Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP-OSC-10 Re Assessment of Plant parameters,EPIP-OSC-15 Re Control Room Communicator & EPIP-TSC-7 Re Response Assistance
	ML20079P386
Person / Time
Site:	Fort Calhoun
Issue date:	12/01/1983
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20079P379	List: ML20079P380; ML20079P386;
References
	PROC-831201-01, NUDOCS 8401310202
	Download: ML20079P386 (67)
	v • d • e

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l VOLUME III OMAHA PUBLIC POWER DISTRICT - FORT CALHOUN STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS

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1. OPERATION SUPPORT CENTER Revision Last Review Procedure No. Title No./Date Date EPIP-OSC-1 Emergency Classification R4 11-18-83 11-18-83 EPIP-OSC-2 Emergency Plan Activation R6 3-31-83 3-31-83 EPIP-OSC-3 Notification of Unusual Event Actions R1 4-23-82 4-23-82

EPIP-OSC-4 Alert Event Actions R1 4-23-82 4-23-82 EPIP-OSC-5 Site Area Emergency Actions R1 1-14-82 1-14-82 i

EPIP-OSC-6 General Emergency Actions R1 1-14-82 1-14-82 EPIP-OSC-7 Personnel Rescue R2 8-30-83 8-30-83 EPIP-OSC-8 Medical Assistance R2 11-18-83 11-18-83 EPIP-OSC-9 Emergency Repairs, Corrective Actions and Damage Control R0 4-23-82 4-23-82 EPIP-OSC-10 Initial Assessment of Plant Parameters and Effluent Monitors to Detemine Source Tem R3 12-01-83 12-1-83 EPIP-OSC-11 Initial Dose Assessment Based on Plant Instrumentation R2 11-18-83 11-18-83 EPIP-OSC-12 Accidental Actuation of Early Warning Stren System R0 11-04-82 .

EPIP-OSC-13 Onsite Radiological Monitoring R0 8-02-83 8-02-83 EPIP-OSC-14 Emergency Duty 0fficer (EDO)

Actions R2 11-18-83 11-18-83 L EPIR-OSC-15 Control Room Communicator R0 12-01-83 12-01-83 l 8401310202 840120 DR ADOCK 05000 _ _

FC/EPIP/1

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TABLE OF CONTENTS (continued)

2. EMERGENCY OPERATION FACILITY Revision Last Review Procedure No. Title No./Date Date EPIP-EOF-1 Activation of Emergency Operation Facility R2 11-18-83 11-18-83 EPIP-EOF-2 Emergency Operation Facility Communication R2 5-13-83 5-13-83 EPIP-EOF-3 Emergency Instruments and Equipment R4 12-1-83 12-1-83 EPIP-EOF-4 Measurement of Airborne Radiaactivity (Incorporated into EPIP-EOF-6) R3 8-18-82 8-18-82 EPIP-EOF-5 Onsite and Offsite Dose Assessment (Computerized Prog.) R0 12-1-83 12-1-83 l

( EPIP-EOF-6 Onsite/OffSite Dose Assessment R4 12-1-83 12-1-83 j EPIP-EOF-7 Protective Action Guidelines R1 4-23-82 4-23-82 EPIP-EOF-8 Environmental Monitoring R1 5-13-82 5-13-82 EPIP-EOF-9 Personnel Accountability R3 5-11-83 5-11-83 EPIP-EOF-10 Personnel Decontamination R2 11-01-82 11-01-82 EPIP-EOF-11 Dostmetry and Records R1 9-14-62 9-14-82 EPIP-EOF-12 Site Security R1 1-06-83 1-06-83 EPIP-EOF-13 Shift Supervisor /EDO to EDO Transition R1 2-01-83 2-01-83 1 EPIP-EOF-14 EDO to Recovery Manager l Transition R1 11-10-82 11-10-82 '

EPIP-EOF-15 Determination of Contamination Release Through Plant Stack R2 11-18-83 11-18-83 L

11 12-01-83 1

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VOLUME III TABLE OF CONTENTS (continued)

2. EMERGENCY OPERATION FACILITY (Continued)

Revision Last Review Procedure No. Title No./Date Date EPIP-EOF-16 Continuing Dose Assessments Based On Plant Instrumentation R1 11-18-83 11-18-83 EPIP-EOF-17 Initiation of Fublic Warning R3 8-16-83 8-16-83 EPIP-EOF-18 Offsite Radiological Surveys R4 11-29-83 11-29-83 j A

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111 11-29-83 l

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VOLUME III TABLE OF CONTENTS (continued)

3. TECHNICAL SUPPORT CENTER <

Revision Last Review Procedure No. Title No./Date Date EPIP-TSC-1 Activation of Technical Support Center R4 11-18-83 11-18-83 EPIP-TSC-2 Technical Support Center Communication R2 5-13-83 9-22-82 EPIP-TSC-3 Plant and Reactor Operation Support - Alert Classification R1 11-04-82 11-04-82 EPIP-TSC-4 Plant and Reactor Operation Support - Site Area Emergency Classification R2 11-09-82 11-09-82 EPIP-TSC-5 Plant and Reactor Operation Support - General Emergency Classification R1 11-04-82 11-04-82

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EPIP-TSC-6 Plant Engineering and Repair R1 11-10-82 11-10-82 EPIP-TSC-7 Emergency Response Assistance Combustion Engineering R0 12-01-83 12-01-83 t

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l I iv 12-01-83

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.- s EPZP-0SC-10-1

- Fort Calhoun Station Unit No.1 Emergency Plan Implementing Precedure l EPIP-OSC-10 l Initial Assessment of Plant Parameters and Effluent Monitors to Determine Source Term I. PURPOSE To detemine the release rates of radionuclides from the plant, following an accidental release of airborne activity, these two methods are used:

A. Estimate release rates using stack or condenser off gas effluent ~

monitor data.

B. Estimate release rates using containment area monitor data, when the containment is isolated.

II. PREREQUISITES A. Emergency classification has been defined per EPIP-OSC-1.

B. Emergency plan has been activated per EPIP-OSC-2.

C. Effluent radiation monitors data is available for estimating release rates frem the stack or condenser off gas.

D. Containment exposure rates data is available from the containment area radiation monitor (s) and the containment has been isolated in order to detemina the release rates from the containment.

E. Post-Accident Procedure OI-PAP 7 is completed. l III. PRECAUTIONS None I

V. PROCEDURE

1. Source term using effluent monitors data.

(1) Complete Form FC-220, for meteorological data and calculation of release rate, 'Q' in Ci/sec. Refer to EPIP-EOF-6 for Form FC-220.

NOTE: Information from Form FC-220 will be used for performing initial dose assessment per EPIP-0SC-11.

G - $h"l g DEC 0 i W FC/35 Ugyw mar R3 12-01-83

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EPZP-0SC-10.-2 I

V. PROCEDURE

(Continued)

2. Source term using containment area monitor data (when containment is isolated).

NOTES: 1. Infomation from Table OSC-10.1 will be used for performing initial dose assessment per EPIP-0SC-11.

2. This procedure is used for obtaining the source tem for any type of accident, provided the dose rates in the containment and the release rates from the contain-ment for LOCA conditions are defined.

(1) Noble gas release rates.

a. Select the time after an accident at which release rate is to be calculated and enter in Table OSC-10.1.

b. Determine the containment area monitor reading from the control room radiation monitor readout and record in Table OSC-10-1.

c. Determine the containment dose rate for LOCA from Figure OSC-10.1 and record in Table OSC-10.1.

d. Determine the noble gas release rate from the containment for LOCA from Figure OSC-10.2 and enter this value in Table OSC-10.1. ___

e. Estimate the noble gas release rate from the containment for any accident by using the equation presented in Table OSC-10.1 and enter the result in Table CSC-10.1.

f. Notify the Plant Manager or EDO about the results.

g. Repeat steps a through e as deemed necessary.

(2) Iodine - 131 release rates.

a. Select the time after an accident at which the release rate is to be calculated and enter in Table OSC-10.1.

b. Detemine the containment area monitor reading from the control room radiation monitor readout and record in Table

- 00C-10.1.

c. Determine the containment dose rate for LOCA from Figure OSC-10.1 and record in Table OSC-10.1.

l

d. Detemine the Iodine -131 release rate from the containment I for LOCA from Figure OSC-10.3 and enter this value in Table OSC-10.1.

I WOTE: For time greater than 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months in Figure OSC-10.3, f use a value of 1.0E-04 Cf /sec.

l FC/35 dC0 iM R3 12-01-83

- EP8P-0SC-10-3 I

V. PROCEDURE

(Continued)

e. Estimate tr.e iodine release rate from the containment for any accident by using the equation presented in Table OSC-10.1 and enter the result in Table OSC-10.1.

f. Notify the Plant Manager or EDO about the results.

g. Repeat steps a through e as deemed necessary.

)

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FC/35 ISSUED -- R3 12-01-83

EPIP-OSC-id-4 TABLE.0SC-10.1 Release Rate Calculation Using Containment Area Radiation Monitors Date and Time of Accident .

1. Noble Gas Release Rates:

Time after the Accident (t): hrs.

Area lionitor Reading: R/hr.

Dose Rate frcan Figure OSC-10.1 at time 't* : R/hr.

Noble Gas Release Rate at Time 't' from Figure OSC-10.2: Ci/sec.

Therefore:

Noble Gas Release Rate (Q) = Area Monitor Reaoing x Noble Gas Release Rate for LOCA, (For any accident) Dose Rate for LOCA, Figure OSC-10.2 -

Figure OSC-10.1 . _. __ __

or: Q= R/hr x C1/sec _ ~

. R/hr _

or: Release Rate (Q) = _

C1/sec.

2. Iodine - 131 Release Rates Time after the Accident (t): hrs Area lionitor Reading: R/hr Dose Rate from Figure OSC-10.1 at time 't': R/hr Release Rate from Figure OSC-10.3 at time 't': Ci/sec ;

I l Therefore:

I-131 Release Rate (Q) = Area Monitor Reading x I-131 Release Rate for LOCA, (For any accident) Dose Rate fo'r LGCA, Figure OSC-10.3 Figure OSC-10.1 or: Q= R/hr x C1/sec R/hr or: Release Rate (Q) = Cf/sec.

t FC/35 R3 12-01-83

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. EPIP-OSC-15-1 Fort Calhoun Station Unit No.1 Emergency Plan Implementing Procedure EPIP-0SC-15 CONTROL ROOM COMMUNICATOR I. PURPOSE To provide a procedure which delineates the duties, responsibilities and actions of the Control Room Connunicator (6th Operator on duty).

Attachment 1 identifies infonnation requiring transmit, receiving activity, emergency response personnel requiring data and telephone numbers used to establish the conference network.

