Potential Armature Binding in General Electric Type Hga RelaysML031050360 |
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 |
---|
Issue date: |
03/24/1997 |
---|
From: |
Martin T Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-97-012, NUDOCS 9703200229 |
Download: ML031050360 (10) |
|
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. 20555-0001 March 24, 1997 NRC INFORMATION NOTICE 97-12: POTENTIAL ARMATURE BINDING IN GENERAL
ELECTRIC TYPE HGA RELAYS
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 two General Electric (GE) type HGA relays failed to reposition when the coils
were deeneivizea. It is expected that recipients will review this 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 requirements; therefore, no
specific action or written response is required.
DescriDtion of Circumstances
On May 15, 1996, Commonwealth Edison Company (ComEd) reported that two 12HGA1 7S63 relays installed in the reset logic for the primary containment isolation system at its Dresden
Nuclear Power Station, Unit 3, failed to reposition when operators removed power to the
relay coils. The relay failures resulted in a failure to seal in isolation signals to a main steam
isolation valve and a recirculation sample isolation valve when operators reset a scram signal
after a reactor scram. Consequently, the valves opened when the scram was reset.
Operators used the manual switches in the control room to reclose the valves. ComEd
personnel removed the relays and disassembled them in an attempt to determine the root
cause of the problem. When a root cause could not be determined, the failed relays were
sent to GE Power Management (GE PM), located in Malvem, Pennsylvania, for a thorough
investigation.
Discussion
GE PM reassembled the failed relay submitted by ComEd for a root cause analysis and it
operated properly, both mechanically and electrically. When GE PM performed a
dimensional analysis of the critical parts, however, the assembly hole of the molded contact
support was found to be slightly off-center. GE PM stated that the mold that produces the
contact support was reworked in 1990 to correct for mold wear and to bring the parts within
the design drawing tolerances.
PDR T -E NoTICAE?-2-0/2 97O523Z
IN 97-12 March 24, 1997 GE PM issued Relay Service Advice Letter 516.1 on October 25, 1996, to alert customers
that HGA relays manufactured between January 1989 and June 1991 may have marginal
armature-to-contact support clearance and may be susceptible to armature binding.
However, some licensees may have procured the relays as commercial-grade, or received
them as basic components from a dedicating entity and, therefore, may not have received the
attached GE relay service advice letter. Consequently, some licensees may not have had
the opportunity to evaluate the information in accordance with 10 CFR Part 21.
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.
Thomas . Martin, Director
Division of Reactor Pro-ram Management
Office of Nuclear Reactor Regulation
Technical contacts: K. Naidu, NRR
(301) 415-2980
E-mail: km@nrc.gov
S. Alexander, NRR
(301) 415-2995 E-mail: sda@nrc.gov
D. Skeen, NRR
(301) 415-1174 E-mail: dls@nrc.gov
Attachments:
1. GE Relay Service Advice Letter 516.1 dated October 25, 1996
2. List of Recently Issued NRC Information Notices
SENT BY:GE %URKETING/XALVEk, 2 ;12- 2-96 ;10:12AM ; GENEIRAL ELECTRIC- Attachment
1 IN 97-12 MULTIUN March 24, 1997 GE Power Management
eh~~,I
ie~tncF Camoe
2O C 9dIVrVaget wr At-er
vrr. PA 13j55. 331 RELAY SERVIC ADVIC LETTER
Subject: HGA Armature Binding Number 516.1 Issued by- Customer Ser.ice DaNte: I025/96 Prepared by: Peter A Kotos
There has beme a report of incoMet operation of an HGA17S63 relay (date code: December,
1989). The relay had been continuously energized and failed to provide correct contact operation
when de-na ed. It was reported that the relay armature was not moving firely, it was
mechanically binding at the hinge area
The rCly was returned for examination. We examined the relay and were not able to reproduce
the bning condition that was reported. (TIe relay was returned disassembled. When assembled
the relay operated properly electrically and mechanicaly).
However, a dimensional analysis of the most critical parts dcted that the molded contact
support was slightly out of tolerance. Specifically, the assemblyrhole of the contact support was
slightly off center.
It is conceivable that this ofset cnbined with the manufacturing tolerances of the armature and
anet frame, possible foreign matter in the hnge ar and maybe excessive side pressure applied
to the con=at support when aembled could caie ftiction between the contact support and
magnetic finve resulting in armature binding.
According to our MS actung Engineering the mold that produces the cont support was
reworked in 1990 to correct for mold wear and bring the part weln within the drawing tolerances.
Currenty produced contact supports were checked and are well within the drawing tolerances
and do not produce armature binding.
Based on the field report, it is assumed that some HGA's may have been ipped with a mrinal
condition of armature clearance until this condition was noted by Quality Control and the mold
was corrected.
