Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8109 Re Radiation Exposure Limits & HNP-8109 Re Continuous Air Monitors,Models AM-3D & Am-33-1,operations & Calibr
	ML20077F688
Person / Time
Site:	Hatch
Issue date:	06/22/1983
From:	Thomas Greene, Nix H, Rogers W; GEORGIA POWER CO.
To:	;
Shared Package
ML20077F682	List: ML20077F686; ML20077F688;
References
	PROC-830622-01, NUDOCS 8308010474
	Download: ML20077F688 (45)
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R_ADIATION EXPOSURE __ LIMITS A.

PURPOCE To provide limits of exposure for the protection of personnel against radiation hazards ar,is,ing from work associated with the operation of the Hatch Nuclear Plant.

The limits 08 exposure as set forth in this procedure are based upon applicable limits as described in 10 CFR 20, Standards for Protection Against Radiation.

A continuous effort will be made to reduce levels of radiation and radioactivity in order to maintain radiation doses as low as reasonably achievable below these established limits.

B.

REFERENCES 1.

10 CFR 20 1

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HNP-8010, 4812, 8005, 8021 l

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Reg Guide 8.13 I-

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Tech. Spec. Unit 1, Sect 6.11 C.

MAXIMLIM PERMISSIBLE EXPOSURE (10 CFR 20)1 (Tech. Sp_e c. Section 6.1 1_)

1.

The maximum quarterly exposure to the whole body, head and trunk, active blood forming organs, lens of the eyes or gonads shall be limited to 3,000 mrem / quarter.

2.

The maximum quarterly exposure to the skin of the whole body shall be limited to 7,500 mrem / quarter.

3.

The maximum quarterly exposure to the extremities, hands and forearms, feet and ankles shall be limited to 18,750 mrem / quarter.

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11 limits of exposure are based upon individuals 18 years of age and older.- No person under 18 years of age shall be occupationally exposed to ionizing j

radiation.

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The limits as set forth above are subject to the following conditions:

a.

The dose to the whole body, when added to the accumulated occupational dose, shall not exceed 5(N-18) rem, where "N"

equals the individual's age in years on i

his last birthday.

b.

The individual's accumulated occupational dose to the whole body has been determined and recorded on Form 1, Occupational External Radiation Exposure History.

No individual will be permitted to receive a whole body t

exposure in excess of 300 mrem / quarter unless he has submitted a signed statement indicating the amount of occupational exposure received during the current quarter from sources of radiation possessed or controlled by other licensees and a reasonable effort yv/

to obtain the individual's prior occupational exposure

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has been made.

In the event an individual.is unable to provide exposure information'for the current quarter, and his duties are likely to result in an exposure in

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excess of 300 mrem before such information could be obtained, authorization to 2500 mrem may be granted using Form 2 of this procedure, by the General Manager l

and the Health Physics Superintendent provided:

(1) a current. quarter exposure of 1250 mrem is assumed, (2) prior quarter exposures are known or have been calculated in accordance with 10 CFR 20.102(c)(1), and (3) the General Manager has declared the individual f

critical to start-up or continued operations.

D.

MAXIMUM PERMISSIBLE CONCENTRATIONS __IN AIR (10 CFR 2O_)_

No individual will be permitted to inhale a quantity of radioactive material in any period of one calendar quarter greater than the quantity which would result from inhalation for 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months per week for 13 weeks at uniform concentrations of radioactive material in air as specified in Appendix 8 Table I, Column 1.

If the radioactive materials are of such form that intake by absorption through the skin is likely, individual exposures to radioactive material shall be controlled so that the uptake of radioactive material by any organ from either inhalation or absorption or both routes of intake in any calendar quarter does not exceed that which would result from inhaling j'

such radioactive material for 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months per week for 13 weeks at

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I uniform concentrations specified in Appendix B Table 1, Column 1 of 10 CFR 20.

Refer to 10 CFR 20.

103 for further details.

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ADMINI,STPATIVE EXPOSURE GUIDES 1.

Administrative exposure guides are established to provide guidelines for plant operations in order that personnel exposures will be maintained within the maximum limits as established in 10 CFR 20 and Section O of this procedure.

2.

Exposure of the whole body shall be limited to 300 mrem / week.

This administrative limit, however, does not relieve the individual or his supervisor from their responsibliity to keep all radiation exposure as low as reasonably achievable (ALARA).

3.

Nhole body radiation exposure above 300 mrem in any week will require written approval from the immediate supervisor and a Lab Foreman on Form 2, Authorization to Exceed Administrative Exposure Guides.

4.

Exposure of the whole body shall be limited to 1,250

,j mrem / quarter.

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Wholebodyradiationexposureabo've1,250 mrem /kuarterupto 2,000 mrem / quarter will require written approval from the

~07, immediate supervisor and a Lab Supervisor on Form 2, Authorization to Exceed Administrative Exposure Guides.

6.

From 2,000 up to 2,500 mrem / quarter will require approval of the individuals supervisor and the Health Physics Superintendent and Manager-Health Physics and Chemistry.

In no case, except for conditions as specified in Section E.7 and H shall a whole body exposure exceed 2500 mrem / quarter as measured by pocket dosimeter or estimated by portable Health Physics instruments.

7.

If the General Manager declares it necessary to start-up or continued operation or the safety of the plant or personnel, he and the Health Physics Manager may, after careful consideration, authorize up to 3,000 mrem / quarter.

8.

All female employees working in the Protected Area will be l

required to acknowledge in writing that they have received instruction concerning prenatal radiation exposure on Form 4.

For purposes of administering a program for limiting exposure to pregnant women, the following administrative guides will be established.

