Information Notice 1993-77, Human Errors That Result in Inadvertent Transfers of Special Nuclear Material at Fuel Cycle Facilities

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Human Errors That Result in Inadvertent Transfers of Special Nuclear Material at Fuel Cycle Facilities
ML031070075
Person / Time
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  Entergy icon.png
Issue date: 10/04/1993
From: Burnett R
NRC/NMSS/FCSS
To:
References
IN-93-077, NUDOCS 9309290006
Download: ML031070075 (17)


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

gauges.

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

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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

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8/

eves

I l

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Burnett

8/ /93Q

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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