Capacitor Failures in Westinghouse Eagle 21 Plant Protection SystemsML031060558 |
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: |
05/09/1994 |
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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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-nr IN-94-033, NUDOCS 9405040254 |
Download: ML031060558 (10) |
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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 May 9, 1994 NRC INFORMATION NOTICE 94-33: CAPACITOR FAILURES IN WESTINGHOUSE EAGLE 21 PLANT PROTECTION SYSTEMS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to two different types of capacitor failures that
can cause loss of power to portions of Eagle 21 reactor protection systems
manufactured by Westinghouse Electric Corporation. 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 the past year, Commonwealth Edison Company (CECo) experienced several
instances of partial loss of electrical power within the Westinghouse Eagle 21 plant protection system at Zion Station, Unit 1, during normal plant
operation. Two types of failures were identified, and these were reported by
CECo Idider Part 21 of Title 10 of the Code of Federal Regulations (10 CFR) on
April , 1994.
One type of failure involved Series RS 300 and RT 300 dc power supplies
manufactured by ASTEC America, with Westinghouse part numbers 2D33574G07 and
2D33574G09. Electrolytic capacitors C2 and C7 failed, causing complete loss
of dc power to the connected loads. Unit 1 at Zion Station has 10 racks of
Eagle 21 equipment. Each rack contains two power supplies. One provides
power to the tester subsystem, which is not essential for performing the
system design safety function. The other power supply provides power for the
loop processor subsystem, which includes reactor protection and engineered
safety features channels and logic, and may include some control room
indication channels. On loss of power, a loop processor channel fails to the
de-energized state, which normally is the tripped state. Containment spray, however, is an energize-to-actuate function, and loss of power would prevent
the channel from tripping. In certain racks, loss of power would also defeat
some control room indications required by Regulatory Guide 1.97.
9405040254 PMk TtC MOA;t 94m033 -e3 14 9
<KIN 94-33 May 9, 1994 The other failure type involved type TDA40DM time delay relays manufactured by
Douglas-Randall, with Westinghouse part number PS12800H02. Ceramic capacitor
C2 failed, causing either repetitive cycling or complete loss of ac power to
the connected loads. The time delay relays are used in the Eagle 21 ac power
distribution panels to sequentially load the power supplies during protection
system startup. The failure consequences are similar to those for the power
supply capacitors described above.
Discussion
The failed capacitors in the ASTEC America dc power supplies were type
SR65, Z5U manufactured by AVX Corporation. The failed capacitors had date
codes from 9130 to 9136 where the first two digits of the date code indicate
the year of manufacture and the last two digits indicate the week within that
year. The capacitors were used in power supplies manufactured in 1991, with
date codes 9134 through 9147. Westinghouse determined that several capacitors
with the suspect date codes shorted or exhibited electrical leakage, and were
cracked or ruptured. The Zion power supplies were returned to Westinghouse, the capacitors with the suspect date codes were replaced, and the power
supplies were tested and returned to service. The ASTEC America power
supplies are used in the following Westinghouse systems:
- Neutron flux monitoring system (NFMS)
- Auxiliary Shutdown Indication System (ASIS)
- Plant Safety Monitoring System (PSMS)
- Qualified Display Processing System (QDPS)
- Reactor Vessel Level Instrumentation System - 86 (RVLIS-86)
- Inadequate Core Cooling Monitor System (ICCM)
- ATWS Mitigating System Actuation Circuitry (AMSAC)
- Eagle 21 CECo and Westinghouse determined that the capacitors in the Douglas-Randall
time delay relays were failing prematurely because of excessive heat
dissipated in the epoxy potted module by nearby resistor RI. The problem was
corrected by returning the relays to Westinghouse, where the resistors were
relocated outside the relay module. The relays were tested and returned to
service.
