Off-Gassing in Auxiliary Feedwater System Raw Water SourcesML031080158 |
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: |
02/11/1993 |
---|
From: |
Grimes B Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-93-012, NUDOCS 9302040248 |
Download: ML031080158 (12) |
|
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 February 11, 1993 NRC INFORMATION NOTICE 93-12: OFF-GASSING IN AUXILIARY FEEDWATER
SYSTEM RAW WATER SOURCES
Addressees
power
All holders of operating licenses or construction permits for-nuclear
reactors.
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information in
notice to alert addressees to problems that could result from off-gassing review
safety-related raw water sources. It is expected that recipients will actions, this information for applicability to their facilities and consider
in
as appropriate, to avoid similar problems. However, suggestions contained
this information notice are not NRC requirements; therefore, no specific
action or written response is required.
Description of Circumstances
7- In March and April 1992, personnel at the McGuire Nuclear Station discovered safety
air pockets in the nuclear service water discharge piping supplying the(the
grade auxiliary feedwater for both Units 1 and 2. Duke Power Company
raw
licensee) determined the source of this air to be the off-gassing of theby the
lake water caused by the warming of the water by the components cooled
nuclear service water system. The air intrusion is a safety concern because
it could cause air binding or damage to the auxiliary feedwater pumps.
two
The auxiliary feedwater system at McGuire Nuclear Station consists of
450 gallon per minute (gpm) motor-driven pumps and one 900 gpm turbine-driven
pump that take suction from either of two sources. The normal, condensate tank, grade source of water for auxiliary feedwater is either the upper surge
the condenser hotwell, or the condensate storage tanks. The safety grade, water
seismic category I source of auxiliary feedwater is the-nuclear service
from the nuclear service water system, system. When aligned to take suction the
train "Al and "B" of the auxiliary feedwater system take suction from 1). The
corresponding nuclear service water system train "A" and "B" (Figure
"A"
turbine driven auxiliary feedwater pump can take suction from either train "A" and
or "B" of the nuclear service water system. In addition to the train
"B" nuclear service water, nuclear service water can be supplied to the
suction of the auxiliary feedwater system through a supply line controlled used to
from the standby shutdown facility. (The standby shutdown facility is
mitigate certain fire and security events.)
9302040248 -' D
Th/L C-
IN 93-12 February 11, 1993 The licensee discovered two different sources of
water system that could have potentially affected air in the nuclear service
auxiliary feedwater system. On March 27, McGuire the operability of the
a high point in the Unit 1 standby shutdown system personnel discovered air at
isolation valves that separate the nuclear service line upstream of the
feedwater systems (Valves ICA161C and ICA162C, Figurewater and the auxiliary
repeatedly vented this line over the following days, 2). McGuire personnel
produced at the high point. After thoroughly searching but air continued to be
performing a detailed engineering and chemical evaluationfor air inleakage and
McGuire staff concluded that the air was produced of the system, raw lake water. As a result of this discovery, the by off-gassing of the heated
found the second source of air at high points in licensee searched for and
service water discharge header (Detail A-A, Figurethe NA" train of the nuclear
operating conditions, these additional sources of 2). Under certain
air could have affected the
"A" auxiliary feedwater pumps and the turbine-driven
on both units. auxiliary feedwater pumps
The auxiliary feedwater line from the "A' train on
the discharge line of the emergency diesel cooling each unit is attached to
point where this line discharges into the main "A" heat exchanger, near the
discharge header. The cooling water from the diesel train service water
flows at the rate of 900 gpm. With the diesel running generator heat exchanger
feedwater pump drawing water from the diesel line, and only one auxiliary
sufficient
would be supplied to the feedwater pump suction without diesel coolant
main NA" train discharge line. However, if the "A" drawing water from the
diesel
is lost, or if both a motor-driven and a turbine-driven generator cooling
pump are operated simultaneously, water could be auxiliary feedwater
drawn from the high point on
the main 'A' train discharge line along with any
in this discharge line. The "B" train on each unitair that might have collected
it had a different piping configuration. was not affected because
Discussion
The events discussed in this information notice highlight
off-gassing ft auxiliary feedwater system raw water the potential for
Henry's law, the solubility of a gas in water at sources. According to
approximately proportional to the partial pressurea constant temperature is
at a constant pressure, however, generally decreasesof the gas. The solubility
with increasing
temperature. The solubility of air in water at atmospheric
example, is reduced from 29 milliliter per liter pressure, for
at OC (320F) to
16 milliliter per liter at 30*C (860F). Raw water
with air in the outside environment is not likely that has become saturated
water system supply piping because the pressure ofto emit gas in the service
increased by pumping while the temperature of the the water has been
water remains near its
original value. As this water is heated by the various
the pressure of the water decreases to near atmospheric plant systems, and as
discharge piping, some of the air can be expected levels in the
to
collect above any elevated, slow moving water volumes evolve from the water and
in the discharge piping.
