ML20107G142
| ML20107G142 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/15/1985 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20107G128 | List: |
| References | |
| PROC-850215, NUDOCS 8502260323 | |
| Download: ML20107G142 (142) | |
Text
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d PROCEDURE Eberline liodel PCit-1 Portal Monitor Opaatton_an.d_fa.littration s PROCEDURE TITLE HNP-8161 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) m_____q . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________.._____________e___..________ APPROVED APPROVED REV. DESCRIPTION DEPT. GEbERAL DATE MANAGER MANAGER
-_____q . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._______________;.___,__ _____ , _..________
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SIGNATURE ' DATE @ LIST ANY QA TRACER NUMBERS EEING ADDRESSED : R LA - h'? $ am % % '4.Cil. I PRG REVIEW : #W -@/M M // / I/89 j SIGNATURE DATE s PRT.SENT STATUS : ( )(,) SAFETY RELATED ; ( ). MON-SAFETY RELATED
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V ( ) YES, TO h) 1 a ; l h THE ABOVE ST'ATUS IS BEING CHANGED: ( ) NO _- h TRAINING REQUIREMENTS (FOR ADMINISTRATIVE PROCEDURES : u ,I A ONLY) aq
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( ) REQUIRES A TECH. SPECS. CHANGE BEFORE THE DOCUMENT CAN BE USED; IF SO, RECORD THE ASSOCIATED DoCR NUMBER : - ( %) NEITHER . 9 hDOESTHEIMPLEMENTATIONOFTHISDOCUMENTREPRESENTANUNREVIEWEDSAFET . QUESTION? ( ) YES ; (K) NO a
; h CIVE THE BASIS FOR THE DETERMINATION OF WHETHER OR NOT THE IMPL DOCUMENT REPRESENTS AN UNREVIEWED SAFETI QUESTION :
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h THE IMPLEMENTATION OF THIS DOCUMENT h DOES NOT) CONSTITUTE AN UNE
, SAFETY QUESTION AS EIPLAINED BELOW:
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,f 1. THE PROBABILITY OF OCCURRENCE AND THE CONSEQUENCES OF AN ACCIDENT OE ,'
W MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY 64B99f ARE NOT) INCREASD . 3, " ABOVE THOSE ANALTZED IN THE'FSAR DUE TO THE IMPLEMENTATION OF THIS DOCUMENT - BECAUSE: A
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. o.1, Georgia Power d .. ~o See Title Page 1 of 22 i' N EBERLINE MODEL PCM-1 PORTAL MONITOR OPERATION AND CALIBRATION A. PURPOSE , This. procedure provides the necessary details and methodology for placing the PCM-1 into operation, performing initial - calibrations, setting operating parameters, and performing the periodic checks on the instrument. , 4 B. SAFETY. Observe Radiation Protection procedures. Do not place the hands, eyes, or other parts of the body in close proximity to the thin window side of the beta sources. C. REFERENCES .
- 1. TDC-6002M, Model PCM-1 Technical Manual, January 1983, 4
- 2. HNP-830, Performance and Review of Plant Functions and
!~ Procedures
- 3. HNP-8116, Eberline Minipulser Procedure
[ D. TEST EQUIPMENT
- 1. Wide range digital voltmeter 11
- 2. Eberline: minipulser
- 3. Oscilliscope
- 4. Calibration and check sources. (Calibration sources must have NBS traceable documentation).
- 5. Electrostatic-Voltmeter 3kv E. DEFINITIONS
- 1. Alarm Hold Time: The length of time the. audible. alarm and-the display module remain activated'during an alarm condition. (Operator determined, 1 to 9-s.econds)
- 2. Alarm Setting (R A): (Operator determined - Modes 1 and 3). The minimum number of counts (N) collected-before a contamination alarm will occur is:
N=RA T + RBT "i s - ,
E. I. Hatch Nuclear Plant . a = ova' aaxte< ~o l H N P- 0161 ! See Title Page~ ,em,os so 1
- o. . Georgia Power d ..e. ~e See Title Page 2 of 22 O Therefore, R4 specifies the minimum activity count rate that will trigger an alarm. The probability that a given
. amount of activity will produce a count rate RA during the period T is determined by the Z factor (see below).
- 3. Count Time (T): (Modes 1 & 2) A predetermined period of time for the count duration of the background update and the personnel count. (Operator determined 1 to 10 seconds) .
- 4. Count Time, Test: 'The length of time that the system counts in the " Count Rate" mode, normally used for source checking individual channels. (Operator determined 1 to 900 seconds)
- 5. Maximum Alarm Limit (R Preset count rate that will cause a high b5$Ng)r:oun(Mode 2) d alarm if the setpoint is exceeded.
- 6. Maximum Count Time (T max): (Mode 3 only) The maximum, allowable amount of counting time, (T). A high background alarm will occur when T 2 Tmax- .
- 7. Reliability of Detection: The probability that activity which produces an average count rate R a in a detector will trigger an alarm during a counting time, T, is determined by
(_ the equation: RA=R a -Z Ra+Rb + Rb where Rb is the background count rate during the counting' time T. RB is the best estimate of Rb . W is the Weighting Factor (see below). Z is determined by choosing the desired confidence level that will produce an acceptable false alarm rate, and still maintain a reasonable confidence in the detection level. This determination should be based on the location of the monitor and the conditions (e.g. background level) under which it is to be used. For 99.9 percent confidence level; F(z) = .999, z = 3.090 For 99.0 percent confidence level, F(z) = .990,.z = 2.326 For 95.0 pe. cent confidence level, F(z) = .950, z = 1.645 For 90.0 percent confidence level, F(z) = .900, z = 1.282-
,o For 75.0 percent confidence level, F(z) = .750, z = 0.674
( ') For 50.0 percent confidence level, F(z) =. 500, z = 0. m
7
*~ao= E. l. Hatch Nuclear Plant aw a waa~o H N P- 8161 See Title Page atv'So*
- 3 Georgia Power d o... ... ~e See Title Page 3 of 22 O 8. Sigma Factor (SF) : A user entered variable that is a multiplier of the background standard deviation used in i determining alarm setpoints .
- a. Mode 1, the SF is used in determining the alarm l s etpoint for the high background alarm. When ,
SF yRBT JL R A T the alarm will occur.
- b. Mode 2, the SF is used in determining the personnel alarm setpoint, R> A wher .. RA = SF g R B /T
- c. Mode 3: the SF is .used in determining the minimum count time, where the alarm setpoint RA is preset and the highest average channel background is R B' T= (SF) 2 RB /(RA)
NOTE () The value of the Sigma Factor will vary based on which of the three modes of operation is to be used. Determine values for the variable represented in the formulas based on the location and operating conditions of the monitor. Use - these to arrive' at an acceptable value. for1the SF that will produce the most sensitive operation with the least amount of false alarms. .,
- d. Units:- The units displayed can be in counts per second or minute, whichever is selected..
- e. Weighting Factor (W): A number that is used in s
compensating-for background variation. . An incre'ase in the W value results in an increased ability-to reject. false ' alarms, but st 'the same- time it increases the amount of time it takes -to -respond to real, changes -in the ambient background. 'A value'between: 5 and 20 is
' recommended.
F. DESCRIPTION m 1. -- Gener al 1 1 '
'd The Eberline Personnel Contamination Monitor, 'Model .PCM-1, isc a microprocessor-based radiation detection system which - 1 provides a quick indication of beta-gama contaminatipn on personnel.-
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. a = ova' E. l. Hatch Nuclear Plant aoaouac ~o 8161 HNP.
See Title Page . ,$o o o., Georgia Power d .. o See Title Page 4 of 22 O The PCM-1 has an operate mode and a test mode. While in the operate mode the monitor will run in its main routine, measuring and storing background for all channels, checking for high background alarm levels, low or high count failure, and low gas pressure conditions. This causes the pa sonnel l monitoring routine to be executed. This routine chucks all channels for high activity alarm conditions with automatic background subtraction, according to the protocol of one of the three operating. modes in which the monitor has been set to operate. The test mode is used to run detector plateaus, determine counting efficiencies, etc. The PCM-1 has fif teen (15) independent gas-flow proportional detectors. Maximum detector sensitivity is achieved through the use of an input preamplifier for each channel which interfaces each detector to the microcomputer. Each channel has adjustable gain and discriminator to permit the operating point to be optimized for each detector. . Each group of five channels has an independently adjustable high voltage power supply, with a nominal range of 500 to' 2500 VDC. The outputs from the fifteen discriminators are fed to a counter board, and then to a central processing unit (CPU) module which includes an Intel 8085 microprocessor, memory, and input / output parameters during periods of power outage.
~
- 2. Controls and Indicators
- a. External (1) Ultrasonic sensing unit: (When in use) Senses one's approach to the monitor and causes l'
background counting to stop and the display to read STEP UP--INSERT RIGHT ARM, accompanled by a short. beep.- (* -(2) Alphanumeric display: Indic'ates approprlate: messages to users in the operate mode and indicates operating conditions and parameters when the monitor is in the test mode. (3) Display lights: Alarm, Counting, Ready and Trouble lights that assist-in indicating
. appropriate: messages-to-users.-
'(4) Photoelectric sensor: Indicates to the monitor that-it is occupied or if the occupant has exited the monitor before the count cycle has been
- . {J completed.
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-- aaaaovat E. l. Hatch Nuclear Plant aw a wai~o 0161 H N P-See Title Page nev,3,o~ ~o om Georgia Power d , . - ~o See Title Page 5 of 22 O (5) Operate / Test switch: A key operated switch that controls the operation of the monitor between the !
normal operation mode and its test and maintenance l routines. (6) Keyboard: A 16 key control board that serves as the interface for communication between the operator and the monitor. . (7) Alarm ack'nowledge: Silences contamination alarm. l
- b. Internal (1) Power Switch: provides on-off capabilities for 110 volt AC power.
(2) Flow gauges: (3) indicate inlet flow rates in cc/ minute for flow groups A, B, & C. . (3) Pressure Regulators: (2) a dual guage fully adjustable control for the P-10 gas used in' the' detectors. They are mounted on -type 1A gas cylinders and are connected to the instrument by 3/16" ID Tygon Tubing. (4). HV Switches: (3) switches that provide on'-off capabilities for each of the three high voltage. sections. (5) HV Adjust: (3) potentiometers that provide a , reference voltage.to each of the high voltage a power supplies en'bling control of the HV setting.
- 3. Test Mode If the OPERATE / TEST switch S1 is set-to TEST, the monitor-runs in its test and maintenance routines.- In this mode, l- the keyboard is active and the other sensors are inactive.
Baci: ground measurements and related computations' are suspended while.in TEST, and all parameters are available for display and/or modification as listed <in Table 1. The display prompts the operator with the name of _the parameter list ready for examination or,.within'a list, the name of-the variable being displayed and its prese.nt value. The keyboard protocol is such that ;touching the _ "+" key causes an increment to the next time, the " " key causes a
. decrement to the' prior item and the ENTER' key causes ~ entry; to that list.
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* - ova' E.1. Hatch Nuclear Plant aaxe=at~o 8161 HNP.
See Title Page . visio~ ~o om Georgia Power b ..e. ~o See Title Page 6 of 22 O 4. Operate Mode If the OPERATE / TEST switch next to the keyboard is set to OPERATE, the monitor will run in its main routine, measuring and storing background for all channels, checking for high background alarm levels, low count failure, and low gas pressure conditions until the actuation of sensing switches calls the personnel monitoring routine. This routine caus.es all channels to check for high activity alarm conditions
~
with automatic background subtraction, according to the protocol of one of the three operating modes in which the monitor has been set to operate:
- a. Mode 1: Preset All
- b. Mode.2: Maximum Sensitivity
- c. Mode 3: Minimum Count Time ,
The ultrasonic unit will, when in use, sense an individual's l approach to the monitor. All background counting will cease, and the display will read STEP UP--INSERT RIGHT ARM. When an individual inserts an arm into the hand / forearm cavity, a light beam will be broken and the monitor will O' initiate counting. The display will read COUNTING RIGHT SIDE for the duration .of the counting time. If no alarm levels are exceeded, the unit beeps and displays RIGHT SIDE
.OK--INSERT LEFT ARM. The display will indicate COUNTING LEFT SIDE when the lef t arm interrupts the light beam in the detector cavity. At the end of the counting time the unit displays COUNT COMPLETE, YOU MAY PASS, accompanied by'a chime if no alarm levels are exceeded.
Contamination _in excess of_ alarm levels is signaled at the end of.Right or Left side counting, or both, by the alarm sonalert and display messages. All contaminated zones will be indicated on the display.
.i Premature arm withdrawal will~cause the alarm sonalert to sound _and COUNT INCOMPLETE ** RECOUNT **-to be displayed.
4 Reinsertion restarts the count. (1) ' Mode 1: Preset'All , In this mode, the alarm setpoint'-(R for each channel, and the counting time -(T) A)d an the sigman factor (SF) for 'all channels, .are: entered via the keyboard. A personnel alarm occurs?if the count n (N) in the counting time (T) is' such that: N1RB T+RA T i ==
7
. a= ova E.1. Hatch Nuclear Plant aaoccouaefu 8
H N P-Soo Title Page oey,sio,. o o.1, Georgia Power d ... e 7 of 22 See Title Page O The high background alarm occurs if: i SF g RB T 2RA T (2) Mode 2: Maximum Sensitivity : In this mode the maximum alarm limit (RA max). counting time (T), and sigma factor (S F)~, are . entered v.ia the keyboard. Each time the background is updated, a new alarm setting (R A) is computed for each channel. RA = SF qR/T B A personnel alarm occurs if: NARB T+RA T The high background alarm occurs if: RA1RA max (3) Mode 3: Minimum Count Time In this mode, R A, SF and maximum count time
\ (T ax) are entered. Each time background is up$ated,anewcount time is computed from; T = (SF) 2 RB/(RA) e
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based on the channel with the highest R B-A personnel alarm occurs if: N2RB T+RA T The high background alarm occurs if: T _> T max
- 5. Failure and Trouble Indications e
- a. High Background If the background count rate, R B, in 'any zone (s) should increase to such an extent that it, and the selected sigma factor, SF, counting time, T, alarm level, RA max alarm limit, RA max, and max count
. time, 'nnax, < relate so as .to satisfy .the inequaltities
[] of Section F.4.a, F.4.b, or F.4.c; the alarm light , trouble light, sonalert, and (ZONE / CHANNEL DESIGNATION). V m ee.
7
.: ^~aova' E. l. Hatch Nuclear Plant aoceouae ~o HNP- 8161 See Title Page nvisio~ ~o 3
om GeorgiaPower A .. e See Title Page 8 of 22 O HIGH BACKGROUND message, will be activated for the duration of the alarm hold time. The trouble light will remain illuminated when the unit automatically reverts to counting background, but the zone (s) involved will not update background or be capable of further alarm sensing until cleared through the DISPLAY TROUBLE LIST section of the test mode menu, which lists all the currect trouble conditions and zones. After . returning to the operate mode, any trouble which persists will cause reactivation of the alarm and message.
- b. High Count Fail If the 64K count capacity of any zone counter is exceeded during a background count interval, the alarm light, trouble light, sonalert, and (CHANNEL DESIGNATION) HIGH COUNT FAIL message, are activated.
The trouble light will remain on and the fail zone will remain inactive until cleared, as in the case of the high background alarm. High count fail _is more likely to be caused by electrical noise than by legitimate Counts. () c. Low Count Fail If a zone counter receives counts below the Low Count Fail-Setpoint, a (ZONE / CHANNEL DESIGNATION) LOW COUNT FAIL message / alarm is activated in a manner identical to the previous ones. Any counts which occur between
, background counting cycles, during the overhead time of the computer, are not registered in the zone counters.
