Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure| ML031060474 |
| 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, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant  |
|---|
| Issue date: |
04/11/1994 |
|---|
| From: |
Grimes B
Office of Nuclear Reactor Regulation |
|---|
| To: |
|
|---|
| References |
|---|
| IN-94-029, NUDOCS 9404060036 |
| Download: ML031060474 (9) |
|
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, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
|---|
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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 [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
I.' 4 A UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 April 11, 1994 NRC INFORMATION
NOTICE 94-29: CHARGING PUMP TRIP DURING A LOSS-OF-COOLANT
EVENT CAUSED BY LOW SUCTION PRESSURE
Addressees
All holders of operating
licenses or construction
permits for pressurized- water reactors.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to the possibility
of a charging pump trip caused by inadequate
suction pressure because too many pumps may be aligned to a single suction path during accident mitigation.
It is expected that recipients
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 are not NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances
During a steam generator
tube rupture event at Palo Verde Unit 2 on March 14, 1993 (NRC Inspection
Report 50-279/93-14), a charging pump tripped off on low suction pressure when the operators
switched the charging pump suction source from the volume control tank to the refueling
water tank. During the subsequent
evaluation
of the event, the licensee determined
that four pumps, three charging pumps and a boric acid makeup pump, were all taking suction through the same 7.6-cm [3-in.] diameter pipe. The licensee also determined
that the high rate of flow through the suction pipe that resulted from the simultaneous
operation
of all four pumps caused a sufficient
pressure reduction
at the suction of the pumps to lower this pressure below the low suction trip setpoints
of the charging pumps.Two charging pumps were already running when the tube rupture occurred.
In addition, the operators
were running a boric acid pump to circulate
the refueling
water through filters to purify it for an upcoming outage; The boric acid pump flow was being recirculated
back to the refueling
water tank and did not contribute
to the makeup water going into the reactor coolant system. The operators
started the third charging pump early in the event in an effort to restore the pressurizer
level, which was decreasing
because of the tube rupture. At that time all of the charging pumps were taking suction from the volume control tank, which is the normal source of makeup water for the reactor coolant system. Approximately
30 minutes later, in accordance
with emergency
procedures, the operators
opened the suction valve from the 9404060036 po-rXE qq-D29 qqoqI n TkId9L III
IN 94-29-V April 11, 1994 refueling
water tank and then closed the suction valve from the volume control tank.At this point one of the charging pumps tripped off. The operators
were able to restore the tripped charging pump to operation
by realigning
the suction of the charging pumps to other suction paths from the refueling
water tank.Discussion
Following
this event the licensee calculated
that, with the boric acid pump running, the remaining
flow capacity of the refueling
water tank suction source that was in use was Just sufficient
for two charging pumps. With all four pumps running the suction pressure was below the low suction trip set points (81.0 kPa to 87.2 kPa [11.75 psia to 12.65 psia]) for the charging pumps. Because the trip set points are set at slightly different
pressures, only one pump tripped. Once this first pump tripped, the resulting
rise in suction pressure allowed the remaining
pumps to keep running.The licensee concluded
that, if recirculation
by the boric acid pump is not in progress, sufficient
suction pressure exists for all three charging-pumps.
Consequently, the licensee revised the emergency
procedures
that involve the charging pumps to specify that any ongoing recirculation
of the refueling water by the boric acid pump is to be terminated
when refueling
water is needed for emergency
makeup.Licensees
of pressurized-water
reactors use the charging systems in a number of ways for accident mitigation, such as including
the charging system as a part of the automatic
safety injection
system. Charging systems are also used as a source of pressurizer
spray to depressurize
the reactor when the reactor coolant pumps are shut down. Emergency
operating
procedures
often refer to the charging systems for other uses as well.Some licensees
do not isolate the volume control tank (or its equivalent)
when the charging system source is switched to the refueling
water tank (or its equivalent), but depend on the static pressure in the refueling
water tank to keep the volume control tank from draining.
Should the volume control tank empty in response to lower-than-expected
suction pressure, hydrogen cover gas normally contained
in this tank could enter the charging system suction and cause the pumps to malfunction.
