Demonstration of Associated Equipment Compliance with 10 CFR 34.20ML031060147 |
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, Three Mile Island, 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 |
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Issue date: |
04/04/1996 |
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From: |
Cool D NRC/NMSS/IMNS |
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To: |
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References |
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IN-96-020, NUDOCS 9603290269 |
Download: ML031060147 (11) |
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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, Three Mile Island, 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 |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 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 [[:Three Mile Island]] 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]] </code>.
[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 [[:Three Mile Island]] 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]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 April 4, 1996 NRC INFORMATION NOTICE 96-20: DEMONSTRATION OF ASSOCIATED EQUIPMENT
COMPLIANCE WITH 10 CFR 34.20
Addressees
All industrial radiography licensees and radiography equipment manufacturers.
Purpose
The U.S. Nuclear Regulatory Commission is issuing this information notice to
inform radiography licensees of acceptable methods to demonstrate that their
associated equipment used in radiographic operations meets the regulations in
10 CFR 34.20. It is expected that recipients will review the information for
applicability to their facilities and consider appropriate actions. However, this information notice does not contain any new requirements; therefore, no
specific action nor written response is required.
Description of Circumstances
Section 34.20 of 10 CFR Part 34 specifies performance requirements for
radiography equipment. Paragraph (d) of 10 CFR 34.20 provided that all newly
manufactured radiographic exposure devices and associated equipment
(manufactured after January 10, 1992) acquired by NRC licensees must meet
Section 34.20 requirements. Paragraph (e) of 10 CFR 34.20 provides that all
radiographic exposure devices and associated equipment in use by NRC licensees
after January 10, 1996, must comply with the requirements specified in
10 CFR 34.20. NRC amended the regulations in 10 CFR 34.20 to permit licensees
to use an alternate value of torque for performance testing criteria and to
allow licensees to use engineering analysis to demonstrate that a modest
change in an already approved design is acceptable without the need to perform
prototype testing. The changes were published in the Federal Register as a
-final rule on May 31, 1995.
NRC Information Notice (IN)95-58: "10 CFR 34.20; Final Effective Date,"
issued on December 18, 1995, to all radiography licensees, reminded licensees
of the final effective date implementing the regulations in 10 CFR 34.20. IN
95-58 also reminded licensees that associated equipment used with radiography
cameras (i.e., source assemblies, drive cables, guide tubes, control tubes, source stops, etc.) were subject to 10 CFR 34.20 requirements. IN 95-58 went
on to explain that, previously, certain associated equipment had not been
independently registered and/or evaluated by the NRC or the Agreement States
(AS). This includes drive cables, guide tubes, and source stops. Most new
9603290269 PADR Ano
Pt 96-oao %oqoq for
IN 96-20
April 4, 1996 camera models and their basic associated equipment
the gamma radiography system as described in the were registered as part of
N432-1980, "Radiological Safety for the Design and American National Standard
Construction
for Gamma Radiography." Therefore, information concerning of Apparatus
equipment to be used with the devices was included certain associated
system evaluation and registration process. Some as part of the overall
labeling their equipment with an identifier, such manufacturers have also been
as the manufacturer's logo, to indicate that the equipment meets the requirements
IN 95-58 went on to remind licensees that 10 CFR of 10 CFR 34.20.
34.20
responsible for ensuring that equipment meets regulatorymakes the licensee
requirements.
NRC and AS review and evaluate radiography-associated
exposure heads, and collimators) as well as sealed equipment (guide tubes, exposure devices (cameras) and source changers for sources, radiographic
Part 34. On completion of this evaluation, acceptablecompliance with 10 CFR
identified on a registration certificate. Information components are
National Registry System maintained by NRC. Regulatory is also included in a
information in their licensing and inspection activities. authorities use this
Discussion
The regulation on performance requirements for radiography
Section 34.20 -- require that the radiographic exposure equipment --
associated equipment must meet the requirements of device and all
ANSI
specific requirements listed in 10 CFR 34.20. Associated N432-1980, and other
source assemblies, drive cables, guide tubes, control equipment includes
tubes, collimators, exposure heads, and source stops. tubes, cranks, "J"
In particular for guide tubes, 10 CFR 34.20(c)(5)
have passed the crushing tests for the control tubestates, "The guide tube must
and a kinking resistance test that closely approximatesas specified in ANSI N432 likely to be encountered during use." In addition, the kinking forces
10 CFR 3 4.20(c)(8)
requires that the connection between the guide tube
to withstand the tensile test for control units and exposure head be able
specified
Section 8.9 of ANSI N432-1980 specifies that radiography in ANSI N432. Since
withstand the endurance test described in that section, systems must
demonstrate that guide tubes and exposure heads licensees must
test. will withstand the endurance
Recently some questions were raised concerning what
head vs. a guide tube. Exposure heads may be a constitutes an exposure
guide tube. NRC's analysis of associated equipmentseparate or integral part of a
tubes, exposure heads) has shown that there is little (i.e., collimators, guide
source travel for equipment that guides a source risk of obstruction of
assembly a distance less than
. I
-. :%
IN 96-20
April 4, 1996 10 times the length of the source capsule. NRC's analysis included a review
of equipment designs and incidents involving source travel obstructions.
