ML022960358
| ML022960358 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/10/2002 |
| From: | Forbes J Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022960358 (31) | |
Text
Nucl Committed to Nuclear Excellence Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC October 10, 2002 10 CFR 50, Appendix E Section V US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Emergency Plan Implementing Procedures Furnished with this letter is a revision to the Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures. The following procedures are revised:
Procedure Procedure Title Revision A.2-INDEX A.2 Emergency Plan Implementing Procedure Index 78 A.2-41 0 Out-of-Plant Surveys 12 Please post changes in your copy of the Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures. Superseded procedures should be destroyed. This revision does not reduce the effectiveness of the Monticello Nuclear Generating Plant Emergency Plan.
Please contact Douglas A. Neve, Licensing Manager, at 763-295-1353 if you require further information.
Jeffr ySFos Site Vice President Monticello Nuclear Generating Plant c: Regional Administrator - Ill, NRC (wI two copies of enclosure)
NRR Project Manager, NRC (w/o enclosure)
Resident Inspector, NRC (w/o enclosure, EPIP dist. by Monticello Document Control)
Minnesota Dept. of Commerce (w/o enclosure)
J %ICENSE\NRC Misc Correspondence\Emergency Plan\EPIP1O-10-02 EPIP letter doc 2807 West County Road 75
- Monticello, Minnesota 55362-9637 WcC5 Telephone. 763.295.5151 e Fax: 763 295.1454
MONTICELLO NUCLEAR GENERATING PLANT A.2-INDEX TITLE: A.2 EMERGENCY PLAN IMPLEMENTING : Revision 78 PROCEDURES INDEX Page1 of 4 p* :REVI,*w D APPROVALS Prepared By: ,
Approved By: Date: /"0 Assoc Ref: A.2 Dn N Freq: 0 rs Rlesp Sumv: EP ARMS: A 2-INDEX IDocType: 1060 -- Admin Initials: Date: 1b, 0 1ur-PROCEDURE PROCEDURE TITLE 000 Series Organization A.2-001 Emergency Organization 100 Series Activation A.2-1 01 Classification of Emergencies, A.2-102 Notification of an Unusual Event A.2-103 Alert A.2-104 Site Area Emergency A.2-1 05 General Emergency
< A.2-106 Activation and Operation of Technical Support Center A.2-107 Activation and Operation of Operations Support Center A.2-1 08 Access Control During Emergencies A.2-109 Activation and Operation of the Backup OSC A.2-110 Response to a Security Threat 200 Series Assessment A.2-201 On-Site Protective Action A.2-202 Off-Site Monitoring During an Emergency A.2-203 ,Radioactive Liquid Releases A.2-204 Off-Site Protective Action Recommendations A.2-205 Personnel Accountability A.2-206 Work Control During Emergencies A.2-207 Deleted 05/01/91 A.2-208 Core Damage Assessment A.2-209 Responsibilities of Radiological Emergency Coordinator A.2-21 0 - Engineering Support in the TSC ,
I/cjt
MONTICELLO NUCLEAR GENERATING PLANT "A.2-INDEX TITLE: A.2 EMERGENCY PLAN IMPLEMENTING Revision 78 Page 2 of 4 I _PROCEDURES INDEX 200 Series Assessment (Cont'd)
A.2-211 Intentionally Blank A.2-212 Intentionally Blank A.2-213 Responsibilities of the Emergency Director 300 Series Protective Actions A.2-301 Emergency Evacuation A.2-302 Activataion of the Assembly Points A.2-303 Search and Rescue A.2-304 Thyroid Prophylaxis (Potassium Iodide use) 400 Series Radiological Surveillance and Control A.2-401 Emergency Exposure Control A.2-402 On-Site Radiological Monitoring A.2-403 Deleted 04/14/94 A.2-404 Emergency Air Sampling and Analysis A.2-405 Release Rate Determination A.2-406 Off-Site Dose Projection A.2-407 Personnel and Vehicle Monitoring and Decontamination A.2-408 Sample Coordination During Emergencies A.2-409 Self-Contained Breathing Apparatus (SCBA) Use During An Emergency A.2-410 Out-of-Plant Surveys A.2-411 Establishment of Secondary Access Control A.2-412 Reactor Coolant Sample Obtained From Reactor Sample Station A.2-413 Small Volume Liquid Sample Obtained at the Post Accident Sampling System A.2-414 Large Volume Liquid Sample and/or Dissolved Gas Sample Obtained at Post Accident Sampling System A.2-415 Containment Gas Sample Obtained at Post Accident Sampling System A.2-416 Deleted 10/31/89 A.2-417 Draining the Trap, Sump and Collector of Post Accident Sampling System A.2-418 Post Accident Sampling Station Dernin Water Tank Fill Procedure I/cjt
"7 A.2-INDEX MONTICELLO NUCLEAR GENERATING PLANT A.2 EMERGENCY PLAN IMPLEMENTING -Revision-78 TITLE:'
Page 3 of 4 PROCEDURES INDEX-400 Series Radiological Surveillance and Control (Cont'd), - - .
A.2-419 Containment Atmosphere Sample Obtained From.
