Design Limitations of Gaseous Effluent Monitoring Systems| ML031220651 |
| 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, 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, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane |
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| Issue date: |
04/29/1986 |
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| From: |
Jordan E NRC/IE |
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| To: |
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| References |
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| IN-86-030, NUDOCS 8604280122 |
| Download: ML031220651 (4) |
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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, 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, 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 [[: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 [[:05000000]] 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 86-30
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C.
20555
April 29, 1986
IE INFORMATION NOTICE NO. 86-30:
DESIGN LIMITATIONS OF GASEOUS EFFLUENT
MONITORING SYSTEMS
Addressees
All nuclear power reactor facilities holding an operating license or a con- struction permit.
Purpose
This notice is provided to alert licensees to two design limitations noted in
the use of Eberline's SPING-4 (system particulate iodine and noble gas) gaseous
effluent monitoring systems.
The first deals with the limitations of the
detection capability of the SPING-4 monitoring system.
Some licensees are
incorrectly relying on the SPING-4 to meet all of the post-accident require- ments of NUREG-0737.
The second deals with noble gas adsorption that could
interfere with routine operational low-level monitoring.
It is expected that recipients will review this information for applicability
to their facilities and consider actions, if appropriate, to preclude problems
related to these limitations at their facilities.
However, suggestions con- tained in this notice do not constitute NRC requirements; therefore, no specif- ic action or written response is required.
Description of Circumstances
The Eberline SPING-4 is designed to monitor radioactive noble gasses, particu- lates and iodines in plant gaseous effluents.
By using three overlapping
channels, the noble gas (NG) monitor has a detection capability of 10-7 to 105 pCi/cc (Xe-133 equivalent).
The low-range channel employs a beta scintillation
detector.
The mid- and high-range channels of the NG monitor use energy- compensated GM tube detectors.
Conformance to NUREG-0737 II.F.1:
Item II.F.1.1 of NUREG-0737, "Clarification of TMI Action Plan Requirements,"
issued November 1980, requires licensees to have the capability to detect and
measure concentrations of NG fission products in plant effluents (up to
lo5 pCi/cc for undiluted containment exhaust) during and following an accident.
Recent NRC regional inspections of NUREG-0737 implementation indicate that
8604280122
IN 86-30
April 29, 1986 some licensees have installed SPING-4 monitors and mistakenly consider them
adequate to meet all of the requirements of Item II.F.1.1.
Although the
SPING-4 does have an upper detection capability of 105 pCi/cc, its associated
microcomputer is vulnerable to radiation damage from a total integrated dose
greater than 1000 rads.
Therefore, it is unlikely the SPING-4 would survive
the course of an accident.
Eberline has indicated that the SPING-4 was
designed primarily as a normal-range monitor with extended capabilities for
brief excursions to concentrations greater than 102 pCi/cc.
Full-range moni- toring consistent with Item II.F.1.1 can be achieved by using the SPING-4 in
conjunction with an accident monitor (with a remote microprocessor) such as
Eberline's model AXM-1.
The accident monitor comes on line when excessively
high activity levels are sensed while the SPING-4 isolates itself and goes into
a purge cycle.
Noble Gas Adsorption:
Eberline has noted noble gas adsorption with the plastic scintillator while
performing a SPING-4 calibration.
This calibration compared the SPING-4 output
with a GeLi detection system output, as the concentration of a reference gas
(Xe-127) was decreased.
The concentration of Xe-127 (initially at 210 pCi/cc)
in the closed test loop was decreased by vent and dilution operations.
Cali- bration was interrupted after 2 days to correct problems with the GeLi system.
The system was allowed to stand idle for 10 days with 0.3 pCi/cc Xe-127 concen- tration.
When the calibration resumed, the response of the beta scintillator
did not decrease in the expected proportions.
An investigation indicated that
both the inner and outer mylar sheets that cover the plastic scintillator had
adsorbed Xe-127 gas.
Although the levels of activity used in this calibration were much higher than
those normally encountered, the noble gas adsorption noted on the low range of
the detection system could indicate a generic operational concern. The high
background resulting from the adsorbed gas could cause overestimations in any
effluent release calculations that are based on the monitor output.
This is
particularly true if low-level monitoring is resumed following either a large
activity excursion (3 or 4 orders of magnitude above normal) or an extended
moderate increase (1 order of magnitude for a week or more).
Following such
releases the monitor should be purged and a new background taken.
It should be
noted that this gas adsorption phenomenon is probably not unique to SPING-4 monitoring systems.
Other manufacturers of plastic scintillation detectors use
similar construction techniques.
Any effluent monitor that employs a plastic
scintillation detector may experience the same difficulties.
IN 86-30
April 29, 1986 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.
ward L. Jordan Director
i
Division of Emergency Preparednes
and Engineering Response
Office of Inspection and Enforcement
Technical Contact:
Roger L. Pedersen, IE
(301)492-9425
James E. Wigginton, IE
(301)492-4967 Attachment:
List of Recently Issued IE Information Notices
Attachment 1
IN 86-30
April 29, 1986
LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issue
Issued to
86-29
86-28
86-27
Effects of Changing Valve
Motor-Operator Switch
Settings
Unauthorized Transfer and
Loss of Control of Indus- trial Nuclear Gauges
Access Control at Nuclear
Facilities
Potential Problems In
Generators Manufactured By
Electrical Products
Incorporated
Traceability And Material
Control Of Material And
Equipment, Particularly
Fasteners
4/25/86
4/28/86
4/21/86
4/17/86
4/11/86
86-26
86-25
All power reactor
facilities holding
an OL or a CP
All licensees author- ized to possess and
use industrial nuclear
gauges.