Based on these findings, NRC's policy is that associated equipment that guides
a source assembly a distance greater than 10 times the length of the source
capsule (i.e., exposure heads, "J" tubes, jet engine probes, source stops) is
considered a guide tube and must meet the testing requirements for guide
tubes. In addition, NRC's policy is that only associated equipment that comes
in contact with the source (e.g., collimators that slip over the end stop)
must meet the applicable testing requirements.
The NRC has identified several ways licensees can demonstrate that their
radiography equipment meets 10 CFR 34.20 requirements. First, the most direct
method would be that the equipment has been labeled by the manufacturer
pursuant to a registration certificate. (If the label has worn off, you
should contact the manufacturer or have support information as described
below.) Alternatively, licensees can make this demonstration if they can
provide a document trail to registered associated equipment. The equipment
will be considered to meet the requirements, if the licensee has in its
possession one of the following for each piece of equipment:
(a) A purchase order(s) listing the radiography equipment that can be
tied-back to a registration certificate; or, (b) Documentation from the manufacturer verifying that the equipment
the licensee is using was approved and registered with the NRC or
AS. The documentation must clearly identify which equipment meets
the requirements; or, (c) A signed NRC or AS recognized checklist(s) certifying that the
licensee has evaluated its equipment, and that it meets the
specifications of the checklist. In order for the checklist to be
recognized, it must have been provided by the manufacturer of the
equipment and approved by the NRC or AS. As of this date, only
one checklist has been approved. See Attachment 1 for the
recognized checklist.
If a licensee possesses and intends to use radiography equipment that is not
labeled by the manufacturer, or that the licensee cannot demonstrate that it
meets 10 CFR 34.20 requirements, then the licensee must submit an application
for a custom evaluation. Attachment 2 includes information on how to file an
application for custom evaluation. Equipment cannot be used in radiographic
operations until it has been approved for use by NRC or an AS.
IN 96-20
April 4, 1996 This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate regional office.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material
Safety and Safeguards
Attachments:
1. Recognized Checklist for Associated Equipment
2. Custom Evaluation of Associated Equipment
3. List of Recently Issued NMSS Information Notices
4. List of Recently Issued NRC Information Notices
Contact: Thomas W. Rich, NMSS
(301) 415-7893 Ar4 Ajar ~
1 II
__-_1i
Attachment 1 IN 96-20
April 4, 1996 Checklist for Amersham's Model 591 Controls
To assure the associated equipment you are using are approved Amersham
manufactured accessories, please perform a side by side comparison against a
known (i.e.,'flying A is legible or'Pos are available) Amersham manufactured
piece. Perform a detailed mechanical and visual inspection of your equipment
against the following checklist... If you have any questions, please call
Amersham for assistance.
Amersham Controls:
1. All controls have a yellow polyvinyl housing with a 9/16 inch outer
diameter.
2._ The fittings are 3 inches long (including the hex nut).
3. The hex nut is 11/16 inch.
4. Check the fittings fo' swage marks,'the fittings will have 3 single
swage marks =1/8'inch wide and = 1/2 inch apart or 4 single swage marks
1/8 inch wide and = 1/2 inch apart.
5. The first swage mark is typically 3/8 inch from the end.
6. The thread pattern for the control connector is 5/8"-18.
7. The 661 connector assembly Will;have an indentation =1/2 inch wide band
behind the jaws, for newer units this will be covered with a red stripe, but this stripe may have worn off on the older models.