7
- d. Loss of Gas Pressure If both gas bottles have pressure when the PCM-1 is l first turned on, gas will be drawn .from bottle #1, through ports 2 and 3 of gas bottle select valve V1 (unactuated), to the , input flowmeter. When bottle il runs out of gas, pressure switch S2 senses -_the loss of-pressure, causing the computer to . activate the alarm-and the message BOTTLE #1 EMPTY, and to actuate V1, drawing gas from bottle f2. _The' trouble light will remain on_until bottle #1 is replaced,. V1.will remain actuated until' Bottle #2 runs out- of gas, whereupon V1 switches back to Bottle: #1, and . the alarm and message -
BOTTLE #2. EMPTY-is activated.- -If both bottles:are out. of gas , :the . alarm and ! message FAILURE **OUT OF GAS' :are- [ activated, all counting-stops, and the message remains 1
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on the display until ~ pressure - is restored to either, ~or v i A .
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a ~ ova' E.1. Hatch Nuclear Plant aaou = = ~o H N P- 8161 See Title Page nvisio= ~o
' 3 o.m Georgia Power A ... e See Title Page 9 of 22
.O both, pressure sensors. If the gas supply fails, the high voltage should be turned off. This is achieved by opening the power switch or by pulling the AC line cord. The gas should be restored prior to re-energizing the system.
- e. All Zones Failed .
If personnel counting is attempted while all zones have failed, the display will indicate FAILED, and no count will be attempted. G. OPERATION OF INSTRUMENT
- 1. Mode 3 is the normally preferred system configuration at Plant Hatch based on system flexibility. Modes 1 or.2 may.
also be utilized, however, (as deemed necessary by the Health Physics Laboratory Supervisor), when conditions or use are such that Mode 3 operation becomes impractical.
- a. The system set-up data must be used to calculate the necessary parameters for Mode 1 or 2 operation Appropriate informational entries should be made in the PCM-1 log book when any mode other than Mode 3 is used.
- 2. nitial Set-up i a'. P-10 gas book up: Install one 1A cylinder of P-10 gas in each side (bottle il is on the lef t, bottle #2 is onL the right) . Set the regulators to minimum. pressure, ,
connect;the pressure regulators on bottles 1 & 2, and connect the 3/16" tygon-tubing to the outlet side of-the regulators. Secure - the ' gas -bottles in place.- l b. Gan Flow and Pressure Adjust: . Adjust 1the pressure-i regulators to 5 + 0.5. psig and the flow regulators to .l-50 + 5.0 cc/ minute.. .; { ! - CAUTION - p . L Do not exceed 50 +15.0 cc/ minute or:5 i 0.5 psig; l because damage to the detectors may occur. Power Connnection: The instrument uses1110. volt AC
- c.
power. It should be pluggedfin;and: turned on.Lat-this-
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time.- - d._ Test the pressure switches by shutting'off : the main:gast Jr3) , bottle valves in'; sequence and. verifying;that the-
, L( trouble and failure alarms foccur as' expected.
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=om E. l. Hatch Nuclear Plant aoaouas ~o
, H N P- 8161 See Title Page aEWSON NO 3
om Georgia Power d - ~o See Title Page 10 o f 22 O e. Initial Purge: Allow approximately 4 to 5 hours purge time at 5015.0 cc/ minute to insure that the system is I completely purged of outside air and moisture. Adjust x the flow rates to 2512.5 cc/ minute for normal I s operation. NOTE n . Complete purging prior to initiation of testing. w
- 3. Tes_ ting
- a. See all alpha threshold voltages to 500 mV on the amplifier / discriminator boards, using the ALPHA THLD controls. Set all beta-gamma threshold voltages to 500 mV using the B-G THLD controls. - Check these items in
, Data. Package 1. .
- b. Set amplifier gains (R411 on amplifier-discriminator boards) to 50. This is accomplished by applying'a ImV (approximately) negative going pulse at the input to
- the channel being adjusted, yielding a 40 mV signal at e the preamp output, TP-1-referenced to TP-3 ground.
. Refer to the Amplifier-Discriminator schematic and O- component layout in that section for more details.
R411 is then adjusted to provide a 2V signal at the
- amplifier-output, TP-2 referenced to TP-3' ground.
Check this item in Data Package 1.
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~
- c. Place 'all the ' ANTI-COIN switches to OUT. . Check this-item in Data-Package 1.
d J' Set 'the TEST /0PERATE switch to TEST, and access the Count Rate Mode, . Upper!%rm display. -This is the typical l beta-gamma channer used for ~ set-up.
~
- 4) e. Place a suitable beta sobrce',' ideally,.aLlarge' area, i ! uniformly! distributed source of 200K to 2M dpe' (4 *K ).
(approximately 75% -Co-60,25% Cs-137 -) on - the screen .of the_ Upper Arm detector. Uset a calibration > jig?(source
$'f q,. holder)-~ to ' position the source , Land plot 7 the -beta plateau,. adjusting' the high' voltagej in the middle ' card cage in = 50 Visteps. Jrhe t plateau . shou.ld ~ extend from.
. . 1100 Rto :1800 volts .--
l Lower lthe. high ' voltage soc that ' the. beta' counti rate is -
~
f '. approxiMa,tely; 50% of the' grossf counts--recorded at the platecuivalue. ~ Record the count rate.
- p. '
. ;!n) . g. ~ Lower ithe-high -voltage in the tother card l cages to they
- 't ,,
same value as in step'f2 4eW. , . if J -1 S seeeee h.
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- h. Position the beta soure on the other zone detectors and adjust the appropriate B-G THLD controls to obtain similar (approximately + 5%) count rates in all the j other zones, except the foot detector, which is treated separately.
1
- i. Increase the high voltage in all three card cages to ,a l value which is midway on the measured beta plateau. ,
Record the vol~tage. ; j .- Beta ef ficiency with Co-60 and Cs-137 should be approximately 10 percent of the 4 cm beta emission rate of the source (or greater) for all zones, except 8 per cent (or greater) for the foot detectors.
- k. Verify the plateaus of the other 14 detectors by counting the beta source when the high voltage is adjusted by -50, 0, and +50 volts from the selected .
plateau value.- If necessary, return to step i. If repeating steps i & j is not adequate, return to step a.
- 1. Using a source of 75% CO-60, 25% Cs-137 (percentages .
are approximate) calibrace all ~the detectors (with the O exception of the foot detector) when- the distance from
~
the active : surface of the source to the face is approximately 3" (use the 3". calibration source -jig). Calculate each detector 's ef ficiency- and enter all data
- on the Data Package. l c m. Measure the ef ficiency ' of -the . foot detector when 'the- -
source lies flat on the footplate. Enter all data on' the Data Package. - ' n.- Calculate the average of all1 the detectors efficiencies,
-(except. the foot detector) and enter on 'the ' Data .
Package. This:overall value, (EFF), is the reference value for the weekly calibration . checks and the control chart -preparation for all but the foot- detector. t -
'o. Calculate Tmax: 4 Tmax= ' (SF)'2*3000' c
-(5000*E1F) 2 where EFF'is' the overalliefficiency (mostf detectors).
If'Tmax exceeds 40 : seconds , reduce the background v count rate, J SF,- or' consider using a dif ferent: operational mode 1 (1 or.2), as appropriate.-
~
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E.1. Hatch Nuclear Plant
. ~~~ **u=aa ~o H N P- 8161 See Title Page aemio~ ~o 3
o.m Georgia Power d ..m mo See Title Page 12 of 22 O p. Calculate RA according to: R A= SCL
- EFF, where SCL = surface contamination limit (dpm/100cm )2 the monitor is expected to detect, and RA has units of cpm.
- q. Set the Low Count Fail Setpoint at 60% of the Average l Background count rate for each channel.
- r. Complete the Data Package and route for review.
H. DAILY ALARM CHECK
- 1. Verify that the P-10 gas regulators are set at 510.5 psig and the gas flows to all three Zone / Channel detector branches are 25 1 2.5 cc/ minute. Adjust as necessary. .
- 2. Turn the Operate / Test switch to the Test position. Access the Display System Parameters Listing and ensure that' the'
" Alarm Hold Time" is set at 2 seconds. Access the Display Channel Parameters Listing and verify that the backgrounds-l .for all Zone / Channel detectors are between 750 and.4000 cpm. l j' 3. Return .the Operate / Test switch to the Operate position and allow the monitor to background count momentarily.
- 4. Place tNe 75% Co-60/ 25% Cs-137 (percentages are a
.(pproximate) approximately ' beta-gamma 5000-10,000source usedcm4,.
DPM/100 fgr the alarm Lcheck uniformly
- j. ' distributed) in " contact" with the screen (use thetcontacts F calibration jig) of each zone / channel detector; while1 standing in the monitor. Verify .that the1 appropriate alarm, L ,
as indicated audibly and on the display is received b L stepping out:of the monitor'between alarms. l- 5. 'In the ' event = that tone or more of' the Zone / Channels does not i alarm, immediately remove the unit: from- service and: L investigate the cause in ~accordance with the- manufacturer 's L check out. procedure. - - ' i- 1, -
' s; 15 . Make an appropriate entry in the PCM-1 log book, ssimilar "All Zone / Channel 1 alarms " satisfactory., monitor
~
, to:
" , or ' Zone
_ ~f '
/ Channel ' alarm ~ for (Zone -f ,cor-
' ;! Channel ) unsatisfactory:for MonitorTf 'f . .
-In = addition, enter the date and time of the alarm check i and print ' the -name of 1the individual who performed 1thef check.
Initial the entry. fq. - .tx.,-) I
+
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7
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- aevat E. l. Hatch Nuclear Plant aaoa=as ~o HNP OL6L l See Title Page aevisio= ~o Georgia Power d o.m ..e ~o See Title Page 13 of 22 O NOTE An entry must be made in the PCM-1 log book for corrective actions taken in the event of a failed alarm check.
I. Weekly Calibration Check .
- 1. Complete the Daily Alarm Check (section H of this procedure).
- 2. Turn the Operate / Test switch to the. Test position. Access the Display System Parameters Listing and record the initial setting for Mode", " Sigma Factor", and " Weighting Factor".
Verify-that the " Alarm Hold Time" is set at 2 s9conds, and that the " Count Time, Test" is at 10 seconds. Record the
" Count Time" - (Mode 1 or 2) , and the " Max.' Count Time" .(Mode 3). Ensure that. the units are in cpm.- -
- 3. Advance to the Display Channel Parameter Listing and press-the " Enter" key twice to gain' access-to the individual' Zone / Channel detector' parameters. Record the " Average Background cpm", the initial _" Alarm Setting cpm" (Mode lLor 3), the " Max Alarm Limit" (Mode 2), and the. Low. Count Fail O ,
Setpoint for.each of the 15' Zone /Chann~el. detectors on Data. Package'2. If-the Low-Count. Fail-Setpoint: is not within
+ 20% of'60% of the Average Background, adjust the Low Count- - l-Fail Setpoint.~ to '60% of the Average Background.' l
- 4. Advance the display-tos the. Count Rate Mode. Press " Enter",to-
~
, gain access to the first~ Zone / Channel 1 displayed. Position-Lthe.75%' cos60/ 25% Cs-137 calibration source (the'NBS Traceable set-up source; percentages are-approximate) usingL .
the 4 3"~ source: jig'at the: centerline of the: detector. Allow,. the' count rate display to. stabilize and< record the displayed-value on' Data. Package 2. Continue'this operation-through alli
'15 ' Zone / Channels ~and record.:all obtained data, with the exce tion thatithe foot} monitor.should.only.be~ checked ~at
~
- the p' contact": posit' ion,land that countErate recorded.
* :5. Return the Operate / Test switch toith'e Operat'e:posi. tion.-
~
. 6. ; Calculate'the1 overall-efficiency of the monitor 5as.in step-G.2.n and' record'on the; Data: Package.*
.: ll
'7.. ' Calculate the weekly effi'ciencies forEeach.of the ,
Zone / Channel detectorsifrom:the 3"idetector. count rates, except1as specifiedninJG.3.m;. O u> - a
#jI s
- + a t.
!, la=ovat E. l. Hatch Nuclear Plant aaouwae ~o H N P- 8161 l See Title Page aavisc~ ~o 3 L- om Georgia Power d ..m ~o i See Title Page . 14 o f 22 O 8. Enter the average detector efficiency, and the foot detector ef ficiency as measured during set-up (section G of this procedure). Verify that all detector efficiencies are within
+ 20% of the appropriate value. If any Zone / Channel detector l exceeds + 20% of the applicable value, determine the cause, g correct the problem, and repeat the steps of this section for that detector . In the event that the measured efficiency of any Zone / Channel detector exceeds + 20% of the appro- -
priate set-up value., and is not correctable, reperform the l steps of section G. Record all information on the appropriate Data Package (s) and plot each detector ef ficiency on the ins trument control chart (average and foot detector charts). 9 .- When operating in Mode 3, calculate Tm , as in step G.3.p, and record on the Data Package.aff Tm seconds, reduce the background rate, reduce $h, exceeds or consider 40 the use of Mode 1 or 2, as appropriate. .
- 10. When operating in' Mode 3, calculate RA as in step G.3 q, and record on the Data Package.
11 '. Turn the Operate / Test switch to the Test position, update the Tmax and RA . values through editing those parameters,- () as necessary, and return the switch to the. Operate position.
- 12. ' Complete the Data Package and ' forward for review.
J. ANNUAL CALIBRATION Once each year , perform the steps in - Section G. 3 e-r in Jplace of-the weekly calibration checks. K. DOCUMENTATION
- 1. Fill out. the attached procedure Data Packageil each time la unit is placed in -service or electronic :repairfis completed.
Complete Data Package 2 each week for the monitors in service. All data must be placed . in 1 the archives. s .. ..
- 12. ' Record' all systems evolutions and changes to the. calibration or edit / entry data of -Table 1 in the PW-lTlogbook.
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H N P- 8161 I See Title Page aevisio= ~o 3 om GeorgiaPower d ..o. ~o , See Title Page 15 o f 22 O TABLE 1 TEST MODE MENU Operating Mode Parameter Mode 1 Mode 2 Mode 3 - List and Present Max. Min. Ct Default. Item All Sens Time Value FITFLAY SYSTEM PARAMETERS Identification and type H H H -- Program Name and Version. H H H -- Mode (1,2, or 3) E E E 2 Sigma Factor (SF) E E E 3.5 l Waighting Factor (W) E(5-20) E(5-20) E(5-20) 10 ALARM Hold Time (seconds) E E E 1 l. Count-Time, Test (seconds)- E. E E - 1 .I Count. Time, (T, seconds) CAL CAL C 1 Min. Count Time (Mode'1 only) C .NA NA . Max. Count Time (Mode 3 only) NA NA E(40) 1 Units CPM CPM . CPM Cps DISPLAY CHANNEL PARAMETERS
'one or Channel Identification jverage_ Background rate (Rg) M M M --
2 Alarm Setting. rate (Rg) CAL NA CAL 1000 (Mode 1 and 3 only) Low Count' Fail Setpoint E 'E E. . - - g, Min.;: Alarm Limit (Mode 1 only) C NA' NA' -- Max. Alarm Limit (Mode 2 only). NA E NA. ;1000
- Alarm Level 1(Mode 2 only)- .
NA C- .NA -- (Repeats for each zone'or channel) COUNT RATE' MODE' Zone or Channel (cps or cpm) M: M' M . -- (Repeats for each' zone or channel) , -DISPLAY TROUBLE LIST ,. . -(evailable.only_if trouble light.'is on);
-Ztne or Channel- Identification High-Background M M- ~M --
High. Count Fail' M , M " M -- Low Count-Fail ML M M -- Bottle'1~ empty ;ML M ?M
-- i
. Bottle 2 empty M' M M -. .
Failure **~Out.of Gas! .M M -
. M- ---
fSYSTEM DIAGNOSTICS Display Test' A ~A A' - -- Kayboard Test: , 01 01- .01! ' --
' Alarm Ack- A- A -A-. --'
. . J;,igh t .Tes t - A' A. A --
.( )
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./ 5
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' - vat E.1. Hatch Nuclear Plant aaoce=as ~o H N P- 8161 l I
See Title Page aavisio= ~o 3 om Georgia Power d ..e. ~o See Title Page 16 o f 22 O TAB LE 1 (CONT) TEST MODE MENU
~
Operating Mode Parameter blode 1 Mode 2 Mode 3 List and Present Max.- Item Min. Ct De fault All Sens Time Value UIEe Test A A A -- _ Road / Write Memory Test A A A -- Program Memory Test A A A -- USAGE Personnel Counter / Elapsed Time M M M -- RESET -
- Re-initialize system parameters E E E --
& background averages .
