ML20077F028

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4530 Re Alert - Operations Supervisor & HNP-8002 Re Radiation Exposure Limits

ML20077F028
Person / Time
Site:	Hatch
Issue date:	06/29/1983
From:	Nix H, Rogers W GEORGIA POWER CO.
To:
Shared Package
ML20077F017	List: ML20077F021 ML20077F028
References
PROC-830629, NUDOCS 8307290530
Download: ML20077F028 (49)

Text

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GEORGIA POWER COMPANY

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HATCH NUCLEAR PLANT PROCEDURE l A1.e rt - Operations _S_u_ pervisor _

PROCEDURE TITLE -

HNP-4530

. . PROCEDURE NUMBER i

Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

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HNP -4530 - -

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ALERT - OPERATIONS SUPERVISOR A. CONDITION - .

l Events are in process or have occurred which involve an actual or i potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline (P.A.G.)

exposure levels.

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B. REFERENCE

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HNP-4520. .

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i C. ACTION

1. Proceed to control room.

2. Assume the duties of the Emergehcy Director until relieved, see HNP-4540 for actions.

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%r . 3. a. Evaluate actions of Shift Supervisor and Count Room Operator to bring emergency under control.

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.' b. Assure ccrrect emergency classification has been

- declared as per HNP-4520.

4. Consult with Shift Supervisor and STA to determine if a more severe emergency class should be declared. Refer to criteria in HNP-4620, 4720 and 4853.

5. The Operations Supervisor is' responsible for notification of Plant Management and NRC as per Emergency Call List and other offsite agencies in accordance with notification procedures HNP-4861. The actual notification process may be delegated to other, specifically trained, shift personnel.

6. Augment shift resources as needed to assess and respond to the event.

7. Make a .sifety assessment to determine if personnel not

( involvrt s in the emergency recovery effort should be evacuat'ed. If possible, consult with Plant Management

. concerning this evacuation.

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' # HATCH NUCLEAR PLANT .

l PROCEDURE 1 Radiation Exnnsore Limits PROCE60RE TITLE HNP-ROOP PROCEDURE NUMBER

. Lab

. RESPONSIBLE SECTION NON-SAFETY RELATED ( )

SAFETY RELATED ( X>

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HNP-8002

$ ,i Ig ,, 71,1, p g, E. l. HATCH NUCLEAR PLANT _ ,

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l RADIATION EXPOSURE LIMITS

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! A. PURPOSE ,

To provide limits of exposure for the protection of personnel against radiation hazards arising from work associated with the

> operation of the Hatch Nucle'r' a Plant.

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The limits of 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. t B. REFERENCES

1. 10 CFR 20 l I gg

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2. HNP-8010, 4812, 8005, 8021 -

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3. Reg Guide 8.13 No 4. Tech. Spec. Unit 1, Sect 6.11  !-

C. MAXIMUM PERMISSIBLE EXPOSURE (10 CFR 2O) . (Tech. Spec. Seetion 6.11)_ - -

1. The maximum quarterly exposure to the wnole 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.

. NOTE dll 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 radiation.

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See Title Page GeorgiaPower 2,,,

4. The-limits as set forth above are subject to the following I

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 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.

'c . No individual will be permitted to receive a whole body 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

.ff to obtain the individual.'s prior occupational exposure

,,7>f-has been made. In the event an individual,is unable to 2I .

provide exposure information'for the current quarter, and his duties are likely to result in an exposure in

~U$$ 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 [

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 20)

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 <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week for 13 weeks at uniform concentrations of

radioactive material in air as specified in Appendix B Table I, i Column 1., If the radioactive materials are of such form that i

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

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inhalation or absorption or both routes of intake in any calendar quarter does not exceed that which would result from inhaling such radioactive material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week for 13 weeks at 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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HNP-8002

• • E. I. HATCH NUCLEAR PLANT See Title Page m ,,o 13 e Title Page Georgia Power u 3 o, ,

E. ADMINISTRATIVE EXPOSURE GUIDES

1. Admi61strative 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 B of this procedure.

2. Exposure of the whole body shall be limited to 300 mrem /w4ek. 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. Shole 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 y mrem / quarter. -

V- 5. Whole, body radiation exposure abo've 1,250 mrem / quarter up to 2,000' mrem / quarter will require written approval from the

~0$i immediate supervisor and a Lab Supervisor on Form 2, Authorization to Exceed Administrative Exposure Guides.

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6. From 2,000 uo 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

,equired to acknowledge in writing that they have received r

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

~ ~

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~~

See Title Page Georgia Power .