Radiation exposure to female employees will be limited to 500 mrem per two month period unless a higher limit is specifically requested in writing by the employee on Form 4 i

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E.1. HATCH NUCLEAR PLANT HNP-8002 See Title Page m m,0%o ou 13 See Title Page Georgia Power eza 4 o, 3 Radiation exposure to pregnant women will be limited to 500 nRem.during the entire gestation period unless a higher limit is specifically requested in writing by the employee on Form 4 F.

ADMINISTRATIVE CONTROL OF INTERNAL EXPOSURE 1.

Exposure to airborne concentrations approaching the MPC's of 10 CFR 20 should be prevented.

If exposure above the MPC's are necessary, the wearing of properly fitted respiratory protective equipment or other appropriate methods will be required as determined by the Health Physics staff.

HNP-80lO specifies administrative controls for use of respiratory equipment.

2.

Plant personnel normally traversing Radiation Control Areas should have a whole body count annually, (see HNP-8021).

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EXPOSURE LIMITS FOR NON-PLANT PERPpNNEL

$7' 1.

Vendors, subcontractors, and other non-plant pe'rsonnel who are likely to receive a whole body radiation exposure in excess of 300 mrem in any calendar quarter shall be required

.,,3*a to furnish current radiation exposure records.

2.

The quarterly exposure to the whole body shall be limited to 1,250 mrem.

Any occupational exposure received at another facility during the current quarter (whether actual, based on TLD or film badge results, or estimated, based on pocket dosimeter results, or a combination thereof) shall be considered in the maintenance of this limit.

However, if mutual agreement between Georgia Power Company and the pertinent outside organization exists, and provided that the requirements of 10 CFR 20, Section 20.101 have been satisfied, this limit may be exceeded.

Refer to Form 2, Authorization to Exceed Radiation Exposure Guides.

Subcontractor personnel must have received the Radiation Protection Orientation lectures or demonstrate knowledge covered in the lectures, and must agree to abide by the regulations and policies of the Georiga Power Company prior to gaining access without escort-to areas where radiation exposures may be received.

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EMERGENCY AND ACCIDENTAL EXPOSURE Although an emergency situation transcends the normal i-requirements of limiting exposure, there are suggested levels for exposure.

Refer to HNP-4812 for guidance.

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ABNOHb1AL PERSONNEL _ EXPOSURES 4

Whenever a situation occurs involving the suspected or known exposure of personnel to ionizing radiation in excess of 10 CFR 1

20 limits specified in this procedure, the incident will be i

promptly investigated and personnel exposures evaluated.

I Personnel monitoring results that are either excessively high or excessively' low with respect to the work that an individual has i

been known to be doing, will also be immediately investigated.

All such' incidents will be immediately reported to the H.P.

Laboratory Foreman or his alternate.

A committee consisting of the L'aboratory Foreman, Health Physics Superintendent or his designee, and supervisor of the group in which the abnormal a

exposure occurred, will conduct an official investigation and i

issue a written report of its findings and recommendations to the concerned individual, his immediate supervisor and the Plant

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General Manager.

Every effort will be made to determine if the

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special bio-assays, whole body counting, radiation sprveys, and V

reviews of work assignments and working procedures.

~r.g The written report submitted will consist of the investigation, J

the evaluation of results documented on Form 3, Abnormal j'

Radiation Exposure, and a Radiation Occurrence Report (Figure 2

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RELATIVE BIOLOGICAL EFFECTIVENESS (R.G.E.) OR GUALITY FACTOR (G.F.)

l TYPE OF RADIATION R._B. E.

OR G.F.

VALUE*

4 X-ray, Beta, Gamma 1

3 Neutrons, Thermal 5

i Neutrons, Fast 10 Alphe and Heavy Particles 20 4

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or G.F.

is Damage Relative to Gamma or X-rays I

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OCCUPATIONAL EXTERNAL RADIATION EXPOSURE HISTORY

'I FORM 1 OCCUPATIQNAL EXTERNN. RADI ATION EXPOSLJ2E HISTORY 1.

NAME (PRINT-LAST, FIRST, AND MIDOLE) 2.

SOCIAL SECURITY NO.

3.

DAlt OF BIRTH (MLX41 H, DAY, YENt )

4.

AGE IN FLLL YEARS (N)

OCCUPATIONAL EXPOSLEE - PREVIOUS HISTgflY_ _

PREVIOUS DOSE HIGTORY

5. PREVIOUS EMPLOYMENTS

6. DATES OF

7. PERIODS OF

8. WHOLE

9. RECOHO EMPLOYMFNTS INVOLVING EM2LOY-EXPOSURE UOOY OR CAL-RADIATION EXPOSLME -

MENT (REMI CULATED LIST NAME Ato ADDRESS (FROM-TO)

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ACCUMULATED OCCUPATIONAL DOSE-TOTAL 10.

REMNtKS CURRENT GUMtTER DATE NET DOSE (CIRCLE ONE)

FROM TO (mrem)

ESTIMA TED/RFCORO EXPOStJ[4E NO YF S

53. CALCUL ATIONS - PERMISSIBLE DOSE 12.

CERTIFICATION: I CERTIFY TIMT TFE EXPO-WHOLE DODY:

SLME HISTORY LISTED IN COLUMNS 5, 6, & 7 IS

- (A) PERMISSIBLE ACCUMULATED DOSE = 5(N-18)

CORRECT & COMPLETE TO 5

REM TFE BEST OF MY KNOW-1 (0) TOTAL EXPOSLEE TO DATE (FROM ITEM 11)

LEDGE APO BELIEF.