To the best of my knowledge the piece of equipment identified below (the
equipment must be uniquely identifiable, either by labeling, marking, or
tagging, or other means to signify which piece of equipment is certified as
meeting the conditions of this checklist)has been manufactured after 1964, meets the conditions of this checklist, and is the same design as a similar
piece of equipment that has been registered and approved by the NRC.
Specify Equipment (i.e., Guide Tube) Signature
Include Identifier/Labeling
Printed or Typed Name
Attachment 1 IN 96-20
April 4, 1996 Amersham Model 402, 489, and 676 Guide Tubes
To assure the associated equipment you are using are approved Amersham
manufactured accessories, please perform a side by side comparison against
a
known (i.e., flying A is legible or POs are available) Amersham manufactured
piece. Perform a detailed mechanical and visual inspection of your equipment
against the following checklist. If you have any questions, please call
Amersham for assistance.
Amersham Guide Tubes:
1. Housing should be yellow polyvinyl with either a 5/8 inch or 3/4 inch
outer diameter.
2. The fittings are yellow iridited steel, the threaded fittings consist of
1 inch 18 thread.
3. The fittings for both the threaded fitting and the source stop fitting
will have 2 single swage marks approx 1/4 inch apart.
4._ The Amersham standard source stops are made from aluminum and are 2 1/2 inches long.
To the best of my knowledge the piece of equipment identified below (the
equipment must be uniquely identifiable, either by labeling, marking, or
tagging, or other means to signify which piece of equipment is certified
meeting the conditions of this checklist) has been manufactured after 1964,as
meets the conditions of this checklist, and is the same design as a similar
piece of equipment that has been registered and approved by the NRC.
Specify Equipment (i.e., Guide Tube) Signature
Include Identifier/Labeling
Printed or Typed Name
Attachment 2 IN 96-20
April 4, 1996 CUSTOM EVALUATION OF ASSOCIATED EQUIPMENT
The information provided below applies to custom registration of associated
equipment.
Product Registration
Either the manufacturer, distributor, or user of the radiographic equipment
can submit the information outlined in 10 CFR 32.210 for evaluation.
If the applicant is located within the jurisdiction of the U.S. Nuclear
Regulatory Commission, the application should be sent to the following
address:
U.S. Nuclear Regulatory Commission
Sealed Source Safety Section
Mail Stop T-8-F-5 Washington, DC 20555 Otherwise, the applicant should submit the information to the appropriate
Agreement State.
Application Contents
General:
Licensees are required to use only radiography equipment, including exposure
heads and source guide tubes, that meets the requirements specified in 10 CFR
34.20. The regulations require that the exposure device and all associated
equipment must meet the requirements in American National Standard N432-1980,
"Radiological Safety for the Design and Construction of Apparatus for Gamma
Radiography," and other specific requirements listed in 10 CFR 34.20. The
standard defines the requirements for the design and method of qualifying
(testing) prototypes of gamma radiography systems.
Refer to Regulatory Guide 10.10, "Guide for the Preparation of Applications
for Radiation Safety Evaluation and Registration of Devices Containing
Byproduct Material" for information on what types of information needs to be
included in your application.
Specific:
Applications for registration for the equipment must, at a minimum, include
the following documentation:
Attachment 2 IN 96-20
April 4, 1996 1. A demonstration, either by testing or by engineering analysis, that
prototypes of the associated equipment meets the appropriate tests
listed below;
2. A list of all radiographic exposure equipment with which the equipment
will be used, and an explanation of how the equipment is compatible with
each piece of equipment;
3. Details of how the associated equipment will be identified, such as by
labeling, marking, or tagging, as meeting the requirements of
Section 34.20;
4. Complete specifications, including materials, details of construction, and complete dimensions of each component of the equipment; and
5. Likely environments (i.e., temperature, pressure, vibration, humidity, impact) and conditions of use of the equipment.
Prototype Tests
Each associated equipment design (e.g., source guide tube, collimator, exposure head) must either pass the appropriate tests listed below, or by
engineering analysis demonstrate that the designs would likely meet the test
requirements.
NRC's policy is that associated equipment that guides a source assembly a
distance greater than 10 times the length of the source capsule (i.e.,
exposure heads, "J"tubes, jet engine probes, source stops) is considered a
guide tube and must meet the testing requirements for guide tubes.
Source Guide Tube Tests
Source guide tubes are required to meet the following:
a. The crushing test specified in Section 8.6 of ANSI N432-1980;
b. a kinking resistance test that closely approximates the kinking
forces likely to be encountered during use;
c. the endurance test specified in Section 8.9 of ANSI N432-1980; and
d. the tensile tests specified in Section 8.7 of ANSI 432-1980 for
control units.
