Contamination of Breathing Air Systems| ML031180698 |
| Person / Time |
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| Site: |
Beaver Valley, Millstone, Hatch, 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, 05000000, 05000262, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane |
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| Issue date: |
01/23/1985 |
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| From: |
Jordan E NRC/IE |
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| To: |
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| References |
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| IN-85-006, NUDOCS 8501230236 |
| Download: ML031180698 (5) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, 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, 05000000, 05000262, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane |
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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 [[: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 [[:05000000]] OR [[:05000262]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] OR [[:Crane]] </code>. |
SSINS No.: 6835 IN 85-06
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C.
20555
January 23, 1985
IE INFORMATION NOTICE NO. 85-06: CONTAMINATION OF BREATHING AIR SYSTEMS
Addressees
All nuclear power reactor facilities holding an operating license (OL) or
construction permit (CP).
Purpose
This information notice is provided to alert licensees to two events resulting
in the radioactive contamination of compressed air systems used to supply
breathing air to respirator users at nuclear power plants.
It supplements
information previously provided in Information Notice 79-08 which discussed
similar events.
Licensee corrective actions and lessons learned from the two
relatively recent events and other previously documented occurrences are
discussed. It is expected that recipients will review this information for
applicability to their facilities and consider actions, if appropriate, to
preclude similar problems occurring at their facilities. However, suggestions
contained in this notice do not constitute NRC requirements; therefore, no
specific action or written response is required.
Description of Circumstances
Event 1 During September 1984, portions of the Browns Ferry service air system (SAS)
were contaminated with gaseous radioactivity directly from the station's
augmented offgas system (AOG).
The SAS and AOG were cross-connected via a
rubber hose (with a single check-valve). Air from the SAS was being supplied
to remove moisture from the AOG hydrogen analyzer sample line downstream of the
AOG hydrogen/oxygen recombiner.
Evidently this was a routine maintenance
activity. When the SAS on-line and backup air compressors failed and the air
receivers bled down, freshly produced radioactive offgas entered the service
air through the temporary hose connection. This condition existed for approxi- mately 2 1/2 hours; fortunately, no one used the system as a breathing air
supply during this period.
Plant personnel became aware of the problem after the air compressors were once
again operable. Apparently the offgas in a portion of the SAS line near an
area radiation monitor tARM) was compressed and caused the ARM to alarm
(lOmR/hr alarm set point). Only short-lived noble gases and their daughter
8501230236
IN 85-06 January 23, 1985 products were found in the SAS, and no explosive or flammability problems were
reported.
Along with tightened administrative controls, double check-valve
backflow protection is now required when cross-connecting to the SAS.
Event 2 On July 19, 1983, workmen while cutting up spent fuel racks inside a
tent-containment structure at H.B. Robinson were wearing air-line respirators
fed by the plant's instrument air system (IAS). While attempting to connect the
air manifold assembly to a different IAS supply point before putting on their
respirators, two workers were exposed to dust and rust particles from the
initial air surge. When "frisked," the two workers found themselves contami- nated.
Air sampled from the contaminated air line contained about 6.6E-8
2 pCi/cc (corresponding to an MPC fraction of 14.1).
On the basis of these air
samples and the whole-body counting, the workers involved were assigned radio- active intakes of less than 40 MPC-hrs.
The licensee investigated the incident, sampled other portions of the IAS, and
found no other radioactive contamination problems.
The source of the IAS
contamination could not be definitely determined.
Therefore, as part of the
corrective actions taken, the licensee now samples and analyzes for radioactiv- ity at each air supply connection point before the breathing air is used.
Discussion
The NRC staff is aware of other instances where installed service air systems
used to provide personnel breathing air have been contaminated (see Attachment
1 for references).
On the basis of a review of licensees' corrective actions
and discussions with the licensees' operating staff, the lessons learned from
the referenced events are summarized as follows:
1.
Radiological air sampling before use can help prevent inadvertent intakes
of radioactivity when infrequently-used portions of service/instrument air
systems are used as breathing air sources.
This precautionary radiologi- cal sampling of the air system would complement the periodic radiological
sampling and industrial hygiene sampling necessary to ensure continued
Grade D quality (or better) for supplied air as required by 30 CFR 11 and
10 CFR 20.
2. Operating procedures can provide for effective administrative controls and
establish physical separation criteria to prevent cross-contamination when
air systems are temporarily connected to contaminated systems.
To mini- mize the potential for cross-contamination, some licensees use intermedi- r
ate air motors (driven by service air) to directly supply air to a
contaminated system.
This approach is applicable only when the air supply
loads are low enough to be supplied by the air motors.
3. There is that potential for "an unreviewed safety question" situation when
system operations are changed from what is described in the Safety Analy- sis Report, such as cross-connecting contaminated and noncontaminated
systems.
