Reduced Reliability of Steam-Driven Auxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL Type GovernorsML031150561 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Issue date: |
03/18/1988 |
---|
From: |
Rossi C Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-88-009, NUDOCS 8803140284 |
Download: ML031150561 (7) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 March 18, 1988 NRC INFORMATION NOTICE NO. 88-09: REDUCED RELIABILITY OF STEAM-DRIVEN
AUXILIARY FEEDWATER PUMPS CAUSED BY
INSTABILITY OF WOODWARD PG-PL TYPE
GOVERNORS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is provided to alert addressees to continuing problems
affecting the reliability of steam-driven auxiliary feedwater pumps caused
by instability problems with Woodward governors. It is expected that recipi- ents will review the information for applicability to their facilities and
consider actions, if appropriate, to avoid similar problems. However, sugges- tions contained in this information notice do not constitute NRC requirements;
therefore, no specific action or written response is required.
Description of Circumstances
The steam-driven auxiliary feedwater pumps at Calvert Cliffs are powered by
Terry steam turbines (GS-2N) with Woodward PG-PL type governors. Before
July 23, 1987, periodic surveillance testing of the steam-driven auxiliary
feedwater pumps (AFWPs) was preceded by a warmup of the turbines before
initiation of the quick startup tests. On July 23, 1987, during a loss- of-offsite-power event, the number 11 AFWP on Unit 1 tripped on its initial
demand as a result of turbine overspeed. To ensure that future periodic
(monthly) surveillance testing of the turbine-driven AFWPs would be con- ducted under more realistic conditions, the test procedures were modified
to require quick starts from cold conditions. During subsequent tests in
July through October 1987, a number of trips of the steam-driven AFWPs oc- curred at Calvert Cliffs. On July 30, 1987, during rapid cold startup testing, both of the Unit 2 steam-driven pumps tripped. On September 26, 1987, the
number 11 AFWP on Unit 1 began oscillating after the initial startup attempt
and subsequently tripped on overspeed. On October 23, 1987, the number 12 AFWP on Unit I tripped on overspeed.
The licensee conducted an intensive testing and troubleshooting program to
determine the causes of the failures. During these tests, a number of test
3140284
IN 88-09 March 18, 1988 failures were experienced because of turbine governor oscillation and overspeed.
The most frequent failure sequences were either rapid initial acceleration of
the turbine to the overspeed trip point, or large undamped speed oscillations
that increased in magnitude to the overspeed trip point. Less frequently, trips
occurred when the mechanical latch mechanism holding the trip valve open (which
appeared to be overly sensitive) tripped. Subsequent attempts to test the pumps
immediately after initial steam-driven AFWP failures were normally successful.
Discussion:
Several factors were identified which appear to have contributed to the reduced
reliability of the AFWPs. These include:
1. Use of governor buffer springs of less than optimal stiffness, resulting
in the inability of the governor to dampen out upset conditions. One of
the installed governors and all three of the spare governors had buffer
springs of a lower stiffness than that listed in the procurement specifi- cation on file at the Woodward company.
2. Excessive condensate trapped in the steam supply lines, resulting in
governor valve damage, governor linkage damage, and throttle control
instabilities as slugs of water hit the governor valve and turbine wheel.
3. Improperly adjusted and degraded governor linkage, resulting in excessive
linkage-play. _
4. Governor valve binding, resulting in governor actuator over-reaction to
small feedback signals.
5. A failed governor on the Unit 2, number 22 AFWP.
6. Damaged and misaligned overspeed trip mechanisms, resulting in
oversensitivity to vibration, Jarring, and waterhammer.
The licensee implemented several corrective actions and plans additional upgrades.
These are described below.
1. Stiffer buffer springs were installed in the governors of all AFWPs to
increase control system dampening at the expense of increased control
system response time.
2. Upgrading of both the procedures and the systems was initiated, which
included more thorough drain procedures and drain lineup verification.
The interval for manually draining the steamlines and turbine casings
was decreased from every 8 to every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Additional manual drains
were Installed in the system low points to eliminate water from the
steamlines.
3. Various parts of the governor valves, governor linkages, and trip linkages
were overhauled, adjusted, and replaced. Trip linkages associated with
IN 88-09 March 18, 1988 the overspeed mechanisms and the trip throttle valves were adjusted to
Increase trip latch engagement and thereby reduce sensitivity to physical
shock. For some parts, such as linkage plates (cams), it was necessary
for the utility to obtain the special materials involved and fabricate
replacement parts in house.