The Zion failures were discussed at an Eagle 21 owners group meeting in
November 1993, but the causes had not been identified at that time. Because
the failures are detectable and a Westinghouse failure analysis determined
that they are aging related and likely to be random rather than simultaneous, Westinghouse elected not to submit a notification under 10 CFR Part 21. For
the power supply failures, Westinghouse advised the NRC that it issued an
Infogram to all customers with Eagle 21 or other affected equipment on
April 29, 1994. For the relay failures, only four of the five Eagle 21 customers are affected, since Sequoyah does not have the relays. Zion is
fully aware of the concerns, and the hardware has been corrected. The Diablo
Canyon system will be corrected before it is shipped to the site.
Westinghouse advised that it was preparing plant-specific followup letters to
Watts Bar, Turkey Point, and Diablo Canyon for issue on April 29, 1994.
V IN 94-33 May 9, 1994 This information notice is being sent to all power reactor licensees because
AVX capacitors and Douglas-Randall time delay relays may be used in other
applications at nuclear power plants.
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 (NRR) Project Manager.
Brian . Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Richard C. Wilson, NRR
(301) 504-3220
Attachment:
List of Recently Issued NRC Information Notices
a 4I
Attachment
IN 94-33 May 9, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-53, Effect of Hurricane 04/29/94 All holders of OLs or CPs
Supp. 1 Andrew on Turkey Point for nuclear power reactors.
Nuclear Generating
Station and Lessons Learned
94-32 Revised Seismic Hazard 04/29/94 All holders of OLs or CPs
Estimates for nuclear power reactors.
94-31 Potential Failure of 04/14/94 All holders of OLs or CPs
Wilco, Lexan-Type HN-4-L for nuclear power reactors.
Fire Hose Nozzles
90-68, Stress Corrosion Cracking 04/14/94 All holders of 01 or CPs
Supp. I of Reactor Coolant Pump for pressurized water
Bolts reactors.
Leaking Shutdown Cooling 04/12/94 All holders of OLs or CPs
Isolation Valves at for nuclear power reactors.
Cooper Nuclear Station
Charging Pump Trip during 04/11/94 All holders of OLs or CPs
a Loss-of-Coolant Event for pressurized water
Caused by Low Suction reactors.
Pressure
92-51, Misapplication and 04/12/94 All holders of OLs or CPs
Supp. 1 Inadequate Testing of for nuclear power reactors.
Molded-Case Circuit
Breakers
Potential Problems with 04/05/94 All holders of OLs or CPs
Fire-Barrier Penetration for nuclear power reactors.
Seals
94-27 Facility Operating 03/31/94 All holders of OLs or CPs
Concerns Resulting from for nuclear power reactors.
Local Area Flooding
DC = Operating License
CP - Construction Permit
IN 94-33 May 9, 1994 This information notice is being sent to all power reactor licensees because
AVX capacitors and Douglas-Randall time delay relays may be used in other
applications at nuclear power plants.
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 (NRR) Project Manager.
Orial signed by
Brian K. Grimeg
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Richard C. Wilson, NRR
(301) 504-3220
Attachment:
List of Recently Issued NRC Information Notices
OFFICE VIB/DRIL SC/VIB/DRIL BC/VIB/DRIL BC/ICB DRCH
NAME RWILSON* GCWALINA* LNORRHOLM* JWERMEIL*
DATE 4/20/94 4/20/94 4/21/94 4/25/94 OFFICE
NAME
TECH ED
MMEJAC*
GCB/DORS
DKIRKPATRICK*
4/18/94 D/DRIL/NRRS
CEROSSI*
4/28/94 BC/GCB/DORS*
AKUGLER
L
4/ /94_
ID
DATE 4/18/94 - f - R - ThI
.94
- - --
OFFICIAL RECORD LUPY U0CUI~eFF rNdme; Vl-SS-2.LN
IN 94-XX
April xx, 1994 This information notice is being sent to all power reactor licensees because
it is possible that the AVX capacitors and the Douglas-Randall time delay
relays may be used in other applications at nuclear power plants.
