Rupture in Extraction Steam Piping as a Result of Flow-Accelerated CorrosionML031050037 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
---|
Issue date: |
12/11/1997 |
---|
From: |
Roe J Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-97-084, NUDOCS 9712090140 |
Download: ML031050037 (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. 20555-0001 December 11, 1997 NRC INFORMATION NOTICE 97-84: RUPTURE IN EXTRACTION STEAM PIPING AS A
RESULT OF FLOW-ACCELERATED CORROSION
Addressees
All holders of operating licenses for nuclear power reactors except those who have permanently
reactor
ceased operations and have certified that fuel has been permanently removed from the
vessel.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
flow- addressees to potential generic problems related to the occurrence and prediction of
will
accelerated corrosion (FAC) in extraction steam systems. It is expected that recipients
actions, as appropriate, to
review the information for applicability to their facilities and consider
notice are not NRC
avoid similar problems. However, suggestions contained in this information
requirements; therefore, no specific action or written response is required.
Description of Circumstances
On April 21, 1997, Omaha Public Power District's Fort Calhoun Station, while operating at 100-
2 [12- percent power, experienced an approximate 0.56 m [6 ftl rupture of a 30.5-centimeter
inch]-diameter sweep elbow (radius equal to five times the pipe diameter) in the fourth-stage
rising
extraction steam piping. The operator, upon hearing steam noise and observing steam
from the turbine deck, believed that a steam line had broken and manually scrammed the
reactor. As a precaution, emergency boration was initiated. The main turbine tripped
the
automatically as a result of the reactor trip. The turbine trip had the effect of isolating
event.
rupture. Plant systems and related parameters responded as expected during the
of the
The steam line rupture damaged a nonsafety-related electrical load center in the vicinity
cable trays and pipe
pipe break. Additionally, collateral damage was experienced in several
Certain
hangers, and insulation containing asbestos was blown throughout the turbine building.
heads
portions of the fire protection system actuated in response to fusible links in the sprinkler
melting because of high temperature. Because there were no personnel in the immediate
vicinity of the rupture, no one was injured.
120 DA ,731t1i, nPD+4NT~ES 17-09 9719-11
9712Wik l a a
IN 97-84 December 11, 1997 turbine
The fourth-stage extraction steam system emanates from the outlet of the high-pressure
and preheats the feedwater heaters. The design operating conditions in the piping are
2068 kilopascal gauge [300 psig] and 218 C [4250F], with a steam quality of approximately
0
thickness of
92 percent. The piping is fabricated of A-1 06B carbon steel and has a nominal wall
to
0.953 centimeter [0.375 inch]. The licensee's root cause assessment attributed the failure
steam line
FAC in the extraction steam piping. Initial indications of degradation in the extraction
the furthest upstream long- at the Fort Calhoun facility were first discovered in 1985, when
of
radius elbow (radius equal to one and a half times the pipe diameter) was replaced because
a pinhole leak. At that time the next upstream sweep elbow was also replaced.
The fourth-stage extraction steam system had been recognized as a system that was
susceptible to erosion and/or corrosion. It was, therefore, being monitored by the licensee's
erosion and corrosion control program. Part of the licensee program was utilizing the
CHECWORKS computer code to identify high-wear-rate areas to be selected for inspection.
long- The CHECWORKS model for the fourth-stage extraction steam piping predicted that
to similar
radius elbows would wear at a higher rate than the sweep elbows when exposed
four long- conditions. Using CHECWORKS predictions, the licensee inspected and replaced all
radius elbows, but the failed sweep elbow was never inspected.
Part of the licensee's corrective actions following the rupture included inspecting all sweep
centimeter
elbows that had not been previously inspected. The measured wall thickness (0.112 the fourth-stage extraction piping was
[0.044 inch]) of the furthest downstream sweep elbow in
[0.107 inch]) specified by
also significantly below the minimum wall thickness (0.272 centimeter
fourth- code requirements and had to be replaced. Additionally, another sweep elbow in the
the wear (measured wall thickness of
stage extraction piping was also replaced because
though it was not below the
0.394 centimeter [0.155 inch]) was considered excessive, even
minimum allowable thickness.
were
The CHECWORKS predictions of the wear in the fourth-stage extraction steam system
on the components, that is, not consistent with the actual observed wear rates as measured
sweep elbows showed substantially greater wear than predicted.
