Potential for Loss of Shutdown Cooling While at Low Reactor Coolant LevelsML031130325 |
Person / Time |
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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 |
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IN-90-006, NUDOCS 9001230175 |
Download: ML031130325 (7) |
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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
SHUTDOWN COOLING
NRC INFORMATION NOTICE NO. 90-06: POTENTIAL FOR LOSS OF COOLANT LEVELS
WHILE AT LOW REACTOR
Addressees
nuclear power
All holders of operating licenses or construction permits for
reactors.
Purpose
to a potential problem
This information notice is intended to alert addressees (RHR) system during
affecting the operability of the residual heat removal
is expected that re- operating conditions involving mid-loop operation. It to their facilities
-cipients will review the information for applicability problems. However, and consider actions, as appropriate, to avoid similar constitute NRC
suggestions contained in this information notice do not
response is required.
requirements; therefore, no specific action or written
Description of Circumstances
the residual heat
On July 18, 1989, at Comanche Peak Unit 1, train 'Al ofloading. The air
removal system was in operation prior to initial fuel
being used to
operated RHR heat exchanger flow control valve (FCV) was water level was
maintain system flow below 2000 gpm. The reactor vessel
legs.
being maintained slightly abpve the center line of the hot
FCV failed. The loss
The inverter supplying power to the controller for the to its emergency core
of power to the controller resulted in the FCV failing open valve caused
cooling system (ECCS) position of being fully open. The flow caused
an increase in system flow to 4400 gpm. This sudden, increased
the RHR pipe con- conditions where vortexing was expected at the suction of
nection to the RCS.
to an alternate
The power supply for the controllers was manually transferred
terminating the event.
source and the FCV was throttled, thus
Discussion:
flow through the
The FCV is manually throttled to maintain a desired rate of to control the
RHR heat exchanger. The heat exchanger flow rate is adjusted
to the vessel. Total system flow is
temperature of the water being returned with the
regulated by throttling the heat exchanger bypass valve coincident
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 Issuance Issued te
Notice No. SubJect
90-05 Inter-System Discharge of 1/26/9O All holders of ULs
Reactor Coelant or Ch for nuclear
power reactors.
90-04 Cracking of the Upper Shall- 1/26/90 All holders of OLs
to-Transition Cone Girth or CPs.for Westinghouse.
Melds Is Steam Generators designed and Combustion
Engineering-disigned
nuclear power reactors.
90-03 malfunction of Borg-Varner 1/23/90 All holders of OLs
SBlted Sonnet Check Valves or CPs for uclewr
Causd by Failure of the power reactors.
Swing Arm
90-02 Potential Degradation of 1/29D All holders of OLs
Secondary Contaient or CPs for Slis.
90-01 lIportace of Proper 1/12/90 All holders of NRC
Response to Self-Identifted materials licenses.
Violations by Licensees
89-90 Pressurizer Safety Valv 12/28/84 All holder of OMs
Lift Setpoint Shift or Ch for Pilb.
89-8 Event Notificatton 12/26/89 All holders of CLs
Workshents or en for nuclear
powerreactors.
89-88 Recent XRC-Sponsored 12/26189 All holders of Ots
Testing of motor-Operated or CPsfor nutlear
Valves poer reactors.
8647 Disablilg of Emergency 12/19189 All helders of OLs
Diesel Generators by or CVs for nuclear
Their Neutral Ground-Fault power reactors.
Protection Circuitry
8945. etalclad. Lou-Voltage 12/IS/19 All holders of OLs
Supp. 2 Power Circuit Dreakars or CPsfor nuclear
Refurbished with power reactors.
Substandard Parts
OL*OpitunceS - _
CV s Construction Permit
UNITED STATES
IPOSTAGE & FEES PAOID
NUCLEAR REGULATORY COMMISSION ISNiRC 1 WASHINGTON, D.C. 20555 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. 8300
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
EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR NRR:SRXB
- NFields: db *BCalure *DCFischer *CJHaughney *CHBerlinger *RJones
1/12/90 1/13/90 1/16/90 1/16/90 1/17/90 1/23/90
1/Z3'90
K)j V%2IN 90-
January , 1990 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the technical
contacts 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
Attachment: List of Recently Issued NRC Information Notices
EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR N R B
- DCFischer *CJHaughney* *CHBerlinger RJV es
/ /90 / /90 / /90 / /90 / /90 I j:/90
D:DOEA:NRR
CERossi
/ /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
Attachment: List of Recently Issued NRC Information Notices
C0Wvtn Au t
AJF VIU46x1 4fhire0rAtU rAI CV
EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR D:DOEA:NRR
NFields:db DCFischer CJHaughney CHBerlinger CERossi
Jr //,/90 I /11/SQ , /14/90 I /14/90 / 117/90 / /90
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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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