Potential for Loss of Shutdown Cooling While at Low Reactor Coolant LevelsML031130325 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Issue date: |
01/29/1990 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
---|
IN-90-006, NUDOCS 9001230175 |
Download: ML031130325 (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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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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 [[: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 [[: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 January 29, 1990 NRC INFORMATION
NOTICE NO. 90-06: POTENTIAL
FOR LOSS OF SHUTDOWN COOLING WHILE AT LOW REACTOR COOLANT LEVELS
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
- This information
notice is intended to alert addressees
to a potential
problem affecting
the operability
of the residual heat removal (RHR) system during operating
conditions
involving
mid-loop operation.
It is expected that re--cipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice do not constitute
NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances:
On July 18, 1989, at Comanche Peak Unit 1, train 'Al of the residual heat removal system was in operation
prior to initial fuel loading. The air operated RHR heat exchanger
flow control valve (FCV) was being used to maintain system flow below 2000 gpm. The reactor vessel water level was being maintained
slightly abpve the center line of the hot legs.The inverter supplying
power to the controller
for the FCV failed. The loss of power to the controller
resulted in the FCV failing to its emergency
core cooling system (ECCS) position of being fully open. The open valve caused an increase in system flow to 4400 gpm. This sudden, increased
flow caused conditions
where vortexing
was expected at the suction of the RHR pipe con-nection to the RCS.The power supply for the controllers
was manually transferred
to an alternate source and the FCV was throttled, thus terminating
the event.Discussion:
The FCV is manually throttled
to maintain a desired rate of flow through the RHR heat exchanger.
The heat exchanger
flow rate is adjusted to control the temperature
of the water being returned to the vessel. Total system flow is regulated
by throttling
the heat exchanger
bypass valve coincident
with the adjustment
of the FCV.001230175 Z ( (' D*1 IC, eo uachr
IN 90-06 January 29, 1990 During this event, there were no indications
of pump air ingestion.
However, the increased
system flow corresponded
to the rate at which vortexing
had been calculated
to occur based on the existing RCS level. The licensee had previously
determined
maximum permitted
flow rates for various reduced levels of the RCS to prevent the possibility
of vortexing
and air entrainment
into the RHR pump.Although RHR pump operation
was never actually impaired, the potential
existed for air to be introduced
to the pump's suction. This concern is exacerbated
by* the fact that the heat exchanger
FCVs for both trains of RHR are powered from the same inverter.
Since the FCVs open fully on a loss of power, both trains of RHR could become inoperable
on a loss of power during mid-loop operation.(A loss of instrument
air would also cause the FCVs to fail to the full open position and could also result in the loss of both trains of the RHR system).During most modes of operation, having the FCVs go -fully open on loss of power or instrument
air is not a safety concern because having the valves fully open does not normally prevent the system from performing
its safety function.
However, having the valves go fully open while at mid-loop could result in the loss of decay heat removal capability.
This loss could persist until electrical
power or instrument
air is restored and air is vented from the RHR system.The licensee has revised procedures
for mid-loop operation
to require manually positioning
the cold leg injection
isolation
valves to limit the maximum flow through the system, even with the FCVs fully open. This lineup will be used whenever the unit is at mid-loop and protects against the consequences
of failure of either electrical
power or instrument
air.Several generic communications
have been issued informing
licensees
of the consequences
of the loss of residual (decay) heat removal and the operating conditions
under which the probability
of a loss increases;
i.e., reduced inventory
conditions.
The most recent publications
include Generic Letter (GL) No. 87-12, "Loss of Decay Heat Removal While the Reactor Coolant System is Partially
Filled;" GL No. 88-17, *Loss of Decay Heat Removal;" NRC In-formation
Notice (IN) 87-23, "Loss of Decay Heat Removal During Low Reactor Coolant Level Operation;" IN 88-36, 'Possible
Sudden Loss of RCS Inventory During Low Coolant Level Operation;" and IN 89-67, "Loss of Residual Heat Removal Caused by Accumulator
Nitrogen Injection." The event described above introduces
a subtle failure scenario which licensees
may not have considered.