SENT BY:GE V1RXETING/N'ALVERKN ;12- 2-96 ;10:13.W GEN RLU ELECTRIC- 301 415 2968;; 3. 4
~ Attachment 1 IN 97-12 March 24, 1997 Page 2 SA #516.1 10/25/96 Although it isnot possible to determine exactly when the possible problem began, itis estimated
that relays manufactured between January, 1989, and June, 1991, (Dare Codes: ND. OD, PD,
RD. SD, M, UTD, VID, WD, XI, YD, ZD, NE, OE, PE, RE, SE, TE, UE, VE, WE, XE, YE,
ZE, NT, OF, P., RF, SF, AND TF) are suspect and may be checked for armature binding as
follows:
1. Do-energize the relay, coil and contacts.
2. Close the armature filly by hand, (push amature against the pole, see Fig. 1), and
gradually release. For corret operation, the armature should move to the filly open
position with no binding and with correct contact action. The normally open contacts
should open and the normally closed conta.ts should dose. If binding is detected, we
recommend the foliowing:
For "Nuclear IE" Applications: Contact General Electric Nuclear Energy Division
Customer Srvice Hotline: 1-800-425-8108 and refer to Service Advice No. S16.1.
For "Non - IE: Appkations: A replacement contact support is recommended.
Replacement contact supports (Par Number 006118683Pl) are available on a no-charge basis
and should be ordered through your local GE district Sales Office. Requests for the contact
supports must inc!ude:
A. AreferencetoServiceAdviccNo. 516.1 B. Date codes of the relays for which the replaement contact supports will be used.
Installation of Le contact support may be accomuplished by following the steps outied in
Attachment A.
Replacement contact supports will be available through November 1, 1997.
Labor for installation of the contact support or relay are the responsbility of the purchaser.
GENERAL ELECTRIC - 301 415 2968;; 4/ 4 SENT BY:GE XRKETING/MALVERN ;12- 2-96 ;10:14.0 ;
Attachment 1 IN 97-12 March 24, 1997 ATTACHMENT A - SA #516.1 The contact support should be replaced as follows: (Refer to Fig. 1)
IA Disengage the control spring from the armature end. (Note the groove location of
the spring hook on the armature).
2. Remove the assembly screw with its lockwasher.
3. Remove the nameplate and spring housing assembly.
4. Remove the moving contacts from the contact support and note their location for
correct reassembly.
S. Remove the contact support.
6. Install the new contact support. Make sure the armature is seated properly in the
contact support
7. Locate the moving contacts in the contact support.
8. Initail the nameplate and spring housing assembly.
9. Tighten the assembly screw and lockwasber (16 in-lbs. approx). Hold contact
support and spring housing assembly together while tightening assembly screw.
10. Engage the control spring on the same groove on the armature of the relay.
11. Operate the armature of the relay by hand to make sure that there is no binding.
12. Electrically check, and adjust if needed, the pickup of the relay in accordance with
instructions given ini the Instruction Book of the particular relay model number.
=0
F*4-rc=
XA&AY4 NOWXf;Al
CrOOLWY Sf.Xct6 J~pe-e A0.SA4.ER -
CaO.'?TL iFawdiV 4 -
--t - (C. o " 'SF
K>
Attachment 2 IN 97-12 March 24, 1997 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
92-27, Thermally Induced 03/21/97 All holders of OLs
Supp. 1 Accelerated Aging or CPs for nuclear
and Failure of ITE/ power reactors
Gould A.C. Relays
Used in Safety-Related
Applications
97-11 Cement Erosion from 03/21/97 All holders of OLs
Containment Subfounda- or CPs 'Jr nuclear
tions at Nuclear Power power reactors
Plants
97-10 Liner Plate Corrosion 03/13/97 All holders of OLs
in Concrete Containments or CPs for power
reactors
97-09 Inadequate Main Steam 03/12/97 All holders of OLs
Safety Valve (MSSV) or CPs for nuclear
Setpoints and Perform- power reactors
ance Issues Associated
with Long MSSV Inlet
Piping
97-08 Potential Failures 03/12/97 All holders of OLs
for General Electric or CPs for nuclear
Magne-Blast Circuit power reactors
Breaker Subcomponents
97-07 Problems Identified 03/06/97 All holders of OLs
During Generic Letter or CPs for nuclear
89-10 Closeout power reactors
Inspections
OL = Operating License
CP = Construction Permit
- BIN K> 97-12 March 24, 1997 GE PM issued Relay Service Advice Letter 516.1 on October 25, 1996, to alert customers
that HGA relays manufactured between January 1989 and June 1991 may have marginal
armature-to-contact support clearance and may be susceptible to armature binding.
However, some licensees may have procured the relays as commercial-grade, or received
them as basic components from a dedicating entity and, therefore, may not have received the
attached GE relay service advice letter. Consequently, some licensees may not have had
the opportunity to evaluate the information in accordance with 10 CFR Part 21.
