Potential Problems with BWR Level Instrumentation Backfill ModificationsML031070176 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
11/26/1993 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-93-089, NUDOCS 9311190454 |
Download: ML031070176 (8) |
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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, 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 [[: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 [[: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 November 26, 1993 NRC INFORMATION NOTICE 93-89: POTENTIAL PROBLEMS WITH BWR LEVEL
INSTRUMENTATION BACKFILL MODIFICATIONS
Addressees
All holders of operating licenses or construction permits for boiling water
reactors (BWRs).
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to potential problems that have been identified by
licensees involving hardware modification to the reactor vessel water level
instrumentation system. 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
NRC Bulletin (NRCB) 93-03, "Resolution of Issues Related to Reactor Vessel
Water Level Instrumentation in BWRs," issued on May 28, 1993, requested that
licensees implement hardware modifications necessary to ensure the level
instrumentation system design is of high functional reliability for long-term
operation. In response to this bulletin, all BWR licensees with the exception
of Big Rock Point, which does not use cold reference leg instrumentation, have
either implemented modifications or have committed to implement modifications.
The majority of these licensees have decided to install a reference leg
backfill system to supply a continuous flow of water from the control rod
drive (CRD) hydraulic system through the reference legs to preclude migration
of dissolved noncondensible gases down the legs. In August 1993, a potential
problem was found at the Susquehanna nuclear power plant during the design of
this backfill modification.
Discussion
It was postulated at Susquehanna that a manual isolation valve in one of the
reference legs (see Figure 1) could be closed by operator error. Closure of
this valve would result in pressurization of that reference leg to CRD system
pressure and erroneous indication of low reactor water level and high reactor
pressure on all instrumentation associated with that reference leg. The
transient resulting from pressurization of the most limiting reference leg
9311190454 KE-e 193-o 93 Ill
K.,_ IN 93-89 November 26, 1993 includes reactor scram and opening of all safety relief valves (SRVs) due to
the false high reactor pressure. The SRVs would remain open and depressurize
the reactor until the valves are closed by operator action, or actual reactor
pressure falls below approximately 446 kPa [50 psig] at which time the valves
can no longer stay open. Reactor depressurization and loss of inventory
through the SRVs, in combination with the false low water level signal on the
affected reference leg, would result in closure of the main steam isolation
valves, actuation of high-pressure and low-pressure emergency core cooling
system (ECCS) and containment isolation. Low-pressure ECCS injection would
commence after the low-pressure permissive is satisfied. This permissive
would be satisfied in this scenario, allowing the low pressure ECCS injection
valves to open, because only one of the pressure transmitters is affected and
the logic would still be satisfied. A single failure could defeat this logic, however, preventing all low-pressure ECCS Injection. The low-pressure
permissive can be bypassed in the control room to open the injection valves
for all four low pressure core spray (LPCS) pumps. The Susquehanna licensee
has informed the NRC that it has physically disabled the manual isolation
valves to prevent misoperation of these valves; in addition, the valves are
not readily accessible as they are located 6.1 meters [20 feet] above the
floor.
This event was recently analyzed for the LaSalle plant by Commonwealth Edison.
The analysis indicates that the low-pressure permissive for opening the low- pressure ECCS injection valve would be defeated for the LaSalle design due to
the false high pressure signal, thus preventing ECCS injection from the
affected division. If a single failure is assumed in the relay for the low- pressure permissive on the other division, no low-pressure ECCS injection
would be available. Because the induced plant transient is potentially so
severe, LaSalle has designed its backfill modification to make the injection
point for the backfill system on the reactor side of the manual isolation
valve and excess flow check valve, thereby precluding the potential for
pressurization of the reference leg through the backfill system.
Commonwealth Edison took a different design approach for its Dresden and
Quad Cities plants. The backfill system design for Dresden and Quad Cities
injects into the reference leg on the instrument rack side of the manual
isolation valve and excess flow check valve. Additional administrative
controls were developed to ensure that the isolation valve would not be
inadvertently closed. The licensee analyzed the inadvertent closure of the
manual isolation valve for the Dresden and Quad Cities plants and concluded
that, while multiple SRVs would open, the resultant plant transient could be
mitigated by appropriate operator actions. Without operator actions, the low- pressure ECCS would be available for event mitigation; however, a single
failure in the instrumentation system could defeat the low-pressure permissive
for opening the low-pressure ECCS Injection valves and result in no low- pressure ECCS being available for this transient. The licensee also
determined that this design presented an unreviewed safety question because it
would increase the probability of a previously analyzed accident, and
submitted an application to amend its license pursuant to 10 CFR 50.90. The
NRC is currently reviewing the licensee submittal.
IN 93-89 November 26, 1993 Other minor problems with the backfill system have been encountered when
installing the system and returning the instrumentation to service after
installation was complete. At the Perry plant, a problem occurred when the
licensee was in the process of venting one of the instrument lines following
the installation of the modification. The job plan directed the operation of
the wrong valve, and instead of opening the vent valve the technician opened
the isolation valve, allowing air into the reference leg. As a result, the
instrumentation associated with the high pressure core spray system (HPCS) was
inoperable until it was re-filled and vented. Similar events have occurred at
other plants due to procedural inadequacy or lack of attention to detail.
Related Generic Communications
by Rapid Depressurization," July 24, 1992.
Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f),"
August 19, 1992.
Observed During Normal Plant Depressurization," April 8, 1993.
Water Level Instrumentation in BWRs,' May 28, 1993.