IE Circular No. 80-18, "10 CFR 50.59 Safety Evaluations for
IN 85-06 January 23, 1985 Changes to Radioactive Waste Treatment Systems" discusses general princi- ples and philosophy of the 10 CFR 50.59 safety evaluation guidance and
provides insight as to when safety evaluations are necessary to ensure
that changes to SAR-described systems are properly evaluated.
4. For permanent, as-designed interconnections between installed compressed
air systems and contaminated systems, periodic function checks;-and mainte- nance of the system separation protection features (e.g., check valves and
air operated ball valves) can help ensure continued integrity of the
separation.
5. Procedures governing the startup, operation, and maintenance of "add-on"
air handling equipment (e.g., pressure regulating/filtration manifold) can
ensure proper air purging (blowing down) to remove contaminants such as
dead-leg water and rust before the air is used for breathing.
While a separate breathing air supply and distribution system is the ideal
source of worker-supplied air and this can be justified for plants at the
design stage, the physical and economic constraints of installing a separate
breathing air system in an existing facility might be overly burdensome.
Properly modified plant SASs and IASs, with attendant maintenance and sampling
surveillance programs, can be adequate, reliable sources of breathing air for
plant workers.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
gL/ ~dan, Director
Divisi n f Emergency Preparedness
and tfgineering Response
Office of Inspection and Enforcement
Technical Contacts: J. E. Wigginton, IE
(301) 492-4967
R. L. Pedersen, IE
(301) 492-9425 Attachments:
1. References
2. List of Recently Issued IE Information Notices
Attachment 1
IN 85-06
January 23, 1985 References
1. U.S. Nuclear Regulatory Commisssion, Office of Inspection and Enforcement, Information Notice No. 79-08, "Interconnection of Contaminated Systems
with Service Air Systems used as a Source of Breathing Air," March 28,
1979.
2. Institute for Nuclear Power Operations, Significant Event Report (SER)
26-82, "Radioactive Contamination of Service Air System," issued 1982.
Attachment 2
IN 85-06
January 23, 1985
LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issue
Issued to
85-05
Pipe Whip Restraints
Inadequate Management Of
Security Response Drills
1/23/85
1/17/85
85-04
85-03 Separation Of Primary Reactor 1/15/85
Coolant Pump Shaft And
Impeller
85-02
85-01
Improper Installation And
Testing Of Differential
Pressure Transmitters
Continuous Supervision Of
Irradiators
Reconcentration Of Radio- nuclides Involving Discharges
Into Sanitary Sewage Systems
Permitted Under 10 CFR 20.303
Potential For Loss Of Water
From The Refueling Cavity
Cracking Of Flywheel On
Cummins Fire Pump Diesel
Engines
1/15/85
1/10/85
12/21/84
12/17/84
12/17/84
All power reactor
facilities holding
an OL or CP
All power reactor
facilities holding
an OL or CP, & fuel
fabrication & pro- cessing facilities
All pressurized water
power reactor
facilities holding an
OL or CP
All power reactor
facilities holding
an OL or CP
All material licensees
possessing irradiators
that are not self- shielded and contain
more than 10,000
curies of radioactive
material
All NRC materials
licensees other than
licensees that use
sealed sources only
All power reactor
facilities holding
an OL or CP
All power reactor
facilities holding
an OL or CP
84-94
84-93
84-92 OL = Operating License
CP = Construction Permit
|
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| list | - Information Notice 1985-01, Continuous Supervision of Irradiators (10 January 1985)
- Information Notice 1985-02, Improper Installation and Testing of Differential Pressure Transmitters (11 January 1985)
- Information Notice 1985-03, Separation of Primary Reactor Coolant Pump Shaft and Impeller (15 January 1985)
- Information Notice 1985-04, Inadequate Management of Security Response Drills (17 January 1985)
- Information Notice 1985-05, Pipe Whip Restraints (23 January 1985)
- Information Notice 1985-06, Contamination of Breathing Air Systems (23 January 1985, Topic: Spent fuel rack)
- Information Notice 1985-07, Contaminated Radiography Source Shipments (29 January 1985)
- Information Notice 1985-08, Industry Experience on Certain Materials Used in Safety-Related Equipment (30 January 1985)
- Information Notice 1985-09, Isolation Transfer Switches and Post-Fire Shutdown Capability (31 January 1985, Topic: Safe Shutdown)
- Information Notice 1985-10, Posttensioned Containment Tendon Anchor Head Failure (6 February 1985, Topic: Stress corrosion cracking)
- Information Notice 1985-11, Licensee Programs for Inspection of Electrical Raceway and Cable Installations (11 February 1985)
- Information Notice 1985-12, Recent Fuel Handling Events (11 February 1985, Topic: Eddy Current Testing)
