Information Notice 1993-77, Human Errors That Result in Inadvertent Transfers of Special Nuclear Material at Fuel Cycle Facilities
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 October 4, 1993 NRC INFORMATION NOTICE 93-77: HUMAN ERRORS THAT RESULT IN INADVERTENT
TRANSFERS OF SPECIAL NUCLEAR MATERIAL AT FUEL
CYCLE FACILITIES
Addressees
All nuclear fuel cycle licensees.
Purpose
This information notice is to alert addressees to possible sampling program
deficiencies that may arise at nuclear fuel cycle facilities because of the
human factors component of nuclear criticality sampling programs. It is
expected that licensees will review the information for applicability to their
facilities and consider actions, as appropriate, to avoid similar problems.
However, suggestions contained in this information notice do not constitute
new U.S. Nuclear Regulatory Commission requirements; therefore, no specific
action or written response is required.
Description of Circumstances
In August 1992, a licensee notified the NRC that an operator had emptied the
contents of a favorable geometry slab hopper, used to store U02 powder on an
interim basis, into an unfavorable geometry blender before receiving the
sample analysis for the contents of the slab hopper. The sampling of the U02 powder in the slab hopper provides one of the controls to ensure that the
moisture content of the powder is below 1 wt(%) H20. This restriction on the
water content in the UO powder is necessary to ensure nuclear criticality
safety in the unfavorable geometry blender.
The licensee conducted an evaluation to determine the cause(s) of the
inadvertent transfer of UO powder from the slab hopper to the blender. This
evaluation revealed that the inadvertent transfer occurred as follows:
(1) An operator erroneously assumed that a completed powder release form
lying on a desk common to all slab hoppers was for a slab hopper whose
sample results had not yet been received.
(2) The operator then retrieved a key from the control room and subsequently
released the contents (750 kg of U02 powder) of the slab hopper into the
unfavorable geometry blender. (This key was supposed to be controlled by
the shift supervisor, as stipulated by procedure.)
9309290006 PDR 3W Notice q3-67 5 9 t1ool- y
IN 93-77 October 4, 1993 (3) The operator informed the supervisor that he
had dumped the contents of
the slab hopper into the blender. The shift supervisor
recorded this information in the shift log. (At subsequently
this time, the shift
supervisor should have realized that this was an
because he had not signed the powder release form unauthorized transfer
required by procedure.) for the slab hopper, as
The inadvertent transfer was later discovered when
found an unsigned powder release form (lying on the the next shift operator
operating room) for the slab hopper whose powder common desk in the
had
operator did note, from the form, that the laboratory been released. The
hopper were within the release limits. The operator results for the slab
who subsequently verified that the results were withininformed the supervisor, limits. The supervisor then completed and signed the prescribed moisture
form. NRC was informed of the event in accordance the powder sampling record
with NRC Bulletin 91-01.
Discussion
The inadvertent transfer of special nuclear material, described event, resulted from deficiencies associated in the previously
component of the licensee's sampling program. In with the human factors
this
program was deficient in two respects. Using a common instance, the sampling
line paper work represented a less than favorable desk for all powder
powder release forms. This led to a situation in method to store completed
easily mistake one powder release form for another. which an operator could
from reoccurring, the licensee uses a separate desk To prevent this problem
each powder line. (This action has made the inadvertent to house the forms for
powder release form unlikely.) reading of the wrong
The licensee's sampling program was also
deficient with respect to securing control of the
keys, which are used to
release the powder from the slab hoppers to the blender.
supervisor control the keys, the licensee created By not having a
a
operator's single mistake could lead to an inadvertent situation where an
licensee's corrective action is to require that the transfer. The
release keys for the slab hoppers. The licensee's supervisor control the
corrective
sufficient to ensure that the following two independent actions are
are necessary before a criticality is possible: and unlikely events
1. The operator mistakenly reads the wrong powder
release form.
2. The supervisor misreads the form and subsequently
key to release the powder from the slab hopper. gives the operator the
K)
IN 93-77 October 4, 1993 It should be noted, however, that another possible path to a nuclear
criticality could involve a contingency in which an operator is given a common
key by the supervisor. In this scenario, the operator could mistakenly use
the common key to release special nuclear material from the wrong slab hopper.