All power reactor
facilities holding
an OL or CP, research
and nonpower reactor
facilities, and fuel
fabrication & pro- cessing facilities
All power reactor
facilities holding
an OL or CP
All power reactor
facilities holding
an OL or CP
All power reactor
facilities holding
an OL or CP; research
and test reactor
facilities; fuel
cycle licensees and
Priority 1 material
licensees
All power reactor
facilities holding
an OL or CP
All power reactor
facilities holding
an OL or CP and
research and test
reactors
86-24 Respirator Users Notice:
4/11/86
Increased Inspection Frequency
For Certain Self-Contained
Breathing Apparatus Air
Cylinders
86-23
Excessive Skin Exposures Due
To Contamination With Hot
Particles
Underresponse Of Radition
Survey Instrument To High
Radiation Fields
4/9/86
3/31/86
86-22 OL = Operating License
PIr
r,.^-,4>.
n,.
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|
| list | - Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986, Topic: Feedwater Heater)
- Information Notice 1986-02, Failure of Valve Operator Motor During Environmental Qualification Testing (6 January 1986)
- Information Notice 1986-03, Potential Deficiencies in Enviromental Qualification of Limitorque Motor Valve Operator Wiring (14 January 1986)
- Information Notice 1986-04, Transient Due to Loss of Power to Intergrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox (31 January 1986)
- Information Notice 1986-05, Main Steam Safety Valve Test Failures and Ring Setting Adjustments (31 January 1986)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986, Topic: Control of Heavy Loads)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, while Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986)
- Information Notice 1986-07, Lack of Detailed Instruction & Inadequate Observance of Precautions During Maintenance & Testing of Diesel Generator Woodward Governors (3 February 1986, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986, Topic: GOTHIC)
- Information Notice 1986-09, Failure of Check & Stop Check Valves Subjected to Low Flow Conditions (3 February 1986)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-10, Feedwater Line Break (10 November 1988, Topic: Coatings, Anchor Darling)
- Information Notice 1986-11, Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants (31 December 1986)
- Information Notice 1986-13, Standby Liquid Control Squib Valves Failure to Fire (5 August 1986, Topic: Squib)
- Information Notice 1986-13, Standby Liquid Control System Squib Valves Failure to Fire (21 February 1986, Topic: Squib)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines (26 August 1991, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-15, Loss of Offsite Power Caused by Problems in Fiber Optics Systems (10 March 1986, Topic: Squib, Loss of Offsite Power)
- Information Notice 1986-16, Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves (11 March 1986, Topic: Squib, Local Leak Rate Testing, Integrated leak rate test)
- Information Notice 1986-17, Update of Failure of Automatic Sprinkler System Valves to Operate (24 March 1986, Topic: Squib)
- Information Notice 1986-18, NRC On-Scene Response During a Major Emergency (26 March 1986, Topic: Squib, Backfit)
- Information Notice 1986-19, Reactor Coolant Pump Shaft Failure at Crystal River (21 March 1986, Topic: Squib)
- Information Notice 1986-20, Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 (28 March 1986, Topic: Squib)
- Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders (31 March 1986, Topic: Squib)
- Information Notice 1986-22, Underresponse of Radiation Survey Instrument to High Radiation Fields (31 March 1986, Topic: High Radiation Area, Squib)
- Information Notice 1986-23, Excessive Skin Exposures Due to Contamination with Hot Particles (9 April 1986, Topic: Loss of Offsite Power)
- Information Notice 1986-23, Excessive Skin Exposures due to Contamination with Hot Particles (9 April 1986, Topic: Loss of Offsite Power)
- Information Notice 1986-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders (11 April 1986, Topic: Hydrostatic)
- Information Notice 1986-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners (11 April 1986)
- Information Notice 1986-26, Potential Problems in Generators Manufactured by Electrical Products Incorporated (17 April 1986)
- Information Notice 1986-27, Access Control at Nuclear Facilities (21 April 1986, Topic: Contraband)
- Information Notice 1986-28, Telephone Numbers to the NRC Operations Center and Regional Offices (24 April 1986)
- Information Notice 1986-29, Effects of Changing Valve Moter-Operator Switch Settings (25 April 1986)
- Information Notice 1986-30, Design Limitations of Gaseous Effluent Monitoring Systems (29 April 1986)
- Information Notice 1986-31, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges (14 July 1986)
- Information Notice 1986-32, Request for Collection of Licensee Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident (2 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & their Actuators (13 May 1986)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & Their Actuators (13 May 1986)
- Information Notice 1986-35, Fire in Compressible Material at Dresden Unit 3 (15 May 1986, Topic: Chernobyl)
- Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-37, Degradation of Station Batteries (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-38, Deficient Operator Actions Following Dual Function Valve Failures (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-39, Failures of RHR Pump Motors and Pump Internals (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters (9 June 1986, Topic: Chernobyl)
- Information Notice 1986-42, Improper Maintenance of Radiation Monitoring Systems (9 June 1986, Topic: Temporary Modification, Chernobyl)
- Information Notice 1986-43, Problems with Silver Zeolite Sampling of Airborne Radioiodine (10 June 1986, Topic: Chernobyl)
... further results |
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