ML20071Q807
| ML20071Q807 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/09/1983 |
| From: | Fey F NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20071Q787 | List: |
| References | |
| PROC-830509, NUDOCS 8306090261 | |
| Download: ML20071Q807 (112) | |
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Revised Procedures for Emergency Procedures Book su ret Revisiens to the.Bnergency Procedures were reviewed in a recent Operations Camtittee Meeting. Listed below are the procedures suxrseded and revised Other pages not revised may have been reprinted with t'w revised pages to facilitate updating the Book.
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f Procedure A.2-410 S.,
Revision 2 Page l'of 21 f-Op. Com. Rev. Req'd.
,,Ye s X. No Q.A. Review Req'd.
Yes No X ALARA Review Req'd.
Yes X No OUT-OF-PLANT SURVEYS Procedure A.2-410 REVIEW AND APPROVAL V!/'f[/3 Prepared by: wb M ALARA Review:
CM//r?h,Lt-Date Reviewed by:
$MI/e,//tsw Q.A. Review:
RW O Date / H-6 L Operations Committee Final Review: Meeting Number
//99 Date 4L 6P5 Approved by:
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Op. Com. Results Review:
Not Required Mtg. # 1056 Date PURPOSE The purpose of this procedure is to specify the method of staffing the survey teams, the monitoring equipment and supplies, and the methods to be employed by the survey teams and the Radiological Emergency Coordinator to monitor and record field survey data.
CONDITIONS AND PREREQUISITES A.
An airborne or liquid release of radioactive material has occurred, is occurring, or may occur.
B.
A survey of the site has been requested or is required.
C.
A survey of off-site areas has been requested or required and the EOF is not staffed sufficiently to do the survey.
ORGANIZATION AND RESPONSIBILITIES A.
Overall Responsibility - Emergency Director 8.
In Charge -
Radiological Emergency Coordinator (REC)
C.
Assistance Monitoring Section Leader (MSL)
DISCUSSION A.
Off-site surveys during an emargency are normally performed by sister plant radiation protection technicians when the corporate organization is fully activated.
Prior to this, off-site surveys must be done by the affected plant's radiation protection personnel.
Surveys of on-site out-of plant areas are always assigned to the affected plant staff.
B.
During the initial stage of an emergency, the number of personnel available for survey work may be small.
The Radiological Emergency Coordinator will make decisions on employment of personnel resources for maximum effect. When the Radiation Protection Support Supervisor (RPSS) position is activiated, all field survey teams will be transferred to the control of the RPSS.
WP/kk
Procedure A.2-410' Revision 2 Page 2 of 21 C.
This procedure is essentially identical to the corporate procedure for off-si' j surveys (EPIP 1.1.10), which sister plant personnel will use when the EOF is activated. The reason for this is to minimize the impact of switching from the plant procedure to the corporate procedure when the EOF and Radiation Protection Support Supervisor position is activated.
D.
At each EOF there is a count room which provides an offsite facility for receipt and analysis of radioactive samples.
This count room is staffed by Radiation Protection Specialists from the affected plant who are familiar with its equipment and operation.
Unless circumstances dictate otherwise, the EOF Countroom will be employed for all samples taken pursuant to this procedure.
RESPONSIBILITIES' A.
Radiological Emergency Coordinator or Monitoring Section Leader 1.
Provide a briefing and dispatch survey teams to perform appropriate radiological surveys in the general path of the projected or actual plume to confirm dose projections results. Determine the necessary radiation protection for survey teams.
2.
Direct the survey teams to the affected areas along the actual or projected plume path.
Direct each team to conduct a plume search, to perform surveys in accordance with the guidelines of this procedure, to record the necessary data, and transmit the results to the TSC using the portable radios.
Each team should initially be directed to conduct a plume search and to perform an air sample survey and/or a stationary dose rate survey at each selected location once the plume has been encountered. When additional information concerning the type of release is available, the type of monitoring may be modified as circumstances dictate.
3.
Determine the need for river sampling following a liquid release.
Off-site monitoring in response to a release of radioactive material to the Mississippi River will depend on the nature and extent of the release, whether or not the release has been stopped, and the release path.
4.
Upon termination of the emergency condition, direct the survey teams to return all equipment to normal locations.
Direct that a complete inventory be conducted to return all equipment inventories to normal levels.
Direct that the EOF count room equipment be shutdown and the count room returned to a standby status.
B.
Survey Team Members 1.
Obtain appropriate monitoring equipment from the survey team kits at the Assembly Points (one kit at each location) or the E0F (three kits).
Obtain and re-zero dosimeters.
2.
Perform operability checks on monitoring and sampling equipment s
before going into fi~ eld:
WP/kk
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Procedure A.2-410 Revision 2 Page 3 of 21 a.
Calibration date b.
Response check c.
Re-zero 3.
Obtain a portable radio frcm the EOF or R.P. Office and operationally l
check the radio before starting the survey.
Keep the radio operational at all times while performing surveys in order to maintain communica-tions with the TSC.
Since radio communications can be intercepted by commercially a.
available scanners, all communications must be brief and factual and free of exclamatory or alarming expressions. All radio communications will utilize the DVP unless directed otherwise.
b.
Carefully word data transmissions to minimize possible confusion.
'In particular, avoid abbreviations such as " MREM" which could be confused with " REM".
Use the complete word or unit (" millirem").
c.
Use the phonetic alphabet (see attachment 6) when communicating sample point identification numbers.
d.
Use a mag-mount external antenna for field communications.
l 4.
If so directed by REC or MSL, use protective clothing and equipment contained in the survey kit.
5.
Conduct a search for the plume when departing the plant.
6.
Observe the respiratory protection and the field dose rate precautions, as stated in Attachment 7 at all times while conducting a plume search, taking dose rate measurements or taking air samples.
7.
At points where the plume is encountered, or at each designated survey point perform surveys in accordance with applicable procedures as directed by the Radiological Emergency Coordinator or Monitoring Section Leader.
l 8.
Identify survey locations using either:
a.
predesignated survey location numbers, as shown on the applicable Radiological Sampling Points map; or l
b.
known landmarks, road intersections, grid coordinates, etc. to identify locations the plume is encountered and/or sampling is done when not at a predesignated survey point.
NOTE:
Map coordinates and/or locations should also be identified as per the mobile sampling locations list.
t 9.
The survey team should accurately document all survey data on a Emergency Sample Results Log, (see example in Attachment 1).
Enter the date, time, name of surveyor, and instrument serial number, and model for each survey entry.
i WP/kk
Procedure A.2-410' Revision 2 Page 4 of 21 10.
Frequently check personal dosimeters and request relief if cumulative exposure approaches administrative control levels'.
Survey team members can contact the R.P. Coordinator to determine current exposure status.
Plant survey team members are also responsible for ensuring that non-plant drivers have dosimetry and that exposure control procedures are followed.
PROCEDURE A.
Precautions 1.
If an instrument malfunctions or " pegs" out during survey operations immediately exit the area by the same route used to enter it, and obtain a new instrument if necessary. A malfunctioning instrument should be appropriately tagged.
2.
Take care not to contaminate or damage survey instruments.
Particular care should be exercised to avoid damage to the beta window of a beta-gamma instrument.
3.
Exposures of personnel in the survey party shall be in accordance with Monticello Nuclear Generating Plant administrative control levels.
Monitoring teams must remain alert to their own exposure and request relief if their cumulative exposure apprcach these levels. The Emergency Director may authorize exposure limit extensions, if necessary (A.2-401). All exposures shall be maintained as low as reasonably achievable.
4.
If the Radiological Emergency. Coordinator so directs, or if substantial airborne activity or contamination is suspected, don protective clothing and/or respirators, as appropriate. Avoid the unnecessary use of respirators and protective clothing.
If observed dose rates exceed 100 millirem per hour while monitoring out of doors, evacuate the area and/or seek shelter, unless otherwise directed by Radiological Emergency Coordinator.
B.
Equipping of Off-Site Survey Teams 1.
Obtain an NSP vehicle, if available. There are normally two station wagons available for off-site surveys. The keys are under control of the R.P. Coordinator. Otherwise, use any available L
privately-own vehicle.
Record starting mileage and gas tank level.
There should be at least 1/2 tank of gas. Obtain another vehicle if necessary and practicable.
C.
Equipment Operation 1.
Survey instrument shall be operated in accordance with standard procedures for each instrument type.
General guidelines for all survey instruments shall be as follows:
WP/kk n.-
Procedure A.2-410 Revision 2 Page 5 of 21 a)
Calibrated within specified. interval b)
Response checked satisfactorily c)
Meter zerced 2.
Since Minnesota has severe winter conditions which can seriously affect instrument readings, the following guidelines have been developed to eliminate most cold weather instrument problems:
i a)
Allow the instrument to completely warm up.
This should take about 2 minutes.
Do this indoors or in a car.
b)
If outside temperature is greater than 32*F (0*C), instrument use is unlimited.
c)
If the outside temperature is between 32*F (O C) and 0 F (-18*C),
any instrument should be used for no more than 5 minutes.
d)
If the outside temperature is between 0 F (-18*C) and -20*F
(-28 C), any instrument should be used for no more than 2 minutes.
e)
If the outside temperature is below -20 F (-28 C), no instrument should be used unless special batteries (alkaline or Ni-Cd) are in the instruments and this would increase the temperature range to -40*F (-40*C).
The instrument should only be used for very short times (less than 30 seconds).
D.
Types of Samples 1.
At each sample point the following samples may be made:
a)
Air Sample gaseous, particulate and radioiodine b)
Stationary Dose Rate Survey 2.
Special samples to be taken as directed by Radiological Emergency Coordinator:
a)
Liquid Samples NOTE:
Re-entry phase monitoring and sampling will be as-directed by the RPSS and is covered by corporate procedure.
E.
Sampling Procedures I
l 1.
Plume Search Technique a)
Equipment Required i
1)
Radiation Survey Instrument (RO-2, or equivalent, with Beta l
Correction Factor) l 2)
Sample Logs (Form 5790-410-1) j 3)
Pen and/or pencil WP/kk
Procedure A.2-410 Revision 2 Page 6 of 21 b)
Procedure 1)
When departing for the field:
a.
Energize the instrument, observing proper precautions for cold weather. Note: All instruments should be response checked prior to entry in the field.
b.
Allow the instrument to stabilize (approximately 30 seconds), then zero the meter.
2)
Periodically hold the instrument out the vehicle window, while in transit, and watch the instrument for a meter defection.
NOTE:
During inclement weather the instrument may be placed against the inside vehicle window or on the dash.
3)
When a meter deflection is observed, stop the vehicle and perform a beta and gamma survey of the area as follows:
a.
Hold the instrument at approximately 1 meter (3 feet) from ground level and scan around the area for maximum meter deflection, b.
Open the probe window for beta gamma reading c.
Record the " window open" reading on sample log d.
Close the probe window e.
Record the " window closed" reading on sample log f.
Determine the corrected beta reading 4)
Record the readings and calculate the beta and gamma dose on sample log.
NOTE:
A beta plus gamma reading will indicate that the plume has been encountered.
A gamma reading with zero beta reading indicates the plume is elevated or displaced.
A gamma reading and a beta reading, indicates that the i
l plume is at ground elevation.
5)
Report the results to the REC or MSL as follows:
1 a.
Location:
1 b.
millirem /hr gamma c.
millirem /hr True Beta NOTE:
If not at a predesignated survey point, use known landmarks, road intersections, grid coordinates, etc.,
to identify the location.
WP/kk i"
4 Procedure A.2-410 Revision 2 Page 7 of 21 2.
Air Sample a)
Equipment Required 1)
Battery powered or generator powered air sampler 2)
Fiberglass Particulate Filter 3)
Silver Zeolite Cartridge 4)
RM-14 or equivalent 5) 2" GM Pancake Probe 6)
Watch or Clock 7)
Plastic Bags 8)
Sample Labels 9)
Pen and/or Pencil
- 10) Sample Logs (Form 5790-410-1)
- 11) Stainless Steel Gas Chamber b)
Particulate and Radioiodine Procedure 1)
Install the particulate filter and silver zeolite absorber into the air sampler cartridge / filter holder.
2)
Start the air sampler.
Record the start time and sample location /or survey point as applicable on Emergency Sample Results Log.
Record the flow rate through the sampler.
NOTE:
If precipitation is occurring, draw sample from covered area.
Umbrella may be used for this purpose.
3)
When the desired sample time has elapsed, record sample volume and stop the air sampler. Thesgmpleshouldbeastandard 25 cubic foot sample, (7.07 x 10 cc or approximately 10 minutes).
Record the stop time.
4)
Carefully remove the particulate filter and silver zeolite absorber. Analyse in accordance with Step 6, below, then place samples in separate plastic sample bags.
5)
Place a sample label on the sample and ensure that all infor-mation is completed.
a) Sample time and date b) Location of sampler c) Volume of sample d) Exposure rate of sample l
6)
Make gross activity estimates in the field by the following methods:
a) Particulate Activity - count with particulate filter using an RM-14 (or equivalent) with a 2" GM pancake probe.
Estimate the gross particulate activity using the following formula:
-7 Activity (pCi/cc) = (Background Corrected Count Rate)(4.5 x 10 pci/ dom)
(Probe Efficiency) (Sample Volume; cc's)(cf)
WP/kk
ProcGdure A.2-410 Revision 2 Page.8 of 21 NOTE 1:
Probe efficiency = 0.1 for RM-14 with a 2" GM pancake probe.
NOTE 2:
Place 2" GM pancake probe about 1/8" from the filter, with filter outside poly bag.
NOTE 3:
CF = Correction factor for sample.
CF is 0.3 for 4 inch paper counted with a 2 inch probe.
b) Iodine Activity count the silver zeolite absorber using an RM-14 or equivalent. Calculate sample activity using the following formula:
Iodine Activity (pCi/cc) = f e Vo m cc's)
NOTE 1:
Where pCi's on absorber = activity on absorber determined froc Attachment 2 using the corrected count rate.
NOTE 2:
If background exceeds 1000 CPM, notify the REC or MSL and proceed to an area of lower back-ground (less than 1000 CPM) for counting, if so instructed.
NOTE 3:
Place 2" GM pancake probe directly on absorber )
with absorber inside poly bag.
l c)
Gaseous Activity Procedure 1)
Remove the stainless steel gas chamber, suction bulb and filter assembly from the survey kit.
2)
Install a clean filter in the filter assembly.
~
3)
Connect filter assembly such that air passes through the filter
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to the gas chamber, then to the suction bulb.
4)
Open the stop cccks on the gas chamber.
5)
Squeeze the suction bulb ten (10) times to obtain a represen-tative sample.
NOTE:
If precipitation is occurring, draw sample from covered area.
Umbrella may be used for this purpose.
6)
Shut the stop cocks on the gas chamber.
7)
Using an RM-14 or equivalent and a 2 inch GM pancake probe obtain a count rate of the chamber volume by placing the probe over the mylar window.
Log the result as " gross CPM".
WP/kk
4 Procedure A.2-410 Revision 2 Page 9 of 21 8)
Obtain a second chamber labeled " Background".
Do not open the stop cocks of the background chamber.
Determine a back-ground count rate by placing the 2 inch GM pancake probe over the mylar window.
Log the result as " Background CPM".
9)
Determine the " Net CPM" by subtracting the " Background CPM" from the " Gross CPM".
1 10)
UsethecurvejgAttachment4todeterminetheconcentration, y
pCi/cc, of Xe equivalent.
d)
Recording 1)
Record the air sample results on the Emergency Sample Results Log, and report the results to the REC or MSL using the portable radio.
2)
As directed, save the sample for future analysis. The central collection point for off site samples is the EOF.
On-site samples may be analyzed at the plant. All samples should have exposure rate marked on the label.
3.
Stationary Survey a)
Equipment Required 1)
Radiation Survey Instrument (RO-2 or equivalent, with Beta l
Correction Factor) 2)
Sample Results Log (Form 5790-410-1) 3)
Pen and/or Pencil b)
Procedure 1)
Before arrival at the designated survey point:
a) Energize the instrument, observing proper precautions for cold weather. NOTE: All instruments should be response checked prior to entry in the field.
b) Allow the instrument to stabilize (approximately 30 seconds) then zero the meter.
i 2)
Upon arrival at one of the designated survey points, perform a beta and gamma survey of the area as follows:
a) Hold the instrument at approximately 1 meter (3 feet) from ground level and scan around the area for maximum meter deflection.
b) Open the probe window for beta gamma reading.
c) Record the " window open" reading on the Sample Results Log.
3-WP/kk L..
^
Procedure A.2-410 Revision 2 Page 10 of 21 d) Close the probe window.
e) Record the " window closed" reading on the Sample Results Log.
f) Determine the corrected beta reading.
3)
Report the results to the REC or MSL as follows:
a) Location:
b) millirem /hr Gamma c) millirem /hr True Beta 4.
Liquid Samples a)
Equipment Required 1)
One Liter Sample Bottles 2)
River Sampling Apparatus 3)
Labels 4)
Pen 5)
Plastic Bags 6)
Survey Instrument 7)
Tape b)
Procedure
/
1)
Cast poly bottle into the water to be sampled.
2)
Allow bottle to fill completely then withdraw.
3)
Label and bag the sample bottle, seal and label bag.
4)
Make a gross estimate of the bottle activity as follows:
a).Use a RM-14 or equivalent with a 2" GM pancake probe to measure activity.
b) Place probe on the bottle side as shown in Attachment 3.
c) Determine the gross activity using the graph shown in.
d) Save the sample for further analysis.
e) Reports results to the REC or MSL at the TSC by portable radio.
f) Record the results on the Emergen y Sample Results Log.
5)
The central collection point for off. tite samples is the E0F. On-site samples may be analyzed at the plant.
WP/kk
~ - -
Procedure A.2-410
~
Rrvision 2 Page 11 of 21 c.
Monticello Locations 1)
Initial surveys of liquid releases will be taken by plant personnel at the plant discharge canal, and the Monticello Bridge.
The off-site survey teams will relieve the plant team taking continuous samples at the Monticello Bridge.
Required sample frequency will be specified by the Radiological Emergency Coordinator.
2)
Additional liquid surveys may be requested by the State or the Emergency Director.
Locations for these surveys shall be specified at that time.
Specific downstream locations for further surveys are:
a)
Elk River Bridge b)
Anoka Bridge c)
Minneapolis and St. Paul drinking water intakes 5.
Contamination Survey a.
Equipment Required 1)
Two (2) inch cloth smears and plastic bags 2)
RM-14 with 2" pancake probe or equivalent b.
Procedure 1)
Obtain tca (2) inch cloth smears and plastic bags.
2)
Number the smears.
3)
Don protective clothing appropriate for the situation to be expected.
4)
Proceed to the area to be surveyed.
5)
Write smear number on survey map for applicable location to be ~ smeared.
6)
Swipe an area by applying moderate pressure along a line or shape, 15 to 18 inches in length.
NOTE:
Surfaces to be smeared should be smooth (e.g., cars, mail boxes, etc.).
7)
Fold the smear folder in half and place in a poly bag.
8)
Count the smears in a low background area, using an RM-14 (frisker), as follows:
a) Obtain background counts from frisker.
WP/kk
Procedure A.2-410 Revision 2 Page 12 of 21 b) Cover work area with poly or absorbent paper to prevent spread of contamination.
I c) Remove the smears from the poly bags.
d) Hold the frisker probe approximately 1/8 inch above the smear to obtain the total counts.
NOTE: Take care not to contaminate the probe.
e) Calculate the smearable activity as follows:
dpm/100 cm2, Total CPM - BKGD CPM (Frisker Efficiency) (0.10)
NOTE:
(3) Contaminatjonlevelsgreaterthan 100,000 dpm/100 cm. requires respiratory protection.
(2).10 is smear efficiency.
f) Log smear results, including date and time on an Emergency Sample Results Log (Attachment 1), and report results to the REC.
6.
Snow Samples a.
Equipment Required 1)
Poly bags 2)
Snow scoop 3)
Spatula b.
Procedure 1)
Using snow scoop, remove surface snow from area to be sampled (to a depth of approximately 1 cm).
2)
Pla~ce snow in poly bag and seal.
l 3)
Arrange to transport snow sample to E0F Count Room for analysis.