K>
Attachment 2 IN 96-20
April 4, 1996 Exposure Head and Collimator Tests
Exposure heads and collimators that are not considered guide tubes, need only
meet the tests listed in item c, and d above.
Engineering Analysis
Engineering analysis will be considered in lieu of actual testing if the
analysis is based on a similar design that has been tested in accordance with
the standard and has been approved by the NRC or Agreement State. The
engineering analysis, at a minimum, must compare the tested design against the
associated equipment you want evaluated and address the effects of the
materials of construction (i.e., wear resistance, strength, corrosion
properties), the wall thickness, the length (i.e., resistance), any bends, bend angles and the minimum bend radii over which the bends will be produced
(curvature), and any other properties that would have an effect on the outcome
of the endurance test.
Attachment 3 IN 96-20
April 4, 1996 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Tn, nnm,+4nn flt - r
I
IL. uI 111i lull UDate OT
Notice No. Subject Issuance Issued to
96-18 Compliance With 10 CFR 03/25/96 All material licensees
Part 20 for Airborne authorized to possess and
Thorium use thorium in unsealed form
96-04 Incident Reporting 01/10/96. All Radiography Licensees
Requirements for and Manufacturers of
Radiography Licensees Radiography Equipment
95-58 10 CFR 34.20; Final 12/18/95 Industrial Radiography
Effective Date Licensees.
95-55 Handling Uncontained 12/6/95 All Uranium Recovery
Yellowcake Outside of a Licensees.
Facility Processing Circuit
95-51 Recent Incidents Involving 10/27/95 All material and fuel cycle
Potential Loss of Control licensees.
of Licensed Material
95-50 Safety Defect in Gammamed 10/30/95 All High Dose Rate
12i Bronchial Catheter Afterloader (HDR) Licensees.
Clamping Adapters
95-44 Ensuring Combatible Use of 09/26/95 All Radiography Licensees.
Drive Cables Incorporating
Industrial Nuclear Company
Ball-type Male Connectors
95-39 Brachytherapy Incidents 09/19/95 All U.S. Nuclear Regulatory
Involving Treatment Commission Medical
Planning Errors Licensees.
95-29 Oversight of Design and 06/07/95 All holders of OLs or CPs
and Fabrication Activities for nuclear power reactors.
for Metal Components Used
in Spent Fuel Dry Storage Independent spent fuel
Systems
storage installation
designers and fabricators.
Attachment 4 IN 96-20
April 4, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-19 Failure of Tone Alert 04/02/96 All holders of OLs or CPs
Radios to Activate When for nuclear power reactors
Receiving a Shortened
Activation Signal
96-18 Compliance with 10 CFR 03/25/96 All material licensees
Part 20 for Airborne authorized to possess and
Thorium use thorium in unsealed
form
95-03 Loss of Reactor Coolant 03/25/96 All holders of OLs or CPs
Supp. 1 Inventory and Potential for PWR power plants
Loss of Emergency Mitiga- tion Functions While in a
Shutdown Condition
96-17 Reactor Operation Incon- 03/18/96 All holders of OLs or CPs
sistent with the Updated for nuclear power reactors
Final Safety Analysis
Report
96-16 BWR Operation with 03/14/96 All holders of OLs or CPs
Indicated Flow Less Than for boiling-water reactors
Natural Circulation
96-15 Unexpected Plant Perform- 03/08/96 All holders of OLs or CPs
ance During Performance for nuclear power reactors
of New Surveillance Tests
96-14 Degradation of Radwaste 03/01/96 All holders of OLs or CPs
Facility Equipment at for nuclear power reactors
Millstone Nuclear Power
Station, Unit 1
96-13 Potential Containment 02/26/96 All holders of OLs or CPs
Leak Paths Through for nuclear power reactors
Hydrogen Analyzers
96-12 Control Rod Insertion 02/15/96 All holders of OLs or CPs
Problems for nuclear power reactors
OL = Operating License
CP = Construction Permit
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy, Overexposure, Depleted uranium)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Eddy Current Testing, Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996, Topic: Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996, Topic: Tone Alert Radio, Siren)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy, Overspeed trip, Overspeed)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Nondestructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Nondestructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Commercial Grade, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996, Topic: Feedwater Heater)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996, Topic: Hardened grease)
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