REM (C) UNUSED PART OF PERMISSIDLE ACCLMULATED DOSE (A - 81 EPPLOYEE SIGNATURE REM

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AUTHORIZATION TO EX_C__EED ADMINISTRATIVE EXPOSURE GUIDES FORM 2 6pTIA7]J Z6T. ION._IO_EMCCQ 6DMINICTRATIVE EwPOBBC GUIQCQ IS AUTHORIZED TO RECEIVE AN EXPOSURC OF TO TFE FOR TFC PERIOD _

TO DPLOYCE'S CURRENT EXPOGURE IS:

WCCHLY GUARTERLY

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REASON FfW1 EXPOCURE IN EXCECS OF ADMINISTRATIVE GUIDES:

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,.1 EMPLOYEE ACKNOWLEDCCS APPROVAt.S 300 to 1,250 Q61E EMPLdYCE'S SUPERVISOR LADORATCHV FOREPAN APPROVAL,3 1,250 to 2,000 DATE EMPLOYEE *S SUPERVISOR LABORATORY SUPERVISOR APPROVALS 2.000 to 2,500 Q61C EMPLOYEE'S SUPERVISOR LABORATORY SUPERINTENDENT f

LADORATORY MANAGER

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FMPLOYCE'S CUPERVISOR HEALTH PHYSICS MANAGER PLANT GEtFRAL MANAGER _

APPROVALS 1,250 to 2,500 Q61G ICALTH PHYRICS SUPERINTENOCNT 1/ P PLANT GENERAL MANAGER,,_

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@ NORMAL RADIATION EXPOSURE

,, FORM'3 A8t#1RMAL~H ADI ATION FXPOgi_1RE INCIDEN1 NO.

DATE NAME DEPT.

JOG TITLE SUPV. IN CHARGE INVFSTICATION DATA f

DATE AND TIME OF INCIDENT LOCATION NATURE OF INCIDENT

,l PROGABLE CAUEE

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.) s EUHVEY INFORMATION RECOMfENDATIOPM COMPLETED HY DATE TLD BADGE READING PROGADLE ACTUAL DOGE DOSIMETER READING "I CERTIFY THAT THE ABOVE INFORMATION IS ACCURATE TO THE DEST OF MY HNOWLEDGE".

GIGNATURE OF MAN EXPOSED 1

SI'CNATURE OF SUPERVIcR i

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RADIATIO!f EXPOSURE _ LIMITS FOR FEMALES

FORM 4 RADIATItW EXPOQlRE LIMITS FOR FEMALES A.

I have received oral and written instructions concerning prenatal radiation exposure.

I have read the Appendnu to Regulatory Gutde l

8.13, "Possible Rasks To Children Of Women Who Are Exposed To

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.Radiatson During Pregnancy".

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SIGNATullE DATE

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I request that my radiation exposure-be limited to the following'

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If 1.

Same as for male workers.

Lsmits as specified in Sections C and Para. E.1 - E.5 of FM2-8002

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OR 2.

Limits as specified in Para. E.6.

of HNP-8002 i.e.,

500 mrem per two month period. For pregnant women, limit of 500 mrem for the enttre gestation period.

SIGNATURE DATE

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PROCECURE t!O. HNP

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,,mwu.no HNP-8109 E. l. HATCH NUCLEAR PLANT See Title Page ewa ~u to um See Title Page 1 of 18 CONTINUQUS AIE_ MON 1IOEG_dODELg_6M;3D AND AM-33-1 Oi2ERATION_6ND CALIBRAT ION A.

PURPQ5E To ensure that the instruments are calibrated properly and to provide operation guides for the user.

I B. REFERENCE @

1.

NMC^ Air Monitor Model AM-3D Instruction Manual 2.

NMC Air Monitor Model AM-33-I Instruction Manual 3.

Determination of Concentrations of Airborne Radioactivity, George L. Helgeson, Health Physics Journal 1963 Vol.

9, pp.

931-942 C.

SAFETY f

Observe Radiation Protection Procedures.

prys D.

TEST EGUIPMENT p

1.

Minipulser MP-1 or equivalent 2.

C1% check source and source holder 3.

Da check source and source holder 4.

Magnehelic g'auge E.

DESCRIPTION OF INSTRU!^ENT The NMC models AM-3D and AM-33-I monitors use a continuously moving filter paper so that replacement of the filter is required only infrequently.

The function of these instruments is to measure the radioactivity from air particulates and gaseous activity by concentrating these particulates on a filter, 1

detecting, and graphing the activity on a graphic recorder.

In the AM-3D and AM-33-I, air is drawn through a special filter paper at a controlled rate.

The build-up of activity on the filter paper is detected by a Geiger-Mueller detector which, in i

turn, operates a count ratemeter, solid state voltmeter alarm system and a graphic recorder.

The alarm system in the AM-30 and i

AM-33-I particulate channel provides two levels of alarm based l

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upon the level of radio-activity.

A high level alarm provides for continuous sounding of a loud bell or sonalert and operation of a red lamp.

The low level alarm is used as a fail-safe indicator that the detectable radioactivity is below that expected in a properly functioning instrument.

This provides a continuously lighted amber lamp.

In addition to particulate air activity, the model AM-33-1 also monitors the' filtered air for iodine and gaseous activity.

These gases are collected by a fixed activated charcoal cartridge.

The Iodine-131 activity build-up on the charcoal cartridge is detected by a scintillation detector.

The scintillation detector is coupled to a single window spectrometer system.

The spectrometer is provided with a window-width control and high voltage control that is set at the Iodine-131 energy base.,

The AM-33-1 incorporates a discriminator system, count rate meter, solid state voltmeter alarm system and a graphic 2 channel recorder.

