Potential Failures of Thermostatic Control Valves for Diesel Generator Jacket Cooling Water ML031190379 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 , 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 , Crane Issue date:
12/26/1991 From:
Rossi C Office of Nuclear Reactor Regulation To:
References IN-91-085 , NUDOCS 9112190286Download: ML031190379 (6)
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Millstone ,
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Monticello ,
Calvert Cliffs ,
Dresden ,
Davis Besse ,
Peach Bottom ,
Browns Ferry ,
Salem ,
Oconee ,
Mcguire ,
Nine Mile Point ,
Palisades ,
Palo Verde ,
Perry ,
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Ginna ,
Diablo Canyon ,
Callaway ,
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Waterford ,
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Robinson ,
Clinton ,
South Texas ,
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Cook ,
Comanche Peak ,
Yankee Rowe ,
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Quad Cities ,
Humboldt Bay ,
La Crosse ,
Big Rock Point ,
Rancho Seco ,
Zion ,
Midland ,
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Fort Calhoun ,
FitzPatrick ,
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Atlantic Nuclear Power Plant ,
Crane Category:NRC Information Notice
[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 [[: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]] OR [[:Crane]] </code>.
'NUCLEAR REGULATORY COMMISSION
Contents
1 OFFICE OF NUCLEAR REACTOR REGULATION 2 December 26, 1991 3 POTENTIAL FAILURES OF THERMOSTATIC CONTROL 4 Addressees 5 Purpose 6 Description of Circumstances
6.1 Upon examining the engine, the licensee 6.2 December 26, 1991 Discussion 6.3 When the jacket water temperature is low, the 6.4 The heat generated 6.5 Licensee personnel examined these elements 6.6 The cracking 6.7 The licensee had also found degraded power 6.8 Related Generic Communications 6.9 December 26, 1991 This information notice requires 6.10 Division of Operational Events Assessment 6.11 Robert Martin, NRR 6.12 William Orders, RII 6.13 John Zeiler, RII 6.14 Problems with Criticality 6.15 Failures Resulted in 6.16 Caused by Hall Thinning 6.17 Switchyard Problems that 6.18 Offsite Power 6.19 Tensioning System During 6.20 Deficiencies in the 6.21 Barrier Materials 6.22 Fuel Pool Draindown 6.23 Control Power for 6.24 All Nuclear Regulatory 6.25 All holders of OLs or CPs 6.26 All holders of OLS or CPs 6.27 All holders of OLs or CPs 6.28 All holders of OLS or CPs 6.29 All holders of OLs or CPs 6.30 All holders of OLs or CPs 6.31 All holders of OLs or CPs 6.32 All holders of OLs or CPs 6.33 UNITED STATES 6.34 WASHINGTON, D.C. 20555 6.35 FIRST CLASS MAIL 6.36 PERMIT No G 67 6.37 December 26, 1991 This information notice requires 6.38 Charles E. Rossi, Director 6.39 Office of Nuclear Reactor Regulation 6.40 Robert Martin, NRR 6.41 William Orders, RII 6.42 John Zeiler, RII 6.43 List of Recently Issued NRC Information Notices 6.44 December xx, 1991 6.45 Charles E. Rossi, Director 6.46 Office of Nuclear Reactor Regulation 6.47 Robert Martin, NRR 6.48 William Orders, RII 6.49 John Zeiler, RII 6.50 List of Recently Issued NRC Information Notices 6.51 CEMCt racken
OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON , D.C.
20555
December 26, 1991 NRC INFORMATION NOTICE 91-85:
POTENTIAL FAILURES OF THERMOSTATIC CONTROL VALVES FOR DIESEL GENERATOR JACKET COOLING
WATER
Addressees All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to the potential for failure of thermostatic control
valves for diesel generator jacket cooling water.
It is expected that recipi- ents will review the information for applicability to their facilities and
consider actions, as appropriate, to avoid similar problems. However, sugges- tions contained in this information notice are not NRC requirements; therefore, no specific action or written response is required.
