ML20071H969
| ML20071H969 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/16/1983 |
| From: | Slaten N UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20071H409 | List:
|
| References | |
| ISSUANCES-OL, NUDOCS 8305250552 | |
| Download: ML20071H969 (23) | |
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MN' g;O = l y-4
/ b UNITED STATES OF AMERth
'o NUCLEAR REGULATORY COMMISSION'E N
g O cf 8
- E p
g BEFORE THE~ ATOMIC SAFETY AND LICEN_ING' BOARD N/
\\
/
In the Matter of-
)
)
UNION ELECTRIC COMPANY
)
Docket No. STN 50-483 OL
)
(Callaway Plant, Unit 1)
)
AFFIDAVIT OF NEAL G.
SLATEN ON REED CONTENTION'17 (RADIOLOGICAL MONITORING)
City'of St. Louis
)
)~
ss.
State of Missouri
)
NEAL G.
SLATEN, being duly sworn, deposes and says as follows:
1.
I am the Supervising Engineer - Environmental, for Union Electric Company.
In the event of a Site or General
. radiological emergency at the Callaway Plant, I will serve as Radiological Assessment Coordinator.
My business address is Union Electric Company, P.O.
Box 149, St. Louis, Missouri 63166.
A summary of my professional qualifications and experience-is attached hereto as Exhibit "A".
I have personal
-knowledge of.the matters stated herein and believe them to be 8305250552 830520 PDR ADOCK 05000483-O PDR
.- gi b.
1 true and correct.
I make this affidavit in response to Reed
. Contention 17 (Radiological Monitoring).
2.
As the Supervising Engineer - Environmental, my normalLresponsibility.is to direct the Union Electric Company corporate Environmental and Health Physics Group, which at present consists of two health physicists and two engineers.
My duties include:
supporting federal, state and local licensing activities; reviewing radwaste, shielding and
. radiation monitoring system engineering design work; estab-lishing and evaluating off-site radiological environmental monitoring programs; establishing corporate ALARA policy; reviewing conformance to-radiological technical specifications; and other duties related to health physics and environmental assessment.
3.
During a Site or General Emergency at the Callaway Plant my duties as the Radiological Assessment Coordinator would include:
evaluating and relaying radiological informa-tion to the Union Electric Recovery Manager concerning the need to make protective action recommendations to'off-site authori-ties; ensuring the coordination of off-site field monitoring
. activities; and ensuring that the Union Electric Recovery Manager is kept appraised of field monitoring results and off-site dose assessment.
4.
The purpose of.this affidavit is to describe the off-t site radiological monitoring capability:of Union Electric Company ("UE") in the event of a: radiological emergency at the LCallaway. Plant.
5.
Sections II.I.7, II.I.8 and II.I.9 of NUREG-0654, Rev.
1,
" Criteria for Preparation and Evaluation of~
Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," referred to by Mr. Reed in Contention 17, relate to off-site radiological monitoring capability.
In' evaluating the capability of responsible organizations and entities to adequately monitor off-site t
radiation doses in the event of an emergency at the Callaway l
Plant, consideration must be given to UE's off-site radiolog-ical monitoring program.
An extensive radiological monitoring organization and capability is a part of UE's planned response in the event of a radiological emergency at the Callaway Plant.
i The monitoring capability of the State of Missouri serves as a l
means of verifying the findings of UE's monitoring program.
UE's monitoring capabilities satisfy the criteria of NUREG-0654.
The Callaway Plant Radiological Emergency Response Plan ("RERP"), chapters 5, 6 and 7, contains a detailed
~
i description of UE's off-site monitoring program and resources.
This affidavit is essentially based on that description.
The Emergency Response Monitoring Organization 6.
'UE's monitoring program is an integral part of the 1
-three distinct UE emergency response organizations capable of l
responding on'a 24-hour-per-day basis-to emergencies at the l
Callaway Plant.
In the event of an emergency which requires implementation of the RERP, e.g.,
an Unusual Event, the normal - _ _ _ - _ _ _ _ _ _.
l on-shift organization'becomes the On-shift Emergency Organization.
This organization operates from the control room.
In the event of an Alert or higher emergency clas-sification, the On-site Emergency Organization is activated.
This' organization operates from the Technical Support Center
("TSC"), the control room and the Operational Support Center
("OSC").