IN 97-84 December 11, 1997 Subsequent investigations by the licensee determined that the inconsistencies between
predicted and actual wear were due to two factors. First, the "line correction factor" calculated
by CHECWORKS for the fourth-stage extraction steamline was not within the acceptable range
specified in the CHECWORKS users' manual. The line correction factor in CHECWORKS is
used to adjust wear rate predictions in a given line to account for plant operating conditions that
may vary with time. It is determined by comparing predicted wear to measured wear at
locations in the line which have been inspected.
In order for the CHECWORKS predicted wear rate for a location to be valid, the line correction
factor must be between 0.5 and 2.5. For the line containing the sweep elbow that failed, the
wear rates calculated by CHECWORKS used a line correction factor that was outside this
range. Therefore, as specified in the CHECWORKS users' manual, the predicted wear rates
for this line were not valid.
Second, the line correction factor was biased and thus underpredicted the wear rates. In 1987, the licensee updated the parameters used by CHECWORKS to include the wear measured in a
long-radius elbow. One of the inputs in CHECWORKS is the length of time the component has
been In service. The licensee assumed that this elbow had been in service since initial
operation of the plant In 1973; however, the elbow had been replaced in 1985. Therefore, the
actual wear occurred over 2 years rather than the presumed 14 years. Thus, the period of time
that was assumed for the wear to have occurred caused CHECWORKS to calculate a line
correction factor that underestimated the wear rates for sites in the line.
This event revealed the importance of understanding the limitation of methodologies used in
computer programs and of incorporating accurate plant-specific data from nondestructive
examination programs.
Related Generic Communications
In NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants," July 9, 1987, the staff
asked licensees and applicants to inform the NRC about their programs for monitoring the wall
thickness of carbon steel piping (Accession No. 8707020018).
In NRC Generic Letter 89-08, "Erosion/Corrosion Induced Pipe Wall Thinning," May 2,1989, the staff asked licensees and applicants to Implement long-term erosion/corrosion monitoring
programs (Accession No. 8905040276).
IN 97-84 December 11, 1997 Additionally, the following NRC information notices (INs) provide information about similar
events related to FAC:
IN 82-22, "Failures in Turbine Exhaust Lines," July 9, 1982 (Accession No. 8204210392).
IN 86-106, nFeedwater Line Break," December 16, 1986 (Accession No. 8612160250).
IN 87-36, "Significant Unexpected Erosion of Feedwater Lines," August 4, 1987 (Accession
No. 8707290264).
IN 88-17, "Summary of Responses to NRC Bulletin 87-01, 'Thinning of Pipe Walls In Nuclear
Power Plants," April 22, 1988 (Accession No. 8804180039).
IN 89-53, "Rupture of Extraction Steam Line on High Pressure Turbine," June 13, 1989 (Accession No. 8906070273).
IN 91-18, "High Energy Pipe Failures Caused by Wall Thinning," March 12, 1991 (Accession No. 9103060153).
IN 91 -18, Supplement 1, "High Energy Pipe Failures Caused by Wall Thinning," December 18,
1991 (Accession No. 9112120218).
IN 93-21, "Summary of NRC Staff Observations Compiled During Engineering Audits or
Inspections of Licensee Erosion/Corrosion Programs," March 25, 1993 (Accession
No. 9303190051).
IN 95-11, "Failure of Condensate Piping Because of Erosion/Corrosion at a Flow-Straightening
Device," February 24, 1995 (Accession No. 9502210050).