IN 93-12 February 11, 1993 Upon discovering air in the auxiliary feedwater supply line for the Unit 1 standby shutdown system, the licensee declared all three of the auxiliary feed
water pumps to be inoperable. The licensee concluded that these pumps had
technically been inoperable since initial plant operation. The licensee
isolated the auxiliary feedwater line by closing one of the isolation valves
in this line and removing the power supply to this valve. Although this
action made the standby shutdown line inoperable, the action was initially
considered to be sufficient to return the rest of.the auxiliary feedwater
system to operability. However, after discovering the second source of air in
the high points of the "A" nuclear service water train discharge lines of both
units, the licensee isolated the turbine-driven pumps of both units from the
"A" service water lines and declared the turbine-driven pumps to be
inoperable. This action returned the "A" motor driven pumps to operability, because these pumps alone could not draw sufficient water to ingest air from
the main nuclear service water discharge lines.
The licensee considered several options to correct the problem permanently.
One possible solution was to reroute the safety-grade auxiliary feedwater
lines to take suction from the nuclear service water supply piping. A second
possible solution was to reroute the suction of the auxiliary feedwater lines
to sections of the nuclear service water discharge piping that were not
susceptible to the formation of air pockets. However, the licensee chose a
third alternative, which was to install permanent vent valves at the high
points where air was accumulating (Valves IRN1060, 1RN835 and 2RN815, Figure 2). The licensee piped these vent valves to drains and throttled the
valves to provide a continuous drainage flow that was sufficient to vent any
air that might accumulate in the emergency feedwater supply.
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: P. Kim Vandoorn, RII
(704) 875-1681 Don Kirkpatrick, NRR
(301) 504-1849 Attachments:
1. Figure 1
2. Figure 2
3. List of Recently Issued NRC Information Notices
5e L laLW
MCGUIRE NUCLEAR STATION
AUXILIARY FEEDWATER SYSTEM
UNIT I
MOP IA AND TOP I SUCTION SUPPLY
FROM NUCLEAR SERVICE WATER (RN)
DISCHAROE HEADER IA
C
FOW 10 ND TOP I SUCTION SUPPLY
FROM NUCLEAR SERVICE WATER IRNI
DISCWJR=E HEADER I1 oQ to c (t
W ,
'0
D
-A I
Figure 1
MCGUIRE NUCLEAR STATION
NUCLEAR SERVICE WATER SYSTEM
1AJ0
PROBLEM DESCRIPTION
V ~ AW- SqUA~Ca
' em, lPTAlL 'A-A"
An. LE -
(
e^eospo^
SV.Hk4%E- ,C=l
Nof
.a
4AfWTP I (
SkyIN j
SPUCTIO.
1oAFW IP^p lltx-or-l
SRwTlow HeA~pevy *-45 (
-fo Co"C1SEpE 0 I '
t! ft ,
rt
ell!eLA-riklo wlk-rEa___ I0'0A~4 P16.SEL
. WEA-ob
Aw WkNLk
f' 0
Y- IDIw0 i%.
loo 4L'AAf SEACE v) "
Isr Ad.% *ARIVA fb#p
sourcL -
OW~ll toB
Figure 2
v)
Attachment 3 IN 93-12 February 11, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-11 Single Failure Vulner- 02/04/93 All holders of OLs or CPs
ability of Engineered for nuclear power reactors.
Safety Features
Actuation Systems
93-10 Dose Calibrator Quality 02/02/93 All Nuclear Regulatory Com- Control mission medical licensees.
93-09 Failure of Undervoltage 02/02/93 All holders of OLs or CPs
Trip Attachment on for nuclear power reactors.
Westinghouse Model DB-50
Reactor Trip Breaker
93-08 Failure of Residual 02/01/93 All holders of OLs or CPs
Heat Removal Pump for nuclear power reactors.