To preclude this event, the licensee utilizes individual keys for each slab
hopper.
In addition to the previously described event, there have been other occasions
in which a deficient nuclear criticality sampling program has led to an
inadvertent transfer of special nuclear material. One such case occurred when
a licensee operator analyzed two samples from one tank, but recorded them as
being from another tank. As a result, an inadvertent transfer occurred.
Another type of event occurred, on two separate occasions, in which a licensee
reported the inadvertent transfer of liquid-bearing uranium to an unfavorable
geometry container. These transfers occurred when an operator mistakenly
entered the analyses for a different tank into the computer.
The previously discussed events illustrate the necessity for licensees to
carefully review their nuclear criticality sampling programs. Licensees
should vigilantly review their respective programs to ensure that the double
contingency principle is fulfilled. This principle requires that at least two
independent and unlikely concurrent process changes occur before a criticality
is possible. For nuclear criticality sampling programs, this requires the
following:
1. Assurance that an operator mistake (contingency) at any juncture
cannot lead to an inadvertent transfer. That is, a second contingency is
necessary before a nuclear criticality event is possible.
2. A contingency must be an unlikely event. This may require one of the
following controls: using color-coded forms, segregating forms, using
different keys, requiring multiple individuals to inspect results, etc.
IN 93-77 October 4, 1993 This information notice requires no specific action or written response. If
you have questions about the information in this notice, please contact the
technical contact listed below or the appropriate regional office.
Robert F. Burnett, Director
Division of Fuel Cycle Safety
and Safeguards
Office of Nuclear Material Safety
and Safeguards
Technical contact: Marc Klasky, NMSS
(301) 504-2504 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
Attachment 1 IN 93-77 October 4, 1993 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-69 Radiography Events at 09/02/93 All holders of OLs or CPs
Operating Power Reactors for nuclear power reactors
and all radiography
licensees.
93-60 Reporting Fuel Cycle and 08/04/93 All fuel cycle and materials
Materials Events to the licensees.
NRC Operations Center
93-50 Extended Storage of 07/08/93 All licensees authorized
Sealed Sources to possess sealed sources.
93-36 Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory
and Records of Misadmin- Commission medical
istrations licensees.
93-31 Training of Nurses 04/13/93 All U.S. Nuclear Regulatory
Responsible for the Commission medical
Care of Patients with licensees.
Brachytherapy Implants
93-30 NRC Requirements for 04/12/93 All U.S. Nuclear Regulatory
Evaluation of Wipe Commission medical
Test Results; Cali- licensees.
bration of Count Rate
Survey Instruments
93-19 Slab Hopper Bulging 03/17/93 All nuclear fuel cycle
licensees.
93-18 Portable Moisture-Density 03/10/93 All U.S.'Nuclear Regulatory
Gauge User Responsibilities Commission licensees that
. ,
during Field Operations possess moisture-density
93-14 Clarification of 02/18/93 All Licensees who possess
10 CFR 40.22, Small source material.
Quantities of Source
Material
Attachment 2 IN 93-77 October 4, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-76 Inadequate Control of 09/21/93 All holders of OLs or CPs
Paint and Cleaners for for nuclear power reactors.
Safety-Related Equipment
93-75 Spurious Tripping of 09/17/93 All holders of OLs or CPs
Low-Voltage Power Circuit for nuclear power reactors.
Breakers with GE RMS-9 Digital Trip Units
93-74 High Temperatures Reduce 09/16/93 All holders of OLs or CPs
Limitorque AC Motor for nuclear power reactors.
Operator Torque
93-73 Criminal Prosecution of 09/15/93 All NRC licensees.
Nuclear Suppliers for
Wrongdoing
93-72 Observations from Recent 09/14/93 All holders of OLs or CPs
Shutdown Risk and Outage for nuclear power reactors.
Management Pilot Team
Inspections
93-71 Fire at Chernobyl Unit 2 09/13/93 All holders of OLs or CPs
for nuclear power reactors.
93-70 Degradation of Boraflex 09/10/93 All holders of OLs or CPs
Neutron Absorber Coupons for nuclear power reactors.