Reactor Sample Station A.2-420 Containment Atmosphere Radiochemical Analysis A.2-421 Deleted 10/31/89 A.2-422 Stack Iodine/Particulate Sampling &Analysis A.2-423 Reactor Building Vents Iodine/Particulate Sampling and Analysis A.2-424 EOF Count Room Counting Procedure' A.2-425 Deleted 03/26/92, 500 Series Communications and Documentation A.2-501 Communications During an Emergency A.2-502 Recordkeeping During an Emergency A.2-503 Deleted 04/28/83 K>J A.2-504 Emergency Communicator Duties in the TSC and OSC 600 Series Re-Entry and Recovery A.2-601 Re-Entry A.2-602 Event Termination or Recovery ,
A.2-603 Deleted 05/19/83 700 Series A.2-701 PANS System 'False Alarm Activation or Failure A.2-702 Response to an Emergency at Prairie Island A.2-703 Response to Off-Site Situations Involving Radioactive Material EOF Procedures 800 Series A.2-801 Responsibilities of the Emergency Manager A.2-802 Activation and Operation of the EOF A.2-803 Emergency-Communications at the EOF A.2-804 EOF Support and Logistics k*-> A.2-805 Technical Support in the EOF A.2-806 Radiation Protection Support in the EOF I/cjt
MONTICELLO NUCLEAR GENERATING PLANT A.2-INDEX TITLE: A.2 EMERGENCY PLAN IMPLEMENTING Revision 78 E PROCEDURES INDEX Page 4 of 4 800 Series EOF Procedures (Con't)
A.2-807 Off-Site Dose Assessment and Protective Action Recommendations A.2-808 Radiological Monitoring and Control at the EOF A.2-809 EOF Security A.2-810 Transfer to the Backup EOF A.2-811 Event Termination or Recovery in the EOF A.2-812 Off-Site Agency Liaison at the EOF I/cjt
MONTICELLO NUCLEAR GENERATING PLANT A.2-41 0 TITLE: OUT-OF-PLANT SURVEYS - - Revision 12 Page 1 of 26 EMERGENCY PLAN IMPLEMENTING PROCEDURE- TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ............................................. .... 2 2.0. APPLICABILITY . .... ; ....... ....... 2 3.0 ORGANIZATION AND RESPONSIBILITIES .................... 2 4.0 DISCUSSIO N ...................................................... 3 5.0 PRECAUTIONS ........-.............. ........... . 3 6.0 INSTRUCTIONS .... :.. .............. .............................. 6.
6.1 - Field Team Activation ........ .. .............. ......... 6 6.2 Plume Search Procedure.. ............................. 8 6.3 Particulate and Iodine Air Sampling ............................. 9 6.4 Gaseous Air Sampling .......... ..... I .................. 11 6.5 Stationary Dose Rate Survey ......... ...... ...... .12 6.6 Liquid Sampling ..................................... 13 6.7 Discharge Canal Sampling (Monticello Only)....................... 14 6.8 Ground Deposition - Direct Frisk Survey ........................ .15 6.9 Ground Deposition --Smear Samples ....................... 15 6.10 Ground Deposition - Gamma Dose Rate Survey ................. 16 1-6.11 --Ground Deposition Sampl6s -'Snow/Dirt Survey .................. 16 6.12 Ground Deposition -Vegetation/Food Sampling .................. 17 6.13 Off-Site Sample Courier Instructions ............................ 18 6.14 Prairie Island Off-Site Field Team Driver Instructions ............. 20 7.0 FIG U RES ......................................................... 21 7.1 -Gross Iodine Activity Table o............ .... ......... 21 7.2 Gas Chamber Table .................................. 22 7.3 Gross Liquid Activity Table ............. ................. 23 7.4 Gross Particulate Activity Table,.........'.................. 24 7.5 On-Site Liquid Sample Locations. ............. .......... 25 7.6 Forms Utilized in this Procedure ................................ 26
- The following Instruction sections begin with a new page for ease of use in the field: 6.2, 6.3, 6.4, 6.5, 6.6, 6.7, 6.8, 6.13, & 6.14.
C>11I Prepared By: - ' .- Reviewed By:
OC Review Req'd: YES 00 Meeting Number: Dl3eF Approved By: , Date:
-:runADMINISTRATIVE 'USE ()
Iis revision incorporates Volume F Memos:_ _ _ _ _ _ ___ _
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated- (12- /1/,61 I Resp"upv:
ARMS*
A EP 1oAssoc A.2-410 _ _FD~ocType: 1060 Ref: A:2 lAdmin Initials: ls:
-I N
.Date:/i r:/
i")/.
'Mae I I/mab
I MONTICELLO NUCLEAR GENERATING PLANT A.2-41 0*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 2 of 26 1.0 PURPOSE This procedure provides instructions for the activation of Off-site Radiological Monitoring Teams (Field Teams) and the various methods of radiological and environmental monitoring during a declared Emergency at either the Monticello or Prairie Island plants.
2.0 APPLICABILITY 2.1 Abnormal conditions exist which involve an airborne or liquid radiological release to the Monticello plant environs and out-of-plant surveys have been requested.
2.2 An emergency (Alert or higher classification), has been declared at the Prairie Island Nuclear Generating Plant and Monticello's assistance has been requested.
3.0 ORGANIZATION AND RESPONSIBILITIES ,
3.1 The Radiological Emergency Coordinator (REC) is responsible for:
3.1.1 Overall direction and control of the Field Teams until these responsibilities are assumed by the Emergency Operations Facility (EOF).
3.2 The Radiation Protection Support Supervisor (RPSS) is responsible for:
3.2.1 Overall direction and control of the Field Teams after these responsibilities are transferred from the Technical Support Center (TSC).
3.3 The Field Team Communicator(s) are responsible for:
3.3.1 Coordination of the Field Teams via radio communication from the TSC or EOF.
3.4 The Field Teams (each team consists of one Radiation Protection Specialist and one Nuclear Plant Helper) are responsible for:
3.4.1 Implementation of this procedure.
3.4.2 Maintaining a constant communication link with the Field Team Communicator in the TSC or EOF.
3.4.3 Performing surveys in accordance with applicable instructions contained in this procedure and as directed by the Field Team Communicator.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-41]0 TITLE: OUT-OF-PLANT SURVEYS Revision 12 L OPage 3 of 26 3.5 The Sample Courier(s) are responsible for:
3.5.1 Transportation .of samples (taken by the Field Teams) to the EOF.
4.0 DISCUSSION " "
Off-site surveys during an emergency are normally performed by sister plant Radiation Protection personnel when the EOF is fully activated. Prior to this, off-site surveys must be performed by the affected plant's Radiation Protection personnel.
Surveys of on-site, out-of-plant areas are always assigned to the affected plant's Radiation Protection pe-rsQnnel..
During the initial stage of an emergency, the number of personnel available to perform surveys may be limited. The REC will make decisions on deployment of personnel resourdes. -Whenthe RPSS position is staffed and the EOF is fully operational, cbntebl'of'the Field Teams will be transferred to the RPSS.
There are normally two Vehicles designated'for off-site monitoring purposes. The Radiation Protection Coordinatoi and Security maintain control of the keys (24 or 25) for these vehicles.