4)
Calculate ground contamination as follows:
6 pCi _
(Total pCi's in Sample) (10 pCi/pCi) 2 2
~4 2 2
m (Area of Snow Sample cm ) (1 x 10 M /cm )
WP/kk i
v-
4 Procedure A.2-410 Revision 2 Page 13 of 21 Example of EMERGENCY SAMPLE RESULTS LOG Form 5790-410-1 Rev. O, 2/20/82 Page 1 of 2 I
DtEICENCY SAMPIE RESJI23 IDG DATE TIME SAMPIE RESU:5
[OSE IWE nEsi.II3 - mJfM/ hr Instrtrefit survey Sample Sanple Sample WDOUW WD00W T1E btfrA (40cel i
I Point Flcw Volume Gross BKG)
Net LCi/cc Type
- Open Closed (See back beraal Start Stoo Rate (cc)
CPM CPM CPM Beta-Gapuna Gama for formilal Nurter
- l. Formulas listed on.aacx
- Sample type includes: Farticulate, Geseous,14adiolouane, Liquid,
- 2. annarks:
Area Dose Rate l
TEQNICIAN SIGMUIE l
l l
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l l
l WP/kk l
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Precedure A.2-410 Revision 2 Page 14 of 21 Form 5790-410-1 Rev. O, 02/20/82 3
Page 2 of 2 (Reverse Side)
Formulas:
1.
Gross Counts Per Minute - Background Counts Per Minute = Net Counts Per Minute CPM (gross) - CPM (bkgd) = CPM (net) 2.
Cubic feet x 2.83 x 104 = cubic centimeters.
3 Ft x 2.83E4 = cc (CPM (net)) (4.5E-7 pCi/ dom) 3 i
(instrument efficiency)(sx time x cfm x 2.83 x 10 )(CF) 4 (part u a e)
(See Note 2 and 4) t 4.
TRUE BETA = (WINDOW OPEN READING - WINDOW CLOSED READING) x Beta l
- Correction Factor - (See Note 1) i NOTES:
1.
Assume 5.0 if correction factor is unknown.
2.
Instrument efficiency depends on probes.
If using 2" GM pancake probe, ASSUME 10% (0.10) efficiency; if using GM tube probe, ASSUME 2% (0.02) efficiency.
3.
List factors affecting reading; height of probe, reading inside vehicle.
l etc.
4.
CF (Correction Factor for air samples) = 0.3 for a 4 inch paper filter size counted with a 2 inch GM pancake probe.
WP/kk 4
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Procedure A.2-410 Revision 2 Page 15 of 21
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Revision 2 Page 16 of 21 GROSS LIQUID ACTIVITY CURVE USING RM-14 WITH HP-210 PROBE 10~2
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,,;r os r SURVEY TEAM EQUIPMENT MCKAGE
.,i 1.
Eachsurveyteamshallbeequippedwitha'kitofthefolicI'ing:
QUANTITY REQUIRED ITEM E
7
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i 1
Dose Rate Instrument R0-2 or eqinivalent 1
Count Rate Instrument RM-14 or equivalent 2
2" GM Pancake Probes 1
Battery Powered Air Sampler 2
Personnel Self-Reading 00simeters (Low Range) 2 Personnel Self-Reading Dosfaetq'rs (High Range) 2 TLDs (if individuals have,a nopally' assigned TLD they Plastic Sampla Bag:.'(App'gned)" :
should wear tnose assi 1 (Package) roximately 100)
.3 1 (Box)
Garbage Bags (Approximately 10) 1 (Package)
Paper Towels or Handiwipe.s 1 2 (Roll)
Masking Tape 20 Silver Zeolite Cartridges'-
2 GMR-I Cannisters
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2 Full Face Respirators I
s 2
Gas Sample Chambers Q
FilterAssembly(GasChamber,k/.
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Suction Bulb-(Gas Chamber)
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Filter Paper (Gas Chambe~r)'
f' 10 One Liter Poly Bottles
/
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Survey Sample Labels (Approxim tely 30) n i
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- 1 Portable Radio with magmtjc base antenna %
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1 Flashlight
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Clipboard
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Pad of Paper (8 2/2" x 11"' Minimum Size), /
1 Watch or Clock
.t 1
Calculator
- /
30 Smears (cloth and paper) '
1 Snow Scoop
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Weighted Poly Bottle Ho] der
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1 Canvas Bag containing motective cloth 1ng for two people /
(respirators, coveralh L gloves, hoods, footcovers, foul weather (rain) Gear,, Umbrella, etc.)
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- (Cont'd.)
SURVEY' TEAM EQUIPMENT PACK' AGE 2.
The Emergency Plan Drawings Binder.'shall'contain:
1 Prairie Island Radiological Sampling Point Map (E-EPD-5.1) and-related list 9f location descriptions.
1 Monticello Radiological Sampling Point Map (E-EPD-4.1) and related list of location descriptions'.
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1 1
Copy of EPIP 1.1.10, "Off-Site Surveys" 10 Eme'rgency. Sample Results Form EPIP 1.1.10, Figure 1 1
Copy of EPIP 1.1.8, "Communcations Equipment and Information" 1
Copy of Procedure A.2-410, 'Out-of-Plant Surveys' 1
Road Map of State of Minnesota 1i Road 11ap of State, of Wis'consin 9
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Revision 2 Page 20 of 21 j
PHONETIC ALPHABET Letter Word Letter Word A
Alpha N
November B
Bravo 0
Oscar C
Charlie P
Papa D
Delta
.Q Quebec E
Echo R
Romeo F
Foxtrot S
Sierra G
Golf T
Tango H
Hotel U
Uniform I
India V
Victor J
Juliet W
Whiskey K
Kilo X
Xray L
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Procedure A.2-410 Revision 2 Page 21 of 21 ATTTACHMENT 7 SURVEY TEAM RADIATION PROTECTION GUIDELINES I.
Respiratory Protection (1) Radiation Survey Team members should don respirators with GMR cannisters 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 mR/hr Beta.
(2) Respiratory equipment may be removed if the following is indicated:
(a) Field measurement of gross iodine activity indicates less than 1E-7 pCi/cc; or (b).The REC /MSL indicates that no significant iodine is or has been released from the plant.
II.
Plume Dose Rates (1) Survey Teams should not linger in areas greater than 100 mR/hr.
(2) Survey Teams should not proceed to areas l greater than 1 R/hr unless directed by the Radiological Emergency Coordinator or Monitoring Section leader.
(3) Survey Teams SHALL NOT proceed to areas exceeding 10 R/hr.
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internal Correspondence cate hhy 2, 1983 D. L. Orrock Locanon Monticello t caen Various Special Distribution of Frergency Procedures subiect Revised Procedures for Faergency Procedures Pook Revisions to the Emergency Procedures were. reviewed in a recent Ocerations Comittee Meeting. Listed below are the procedures superseded and revised.
Other pages not revised may have been reprinted with the revised pages to facilitate updating the Book.
Superseded Pages List of Current Procedures (2/18/83)
Procedure A.2-301, Pages 1 through 10, Revision 1 Procedure A.2-503 - DELETED 4/28/83 Procedure A.2-302, Pages 1 through 8, Revision 2 Procedure A.2-303, Pages 1 through 3, Revision 2 Procedure A.2-411, Pages 1 through 4, Revision 0 Procedure A.2-106, Pages 1 through 4, Revision 3 Procedure A.2-201, Pages 1 through
, Revision 2 Procedure A.2-205, Pages 1 through
, Revision 1 Procedure A.2-403, Pages 1 through 9, Revision 2 Revised Pages List or Current Procedures (5/2/83 Procedure A.2-301, Pages 1 through)10, Revision 2 Procedure A.2-302, Pages 1 through 7, Revision 3 Procedure A.2-303, Pages 1 through 3, Revision 3 Procedure A.2-411, Pages 1 through 4, Revision 1 Procedure A.2-106, Pages 1 through 4, Revision 4 Procedure A.2-201, Pages 1 through 9, Revision 3 Procedure A.2-205, Pages 1 through 8, Revision 2 Procedure A.2-403, Pages 1 through 9, Revision 3 l
Prepared by:
/Od b w)J ~
Reviewed by:
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Op. Com. Final Review: Meeting #
//ff Date
- -JF-53 Approved by:
kh)
Date 6~3-P3 e
~
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L 's.
s I
, NT.~.AL CORRESPONDENCE c/. (p - T}
toenkon ' / fd & l vzw t
Special Distribution of 6ergency Procedures To Location 7
Revised Procedures for Sergency Procedures Ecok svan:r Revisiens to the berge cy Procedures were reviewed in a recent Cperations Cc=ittee Meeting. 1.isted below are the procedures superseded and revised.
Other pages not revised may have been reprinted with the revised pages to facilitate updating the Ecok.
Surerseded Pates L, f cawt*d Jdjn
/
A. 2 - vol,s Jyts
/-/?
c Revised Paces L !s f o f c u w s A
- B ' S
/ J d z - <fa c ysny>
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[,.g Reviewed By k Op. Cc=. Final Review Mtg.5, //9 / Date 2/ /4/A O Aaproved By 3kNQ Date M-39 -8 3
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.IN_T.E..RN.AL CORRESPONDENCE f'd6 43 onre R**
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//th N LocAT'o"
//ar[c.< f Special Distribution of Bnergency Procedures T3
'ocar'oa Revised Procedures for Energency Procedures Book susact Revisions to the Energency Procedures were reviewed in a recent Operations Gomittee Meeting. Listed below are the procedures superseded and revised.
Other pages not revised may have been reprinted with the revised pages to facilitate updating the Book.
Suoerseded Pages c.c>.n.,,,,,,. ; Gas S n.,,/a Olhmerf < / Ar Ac<ab,P S.ya 4,s w a
y S
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/ c.e <</c.. e ^ A. 2 - +w
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7 koc e rba r e A J' - 4/6,
key'. ],,0) s l** T Revised Pages Co,M,,,,,,/- G.$b,,.</e Q6h ke<f of kt.kcN k SI,,y.,, 5,st n
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,4.2-vrr les 2, pp. /- 7 Cyr4.ms.se.,f.Z'>4e..ud S Aiu /a k. Sa, p4 s Cdhr,acef ai - /Es+ -
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d Prepared By M.csh Reviewed By Tf/ /))t,-pf
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Op. Com. Final Review Mtg.R //?J' Date Approved By 3 ck M Date N -2 7-83 0
O e
I
b 05/02/83 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES LIST OF CURRENT PAGES PROCEDURE PROCEDURE TITLE REVISION NUMBER 000 Series Organization A.2-001 Emergency Organization 5
100 Series Activation A.2-101 Classification of Emergencies 4
A.2-102 Notification of an Unusual Event 3
A.2-103 Alert 4
A.2-104 Site Area Emergency 3
A.2-105 General Emergency 3
A.2-106 Activation of Technical Support Center 4
A.2-107 Activation of Operations Support Center 5
A.2-108 Access Control During Emergencies 0
200 Series Assessment A.2-201 On-Site Monitoring and Protective Action Criteria 3
A.2-202 Off-Site Monitoring During an Emergency 1
A.2-203 Deleted 3-1-82 A.2-204 Off-Site Protective Action Recommendations 2
A.2-205 Personnel Accountability 2
A.2-206 Deleted 3-1-82 A.2-207 Sampling Priorities During an Emergency 0
A.2-208 Core Damage Assessnent 0
A.2-209 Responsibilities of Radiological Emergency Coordinator 0
300 Series Protective Actions A.2-301 Emergency Evacuation 2
A.2-302 Assembly Point Activation 3
A.2-303 Search and Rescue 3
A.2-304 Thyroid Prophylaxis 2
400 Series Radiological Surveillance and Control A.2-401 Emergency Exposure Control 2
A.2-402 Contamination Control 1
A.2-403 In-Plant Emergency Surveys 3
A.2-404 Airborne Iodine Sampling and Analysis 3
A.2-405 Release Rate Determination 2
A.2-406 Off-Site Dose Projection 67 l
A.2-407 Personnel and Vehicle Monitoring 2
l A.2-408 Sample Coordination During an Emergency 1
l A.2-409 Self-Contained Breathing Apparatus (SCBA) Use During An Emergency 0
A.2-410 Out-of-Plant Surveys 2
A.2-411 Establishment of Secondary Access Control 1
A.2-412 Deleted 1-6-83 A.2-413 Small Volume Liquid Sample Obtained at the Post Accident Sampling System 1
A.2-414 Large Volume Liquid Sample and/or Dissolved Gas Sample Obtained at Post Accident Sampling System 1
A.2-415 Containment Gas Sample Obtained at Post Accident Sampling System 2
_j_
AAA056 l
l
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05/02/83 A. 2 EMERGENCY PLAN IMPLEMENTING PROCEDURES LIST OF CURRENT PAGES PROCEDURE PROCEDURE TITLE REVISION NUMBER 400 Series Radiological Surveillance and Control (Cont'd.)
A.2-416 Containment Iodine and Particulate Samples Obtained at Post Accident Sampling System 2
A.2-417 Draining the Trap, Sump and Collector of Post Accident Sampling Sy' stem 1
A.2-418 Post Accident Sampling Station Demin Water Tank Fill Procedure 0
A.2-419-Liquid Radiochemical Analysis 0
A.2-420 Containment Atmosphere Radiochemical Analysis 0
A.2-421 Containment Atmosphere Iodine / Particulate Analysis 0
A.2-422
. Stack Iodine / Particulate Sampling & Analysis 1
A.2-423 Reactor Building Vents Iodine / Particulate Sampling and Analysis 1
A.2-424 EOF Count Room Counting Procedure 0
A.2-425 Post-Accident Gas Sample Line Heat Trace 0
500 Series Communications and Documentation A.2-501 Communication During an Emergency 1
A.2-502 Recordkeeping During an Emergency 0
A.2-503 Deleted - 04/28/83 600 Series Re-Entry and Recovery A.2-601 Re-Entry 0
A.2-602 Deleted 11-19-81 A.2-603 Repair and Corrective Action 1
700 Series A.2-702 Response to an Emergency at Prairie Island 2
A.2-703 Response to Off-Site Situation Involving Radioactive Materials 0
- ii -
AAA056
4 Procedure A.2-106 Revision 4
' Page 1 of 4 Op. Com. Rev., Reg'd.
Yes< X No Q. A. Review Req'd. '
Yes No X ALARA Review Req'd.
Yes No X ACTIVATION OF THE TECHNICAL SUPPORT CENTER (TSC)
A.2-106 Prepared by: IMw4 )
ALARA Review:'
Revision 0 Date 3/27/81 (Eb /7 uhk s -
Q.A. Review:
Revision 0 Date 3/28/81 Reviewed by:
0 Operations Committee Final Review: Meeting Number
,, oo Date 4/?s/83 Approved by:
l)ekb>yg A
Date SI-3-2 3 Op. Com. Results Review: Not Required Mtg. # 948 Date 3/25/81 PURPOSE This procedure provides specific information and instructions for the organiza-tion, activation and operation of the Technical Support Center (TSC) in support of the Monticello Nuclear Generating Plant and NSP Emergency Plans.
CONDITIONS AND PREREQUISITES An emergency condition corresponding to an Alert or a higher rmergency classifica-tion has been declared at the Monticello Nuclear Generating Plant as provided in the MNGP Emergency Plan.
PRECAUTIONS The TSC facilities may be used for normal daily operations as well as-for training and emergency drills provided that these activities do not interfere with the immediate activation of the TSC or the continuing TSC operations in the event of an accident.
TSC facility use during normal operation shall be limited to activities that will not degrade the level of TSC preparedness to react to accident situations and will not reduce TSC systems reliability.
ORGANIZATION AND RESPONSIBILITIES A.
Emergency Director - Overall In-Charge B.
TSC Coordinator - Responsible for logistics and administrative aspects of TSC activation and operation.
C.
TSC Staff - Assist TSC Coordinator, as requested, with operational aspects of TSC.
DISCUSSION A.
TSC Function TSC personnel will provide guidance to the Control Room operating personnel in the management of abnormal conditions and in accident mitigation.
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Page 2 of 4 recovery operations, the TSC shall, provide pla~nt systems support for the management personnel who will be-located in the Emergency Operations Facility (EOF). -The TSC will function as the primary. information source to the EOF 'ar to the NRC for plant operations..The TSC shall perform'the. functions of-the EOF until the EOF is staffed.
B.
Location The TSC is located on the second. floor of the Administration Building.
C.
Data and Information Resources The TSC area contains the following:
1.
A comple'te set of-up-to-date as-built drawings of plant structures and
~
systems. (Normally located in the-Library on 3rd floor of Administration Building.
2.
The current Plant Technical Specifications.
3.
Plant Operating Procedures 4.
Safety Analysis Report (USAR) 5.~
Complete set of essential technical manuals 6.
Emergency Plan Implementing Procedures D.
Communications The TSC contains the following:
l 1.
NRC Operations - Hotline Telephone (ENS) 2.
NRC Health Physics - Dedicated Telephone (HPN) 3.
EOF-to TSC'- Hotline Telephones (2) 4.
Control Room - Intercom t
5.
Access Control - Intercom 6.
State E0C to TSC - Hotline Telephone 7.
State DES Radio Hotline 8.
Commercial Telephones (4) 9.
Plant Extensions (17)
- 10. Telecopier
- 11. Control room to TSC Party Line E.
Equipment and Facilities The TSC contains the following:
1.
Two Process Computer CRT's (Control Room Repeaters)
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Equipment and Facilities (Cont'd.)
2.
Off-Site Dose Projection Computer Terminal 4.
Apple Computer, CRT & Printer 5.
Instrument Cabinet (4 Strip Chart Recorders) 6.
-7.
Status Boards 8.
Wall Maps 9.
Procedure form racks 10.
Portable CAM
- 11. Area Radiation Monitor F.
Supplies 1.
Paper and pens 2.
Self-Reading Dosimeters and charger 3.
. Telephone headsets 4.
"Mega phone 5.
Thyro-bloc tablets 6.
Log books 7.
Chart paper 8.
MET printer paper 9.
Telecopiar paper PROCEDURE PART I - ACTIVATION STEP 1 Activate computer CRT's (push in button on upper right hand corner of CRT's).
l STEP 2 Activate CRT for the Control Room CCTV (switch on CRT and camera control).
Check with the Control. Room to verify that the camera is turned on.
STEP 3 Check the TSC instrument cabinet.
This cabinet contains an ARM
-~
which is normally on.
The four (4) charts are scram activated but can be turned on by momentarily turning the power switch to test.
Activate the charts if not already activated and mark the chart with date, time and initials.
STEP 4 Check the intercoms to Access Control and Control Room.
l NOTE:
If the OSC intercom does not work, check switch on bottom of unit.
STEP 5 If habitability is of concern, request radiological survey of the TSC. The REC will be responsible for ensuring routine surveys of the TSC and for evaluation of the results.
Prior to the REC's arrival, a survey may be requested of any available Radiation-Protection personnel.
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4 Proc: dure A.2-f06 Revision 4 Page 4 of 4 STEP 6 Activate the CAM used to monitor the air in the TSC.
(The CAM is located on a cart in the TSC.) Move the cart to the hallway south of the TSC and activate the system by plugging the electrical cord into a wall outlet.
Mark the chart with date, time and initials.
STEP 7 Clear the TSC of interferring equipment, personnel or furniture.
STEP 8 Move the aperture card file and Minolta RP407 card reader from the library on 3rd floor down to the TSC.
PART II - OPERATION NOTE:
The following is a list of procedural steps for which the TSC Coordinator is responsible.
Each step which contains the word
' continually' means that the step should be repeated regularly as needed while the TSC is in operation.
9 STEP 1 Continually maintain the Emergency Organization and E0F Status boards.
This will require an exchange of information with the other emergency centers. The desired result of the exchanges is that all response centers have up-to-date status boards.
If one or more of the TSC staff positions is not filled, determine from the Emergency Director whether further efforts should be made to fill the position (s).
STEP 2 If the emergency condition is expected to extend beyond the time when TSC personnel should be relieved, assist the Emergency Director with setting up a shift coverage schedule.
Continually ensure 24-hour coverage for TSC duties.