93-69 Radiography Events at 09/02/93 All holders of OLs or CPs
Operating Power Reactors for nuclear power reactors
and all radiography
licensees.
93-68 Failure of Pump Shaft 09/01/93 All holders of OLs or CPs
Coupling Caused by for nuclear power reactors.
Temper Embrittlement
during Manufacture
OL = Operating License
CP = Construction Permit
IN 93-77 October 4, 1993 This information notice requires no specific action or written response. If
you have questions about the information in this notice, please contact the
technical contact listed below or the appropriate regional office.
Robert F. Burnett, Director
Division of Fuel Cycle Safety
and Safeguards
Office of Nuclear Material Safety
and Safeguards
Technical contact: Marc Klasky, NMSS
(301) 504-2504 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
- C-o nrftD
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-aJcl:p-cVI r "a V IIg cic
OF FCLB* FCLB* lE FCLB* lE FCLB* lE
NAME MKlasky VTharpe MTokar RPierson
DATE 8/05/93 8/05/93 8/10/93 8/10/93 FCK FCOB* l DD:FCS l K I aILI I IL
NAME MSmith RBurnett i
lDATE 9/14/93 09/22/93 Ira_ Io_
DOC NAME: 93-77.IN
IN 3-XX
ptember , 1993 age 4 of 4 This information notice requires no specifi ct r written response. If
you have questions about the information this tice, please contact the
technical contact listed below or the a ri egional office.
Robert F. Bur tt, Director
Division of F el Cycle Safety
and Safegu rds
Office of N lear Material Safety
and Safe ards
Technical contact: Marc Klasky, NMSS
(301) 504-2504 Attachments:
1. List of Recently Issued NMSS Info tion Notices
2. List of Recently Issued NRC Info tion Notices
- See previous concurrence/ [G:\Sampling] 3 OFC l CLB* FCLB* E FCLB* E FCLB* E
NAME MKlasky VTharpe MTokar RPierson
DATE 8/05/ 9 8/05/93 8/10/93 8/10/93 OFC F [ i JDD:FCSS
j D:FC I L I [
NAME l,E c R e
DATE T 9/14/93 9/ /93 9/41193 1
IN 93-XX
August , 1993 In addition to the previously described event, there have been oth occasions
in which a deficient nuclear criticality sampling program has le to an
inadvertent transfer of special nuclear material. One such cas occurred when
a licensee operator analyzed two samples from one tank, but rcorded them as
being from another tank. As a result, an inadvertent trans r occurred.
Another type of event occurred, on two separate occasions in which a licensee
reported the inadvertent transfer of liquid-bearing ura um to an unfavorable
geometry container. These transfers occurred when an erator mistakenly
entered the analyses for a different tank into the c puter.
The previously discussed events illustrate the n essity for licensees to
carefully review their nuclear criticality samp. ng programs. Licensees
should vigilantly review their respective pro ams to ensure that the double
contingency principle is fulfilled. T nciple requires that at least two
independent and unlikely concurrent oce changes occur before a criticality
is possible. For nuclear criticali y s ing programs, this requires the
following:
1. Assurance that an operator ke Cc ntingency) at any juncture
cannot lead to an inadvertent transfe. That is,a second contingency is
necessary before a nuclear criticali y event is possible.
2. A contingency must be an unlikely vent. This may require one of the
following controls: using color- oded forms, segregating forms, using
different keys, requiring multip e individuals to inspect results, etc.
This information notice requires n specific action or written response. If
you have questions about the infor ation in this notice, please contact the
technical contact listed below o the appropriate regional office.
Robert F. Burnett, Director
Division of Fuel Cycle Safety
and Safeguards
Office of Nuclear Material Safety
and Safeguards
Technical contact: Marc lasky, NMSS
(30 504-2504 Attachments:
1. List of Recently ssued NMSS Information Notices
2. List of Recentl Issued NRC Information Notices
- See Drevious con rrence
OFC FCLB FCLB*LB
NAME _ i_
_ asky VTharpe MTok-a*1' R
DATE 8/05/93 8/05/93 8/e/93 8/(4/93 OFC
NAME
DATE
iF:FCSS
8/
eves
I l
__
D:FCS
Burnett
8/ /93Q
l J co
d goPdM It
lI I I I
- . COVER E-= COVER & ENCLOSURE N= NO COPY
[G:\Sampling]
KYJ IN 93-XX
August , 1993 In addition to the previously described event, there have been other occasions
in which a deficient nuclear criticality sampling program has led to an
inadvertent transfer of special nuclear material. One such case occurred when
a licensee operator analyzed two samples from one tank, but recorded them as
being from another tank. As a result, an inadvertent transfer occurred.