In the event of a Site or General Emergency, the Corporate Emergency Organization is activated.
This organiza-tion operates from the Emergency Operations Facility (" EOF").
The RERP, 5 5.2, describes these UE emergency response organi-zations.
7.
The On-shift Emergency organization, responsible for initial immediate emergency response, includes the on-shift rad / chem foreman, who assumes the emergency position of Health rhysics ("HP") Coordinator.
Among other things, the rad / chem foreman is responsible for off-site dose assessment activities until activation of the TSC, at which time the permanent HP Coordinator assumes this responsibility.
On-shift rad / chem technicians, approximately two per shift, report to the rad / chem foreman.
These individuals are responsible for conducting health physics activities, including field moni-toring.
8.
The On-shift Emergency Organization is staffed to be self-reliant for a sufficient period of time, which is antici-pated to be approximately 30 to 75 minutes, to allow for mobilization of the On-site Emergency Organization.
Figure 5-5 -
of the RERP,. attached as Exhibit "B",
is a diagram of that organization.
One of:the members of the On-Site Emergency
-Organization is the HP Coordinator, who is responsible for directing in-plant health physics and off-site dose assessment.
He-reporte to the Emergency Coordinator, who is in charge of
'all emergency. response activities.
Upon activation of the EOF,
.tte responsibility for off-site dose assessment is transferred from.the HP. Coordinator to the Radiological Assessment Coordin-ator ("RAC") in the EOF.
The following five individuals will be trained for the position of HP Coordinator:
Superintendent, Health Physics; Supervisor, Health Physics Operations; Supervisor,-Health Physics Technical Support; and two staff
. health. physicists and/or nuclear scientists.
9.
Working for the HP Coordinator in the TSC is the Dose l
. Assessment Coordinator.
This individual assumes the responsi-l bility for calculating off-site dose projections from the On-shift Emergency Organization.
He directs off-site field monitoring activities through the Field Team Communicator, who coordinates ~ communications with the Field Monitoring Teams,
' logs radiological field-data as it is received, and reports this information to the Dose Assessment Coordinator.
Upon the activation of the EOF;'both the Dose Assessment. Coordinator and
_the Field Team Communicator's responsibilities are transferred l
to individuals with the same. titles located in the EOF.
Plant personnel trained'for the position of Dose Assessment Coordin-h ator include all of the individuals trained as HP Coordinator,
. I
1 with the exception of the Superintendent, Health Physics, as well as'the rad / chem-foremen.
-There are approximately 30
)
~rad / chem. technicians trained for the position of Field Team Communicator.=
- 10.
Also reporting'to the HP Coordinator is the Radio-logical Controls-(" Rad Con") Coordinator.
Among the Rad Con I
-Coordinator's responsibilities are:
(i)1 forming, briefing and dispatching Field Monitoring Teams as directed by the HP Coordinator; (ii) ensuring the briefing and debriefing of all emergency teams before entering and after leaving a radiolog-ical area; and (iii) ensuring-health physics equipment is available to support emergency assessment activities.
Approximately ten rad / chem foremen will be trained for the position of Rad Con Coordinator.
The rad / chem technicians report _to the Rad Con Coordinator.
11.
UE has the capability to field four Field Monitoring i
Teams per shift.
These teams will collect radiological samples l'
in the field for verification of dose projections.
Each team consists of tw.> members of which at least one member is a j
rad / chem technician.
The,other individual is a member of'the
. plant staff who serves as the vehicle driver and assists the i.
' technician as required.
The teams report to and actablish communications with the Field Team Communicator, e
~
12.
Upon activation of the Corporate Emergency Organi-zation, the coordination of off-site radiological monitoring shifts.to the EOF.
The Recovery Manager, located at the EOF, l e,
-.-,,,,..--,,--.~.--...n.
+. -.,
. has overall-command and control of the entire UE emergency
. response organization..Among other responsibilities, the
- Recovery: Manager makes protective action recommendations to
.off-site authorities, a task assumed by the Emergency Coordina-j i
tor prior to activation of the Corporate Emergency Organization, and ensures-that there is a coordinated emergency response among UE and off-site agencies, such as the State Bureau 1of Radiological Health ("BRH").
13.
An Off-site Liaison Coordinator, located in the EOF, assists the Recovery Manager by, among other things, trans-mitting radiological information to and receiving any
- responding representations from off-site organizations.