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.
j original signed by M.M. Slosson
Thomas T. Martin, Director
~/ Division of Reactor Program Management
{ Office of Nuclear Reactor Regulation
Technical contacts: K. Naidu, NRR S. Alexander, NRR
(301) 415-2980 (301) 415-2995 E-mail: km@nrc.gov E-mail: sda@nrc.gov
D. Skeen, NRR
(301) 415-1174 E-mail: dls@nrc.gov
Attachments:
1. GE Relay Service Advice Letter 516.1 dated October 25, 1996
2. List of Recently Issued NRC Information Notices
Tech Editor has reviewed and concurred on 2/14/97 DOCUMENT NAME: 97-12.IN
To receive a copy of thIs document. indicate hI the box: C - Copy w/o
attachmentenclosure E - Copy w/attachmentlenclosure 'N' - No copy
OFFICE TECH CONTS C/PECB:DRPM I / ZZLI I LL --
NAME KNaidu* AChaffee* TMartin
SAlexander*
DSkeen* _ _.-
DATE 02/24/97 02/27/97 / /
l _ 02/20/97 OFFICIAL RECORD COPY
11-1/
IN 97-XX
March , 1997 GE PM issued Relay Service Advice Letter 516.1 on October 25, 1996, to alert customers
that HGA relays manufactured between January 1989 and June 1991 may have marginal
armature-to-contact support clearance and may be susceptible to armature binding.
However, some licensees may have procured the relays as commercial-grade, or received
them as basic components from a dedicating entity and, therefore, may not have received the
attached GE relay service advice letter. Consequently, some licensees may not have had
the opportunity to evaluate the information in accordance with 10 CFR Part 21.
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.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: K. Naidu, NRR S. Alexander, NRR
(301) 415-2980 (301) 415-2995 E-mail: kmrnrc.gov E-mail: sdaenrc.gov
D. Skeen, NRR
(301) 415-1174 E-mail: dls@nrc.gov
Attachments:
1. GE Relay Service Advice Letter 516.1
2. List of Recently Issued NRC Information Notices
OFC PECB:DRPM PSIB:DISP PSIB:DISP C/PSIB:DISP C/PECB:DRPM
NAME D. Skeen* SAlexander KNaidu* RGallo* AChaffee*
DATE 02120/97 02124197 2124197 2/24/97 2/27/97 Y ,- IN I I
OFC D/DRPM ,ndel, uZ/.74(?7 NAME T. Martin
DATE I /97 col
i - - annA par-.
UL PNUIAL Krt.#UKU %.VITJ DOCUMENT NAME: G:\DLS\iN97-XX.HGA
February xx, 1997 GE PM issued Relay Service Advice Letter 516.1 on October 25, 1996. to alert
customers that HGA relays manufactured between January 1989 and June 1991 may
have marginal armature-to-contact support clearance and may be susceptible to
armature binding.
However, some licensees may have procured the relays as commercial-grade, or
received them as basic components from a dedicating entity and, therefore, may
not have received the attached GE relay service advice letter. Consequently, some licensees may not have had the opportunity to evaluate the information in
accordance with 10 CFR Part 21.
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.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: K. Naidu, NRR
(301) 415-2980
E-mail: krn@nrc.gov
S. Alexander, NRR
(301) 415-2995 E-mail: sda@nrc.gov
D. Skeen, NRR
(301) 415-1174 E-mail: dls~nrc.gov
Attachments: 1. GE Relay Service Advice Letter 516.1
2. List of Recently Issued NRC Information Notices
OFC PECB:DRPM* PSIB:DISP* PSIB:DISP* C/PSIB:DISP* P
NAME D. Skeen S. Alexander K. Naidu R. Gallo A. C _affee
DATE 02/20/97 - 02/24/97 I~~~~~ ff __
2/24/97
_ _ _ _ _ _ _ _ -
2/24/97 p /q9
(- 4\\/
OFC D/DRPM
'\.
NAME T. Martin
DATE / 197 tOFFICIAL RECORD COPY]
DOCUMENT NAME: G:\DLS\IN97-XX.HGA
J; I 1. as
1, K>
IN 97-XX
February xx, 1997 GE PM issued Relay Service Advice Letter 516.1 on October 25, 1996. to alert
customers that HGA relays manufactured between January 1989 and June 1991 may
have marginal armature-to-contact support clearance and may be susceptible to
armature binding.
However, some licensees may have procured the relays as commercial-grade, or
received them as basic components from a dedicating entity. Therefore, some
licensees may not have received the attached letter and, consequently, may not
have had the opportunity to evaluate the information in accordance with 10 CFR
fr 2A1. ZJ1 d r orA: I
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.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: K. Naidu, NRR S. Alexander, NRR
(301) 415-2980 (301) 415-2995 E-mail: krn@nrc.gov E-mail: sda@nrc.gov
D. Skeen, NRR
(301) 415-1174 E-mail: dls@nrc.gov
Attachments: 1. GE Relay Service Advice Letter 516.1
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\DLS\IN97-XX.HGA
To receive a cop of this document Indicate In the box: "C" n Coov without enclosures "E" h nov
wkih enclosures ON" a No coov
OFFICE PSIB/ ISP T PECB/DRPM I WS IB1l I A'C:PECB/DRPM I IID:DRP
gNAME SAle DSke~ "RGT a l AChaffee l TMartin
DATE 02/ /97 02 /97vsb 02/A 97 '02/ /97 l 02/ /97 UFFICIAL RECORU COPY
|
---|
|
list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch)
... further results |
---|