The AM I iodine channel has a single (high) alarm

,gp/

system based on the level of iodine and gaseous activity 3* '

deposited on the charcoal cartridge.

This high level, alarm provides for continuous sounding as previous described.

~0$',

F.

DESCRJPTION OE CONTRO' G 3

1.

External controls.

a.

Master switch - Turns power on to the counting ratemeter and moving filters drive unit.

b.

H.V.

switch - Turns on high voltage for detector operation.

1 c.

H.V. Test switch - Displays the detector voltage on the rate-meter (AM-33-I).

d.

Input Mode Switch - In the TEST position, inserts a 3600 CPM signal to the ratemeter input for instrument l

check.

In the OPERATE position it places the GM detector in service for normal operation.

d e.

Q and D switch positions are the boundries of the spectrometer window and operate from the gamma scintillation probe, (AM-33-I).

f.

N. switch position is the window position and normal

.l)l operating condition (AM-33-I).

Window Width Switch-Provides 11 window levels from 0 to l l' g.

5%.

The instrument is optimized for the 5% window

?.' 7-'-

(setting 5).

This setting should be used unless there is significant interference from some other emitter

?

with an 'eo'ergy peak close to that of. iodine 131.

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E. I. HATCH NUCLEAR PLANT FNP-alos See Title Page

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cau 10 See Title Page 3 of 18 h.

Alarm Reset Pushbutton - Resets the alarm circuit after alarm condition.

i.

Meter Reset Pushbutton - Resets the meter to minimum when depressed.

j.

Blower Power Switch - Turns blower DN or OFF.

k.

Continuous-Stepwise Ewitch in CONTINUOUS position, filter paper advances continuously.

In STEPWISE position, filter paper advances only when the Fast Advance pushbutton is depressed.

I 1.

Magnehelic gauages:

6 (1)

AM-3D Indicates air flow rate through filter i

paper.

An adjustment screw on the guage provides adjustment of the flow rate control.

Clockwise adjustment increases the flow rate.

, jy

< ej.

V.

(2)

AM-33-I (Photohelic) Indicates air flow rate through filter paper and charcoal cartridge

.5e assembly.

Flow rate adjustment is accomplished by dual set point controls.

The left set point control governs the minimum flow rate setting.

The right set point control governs the maximum Flow rate setting.

m.

Flow jog indicator lamps-mounted on the right end of the cart.

Yellow lamp ON continually indicates i

blockag'e of filter paper. Red lamp DN continually l

indicated rupture, loss of filter paper or a leak in the system.

2.

Internal Controls a.

H.V. Adj ust - Allow setting of high vol tage on G.M.

tube.

I b.

High potentiometer - Adjusts high alarm setpoint on I

i alarm assembly module.

Low potentiometer - Adjusts low alarm setpoint'on alarm c.

assembly module, ll d.

The AM-33-I monitor is labeled "I"

or "G" to indicate l

iodine or G-M detectors adjustment.

,)

11 e.

Bias potentiometer - Calibrates low end of.ratemeter 1j l

'{l

, j y..

scale.

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High potentiometer - Calibrates high end of ratemeter scale.

g.

Low potentiometer - Calibrates mid-scale of ratemeter scale.

~

G.OPFRATION OF INSTRUMENT 1.

Install filter paper roll per instructions in paragraph 5.7.

Instruction-Manual (AM-3D) or paragraph 2.1 (AM-33-I) also insert the charcoal cartridge in the detector shield plug. (AM-33-I).

2.

Switch the Continuous-Stepwise Toggle switch on filter transport mechanism to CONTINUOUS.

a.

The filter paper speed can be varied for either monitor as per paragraph 4.7.1 (AM-30) or paragraph 1.3 and programming key on Drawing # DOO5923 (AM-33-I).

.yjfY 3.

Plug the instrument into a 11'5 V.A.C receptacle.

d 4.

Switch the Blower Power switch to ON.

Adjust air flow rate

~ c,e -

to 5 CFM using adjustment on Magnehelic gauge after about 24 l'

hours of operation (AM-3D).

Adjust AM-33-I photohelic gauge flow set point controls to 3.5 CFM and readjust after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months if necessary.

~

5.

Switch the Master-Switch to ON.

6.

Place the Input Mode switch to TEST and observe count ratemeter an'd recorder.

Reading should be 3600 1 400 CPM, if not report findings to the Health Physics Foreman.

7.

Switch the High Voltage switch to ON.

The red indicator light should be on.

8.

Return the Input Mode switch to "OP" (AM-3D) or "N"

(AM-33-I).

i H.

INTERPRETATION OF INSTRUMENT RESPONGC t

1.

Background radioactivity The normal background before collectine may be in the vicinity of 50 C/M.

Upon collecting, this count will rise rapidly due to the presence of radon gas and its radioactive daughters in the air.

The count should rise to a level i.

between 100 and 5000 C/M, depending upon the environment, F

the air cleaning used in the facility and atmospheric

'33 7....

conditions at the time.

This is an exceedingly sensitive instrument and a.high rate of count from redon and its L

progeny is to b,eserpected.

(Particulate activity-CAM only).

s

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.sf E.1. HATCH NUCLEAR PLANT HNP-8109

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4 See Title Page

. mo. o um 10 See Title Page 5 of 18 A fail-safety alert level is set at 10-50 C/M.

Whenever the counting meter indicates below this level, the amber lamp on top of the instrument cabinet will light.

This is to show that the instrument is operating below the preset level.

The amber light will also remain lit after changing or upon advancing the filter paper.

2.

Long half-life radioactivity.