STEP 3 Continually ensure logistical support for TSC personnel, e.g. stationary supplies, food and beverages (especially coffee).
STEP 4 Continually ensure that the TSC is kept clear of unassigned and-unnecessary personnel who may interfere with TSC operation.
The Security Group Leader may be requested to assist in this function.
i STEP 5 If the personnel accountability procedure is implemented, assist the l
Security Group Leader with accounting for TSC personnel.
l l
REFERENCES l
1.
Monticello Nuclear Generating Plant Emergency Plan l
2.
Monticello Nuclear Generating Plant Operations Manual l
3.
NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" l
l WP/kk I
4 Procedure A.2-201 Ravision 3
~
Page 1 of 9 Op. Com. Rev. Req'd.
Yes X No Q.A. Review Req'd.
Yes No X ALARA Review Reg'd.
Yes X No ON-SITE MONITORING AND PROTECTIVE ACTION CRITERIA Procedure A.2-201 Prepared by: l b d w # ; ALARA Review: 6dkIkw DateI!/dO 5 0 /Ir. d < -
Q.A. Review:
Revision 0 Date 3/28/81 Reviewed by:
t Operations Committee Final Review: Meeting Number NW Date
-/. r.*y-n Approved by:
bk Date 7 ? ~5 Op. Com. Results Review:
Not Required Mtg. #
948 Date 3/25/81 PURPOSE The purpose of this procedure is to (1) provide coordination and d'irection for on-site radiological monitoring efforts during an emergency and (2) to provide criteria for on-site protective action implementation.
This procedure is not intended to supersede procedures A.2-104 (Site Area Emergency) or A.2-105 (General Emergency) which direct specific levels of evacuation.
These evacuations should be implemented per the applicable procedure.
However, if the criteria contained in this procedure is more limiting (i.e., calls for an earlier or higher level of evacuation) than procedures A.2-104 or A.2-105, then this procedure shall take precedence.
CONDITIONS AND PREREQUISITES A.
A declared emergency condition at the Alert level or higher exists, or B.
The Emergency Director or Radiological Emergency Coordinator, has reque-ted a survey of areas within the site boundary (including in plant areas).
PRECAUTIONS A.
Monitoring teams should be reminded to remain alert to their own exposure and request relief if their cumulative exposure approaches a MNGP adminis-trative control level.
The Emergency Director may authorize exposure limit extensions, if necessary.
B.
Communications with the monitoring team will normally be via operations l
portable radios.
Since radio communications at this frequency can be inter-cepted by commercially available scanners, ensure that all communications related to reporting survey data are brief, factual and free of exclamatory or alarming expressions.
The DVP mode will be used unless directed otherwise.
C.
Ensure that instructions and data transmissions are carefully worded and
' clearly understood.
1.
Avoid abbreviations (such as " mrem" which could be confused with
" rem").
Use the complete word or unit, i.e., " millirem".
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Proccdure A.2-201 Revision 3 Page 2 of 9 2.
Clearly identify survey locations, using predesignated survey location numbers, map coordinates, and equipment / building names, as available.
D.
Prior to recommending an evacuation of site personnel to the Emergency Director, the Radiological Emergency Coordinator should determine, based on the best information available, that evacuation is the protective action that will result in the lowest personnel exposure.
In making an evacuation recommendation, the Radiological Emergency Coordinator should consider (1) dose rates at Assembly Points, on-site and along evacuation routes; and (2) whether or not these conditions can be mitigated prior to personnel receiv-ing significant exposures.
E.
Evacuations should be accomplished either before or after the passage of the release, and evacuation routes should be chosen that lead personnel away from the path of the plume.
ORGANIZATION AND RESPONSIBILITIES Emergency Director (ED) - Overall responsibility Radiological Emergency Coordinator (REC) and/or Monitoring Section Leader (MSL) - Direct on-site survey effort, review results, and implement or recommend onsite protective actions.
Radiation Protection Specialist -
Perform surveys, collect and analyze
)
samples and report results.
' /
Radiation Protection Coordinator -
Assist REC /MSL with coordination of l
survey teams.
-DISCUSSION A.
The extent and degree of on-site radiological monitoring following a release of radioactive material will depend on the nature, the severity, the physical /
chemical-form and the radioisotopic composition of the release. The Emergency Director, Radiological Emergency Coordinator or MSL will determine the extent and nature of post-accident radiological monitoring.
B.
For releases which occur during normal working hours, sufficient Radiation Protection personnel will be available to support several monitoring teams.
During other times, it may only be possible to deploy one monitoring team.
In these circumstances, the ED, REC or MSL will assign priorities for radio-logical monitoring based on the known or expected extent and severity of the release and/or related radiological conditions, while calling in additional personnel.
C.
In the event of a radioactivity release determined or estimated to be equivalent to or greater than the levels contained in Guideline No. 1,
" Radioactive Effluents" for a ALERT in Procedure A.2-101, " Classification of Emergencies", a monitoring team should be dispatched to perform a beta gamma dose rate survey on-site.
The purpose of this survey is to confirm that a release is (has) taken place, and to assess the need for WP/kk
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- Procedure A.2-201 Revision 3 Page 3 of 9 protective. actions. The starting point of this survey should be consistent with the expected source and magnitude of the release and extend out to the site perimeter in the sector with the highest projected. dose rate.
This survey should be limited to specific survey points rather than a " scan" survey.in order to obtain initial data rapidly.
Following this, time and personnel permitting,'more extensive scan surveys may be performed,
. if warranted. Based on the survey results at Lthis point, the monitoring team _should proceed along the site perimeter for a sufficient distance, in either direction, to ensure that the maximum levels have been identified.
This survey should be performed periodically if the release continues and if personnel are available.
D.
Silver zeolite cartridges will be used for all air samples. All sample media obtained by the monitoring teams will be retained for possible.
further analysis.
NOTE:
Silver Zeolite (and charcoal cartridges if desired) may be reused during off-site monitoring in a particular emergency, as long as the cartridges exhibit count rates less than back-ground, and are undamaged.
In particular, silver zeolite cart-ridges used for low-level environmental monitoring (negligible count rate) could be advantageously used within the plant in areas having high noble gas activity as well as high radioiodine concentrations. The Radiological Emergency Coordinator or MSL will' direct the reuse of sample cartridges if warranted.
E.
The habitability or conditions in the following areas should be assessed 1
l as specified.
[
1.
If a Local Evacuation has been initiated, based on area radiation monitors or continuous air monitors, an appropriate survey should be performed to verify the alarm condition, and to attempt to determine the reason for the increase from normal levels.
2.
If a Plant Evacuation is declared, a survey should be performed in the primary assembly areas to assess the habitability of the assembly area, in addition to the survey described in Paragraph C above.
3.
The Control Room and TSC ARM readings should be monitored, and an air sample for particulate and iodine radioactivity should be obtained, if the monitor indicates the need, or if airborne activity is suspected.
-2 4.
If high airborne levels (> 10 pCi/cc) are known or expected to exist in the Reactor Building, dose rate surveys should be performed in areas which'can receive " shine" radiation from the 1027-1074 level of secon-dary containment.
i 5.
Dose rate surveys.should be performed in the proximity of the stack if high release rates (> 10 Ci/sec) are occurring.
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Procedure A.2-201 R vision 3 Page 4 of 9 6.
If significant fuel damage is known or expected to have occurred
(> 100 R/hr on the con 6ainment monitor or > 100 pCi/cc in the reactor
)
coolant), surveys should be performed around the perimeter of the plant structure, especially near the Reactor Bldg. railroad doors.
7.
The habitability of the location of the security guard at the access road barricade should be assessed, and of any personnel who may be in the Guard House.
8.
Assess contamination levels of any food, water, or eating / food prepar-ation surfaces in the plant, guard house, or any other eating area within an evacuated area, i.a.w. procedure A.2-402.
9.
The habitability of the OSC, TSC and Access Control Areas should be l
assessed.
PROCEDURE STEP 1:
Use available information (meteorological information, effluent monitors, radiation monitors, etc.) to define sector (s) or area (s) to be monitored.
Continually review Attachment 1 to ensure the proper areas are being surveyed as necessary.
-STEP 2:
Assemble monitoring team (s).
Ensure that at least one member of each team is qualified to perform emergency surveys per Procedure A.2-403 or A.2-410, whichever is applicable.
STEP 3:
Brief monitoring team (s) on sector (s) or area (s) to be monitored; radiological conditions and other potential hazards that may be encountered; precautions to be observed; and protective clothing or equipment as necessary.
NOTE:
If necessary, ensure that Emergency RWP checklists and/or Emergency Exposure Authorizations are initiated.
STEP 4:
Dispatch monitoring team (s). Maintain frequent radio contact and track progress of team (s) on a map or plan view as appropriate.
STEP 5:
Record monitoring data as it is received over the radio (Form No.
5790-202-1 may be used for. this purpose).
Direct backup readings or samples be taken if appropriate. Remind team members to monitor their own exposures.
STEP 6:
If initial results indicate that more complete data is needed, or that adjacent areas should be surveyed, direct monitoring team (s) to perform additional monitoring at specified locations.
STEP 7:
Determine the need for contamination control measures and implement Procedure A.2-402 if necessary.
STEP 8:
Upon completion of monitoring recall monitoring team (s).
Instruct team leader to report to the TSC for debriefing if necessary.
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Procedure A.2-201 Revision 3 Page 5 of 9 STEP 9:
Evaluate monitoring data. Compare results to criteria in Attach-ment 2, On-Site Protective Action Criteria, and implement or recommend protective actions as appropriate to protect on-site personnel.
If you are recommending an evacuation, initiate Form No. 5790-201-1, Evacuation Criteria Checklist (Attachment 3) - and forward to the Emergency Director.
REFERENCES 1.
Monticello Nuclear Generating Plant Emergency Plan 2.
Monticello Nuclear Generating Plant Operations Manual ATTACHMENTS 1.
On-Site Monitoring Checklist 2.
On-Site Protective Action Criteria 3.
Example of Evacuation Criteria Checklist 1
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Procadura A.2-201 R2 vision 3 Page 6 of 9 ATTACHMENT 1 x
Page 1 of 1 ON-SITE MONITORING CHECKLIST I
1.
Assess habitability in the following areas, as appropriate.
a.
Control Room /TSC /OSC b.'
Access Control (including SAS) a c.
Guard House d.
Assembly Point a
e.
Security guard at access road barricade f.
Other site locations in which it is known or suspected people may be present, such as the cold shop, office trailers, EPA field station, Big Oaks Park.
The Owner Controlled Area Log should be utilized to verify all appropriate locations are checked.
Issue TLD's/SRD's to personnel in these areas if dose rate is
> 1 mR/hr or at REC /MSL discretion.
I I
NOTE:
The REC /MSL must ensure that, when dosimetry is issued, the information is recorded and dosimetry is collected, as appropriate.
2.
Assess radiological conditions in following special areas, as appropriate.
a.
site areas which can be affected by 1027-1074 airborne shine b.
stack area if high ' release rate c.
plant structure perimeter d.
food, water or eating / food preparation surfaces e.
Local evacuation areas f.
Protected area perimeter
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4 Procedure.A.2-201 Revision 3 Page 7 of 9 ATTACHMENT 2 Page 1 of 2 On-Site Protective Action Criteria Whole Body Exposure Rates (mrem /hr)
Criteria Action Significant Evacuate the affected buidling(s) increase (2 x normal) in the plant has occurred s
or is imminent.
> 1 in Evacuate occupied areas not part of emergency response Clean Area
> 10 Consider evacaution of women who still may be present.
> 100 Evaluate personnel doses.
Execute A.2-401 for those personnel approaching administrative limits and deemed by the Emergency Director as vital to the emergency response effort.
Evacuate all others.
> 1000 Consider evacuation of all affected areas except the Control Room.
2 Smearable Surface Contamination Levels (dpm/100 cm )
Criteria Action Significant Evacuate affected areas or building (s).
increase in the plant has occurred or is imminent.
l
> 100 in Evacuate occupied areas within the Clean Area not part of Clean Area emergency response effort; control eating, drinking and smoking in other occupied areas.
t
> 500 Consider protective clothing use
> 5000 Ensure protective clothing use l
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Procedure A.2-201 R: vision 3 Page.8 of 9 ATTACHMENT 2 Page 2 of 2 Airborne Radioactivity. Levels (MPC)
Criteria Action
> 0.1 Evacuate occupied areas not part of emergency response effort.
> 0.25 Evaluate personnel MPC-hrs Limit exposures to ( 40 MPC-hrs / week if possible.
Use respirators whenever practical.
.)1 Evacuate all personnel not deemed by the Emergency Director as vital to the emergency response effort.
Consider use of KI i.a.w. A.2-304.
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ProcGdure A.2-201 Revision 3 Page 9 of 9 ATTACHMENT 3 Form 5790-201-1 Revision 1, 02/26/82 Page 1 of 1 Example of i
~
EVACUATION CRITERIA CHECKLIST i
1.
Condition (s) considered as possible reasons for evacuation:
REC Initials Time Date 2.
Area (s) affected:
REC Initials Time Date 3.
Precautions Section of Procedure A.2-201 given full consideration.
REC Initials Time Date 4.
Type of evacuation recommended (if applicable)
If Local Evacuation, area (s) evacuation is recommended for:
REC Initials Time Date l
5.
Evacuation (implemented /not implemented)
Emergency Director
, Time Date NOTE:
After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.
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Procedure A.2-205 Revision 2 Page 1 of 8 Op. Com. Rev. Req'd.
Yes ~X No Q.A. Review Reg'd.
Yes No X ALARA Review Reg'd.
Yes __ No X PERSONNEL ACCOUNTABILITY A.2-205 Prepared by: bhwJu ALARA Review:
Revision 0 Date 3/27/81 Reviewed by:
Cd/hMO-Q.A. Review:
Revision 0 Date 3/28/81 Operations Committee Final Review: Meeting Number 1199 Date 4/28/83 Approved by:
Date 6 & 3 Op. Com. Rasults Review:
Not Reouired Mtg. # 948 Date 3/25/81 PURPOSE The purpose of this procedure is to provide instructions for accounting for personnel in the event of an evacuation. ' This procedure applies specifically to the three levels of evacuation described in procedure A.2-301, Emergency Evacuation.
CONDITIONS AND PREREQUISITES A.
An emergency condition has occurred at Monticello Nuclear Generating Plant resulting in radiological and/or other hazardous conditions and making personnel evacuation to unaffected areas necessary.
B.
Procedure A.2-104 (Site Area Emergency), A.2-105 (General Emergency), or A.2-301 (Emergency Evacuation) has been implemented.
ORGANIZATION AND RESPONSIBILITIES Emergency Director -
Overall in-charge;-responsible for ensuring completion of this procedure whenever implemented.
Security Group Leader - Responsible for conduct of this procedure when implemented for plant or site evacuation.
Assembly Point Coordinator - Each responsible for accountability of personnel TSC Coordinator -
reporting to respective response centers.
OSC Coordinator -
Site Superintendent -
R.P. Coordinator -
l CAS Operator -
Responsible for security computer operations as directed by Security Group Leader.
DISCUSSION A.
In the case of a plant evacuation, the accounting process should be completed within 30 minutes.
The purpose of a speedy accounting is to allow for a timely search for missing personnel.
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This procedure provides both a primary and a backup method of doing the accou-ing in the event of a plant or site evacuation. The primary method de' pends o.
the availability of the security computer system and is quick and efficient.
The backup method is a manual method which is much slower and not 100% efficient.
PROCEDURE PART I - Local (or Building) Evacuation NOTE:
This is for a localized area only.
The number of personnel involved in a local evacuation is normally small, and involves areas which when occupied, are normally attended by supervisory personnel. The following methods, thus, should be applicable.
STEP 1:
Contact the supervisor (s) of the pertinent work party (ies) and verify the presence of individuals in the work party (ies).
Initiate Personnel Account-ability-Local Evacuation Checklist, Form 5790-205-1 (Attachment 1).
STEP 2:
If any individuals are not accounted for they should be paged.
NOTE 1:
Their presence on site may be verified by a computer printout of personnel on site (EONS Log), with Security Guardhouse sign-in sheets (for visitors), and/or with other pertinent registers or logs.
NOTE 2:
If further verification that all personnel are clear of the
. N area is necessary, consider either a search of the area or a check of dosimeter exposure cards in the ACTIVE racks.
A last resort may be a plant evacuation and full accounting.
STEP 3:
Advise the Emergency Director to initiate Search and Rescue activities (Procedure A.2-303) if an individual (s) is still unaccounted for and suspected to be in a hazardous area, trapped or injured.
Complete Personnel Accountability-Local Evacuation Checklist, Form 5790-205-1 (Attachment 1).
PART IIs - Plant / Site Evacuation - Primary Method l
STEP 1:
Direct CAS Operator (X-1246) to enter the EEV command to put the security computer in the accounting mode.
Initiate checklist, Form 5790-205-2 (Attachment 2).
STEP 2:
Notify the OSC Coordinator, R.P. Coordinator and TSC Coordinator to ensure l that each person in the various response centers inserts his/her Security Badge into the reader designated for emergency personnel accounting.
Further direct a return notification when all personnel are processed.
CAUTION:
Caution these people to ensure an orderly proceeding and to make sure that cards are inserted properly to prevent alarms and that the red light is received after each card.
If possible, assign one person to insert all cards to prevent tamper alarms due to improper techniques.
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Procedure A.2-205 Revision 2 Page 3 of 8 STEP 3 Notify the Site Superintendent (in the Control Room) and the Security Shift Supervisor (in the Guard House).
Direct that a list of names, initials, and badge numbers be compiled for all personnel in the area.
The Control Room list should include the SS Office and the security list should include the CAS, SAS and PCR operators.
ST'P 4:
If the Substation Assembly Point or an offsite assembly point is E
activated, notify the CAS Operator and direct that an EVACNT Report be generated as soon as all badges from evacuating personnel have been processed.
If the Warehouse Assembly Point is activated, the Coordinator will notify the Security Group Leader when all personnel have been processed through the card readers. Upon this notification, direct the CAS Operator to generate an EVACNT Report.
In both cases direct that the EVACNT list be transmitted and/or carried to the TSC immediately upon completion along with the list of personnel who reported to the Guard House, the Visitors Log, and the OWNER-CONTROLLED AREA LOG. Also notify the Site Superintendent and direct that the list of personnel in the Control Room be carried to the TSC.
NOTE:
During the accounting process, persons at;empting to enter the Protected Area will not be permitted to do so.
These persons should be held in the Conference Room in the Security Building until the EVACNT list has been printed. After that, individuals may be admitted with permission of the Emergency Director.
Requests for such permission should be forwarded through the Security Group Leader.
STEP 5:
When the EVACNT list arrives at the TSC, take immediate action to account for anybody whose name appears on the report. As soon as it is recognized that one or more individuals are still missing, immediately attempt to determine the possible location of the individual.
Direct appropriate personnel to:
a.
Check response centers for late arrivals b.
Page the individual c.
Confer with the individual's supervisors or co-workers d.
Conduct brief searches of the last known location, if possible e.
Call the individuals home f.
Report back with any information relating to a e STEP 6:
If any individual remains unaccounted for following STEP 5, and the individual may be in a hazardous area, trapped or injured, advise the Emergency Director to implement Search and Rescue Activities (Procedure A.2-303).
STEP 7:
Direct CAS operator to enter TEV command to take computer out of the accounting mode and complete Personnel Accountability-Plant / Site Evacuation Checklist, Form 5790-205-2 (Attachment 2).
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Procedure A.2-205 Revision 2 Page 4 of 8 PART iib - Plant / Site Evacuation - Backuo Method (To be used when security computer is not available.)
)
STEP 1:
Direct the CAS Operator (X-1246) to send tha most current EONS list to the active assembly point.
Initiate che ulist, '5790-205-3, (Attachment 3).
's l s
j STEP 2:
Notify the Assembly Point Coordinator to disregard procedure step C.
requiring use of card readers and to assemble personnel in preparaE$0n
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for roll call accounting.
Further direct Coordinator to-(1) contact roll call using EONS listing and to cross off names of yersons at th'e m assembly point, and (2) to send list to TSC immediately after roll call is complete.
