Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring ML031070066 Person / Time Site:
Beaver Valley , Millstone , Hatch , Monticello , Calvert Cliffs , Dresden , Davis Besse , Peach Bottom , Browns Ferry , Salem , Oconee , Mcguire , Nine Mile Point , Palisades , Palo Verde , Perry , Indian Point , Fermi , Kewaunee , Catawba , Harris , Wolf Creek , Saint Lucie , Point Beach , Oyster Creek , Watts Bar , Hope Creek , Grand Gulf , Cooper , Sequoyah , Byron , Pilgrim , Arkansas Nuclear , 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 , Crane Issue date:
01/07/1994 From:
Grimes B Office of Nuclear Reactor Regulation To:
References IN-94-002 , NUDOCS 9401030245Download: ML031070066 (9)
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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 ,
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 ,
Crane Category:NRC Information Notice
[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 [[: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]] OR [[:Crane]] </code>.
Contents
1 NUCLEAR REGULATORY COMMISSION 2 WASHINGTON, D.C. 20555 3 Addressees 4 Purpose 5 Description of Circumstances 6 DISCUSSION
6.1 Brian K. Grimes, Director 6.2 Office of Nuclear Reactor Regulation 6.3 Kamalakar R. Naidu, NRR 6.4 List of Recently Issued NRC Information Notices 6.5 Attuacment I 6.6 January 7, 1994 LIST OF RECENTLY ISSUED 6.7 Turbine Blade Failures 6.8 Excitation from Electrical 6.9 Reporting Requirements 6.10 Potential Deficiencies 6.11 Distribution System 6.12 Undervoltage Relay and 6.13 Motor Brakes on Valve 6.14 Failures of Yokes 6.15 Gate and Globe Valves 6.16 Emergency Diesel 6.17 Offsite Power Events 6.18 Unauthorized Forced 6.19 Mile Island Unit 1 on 6.20 All holders of OLs or CPs 6.21 All holders of OLs or CPs 6.22 All U.S. Nuclear Regulatory 6.23 All holders of OLs or CPs 6.24 All holders of OLs and CPs 6.25 All holders of OLs and CPs 6.26 All holders of OLs or CPs 6.27 All holders of OLs or CPs 6.28 All holders of OLs or CPs 6.29 All holders of OLs or CPs 6.30 Brian K. Grimes, Director 6.31 Office of Nuclear Reactor Regulation 6.32 J. Frederick Ringwald, RIV 6.33 Kamalakar R. Naidu, NRR 6.34 List of Recently Issued NRC Information Notices 6.35 Brian K. Grimes, Director 6.36 Office of Nuclear Reactor Regulation 6.37 J. Frederick Ringwald, RIV 6.38 Kamalakar R. Naidu, NRR 6.39 List of Recently Issued NRC Information Notices 6.40 December xx, 1993 6.41 Brian K. Grimes, Director 6.42 Office of Nuclear Reactor Regulation 6.43 J. Frederick Ringwald, RIV 6.44 Kamalakar R. Naidu, NRR 6.45 List of Recently Issued NRC Information Notices 6.46 U rurrr. rrWI 6.47 Brian K. Grimes, Director 6.48 Office of Nuclear Reactor Regulation 6.49 J. Frederick Ringwald, RIV 6.50 Kamalakar R. Naidu, NRR 6.51 List of Recently Issued NRC Information Notices 6.52 Brian K. Grimes, Director 6.53 Office of Nuclear Reactor Regulation 6.54 J. Frederick Ringwald, RIV 6.55 Kamalakar. R. Naidu, NRR 6.56 List of Recently Issued NRC Information Notices 6.57 Brian K. Grimes, Director 6.58 Office of Nuclear Reactor Regulation 6.59 J. Frederick Ringwald, RIV 6.60 Kamalakar. R. Naidu, NRR 6.61 List of Recently Issued NRC Information Notices
NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 7, 1994 NRC INFORMATION NOTICE 94-02:
INOPERABILITY OF GENERAL ELECTRIC KAGNE-BLAST
BREAKER BECAUSE OF MISALIGNMENT OF CLOSE-LATCH
SPRING
Addressees All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees that a misalignment of the close-latch reset spring
(tension style) in 4.16 kV General Electric (GE ) Magne-Blast circuit breakers
could prevent the breaker from closing on demand. 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 On April 7, 1993, the Arizona Public Service Company, licensee for the
Palo Verde Nuclear Generating Station, notified the NRC that a safety-related
4.16 kV GE Magne-Blast breaker (Model AM-4.16-250-9H , 1200 ampere breaker with
ML-13 mechanism) was found inoperable with the closing springs discharged.