- Information Notice 1985-13, Consequences of Using Soluble Dams (21 February 1985, Topic: Hydrostatic)
- Information Notice 1985-14, Failure of a Heavy Control Rod (B4C) Drive Assembly to Insert on a Trip Signal (22 February 1985)
- Information Notice 1985-15, Nonconforming Structural Steel for Safety-Related Use (22 February 1985)
- Information Notice 1985-16, Time/Current Trip Curve Discrepancy of ITE/Siemens-Allis Molded Case Circuit Breaker (27 February 1985)
- Information Notice 1985-17, Possible Sticking of Asco Solenoid Valves (1 March 1985)
- Information Notice 1985-18, Failures of Undervoltage Output Circuit Boards in the Westinghouse-Designed Sold State Protection System (7 March 1985)
- Information Notice 1985-19, Alleged Falsification of Certifications and Alteration of Markings on Piping, Valves, and Fittings (11 March 1985)
- Information Notice 1985-20, Motor-Operated Valve Failures Due to Hampering Effect (12 March 1985)
- Information Notice 1985-21, Main Steam Isolation Valve Closure Logic (18 March 1985)
- Information Notice 1985-22, Failure of Limitorque Motor-Operated Valves Resulting from Incorrect Installation of Pinion Gear (21 March 1985)
- Information Notice 1985-23, Inadequate Surveillance and Postmaintenance and Postmodification System Testing (22 March 1985)
- Information Notice 1985-24, Failures of Protective Coatings in Pipes and Heat Exchangers (26 March 1985, Topic: Ultimate heat sink, Coatings)
- Information Notice 1985-25, Consideration of Thermal Conditions in the Design and Installation of Supports for Diesel Generator Exhaust Silencers (2 April 1985, Topic: Coatings)
- Information Notice 1985-26, Vacuum Relief System for Boiling Water Reactor Mark I and Mark II Containments (2 April 1985, Topic: Coatings)
- Information Notice 1985-27, Notifications to the NRC Operations Center and Reporting Events in Licensee Event Reports (3 April 1985, Topic: Coatings)
- Information Notice 1985-28, Partial Loss of AC Power and Diesel Generator Degradation (9 April 1985, Topic: Coatings, Overspeed)
- Information Notice 1985-30, Microbiologically Induced Corrosion of Containment Service Water System (19 April 1985, Topic: Hydrostatic, Coatings, Biofouling)
- Information Notice 1985-31, Buildup of Enriched Uranium in Ventilation Ducts and Associated Effluent Treatment Systems (19 April 1985, Topic: Coatings)
- Information Notice 1985-32, Recent Engine Failures of Emergency Diesel Generators (22 April 1985, Topic: Coatings)
- Information Notice 1985-33, Undersized Nozzle-To-Shell Welded Joints in Tanks and Heat Exchangers Constructed Under the Rules of the ASME Boiler and Pressure Vessel Code (22 April 1985)
- Information Notice 1985-34, Heat Tracing Contributes to Corrosion Failure of Stainless Steel Piping (30 April 1985, Topic: Hydrostatic)
- Information Notice 1985-35, Failure of Air Check Valves to Seat (30 April 1985, Topic: Loss of Offsite Power)
- Information Notice 1985-35, Failure of Air Check Valves To Seat (30 April 1985, Topic: Loss of Offsite Power)
- Information Notice 1985-37, Chemical Cleaning of Steam Generators at Millstone 2 (14 May 1985, Topic: Feedwater Heater, Eddy Current Testing)
- Information Notice 1985-38, Loose Parts Obstruct Control Rod Drive Mechanism (21 May 1985)
- Information Notice 1985-39, Auditability of Electrical Equipment Qualification Records at Licensees Facilities (22 May 1985)
- Information Notice 1985-40, Deficiencies in Equipment Qualification Testing and Certification Process (22 May 1985)
- Information Notice 1985-43, Radiography Events at Power Reactors (30 May 1985, Topic: High Radiation Area, Scaffolding)
- Information Notice 1985-44, Emergency Communication System Monthly Test (30 May 1985, Topic: Health Physics Network)
- Information Notice 1985-46, Clarification of Several Aspects of Removable Radioactive Surface Contamination Limits for Transport Packages (10 June 1985)
- Information Notice 1985-47, Potential Effect of Line-Induced Vibration on Certain Target Rock Solenoid-Operated Valves (18 June 1985)
- Information Notice 1985-48, Respirator Users Notice: Defective Self Contained Breathing Apparatus Air Cylinders (19 June 1985, Topic: Hydrostatic)
- Information Notice 1985-49, Relay Calibration Problem (1 July 1985)
- Information Notice 1985-50, Complete Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox (8 July 1985, Topic: Overspeed trip, Overspeed)
- Information Notice 1985-51, Inadvertent Loss or Improper Actuation of Safety-Related Equipment (10 July 1985)
- Information Notice 1985-52, Errors in Dose Assessment Computer Codes and Reporting Requirements Under 10 CFR Part 21 (10 July 1985, Topic: Basic Component)
- Information Notice 1985-53, Performance of NRC-Licensed Individuals While on Duty (12 July 1985)
- Information Notice 1985-54, Teletherapy Unit Malfunction (15 July 1985)
... further results |
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