The Off-site Liaison Coordinator also assists the Recovery Manager in coordinating UE emergency response with off-site agencies.
The Manager, Nuclear Safety and Emergency Preparedness, and the Supervisor, Emergency Preparedness, will be trained for this position. = Working for the Off-site Liaison Coordinator are two EOF Communicators, who notify and communicate with off-site agencies as directed.
14.
Reporting to the Recovery Mancger is the Radiological J
Assessment Coordinator ("RAC"), who. assumes the responsi-
'bilities of off-site dose assessment from the HP. Coordinator RAC responsibilities include:
. (i). evaluating and relaying radiological information to the Recovery Manager concerning the i
, need to make protective action recommendations'to off-site
- authorities; (ii) ensuring'the coordination of off-site field' s
l
monitoring activities through the EOF Dose Assessment Coordinator; and (iii) ensuring the Recovery Manager is kept appraised of field monitoring results and other off-site dose assignment activities.
Personnel trained for this position are the Supervising Engineer, Nuclear Environmental, as well as two staff health physicists.
15.
Assisting the RAC is the EOF Dose Assessment Coordin-ator who assumes the responsibilities of the Dose Assessment 1.
Coordinator in the TSC described in paragraph 9, above.
The EOF Dose Assessment Coordinator performs dose projection calculations and provide the RAC with the results of his evaluation.
Six staff health physicists and approximately ten rad / chem foremen will be trained for this position.
I
'16.
Reporting'to the Dose Isssessment Coordinator at the EOC is the Field Team Communicator, who assumes the responsi-bilities of the Field Team Coordinator located at the TSC described in paragraph 9, above.
The rad / chem foremen and approximately 30 rad / chem technicians will be trained for the position of Field Team Communicator.
17.
The response organization described above coordinates its radiological monitoring and assessment effort with BRH, whose responsibilities in the event of a radiological accident at the Callaway Plant are described generally in'5 5.4.2.2 of the RERP, andlin detail in Annex-A'of the' Missouri Nuclear Accident Plan - Callaway (" State Plan").
UE has provisions for receiving BRH representatives at the EOF at ALERT or' higher
-=
~..
~"
(mergency clas; Tication. levels.
Office space and communication L :ilities are provided in the EOF for BRH representatives.
Assessment of Radiological Releases fl8.
Effective coordination and direction of all elements of'the emergency organizations, including public~ agencies, J
requires continuing assessment throughout the emergency.
Priority will be given to continuing assessment actions that
- will result in maintaining control of the plant, protective action recommendations for the health and safety of the general
- public, protective actions for on-site personnel, and correc-tive actions in order to mitigate the consequences of an emergency.
19.
Incidents involving potential or actual releases of radioactive materials to the environment require special methods of assessment to ensure that responses are appropriate for. protection of the population at risk and site personnel.
Rapid assessment of potential or actual releases of radioac-tivity to the environment is critical for deciding what protective actions will be required.
Within 30 to 60 minutes of the declaration of an emergency, and within 10 to 45 minutes
. of a release, a UE monitoring program will be established to assess the extent of the release and to provide guidance for appropriate protective measures.
This incudes the capability to deploy one or more Field Monitoring Teams.
1 1 _
,N
" " ~ ~ '
20.
The principal immediate health concerns are radiolog-ical exposure to the thyroid gland due to inhalation of radioactive iodines and to the whole body _from immersion in a
. cloud of radioactive noble gases.
Criteria for taking protec-tive actions such as sheltering and evacuation are expressed in terms of these two variables.
Early efforts of off-site government agencies will be directed toward this assessment.
Following this, efforts by off-site authorities normally will be directed toward the evaluation of possible long-term exposures from ground deposition and various food chain
)
pathways.
21.
A short term assessment to determine off-site doses will be performed by UE with the use of its Radioactive Release
-Information System ("RRIS").
The RRIS provides near real-time predictions of atmospheric transport and diffusion estimates of radioactive releases.
This information is provided to the control room, TSC, EOF, Backup EOF, and the on-site health physics office.
(The Health Physics Office is located in the Control Building at elevation 1984'.
This office is used by health physics personnel for issuing radiation work permits and monitoring and controlling access to plant radiological areas.)