4. Further steamline drain improvements are being evaluated.
The Calvert Cliffs problems highlight the importance of optimally sizing buffer
springs, since the single, most effective short-term corrective action appeared
to be installation of the stiffer buffer springs. However, changes in spring
stiffness for the purpose of improving stability can adversely affect other
governor response characteristics. Therefore, the selection of optimal spring
stiffness should be carefully considered. In addition, it is important to
ensure maintenance of proper spring stiffness following initial determination
of optimal stiffness. In the case of Calvert Cliffs, the addition of stiffer
springs appeared to provide an extra margin of stability. This temporarily
compensated for other auxiliary feedwater system deficiencies that also re- quired correction.
Reliability problems were much more evident when the auxiliary feedwater pumps
were periodically tested using quick starts from cold conditions. This demon- strates the importance of surveillance testing which, in so far as practical, duplicates the service conditions that would exist if the equipment were called
on tooperate.
Information Notice 86-14, "PWR Auxiliary Feedwater Pump Turbine Control Prob- lems,' and 86-14, Supplement 1, "Overspeed Trips of AFW, HPCI, and RCIC Tur- bines," discuss problems closely related to those discussed in this information
notice.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
mAs . os*torV
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
D. Limroth, RI
(215) 337-5121 Attachment: List of Recently Issued NRC Information Notices
Attamelnt
March aI 1988 ,_^
Po I1 ; I
LIST Of RE2CVLY ISSUEM
NRCINFOIATIOX 11MCES
Infornation Dt.* -0
btice No. Subject v ,
Issuance Issued to
88-0 cinical Reactione with 3/2418 All NRClicsees
Radioactive Watt generating or pro.
Solidification Age"t ceasing lo level
radioactive waste.
88407 Inadvertnt Transfer of 3/718 All IRCbroad lcenses
Licensed Material te and liceses authoried
Uncontrolled Locations to possess byproduct
mterial as sealed
sources In telutherepy
usits or *self-conteior
Irradiator,.
83-06 Foreiga Objects in Stem 2198 All holders of CLs
Genrntors or CPs for PM .
Fire In Aununciator Contrel 2/11188 All holders of Ols
Cabinets or CPs for nualear
poewr reactors.
Inadequate Qualification 2W/83 All holders of Ms
and Documentation of Firs or CPs for nuclear
Berrier Penetration Seals powr reator.
n-OS Cracks In Shroud SuPICort 2/2/ All holders of Mls
Access Hole Cover Wods or CPSfor Dies.
88-02 Lost or Stela rauge 2/J8 All NuClic ees
authorized to posse
gauges under a
specttie or geea
licesm.
a8401 Safety Injection Pip& 1/M/3 All holders of OLs
Failure or CU for nuclear
pwe reactors.
U-J1, Drokn External Clo 2/11E13 All hulder, of
Supp. 1 Springs os Atwbod
or CPs for nuclear
Main Steam Isolation Valve powr reactor.
Ct
Cf
UNITED STATES FIRST CLASS MAIL
NUCLEAR REGULATORY COMMISSION POSTAGE a FEES PAID
WASHINGTON, D.C. 20555 USNRC
PERMIT No. 0-67 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. $300
IN 88-09 March 18, 1988 the overspeed mechanisms and the trip throttle valves were adjusted to
increase trip latch engagement and thereby reduce sensitivity to physical
shock. For some parts, such as linkage plates (cams), it was necessary
for the utility to obtain the special materials involved and fabricate
replacement parts in house.
4. Further steamline drain improvements are being evaluated.
The Calvert Cliffs problems highlight the importance of optimally sizing buffer
springs, since the single, most effective short-term corrective action appeared
to be installation of the stiffer buffer springs. However, changes in spring
stiffness for the purpose of improving stability can adversely affect other
governor response characteristics. Therefore, the selection of optimal spring
stiffness should be carefully considered. In addition, it is important to
ensure maintenance of proper spring stiffness following initial determination
of optimal stiffness. In the case of Calvert Cliffs, the addition of stiffer
springs appeared to provide an extra margin of stability. This temporarily
compensated for other auxiliary feedwater system deficiencies that also re- quired correction.
Reliability problems were much more evident when the auxiliary feedwater pumps
were periodically tested using quick starts from cold conditions. This demon- strates the importance of surveillance testing which, in so far as practical, duplicates the service conditions that would exist if the equipment were called
on to operate.