IN 97-84 December 11, 1997 This information notice requires no specific action or written response. However, recipients are
reminded that they are required to consider industry-wide operating experience (including NRC
information notices) where practical, when setting goals and performing periodic evaluations
under Section 50.65, Requirement for monitoring the effectiveness of maintenance at nuclear
power plants," to Part 50 of Title 10 of the Code of Federal Regulations. If you have any
questions about the information in this notice, please contact the technical contact listed below
or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
J.). RoActing Director
Pi ision of Reactor Program Management
ice of Nuclear Reactor Regulation
Technical contact: J. Shackelford, RIV
(817) 860-8144 E-mail: jIs2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 97-84 December 11, 1997 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
95-49, Seismic Adequacy of 12/10/97 All holders of OLs for nuclear
Sup. 1 Thermo-Lag Panels power reactors
97-83 Recent Events Involving 12/05/97 All holders of OLs for pressurized- Reactor Coolant System water reactors, except those
Inventory Control During licensees who have permanently
Shutdown ceased operations and have
certified that fuel has been
permanently removed from the
reactor vessel
97-82 Inadvertent Control Room 11/28/97 All holders of OLs for nuclear
Halon Actuation Due to a power reactors
Camera Flash
97-81 Deficiencies in Failure 11/24197 All holders of OLs for nuclear
Modes and Effects Analyses power reactors except those
for Instrumentation and Control who have ceased operations
Systems and have certified that fuel
has been permanently removed
from the vessel
97-80 Licensee Technical 11/21197 All holders of OLs for
Specifications nuclear power reactors
Interpretations
OL = Operating License
CP = Construction Permit
e e
i' ,E' KY
IN97-84 December 11, 1997 This information notice requires no specific action or written response. However, recipients are
reminded that they are required to consider industry-wide operating experience (including NRC
information notices) where practical, when setting goals and performing periodic evaluations
under Section 50.65, "Requirement for monitoring the effectiveness of maintenance at nuclear
power plants," to Part 50 of Title 10 of the Code of Federal Regulations. If you have any
questions about the information in this notice, please contact the technical contact listed below
or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: J. Shackelford, RIV
(817) 860-8144 E-mail: jls2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
OFC TECH EDITOR* RIV/DRS*by email RIV/DRS*by email PECB:DRPM*
NAME R. Sanders J. Shackelford D. Chamberlain T. Greene
l DATE 09/11/97 09/16/97 109/16/97 09/20/97 OFC EMCB:DE* C(A)/EMCB:DE* D:DE* SUPECB:DRPM*
NAME K. Parczewski E. Sullivan B. Sheron R. Dennig
DATE 9/23/97 9/23/97 9/23/97 11/21/97 I OFC
NAME
I C/PECB:DRPM*
S. Richards
l(AED9RPM
J. &
DATE 11/26/97 12/6197 j
[OFFICIAL RECORD COPY]
DOCUMENT NAME: 97-84.IN
I
IN 97-XX
November XX, 1997 This information notice requires no specific action or written response. However, recipients are
reminded that they are required to consider industry-wide operating experience (including NRC
information notices) where practical, when setting goals and performing periodic evaluations
under Section 50.65, "Requirement for monitoring the effectiveness of maintenance at nuclear
power plants," to Part 50 of Title 10 of the Code of Federal Regulations. If you have any
questions about the information in this notice, please contact the technical contact listed below
or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: J. Shackelford, RIV
(817) 860-8144 E-mail: jis2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
OFC l TECH EDITOR* RlV/DRS*by email RIV/DRS*by email PECB:DRPM*
NAME R. Sanders J. Shackelford D. Chamberlain T. Greene
DATE j 09/11/97 09/16/97 09/16/97 09/20/97 OFC EMCB:DE* C(A)/EMCB:DE* D:DE* SL/PECB:DRPM*
NAME K. Parczewski E. Sullivan B. Sheron R. Dennig
DATE __9/23/97 9/23/97 j_9/23/97 j_11/21/971
, 1^_
AN I/,b(7 OFC lC/PECB:DRPM*1 (A)D/DF3PM
NAME S. Richards J.