II. PREREOUISITES The Control Room Communicator has been trained.

III. PRECAUTIONS FC-194 and FC-197 are available in the control room emergency locker.

IV. PROCEDURE _

1. Reports to the Shift Supervisor and makes initial and follow-up i contact with State and County officials utilizing the Conference ,

Operations Telephone Network (COP) (Green _ Phone).

2. Take over the function of calling persons listed on the Emergency Call List from the Shift Supervisor. Continues this function until all personnel requiring notification (based upon accident classification (s)] have been contacted or the TSC phone talker assumes the responsibility.

3. Initiate and maintain an open telephone conference network with the following activities utilizing numbers listed below. Attachment 2 provides guidance in establishing the conference network and steps to follow when receiving or placing calls while in conference:

a. Control Room . . . . . . . . . . 6623:

b. OSC Manager . . . . . . . . . . 6632

c. ED0/TSC Manager phone talker . . 6787

d. Recovery Manager . . . . . . . . 6731

e. Emergency Coordinator . . . . . 6732

f. TSC Dose Assessment . . . . . . 6643

! NOTE: Personnel in this conference call should be phone talkers and i

not the principle person unless necessary.

R0 12-1-83 FC/EPIP/1 g,cp .

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EPIP-OSC-15-2 IV. PROCEDURE (Continued)

4. The on-shift STA ud11 collect meteorological dose assessment and l operational data from plant instrumention and complete FC-194 and FC-197, Part I and II, and the STA will pass this information to the Control Room communicator who will pass this information over the open conference network automatically every 15 minutes.

5. Maintain the control room emergency action log of all events. Thi s includes telephone notirication calls, telephone conversations, personnel accountability, etc.

DEC 0i SEB FC/EPIP/1 IS hD R0 12-1-83

,' AttaChmen 1 i

EMERGENCY RESPONSE FACILITIES CONFERENCE SYSTEM EPIP-0SC-IS-3 DA = DOSE ASSESSMENT CONFEfjfNCE 01 = OPERATIONAL INFORMATION TEl EPHONE CONIACT NUMBEfiS.

CH f423 OSC MAIJAGEH 6632

( OK PHONE I AL ER)

IPHONE TALKEHS (2 EACHs E00 J 1. M.)INTAIt4S LOG / POST ST ATUS BOARO ED0/TSC HAtlAGER 6787

/ L2. RECORDS MESSAGE ON FORMS. ( TSC PilONE TALKERI itLCOVE HY MANAGLH 6731 (REC MGR SECHETARY) o% g. - EMLHGf f4CY COOftu 6/32 4 (DOSE ASSESSMEt4T UPH) 6 th OPLHAIDH U.A. ISC DO5E ASSESSMEt4T 6643 Do (RAD PROI IECH) 0 0 C

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m TSC MCR STATUS BOARD en :~r H( V -

MGR CD INFORMATION REQUIRING INFORMATION RECEIVED BY M

a TRANSMIT o A. OPERATIONS INF ORMATION A. OPERATIONS INFORMATION

" 1. CH - CR COMMUNICAiOR 6th OPERATOR 1. E00 ( PHOT 4E T AIJER)

2. EDO ( THANSFERED l0 RECOVERY MANAGEH) 2. OSC (CLEHICAI %PT - PHOr.E T/4 VE R)

3. OSC Mt. NAGER 3. ISC (EDO PHONE TAlVEH)

1. TSC MANfaiEH 4. EOF ICLLHICAt ASSISTANil

8. DOSE ASStSSMENI INF OHMA l lON 0. DOSE ASSESSMENT DATA 1, CH - CR COMMUNICAluH nth OPLHAIDH 1. EDO I PtW4E T AL KEH)

2. Elki t THANSFEHED 10 EMER. EUURD.) 2. DA (RAD PROI.1ECH.)

3. OSC JOSE ASSESSMENT 3. EOF ( DOSE A55c.SSMEN T OFH. )

R0 12-1-83

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EPIP-03C-15-4 Attachment 2 ESTABLISHING A CONFERENCE CALL

1. Dial first number - tell individual to wait

2. Flash

3. Dial next number - tell individual to wait

4. Flash

5. Press

4 - now everyone is in conference

6. Repeat steps 2 thru 5 for all numbers RECEIVING CALL WHILE IN C0tFERENCE

1. Beep - (beep is heard when calling party waits on busy signal for 10 seconds)

2. Flash

3. Press

1 - you are now connected to caller

4. Flash Sa. Press

1 - you are now back in conference 5b. Prcss

4 - caller and you are now back in conference call PLACING CALLS WiiILE IN CONFERENCE

1. Flash

2. Dial Number - you may call wherever you wish

3. Flash

4. Press

1 - you are reconnected to conference FC/EPIP/1 eJ*b R0 12-1-83 l

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EP I.8-EOF-3-1 m

Fort Calhoun Station Unit No.1 Emergency Implementing Procedure J EPIP-EOF-3 EMERGENCY OPERATION FACILITY EMERGENCY INSTRUMENTS AND EQUIPMENT

{

I. PURPOSE The purpose of this procedure is to provide instructions for the use of instruments and equipment provided for use during dcsignated emergencies.

II. ,PREREOUISITE A. All emergency monitoring team members have been trained in the use of their instruments and equipment and the responsibilities of their jobs.

III. PRECAUTIONS

{

A. Samples of type which are collected during an emergency should be retained for subsequent analysis. f B. Instrument problems or malfunctions should be immediately brought to the I attention of the Monitor Team Coordinator.

IV. PROCEDURE

1. Operate radiation monitoring instruments in the following manner: l l

a. Operation of the E-520 (1) Check the instrument for physical damage.

(2) Place the instrument scale switch to the battery check position. The batteries are satisfactory if the needle is within the battery range indicated on the meter face.

l (3) When performing General Area Surveys, hold the instrument I detection at waist level. Approach the area or room to be '

surveyed with the instrument on the highest scale (2000 MR for E-520, 200 MR for E-530). Switch to lower scales as necessary to achieve an on scale reading.

(4) Contact readings are made by placing the detector in contact with the article to be surveyed. Down shift scales as necessary.

18 SUED ~

FC/26 R4 12-1-83

EPIP-EOF-3-2 l l

IV. PROCEDURE (Continued)

b. Operation of the HRTP (High Range Telescoping Probe):

(1) Check the ir,strument for physical damage.

(2) Place the instrument scale switch to the battery check position. The batteries are satisfactory if the necdle is I within the battery range indicated on the meter face.

(3) When performing General Area Surveys, hold the instrument detector at waist level. The probe should be extended to full length when entering an area or room of unknown radiation levels. Approach the area or room to be surveyed with tne instrument on the highest scale (500 Rem). Switch to lower scales as necessary to achieve an on scale reading.

(4) Contact readings are made by placing the detector in contact with the article to be surveyed. Down shift scales as necessary.

c. Operation of the Teletector:

(1) Check the instrument for physical damage.

(2) Place the instrument scale switch to the battery check position. The batteries are satisfactory if the needle is within the battery range indicated on the meter face.

(3) When performing General Area Surveys, hold the instrument detector at waist level. The probe should be extended to full length when entering an area room of unknown radiation levels.

Approach the area or room to be surveyed with the instrument on the highest scale (1000 Rem). Switch to lower scales as necessary to achieve an on scale reading.

(4) Contact readings are made by placing the detector in contact with the article to be surveyed. Down shift scales as necessary. _

d. Operation of the R0-2 and R0-2A, R0-4A and R0-5A (1) Check the instrument for physical damage.

(2) Check the instrument batteries by turning the function switch to BAT 1 and BAT 2 positions. The batteries are satisfactory if the needle reads above the BATT cut off line in both cases, i

(3) Turn the function switch to the zero position. Check that the meter reads zero. If not, set it with the zero knob.

(4) Perform an instrument function check as required by function check procedures.

DEC 6' 3 53 FC/26 , y -R4 12-1-83 l

l EP!P-EOF-3-3 IV. PROCEDURE (Continued)

(5) When performing General Area Surveys, hold the instrument at waist level. Approach the area or room to be surveyed with the instrument on the hignest scale. Switch to lower scales as necessary to achieve an on scale reading. 1 (6) Contact readings are made by placing the detector in contact ;

with the article to be surveyed. '

)

(7) When measuring Beta or Low Energy Gamma, open the sliding beta :

shield on the bottom of the case and face the bottem of the i instrument toward the radiation source.

2. Operate sample counters and friskers in the following manner:

a. Operation of the E-120 sample counter (1) Check the instrument for physical damage.

(2) Place the instrument scale switch to the battery check position. The batteries are satisfactory if the needle is within the battery range indicated on the meter face.

(3) Observe the background level prior to each sample count.

(4) Position the sample to be counted as indicated by the b instructions attached to the E-120.

(5) Start the sample count with the Range Switch on the highest scale. Down switch the scale until a good count rate is obtained.

(6) Observe the count rate for at least ten seconds. If the count rate continues to increase, observe until the count rate beccmes steady.

(7) Calculate the smear activity using the fannula given by the instructions attached to the E-120.

(8) Record and/or report the activity, time, date and location of the sample. Label each smear and save for later analysis.

b. Operation of the RM-14/RM-15 Frisker (1) Check the instrument for physical damage.

(2) Plug the power cord into a 115 VAC, 60Hz power supply. Place the instrument scale switch to the battery check position.

The batteries are satisfactory if the needle is within the

, battery range indicated on the meter face.

v 6

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EPIP-EOF-34 IV. PROCEDURE (Continued)

(3) If the batteries are low or dead, the instrument will not respond properly in either AC or battery operation.

(4) Detennine a background reading by holding the probe at waist level, facing downward for 15 to 20 seconds. Observe the count rate on the meter face. If the background levels are greater than 300 CPM, move the instrument to an area of lower background.

(5) Hold the probe approximatey one half-inch from the surface to De monitored. Move the probe at a rate of approximately four inches per second.

(6) Observe the count rate. To arrive at DPM/ probe, subtract the background reading from the meter reading and multiply the result by the efficiency factor listed on the instrument.

(CPM-CPM bkg.) Eff. = dpm/ probe.

c. Operation of the SAM-2 (1) Set up the SAM-2 as follows:

(a) Plug the power cord into the power supply provided in the vehicle.

(5) Connect the Eberline RD-22 detector to the SAM-2.

(c) Place the Channel 1 and 2 'IN-0VT" switches in the "IN" position.

(d) Check that Channel 1 " THRESHOLD" control is set at 3.27.

(e) Check that Channel 1 " WINDOW" control is set at 0.72.

(f) Place the Channel 1 "+0FF " switch in the "+" position.

(g) Place the Channel 2 "+0FF " switch in the "0FF position.

(h) Place the Count Mode Switch to the "STOP" position.

(f) Check that the Multiplier Switch is "0FF".