4 o# S Radiation exposure to pregnant women will be limited to 500 mrem.during the entire gestation period unless a higher limit is specifically. requested in writing by the employee on Form 4 ,

F. ADMINISTRATIVE ' CONTROL OF IbrTERNAL 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-8010 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). g G. EXPOSURE LIMITS FOR NON-PLANT PERSONNEL id' 1. Vendors, subcontractors, and other non-plant pe'rsonnel who are likely to receive a whole body radiation exposure in

'.g*

• excess of 300 mrem in any calendar quarter shall be required 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 an'd policies of the Georiga Power Company prior to gaining access without escort to areas where radiation exposures may be received.

H. EMERGENCY AND ACCIDENTAL EXPOCURE Although an emergency situation transcends the normal requirements of limiting exposure, there are suggested levels for exposure. Refer to HNP-4812 for guidance.

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. See Title Page atvoo. o

ous 13 3 e. " . W"'r" Georgia Power - -

,. j See Title Page o 5 of 9 I. ABNORMAL PERSONNEL EXPOSURES f

Whenever'a situation occurs involving the suspected or known exposure of personnel to i.onizing radiation in e:: cess of 10 CFR 20 limits specified in this procedure, the incident will be J w~ ".  ? .promptly investigated and personnel exposures evaluated.

!*~ ' - " Personnel monitoring results that are either excessively high or excessively' low with respect to the work that an individual has been known to be doing, will also be immediately investigated.

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

Labor,atory Foreman or his alternate. A committee consisting of the Laboratory Foreman, Health Physics Superintendent or his designee, and supervisor of the group in which the abnormal exposure occurred, will conduct an official investigation and issue a written report of its findings and recommendations to the concerned individual, his immediate supervisor and the Plant i

General Manager. Every effort will be made to determine if the 'l j suspected exposure is actual exposure using, as necessary,

~5. ' special bio-assays, whole body counting, radiation sprveys, and t V reviews of work assignments and working procedures.

t rg*, The written report submitted will consist of the investigation, .

the evaluation of results documented on Form 3, Abnormal Radiation Exposure, and a Radiation Occurrence Report (Figure 2 HNP-8005).

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

I TYPE OF RADIATION R.B.E. OR G.F. VALUE*

X-ray, Beta, Gamma 1

Neutrons, Thermal 5 Neutrons, Fast 10 l

Alpha and Heavy Particles 20

• R.B.E. or G.F. is Damage Relative to Gamma or X-rays l

l

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t 164Ua8 SET

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.. PHOC&OURk feO f HNP-8002

1. s f~m E. I. HATCH NUCLEAR PLANT *veoe w  ;

See .Titis- Page 13 om 6 of 9 See Title Page t FIGURE 1_

TFORM 1)

OCCUPATIONAL EXTERNAL RADIATION EXPOSURE HISTORY

[')**FORMI QCCtJPATIONAL EXTERNAL RADIATION EXPOSLEE HISTORY NME (PRINT-LAST, FIRST, ArO MIDDLE) 2. SOCIAL SECURITY NO.

1.

DATE OF BIRTH (MONTH, DAY, YEAR) 4. AGE IN F1)LL YEARS (N) 3.

OCCUPATIONAL EXPOSURE - PREVIOUS HISTORY PREVIOUS DOSE HISTOR_Y_

6. DATES OF 7. PERIGOS OF 8. WHOLE 9. RECORO

5. PREVIOUS EMPLOYMENTS BODY OR CAL-EWLOTMFNTS INVOLVING EW LOY- EXPOSURE PENT (REM) CULATED RADIATION EXPOSURE - (INSERT LIST NAME APO ADORESS (FROM-TO)

OPE)

OF EMPLOYER WW.

t

• • PL% ,

' 48 o

10. HEMARKS

• 11. ACCUMULATED OCCUPATIONAL DOSE-TOTAL OATE NET OOSE (CIRCLE OMD CURRENT QUARTER FROM TO (mrem) ESTTMATED/RECORC EXPOGURE VES l NO

13. CALCULATIONS - PERMISSIBLE DOSE 12. CERTIFICATICN: I CERTIFY THAT TE EXPO-WHOLE BODY: SURE HISTORY LISTED IN l COLUMNS 5, 6, & 7 IS l

. (A) PERMISSIBLE ACCUMULATED DOSE = 5(N-18) CORRECT & COMPLETE TO l

5 REM DE BEST OF MY KNOW-l (83 TOTAL EXPOSURE TO DATE (FROM ITEM 11) LEDGE AND BELIEF.

REM (C) UMJSED PART OF PERMISSIDLE ACCUMULATED DOSE (A - 8) EW LOYEE SIGNATURE

= REM OATE 14.