In the moving filter CAM, the GM tube only " detects" one half of the activity at any given time because as the paper moves into the suction area, it is just starting to collect particulates, whereas, as the paper moves out of the suction area, it has collected its maximum number of particulates, hence, a factor of 2 is needed to correct for this. '

Furthermore, the sampling time is limited, i.e.,

after the filter paper has moved out of the suction area, it stngs collecting _garticulates, srJ/

'T '

The following formula (1) appl ies; s

4 C = 5.3 v 10~

As Where C= Concentration in uCi/cc l

~U3l.

Fga A= Count rate in CPM s= Speed of filter paper in in./hr.

a= Suction ares in inches F= Flow rate in SCFM g= Detector efficiency The speed of. the filter paper is set at one (1) inch per hour.

Shorter speeds can be set; however, a speed of one inch per hour allows greater sensitivity and the added ability to earlier detect changing air concentrations.

The above formula (1) is derived with the basic assumption that airborne radioactivity concentrations are constant during the sampling period of concern.

Sudden changes in airborne concentrations will be discussed later.

The average efficiency of the AM-3D, and AM-33-I continuous air monitors is about.20 (20.0%) and.080 (8%)

respectively.

A concentration vs count rate graph is attached to each unit.

Thus, during periods of " static" conditions the average air concentrations can be determined.

By applying the filterL, peed and CAM detectorY, i

s 103, 104, 5 x 10 efficiency and substituting 10, 10 and 10b counts per minute respectively we can exhibit the average concentration for a give,n count rate.

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~ ~e 6 of 18 see Tiue eese Substituting formula (1).

uCi/cc=(2.65v10 ')(cgm 1 Column 2 (5.3v10~'D

)(1)

(cpm)*

=

(5)(0.2)(2)

(factor for 20%

efficency)

Am-30

_5.3x10"~'3)(1)

(cpm)*=uCi/cc= ( 5. 3E--13 ) (cgm 1 Column 3

(

(3.5)(.080)(2)

(factor for 8%

efficency)

AM-33-I

Instrument background has been subtracted.

IABLE 1 COLUMN 1 COLUMN _2 COLUMN 3 A (cpm) c(uCi/cc for AM-3D) c(uCi/cc for AM-33-I)

..cd

'?g '

10 2.65s10-12 9.46x10-13 100 2.65v10-11 9.46x10-12 1,000 2.65x10-10 9.46x10-11 1,320 3.49x10-10 1.24x10-10 1,600 4.24x10-10 1.51x10-10 10,000 2.65x10- 9 9.46x10-10 50,000 1.32x10- 8 4.73x10- 9 5

10 1.32v10- 7 4.73x10- 8 106 2.65x10- 7 9.46x10- 8 3.

Rising Air Concentrations

~#

Formula (2)

C = 0.1C.x10 (A) fgts Assumes that the concentration is constant only over short intervals.

We can determine the rate of rise in cpm / minute and t (sample time) becomes 1 minute (for graph interpretation).

By this method we can observe any portion of the rise or peak activity and determine the concentration for that period.

For example:

If the air concentration for any given CAM rose from a " static" condition of 200 cpm to 1200 cpm in 10 minutes then:

Average rate of-rise =

(rise)

(static) 100 cpm / min

=

(in cpm / min) 12OOcom - 200 com (4 A) j.

10 min.

t-(rise time)

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C=

(._16v10

) (

A)_

Where: c = Concentration in uCi/cc fgts A=

cpm

~

Formula (2)

F = Flow rate in SCFM g = Detector efficency t

= Sample time 3

The above formula may be reduced by determing the average rate of rise as previously mentioned.

~

Then: C = (.16x10

)

(o A)

Where: A A = cpm / min.

Fg Substituting the detector efficiencies and flow rates of the AM-30 and AM-33-I CAMS the following results in Table 2 can be graphed.

Column 2 1.1Gx10~#) (cpm / min) uCi/cc = _(1.GOx10

)(com/ min)

=

Fg (factor for 20%

efficency) AM-3D.

j*

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d-Column 3 (.1Gx10~'U) (cpm / min) = uCi/cc = (5.71E

)(cgm / min)

~@pl Fg (factor for 8% efficency) AM-33-I TABLE 2 COLUMN 1 COLUMN 2 CCLUMN 3 c(uCi/cc for AM-3D) c(uCi/cc for AM-33-I) c ( uC i / c c f o r AM-33-I )

(PARTICULATE)

(IODINE) i 1.60x10-10 5.71x10-10 8.79x10-10 4.80x10-10 1.71x10- 9 2.63x10- 9 8.OOx10-10 2.85v10- 9 4.39x10- 9 1.60x10- 9 5.71x10- 9 8.79x10- 9 4.OOx10- 9 1.42x10- 8 2.19x10- 8 8.OOx10- 9 2.85x10- 8 4.39x10-'8 1.60x10- 8 5.71x10- 8 8.79x10- 8 8.OOx10- 8 2.85v10- 7 4.39x10- 7 1.60x10- 7 5.71x10- 7 8.79x10- 7 l

8.OOx10- 7 2.85v10- 6 4.39x10- 6 8.00x10- 6' 2.85x10- 5 4.39x10- 5 The following rate of rise ratas are equal to the administrative limits of 1x10'i uCi/cc.

~;

l AM-3D AM-33-I

, l ti il Particulate D +

activity 27 cpm / min 22 cpm / min al Iodine-131

12. cpm / min ll j\\

v

,/.r-..

A rate of rise graph will be attached to each air monitor..

jj I

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4.

Determination *o.f Airborne Iodine Concentrations.