Description of Circumstances On September 10, 1991 at the Catawba Nuclear Station, Unit 2, the Duke Power
Company (the licensee3 removed emergency diesel generator (EDG ) 2A from service
for minor corrective and preventive maintenance. The next day, the engine was
successfully tested for its performance in a no load condition for 5 minutes
and was shut down.
Shortly afterwards, the engine was restarted for a 1-hour
operability test. After operating the EDG for 15 minutes at full load, opera- tors observed that the engine cooling water and lube oil temperatures were
increasing abnormally. The engine oil level was checked and found to be within
normal range. After about 20 minutes, alarms for high lube oil inlet and
outlet (1750F) and high jacket water (1750F) temperatures were received.
Responding to these alarms, an operator verified that the nuclear service water
supply valve was open and that the flow was within normal range. After operat- ing for about 28 minutes, the engine tripped on a high lube oil outlet tempera- ture (2000F).
After the trip and while the engine was coasting to a stop, an
explosion occurred in the crankcase.
Upon examining the engine, the licensee determined that a thermostatic valve in the jacket cooling water system had
failed resulting in the engine overheating, which resulted in significant
engine damage.
Further details of the event may be found in Licensee Event Report 50-414/91-10
or NRC Inspection Report 50-414/91-21.
(I:9129086
IN 91-85
December 26, 1991 Discussion At Catawba, the cooling water system for the Transamerica Delaval DSRV-16-4
(16 cylinder) diesel generator engine supplies cooling water to the engine
jacket, the engine lube oil cooler, the combustion air after-coolers, and the
governor lube oil cooler. An engine-driven circulation pump circulates cooling
water through the closed loop system that includes a three-way thermostatic
control valve (AMOT Model 8D).
When the jacket water temperature is low, the AMOT valve, which works similarly to the thermostat in an automobile engine, diverts diesel jacket cooling flow from the heat exchanger, which is cooled by
nuclear service water . The AMOT valve modulates open to control the tempera- ture of the diesel jacket water to about 1650F as the engine reaches operating
temperature.
Heat is transferred through the heat exchanger to the plant's
nuclear service water system.
The licensee's investigation revealed that the AMOT thermostat valve had
malfunctioned and caused the engine to overheat.
During the operability test, the AMOT valve only partially opened from the bypass position, thus allowing
the jacket and lube oil temperatures to rise above normal operating tempera- tures.
With the engine fully loaded, the temperature of the oil and water rose
to 2000F. At these elevated temperatures, the oil emitted an increased amount
of vapors. The elevated temperatures also affected the clearances between the
moving parts and reduced the oil's lubricating qualities.
The heat generated by-th- friction-between-the-piston-and-liner--ignited-the-oil-vapors._The
-
ignition of the oil vapors caused the rapid pressure increase and the explosion
in the crankcase.
The AMOT valve malfunctioned because two of the four "power elements" (sensing
elements) in the valve had failed.
Licensee personnel examined these elements at the licensee's metallurgical laboratory and attributed the root cause of the
failure to slow growing intergranular stress corrosion cracking .
The cracking caused small openings that allowed the thermally active medium of the power
element to leak out.
This loss of thermally active medium directly affects the
actuating rod travel (valve stroke). The failed elements were those originally
provided with the engine in 1979.
The licensee had also found degraded power elements during a recent inspection of the Unit 1 diesel engines.
The vendor's
documentation indicates that the power elements have a 15-year shelf life and
should be inspected at intervals of 2 to 3 years to detect and make provision
for normal wear.
The licensee's corrective actions include changing the AMOT power element
replacement schedule and evaluating changing the engine oil to a type with
increased film strength and greater stability at elevated temperatures.
Related Generic Communications A similar failure of a thermostatic control valve, but resulting from a differ- ent failure mechanism, was discussed in NRC Information Notice 82-56 ,
"Robertshaw Thermostatic Flow Control Valves," December 30, 1982.