NAPE OF LICENSEE

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13 See Title Page '

7 of 9

. FIGURE 2

, (FORM 2)

AUTHORIZATION TO EXCEED

., ADMINISTRATIVE EXPOSURE GUIDES

~, . .

E9RM it AUTHORIZATION _ TO_EYCEEQ ADMINISTRATIVE CYP _QSURE GUIQES IS AUTHORIZED TO RECEIVE AN EXPOSIRE OF TO TFE FOR TFE PERIOD , TO i F)PLOYEE'S CURRENT EXPCCURE IS:

WEEKLY QUARTERLY

..M

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REASON FTIR EXPOSURE IN EYCESS OF ADMINISTRATIVE GUIDES:

A' .

, t b EMPLOYEE ACKM)WLEDGES ~-

APPROVALS 300 to 1,250 ME EPPLdYEE'S SUPERVI'SOR LAGORATORY FOREMAN APPROVALS 1,250 to 2,000 QAE _

EPPLOYEE'S SUPERVIeR LABORATCRV GUPERVISOR APPROVALS 2.000 to 2,500 Qg EMPLOYEE'S'SUPERVIF.OR LABORATORY SUPERINTENDENT t.ABORATORY MANAGER

. APPROVA(S 2,500 to 3,000 QA_E FMPLOYEE'S SUPERVISOR FEALTH PHYSICS MANAGER PLANT CCNFRAL MANAGER APPROVALS 1,250 to 2,500 DJE

,, 6EALTH PHYF ICG SUP.ERINTOCENT -,z PLANTCENCIALMANbER HW-GOO 2 R13

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, FIGURE 3 (FORM 3)

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ABNORMAL RADIATION EXPOGURE

, ,FORf( 3 ABNORMAL RADIATTON EXPOSURg INCIDENT NO. DATE NAME DEPT. __

JOR TITLE SUPV. IN CHARGE INVFSTICATION DATA DATE Aro TIPE OF INCIDENT LOCATION 4

NATURE OF INCIDENT W

..u. - .

.i .

PROBABLEtCAUSE 1 -

! -m* D -

SURVEY IWORMATION RECOMMENDATIONS I

COPPLETED RY DATE TLD BADGE READING PilOOABLE ACTUAL DOSE DOSIMETER READING

'I CERTIFY THAT THE ABOVE INFORMATION IS ACCURATE TO THE BEST OF MY KNOWLEDGE'.

SIGNATURE OF MAN EXPOSED l SI'GNATURE OF SUPERVISOR SIGNATURE OF LAB SLFERVISOR/ FOREMAN

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13 See Title Page Georgia Power mi . ,,,

FIGURE 4

- (FORM 4)

RADIATION EXPOSURE LIMITS FOR FEMALES ,

T

, FORM 4 I

, R MIATION EXPOSURE LIMITS FOR FEMALES A. I have received oral and written instructions concerning prenatal .

radiation exposure. I have read the Appendis to Regulatory Guide l 8.13, "Possible Risks To Children Of Women Who Are Exposed To 9 i

. Radiation Oursng Pregnancy *.

i i .'

I

/ f

/

SIGNATURE DATE  !

l I request that my radiation esposure"be limited to the following: l

. . /'

B.

d;j. 1 Same as for male workers.

Limits as specified in Sections C and Para. E.1 - E.5 of HM'-8002 g* .j s . .

SIGNATURE DATE / /

08

2. . Limits as specified in Para. E.6. of HNP-BOO 2 i.e., 500 mrem per two month period. For pregnant women, limit of 500 mrem for the entire gestation period.

SIGNATURE DATE / /

I

. : g. . . .*

FNa.8002 Rg i

• ,.,'i Figure 4

-.- , . . - = _ , . . _ . - . - - _ . . . . - - - - . . - - - . -- =.-- - - =: = : ,-

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• GEORGIA POWER COMPANY j i

. . 4 ..~

. a HATCH NUCLEAR PLANT PROCEDURE

- .I Continuous Air Monitors Models AM-3D and AM-33-1 Operation and Calibra__ tion

- PROCEDURE TITLE .

HNP-8109

. PROCEDURE NUMBER .

Lab

- RESPONSIBLE SECTION I NON-SAFETY RELATED ( )

SAFETY RELATED ( X )

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( ) %, s . (,)<) No .

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( ) An unrnviewed Safety Guestion

(- ) Tech. Specs. ( A<) Neither

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Safety Related O<') Non-Safety Related ( )

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G the sy_s_tsa rescends and is coerated as before the_, chance. -

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-. _ d- . chane,e anv limited safetf system settinos ghich would allow a safety limit _ to _be exceeded or to allow a limitinc condition for --

ooerations to be exceedeJ_ as stated in' Technical Soecifications.