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 (NRR) Project Manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Richard C. Wilson, NRR
(301) 504-3220
Attachment:
List of Recently Issued NRC Information Notices
OFFICE VIB/DRIL SC/VIB/DRIL BC/VIB/DRIL BC/ICB DRCH
NAME RWILSON* GCWALINA* LNORRHOLM* JWERMEIL*
DATE 4/20/94 4/20/94 4/21/94 4/25/94 OFFICE TECH ED GCB/DORS D/DRIL/NRRS BC/GCB/DORS D/DORS
NAME MMEJAC* DKIRKPATRICK* CEROSSI* AKUGLER BKGRIMES2!,
D4/18/94
- --
- - -IUA
UFFtCIAL KtCUKU ---
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IN 94-XX
April 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 (NRR) Project Manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Richard C. Wilson, NRR
(301) 504-3220
Attachment:
List of Recently Issued NRC Information Notices
OFFICE :IB/DRIL SC/VIB/DRIL BC/VIB/DRIL BC/ICB DRCH __]
NAME RWILSON* GCWALINA* LNORRHOLM* JWERMEIL* l
DATE 4/V/94 4/i0/94 4/2//94 4_ _ _l
__94 OFFICE TECH ED GCB/DORS D/DRILLNRRS BC/GCB/DORS D1DORS
NAME MMEJAC* DKIRKPATRICK* C AKUGLER BKGRIMES
DATE 4/18/94 4/18/94 44/L2'04 . 4 /94 4/ /94 OFFICIAL RECORD COPY Document Name:LAULMAN
IN 94-XX
April 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
one of the technical contacts 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: Richard C. Wilson, NRR
(301) 504-3220
Attachment:
List of Recently Issued NRC Information Notices
OFFICE VIB/DRIL SCVIB/DRIL BC I/RIL R BC/ICB D__W_ _ _
NAME RWILSO Ai N GCM A LM JWERMEILX
DATE 4/20/94 4/2t/94 4/ZI/94 4/25 9I
OFFICE TECH ED GCB/DORS D/DRIL/NRRS BC/GCB/DORS D/DORS
NAME MMEJAC* DKIRKPATRICK* CEROSSI AKUGLER BKGRIMES
DATE 4/18/94 4/18/94 4
4/ /94 4/ /94 4/ _ _ __
OFFICIAL RECORD COPY Document Name:EAGLE21.IN
IN 94-XX
April 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
one of the technical contacts 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 contactA Richard C. Wilson, NRR
(301) 504-3220
Attachment:
List of Recently Issued NRC Information Notices
OFFICE VIB/DRIL ICB/DRCH SC/VIB/DRIL BC/VIB/DRIL BC/ICB/DRCH
NAME RWILSON CDOUTT GCWALINA LNORRHOLM JWERMEIL
lDATE 4/ /94 14/ /94 14/ /94 4 /LL94 4/ /94 OFFICE
NAME
D _
17/19/93 GCB/DORS
DKIRKPATRICK
4/lW/94 0 Z
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CEROSSI
4/ /94
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BKGRIMES
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- - - - - -- ------
OFFICIAL RECORD LUPY U0CUffent HdJme:rLCCLL1.ln
IN 93-XX
July 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
one of the technical contacts 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 contacts: Richard C. Wilson, NRR
(301) 504-3220
Clifford K. Doutt, NRR
(301) 504-2847 Attachment:
List of Recently Issued NRC Information Notices
OFFICE VIB/DRIL ICB/DRCH SC/VIB/DRIL BC/VIB/DRIL BC/ICB/DRCH
NAME RWILSON CDOUTT GCWALINA LNORRHOLM JWERMEIL
DATE 4/ /94 4/ /94 4/ /94 4/ /94 COPY YES YES YES YES NO YES NO
OFFICE TECHED GCB/DORS D/DRIL/NRRS BC/GCB/DORS DDR
NAME rA. rA WOO DKIRKPATRICK CEROSSI AKUGLER BKGRIMES
DATE 711-193 4/ /94 4/ /94 9/ /93 /94 COPY YES YES NO YES NO YES NO YES NO
ar-rowAL ------ --- vY roc rAl___ re
UttILIAL KtLUKU LUPY Document Name:MI.IN
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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)
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