-
'\\K )
IN 91-85
December 26, 1991 This information notice requires you have any questions about the
of the technical contacts listed
Reactor Regulation (NRR ) project
no specific action or written response. If
information in this notice, please contact one
below or the appropriate Office of Nuclear
manager. .
arles E. Rossi, Director
Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Technical contacts:
Robert Martin, NRR (301) 504-1493
William Orders, RII (803) 831-2963
John Zeiler, RII (803) 831-2963
-Attachment: -List-of Recently Issued-NRC Information Notices -
Attachment
IN 91-85 December 26, 1991 LIST OF RECENTLY
ISSUED
NRC INFORMATION
NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
91-84
91-83
91-18, Supp. 1
91-82
91-81
91-80
91-79
88-92, Supp. 1
91-78
Problems with Criticality Alarm Components/Systems
Solenoid-Operated Valve
Failures Resulted in Turbine Overspeed
High-Energy Piping Failures
Caused by Hall Thinning Problems with Diaphragms
in Safety-Related Tanks
Switchyard Problems that Contribute to Loss of
Offsite Power Failure of Anchor
Head Threads on Post-
Tensioning System During Surveillance Inspection
Deficiencies in the Procedures for Instal- ling Therno-Lag Fire
Barrier Materials Potential for Spent
Fuel Pool Draindown Status Indication of
Control Power for Circuit Breakers Used
in Safety-Related Appli- cations
12/26/91
All Nuclear Regulatory Commission (NRC) fuel
cycle licensees, Interim
spent fuel storage licens- ees, and critical mass
licensees.
12/20/91
All holders of OLs or CPs for nuclear power reactors.
12/18/91
All holders of OLS or CPs for nuclear power reactors.
12/18191
All holders of OLs or CPs 1 for nuclear power reactors.
12/16/91
All holders of OLS or CPs for nuclear power reactors.
12/11/91
All holders of OLs or CPs for nuclear power reactors.
12/06/91
All holders of OLs or CPs for nuclear power reactors.
11/29/91
All holders of OLs or CPs for nuclear power reactors.
11/28/91
All holders of OLs or CPs for nuclear power reactors.
OL - Operating License
CP
UNITED STATES NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300
FIRST CLASS MAIL POSTAGE b FEES PAID
USNPIC
PERMIT No G 67 IN 91-85
December 26, 1991 This information notice requires you have any questions about the
of the technical contacts listed
Reactor Regulation (NRR ) project
no specific action or written response.
If
information in this notice, please contact one
below or the appropriate Office of Nuclear
manager.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical contacts:
Robert Martin, NRR (301) 504-1493
William Orders, RII (803) 831-2963
John Zeiler, RII (803) 831-2963 Attachment:
List of Recently Issued NRC Information Notices SEE PREV OUS 4ONCURRENCES D/ X AyRlyI
C/SPLB:DST:NRR*SELB:DST:NRR CHBerlinger
TechEd
CEMCCracken
OPChopra
12/Z991
12/18/91
12/16/91
12/17/91
12/17/91
D/PD23:DRP:NRR*RESINSP:RII PCWen
REMartin
DMatthews
JZeiler
WTOrders
12/11/91
12/12/91
12/12/91
12/11/91
12/11/91 DOCUMENT NAME: IN 91-85
I
IN 91-XX
December xx, 1991 This information notice requires
you have any questions about the
of the technical contacts listed
Reactor Regulation (NRR ) project
no specific action or written response. If
information in this notice, please contact one
below or the appropriate Office of Nuclear
manager.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical contacts:
Robert Martin, NRR (301)
504-1493
William Orders, RII (803) 831-2963
John Zeiler, RII (803) 831-2963 Attachment:
List of Recently Issued NRC Information Notices Document Name: EDG THERMOSTATIC CONTROL
SEE PREVIOUS CONCURRENCES D/DOEA:NRR
C/OGCB:6WOAN-R*RPB:ADM
CERossi
CHBerlinger
TechEd
12/
/91
12//r/91
12/16/91
PCWen
REMartin
DMatthews
12/11/91
12/12/91
12/12/91 VALVE A
+
C PLB:DST:NRF
CEMCt racken 12//'//91
NRR*RESINSP:RII JZeiler
12/11/91 I SELB:DST:NRR
OPChopra &12-.