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.. REVISICN Cst:0I3 MODE OF .CPERATICt! 03 INTENT AS DEGCRIDEO It' FSAR: '

( ) Yes - . ( 2d No .

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(,)< > No .

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'.',^ HNP-8109 E. l. HATCH NUCLEAR PLANT at v-See Title Page ou. 10 See Title Page 1 of 18 CONTINUOUS AIR MONITORS MODELS AM-3D AND AM-33-1 OPERATION AND CALIBRATION A. PURPOEg To ensure that the instruments ar'e calibrated properly and to provide operation guides for the user.

I B.REFEREN,CES

1. NMC' Air Monitor Model AM-30 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 I

, gyp C. SAFETY ,

y. < '

V. Observe Radiation Protection Procedures.

s

-F ge D. TEST EGUIPMENT .

1. Minipulser MP-1 or equivalent

2. C13b. check source and source holder

3. Ba check source and source holder

4. Magnehelic gauge E. DESCRIPTION _OF INSTRUMENT 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, 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 turn, operates a count ratemeter, solid state voltmeter alarm system and a graphic recorder. The alarm ystem in the AM-3D and AM-33-I particulate channel provides two levels of alarm based

+. .. ;_

3

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Georgia O Power al ' 2 of 18 See Title Page upon the level of ra/io-activity. A high level alarm provides operation for continuous sounding of a loud bell or sonalert and of a red ihmp. The low level alorm is used as a. fail-safe indicator that the detect 6ble 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-I also monitors the~ filtered air for iodine and gaseous activity. These The gases are collected by a fixed activated charcoal cartridge.

cartridge ic Iodine-131 activity build-up on the charcoal detected by a scintillation detector. The scintillation The de.ector is coupled to a single window spectrometer system.

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

The AM-33-I incorporates a discriminator system, count rate meter, solid state voltmeter alarm system and a graphic 2 channel recorder. The AM-33-I iodine channel has a single (high) alarm

,,_. <// system based on the level of iodine and gaseous activity lf ' deposited on the charcoal cartridge. This high level, alarm provides for continuous sounding as previous describe'd.

~UTe F. DESCRJPTION OF CONTRO', S '

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.

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

d. Input Mode Ewitch - In the TEST position, insects a 3E.00 CPM signal to the ratemeter input for instrument check. in the OPERATE position it places the GM detector in service tor normal operation.

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 operating condition (AM-33-I).

9 Window Width Switch-Provides 11 window levels from 0 to 5%. The, instrument is optimized for the 5% window . .

(setting 5). This setting should be used unless there'79ma

' ?-- -

is significant interference from some other emitter with an e.nergy peak close to that of iodine 131.

i .

- 6Ayas SET

+. ... .

.- --.j. .. '. - -- .. ..- - - - . . -.. . .. =- . - .

- -um o HNP-8109

. t " E. l. HATCH NUCLEAR PLANT miwe au See Title Page om lo 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 Switch in CONTINUOUS position, filter paper advances continuously. In STEPWISE position, filter paper advances only when the Fast Advance pushbutton is depressed.

1. Magnehelic gauages: .

(1) AM-3D Indicates air flow rate through filter paper. An adjustment screw on the guage provides adjustment of the flow rate control. Clockwise jy adjustment increases the flow rate.

~?"J- o 9/ . (2)

AM-33-I (Photohelic) Indicates air flow rate through filter paper and charcoal cartridge co#', 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 blockag'e of filter paper. Red lamp DN continually indicated rupture, loss of filter paper or a leak in the system.

2. Internal Controls

a. H.V. Adjust - Allow setting of high voltage on G.M.

tube.

b.

High potentiometer - Adjusts high alarm setpoint on 31 arm assembly module.

c. Low potentiometer - Adjusts low alarm setpoint on alarm assembly module.

d. The AM-33-I monitor is labeled "I" or "G" to indicate '

iodine or G-M detectors adjustment.

e. '

Glas potentiometer - Calibrates low end of ratemeter ~

e,. scale'. i . .

i .

.[ ,, _ , t , ,

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Power '

4 of 18

f. High potentiometer - Calibrates high end of ratemeter scale. -

g. Low potentsometer - Calibrates mid-scale of ratemeter scale.

G. OPERATION OF INERUMTNT . .

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 plu,g. (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 # COO 5923 (AM-33-I).

