Potential Inadequacies in the Prediction of Torque Requirements for and Torque Output of Motor-Operated Butterfly ValvesML031210639 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
---|
Issue date: |
09/28/1994 |
---|
From: |
Grimes B Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-94-069, NUDOCS 9409210211 |
Download: ML031210639 (9) |
|
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 |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 September 28, 1994 NRC Information Notice 94-69: POTENTIAL INADEQUACIES IN THE PREDICTION OF
TORQUE REQUIREMENTS FOR AND TORQUE OUTPUT OF
MOTOR-OPERATED BUTTERFLY VALVES
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 to potential inadequacies in the prediction of
torque requirements for and torque output of motor-operated butterfly valves.
It is expected that recipients will review the information for applicability
to their facilities and consider actions, as appropriate, to avoid similar
events or problems. However, suggestions contained in this information notice
are not NRC requirements; therefore, no specific action or written response is
required.
Description of Circumstances
Several problems regarding inadequacies in the prediction of torque
requirements to operate butterfly valves and available torque from their motor
actuators have been reported through Generic Letter (GL) 89-10 reviews.
A significant example pertains to an event that occurred at the Catawba
nuclear power plant.
On February 25, 1993, the licensee for the Catawba facility determined that
both loops of the service water systems had been inoperable since August 1992, because three of the four service water pump discharge valves could not open
against the pump discharge pressure. In August 1992, the licensee had reduced
the torque switch settings on two of the four service water system discharge
valves (one in each train) to address a concern that, under minimum voltage
conditions, the motor operators for these valves might stall at a torque value
lower than the maximum torque setpoint. The new torque switch settings were
measured on a test bench and judged to be adequate based on manufacturer
sizing equations. Following this modification of the two valves, differential
pressure testing was not conducted to ensure the valves would function under
design-basis conditions.
iyo
9409210211 PD
oJsLIq 7(j I,
Wy~k ffy an'ee
IN 94-69 September 28, 1994 The licensee determined that these valves failed to open at the established
torque output because the seat material had hardened with age and bearings had
degraded with raw water service. Such other variables as gearbox efficiency, application-specific flow characteristics, and packing friction also affect
the torque required to operate a butterfly valve. This event indicated that
the engineering analysis performed to derive the torque requirements of the
two referenced valves did not adequately address age degradation of the
valves.
Some significant problems at other nuclear power plants relating to torque
requirements of butterfly valves and available torque from their motor
actuators are discussed below:
- In March 1994, the licensee for the Perry facility found that certain
butterfly valves required higher seating torque than expected. Dynamic
testing showed that the bearing friction coefficient for certain
butterfly valves with stainless steel bushings was higher than the value
originally assumed (0.25) in the calculations. Specifically, the
bearing coefficient of friction was 0.634 for a fuel pool cooling and
cleanup valve with stainless steel bushings, and 0.334 for an emergency
service water valve with graphite-lubricated stainless steel bushings.
The licensee investigated the effect of this information on 17 motor- operated valves, the entire plant population of motor-operated butterfly
valves with stainless steel bushings. No operability problems were
found. However, the licensee is evaluating possible modifications to
improve margins for the four butterfly valves in the fuel pool cooling
and cleanup system.
- In November 1993, the licensee for the Palo Verde facility determined
that the condensate storage tank isolation valve would not have opened
or closed completely under design-basis conditions with the as-found
torque switch settings. The safety function of the valve is to isolate
the condensate storage tank should non-seismic piping rupture
downstream. The licensee also found that a containment isolation valve
would not have closed under design-basis conditions with the as-found
torque switch settings because the measured closing torque at torque
switch trip was less than the minimum torque required in accordance with
the design-basis calculation.
