or CPs for nuclear power reactors.(08/16/93 All holders of OLs or CPs for pressurized
water reactors.
IN 93-xx September
xx, 1993 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Jeffrey B. Jacobson, NRR (301) 504-2977 Thomas G. Scarbrough, NRR (301) 504-2794 Enclosures:
1. Current/Torque
Changes from 25 to 180 Centigrade
2. List of Recently Issued NRC Information
Notices* C^i^ Dy-pA,4wIc
rnnemitronra
OFFICE: *RSIB:DRIL
I *C:RSIB:DRIL
NAME: JBJacobson
DPNorkin EVImbro CERossi nATr.no ii 9 /02 Rl/I 2 /IQ 08/13/93 08/16/93 I I L. I Ia S. rIe .r I ,_ -- I --, OFFICE: *EMEB:DE _ *OGCB:DORS
D:DORS:NRR
NAME: TGScarbrough
RJKiessel
DGable GHMarCus K BKGrimes DATE: 1 08/23/93 9/ 1/93 9/ 1/93 9/,?/93 9 Document Name: NKL1IN.3!0
for.Additional
information
concerning
motor operator performance
can be found in NRC kIspection
/eport 99900100/93-01 issued June 28, 1993.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
Jeffrey B. Jacobson, NRR (301) 504-2977 Thomas G. Scarbrough, NRR (301) 504-2794 Enclosures:
1. Current/Torque
Changes from 25 to 180 Centigrade
2. List of Recently Issued NRC Information
Notices Document Name: nrcin.391* Previously
Concurred OFFICE: *RSIB:DRIL
NAME: JBJacobson
DPNorkin EVImbro CERossi nATFP e I 0lR12/QA I n8/12/93 I 08/13/93 1 08/16/93 VF_ IL._ I ___- __ __ _ __ _ ___I____ ___ ____ __ --T --__ _ _OFFICE: *EMEB:DE OGCB:DORV
gTech Ed C:OGCB:DORS
D:DORS:NRR
NAME: TGScarbrough
RJKiesse __77___ GHMarcus BKGtimes DATE: 08/23/93 09/) /93 09// /93 09/ /93 09/l g 3 IN 93-XX August 18, 1993 On May 13, 1993, Limitorque
issued a "Potential
10 CFR 21 Condition" report which contained
a tabulation
of motor types and expected torque reductions
for ambient temperature
increases
from 250C to 1800C. This tabulated
data is attached as Enclosure
(1). Limitorque
has since Indicated
that the torque reductions
would only be applicable
for motors in ambient conditions
above 40°C as the motors are designed to deliver full rated torque up to 40C.Limitorque
has stated that the torque reduction
is linear with respect to temperature.
The Limitorque
table also contains information
on the expected reduction
in locked rotor current at elevated temperatures.
The reduced locked rotor current would provide a slightly higher motor terminal voltage.This would improve the calculated
reduced voltage motor performance, however, not nearly enough to compensate
for the torque reduction
due to elevated temperature.
Also, Limitorque
stated that motor temperature
rise due to prior motor energization
and motor run time (valve stroke time) must be accounted for.Additional
information
concerning
motor operator performance
can be found in NRC inspection
report 99900100/93-01 issued June 28, 1993.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
Jeffrey B. Jacobson, NRR (301) 504-2977 Thomas G. Scarbrough, NRR (301) 504-2794 Enclosure
1: Current/Torque
Changes from 25 to 180 Centigrade
Distribution:
JBJacobson
DPNorkin EVImbro RPZimmerman
CERossi BKGrimes Central Files DOEA R/F RSIB R/F* Previously
Concurred_
I OFFICE: RSIB:DRIL
SC:RSIB:DRIL
TECH EDITOR C:RSIB:DRIL
NAME: JBJacobson*
DPNorkin*
EVImbro*DATE: 08/12/93 08/12/93 08/ /93 08/13/93 OFFICE: D:DRIL:NRR
E D:DOEA:NRR
NAME: CERossi* TGScarbrough
BKGrimes l DATE:_08/16/93
08/1930 /93 I 08/ /93 8 As .-n^rllrMKIT
UMAME. * \ TJFnNfnT .1R.1 OFFICIAL RECORD COPY UVI-WIL11 I IVIVIL. U. N &I'll %#law I .---
IN 93-XX August 13, 1993 On May 13, 1993, Limitorque
issued a 'Potential
10 CFR 21 Condition 3 report which cottlined
a tabulation
of motor types and expected torque reductions
for ambient temperature
increases
from 25"C to 180"C. This tabulated
data is attached as Enclosure
(1). Limitorque
has since indicated
that the torque reductions
wouMd only be applicable
for motors in ambient conditions
above 400C as the moto.ds are designed to deliver full rated torque up to 40*C.Limitorque
has stat that the torque reduction
is linear with respect to temperature.
The torque table also contains information
on the expected reduction
in locked rotor current at elevated temperatures.
The reduced locked rotor current wou'd provide a slightly higher motor terminal voltage.This would improve the cal ulated reduced voltage motor performance, however, not nearly enough to compen ate for the torque reduction
due to elevated temperature.
Also, Llmitorq stated that motor temperature
rise due to prior motor energizatlon
and motor r time (valve stroke time) must be accounted for.Additional
Information
concerning
tor operator performance
can be found in NRC inspection
report 99900100/93-01 ssued June 28, 1993.This information
notice requires no spe ific action or written response.
