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Category:NRC Information Notice
MONTHYEARML19017A1172019-12-0303 December 2019
Table 1 for the in 2012-22 Counterfeit, Fraudulent, Suspect Item Training Offerings, List of CFSI-Related Training Offerings
Information Notice 2012-22, Rev. 1 - Counterfeit, Fraudulent, Suspect Item Training Offerings2019-11-20020 November 2019
Rev. 1 - Counterfeit, Fraudulent, Suspect Item Training Offerings
Information Notice 1985-61, Misadministrations to Patients Undergoing Thyroid Scans1985-07-22022 July 1985
Misadministrations to Patients Undergoing Thyroid Scans
Information Notice 1985-53, Performance of NRC-Licensed Individuals While on Duty1985-07-12012 July 1985
Performance of NRC-Licensed Individuals While on Duty
Information Notice 1980-43, Failures of Continuous Water Level Monitor for Scram Discharge Volume at Dresden Unit No.21980-12-0505 December 1980
Failures of Continuous Water Level Monitor for Scram Discharge Volume at Dresden Unit No.2
Information Notice 1980-42, Effect of Radiation on Hydraulic Snubber Fluid1980-11-24024 November 1980
Effect of Radiation on Hydraulic Snubber Fluid
Information Notice 1980-41, Failure of Swing Check Valve in Decay Heat Removal System at Davis Besse Unit No.11980-11-10010 November 1980
Failure of Swing Check Valve in Decay Heat Removal System at Davis Besse Unit No.1
Information Notice 1980-40, Excessive Nitrogen Supply Pressure Actuates Safety-Relief Valve Operation to Cause Reactor Depressurization1980-11-0707 November 1980
Excessive Nitrogen Supply Pressure Actuates Safety-Relief Valve Operation to Cause Reactor Depressurization
Information Notice 1980-39, Malfunction of Solenoid Valves Manufactured by Valcor Engineering Corp1980-10-31031 October 1980
Malfunction of Solenoid Valves Manufactured by Valcor Engineering Corp
Information Notice 1980-38, Cracking in Charging Pump Casing Cladding1980-10-30030 October 1980
Cracking in Charging Pump Casing Cladding
Information Notice 1980-37, Containment Cooler Leaks & Reactor Cavity Flooding at Indian Point Unit 21980-10-24024 October 1980
Containment Cooler Leaks & Reactor Cavity Flooding at Indian Point Unit 2
Information Notice 1980-34, Boron Dilution of Reactor Coolant During Steam Generator Decontamination1980-09-26026 September 1980
Boron Dilution of Reactor Coolant During Steam Generator Decontamination
Information Notice 1980-31, Maloperation of Gould-Brown Boveri 480 Volt-Type K-6005 & K-Don 6005 Circuit Breakers1980-08-27027 August 1980
Maloperation of Gould-Brown Boveri 480 Volt-Type K-6005 & K-Don 6005 Circuit Breakers
Information Notice 1980-29, Broken Studs on Terry Turbine Steam Inlet Flange1980-08-0707 August 1980
Broken Studs on Terry Turbine Steam Inlet Flange
Information Notice 1980-06, Notification of Significant Events at Operating Power Reactor Facilities1980-07-29029 July 1980
Notification of Significant Events at Operating Power Reactor Facilities
Information Notice 1980-27, Degradation of Reactor Coolant Pump Studs1980-06-11011 June 1980
Degradation of Reactor Coolant Pump Studs
Information Notice 1980-26, Evaluation of Contractor QA Programs1980-06-10010 June 1980
Evaluation of Contractor QA Programs
Information Notice 1980-22, Breakdowns in Contamination Control Programs1980-05-28028 May 1980
Breakdowns in Contamination Control Programs
Information Notice 1980-21, Anchorage & Support of Safety-Related Electrical Equipment1980-05-16016 May 1980
Anchorage & Support of Safety-Related Electrical Equipment
Information Notice 1980-20, Loss of Decay Heat Removal Capability at Davis-Besse Unit 1 While in a Refueling Mode1980-05-0808 May 1980
Loss of Decay Heat Removal Capability at Davis-Besse Unit 1 While in a Refueling Mode
Information Notice 1980-19, Niosh Recall of Recirculating-Mode (Closed Circuit) Self-Contained Breathing Apparatus (Rebreather)1980-05-0606 May 1980
Niosh Recall of Recirculating-Mode (Closed Circuit) Self-Contained Breathing Apparatus (Rebreather)