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STEP 3:
Notify the OSC Coordinator, R.P. Coordinator, TSC Coordir.ator, Site l,
Superintendent (in Control Room) and Guard House.' Direct that a list e
of names, initials, and TLD numbers be generated,for all persons at the' various response centers.
Further direct that the to the TSC as soon as they are completed and that @,ii.sts be transportyd g
e-VISITORS LOG and OWNER-CONTROLLED AREA LOG be included with the list from the Guz:rd HCuse. p s
4 STEP 4:
When the EONS list arrives at the TSC, reconcile the EONS list with the other response center lists.
(Use as many persons as necessary to accomplish this task in a timely manner.)
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STEP 5:
As soon as it is recognized that one or more individuals are stijl s
missing, immediately attempt to determine the possible locadon of \\]-
y the individual. Direct appropriate personnel to:
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Check response centers for late arrival; '
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b.
Page the individual 5, I
's-c.
Confer with the individual's supervisors or co-workers d.
Conduct brief searches of the last known location, if possible e.
Call the individuals home l
f.
Report back with any information relating to a-e i
y STEP 6:
If any individual remains unaccounted for following STEP 5, and~tfie individual may be in a hazardous area, trapped or injured, advise the Emergency Director to implement Search and Rescue Activities s g.-
(Procedure A.2-303).
Complete Personnel Accountability-Plant /, tite Evacuation Backup Method Checklist, Form 3750-205-3 (Attachment'3)
REFERENCES 1.
Monticello Nuclear Generating Plant Emergency,Plaa I"
2.
NUREG-0654/ FEMA-REP-1, " Criteria for Preparation MG TvUbakion fif(
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Radiological Emergency Response Plans and Preparedach in Support j'
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of Nuclear Power Plants"
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Procedure A.2-205 R vision 2 Page 5 of 8 w
ATTACHMENTS 1.
Example of Personnel Accountability - Local Evacuation Checklist, Form 5790-205-1
. ~
F 2.
Example of Personnel Accountability - Plant / Site Evacuation Primary s.
Method Checklist, Form 5790-205-2 s
3.
Example of Personnel Accountability - Plant / Site Evacuation, Backup Method Checklist, Form 5790-205-3
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ATTACHMENT 1 Form 5790-205-1 I
Revision 2, 2/13/82
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Example of
/- _,
PERSONNEL ACCOUNTABILITY - LOCAL. EVACUATION CHECXLIST g
(For Use With Proceduze A.2-205) 1.
Contacted supervisor (s) of evacuated s
work party (ies).
Sec. Group [LE Time s,
Date l>
g 2.
Attempted to locate personnel who were not accounted for.
Sec. Group Lor.
Time Date 6
3.
Notified ED that:
a)
All personnel have been Sec. Group Lor.
Time Date 3
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b)
One or more 1ndividuals are missing and could not be located.
Sec. Group Ldr.
Time Date I
i NOTE:
After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.
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Procedure A.2-205 j.
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Revision 2 Page 7 of 8 ATTACHMENT 2 Form 5790-205-2 Revision 3, 04/15/83 a
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. Example of j
PERSONNEL ACCOUNTABILITY - PLANT / SITE EVACUATION PRIMARY METHOD CHECKLIST (ForUseWithF[ocedureA.2-205) i i
1.
Directed CAS Operator (X-1246) to setup computer for accounting.
l Sec. Group Ldr.
Time Date 2.
Notified TSC, Access Control and OSC l
to implement accounting via card readers.
e Sec. Group Ldr.
Time Date 3.
Notified Control Room and Guard House to generate lis.ts.
Sec. Group Ldr.
Time Date 4.
Directed CAS Operator to generate EVACNT List.
Sec. Group Ldr.
Time Date i
5.
Notified response centers to forward lists to TSC.
Sec. Group Ldr.
Time Date 6.
Reconciled lists.
~
Sec. Group. Ldr.
Time Date 7.
Notified ED that-i-
a)
All personnel have been y
accounted for, Sec. Group Ldr.
Time Date g
4 b)
One or more individuals are missing 1
i and could not be located.
Sec. Group Lor.
Time Date 8.
Directed CAS Operator (X-1246) to take computer out of accounting mode.
Sec. Group Ldr.
Time Date
]
NOTE:
After this checklist is completed and is not required for immediate
~~
use, it shall be placed in the appropriate container provided for s
Emergency Records.
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Procedura A.2-2 5 R; vision 2 Page 8 of 8 ATTACHMENT 3 Form 5790-205-3 Revision 0, 02/13/82 Page 1 of 1 Example of PERSONNEL ACCOUNTABILITY - PLANT / SITE EVACUATION BACKUP METHOD CHECKLIST 1.
Directed CAS Operator to send EONS List to Assembly Point.
Sec. Group Lor.
Time Date 2.
Notified Assembly Point Coordinator to use roll call and to send list to TSC upon completion.
- Sec. Group Ldr.
Time Date 3.
Notified response centers to generate lists and forward to TSC.
Sec. Group Ldr.
Time Date a
4.
Reconciled lists.
I
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5.
Notified ED that:
a)
All personnel have been accounted for, Sec. Group Ldr.
Time Date SE i
b)
One or more individuals are l
missing and could not be located.
Sec. Group Ldr.
Time Date NOTE After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.
l l
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Procedure A.2-301 Revision 2 Page 1 of 10 Ops. Com. Rev. Reg'd. Yes X No Q. A. Review Req'd.
Yes No X ALARA Review Req'd.
Yes T No EMERGENCY EVACUATION A.2-301 Prepared by: /L[w/ J ALARA Review:
6 h/0cf h Date
'/3 Reviewed by: G3//'hNS Au-Q.A. Review:
Revision 0 Date 3/28/81 Operations Committee Final Review: Meeting Number 1199 Date 4/28/83 Approved by:
kbA Date 6-343 Op. Com. Results Review:
Not Reauired Mtg. #
948 Date 3/25/81 PURPOSE This procedure provides instructions for implementing an emergency evacuation of radiologically affected areas within the Monticello Nuclear Generating Plant and adjacent areas onsite.
This procedure is applicable to Local, Plant and Site Evacuations; it does not apply to evacuation of members of the general public from affected areas beyond site boundaries.
The basic instructions in this procedure may also be applied as appropriate, to evacuations related to other hazards affecting habitability, such as fire, toxic gas, etc.
CONDITIONS AND PREREQUISITES A.
An emergency condition has occurred at Monticello Nuclear Generating Plant resulting in radiological and/or other hazardous conditions.
B.
" Site Area Emergency", Procedure A.2-104 or " General Emergency", Procedure A.2-105 have been implemented.
PRECAUTIONS A.
Prior to implementation of an evacuation, the Emergency Director (Shift Supervisor until relieved) should determine, based on the best information available, that evacuation is the protective action that will result in the lowest personnel exposure.
In making an evacuation decision, the Emergency Director should consider (1) dose rates at Assembly Points, on-site, and along evacuation routes; and (2) whether or not these conditions can be mitigated prior to personnel receiving significant exposures.
B.
Evacuations should be initiated either before or after the passage of the release, and evacuation routes should be chosen that lead personnel away from the path of the plume.
WP/kk
A Procedure A.2-301 Revision.2 Page 2 of 10 PERSONNEL REQUIREMENTS a
Emergency Director PROCEDURE NOTE:
The checklists pertaining to this procedure should be completed, but completion of the checklists shall not delay evacuation.
Local Evacuation NOTE:
A Local Evacuation may be initiated by personnel in the affected area in response to observed conditions, survey instrument indications, or locally-alarming radiation monitors. The procedure steps below assume that the evacuation is initiated by indications / alarms observed in the Control Room. As a result, some steps may not be applicable to all Local Evacuations.
STEP 1:
Have the following announcement made over the public address system:
" ATTENTION ALL PERSONNEL: THERE IS A (specify hazard)
INDICATED IN (Specify area). ALL PERSONNEL SHOULD EVACUATE FROM THE (Specify area) AND STAY CLEAR OF (specify area).
This message should be repeated twice and additional instructions may be provided as required.-
Initiate Emergency Evacuation Checklist, Form 5790-301-1 (Attachment 1).
STEP 2:
Ensure that the applicable portion of procedure A.2-205, PERSONNEL ACCOUNTABILITY, is implemented.
STEP 3:
Direct the Radiation Protection Group to assume control of entries to the affected area for exposure control purposes.
NOTE:
When the hazard has been cleared and the Radiation Protection Group has surveyed the area, allow a return to normal use of the area or establish appropriate access control provisions l
for restricted use.
l STEP 4:
Complete Emergency Evacuation Checklist, Form 5790-301-1
(
(Attachment 1).
I l
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Procedure A.2-301 Revision 2 Page 3 of 10 Plant Evacuation STEP 1:
Determine which onsite assembly point will be used.
Consider wind direction, assembly point capacity and possible habitability problems.
STEP 2:
If not already designated, assign an Assembly Point Coordinator.
(See Procedure A.2-001 for qualified personnel listing.) Direct Coordinator to implement procedure A.2-302, ASSEMBLY POINT ACTIVATION, if not already implemented.
STEP 3:
Direct the Security Group Leader to prepare to implement procedure A.2-205, PERSONNEL ACCOUNTABILITY.
STEP 4:
Direct the REC to provide personnel for monitoring and assistance at the Assembly Point.
STEP 5:
Direct the Control Room Operator to sound the evacuation siren and to make the following announcement over the public address system:
" ATTENTION, ALL PLANT PERSONNEL:
THIS IS A PLANT EVACUATION.
ALL MEMBERS OF THE EMERGENCY ORGANIZATION REPORT TO YOUR DUTY STATIONS.
ALL OTHER PERSONNEL PROCEED TO THE (Warehouse / Substation /Other) ON-SITE ASSEMBLY POINT."
The message thould be repeated twice and additional instructions may be provided as required.
Initiate Emergency Evacuation Checklist, Form 5790-301-2 (Attachment 2).
STEP 6:
Implemer.t the applicable portion of Procedure A.2-205, PERSONNEL ACCOUNTABILITY.
I STEP 7:
Direct the Radiological Emergency Coordinator to assume control of entries to the affected area for exposure control purposes and to implement procedures A.2-407, PERSONNEL AND VEHICLE MONITORING, and A.2-201, ONSITE MONITORING AND PROTECTIVE ACTION CRITERIA.
I STEP 8:
When the accounting procedure is completed, direct the removal of unnecessary personnel from the site according to the following:
a.
Unnecessary personnel in Control Room, OSC, and TSC should be either sent home or to the assembly point or EOF to Stand-by; b.
Key personnel at the assembly point should be authorized re-entry or directed to Stand-by; c.
Other plant personnel at the assembly point should be sent home or to the EOF; WP/kk
Procedure A.2-301 Revision 2 Page 4 of 10 d.
Non plant personnel at the assembly point should be directed offsite; All personnel in the Owner Controlled Area, including the office e.
trailers and EPA field station, should be directed offsite.
(The Security Group should be directed to conduct an orderly evacuation with means available).
STEP 9:
Complete Emergency Evacuation Checklist, Form 5790-301-2 (Attachment 2).
Site Evacuation NOTE:
The condition under which a Site Evacuation would be initiated could involve significant release off-site with resultant contamination of environmental surfaces off-site.
Under these conditions, delaying Site Evacuation to monitor and/or decontaminate personnel or vehicles would be superfluous, in light of the potential for re contamination offsite.
In this case, personnel should be directed to proceed directly to the upwind offsite assembly area for monitoring.
If all offsite assembly areas are within sectors from which the population is being evacuated, the Emergency Director, in cooperation with NSP manage-ment, State and County Agencies, shall designate an assembly area at which personnel monitoring will be performed.
(Possible offsite assembly areas are the
)
Sherco Plant and the NSP Service Center in Monticello.)
In this event, vehicles will be monitored as provided in the Corporate Emergency Plan Implementing Procedures (EPIP 1.1.16).
STEP 1:
If time and conditions allow, direct the Radiological Emergency Coordinator to establish appropriate radiological monitoring stations consistent with the guidelines in the above and Procedure A.2-407, (Personnel and Vehicle Monitoring).
STEP 2:
Determine which offsite assembly point will be used.
Consider wind direction, assembly point capacity and possible habitability problems.
Also determine which route will be used to get to the assembly point.
STEP 3:
Direct Security to provide appropriate personnel to direct traffic on site and at the intersection of the site access road and RTE 75 and to handout copies of Form 5790-301-4, SITE EVACUATION INSTRUCTIONS.
Depending on other operations, State Police or local police may relieve the security guard directing traffic off-site.
NOTE:
Security personnel directing traffic should be equipped with appropriate respirators and protective clothing if radiological conditions warrant.
They should also have a supply of Form 5750-301-4, SITE EVACUATION INSTRUCTIONS.
WP/kk 1
Procedure A.2-301 Revision 2 Page 5 of 10 STEP 4:
Direct the Control Room Operator to sound the evacuation siren and to make one of the following announcements over the public address system:
" ATTENTION ALL PERSONNEL: ALL PERSONNEL EXCEPT THOSE WITH EMERGENCY ASSIGNMENTS SHALL PROCEED TO THE PERSONNEL MONITORING STATION AT (Specify location), AND THEN PROCEED TO YOUR CARS AND ORIVE TO THE AUTOMOBILE MONITORING AREA AT (specify location).
ONCE RELEASED, PROCEED T0 (specify location and route) AND AWAIT FURTHER INSTRUCTIONS."
or,
" ATTENTION ALL PERSONNEL: ALL PERSONNEL EXCEPT THOSE WITH EMERGENCY ASSIGNMENTS SHALL EVACUATE THE SITE IMMEDIATELY.
PROCEED IN YOUR CAR T0 (specify location and route) AND AWAIT FURTHER INSTRUCTIONS."
The message should be repeated twice and additional instructions may be provided as required.
Initiate Emergency Evacuation Checklist, Form 5790-301-3 (attachment 3).
STEP 5:
Ensure that the applicable portion of Procedure A.2-205, PERSONNEL ACCOUNTABILITY, is implemented.
STEP 6:
If not already implemented, direct Radiological Emergency. Coordinator to implement Procedure A.2-201, ON-SITE MONITORING AND PROTECTIVE l
ACTION CRITERIA.
Ensure that assembly points are monitored.
STEP 7 Direct the Security Group to initiate an orderly evacuation of all per-sonnel in the Owner-Controlled Area, including all trailers and the Guard House.
STEP 8 Direct unnecessary personnel in Control Room, OSC and TSC to stand-by at the EOF or to go home.
STEP 9:
When conditions allow, release personnel at the assembly point or issue further instructions to them.
Key personnel may be authorized re-entry to the site.
STEP 10: Complete Emergency Evacuation Checklist, Form 5790-301-3 (Attachment 3).
REFERENCES 1.
Monticello Nuclear Generating Plant Emergency Plan 2.
Monticello Nuclear Generating Plant Operations Manual 3.
NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" WP/kk t
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Procedure A.2-301 '
Revision 2 Page 6 of 10 ATTACHMENTS
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1.
Example of Emergency Evacuation Checklist-Local Evacuation, Form 5790-301-1
{
2.
Example of Emergency Evacuation Checklist-Plant Evacuation, Form 5790-301-2 3.
Example of Emergency Evacuation Checklist-Site Evacuation, Form 5790-301-3 4.
Example of Site Evacuation Instructions, Form 5790-301-4 4
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Procedure A.2-301 Revision 2 Page 7 of 10 I
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ATTACHMENT 1 Form 5790-301-1 Revision 2, 1/21/82 Page 1 of 1 Example of EMERGENCY EVACUATION CHECKLIST LOCAL EVACUATION (For Use With Procedure A.2-301) 1.
Declared and announced a Local Evacuation.
ED Initials Time Date 4
2.
Accountability procedure implemented.
t-ED Initials Time Date 3.
Access Control assigned to RP Group.
ED Initials Time Date J
4 L
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NOTE:
After this checklist is completed and is not required for.immediate use, it shall be placed in the appropriate container provided for Emergency Records.
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Procedure A.2-301 i
Revision 2
.Page 8 of 10
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ATTACHMENT 2 i
)
Form 5790-301-2 Revision 2, 1/21/82 Page 1 of 1 Example of EMERGENCY EVACUATION CHECKLIST l
PLANT EVACUATION i-(For Use With Procedure-A.2-301) 1.
Declared and announced a Plant Evacuation.
ED Initials Time Date 2.
Accountability procedure implemented.
l ED Initials Time Date 3.
Access Control assigned to RP Group and monitoring procedures implemented.
,).
ED Initials Time Date 4.
Personnel at Assembly Point released.
ED Initials Time Date 5.
Unnecessary personnel evacuated.
ED Initials Time Date NOTE:
After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records, e
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1 Procedure A.2-301 Rzvision 2 Page 9 of 10 ATTACHMENT 3 Form 5790-301-3 Revision 2, 1/21/82 1
Page 1 of 1 Example of EMERGENCY EVACUATION CHECKLIST SITE EVACUATION (For Use With Procedure A.2-301) 1.
Monitoring station established.
ED Initials Time Date 2.
Traffic control established.
ED Initials Time Date 3.
Evacuation and Assembly Point announced.
ED Initials Time Date 4.
Accountability procedure implemented.
ED Initials Time Date E
5.
Access Control assigned to RP Group and monitoring procedures implemented.
ED Initials Time Date t
6.
-Owner Controlled Area evacuated.
ED Initials Time Date 7.
Unnecessary personnel evacuated from
(
plant.
l ED Initials Time Date l
8.
Personnel at Assembly Point released l
or given further instructions.
L ED Initials Time Date NOTE:
After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for l
Emergency Records.
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Proceduro A.2-301 Revision 2 Page 10 of 10 Form 5790-301-4 Revision 0, 01/30/82 Page 1 of 1 ATTACHMENT 4 Example of SITE EVACUATION INSTRUCTIONS g
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I Evacuation Routes To SherCo A.
West access road to 75 Right on 75 to 24 Right on 24 to 8 Right on 8 to SherCo Assembly Poi l
I B.
South access road to 75
- Left on 75 to 25
- Left on 25 to 11
]
5 Left on 11 to 10 P'
Left on 10 to SherCo Access
,'f To NSP Monticello Service Center s,,,%
C.
South access road to 75 Left on 75 to 39 Right on 39 to Service Center O scatin INSTRUCTIONS 1.
Proceed to offsite Assembly Point
( db along designated route.
/
2.
Keep windows rolled up; turn 1,
heaters and air conditioners off.
-e 3.
Do not smoke, eat or drink.
) l 4.
Do not leave Assembly Point
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'1 until released.
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Procedure A.2-302 Revision 3
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Page 1 of 7 Op. Com. Rev. Reg'd.
Yes X No _
Q.A. Review Reg'd.
Yes _ No X ALARA Review Req'd.
Yes _ No X ACTIVATION OF THE ASSEMBLY POINT A.2-302 REVIEW AND APPROVAL Prepared by: hbed/
ALARA Review:
Revision 0 Date 3/27/81 Reviewed by:
D4 AMtJc-Q.A. Review:
Revision 0 Date 3/28/8I Operations Committee Final Review: Meeting Number
/f f o Date -//2 r/ ra Approved by:
bkM Date 5'-3 -P 5 Op. Com. Results Review:
Not Required Mtg. #
948 Date 3/25/81 PURPOSE This procedure provides information and instruction for the organization, activation and operation of the on-site Assembly Points in support of the Monticello Nuclear Generating Plant and NSP Emergency Plan.
CONDITIONS AND PREREQUISITES An emergency condition which may require plant or site evacuation has been declared at the Monticello Nuclear Generating Plant.
l PRECAUTIONS In the event of a radiological release at MNGP, the Assembly Point may be found unsafe for habitation.
If such a situation occurs, the Emergency Director must be immediately contacted and informed of conditions.
ORGANIZATION AND RESPONSIBILITIES A.
Emergency Director -
Overall In-Charge Responsible for decision to evacuate.
B.
Assembly Point Coordinator-In charge of Assembly Point (reports to Emergency Director).
Responsible for implementation of this procedure.
C.
Radiation Protection Specialist - Assists Assembly Point Coordinator.
Responsible for ensuring radiation protection procedures are followed.