- The EOF Count Roorfii~'the prim.ry bff-site facility for the receipt and analysis of radioactive' samples. -The EOF Count Room is staffed byChemistry personnel from the affected plant who*are familiar-with its equipment and operation. Unless circumstances dictateotherwise, the EOF Count Room will be used for most samples taken pursuant to this procedure.
5.0 PRECAUTIONS-. - - -:.
5.1 ' Monitoring and sampling instruments SHALL be operated in accordance with standard procedures for each instriument type.
5.2 During off-hours activations, Field Team personnel should verify their
-- - fitness-for-duty (FFD) with appropriate supervisory personnel (F/T
" communicator) prior to engaging in activities Which directly affect the Health and Safety of-the public (e.g. off-site' surveys to validate MIDAS projections).
This confirmation may be conducted via radio (or telephone) and need not occur in person.
5.3 Minnesota has severe weathr c6rditions which can seriously affect instrument operation. The following guidelines have been established to eliminate or minimize cold weather instrument problems:
5.3.1 Allow approximately 5 minutes for the instrument to warm up completely.
5.3.2 Ifthe outside temperature is greater than 32 0 F(0°C), instrument use is.
not restricted by temperature.
5.3.3 Ifthe outside temperature is between 32 0 F (00C) and 0°F (-18°C), use the instrument outside no more'than 5 (five) minutes.
i/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 1 Page 4 of 26 5.3.4 Ifthe outside temperature is between 00 F (-18oC) and -20°F (-28°C),
use the instrument outside no more than 2 (two) minutes.
5.3.5 Ifthe outside temperature is below -20°F (-28°C), the instrument should not be used outside unless special batteries (alkaline or Ni-Cd) are installed in the instrument. These batteries increase the minimum temperature range to -40°F (-40°C) but allows less than 30 seconds of use in this type of environment.
5.4 Ifan instrument malfunctions or "pegs out" during survey operations, immediately exit the area by the same route used to enter, and obtain a new instrument if necessary.
5.5 During radio and cellular phone communications, observe the following precautions:
5.5.1 Since radio and cellular phone communications can be intercepted by commercially available scanners, all,,communications must be brief, factual and free of all exclamatory or alarming expressions.
5.5.2 Carefully word data transmission to minimize confusion, in particular, avoid abbreviations such as "mrem" which could be misinterpreted as "rem".
5.5.3 Use the phonetic alphabet when communicating sample points location, etc., as follows:
A ALPHA J JULIET S SIERRA B BRAVO K KILO T TANGO C CHARLIE L LIMA U UNIFORM D DELTA M MIKE V VICTOR E ECHO N NOVEMBERW WHISKEY F FOXTROT O OSCAR X X-RAY G GOLF P PAPA Y YANKEE H HOTEL Q QUEBEC Z ZULU I INDIA R ROMEO I/mab
MONTICELLO NUCLEAR GENERATING PLANT . A.2-410*"
TITLE: OUT-OF-PLANT SURVEYS Revision 12 I Page 5 of 26 5.5.4 Preface each communication with the title or name of the receiving party and your title and name. For example: "Monticello TSC";
Monticello Field Team 1.."
After the communication is completed; request the receiving party to repeat the'message, if-numerical data was relayed.
End message transmission with an appropriate termination phrase.
For example: "Monticello Field Team 1, out." During drills always include-The words, HIS IS A DRILL," with each transmission.
5.6 Observe respiratory protection and exposure precautions at all times while performing off-site monitoring. Ifsubstantial airborne activity or contamination "issuspected,-don appropriate protective clothing as directed by the REC (or RPSS) lAW the following guidelines:
5.6.1 LField-,Team-members should don respirators with GMR canisters if the
. -: following,-conditions occur:
A. A General Emergency is declared and the affected sectors have been evacuated; and B. Measured dose rates are more than 100 mrem/hr true Beta.
5.6.2 '-Respiratory equipment may be removed if the following is indicated:
A. Field measurements of gross iodine activity indicates less than 1E-7 [tCi/CC; or -
B. The REC/RPSS in-dicates that no significant iodine is or has been
"- released from the'plant; and
-: C. Measured dose rates are less than 100 mrem/hr true Beta.
5.7 Exposures-bf.ýurxeytearni 1elrsbnnel SHALL be lAW administrative control
-levels. All Field Team members and Sample Couriers SHALL have proper dosimetry, which is frequently checked. -They, SHALL remain alert to their own exposure and request relief if cumulative exposure approaches administrative control levels. ,The Emergency Director may authorize exposure limit "extensions'ifnecessary (refer to A:.2401)., All exposures SHALL be maintained AS LOW AS REASONABLY ACHIEVABLE aided by the following guidelines: ,
""5.7.1 Field Teams should n6t linger in areas greater than 100 mr/hr.
5.7.2 Field Teams should not proceed to areas projected to be greater than 1000 mr/hr unless directed by the REC or RPSS. ., : ,
5.7.3 Field Teams SHALL NOT proceed to areas projected to exceed 10,000 mr/hr. - - - ,
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-41 0*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 6 of 26 5.8 During off-site monitoring operations, vehicles and/or survey instruments could become highly contaminated and plume, ground contamination or background radiation conditions may be encountered which could interfere with sample analysis or survey results. Remain alert to these conditions and take appropriate precautions to ensure accurate sample/survey results (i.e., move away from vehicle to analyze samples, prevent instrument contamination by bagging instrument, prevent sample from cross-contamination, etc.).
6.0 INSTRUCTIONS 6.1 Field Team Activation 6.1.1 If respondin9 to a MNGP event, refer to the OSC tagboard to determine Field Team assignment. S t 6.1.2 Obtain Emergency vehicle keys. (From the Radiation Protection Controlled Key Cabinet or Security Key Cabinet.) If necessary obtain a dose rate meter for use enroute to the EVES Building.
6.1.3 Log in on RWP 902. If responding-to an event at MNGP, then retain your personal dosimetry (TLD, and electronic dosimeter) from the plant when exiting. If responding to an event at Prairie Island or circumstances prevent use of normal plant dosimetry, then obtain dosimetry from the Emergency Kits in the EVES building.