LEGEND H-O' E-Fixed by hardware /firmware configuration Edit / Enter via keyboard-(value must be between 0.25 and 600) E()- Edit / Enter. via keyboard-(value or range in parenthesis -normally used) C- Computed variable M-- Measured variable NA - Not~available A- Auto sequence 01 . Operator Input. [ CAL- Edit / Enter via keyboard based on calibration i s 8 9 8 F G -y Y. W g A
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o.,e Georgia Power d a.m ~o See Title Page 17 o f 22 O PROCEDURE DATA PACKACE DOCUMENT NO: HN P- 8161-1 SERIAL NO: R03-MPL NO: RTYPE: G15.14 XREF: TOTAL SHEETS: 3 FREQUENCY: As Required COMPLETED BY: DATE COMPLETED: I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HNP-830. ACCEPTABLE UNACCEPTABLE REVIEWED BY: DATE REVIEWED: RD(ARKS: d Page 1 of 3 g HNP-8161 R03
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FIGURE 1 Page 1 of 3'
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Sao Title Page aevisio~ ~o 3 o... Georgia Power d ..e. ~o See Title rage 18 o f 22 DATA PACKACE 1 PCM-1 SET-UP AND INITIAL CALIBRATION Location: MPLf: Serial #: Completed By: Date: - ALPHA THLDS Set 500 mV: ( )' B-G THLDS Set 500 mV: ( ) AMP Gains Set 50: ( ) ANTI-Coin Switches Set out: ( ) Beta Source #: Radionuclide(s): Beta Activity: DPH On Date: Source Placement: Cas/ Flow (cc/ min):
.1. PLATEAU DETERMINATION
- Upper Arm Detector -
Average High Gross Detector Ne t Voltage CPM Backaround CPM l
,00 50 O ..N00
( :.[50
.s00 350
.400 HV Set:
T50 HV 50% Plateau
,500 Countrate:
- 550 50% Net CPM:
.600
- .650
,700
- .750
.500 B-G THLD Roset (Value):
mV - B-G THLD Reset On All But Foot Detector: ( ) Plateaus Verified: .( ) 5. r b Page 2 of 3 HNP-8161 R03 .
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. J FIGURE 1
- 'Page . 2.o f - 3
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( l DATA PACKAGE 1 (CONT) l l II. SET-UP CALIBRATION Source f: Radionuclides: Activity: DPM On Date: . Decay Corrected Activity: DPM ZONE / CHANNEL ZONE / CHANNEL CPM BACKGROUND NET CPM EFFICIENCY Zone L Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Zone 7 . Ione 8 Feed loper Are Foraara Pate Th th Ca:.f Average X -- " - r f]g
\ Foot (contact) i III. MODE 3 PARAMETER DETERMINATION Detector Overall Efficiency: -EFF Instrument Thax: seconds cpa Instrument Re:
- Fage 3 of 3 HNF-8161 R03
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r- , e a==va E. l. Hatch Nuclear Plant aaxt=ae~o HNP. 8161 See Title Page asvisio= ~o 3
- o. . Georgia Power A a.e. ~o See Title Page 20 of 22 O h PROCEDURE DATA PACKAGE DOCUMENT NO: HNP-8161-2 ,
SERIAL NO: R03-MPL NO: RTYPE: G15.14 XREF: TOTAL SHEETS: 3 FREQUENCY: 'Weekiv l CMPLOTED BY: DATE COMPLETED: I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HNP-830. ACCEPTABLE UNACCEPTABLE REVIEWED BY: DATE REVIEWED: i REMARKS: 1; Page 1 of 3
- . .NNP-8161 nos D
l V - FIGURE 2 Page 1 of.3- -
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.... GeorgiaPower A a.- o .
See Title Page 21 o f 22 DATA PACKAGE 2 PCM-1 WEEKLY CALIBRATION CHECK Location: MPLf: Serial #: , Completed By: Date: Mode: 1 2 3 (Circle one) SIGMA Factor : Weighting Factor: . Count Time (Mode 1 or 2): seconds Source #: Radionuclides: Ar.tivity is DPM, On Date: Decay Corrected Activity: DPM ^ (Mode 1 or 3) i (Mode Z) Inw count ZONE / CHANNEL ALARM SETTING CPM MAX ALARM LIMIT FAIL SETPOINT Zone L Zone 2 Zone 3 Zone 4 (' Zone 5
\- Zone 6 Zone 7 Zone 5
, Feed Iloper Are Foreara
ala Th th Ca;.f Foot
{. v J Page 2 of 3 o HNP-8161 R03 I )
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FIGURE 2 Page 2 of 3
I aaa m va' E. I. Hatch Nuclear Picnt aaoaouae ~o H N P- 816L ] See Title Page aevisio= ~o 3 c: o.m Georgia Power d .. See Title Page 22 of 22 O DATA PACKAGE 2 (CONT) PCM-1 WEEKLY CALIBRATION CHECK CPM E ZONE / CHANNEL NET WEEKLY ZONE / CHANNEL 3" BACKGROUND CPM EFFICIENC1 l Zone 1 = Zone Z = - Zone 3
- Zone 4
- Zone 5
- Zone 6
- Zone 7 =
Tone 8 * ,
-ead
- oper Are *
'oreare *
'a:,a =
W sh a Ga..f " Joot(Contact) == - Cas Pressures: 1. PSI Regulator - A cc/ min Flow ,
- 2. PSI Regulator - B cc/ min Flow ,
-C cc/ min Flow l Overall Monitor Efficiency: cpe/dpa
- Average Set-Up Efficiency: cpe/dpa
\ ** Foot Detector Set-Up Efficiency: cps /dpa hax (Mode 3): seconds Rg (Mode 3): cpa Revised Max and Rg Entered in Instrument ( )
Remarks:
- Weekly Efficiency must'be within i 20% of Average Set-Up Efficiency I
** Weekly Efficiency must be within + 20% of Set-Up Effelency l-t
-Fase 3 of 3 WP-4161> R03 FIGURE 2 1 O~.(> Page _3 of : 3
( AI i
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT rN k PROCEDURE Waste Classification and Manifest Reporting Resin Shi E ments PROCEDURE TITLE HNP-8036 PROCEDURE NUMBER Lab - - - RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
/' PROVED APPROVED DESCRIPTION DEPT. GENERAL ~DATE REV.
MANAGER MA ER O New Procedure ,
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7 - 5 PROCEDURE REVISION REQUEST PROCEDURE NO. HNP- 'N' SHEET 1 0F 3 E CURRENT REVISION NO. / REQUESTED BY : U/t a t/t 4 Nt7 _ N /d4/$ '~
,j SICNATUREg DATE ,.
5 DEPAF.TMENT MANAGER APPROVAL :k dld 3 LMI N b /0/ 24/ 8y e @' f)Mr- - [//4) / SIGNATURE DATE I~ PRESENT STATUS : ( /) SAFETY RELATED ; ( ) NON-SAFETY RELATED THE ABOVE SAFETY /NON-SAFETY STATUS HAS CHANGED: ( ) YES; TO LIST ANY APPLICABLE QA TRACER NUMBER's : 8Y-/W W 8W857 # T7'87$ , IF QA TRACER IS APPLICABLE, INDICATE REVIEW BY REG. COMP. : io-A b a4-MARKED-UP COPY OF CURRENT PROCEDURE Elf,T,BE ATTACHED TO THIS FORM!
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c( McTW Q l PRB RECOMMENDS APPROVAL: ( d YES ; ( ) NO Nst NWa4 I _ 5 PRB SECRETARY'n SIG9ATURE P9B NUMBER : Ib M# ; DATE : / 4-/.Wd HNP - 9 p.rt 2-y h N I
f . SHEET 2_ 3 0F SAFETY EVALUATION O TYPE OF DOCTIENT TO WHICH THIS EVA!.UATION APPLIES . ( ) NEW PROCEDURE ( v') PROCEDURE REVISION DOES THIS DOC & LENT CHANGE THE MODE OF OPERATION OR INTENT AS DESCRIBED IN THE FSAR? () YES ; ( v) NO DOCTIENT INWLVES : ( ) AN UhREVITED SAFETY QUESTION , ( ) TECH. SPECS. , ( NEITHER IF A DOCR NO. TECH. SPECS. REVISION IS INVOLVED RECORD THE ASSOCIATED DOCR N11BER BEIDW: DOES THE IMPLDIENTATION OF THIS DOC &!ENT REPRESENT AN UNREVIEWED SAFETY QUESTION T - - 1 'TN- ~ ; (M 'NO GIVE THE BASIS FOR THE Dt.rt.@11 NATION OF WHETHER OR TOT THE . IMPLEMENTATION OF THIS DOCGIENT REPRESENTS AN UNREVIEWED SAFETY : QUESTI
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, OF __ Is SAFETY EVALUATION (CONTINUED)
THE IMPLTMENTATION OF THIS DOCUMENT 09995 / DOES NOT) CONSTITUTE AN UNREVIE%ED SAFETY QUESTION AS EXPLAINED BELOW:
- 1. THE PROBABILITY OF OCCURRENCE OR THE CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY (ARG- / ARE NOT) IN' CREASED ABOVE THOSE PREVIOUSLY ANALY2ED IN THE FSAR DUE TO THE IMPLEMENTATION OF THIS DOCUMENT BECAUSE: .M. ,
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pff[,, r v i L f' C. ? I j 3. THE MARCIN OF SAFETY AS DEFI!3D IN THE BASIS FOR ANY TECHNICAL ! SPECIFICATION (46-/ IS NOT) REDUCED DUE TO THE IMPLEMENTATION OF THIS DOCUMENT BECAUSE: f f ? ni< [ S ,.. h ',._ l 0 -/,. / n. A ,.. . M a d v v . h A;u.' E ._ n , t .-ln <i ,A.< b h u h l,,.. A u ,
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l i SAFETY EVALUATION PERFORMED BY: I N' r k' 'h N Y /M / ,Y SIGNATURE DATE n DEPARTMENT MANAGER APPROVAL : Y Lt3 Fatb444#u- e/29eR4 DATE
/ SIGNATURE ~
HNP - 9 REV 25 i
'. t, 2em E. l. Httch Nuclear Picnt acs== ~o HNP.8036 Sao Title Page .. .se= ~o See Title Page Georgia Power d ..e.~o 1 of 10 [ 0 WASTE CLASSIFICATION AND MANIFEST REPORTING RESIN SHIPMENTS A. PURPOSE To detail the steps necessary to classify radioactive waste resin shipments in accordance with the requiremants of 10 CFR 61.55 and to identify manifest reporting requirements in accordance with 10 CFR 20.311. B. REFEHENCEG
- 1. 10 CFR 20, Standards for Protection Against Radiation.
- 2. 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste. ,
- 3. HNP-8016 Shipment of Radioactive Material.
C. SAFETY , },- Observe radiation protection procedures. , O
.Q D. DEFINITIONS
- 1. TRU - Alpha emitting transuranic nuclides with half-lives
. greater than 5 yr. (in particular - Pu-238, Pu-239, Pu-240, Am-241, Pu-242, Cm-243 and CM-244).
- 2. Principle gamma emitters - any radionuclide of plant origin identified by gamma spectroscopy and contributing > 1% of the total identifiable gamma activity for the waste under consideration.
E. PRECAUTIONS , If the shipment includes multiple containers with differing waste composition,' separate analysis for each different type waste should*be performed. A single analysis may be used for multiple containers of the same-type waste provided the container composition (i.e., radionucIlde distribution) is considered the. same. F. QATA SHggT 1 GJIDANCE
- 1. Obtain results of gamma spectrum analysis of the resin sample for the resin shipment that has been' collected and analyzed per Procedure HNP-8016.
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*=cm E. l. Hatch Nuclear Plant =ou= ~o HNP.8036 Sao Title Pags nwsio~ ~o om Georgia Power A . . . ~o See Title Page 2 of 10 0 2. Enter the sample identification information and the results of the gamma spectrum analysis on Data Package 1, Data Sheet
- 1. Record the measured concentration for each principal gamma emitter in the designated entries in Column #1 and
#2. The blank entries in Column #1 may be used to record radionuclides that are identified but not specifically listed.
- 3. Total the radionuclide concentration for Column #1 and #2 entries to determine Subtotals #1 and #2.
- 4. Using the entries under Column #3, calculate the concentrations of the correlated radionuclides. Multiply the previously determined concentration of the scaling radionuclide, as listed, by the scaling factor (SF); the product is the correlated radionuclide concentration.
E Generic scaling nuclides and generic resin i scaling factors (SF) have been included in j , the Column #3 and #4 entries. If other than ' generic scaling nuclides or SF are to be used, - cross through the generic value and insert O the appropriate value. The Lab Supervisor (or designated alternate) will determine if other than the generic values should be used. H-3 and C-14 are not correlated to any other radionuclides. The concentrations listed under Column #3 for these nuclides are conservative, generic values. Technical bases for selection of scaling factors (if other than the generic resin values) shall be' documented on Data Package 1 (or by an accompanying attachment). M The generic scaling factors will normally be
, updated yearly or once every'two years as ap-propriate for the particular type of weste and activity levels.
- 5. ' Bimilarly for Column #4,. calculate the correlated concentration of TRU,'Pu-241 and Cm-242, as indicated, by multiplying the measured Cs-137 concentration by the designated-scaling factor (SF). These correlat .
concentratigns shall be multiplied by 1.25 X'10gd to convert from uCi/cm to nCA/g'(based on a dowatered resin density'of - 0.5 g/cm4 ) for use in comparison with the weste () classification limits cui Data Package 1. . 9M' Y
. caaam E. l. Hitch Nucicar PI:nt ax = = u ~o HNP- 8036 Sso Title Page " a"3* *o
- Georgia Power ..m.o See Title Pace 3 of 10 l )
V G. Calculate Subtotal #3 by adding the Column #3 entries, Subtotal #4 by adding the Column #4 entries.
- 7. Determine the total radionuclide concentration (GRAND TOTAL) by summing Subtotals #1, #2, #3 and #4.
- 8. For each nuclide as identified or correlated above, determine its fractional abundance by dividing its . o concentration (uCi/cm 3 ) by the GRAND TOTAL. The quotient is the fractional abundance for the nuclide.
- 9. Determine the TOTAL MILLICURIES (total activity, in millicuries, of the shipment) by multiplying the GRAND TOTAL concentration by the volume of the waste (which may be less than the container size but in no case larger) and a conversion factor of 28.3 (cm 3 /ft 3
- mci /uCi).
- 10. Similarly, determine the total activity (millicuries) of the shipment for the nuclides H-3, C-14, Tc-99 and I-129.
(Total activity of these radionuclides must be included on the shipping manifest). , G. DATA T>EET 2 GUIDANCE . f i 1. Transfer the radionuclide concentrations for Data Package 1 for each radionuclide or radionuclide grouping to appropriate entries on Data Package 1, Data Sheet 2.
- 2. The concentrations (and corresponding limits) for all nuclides are expressed as uC1/cm 3, except for TRU, Pu-241 and Cm-242 for which the units are nCi/g. Therefore, the concentrations for TRU, Pu-241 and Cm-242 that should be used are those under the heading Conc. (nCi/g) from Data Package 1.
- 3. Perform the required calculations to determine waste class.
After dividing each radionuclide concentration by the 10 CFR 61 limit (as included on Data Package 1), determine the " sum of fractions" for each column.
- 4.
- Waste class is determined per the guidance included on Data Package 1.
- 5. Enter the WASTE CLASS; sign and date Data Package 1.
- 6. Provide completed Data Package 1 to the Lab Foreman (or designated alternate).