Information Notice 86-14, "PWR Auxiliary Feedwater Pump Turbine Control Prob- lems," and 86-14, Supplement 1, "Overspeed Trips of AFW, HPCI, and RCIC Tur- bines," discuss problems closely related to those discussed in this Information
notice.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
D. Limroth, RI
(215) 337-5121 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
- OGCB:DOEA:NRR *RI *PPMB:ARM *C/OGCB:DOEA:NRR /D
DCKirkpatrick DLimroth TechEd CHBerlinger A t ,
03/07/88 03/10/88 03/09/88 03/11/88 03//t788
IN 86-14, Supplement 2 March xx, 1988 shock. For some parts, such as linkage plates (cams), it was necessary
for the utility to obtain the special materials Involved and fabricate
replacement parts in house.
4. Further steamline drain improvements are being evaluated.
The Calvert Cliffs problems highlighted the importance of optimally sizing
buffer springs, since the single, most effective short-term corrective action
appeared to be installation of the stiffer buffer springs. However, changes in
spring stiffness for the purpose of improving stability can adversely affect
other governor response characteristics. Therefore, the selection of optimal
spring stiffness should be carefully considered. In addition, licensees should
ensure maintenance of proper spring stiffness following initial determination
of optimal stiffness. In the case of Calvert Cliffs, the addition of stiffer
springs appeared to provide an extra margin of stability. This temporarily
compensated for other auxiliary feedwater system deficiencies that also re- quired correction.
Reliability problems were much more evident when the auxiliary feedwater pumps
were periodically tested using quick starts from cold conditions. This demon- strated the importance of surveillance testing which, in so far as practical, should duplicate the service conditions that would exist if the equipment were
called on to operate.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
D. Limroth, RI
(215) 337-5121 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
- OGCB:DOEA:NRR RI *PPMB:ARM C/OG0B:WDEA:NRR D/DOEA:NRR
DCKirkpatrick DLimroth TechEd CHBerlinger CERossi
03/07/88 03/ /88 03/09/88 03// /88 03/ /88
IN 88-xx
March xx, 1988 4. Further steam lines drain Improvements are under evaluation.
The Calvert Cliffs problems highlighted the importance of optimal sizing of
buffer springs in that the single most effective short term corrective action
appeared to be installation of the stiffer buffer springs. However, changes in
spring stiffness for the purpose of improving stability can adversely impact
other governor response characteristics. Therefore, the selection of optimal
spring stiffness should be carefully considered. In addition, licensees should
ensure maintenance of proper spring stiffness following initial determination
of optimal stiffness. In the case of Calvert Cliffs the addition of stiffer
springs appeared to provide an extra margin of stability. This temporarily
compensated for other auxiliary feedwater system deficiencies which also
require correction.
Reliability problems were much more evident when the auxiliary feedwater pumps
were tested by quick starts from cold conditions. This demonstrated the
importance of surveillance testing which, in so far as practical, duplicates
expected service conditions which would exist if the equipment were called upon
to operate.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
D. Limroth, RI
(215) 337-5121 Attachment: List of Recently Issued NRC Information Notices
OGCB:DOEA:NRR RIpi~,bAPPMB:ARM C/OGCB:DOEA:NRR D/DOEA:NRR
DCKirkpat jk DLiiioth TechEd OM' CHBerlinger CERossi
03O'88L/ 03/40/88 03/1 /88 03/ /88 03/ /88
|
---|
|
list | - Information Notice 1988-01, Safety Injection Pipe Failure (27 January 1988, Topic: Unidentified leak, Water hammer)
- Information Notice 1988-03, Cracks in Shroud Support Access Hole Cover Welds (2 February 1988, Topic: Stolen)
- Information Notice 1988-04, Inadequate Qualification and Documentation of Fire Barrier Penetration Seals (5 February 1988, Topic: Fire Barrier, Fire Watch, Stolen)
- Information Notice 1988-05, Fire in Annunciator Control Cabinets (12 February 1988, Topic: Stolen)
- Information Notice 1988-06, Foreign Objects in Steam Generators (29 February 1988, Topic: Stolen)
- Information Notice 1988-07, Inadvertent Transfer of Licensed Material to Uncontrolled Locations (7 March 1988, Topic: Stolen)
- Information Notice 1988-08, Chemical Reactions with Radioactive Waste Solification Agents (14 March 1988, Topic: Process Control Program, Stolen)