6.1.4 At the EVES Building initiate Form 5790-410-02 (OUT-OF-PLANT SURVEY CHECKLIST).
6.1.5 Obtain one (1) Instrument Kit (aluminum case) and one (1) Equipment Kit (grey case) from the storage area in the EVES Building.
NOTE: Emergency Instrument and Equipment Kits may be stored in the vehicles.
6.1.6 Ensure that each member of the monitoring team has dosimetry (one TLD and either an electronic dosimeter, or a 0-200 mR DRD and a 0-5000 mR DRD).
6.1.7 Record the applicable dosimetry information for each member of the team on Form 5790-410-02.
6.1.8 Obtain a count rate meter with 2" pancake probe and dose rate meter J from the cabinet and perform the applicable operability and source checks. Leave the instruments on.
NOTE: A "check source" is provided in the EVES Building for this purpose.
6.1.9 Obtain one (1) cellular phone and one (1) cellular phone adapter unit from the EVES Building and install in vehicle.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT -A.2-410*
TITLE: OUT-OF-PLANT SURVEYS .Revision 12 Page 7 of 26 6.1.10 Perform an operability check of the mobile radios by establishing contact with the TSC or EOF (when staffed). Obtain a phone number in the area (TSC or EOF) to call. Perform an operability check of the
-cellular phone by calling the number obtained.
NOTE: Instructions for using the cellular phones are located in each vehicle.
6.1.11 For emergency events at the Monticello plant, contact the Field Team Communicator (TSC/EOF). When ready to depart, obtain updated information pertaining to the event and wait for further instructions.
6.1.12 If responding to a PI event, refer to Section 6.3 of EPIP A.2-702 (RESPONSE TO ANEMERGENCY AT PRAIRIE ISLAND) for travel
'routes arid instructions for response to the Prairie Island EOF.
6.1.13 .When departing the plant site area (or entering PI 10 mile EPZ), initiate
""-I* 'esearh(ifapplicable) lAW Section 6.2 of this procedure.
6.1.14 Document all survey/sample data on Form 5790-410-01 (EMERGENCY SAMPLE RESULTS LOG) or Form 5790-410-03 (GROUNDIDEPOSITION SAMPLE RESULTS LOG) as applicable.
6.1.15 Repoh ail survey/sample results to the Field Team Communicator.
6.1.16 Forward samples Which require further analysis (as directed by the Field Team.Communicator) to the EOF Count Room via sample courier or retain the' samjoles for future analysis and/or disposal as directed.
6.1.17 When directed, return to the EOF f.or'debriefing and reassignment.
Complete and submit all samlple result logs and Form 5790-410-02 to the RPSS for review.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-41 0*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 8 of 26 6.2 Plume Search Procedure 6.2.1 With the count rate meter on the lowest scale (on which meter I deflection can be observed) place the probe on the dashboard facing the windshield and observe the instrument for meter deflection while in I
transit.
6.2.2 Ifa meter deflection is observed, stop the vehicle and perform a dose rate survey in accordance with Section 6.5 NOTE: A BETA reading indicates that the plume has been encountered. A GAMMA reading with zero BETA indicates the plume is e!evated or displaced.
6.2.3 Report the survey results to the Field Team Communicator as recorded I on Form 5790-410-01. I NOTE: If the survey location is NOT at a predesignated survey point, identify the location using known landmarks or road intersections, etc.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 9 of 26 6.3 Particulate and Iodine Air Sampling 6.3.1 Install a particulate filter and a Silver Zeolite cartridge into the air sampler cartridge/filter holder.
6.3.2-- Connect the air sampler to-the vehicle power supply and start the air sampler.
NOTE 1: Engine should be'running to mairitain a steady battery voltage.
NOTE 2: If precipitation is occurring, the'sample should be drawn from a covered area. The umbrellainicluded in'the Emergency Kit may be used for this purpose.
6.3.3 Record the sample START TIME, SURVEY POINT (sample location),
sample FLOW RATE and SURVEY TYPE on Form 5790-410-01.
6.3.4 '-WhenithJdbsired sample time has lapsedi stop the air sampler and record the sample STOP TIME.
NOTE: Whenever possible air samples should be a standard 25 cu. ft. sample (i.e. 7.07 SE+5 CCs or approximately 10 minute sample run time).
6.3.5 Calculate and record the sample volume in cubic centimeters (cc) using the following formula:
Sample Volume in CCs = (Flow Rate in CFM) x (Sample Time in Minutes) x (2.83 E+4 CCs/ft3 ).
6.3.6 Remove the particulate filter and the Silver Zeolite cartridge from the filter cartridge holder, place them in SEPARATE plastic sample bags and seal the bags.
6.3.7 Complete a pre-printed sample label including the sample time and date, sample location, sample volume and the contact dose rate and attach a label to each sample bag.
6.3.8 In a low background area (i.e. < 1000 CPM) determine the gross activity of each sample by using the following methods:
A. Particulate Activity
- 1. Count the particulate filter using a count rate meter with a 2" pancake probe. Subtract the background to determine the Net CPM of the sample.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 10 of 26
- 2. Calculate the gross particulate activity of the sample using the Gross Particulate Activity Table (FIGURE 7.4) or the following formula:
ACTIVITY ([tCi/CC) = {NET CPM)__( 4.5 E-7 gCi/DPM)
(PROBE EFFICIENCY) x (SX VOLUME in CCs) x (CF)
NOTE 1: Probe Efficiency = 0.1 (10%) for Count Rate Meter with a 2" pancake probe.
NOTE 2: Correction Factor (CF) = 0.3 for 4" filter paper counted with a 2" pancake probe or 1.0 for 2" filter paper counted with a 2" pancake probe.
B. Iodine Activity
- 1. Count the Silver Zeolite cartridge using a count rate meter with a 2" pancake probe. Subtract the background to determine the Net CPM of the sample.
- 2. Calculate the sample activity using the Gross Iodine Activity Table (FIGURE 7.1) and the following formula:
IODINE ACTIVITY ([tCi/CC) = (LCi(s) oncartridge determined by Table)
(SX volume in CCs) 6.3.9 Record the results on Form 5790-410-01.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT, A.2-410*
TITLE:- OUT-OF-PLANT SURVEYS F Revision 12 Page 11 of 26 6.4 Gaseous Air Sampling.