- 7. The Lab Foreman (or designated alternate) will review the calculations and waste class determination of Data Package
- 1. If satisfactory, the Lab Foreman (or designated alternate) will sign and date the data sheets.
4
. -mm E. l. Hctch Nuclocr Plent *u== ~o HNP- 803G See Title Page
..,, Georgia Power .. -
Gee Title Page 4 of 10
- 8. The Lab Foreman (or designated alternate) shall complete Data Package 1, Data Sheet 3, GA/GC Check List. A "N/A" entry shall be recorded for any i tem of Data Sheet 3 that is not applicable to the type waste being evaluated. Any designated "No" response shall be explained on the data sheet (or by an accompanying attachment).
- 9. The completed data sheets shall be provided to the Lab . *.
Supervisor (or desingated alternate) for review. The Lab Supervisor (or designated alternate) will sign and date Data Sheet 3, GA/GC Check List.
- 10. All completed Data Sheets 1, 2, and 3 shall be included in the station records for the waste shipment.
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HNP.8036 See Title Page amso= ~o
.... Georgia Power d ..mo See Title Page 5 of 10 O
U PROCEDURE DATA PACHACE DOCUMENT NO: lW-80%-1 RO2- *- SERIAL NO: PFL NO: RTYPE: C15.14 XREF: TOTAL
- GFEETS: 6 FREQUENCY:
2 COPPLETED BY: :) . - DATE COPPLETED: O V I HAVE REVIEWED THIG DATA PACHACE FCII COPPLETOESS APC AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH FDP-830. ACCEPTABLE LNACCEPTABLE REVIEWED BY! DATE REVIEWED: REMARHG: s,. Page 1 of 6 HPr-so m Roa j h. FIGlJtE 1
. Page 1 of 6
^^
- - - . - . - _ . .-.- __ - i
. -ao* E. I. Hctch Nucl:ar Plcnt =cnuu ~o HNP. 8036 See Title Page at*$** *
=
o.,c Georgia Power A ..- ~o See Title Page 6 of 10 s DATA PAQM__AQg_1 QeLA_SL{GI_1 WAGTC CLACGIFICATION - RESIN Sample Identification: Shipment #: Type Weste: Technician: " Volume of Shipment: ft Date: CAMMA SPECTRLN ANALYSIS RADIONUCLIDES Column #1 Column #2 Radionuclides with T 1/2 45 yr. 10 CFR 61 Nuclides Fractional Conc. Fractional Conc.3 _iyCl/cm ) Abundaneg. luc 1/cm3 ) .3bundance. Cr-51 Co-60 Mn-54 Cs-137 Fe -5') . Co-58 Subtotal ! In-65 . #2 A . Cs-134 _ Co-144 , e [m)' ( ,/
- Subtotal
#1 CALCtLATICN OF CORRELATED RADICMJCLIDES Column #3 Fractional Conc.8 (uci/cm ) A MDjente H-3 = = 4E-04 C 14 = = SE-04 Ni-63 = (Co-60)
- 4E-02 (F) =~
- Sr-90 = (Cs.137)
- EE-03 (SF) =
Tc-93 = (Cs-137)
- 1E-04 (DF) =
. 1-129 = (Cs-137) 0 1E-05 (SF) = _ _ , , _
Subtotal #3 =
, o Page 2 of 6
,. Per-soas noe FIGLEtE 1 Page a of G i.
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- ao= E. l. H:,tch Nuclocr Plent **ciour= ~o HNP.8036 See Title Page a- 'o= ~o
.. : Georgia Power d a.- ~o See Title Page 7 of 10 O
DATA PACKACC 1 (CONT) DATA GHECT 1 (CONT 1 WASTC CLAGGIFICATION - RCUIN CALCULATION OF CORRELATCD RADIONUCLIDES (CONT) Column #4 ,,
- Conversion = Conc. Fractional Cone.
igCi/cm 3) Factor (nC1/c) Abundance _ TRU =. _' 2E-04 =
- 1.25 10' =
(Cs-137) (GF) 3 Pu-241= _.
- CE-03 =
- 1.25 10 =
(Cs-137) (SF) Cm-242*
- 7E-05 =
- 1.25 s 10 =
(Cs-137) (GF) Subtotal #4 = DETERMINATION OF TOTAL ACTIVITY , grate TOTAL = + + + = uCi/cm 8 $ * (Subtot (Subtot (Subtot LGubtot 3
#1) #2) #3) #4) ,
TOTAL h / MILLICURIES = CRAf0 TOTAL uCi/cm3* ftI (vol. of weste)
- ES.3 = mci Total H-3 -= 4E-04 uC1/cm3* ft3 (vol. of waste)
- 25.3 = mci Total C-14 = SE-04 uC1/cm3* ft3 (vol. of waste)
- 28.3 = mci Total Tc-99 = uC1/cm3* - fta (vol. of waste)
- 28.3 = mct Total T-129 = uC1/cmI* ft3 (vol. of waste)
- 28.3 = mci Page 3 of 6 HPP-903E R02
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J "Page 3 of 6 W.
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6
'"ao* E. l. Httch Nuclcar Plant noce== No HNP. 8036 See Title Page nws,o,. o o.m Georgia Power d ..e No l See Title Page a op to k
DATA PACKAGE M CONT) QATA QL{gLa WAGTE CLASSIF ! CATION WQRMSHECT
..... . ...... .S. P OF "aCI19JIL:.19.GS.5LIeets..t LI'.!!.I.3.. -
g m its et Nu
...ct6de -4 Ente
.C.......
lass A .......... ..... Ctese.c .............
.....r..I uC6/cm e 0.e = 6 e.O =
c .te99 uC&/ce' 4 0.3
- 6 3.0
- Ts.129 1 uC t /cm3 0 0.00s
- e 0.0e
- 10.0 = 1 100.0
- TRU til/2 )$ yet pC6/g t Pu-248 nC4/g i MO.0
- t 3500.
- t a000. a e er e 04 a Co-a.a nCa/s 4: ; l- unaceeetens sum
- re.<ttens l= e., e. ..n 6
-3RLF GeGIlggl.:.19 .
CFR 61. Ige (C.g LIME -. , . - I Units e# Clas Mus
..l.i.de... .
Entry Class A
................. . ........C.la.se
. ..... e _ . ..............s ..C. .....
4 700.o
- N/A N/A r Total uC4/cm '*
478/d($ yet M/A P4/4 De- 3 uC6/cm 3 5 40.o * , N/A uC4/re' 4 700.0
- N/A Co-40 4 70.0
- 6 700 e a N6 43 uC6/cm1 6 3. s
- uC4/ce' e 0.04 e e 150.0 e 9 7000. e .
Sr.90 44.0 e t 4400. e . Co.877 uC 8 / cmI t 8.0 e t (m m ese et Feastaene l= . [* ; [* un... t .. e , o.es.: The waste classification is determined by the highest class for eehich' the " sum of fractions
- does not exceed 1.
If the ' sum of fractions
- for Table 1, Class A <1, weste class is determined by highest column of Table 2 with " sum of fraction' (.1.
If " sum of f raction" of Table 1, Class A is > 1 but Class C < 1, waste is Class C, provided Table 2, Class C
- sum of f raction" < 1.
1 If " sum of f ractions" of Table 1, Class C > 1 or if " sum of f raction* of Table 2, Class C > 1, waste not suitable for burial.
' Units for all nuclides are uCi/cm 3 except for TRU,' Pu-241 and Cm-242 for which the units are nC1/g.
WASTE CLASS: Technician Date: Lab Foreman: Dates Page 4 of G HNP-SO36 ROE
\
FIGLJtE 1
, Page 4 of 6 ;y posses O
* ""*^' E. l. Hatch Nuclear Plant aociouas ~o HNP.8036
- See Title Page asesiou o om GeorgiaPower A a.. .
See Title Page 9 of 10 DATA PACHACE 1 (CCNT) DATA 9EET 3 4 WASTE CLASSIFICATI(74 AfC MANIFEST REPCRTING l Weste Class Shipment #* 4 s. j YES lE
- 1. Has waste been properly classified? Data Sheet 1 l ___ ___
(and Data Sheet 2, if applicable) completed?
- 2. Has waste container been labeled CLASS A, CLASS B, or CLASS C?
Weste Stettility Characteristics l YES CG f 1. Has proper waste container been selected (Class A - carbon steel, Class B or C - HIC)?
- 2. If HIC used, has User Checklist been completed? 4
- 3. Confirm proper dewatering of resins ( < 11 water). -j .
- 4. Have void spaces been reduced to estent practical? .
19 5 i For shipments to Richland, the site criteria prohibits rece,ipt of waste containing transuranics in excess of 10 nCl/g with-out special approval by Washington state. Page 5 of 6 we-soas not. m . t s ) .' v FIGURE 1 Page 5 of 6 L _. 2
t. a = ova' E. l. Hatch Nuclear Plant aoceouae ~o HNP- 8036 See Title Page aevisio~ ~o o.m Georgia Power d ... o See Title Page 10 of 10 DATA PACliME_1_iqQ[jIl QATA SFEET _3 (CONT ) WASTE CLASS 1F_1 CATION ATO MANIFEST REPORTING t!*niin1_!!sagr_11ns
. 5 XEG CA .
- 1. Have the total millicurie quantities of H-3, C-14, Tc-99 and 1-129 been determined and included on Manifest?
- 2. Have a_11 princspal gamma emitters and gli correlated radionuclides been included on mansfest? Barnwell site criteria require reporting correlated abundances of TRU, Pu-241 and Cm-242.
- 3. Ensure accounting for at least 99% of total activity by individual radionuclide identification.
- 4. Confirm identificatisn of Waste Class.
't;
- 5. Ensure correct physical description of waste.
- 6. Confirm total volume of waste (same as used for '*
determining millicurie content; if different explain below). v __ __
- 7. Confirm correct chemical form.
___ - 8 . ConfirIn exclusion of chelating agents (if > 0.1%, chelating agents must be identified). Lab Foreman: Date: Lab Supervisor: Date: Page.6 of 6 w -soas Ro2 ( . x_/ FIGLRE 1 Page 6-of 6
- seeeee .
.=.
GEORGIA POWER COMPANY 9 HATCH NUCLEAR PLANT
- PROCEDURE Mini-Scaler Model MS-2 PROCEDURE TITLE M43-8106 PROCEDURE NUMBER Lab . ..
RESPONSI LE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. GE!ERAL DATE MANAGER MANAGER
' pas 6 Pages 1-5 and 7 g 9- .
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l 7;y'e-:- PuSENT STATUS : ( SAFETY HLATED ; ( ) NON-SAFETY REL&EEF F i THE ABOVE STATUS IS BEING CHANCED: ( ) MS , TO ,
; (4#[ NO M!A ONLY)
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@ TRAINING REQUInnenrTS (PoR ADu1NISTRATIVE PROCEDURES
@ DEPARTMENT MANAGER ENDORSEMENT : I/ 3/If !
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PROCEDURE REVISION REQUEST (CONTINUATION SHEET) HNP - 8 i O lo SHEET b of .#) hPROCEDURENO. . REVISION NUMBER OF. CURRENT PROCEDURE : 5
- ai F 5 y : % e.le.+e sec.p, o n so < u s' nq
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i i A O: - Y . t. A. O PROCE9URE NO. : HNP - 'I I D .,,, SHEET _N of b _ REVISION NUMSER OF CURRENT PROCEDURE : _D (N/A IF FOR NEW PROCEDURE ) PROCEDURE TITLE : O' ' 8 *- > U a ! s'-v ' Ik I b l' I ll 6 - 1 TYPE OF DOCUMENT TO WHICH THIS EVALUATION APPLIES : ( ) NEW PROCEDURE c. ( v) PROCEDURE REVISION 1 DOES THIS DOCUMENT CHANGE THE MODE OF OPERATION OR INTENT AS AESCRIBRD IN THE FSARf ( ) YES ; ( p[ NO DOCUMENT : ( ) INVOLVES AN UNREVIEWED SAFETY QUEETION ( ) REQUIRES A TECH. SPECS. CHANGE BEFORE THE DOCUMENT CAN BE V8 ; y } IF SO, RECORD THE ASSOCIATED DoCR NUMBER :
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( <) NEITHER i I
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k { } hDOESTHEIMPLEMENTATIONOFTHISDOCUMENTREPRKSENTAMUNREVI.EWEDSAFETY ( ) YES ; (v) NO l QUESTIONf 1 GIVE THE BASIS FOR THE DETERMINATION OF W'1 ETHER OR NOT THE IMPLEMENTATION OF THIS DOCUMENT REFRESENTS AN UNREVIEWED SAFETY QUESTION : Yt Yf d, 5 '. o r3 Ck ih '. 5 doc 4 n 1 t. ) h t{ees po{ n'e Ae %-)E
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S A FETY EVA LUA TION ! (CONTINUED) l PROCEDURE NO. HNF - bIL'b SHEET '$ of *> L
, REVISION NUMBER OF CURRENT FROCEDURE : b (N/A IF FOR NEW PROCEDURE )
CONSTITUTE AN UNRIVIEWED h THE IMPLEMENTATION OF THIS DOCUMENT (DOES / DOES NOT) SAFETY QUESTION AS EXPLAINED BELOW:
- 1. THE PROBABILITY OF OCCURRFNCE AND THE CONSEQUENCES OF nN ACCIDENT OR _ ,_
MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY (ARE / ARE NOT) INCREASED ABOVE THOSE ANALYZED IN THE FSAR DUE TO THE IMPLEMENTATION OF THIS DOCUMENT BECAUSE: Th . s rc.o'. s : o n only p ro u'. d e,s a_ c.h o ne '. n the s m < t h ed. o 't p res eni'. no the_ c.h'. - 59uon Ata a.n d ha'.II : Ilol ' ntit45+ a }ht pecbwb'i l'. tv of M ~4 c e.' cl e n 6 o v- $ d.lfun4'op l Ok Eq t/. p en e n t '. m povh n+ to sc4<.Tv. J- 1 I . 7 -l 2. THE POSSIBILITY OF AN ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE THAN; ANALYZED IN THE FSAR (DOES / DOES NOT) RESULT FROM THE IMPLEMENTATION'8F* Y. 5 Pe v'. S'. o o Only Prowe'de d e_l <[. O n _ Fi-l oi o qrc eh by e.n w'. no. cic_t
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- 3. THE MARGIN OF SAFETY AS DEFINED IN TECHNICAL SPECIFICATIONS (IS / IS NOT)_
REDUCED DUE TO THE IMPLEMEMTATION OF THIS DOCUMENT BECAUSE:
. ' T he rt.v'.s'. o n onI V i n v o l u e.s de_IttIon of a 4 r c.ph 1
Cnd.S Mo n .*.to rt.d bo Curre.nf. ~Pic.d'.ef! o 7 3 roft. d o n 3ro t' e el ure k. ; l l h SAFETY EVALUATION PERFORMED : BY '$.in1%I h 31 / .2 I / 8 'l l
- M / /
h SAFETY EVALUATION REVIEWED BY s DE, - _ E A., _ . AW A . , .
, , s , sc !
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. amom E. l. Hatch Nuclear Plant aaoce=as ~o HNP- 8106 Sao Title Page aemio~ ~o GeorgiaPower A .. , ~ o 6 I See Title Pace 1 op 9 MINI-SCALER MODEL MS-2 A. Pt.RPOSE
-To ensure that the instrument is calibrated properly and to provide operation guides for the user.
B. FREQUENCY . ..
- 1. Daily Chi Square check
- 2. Guarterly Calibration C. REFERENCE Mini-Scaler Model MS-2 technical manual. TDC #0524M D. SAFETY Observe radiation protection procedures. g i
l E. . DESCRIPTION OF INSTRUPENT U I The Mini-scaler system consists of a variable high voltage supply, charge sensitive input amplifier, single. channel pulse height analyzer, six decade scaler, and timer. It is designed for practically any scintillation, Geiger Mueller, or propcrtional detector and_can be powered by either 110 VAC or. 7.5-14 VDC. F. DESCRIPTION OF CONTROLS AfO CONhECTORS
- 1. External
- a. : Detector - Connection to detector P9IV series coaxial.
i'
- b. H.V. Adjust'- Ten turn calibrated dial for settin'g and-i changing high voltage.