Another event occurred, on two separate occasions, in which a licensee
reported the Inadvertent transfer of liquid-bearing uranium to an unfavorable
geometry container. These transfers occurred when an operator mistakenly
entered the analyses for a different tank into the computer.
The previously discussed events illustrate the necessity for licensees to
carefully review their nuclear criticality sampling programs. Licensees
should vigilantly review their respective programs to ensure that the double
contingency principle is fulfilled. This principle requires that at least two
independent and unlikely concurrent process changes occur before a criticality
is possible. For nuclear criticality sampling programs, this requires the
following:
1. Assurance that an operator mistake (contingency) at any juncture
cannot lead to an inadvertent transfer. That is,a second contingency is
necessary before a nuclear criticality event is possible.
2. A contingency must be an unlikely event. This may require one of the
following controls: using color-coded forms, segregating forms, using
different keys, requiring multiple individuals to inspect results, etc.
This information notice requires no specific action or written response. If
you have questions about the information in this notice, please contact the
technical contact listed below or the appropriate regional office.
Robert F. Burnett, Director
Division of Fuel Cycle Safety
and Safeguards
Office of Nuclear Material Safety
and Safeguards
Technical contact: Marc Klasky, NMSS
(301) 504-2504 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices l
OFC [ZKL FCLB
NAME MKAVY X .rpe MTokar RPierson
DATE 8/5 /93 8/ 5/93 8/ /93 8/ /93 NiC DD:eFCSS rD:tFCSS
OAZL JGreeves RBurnett
DATE 8/ /93 8/ /93 C = COVER E = COVER & ENCLOSURE N= NO COPY
[G:\Sampling]
PAGE 1 MATERIAL LICENSE PROGRAM CODES SEPTEMBER 1993 PROGRAM
CODE TITLE
01100 ACADEMIC TYPE A BROAD
01110 ACADEMIC TYPE B BROAD
01120 ACADEMIC TYPE C BROAD
01200 ACADEMIC OTHER (SECONDARY CODE)
02110 MEDICAL INSTITUTION BROAD
02120 MEDICAL INSTITUTION LIMITED
02121 MEDICAL INSTITUTION CUSTOM
02200 MEDICAL PRIVATE PRACTICE - LIMITED
02201 MEDICAL PRIVATE PRACTICE - CUSTOM
02209 GRANDFATHERED IN-VIVO GENERAL MEDICAL USE
02210 EYE APPLICATORS STRONTIUM-90
02220 MOBILE NUCLEAR MEDICINE SERVICE
02230 HIGH DOSE RATE REMOTE AFTERLOADER
02231 MOBILE HIGH DOSE RATE REMOTE AFTERLOADER
02300 TELETHERAPY
02400 VETERINARY NON-HUMAN
02410 IN-VITRO TESTING LABORATORIES
02500 NUCLEAR PHARMACIES
02511 MEDICAL PRODUCT DISTRIBUTION - 32.72 - PREPARED RADIOPHARMACEUTICALS
02512 MEDICAL PRODUCT DISTRIBUTION 32.73 - GENERATORS AND KITS
02513 MEDICAL PRODUCT DISTRIBUTION - 32.74 - SOURCES AND DEVICES
03110 WELL LOGGING BYPRODUCT AND/OR SNM TRACER AND SEALED SOURCES
03111 WELL LOGGING BYPRODUCT AND/OR SNM SEALED SOURCES ONLY
03112 WELL LOGGING BYPRODUCT ONLY-TRACERS ONLY