WP/kk
Procedure A.2-302 Revision 3 Page 2 of 7 DISCUSSION A.
Assembly Point Operation The function of the Assembly Point is to provide a center for personnel accountability and radiological contamination screening along with any other immediately necessary actions in the event of a Plant Evacuation.
The steps in this procedure assume an orderly evacuation in which some time is available for staging.
In the event that there is no time for prepara-tion, some of the steps in this procedure may have to occur out of sequence or simultaneously. The persons who are candidates for Assembly Point Coordinator should be familiar with the intended function of the Assembly Point so that this procedure can be adjusted to fit the circumstance.
B.
Location The primary on-site A:sembly Point is located east of the reactor building, in the south end of Warehouse #1.
The assembly coincides with the cold machine shop. An alternate on-site Assembly Point is located approximately 1000 feet south of the reactor building across from the substation.
The off-site Assembly Points are located at the Monticello Service Center and at the SherCo Plant.
C.
Data and Information Resources Each On-Site Assembly Point contains the following:
1.
Monticello Emergency Plan Drawings 2.
Appropriate Emergency Plan Implementing Procedures 3.
Emergency Preparedness Telephone Directory l
D.
Communications 1.
On-Site Assembly Points have plant telephone extensions and the Assembly Point Coordinator will be issued a portable radio for communications with all emergency response centers.
l E.
Equipment and Facilities l
Each On-Site Assembly Point contains the following:
l 1.
10 (0-200 mR) pocket dosimeters and charger l
2.
10 badges
(
3.
1 dose rate meter l
4.
1 GM survey meter 5.
1 air sampler with supply of particulate filters, charcoal and l
Silver Zeolite cartridges l
6.
1 decontamination kit 7.
10 sets of protective clothing WP/kk
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Procedure A.2-302 Revision 3 Page 3 of 7 E.
Equipment and Facilities (Cont'd.)
8.
Radiation barrier tape / rope and radiation signs 9.
-First aid kit 10.
Stationary supplies ll'.
Portable generator 12.
RM-14 with HP-210 probe and power cords 13.
Flashlights and batteries 14.
50 foot extension cords
- 15. Water sampler and poly bottles 16.
Emergency survey team kit and duffel bag NOTE:
No equipment is stored at the off-site Assembly Points.
PROCEDURE PART I - ACTIVATION STEP 1 Proceed to the TSC.
Ask the Emergency Director which Assembly Point will be activated.
Contact the Security Group Leader and arrange for security force member to assist at Assembly Point.
Collect the following items before proceeding to the designated assembly point:
a.
Keys to assembly point (from Shift Supervisor) l b.
Baseball cap with Assembly Point Coordinator designation Initiate ASSEMBLY POINT ACTIVATION CHECKLIST, Form 5790-302-1 (example: ).
I STEP 2 At the assembly point, unlock applicable doors and position radiation barrier rope for contamination control and radiological screening.
String rope from point A to B (and from C to D at the warehouse location) as depicted in Attachments 1 and 2, ON-SITE ASSEMBLY POINT DIAGRAMS.
STEP 3 Contact the CAS Operator (X-1246) and verify that the security computer is set up for accountability.
STEP 4 Direct Radiation Protection personnel to set up step-off pad (s) and frisker(s) at point F (as designated in Attachment 1) and to conduct a radiological survey of the area.
STEP 5 Contact the TSC and notify the Security Group Leader that the Assembly Point is prepared for a plant evacuation.
WP/kk
Procedure A.2-302 Revision 3 Page 4 of 7 PART II - OPERATION
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STEP 1 If the warehouse location is being used, channel all evacuees from the Cold Shop area, through the classroom and into the radiological holding area.
Ensure that each person properly inserts his (her) security.
badge into one of the card readers at point G (see Attachment 1) and that the red light is received after each card.
NOTE:
Time is important. Use both readers and do what is necessary to keep the process moving until all evacuees, including the Radiation Protection personnel and yourself, have been processed through the card readers.
STEP 2 If the warehouse location is being used, contact the TSC and notify the Security Group Leader as soon as the last of the evacuees has been
. processed.
NOTE:
Once the Security Group Leader has been contacted it is very important to' start a sign-in sheet for all persons arriving subsequently at the Assembly Point. Maintain the sign-in process (use Form #5790-107-1) until notified that the accountability procedure is completed.
STEP 3 Direct personnel in the radiological holding area to pass through the control point, using the frisker to detect contamination as they do so.
A Radiation Protection Specialist should be available at the control x
point to oversee this process.
Contact the TSC and notify the REC of
)
.any contamination and when the radiological screening is complete.
~
STEP 4 Keep all personnel at the Assembly Point unless and until directed otherwise.
E STEP 5 If available, direct Radiation Protection personnel to survey, and clear if possible, the radiological holding areas (and also the classroom and south end of the Cold Shop if applicable).
STEP 6 Maintain communications with the TSC.
Keep appropriate TSC personnel apprised of status.
STEP 7 Release personnel when so ordered by the Emergency Director and complete the checklist.
REFERENCES 1.
Monticello Nuclear Generating Plant Emergency Plan 2.
Monticello Nuclear Generating Plant Operations Manual 3.
NUREG-0654/ FEMA-REF-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" ATTACHMENTS 1.
On-Site Assembly Point Diagrams 2.
On-Site Assembly Point Diagrams 3.
Example of Assembly Point Activation Checklist WP/kk
Pr:cedure A.2-302
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Revision 3 Page 5 of 7 ATTACHMENT 1 WAREHOUSE ASSEMBLY POINT e
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. SUBSTATION ASSEMBLY POINT I
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Revision 3 Page 7 of 7 Form 5790-302-1 ATTACHMENT 3 Revision 2, 2/02/82 Page 1 of 1 a
Example of ASSEMBLY POINT ACTIVATION CHECKLIST (For Use With Procedure A.2-302) 1.
Assumed the responsibilities of Assembly Point Coordinator.
APC Initials Time Date 2.
Security computer ready for account-ability.
APC Initials Time Date 3.
Survey of Assembly Point Area initiated and radiological control point established.
APC Initials Time Date 4.
Emergency Director notified that Assembly Point is prepared for evacuation.
APC Initials Time Date 5.
If warehouse location is activated, notified Security Group Leader when all evacuees were processed.
APC Initials Time Date 6.
Completed radiological screening and so notified REC.
APC Initials Time Date 7.
Peleased Assembly Point personnel on order from Emergency Director.
APC Initials Time Date NOTE:
After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for i
the Emergency Records.
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i Procedure A.2-303 Rsvision 3 Page 1 of 3 Op. Com. Re,v. Req'd.
Yes X No Q.A. Review Req'd.
Yes No X ALARA Review Req'd.
Yes X No SEARCH AND~ RESCUE A.2-303 REVIEW AND APPROVAL
/!//[/'>
Prepared by: bow / J ALARA Review:
6d/4Mdu_
Date Reviewed by: 65 //[dd.b-Q.A. Review:
Revision 0 Date 3/26/81 Operations Committee Final Review: Meeting Number ligg Date 4/28/83 Approved by:
$$h$<5kt>-(
Date 6I-3 -f 3 f
Op. Com. Results Review: Not Required Mtg. #
949 Date 3/26/81 PURPOSE This procedure provides instructions pertaining to in plant search and rescue operations if required to locate and/or rescue personnel who are unaccounted for during or following an emergency.
CONDITIONS AND PREREQUISITES A.
One or more individuals are missing following an evacuation of an affected area, or B.
A report has been received of personnel trapped and/or disabled within i
the plant.
PRECAUTIONS Permissible exposures incurred during search and rescue operations are governed by A.2-401, " Emergency Exposure Control".
PERSONNEL REQUIREMENTS Emergency Team Leader Emergency Teams ORGANIZATION A.
Overall Responsibility - Emergency Director B.
In Charge - Emergency Team Leader 3
C.
Assistance i
(
1.
Emergency Team Members l
2.
Radiation Protection Group
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Procedure A.2-303 Revision 3 Page 2 of 3 RESPONSIBILITIES
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A.
Emergency Director 1.
Appoint Emergency Team Leader.
g B.
Emergency Team Leader 1.
Select Emergency Team Members.
2.
Instruct Team Members on probable locations of missing personnel and expected dose rates.
3.
Ensure that. proper equipment and first aid supplies are obtained to perform necessary action.
C.
Emergency Team Members Perform search and rescue.
D.
Radiation Protection Group Provide radiological information and emergency exposure control.
DISCUSSION A.
If an individual is trapped or disabled in a high radiation area, the rescue must be performed as expeditiously as possible to minimize the dose to the victim and the doses to the rescue personnel, and to ensure that first aid
)
can be provided as soon as possible.
B.
In an emergency situation, an exposure of 75 rem to rescue and first aid personnel is appropriate if necessary to save a life.
Refer to A.2-401 (Emergency Exposure Control).
C.
Rescue of a victim shall take precedence over fire-fighting or damage i
control efforts, unless such actions are necessary to effect rescue, or to relieve an immediate threat to the lives of other personnel.
~
D.
Rescue of a victim shall take precedence over isolation of steam, hot water under pressure, hydraulic fluids, etc., unless such isolation is necessary to effect rescue; or if failure to isolate will seriously affect reactor safety or will place the lives of other personnel in immediate danger.
E.
Emergency Team Members should be selected from volunteers, as these opera-tions could involve high exposure and risk.
PROCEDURE STEP 1:
Upon notification of missing / trapped / disabled individuals, select Team Members from available personnel and direct Emergency Team in search and rescue operation.
i NOTE:
An emergency team shall be composed of a minimum of two individuals, one of which should be a Radiation Protection Specialist.
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Procedure A.2-303 Revision 3 Page 3 of 3 STEP 2:
The Emergency Team Leader shall ensure that members of the team:
a.
are briefed on the estimated or expected radiological conditions in the plant.
b.
are aware of actions to be taken if unexpected radiological conditions are encountered.
STEP 3:
Obtain necessary equipment and dosimetry.
Don protective clothing and any respiratory equipment required by the Health Physics Group (RWP).
If exposure limit extensions are necessary, refer to Procedure A.2-401, Emergency Exposure Control.
STEP 4:
Proceed to the designated search area as directed by the Emergency Director or his designee, while mair.taining radio contact. The RPS should lead the team while monitoring the radiological conditions.
STEP 5:
Provide the followinc information, as known:
a.
Location of victim b.
Extent of injuries c.
Additional assistance required, if necessary d.
Complications affecting rescue STEP 6:
Perform search ana/or rescue operation as expeditiously as possible.
a.
If the individual (s) cannot be moved immediately, first aid should be applied as necessary.
b.
If appropriate, move the individual to the closest safe area and apply first aid as necessary.
c.
Evaluate the condition o.' the individual:
(1) If the individual is injured and requires off-site medical treatment, refer to MNGP Operations Manual, Procedure A.5-100.
(2) If the individual ~has or may have received a biologically significant overexposure, report to Radiological Emergency Coordinator.
STEP 7:
Complete all necessary forms and submit to appropriate group for l
recording and filing.
REFERENCES 1.
Monticello Nuclear Generating Plant Emergency Plan 2.
Monticello Nuclear Generating Plant Operations Manual 3.
NUREG-0654/ FEMA-REP-1, "Critieria for Preparation and Evaluation of Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" l
ATTACHMENTS I
None WP/kk l
Procedurs A.2-403 R1 vision 3 Page 1 of 9 Op. Com. Rev. Reg'd. Yes X No Q.A. Review Req'd.
Yes No X ALARA Review Reg'd.
Yes X No IN-PLANT EMERGENCY SURVEYS A.2-403
/Y!O Prepared by:
/
Mjv ALARA Review:
C/ OLA (M Date Reviewed by:
Cvd[/ttdble-Q.A. Review:
Revision 0 Date 3/28/81 Operations Committee Final Review: Meeting Number 1199 Date 4/28/83 Approved by:
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Oate 6-L F 3 Op. Com. Results Review:
Not Required
'Mtg. #
949 Date 3/26/81 PURPOSE The purpose of this# procedure is to provide instruction and guidance on conducting radiation surveys during an emergency condition that could involve high dose rates, and/or high airborne / surface contamination levels in the survey area and the means by which monitoring equipment and supplies will be obtained.
CONDITIONS AND PREREQUISITES A.
An emergency condition has been declared at the Monticello Nuclear Generating Plant as provided by the MNGP Emergency Plan.
B.
A survey within the plant is necessary.
C.
Radiological conditions in the survey area may involve high dose rates, high airborne / surface contamination levels, and/or high levels of beta radiation.
PERSONNEL REQUIREMENTS Radiation Protection Specialist (s) - to conduct survey and analyze samples.
Monitoring Section Leader (MSL) - to identify survey requirements and review results.
Radiological Emergency Coordinator (REC) - in charge.
Radiation Protection Coordinator (RPC) -
Provide field support for the REC and
,l MSL.
PRECAUTIONS A.
In general, ion chamber instruments should be used to measure dose rates.
Do not use a GM instrument (except Teletector) in a high level radiation field because the detector may saturate causing the instrument to errone-ously read "zero" or below scale.
B.
If an instrument malfunctions or " pegs" out during survey operations, immediately exit the area by the same route used to enter it, and obtain a new instrument if necessary. A malfunctioning instrument should be appropriately tagged.
C.
Take care not to cantaminate or damage survey instruments.
Particular care should be exercised to avoid damage to the beta window of a beta-gamma instrument.
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Procedure A.2-403 Revision 3 Page 2 of 9 D.
Ensure that appropriate protective clothing and equipment (e.g. respirators)
' is worn by all members of the survey party.
If there is a potential for high-beta dose rates, use protective eyewear.
E.
Exposures of personnel in the survey party shall be in accordance with MNGP administrative control levels. Monitoring teams must remain alert to their own exposure and request relief if their cumulative exposures approach these levels. The Emergency Director may authorize exposure limit extensions, if necessary (A.2-401). All exposures shall be maintained as low as reasonably achievable by employing the following methods or techniques:
1.
Limit the number of personnel in the survey party to the minimum number necessary to perform the survey in a safe and efficient manner.
2.
If time is available, plan the survey in advance to ensure gathering a maximum amount of data in a minimum time period.
Conduct a pre-survey briefing to ensure all members of the party understand their tasks.
3.-
Ensure that the party has all equipment and supplies it needs, including survey maps and forms.
Pre-number smears and take other measures to minimize time in the radiation field.
4.
Use extendable probe instruments (such as the Teletector) to minimize exposure when monitoring " hot spots" or hard to reach areas.
5.
Use available equipment or structures as shielding when appropriate.
}
F.
Alarming dosimeters should be considered in addition to high range self-reading dosimeters.
G.
Careful attention shall be given to the safety of the survey party, both radiological and physical.
The " buddy" system should be adopted for all entries into the affected area, where necessary to assure the physical safety of the personnel conducting the survey. However, the number of instruments and measurements required and the need for a rapid but thorough appraisal of the conditions within the eccident site also dictate the need for more than one individual per survey party.
If there is more than one person in the survey party, an RPS with a dose rate meter will lead the group.
DISCUSSION A.
An essential part of coping with any radiation emergency is a prompt assessment of the radiation status at the site of the event and in surrounding areas.
Early detection of changing conditions can prevent the involvement of large numbers of personnel and larger areas of the l
Event Site.
B.
Surveys of the event site with portable survey instruments are necessary to provide basic data on the radiological situation.
Careful planning can limit the exposure of emergency personnel.
Keep in mind during this l
planning tnat:
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Procedure A.2-403 Revision 3 Page 3 of 9 1.
The location of the sources of radiation 'may be unknown.
2.
Physical safeguards may have been destroyed.
3.
The physical process or reaction that caused the emergency may still be occurring.
C.
The survey should be designed to obtain gross answers concerning the status of the facility.
Precise answers are not required immediately and may never be required.
In order to conserve time, no attempt should be made to correct instrument readings. This refinement can be made at a later time based on the data accumulated from the survey and the instrument capabilities.
D.
Techniques such as use of the attenuation of the surveyor's body or other objects to assist in locating the radiation source (s) are useful.
E.
After the radiation levels have been determined, the magnitude and extent of the surface and airborne contamination spread should be established.
The survey may entail the measurement of surface contamination levels directly or it may require the collection of smears for evaluation outside of the event site.
F.
Determine / discuss the dose rates to be expected during the conduct of this procedure.
G.
The use of the PAS System should be considered for taking gaseous samples in lieu of Attachment 2.
PROCEDURE STEP 1 Plan the survey.
Considering the objective of the survey, expected radiological conditions and any other pertinent circumstances, initiate an Emergency RWP Checklist (Form #5790-107-2) for the survey.
Specify the equipment to be used, protective clothing requirements, and the particulars of the survey.
STEP 2 Collect required equipment from either normal inventory or from emergency lockers. Check radios and instruments for operability and proper response.
STEP 3 Don protective clothing and equipment.
Establish communications with Access Control and maintain communications throughout the conduct of the survey.
Notify REC /MSL that survey party is ready to commence survey.
Standby for approval from REC /MSL.
STEP 4 When the REC /MSL so directs, commence survey in accordance with pre-planning. While enroute to the assigned survey location, and at any other time while moving about the plant, have the survey instrument turned on (with the beta window open, if applicable).
Frequently observe the survey meter and report readings to Access Control. Record l
abnormal readings or other readings having special significance.
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'g Procedure A.2-403 1
Javision 3 Page 4 of 9 STEP 5 Approach survey location with caution and continue to monitor dose rates frequently. Take samples of surface contamination, airborne contamination samples, and dose rates as planned.
Record dati"as required.
Refer to Attachment 2 for Gaseous Sampling Proceaure.
-l STEP 6 Leave the affected area as planned.
Analyze any air samples or ;mears in accordance with Attachment 1.
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STEP 7
. Record all survey results on plant survey forms.
Deliver results to
'i l'l RPC who will relay results to the MSL or REC.
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. PRECAUTIONS j
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Take proper radiological p^re'ca$tions Ehile bandling samol g, 5amples could'contain high. activity lov'els.
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' Insure samp!es are properl b'aggey to prevent con,tamination of the counting facility.
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' Count the fjlter with an RM-14.
If the countrate is ( 50,000 cpm refer i
't to Tihle l'fcr method of analysis..If the countrate is too high to be s
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Part II Charcoal and Silver Zeolite Cartridges STEP 1 Count the cartridge with'an RM-14.
If the countrate is ( 50,000 cpm 2
)
refer to Table 1 for ciethod of ana' lysis.
If the ountrate is too high
.Q < " w to be d?fermined withlan Rfi-14, m'asure-the dose rate with a Radector e
f III and refer to Table 1 for metho'd of Mnalysi;.
k NOTE 1:
If the cartr1dge dose rate is greater than 10 mR/hr perform r
a purge of_the cartridge by placing the cartridge in a sample holder anj purging with service air for five minutes in the hot lab' sample hood.
Repeat STEP.I.
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e Part III Smears
~'r STEP 1 Count thE smear with an+RM-14 If the count rate is (50,000 cpm refer
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to Table'I for method of analysis.
If the count rate is too high to be a
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determined w?th an RM-14, measure the dose rate with a Radector III 1
and refer to Table Js for method of analysis.
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Procedure A.2-403 Revision 3 Page 6 of 9 (Cont'd.)
TABLE 1 2 10,000 cpm 2 50,000 cpm 5 10,000 cpm 5 50,000 cpm 5 10 mR/hr 2 10 mR/hr Particulate I ASC I
RM-14 I
GeLi I. Radector III I
Filter I (Formula #1) I (Formula #2)
I (Formula #3) I 1 Foot Reading I
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I (Formula #4)
I I (Formula #3) I (Formula #3)
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GeLi I Radector III I
Filter I (Formula #5) I (Formula #5)
I (Formula #3) I (Note 1)
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I GeLi I
GeLi I
I l Foot Reading I
I'(Formula #3) I (Formula #3)
I I (Formula #6)
I Silver I Well Counter I Well Counter I
GeLi I Radector III I
Zeolite I (Formula #7) I (Formula #7)
I (Formula #3) I (Note 1)
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or I
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I GeLi I
GeLi I
I 1 Foot Reading I
I (Formula #3) I (Formula #3)
I I (Formula #6)
I Smear I
ASC I
RM-14 I Radector I Radector I
I (Formula #8) I (Formula #9)
I' III I
III T.