- c. Threshold - Ten turn calibrated dial for.-setting and changing baseline sensitivity.
d.: , Window. ' Ten turn calibrated dial for. setting and-changing range of: pulse heights to be counted.. l: l
- e. :In - Out SwitcK.-' Switch to select gross countingz (OUT) or PHA-(IN). .
f.. Test---Switch to' insert test signal:~1nto. scaler.
.~/fR
( -s -. 7C ,,. ._s -,;,
- . . , * , ;4
- yeesee .
-- m .
. ^~aova' E. l. Hatch Nuclear Plant aaoa mas ~o H N P- 8106 See Title Page aEvmon e 6
Georgia Power d l- o.m See Title Pace 2 of 9 i g. Timed - Stop - Man - Switch to select counting mode.
, b. Reset - Start Switch to reset all appropriate circuitry to zero and start a counting i - sequence.
- i. Count Time In Minutes - Switches to select desired counting time - o
- j. Power - Switch to supply power to instrument. (Rear Panel)
- k. Battery - Connector for plugging in external battery.
(Rear Panel)
- 2. Internal
- a. Gain (Amplifier Board) - Control for adjusting gain of amplifier.
1 ~. i b. Time (Timer Board)- Control to calibrate time base when operating with external batn r'y .
- c. Rate Meter Calibration (Rate Meter Board)-Contro s'to calibrate
- meter reading
- G. OPERATION OF INSTRUPENT l NQTE
' Two MS-2 instruments will'normally be connected to-an FF210 probe (G.M.) mounted on a shielded sample holder. The other MS-2 will be connected to a gas flow propor-I :tional detector mounted in a sample holder _and_will be- l. calibrated for-alpha counting. 1.. 'Be sure that the instrument-calibration is current. l
- 2. Turn Power-Switch to ON. ]
3. Position Timed - Stop - Man switch to counting mode desired. 1
- 4. Position Count Time In Minutes' switches to_ counting: time; 'l.
- desired.
- 5. ' Press Reset--Start switch ; and release. -Instrument sh'ould i L begin counting.-
-M _
U e 1
. ==$va E. l. Hatch Nuclear Plant a=ct=ae ~o HNP- 8106 See Title Page aavisio~ ~o om Georgia Power A .. . e See Title Page 3 of 9 O 6. Daily Calibration l
- a. Set Test Switch to DN.
- b. Set Timed-Stop-Pun. Switch to MAN. Units should begin to count. Record results in Man. CK column of Data Sheet 1.
t
- c. Set Timed-Stop-Man switch to TIMED.
- d. Set Count Time In Minutes switches to 1 and X1. Press Start-Reset switch and release. . Units should stop counting after 60 seconds, registering 3580-3600 counts. Record on Data Sheet 1.
- e. Turn Test switch to DFF.
- f. Perform a 10 minute background count and record the background counts in C.P.M. on Data Sheet 1.
-i 1
- g. Place a radioactive standard in position.for counting and count for 5 minutes.. Record results on DatM Sheet-1 in C.P.M. . 'l M
For instruments with Geiger-Mueller detector use Tc-99m beta source ( of 104 dpm) centered in a S.S. planchet. For instrument with gas flow proportional detector, a Pu239 alpha source ( c: lO4 dpm) . centered in a S.S. qg , planchet and placed.on top counting shelf.
- h. The reading should be within 1 3 sigma of the-source's -
known count rate. M If count rate is greater than or less than i 3 sigma for three consecutive counts, then a new Chi-Square Test must be performed. Record.the results by entering "M" or "!g" in the 1.3 sigma column of Data Package 1:(Data Sheet.1).. i.. Calculate the counter efficiency:and record on Data l
! Sheet 1.
Net C.P.M. efficiency = D.P.M.' X 100 0 - a
~
. ....o m h. l. Hatch Nuclear Plant aaxt=A H N P- 8106 aEv4 CN W See Title Page g 6
- m. Georgia Power sA ..e. ~e See Title Pace 4 of 9 O H. CALIBRATION OF INSTRUPENT
- 1. GM Detectors
- a. Adjust H.V. Adjust to operation voltage of the detector being used. Refer to technical manual Figure 2-3.
CAUTION . ,. Do not over-voltage the GM tube. (900 volts)
- b. Connect detector, i c. Set Threshold to 10.00.
- d. Set Window In-Out switch to OUT.
- e. Push Start-Reset switch and expose detector to a check source.
- 2. Scintillation detectors - gross counting smears. ,
- a. Connect detector. ^-
i () b. c. Set Threshold to 5.00 and Window In-out Switch to OUT. With the detector exposed to a. radiation source'of the isotope to be counted, run a plateau of. counts vs. High Voltage setting (See Figure 2-4 of technical manual).
- d. Remove radiation source and repeat step H.2.c for l background.
- e. Set H.V. Adjust to a point on the plateau within the first one third of the. slope of the plateau..
- 3. , Scintillation detectors - Pulse height analysis,
- a. Turn H.V. Adjust to 0.OO and Window In-Out switch =to IN.
'b. Expose detector to a gamma field of known energy..
- c. Adjust. Threshold to the desired knob reading forithe~
energy being used.: ; J'4 d.- Set Window to 25%~of. Threshold.
- e. Plot a curve of-counts vs. Thigh voltage. (See' Figure [
5 of technical manual).' ',
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' a == E. l. Hatch Nuclear Plant *ce== ~o HNP- 8106 Sao Title Page unio = ~o om Georgia Power d ..e. .
See Title Pace 5 of 9 I
- f. Adjust H.V. Adjust for the peak reading.
- g. To optimize window width, plot several curves of counts '
vs. threshold with wider and narrower windows and i choose the one best suited. (See Figure 2-6 of
- technical manual). Adjust H.V. Adjust to obtain the maximum reading at the Threshold dial reading selected.
- 4. Proportional Detectors
- a. Set the Threshold control to 2.50 and the Window In-Out to DUT.
- b. Plot a curve of counts vs high voltage with the detector exposed to an alpha source (Pu-239)(See Figure 2-7 of technical manual).
- c. Remove the source from the instrument detector and plot a background curve. (See Figure 2-7 of technical manual). 3*
- d. Adjust H.V. Adjust.For a point on the plateau wikh'in ,
the first one third of the slope of the plateau.^- (See Figure 2-7 of technical manual). O 5. Chi-Square Test (Guarterly test)
- a. Perform a one minute background count and record the background counts in BMG CPM on Data Sheet 2.
- b. Place a radioactive standard in position for counting. -
Use the same standards which will be used in the daily calibration.
- c. Count the source for one minute duration twenty times and record net counts on Data Sheet 2.
'd. Calculate chi-square. _If results are between-7 and 35,
. the instrument should be functioning properly.
' e. _ Calculate 1er , 2cf , and 3cf error.
E
-The computer program CHI Square may.be used to determine Chi-Square data.
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. aa == E. I. Hatch Nuclear Plant aaouwaa ~o HNP- 8106 See Title Page o.,, Georgia Power ..- ~o See Title Paae 6 of 9 O
PROCEDL.RE DATA PACKAGE DOCt. PENT IC: HNP-8106-1 _ . .. SERIAL NO: RO6-19L NO: RTYPE: G15.14 XREF: TOTAL SHIETS: 2 I-FRE(EEICY Month 1y i CGPLETED BY ' DATE CGPLETED: I HAVE REVIEbED THIS DATA PACHACE FGt CGPLETEPESS APO AGAINST ACCEPTANCE CRITERIA IN ACCCRT,ANCE WITH HP-830.
' ACCEPTABLE LNACCEPTABLE REVIElED BY:-
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DATA SHEET 1 MS-2 DAILY CALIBRATION
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COPPLETED BY: .' . [mh $k V DATE COPPLETED: . 04 I HAVE REVIEWED THIS DATA PACKAGE FCR COPPLETE?ESS .!.
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PROCEDURE Geiaer Counter E-400 Ogeration and Calibration PROCEDURE TITLE HP-8107 PROCEDURE NUPEER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
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^~=va' E. l. Hatch Nuclear Plant aaououas~o i HNP- 8107 See Title Page aevision o ,
i 6 Georgia Power d O on See Title Paae
..e. e 1 of 6 l vb GEIGER COUNTER E-400 OPERATION AND CALIBRATION 4
i A. PURPOSE To establish a standard technique for operation and calibration of , the model E-400 geiger count'er.
- B. FREQUENCY
- 1. Operation of counters: As needed
- 2. Calibration of counters: Guarterly C. I REFERENCES
. 1. Geiger Counter Model E400 Technical Manual TDC #0540M, i 1
- 2. Eberline checkout procedures -j - g D. SAFETY g Observe radiation protection procedures.
4 E. TEST EGUIPPENT l-4 1.- Coaxial connection cable
'2.
IP-177B Detector or equivalent
- 3. Gamma source with mR/hr intensities of each' decade F. DESCRIPTION OF INSTRLPENT
- 1. .The E-400 is a portable,' battery-operated instrument used for the measurement of gamma and the detection of beta radiation. It has a geiger tube detector, and the count
. rate is read out by the Eberline Lin-Log presentation.,
- 2. - The range of the-scale'is O to 200 mR/hr calibrated to an appropriate gamma field. The scale has four_de. cades which-are 0.2, 2, 20, and 200 mR/hr-respectively. A battery check'.
position is also provided on.the scale.
- 3. -The battery pack uses five. standard D size batteries offany type. commercially available.
,~) G. DESCRIPTIQN OF CONTROLS
~
- 1. . External controis
- a. ' Switch - Three position switch turnsLinstrument W F,
- (31, or. Battery Check.
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aaaaova' E. l. Hatch Nuclear Plant aaxe=ae~o HNP- 8107 . Sse Title Page aevisio~ o f' m. See Title Page Georgia Power d .. . o 2 of 6
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- b. High Voltage Adjustment - Controls the magnitude of high voltage applied to the detector. Clockwise rotation increases voltage.
- c. Phone - For connection of headset, speaker, or external j scaler.
L d. Detector Connector - For connection to the detector. ! 2. Internal Controls
- a. Calibrction Controls - Four controls to adjust the meter reading to agree with gamma field intensity at
- detector.
- b. Sensitivity Control - 20 turn control mounted on P-202 card adjusts the input sensitivity.
H. OPERATION OF INSTRt. PENT ^2
.\ l 1.
Ensure that instrumt at calibration sticker is currenti -
- 2. To start instrument turn the switch to BATT. The lef5 pointer (Black) should read in the green area. Release the switch, and it will return to the ON position. If the black pointer did not read in the BATT OK area then tag the instrument out with a To Shop Tag.
- 3. Operation Check
- a. With the probe removed from.the check source the-background should be less than 0.5 mR/hr.
- b. Hold the Check Source against the sensitive portion of the detector and ensure that the instrument responds properly (i.e. within i 20% of expected reading of source). l
!EIE The position of the source will vary the instrument reading.
- 4. Read the pointer that is on scale.- The black pointer is read up to.2 mR/hr above-which it disappears from view and the red pointer is read. Fluctuation of the pointer is normal.
(s 5. -When using the earphones a click will be heard.for each .
\m ) event counted. Using a BK-1_ speaker, only one-half the number of events will be heard.
. , , _ _ _ _ _ _ , , _ &* A.J .amm J A ,,a a: m > - -e. a mJ. A .__.a. -- m .4-- _. - w - m a _a -
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** wva' E. I. Hatch Nuclear Plant **awae ~o HNP.8107 See Title Page aev+o= ~o oar. Georgia Power A ..m me See Title Page 3 of 6 1 6. When surveying a general area for gamma radiation with the HP-1778 Geiger-Muller Detector, the probe should be held j parallel to the source of radiation and at waist level. For i i beta detection, open the beta window and hold the detector l i as close as possible to the surface being surveyed. Now close the beta windaw and monitor the surface again. When l ! no significant difference is seen in the needle deflection i j with the beta window open and the beta window closed, the - i
! radiation should be' reported as gamma only. When
- significant differences are seen in the needle deflection
- with the beta window open and the beta window closed, beta
! radiation is present. For true beta dose rate, obtain an j RO-2A or RO-3A or equivalent type instrument. ! 7. To shut off the instrument, move the switch to the DFF i position. } I. GUARTERLY CALIBRATION OF INSTRt. PENT 1 . l, ! 1. Turn control switch to BATT position and ensure that 1:tur left pointer (Black) reads in the green area. If the? . pointer does not read in the green area the batteries'must ~ be replaced. ( 2. Place the detector with beta window closed, in a gamma field of about 0.15 mR/hr, 1.5 mR/hr, 15 mR/hr and 140 mR/hr successively and check readings. Record readings on Data Package 1 (the Instrument Calibration Data Sheet) in As . Found column.
- 3. If readings are not within i 20% of the. gamma field proceed to step I.S. .
- 4. If readings are within i 20% of field, turn switch OFF, complete Figure 1, replace the calibration sticker with a new one bearing the test date and when.the instrument is next due for its quarterly calibration.-
E { " Even-though the instrument is i 20%.of calibration points revery effort should be made.to make it read as'close as l possible to the calibration points. , i 5. Remove the instrument'from the case and= remove the High Voltage supply card f rom the - instrument. Connect ~a mini-pulser at-the spring connector (junction R8 and:C2) and set the mini-pulser for negative pulses at 10 millivolt amplitude. Adjust sensitivity ~ control. pot (located on
.g~)'
( P-202) for. optimum setting of 10 millivolts. Replace High Voltage supply card. l h _ . - s 'L -, .J- _ , - - _ _ . ~ - -
--. . . ._- . - . - . . - ~ - - - __ __ - -__- _ _ _ . . . -
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! nca E. l. Hatch Nuclear Plant aaoa = = ~o j HNP- 8107 . Sse Title Page nwsio= ~o f' om See Title Page Georgia Power A ..m ~e 4 of 6 l 6. Connect electrostatic voltmeter at spring connector and 2
' adjust high voltage to around 900 volts. Note electrostatic l voltmeter MPL number in the REMARKS section of the ,
! Instrument Calibration Data Sheet (Data Package 1). ! ! 7. Connect the detector cable to the High Voltage connector ! using either an EIC Model SK-1006 adapter or shielded clip. m i leads. Turn R3 and R5 to the maximum clockwise position. i 8. Place the detector in a gamma field of about .15 mR/hr and j turn R g until the instrument reading corresponds to 0.15 i
- 20% mR/hr and record on Data Package 1 (the Instrument ,
! Calibration Data Sheet) in the As Left column. ! 9. Place the detector in a gamma field of about 1.5 mR/hr and
-turn R3 down until the instrument reading corresponds.to i the actual dose rate i 20% mR/hr and record the reading.on Data Package 1 (the Instrument Calibration Data Sheet) in the As Left column. a l \-
j 10. Place the detector in a gamma field of about 15 mR/hN ahd l turn R4 until the reading corresponds to the actual dose
- rate i.20% mR/hr and record the reading on Data Package 1 1
O (the Instrument Calibration Data Sheet) in the As Left column. i .
- 11. Place the detector in a gamma field of about 140 mR/hr and turn Ry'until the reading: corresponds to the actual dose-rate i 20% mR/hr and record the reading on Data Package 1 (the Instrument Calibration Data Sheet) in the As Left column.
- 12. If'the instrument performs within i 20% of the gamma field readings, the calibration is complete. Turn instrument.0FF.
- 13. Remove the high voltage adapter, place the instrument-back
~in its case and proceed to step I.4. l.
- 14. If the instrument cannot be calibrated initiate repairs.