- In March 1993, the licensee for the Comanche Peak facility reported that
a valve in the containment hydrogen purge system had demonstrated a
lower torque output at torque switch trip during loaded testing on a
torque test stand than that delivered at torote switch trip during
static insitu testing. The licensee demonstrated that no operability
concern existed for this valve. However, this apparent reduction in
torque output at torque switch trip under loaded conditions for a
motor-operated butterfly valve could have implications for other motor- operated valves.
IN 94-69 September 28, 1994 - In May 1992, the licensee for the Zion facility determined that 12 of
the 15 butterfly valves in the service water system were inoperable
because their torque switch settings did not support the original design
basis maximum differential pressure of 862 kPa [125 psid]. The
remaining three valves would have supported a maximum differential
pressure of 862 kPa [125 psid]; however, it would not have supported the
current design requirement of 971 kPa [141 psid]. This event was caused
by deficiencies in the pre-service design installation testing.
- In March 1992, the licensee for the Grand Gulf facility determined that
the actuators for the suppression pool makeup system dump valves were
undersized (they could not meet the torque requirements). It was found
that the actuators were undersized because the flow rate specified in
the design specification for the valves, which was used by the valve
manufacturer to size the actuators, was the minimum required flow rate
to ensure a "post-loss of coolant accident" drywell vent coverage of at
least two feet above the top row vents with maximum emergency core
cooling systems pump-down of the suppression pool. The size of the
valves should have been determined using maximum expected design-basis
flow rate based on the actual configuration of the system.
- In March 1991, while performing diagnostic tests on a butterfly valve of
the primary containment purge and exhaust system, the licensee for the
Limerick facility discovered that the "as-found" torque switch setting
for the valve motor actuator was too low. This would have resulted in
the motor actuator tripping on high torque before the valve could
adequately close and seat if this valve was required to close during a
design-basis differential pressure condition. In addition, the testing
indicated that the actual motor actuator torque output for this valve
was lower than the design torque output requirement. As a result, the
valve would not have been capable of performing its primary containment
isolation design function. When the licensee reviewed the original
startup test records for all motor-operated butterfly valves in the same
system, it found eight other valves that did not meet the design torque
specifications for adequate valve seating in the event of a design basis
differential pressure condition, or for which no test data were
available to support the adequacy of butterfly valve testing.
Discussion
These examples of recent problems illustrate that many variables affecting the
application of butterfly valves, including flow, pressure, seat material
degradation, gearbox efficiency, turbulence in the system, as well as packing
and bearing frictions, can have an impact on the required tor;ue to operate a
butterfly valve and on the torque output of their motor actuators. A primary
basis for the NRC issuance of Generic Letter (GL) 89-10, "Safety-Related
Motor-Operated Valve Testing and Surveillance," with its request to test
safety-related motor-operated valves under design-basis conditions where
IN 94-69 September 28, 1994 practicable, is the uncertainties surrounding the prediction of torque/thrust
requirements by valve vendors.
Related Generic Communications
Performance Prediction Program by the Electric Power Research
Institute," November 30, 1993
Butterfly Valves To Operate Because Valve Seat Friction Was
Underestimated," March 22, 1990
° NRC Information Notice 84-04, "Failure of Elastomer Seated Butterfly
Valves Used Only During Cold Shutdowns," January 18, 1984 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.
Director 4cc
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Thomas G. Scarbrough, NRR
(301) 504-2794 William T. Orders, RII
(803) 383-4571 Perry C. Hopkins, RII
(803) 831-2963 Christine Lipa, RIII
(319) 851-5111 Attachment:
List of Recently Issued NRC Information Notices
444)' zJa
-Attachment
IN 94-69 September 28, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-68 Safety-Related Equip- 09/27/94 All holders of OLs or CPs
ment Failures Caused by for nuclear power reactors.
Faulted Indicating Lamps
94-67 Problem with Henry 09/26/94 All holders of OLs or CPs
Pratt Motor-Operated for nuclear power reactors.
Butterfly Valves
94-66 Overspeed of Turbine- 09/19/94 All holders of OLs or CPs
Driven Pumps Caused by for nuclear power reactors.