Information Notice 1980-19, Niosh Recall of Recirculating-Mode (closed Circuit) Self-Contained Breathing Apparatus (rebreather)1980-05-0606 May 1980
Niosh Recall of Recirculating-Mode (closed Circuit) Self-Contained Breathing Apparatus (rebreather)
Information Notice 1980-16, Shaft Seal Packing Causes Binding in Main Steam Swing Disc Check & Isolation Valves1980-04-29029 April 1980
Shaft Seal Packing Causes Binding in Main Steam Swing Disc Check & Isolation Valves
Information Notice 1980-15, Axial (longitudinal) Oriented Cracking in Piping1980-04-21021 April 1980
Axial (longitudinal) Oriented Cracking in Piping
Information Notice 1980-15, Axial (Longitudinal) Oriented Cracking in Piping1980-04-21021 April 1980
Axial (Longitudinal) Oriented Cracking in Piping
Information Notice 1980-14, Safety Suggestions from Employees1980-04-0202 April 1980
Safety Suggestions from Employees
Information Notice 1980-13, General Electric Type Sbm Control Switches Defective CAM Followers1980-04-0202 April 1980
General Electric Type Sbm Control Switches Defective CAM Followers
Information Notice 1980-12, Instrument Failure Causes Opening of Porv & Block Valve1980-03-31031 March 1980
Instrument Failure Causes Opening of Porv & Block Valve
Information Notice 1980-11, Generic Problems with Asco Valves in Nuclear Applications Including Fire Protection Systems1980-03-14014 March 1980
Generic Problems with Asco Valves in Nuclear Applications Including Fire Protection Systems
Information Notice 1980-10, Partial Loss of Non-Nuclear Instrument System Power Supply During Operation1980-03-0707 March 1980
Partial Loss of Non-Nuclear Instrument System Power Supply During Operation
Information Notice 1980-09, Possible Occupational Health Hazard Associated with Closed Cooling Systems for Operating Power Plants1980-03-0707 March 1980
Possible Occupational Health Hazard Associated with Closed Cooling Systems for Operating Power Plants
Information Notice 1980-08, the States Company Sliding Link Electrical Terminal Block1980-03-0707 March 1980
the States Company Sliding Link Electrical Terminal Block
Information Notice 1980-08, The States Company Sliding Link Electrical Terminal Block1980-03-0707 March 1980
The States Company Sliding Link Electrical Terminal Block
Information Notice 1980-07, Pump Shaft Fatigue Cracking1980-02-29029 February 1980
Pump Shaft Fatigue Cracking
Information Notice 1980-03, Main Turbine Electrohydraulic Control System1980-01-31031 January 1980
Main Turbine Electrohydraulic Control System
Information Notice 1979-35, Control of Maintenance & Essential Equipment1979-12-31031 December 1979
Control of Maintenance & Essential Equipment
Information Notice 1979-36, Computer Code Defect in Stress Analysis of Piping Elbow1979-12-31031 December 1979
Computer Code Defect in Stress Analysis of Piping Elbow
Information Notice 1979-37, Cracking in Low Pressure Turbine Discs1979-12-28028 December 1979
Cracking in Low Pressure Turbine Discs
Information Notice 1979-34, Inadequate Design of Safety-Related Heat Exchangers1979-12-27027 December 1979
Inadequate Design of Safety-Related Heat Exchangers
Information Notice 1979-33, Improper Closure of Primary Containment Equipment Access Matches1979-12-21021 December 1979
Improper Closure of Primary Containment Equipment Access Matches
Information Notice 1979-31, Use of Incorrect Amplified Response Spectra1979-12-13013 December 1979
Use of Incorrect Amplified Response Spectra
Information Notice 1979-12A, Attempted Damage to New Fuel Assemblies1979-11-0909 November 1979
Attempted Damage to New Fuel Assemblies
2019-12-03
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UNITED STATES SSINS No.: 6870
NUCLEAR REGULATORY COMMISSION Accession No.:
OFFICE OF INSPECTION AND ENFORCEMENT 7912190666 WASHINGTON, D.C. 20555 January 31, 1980
IE Information Notice No. 80-03
MAIN TURBINE ELECTROHYDRAULIC CONTROL SYSTEM
Description of Circumstances
On September 6, 1979, while performing a routine startup of the Trojan Nuclear