~

.[ 3. Plug the instrument into a 115 V.A.C receptacle; -

4. Switch,the Blower Power switch to ON. Adjust air flow rate gte to 5 CFM using adjustment on Magnehelic gauge after about 24 .

1. ' hours of operation (AM-3D). Adjust AM-33-I photchelic gauge flow set point controls to 3.5 CFM and readjust after t 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if necessary.

i .

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 3 GOO i 400 CPM, if not report findings to the Health Physics Foreman. l

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).

H. INTERPRETATtON OF IN9TRUMENT RESPONgE

1. Backg60und radioactivity The normal background before collecting 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 between 100 and 5000 C/M, depending upon the environment.

the air cleaning used in the facility and atmospheric - -

- . , . . c ond i t i o_n.5 , a tj t he t ime. This is en exceedingly sensitive -

instrument and a high rate of count from radon and its progeny is to*be expected. (Particulate activity-CAM only).

5 4....

- 16A08' SET

. -- -- Q. - . . _.AWHuvAt

. .-- .. - - . . - - . . . - . . . . . . =

8%A4 DUH4 NO MP-8109

. v,4 .r.l See Title Page E. I. HATCH NUCLEAR PLANT

• vew ao ws 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 pap,er. -

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 stogs collectino garticulates.

.e.W -

The following formula (1) applies; s f.?

?.' .'

C = 5.'3 w 10~* As

~~

Where C= Concentration in uCi/cc l

~U3 . Fga A= Count rate in CPM -

s= Speed of filter paper in in./hr.

a= Suction area 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-30, and AM-33-1 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 filten s efficiency and substituting 10, 10k , peed 103,and CAM 104 detectorY,

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

. ' ~~-

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E. l. HATCH NUCLEAR PLANT HNP-8109 See Title Page mvw =o we 10

~ ~a g,,71,1,g,,, Georgia Power , ,, 13

=

l l

l Subst,ituting f6rmula (1).

Column 2 J,5.3x10' )(1) (cpm)* = uC i / c c = ( 2. E.5 v 10~ ) ( cam),

(5)(0.2)(2) (factor for 20%

efficency)

Am-3D Column 3 (5.3x10-0 )(1) (cpm)*=uCi/cc= (5.3E~'3) fcom)

. (3.5)(.080)(2) (Factor for 8%

efficency)

. AM-33-I

• Instrument background has been subtracted.

TABLE __1_

COLUMN 1 COLUMN 2 COLUMN 3 A (cpm) c(uCi/cc for AM-30) c(uCi/cc for AM-33-I)

. rA

' 10 2.65x10-12 9.46x10-13

1. • 100 2.65x10-11 9.46x10-12 s

1,000 2.65x10-10 9.46x10-11

~Ti 1,320 3.49x10-10 1.24y10-10 -

1, E.OO 4.24x10-10 1. 51 x 10- 10 10,000 2.65x10- 9 9.46x10-10 50,000 1.32x10- 8 4.73x10- 9 10 0

. 1.32x10- 7 4.73x10- 8 10b 2.65x10- 7 9.46x10- 8

3. Rising Air Concentrations

~

Formula (2) C = 0.16x10 (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 cose from a " static" condition of 200 cpm to 1200 cpm in 10 minutes then:

Average cate of cise = (rise) (static) = 100 cpm / min (in cpm / min) 12OOctm - 200__cnm (o A) 10 min. . .

(rise time) w .:

7 .

3 .

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'#" # WP-8109 E. I. HATCH NOCLEAR PLANT See Title Page e,wo can . 10 l See Title Page 7 of 18 C = (.16r10~#) (

A) Where: c = Concentration in uCi/cc fgts A = cpm Formula (2) F = Flow rate in SCFM i g = Detector efficency )

t3 = Sample time The above formula may be reduced by determing the average rate of rise as previously mentioned.

Then: C = (.1Gr10~' ) (6 A) Where: 6A = cpm / min.

Fg Substituting the detector efficiencies and flow rates of the AM-3D and AM-33-I CAMS the following results in Table 2 can be graphed.

~

Column 2 f.16x10-b (cpm / min) = uC i / c c = ( 1. E.O x 10 ") ( cpm /m i n )_

Fg (factor for 20%

[ ,,fg . efficency) AM-3D.

.s.

- Column 3 f.16x10~'*) (cpm / min) = '_uci/cc = (5.71k~")(cp_m/ min) s Fg (factor for 8% efficency)AM-33-I 4,' .