(j) Place the rate meter display switch to the Channel "1" position.

(k) Place the rate meter scale switch to the "XIK" position.

(1) Adjust the response switch to approximately mid range.

(m) P1 ace the display switch in the "0N" position.

(n) Place the stabilizer switch in the "0N" position.

FC/26 'R4 12-1-83

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EPIP-EOF-3-5 I

V. PROCEDURE

(Continued)

(o) Place the power switch to the "0N" position.

(p) Select a count time of 20 minutes.

(q) Place the count mode switch to the " TIMED" position.

1 (r) Obtain a background reading as follows:

1) Place an unused silver zeolite cartridge in the sample holder on shelf 4.

a) Press the " RESET-START" switch.

b) Record the counts from the digital display.

c) Divide the displayed count value by 20.

d) Record the gross count rate cpm.

(2) Collect the radiof odine and particulate sample.

(a) Properly place the silver zeolite cartridge and particulate filter into the 2 inch sample holder of the RADeC0 H809V.

t (b) With the power switch in the OFF position, plug the sample into a 115VAC/60HA outTbT.

(c) Adjust the motor reostat to give the lowest flow rate when the sampler motor is energized.

(d) Flip the power switch to the VARIABLE postion, and adjust the flow rate to 3 ft 3/ min. sample at this rate for 70 seconds.

(e) Turn the power switch to 0FF, and carefully remove the cartridge and particulate TTiter for analysis.

(f) Make appropriate sample log entries.

FC/26 ye *Jh am ar g4 12 1-83

1 l

EPIP-EOF-3-6 IV. PROCEDURE (Continued)

(3) Analyze the radiofodine sample with the SAM-2 (a) Place the silver zeolite cartridge in the sample holder on the desired shelf.

1) The first count should be performed on shelf 5. If there are no counts or the counts are low, proceed to shelf 4, then shelf 3. Additional samples from the same location may continue to be counted on the same shelf until a large change in count rate is noted.

(b) Select a count time of 5.0 minutes !

(c) Press the " reset-start" switch. Observe the count rate meter, adjust the scale switch as necessary.

(d) Record the counts from the digital display.

(e) Divide the displayed counts by 5 to get cpm.

(f) Calculate the radiofodine concentration of the sample.

uci/cc = bkg (Shelf Factor) 99110 (2.22 E+06) where:

Shelf Factor = Multiplication factor for the shelf used Shelf 5 = 91.7 Sheli 4 = G7.2 Shelf 3 = 50.4 2.22 E+06 = The conversion factor from DPM to microcuries (g) Record and/or report the sample concentraticn.

3. Use of Fixed Monitors

a. Area Radiation Monitors (1) To obtain information about radiation levels monitored by Area Monitors (RM-070 through RM-089 and RM-091A, RM-0918) contact the control rocm.

b. Process 14nitors (1) To obtain information about process monitor indications (RM-050 through RM-064) contact the control roon'.

c. Meterological Tower (1) To obtain meteorological data, contact the control room.

FC/26 CEC 0133 R4 12-1-83

6 .

EPIP-EOF-3-7 I

V. PROCEDURE

(Continued)

4. Use of power converters i , a. When the vehicle engine is started, the inverter will automatically

operate to provdie both AC and DC power to the installed outlets in i the vehicles.

] b. Other than maintenance, no operator action is required.

1 i

4 l

1 I

(

)

1 4

1 i

I 4

1

.R4 12-1-83

EPIP-EOF-5 1 Fort Calhoun Station Unit No.1 Emergency Plan Implementing Procedure EPIP-EOF-5 ONSITE AND OFFSITE DOSE ASSESSMENT (Computerized Program)

I. PURPOSE This procedure establishes step by step instructions for the operation of the Tektronix-4105 computer tarminal to execute the Emergency Assessment of Gaseous and Liquid Effluents (EAGLE) Program on VAX 11/780. This procedure is the preferred method and a back-up method is provided in EPIP-EOF-6.

II. PREREQUISITES A. Emergency classification has been initiated per EPIP-OSC-1.

B, The Emergency Plan has been activated per EPIP-0SC-2.

C. The Emergency Operation Facility has been activated per EPIP-EOF-1.

D. Post Accident Procedure OI-PAP-7 is available.

( E. The Technical Data Book is available.

F. The Tektronix terminal along with associated equipment is available in the Dose Assessment rooms.

G. The Terminal and the Modem are plugged into an AC outlet.

H. A working knowledge of the Tektronix terminal is helpful.

I. The appropriate fom has to be filled out for each plume, for meteorological data and appropriate radiological data.

J. Release rate calculations have to be performed utilizing 1) Form FC-220 (attached to EPIP-EOF-6) or 11) EPIP-OSC-10, if the containment is isolated and there are no releases thru the stack.

III. PRECAUTIONS A. All releases (actual or potential) are treated as ground level for conservati sm.

B. Always use the lowest level winds and differential temperature data as input to the program.

C. Use the 10 meter temperature value as ambient te.nperature and effluents exit temperature (s).

~..

D. Update and perform the dose assessments ever, fifteen (15) minutes.

FC/34 R0 12-1-83

EPIP-EGE-5 IV. LIMITATIONS AND ACTIONS A. If either VAX 11/780 is down or communication with the computer via terminal 4105 cannot be established, the "Onsite and Offsite Dose Assessment" can be perfomed by EPIP-EOF-6.

B. Dose calculations cannot be perfomed concurrently on both teminals (one in the TSC and one in the EOF). The program has to be ended by one party (TSC or EOF) on a given plume befo.e the next party (E0F or TSC) can start calculation on the next plume.

Tabular displays menu for previous plumes can, however, be executed by a second party while the first party 13 perfoming calculations on the current 15-minute plume.

C. The dose calculations have to be ended on the current 15-ninute plume before switching to the tabular displays menu for additional data on the current plume.

V. PROCEDURE,

~

A. Entering the Computer System The remote telecommunicating accessibility between the VAX and the teminal is provided via 1200-baud modem lines. The log-on and the program calculations consist of the following steps:

1. Turn the terminal on by pushing the button on the CRT.

2. Pickup the telephone receiver, push the button on the modem to "TK" mode, listen to the dial tone on the telephone receiver and dial the following number in Los Angeles:

9-1-(213) 627-8523 Allow the telephone to ring until a cantinuous high pitched tone is received. Push the button on the modem to "DA" mode and hang up the receiver. YOU ARE NOW CONNECTED TO THE VAX SYSTEM.

NOTE: If the above telephone number is inaccessible due to any technical prplems, dial the following number in Chicago:

9-1-(312) 297 +d94 f Should the above communicatica lines develop any l

technical problems, the following number in Los Angeles may be used:

1 9-1-(213) 623-7187

3. Press the < RETURN > key twice and the VAX will prompt you to enter your user name as follows:

USER NAME:

FC/34 ISSUED ~ -

R0 12-1-83 l --

w s

EPIP-EGF-5-3 V. PROCEDURE (Continued)

A. Entering the Comeuter System (Continued)

4. Enter the following user name:

OPPD

5. Press the < RETURN > key and the VAX will now prompt you to enter the password as follows:

PASSWORD:

6. Enter the password and hit < RETURN) (only authorized individuals are provided the password).

NOTE: There will be no screen display of the password entered. Be sure to rerember the password. If wrong entry is made, the computer will log itself off automatically. Then go to step 2, above, for log-cn process.

7. Wait a few seconds and the following sign will appear:

3

8. Press the " Caps Lock" key down on the keyboard.

( 9. Enter @MODEL, following 3 and hit < RETURN >.

10. Hit < RETURN > at the end of the title page on the screen and the program will prompt you to the following menu indices on the screen:

MENU EMERGENCY ASSESSMENT OF GASEOUS AND LIQUID EFFLUENTS (EAGLE)

1. ATMOSPHERIC DIFFUSION AND DOSE CALCULATIONS

2. TABULAR DISPLAYS OF MODEL RESULTS

3. EXIT' ENTER MENU INDEX (1 thru 3) F3R PROGRAM EXECUTION:

r

11. Eriter "1" to start the program-.in response to "(1 thru 3)"

- ,above and hit < RETURN >. The menus within the program will guide you to various options that are available for diffusion and dose calculations.

NOTE: The diffusion and dose calculations can be aborted,

_ i.e., any mistakes can be corrected, by simultaneously v ,

pressing the following keys:

s <CTiiL> and <Y>

DEC o't g s FC/34 ~

- R0 12-1-83 N

s n

I EPIP-EOF-5-4 l V. PROCEDURE (Continued)

A. Entering the Computer System (Continued)

12. End the program for " Atmospheric Diffusion and Dose Calculations", for a given plume, by entering <END> at the end of a given plume. This will prompt you back to the menu indices as in Step 9, above. Enter "2" and hit < RETURN) to see the tabular displays for a given plume.

NOTE: Tabular displays can be exited by either following the instructions on the screen for Tabular Display Menu for by simultaneously pressing < CTRL > and <Y) keys.

B. Leaving the Computer System It is important to log-off the system when you are done with the program calculations. This can be done by simply entering the following command following "5" sign:

LOG 0FF i

l ISSUED l FC/34 R0 12-1-83 1

. EPIP-EOF-6-1

-- Fort Calhoun Station Unit No.1 DIERGENCY PLAN D1PLE!!ENTING PROCEDURE EPIP-EOF-6 Onsite and Offsite Dose Assessment I. PURPOSE A. This document provides instructions and calculations necessary to predict offsite dose rates based upon actual meteorological data, release rates and dispersion factor overlay.

3. This document also provides instructions and calculations necessary to determine actual offsite dose rates and verify activity release rates utilizing information from the onsite and offsite monitor teams.

II. PREREOUISITES A. Emergency classification has been defined per EPIP-OSC-1.

B. Emergency Plan has teen activated per EPIP-OSC-2.

C. Emergency Operation Facility has been activated per EPIP-EOF-1.

D. Instructions for the use of Emergency Instruments and Equipment

(, have been completed per EPIP-EOF-3.

E. Post Accident Procedure 01-PAP-7 is available.

F. Technical Data Book is available.

III. PRECAUTIONS None IV. PROCEDURE SECTION 1 - Assessment of Gaseous Releases.

1. Contact the control room and obtain the meteorological and radiological information necessary to complete Form FC-220.

2. Update the information in Step 1, above, as frequently as necessary, or at least every hour during an actual release.

3. Predicted Dose Rates:

A. USING THE TI-59 CALCULATOR (1) Complete attached Form FC-220, for meteorological data and calculation of. release rate, 'Q' by performing the following: Insert both sides of Mag Card marked " EOF Section 6.1" in side of calculator. Press 'CLR'.