If hands are contaminated, handle chamber with clean surgeon gloves. - F "6.4.1 Obtain the gas' sampling chamber, 'suction b~ulb and filter assembly
-- from the Emergency Kit.
6.4.2 Install new
' filter in the filter holder assembly.
6.4.3 .Connect the suction bulb,' sample chamber and filter assembly such that air passes through the filter assembly into the sample chamber then to.the suction bulb.
6.4.4 Open the stop cocks on the gas sample chamber, squeeze the suction bulb ten,(1 0) times to obtain a representative sample, then shut the stop cocks on the gas sampling chamber.
"6:4.5 Record the SAMPLE TIME, SURVEY POINT, (sample location) and
-,SAMPLE TYPE on Form 5790-410-01..
6.4.6 In a low. background area (i.e., <1 000 cPM) determine the activity of the gas sample (10Ci/CC of Xe 133 equivalent) using the following
...method:
"A. Count the gas sample chamber using a count rate meter with a 2" pancake probe by placing the probe on the chamber over the mylar window. Record the results as GROSS CPM on Form 5790-410-01; B. Obtain a second "empty" gas sample chamber from the Emergency Kit and count the "empty" chamber using a count rate meter with a 2" pancake probe by placing the probe on the chamber over the mylar window. Record the result as the BACKGROUND CPM in Form 5790-410-01; C. Calculate the NET CPM.
D. Determine the gas sample activity by using the NET CPM and the Gas Chamber Table (FIGURE 7.2).
6.4.7 Record the sample results on Form 5790-410-01.
6.4.8 Complete a pre-printed sample label with all applicable sample data.
Place the sample in a plastic sample bag, seal the bag and attach the label to the bag.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 12 of 26 6.5 Stationary Dose Rate Survey 6.5.1 Energize the instrument and allow the instrument to stabilize (approximately 30 seconds) then re-zero the meter.
6.5.2 Perform a BETA/GAMMA survey of the area as follows:
A. With the window open, hold the instrument approximately one (1) meter from ground level and survey the area for the maximum meter deflection; B. Record the "WINDOW OPEN" (BETA/GAMMA) reading.
C. Close the instrument window and obtain the GAMMA reading; D. Record the 'WINDOW CLOSED' (GAMMA) reading.
E. Calculate the "TRUE BETA" roading as follows:
TRUE BETA = (WINDOW OPEN - WINDOW CLOSED)
X (BETA CORRECTION FACTOR)
NOTE: Assume a BETA CORRECTION FACTOR of 5.0 if the BETA CORRECTION FACTOR for the instrument is unknown.
F. Record the TRUE BETA results on Form 5790-410-01.
NOTE: If the survey location is NOT a predesignated survey point, identify the location using known landmarks or road Intersections, etc.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-41 0*
TITLE:- OUT-OF-PLANT SURVEYS Revision 12
-I Page 13 of 26 6.6 Liquid Sampling
'6.6.1- Obtain a 1, liter sample bottle and install the bottle in the holder.
NOTE: An additional supply of sample bottles are available at the EOF.
6.6.2 Use the appropriate' radiological precautions when handling pot7eritially radioactivesamples.
Casto r lower the'bottle into the water to be sampled, allow the bottle "tofill completely then withdraw and cap the bottle.
6.6.3 Bag the sample bottle, complete a pre-printed label. Attach the label tb the-sarbple bottle, label and seal the plastic bag.
6.6.4 Record&Thl sampleTIME, SURVEY, POINT (sample location) and SURVEY TYPE on Form 5790-410-01.
6.6.5 In a loW background'area (i.e., <1000 CPM) determine the gross activity of the sample'using the followirg' method:
A. CoUnt the samnpie using a count'rate meter with a 2" pancake probe by placing the probe on the sample as indicated on the
'Gross Liquid-Activity Table (FIGURE,7.3). Subtract the background todetermine the Net'CPM of the sample.
B. Record the background, and Net CPM on Form 5790-410-01 (EMERGENCY SAMPLE RESULTS LOG);
C. Determine the activity of the sample using the Gross Liquid
,Activity Table (FIGURE 7.3) and the NET CPM of the sample.
6.6.6 Record the sample results on Form 5790-410-01.
I/mab
TITLE: IOUT-OF-PLANT SURVEIYS ... Revision 12 iMONTICELLO"NUCLEAR-GENERATIN-G"PL[ANT"'*"..... ... A.2"410 I*
I. ... . .....
. . . . . . ... .. .... . .. ., ... ... P a ge 14 of 2 6 6.7 Discharge Canal Sampling (Monticello Onlvn 6.7.1 Obtain 1 liter sample bottles from an Emergency Kit or from the Chemistry lab.
6.7.2 Obtain the keys for one of the Plant vehicles (ifneeded) and a hand held radio. (Radios are available in the TSC and OSC. Use talk group 2A unless directed otherwise.)
6.7.3 Proceed to the Discharge Canal Sample Station (DCSS) located on the south bank of the discharge canal approximately 550' downstream of the discharge structure. (FIGURE 7.5) Sample point (3) of on-site liquid sample locations map.
6.7.4 In the DCSS Building locate pumps P-11 2A and P-11 2B. Verify the sample flow into the drain trough down stream of CW-27 is at least 10 GPM as indicated by reading flow indicator FIS-1 905 centered above pumps P-11 2A and P-1 12B. -
6.7.5 Using a 1 liter bottle, take the desired sample(s) from the 1.5 inch line dumping water into the trough.
6.7.6 Bag the sample bottle, complete a pre-printed sample label, attach the label to the sample bottle, label and seal the plastic bag.
6.7.7 Record the sample TIME, SAMPLE POINT (sample location) and SURVEY TYPE on Form 5790-410-01.
6.7.8 Determine the gross activity of the sample using the following method:
A. Count the sample using a count rate meter with a 2" pancake probe by placing the probe on the sample as indicated in Gross Liquid Activity Table (FIGURE 7.3). Subtract the background to determine the Net CPM of the sample.
B. Record the background and Net CPM on Form 5790-410-01; C. Determine the activity of the sample using the Gross Liquid Activity Table (FIGURE 7.3) and the Net CPM of the sample.