03113- FIELD FLOODING STUDIES
03120 MEASURING SYSTEMS FIXED GAUGES
03121 MEASURING SYSTEMS PORTABLE GAUGES
03122 MEASURING SYSTEMS ANALYTICAL INSTRUMENTS
03123 MEASURING SYSTEMS GAS CHROMATOGRAPHS
03124 MEASURING SYSTEMS OTHER
03211 MANUFACTURING AND DISTRIBUTION TYPE A BROAD
03212 MANUFACTURING AND DISTRIBUTION TYPE B BROAD
03213 MANUFACTURING AND DISTRIBUTION TYPE C BROAD
03214 MANUFACTURING AND DISTRIBUTION OTHER
03218 NUCLEAR LAUNDRY
03219 DECONTAMINATION SERVICES
03220 LEAK TEST SERVICE ONLY
03221 INSTRUMENT CALIBRATION SERVICE ONLY --SOURCE LESS THAN 100 CURIES
03222 INSTRUMENT CALIBRATION SERVICE ONLY - SOURCE GREATER THAN 100 CURIES
03223 LEAK TEST & INSTR CALIBRATION SERVICE -.SOURCE LESS.THAN 100 CURIES
03224 LEAK TEST & INSTR CALIBRATION SERVICE - SOURCE GREATERTHAN 100 CURIES
03225 OTHER SERVICES
03231 WASTE DISPOSAL (BURIAL)
03232 WASTE DISPOSAL SERVICE PREPACKAGED ONLY
03233 WASTE DISPOSAL SERVICE INCINERATION
03234 WASTE DISPOSAL SERVICE PROCESSING AND/OR REPACKAGING
03235 INCINERATION - NONCOMMERCIAL (SECONDARY CODE)
03240 GENERAL LICENSE DISTRIBUTION - 32.51
03241 GENERAL LICENSE DISTRIBUTION - 32.53
PAGE 2 MATERIAL LICENSE PROGRAM CODES SEPTEMBER 1993 PROGRAM
CODE TITLE
03242 GENERAL LICENSE DISTRIBUTION - 32.57
03243 GENERAL LICENSE DISTRIBUTION - 32.81
03244 GENERAL LICENSE DISTRIBUTION - 32.71
03250 EXEMPT DISTRIBUTION - 32.11 - EXEMPT CONCENTRATIONS AND ITEMS
03251 EXEMPT DISTRIBUTION - 32.14 - CERTAIN ITEMS
03252 EXEMPT DISTRIBUTION - 32.17 - RESINS
03253 EXEMPT DISTRIBUTION - 32.18 - SMALL QUANTITIES
03254 EXEMPT DISTRIBUTION - 32.22 - SELF LUMINOUS PRODUCTS
03255 EXEMPT DISTRIBUTION - 32.26 - SMOKE DETECTORS
03310 INDUSTRIAL RADIOGRAPHY FIXED LOCATION
03320 INDUSTRIAL RADIOGRAPHY TEMPORARY JOB SITES
03510 IRRADIATORS SELF SHIELDED LESS THAN 10000 CURIES
03511 IRRADIATORS OTHER LESS THAN 10000 CURIES
03520 IRRADIATORS SELF SHIELDED GREATER THAN 10000 CURIES
03521 IRRADIATORS OTHER GREATER THAN 10000 CURIES
03610 RESEARCH AND DEVELOPMENT TYPE A BROAD
03811 RESEARCH AND DEVELOPMENT TYPE B BROAD
03612 RESEARCH AND DEVELOPMENT TYPE C BROAD
03613 R & D BROAD - MULTISITE-MULTIREGIONAL
03820 RESEARCH AND DEVELOPMENT OTHER
03710 CIVIL DEFENSE I
03800 BYPRODUCT MATERIAL POSSESSION ONLY
03900 DECOMMISSIONING OF BYPRODUCT MATERIAL FACILITIES
08100 LOW-LEVEL WASTE STORAGE AT REACTOR SITES
08101 LOW-LEVEL WASTE STORAGE - OTHER (SECONDARY CODE)
11100 MILLS
11200 SOURCE-MATERIAL OTHER LESS THAN 150 KILOGRAMS
11210 SOURCE MATERIAL SHIELDING
11220 SOURCE MATERIAL MILITARY MUNITION - INDOOR TESTING
11221 SOURCE MATERIAL MILITARY MUNITION - OUTDOOR TESTING
11230 SOURCE MATERIAL GENERAL LICENSE DISTRIBUTION - 40.34
11300 SOURCE MATERIAL OTHER GREATER THAN 150 KILOGRAMS
-11400 URANIUM HEXAFLUORIDE (UF8O PRODUCTION PLANTS
11500 SOLUTION MINING (R & D AND COMMERCIAL FACILITIES