- Information Notice 1988-09, Reduced Reliability of Steam-Driven Auxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL Type Governors (18 March 1988)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 FR 43950, October 31, 1988) (23 December 1988)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988) (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-10, Memorandum of Understanding Between NRC and Osha Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988. (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-11, Potential Loss of Motor Control Center And/Or Switchboard Function Due to Faulty Tie Bolts (7 April 1988)
- Information Notice 1988-12, Overgreasing of Electric Motor Bearings (12 April 1988)
- Information Notice 1988-13, Water Hammer & Possible Piping Damage Caused by Misapplication of Kerotest Packless Metal Diaphragm Globe Valves (18 April 1988)
- Information Notice 1988-14, Potential Problems with Electrical Relays (18 April 1988)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (FDA) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (Fda) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988)
- Information Notice 1988-16, Identify Waste Generators in Shipments of Low-Level Waste to Land Disposal Facilities (22 April 1988, Topic: Water hammer)
- Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. (22 April 1988, Topic: Safe Shutdown, Weld Overlay, Feedwater Heater, Through-Wall Leak, Water hammer)
- Information Notice 1988-18, Malfunction of Lockbox on Radiography Device (25 April 1988, Topic: Overexposure)
- Information Notice 1988-19, Questionable Certification of Class Ie Components (26 April 1988, Topic: Water hammer)
- Information Notice 1988-19, Questionable Certification of Class IE Components (26 April 1988)
- Information Notice 1988-20, Unauthorized Individuals Manipulating Controls and Performing Control Room Activities (5 May 1988)
- Information Notice 1988-21, Inadvertent Criticality Events at Oskarshamn and at U.S. Nuclear Power Plants (9 May 1988, Topic: Shutdown Margin)
- Information Notice 1988-22, Disposal of Sludge from Onsite Sewage Treatment Facilities at Nuclear Power Stations (12 May 1988)
- Information Notice 1988-23, Potential for Gas Binding of High-Pressure Safety Injection Pumps During a Loss-Of-Coolant Accident (12 May 1988)
- Information Notice 1988-24, Failures of Air-Operated Valves Affecting Safety-Related Systems (13 May 1988)
- Information Notice 1988-25, Minimum Edge Distance for Expansion Anchor Bolts (16 May 1988, Topic: Earthquake)
- Information Notice 1988-26, Falsified Pre-Employment Screening Records (16 May 1988)
- Information Notice 1988-27, Deficient Electrical Terminations Identified in Safety-Related Components (18 May 1988)
- Information Notice 1988-28, Potential for Loss of Post-Loca Recirculation Capability Due to Insulation Debris Blockage (19 May 1988, Topic: Coatings)
- Information Notice 1988-29, Deficiencies in Primary Containment Low-Voltage Electrical Penetration Assemblies (24 May 1988)
- Information Notice 1988-30, Target Rock Two-State SRV Setpoint Drift Update (25 May 1988)
- Information Notice 1988-31, Steam Generator Tube Rupture Analysis Deficiency (25 May 1988)
- Information Notice 1988-32, Prompt Reporting to NRC of Significant Incidents Involving Radioactive Material (25 May 1988)
- Information Notice 1988-33, Recent Problems Involving the Model Spec 2-T Radiographic Exposure Device (27 May 1988)
- Information Notice 1988-34, Nuclear Material Control & Accountability of Non-Fuel Special Nuclear Material at Power Reactors (31 May 1988)
- Information Notice 1988-36, Possible Sudden Loss of RCS Inventory During Low Coolant Level Operation (8 June 1988)
- Information Notice 1988-37, Flow Blockage of Cooling Water to Safety System Components (14 June 1988, Topic: Ultimate heat sink)
- Information Notice 1988-38, Failure of Undervoltage Trip Attachment of General Electric Circuit Breakers (15 June 1988)
- Information Notice 1988-39, Loss of Recirculation Pumps with Power Oscillation Event (15 June 1988)
- Information Notice 1988-40, Examiners' Handbook for Developing Operator Licensing Examinations (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (RERs) (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (Rers) (22 June 1988)
- Information Notice 1988-42, Circuit Breaker Failures Due to Loose Charging Spring Motor Mounting Bolts (23 June 1988, Topic: Loctite)
- Information Notice 1988-43, Solenoid Valve Problems (23 June 1988, Topic: Stroke time)
- Information Notice 1988-44, Mechanical Binding of Spring Release Device in Westinghouse Type DS-416 Circuit Breakers (24 June 1988)
- Information Notice 1988-45, Problems in Protective Relay & Circuit Breaker Coordination (7 July 1988, Topic: Safe Shutdown)
- Information Notice 1988-46, Licensee Report of Defective Refurbished Circuit Breakers (8 July 1988)
- Information Notice 1988-47, Slower-than-Expected Rod-drop Times (14 July 1988)
... further results |
---|