DEC 0 ' SE3 FC/35 R4 12-01-83

EPIP-EOF-6 IV. PROCEDURE (Continued)

Meteorological Data:

a. Press 'A'. Enter the present hour's windspeed in mph, Press 'R/S'.

b. Enter the previous hours wind speed in mph, Press 'R/S'.

c. Record average wind speed from the display in m/sec.

d. Enter stack flow rate in CFM, Press 'R/S'.

PROCESS MONITOR DATA: (Frcm Control Room)

No. 1 RM-062*

a. Press 'CLR'. Press 'B', Enter counts-per-minute, Press 'R/S'.

b. Enter background counts-per-minute, Press 'R/S'.

c. Record net counts-per-minute from display on FC-220.

d. Enter monitor sensitivity in cpm , Press 'R/S';

uct/cc Record 'Q' (Release Rate) from display on

e. Press 'C',

FC-220 and DATA RI. CORD EOF-6.1 No. 2 RM-052 Repeat the above steps for RM-062 using parameters for RM-052.

No. 3 RM-060

a. Repeat steps a b, c, of No. I above, using RM-060 parameters.

b. Enter monitor sensitivity in . Press 'R/S'.

c. Press 'R/S' again, Enter RM-060 flow rate, Press 'R/S'.

d. Enter time of filter cartridge in service since the start of accident in minutes, Press 'R/S'.

e. Record 'Q' (Release Rate) from display on FC-220 and DATA RECORD E0R-6.1.

When RM-062 is not in service, use the data for RM-052.

DEC c 363 FC/35 w.v ** R4 12-01-83

F EPIP-EOF-6-3 IV. PROCEDURE (Continued)

?lo. 4 RM-061

a. Repeat steps a,b,c, of No. 1, above, using RM-061 parameters.

b. Enter monitor sensitivity in com, Press 'R/S'.

W

c. Press 'R/S' again, $nter RM-061 flow rate, Press 'R/S'.

d. Enter time of filter cartridge in service since the start of accident in minutes, Press 'R/S'.

e. Record 'Q' (Release Rate) from display on FC-220 and DATA RECORD EOF-6.1.

(2) To calculate the whole body or thyroid dose rate for the site boundary at plume center line, enter the actual x/Q in the calculator from Form FC-220. Press 'STO 06'. Proceed to (3).

To calculate the whole body or thyroid dose rate for other selected points, determine the diffusion factor, D.F., from the appropriate overlay, as determined from data on Fonn FC-220 and calculate x/Q from D.F. and average wind speed,ii as follows:

a. Press '0', Enter D.F. (di ffusion factor), Press 'R/S'. ,

b. Record 'x/Q' from display in DATA RECORD E0F-6.1.

(3) Calculate the dole body dose rate for the selected locations as follows:

a. Enter 'Q' in C1/sec for RM-062* from FC-220. Press 'ST0 05'.

b. Press '2nd A', 'RCLO6', then 'R/S' .

c. Record 'DWB' Whole Body Dose Rate from display in DATA RECORD EOF-6.1.

(4) Calculate thyroid dose rate at the selected locations as follows:

a. Enter 'O' in Cf/sec for RF-060 from FC-220, Press 'STO 05',

then '2nd D' , 'R/S' .

b. Record 'Dr' Thyroid Dose from display in DATA RECORD EOF-6.1 v .,

Use RM-052 f f RM-062 is unavailable.

FC/25 OEC 0 1583 R4 12-01-83 l

L --

I EP IP-EOF-6-4 IV. PROCEDURE (Continued)

(5) Record the selected location coordinates, D.F., x/Q, Dyg, and D 7 i for each selected location on DATA RECORD EOF-6.1. j (6) Convey the dose rate data to the Emergency Coordinator and post the data on the status board.

B. USING THE MANUAL CALCULATIONS (1) Complete attached Form FC-220, for meteorological data and calculation of release rate, 'Q' .

(2) To calculate .the whole body or thyroid dose rate for the site coundary ac plume center line, enter the actual x/Q from Form FC-220 in DATA RECORD EOF-6.1. Proceed to (3).

To calculate the whole body or thyroid dose rate for other selected points, determine the diffusion factor, D.F., from the appropriate overlay, as determine from data on Form FC-220 and calculate x/Q from D.F. and average windspeed, uI, as follows:

= /

x/Q = 0.F. u. v .

u u

= sec/m3, enter this value in DATA RECORD EOF-6.1.

(3) Calculate Whole Body dose rate for the selected locations as follows:

OWB = 0.25 x 0.80 x 3.6 x 106x Q x x/g mrem hr

= 7.2 x 105 x x Q for RM-062 x/Q (or RM-052)*

= mrem /hr.

(4) Calculate thyroid dose rate for the selected locations as follows:

Dr = B x DCF x Q x x/Q x 3.6E + 06 mrem hr

= 3.6E+06 x 5.9E-05 x 6.23E+06 x Q x x/Q

= 1.55E+09 x x Q for RM-050 x/Q

= mrem /hr

Use RM-052 data only if RM-062 is unavailable.

R4 12-01-83 FC/35 SEC o r

33

l EPIP-EOF-6-5 (5) Record the selected location coordinates, D.F., x/Q, DWB and D7 for each selected location on DATA RECORD E0F-6.1.

(6) Convey the dose rate data to the Emergency Coordinator and post the data on the status board.

4. Actual Dose Rates (at selected locations utilizing data from onsite and offsite monitor teams).

A. USING THE TI-59 CALCULATOR (1) Obtain the whole body dose rate from the monitor team for direct radiation dose rate measurements and enter in DATA RECORD EOF-6.1.

(2) Calculate Thyroid dose rate for selected locations as follows:

a. Press 'E', Enter ' x' supplied by monitor team.

Press 'R/S'.

b. Enter

x' in display again.

c. Press 'R/S'. Record 'Dr' thyroid dose from display in DATA RECORD E0F-6.1.

(3) Convey the dose rate data to the Eraergency Coordinator e and post the data on the status board.

B. USING THE MANUAL CALCULATIONS (1) Obtain the whole body dose rate from the monitar i

team for direct radiation dose rate measurements and enter in DATA RECORD E0F-6.1.

(2) Calculate thyroid dose rate for selected 1ccations as follows:

D r = 3 x DCF x x x 3.6E+06

= 3.6E+06 x 6.9E-05 x 6.23E+06 x x ,

1

= 1.55E+09 x mrem /hr x*

(3) Record actual dose rates on DATA RECORD E0F-6.1.

(4) Convey the dose rate data to the Emergency Coordinator and post the data on the status board.

b

Supplied by monitor team. ;

FC/35 OEC 0 ,g R4 12-01-83

s

EPIP-EOF-6-6*

3 IV. PROCEDURE (Continued)

5. In the event that RM-060, or RM-062, (RM-052 f f RM-62 is not available) are off scale, refer to Fort Calhoun Station Unit No.1 OPERATING INSTRUCTION 01-PAP-7, POST ACCIDENT PROCEDURE.

(1) Determine Thyroid or Whole Body dose rates, as per sections A.4 or A.5 of this instruction, utilizing specific activity, x, or release rate, Q, from OI-PAP-7.

(2) Convey the dose rate data to the Emergency Coordinator and post the data on the status board.

i N CEC C 130 FC/35 5EI"- ~

R4 12-01-83 P

. EPIP-EOF-6-7 IV. PROCEDURE (Continued)

SECTION 2 - Assessment of Liquid Releases Estimate the total specific activity in the Missouri River at the MUD intake structure after a Liquid Release under accident conditions:

Part I - RM-055 or RM-055A Functioning:

NOTE: Go to Part II if neither RM-055 nor RM-055A is functioning.

1. Obtain the tank release rate from the control room and record here gpm.

2. Obtain the RM-055 or RM-055A reading from the control room. Subtract '

the background reading and record here ncpm'.

3. Obtain the Missouri River flow rate and speed from the U.S.

Coast Guard, phone 221-4712, and record here cfs, mph.

4. Plot the intersection point of the tank release rate and RM-055 (in ncpm) or RM-055A (in nepa) reading on Figure EOF-6.1 or Figure EOF-6.2. (Use Figure EOF-6.1 for RM-055 and Figure EOF-6.2 for RM-055A). This point defines a line of constant activity release rate on or parallel to those in Figure EOF-6.1 or Figure EOF-6.2.

I

5. Follow the nearest higher if ne of constant activity release rate to the river flow rate (Y-axis).

6. Read the total activity at MUD intak3 structure from the top scale based upon the intersection point of 5, above and record the value here pC1/ml and in Table E0F-6.1.

7a. USING THE TI-59 CALCULATOR:

Press ' SBR CE' Enter the radionuclide activity from Column I of Table EOF-6.1.

Press 'R/S'. Record the resulting data in Column III of Table EOF-6.1.

Enter the radionuclide activity, again and press 'R/S'. Record data in Table EOF-6.1. Continue until the five listed radionuclide activities are calculated.

7b. USING THE MANUAL CALCULATIONS:

Calculate the isotopic activity of the radionuclide from Column I and II of Table EOF-6.1 and enter the data in Column III of Table E0F-6.1.

8. Protective actions -

If the projected activity at the MUD intake structure, or any of the radio-nuclide under Column III of Table EOF-6.1 is greater than or equal to pertinen s~

values shown under Column IV, notify the MUD (554-7946) and tne State of Nebraska (402-473-1721) imediately for appropriate protective action (s).

(monitor reading in m - backgrcund in cpm) i

k:y@ghD a T R4 12-01-83 FC/35 .

DEC c ; M3 p es t_ s l

I '

EPIP-EOF-6 IV. PROCEDURE (Continued)

Part II - RM-055 or RM-055A Not Functioning:

1. Obtain the tank release rate from the control rcen and record here gpe.

2. Obtain the river flow rate and speed from the U.S. Coast Guard, phone 221-4712, and record here cfs, mph.

1

3. Obtain the total tank Gamma specific activity from the control room copy of the Liquid Release Permit and record here ,

uCi/ml. .

4. Plot the tank flow rate and total tank Gamma activity on Figure

! EOF-6.1 to define the line of constant activity release rate. i NOTE: Use Figure EOF-6.1 only as it provides conservative results. ,

5. Follow the nearest higher constant activity release rate line to the river flow rate (Y-axis).

6. Read the total activity at the MUD intake structure from the top scale from the intersection point of step 5 of this section and I record here uCi/ml and in Table E0F-6.1.

l 7a. USING THE TI-59 CALCULATOR:

Press ' SBR CE'. Enter the radionuclide activity from Column I.

Press 'R/S'. Record the resulting data in Column III of Table EOF-6.1. Enter the radionuclide activity ' again, and press 'R/S' .

~

Record data in Table EOF-6.1. Continute until the five listed radio-nuclide activities are calculated.