Governor Valve Stem
Binding
94-65 Potential Errors in 09/12/94 All U.S. Nuclear Regulatory
Manual Brachytherapy Commission medical
Dose Calculations licensees.
Generated Using a
Computerized Treatment
Planning System
94-64 Reactivity Insertion 08/31/94 All holders of OLs or CPs
Transient and Accident for nuclear power reactors
Limits for High Burnup and all fuel fabrication
Fuel licensees.
94-63 Boric Acid Corrosion of 08/30/94 All holders of OLs or CPs
Charging Pump Casing for pressurized water
Caused by Cladding Cracks reactors.
94-62 Operational Experience 08/30/94 All holders of OLs or CPs
on Steam Generator Tube for pressurized water
Leaks and Tube Ruptures reactors.
94-61 Corrosion of William 08/25/94 All holders of OLs or CPs
Powell Gate Valve Disc for nuclear power reactors.
Holders
94-60 Potential Overpressuriza- 08/22/94 All holders of OLs or CPs
tion of Main Steam System for pressurized-water
reactors.
OL = Operating License
CP = Construction Permit
'~ IN 94-69 September 28, 1994 practicable, is the uncertainties surrounding the prediction of torque/thrust
requirements by valve vendors.
Related Generic Communications
° NRC Information Notice 93-88, "Status of Motor-Operated Valve
Performance Prediction Program by the Electric Power Research
Institute," November 30, 1993 o NRC Information Notice 90-21, "Potential Failure of Motor-Operated
Butterfly Valves To Operate Because Valve Seat Friction Was
Underestimated," March 22, 1990
° NRC Information Notice 84-04, "Failure of Elastomer Seated Butterfly
Valves Used Only During Cold Shutdowns," January 18, 1984 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.
original signed by C.I. Grimes
Brian K. Grimes, Director
/ -Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Thomas G. Scarbrough, NRR
(301) 504-2794 William T. Orders, RII
(803) 383-4571 Perry C. Hopkins, RII
(803) 831-2963 Christine Lipa, RIII
(319) 851-5111 Attachment:
List of Recently Issued NRC Information Notices
- See previous concurrences
OFFICE *EMEB:DE *EMEB:DE *EMEB:DE *EMEB:DE *DE:NRR
NAME MKhanna TScarbrough GJohnson RWessman BSheron
DATE [08/01/94 ]08/01/94 I--
108/02/94 I
[08/05/94 .08/26/94 OFFICE I*TECH ED I*OGCB:DORS I*OGCB:DORS IDORSN;.,
NAME IJMain TJKim EDoolittle BGrime I
DATE 1
108/31/94 09/01/94 09/07/94 109/2.1/94 J
DOCUMENT NAME: 94-b9.IN
IN 94-XX
September XX, 1994 practicable, is the uncertainties surrounding the prediction of torque/thrust
requirements by valve vendors.
Related Generic Communications
° NRC Information Notice 93-88, "Status of Motor-Operated Valve
Performance Prediction Program by the Electric Power Research
Institute," November 30, 1993
° NRC Information Notice 90-21, "Potential Failure of Motor-Operated
Butterfly Valves To Operate Because Valve Seat Friction Was
Underestimated," March 22, 1990
o NRC Information Notice 84-04, "Failure of Elastomer Seated Butterfly
Valves Used Only During Cold Shutdowns," January 18, 1984 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: Thomas G. Scarbrough, NRR
(301) 504-2794 William T. Orders, RII
(803) 383-4571 Perry C. Hopkins, RII
(803) 831-2963 Christine Lipa, RIII
(319) 851-5111 Attachments:
List of Recently Issued NRC Information Notices
- See previous concurrences
OFFICE *EMEB:DE *EMEB:DE *EMEB:DE *EMEB:DE *DE:NRR
NAME MKhanna jTScarbrough GJohnson RWessman BSheron
DATE [08/01/94 J08/01/94 08/02/94 L08/05/94 .08/26/94
-
OFFICE I *TECH ED I *OGCB:DORS I *OGCB:DORS I DORS:NRR
NAME JMain TJKim EDoolittle BGrimes -
DATE 08/31/94 09/01/94 09/07/94 09/ /94
--t x u ,!;' ';1--'0,
pP 0V
IN 94-XX
September XX, 1994 practicable, is the uncertainties surrounding the prediction of torque/thrust
requirements by valve vendors. Licensees should remain aware of this basis
for GL 89-10 when setting motor-operated valves, including butterfly valves, based on vendor information, and scheduling followup dynamic testing.