12/X7/91
WTOrders
12/11/91
list Information Notice 1991-01, Supplier of Misrepresented Resistors 4 January 1991 Topic Fitness for Duty Overspeed Information Notice 1991-02, Brachytherapy Source Management 7 January 1991 Topic Brachytherapy Information Notice 1991-03, Management of Wastes Contaminated with Radioactive Materials (Red Bag Waste & Ordinary Trash) 7 January 1991 Information Notice 1991-04, Reactor Scram Following Control Rod Withdrawal Associated with Low Power Turbine Testing 28 January 1991 Topic Fitness for Duty Information Notice 1991-05, Intergranular Stress Corrosion Cracking in Pressurized Water Reactor Safety Injection Accumulator Nozzles 30 January 1991 Topic Hydrostatic Intergranular Stress Corrosion Cracking Liquid penetrant Information Notice 1991-06, Lock-up of Emergency Diesel Generator and Load Sequencer Control Circuits Preventing Restart of Tripped Emergency Diesel Generator 31 January 1991 Topic Fitness for Duty Brachytherapy Overspeed Information Notice 1991-07, Maintenance Deficiency Associated with General Electric Horizontal Custom 8000 Induction Motors 4 February 1991 Information Notice 1991-08, Medical Examinations for Licensed Operators 5 February 1991 Topic Brachytherapy Information Notice 1991-09, Counterfeiting of Crane Valves 25 September 2007 Information Notice 1991-10, Summary of Semiannual Program Performance Reports on Fithess-For-Duty (FFD) in the Nuclear Industry 12 February 1991 Information Notice 1991-12, Potential Loss of Net Positive Suction Head (NPSH) of Standby Liquid Control System Pumps 15 February 1991 Information Notice 1991-13, Inadequate Testing of Emergency Diesel Generators (Edgs) 4 March 1991 Topic Loss of Offsite Power Information Notice 1991-13, Inadequate Testing of Emergency Diesel Generators (EDGs) 4 March 1991 Topic Loss of Offsite Power Information Notice 1991-14, Recent Safety-Related Incidents at Large Irradiators 5 March 1991 Topic Coatings Incorporated by reference Uranium Hexafluoride Overexposure Information Notice 1991-15, Incorrect Configuration of Breaker Operating Springs in General Electric AK-Series Metal-Clad Circuit Breakers 6 March 1991 Information Notice 1991-16, Unmonitored Release Pathways from Slightly Contaminated Recycle and Recirculation Water Systems at a Fuel Facility 6 March 1991 Information Notice 1991-17, Fire Safety of Temporary Installation or Services 11 March 1991 Information Notice 1991-18, High-Energy Piping Failures Caused by Wall Thinning 18 December 1991 Topic Feedwater Heater Information Notice 1991-19, Steam Generator Feedwater Distribution Piping Damage 12 March 1991 Information Notice 1991-20, Electrical Wire Insulation Degradation Caused Failure in a Safety-Related Motor Control Center 19 March 1991 Information Notice 1991-21, Inadequate Quality Assurance Program of Vendor Supplying Safety-Related Equipment 19 March 1991 Information Notice 1991-22, Four Plant Outage Events Involving Loss of AC Power or Coolant Spills 19 March 1991 Topic Loss of Offsite Power Spent fuel rack Information Notice 1991-23, Accidental Radiation Overexposures to Personnel Due to Industrial Radiography Accessory Equipment Malfunctions 26 March 1991 Topic Overexposure Information Notice 1991-24, Recent Operating Experience Involving Reactor Operation Without a Licensed Reactor Operator or Senior Reactor Operator Present in the Control Room 26 March 1991 Information Notice 1991-25, Commercial-Grade