- 15. After repairs of instrument go to step-I.S.
l O w h'
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a = ova' E. l. Hatch Nuclear Piant aaociouas ao HNP- 8107 asvis.e,. ~o , Sao Title Page 6 I o.r. Georgia Power d ..os so See Title Pace 5 of 6 l PROCEDWE DATA PACKAGE DO'CtPENT NO: FeF-F107-1 SERIAL NO: R06-PFL NO: RTYPE: G15.14 XREF: TUTAL SHEETS: 2 i i
- - a FREGLENCY: Quaeter1y .
CCPPLETED BY: DATE CCDPLETED: I HAVE REVIE1ED THIS DATA PACKAGE FGt CDPPLETDESS AFO AGAINST ACCEPTANCE CRITERIA IN ACCGtDANCE WITH HP-830. ACCEPTABLE LNACCEPTABLE REVIDED BY: DATE REVIEWED: REMARMS: Page 1 of 2 M -8107 R06
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*aaaova E. I. Hatch Nuclear Plant aaxt= e ~o HNP- 8107
- See Title Page aevisio= ~o e om Georgia Power d ..oe ~o See Title Pace 6 of 6 DATA PACKAC Q INSTRLPENT CALIBRATION DATA SWET INSTRUPENT E-400 , LOCATION PFL NO.
INSTRUENT REAQI%S ACTUAL ACTUAL DATE: CALIO. CulkJT DOSE CALIB. gY: _ _ SOURCg RATE RATE AS FDLPO AS LEFT__ j Cs-137 N/A O.15 mR/hr mR/he mR/hr N/A 1.5 mR/hr mR/hr mR/hr N/A 15 mR/hr mR/hr mR/hk N/A 140 mR/hr udt/hr mR/hh - (
\
i H.V. Pruni StPPLY SENS. SET (CIRCLE HV. PS. ! ENS MAINT. PurmriED REMARMS ( ) Page 2 of 2 v/ M -8107 R06 FIGLRE 1 Page 2 of 2
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GEORGIA POWER COMPANY t HATCH NUCLEAR PLANT () PROCEDURE Radiation Monitor RM-14 Operation and Calibration PROCEDURE TITLE HNP-8114 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( ) ___---+-__---m__-----------..-___-----_--_-- . APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER -
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( d PROCEDURE REVISION 7W,
', DOES THIS DOCUMENT CHANGE THE MODE OF OPERATION OR INTENT AS) ESCRIBED IN THE FSAR? ( ) YES ; ( v7 NO DOCUMENT : ( ) INVOLVES AN UNREVIEVED SAFETY QUESTION
( ) REQUIRES A TECH. SPECS. CHANGE BEFORE THE DOCUMENT CAN BE USED;
, IF SO, RECORD THE ASSOCIATED DoCR NUMBER :
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-@ . SAFETY QUESTION AS EXPLAINED BELOW:
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1.3 ~i 1. THE PROBABILITY OF OCCURRENCE AND THE CONSEQUENCES OF AN ACCIDENT OR _ _ ,
,M- < MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY CARB- / ARE NOT) INCREASED
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I a == E. l. Hatch Nuclear Plant eaxt== ~o HNP 8114 See Title Page mvisios so om Georgia Power d .. so See Title Page 1 of 9 (6 h)
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RADIATION MONITOR RM-14 OPERATION AND CALIBRATION A. PURPOSE To establish a standard technique for operation and calibration of the Model RM-14 radiation monitor. B. FREGUENCY ,
- 1. Operation of counters: As needed
- 2. Calibration of counters: Semi Annual C. REFERENCES l
- 1. Radiation Monitor Model RM-14 Technical Manual
- 2. Minipulser Procedure HNP-8116
- 3. Eberline Checkout Procedures 3 D. SAFETY ,
() E. Observe radiation protection procedures. TEST EGUIPMENT - l
- 1. Minipulser with coaxial cable and capacitor with-rating greater than 1KV
- 2. RM-14 CS-137 Check Source l_
F. DESCRIPTION OC INSTRUMEbT l The RM-14 is a small, compact count rate. meter: operated by AC-power or a battery which is continuously trickle charged while the unit'is plugged into the A.C. line. Battery condition is checked by front panel centrol.
-The monitor is intended primarily for use.with a Geiger-Mueller-detector, but'with slight modifications, can be used~with' appropriate scintillation detectors.
-The instrument presents a' meter-reading of' counts-per-minute !
(CPM) in three linear. ranges. ..They are O.to500 CPM; O to 5000 CPM; O to 50,000 CPM. In areas having a ' very : high coun t - rate, it is possible to saturate-the instrument. For: example, as.the detector approaches the surface to be monitored,.the meter will ("N read full scaleJon the highest count rate. Then'as?the~ detector i) is moved still closer to the surface, the meter reading'may dro'p-off to zero. lA_ speaker. assembly with-volume. control'is-
~
.l-incorporated as part.of.the instrument.-
. -== E. l. Hatch Nuclear Plant aaou=at ~o l HNP 8114 l See Title Page aevisio~ ~o
- o. . Georgia Power A ..m ~e ,
See Title Page 2 of 9 The meter has an adjustable, high limit contact which will sound an alarm when the meter reading reaches the limit. G. DESCRIPTION OF CONTROLS - l
~1. External Controls
- a. Switch: The Power and Range Selector Switch is , ,,
contained in one assembly. Power is applied to the instrument any time the Selector Switch is in any position except OFF. The position of this switch also provides the meter multiplier function.
- b. Power Lamp: A power light is provided for positive indication that AC power is being applied to the instrument.
- c. Response Toggle Switch: A switch to set response' time either Fast or Slow for best compromise between speed and fluctuation for the particular usage. ,
i
- d. Reset Switch: The Reset Switch (push button typa)*is l used to bring the meter reading-to zero rapidly and to -
turn off the alarm. O
^~ / e' . Volume Control: A continuously variable control-is provided for the adjustment of the audio output. This control may vary the output from no audible cutput to a
.high level.
- f. Detector: Connection to detector. BNC series coaxial.
- g. Alarm Set: Controls-point on meter scale that alarm will actuate. Numbers 1 thru 5 correspond to whole increments on meter scale.
h.. A.C. Power Connector: AC Power Connector-is a Polarized Recessed Male Connector.
' i '. Recorder Connector: Connection.for external fifty microamp' recorder.
J.- Test On Switch: -The Test Ors Switch is=to ensure-that- -l the instrumentifunctions properly. When the instrument
.is put'on AC:and Test On' Switch'to ON, it should. read ~
3600 CPM on the meter face. L2. Internal Controls. f'-] E
- a. Calibration Controls: One control for:each range which
() individually calibrates that range'to' agree with input: count rate.- t-nm <
. = = < E. l. Hatch Nuclear Plant aaociouac ~o HNP 8114 See Title Page navisieu ~o om Georgia Power d ..m ~o See Title Page 3 of 9 O
O b. Alarm Set Calibrate: Control to set correlation between alarm set and meter reading at alarm point. H. OPERATION OF INSTRUMENT l NOTE If the Range Selector Switch must be on higher . . . . scale than X1 because of background, consideration must be given toward moving the instrument or shielding the detector to lower the background.
- 1. Check the instrument for physical damage.
- 2. Check instrument and ensure that the calibration due date has not expired.
- 3. Connect the proper detector to the detector connection.
- 4. Plug the AC power connector into 115V, 60Hz line and ;pnsure l that the AC ON light is on. '.
U -
- 5. Turn the switch to BATT position and ensure that the meter ' f indicates in the BATT OK area, if not recharge the
/~ \ instrument batteries.
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- 6. Establish the average background count rate.
- 7. Set the Range Selector Switch to the scale which will allow the alarm point to be set at the full scale value of that range. Set the alarm. point to approximately full scale l value for the range'the instrument is operating at, except as noted below.
NOTE. If the instrument.is located at a control point where it is being used for whole~ body frisking, or at exit doors, the ALARM point'should.be set at~100 i 20 CPM over-the background. count rate. 1B. Instrument Check. (Weekly during normal plant operation.
-Twice per week during1 refueling, maintenance and extended shutdowns)..
' ~ Use the-following steps with Data Package 2:
- a. Record instrument's. location and instrument's serial
. number on Data Package 2.
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- b. Establish the ba'kground c count rate and' record.
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* **== E. I. Hatch Nuclear Plant aaoa mae~o HNP 8114 See Title Page aav s o= ~a om GeorgiaPower A ..m ~o See Title Page 4 of 9 O o
- c. Turn range selector switch to BATT and ensure that the l meter reads within the BATT OK region. Turn range selector switch back to appropriate scale.
_ d. Place RM-14 monitor check source near detector and ], ensure that the alarm point is set approximately fullscale except as noted at H.7 for the range that the ; instrument is operating at. Adjust alarm set point, if ,. necessary, and. record a check under ALARM CHECK on Data Package 2.
- e. Operate the Reset Switch and observe that the meter reading drops off toward zero and that alarm turns off. Record indication under RESET CHECK on Data Package 2.
- f. Turn range selector to X100 range and response toggle switch to FAST response. Place the check source in contact with the detector face or window. Always place the source on the face where the webbing will haye the least effect on the count rate. i 7
- g. Ensure that the meter indication is approximately.'the ' [
value of.the background plus the value of the source i 73 20%. Record indication on Data Package 2. ( ) I. CALIBRATION OF INSTRUMENT (Semi Annual) l
- 1. Turn Range Switch to BATT., the meter.should read to the BATT OK region. If not, plug instrument into 115 VAC outlet and let batteries charge until-they check properly.
- 2. Couple Minipulser to Detector Inlet connector using a capacitor with a 1 KV or higher rating.
- 3. Turn Selector Switch to XI on -the RM-14. i l
~4. Adjust Minipulser to a pulse height of 100 millivolts and a-frequency of 200 CPM and 400 CPM. Record scale readings on Data Package 1 in the As.Found' column.
- 5. Repeat step I.3 and I.4 for X10' range and 2K CPM and 4K l CPM. Record on Data Package.l.
Repeat step I.3 and I.4-for X100 range and 2OK: CPM and 40K
- 6. l; CPM.
'7. - If readings are within i 20% of the Minipulser frequency, connect the HP-210 probe to the RM-14'and perform am instrument check as in step H.8. Record meter reading on'.
('T s
.(j ' Data' Package 1 in'the As Left column. Proceed to step I.17.
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r. '. anom E. l. Hatch Nuclear Plant aoaowa ao HNP S114 See Title Page aawsio~ ~o o... Georgia Power A .. ~o See Title Page 5 of 9 O V NOTE Even though the instrument is i 20% of calibration points every effort should be
. made to make it read as close as possible to the calibrat(on point.
- 8. If readings are not within i 20% of the Minipulser frequency .
proceed to step I.9. l
- 9. Connect the Minipulser as in step I.2. l
- 10. Turn Selector Switch to X1 on the RM-14.
- 11. Adjust Minipulser to a pulse height of 100 millivolts and a frequency of 400 cpm.
12.- Adjust the Calibration Control XI inside instrument until the meter' reading agrees with the Minipulser frequency. Record reading on Data Package 1 in the As Left colump.
- 13. Repeat steps I.11 and I.12 for X10 and X100 ranges and 4,000 _ l CPM and-40,000 CPM respectively.
() 14. 15. Repeat step I.7. If the instrument can not be calibrated initiate repairs.
.l
- 16. Repeat steps I.7 - I.17 when instrument is repaired. 'l
- 17. If the instrument checks out properly, complete Data Package 1, repla~ce'the calibration sticker with a new one bearing
. this test date and-when the instrument is due foriits next routine semi annual calibration.
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E.1. Hatch Nuclear Plant
. aaaaova aaoctouas ~o -
HNP 8114 See Title Page navisio= ~o
- o. . Georgia Power d .. . ~o See Title Page 6 of 9 b
v PROCEDURE DATA PACKAG~
-DOCUMENT PO: INP-8114-1 SERIAL PO:__Q11-MPL NO:
RTYPE: G15.14 XREF: RM-14
. TOTAL CHEETS: 2 .
~
FREGUENCY: Gemi Annual . COPPLETED BY: h,V) DATE COPFLETED: I HAVE REVIEWED THIS DATA PACKAGE FOR COPFLETENESS AND AGAItGT ACCEPTANCE CRITERIA IN ACCORDANCE WITil FNP-830. ACCEPTACLE LNACCEPTADLE REV'EWED BY: DATE REVIEWED: , REMARKS: 9 Page 1 of 2 . F#P-B114 - R11 -
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See Title Page 7 Of 9
-lt V
QATA PACKAGE 1 INSTRUMENT CALIGRATIQN DATA SHCET INSTRUMENT PM-14 LOCATION . ..
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MPL NUMBER - S.N. INSTRUtENT READINGS ACTUAL ACTUAL DATE: CALIG. COUNT DOGE CALID. DY: GOURCC RATE RATE AG FOUto AG LEFT *
' MP-1 200 CPM N/A CPM CPM SN- 400 CPM 'N/A CPM CPM 2000 CPM N/A CPM CPM ..
e 4000 CPM N/A CPM CPM ,
,/ S 20000 CPM N/A CPM CPM t
k- ' 40000 CPM N/A CPM CPM CS-137 1C4( to 8 ugi 24 Kcom N/A CPM CPM
. . . . . . . . . . . . . . . . . _ _ _ _ - = - - _ ...--.--......- ..--.....----.......-----..-
GENS. SET (CIRCLE) GENS. MAINT. PERFORMED
. REMARKS:
-5 g.. .
, Semi Annual Calibration.-
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. a m ova' E. I. Hatch Nuclear Plant a*ct=as ~o HNP 8114 See Title Page .evisio~ ~o - o... Georgia Power d ..m ~o See Title Page 8 of 9 0
PROCEDURE DATA PACKAGE DOCtA4ENT NO: HNP-8114-g SERIAL NO: R11-MPL NO: RTYPE: G15.14 s XREF: N/A TOTAL DEETS: 2
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FREGUENCY: Weekly COPFLETED BY: O
-(w/ 8 DATE COPFLETED: ,
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AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 149 -830. ACCEPTABLE UNACCEPT/ ALE l
. REVIEWED BY:
DATE REVIElED: s-REPIARKS: Unit #1 & 2
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V DATA PACKAGEJ RM-14 RADIATION MONITOR IPCTRUMENT CHECK DATE: UNIT NUMDER (FOTE 2) TODAY'S INGT. CER. DKG SOURCE ItCT. READItM RESET ALARM ACCEPTED DY LOCATION NUMDER_ CPM CPM W/CQLUCE CPN CICCU CHECK (NOTE 1) 16 K to ' ~ 24 K 16 K to 24 K 16 K to 24 K 16 K to . 24 K - 16 K to 24 K 16 K to 24 K i 16 K to -. . 24 K , 16 K to . 24 K
/ 16 K to t .
24 K Y. 16 K to 24 K 16 K to 24 K 16 K to 24 K 16 K to 24 K 16 K to 24 K 16 K to 24 K 16 K to 24 K 16 K to 24 K POTE 1: WHEN UNACCEPTADLE, NOTE IN THIS COLUPN APO REPORT TO
, LADORATORY FOREMAN OR DESIGNATED ALTERNATE.
NOTE 2: ACCEPTANCE CRITERIA FOR SOURCE CPM SHOLLD BE BETbEEN 16K-24K CPM ADOVE BACKGRutRO AT LOCATION.
. LABORATORY FOREMAN
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'Page 2 of'2' i+P-B114 R11
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/ HATCH NUCLEAR PLANT PROCEDURE o
Geiaer Counter Model E-120 Operation and Calibration PROCEDURE TITLE
. HNP-8120 PROCEDURE NUPEER Lab ..
RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )
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( PROCEDURE REVISION p ,
. 6 DOES THIS DOCUMENT CHANGE THE MODE OF OPERATION OR INTENT AS DESCRIBED IN - '
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HNP- 8120 See Title Page at m o* ~o 5 om Georgia Power d ..m ~o [ See Title Page 1 of 6 O GEIGER COUNTER MODEL E-120 OPERATION AND CALIBRATION A. PURPOSE To provide instructions for operation and calibration of the model E-120 portable survey meter with a Geiger-Muller type detector, normally used with a HP-260 hand probe. . .. B. FREGUENCY
- 1. Operation of counter: as needed.
