Information Concerning the Use of Anaerobic Adhesive/SealantsML031130317 |
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
---|
Issue date: |
10/09/1987 |
---|
From: |
Rossi C Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-87-048, NUDOCS 8710050169 |
Download: ML031130317 (7) |
|
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
---|
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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
o w SSINS No.: 6835
- :IN 87-48 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C.- .20555 October 9, 198.7 NRC INFORMATION NOTICE NO.: 87-48: INFORMATION CONCERNINGATHE USE OFi -
ANAEROBIC ADHESIVE/SEALANTS
Addressees
- . -
All nuclear power reactor facilities holding an operating license or a con- struction permit.
Purpose
This information notice is provided to-alert recipients to a potentially
significant safety problem pertaining to the use of anaerobic adhesives and
sealants. It is expected that recipients will review the information for
applicability to their facilities and consider actions,, 1f apPropriate;:tb.-
preclude a similar problem. However, suggestions contained in this notice do
not constitute NRC requirements; therefore, no specific action or written
response is required.
Description of Circumstances
On July 1, 1987, Carolina Power and Light Company reported that following a
reactor trip/turbine trip at the BrunswickSteam Electric Plant, Unit 1 (Brunswick), one safety relief valve (SRV) failed to open when manually actu- ated for pressure control. The SRV is part of the automatic depressurization
system (ADS) at that plant. Subsequent testing of other ADS valves on July 3 resulted in a second valve failing to open on manual actuation. During post- failure examination it was determined that Loctite RC 620 was used as a secondary
lock between the stem and the plunger in the solenoid assembly when the valves
were rebuilt by Target Rock Corporation at Wyle Laboratory. This material then
migrated to the clearance around the plunger before setting.
Discussion:
This event is similar to the one described in Information Notice 84-53, "Infor- mation Concerning the Use of Loctite 242 and Other Anaerobic Adhesive/
Sealants." In that event, Loctite 242 threadlocking adhesive/sealant was used
in the assembly of scram pilot solenoid valves. An investigation into the
failure of several scram solenoid valves revealed that maintenance technicians
failed to wipe excess Loctite from the assembly, which resulted in the bonding
of the solenoid core plunger to the core tube.
8710050169
IN 87-48 October 9, 1987 The Brunswick SRVs also failed because the contractor technician did not clean
the excess Loctite RC 620 from the plunger assembly. Because this substance is
anaerobic (cures in the absence of air, e.g., the inerted containment atmo- sphere), the plunger did not become seized until after the valves with excess
Loctite were placed in the inerted atmosphere that exists in the reactor
containment when the reactor is brought to power conditions.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Drector
Dsi, Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Ray Scholl, NRR
(301) 492-8213 Attachment: List of Recently Issued NRC Information Notices
114, Attachmnt- IN-87-48 October 9, 1987 LIST OF RECENTLY ISSUED
INFORMATION NOTICES 1987 Information Date of
Notice No. Subject Issuance Issued to
87-47 Transportation of Radio- 10/5/87 All NRC licensees
graphy Devices authorized to manu- facture, distribute
and/or, operate radio- graphic exposure
devices and/or
source changers.
87-46 Undetected Loss of Reactor 9/30/87 All PWR facilities
Coolant holding on OL or CP.
87-45 Recent Safety-Related 9/25/87 All NRC licensees
Violations of NRC authorized to possess
Requirements by Industrial and use sealed sources
Radiography Licensees for industrial radio- graphy.
87-44 Thimble Tube Thinning in 9/16/87 All PWR facilities
Westinghouse Reactors employing a W nuclear
. _T steam supply system
holding an OL or CP.
87-43 Gaps in Neutron-Absorbing 9/8/87 All nuclear power
Material in High-Density reactor facilities
Spent Fuel Storage Racks holding an OL or CP.
87-42 Diesel Generator Fuse 9/4/87 All nuclear power
Contacts reactor facilities
holding an OL or CP.
87-41 Failures of Certain Brown 8/31/87 All nuclear power
Boveri Electric Circuit reactor facilities
Breakers holding an OL or CP.
87-40 Backseating Valves Routinely 8/31/87 All nuclear power
to Prevent Packing Leakage reactor facilities
holding an OL or CP.
87-39 Control of Hot Particle 8/21/87 All nuclear power
Contamination at Nuclear reactor facilities
Power Plants and spent fuel
storage facilities
holding an NRC
license or CP.