The RRIS utilizes real-time meteorological data,. radioactive release rate data, isotopic concentrations, release flow rate data, and site-specific terrain and climatological features
-that affect atmospheric diffusion and the trajectories of the
-plume.
This data is automatically transmi:tted-te the-RM&,-.
The.RRIS output includes the plume position, the location, magnitude and arrival time of peak concentrations, and thyroid and whole body dose rates and cumulative dose.
The NRC also will receive this data through the NRC Nuclear Data Link interface with the RRIS.
In the event the computer is inoperable, manual calculations can be performed by the Dose Assessment Coordinator in a short timeframe.
Based on off-site dose projections, protective action will be taken as specified in Annex B of the State Plan.
I 22.
The Field Monitoring Teams are used to verify the j
l initial assessment of off-site radiological conditions per-formed with the use of the RRIS.
Deployment of Field Monitoring Teams is anticipated to occur within 30 to 45 minutes from the time a release is discovered or expected.
i Field Monitoring Teams will be equipped with health physics monitoring instrumentation to evaluate actual off-site dose rates and airborne radioactivity concentrations.
Instrumentation available to the monitoring team (s) includes:
l l
low and high range beta-gamma survey meters, a rate meter instrument w/gm pancake probe, portable single channel analyzer with NaI detector, and an air sampler with supply of filter media and silver zeolite cartridges.
This instrumentation provides the Field Monitoring Teams with the capability to analyze airborne and liquid environmental samples as well as the ability to monitor for surface contamination.
In-field evaluation of radioiodinpleveks.-ie eccerpiehM by-sampling - - - -
with a low volume air sampler using a silver zeolite cartridge as the collection media.
Analysis of the cartridge is per-formed by using portable gamma spectroscopy equipment in the l
field.
The sensitivity of this method enables measurement of
-7 iodine concentrations as low as 10 microcuries/ cubic centimeter under low, background counting conditions.
Table E-1, attached as Exhibit "C",
from Appendix E of RERP, is a list of the portable radiation monitoring devices available to UE health physics personnel.
23.
Specific guidance for sampling and analysis for environmental radiciodine levels will be provided in an RERP implementing procedure.
Data will be reported by Field Monitoring Teams via radio to the Field Team Communicator, who then relays this information to the Health Physics Coordinator or the Dose Assessment Coordinator.
24.
Long-term radiological assessment normally will be directed toward the evaluation of possible exposures from ground deposition and various food chain pathways.
To accom-plish this analysis, soil, vegetation, milk and water samples will be taken in accordance with the Radiological Environmental
-Monitoring Program ("REMP").
The REMP consists of sampling the following:
(a) air particulate - sampled at 14 locations surrounding the plant; (b) air iodine - sampled at 7 locations surrounding the plant; (c) gamma dose - sampled at 52 TLD locations surrounding the plant; (d) soil - collected at 4 sites-surreunding-th; plant;- (e }-vegetation - green broad leaf h
. _ _ _. 1_
_1___.___________
j vegetation is collected at 4 sites surrounding the plant; (f) milk.- both cow and goat milk is collected at 3 sites surround-ing the plant; (g) surface water - Missouri River Water is collected both upstream and downstream of the plant and at the St. Louis City Drinking Water Intake station; (h) ground water
- collected at 3 wells surrounding the plant; (1) river sediment - collected from the Missouri River both upstream and downstream of the plant and at the western border of St. Louis County; and (j) fish - collected from the Missouri River both upstream and downstream of the plant and at the western border of St. Louis County.
The analysis performed on each sample and the analysis frequency are shown on Exhibit "D".
Radiological Monitoring Equipment 25.
The equipment available to UE to be used to aid in or for use in conjunction with the assessment of off-site radia-tion levels, includes:
(1) the radiological monitoring equipment
. described above in V 22 and listed in Exhibit "C".
(2) the RRIS, described above in 1 21.
(3) a permanent, fully equipped analytical-laboratory, located in the EOF, which is a backup facility-to the laboratories located on-site, including the hot chemistry lab cr.d-the-counting room.
The EOF lab has the j I
.J capability to support radiochemistry analysis and the evaluation of radiological-l l
samples.
EOF laboratory equipment and analytical capabilities include (i) gamma spectroscopy equipment which will provide the capability for manual or machine-assisted radioisotopic identication and quantification of radiological samples; (ii) gas flow proportional counter for alpha and beta counting applications; and (iii)-GM detector and scaler for gross
~
activity evaluation of samples.