Related Generic Communications
° NRC Information Notice 93-88, "Status of Motor-Operated Valve
Performance Prediction Program by the Electric Power Research
Institute," November 30, 1993
° NRC Information Notice 90-21, "Potential Failure of Motor-Operated
Butterfly Valves To Operate Because Valve Seat Friction Was
Underestimated," March 22, 1990
o NRC Information Notice 84-04, "Failure of Elastomer Seated Butterfly
Valves Used Only During Cold Shutdowns," January 18, 1984 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: Thomas G. Scarbrough, NRR
(301) 504-2794 William T. Orders, RII
(803) 383-4571 Perry C. Hopkins, RII
(803) 831-2963 Attachments:
List of Recently Issued Information Notices
- See previous concurrences
OFFICE *EMEB:DE *EMEB:DE *EMEB:DE *EMEB:DE *DE:NRR
NAME MKhanna TScarbrough GJohnson RWessman BSheron
DATE L08/01/94 ]08/01/94
_ _ _ __ - _
I08/02/94 08/05/94 I
08/26/94 j
nFFTrr I *TECH4 FD OICM:DORS IOG6E&DORS IDORS:NRR
NAME JMain TJ KimR, EK e BGrimes
9ttl
DATE 08/31/94 09/ 1/94 09/7/94 09/ /94
IN 94-XX
August XX, 1994 practicable, is the uncertainties surrounding the prediction of torque/thrust
requirements by valve vendors. Licensees should remain aware of this basis
for GL 89-10 when setting motor-operated valves, including butterfly valves, based on vendor information, and scheduling follow-up dynamic testing.
Related Generic Communications
° NRC Information Notice 93-88, "Status of Motor-Operated Valve
Performance Prediction Program by the Electric Power Research
Institute," November 30, 1993
° NRC Information Notice 90-21, "Potential Failure of Motor-Operated
Butterfly Valves to Operate Because Valve Seat Friction Was
Underestimated," March 22, 1990
° NRC Information Notice 84-04, "Failure of Elastomer Seated Butterfly
Valves Used Only During Cold Shutdowns," January 18, 1984 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
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: Thomas G. Scarbrough, NRR
(301) 504-2794 William T. Orders, RII
(803) 383-4571 Perry C. Hopkins, RII
(803) 831-2963 Attachments:
List of Recently Issued Information Notices
- See previous concurrences -
OFFICE l *EMEB:DE *EMEB:DE *EMEB:DE *EMEB:DE D
NAME MKhanna TScarbrough GJohnson RWessman B
DATE 108/01/94 j08/01/94 J 08/02/94 J 08/05/94 108/1&/94J 4v v
OFFICE ITECH ED IOGCB:DORS IOGCB:DORS I
IDORS:NRR
NAME TJKi EDoolittle BGrimes
DATE 08/3//94 /94 08/ /94 08/ /94 ole.; Qon-mew Acer 14 Ot'-CO're5 ' 4ewt amvec 'krs aftd AJ/eR Rn 7Jecl )ncLt fyer5 Were co/;c;ied. gee evenePr.-V. #Kc (?ptiu.A'be PMa "kS received E-4 A&t
ieCok stACirpfrdled.
|
---|
|
list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994, Topic: Overspeed trip)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level, Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
... further results |
---|