Plant, a speed control problem was encountered during warmup of the General
Electric turbine and increase of turbine speed to normal operating speed
(1800 RPM). Technicians were notified and trouble shooting in accordance with
the technical manual was commenced to resolve the apparent oscillation between
the primary and backup speed control circuits which was hindering normal turbine
startup operations. The technical manual indicates that it is permissible to
remove either the primary or backup low value gate circuits which contain speed
and acceleration error amplifiers. Upon removal of the primary low value gate
circuit card, the backup card amplifiers, coming from a saturated condition, became the controlling circuit. During the shift in control circuits (primary to
backup), the speed/acceleration error signal went to maximum which resulted in
a full open signal to the turbine control valves. Under existing plant conditions
this appeared to the safety injection system as a major steam break downstream of
the main steam isolation valves which resulted in a safety injection system
actuation and reactor trip.
The Electrohydraulic Control System (EHC) technical manual indicated that slight
load changes are likely when a low value gate card is removed. The effect on an
unloaded turbine appears to be much more significant and tests conducted by
- GEK Instruction Book 11381-D, "Speed Control Unit", Maintenance Section, Page 4.
IE Information Notice No. 80-03 January 31, 1980 Trojan personnel indicate that the transient is initiated whether the turbine is
at a set speed or in an acceleration mode to a set speed. Discussions with General
Electric personnel by the licensee have been initiated in an attempt to verify
the phenomenon observed and, if applicable, alert other facilities which operate
a turbine with a M1K 1 EHC System regarding the potential operation of the control
valves when trouble shooting the speed control unit in accordance with existing
instructions.
This information is provided as an early notification of a possible significant
matter. It is expected that recipients will review the information for possible
applicability to their facilities. No specific action or response is requested
at this time. If further NRC evaluations so indicate, an IE Circular or Bulletin
will be issued to recommend or request specific licensee actions. If you have
questions regarding this matter, please contact the Director of the appropriate
NRC Regional Office.
Enclosure:
List of Recently Issued
IE Information Notices
IE Information Notice No. 80-03 Enclosure
January 31, 1980
RECENTLY ISSUED
IE INFORMATION NOTICES
Information Subject Date Issued To
Notice No. Issued
80-02 8X8R Water Rod Lower 1/25/80 All BWR Facilities
End Plug Wear holder power reactor
OLs or CPs
80-01 Fuel Handling Events 1/4/80 All holders of power
reactor OLs and CPs
79-37 Cracking in Low Pressure 12/28/79 All power reactor OLs
Turbine Discs and CPs
79-36 Computer Code Defect in 12/31/79 All power reactor OLs
Stress Analysis of Piping and CPs
Elbow
79-35 Control of Maintenance 12/31/79 All power reactor facilities
and Essential Equipment with an OL or CP
79-34 Inadequate Design of 12/27/79 All holders of power reactor
Safety-Related Heat OLs and CPs
Exchangers
79-33 Improper Closure of 12/21/79 All power reactor facilities
Primary Containment holding OLs and CPs
Access Hatches
79-32 Separation of Electrical 12/21/79 All power reactor facilities
Cables for HPCI and ADS holding OLs and CPs
79-31 Use of Incorrect Amolified 12/13/79 All holders of power reactor
Response Spectra (ARS) OLs and CPs
79-30 Reporting of Defects and 12/6/79 All power reactor facilities
Noncompliance, 10 CFR Part 21. holding OLs and CPs and
vendors inspected by LCVIP
79-29 Loss of NonSafety-Related 11/16/79 All power reactor facilities
Reactor Coolant System holding OLs or CPs
Instrumentation During
Operation