- . TABLE 2 -

COLUMN 1 COLUMN 2 CCLUljN__3 c(uCi/cc for AM-30) '

c ( uCi / c c f o r AM-33 -I ) c(uCi/ cc f or AM-33-I)

(ICDINE)

~'

(PARTICULATE) (PARTICULATE) 1.60x10-10 ,

5.71x10-10 8.79x10-10 l 4.80x10-10 1.71x10- 9 2.63x10- 9 1

8.OOx10-10 2.85r10- 9 4.39x10- 9 1.60x10- 9 5.71>10- 9 8.79x10- 9 4.OOx10- 9 1.42x10- 8 2.19x10- 8 l 8.OOx10- 9 2.95x10- 8 4.39x10- 8 l 1.60x10- 8 5.71v10- 8 8.79x10- 8 8.OOx10- 8 2.85v10- 7 4.39x10- 7 1.60x10- 7 5.71x10- 7 8.79x10- 7 8.OOx10- 7 2.85r10- 6 4.39x10- 6 8.00x1,0- 6' 2.85v10- 5 4.39x10- 5 l The fo11'owing rate of rise ratas are equal to the administrative limits of 1x10~i uCi/cc.

AM-30 AM-33-I Particulate O + activity 27 cpm / min 22 cpm / min Iodine-131 ---

12 cpm / min f r. A*- ra t e o f r i s'e graph will be attached to each air monitor.

4. Determination *of Airoorne Iodine Concentrations.

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E. I. HATCH NUCLEAR PLANT HNP-8109 l See Title Page mem w om 10 See Title Page Georgia Power d. ~~

8 of 18

a. The Model AM-33-I air monitor incorporates a scintillation detector and fixed charcoal cartridge to l access the Radio-iodine levels. Because the collecting I 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; Col'umn 4 C=(1.6x10~N ) (d Al Where: OA= cpm / min (F) (dts)(g)(Ce) F = Flow ra te in SCFM dt 3 = Sampling time min.

g = Detector efficency Ce = Filter Media Collection Efficency C = Concentration in

,,3 j' . uCi/cc.

s if By assuming the flow rate, d'etector efficiency and 6.ilter media collection and the absorption factor is "U3', accounted for during detector calibration formula (3) .

can be reduced to:

C = Ali', Where M' = .16v10 #

tg ,

FgCe Then K' .16 r 10 -I" = 5.77E-11 and C =A (5.77E-11)~

(3.5)(.08)(.99) ts 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 cha.r t 10 cpm / min). The counting rate is 200 cpm and

[ the sample has been on for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> then.

12OO)(5.77E-11 ) =9.62E-11 uCi/cc 120 min, t

b. The average concentration for a change in airborne

[ activity may be determined by subtracting the stable I

airborne concentration from the peak concentration and l dividing the difference by the elapse time period of stable and peak activity. Use formula (1) to determine the results.

( c on cent ra t i on _a t __ tg - concentration atp tl=4A

. t- t, (in minutes) .

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4 See Title Page atv e .o

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

. t, = static condition time ,

tg = 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.

Then: [800-2OO)f5.77E-11) = 1.15E-9 uCi/cc l 30-(t - t)

2. i

~

A graph is attached to each CIM exhibiting a static condition and a cate of rise condition. The charcoal cartridge should be changed when the collected activity indicates a level of 5:10 uCi/cc ( 8500 cpm) in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The charcoal cartridge will be further assessed by l laboratory counting methods. Normally the charcoal ce-tridge (CESCO) will be changed once per week. The

. v/f .j.

following graphs will be attached to the CIM:

V*

Graph #1. Assumes the Iodine 131 concentrations are

.,,3 essentially constant during the collection .

• J' periods of 2 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 its may be expanded neglecting all but the first two terms; Cj = (0.1Gr10-'O)34A = 10.1Gv10"IO A) 1 FgCe(1 .tr3jts) FgCe ,,4jM - (jits)24...)

(1-1+1! - 2 !

Cj = 0.16vtO-lO A Formula (3)

FgtsCe j

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_ MP-8109

.' / E. I. HATCH NUCLEAR PLANT *v6e w .

See Title Page 10 um ~~

See Title Page Geea% D Power 10 of 18 Where: ts = sample time

- td = delay in minutes before the sample is counted 2j = the decay constant of a particular isotope.

Cj = concent. ration of a pa.rticular isotope.

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

. F = f ir:-n rate in SCFM.

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) 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..

,j*

?.s.

T (3) Short half-life material decaying', showing a i stop or decrease in activity.

(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. CAM LOCATIONS AND OPERATION

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

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

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.

4. The distance from the airborne source should also be taken . .

into account.,

q 4 The alarm level shall be set in the following manner.