OL = Operating License
CP = Construction Permit
Ik -> IN 87-48 V October 9, 1987 The Brunswick SRVs also failed because the contractor technician did not clean
the excess Loctite RC 620 from the plunger assembly. Because this substance is
anaerobic (cures in the absence of air, e.g., the inerted containment atmo- sphere), the plunger did not become seized until after the valves with excess
Loctite were placed in the inerted atmosphere that exists in the reactor
containment when the reactor is brought to power conditions.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Ray Scholl, NRR
(301) 492-8213 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
- OEAB:DOEA:NRR *OGCB:DOEA:NRR *PPMB:ARM *C/OGCB:DOEA:NRR
RScholl RJKiessel TechEd CHBerlinger
09/14/87 09/14/87 09/18/87 10/1/87 1015/87
0.
IN 87-XX
October xx, 1987 The Brunswick SRVs also failed because the contractor technician did not clean
the excess Loctite RC 620 from the plunger assembly. Because this substance Is
anaerobic (cures in the absence of air e.g., the inerted containment atmo- sphere), the plunger did not become seized until after the valves with excess
Loctite were placed in the inerted atmosphere that exists in the reactor
containment when the reactor is brought to power conditions.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Ray Scholl, NRR
(301) 492-8213 Attachment: List of Recently Issued Information Notices
- SEE PREVIOUS CONCURRENCES
- OEAB:DWEA:NRR *OGCB:DOEA:NRR *PPMB:ARM
C #/
C/OGCB:DOEA:NRR D/DOEA:NRR
RScholl RJKiessel TechEd CHBerlinger CERossi
09/14/87 09/14/87 09/18/87 bQ/ /87 09/ /87
IN 87-XX
August xx, 1987 The Brunswick SRVs also failed because excess Loctite was not cleaned by the
contractor technician from the plunger assembly. In this latter case, Loctite
RC 620 was used. This substance is anaerobic (cures in the absence of air).
Thus, the plunger did not become seized until after the valves with excess
Loctite were placed in the inerted atmosphere which exists In the reactor
containment when the reactor is brought to power conditions.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Ray Scholl, NRR
(301) 492-8213 Attachment: List of Recently Issued Information Notices
OEAB:DOEA:NRR OGCB:DOEA:NRR PPMB:ARI C/OGCB:DOEA:NRR D/DOEA:NRR
RScholl RJKiessel TechEd(' CHBerl inger CERossi
C / F 87 0//Y/87 019/i 7 0C/ /87 Cq/ /87
|
---|
|
list | - Information Notice 1987-02, Inadequate Seismic Qualification of Diaphragm Valves by Mathematical Modeling and Analysis (13 January 1987, Topic: Boric Acid, Overspeed trip)
- Information Notice 1987-03, Segregation of Hazardous and Low-Level Radioactive Wastes (15 January 1987, Topic: Boric Acid, Overspeed trip)
- Information Notice 1987-04, Diesel Generator Fails Test Because of Degraded Fuel (16 January 1987, Topic: Boric Acid, Coatings)
- Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System (2 February 1987, Topic: Unanalyzed Condition, Boric Acid)
- Information Notice 1987-06, Loss of Suction to Low-Pressure Service Water System Pumps Resulting from Loss of Siphon (30 January 1987, Topic: Boric Acid)
- Information Notice 1987-07, Quality Control of Onsite Dewatering/Solidification Operations by Outside Contractors (3 February 1987, Topic: Boric Acid, Process Control Program)
- Information Notice 1987-08, Degraded Motor Leads in Limitorque DC Motor Operators (4 February 1987, Topic: Boric Acid, Anchor Darling)
- Information Notice 1987-09, Emergency Diesel Generator Room Cooling Design Deficiency (5 February 1987, Topic: Probabilistic Risk Assessment)
- Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps (11 February 1987, Topic: Water hammer)
- Information Notice 1987-11, Enclosure of Vital Equipment within Designated Vital Areas (13 February 1987, Topic: Contraband, Water hammer)
- Information Notice 1987-11, Enclosure of Vital Equipment Within Designated Vital Areas (13 February 1987, Topic: Contraband, Water hammer)
- Information Notice 1987-12, Potential Problems with Metal Clad Circuit Breakers, General Electric Type AKF-2-25 (13 February 1987, Topic: Water hammer)
- Information Notice 1987-13, Potential for High Radiation Fields Following Loss of Water from Fuel Pool (24 February 1987, Topic: Water hammer)