This information notice requires no specific action or written response. If
you have any questions regarding the information in this notice, please
contact the technical contact listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Amy Cubbage, NRR
(301) 504-2875 Attachments:
1. Simplified Sketch of Backfill Modification
2. List of Recently Issued NRC Information Notices
rfl
tO CONDENSATE POT
REACTOR VESSEL
(
DRYWELL
REACTOR BLDG
U
7 MANUAL
L ISOLATION
C EXCESS FLOW
QA BOUNDARY $ CHECK VALVE
CRD CHARGING
WATER HEADER
REFERENCE LEG
INSTRtUm
VARIABLE
LEG
RACK C
e0 (
FIGURE 1 - SIMPLIFIED SKETCH OF BACKFILL MODIFICATION
cI-
Ij3 ED
w,
A4...achment 2 IN 93-89 November 26, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-88 Status of Motor-Operated 11/30/93 All holders of OLs or CPs
Valve Performance Pre- for nuclear power reactors.
diction Program by the
Electric Power Research
Institute
93-87 Fuse Problems with 11/04/93 All holders of OLs or CPs
Westinghouse 7300 for nuclear power reactors.
Printed Circuit Cards
93-86 Identification of Iso- 10/29/93 All holders of OLs or CPs
topes in the Production for test and research
and Shipment of Byproduct reactors.
Material at Non-power
Reactors
93-85 Problems with X-Relays 10/20/93 All holders of OLs or CPs
in DB- and DHB-Type for nuclear power reactors.
Circuit Breakers Manu- factured by Westinghouse
93-84 Determination of Westing- 10/20/93 All holders of OLs or CPs
house Reactor Coolant for pressurized water
Pump Seal Failure reactors (PWRs).
93-83 Potential Loss of Spent 10/07/93 All holders of OLs or CPs
Fuel Pool Cooling for boiling water reactors
Following A Loss of (BWRs).
Coolant Accident (LOCA)
93-82 Recent Fuel and Core 10/12/93 All holders of OLs or CPs
Performance Problems in for nuclear power reactors
Operating Reactors and all NRC-approved fuel
suppliers.
93-81 Implementation of 10/12/93 All holders of OLs or CPs
Engineering Expertise for nuclear power reactors.
on Shift
OL - Operating License
CP - Construction Permit
IN 93-89 a-> November 26, 1993 Other minor problems with the backfill system have been encountered when
installing the system and returning the instrumentation to service after
installation was complete. At the Perry plant, a problem occurred when the
licensee was in the process of venting one of the instrument lines following
the installation of the modification. The Job plan directed the operation of
the wrong valve, and instead of opening the vent valve the technician opened
the isolation valve, allowing air into the reference leg. As a result, the
instrumentation associated with the high pressure core spray system (HPCS) was
inoperable until it was re-filled and vented. Similar events have occurred at
other plants due to procedural inadequacy or lack of attention to detail.
Related Generic Communications
by Rapid Depressurization," July 24, 1992.
Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f),"
August 19, 1992.
Observed During Normal Plant Depressurization," April 8, 1993.
Water Level Instrumentation in BWRs," May 28, 1993.
This information notice requires no specific action or written response. If
you have any questions regarding the information in this notice, please
contact the technical contact listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
orig /s/'d by BKGrimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Amy Cubbage, NRR
(301) 504-2875 Attachments:
1. Simplified Sketch of Backfill Modification
2. List of Recently Issued NRC Information Notices
SRXB:DSSA* OGCB:DORS* TECH ED.* SRXB:DSSA* SRXB:DSSA* D:DSSA* OGCB:DORS*
ACUBBAGE PWEN RSANDERS WLYON RJONES ATHADANI GMARCUS
1 11/16/93 11/15/93 11/16/93 11/18/93 11/20/93 11/23/93
11/2.493 DOCUMENT NAME: 93-89.IN
IN 93-xx
November xx, 1993 This information notice requires no specific action or written response. If
you have any questions regarding the information in this notice, please
contact the technical contact listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contact:
Amy Cubbage, NRR
(301) 504-2875 Attachments:
1. Simplified Sketch of Backfill Modification
2. List of Recently Issued NRC Information Notices
SRXB:DSSA* OGCB:DORS* TECH ED.* SRXB:DSSA* SRXB:DSSA* D: DSSA* OGCB:DORS
ACUBBAGE PWEN RSANDERS WLYON RJONES ATHADANI GMARCUS At'i
11/15/93 11/16/93 11/15/93 11/16/93 11/18/93 11/20/93 11/23/93 D: DORS
BGRIMES
11/ /93 DOCUMENT NAME: BWRWTLVL.WEN
instrumentation associated with the high pressure core spray system (HPCS) was
inoperable until it was re-filled and vented. Similar events have occurred at
other plants due to procedural inadequacy or lack of attention to detail.
Related Generic Communications
by Rapid Depressurization," July 24, 1992.
Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f),"
August 19, 1992.
Observed During Normal Plant Depressurization," April 8, 1993.
Water Level Instrumentation in BWRs," May 28, 1993.
This information notice requires no specific action or written response. If
you have any questions regarding the information in this notice, please
contact the technical contact listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contact:
Amy Cubbage, NRR
(301) 504-2875 Attachments:
1. Simplified Sketch of Backfill Modification
2. List of Recently Issued NRC Information Notices
EDITED BY: R. Sanders
DATED: 11/15/93 SRXB:DSSA* OGCB:DORS* SRXB:DSSA* SRXB:DSSA* D:DSSA OGCB:DORS D:DORS
ACUBBAGE PWEN WLYON RJONES ATHAqkNI GMARCUS BGRIMES
11/15/93 11/16/93 11/16/93 11/18/93 11/?V/93 11/ /93 11/ /93
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list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
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