5.

t 5 .' 6 >ius' SET

~ ~~ - , . -~

y... AM M) VAL PRQC(DVH1 NQ

. 4

/" See Title Page E. l. HATCH NUCLEAR PLANT *mam ~o HNP-8.109 oAn 10 See Title Page Geareia Power A.

~. - - . . 11 of 18

a. The CAMS shall be operated for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 s vary depending on Ra-Th concentration, area background and CAM eff *.lenc'y.' Using the long lived graph the number should be written 1500 cpm i 10%(AM-3Di. For example, if the CAM background is 500 cpm and the 1x10-T uCi/cc critecion 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 v 10~ uCi/cc. The actual alarm setting will vary depending on area background and cin '

efficiency. A rate of rise of 12 cpm / min or 720 cpm.br is equal to 1x10'q uCi/cc. (See formula 3 and its variations). It the background is 100 cpm then the alarm point is set at 820 cpm.

GNI J. CALIBRATION ANO CNECMS -

s

1. Daily or Shift Check

~ "GTs Insure the AM-3D and AM-33-I air f1ow is maintaining a a.

5 and 3.5 SCFM flow rate adjust as necessary.

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 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 v 10~i uCi/cc).

d. Insure there is a sufficient filter paper suoply (24 inches per day) and draw a vertical line across the filter paper. The line is used as a reference point to determine if the filter paper is advancing.

e. Note the Flow, concentration, date and time on the chart paper and initial the chart paper.

2. Weekly Check (AM-30)

a. Check flow rates of cams and cim-cams to assure proper -

flow on magnehelic or photobelic guages and record on DATA SHEET _l, Data Package 1. .

.n: y

.g l ~

? - .

.o.' -

. . M*dU A' SET ..

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,_._.f.__...____...___._-._. _ _ _ _ . _ _ - - - -. - . . . _ . - - - --- -

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.8 E.1. HATCH NUCLEAR PLANT HNP-8109 S4e Title Pace "t viww w um 10 See Title P g Gecdf.twer O

- ~~

12 of 18

b. Place the' Input Mode switch to TEST and observe

,'ratemeter and recorder. Reading should be 3600 i 400 CPM. Record results on Data Sheet 1, Data Package 1.

Weekly Continuous Air Monitor Check. Mark " TEST" on the chart pap,er turn the pump off and open or remove the detector rl'd in g .

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 AM33-1 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

,gf/ centered and against the detector window. Proceed as ej. .' mentioned in the previous par,agraph. s

d. After completion of the above checks return the CAM to l

~U$i 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

, coincide. If the detector efficency is low,

, calibrate the cim in accordance with the

. Semi-Annual checks prescribed below.

(3) Semi-Annual Calibration.

(a) Test Shop will calibrate the magnehelic or Photchelic on the cam or cim-cam (MR's are to be written by Instrument Techs) semi annually. .

.- N . .

A

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M* 4 30s: SET

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A8MJHL PHQ(ADu64L NQ

.N Seer Title Page E. l. HATCH NUCLEAR PLANT HNP-8109 mve nu van 10 See Title Page 13 of 18 (b) .. Note on the chart paper the Semi-annual

. calibration is occuring. Turn the instrument high voltage off and remove the probe connector.

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

. connector ilocated on left side of probe connector), (AM-30) 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 min' pulser at 1.0 volt amplitude.

,, ,v9 Set the counting rate of the mini, pulser to

!f 100, 1000, 10,000,.40,000, and 800,000 cpm.

Adjust the bias, low and high-end controls es necessary to correspond to the input pulse

~U$,s being generated.

NOTE b

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

Disreguard 800,000 cpm step.

(f) After this calibration insert the eneck 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 nas not drifted and instrument efficiency is within 10% of the last efficiency check, return the instrument to operation. (AM-30).

(g) The cia detector Iodine 131 operating voltage l is set by inserting the Sa 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 until the c/m meter indicates and optimum value. Then set the high voltage control 1% lower than indicated reading.

i chart.- jal (h) , Replace calibration sticker and initial y_ i 2 .

--AQ a

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. 0..' E. I. HATCH NUCLEAR PLANT HNP-8109

.e See Title Page  %,,r,. w om to Gee Title Pag, Georgia PotVer m. ~~

, ,, 13 (i) ,. Complete the necessary forms (see attached l

. forms).

NOTE The AM-3D an<j.Am-33-I is designed to measure general air trends and changes in these trends.

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

. documented.