6.7.9 Record sample results on the Form 5790-410-01.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410" TITLE: OUT-OF-PLANT SURVEYS 2 Revision 12 Page 15 of 26 6.8 Ground Deposition - Direct Frisk Survey.
6.8.1 Obtain a count'rate meter with a 2" pancake probe or equivalent.
6.8.2 Proceed to the designated survey point and carefully scan flat surfaces in the area.(e.g., roads, lawns, mailboxes, vehicles, fields, etc.).
6.8.3 Record the sa mple TIME and SURVEY POINT (sample'10cation) on Form 5790-410-03.
6.8.4 '-Calculate-tlegrouhddeposition activity as follows:
[tCi/m2 = Gross CPM - BKGD CPM 400 6.8.5 Recordsample'results on Form 5790-410-03.
6.9 Ground Deposition - Smear Samples 6.9.1 Obtair Mdp~ropriatenumber of cloth smears from-the Emergency Kit and number the smears (if necessary).
6.9.2 Proceed to-area to'be surveyed and smear selected smooth surfaces (e.g., cýrs mail boxes; machiniery,- rainf'gutters etc.).
NOTE: Each smear area should'be clearly/identified on a map of the area or in a written description of the-area..
6.9.3 Plac'tlhe smear(s) in plastic samplebag(s) and seal and label the bag(s).
6.9.4 Recordtthe samplelTIME AND SURVEY POINT (sample location)
SURVEY TYPE on Form'5790-410-03.
6.9.5 In a low background area (i.e., <1000 CPM), 'calculate the smearable
'* -activity of each smear sample using the following method:
A. Establish an area suitable for counting potentially contaminated
,.*.... sm ears;,, . -,' , ,
B. Determine the background CPM;
- C. Remove the smear(s) from the bag (s) and count using count rate
,.o :meter with a 2" pancake probe.
"D. Calculate the ground deposition activity as follows:
""RCi/m2= Smear CPM - BKGD CPM S-' 200 I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410 TITLE: OUT-OF7-PLANT SURVEYS Revision 12 Page 16 of 26 6.9.6 Rebag the smear sample(s). Contact the Field Team Communicator and arrange to have the sample(s) transported to the EOF Count Room for analysis or retain the samp!e(s) for future analysis and proper disposal.
6.9.7 Record smear sample results on Form 5790-410-03.
6.10 Ground Deposition - Gamma Dose Rate Survey 6.10.1 Obtain a dose rate meter. Energize-the dose rate meter and allow the instrument to stabilize (approximately 30 seconds) then re-zero the meter.
6.10.2 Proceed to the designated survey area and perform a closed window dose rate survey of the area at 1 meter above the ground.
6.10.3 Record the sample TIME, SURVEY POINT (sample location) and SAMPLE TYPE on Form 5790-410-03.
6.10.4 Calculate ground deposition as follows:
[tCi/m2 = 100 x (CLOSED WINDOW mr/hr READING) 6.10.5 Record sample results on Form 5790-410-03 and report the results to the Field Team Communicator.
6.11 Ground Deposition Samples - Snow/Dirt Survey 6.11.1 Proceed to the designated survey area and select an area where the sample will be taken.
NOTE: The selection should be based on an evaluation of current weather and ground cover conditions (high winds, rain, snow, etc.) such that the sampled area is representative of the ground cover surface. Sample the area where the deposition of contamination is most likely to occur.
6.11.2 Obtain the aluminum scoop and a large plastic sample bag from the Emergency Kit.
6.11.3 Using the scoop, remove snow/dirt from a surface area of about 1000 cm 2 to a depth of about 1 centimeter (0.4 inches).
NOTE: The area of the scoop is approximately 1,000cm 2. When removing surface snow to a depth of 1 centimeter the volume of the melted snow is approximately 100 CC of liquid. This assumes a 10:1 snow to water ratio.
6.11.4 Place the sample material in a large zip-lock bag, seal and label.
6.11.5 Record the sample TIME, SURVEY POINT (sample location), and the SAMPLE TYPE on Form 5790-410-03.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT . A.2-410*
TITLE: OUT-OF PLANT SURVEYS Revision 12 Page 17 of 26 6.12 Ground Deposition -Vegetation/Food Sampling 6.12.1 Proceed to the designated survey area and select the area where the sample will be taken.
6.12.2 Obtain scissors or trimming device and large zip-lock bag from the Emergency Kit.
NOTE: The selection should be based on locating herbage eaten by grazing animals, since the herbage lprovides a'key paithway to human exposure. Also, depending on season of year, plant-fruit (strawberries, sweet corn, beans, Swheat, oats, etc.) may be selected for sampling.
6.12.3 Obtain .enough vegetation/food to fill the zip~lock bag. This is about a 1/3-of 9 kilogram.
2 NOTE: If the vegetation is'grass an area of at least 1 M of ground should be sampled.
The Vegetation should be cut at approximately .5 to 1 inch from the ground and should not be contaminated in the process by soil.
6.12.4 Compress the air from the bag, seal and label bag.
6.12.5 Rec6rd the sample TIME, SURVEY POINT (sample location) and SURVEY TYPE on Form 5790-410-03. -:
' 6.12.6 Calculate the activity of the sample using the following method:
A. 'Flatten the bag and lay probe ofta count rate meter with 2" paficake probe on the center of the-bag.
B. -,Wrap.bag around probe and note reading.
C. ,Calculate the activity using the following formula:
ltCi/kg =CPM -BKGD CPM
.* -1.32 NOTE: This calculation is based on 1-131 and CS-137..
t6.12.7 Record the sample results on Form 5790-410-03 and report the results
, to the Field Team Communicator-,. -
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 18 of 26 6.13 Off -Site Sample Courier Instructions 6.13.1 When dispatched from the OSC Coordinator, obtain an electronic dosimeter (either from the OSC or Access Control) and log onto Emergency RWP 902. Retain your TLD and dosimeter when departing the plant.
6.13.2 Obtain the keys for a plant vehicle and the keys to EVES building.
Keys may be obtained from the Guard House or Nuclear Plant Helper Supervisor key cabinet.