- 2. Calibration of counter: semi annual.
C. REFERENCES
- 1. Geiger Counter Model E-120 Technical Manual, TDC #0517M
- 2. Mini-Pulser Procedure HP-8116 3 D. SAFETY U Observe radiation protection procedures.
E. TESr EQUIPMENT .
- 1. Mini-Pulser with coaxial cable.
- 2. RM-14 Cs-137 check source.
F. DESCRIPTION OF INSTRUPENT
- 1. The E-120 is a portable battery operated instrument used for the detection and measurement of beta or gamma radiation.
It has a geiger tube detector and the count rate is read out on a linear scale.
- 2. The full range of the instrument is 50 mR/hr or 70 K CPM.
- 3. 'The battery pack uses two standard D size batteries of any type commercially available.
G. QEECRIPTION OF CONTROLS .
- 1. External controls
- a. Switch - Five position switch turns _ instrument OFF, BATT, XO.1, X1, and X10 scales.
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aa aov>< . I. Hatch Nuclear Plant ou== ~o HNP- 8120 uvisio= ~o Sao Title Pags 5 Georgia Power A om ..m ~o See Title Paae 2 of 6 O b. Response - Controls response time of meter to most desirable compromise between speed and fluctuation for the particular range.
- c. Reset - Discharges integrating capacitor, bringing meter to zero rapidly.
- d. Phone - Pulse output for use with earphone, speaker or. ,,
external scaler.
- 2. Internal controls Calibration controls - one control for each range which individually calibrates that range to agree with the Mini pulser input.
H. OPERATION OF INSTRlPENT
- 1. Ensure that the instrument calibration is current.
- 2. To start instrument turn the switch to the BATT position.
The meter should indicate within the BATT OK area, if;not tag the instrument out with a TO SHOP tag. ., O 3. Place a check source in a repeatable position adjacent to the detector and move the switch to the.X10 scale. Compare reading on the meter to the correct value of the source. Using an 8 microcurie CS 137 check source reading should be between 20,000 & 40,000 cpm.- If instrument does not read within above values, tag it out with a TO SHOP tag.
- 4. Push the RESET button and the reading should drop to zero rapidly, then climb back to the source reading in step 2 when the RESET is released. The RESPONSE may-be adjusted to get the most desirable compromise between speed of response and meter fluctuation. ,
- 5. Interpretation of readings:
LEE
-All E-120's are calibrated to read in C.P.M.
unles's~otherwise stated on the instrument case.
- a. The meter' reading must be multiplied by the scale multiplier to obtain the' proper' reading. The fluctuation of the meter is normal and is caused by the
_u random nature of radioactive decay. R> , ( ..
- *a xo m E. l. Hatch Nuclear Plant aou*as ~o HNP- 8120 Sss Title Pags aswsio* ~o
- c. . GeorgiaPower A ..m ~o See Title Page 3 of 6 O b. The E-120, used with an HP-210 or HP-260 probe, has been calibrated using a mini-pulser (pulse generator) and should be used principally for contamination survey work. They should NOT be used to measure dose rates.
I. CALIBRATION OF INSTRUMENT
- 1. Remove the instrument from the case. . ..
- 2. Turn the control switch to BATT position and check battery condition. Replace if necessary.
- 3. Connect the Mini pulser into the probe connector.
- 4. Set Mini-pulser for negative pulses at 0.25 volt amplitude.
- 5. Set the Mini pulser to 400 cpm, 4,000 cpm, and 40,000 cpm successively and check and record readings on Instrument Calibration Data Sheet (Figure 1) in the As Found column.
1
- 6. If readings are within i 5% of full scale, turn instrument DFF, remove Mini pulser cable, place instrument in case, ' i reconnect detector and cable, and proceed to step I.12. l NOTE i 5%-of full scale X O.1 scale 35 cpm X 1 scale 350 cpm X 10 scale 3500 cpm
- 7. If reading are not within i 5% proceed to Step I.S. l
- 8. Set the Mini-pulser to 400 cpm and adjust.the XO.1 control for 400 cpm on the meter.
- 9. Set the Mini pulser to 4,000 cpm and adjust the X1 control for 4,000 cpm on the meter.
- 10. ' Set the Mini pulser to 40,000 cpm and adjust the X10 control for 40,000 cpm on'the meter.
- 11. Proceed to step I.5 but record readings in the As Left column of Figure 1 if readings are now acceptable. If instrument cannot be calibrated, initiate repairs and repeat Section I.
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> . = ov.' E. l. Hatch Nucicar Plant aaxt=ai ~o HNP.8120 S2e Title Pags aamio= ~o 5 o... Georgia Power d ..m ~o See Title Page 4 of 6 O 12. Place the RM-14 check source on contact with the detector, reading should be about 20,000 cpm. Record results in the As Found column and, if within i 20% of actual count rate, record also in the As Left column. Count rate of the RM-14
- check source is about 20,000 cpm contact with G.M. detector.
NOTE Normal wide fluctuation in the meter is normal with the instrument on X.1 scale.
- 13. If results in I.12 are not within the limits specified, replace GM detector and repeat.
- 14. If the instrument checks out properly, complete Instrument Calibration Data Sheet, replace calibration sticker with a new one bearing the test date and when the instrument is due for its next routine semi annual calibration.
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,,,, Georgia Power - ~e See Title Page 5 of 6 PROCEDURE DATA PACHACE DOCLPENT ND: M -8120-1 SERIAL ND: ROS-PFL NO: 021-N RTYPE:__CIS.14 __
XREF: N/A TOTAL SEETS: 2 FREQUENCY: _Qgarter1y
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_xAP R_ A_N_1 _2 IN"TRUMENT CA6IBRA_TlQN DATA SHER INSTRUMENT _EB_E_R_LINE E _1gg__ LOCATION __ MPL NUPEER -N s. d INSTRUMENT READING ACTUAL ACTUAL DATE: CALIB. COUNT COUNT ---------------. i----------..--- SOURCE RATE RATE CALIB. BY: (CPM) ----------------- ---.---------.- AS FOUND AS LEFT (CPM) (CPM) MINI PLLSER 400 CPM N/A SN 4000 CFM N/A 40,000 CPM N/A
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- ~ o i e GEORGIA POWER COMPANY
. HATCH NUCLEAR PLANT PROCEDURE
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Regulated Air Sampler Model RAS-1 Operation and Calioration PROCEDURE TITLE hbp-8128 PROCEDURE NUPEER Lab . .. RESPONSIBLE SECTION SAFETY RELATED ( ) NON-SAFETY RELATED ( X )
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Gee Titis Page N l RECtLATED AIR SAPPLER MODEL RAS-1 l OPERATION AfC CALIBRATION A. PURPOSE To establish a standard technique for the operation and cali-
- bration of Low Volume Air Samplers. . ..
B. FREGLENCY
- 1. Operation of air sampler: As needed t
- 2. Calibration of air sampler: Semi Annual C. REFERENCES
- 1. i+F-8013 Airborne Radioactivity Concentration Determination
- 2. Merriam Flow Meter, D-40-NOO7 Instruction Book TDC 20.77M l 1
D. SAFETY 7
- l , -l l
Observe Radiation Protection Procedures. I E. TEST EQUIPPENT
- 1. Merriam Flow Meter - With Gauge F. DESCRIPTICN OF INSTRlPENT l The RAS-1 is used for sampling air throughout the plant for particulate and.radiciodine airborne radioactivity. The
- . regulated air pump offers a constant air flow, while depositing
! particulate on a 47 mm glass fiber filter then through an' iodine cartridge for iodine collection. l- .G. DESCRIPTIG4 OF CCMTRCLS AfC CObNECiunS None H. OPERATICN CF INSTRLPENT 1
- 1. Be sure the sampler bearsis current calibration. sticker. l 2.- Remove _the outer; ring by turning'it counterclockwise and install a 47 nun glass fiber filter paper in' the holder.
-Replace outer ring-securely.
Open the. charcoal cartridge holder and place an' iodine (N 3. .
- ' O cartridge into the holder, making certain-to note the.
direction of sample flow through the cartridge..
. . _ _ ~
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I- - . *aaaova' E. l. Hatch Nuclear Plant awa** ~o . HNP- 8128 "v*o* No ! Sse Title Page l* om Georgia Power d ..m ~o I See Title Paae 2 of 7 !O 4. The sample LOCATION, DATE and TIME ON should be written on the iodine cartridge and on an air sample envelope. i 5. Plug the sampler in and turn it on, allowing a two minute
- warm-up time. Read the rotameter (center of the ball) and l t
multiply the flow in L.P.M. times the correction factor for that instrument. Record this initial flow rate (L.P.M.) on the air sample envelope. . .- i 1 j 6. When the sample is complete, note the final reading on the
- rotameter (center of the ball) in L.P.M. and multiply it by ;
the instruments correction factor. Record the TIME OFF and . the final flow rate on the iodine cartridge and the air ! sample envelope. : i
- 7. Place filter and cartridge in the air sample envelope and
- return both sanples to the Health Physics Office for I
counting. I
- 8. Take the AVERAGE flow rate between the initial and final
! flow rates, as the sample flow rate in L.P.M., and complete Figure 2 of HNP-8013 using the appropriate formulas given on , the bottom for the calculations and follow instructions as , found in FDP-8013. I. CALIBRATION l
- 1. Place filter paper and charcoal in sampler as though preparing to take a sample, making sure that tne cartridge
- holder and the filter paper retaining ring are tightened together.
- 2. Plug the sampler in-and turn.the pump on, allowing a minimum warm-up time of-two minutes.
- 3. Press the rubber adaptor provided on the Merriam Flow Meter.
.up tight against_the filter-paper on the sample head.
- 4. J0'bserve the.magnehelic gauge reading (in inches of water and
, record reading on Data Package-1. Remove adaptor from sample' head.
- 5. Using the prepared graphs'for the merriam flow meter, convert inches of water to L.P.M. and. record this value~on Data Package 1.
15." -Observe the rotameter _ reading (center 1of the ball):and' record this reading'on. Data Package 1.in L.P.M.
- 7. Complete Data Package'1,1 dividing the magnehelic reading.-
\ '(L.P.M.) by the rotameter reading (L.P.M.),.to get.the correction fuctor for that low volume air-sampler. Place a
-tag on the sampler bearing its correction factor.
~ ~~ ~~
- , i, o..t E. I. Hatch Nuclear Plant aaxiovaa ~o HNP- 8128 l Sao Title Page a'v'5$$ No L- .... Georgia Power .. .. ~o See Title Paae 3 of 7 1
; 8. Replace the calibration sticker with a new one bearing the test date and the date of its next routine semi-annual i 21 day calibration.
I
.9 . Complete Data Package 2 and place in Health Physics Office in the Low Volume Air Sample Log Books (I and II).
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* ' " * * ' E. l. Hatch Nuclear Plant aociovas ~o HNP- 8128 Sao Title Pags aavisio~ ~o o.,a GeorgiaPower A ,.mo ;
see Title Paae 4 of 7 i PROCEDURE DATA PACHACE
' DOCUMENT NO: W -8128-1 i
SERIAL NO: RO2 PFL NO: RTYPE: C15.14 XREF: TOTAL SFEETS: 2
*Z FREQUENCY: SEMI APNUAL
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.(' COPPLETED BY:
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. DATE COMPLETED:
I HAVE REVIEbED THIS DATA PACKAGE FGt COPFLETEPESS AbD AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH F#5'-830. ACCEPTABLE LNACCEPTABLE REVIEbED BY: DATE REVIEbED:- REMARMS:
~
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- l. = = ova' E. I. Hatch Nuclear Plant awawa ~o HNP- 8128 Sse Title Pags a.visio= ~o ca,. Georgia Power d ..c.. ~e See Title Pace 5 of 7 DATA PACMACE 1 RAS CALIBRATICN SEET M.P.L. PO GER SERIAL PU'GER .-
MAGPE}ELIC INCES OF WATER LPM ROTAPETER LPM
- CORRECTION FACTOR:
TEST EQUIPPENT USED* PFL (FLCM PETER) MAINTENANCE PERFORPED: LOCATION: CALIBRATED BY: , e' DATE:
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- CORRECTION FACTOR = MAGPGELIC READING IN L.P.M.
ROTAPETER READING IN L.P.M. W:,4
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f* *=ma' E.1. Hatch Nuclear Plant a==a. ~o HNP- 8128 Sao Title Pags a. vision ~o oar. GeorgiaPower e A .. e. . i See Title Pace 6 of 7 l PRDCEDURE DATA PACKAGE l*
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. DOCUMENT NO: HNP-8128-2 SERIAL NO: RO2 PFL NO:
RTYPE: C15.14 XREF: TDTAL SHEETS: 2 i
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FREGLENCY: SEMI APG4.lAL , COPPLETED BY: DATE COPPLETED: I HAVE REVIEbED THIS DATA PACKAGE FOR COPPLETEPESS APO AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH Mf-830. ACCEPTABLE LNACCEPTABLE REVIEbED BY: DATE REVIEbED:
. RF.MARMS:
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Gee Title Page 7 op 7 DATA PACHACE 2 RAS FLOW RATE LOG
- SERIAL NUMBER I
- CORRECTION FACTOR LOCATION REMARKS 1
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- (d SAFETY RELATED ; ( ) NON-SAPITY RELATED hPRESENTSTATUS h THE ABOVE STATUS IS BEING CHANGED: ( ) YES, TO __ ; (d NO
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6 l TYPE OF DOCUMENT TO WHICH THIS EVALUATION APPLIES ( ) NFW PROCEDURE (W PROCEDURE REVISION DOES THIS DOCUMENT CHANGE THE MODE OF OPERATION OR INTENT AS DESCRIBED IN THE FS7R? ( ) YES ; ( WMO DOCUMENT ( ) INVOLVES AN UNREVIEVED SAFETY QUESTION ( ) REQUIRES A TECH. SPECS. CHANGE BEFORE THE DOCUMENT CAN BE USED; [ IF SO, RECORD THE ASSOCIATED DoCR NUMBER . 3 ( } NEITHER O.. DOES THE IMPLEMENTATION OF THIS DOCUMENT REPRESENT AN UNREVIEVED SAFETY QUESTION? ( ) TES ; (L F NO 4a Y CIVE T'dE BASIS FOR THE DETERMINATION OF WHETHER OR NOT THE IMPLEMENTATION OF THIS , DOCUMENT REPRESENTS AN UNREVIEWED SAFETY QUESTION : M m- rcm , s < _. . e9 . r 4. ,
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- 1. THE PROBABILITY OF OCCURRENCE AND THE CONSEQUENCES OF AN ACCIDFNT OR .
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- . See Title Pace l 1 of 7 l BETA COUNTER MODEL BC-4 l i
A. Pt.RPOSE i
- l
.To insure the instrument is calibrated properly and to provide operation instructions for the user.
. s.
i B. FREQUENCY
- 1. Daily Chi-Square Check
- 2. 'Guarterly Calibration C. REFERENCE i
5 BETA COUNTER MODEL BC-4 Technical Manual TDC #O516M , l D. SAFETY 'l f-Observe radiation protection procedures.
- i E. DESCRIPTION OF INSTRtPENT -g The Model BC-4 Beta Counter is a system consisting of a two-inch 4 Ox detector, high voltage power supply, pulse amplifier, timer and.
. six decade readout. All circuits are solid state with use of
^ integrated circuits. F. DESCRIPTION OF CONTROLS l
- g. 1. EXTERNAL
- a. Count Mode Selects timed or manual counting mode.
- b. Reset-Start - Resets all appropriate-circuitry to zero and starts a timed counting sequence.
- c. Count Time-In-Minutes - Selects desired. counting time.
- d. Power - Supplies' power to the~ instrument.
- e. 115 or 230 VAC' Switch ' Selects either'115V, 60 Hz, or 230V, 50 Hz. (Set tc 115V,;60 Hz)
.l
- 2. INTERNAL-a.-.