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The Model AM-33-I air monitor incorporates a scintillation detector and fixed charcoal cartridge to p

access the Radio-iodine levels.

Because the collecting U

media is fired and the collecting efficency for Iodine is not 100% the following formulas are necessary to determine the airborne concentrations.

Collection efficency of the F & J cartridge is 99% or O.99.

For " Static" conditions where there is no appreciable rate of rise formula (3) applies; Column 4 C=(1.E.x10~##

)(AA)

Where: 8A= cpm / min (F) fots)(g)(Ce)

F = Flow rate in SCFM dt

= Sampling time min.

g g = Detector efficency Ce = Filter Media Collection Efficency C = Concentration in uCi/cc.

, j' rs.

V Dy assuming the flow rate, d'etector efficiency and filter media collection and the absorption factor is

~$,

accounted for during detector calibration formula (3) can be reduced to:

C = All' Where K' =.16x10 #

t FgCe g

Then K'

.1 E.r 10 -'

= 5.77E-11 and C =A (5.77E-11)~"

(3.5)(.08)(.99) t 3

F g

Ce From the above data the average Iodine-131 airborne concentration can be determined.

For example, if

" Static" conditions exist (slow rise or no rise on the chart 10 cpm / min).

The counting rate is 200 cpm and the sample has been on for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months then.

lI 1200)(5.77E-11

)

=9.E.2E-11 uCi/cc 120 min.

b.

The average concentration f or a change in airborne activity may be determined by subtracting the stable airborne concentration from the peak concentration and dividing the difference by the elapse time period of stable and peak activity.

Use formula (1) to determine j

the results.

(concentration at t _-__ concentration at tg) =4 A l,

g t -

t,,

(in minutes)

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mit 10 See Title Pace 9 of 18 Where: dA = average rise in cpm / min t

=

static conditien time t,g= peak condition time For example, over the'last two hours the counting rate for Iodine-131 has risen from O'to 200 cpm but over the last 30 minutes the concentration has risen from 200 to 800 cpm.

h Then: (GOO-2OO)f5.77E-11) 1.15E-9 uCi/cc

=

30 (t - t)

A I

A graph is attached to each CIM exhibiting a static condition and a rate of rise condition.

The charcoal cartridge should be changed when the collected activity indicates a level of Sv10 uCi/cc (

8500 cpm) in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The charcoal cartridge will be further assessed by h

laboratory counting methods.

Normally the charcoal cartridge (CESCO) will be changed once per week.

The

.4,/f following graphs will be atta'hed to the CIM:

c

??

Graph #1.

Assumes the Iodine 131 concentrations are

.,,:n.

essentially constant during the collection l

periods of 2 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Graph # 2.

Assumes the Iodine 131 concentrations are

. essentially constant during the collection

. periods of one to seven days.

Graph # 3 Assumes the Iodine 131 concentrations are.

constant only during short intervals, where t.

is reduced to one minute.

(rate of rise in cpm / min).

NOTE Because Iodine-131 has a long half-life, compared with t

or t (redioactive decay is not accounted for in the derivations) jtd is essentially zero and jtd =

=1, also jts may be expanded neglecting all but the first two terms; Gj = _(0.1C.v10~'O)3fA = (0.16v10'ID A) 1 FgCe ( 1.4-3j ts )

FgCe

. lits - (jits)21...)

(1-1+1!

-2!

CJ = 0.16x10-fo A Formula (3)

.j FgtsCe l

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c. i l

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vuou r.o See Title Page to om 10 of 18 See Title Page Where ts = sample time td = delay in minutes before the sample is counted 3j = the decay constant of a particular isotope.

CJ = concentration of a particular isotope.

A= cpm (counting rate on the filter media).

l

. F = flow rate in SCFM.

l g = detector efficiency Ce = collection efficiency of the filter media.

5.

Other observations for moving and fixed filter CAMS.

a.

Down trend in chart recorder.

1 (1)

This could be due to long half-life ac,tivity which has stopped forming and the filter is moving out of the detection area.

(2)

A decrease in long half-life airborne concentrations

,,y

,w

Y! -

(3)

Short half-life material decaying', showing a stop or decrease in activity.

po' D

(4)

A combination of these reasons.

b.

Horizontal line straight across chart.

(1)'

Sudden increase in background from sources or-casks.

(2)

Extremely.high airborne radioactivity.

(3)

CAM Filter paper not moving,. activity buildup.

1 I.

CAM _ LOCATIONS AND_ OPERATION 1.

The CAM units shall be placed in areas where.the occupation factors and the possibility.of airborne problems are most predominated.

p 2.

IT possible the CAM's should be placed near air exhaust vents'to better access overall airborne concentrations.

p

~

3.

The CAM's shall be equipped with an air sample intake extension in that the sample collected is representative of a " breathing zone" for personnel.

]

1 4.

The distance ~from the airborne' source should also be taken t

into-account.

-4

/ c.

shall be set in theffollowing manner.

4 5.

The alarm level g, y

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10 Geo.mip Power nl 11 of 18 See Title Pace l

l i

a.

The CAMS shall be operated for a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period to

, establish'a relative Ra-Th equillibrium, b.

The CAM alarm point is set at the administrative level of 3.0 x 10~9 uCi/cc.

The actual alarm setting will vary depending on Ra-Th concentration, area background and CAM offig, enc'y.'

Using the long lived graph the number should'be written 1500 cpm i 10%(AM-3D~s.

For example, if the CAM background is 500 cpm and the 1x10-9 uCi/cc criterion is equal to 1500 cpm then the alarm point is set at 2000 cpm.