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~w See Title Page . :.-J6T'l8 POWef L - 15 of 18 Pet 0CEDLRE DATA PACMAGE Doct# Cif NO: 6+# -8109- 1 SERIAL NO: #10-

>PL NO:

RTWE: C15.1 A e

XREF:

TOTAL SHEETS: 2 FREQlINCY;*LEEWLY

.ej.M* .,

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C&PLETED BY

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DATE'COM*LETED:

I HAW REVIELED THIS DATA PACMAGE FOR CCMoLETENECS APO AGA1HST ACCDSTANCE CRITERIA IN ACCCFDWE WITH Ffe-830.

ACCEPTABLE LNACCEPTABLE REVIDED BY:

DATE REVIEWED:

i Roms:

Page 1 of 2 H'P-8109 R10 l

l

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10 .

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See Title Page Gcorgia Power m .

17 0, 13 '

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PROCEDLPE DATA PACKAGE b

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j DOctJENT NO: w -9109-2 .

SERIN. to: 410-9 PPL N3: ..

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RTYPE: C15.16 -

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XREF: p t-  ??

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I HAVE REVIEWED THIS DATA PACWACE FOR COMPLETDESS Ato AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH W -830. [

I ACCEPTA8LE t.NACCEPTMLE REVIEbED BY:

DATE REVIEWED:

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DATA PACMACg,g (Data sheet 2)

INSTDtf0f7 CALIBoATforJ DATA 9EET i :iii: *

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Y . HATCH NUCLEAR PLANT PROCEDURE .

ARM Portable Calibration Unit PROCEDURE TITLE

. HNP-8111 PROCEDURE NUMBER

' . L a b' RESPONSIBLE SECTION NON-SAFETY RELATED ( )

SAFETY REl.ATED ( Y )

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APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER

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• PROCEDUGE N'O. IW - <fO! *

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DrPARTMENT :-iFr.n APPun'w. ~~~~

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.. REVISION CHAT:GES MCCE OF .CPERATION 03 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 Rel.ated ( .

.Nnn-Safety Related' ( ) . , .

T Safety /Non-safety Status Change ( ) Yes

( [ No '

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

REASON Fdn RECUEST A U V 6-Z.h'V vpG-7t* MAf bib 77: (W&W ADD _

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the revision does not chance the ourcose or oerformance of the .

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2. The possibility of an accident or malfunction of a different tvoe. 7 .

than an_a_l X ze_d__in the FSAR cces not result from__t_his c_ha_n_c_e becaus_e__u_

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t the sy,, stem resconds and is ccerated as before the chance.

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3. The maroin of safety as de#ined in the Technical Soecifications f

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i is_ not reduced due to this revision because the__re_ vision __d_o.e._s _n_o_t_____

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chance anv limited safety sys_t_em settinos which _would allcw a s_a_f_e_t'fi ._' l,i_m_i t to be__excee_de_d_or to allow a_limi tina _. cond.i.t_ ion for___-

operations to be exceeded as_ s_tated in_ Technical Scecifications.

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F,, E. I. HATCH NUCLEAR PLANT HNP-Bill She Title Page *vem w r[

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ARM PORTABLE CALIBRATION UNIT A. PURPOSE To ensure that the instruments are operated properly.

8. GAFETY Observe radiation protection procedures.

C. REFERENCES

1. S-17978 CEK-865C Portable Calibration Unit for Area Radiation Monitor

2. HNP-8014 Handling of USNRC Licensed Radioactive Material

,,.p j 3. HNP-8017 Control and Accountability of Radioactive Material rj. ' .

d D. DESCRIPTIGy OF UNIT fS *,

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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 source, Cobalt 60, has a half life of 5.25 years, allowance 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 NOTE 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 6G54071 and 6339537. Charts are furnished for both.

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CAUTION "This units contain approximately 200 microcuries of Cobalt GO. Exercise care in handling the unit to minimize radiation exposure.

1. Insert the sensor a';.i 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. f 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.

. .d f* 5. When the ARM calibration is complete set the source control to OUT,and both shield controls to IN to provide maximum shielding of the source. Install top cover and return unit

~$i to area which it is assigned and complete 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 complation of HNP-8014, Form i by the person requesting the source.

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. 4 See Title Page $ 3 of 8 FIGURE 1 CALIBIfdE. DATE 5-22-73 l SERIAL NUMBER 6554071 SOURCE & GROUPS GROUTS Ch0UPtil SilIELD 11612 13&l5 14,16 POSITIONS &l7

- SOURCE IN 354.3 40~,.0 403.0

.S!! 1 OUT -

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Sll 1 OUT

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NOTE: CALIBRATED WITil A G.E.

• STANDARD GRt.'!A COSALT-60 '

SOURCE IN SAN JOSE.

CAUTION: ATTER USE, PUSH EOTI!

SHIELDS & SOURCE TO LCCK POSITION.

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