Bearings due to High
Thrust Loading
93-07 Classification of Trans- 02/01/93 All Licensees required to
portation Emergencies have an emergency plan.
93-06 Potential Bypass Leak- 01/22/93 All holders of OLs or CPs
age Paths Around Filters for nuclear power reactors.
Installed in Ventilation
Systems
93-05 Locking of Radiography 01/14/93 All Nuclear Regulatory
Exposure Devices Commission industrial
radiography licensees.
93-04 Investigation and Re- 01/07/93 All U.S. Nuclear Regulatory
porting of Misadministra- Commission medical
tions by the Radiation licensees.
Safety Officer
93-03 Recent Revision to 01/05/93 All byproduct, source, and
10 CFR Part 20 and special nuclear material
Change of Implementa- licensees.
tion Date to
January 1, 1994 OL = Operating License
CP - Construction Permit
IN 93-XX
January xx, 1993 Upon discovering air in the auxiliary feedwater supply line for the Unit 1 standby shutdown system, the licensee declared all three of the auxiliary feed
water pumps to be inoperable. The licensee concluded that these pumps had
technically been inoperable since initial plant operation. The licensee
isolated the auxiliary feedwater line by closing one of the isolation valves
in this line and removing the power supply to this valve. Although this
action made the standby shutdown line inoperable, the action was initially
considered to be sufficient to return the rest of the auxiliary feedwater
system to operability. However, after discovering the second source of air in
the high points of the "A"nuclear service water train discharge lines of both
units, the licensee isolated the turbine-driven pumps of both units from the
"A" service water lines and declared the turbine-driven pumps to be
inoperable. This action returned the "A"motor driven pumps to operability, because these pumps alone could not draw sufficient water to ingest air from
the main nuclear service water discharge lines.
The licensee considered several options to correct the problem permanently.
One possible solution was to reroute the safety-grade auxiliary feedwater
lines to take suction from the nuclear service water supply piping. A second
possible solution was to reroute the suction of the auxiliary feedwater lines
to sections of the nuclear service water discharge piping that were not
susceptible to the formation of air pockets. However, the licensee chose a
third alternative, which was to install permanent vent valves at the high
points where air was accumulating (Valves IRN1060, 1RN835 and 2RN815, Figure 2). The licensee piped these vent valves to drains and throttled the
valves to provide a continuous drainage flow that was sufficient to vent any
air that might accumulate in the emergency feedwater supply.
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: P. Kim Vandoorn, RII
(704) 875-1681 Don Kirkpatrick, NRR
(301) 504-1849 Attachments:
1. Figure 1.
2. Figure 2.
3. List of Recently s
W NRC Information Notices
- SEE PREVIOUS ENCES Document Name: OFFGAS.IN
R .NRR
es
3 GMarcus
l0
1/ai/93 Ofi
C/OGCB:DORS:NRR *RPB:ADM
TechEd
11/05/92 JJohnson
01/26/93
- OGCB:DORS:NRR C/S B:DSSA:NRR*PD2-3:ADR2:NRR *C/PD2-3:ADR2:NRR *RII
DKirkpatrick:mkm CMcCracken TReed DBMatthews WMiller
11/04/92 12/04/92 12/21/92 12/22/92 01/26/93
T 3-12 L r~uary 11, 1993 Upon discovering air in the auxiliary feedwater supply line for the Unit 1 standby shutdown system, the licensee declared all three of the auxiliary feed
water pumps to be inoperable. The licensee concluded that these pumps had
technically been inoperable since initial plant operation. The licensee
isolated the auxiliary feedwater line by closing one of the isolation valves
in this line and removing the power supply to this valve. Although this
action made the standby shutdown line inoperable, the action was initially
considered to be sufficient to return the rest of the auxiliary feedwater
system to operability. However, after discovering the second source of air in
the high points of the RA" nuclear service water train discharge lines of both
units, the licensee isolated the turbine-driven pumps of both units from the
'A" service water lines and declared the turbine-driven pumps to be
inoperable. This action returned the *A"motor driven pumps to operability, because these pumps alone could not draw sufficient water to ingest air from
the main nuclear service water discharge lines.
The licensee considered several options to correct the problem permanently.