6.13.3 Obtain one Sample Courier Kit (aluminum case), one portable mobile radio kit (Channel 2A) from the EVES Bldg.
6.13.4 Place the Sample Courier Kit in the vehicle and install the mobile radio and antenna.
6.13.5 Perform an operability check of the installed radio unit, prior to departing the EVES Building, by contacting the TSC (or EOF). Ensure the radio is selected to Channel 2A.
6.13.6 Proceed to the EOF Command Center, using the back (Receiving Area) personnel entrance, and contact the Radiation Protection Support Supervisor (RPSS) immediately upon arrival.
6.13.7 Standby in the EOF for assignments as directed by the RPSS.
6.13.8 When dispatched from the EOF to pick up samples:
A. Logout of the EOF (ifnecessary) with EOF Security (ensure you keep your dosimetry when departing the EOF).
B. Establish and maintain constant radio communication with the Field Team Communicator and follow the communicators instructions regarding travel routes, etc.
C. Rendezvous with Field Teams at designated locations for sample pickup.
D. Frequently check your dosimeter and notify the Field Team Communicator when exposure approaches administrative limits.
6.13.9 When picking up samples from the Field Team(s):
A. Obtain any special instructions fcr handling the sample(s) from the RPS (e.g. ALARA precautions, etc.).
B. Ensure the sample(s) are properly packaged (bagged) and labeled.
I/mab
4
- - -. -' r V -
MONTICELLO NUCLEAR GENERATING PLANT A.2-410*
TITLEE:] -OUT-OF-PLANT SURVEYS -,"-' Revision 12 Page 19 of 26 "C. Confirm radiological conditions along your travel route(s) with the RPS and follow the RPS's instructions regarding the use of protective clothing (e.g. respiratory protection) that may be warranted.
NOTE: Protective clothing is provided in the Sample Courier Kit.
6.13.10 Transport the sample(s) promptly.to the EOF Count Room for analysis.
While enroute (to the EOF)'contact the EOF Count Room (by radio) and inform the Count Room.RPS you willbe delivering samples.
.- 6.13.11 Upon arrival atthe EOF use the back (Receiving area) personnel entranceinto the EOF Controlled Area (the posted Contaminated area in the EOF loading dock) and:
A. Notify the Count Room RPS samples have arrived.
B.. -eEnsure the samples are properly re-bagged, re-labeled and
- -surveyed (with a frisker or dose rate meter) prior to transfer out of the'posted Contaminated Area into the EOF Count Room.
6.13.12 While atthe.EOF:"
A. Check and report dosimeter. readings to the RPSS.
-'B. Perform a whole body frisk (check) prior to proceeding back into the field (ifimmediately dispatched).
C. If remaining at the EOF, doff protective clothing (ifapplicable) and perform a whole.body frisk when exiting the posted
'Contaminated Area (at the Step-Off-Pad).
D. -Perform personnel decontamination (as necessary) under the direction of the Count Room RPS.
6.13.13 Upon completion of sample delivery notify the Field Team Communicator you are ready to be dispatched again.
6.13.14 Ifdispatched into the field again, obtain additional sampling supplies (e.g: sample bottles, filters, etc.) from the storage cabinet in the Receiving Area and deliver the supplies to the Field Teams (as requested).
6.13.15 When sample courier(s) are no longer required (or when relieved by the next shift) report to the RPSS for debriefing and next shift assignments. -.
l/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 20 of 26 6.14 Prairie Island Off-Site Field Team Driver Instructions 6.14.1 When dispatched by the OSC Coordinator, obtain an electronic dosimeter (either from the OSC or Access Control) and log onto Emergency RWP 902. Retain your TLD and electronic dosimeter when departing the plant.
6.14.2 Report to the EOF and check in with the Radiation Protection Support Supervisor (RPSS).
6.14.3 Serve as a driver for the Prairie Island Off-Site Survey Team RPS. The EOF Field Team Communicator will provide instruction on desired sample points.
6.14.4 Request advice from the RPS regarding procedures or special precautions which should be considered when approaching or searching for the plume.
6.14.5 Provide assistance to the RPS as requested.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410*
TITLE: -'OUT-OF-PLANT SURVEYS.'. Revision 12 I Page 21 of 26 7.0 FIGURES FIGURE-,
-7.1 Gross Iodine Activity Table Using Count Rate Meter with 2 inch Pancake Probe and Silver Zeolite Absorber Run Time 10 Minutes Volume 707500 cc Flow Rate 2.5 GFM Probe eff. 0.10 FlowCF 1.0
-NOTE: The [tCi/cc activity assumes the above conditions.
NcPM L [,i/cc,-NCPM JCc, gici [L NM ,Iodine' iodine ,ci/cc NCPM Iodine liCi/cc 4.E016E-7
'80 6000 -'* 3.2E-05E6 100 .3E-02. 6.E-08 000 3.E-00 5.E-06 120o, 5.3E-02 7.E-08 ,,900,1: 4.6E-01 7.E-07 ,',700O 3.8E-00 5.E-06 140.* 6.0E-02, 8.E-08 :,1 000-,' 5.OE-01 7.E-07 _8000 4.5E-00 6.E-06 "160, 7.OE-02 1.E-07 ,1200% 6.OE-01 -8.E-07 79000 ; 5.OE-00 7.E-06 S 9.OE-02 7.E-07 1400 7.OE-01 1.E-06 110000 5.6E-00 8.E-06 200, .OE-01, - 1.E-07 71600 8.OE-01 1.E-06 -12000, 6.OE-00 8.E-06 220 1.2E-01 2.E07, 800 9.E01 1.E06 14000,-, -7.5E-00 1.E-05
, 240-: 1.4E-01 2.E-07 '2000* 1.OE-00 1.E-06 '6000 1.OE+01 1.E-05
',,260( 1.5E-01 2.E-07 ;1. 1E-00 2.E-06 1 80 0 0 1.3E+01 2.E-05
'280 1.6E-01 2.E-07 ý,24000 1.2E-00 2.E-06 20000 1.5E+01 2.E-05 300 1.7E-01 2.E-07 2600 1.1E-00 -2.E-06 25000 2.5E+01 4.E-05 1.8E-01 3.E-07 2800',' 1.5E-00 ,2.E-06 3.5E+01 3.30000 5.E-05 2.0&E01
-QQ:3 3.E ,_3000, 1.6E-00 ,2.E-06 ,'35000 5.OE+01 7.E-05 2.3E-01 3.E-07 1.8E-00 &.E-06 400009' 6.OE+01 8.E-05 4500 ', 2.6E-01 4.E-07 ,-4000n 2.1 E-00 3.E-06 45000'-- 1.OE+02 1.E-04 600 3.OE-01 4.E-07 2.5E-00 4.E-06 54500
,7500':. 3.6E-01 5.E-07 '*5000"- 2.8E-00 4.E-06 '- :.