- Information Notice 1987-14, Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment (23 March 1987, Topic: Water hammer)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223b of the Atomic Energy Act of 1954, as Amended (25 March 1987)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223B of the Atomic Energy Act of 1954, As Amended (25 March 1987)
- Information Notice 1987-16, Degradation of Static O Ring Pressure Switches (2 April 1987, Topic: Commercial Grade)
- Information Notice 1987-17, Response Time of Scram Instrument Volume Level Detectors (7 April 1987, Topic: Scram Discharge Volume, Water hammer)
- Information Notice 1987-18, Unauthorized Service on Teletherapy Units by Nonlicensed Maintenance Personnel (8 April 1987, Topic: Water hammer)
- Information Notice 1987-19, Perforation and Cracking of Rod Cluster Control Assemblies (9 April 1987)
- Information Notice 1987-20, Hydrogen Leak in Auxiliary Building (20 April 1987, Topic: Excess Flow Check Valve)
- Information Notice 1987-21, Shutdown Order Issued Because Licensed Operators Asleep While on Duty (11 May 1987, Topic: Inattentive)
- Information Notice 1987-22, Operator Licensing Requalification Examinations at Nonpower Reactors (22 May 1987, Topic: License Renewal)
- Information Notice 1987-23, Loss of Decay Heat Removal During Low Reactor Coolant Level Operation (27 May 1987, Topic: Boric Acid)
- Information Notice 1987-24, Operational Experience Involving Losses of Electrical Inverters (4 June 1987)
- Information Notice 1987-25, Potentially Significant Problems Resulting from Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed trip)
- Information Notice 1987-25, Potentially Significant Problems Resulting From Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders (11 June 1987, Topic: Boric Acid)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter Uf6 Cylinders (11 June 1987)
- Information Notice 1987-27, Iranian Official Implies Vague Threat to U.S. Resources (10 June 1987, Topic: Boric Acid)
- Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors (28 December 1987, Topic: Boric Acid)
- Information Notice 1987-29, Recent Safety-Related Incidents at Large Irradiators (26 June 1987, Topic: Coatings, Temporary Modification, Biofouling, Uranium Hexafluoride)
- Information Notice 1987-30, Cracking of Surge Ring Brackets in Large General Electric Company Electric Motors (2 July 1987)
- Information Notice 1987-31, Blocking Bracing, and Securing of Radioactive Materials Packages in Transportation (10 July 1987, Topic: Uranium Hexafluoride)
- Information Notice 1987-32, Deficiencies in the Testing of Nuclear-Grade Activated Charcoal (10 July 1987)
- Information Notice 1987-33, Applicability of 10 CFR Part 21 to Nonlicensees (24 July 1987, Topic: Commercial Grade)
- Information Notice 1987-34, Single Failures in Auxiliary Feedwater Systems (24 July 1987)
- Information Notice 1987-35, Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open on Manual Initiation from the Control Room (30 July 1987)
- Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines (4 August 1987)
- Information Notice 1987-37, Compliance with the General License Provisions of 10 CFR Part 31 (10 August 1987)
- Information Notice 1987-39, Control of Particle Contamination at Nuclear Power Plants (21 August 1987, Topic: Fuel cladding, Overexposure)
- Information Notice 1987-40, Backseating Valves Routinely to Prevent Packing Leakage (31 August 1987, Topic: Packing leak)
- Information Notice 1987-41, Failures of Certain Brown Boveri Electric Circuit Breakers (31 August 1987)
- Information Notice 1987-42, Diesel Generator Fuse Contacts (4 September 1987)
- Information Notice 1987-43, Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage Racks (8 September 1987)
- Information Notice 1987-44, Thimble Tube Thinning in Westinghouse Reactors (16 September 1987)
- Information Notice 1987-45, Recent Safety-Related Violations of NRC Requirements by Industrial Radiography Licensees (25 September 1987, Topic: High Radiation Area, Overexposure)
- Information Notice 1987-46, Undetected Loss of Reactor Coolant (30 September 1987)
- Information Notice 1987-48, Information Concerning the Use of Anaerobic Adhesive/Sealants (9 October 1987, Topic: Loctite)
- Information Notice 1987-49, Deficiencies in Outside Containment Flooding Protection (9 October 1987, Topic: Safe Shutdown)
... further results |
---|