DATE %ItZ697 <1/897U7
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:\TAG\INFAC
IJ I oA
IN 97-XX
November XX, 1997 This information notice requires no specific action or written response. However, recipients
are reminded that they are required to consider industry-wide operating experience (including
NRC information notices) where practical, when setting goals and performing periodic
evaluations under Section 50.65, "Requirement for monitoring the effectiveness of
maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of Federal
Regulations. If you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: J. Shackelford, RIV
(817) 860-8144 E-mail: jIs2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
OFC TECH EDITOR* RIV/DRS*by email RIVIDRS*by email PECB:DRPM*
NAME R. Sanders J. Shackelford D. Chamberlain T. Greene
DATE 09/11197 09/16/97 09116197 09/20/97 OFC EMCB:DE* C(A)/EMCB:DE* D:DE* SUPECB:DRPM
IOFC
NAME K. Parczewski E. Sullivan B. Sheron R. DennigI
DATE 9/23/97 9/23/97 9/23/97 11/21/97 NAME
DATE
C/PECB:DRPM*
S. Richards
I /97 f (A)D/DRPM
J. Roe
[__ /97
[OFFICIAL RECORD COPY]a Y/y7/
DOCUMENT NAME: G:\TAG\INFAC
IN 97-XX
November XX, 1997 This information notice requires no specific action or written response. However, recipients
are reminded that they are required to consider industry-wide operating experience (including
NRC information notices) where practical, when setting goals and performing periodic
evaluations under Section 50.65, "Requirement for monitoring the effectiveness of
maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of Federal
Regulations. If you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: J. Shackelford, RIV
817-860-8144 E-mail: jls2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
OFC TECH EDITOR* RIV/DRS*by email RIV/DRS*by email PECB:DRPM*
NAME R. Sanders J. Shackelford D. Chamberlain T. Greene
D 09/11/97 09/16/97 09/16/97 09/17/97 111,0111 OFC EMCB:DE* jC(A)IEMCB:DE* D:DE* S1IPA PM
NAME K. Parczewski E. Sullivan B. Sheron .FLenn/ig
lDATE 9/23/97 9/23/97 9123197 n 197 OFC C/PECB:DRPM (A)D/DRPM
NAME S. Richards J. Roe
DATE / /97 / /97 lj
See previous concurrence
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:NTAGIINFAC
e 4 t
IN 97-XX
October XX, 1997 This information notice requires no specific action or written response. However, recipients
are reminded that they are required to consider industry-wide operating experience (including
NRC information notices) where practical, when setting goals and performing periodic
evaluations under Section 50.65, "Requirement for monitoring the effectiveness of.
maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of Federal
Regulations. If you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: J. Shackelford, RIV
817-8604144 E-mail: jls2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
OFC TECH EDITOR RIVIDRSa s - /:$Aq PECB:DRPM
NAME R. Sanders* J. Shackelford i D. ChamberlainO)T. Greene ) (i
DATE 09111/97 09/16/97 09/16/97 09/17/97 OFC EMCB:DE C(A)/EMCB:DE :DE Si.
SLIPECB:DRPM
NAME K. Parczewski E. Sullivan _. Dennig
DATE /S3197 19 4A7(97;)J41 110/974J31;};3 1/97l
lOFC C(A)/PECB:DRPM D/DRPYA
NAME E. Goodwin J. Roe
DATE / /97 1 /97
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:\TAG\INFAC
W . I a. I
K) IN 97-XX
September XX, 1997 This information notice requires no specifi action or written response. However, recipients
are reminded that they are required to industry-wide operating experience (including
NRC information notices) where practical, when setting goals and
performing periodic evaluations under Section 50.65, "Requirement for monitoring the
effectiveness of maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of
Federal Regulations. If you have any questions about the information in this notice, please
contact the technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: J. Shackelford, RIV
(7817-860-8144
_ E-mail: jls2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
OFC TECH EDITOR RIV/DRS RIV/DRS l PECB:DRPM
NAME R. Sanders 0 J. Shackelford D. Chamberlain T. Greene
l DATE ljul11/97 //97 1 //97 1 /97 OFC C/EMCB:DE D:DE SL(A)/PECB:DRPM C(A)/PECB:DRPM
NAME J. Strosnider B. Sheron C. Petrone R. Dennig
DATE I /97 _ I/197 //97 1 /97 I OFC
NAME
DIDRPM
J. Roe
DATE l /97
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:%TAGINFAC
|
---|
|
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 |
---|