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-410*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 22 of 26 FIGURE 7.2 Gas Chamber Table using Count Rate Meter with 2 inch Pancake Probe and 100 cc S.S. Gas Chamber I NCPM 1lCi/cc p.Ci/cc NCPM___ (Xe-1 33 equiv.) NCPM (Xe-1 33 equiv.)
S <* ;100 .. 1.OE-05 *-- "2500-, 4.5E-04
~150 .E0 3000 5.5E-04
.00 .... O 0E-05 3500 6.5E-04
.. '250 0-1z 2.5E-05 1-.5E5.
-05,13E0 ; 0000.... . 2.5E-04 200,ý 3.2E-05 45000 .0 E-04 34.OE-05 51000, ., 1.1 E-03 4,00, - 4.5E-05 #::l" 5500'w` 1.3E-03 5.1 E-05 5450 -. 1000i; 5E-03
" *-2000'- 6.OE-05 8000. 1-.8E-03 600 7.5E-05 1000O0~, 2.5E-03
--,800 1.1 E-04 120900 3.OE-03 1000 1.5E-04 .14000' 3.5E-03 1200- 1.7E-04 _116000 4.OE-0 1400 2.OE-04 180003/4 4.7E-03 1600 2.5E-04 ,200W0 5.5E-03
~1800,ý 3.OE-04 25Q~75-03 2000 3.5E-04 -"30000 9.5E-03 I/mab
S7, I TITLE:
,.j i MONTICELLO .... OUT-OF-PLANT
~ ~.. . NUCLEAR GENERATING PLANT SURVEYS. **I
.1; I
I Revision 12 I
A.2-410* 1 Page 23 of 26 I
I
-: -FIGURE 7.3. Gross Liquid Activity Table using Count Rate Meter with 2 inch;Pancake Probe and,1 000 ML Poly Bottle I
-NCPM --.- : pCi/ML"_
. 0 - 1.5E-04 200 - . . 2.5E-04 3.5E-04
,0
- *400 ~'4.5E-04.
500 5.5E-04'
'ý600,4+§~;7 6.5E-04
~ ~700 .5E-04
!7-8008.E0
'900" 9.5E-05, "J1000 1.OE-03 21000<
,. -> " 71.8E-03
'3000-- .6-0
-: ;~~ 7?.3.4E-03 4Q0~~
~500Q>~ ,-" 4.1 E-03
- 2 ,Q:000 - ~ 4.8E-03
'7j000", 5.5E-03w
-8000'"', -6.2E-03
'9000T:- 6.9E-03
--- i0OoO":1K' 7.6E-03 t
Detector Position I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-41 0*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 Page 24 of 26 FIGURE 7.4 Gross Particulate Activity Table I using Count Rate Meter with 2 inch Pancake Probe Run Time 10 Minutes Volume 707500 cc 4" filter CF 0.3 Flow Rate 2.5 CFM Probe eff. 0.10 Flow CF 1.0 Conversion 4.51 E-07 [,Ci/dpm NOTE: The [Ci/cc activity assumes the above conditions.
NCPM pCi/cc NCPM [,Ci/cc NCPM [LCi/cc 100 2.E-09 900*2.E-8 <<100¶y -- 1.E-07 "120 3.E-09 1000 :.- 2.E-08, -.... 7000 . 1.E-07 140 3.E-09 _,200, 3.E-08 2.E-07 160 3.E-09 *j40* 3.E-08 , $9000, 2.E-07
".:;,l 80--,.4
.. E 09 *.**, 1600,,'
1 '.
- ":=+'*; 3.E-08
- 1OO 10000 - 2.E-07 2E0
-200 4.E-09 1800*, 4.E-08 *W'12000@*.;' 3.E-07 220, 5.E-09 :2OO0, 4.E-08 1,4000,- 3.E-07 240 5.E-09 ' 2200,. 5.E-08 16000- 3.E-07 260, 6.E-09 :,. 2400 5.E-08 . 8000 4.E-07
-280 6.E-09 2600& 6.E-08 20000 4.E-07 6.E-09 2800,,-300 , 6.E-08 , .- 25000`,,-- 5.E-07
-350 7.E-09 3000 *. 6.E-08 30000- 6.E-07 8.E-09 3500 7.E-08 6400 .. 6.E-07
- ,:500 1.E-08 ..... ,40'00,, 8.E-08 ':' 40000 8.E-07
,5600 1.E-08 4500 1.E-07 : 4.5000' .. E...
..... ... . . . *;-07: 1.E-06
- 700 1.E-08 ;--45000: 1.E07 [ __, _ __ ___ ___77_
800. 2.E-08 5500*.
- 1.E-07 , __...______
I/mab
I MONTICELLO NUCLEAR GENERATING PLANT A.2-41 0*
TITLE: OUT-OF-PLANT SURVEYS' Revision 12.
Page 25 of 26
"- FIGURE
- 7_ 5 On-Site [inuid SAmDiA Locations Liguld Samnla Locations I By I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-41 0*
TITLE: OUT-OF-PLANT SURVEYS Revision 12 I Page 26 of 26 FIGURE 7.6 Forms Utilized in this Procedure
- 1. 5790-410-02 OUT-OF-PLANT SURVEY CHECKLIST
- 2. 5790-410-01 EMERGENCY SAMPLE RESULTS LOG
- 3. 5790-410-03 GROUND DEPOSITION SAMPLE RESULTS LOG 33, , - .
f--' -3,
- '-'S-'
- - 5,3*.3
- - - 3- *-c, *
.3.-
- 5- 33. -
1 .. -
- -. '--3
". .. ._ . 1 "13-;', - .
I/mab