Structural Framing Components Supplied As Nuclear Safety-Related Equipment 1 April 1991 Information Notice 1991-25, Commercial-Grade Structural Framing Components Supplied as Nuclear Safety-Related Equipment 1 April 1991 Information Notice 1991-26, Potential Nonconservative Errors in the Working Format Hansen-Roach Cross-Section Set Provided with Keno and Scale Codes 2 April 1991 Topic Brachytherapy Information Notice 1991-27, Incorrect Rotation of Positive Displacement Pump 10 April 1991 Information Notice 1991-28, Cracking in Feedwater System Piping 15 April 1991 Information Notice 1991-29, Deficiencies Identifie During Electrical Distribution System Functional Inspections 15 April 1991 Information Notice 1991-30, Inadequate Calibration of Thermoluminescent Dosimeters Utilized to Monitor Extremity Dose at Uranium Processing and Fabrication Facilities 23 April 1991 Topic Uranium Hexafluoride Depleted uranium Information Notice 1991-31, Nonconforming Magnaflux Magnetic Particle (14AM) Prepared Bath 9 May 1991 Information Notice 1991-32, Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and Engineering 15 May 1991 Topic Hot Short Intergranular Stress Corrosion Cracking Liquid penetrant Information Notice 1991-33, Reactor Safety Information for States During Exercises and Emergencies 31 May 1991 Information Notice 1991-34, Potential Problems in Identifying Causes of Emergency Diesel Generator Malfunctions 3 June 1991 Topic Loss of Offsite Power Information Notice 1991-35, Labeling Requirements for Transporting Multi-Hazard Radioactive Materials 7 June 1991 Information Notice 1991-36, Nuclear Plant Staff Working Hours 10 June 1991 Information Notice 1991-37, Compressed Gas Cylinder Missile Hazards 10 June 1991 Information Notice 1991-38, Thermal Stratification in Feedwater System Piping 13 June 1991 Topic Unanalyzed Condition Information Notice 1991-39, Compliance with 10 CFR Part 21, Reporting of Defects and Noncompliance 17 June 1991 Topic Basic Component Information Notice 1991-40, Contamination of Nonradioactive System and Resulting Possibility for Unmonitored, Uncontrolled Release to the Environment 19 June 1991 Information Notice 1991-41, Potential Problems with the Use of Freeze Seals 27 June 1991 Information Notice 1991-42, Plant Outage Events Involving Poor Coordination Between Operations and Maintenance Personnel During Valve Testing and Manipulations 27 June 1991 Information Notice 1991-43, Recent Incidents Involving Rapid Increases in Primary-To-Secondary Leak Rate 5 July 1991 Topic Grab sample Information Notice 1991-45, Possible Malfunction of Westinghouse Ard, Bfd, & Nbfd Relays, & A200 DC & DPC 250 Magnetic Contactors 5 July 1991 Topic Commercial Grade Information Notice 1991-46, Degradation of Emergency Diesel Generator Fuel Oil Delivery Systems 18 July 1991 Information Notice 1991-47, Failure of Thermo-Lag Fire Barrier Material to Pass Fire Endurance Test 6 August 1991 Topic Safe Shutdown Fire Barrier Information Notice 1991-48, False Certificates of Conformance Provided by Westinghouse Electric Supply Company for Refurbished Commercial-Grade Circuit Breakers 9 August 1991 Topic Fire Barrier Information Notice 1991-49, Enforcement of Safety Requirements for Radiographers 15 August 1991 Topic High Radiation Area Overexposure Information Notice 1991-50, A Review of Water Hammer Events After 1985 20 August 1991 Topic Water hammer ... further results