7b. USING THE MANUAL CALCULATIONS:

Calculate the isotopic activity of the radionuclides from Columns I and II of Table EOF-6.1 and enter the data in Column III of Table EOF-6.1.

8. Protective actions -

If the projected activity at the MUD intake structure, er any of

, the radionuclide under Column III of Table E0F-6.1 is greater than l

or equal to pertinent values shown under Column IV, notify the MUD i (554-7946) and the State of Nebraska (402-473-1721) immediately for l appropriate protective action (s).

l l

FC/35 R4 12-01-83

EPIP-EOF-6-9 IV. PROCEDURE (Continued)

SECTION 3 - Relationship of Key Isotopes and Trend Analysis

1. Meteorological Data:(use the current Form FC-220 data)

(1) Wind direction at 10 meters is

at hours.

(2) Obtain the actual X/Q value at the site boundary from the computer x/Q = _sec/m3 (3) If the selected location is not the site boundary, then use the following data to calculate the X/Q values at the selected location.

a. Wind speed at 10 meters is epa at __h o urs .

(present)

b. Wind speed at 10 meters is mph at hours.

(previous hours)

c. AVERAGE WIND SPEED (ii) = mph x 0.447.

= m/sec.

d. Assume a diffusion factor of 1.0 E-03 m-2 for population

(' exposure in the 2 mile zone.,

e. Assume a diffusion factor of 1.0 E-04 m-2 for population exposure in the 2 to 5 mile zone.

f. Assume a diffusion factor of 1.0 E-05 m ' for population exposure in the 5 to 10 mile zone.

g. Calculate the X/Q as follows using the average wind speed per step (3)c and the appropriate diffusion factor (D.F.)

per step (3)f, 3(g), or 3(h):

X = D.F. = ( ) m-2 V __

t ) m/sec n

(4) Stack flow rate = cfm (5) Condenser off gas flow rate = cf:n RM-057 ONLY

2. Whole Body Dose Estimates A. USING THE TI-59 CALCULATOR:

(1) Request for an air (gas and particulate) sample from the stack via RM-061 air pump or from the condenser off gas via RM-057 L air pump be drawn, and for an isotopic analysis of radionuclide listed in Table EOF-6.2.

DEC 1 3 R4 12-01-83 FC/35 . .

EPIP-EOF-6-10 -

IV. PROCEDURE (Lontinued)

(2) Enter the concentrations in Cf /m3 in Table EOF-6.2.

NOTE: luCf/cc = 1Ci/m3 (3) Enter '3' in the display. Press '2nd 9 17' , then ' CLR' . Insert sides 1, 2 and 3 of the two cards marked " EOF-6, Section 3" and "DWB, rO , Do, Table Construction" in the side of the calculator, pressing 'CLR' after each side is read.

(4) Enter x/0 (either calculated or actual) in the display Press 'STO 00'.

(5) Enter the ' stack or condenser off gas flow rate in 'cfm' in Table E0F-6.2 from 1.(4) or 1.(5) of this section and convert to 'm3/sec.' Press ' SBR x2 ' then 'R/S'. Enter the Stack Flow or Condenser off-gas flow rate in m3/sec in the display.

Press 'R/S'.

(6) Enter the radionuclide concentration in the display. Mul tiply the stack flow or condenser off-gas flow rate by the Radionuclide Concentration by pressing 'R/S' . Enter the Radionuclide release rate from the display into Table EOF-6.2.

NOTE: The average gamma energy factors are contained in the calculator program.

\

(7) Press 'R/S' and Er.ter the "Whole Body Dose Factor" from the display in Table E0F-6.2. Press 'R/S'. The Entry number 'n' will be displayed. If additional radionuclides are to be entered, press 'R/S', then repeat steps (6) and (7).

After the last "Whole Body Dose Factor" is displayed, press 'CLR', 'R/S', then on to Step (8).

(8) Press 'R/S' and enter the summation "gn (Qi) (Eyj)" in Table EOF-6.2 from the display.

(9) Press 'R/S' to calculate the Whole Body Dose Rate. Enter the i value' in the display in Table E0F-6.2.

1 (10) Repeat steps (1) through (9) as deemed appropriate. 1 B. USING THE MANUAL CALCULATIONS: l (1) Request for an air (gas and particulate) sample from the stack l via RM-061 air cump or from condenser off gas via RM-057 air I pump be drawn, and for an isotopic analysis of radionuclides listed in Table E0F-6.2.

(2) Enter the concentrations in Cf /m3 in Table EOF-6.2 UOTE: luci/cc = 1Ci/m3 R4 12-01-83 FC/35

EPIP-EOF.6-11 IV. PROCEDURE (Continued)

(3) Enter the stack or condenser off gas flow rate in 'cfm' in Table EOF-6.2 from 1.(4) or 1.(5) and convert to m3/sec.

(4) Multiply the radionuclide concentration by the stack or condenser off gas flow and enter the radienuclide release rate in Table

,! EOF-6.2.

(5) Obtain the "Whole Body Dosa Factor" by multiplying the radionuclide release rate by the average gama energy per disintegration and enter the value in Table EOF-6.2.

4 (6) Take the summation of "Whole Body Dose Factor" for all radionuclides and enter the value in Table EOF-6.2.

(7) Calculate the whole body dose rates by using the following i equation and enter the value in Table EOF-6.2.

DWs = 9.0 E+05 x/Q In (Qi) (Eyi)

Where:

DWB is the sole body rate in mrem /hr e

Qi is the radionuclide 'i' release rate in C1/sec EY is the average gamma energy per disintegration for i radionuclide '1' x/Q is the dispersion factor for a selected downwind distance in sec/m3 obtained from step 1.(3) above gn is the summation for radionuclides 'i' through 'n' and I

i 3 9.0 E+v5 is the conversion factor (8) Repeat steps (1) through (7) as deemed appropriate.

3. Thyroid Dose Estimates A. USING THE TI-59 CALCULATOR:

(1) Request for an air (filter and charcoal cartridge) sample from the stack via RM-060, and for an isotopic analysis of radio-nuclides Ifsted in Tables EOF-6.3 and E0F-6.4.

(2) Enter the concentrations in Cf /m3 in Tables E0F-6.3 and E0F-6.4.

( NOTE: luci/cc = ICi/m3 l l

1 C'EC 0 i l9t3 FC/35 t'e p.g.g} lim R4 12-01-83 1 s

EPIP-EOF-6-12 I

V. PROCEDURE

(Continued)

(3) Enter the stack flow rate in 'cfm' in Tables EOF-6.3 and EOF-6.4 from step 1.(4) above and convert to m3/sec.

a. If the whole body dose assessments have just been calculated using the TI program, continue by pressing 'CLR', ' SBR Inx',

and then 'R/S'.

b. If the whole body dose assessments have not just been calcu-lated using the program, enter '3' in the display. Press

' 2nd 9 17' , then ' CLR' . Insert sides 1, 2 and 3 of the two cards in the side of the calculator, pressing 'CLR' after each side is read. Press '522 STO 07', then ' SBR inx',

then 'R/S'. Enter x/Q (either calculated or actual) in the display. Press 'ST0 00'.

c. Enter the stack flow rate in m3/sec in display. Press 'R/S'.

(4) Enter the radionuclide concentration in the display. Multiply the stack flow or condenser off-centration by pressing 'R/S' gas .

flow Enter the rate by the Radionuclide Radionuclide release rate Con-from the display into Table EOF-6.3.

NOTE: The Thyroid Dose Conversion factors are contained in' the calculator program. ~

(5) Press 'R/5' and enter the " Thyroid Dose Factor" from the ,

display in Table EOF-6.3. Press 'R/S'. The entry number

'n' will be displayed. If additional Radionuclides are to be entered, press 'R/S', then repeat steps (4) and (5).

After the last " Thyroid Dose Factor" is displayed, Press 'CLR',

'R/S', then on to step 6.

(6) Press 'R/S' and enter the summation "In (Qt)(DCFi)" in i

Table E0F-6.3 from the display.

(7) Calculate the Thyroid dose rates to adults for different time intervals by the following:

a. For time interval <8 hours:

Press 'R/S'. When the display is stable, press 'R/S' again. Enter the value of the display in Table EOF-6.3 for Dose Rate <8 hours.

b. For time interval >8 hours:

Press 'R/S'. Enter the value in the display in Table EOF-6.3 for >8 hours.

(8) Repeat steps (1) through (7) as deemed appropriate.

I ne FC/35 fe

. g ,3,. g -j a: DEC oi SS R4 12-01-83 l

l .

. EPIP-ECF-6-13 IV. PROCEDURE (Continued)

B. USING THE MANUAL CALCULATIONS,:

(1) Request for an air (filter and charcoal cartridge) sample from the stack via RM-060, and for an isotopic analysis of radionucliees listed in Tables EOF-6.3 and EOF-6.4.

(2) Enter the concentrations in Cf/m3 in Tables EOF-6.3 and EOF-6.4.

NOTE: luci/cc

ICi/m3 (3) Enter the stack flow rate in 'cfm' in Tables EOF-6.3 and EOF-6.4 from step 1.(4) above and convert to m3/sec.

(4) Multiply the radionuclide concentration by the stack flow rate and enter the release rate in Tables EOF-6.3.

(5) Obtain the " Thyroid Dose Factor" by multiplying the release rate by the dose conversion factor (DCF) and enter the value in Table E0F-6.3.

(6) Take the sunnation of " Thyroid Dose Factors" for all radio-nuclides and enter the value in Table EOF-6.3.

(7) Calculate the thyroid dose rates to adult by using the following equation and enter the values in Tables E0F-6.3.

a. For Time Interval 0-8 Hours:

Dose Rate = B . x/Q Ini (Qi) (DCFi) rem /sec or D = 1.25 E+03 x/Q In (Qi) (DCFi) mrem /hr 1

Where:

0 is the thyroid dose rate in mrem /hr x/Q is the dispersion factor for a selected downwind j distance in sec/m3 obtained from step A.3 above In is the summation for radionuclides 'i' through 'n' Qi is the radionuclide 'i' release rate in Ci/sec.

DCFi is the dose conversion factor in rem /C1

! 1.25 E+03 is the conversion factor, and v B is the breathing rate for an adult in 3.47 E-04 m3/sec.

3 A3 g 759 g

"% MS i', Md $aM

. DEC : : 3

[ FC/35 -1 .. R4 12-01-83 l

- .~ ..

EPZP-EOF-6-14 IV. PROCEDURE (Continued)

b. For Time Interval Greater Than 8 Hours Dose rate = B .

x/Q rn (Qi) (DCFi) rem /sec i

or D = 8.35 E+02 x/Q zn (Qi) (DCF1) mrem /hr X i Where the terms are same as defined in step 7.1. above,

' with the exception of breathing rate of 2.32 E-04 m3/sec.