The inoperability was caused by misalignment of the close-latch reset spring.
This misalignment resulted in the coils of the spring catching on the close- latch monitoring switch mounting plate. This prevented the close-latch
monitoring switch from closing and prevented the charging motor from
recharging the closing springs, which rendered the breaker inoperable . The
condition was identified by an auxiliary operator who noticed that the clear
control power/closing springs charged lamp was not illuminated on the front of
the breaker cubicle. There was no indication of this problem in the control
room.
Further details can be found in NRC Inspection Report 50-528; 50-529; and
50-530/93-11.
9401030245 PUR~~~
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<>IN 94-02 January 7, 1994
DISCUSSION GE Magne-Blast breakers are used in many safety-related circuits throughout
the nuclear industry. At Palo Verde, these breakers are used for numerous
safety-related pumps (e.g., high-pressure safety injection, low-pressure
safety injection, and containment spray ) and in safety-related load centers.
While this condition occurred in a 4.16 kV breaker, all GE Magne-Blast
breakers equipped with the ML-13 mechanism having the tension style close- latch spring may be susceptible to this problem.
There are two different designs for the close-latch spring in the GE Magne- Blast breakers. The design that caused the problem was the tension-style
spring that is positioned beside the close-latch monitoring switch. GE
subsequently replaced this spring with a torsion-style spring, which surrounds
the close-latch shaft and prevents the spring from catching on the mounting
plate. GE considers this modification to be a design enhancement and has not
issued a service advisory letter or instruction on this subject.
The failed condition described above may not be evident if a breaker racking
operation is performed before the close-latch spring is inspected.
The
vibration associated with the racking operation may be sufficient to free the
spring from the close-latch monitoring switch mounting plate. However, during
subsequent breaker operation, the spring coils may catch and render the
breaker inoperable . Although there would likely be local indication that the
spring was not fully charged, there would be no control room indication of the
inoperability of the breaker.
No specific action or written response is required by this information notice.
If you have any questions regarding this matter, please contact one of the
technical contacts listed below or the appropriate Office of Nucl ar Reactor
Regulation (NRR ) project manager.
Brian K. Grimes, Director Division of Operating Reactor Support
Office of Nuclear Reactor Regulation Technical contacts: J. Frederick Ringwald, RIV
(316) 364-8653
Kamalakar R. Naidu, NRR (301) 504-2980
Attachment:
List of Recently Issued NRC Information Notices K>
Attuacment I IN 94-02
January 7, 1994 LIST OF RECENTLY ISSUED NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
94-01
93-101
93-100
91-29, Supp. 2
93-99
93-98
93-97
93-96
93-95
93-94
Turbine Blade Failures Caused by Torsional
Excitation from Electrical System Disturbance
Jet Pump Hold-Down Beam
Failure
Reporting Requirements for Bankruptcy
Potential Deficiencies Found During Electrical
Distribution System Functional Inspections
Undervoltage Relay and Thermal Overload Setpoint
Problems
Motor Brakes on Valve Actuator Motors
Failures of Yokes Installed on Walworth
Improper Reset Causes
Emergency Diesel Generator Failures
Storm-Related Loss of
Offsite Power Events due to Salt Buildup
on Switchyard Insulators
Unauthorized Forced Entry into the Pro- tected Area at Three
Mile Island Unit 1 on February 7, 1993
01/07/94
12/17/93
12/22/93
12/22/93
12/21/93
12/20/93
12/17/93
12/14/93
12/13/93
12/09/93
All holders of OLs or CPs for nuclear power reactors
All holders of OLs or CPs for boiling-water reactors
All U.S. Nuclear Regulatory Commission licensees.