One possible solution was to reroute the safety-grade auxiliary feedwater
lines to take suction from the nuclear service water supply piping. A second
possible solution was to reroute the suction of the auxiliary feedwater lines
to sections of the nuclear service water discharge piping that were not
susceptible to the formation of air pockets. However, the licensee chose a
third alternative, which was to install permanent vent valves at the high
points where air was accumulating (Valves lRN1060, 1RN835 and 2RN815, Figure 2). The licensee piped these vent valves to drains and throttled the
valves to provide a continuous drainage flow that was sufficient to vent any
air that might accumulate in the emergency feedwater supply.
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 appropriat eQ fice of
Nuclear Reactor Regulation (NRR) project manager. Original signeuY
Brian K. Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: P. Kim Vandoorn, RII
(704) 875-1681 Don Kirkpatrick, NRR
(301) 504-1849 Attachments:
1. Figure 1
2. Figure 2
3. Ls cently Issued NRC Information Notices
CONCURRENCES Document Name: I
- SE ONURRE*C/OGCB:DORSDuNRR *RPB:ADM *RI N
GMarcus TechEd JJohnson
OR/°/93 01/29/93 11/05/92 01/26/93
- OGCB:DORS:NRR *C/SPLB:DSSA:NRR*PD2-3:ADR2:NRR *C/PD2-3:ADR2:NRR*RII
DKirkpatrick:mkm CMcCracken TReed DBMatthews WMiller
11/04/92 12/04/92 12/21/92 12/22/92 01/26/93
IN 93-XX
January xx, 1993 Upon discovering air in the auxiliary feedwater supply line for the Unit 1 standby shutdown system, the licensee declared all three of the auxiliary feed
that these pumps had
water pumps to be inoperable. The licensee concluded The licensee
technically been inoperable since initial plant operation. of the isolation valves
isolated the auxiliary feedwater line by closing onevalve. Although this
in this line and removing the power supply to this it was initially considered
action made the standby shutdown line inoperable, feedwater system to
to be sufficient to return the rest of the auxiliary source of air in the high
operability. However, after discovering the second
discharge lines of both units, points of the "A"nuclear service water train units from the
the licensee isolated the turbine-driven pumps of both
pumps to be
"A" service water lines and declared the turbine-driven pumps to operability, inoperable. This action returned the "Al motor driven ingest air from
because these pumps alone could not draw sufficient water to
the main nuclear service water discharge lines.
The licensee considered several options to permanently auxiliarycorrect the problem.
safety-grade feedwater
One possible solution was to reroute the supply piping. A second
lines to take suction from the nuclear service water
of the auxiliary feedwater lines
possible solution was to reroute the suction piping that were not
to sections of the nuclear service water discharge
susceptible to the formation of air pockets. However, the licensee chose a
third alternative, which was to install permanent vent valves at the high
points where air was accumulating (Valves IRN1060, IRN535 and 2RN815, Figure
these vent valves to drains and throttled
2). The licensee permanently piped was sufficient to vent
the valves to provide a continuous drainage flow that
any air that might accumulate in the emergency feedwater supply.
This information notice requires no specific action ornotice, written response. If
you have any questions about the information in this please contact
Office of
one of the technical contacts listed below or the appropriate
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Bill Miller, RII
(404) 331-4198 Don Kirkpatrick, NRR
(301) 504-1849 Attachments:
1. Figure 1.
2. Figure 2.
3. List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES Document Name: OFFGASIN
C/OGCB:DORS:NRR *RPB:ADM RI I i'
D/DORS:NRR JJohnsoneQLT,
BKGrimes GMarcus TechEd
01/ /93 01/ /93 11/05/92 01/2&93 -e6p4f
- C/SPLB:DSSA:NRR*PD2-3:ADR2:NRR *C/PD2-3:ADR2:NRR RII
- OGCB:DORS:NRR WMiller0%/WA
DKirkpatrick:mkm CMcCracken TReed DBMatthews
12/21/92 12/22/92 01/.Z /93 jaw
11/04/92 12/04/92
IN 92- November , 1992 Upon discovering air in the auxiliary feedwater supply line for the Unit 1 standby shutdown system, the licensee declared all three of the auxiliary feed
water pumps to be inoperable. The licensee concluded that these pumps had
technically been inoperable since initial plant operation. The licensee
isolated the auxiliary feedwater line by closing one of the isolation valves
in this line and removing the power supply to this valve. Although this
action made the standby shutdown line inoperable, it was initially considered
to be sufficient to return the rest of the auxiliary feedwater system to
operability. However, after discovering the second source of air in the high
points of the "A" nuclear service water train discharge lines of both units, the licensee isolated the turbine-driven pumps of both units from the "A"
service water lines and declared the turbine-driven pumps to be inoperable.