I (8) Repeat steps (1) thro 0gn (7) as deemed appropriate.

I e

6 I

e '

e DEC 0 i 9 FC/35 l _. '~N 1.)i 6.

1" '~:.)d R4 12-01-83

. EP8P-EGF-6-15 IV. PROCEDURE (Continued)

4. Lung Dose Estimates A. USING THE TI-59 CALCULATOR:

(1) Request for an air (filter and charcoal cartridge) sample from the stack via RM-060, and for an isotopic analysis of radionuclides 11sted in Tables EOF-6.3 and E0F-6.4.

(2) Enter the concentrations in Ci/m3 in Tables EOF-6.3 and EOF-6.4.

NOTE: luci/cc = 1Cf/m3 (3) Enter the stack flow rate in 'cfm' in Tables EOF-6.4 and from step 1.(4) above and convert to m3/sec.

a. If the thyroid dose assessments has just been calcu-lated, using the TI program, continue by pressing

'CLR'. Press ' SBR inx', then 'R/S'.

b. If the thyroid dose assessments have not just been cal-culated using the TI program, enter '3' in the display.

Press '2nd 9 17*, then CLR'. Insert sides 1, 2 and 3 of the two cards in the side of the calculator, pressing

(.- 'CLR' after each side is read. Press '588 ST0 07',

then ' SBR inx', then 'R/S'. Enter x/Q (from Section 3.1) in the display. Press 'ST0 00'.

c. Enter the stack flow rate in m3/sec in display.

! Press 'R/S'.

l (4) Enter the radionuclide concentration

in the display. Mul ti-ply the stack flow or condenser off-cas flow rate by the Radionuclide Concentration by pressing 'R/S'. Enter the Radionuclide release rate from the display into Table EOF-6.4.

NOTE: The Lung Dose factors are contained in the calculator program.

(5) Press 'R/S' and enter the " Lung Dose Factor" from the display in Table E0F-6.4. Press 'R/S'. The entry number

'n' will be displayed. If additional Radionuclides are to be entered, press 'R/S', then repeat steps (4) and (5).

After the last " Lung Dose Factor" is displayed, Press 'CLR',

'R/S', then on to step 6.

.

NOTE: If the Dose Conversion Factor (DCF) in Table EOF-6.4 is left blank for a particular radionuclide, do not enter that radionuclide concentration in the display.

., n e. . Enter the next concentration for which a conversion

factor is given, and continue.

FC/35 2" 2 P ? d] i.d f.3J, C 0 : g R4 12-01-83

EPIP-E0F-6-16 IV. PROCEDURE (Continued (6) Press 'R/S' and enter the summation "In (Qi) (DOFi)" in i

Table E0F-6.4 from the display.

(7) Calculate the lung dote rates to adult for different time intervals by, the following:

a. For time interval <8 hour s:

Press 'R/S'. When the display is Stable, press 'R/S' again. Enter the valua of the display in Table E0F-6.4 for Dose Rate <8 hours. ,

i

b. For time interval >8 hours:

Press 'R/S'. Enter the value in the display in Table EOF-6.4 for >8 hours.

(8) Repeat steps (1) through (7) as deemed appropriate.

B. USING THE MANUAL CALCULATIONS:

(1) Request for an air (filter and charcoal cartridge) siimple from the stack via RM-060, and for an isotopic analysis of radionuclides listed in Tables EOF-6.3 and EOF-6.4.

(2) Enter the concentrations in Ci/m3 in Table [ EOF-6.3 and E0F-6.4.

NOTE: luci/cc = 1Ci/m3 (3) Enter the stack flow rate in 'cfm' in Tables EOF-6.3 and E0F-6.4 fram step 1.(4) above and convert to m3/sec.

(4) Multiply the radionuclide concentration by the stack flow rate and enter the release rate in Table EOF-6.3 and EOF-6.4.

(5) Obtain the " Lung Dose Factor" by multiplying the release rate by the dose conversion factor (DCF) and enter the value in Table EOF-6.4.

(6) Take the summation of " Lung Dose Factor" for all radionuclides and enter the value in Table E0F-6.4.

(7) Calculate the lung dose rates to adult by using the following equation and enter the values in Tables EOF-6.3 and E0F-6.4.

a. For Time Interval 0-8 Hours:

Dose Rate = B -

X/Q In. (Qi) (DCFi) rem /sec i

or D = 1.25 E+03 X/Q In (Qi) (DCF1) mrem /hr-i

\ qpm,q'm

,? . CEC 0 , y FC/35

.., R4 12-01-83 l

~

EPIP-EOF-6-17 IV. PROCEDURE (Continued)

B. USING THE MANUAL CALCULATIONS: (Continued)

Where:

D is the lung dose rate in mrem /hr X/Q is the dispersion factor for a selected downwind distance in sec/m3 obtained from step A.3 above In is the summation for radionuclides 'i' through 'n' i

Qi is the radionuclide 'i' release rate in Ci/sec.

OCPi is the dose conversion factor in rem /Ci 1.25 E+03 is the conversion factor, and B is the breathing rate for an adult in 3.47 E-04 m3/sec.

b. For Time Interval Greater Than 8 Hours Dose rate = B x/Q In (Qi) (DCFi) rem /sec i

( of D = 8.35 E+02 x/Q gn (Qi) (DCFi) mrem /hr i

Where the terms are same as defined in step (7)a. above, with the exception of breathing rate of 2.32 E-04 m3/sec.

(8) Repeat steps (1) through (7) as deemed appropriate.

C

)j,$%%c?

- XC G 1 '.gn i

.4 .

FC/35 R4 12-01-83 l

e EPIP-EOF-6-18 Fort Calhoun Station Unit No.1 FC-220 1 of 4 Meteorological Data and Release Rates Calculation Sheet Time Cate , 19 Monitor METEOROLOGICAL DATA (From Control Room)

1. Wind direction at 10 meters is

at hours.

2. Temperature Difference ( AT) is 'c at hours.

STABILITY CLASS (from ( AT) and table below)

3. Wind speed at 10 meters is mph at hours.

(present)

4. Wind speed at 10 meters is mph at hours.

(previous hour)

AVERAGE WIND SPEED (u) = mph x 0.447 = meters /second

5. Stack flow rate = c fm.

6. Condenser off gas flow rate = cfm l RM-057 ONL/~l

7. x/Q (at site boundary) = sec/m3 _

STABILITY CLA55E5 )

AT('c) Class

<-1.9 A

-1.9 to -1.7 B

-1.7 to -1.5 C

-1.5 to -0.5 0

-0.5 to 1.5 E 1.5 to 4.0 F

>4.0 G PROCESS MONITOR DATA (From Control Room)

1. RN-052 reads cpm at hours RM-052 background cpm at hours RM-052 net cpm is ncpm.

I i

Q= cfm x [ ncpm ] x 4.72E-04 Itack Flow Rate [ 2.4E+06 cpm]

f ~.

[ (1) uGt/ccj RELEASE RATE (Q) = __ Ci/sec .

(1) Monitors sensitivity factors are per Revision 32, dated February 22, 1983 of the Technical Data Book. Use the revised data, if available.

R4 12-01-83 l FC/35 f DEC ot aga E

2

1 EP !P-EOF 19 FC-220 2 of 4

2. RM-062 reads cpm at hours RM-062 background cpm at hours RM-062 net cpm is neom.

Q= cfm x [ ncpm ] x 4.72E-04 5 tack Flow Rate [ 3.50E+07_ cpm ]

[ (1) pC1/cc ]

RELEASE RATE (Q) = _

Cf/sec

3. RM-060 reads cpm at hours.

RM-060 background cpm at hours.

RM-060 net cpm is ncpm.

RM-060 sample volume:

Sample Volume (cc) = [ Rft-060 flow rate (cfm)* ] x [ Time cartridge in service (min) ] x [ (28,317 (cc/ft3) ]

= CC

The average flow rate for RM-060 is approximately 2.3 cfm.

Q= cfm x [ nc Stack Flow Rate cc ]pm ] x 4.72E-04

[ 1.51E+04 Ac m x l

[ (1) pc1 (Sample Vol.)]

RELEASE RATE (Q) = Ci/sec NOTE: If the specific activity for fodine-131 has been detemined from the sample cartridge using isotopic ganna spectroscopy, the release rate from the plant may be calculated using the following equation:

Q= cfm x uCf/cc x 4.72E-04 Stack Flow Rate I-131 Spec. Activity RELEASE RATE (Q) = Cf/sec (1) lionit~ ors sensitivity factors are per Rivision 32, dated February 22, 1983 l of the Technical Data Boot. Use the revised data, if available. !

- ,g r m FC/35

{* '(

g DEC 0 i St R4 12-01-83 n: .h I

l

EPIP-E0P-6-20' FC-220 3 of 4 '

4. RM-061 reads cpm at hours.

Rtt-061 background cpm at hours.

RM-061 net cpm is ncpm.

RM-061 Sample volume Sample Volume (cc) = [RM-061 flow rate (cfm)*] x [(Sample collection time (min)*=] x [28,317 (cc/ft3 ]

= CC

The average flow rate for RM-061 is approximately 7 cfm.

Q= cfm x [ ncpm ] x 4.72E-04 5 tack Flow Rate [ 4.56E+05 cpm x cc ]

[ (1) uti~ (Sample Vol .)]

RELEASE RATE (Q) = Ci/sec

- The normal :anple collection time used for RM-061 is 60 minutes.

5. RM-057 reads cpm at hours.

RM-057 background cpm at hours. )

RM-057 net cpm is _ncpm 0= cfm x [ ncpm ] x 4.72 E-04 condenser off gas flow rate [ 4.0E+07 cpm ]

[ (1) uCi/cc ]

RELEASE RATE (Q) = Cf/sec.

6. RM-064 (is in review process)

(1) Monitors sensitivity factors are per Revision 32, dated February 22, 1983 i of the Technical Data Book. Use the revised data, if available. .

FC/35 s y.. m R4 12-01-83

- ',e DEC c . .vera

_ , ,'J \ ., : . .

^

l

EPIP-EOF-6-21 FC-220

7. PROCEDURE FOR DETERMINATION OF RELEASE RATE 7.1 RM-063L, RM-063M, and RM-063H for determination of noble gas releases:

RM-063 (L, M, or H) reads cpm At HOURS RM-063 (L, M, or H) background _

cpm At HOURS !