00 HEAP LEACH, ORE BUYING STATIONS AND BYPRODUCT RECOVERY
1700 RARE EARTH EXTRACTION AND PROCESSING
11800 SOURCE MATERIAL POSSESSION ONLY
11900 DECOMMISSIONING OF SOURCE MATERIAL FACILITIES
21130 HOT CELL OPERATIONS
21135 DECOMMISSIONING OF ADVANCED FUEL R&D AND PILOT PLANTS
21200 URANIUM ENRICHMENT PLANTS
21210 URANIUM FUEL FABRICATION PLANTS
21215 DECOMMISSIONING OF URANIUM FUEL FABRICATION PLANTS'
21240 URANIUM FUEL R&D AND PILOT PLANTS
21310 CRITICAL MASS MATERIAL - UNIVERSITIES
21320 CRITICAL MASS MATERIAL-- OTHER THAN UNIVERSITIES
235. DECOMMISSIONING OF CRITICAL MASS - OTHER THAN FUEL FABRICATION
2211 SNM PLUTONIUM - UNSEALED LESS THAN A CRITICAL MASS
22111 SNM U-235 AND/OR U-233 UNSEALED LESS THAN A CRITICAL MASS
22120 SNM PLUTONIUM - NEUTRON SOURCES LESS THAN;200 GRAMS
22130 POWER SOURCES WITH BYPRODUCT AND/OR SPECIAL NUCLEAR MATERIAL
22140 SNM PLUTONIUM - SEALED SOURCES IN DEVICES
22150 SNM PLUTONIUM - SEALED SOURCES LESS THAN A CRITICAL MASS
22151 SNM U-235 AND/OR'U-233 SEALED SOURCES LESS THAN A CRITICAL-MASS
22180 PACEMAKER BYPRODUCT AND/OR SNM - MEDICAL INSTITUTION
22181 PACEMAKER BYPRODUCT AND/OR SNM - INDIVIDUAL
22162 PACEMAKER BYPRODUCT AND/OR SNM - MANUFACTURING AND DISTRIBUTION
22170 SNM GENERAL LICENSE DISTRIBUTION (70.39)
22200 DECOMMISSIONING OF OTHER SNM FACILITIES - LESS THAN CRITICAL MASS
---23100 FRESH FUEL STORAGE AT REACTOR SITES
-23200 INTERIM SPENT FUEL STORAGE
23300 SNM POSSESSION ONLY - OTHER THAN REACTOR FUEL
_-25110 TRANSPORT-PRIVATE CARRIAGE
IN q3- &ary' 67rrof-S 4ide- t~ct It/eLs
GENERIC COMMUNICATIONS INC)EX INPUT FORM
GENERAL SYSTEM OR TOPIC SPECIFIC COMPONENT
(Pick a Maximum of 2) (Pick a Maximum of 2)
Ad trative Actuators, Air
(Crnelysij?> Actuators, Motor
A~iT1Tiry Feedwater Actuators, Other
Chemistry Actuators, Solenoid
Containment Bolting
Cooling Water Circuit Breakers
Decay Heat Removal Concrete/Masonry
ECCS Control Rods and Drives
Electric Power Control Room Operators
Emergency Prep Diesel Engines
Equipment Qualifi-cation Electrical Generators
Feedwater Electrical, Other
Fire Protection Fuel and Assemblies
Foundations Mechanical, Other
HVAC M lti le
Instrumentation and Control
Multiple lPiping
0jarations Pumps
Rad Monitoring
Pneumatic Rad Protective Equipment
Power Conversion Rad Regs and Program
Quality Assurance Reactor Internals
ad ro - aon Reacto Relays
Sealed Sources
Radwaste Snubbers, Hydraulic
Reactivity Control Snubbers, Mechanical
Reactor Soil/Rock
Reactor Coolant Steam Generators
Reactor Trip Steel/Tendons
Reg Guidance Structural, Other
Reg Policy Supports, Other
Security Switches
Structures, Containment Testing
Structures, Other Transport Packages
Transportation Turbines
Upgrading Commercial Parts Valves, Check
Valves, Main Steam Iso
Valves, Other
Valves, Relief
Welds
Wiring and Cable
(for MUTIPLE or OTHER, add a footnote for entry into the remarks section)
- quLw fMAhev"
pJQV.