If you have any questions
about the informa on in this notice, please contact one of the technical
contacts listed belo or the appropriate
Office of Nuclear Reactor Regulation (NRR) project ma ger.Brian K. Gmines, Director 1 .Division of Operat Office of Nucear Reactor Regulation
Technical
contacts:
Jeffrey B. Jacboson, NRR (301) 504-2977 Thomas G. Scarbrough, NRR (301) 504-2794 Enclosure
1: Current/Torque
Changes from 25 to 180 Centlgr e Distribution:
JBJacobson
DPNorkin EVImbro RPZlmmerman
CERossi BKGrimes Central Files DOEA R/F RSIB R/F \* Previously
Concurred OFFICE: RSIB:DRIL
/ SC:RSIB:DRIL
TECH EDITOR C:RSIB:oRIL
NAME: JBJacobson*
DPNorkin*
EVImbro*DATE: 0812/93 [08/12/93
08/ /93 08/13/93 OFFICE: D:DRIL:NRR
D:DOEA:NRR
lNAME: C05; BKGrimes DATE: 08//ip93 08/ /93 I__Tat ______ __.____OFFICIAL RECORD COPY DOUMENT NAME: G ;\ INFONO I .d JJ
IN 93-XX August 13, 1993 0 May 13, 1993, Limitorque
issued a 'Potential
10 CFR 21 Condition" report whi contained
a tabulation
of motor types and expected torque reductions
for amble t temperature
increases
from 250C to 1800C. This tabulated
data is attach as Enclosure
(1). Limitorque
has since indicated
that the torque reductio would only be applicable
for motors in ambient conditions
above 400C as th motors are designed to deliver full rated torque up to 400C.Limitorque
h stated that the torque reduction
is linear with respect to temperature.
e Limitorque
table also contains information
on the expected reduction
in 1c -ted rotor current at elevated temperatures.
The reduced locked rotor curr t would provide a slightly higher motor terminal voltage.This would improve he calculated
reduced voltage motor performance, however, not nearly enough to ompensate
for the torque reduction
due to elevated temperature.
Also, Iitorque stated that motor temperature
rise due to prior motor energization
and tor run time (valve stroke time) must be accounted for.Additional
information
conce ing motor operator performance
can be found in NRC inspection
report 99900100 3-01 issued June 28, 1993.This information
notice requires specific action or written response.
If you have any questions
about the in Qrmation in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) proJed4 manager.Brian .Grimes, Director Divisioh of Operation
Events Assessment
Office o#?Nuclear
Reactor Regulation
Technical
contacts:
Jeffrey B. Jacboson, NRR (301) 504-2977 Thomas G. Scarbrough, NRR (301) 504-2794 Enclosure
1: Current/Torque
Changes from 25 to 180 Cent grade Distribution:
JBJacobson
DPNorkin EVImbro RPZimmerman
CERossi BKGrimes Central Files DOEA R/F RSIB R/F* Previously
Concurred
_OFFICE: RSIB:DRIL
SC:RSIB:DRIL
TECH EDITOR C:RSIB'.-DRIL
NAME: JBJacobson*
DPNorkin*
Vlmbro DATE: 08/12/93 08/12/93 08/ /93 08 93 OFFICE: D:DRIL:NRR
D:DOEA:NRR
_NAME: CERossi BKGrimes DATE: 08/ /93 08/ /93 ___________
_____________
OFFIIAL ECOR LUP UULI.Ip4in
i mIir IE 1-; u;zeu1u,.uuu
1 OFFICIAL RECORD COPY UU6UMtNj MM; U;\JL11rV1'4V1.VUU
IN 93-XX August 12, 1993 On Ma 13, 1992, Limitorque
issued a "Potential
10 CFR 21 Condition" report which ontained a tabulation
of motor types and expected torque reductions
from 25 to 1800C. This tabulated
data is attached as Enclosure
(1).Limitorqu
has since indicated
that the torque reductions
would only be applicable
or motors in ambient conditions
above 40eC as the motors are designed to eliver full rated torque up to 40C.Limitorque
has lso stated that the torque reduction
is linear with respect to temperature.
Th Limitorque
table also contains information
on the expected reduction
in locatd rotor current at elevated temperatures.
The reduced locked rotor curren would provide a slightly higher motor terminal voltage.This would improve t calculated
reduced voltage motor performance, however, not nearly enough to mpensate for the torque reduction
due to elevated temperature.
Also, LimUtorque
stated that motor temperature
rise due to prior motor energization
and m or run time (valve stroke time) must be accounted for.Additional
information
conce ing motor operator performance
can be found in NRC inspection
report 99900100 3-01 Issued June 28, 1993.This information
notice requires o specific action or written response.
If you have any questions
about the i formation
in this notice, please contact one of the technical
contacts liste below or the appropriate
Office of Nuclear Reactor Regulation (NRR) pro ct manager.Brian K. Grimes, Director Divisi of Operation
Events Assessment
Office Nuclear Reactor Regulation
Technical
contacts:
Jeffrey B. Jacboson, NRR (301) 504-2977 Thomas G. Scarbrough, NRR (301) 504-2794 Enclosure
1: Current/Torque
Changes from 25 to 180 Ce tigrade Distribution:
JBJacobson
DPNorkin EVImbro RPZimmerma
CERossi BKGrimes Central Files DOEA R/F RSIB R/F OFFICE: RSIB:DRIL
RIL TECH EDITOR RSI:DRILlNAME: JBJacobJ0#
r o Hhtnbk DATE: 108/)I J_____ _93 08/ /93 08/ 939 OFFICE: D:DRIL:NRR
D:DOEA:NRR
m NAME: CERossi BKGrimes \DATE: 08/ /93 08/ /93 \nfFITTlAI
DFrnR) rAYDV HlAlIIMFCT
WAMF-. n. TUFlAflT Io"I...... ovrd -o-v wvv I u'.J'.uIEIcn1 I *leriL. U. X LIS I % UVI .U IV
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list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
... further results |
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