(4)- the Process / Effluent Radiation Monitoring System, which monitors, records, alerts and controls the release of radioactive materials.
This system is described in detail in 5 7.3.1.2.1 of the RERP.
(5) a dedicated Health Physics telephone line between the OSC and the TSC to relay in-plant radiological information.
(6) a dedicated Dose Assessment telephone line; between the TSC, the health physics office g
in the plant and the EOF, to be used primarily.to relay information concerning dose assessment activities.
m 4
-v (7) a dedicated Operational Support telephone
'line-connecting the OSC to the control room and the TSC. :The primary purpose ~of this phone will be to obtain personnel' support, such as the formation of emergency teams.
(8) a dedicated Emergency Management telephone line linking the EOF, the TSC and the control room, to be used by emergency management personnel.
(9)- the Health Physics Network, a dedicated phone line between the.Callaway Plant and the NRC Operations Center in Bethesda, Maryland.
Phones are located in the EOF and the TSC, and will be ' activated by.the NRC. ' This phone is-to be used primarily for the transmittal of radiological information.
(10) protective equipment,-including clothing and breathing apparatus.
'(11) personnel monitoring equipment.
-26.
Personnel. assigned responsibilities during an l emergency for radiological. response are members.of~the plant
. staff or UE's corporate. headquarters in St. Louis who have health physics orTnuclear engineering degrees and/or are
. trained-radiation / chemistry technicians.
All of these
. individuals will receive specific training in radiological,
w
j monitoring and analysis as well as other emergency-related subjects, such as the transmission of emergency information and
- instructions.
27.
In conclusion, UE has established a radiological emergency organization which includes extensive radiological monitoring capability and resources.
During a radiological accident at the Callaway Plant, UE's monitoring program will_be an important source of information about radiation releases for federal, state and local agencies and for the public at large.
The redundant monitoring capability of-the State of Missouri will serve as a means for verifying the findings of UE's Field Monitoring Teams.
M Ndal G.
Slaten Subscribed and sworn to before me this 16th day of May, 1983.
M2 NOTARY PUB IC TAhEMissougg Notary Publi b
- v/
.u.Y COMuission EXPlRES APRit 22. 1985 ST. LOUIS COUNW My Commission expires:
4/22/85 2.
EXHIBIT A PROFESSIONAL QUALIFICATIONS & EXPERIENCE t
Neal G. Slaten - Supervising Engineer, Nuclear Environmental 2-Education -
Bachelor of Science, Aerospace Engineering, St. Louis University Master of Science, Nuclear Engineering, University of Missouri - Columbia Related Training Westinghouse International School for Environmental Management Colorado State University, 1973 i
Westinghouse " Head Start" Program, 1973 s
Westinghouse " Head Start" Program Simulator, 1973 1
i AIF Seminar, " Preparing Environmental Technical Specifications for Nuclear Power j
Plants", 1974 l
Course in " Environmental Analysis and l
Environmental Monitoring for Nuclear Power Generation"
]
University of California - Berkeley, 1974 i'
Course in " Environmental Radiation j ~
Surveillance for Nuclear Power" Harvard School of Public Health, 1976 i
AIF Seminar, " Current Issues on Environmental Regulation of Nuclear Power Facilities", 1977 j'
1 Bechtel Auditor Training, 1978 NRC Seminar, Model Radiological Effluent Technical Specifications for Nuclear Power Plants, 1979 i
i
'ASME/EPRI Radwaste Workshop, 1979 AIF Seminar, Standard Emergency Response Plan, 1979 4
NRC Seminar, Emergency Planning, 1980 l
INFO Radiological Protection Seminar, 1982
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Hazardous Waste Management Summer Institute University of Missourl, Columbia, 1982 Seminar on Medical Management of Radiation Injuries, 1982 l
Applied Health Physics Course
' Oak Ridge Associated Universities, 1982 i
EEI Health Physics Committee Representative, 1977 to present Professional - Health Physics Society.
. Societies 1
1972-1978, Engineer.
Responsibilities Experience included Licensing and NSSS design review.
1978-1980,. Nuclear Environmentl Engineer.
Responsibilities. included Radwaste Systems design review, Environmental Assessment and
- monitoring programs,. Environmental Report &
general Licensing.activitier.
1980-Present, Supervising Engineer, Environmental.