IN 94-29 April 11, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation
project manager.Brian K. Gr es, Director ter-Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact: Warren C. Lyon, NRR (301) 504-3892 Attachment:
List of Recently Issued NRC Information
Notices
Ak-1achment
IN 94-29 April 12, 1994 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 92-51, Supp. 1 94-28 94-27 94-26 Misapplication
and Inadequate
Testing of Molded-Case
Circuit Breakers Potential
Problems with Fire-Barrier
Penetration
Seals Facility Operating Concerns Resulting
from Local Area Flooding Personnel
Hazards and Other Problems from Smoldering
Fire-Retard- ant Material in the Drywell of a Boiling-Water Reactor Safety Systems Response to Loss of Coolant and Loss of Offsite Power Failure of Containment
Spray Header Valve to Open due to Excessive Pressure from Inertial Effects of Water Inadequate
Maintenance
of Uninterruptible
Power Supplies and Inverters Guidance to Hazardous, Radioactive
and Mixed Waste Generators
on the Elements of a Waste Minimization
Program 04/12/94 04/05/94 03/31/94 03/28/94 03/25/94 03/25/94 03/24/94 03/25/94 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All NRC Licensees.
93-17, Rev. 1 94-25 94-24 94-23 OL -Operating
License CP -Construction
Permit
.I If IN 94-29 April 11, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation
project manager.orig /s/'d by CIGrimes Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact: Warren C. Lyon, NRR (301) 504-3892 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFFICE *OGCB *TECH ED *SRXB/DSSA
NAME DCKirkpatrick
RSanders WCLyon RJones DATE 111/30/93
111/30/93 , 12/20/93 12/22/93*D:DSSA*C:OGCB/DORS
D:DORS/NRR
AThadani GHMarcus BKGrimes6 01/04/94 01/11/94 04/L /94 VULUMMN NAME: 4-M. IN
IN 94-xx March xx, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation
project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contact: Warren C. Lyon, NRR (301) 504-3892*SFF PREVOUS CONCURRENCE
OFFICE *OGCB *TECH ED *SRXB/DSSA
NAME DCKirkpatrick
RSanders WCLyon RJones DATE 11/30/93 11/30/93 12/20/93 1 12/22/93.-- .1*D: DSSA*C:OGCB/DORS
D:DORS/NRR
AThadani GHMarcus BKGrimes 01/04/94 01/11/94 03/ /94 I=01tw DOCUMENT NAME: CHARGING.DCK
IN 94-xx January xx, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation
project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
Contact: Warren C. Lyon, (301) 504-3892 NRR*SEE PREVIOUS CONCURRENCE
OFFICE *OGCB *TECH ED *SRXB/DSSA
NAME DCKirkpatrick
I RSanders WCLyon RJones DATE I1/30/93 J >/BY 11/30/93 112/20/93
12/22/93 D:DSSA Okl C:OGCB/DORS
D:DORS/NRR
c llAThadani GHMarcus MYA1 BKGrimes 01/04/94 01/ti/94 01/ /94 DOCUMENT NAME: CHARGING.DCK
-* I IN 93-xx December xx, 1993 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation
project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
Contact: Warren C. Lyon, NRR (301) 504-3892 Af. -.-/*SEF PREVIOUS CONCURRENCE
,____1 ____ _ _____' /s OFFICE *OGCB *TECH ED ' XifDSSA SU C:SRXB/DSSAI
I NAME DCKirkpatrick
RSanders WCLyon TC K ns RJones V DATE 11/30/93 1 11/30/93 2 /£ ./z/'?L I3 L , ..a D:DSSAM C:OGCB/DORS
D:DORS/NRR
ATha n GHMarcus I BKGrimes F 1k/ & _ /91 _ 1 /93r4 DOCUMENT NAME: CHARGING.DCK
3 a9 IN 93-xx December xx, 1993 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation
project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
Contact: Warren C. Lyon, NRR (301) 504-3892 t OFFICE OGCB TECH ED SRXBA 54 l C:OGCB/DORS
D:DORS/NRR
NAME fDCKirkpatrick
RPoUlm'us
WCLyon GHMarcus BKGrimes DATE /(1g9/93PZ-@
Iit/3093 j/93 / /93 / /93 1 DOCUMENT NAME: CHARGING .CK l"05-- 1
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| list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
... further results |
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