RM-063 (L, M, or H) net count ncpm i

Q= cfm X [ ncpm] X 4.72 E-04 x 2.31 j Stack Flow Rate [ cpm ]

[ (1) pCi/cc j Release Rate (noble gas) Q N.G. = Cf/sec 7.2 Determination of Release Rate for I-131 from the Ventitation Stack:

RM-063 Accident filter Contact Dose Rate At mr/hr AT HOUR Dose Rate The Surface of Filter Measured by Teletector Background Radiation In The Area Where The mr/hr AT HOUR Filters Are Measured

,- RM-063 Accident Filter Contact Dose Rate ar/hr

'? Net Dose Rate Subtracted By

Background

Convert net dose rate (mr/hr) to net filter activity (pC1) by multiplying by conversion factor 7.027 X 10-1 pCi/mr/hr (I-131) pC1 Sample Volume (cc) = (RM-063M or H Flow Rate 500 cc/ min) X (S g g Time

= CC uCi Q = cfm X-1 Net Filter Activity X 4.72 E-04 stack Flow Rate cc Sample Volume i

'l Q (I-131) = Ci/sec ij l

(1) Obtain the monitors sensitivity factors from the Technical Data Book.

FC/35 R4 12-01-83 l

. , p, 0

'2 " Yii M CEC : t S

. s"}kY b) fi6:b

D I

O R

Y L H A T

) U r I h G

/ A Y m D e O r B m

( E L

S O E H L T W A A U R T

C E A S O D d D I n O a R Y

2 D DH 2 E LT

- T I 3 6 C G 8

- I I -

F D D Y 1 O E E D 0 E 1R R O -

- .P P B 2 P 6 1 I - E P F: L 4 E OS O R EE H T W DA RR O

CE ES RO D

A EQc TE S e AT A ,s DI EE/

S LT1

- EAC F RR F

O D 3 N m A Q/

/c E xes T

I S

N O

N OR2 IOm ST/

UC1 FA FF I

D D

sl l uI tW iS tS.

N MO O R I

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MO C D F 3ns3.$0 e :s. O l:

h.

Ra <> so

.(# s..r t :

rk {~W

- EPIP-EOF-6-23 TABLE EOF-6.1 Projected Isotopic Activity at the MUD Intake Structure Comparison with the EPA Orinking Water Standard

1. Total activity using RM-055 or RM-055A: uCi/ml.

2. Total activity using the monitor tank data: uCi/ml.

Column I Column II_ Column III Column IV Total Isotope Projected Isotopic Activity Di stri'oution Activity (uC1/ml) EPA Standards *'*

Radionuclide From Above Factor (Col. I x Col. II (cC1/ml)

I-131 I O.15 3.0 E-09 Cs-134 0.45 2.0 E-05 Cs-137 0.10 2.0 E-07 Co-60 0.30 1.0 E-07 f

' - H-3 , 0.70 2.0 E-05 k

j

Reference:

National Interim Primary Drink Water Regulation EPA-570/9-76-003.

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3 0 '2' laNO'e i?

DEC[2 o: g aus R4 12-01-83 l

FC/35 l

3

EPIP-EOF-6-24

! TABLE E0F-6.2 Whole Body Dose Rate Stack or Coldenser Off Gas Flow Rate efm or cfm x 4.72 E-04

= m3/sec.

t '

Radio-nuclide Radionuclide Release Whole Body Concentration Ci/sec* Avg. Gamma Energy Dose Rate Factor Radionuclide Ci/m3 (Qi) Eyj (Mev/ dis) (Qi) (Ey ()

Kr-88 2.03 E+00 I-131 3.92 E-Oi !

I-133 6.24 E-01 I-135 1.56 E+00 Te-132 2.31 E-01 Xe-133 4.50 E-02 Xe-135 2.62 E-01 Cs-134 1.59 E+00 Cs-137 5.36 E-01 I"(Qi)(Eyi) =

Whole Body Dose Rate (DWB)*

= 9.0 E+05 x/Q rn (Qi) (Eyi)

= mrem /hr.

Radionuclide concentration (Ci/m3) x Stack or condenser off gas flow rate (m3/sec)

UI E FC/35 4 .7 w us R4 12-01-83

I EPIP-EOF 6-25 TABLE EOF-6.3 Thyroid Dose Rate l

Stack Flow Rate cfm or cfm x 4.72 E-04

= m3/sec.

Radio-nuclide Dose Radionuclide Release Conve nion Factor Thyroid Dose Concentration Ci/sec* Reu/Ci Factor Radionuclide Ci/m3 (Qi) (DCFi ) (Qt)(DCFi)

I-131 1.4 E+06 1-132 6.5 E+03 i

I-133 1.8 E+05 I-134 2.5 E+04 I-135 4.4 E+04 Te-132 9.7 E+04

(

In(Qi) (DCFi) =

1 Thyroid Dose Rate: {Dr ):

< 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months = 1.25 E+03 x/Q In (Qi) (DCFi) i mrem /hr

> 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months = 8.35 E+02 x/Q In (Qi) (DCFi) mrem /hr

Radionuclide concentration (C1/m3) x Stack flow rate (m3 /sec)

O%.E4) 3- DEC c 1 g i % a .--

n.Hj)y#Du 2.5 R4 12-01-83 FC/35

EPIP-EOF-6-26 TABLE EOF-6.4 Lung Dose Rate i Stack Flow Rate cfm or cfm x 4.72 E-04

= m3/sec.

Radio-

'nuclide Dose Radionuclide Release Conversion Factor Lung Dose Concentration Ci/sec* Rem /Ci Factor Radionuclide Cf/m3 (Qt) (DCFi ) (Qi)(DCFj)

I-131 2.4 E+06 I-132 1.0 E+03 I-133 3.1 E+03 I-134 -

I-135 2.5 E+03 Ru-106 3.9 E+06 Te-132 3.0 E+04 Cs-134 5.1 E+04 Cs-137 4.0 E+04 Ce-144 -

I

=

zn(Qt)(DCFi) i Lung Dose Rate: (Dg)

< 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months = 1.25 E+03 x/Q gn (Qi) (DCFi) i mrem /hr

> 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months = 8.35 E+02 x/Q rn (Qi) (DCFi) i mrem /hr

Radionuclide concentration (Ci/m3) x Stack flow rate (m3/sec) .

l@..sO E,,D4 FC/35 5"OIS

$ EC o t M R4 12-01-83

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.~'. EPIP-EOF-18-1 Fort Calhoun Station Unit No.1 Emergency Plan Implementing Procedure EPIP-EOF-18 0FFSITE RADIOLOGICAL SURVEYS I. PURPOSE To describe the actions to be taken by the offsite monitor team, Emergency Team Tag No. 5, 6, 7 and 8, in order to locate and define the radioactive plume.

II. PREREQUISITES, A. Individuals serving on the team have been trained in offsite radiological monitoring techniques, duties and responsibilities.

B. An ' Alert" or greater emergency classification has been declared.

C. Portable radiological survey instruments have been properly checked for operability prior to leaving the site and kept in service through-out monitoring process.

D. Communications equipment has been tested prior to leaving the site.

E. A copy of the "Erergency Radiological Monitor Station Booklet" is available in the monitor vehicle.

(' ~

F. The equipment / supplies listed below are in the monitor vehicle prior to departure from site:

1. SAM-2 Analyzer with RD-19 Detector 11. Plastic Bags for Waste

2. Air Samplers Radeco H809V (large size)

3. E-120 Survey Instrument with 12. Smear fledium (2" cloth smears)

HP-190 Probe and sample holder 13. Iodine Filter Cartridges

4. Water Sample Bottles (silver Zeolite)

S. Plastic Bags for Samples 14. Particulate Air Sample Filters (Small Size) 15. EPIP-E0F-3

6. Writing Tools 16. EPIP-EOF-8

7. Clipboard 17. Anti-Contamination Clothing

8. Survey Form (s) 18. Respirators

9. Disposal Gloves 19. Cold Weather Clothing

10. Extra Batteries (D-cell) (if appropriate)

20. Radio Operator Logs III. PRECAUTIONS A. Obtain or retain personnel dosimetry prior to leaving the site and wear it throughout the offsite monitoring process.

B. Allow counting instrumentation adequate "wann-up" time to prevent erratic counting results.

. C. Prevent cross contamination of samples by using care and disposal gloves when handling smears and particulate air filters.

EPIP/FC/35 * ?

Nt3 R4 11-29-83

EPIP-EOF-18-2 III. PRECAUTIONS (Continued)

D. Retain all samples. Clearly label each sample with collection location, ,

date time and name of person performing the survey (s) and complete the appropriate log located in the back of this procedure. Also note the j volume of air sampled for air samples. Store each sample in individual plastic bag.

E. When using the radio for communications speak slowly and clearly. (If 1

communications should fail, one member of the team should call either the Monitor Coordinator at the TSC or the Oose Assessment Coordinator at the EOF, dependent upon which function is controlling the teams. or physically report to the TSC or EOF, as appropriate, for additional comunications equipment and/or instructions.

TSC Monitor Coordinator: (402) 426-6780 EOF Dose Assessment Coordinator: (402) 536-4841 F. Maintain instruments in service during transit in order to identify trends.

G. Use Channel No. I to communicate with the Radio Operators at the TSC and EOF unless instructed otherwise by the Monitor Coordinator or Dose Assessment Coordinator. During drills and/or exercises, all radio transmissions will start and end with "THIS IS A DRILL MESSAGE" or "THIS IS AN EXERCISE MESSAGE".

H. Count all samples in low background area. This may necessitate '

leavinDe plume rea.

J IV. PROCEDURE

1. Assemble at the TSC.

2. One member of the team must pickup the keys to the designated emergency monitor vehicle which is parked on the east side of the GSB.

(NOTE: Keys for the vehicles are located inside each of the offsite monitor team kits. Kits are numbered the same as the OPPD vehicle

+ identification number.

3. Place offsite emergency kit and additional equipment / supplies (as listed under II.F of this procedure) into the monitor vehicle pr verify that they are already in place.

4. Prepare the SAM-2 for operation by referring to EPIP-EOF-3 for l instructions on set up and operation procedures.

5. Obtain initial instructions for sample type and location for first t l

j monitor station.

EPIP/FC/35 OV'4 Y R4 11-29-83

EP!P-EOF-18-3

. 1 I V. PROCEDURE (Continued)

6. Locate monitor station using the " Emergency Radiological Monitor Station i Booklet"; and proceed to the rionitor station as described in the directions j of the booklet. I

7. Begin surveying for radiation dose rate prior to entering vicinity of monitor station. Cetermine dose rates with either an E-120 with G-M probe or a RD-4 Ion Chamber meter. Record location (s) and dose rate reading (s) into log, Figure 18.1 of this procedure.

8. Report significant dose rate changes to the lionitor Coordinator or the Dose Assessment Coordinator, as appropriate, through the TSC or E0F Radio Operator. Refer to Section III.G. above for Precautions.

9. Coordinate locating'the plume's length, width and intensity with the Monitor Coordinator.

10. Prepare SAM-2 for counting iodine cartridge samples, as outlined in EPIP-EOF-3,Section IV.2.c.(1)

11. Setup E-120 with HP-190 probe for counting particulate air samples and scears, as outlined in EPIP-EOF-3,Section IV.2.a.