IN 90-06 January 29, 1990 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
NRR project manager.Charles E. Rossi, irector Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts:
Nick Fields, NRR (301) 492-1173 Steve Bitter, RIV (817) 897-1500 Attachment:
List of Recently Issued NRC Information
Notices
I IN 90-06 January 29, 1990 During this event, there were no indications
of pump air ingestion
However the increased
system flow enrraenan~nA
n~ -~ neto. Hwvr Attachment
~q ) sx 90-06 Jasmary 2§ 1990 Page I of I LIST OF RECEITLT ISSUED NIR INFORtAT1011 OTICES JCW --lnfonation
Notice No.90-05 90-04 SubJect Inter-System
Discharge
of Reactor Coelant Issuance 1/26/9O Cracking of the Upper Shall- 1/26/90 to-Transition
Issued te All holders of ULs or Ch for nuclear power reactors.All holders of OLs or CPs.for Westinghouse.
designed and Combustion
Engineering-disigned
nuclear power reactors.All holders of OLs or CPs for uclewr power reactors.All holders of OLs or CPs for Slis.All holders of NRC materials
licenses.90-03 malfunction
of Borg-Varner
SBlted Sonnet Check Valves Causd by Failure of the Swing Arm 90-02 Potential
Degradation
of Secondary
Contaient 90-01 lIportace
of Proper Response to Self-Identifted
Violations
by Licensees 89-90 Pressurizer
Safety Valv Lift Setpoint Shift 89-8 Event Notificatton
Workshents
89-88 Recent XRC-Sponsored
Testing of motor-Operated
Valves 8647 Disablilg
of Emergency Diesel Generators
by Their Neutral Ground-Fault
Protection
Circuitry 8945. etalclad.
Lou-Voltage
Supp. 2 Power Circuit Dreakars Refurbished
with Substandard
Parts 1/23/90 1/29D 1/12/90 12/28/84 All holder of OMs or Ch for Pilb.12/26/89 All holders of CLs or en for nuclear power reactors.12/26189 All holders of Ots or CPs for nutlear poer reactors.12/19189 All helders of OLs or CVs for nuclear power reactors.12/IS/1 9 All holders of OLs or CPs for nuclear power reactors.OL*OpitunceS
-_CV s Construction
Permit UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, D.C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. 8300 IPOSTAGE & FEES PAOID ISNiRC 1 IN 90-06 January 29, 1990 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
NRR project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: Nick Fields, NRR (301) 492-1173 Steve Bitter, RIV (817) 897-1500 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
EAB:NRR*NFields:
db 1/12/90 TECH:EDITOR
- BCalure 1/13/90 EAB:NRR C:EAB:NRR*DCFischer
1/16/90 1/16/90 C:OGCB:NRR
1/17/90 NRR:SRXB*RJones 1/23/90 1 /Z3'90
K)j V%2IN 90-January , 1990 No specific action or written response is required by this information
If you have any questions
about this matter, please contact one of the contacts listed below or the Regional Administrator
of the appropriate
office.notice.technical regional Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
EAB:NRR*NFields:db
/ /90 D:DOEA:NRR
CERossi/ /90 TECH:EDITOR
- BCalure/ /90 EAB:NRR*DCFischer
/ /90 C:EAB:NRR*CJHaughney*
/ /90 C:OGCB:NRR
/ /90 N R B RJV es I j:/90
IN 90-January , 1990%...Z'age
3 of 3 No specific action or written response is required by this infornation
notice. If you have any questions
about this matter, please contact the technical
contact listed below or the Regional Administrator
of the appropriate
regional office.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500 List of Recently Issued NRC Information
Notices Attachment:
AJF EAB:NRR NFields:db
Jr //,/90 C0Wvtn Au t VIU46x1 4fhire0rAtU
rAI TECH:EDITOR
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list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination, Thermal fatigue)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan, Uranium Hexafluoride)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Dissimilar Metal Weld)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990, Topic: Overexposure)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990, Topic: Siren)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990, Topic: Siren)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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