All holders of OLs or CPs for nuclear power reactors.
All holders of OLs and CPs for nuclear power reactors.
All holders of OLs and 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
located close to a large
body of salt water.
All holders of OLs or CPs for nuclear power reactors.
OL = Operating License
CP = Construction Permit
94-02 January 7, 1994 No specific action or written response is required by this information notice.
If you have any questions regarding this matter, please contact one of the
technical contacts listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR ) project manager.
rigial sIgned by
Brian K.
Grimes
Brian K. Grimes, Director Division of Operating Reactor Support
Office of Nuclear Reactor Regulation Technical contacts:
J. Frederick Ringwald, RIV (316) 364-8653
Kamalakar R. Naidu, NRR (301) 504-2980
Attachment:
List of Recently Issued NRC Information Notices SFF PRFVTOfUS CONCURRENCE OFFICE
NAME
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IN 94-02 January 7, 1994 No specific action or written response is required by this information notice.
If you have any questions regarding this matter, please contact one of the
technical contacts listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR ) project manager.
g1nal figned by
Brian K.
GriMes
Brian K. Grimes, Director Division of Operating Reactor Support
Office of Nuclear Reactor Regulation Technical contacts:
J. Frederick Ringwald, RIV (316) 364-8653
Kamalakar R. Naidu, NRR (301) 504-2980
Attachment:
List of Recently Issued NRC Information Notices rAnIriiFJNCF
OFFICE
NAME
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DATE
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IN 93-XX
December xx, 1993 No specific action or written response is required by this information notice.
If you have any questions regarding this matter, 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:
J. Frederick Ringwald, RIV (316) 364-8653
Kamalakar R. Naidu, NRR (301) 504-2980
Attachment:
List of Recently Issued NRC Information Notices OFFICE
NAME
PCWen/vsb
FRingwald
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HJWong
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DATE
10/05/93
10/05/93
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October xx, 1993 No specific action or written response is required by this information notice.
If you have any questions regarding this matter, 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:
J. Frederick Ringwald, RIV (316) 364-8653
Kamalakar R. Naidu, NRR (301) 504-2980
Attachment:
List of Recently Issued NRC Information Notices PRFVTIOU
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October xx, 1993 No specific action or written response is required by this information notice.
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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:
J. Frederick Ringwald, RIV (316) 364-8653
Kamalakar. R. Naidu, NRR (301) 504-2980
Attachment:
List of Recently Issued NRC Information Notices Un
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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:
J. Frederick Ringwald, RIV (316) 364-8653
Kamalakar. R. Naidu, NRR (301) 504-2980
Attachment:
List of Recently Issued NRC Information Notices OFFICE OGCB/DORSpcvj R/RI
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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 Topic Stress corrosion cracking 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 Topic Overspeed trip Overspeed Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment 9 February 1994 Topic Loss of Offsite Power Overspeed Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment 28 June 1994 Topic Spent fuel rack 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 Topic Overspeed Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge 2 March 1994 Topic Overspeed Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination 3 March 1994 Topic Overspeed Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use 11 March 1994 Topic Brachytherapy Overspeed Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use 11 March 1994 Topic Brachytherapy Overspeed 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 Topic Inactive license 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 Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters 24 March 1994 Topic Safe Shutdown 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 Water hammer 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 Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding 31 March 1994 Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals 5 April 1994 Topic Fire Barrier Operability Determination 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 Local Leak Rate Testing 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 Stress corrosion cracking Earthquake Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems 9 May 1994 Topic Stress corrosion cracking Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns 13 May 1994 Topic Fire Barrier Stress corrosion cracking 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 Topic Stress corrosion cracking 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 Stress corrosion cracking Integrated leak rate test Gas accumulation Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure 27 May 1994 Topic Stress corrosion cracking 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 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors 7 June 1994 Topic Stress corrosion cracking Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate 10 June 1994 Topic Grab sample Main Steam Line Radiation Monitor 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 Topic Unidentified leakage Information Notice 1994-47, Accuracy of Information Provided to NRC During the Licensing Process 21 June 1994 ... further results