Responsibilities include:
directing ~the corporate Environmental and Health Physics Group;-L'icensing support; reviewing radwaste, shielding and radiation monitoring system engineering design work; evaluating off-site radiological and non-radiological environmental monitoring programs; establishing corporate ALARA policy; reviewing conformance to provisions-contained within technical-specifications and applicable license provisions pertaining to radiological matters;
~
providing technical expertise to QA audit teams; reviewiag design modifications to-assure compliance with ALARA philosophy; acting-as Radiological Assessment Coordinator'during a-site or General Emergency at Callaway Plant.
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ON-SITE EMERGENCY ORGANIZATION T.S C.
T.S.C.
EMERGENCY COOROMATOR
@TE STATUS SOARO LIAsSON LOG KEEPER COOROMATOR s
i I
i I
g HEALTH TECHNICAL COMM*CATRONS ADMet PHYSICS ASSESSMENT CNM COOROMATOR COOROINATOR COOROMATOR
^
STATUS SOARO T.S.C.
SUPPORT g
LOG MEEPER COMM*CATORS pgggg I
I OOSE T.S.C.
SECURITY MAINTENANCE ASSESSMENT ENO4NEERMG COOROMAM COOROMATOR COOROMATOR STAFF i
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g T.S C.
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ST ATUS SOARD CONTRM ROCM LOG KEEPER OPERA TIONAL RAD CON SUPPORT CA/TSC CENTER COORONATOR LIAISON COORMAM FIELO TE AM COMM'C A T OR 4
OPERATIONS
]
R AD/CHE M ggmy T S C-SUPPORT STA.
TECHS SUPERVISOR trj ON-SITE OFF-SITE PERSONEL N
4 y
P-SECMITY WO l
EMERGENCY OPERATWG MONSTORING (f
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SHIF T -
TEAMS SUPERVISOR SUPERvtSOR TEAMS (D
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8 SECURITY ROOM
- 1 j
{0RCE PERSONEL
'i j
D IGUR E S - 5 Rev.SA 0
2#83
--- -__ _ ___________________ _j
PORTABLE SURVEY INSTRUMENTS TABLE E-1 MANUFACTURER /MODEL RADIATION TYPE (OR EOUIVALENT)
DETECTED RANGE SCALES DETECTOR TYPE POWER SUPPLY REMARKS Alpha-i
.Ludlum Model 3 Alpha 0-5E5 CPM 0-500 cm ens 2 D-Cell Built in Survey Rate Meter Particles 0-5K CPM Scintillation Batteries Speaker for Meter:
w/ 4?-5 Probe 0-50K CPM Probe Audible 0-500K CPM R*8Ponse Portable Ludlum Model 3
- Beta, 0-5E5 CPM 0-500 CPM GM 2 D-Cell Same Frisker Gamma 0-5K CPM Pancake Batteries 0-50K CPM 0-500K CPM Control Ludlum Model 177
- Beta, 0-5E5 cm 0-500 CRt GM AC Line or Adjustable Point Gamma 0-5K CPM Pancake Gel-Cel Audible Frisker 0-50K CPM Battery Pack Alarm 0-500K CPM Low Ludlum Model 14C
- Beta, 0-2000 MR/hr 0.2 MR/hr Thin Wall 2 D-Cell Built in Range Gamma 0-2 MR/hr GM W/
Batteries Speaker for Survey 0-20 MR/hr Beta Shield Audible
+
Meter '
0-200 MR/hr Responsa j
0-2000 MR/hr High Eberline Model
- Beta, 0-1000 R/hr
' 0-2 MR/hr Dual GM 4 C-Cell Extendable Range 6112 Teletector Gas =ma 0-50 MR/hr Tubes Batteries Probe l
Survey 0-2 R/hr Resists Sat-Meter 0-50 R/hr uration in h
0-1000 R/hr
- Fields up to d
- 3E4 R/M 1
fEquippedw/
Survey l Eberline RO-2
- Beta, 0-5 R/hr
- O-5 MR/hr Ionizp tio'n 3 9-Volt Gamma 0-50 MR/hr Chamber Batteries gSliding Beta Instrument 1
0-500 MR/hr 4 Window l
0-5000 MR/hr j
b tn X
D" P-tT H.
O E-?