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I (Formula #10) I (Formula #12)
Gas I RM-14 I
RM-14 I
GeLi I Radector I (Formula #11) I (Formula #11) I.(Formula #3) I III I
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-or I
or I
I (Formula #12)
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GeLi I
GeLi I
I I
I (Formula #3) I (Formula #3)
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Refer to Table 2 for formulas.
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Procedure A.2-403 Revision 3 Page 7 of 9
- (Cont'd.')
TABLE 2 3
NOTE:
Sample Volume in ec's = ft / min x 2.83E4 x sample time or = 1pm x 1000 x sample time 1.
Net CPM (ASC Efficiency) (Sample Volume) (2.11E6)
=p cc Formula assumes 95% filter efficiency.
2.
Net CPM C1/cc
=
(2.11E5) (Sample Volume)
Formula assumes 10% detector efficiency and 95% filter efficiency.
3.
Count for 600 seconds then do one of the following as directed by the REC:
.Run GAMMAK Run GAMMA Run GAMMAK and Run MPRAIR 4.
1 ft dose rate in mR/hr x 610 pCi/mR/hr =
Ci/cc Sample Volume (Formula based on.5 Mev gammas and.5 gammas per disintegration) 5.
Net CPM (1.24E5) (Sample Volume) = pCi/cc (based on a 70% filter efficiency for I-131) 6.
1 foot dose rate in mR/hr x 420 pCi/mR/hr = pCi/cc
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(Sample Volume)(Filter Efficiency)
(Activity based on I-131)
Use efficiency of.7 for charcoal filter Use efficency of.99 for Silver Zeolite 7.
Net CPM (1.76ES) (Sample Volume) = pCi/cc (based on a 99% Filter Efficiency for I-131) 8*
Net CPM 2
= DPM/100 cm instrument efficiency 9.
Net CPM 2
= OPM/100cm
.1 10.
Report results in 1,000,000 dpm/mR/hr
- 11. Determine net CPM and refer to Figure 1 for activity determination.
12.
Report results in mR/hr.
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Attachmsnt 1 (Cont'd.)
Procadure A.2-403 Rwision 3 FIGURE 1 Page 8 of 9 GAS C E iBER CALIBRATION CURVE c '.
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Proc: dure A.2-403 Revision 3
.Page 9 of 9 Gaseous Sampling and Analysis STEP 1 Remove the stainless steel gas chamber suction bulb and filter assembly from the survey kit.
STEP 2 Install a clean filter in the filter assembly.-
STEP 3 Connect filter assembly such that air passes through the filter to the gas chamber, then to the suction bulb.
STEP 4 Open the stop cocks on the gas chamber.
STEP 5 Squeeze the suction bulb ten (10) times to obtain a representative sample.
STEP 6 Shut the stop cocks on the gas chamber.
STEP 7 Count the gas chamber with an RM-14.
If the count rate is < 50,000 cpm refer to Table I for method of analysis.
If the count rate is too high to'be determined with an RM-14, measure the dose rate with a Redector III and refer to Table I for method of analysis.
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Procedure A.2-406 L
Revision 7 Page 1 of 16 Op. Com. Rev. Req'd.
Yes X No Q.A. Review Req'd.
Yes No X ALARA Review Req',d.
Yes No X OFF-SITE DOSE PROJECTION A.2-406 REVIEW AND APPROVAL Prepared by:
k% h.~ ALARA Review:
Revision 0 Date 3/29/81 Reviewed by: M h d Q.A. Review:
Revision 0 Date 3/29/81 Operations Committee Final Review: Meeting Number ILQF Date // - 1/ - P.5 Approved by:
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Date N. '2 9-f3,
Op. Com. Results Review: Not Reauired Mtg.#
949 Date 3/26/81 PURPOSE The purpose of this procedure is to provide guidance and instructions for estimat-ing off-site doses resulting from an unplanned and/or abnormal airborne release of radioactive material.
The main body of this procedure identifies criteria and guidelines for dose projection, such as how often it should be performed, and which dose projection method to use. The attachments to this procedure provide instructions for performing dose projection using the various methods.
Alternate methods are provided to cover possible contingencies such as offscale monitors, inoperative instrumentation, etc.
CONDITIONS AND PRERE0VISITES A.
An emergency condition has been declared at Monticello Nuclear Generating Plant as provided in the Emergency Plan.
B.
An airborne release of radioactive materials in excess of environmental technical specifications has occurred, is suspected to have occurred, or is imminent.
PRECAUTIONS Precautions are verified in the text of the applicable attachment (s).
ORGANIZATION Responsible-Radiological Emergency Coordinator In-Charge - Off-Site Dose Assessment and Chemistry Section Leader Assistance - Radiation Protection Specialist DISCUSSION A.
General Applicability The region surrounding the plant site is divided into sixteen 22 1/2 degree sectors. The regions of interest extend from the effluent release points out to fifty miles in each sector. Contained within the regions of interest are special locations of interest. The special locations are the site WP/kk
Proccdure A.2-406 Revision 7 Page 2 of 16 boundary and the nearest receptor.
The site boundary and the nearest receptor locations differ for each sector.
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B.
Dose Projection Methods This procedure provides 2 different methods for performing dose projections.
The method (s) used will depend on the availability of release and meteoro-logy information and the operability of cornputers.
They appear as attach-ments to this procedure with Attachment I being the most preferred method and Attachment 2 being the least preferred.
- 1. Dose Projection By Computer (MODCOM)
The Monticello Off-Site Oose Computation System (MODCOM) is a computerized atmosphuric dispersion and radiological dose assessment software system.
The system is specific for the Monticello Nuclear Generating Plant and is structured in the form of an executive main program (M00COM) and several subprograms.
The software syst.em is coded in a high level interpretive language called C.L.A.S.S..
The software runs on Digital Equipment Corporation computer systems which are located at the plant site.
Data required for input to the software system are: (1) meteorlogical infor-mation acquired from the met.eorological tower (MET Tower) 5.E.D.A.R. computer system, and, (2) plant stack and R.B. ventilation radioactive airborne effluents release rate information acquired from effluents monitors or dose rate readings converted to release rates. Wind direction data is used to determine the correct sector. Wind speed data is used to determine the m
plume dispersion parameters and maximum plume distance.
Temperature
)
difference values are used to determine the plume dispersion parameters.
The plume is assumea to completely fill the sector in which it is located.
Release rate data is combined with dispersion data to yield dose rate data.
The release rate data is input in the form of pCi/sec for noble gases, iodines, and particulates for the plant stack and Reactor Building ventilation release points. Whole body and thyroid dose factors as well as default nuclide concentration ratios are contained in system mass storage files for use in calculating dose rates.
Data is accumulated into the program at 15, 30, or 60 minute intervals.
The program computes dose rates at the site boundary, the nearest receptor, and out to the maximum plume distance which may be anywhere from one mile to 10 miles in one mile increments.
The dose rate values are reported in mrem / hour.
The dose rate values are converted to an accumulated dose for that period.
The dose values are then stored according to sector for the whole body and thyroid. During the course of an accident, dose values are accumulated in several sectors, as the stack plume and R.B. vents plume are sometimes not in the same sector, and wind direction shifts will cause the accumulated doses to be placed into several different sectors over a period of time. Accumulated dose information may be extracted from storage and read out according to sector, or a specific distance from the plant for all sectors. Accumulated dose information is reported in " mrem".
NOTE: Thyroid doses are calculated for the child thyroid.
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Procedura A.2-406 Revision 7 Page 3 of 16
- 2. Dose' Projection By Hand Calculation This' method calculates the whole body and thyroid doses in the event that the computer systems are not available.
PROCEDURE STEP 1: When directed by the Radiological Emergency Coordinator or the Emergency Director, perform off-site dose projections in accordance with Attachments 1 or 2. is the most preferred method and Attachment 2 is the least preferred method.
STEP 2: Continue doing dose projections until otherwise directed by the Radiological Emergency Coordinator or Emergency Director.
REFERENCES 1.
Monticello Nuclear Generating Plant Emergency Plan 2.
NUREG-0654/ FEMA-RFP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans for Preparedness in Support of Nuclear Power Plants" ATTACHMENTS 1.
Dose Projection by Computer (MODCCM) 2.
Dose Projection by Hand Calculation 3.
Example of Off-Site Dose Projection Worksheet 4.
Obtaining Meteorological Data From Weather Information Service 5.
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b Procedure A.2-406 Revision 7 Page 4 of 16 ATTACHMENT 1 Page 1 of 4 DOSE PROJECTION BY COMPUTER (M00COM)
PRERE0VISITES 1.
Proceed to the Body Count Room and place the computer system in the time-sharing mode (TYPE " Control-C", then RUN TSGO).
2.
Proceed to the TSC and turn on the Plant Computer CRTs, if this has not already been done.
Release and meteorological data must be available for this method.
PROCEDURE STEP 1: Turn on the dose projection printer.
Dep~ress the return key and the terminal will print:
TSX Version CIO7E (Date-Time)
STEP 2: Type in "RUN CLASS" and press carriage return.
The terminal will respond with:
4 CLASS V04.24-RT (DATE)
NOTE:
System operation may be verified by running program and
)
using information from Attachment 5.
'l STEP 3: Type in "RUN MODCOM" and press carriage return. The terminal will respond with:
INITIAL EVALUATION ? :
STEP 4: Respond as follows:
CAUTION: Do not Fispond with "Y" unless this is the first post-release execution of this procedure, as all stored data will be lost.
If this is the initial evaluation, type in "Y" and press carriage a.
return. The terminal will respond with "ARE YOU SURE?".
Respond with "YES", the terminal will respond with "PLEASE ENTER THE OPTION YOU DESIRE:".
b.
If this is a subsequent evaluation, type in "N" and press carriage return. The terminal will respond with:
PLEASE ENTER THE OPTION YOU DESIRE:
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Procedure A.2-406 Revision 7 Page 5 of 16
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ATTACHMENT 1 (Cont'd.)
Page 2 of 4 STEP 5: Select one of the following options:
OPTION DESCRIPTION 1
PERFORM TYPICAL DOSE RATE CALCULATION 2
LIST ACCUMULATED DOSES FOR ANY SECTOR (A-R) 3 SEARCH ALL SECTORS FOR HIGHEST DOSE AND REPORT DOSE DATA 4
PRINT ALL SECTOR DOSES (A-R) AT A SPECIFIED DISTANCE 5
UPDATE THE NUCLIDE DATA FILE 6
PERFORM DOSE PROJECTION (N0 DATA STORAGE) 7 LIST ACCUMULATED POPULATION DOSES FOR ANY SECTOR (A-R) 8 LIST ACCUMULATED GROUND CONTAMINATION FOR ANY SECTOR (A-R) 9 STOP PROGRAM EXECUTION and proceed to the appropriate portion of this procedure.
NOTE:
Option 1 should be used unless specific information available through one of the other options is sought.
STEP 6: PERFORM TYPICAL DOSE RATE CALCULATION:
a.
Type in "1" and press carriage return.
The terminal will respond by requesting that you enter current date information.
Type in this information as-it is requested.
The terminal will then respond with:
PLEASE ENTER THE FOLLOWING METEOROLOGICAL DATA FROM THE SEDAR COMPUTER PRINTOUT:
NOTE:
If the meteorological tower met system data is unavail-able, use backup tower data, by switching the met data printer to backup mode. Do this by placing the switch behind printer to backup tower position and changing speed switch under cover of printer to Hi speed for backup, low speed for primary.
If neither backup or primary mode are operable refer to Attachment 4 and use the St. Cloud reporting station data for stability class, windspeed and wind direction data.
Enter a Zero for the requested day and time information.
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P Procedure A;2-406 Revision 7 Page 6 of 16 ATTACHMENT 1 (Cont'd.)'
Page 3 of 4 PLEASE ENTER THE FOLLOWING EFFLUENTS RELEASE RATE DATA:
'!i The. terminal will request specific numerical information. Obtain.
this information from the_ Plant Computer CRTs and type-it-in as requested.
If release rate data is not available, refer to Procedure A.2-405.
t NOTE:
During the early stages of an accident when Iodine release rates are not available, enter Iodine release rate values
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corresponding to about 2% of that release points noble gas release rate.
This should be done until grab samples have been taken and analyzed.
Grab samples should be.
taken and anlayzed as soon as possible.
b.
The terminal will respond with a printout of off-site dose projections for the affected sector (s) from the Site Boundary to a distance of 10 miles.
Communicate this information to
'the Radiological Emergency Coordinator.
c.
The terminal'will then print:
).3 PLEASE ENTER THE OPTION YOU DESIRE:
d.
Type'in the option number per STEP 5 or STEP 9.
NOTE:
MET data is updated every 15 minutes and that should be the frequency with which Option 1 is run' during an emergency condition with an airborne release. You
-should continue to update dose rate data every 15 minutes until the Radiological Emergency Coordinator directs other-wise.
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STEP 7: LIST ACCUMULATED DOSES FOR ANY SECTOR l
a.
Type in "2" and press carriage return. The terminal will respond with:
ENTER THE SECTOR (A-R) FOR WHICH YOU WANT THE ACCUMULATED DOSES REPORTED.
~ SECTOR:
i b.
Type in the sector letter (A-R).
The terminal will ask you if you wish to perform dose projection calculations. Answer Y or N, then the terminal will respond with a printout'of the accumulated j
doses for the affected sector from the Site Boundary to a distance of 10 miles.
Communicate this information to the Radiological Emergency Coordinator.
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Procedure A.2-406 Revision 7 Page 7 of 16 ATTACHMENT 1 (Cont'd.)
Page 4 of 4 c.
The terminal will then print:
PLEASE ENTER THE OPTION YOU DESIRE:
d.
Type in the option number per STEP 5 or STEP 9.
STEP 8: SEARCH ALL SECTORS FOR HIGHEST DOSE AND REPORT DOSE DATA a.
Type in "3" and press carriage return.
The terminal will respond with a printout of the accumulated dose values to the highest sector (s).as well as a list of the sectors where accumulated whole body or thyroid doses exceeded pre programmed limits.
Communicate this information to the Radiological Emergency Coordinator.
b.
The terminal will then print:
PLEASE ENTER THE OPTION YOU DESIRE:
c.
Type in the option numbers per STEP 5 or STEP 9.
STEP 9: Should it be desirable to cease dose projection activities for extended periods of time (with the concurrence of the Radiological Emergency Coordinator), when the terminal prints:
PLEASE ENTER THE OPTION YOU DESIRE:
Type in "9" and press carriage return.
You may subsequently re-enter the program by typing in "RUN MODCOM".
STEP 10 Upon receiving instructions from the Radiological Emergency Coordinator to secure from dose projection activities, turn off all equipment and ensure that all data is appropriately filed.
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l Procedure A.2-406 Revision 7 Page 8 of 16 ATTACHMENT 2 Page 1 of 4' DOSE PROJECTION BY HAND CALCULATION EQUIPMENT REQUIRED 1.
Calculator (with scientific notation capability) 2.
Supply of 0FF-SITE DOSE RATE PROJECTION WORKSHEET Forms (TSC),
Form 5790-406-4 (Attachment 3) l PROCEDURE STEP 1: In the INPUT DATA section of the worksheet, enter the date and time for which this projection will be made.
STEP 2: Enter the TIME AFTER REACTOR TRIP value. This is the elapsed time from the reactor trip to the time recorded in STEP 1.
If there has not been a reactor trip, enter ZERO.
STEP 3: Determine the necessary meteorological parameters and record as indicated on the worksheet. This data should be taken from the meteorological tower printer.
If the printer is unavailable, refer to Attachment 4.
NOTE:
'If the meteorological tower me.t system data is unavailable, use backup tower data, by switching the met data printer to backup mode. Do this by placing the switch beind printer to backup tower position and changing speed switch under cover of printer to Hi speed for backup, low speed for primary.
If neither backup or primary mode are operable refer to Attach-ment 4 and use.the St. Cloud reporting station data for stability class, windspeed and wind direction data.
Enter a Zero for the requested day and time information.
a.
RB Vent Stability Class - Divide the value for DT1 by 100, paying attention to whether the value is positive or negative. Use the result to enter Table I.
Record the class designation.
b.
Stack Stability Class - Divide the value for DT2 by 100, paying attention to whether the value is positive or negative.
Use the result to enter Table I.
Record the class designation.
c.
RB Vent Windspeed - Record the windspeed at the 33 feet level (use 1 mph when indication is zero).
d.
Stack Windspeed - Record the windspeed at the 330 feet level (use 1 mph when indication is zero).
e.
Stack Wind Direction - Record the wind direction at the 330 feet level.
(If value is greater than 360, subtract 360 before recording.)
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Procedure A.2-406 Revision 7 Page 9 of 16 ATTACHMENT'2 (Cont'd.)
Page 2 of 4 TABLE I Stability Class R8 Vent (DT1/100)
Stack (DT2/100)
A Less than -0.62 Less than -1.71 B
-0.62 to -0.56
-1.71 to -1.53 C
-0.55 to -0.49
-1.52 to -1.35 D
-0.48 to -0.16
-1.34 to -0.45 E
-0.15 to +0.49
-0.44 to +1.35 F
+0.50 to +1.31
+1.36 to +3.60 G**
Greater than +1.31 Greater than +3.60 Stability Class G is not to be used.
(Ref: Letter of 3/9/81 from certified consulting meteorologist to Bert Clark.) Use Class F when G is indicated.
STEP 4: Determine and record the SECTOR designation (A-R).
Use the 330 feet wind direction and Table II to find the letter designation for the area directly downwind from the plant.
NOTE:
If the wind speed indicates zero, use Sector designation "L" (most critical sector based on nearest receptor).
TABLE II Wind Direction Sector 168.75 to 191.25 A
191.25 to 213.75 B
213.75 to-236.25 C
236.25 to 258.75 0
258.75 to 281.25 E-281.25 to 303.75 F
303.75 to 326.25 G
326.25 to 348.75 H
348.75 to 11.25 J
11.25 to 33.75 K
33.75 to 56.25 L
56.25 to 78.75 M
78.75 to 101.25 N
101.25 to 123.75 P
123.75 to 146.25 Q
146.25 to 168.75 R
STEP 5: From Table III select and record the XU/Q values as required.
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Procedure A.2-406' Revision 7 Page 10 of 16 ATTACHMENT 2 (Cont'd.)
Page 3 of 4 TABLE III R.B. VENTS XU/Q Stab. Class A-B-C D
E F-G Distance
'SB 6.4E-5 9.4E-5 1.2E-4 2.1E-4 NR 6.4E-5 9.4E-5 1.2E-4 2.1E-4 1
1.9E-5 4.3E-5 5.8E-5 1.9E-4 2
5.7E-6 1.7E-5 2.6E-5 1.0E-4 3
2.9E-6 1.0E-5 1.8E-5 7.4E-5 4
1.9E-6 7.2E-6 1.3E-5 5.9E-5 5
1.3E-6 5.1E-6 9.9E-6 4.8E-5 10 4.6E-7 2.1E-6 4.6E-6 2.6E-5 STACK XU/Q Stab. Class A-B-C D
E F-G Distance
!B 2.74-4 4.03E-7 6.17E-10 2.54E-18 tR 2.74-4 4.03E-7 6.17E-10 2.5E-18 1
1.2E-5 6.4E-6 1.6E-6 1.1E-9 2
5.0E-6 9.0E-6 7.0E-6 4.4E-7 3
2.7E-6 6.7E-6 6.4E-6 1.1E-6 4
1.8E-6 5.4E-6 6.2E-6 1.7E-6 5
1.3E-6 4.2E-6 5.4E-6 2.1E-6 10 4.5E-7 2.0E-6 3.6E-6 3.2E-6 STEP 6: From Table IV, determine and record the Noble Gases Factor arid the Iodines Factor as appropriate for the elapsed time value previously recorded.