Issue Date: 08/30/91 E-3 0720
K)-j
GENERIC COMMUNICATIONS INDEX INPUT FORM - continued
CAUSE OR DEFECT POTENTIAL EFFECT
(Pick a Maximum of 2) (Pick a Maximum of 2)
Aging WAccden
us e
Analysis Common Mode Failure
Construction Damaged Equipment
Corrosion or Cracking Degraded Safety System
Design Inoperable Safety Function
Documentation Multiple
Equipment Failure Noncompllance
Installation
Maintenance aiFge
Manufacturing Personnel Hazard
Misconduct or Fraud Rad Exp-Occupational
Rad Exp-Public
Rad Release
Procurement
Training
(for MUTIPLE or OTHER, add a footnote for entry into the remarks
section)
V k X eCrL4x
0720 E-4 Issue Date: 08/30/91
GENERIC COMMUNICATIONS INDEX INPUT FORM - continued
VENDORS
(Pick a maximum of 3)
- A- Babcock & Wilcox Control Valves Spec.
Bahnson Co. Cooper Industries
ABB Brown Boveri Barton Cooper-Bessemer
ACF Industries Beau Products Copes-Vulcan
AECL Bechtel Copperweld Steel
AXO, Inc Beloit Power Systems Cor-Val
ANBEX Bendix Coratomic, Inc.
ASCO Bergen-Paterson Cornell-Dueb111er
AVCO Bethlehem StI. Corp. Corner & Lada, Inc.
Acurex Aerotherm Bettis
Adams and Westlake Crane
Bi cron Corp Crosby Valve
Advanced Nuc Fuel Bingham-Willamette
Agastat Cummins
Biomarine Corp. Cutler-Hammer
All NSSS Vendors Blomarine Industries
All PWR NSSS Vendors Bisco Products
Allied Signal -0D -
Boeing Company
Allis Chalmers Borg-Warner D.G. O'Brien Co.
Alloy & Carbon Steel Brown Boveri DIS/ADLPIPE, Inc.
Alloy Steel Products Bunker Ramo Darling
Alpha Associates Bussman Delta Southern
Amer. Atomics Corp. Byron Jackson Descote
Amer. Tank & Fabrica Detroit Diesel Al'sn
Amerace Corp - C - Dow Chemical Corp
American Air Filter Dravo Corp
Amersham C&D Dresser-Consolidated
Amp C&D Power Systems DuPont
Anaconda C.P.Clare Duer Spring
Anchor Darling CMA Durametall1ic
Anderson Greenwood CMA International
Anker-Holth California Breakers - E -
Anti-Theft Systems Calvert Co.
Assoc Piping & Engr Capitol Pipe & Steel E-Systems, Inc.
Atomic Energy of Can Carter-Wallace EG&G
Atwood & Morrll Chem-Nuclear Corp EGS Corp
Auburn Steel Company Chicago Bridge & Irn ELMA Engineering
Automatic Sprinkler Chris-Craft Ebasco
Automatic Switch Co. Circuit Brkr Sjstems Eberline Instrument
Automatic Valve Corp Cogenel (France) Electrical Products
Automation Ind. Colt Industries Electro Devices
Combustion Engrg. Electro Motive, GMC
-8 - Comsip Exide
Con-Chem, Inc.
B&B Promatec Conax -F-
BBC Brown Boveri Consolidated Pipe
BIF/General Signal Control Components Fairbanks Morse
Issue Dates 08/30/91 E-5 0720
1V
GENERIC COMMUNICATIONS INDEX INPUT FORM - continued
VENDORS
(Pick a maximum of 3)
Familian Northwest Impala Electronics Midwest Valve & Supp
Fisher Controls Co. Indstr Control Supp Mine Safety Appli.
Fletcher Suit Indstrl Process Engr Mission Mfg. Co.