This action returned the "Al motor driven pumps to operability, because these
pumps alone could not draw sufficient water to ingest air from the main
nuclear service water discharge lines.
The licensee considered several options to permanently correct the problem.
One possible solution was to reroute the safety-grade auxiliary feedwater
lines to take suction from the nuclear service water supply piping. A second
possible solution was to reroute the suction of the auxiliary feedwater lines
to sections of the nuclear service water discharge piping that were not
susceptible to the formation of air pockets. However, the licensee chose to
install permanent vent valves at the high points where air was accumulating
(Valves IRN1060, 1RN535 and 2RN815, Figure 2). The licensee permanently piped
these vent valves to drains and throttled the valves to provide a continuous
drainage flow that was sufficient to vent any air that might accumulate in the
emergency feedwater supply.
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 : Bill Miller, RI!
(404) 331-4198 Don Kirkpatrick, NRR
(301) 504-1849
- SEE PREVIOLISCONCURRENCES Document Name: OFFGASIN
Attachment: List of Recently issued NRC Informat N ices
- OGCB:DORS:NRR *TECH ED *C:SPLB:DSSA:NRR PD j1B2:NRR
DKirkp trick:mkm JMain CMcCracken TRe
11 11/05/92 12/04/92 12/p)/92 C: J ADR2:NRR RII RII C:OGCB:DORS:NRR D:DORS::NRR
Z DB ews WMiller JJohnson GHMarcus BKGrimi-s
12/41/92 12/ /92 12/ /92 12/ /92 12/ /' '92
IN 92- November , 1992 Upon discovering air in the auxiliary feedwater supply line for the Unit 1 standby shutdown system, the licensee declared all three of the auxiliary feed
water pumps to be inoperable. The licensee concluded that these pumps had
technically been inoperable since initial plant operation. The licensee
isolated the auxiliary feedwater line by closing one of the isolation valves
in this line and removing the power supply to this valve. Although this
action made the standby shutdown line inoperable, it was initially considered
to be sufficient to return the rest of the emergency auxiliary feedwater
system to operability. However, after discovering air in the high points of
the "A"train main discharge lines of both units, the licensee isolated the
turbine-driven pumps of both units from the "Al service water lines and
declared the turbine-driven pumps to be inoperable. This action returned the
"A"motor driven pumps to operability, because these pumps alone could not
draw sufficient water to draw air from the main raw water discharge trains.
The licensee considered several options to permanently correct the problem.
One possible solution was to reroute the emergency-grade auxiliary feedwater
lines to take suction from the nuclear service water supply piping. A second
possible solution was to reroute the suction of the auxiliary feedwater lines
to sections of the nuclear service water discharge piping that were not
susceptible to the formation of air pockets. However, the licensee chose to
install permanent vent valves at the high points where air was accumulating.
The licensee permanently piped these vent valves to drains and throttled the
valves to provide a continuous drainage flow that was sufficient to vent any
air that might accumulate in the emergency feedwater supply.
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: Bill Miller, R11
(404) 331-4198 Don Kirkpatrick, NRR
(301) 504-1849
- SEE PREVIOUS CONCURRENCES Document Name: OFFGASIN
Attachment: List of Recently issued NRC Information Notices
- OGCB:DORS:NRR *TECH ED C:SPLB:DSSA R PD2-3:ADR2:NRR
DKirkpatrick:mkm JMain CMcCracken4e TReed
11/04/92 11/05/92 17./%/92 11/ /92 C:PD2-3:ADR2:NRR RII RII C:OGCB:DORS:NRR D:DORS:NRR
DBMatthews WMiller JJohnson GHMarcus BKGrimes
11/ /92 11/ /92 11/ /92 11/ /92 11/ /92
IN 92- November , 1992 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: Bill Miller, R11
(404) 331-4198 Don Kirkpatrick, NRR
(301) 504-1849 Attachment: List of Recently issued NRC Information Notices
OGCB:DORS:NRR TECH ED C:SPLB:DSSA:NRR PD2-3:ADR2:NRR
DKirkpatricktmk 1ain
1//h CMcCracken TReed
I1/4 /92-161 11/3>~/92 11/ /92 11/ /92
|
---|
|
list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
... further results |
---|