TABLE IV Elapsed Time (Hours)
Noble Gases Iodines From To Factor Factor 0.00 0.49 6.49E-01 254 0.50 0.99 5.48E-01 282 1.00 1.99 4.06E-01 329 2.00 3.99 3.43E-01 398 4.00 7.99 2.93E-01 485 8.00 15.99 1.65E-01 607 16.00 23.99 8.70E-02 705 24.00 47.99 6.10E-02 923 48.00 95.99 3.90E-02 1117
~
96.00 167.99 3.30E-02 1270 168.00 335.99 3.30E-02 1280 336.00 719.99 3.20E-02 1280 720.00 1439.99 2.60E-02 1280 1440.00 Beyond 3.60E-03 1280 WP/kk s
Procedure A.2-406 Revision 7 Page 11 of I6 ATTACHMENT 2 (Cont'd.)
Page 4 of 4 STEP 7: Record the release rates (pCi/sec) for the gas and iodine portions of the stack and vent effluents. The gas portion release rates may be obtained directly from effluent monitor readings.
If direct monitor readings are unavailable, obtain release rates from procedure A.2-405 (Release Rate Determination).
The iodine portions will be determined by Radiation Protection Group personnel through actual samples.
If sample analysis data is not available, use a value of 2% of the noble gas release rate values.
STEP 8: Using the values recoraed in the INPUT DATA section, complete calcula-tions for the location of interest as required.
i I
4 l
1 l
l l
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Procedure A.2-406 Revision 7 Page 12 of 16 ATTACHMENT 3 Form 5790-406-4 Revision 2, 03/07/83 Page 1 of 1 Example of 0FF-SITE DOSE RATE PROJECTION WORKSHEET (For use with Procedure A.2-406, Attachment 2) l INPUT DATA Time Date Time After Reactor Trip hours Stability. Class: RB Vent Stack Windspeed:
RB Vent mph (c)
Stack mph (c)
Wind Direction:
Sector Location (S.B., N.R., or distance):
XU/Q Value for Location (m-2):
Noble Gas Release Rate (pCi/sec):
(a) 3 Noble Gas Factor (mrem-m /hr pCi)-
p)
Iodines Release Rate (pCi/sec):
(d) 3 Iodines Factor (mrem-m /hr pCi):
(e)
WHOLE BODY DOSE RATE Compute:
(a) x (b) x 50/0 =
mrem /hr (c) x.447 O mph THYROID DOSE RATE Compute:
(d) x (e) x EU/Q =
committed (c) x.447 m3 mrem / hour mph of exposure.
REVIEW AND APPROVAL Completed by:
/
Date Reviewed by:
Date Radiological Emergency Coordinator NOTE:
After this checklist is completed and is not required for immediate use, tI shall be placed in the appropriate container provided for Emergency Records.
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^-
Procedure A.2-406 Revision 7 o
Page 13 of 16 ATTACHMENT 4 l'
PROCEDURE FOR USE OF THE WEATHER INFORMATION SERVICE s
EQUIPMENT:
Western Union Terminal, Telephone and Accoustic Coupler 1.
Turn terminal on (back right of terminal).
Set terminal to MED Speed.
Set terminal to full duplex, modem set to full duplex.
Set all caps key to ON.
Depress on-line button.
2.
DELETED When tone is heard, place phone in terminal coupler with the cord to the rear. Green light on coupler in 5-15 seconds.
NOTE:
If no green light, hang-up and re-do STEP 2.
OPERATOR ACTION PRINTER OUTPUT 3.
Press return twice.
TELENET TERMINAL =
4.
Type "D1" Press return 5.
Type "C 617133" Press return.
617 1338 CONNECTED 6.
Press return.
PLEASE LOG IN 7.
Type "LOGIN NSM".
Press return.
PASSWORD 8.
Type " POWER".
Press return.
LOGGED INTO WEATHER SERVICES -------
+
+ Indicates computer awaiting instructions.
9.
Type"MONT".
Press return.
- 10. When printout is completed type "LOGOUT" Press return.
When computer prints out that it is disconnected immediately hang-up phone.
NOTE:
Use this service only as neuded.
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Proccdure A.25406 Revision 7 Page 14 of 16 ATTACHMENT 5 CLASS V04.24.24-RT f
16-NOV-77 N.
SYSTEM VERIFICATION EXAMPLE
- RUN MODCOM IN!JJALEVALUATION?"YES ARE YOU SURE
?. (IF SO ANSWER YES) : _YES FREQUENCY AT WHICH YOU WISH TO P(RFORM COMPUTATIONS (15,30,0R 60 MINUTES) : _15 THE AVAILABLE OPTIONS ARE AS FOLLOWS:
OPTION DESCRIPTION 1
PERFORM TYPICAL DOSE RATE CALCULATION 2
LIST ACCUMULATED DOSES FOR ANY SECTOR (A-R) 3 SEARCH ALL SECTORS FOR HIGHEST DOSE AND REPORT OOSE DATA 4
PRINT ALL SECTOR DOSES (A-R) AT A SPECIFIED DISTANCE 5
UPDATE THE NUCLIDE DATA FILE 6
PERFORM DOSE PROJECTION (N0 DATA STORAGE) 7 LIST ACCUMULATED POPULATION DOSES FOR ANY SECTOR (A-R) 8 LIST ACCUMULATED GROUND CONTAMINATION FOR ANY SECTOR (A-R) 9 STOP PROGRAM EXECUTION PLEASE ENTER THE OPTION YOU DESIRE:
_6 THIS IS EVALUATION #
1 PLEASE ENTER THE FOLLOWING :
CURRENT YEAR 1982 CURRENT MONTH OF YEAR (1-12) : 07 t
CURRENT DAY OF MONTH (1-31) :
H PLEASE ENTER THE FOLLOWING METEOROLOGICAL DATA FROM SEDAR COMPUTER PRINTOUT :
DAY AND TIME ( 7 DIGIT NUMBER )
- 2090830 33' WINDSPEED
- 8 330' WINDSPEED 5
33' WIND DIRECTION 337 330' WIND DIRECTION 6
DT1 (VALUE MAY BE NEGATIVE) 43 DT2 (VALUE MAY BE NEGATIVE)
- M PLEASE ENTER THE FOLLOWING EFFLUENTS RELEASE RATE DATA -
l STACK GAS pCI/SEC.
1.0E7 l
STACK IODINES pCI/SEC.
2.0E5 l
STACK PARTICULATES pCI/SEC.
1.0E4 L
R.B.V. GAS pCI/SEC.
1.0E7
(-
R.8.V. 10 DINES pCI/SEC.
/
2.0E5
(.
R.B.V. PARTICULATES pCi/SEC.
1.0E4 WP/kk m
Procedure A.2-406 Revision 7 Page 15 of 16 ATTACHMENT 5 (Cont'd.)
MONTICELLO NUCLEAR GENERATING PLANT OFFSITE DOSE RATE COMPUTATIONS SPECIAL CALCULATION :
7-28-82 0830 STACK SECTOR = J S.
VENTS SECTOR = H SSE-STACK WINDSPEED = 5 MPH, VENTS WINDSPEED
= 8 MPH MAX PLUME DISTANCE = 10 MILES.
STACK STABILITY CLASS = 0.
VENTS STABILITY CLASS = D NO STACK FUMIGATION THE CALCULATED WHOLE BODY DOSE RATE VALUES ARE IN MREM / HOUR.
THE CALCULATED THYROID 00SE RATE VALUES ARE COMMITTED MREM PER HOUR OF EXPOSURE.
STACK STACK STACK EST'D VENTS VENTS W. 800.
W.800.
THYROID PLUME W.800.
THYROID MREM /HR MREM /HR MREM /HR ARRIV MREM /HR MREM /HR FINITE SEMINF S.B.
9.7 5.33E-04 4.92E-03 8:32 4.51E+02 3.64E+03 N. R.
7.3 0.2 2.4 8:36 96.
1.05E+03 1 MI 5.0 9.1 1.46E+02 8:37 56.
7.52E+02 2 MI 2.8 8.5 1.78E+02 8:45 16.
2.66E+02 3 MI 1.9 5.9 1.54E+02 8:52 7.5 1.45E+02 4 MI 1.2
- 3. 7 1.18E+02 9: 0 4.2 95.
5 MI
- 0. 7 -
2.3
- 90. '
9: 7 2.7 68.
6 MI 0.5 1.4 72.
9:15
- 1. 8 52.
7 MI 0.3 0.9 60.
9:22 1.2 42.
8 MI 0.2 0.5 50.
9:30 0.8 34.
9 MI 0.1 0.3 43.
9:37 0.6 29.
10MI 9.90E-02 0.2 37.
9:45 0.4 25.
STACK STACK VENTS VENTS PLUME X/Q PLUME X/Q WIDTH SEC/M3 WIDTH SEC/M3 METERS METERS S.B 1.72E+02 1.10E-10 1.87E+02 8.11E-05 N. R.
2.51E+02 5.33E-08 4.05E+02 2.34E-05 1 MI 4.95E+02 3.25E-06 4.95E+02 1.68E-05 2 MI 9.26E+02 3.96E-06 9.26E+02 5.92E-06 3 MI 1.34E+03 3.43E-06 1.34E+03 3.24E-06 4 MI 1.73E+03 2.64E-06 1.73E+03 2.12E-06 5 MI 2.12E+03 2.01E-06 2.12E+03 1.52E-06 6 MI 2.50E+03 1.60E-06 2.50E+03 1.17E-06 7 MI 2.87E-03 1.33E-06 2.87E+03 9.30E-07 8 MI 3.24E+03 1.11E-06 3.24E+03 7.65E-07 9 MI 3.60E+03 9.48E-07 3.60E+03 6.45E-07 10MI 3.96E+03 8.21E-07 3.96E+03 5.53E-07 WP/kk
Procedure A.2-406 Revision 7 Page 16 of 16 ATTACHMENT 5 (Cont'd.)
ana************mana************a****************a***************ma**xnamaanama NOTE TO SHIFT SUPERVISOR OR R.E.C.
WHOLE BODY PROTECTIVE ACTION GUIDELINE = 1000 MREM.
THYROID PROTECTION ACTION GUIDELINE = 5000 MREM.
SECTOR J S
SECTOR H SSE DISTANCE HOURS EST'D HOURS TO PLUME TO REi.CH ARRIVAL REACH A PAG TIME A PAG S.B.
1.03E+02 8:32
- 1. 4 N.R.
1.37E+02 8:36 4.8 1 MI 34.
8:37 6.7 2 MI 28.
8:45 19.
3 MI 33 8:52 34.
i 4 MI 42.
5 MI 55.
^
9: 0 53.
9: 7 73.
6 MI 70.
9:15 96.
7 MI 84.
9:22 1.20E+02 8 MI 1.00E+02 9:30 1.46E+02 9 MIN 1.18E+02 9:37 1.73E+02 10 MIN 1.36E+02 9:45 2.02E+02 INITIATE EMERGENCY PROCEDURE A.2-105, ATTACHMENT 2.
CONSIDER PROTECTIVE ACTION FOR SECTOR H SSE PLEASE ENTER THE OPTION.YOU DESIRE :
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Procedure A.2-411 Revision 1 Page 1 of 4 Op. Com, Rev. Reg'd.
Yes X No Q.A. Review Req'd.
Yes No x ALARA Review Req'd.
Yes' No X ESTABLISHMENT OF A SECONDARY ACCESS CONTROL POINT Procedure A.2-411 i
REVIEW AND APPROVAL Prepared by:
b r(95,v u ALARA Review:
Revision 0 Date
-1/26/82 Reviewed by: 6 3/hectli. - Q.A. Review:
Revision 0 Date 1/27/82 Operations Committee ~ Final Review: Meeting Number 1199 Date 4/28/83 Approved by:
'\\$lhbtsl.
Date 5-3-23 Oper.' Com. Results Review: Not Required Mtg. # 1064 Date 2/18/82 PURPOSE
~
The purpose of this proceaure is to provide instructions for establishing Access Control at an alternate location in the event that the active Access Control must be relocated.
CONDITIONS AND PREREQUISITES A.
High radiation exposure rates, contanination or airborne are present in the active Access Control area.
B.
The REC has recommended that Access Control be moved and the Emergency.
Director has so directed.
ORGANIZATION AND RESPONSIBILITIES A.
Overall Responsibility'- Emergency Director B.
In Charge - Radiological Emergency Coordinator (REC)
C.
Procedure Implementation - Radiation Protection Coordinator l
DISCUSSION The procedure establishes a Secondary Access Control Point ensuring that all personnel are properly badged with TLDs and dosimeters when the normal access control point has been evacuated.
It will also ensure that a means is available to monitor individual exposure and prevent exceeding exposure control limits.
RESPONSIBILITIES A.
Radiological Emergency Coordinator
- 1. Evaluate survey results and make recommendations to the Emergency Director regarding the necessity and location for a Secondary Access Control Point.
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Procedure A.2-411 Ravision 1 Page 2 of 4
- 2. Continue to monitor survey results, re-evaluating need and location of the Secondary Access Control Point.
B.
Radiation Protection Coordinator (RPC) l Upon notification of the establishment.of a Secondary Access Control Point implement this procedure and insure that all items listed in Figure 1 of this procedure are transported to the Secondary Access Control Point.
PROCEDURE STEP 1 On notification to establish a Secondary Access Control Point, transfer all TLD badges, self-reading dosimeters (low and high range), dosimeter chargers, personal history forms, exposure' records and blank dosimeter cards from the normal Access Control Point to the designated Secondary Access Control Point.
List of specific items are on Attachment 1.
STEP 2 Designate an RPS to be in charge of the Secondary Access Control Point.
Insure that Radiation Protection Group pdrsonnel maintain exposure control at the Secondary Access Control Point on a continuous basis (twenty four (24) hours per day).
Insure the issuance of TLD's and dosimeters is in accordance with Radiation Protection procedures.
NOTE:
With the possibility of high radiation areas existing, all personnel shall complete an Exposure History Form (NRC Form 4) prior to entry
)
into controlled areas which could result in exposure exceeding 300 millirem.
STEP 3 Establish communications between Secondary Access Control and the REC.
STEP 4 Place Secondary Access Control Point into operation following normal Access Control procedures.
STEP 5 Complete Establishment of Secondary Access Control Point Checklist, Form 5790-411-1.
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Proc @ dure A.2-411 Revision 1 Page 3 of 4 Figure 1 Secondary Access Control Point Equipment 1.
All unissued TLD's (50 additional TLD's are located at the EOF)
'2.
About 100 0-5R Dosimeters 3.
About 50 0-1R Dosimeters 4.
About 100 0-200 mR Dosimeters 5.
Dosimeter Charger / Spare Battery 6.
TLD Log Book 7.
Personal History Forms (#5525) 8.
NRC-4 Forms 9.
Monticello & Prairie Island Exposure Log Books 10.
Pens 11.
RWP Blank Forms (#5608) 12.
Blank Dosimeter Cards
- 13. Marking Pens 14.
High Radiat' ion / Airborne Area Entry Logs (#5503) 15.
Emergency Radio 16.
Compu,ter Exposure Records 17.
Frisker E
b F
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b Procedure A.2-411 Revision 1 Page 4 of 4 ATTACHMENT 1 Form 5790-411-1 Revision 1, 03/24/83 Page 1 of 1 Example of Establishment of a Secondary Access Control Point Checklist-1.
Date and Time Notified to Move Access Control:
Date:
Time:
Signature 2.
Equipment Moved to New Access Control Location:
I j-Signature ar-3.
RPS Designated to be in charge of Secondary Access Control:
Name of Person In Charge Signature 4.
Secondary Access Control in Operation:
Date:
Time:
Signature NOTE:
After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.-
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Procedura A.2-415 Revision 2 Page 1 of 7 Op. Com. Rev. Reg'd.
Yes X No Q.A. Review Reg'd.
Yes No X ALARA Review Reg'd.
Yes X No CONTAINMENT GAS SAMPLE OBTAINED AT POST ACCIDENT SAMPLING SYSTEM Procedure A.2-415 Prepared by:
h ALARA Review:
- 6) /.; / f.k Date 3bo[/3 Reviewed by:
//MM Q.A. Review:
Revision 0 Dato. 8/16/82 Operations Committee Final Review: Meeting Numbe :
//98' Oate 4//.2 //EG Approved by:
N.
Date 4 '2 7-R3 Op. Com. Results Review: Not Required Mtg. # 1100 Date 7/29/82 PURPOSE The purpose of this procedure is to provide special instructions and precautions for collection and handling of containment gas samples during and following an emergency at Monticello Nuclear Generating Plant.
CONDITIONS AND PREREQUISITE]
The Emergency Director / REC /CSL has requested analysis of torus, drywell or secondary containment (935') gas samples.
Actual or potential radiological conditions are such that special methods and/or precautions are necessary in order to collect and analyze samples under conditions which may present a much greater than normal radiation hazard to individuals performing the sampling and analyses. Unless directed otherwise, this procedure should be used in lieu of routine sampling and analysis procedures whenever an Alert or higher emergency classification is declared.
The torus and drywell gas sample line heat tracing should be on per Procedure A.2-425.
If a Group 2 isolation signal exists refer to Operations Manual Section B.4.1 for instructions to opening the samples valves (except SV-4081 and SV-4082) in STEP 1 of this procedure. To open sample isolation valves SV-4081 and SV-4082 (mid-drywell sample) an operator shall perform the following steps:
1.
Place the handswitches at panel C26 for the following valves to CLOSE:
SV-3307 CV-3311 CV-3313 SV-4081 SV-3308 CV-3312 CV-3314 SV-4082 2.
At panel C26, lift and tape the external wires at the following terminals:
a.
QS30/1 b.
Q528/1 WP/kk
b Procedura A.2-415 Revision 2 Page 2 of 7 l
3.
At panel C26, jumper the following terminals:
a.
QS30/X1 - Q530/1 b.
Q528/X1 - Q528/1 4.
Open sample isolation valv'es SV-4081 and SV-4082 by placing the handswitches HS-3305 and HS-3306 to AUT0/0 PEN.
ORGANIZATION AND RESPONSIBILITIES Emergency Director - Overall responsibility REC /CSL -
Responsible for assigning sample priority and frequency and results review.
Chemistry Technicians - Responsible for sample collection, analysis and results reporting.
PRECAUTIONS A.
Exposures of sampling and analysis personnel shall be in accordance with A.2-401, " Emergency Exposure Control".
B.
Exposure to all personnel due to sampling and analysis operations should be maintained as low as is reasonably achieveable.
Techniques such as temporary shielding, remote handling and sample dilution prior to analysis should be considered to reduce exposure to personnel.
C.
When actual or potential radiation levels so warrant, high range portable survey instruments, and self" reading dosimeters shall be provided to sampling and analysis personnel to permit rapid assessment of high exposure rates and accumulated personnel exposure. Alarming dosimeters should also be considered.
D.
Appropriate extremity dosimeters should be provided and worn when handling samples which themselves represent high level radiation sources.
E.
Calculations for exposure sates resulting from radiation within a few hours after a Loss of Coolant Accident point out the desirability of spending mini-mum amount of time that is necessary near the surface of the sample enclosure.
Most of the operation of the Post Accident Sampling System located at 951' of Turbine Building can be performed from the control panel. With the control panel located ten or more feet away from the sample enclosure the dose rates at the control panel due to radiation from the sample enclosur4 will be below 100 MR/HR.
The indicator for the area radiation detector RE-507 is on the PASS control panel and its reading should be noted whenever the presence of radiation is suspected.
REMARKS 1.
Prior to sampling notify the Control Room and advise Shift Supervisor of your intentions.
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e Procedure A.2-415 Revision 2 Page 3 of 7 REMARKS (Cont'd.)
2.
The Post Accident Sampling Station is located on the south side of the 951' level of the Turbine Building. The most efficient route to the PASS is through access control and into the Turbine Building. Move to the 951' level via the east stairway.
3.
Two-man teams should be used to obtain a post-accident sample when possible.
4.
Obtain controlled access key 33A from R.P. Coordinator and key #153 from Shift Supervisor.
EQUIPMENT RE0VIRED 1.
15 mi sample vial 2.
Gas vial positioner 3.
Gas vidl carrying cask 4.
Needles 5.
Neoprene cap 6.
Needle changing tool 7.
Flashlight 8.
Vial retainer ring crimper 9.