Rev. 5 m
PORTA' TIE SURVEY INSTILMENT3 (COelTINUbO) 1 TA?I2 E-1 MANUFACTURER /MODEL RADIATION TYPE (OR EOUIVALEnrF)
DETECTED RANGE SCALES DETECTOR TYPE POWER SUFFLY REMARKS
.. Neutron Eberline Model
. Neutron 0-10 Rem /Hr.
MR/hr BF Tube Gell Cell Digital Dis-Survey PRS-2P Rascal CPM Enclosed in Battery Plays Func-Meter w/ " Rem ball" Counts Polyethlene Pack or 5
'tions as rate-CPS Sphere D-Cell meter, Scalor Batteries.
and Dose Equiv-alent mate Meter Discri-minates Against Gamma t
Portable Eberline RM-16
- Beta, 0-200 MR/hr MR/hr GM Tube AC Line or Adjustable l
Area Gamuna 0-1E4 Mrem /hr or or SF Trickle
. Audible l
Radiation and (Neutron)
Mrem /hr Sphere Charge Alarm (Neutron)
Battery Monitor.
I Neutron I
t
[
Portable.
Nuclear Data Gamma 0-999,999 N/A NaI AC Line 256 Data Gamuna
- ND 6 Counts Cryetal or Chanr.els:
l Battery MDk<10E-7 S~pectrometer Pack uci/cc I-131 1'
Survey-Eberline Model
- Beta, 0-1000 R/M 0-1000 MR/hr Gas Filled 2 9-Volt Equipped w/
In st rtunent PIC-6A Gamma 0-1000 R/hr Ionization Batteries Sliding Beta Chamber Nipdow i
p t
f i
Rev. 5 F-3 4
0/82 4
s.
t
)
J RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR THE CALLAWAY PLANT UNIT 1 ll' l
ANALYSIS i OF TOTAL i j
b 4 AMPLE' I
~
ANALYSIS FREQUENCY LOCATIONS
-ANALYSIS j
1
- 1. Air.
. Gross Beta-Weekly 14 728 Pcrticulate Gamma Spectrometry Quarterly-Composite 14 56
}
l SR-89, -90 Quarterly-Composite 14 56 i
2> AirT odine
--I-131 ~ -
Weekly 7
364 I
. 3.' _ TLD Gamma Dose Monthly' 52 624 52 52 Annually
?4. Soil' Gamma Spectrometry
- Annually, 4
4 Gross Alpha Annually 4
4 Gross Beta Annually 4
4
- 5. Vcgetation.
Gamma Spectrometry Annually.
4 12 Gross Alpha Annually 4
12 Gross gyta Annually 4
12 I-131
- 6. Milk I-131 Semi-Monthly (6 mo.)
4 72 Ga g Spectrometry Monthly (6 mo.)
4 72 4
72 Ca Sr-89, -90(2) 4 72 7.1 Surface
. Gamma Spectrometry Monthly 3
36 Water Gross Alpha Monthly 3
36 Gross Beta Monthly 3
36 M
5 i
Tritium-Monthly 3
36
'Sr-89, -90 Monthly 3
36 8.. Ground &
Gamma Spectrometry Monthly 3
36 U
Drinking Gross Alpha Monthly 3
36 Water Gross Beta Monthly 3
36 Tritium Monthly 3
36 i
St-89, -90 Monthly 3
36
"s 5
ANALYSIS i OF TOTAL 9
>4 LOCATIONS ANALYSIS L
SAMPLE ANALYSIS-FREQUENCY 9.' B0ttom-Gamma Spectrometry
. Monthly 3
36 S:diment Gross Alpha Monthly.
3-36 Gross Beta Monthly 3
36 Sr-89, -90 Monthly 3
36 LO..Baseload
. Gamma Spectrometry Monthly 3
36 S:diment.
Gross. Alpha Monthly 3
36 Gross Beta Monthly 3
. 3 16 Sr-89, -90.
Monthly 3
36 36 Ll. Washload Gamma 3 Spectrometry'.. Mon th ly 3
Stdiment Gross Alpha' Monthly 3
36 Gross Beta Monthly 3
36 Sr-89, -90
. Monthly' 3
36 L2. Fish
- Gamma' Spectrometry Monthly 3
180 Gross Alpha Monthly 3
180 Gross Beta Monthly 3
180
-Sr-89, -90 Monthly 3
180 Q.