The CIM alarm point is to be set at the administrative level of 3.0 x 10-9 uCi/cc.

The actual alarm setting will vary depending on area background and cim '

efficiency.

A rate of rise of 12 cpm / min or 720 cpm.br is equal to 1x10'9 uCi/cc.

(See formula 3 and its variations).

It the background is 100 cpm then the alarm point is set at 820 cpm.

Yb,

CALIG_. RATION AND CHECMG s

J.

,f 1.

Daily or Shift Check s

" 3; a.

Insure the AM-3D and AM-33-I air flow is maintaining a 5 and 3.5 SCFM flow rate adjust as necessary.

I b.

Observe,the chart and insure the pen is inking.

c.

Calculate the present air concentration using the appropr.iate praph (graph #1).

If any spikes or a rate l

of rise is indicated determine the concentration during the rise and notify the H.P Supervisor (provided the rate of rise is nr was in excess of administrative limits-3.0 s 10~9 uCi/cc).

d.

Insure there is a sufficient filter paper supply (24

?

inches per day) and draw a vertical line across the filter paper.

The line is used as a reference point to y

determine if the filter paper is advancing.

J e.

Note the flow, concentration, date and time on the h

chart paper and initial the chart paper.

[

2.

Weekly Check (AM-3D) a.

Check flow cates of cams and cim-cams to assure proper flow on magnehelic or photohelic guages and record on DATA GMPET 1, Data Package 1.

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g_,,

1g,, 1g b.

Place the~ Input Mode switch to TEST and obt.erve

'ratemeter an; recorder.

Reading should be 3G00 i 400

' CPM.

Record results on Data Sheet 1, Data Package 1.

Weekly Continuous Air Monitor Check.

Mark " TEST" on the chart paper turn the pump off and open or remove the detector shiel' ding.

c.

Place radioactive check source provided to the center of the detector and check the instrument response and alarm setpoint.

Record results and complete Data Sheet 1,

Data Package 1.

Note on the chart paper and insure the c/m meter and chart readout match.

If the detecter efficiency is low, calibrate the CAM in accordance with the Semi-Annual checks prescribed below.

For the Model AM33-I CAM, place the radioactive check source on the end of a metal rod and insert the source gently into the detector chamber.

Insure the source is

,.f. p centered and against the -detector window.

Proceed as j

mentioned in the previous par.agraph.

f d.

After completion of the above checks return the CAM to l

~U5)',

operation and note on the chart paper the time, date and calibration completed by initial, e.

The CIM (AM-33-I) may be source checked in the l

following manner.

(1)

With the pump off, remove the filter holder-detector shield plug, remove the charcoal cartridge, and place the Ba 133 check source in the filter holder-detector shield plug.

Reinsert the detector shield.

(2)

Check the instrument response and alarm setpoint.

Record the results and complete Data Sheet 1, Data Package 1.

Note the results on the chart paper and check the count rate meter and chart readout i

coincide.

If the detector efficency is low, calibrate the cim in accordance with the Semi-Annual checks prescribed below.

(3)

Semi-Annual Calibration.

l (a)

Test Shop will calibrate the magnehelic or l

Photchelic on the' cam or cim-cam (MR's are to be written by Inst,rument Techs) semi annually.

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~~

S Title Page 13,, 13 (b), Note on the chart paper the Semi-annual calib ra tion is occuring.

Turn the instrument high voltage off and remove the probe connector.

~

Connect.the o'utput of the Minipulser from (c) positive (red lead) to pin "F"

of the input connector flocated on left side of probe connector), (AM-3D) Ground the other lead (black) to the frame.

Remove the probe connector to the scintillation detector (AM-33-I) and connect output of the Minipulser from positive (red lead) to pin "F"

of the connector.

(d)

Switch the input mode on the counting ratemeter to "OP" or D.

(e)

Set the minipulsen at 1.0 volt amplitude.

~$.sv Set the counti6g rate of the minipulser to

~f '

100, 1000, 10,000,-40,000, and 8dO,000 cpm.

Adjust the bias, low and high-end controls as

~03,,

necessary to correspond to the input pulse being generated.

NOTE

.'Am-3D's scale reads to 50,000 cpm only.

Disreguard 800,000 cpm step.

(f)

After this calibration insert the check ll source as prescribed in J.2 and perform a plateau check.

(Instrument high voltage back on).

See the instruction manual Section IV 4.4.

If the high voltage plateau has not drifted and instrument efficiency is within 10% of the last efficiency check, return the instrument to operation.

(AM-3D).

~

(g)

The cim detector Iodine 131 operating voltage is set by inserting the Ga 133 source as prescribed in Section J.2.e. With the input mode selector switch in "N"

position, adjust the 10- turn high voltage control uritil the c/m meter indicates and optimum value.

Then set the high voltage control _1% lower than indicated reading.

ti (h)

Replace calibration sticker'and initial chart.

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~ ~v cee Title n., g e 1,,

,, 13 (i). Conip l e t e the necessary forms (see attached forms).

NOTE The AM-3D an ci.Am-33--I is designed to measure

' general air trends and changes in these trends.

Any' unusual rises in airborne activity should be verif-ied by additional air sampling (high or low volume) isotope identification should be made and documented.

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I HAW REVIEWED THIS DATA PACKACE FCR C04oLETENESS APO AGAINST ACCEPTANCE CRITERIA IN ACCORDAtCE WITH FNP-830.