Aluminum retainer ring PROCEDURE STEP 1 Call Control Room and request an operator open the following valves depending on the sample desired (the opening of these valves shall be documented on the attached checklist):
Sample Valves Control Panel Descriotion Drywell SV-4081 C26 PAS System Isol. Valve SV-4082 C26 PAS System Isol. Valve SV-4020A C259 Inboard Drywell Isol. Valve SV-4001A C259 Outboard Drywell Isol. Valve SV-4004A C259 Inboard Sx Return Isol. Valve SV-4005A C259 Outboard Sx Return Isol. Valve Torus SV-4002A C259 Inboard Torus Isol. Valve SV-4003A C259 Outboard Torus Isol. Valve SV-4002B C260 Inboard Torus Isol. Valve SV-4003B C260 Outboard Torus Isol. Valve SV-4004A C259 Inboard Sx Return Isol. Valve SV-4005A C259 Outboard Sx Return Isol. Valve STEP 2 Open the nitrogen supply and regulate the supply pressure to 100 psi.
STEP 3 Turn on ventilation unit by depressing " START" button.
Verify vacuum by feeling suction at one of the gas ports.
STEP 4 Set switch HC-600 to position A if not already done. With the " Sump Drain System Switch" (HC-715) in the off position place switch HC-700 (Liquid / Gas Selector) in the " Gas" position.
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Procedure A.2-415 Revision 2 Page 4 of 7 s
PROCEDURE (Cont'd.)
STEP 5 Install the gas filter drawer into position.
STEP 6 Place a standard 15 milliliter off gas vial with rubber sectum into
~~
the gas vial positioner, slide the positioner into the gas cort (the higher of the two ports) at the sample station and turn it to lock it into place. Observe that the bottle status light changes from red to green.
STEP 7 Turn the " Gas Sample Selector Switch" (HC-723) to the desired sample location.
In addition set switch HC-500 to the position correspond-ing to the sample desired.
STEP 8 Turn the "15 ML Gas Sample Switch" (HC-705) to position 2 and " Circulate Gas" for a minimum period of 5 minuter.. Be sure that there is flow as read by the rotameter through the sample enclosure window (FI-725).
Record flow and flush duration on the Containment Gas Samo;ing and Analysis Checklist, Form #5790-415-1.
STEP 9 Turn HC-705 to position 3 and " Evacuate" the off gas vial.
Record the pressure of the evacuated vial (PI-708) on the checklist.
(Mike sure the vacuum in the gas vial reaches a stable minimum reading before recording pressure.)
r STEP 10 Turn HC-705 to position 4 "Take Sample".
Observe that the cressure
)
reading on PI-708 does not change as such would indicate a system leak.
STEP 11 Press the button to the left of HC-705 (HC-720 " Press for Sample") to obtain a sample.
Keep this button depressed until a steady pressure is reached.
This will require approximately 5 seconds.
Record the final pressure of the sample (PI-708) on the checklist. This pressure corre-
.sponds to the actual pressure of the sample being obtainea.
Record sample temperature (TI-724) on the checklist.
STEP 12 Turn HC-705 to position 5 " FLUSH SYSTEM" and flush for approximately 7
1 minute or until the area radiation monitor located on the sample station reaches a minimum.
STEP 13 Turn HC-705 through position 6, 7 and 8 and then straight up to "0FF".
STEP 14 Turn to unlock and withdraw the gas vial positioner.
Keep the vial at a maximum distance and quickly insert the sample bottle into the gas vial cask.
Close and latch the gas vial cask.
Put the gas vial positioner back into the port in the sample station.
STEP 15 Perform the Drain, Sump and Collection procedure (Procedure A.2-417).
STEP 16 Call Control Room and request that an operator close the valves that were opened in STEP 1 (the closing of these valves shall be documented on the attached checklist).
STEP 17 Turn ventilation off by depressing "STOP" button.
l l
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Procedure A.2-415 Revision 2 Page 5 of 7 PROCEDURE (Cont'd.)
STEP 18 Transport the sample to the hot lab for dilution and counting per Containment Atmosohere Radiochemical Analysis, Procedure A.2-420, or for hydrogen, oxygen and nitrogen per Chemistry Procedure I.1.36.
STEP 19 Calculate the sample volume (see NOTE 1) at the sample pressure and temperature as recorded in STEP 11 and record on Containment Gas Sampling and Analysis Checklist.
NOTE 1 Temperature ar.d pressure values must be converted to units of
- Kelvin and atmospheres prior to calculating gas volume.
= atmosphere
.0 h*(F-32)+273.15=
Kelvin 14.9x[1 x 298.15 = actual sample volume (cc)
T 1 Where P1 = final sx pressure (atm)-absolute pressure of vial (atm)
Ty = TI-724 (converted to KeIvin)
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Procedure A~2-415 Revision 2 Page 6 of 7 Form 5790-415-1 Example of x
Revision 2, 03/18/83
)
Page 1 of 2 CONTAINMENT GAS SAMPLING AND ANALYSIS CHECKLIST Samoling Initial 1.
Sample Source Date Time RPS 2.
~Sampie Identification No.
3.
Samole Flow FI-725 Flush Duration Min.
4.
Absolute Pressure of Vial PI-708 (psia) 5.
Final Sample Pressure PI-708 (psia) 6.
Samole Temperature TI-724 ( F) 7.
Calculated Sample Volume cc- (As Calculated)
Open the following valves corresponding to the desired sample (STEP 1 of procedure).
Valve Opened Verified By By Samole Valves Control Panel (Operator)
(RPS)
Drywell SV-4081 C26 SV-4082 C26 SV-4020A C259 4
SV-4001A C259 SV-4004A C259 SV-4005A C259 f
Torus SV-4002A C259 SV-4003A C259 SV-40028 C260 SV-40038 C260 SV-4004A C259 i
SV-4005A C259 WP/kk 4
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Procedura'A.2-415 Revision 2.
Page 7 of 7 Form 5790-415-1 Revision 2, 03/18/83 Page 2 of 2 Close the following valves corresponding to the desired sample (STEP 16 of procedure).
-Valve Closed Verified By By Sample Valves Control Panel (Operator)
(RPS)
Drywell SV-4081 C26 SV-4082 C26 SV-4020A C259 SV-4001A C259 SV-4004A C259 SV-4005A C259 Torus SV-4002A C259 SV-4003A C259 SV-40028 C260 SV-4003B C260 l
SV-4004A C259 SV-4005A C259 Analysis 1.
Spectrum Ran (Dilution Factors x
)
2.
Spectrum Analyzed 3.
Activity Calculated pCi/cc 4.
%H
-0
-N (See Chemistry Procedure I.1.36) 2 2
2 5.
Other analysis results as requested and comments:
Performed By:
Date:
Reviewed by: CSL or REC Date:
NOTE:
After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.
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Procedure A.2-416 Revision 2 Page 1 of 9 Op. Com. Rev. Reg'd.
Yes X No Q.A. Review Reg'd.
Yes No 1 ALARA Review Req'd.
Yes X No _
CONTAINMENT IODINE AND PARTICULATE SAMPLES OBTAINED AT POST ACCIDENT SAMPLING SYSTEM Procedure A.2-416 7k.A Prepared by:
egen-ALARA Review:
Od[I Date
.u- -
j Reviewed by: 77lI$ ct^t' Q.A. Review:
Revision 0 Date 8/4/82 Operations Committee Final Review: Meeting Number:
//97 Date e//2/ /f r Approved by:
M Date J/-27-f 3 o'
Op. Com. Results Review:
Not Required Mtg. # 1100 Date 7/29/82 PURPOSE 4
The purpose of this procedure is to provide special instructions and precautions for collection and handling of iodine and particulate samples during and follow-ing an emergency at Monticello Nuclear Generating Plant.
CONDITIONS AND PREREQUISITES The Emergency Director / REC /CSL has requested iodine / particulate analysis of torus, drywell or secondary containment (935') gas samples.
Actual or potential radiological conditions are such that special methods and/or precautions are necessary in order to collect and analyze samples under conditions which may present a much greater than normal radiation hazard to individuals performing the sampling and analyses.
Unless directed otherwise, this procedure l
should be used in lieu of routine sampling and analysis procedures whenever an Alert or higher emergency classification is declared.
l t
The torus and drywell gas sample line heat tracing should be on per Procedure A.2-425.
If a Group 2 isolation signal exists refer to Operations Manual Section B.4.1 for instructions to opening the sample valves (except SV-4081 and SV-4082) in STEP 1 of this procedure. To open sample isolation valves SV-4081 and SV-4082 (mid-drywell sample) an operator shall perform the following steps:
1.
Place the handswitches at panel C26 for the following valves to CLOSE:
SV-3307 CV-3311 CV-3313 SV-4081 SV-3308 CV-3312 CV-3314 SV-4082 2.
At panel C26, lift and tape the external wires at the following terminals:
a.
Q530/1 b.
Q528/1 WP/kk 9
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Procedura A.2-416 Revision 2 Page 2 of 9 CONDITIONS AND PREREQUISITES (Cont'd.)
3.
At panel C26, jumper the following terminals:
a.
Q530/X1 - Q530/1 b.
Q528/X1 - Q528/1-4.
Open sample isolation valves SV-4081 and SV-4082 by placing the handswitches HS-3305 and HS-3306 to AUT0/0 PEN.
ORGANIZATION AND RESPONSIBILITIES Emergency Director - Overall responsibility REC /CSL -
Responsible for assigning sample priority and frequency and results review.
Chemistry Technician - Responsible for sample collection, analysis and results reporting.
PRECAUTIONS A.
Exposures of sampling and analysis personnel shall be in accordance with A.2-401, " Emergency Exposure Control".
B.
Exposures to all personnel due to sampling and analysis operations should
)
be maintained as low as is reasonably achieveable.
Techniques such as temporary shielding, remote handling and sample dilution prior to analysis should be considered to reduce exposure to personnel.
C.
When actual or potential radiation levels so warrant, high range portable survey instruments, and self-reading dosimeters shall be provided to sampling and analysis personnel to permit rapid assessment of high exposure rates and accumulated personnel exposure. Alarming dosimeters should also l
be considered.
D.
Appropriate extremity dosimeters should be provided and worn when handling samples which themselves represent high level radiation sources.
E.
Calculations for exposure rates resulting from radiation within a few hours l
after a Loss of Coolant Accident point out the desirability of spending mini-mum amount of time that is necessary near the surface of the sample enclosure.
Most of the operation of the Post Accident Sampling System located at 951' of Turbine Building can be performed from the control panel. With the control panel located ten or more feet away from the sample enclosure the dose rates at the control panel due to radiation from the sample enclosure will be below 100 MR/HR.
The indicator for the area radiation detector RE-507 is on the PASS control panel and its reading should be noted whenever the presence of radiation is suspected.
]
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,4 Procedure A.2-416 Revision 2 Page 3 of 9 REMARKS 1.
Prior to sampling notify the Control Room and advise Shift Supervisor of your intentions.
2.
The Post Accident Sampling Station i located on the south side of the 951' level of the Turbine Building. The most efficient route to the PASS is through access control and into the Turbine Building.
Move to the 951' level via the east stairway.
3.
Two-man teams should be used to obtain a post-accident sample when possible.
4.
Obtain controlled access key 33A from R.P. Coordinator and key #153 from Shift Supervisor.
. EQUIPMENT REQUIRED 1.
Silver zeolite cartridges (4) 2.
Particulate filters 3.
Sample carrying cask 4.
Poly bag (medium) 5.
Radector III or equivalent
?ROCEDURE STEP 1 Call the Control Room and request that an operator open the following valves depending on the sample desired (the opening of these valves shall be documented on the attached checklist):
Samole Valves Control Panel Description Drywell SV-4081 C26 PAS System Isol. Valve SV-4082 C26 PAS System Isol. Valve SV-4020A C259 Inboard Drywell Isol. Valve SV-4001A C259 Outboard Drywell Isol. Valve SV-4004A C259 Inboard Sx Return Isol. Valve SV-4005A C259 Outboard Sx Return Isol. Valve Torus SV-4002A C259 Inboard Torus Isol. Valve SV-4003A C259 Outboard Torus Isol. Valve SV-40028 C260 Inboard Torus Isol. Valve SV-40038 C260 Outboard Torus Isol. Valve SV-4004A C259 Inboard Sx Return Isol. Valve SV-4005A C259 Outboard Sx Return Isol. Valve STEP 2 Open the nitrogen supply and regulate the supply pressure to 100 psi.
STEP 3 Turn on ventilation unit by depressing " START" button.
Verify vacuum by feeling suction at one of the two gas ports.
STEP 4 Set switch HC-600'to position A if not already done.
Set switch HC-500 to the position corresponding to the sample desired.
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Procedure A.2-416 Revision 2 Page 4 of 9 PROCEDURE (Cont'd.)
}
STEP 5 Verify that the " Sump Drain System" (switch HC-715) is in the OFF position.
Place switch HC-700 (Liquid / Gas Selector) in the Gas position.
N'OTE 1 See Attachment 1 for a description of filter cartridge retainer.
STEP 6 Pull out the gas filter drawer and check the filter cartridges.
If not already in place, put the 4 filter cartridges (numbered 1 through
- 4) into the cartridge retainer, and a particulate filter paper in the cap of the cartridge retainer.
Then put the cartridge retainer into the gas filter drawer and put the drawer into the sample station and verify that the drawer position light is green.
STEP 7 If a high activity condition exists or is suspected a timed sample should be taken.
For a timed sample set the timer KC-712 between the range of 0 to 30 seconds.
Select a low enough time so that the activity on the filter cartridge will not be unnecessarily high and cause special handling problems.
It is suggested that 5 seconds be used for the first try.
Observe the RE-704 reading to determine if there is a rapid activity buildup.
(This reading will also include non-adsorbing gases.) If the activity level does not exceed a preset value of 10 mR/hr, another timed flow through the cartridges can be made.
Record the selected time on the Iodine / Particulate Sampling and Analysis Checklist, Form #5790-416-1 or record that the sample is
)
untimed.
Set the switch located to the left of the timer labeled
" Time Sample" on either yes or no as appropriate.
If the activity of the first filter is > 10 mR/hr the 2nd, 3rd or 4th filters may be used for counting assuming previous filters are 99% efficient.
STEP 8 Turn the " Gas Sample Selector Switch" (HC-723) to the desired sample source.
STEP 9 Turn the " Iodine Cartridge Sample Switch" (HC-712) to position 2 and
" Circulate Gas" for a minimum period of 5 minutes.
Record the flush time on the checklist.
STEP 10 Observe flow as read by the rotameter which is visible through the window in the sample station enclosure.
Record the flow (FI-725),
temperature (TI-724) and pressure PI-726 and PI-727 on the checklist.
1 The two pressure gauges (PI-726 and PI-727), as read through the window, should be the same.
When the switch HC-712 is turned to position 3 the sample gas will start to flow through the filter cartridges. When the upstream pressure (PI-727) is > 16 inches of Hg. and PI-726 is about 0 inches of Hg, the flow will be " critical".
For a short duration timed cycle it will be necessary to have one technician ready to read the down-stream pressure gauge at the sample station while another turns the selector switch at the control panel in order to verify that the flow is " critical". When ready, turn switch HC-712 to position 3.
On the
_)
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Procedura A.2-416 Revision 2 Page 5 of 9 PROCEDURE (Cont'd.)
checklist record pressure PI-727, PI-726 and the sample time duration in seconds.
If flow is not critical record flow as indicated by FI-725.
STEP 11 After the timer has timed out for a timed sample or after the appropriate time has elapsed for a non-timed sample, turn selector switch HC-712 to position 4 to evacuate the filter cartridge.
STEP 12 After approximately 10 seconds turn switch HC-712 to position 5 which l
will admit an air or nitrogen flush through the filter cartridge to remove Krypton and Xenon gases.
This purge should last approximately 20 seconds or until RI-704 is stable.
Read and record RI-704 on the checklist.
STEP 13 Rotate HC-712 to its up and off position.
Turn other switches off.
Withdraw the filter drawer and remove the cartridge retainer and put it into a plastic bag.
Close the bag and tie or tape it closed.
Put the filter drawer back into the sample enclosure.
CAUTION:
No shielding cask is provided for the cartridge retainer and filter (s).
Survey the plastic bag which contains the sample and determine the dose rate. Use tongs to increase your distance from the sample. At the hot lab remove the filter cartridges.
STEP 14 Perform the Drain of Trap, Sump and Collector Procedure (Procedure A.2-417).
STEP 15 Call Control Room and request that an operator close the valves that i
were opened in STEP 1 (the closing of these valves shall be documented on the attached checklist).
STEP 16 Turn ventilation off by depressing "STOP" button.
I STEP 17 Transport the cartridge retainer to the hot lab for preparation fo'r radiochemical analysis per Procedure A.2-421.
STEP 18 Remove the filter cartridges and label 1, 2, 3 and 4.
Install new particulate and silver zeolite cartridges into the cartridge retainer for the next sample.
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Procedure A.2-416 Revision 2 Page 6 of 9
}
Page 1 of 1 CUT AWAY VIEW 0F FILTER CARTRIDGE NOTE: STAND ALONE NUMBERS ARE O-RINGS.
PARTICULATE FILTERS & HOLDERS 1.
(
T 3.
-C ARTRIDGE A
h 1 1 3 L/M l
ORFICE
~*I lar-i q2 l
I FLOW FLOW FLOW FLOW AIR FLOW 3q i) r O
O O
O
- i
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=
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s.L J.L J.L J n a n
u LARGE ILTER PAPER P ARTICUL A TE-RET AIN E R (4) SILVER ZEOLITE
(.003 lNCH S.S.
FILTERS SCEEEN)
FILTER PAPER NOTE:
Place cartridge into sample drawer with orifice end to the fixed butting surface.
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o; Procedure A.2-416 Revision 2 Page 7 of-9 Form #579C..
1 Example of Revision 2, 03/18/83 Page 1 of 3 IODINE / PARTICULATE SAMPLING AND ANALYSIS CHECKLIST SAMPLING 1.
Sample Source Date Time RPS 2.
Sample Identification No.
3.
Time Sample YES or N0 4.
Flush Time in Minutes 5.
Sample Flow SCFM FI-725 (not through cartridge)
Temperature TI-724 ( F)
Pressure PI-726 (psia)
Pressure PI-727 (psia) 6.
Pressure PI-726 (flow through cartridge)
Pressure PI-727 (flow through cartridge)
If flow not critical, Sample Flow SCFM FI-725 If flow critical flow is 3 liters / min.
Flow Duration Seconds 8.
Radiation RI-704 (mR/hr)
Open the following valves corresponding to the desired sample (STEP 1 of Procedure):
Valve Opened Verified by by
. Samole Valves Control Panel (Operator)
(RPS)
Orywell SV-4081 C26 SV-4082 C26 SV-4020A C259 SV-4001A C259 SV-4004A C259 SV-4005A C259 Torus SV-4002A C259 SV-4003A C259 SV-40028 C260 SV-40038 C260 SV-4004A C259 SV-4005A C259 WP/kk
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Procedure A.2-41o~u Revision 2 Page 8 of 9 Form #5790-416-1 Revision 2, 03/18/83-
)
Page 2 of 3 Close the following valves corresponding to the desired sample (STEP 15 of procedure):
Valve Closed Verified by by Samole Valves Control Panel (Ocerator)
(RPS)
Drywell SV-4081 C26 SV-4082 C26 SV-4020A C259 SV-4001A C259 SV-4004A C259 SV-4005A C259 Torus SV-4002A C259 SV-4003A C259 SV-4002B C260 SV-4003B C260 SV-4004A C259 SV-4005A C259
')
ANALYSIS Initial A.
IODINE 1.
Spectrum Collected 2.
Spectrum Analyzed 3.
Sample Volume cc 4.
Activity Calculated pCi/cc 5.
Filter Number Counted (1-4) 8.
PARTICULATE i
1.
Spectrum Collected 2.
Spectrum Analyzed 3.
Sample Volume cc 4.
Activity Calculated pCi/cc WP/kk 4
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Procedure A.2-416 w
Revision 2 Page 9 of 9 Form 5790-416-1 Revision 2, 03/18/83 Page 3 of 3 C.
Other Analysis Results as Requested.and Comments:
Performed by:
Date 4
Reviewed by: CSL or REC Date NOTE:
After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.
4 1
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