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SSINS No.:
6870
Accession No.:
UNITED STATES
7912190673
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C.
20555
February 8, 1980
IE Information Notice No. 80-05 CHLORIDE CONTAMINATION OF SAFETY RELATED PIPING AND COMPONENTS
A Bechtel Power Corporation Study at the Wolf Creek Project has revealed that
a fire retardant coating is potentially corrosive in contact with stainless
steel.
Albi "Duraspray" is a fire retardent coating which contains magnesium oxychloride, and is used for fireproofing of exposed structural steel in some Nuclear Power
Plants. There appears to be no deleterious effect when it is applied over
unprimed, inorganic zinc coated, or galvanized steel, however, it may be corrosive
in contact with stainless steel, bare aluminum or copper.
Droppings or overspray
of this material cannot be properly removed with water.
Diluted Nitric acid
has been proven to be a useful cleanser, however, it presents a safety hazard.
Applicants and holders of construction permits and licensees of operating
power reactors are advised to protect all stainless steel, copper and aluminum
material from overspray and droppage of cementitious oxychloride materials and
to remove accidently applied materials immediately and completely employing
strict safety precautions d'uring the process.
Special attention should be given
to weld areas in any removal procedures.
No written response to this information notice is required.
If you require
additional information regarding this matter contact the Director of the
appropriate NRC Regional Office.
L^
IS Information Notice No. 80-05
February 8, 1980
Enclosure
RECENTLY ISSUED
IE INFORMATION NOTICES
Information
Notice No.
Subject
Date
Issued
Issued To
80-04
80-03
80-02
80-01
79-37
79-36
79-35
79-34
79-33
79-32
79-31
79-30
79-29
BWR Fuel Exposure in
Excess of Limits
Main Turbine Electro-
Hydraulic Control System
8X8R Water Rod Lower
End Plug Wear
Fuel Handling Events
Cracking in Low Pressure
Turbine Discs
Computer Code Defect in
Stress Analysis of Piping
Elbow
Control of Maintenance
and Essential Equipment
,
Inadequate Design of
Safety-Related Heat
Exchangers
Improper Closure of
Primary Containment
Access Hatches
Separation of Electrical
Cables for HPCI and ADS
Use of Incorrect Amplified
Response Spectra (ARS)
Reporting of Defects and
Noncompliance, 10 CFR Part 21.
Loss of NonSafety-Related
Reactor Coolant System
Instrumentation During
Operation
2/4/80
1/31/80
1/25/80
1/4/80
All BWR's holding a
power reactor OL or CP
All holders of power
reactor OLs and CPs
All BWR Facilities
holder power reactor
OLs or CPs
All holders of power
reactor OLs and CPs
12/28/79
All power reactor OLs
and CPs
12/31/79
All power reactor OLs
and CPs
12/31/79
All power reactor facilities
with an OL or CP
12/27/79
All holders of power reactor
OLs and CPs
12/21/79
All power reactor facilities
holding OLs and CPs
12/21/79
All power reactor facilities
holding OLs and CPs
12/13/79
All holders of power reactor
OLs and CPs
12/6/79
All power reactor facilities
holding OLs and CPs and
vendors inspected by LCVIP
11/16/79
All power reactor facilities
holding OLs or CPs
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| list | - Information Notice 1980-03, Main Turbine Electrohydraulic Control System (31 January 1980, Topic: Water rod)
- Information Notice 1980-05, Chloride Contamination of Safety Related Piping & Components (8 February 1980, Topic: Water rod)
- Information Notice 1980-06, Notification of Significant Events at Operating Power Reactor Facilities (29 July 1980, Topic: Loss of Offsite Power, Earthquake, Fatality)
- Information Notice 1980-07, Pump Shaft Fatigue Cracking (29 February 1980, Topic: Water rod)
- Information Notice 1980-08, The States Company Sliding Link Electrical Terminal Block (7 March 1980, Topic: Water rod)
- Information Notice 1980-09, Possible Occupational Health Hazard Associated with Closed Cooling Systems for Operating Power Plants (7 March 1980, Topic: Water rod)
- Information Notice 1980-10, Partial Loss of Non-Nuclear Instrument System Power Supply During Operation (7 March 1980, Topic: Core Exit Thermocouple, Water rod)
- Information Notice 1980-11, Generic Problems with Asco Valves in Nuclear Applications Including Fire Protection Systems (14 March 1980, Topic: Water rod)
- Information Notice 1980-12, Instrument Failure Causes Opening of Porv & Block Valve (31 March 1980, Topic: Water rod)
- Information Notice 1980-13, General Electric Type SBM Control Switches Defective CAM Followers (2 April 1980, Topic: Water rod)
- 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, Topic: Overspeed trip)
- 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, Eddy Current Testing)
- 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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