12. Pull and analyze air samples as directed:

~

a. Collect the radiofodine and particulate sample (s) using a _ _ _

Radeco air sampler in the manner described in EPIP-E0F-3,

( Section IV.2.c.(2).

b. Analyze the radiofodine sample using the SAM-2 analyzer, in accordance with EPIP-EOF-3,Section IV.2.c.(3).

c. Analyze the particulata air sample using the E-120 with HP-190 probe, in accordance with EPIP-EOF-3,Section IV.2.a.

13. Smear flat surfaces of 100 cm2 area for each smear.

14. Analyze smears using E-120 with HP-190 probe, as outlined in EPIP-EOF-3,Section IV.2.a.

15. Log all results. (Samples of survey logs are provided in Figures 18.1, 18.2 and 18.3.)

16. Report all results to the fionitor Coordinator or the Dose Assessment Coordinator through the Radio Operator.

17, Continue surveying for radiation dose rate trends.

18. P.cceed to next sample station (s) in accordance with directions.

Identify instrument fluctuations while travelling. At next monitor station, repeat procedure Steps 12 through 17.

S.)V 2 9 {gll R4 11-29-83 EPIP/FC/35 1

i

EPIP-E0F-18.-4 I

V. PROCEDURE

(Continued)

19. Continue perfonning radiological surveys (i.e. air samples, smears, dose rate surveys) until the full plume is defined and the team is -

instructed to return. l

20. Upon returning to the site, remove all protective clothing and contact the gate monitor for a thorough frisk. This should be done on the west side of the GSB, to facilitate decontaminatien, if necessary.

21. Deliver all samples and logs to the Monitor Coordinator in the TSC or the Dose Assessment Coordinator in the E0F upon returning.

i l

EPIP/FC/35 R4 11-29-83 l

EP!P-EOF-18-5 FIGURE E0F 18.1 SAMPLE OF 00SE RATE SURVEY LOG Date:

Instruments (s) Used (Type and Serial No.):

Description of Station Type of Dose Rate Time Sample Location ID Survey (B, 8) (mP/hr) Surveyor

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EPIP/FC/35 R4 11-29-83

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EPIP-TSC-7-1 Fort Calhoun Station Unit No.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-TSC-7 Emergency Response Assistance Combustion Engineering I. PURPOSE This procedure provides the instructions to be followed when an emergency occurs at Fort Calhoun Station that requires the support and assistance of Combustion Engineering, Nuclear Emergency Response Organization. It is expected that the Administrative Logistics Manager or his representative will perfonn this action.

II. PREREQUISITES A. Emergency classification has been defined per EPIP-OSC-1.

B. Technical Support Center has been activated per EPIP-TSC-1.

C. The recovery organization has been activated per EPIP-RR-1.

III. PRECAUTIONS f Hone IV. PROCEDURE

1. Den the C-E Nuclear Emergency Response Plan is activated, C-E will make available to the maximtan extent possible, any support or resources which is reasanably requested by OPPD. This support can include, but is not limited to:

a. On-site technical advice and consultation.

b. Off-site analysis and evaluation support.

c. On-site technical and construction support.

d. Overall support using C-E management, engineering, manufacturing, transportation, procurement, and construction resources.

2. Obtain the necessary information and complete the C-E Nuclear Emergency Response Initial Notification " Emergency Infomation" form (attachment 1).

l ISSllB R0 12-01-83 l

FC/EPIP/01 1

EPIP-TSC-7-2 IV. PROCEDURE (Continued)

3. Activate the Combustion Engineering Emergency Response Plan by calling OPPD's C-E Project Manager Ray Mills, 9-1-(203)285-9264 during normal work hours or 9-1-(203)243-1070 (Home Phone) after normal work hours.

If all attempts to reach Ray Mills fails the C-E Emergency Response Plan can also be activated by calling the following dedicated telephone number at any time: 9-1-(203)683-4669. This number will be answered by the C-E Security Force and is held in confidence at C-E. It is reserved strictly for utility activation of the C-E Nuclear Emergency Response Plan. If this fails see Step 6 below, i

4. When the initial contact answers (Ray Hills or Security Supervisor),

give him all information indicated on the C-E Nuclear Emergency Response Initial Notification " Emergency Information" form. He will be recording the information in a similar form. Be sure to indicate whether the message is for an EMERGENCY or a DRILL.

5. After the initial activation call, make sure the CALL BACK telephone numbers that wre given to C-E off of the " Emergency Infonnation" form are accessible and that personnel are available to provide C-E with updated information. This will enable C-E to initiate the appropriate emergency response. Attachment 2 - explains the type of response that can be expected. If communication difficulties are expected, keep the line to C-E open. If this is the case instruct the C-E individual not to hang up the phone. ,

6. In the event that the emergency number in Step 3 is inoperable and the C-E Project Manager (Ray Mills) cannot be reached, contact one of the individuals on " CALL LIST I" (See attachment 3) or another C-E Project Manager listed on the "C-E PROJECT MANAGER CALL LIST" (See attachment 4).

l' l

l 1

l FC/EPIP/01 ISSUED -- R0 12-01-83

EPIP-TSC-7-3

~

'C-E NUCLEAR EMERGENCY RESPONSE Attachment 1 INITIAL NOTIFICATION EMERGENCY INFORMATION I. CALLER _ TITLE __

(Blair, Nebraska)

(Fort Calhoun) LOCATION II. PLANT III. CALL BACK NUMBERS (402) 536-(Give two) (402) 536-IV. Is this call for an EMERGENCY or a DRILL ?(Circleone)

V. What is the NOTIFTCATION LEVEL? (Check one or more)

(, PHONE EXERCISE ( ) ALERT ( )

PRACTICE ( ) SITE 94ERGENCY ( )

NOTIFICATION ( ) GENERAL EMERGENCY ( )

VI. What is the C-E RESPONSE to be? (Check one)

.NONE ( ) CENTER ACTIVATION ( )

ALERT ( ) FULL RESPONSE ( ) ;

I VII. Is there additional EVENT DESCRIPTION? (Include dates and times)

You should give no more than one sentence at this tims.

VIII. READ THIS FORM BACK TO RECEIVER FOR VERIFICATION. _

Section 2.2 Rev.0 OEC 0 1 132 Effective June 18 19xF l

S D Page 3 OId R0 12-1-83 ,

l

EPIP-TSC-7-4 -

C-E MICLEAR EERGBCf RESPONSE Attachment 2 INITIAL N MIFICATION DERGENCY INFOR1ATION GLOSSARY I. CALLER, TITLE - That employee of the utility who is authorized to activate the C-E Plan and stipulate the level of response that C-E is to provide.

V. NCITIFICATION LEVEL - An indication of the degree of seriousness for which the C-E Plan is being activated.

PHCEE EXERCISE - A check of telephone operability.

PRACTICE - An emergency drill situation.

NOTIFICATICN, ALIRT, Sill! BfERGENCY, GENERAL 91ERGENCY -

As defined in h654, " Criteria for Preparation and Evaluktion -

of Radiological Emergency Response Plans and Preparedness in Support of M2 clear Power Plants".

VI. C-E RESPONSE - The C-E response action authorized by the utility.

NONE -

No C-E action authorized.

ALERT - C-E to inform its Emergency Response Organization but no further action is authorized. ,

CENIER ACTIVATION - C-E to infom its Emergency Response organization and assemble the Emergency Response Team at the Energency Control Center. Further action would be specified by the utility.

FULL RESP (NSE - C-E to provide Center Activation and in addition, bring all other Plan usources up to full alert.

Further action would nomally be specified by the utility, l but C-E would be authorized to take prudent, indepr. dent I action where timely utility approval could not be r.btained.

l 1

I Section 2.2 Rev.o

~

DEC oi g Effective June 18, 1981 l SUED Page 4 of~6 R0 12-1-83

.. . \ '

- EPZP-TSC-7-5 C-E NUCLEAR EMERGENCY RESPONSE Attachment 3 INITIAL NOTIFICATION CALL LIST I NOTE: If busy, have operator break in on call.

EMERGENCY or DRILL 7 (Circle one)

(203) 688-1911 NAME C-E WORK EXTENSION HOME PHONE John Conant 3862/4362 (203) 653-7678 Rsy Hills 4738 (203)243-1070 Jonas Strimaitis 3654/4681 (203)651-3601 Reid Wolf 5661/3762 (203)688-4818

(

Fred 5 tern 3111/9541 ,.(203) 232-6056 , ',

~

Section 2.2 Rev 1 DECO 1 W 1

I S ED Effective November 4.1981 Page 5 of 6 R0 12-1-83

C-E MICIJiAR IMiRGINCY RESIO4SE INITIAL MTTIFICATION C-H IWulrr MANAGER CALL I.IST ummmme *

@ M7ill: If busy, have operator bmak in on call.

M INDICENCY or DRILLT (Circle one)

LTilLITY PinJECT MANAGER ASSISTA>(r PRQ',ECT MANAGER rT1

@ AP6L llame Tel.

T. A. Jots!S (1TN)

(413)357-8764 R. P. O'NE111 (RIGI)

(203)651-8855 g Work Tel. (203)688-1911'X3173 (203)688-l'311 X3635 o BGGE.

~ P. W. KIUSE O' tis t:) M. A. MICilELSEN (MARK) lione Tel. (203)658-9377 (203)749-9508 Weekends.

8 Work Tel.

(203)739-9055 (203)688-1911 X2521 (203)f,88-1911 X2869 -

CPC W. D. MEIMilst (BILL) J. E. DAVISON (JOIN) llame Tel. (203)688-0559 (20i)6fl8-9116 -

Work Tel. (203)688-1911 X5594 (203)688-1911 X2868

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FPEL R. R. MILLS (RAY) T. P. GATES ('IIM) llome Tel. (203)243-1070 (413)357-6443 Work Tel. (203)688-1911 X4738 (203)688-1911 X3613 MAINE YANKim R. C. JAQUES (RAY) N. L. MARilGG (MARTY) llome Tel. (203)653-3538 (203)623-4113 2QW

Work Tel. (203)688-1911 X5592 (203)688-1911 X3110 meS g 2*- NEU R. C. JMEINIS (RAY) A. R. KASPER (AL) o ap3

u

% Tel. (203)653-3538 (203)749-0809 or 872-3586 g ,

krk Tel. (203)688-1911 X5592 , (203)688-1911 X3741 h S Un'ru R. R. MILLS (RAT) A. G. 50DENIlIRNM (AL) 8 @, lione Tel. (203)243-1070 (203)658-0759

$ g' b rk Tel. (203)688-1911 14738 (203)688-1911 X3133 i

s

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ML20079P386

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ML20079P386

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V. PROCEDURE

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