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| list | - Information Notice 1980-03, Main Turbine Electrohydraulic Control System (31 January 1980)
- Information Notice 1980-05, Chloride Contamination of Safety Related Piping & Components (8 February 1980)
- Information Notice 1980-06, Notification of Significant Events at Operating Power Reactor Facilities (29 July 1980, Topic: Earthquake, Fatality)
- Information Notice 1980-07, Pump Shaft Fatigue Cracking (29 February 1980)
- Information Notice 1980-08, the States Company Sliding Link Electrical Terminal Block (7 March 1980)
- Information Notice 1980-08, The States Company Sliding Link Electrical Terminal Block (7 March 1980)
- Information Notice 1980-09, Possible Occupational Health Hazard Associated with Closed Cooling Systems for Operating Power Plants (7 March 1980)
- Information Notice 1980-10, Partial Loss of Non-Nuclear Instrument System Power Supply During Operation (7 March 1980)
- Information Notice 1980-11, Generic Problems with Asco Valves in Nuclear Applications Including Fire Protection Systems (14 March 1980)
- Information Notice 1980-12, Instrument Failure Causes Opening of Porv & Block Valve (31 March 1980)
- Information Notice 1980-13, General Electric Type Sbm Control Switches Defective CAM Followers (2 April 1980)
- Information Notice 1980-14, Safety Suggestions from Employees (2 April 1980)
- Information Notice 1980-15, Axial (Longitudinal) Oriented Cracking in Piping (21 April 1980, Topic: Liquid penetrant)
- Information Notice 1980-15, Axial (longitudinal) Oriented Cracking in Piping (21 April 1980, Topic: Liquid penetrant)
- Information Notice 1980-16, Shaft Seal Packing Causes Binding in Main Steam Swing Disc Check & Isolation Valves (29 April 1980)
- Information Notice 1980-19, Niosh Recall of Recirculating-Mode (Closed Circuit) Self-Contained Breathing Apparatus (Rebreather) (6 May 1980)
- Information Notice 1980-19, Niosh Recall of Recirculating-Mode (closed Circuit) Self-Contained Breathing Apparatus (rebreather) (6 May 1980)
- Information Notice 1980-20, Loss of Decay Heat Removal Capability at Davis-Besse Unit 1 While in a Refueling Mode (8 May 1980)
- Information Notice 1980-21, Anchorage & Support of Safety-Related Electrical Equipment (16 May 1980, Topic: Earthquake)
- Information Notice 1980-22, Breakdowns in Contamination Control Programs (28 May 1980)
- Information Notice 1980-25, Transportation of Pyrophoric Uranium (30 May 1980)
- Information Notice 1980-26, Evaluation of Contractor QA Programs (10 June 1980)
- Information Notice 1980-27, Degradation of Reactor Coolant Pump Studs (11 June 1980, Topic: Boric Acid)
- Information Notice 1980-29, Broken Studs on Terry Turbine Steam Inlet Flange (7 August 1980)
- Information Notice 1980-31, Maloperation of Gould-Brown Boveri 480 Volt-Type K-6005 & K-Don 6005 Circuit Breakers (27 August 1980)
- Information Notice 1980-34, Boron Dilution of Reactor Coolant During Steam Generator Decontamination (26 September 1980, Topic: Boric Acid, Shutdown Margin)
- Information Notice 1980-37, Containment Cooler Leaks & Reactor Cavity Flooding at Indian Point Unit 2 (24 October 1980)
- Information Notice 1980-38, Cracking in Charging Pump Casing Cladding (30 October 1980, Topic: Boric Acid, Nondestructive Examination)
- Information Notice 1980-39, Malfunction of Solenoid Valves Manufactured by Valcor Engineering Corp (31 October 1980)
- Information Notice 1980-40, Excessive Nitrogen Supply Pressure Actuates Safety-Relief Valve Operation to Cause Reactor Depressurization (7 November 1980)
- Information Notice 1980-41, Failure of Swing Check Valve in Decay Heat Removal System at Davis Besse Unit No.1 (10 November 1980)
- Information Notice 1980-42, Effect of Radiation on Hydraulic Snubber Fluid (24 November 1980)
- Information Notice 1980-43, Failures of Continuous Water Level Monitor for Scram Discharge Volume at Dresden Unit No.2 (5 December 1980, Topic: Scram Discharge Volume)
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