ACCEPTAGLE LNACCEPTABLE REVIEKD BY:

DATE REVIEWED:

PEMARKS:

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ACCEPTe&LE LNACCEPTMILE REVIE G BY DATE REVIEWED:

REMARKS:

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GEORGI A POLER COMPANY HATCH NUCLEAR PLANT PROCEDURE ARM Portable Calibration Unit PROCEDURE TITLE HNP-8111 PROCEDUIEE NUMBER Lab' RESPONSIBL5 SECTION SAFETY RELATED ( Y )

NON-SAFETY RELATED (

)

APPROVED APPROVED REV.

DESCRJPTION DEPT.

PLANT DATE HEAD MANAGER

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I Paces 2 and 4_ _

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PROCEDURE N'O.

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Revision No._. 3 R F.C_U_;;F._T F_D_ _R_Y_ _ _ _____

D'..P._ AR _TME_N__T_HF_M._. A P P_ H_ O V..t_. _ _ _

N;.me ;

Da t 6::

Signature:

Date:

Ej"S o o2.3*83 OI~~ N

~

-- _ f REVISION CHAT:CES MODE OF.CPERATION O.3 INTENT AS DESCRIDED IN FSAR:

(

) Yes

(

) No CHANGE INVOLVES:'

(

) An unreviewed Safety Guestic.n

(

) Tech. Specs.

(

Neither (See back for Safety Evaluation if required).

~~

Safety Related

(

.Non-Safety Related' (

)

.(

,.C Safety /Non-safety Status Change (

) Yes

~

( [No

~

Attach marked up copy of procedure to thi's form.

AN V&LQJg_fgp(f.,c c,<.4 h AE7f 64Jhtf GDD REA5ON F R RECUEST

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________e.e.______________________e___e._e.______e._

_The revision of this procedure does not constitute an unreviewed sa fety___---__'__ '-

qu es t io n a s e xpl a i n e_d__b _el o.w._.______

_e

______.u 1.__T_h_e p_ro.b. _a.b. _i l_i_t y_o..f.._o.c._c u_r_r e

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e or mal fu_n_c.t.i_c_n__o f _e_c_u.i n_e._s_._t _i_m_o_o.rtan.t_to__s_a.fe_ty are__not_i_n_cr.e.a_s_ed_-__

. = _

above those analyzed in t_5._-CJAR due_10._!;be-.Chac_oas_htc.AUSE___ -

_-.t_h_e__revi s ion _ d.o._esn..o.e.c_h_a_n_ce__t_h.e._o__ur.o_os_e o_r oer..f._ormance of the

-- t system.

2.

Th'e possibility of an accidsnt or malfunction of a different tyce than analyzed in th.e._FSAP. dess__not re_sult from this chance because

- -- -u n

c the system resconds and i_s oterated as before the chan.ae._ - _ -_

=_

4., /,

2 3.- - -.The marcin of saf_e_t_y a.s__d.e._#i_n_ed in the Te'chnical._S_ oeci fica _tio.n_ s

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is not reduced _due to this tevision because the_ revision does__n_o_t- _-

J

chance anv limited safety system settinas which would all_ow a safetil-_'l,imit to be__e_x_cee.d_e_d or to allow a limi tina conditi_on for i

oRerations to be exceede_d _as_ stated in Technical _Soecifica_t_ ions.

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4 um

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1 See Title Page o

1 of 8 ARM PORTADLE CALIBRATION UNIT A.

PURPOSE, To ensure that the instruments are operated properly.

9.

SAFETY Observe radiation protection procedures.

C.

REFERENCES 1.

S-17978 GEK-865C Portable Calibration Unit for Area Radiation Monitor 2.

HNP-8014 Handling of USNRC Licensed Radioactive Material l

3.

HNP-8017 Control and Accountability of Radioactive Material

, j*

'j.

V D.

DESCRIPTION OF UNIT

~O$

The ARM portable calibration units provide a graded series of radiation rates which are used for calibration of area radiation monitors on plant site.

When a sensor and converter of an ARM is inserted in the cavity a dose rate can be applied to it by setting the source and shield control levers to an appropriate position.

Five discrete dose rates can be set in this manner.

A chart furnished with the units show the calibrated dose rates for each position of.the levers at the date on the chart.

Since the j

source, Cobalt GO, has a half life of 5.25 years, allowance j

should be made for decay of the source.

E.

DESCRIPTION OF CONTROLS 1.

Source control lever - positions source in or out.

2.

Shield control levers positions shields in or out.

F.

OPERATION OF UNIT e

NOTE i

For reference the calibration charts furnished with the units are shown in Figure 1 and in Figure 2.

Two units are available-for use serial number 6554071 and 6339537.

Charts are furnished

'(

for both.

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2 of 8 See Title Page s,

CAUTION

'This units contain approximately 200 microcuries of Cobalt 60.

Exercise care in handling the unit to minimize radiation exposure.

1.

Insert the sensor and co'nverter unit to be calibrated into the cavity.

2.

Determine the corrected dose rate for the lever positions desired by using Figure 1, graphs 1 and 2; or Figure 2, graphs 3 and 4.

3.

If the sensor and converter is supplied with a bug source add the bug source radiation level to the level determined in step F.2 and use this value for ARM calibration.

4.

Repeat steps F.1 - F.3 as often as necessary to complete the ARM calibration.

.,cA

~3 '

5.

When the ARM calibration is complete set the source control to OUT and both shield controls to IN to provice maximum shielding of the source.

Install top cover and return unit

~F1 to area which it is assigned and complate Form 1 of HNP-8014. -

NOTE Sources are controlled by a Laboratory Foreman

~

and are stored at designated areas.

All sources used outside the laboratory will require the completion of HNP-8014, Form 1 by the person requesting the source.

h I

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_, 517 SOURCE IN 354.3 4 0 ~,. C 403.0 g,; 1 g;;7 t

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