High Temperatures Reduce Limitorque AC Motor Operator TorqueML031070330 |
Person / Time |
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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 1690C [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
0 0
torque reductions for ambient temperature increases from 25*C [77 F] to 180 C
9309100374 xIotNc4~°> 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 0F] 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 *SC:RSIB:DRIL *C:RSIB:DRIL *D:DRIL:NRR
NAME: JBJacobson DPNorkin EVImbro CERossi
DATE: 08/12/93 08/12/93 08/13/93 08/16/93
._, _ _ ,__ , -, _ _ . , _ . .1 OFFICE: *EMEB:DE *OGCB:DORS *Tech Ed *C: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
% Current % Torq
'a#1 P8 Frame Mu2e3# Loss
2'#/1800 56 M2735A 27.8% 20.7%
5'#/1800 48 M2734 29.0% 18.6%
5'#/1800 56 M1658 21.8% 21.9%
7.5'#J1800 56 M2925 22.4% 5.7%
10'#/1800 56 M1468 26.9% 27.7%
15'#/1800 56 M1476 23.7% 23.1%
25'#/1800 56 M1480 23.1% 23.2%
40'#/1800 56 M1488 21.1% 23.4%
60'#/1800 58 M5204 20.8% 20.9%
60'#/1800 180 SK-59454 19.6% 18.2%
80'#/1800 210 SK-59423 16.1% 15.8%
100'#/1800 210 SK-59419A 17.0% 13.1%
200'#/1800 256 SK-4177 13.5% 9.0%
250'#/1800 256 SK-34193 11.8% 6.9%
300'#I1800 326 SK-34183 11.7% 5.8%
2'#/3600 48 413018-03 28.3% 16.0%
5'#13600 48 M199 27.7% 18.5%
5'#/3600 56 M1454 24.7% 26.8%
7.5'#/3600 56 M1457 27.6% 16.7%
10'#13600 56 M1458 23.5% 30.8%
15'#/3600 56 M1460 19.2% 21.4%
25'#13600 56 M1463 16.2% 24.1%
40'#/3600 56 M4635 27.9% 15.9%
40'#/3600 180 SK-59450 16.2% 11.8%
60'#/3600 210 SK-59446 18.2% 16.5%
80'#/3600 210 SK-59448 18.0% 18.3%
100'#/3600 256 SK-34176 14.1% 9.8%
150'#/3600 256 SK-34184 13.9% 10.0%
200'#/3600 326 SK-34188 10.5% 3.4%
250'#/3600 326 SK-34173 9.3% 3.4%
300'#/3600 326 SK44171 10.8% 2.9%
400'#/3600 365 SK44800- 8.8% -1.8%'
Z
a
I
Z
n
bC)
- -
-I Attachment 2 IN 93-74
- 0 0 September 16. 1993 Page I of I
Nm Xn =
(30
o02 (0
CQ)
LIST OF RECENTLY ISSUED
o _1 NRCINFORMATION NOTICES
m o
C
0' o- 0V-1 Information Date of
Notice No. Subject Issuance Issued to
o0c
z -
0 09/15/93 All NRC licensees.
Criminal Prosecution of
(
93-73 Nuclear Suppliers for
ow Wrongdoing
93-72 Observations from Recent 09/14/93 All holders of OLs or CPs
Shutdown Risk and Outage for nuclear power reactors.
Management Pilot Team
Inspections
93-71 Fire at Chernobyl Unit 2 09/13/93 All holders of OLs or CPs
for nuclear power reactors.
93-70 Degradation of Boraflex 09/10/93 All holders of OLs or CPs
Neutron Absorber Coupons for nuclear power reactors.
93-69 Radiography Events at 09/02/93 All holders of OLs or CPs
Operating Power Reactors for nuclear power reactors
and all radiography
licensees.
93-68 Failure of Pump Shaft 09/01/93 All holders of OLs or CPs
Coupling Caused by for nuclear power reactors.
Temper Embrittlement
during Manufacture
92-16, Loss of Flow from the 08/23/93 All holders of OLs or CPs
Supp. 2 ResIdual Heat Removal for nuclear power reactors.
Pump during Refueling
Cavity Oraindown
93-67 Bursting of High 08/16/93 All holders of OLs or CPs
Pressure Coolant for nuclear power reactors.
Injection Stem Line
Rupture Discs Injures
Plant Personnel
93-66 Switchover to Hot-Leg 08/16/93 All holders of OLs or CPs
Injection Following for pressurized water
A Loss-of-Coolant reactors.
Accident in fres- surized Water Reactors
'I L Operat'ng License
CP
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 *SC:RSIB:DRIL I*C:RSIB:DRIL *D:DRIL:NRR
NAME: JBJacobson DPNorkin EVImbro CERossi
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08/16/93 I
OFFICE: *EMEB:DE _ *OGCB:DORS *Tech Ed C:OGCB:_ORS 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.
in
Additional information concerning motor operator performance can be found
NRC kIspection /eport 99900100/93-01 issued June 28, 1993.
If
This information notice requires no specific action or written response.
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
OFFICE: *RSIB:DRIL *SC:RSIB:DRIL *C:RSIB:DRIL *D:DRIL:NRR
NAME: JBJacobson DPNorkin EVImbro CERossi
nATFPe
VF_ IL._ ___-
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I n8/12/93
___I____ ___
I 08/13/93
____ __ - -
1 08/16/93 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
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
CERossi* TGScarbrough BKGrimes l
NAME:
DATE:_08/16/93 /93
08/1930 I 08/ /93 8
.1R.1 As- . n^rllrMKIT UMAME. * \ TJFnNfnT
UVI-WIL11 I IVIVIL. U. N&I'll %#lawI .---
OFFICIAL RECORD COPY
IN 93-XX
August 13, 1993 3 On May 13, 1993, Limitorque issued a 'Potential 10 CFR 21 Condition 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, Director1 .
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 \
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
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 ___________ _____________
i mIir
IE u;zeu1u,.uuu
1-; 1 OFFICIAL RECORD COPY ECOR
LUP
OFFIIAL UULI.Ip4in
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:DRILl
NAME: JBJacobJ0#o r Hhtnbk
DATE: 108/)I J_____ 939 _93 08/ /93 08/
OFFICE: D:DRIL:NRR D:DOEA:NRR m
NAME: CERossi BKGrimes \
DATE: 08/ /93 08/ /93 \
nfFITTlAI DFrnR) rAYDVI
wvv
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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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