Foxboro Industrial Nuclear
Furmanite Mitsubishi
Ingersoll-Rand Mobil Oil
Inryco Mock Mfg
- 6 -* Interstate Stl.Sply. Morrison-Knudson
Intnl Nuclear Safegd Motorola
6. H. Bettis Co.
GE Multiple
GNB Batteries, Inc. -3-
- N-
GPE J.T.Baker Chemical
GTE Sylvania Joseph Oat
Gamma Industries NAMCO Controls
Gamma Pipeliner Nomex-Kapton
-K - Nordberg
Geiger-Muller
General Motors Nortec Corp
Kay-Ray, Inc. Noryl
Golden Gate Forge Kerotest
Gould, Inc. Nuclear Containers
Kerr-McGee Nuclear Data, Inc.
Gould-Brown Boveri Kinemetrics
Gould-Showmut Korean Ind Testing
Greer Hydraulics - O-
Kulka
- H- -L -
Hamnel l-Dahl Owens-Corning
LND Inc.
Hardware Specialty Liberty Equipment
Hayward Tyler Pump Limitorque
Henry Pratt Company Littlefuse PAL
Hexcel/MCI Lixi, Inc. Pacific Pump
Heyer-Scholte Loctite Corp. Pacific Resistor
Hilti Louis Allis Pacific Scientific
Hollinsworst- Luxfer USA Ltd. Pacific Valves, Inc.
Honeywell Page Company
Huico - M- Panalarm
Hydro-Line Mfg Co Panasonic
MN Mining & Mfg (3M) Parker-Hannifin
- I- MQS Inspection Parkwell Labs.
Magnaflux Paul Munroe Hyd
ITE Malcolm Foundry Peerless Pump
ITE/Siemens-Allis Marathon Peerless-Winsmith
ITT Barton Marvin Engineering Phoell Manufacturing
ITT Cannon Masonellan-Dresser Phoenix Steel Corp.
ITT General Controls McDonnell-Millen Co. Picker/AMS
ITT Grinnell Meredith PYN Piping Supplies
E
0720 E-6 Issue Date: 08/30/91
'4 -
GENERIC COMMUNICATIONS INDEX INPUT FORM - continued
VENDORS
(Pick a maximum of 3)
Pittsburg Testing Lb Solidstate Controls ,; W -
Planned Maint Sys Source Prod & Equip
Potter & Brumfield Southwestern Engr W-K-M Division
Power Inspection Inc Spectronics W.H.Stewart
Powerplant Spec States Walworth Company
Pratt Company States Company West Jersey Mfg
Presray Static 0-Ring Western Piping
Pressure Vessel Nuc Stokley Enterprises Westinghouse
Pullman Higgins Stone & Webster William Powell Co.
Sun Shipyard Corp Wisc. Prot. Coatings.
. Q _ Superior Valve Woodward Governor
SurvivAir Wyle Labs
Swagelok
Systems Control v -
R. A. Hiller Company
Radiation Technology -T -
Radionics, Inc.
Ray Miller, Inc. TRC YOH Security
Raychem Target Rock Yarway
Reliance Electric Terry Turbine Young Radiator
Rexnord Thomas & Betts Youngstown Welding
Riley-Beard, Inc. Topaz
Robertshaw Controls Torrington Co. Z Zp
Rockbestos Co. Transamerica DeLaval
Rockwell Tube Turns Zenith Supply Co.
Rackwell-Intnl. - Tube-Line Corp
Rockwell-Edward
Rosemount - U -
Rotork
Ruskin Mfg U. S. Steel
UE&C
-a- Union Pump
Unistrut Corp
S. T. Semicon- SOR, Inc. _ y _
SPEC-2T
Sargent & Greenleaf V.W.R. Scientific
Satin American Valcor Engineering
Schutte & Koerting Velan Engineering
Scott Velan Valve Corp
Scott Aviation Viking Corporation
Service Supply Vogt Machine Co.
Shelwell Services
So Cal Valve Maint.
Sodeco
(for MULTIPLE or OTHER, add a footnote for entry into the remarks
section)
E - ¢ a/lle- A 4C v- Issue Date: 08/30/91 E-7 0720