Time' Base (Timer' Board) - Control'for adjusting time- *
' base of the timer.when instrument is used with-a r
fT battery.- .
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. aaa *va' E.1. Hatch Nuclear Plant **ce=as ~o HNP- 8136 Sao Title Page aavisc~ e
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See Title Page 2 of 7 O G. OPERATICN OF INSTRlPENT l
- 1. Be sure the instrument calibration is current. l
.2. Turn Power Switch to ON.
- 3. Position Count Mode switch to desired mode.
- 4. Position Count Time.In Minutes switch to counting time
-desired.
- 5. Press Reset-Start switch and release. Instrument should begin counting.
~6. Daily Calibration.
- a. Set Count Mode switch to Manual. Instrument should begin to count. Record results in Man. CK column of Data Package 1 (Data Sheet 1).
s
- b. Set Count Mode switch to TIMED. .
- i c.
Perform a 10 minute background count and record the
-- background counts in C.P.M. on Data Package 1 (Data Sheet 1).
- d. Place a radioactive standard in position'for counting and count for 5 minutes.- Record results on Data Package 1 (Data Sheet 1) in C.P.M. l M
A TC-99m beta ~ source centered:in a stain-less steel plachet should be used.
- e. If count rate is greater,or less than 3 sigma in 3 consecutive counts, then a-new chi-square must be performed. Record results by entering yes or no in the
~
i 3 sigma. column of. Data Package 1-(Data Sheet 1).
~
- f. Calculate the-counter efficiency for the_ geometry in-step e d and record on . Data Package: 1:.(Data Sheet 1).
Efficiency =LNet C.P.M. X1100'
.D.P.M. .
Hi CALIBRATION OF INSTRLDENT
- l c -
- 1. Adjust H.V.1.to 900: Volts. ' Refer toHtechnical manual.z
.f
-s CAUTION Do not over-voltagefthe CM' tube. .( 900l volts)
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- See Title Page aavisio= ~o 3
- o. . Georgia Power d ..os ~o See Title Page 3 of 7
- 2. Chi-Square test (Guarterly test).
- a. Perform a one minute background count and record the background counts in BMG. CPM on Data Package 2 (Data '
Sheet 2).
- b. Place a radioactive standard in position for counting.
Use the same standard which will be used in the daily. .. calibration.
- c. Count the source for one minute durations twenty times and record net count results on Data Package 2 (Data I
Sheet 2).
- d. Calculate chi-square. If results is between 7 and 35, the instrument shoul.d be functioning properly.
- e. Calcualte 1 6 , 2 6 and 3 ( error.
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-me
l
* = ova E. l. Hatch Nuclear Plant aaoCemas ~o HNP 8136 See Title Pags aevisio= ~a o.1. Georgia Power A ..o. ~o See Title Page 5 of 7 x
DATA PACHACE 1 BC-4 DAILY CALIBRATION DATA SWET 1 Month 19
. t.
SOURCE: SER. NO. ACTIVITY DPM INST. M.P.L. NO: 021-SOURCE COUNT RATE (6)= CPM
- COUNT TIPE: BACHGROLJO - 10 Minutes 6 + 3(= CPM
- SOURCE - 5 Minutes n - 3s= CPM
- COE BY
^
OAy CATE MAN SNG. !KUICE EKERCE W. WITHIN i 3 SIGMA REM 4RMS CM. C.P.M. C.P.M. IET C.P.M. 1 2 3 4 r> 4,
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FIGURE II :- !
' Page 2.of 2 a
Li 3 *" - ~ _
, .a-ov.t E. l. Hatch Nuclear Plant aaouwas ~o HNP.8136 Sne Title Page navisio~ ~o o.1. Georgia Power A ..m ~o See Title Page 6 of 7 O
PROCEDURE DATA PACKAGE DOCUMENT NO: HNP-812{L-2 . s. SERIAL NO: RO3-MPL NO: RTYPE: G15.14 XREF: . TOTAL SMITS: 2
, i FREGlKNCY: Guarteriv _
CCDFLETED BY: O DATE CCPPLETED: . I HAVE REVIEEED THIS DATA PACKAGE FOR COPFLETEbESS Abo AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH i+F-B30. ACCEPTABLE LNACCEPTABLE REVIEbED BY:
* ~'
. DATE REVIEhED:
REMARKS:.
-Page 1 of 2 i+F-2136 RO3 yf '
. C/' L FIGLRE 2 l Page 1 of 2:
+
a
' ^~a va' E. l. Hatch Nuclear Plant aocco= ~o HNP- 8136 Sne Title Page aavisio~ ~o om GeorgiaPower A .... ~o
)
See Title Page 7 of 7 DATA PACKAGE 2 j CHI-SOUARE TEST i, i $ DATA SEET 2 ; i BC-4 M.P.L. NO. a DATE: _ 6 SOLRCE: MIN SOURCE SER. NO. i COUNTE TIPE BMG CPM H. V. SETTING RlN NO. n* n-n (n-6)^ ) ' - 1 2 3 4 5 6 7 .. 8 ~ 9 ',' 10 .. 11 'a 12 1 15 16 17 18 19 20 SLN (2)
,2
- BET. COLJ4TS Xy (Chi-Square) = E(n-n) =
N = ED = h 20 # must be between 7 8r 35 X E (n-6) must be zero
/ DATE a = 1 g=~ CCPPLETED BY:
as= ' 3T= 9' . 6+Ig= 6. - If = 4 6 + Eg = 6 - Es = 6' - 3r = j 6 + 3( =
'Pege 2 af 2:
14F-8136 : RO3
.~
( ). . FIGLRE ~2.. - V' Page 2 of 2. e f 1
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"- HATCH bAJCLEAR PLANT PRDCEDURE (Ov
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, ( PROCEDURE REVISION 4 4 h DOES THIS DOCUMENT CHANGE THE MODE OF OPERATION OR INTENT A DE THE FSAR? . ( ) YES ; ( NO --
( ) INVOLVES AN UNREVIEVED SAFETY QUESTION hDOCUMENT: ( ) REQUIRES A TECH. SPECS. CHANGE BEFORE THE DOCUMENT CAN.,BE USED; IF So, RECORD THE ASSOCIATED DoCR NUMBER : ( NEITHER - ca. J_ D SAFETY hECESTHEIMPLEMENTATIONOFTHISDOCUMENTREPRESENTANUNREVI QUESTION? ( ) YES ; ( NO h CIVE THE BASIS FOR THE DETERMINATION OF WHETHER OR NOT THE IMPLE DOCUMENT REPRESENTS AN UNREVIEVED SAFETY QUESTION :
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, g. @ SAFETY EVALUATION PERFORMED s) v ' /,' .u i r 25 - I g- h SAFETT EVALUATION REVIEWED : BY. . // N W '
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. ^~ mat E. l. Hatch Nuclear Plant x<=as ~o 1 H N P- 8430 l Sao Title Page aeosm~ w I 5
o.r. GeorgiaPower A ..m ~e See Title Page 1 of 15 OPERATION OF WASTE SEPARATION AND TEMPORARY STORAGE FACILITY A. PURPOSE The purpose of this procedure is to provide instructions in the operation of the waste separation and temporary storage facility. B. FREGUENCY Not applicable to this procedure. C. REFERENCES ,
- 1. FNP-8012 Radiation & Contamination Surveys i HNP-8016 Shipment of Radioactive Material I 2.
- 3. HNP-8028 Release Surveys for Trash and Materials Leaving l Operating Buildings - I D. SAFETY , l I
- 1. Observe Radiation Protection Procedures.
- 2. Observe Georgia Power, SAFETY, Section "O". l E. SPECI AL EQUIPPENT .l
- 1. Appropriate survey instruments.
- 2. Appropriate protective clothing.
- 3. Appropriate signs, placards, and labels.
F. DETERMINATION OF MATERIALS TO BE TRANSFERRED TO TE WASTE l SEPARATION abo TEPPORARY STORAGE FACILITY (WS-TSF)
- 1. All waste transferred to the W3-TSF will be transported-in such a manner as to prevent the release of contamination to
- the environs during transport.
- 2. Liquids should not be transferred to the WS-TSF. Transfer l of any liquids must be approved by the H.P. Supervisor or i his designee.
- 3. Each bag or piece of. material.should be surveyed b'y'a Health Physics Technician prior'to leaving the operating buildings. i+P-8028.
[ ,\ . C' 4. There should be.no external surface contamination on'the-Also, no waste reading in excess of 50 mr/hr container. contact will be transferred-to the WS-TSF without the approval of the Health Physics Supervisor or his. designee.- l.
'*"*~
a== vat E. I. Hatch Nuclear Plant am a mas ~o I
' HNP. 8430 ; See Title Page aavisio~ ~o l !- om Georgia Power A ..m ~o 5
See Title Page 2 of 15 l O 5. Each container or piece of material must be labeled with a i Radioactive Material label containing the following j- information: i
- a. A general description of the waste
- b. Surface contamination results
- c. Highest contat.t dose rates
- d. Date
- e. Surveyor's name NOTF Any material with a contact ,
dose rate greater than 50 mr/hr must be taken to the Unit II t radwaste trash compacting area , ! on the R/W 132' elevation, unless exempted per Paragraph F.4. , l G. TRANSFER OF WASTE TO THE WASTE SEPARATION Ab0 TEPPORARY STCIRAGE l FACILITY (WS-TSF)
- 1. Material shall be transported to the WS-TSF by truck or other appropriate means.. The vehicle will be loaded in an-area designated by a Health Physics Foreman or Supervisor.
. 2. During the loading, transporting, and unloading'of waste from the vehicle, the vehicle shall be posted " Radioactive
. Material" on the front rear and each side of the vehicle.
- 3. After the' loading of waste onto the transport vehicle has been completed, the_ vehicle shall be locked'and sealed and shall remain locked and sealed, until the commencement of i
unloading at the WS-TSF. If transport vehicle is a flat bed trailer, locks and seals do not apply.
-4. The. vehicle-shall'be surveyed prior _to leaving the protected ~
' area. ' Dose rates outside the vehicle should be within-limits specified in D.O.T. regulations. IF-not, notify the Lab Supervisor for approval ~to proceed with the.-transfer. Survey:results_will be documented.on Figure 1 of HNP-8012.
- 5. .The vehicle should travel unimpeded and by the quickest route 1:o the WS-TSF. There shall be no' unauthorized ~ stops
_along the way. ' Emergency stops _(such as mechanical ~ failure,
/ flat tire, etc.-)ishall require the immediate notification.cHL
, ( a Health Physics Foreman. }
' m
4 aa aov= E. l. Hatch Nuclear Plant aaoceouas ~o HNP- 8430 See Title Page aevisc~ ~o 5 i om GeorgiaPower A ..mo See Title Page 3 of 15
- 6. After the vehicle has been unloaded, a survey shall be performed. The interior of the vehicle or the surface of the flat bed. trailer will be smeared for surface contamination. Survey results will be logged on Figure 1 of procedure HNP-8012.
H. RECEIPT OF WASTE AT T}E WASTE SEPARATION AND TEPPORARY STORAGE l FACILITY - 6- , 1.- Upon receipt of waste at the WS-TSF, all waste should be
- separated or classified according to dose rate and type of waste.
- 2. Waste reading less than 5 mr/hr should be set aside for i processing by the waste separation facility. Waste reading
. greater than 5 mr/hr should be. prepared for shipment for burial.
- 3. Non-compactable waste should be set aside for packing B-25 shipping containers or equivalent. -
- 4. Compactable contaminated waste should be set.aside for _
compacting. ( 5. All bags containing waste should be opened and investigated for salvageable.pr,otective clothing and equipment. d E Any deviation from the above guides requires approval from a Health Physics. Foreman or Supervisor.- I. WASTE SEPARATION q 1.- Bags of waste reading less than-5 mr/hr contact should be- , . opened.and the waste should be placed;on the waste sorting
. tables 1for-inspection.
l 2.' All waste shall be scanned'with'an RM-14/HP-210. probe;or an: E-120 or equivalent. Waste found to be' reading 100 cpm above background at one half inch will be considered contaminated and will.be processed ~as' Radioactive Waste.
~
The. remaining material will be:placed in ereen: plastic bags and sent to the landfill as non-contaminated trash. 3.' . .Before'any clean waste is released to the landfill,Jeach bag; is.to'be checked with a micro-R meter or a'PRM-4A/9PA-3. i This' check is to be performed at the landfil11by an ANBI. qualified-H.P. Any bag offclean. trash reading greater than-O ..two times' background will-be-returned to'the-waste - separationLfacilityLforfreprocessing;
-%r - . . * . . . - - ,.,y ,# , , -, , . , y . . ,
- i. a *= E. l. Hatch Nuclear Plant =uovas ~o HNP- 8430
} See Title Page ainsio= ~o 5 !- om See Title Page Georgia Power d .. - ~o 4 of 15
- q O 4. A written log will be kept of all materials leaving the j WS-TSF as non-contaminated trash. This log should contain:
- a. Date
{- j b. Time i f c. Number of bags of trash t. i - i d. Type of trash i
- e. Surveyor's name i
- f. Instrument serial number J. PROCESSING OF RADIOACTIVE WASTE l-'
- 1. All radioactive waste packaged for shipment will be in an l appropriate DOT shipping container. When compacting in a l B-25 box, place all material greater than 20 mr/hr in..the center of the box in order to limit the surface dose rates.
The highest average reading should not-exceed 500 mr/hr ' 9/ meter-from the box. . O 2. .All shipping containers will be labeled with a radioactive materials sticker and the following information:
- a. I.D. number.
- b. General description of contents.
- c. Highest contact dose rate I d. Container contamination levels
! -e. Gross weight - L
- f. Date. packaged and surveyor's.name- -}
(
- 3. C'ontainers should be numbered ~ consecutively.with the numbers
". preceded'by HNP and the~ year.
~
l Example: HNP-85-1. l HNP-85-2 -
- 4. Radioactive LSA stickers will'be_placed on two. opposite sides of each container.
' ~
- 5. : Containers should:be stored'in such a.way as to 11mit
-exposure'and allow easy access.~ -
M l t , _ . _ - - . .- ,- - - . . , . . ./.. ,-
. aa ao = E.1. Hatch Nuclear Plant movas ~o HNP- 8430 aswsio=~o See Title Page 5 om GeorgiaPower A .. ~o See Title Pace 5 of 15 O NOTE When containers are shipped, the containers that were Dackaced first should be shipped first. K. ROUTINE SURVEYS g
- 1. Routine contamination and radiation surveys will be performed at least once per day during manning of the facility or following any event which might cause a change in conditions. Survey results are to be logged on Figure 1, 2, or 3 of HNP-8012.
L. RADIATION abo CONTAMINATION CONTROL l
- 1. Personnel working in the WS-TSF will be required to wear pocket dosimeters and TLDs at all times.
- 2. Radiation Work Permits will be administered in accordance to HNP-8008.
- 3. All exits from contaminated areas will have step-off pads. ' l Any person exiting a contaminated area must perform a whole O body fr r.
NOTE Any material leaving or taken out of the WS-TSF must be surveyed by an H.P. staff person.
- 4. The storage area will be inspected monthly for signs ~of container deterioration or leakage. Appropriate-corrective action will be takenLif damaged containers are found.
Documentation will be on Data Sheet 1 of Data Package 2.
- 5. Any water that accumulates in the floor sump will be sampled and analyzed by Health Physics. If the liquid contains radioactive material other than natural radioactivity, it
*will be transferred to the radwaste system for processing.
When liquid is faitnd, . the source should be identified and stopped.
- 15. When the buildingris not in use, Health Physics will perform; a survey.of.the building interior on a weekly basis..
- 7. No' materials may be stored within 18 inches of the-overhead-fire sprinkler: system. -
e's ()- f
- 8. Fans used at.the WS-TSF must'be positioned such that they-do not blow air from:a contaminated area into a'non-contaminated area.
n-.. N
* * *a**va' E. I. Hatch Nuclear Plant aaou = = ~o HNP.8430 Sne Title Page aavisio~ ~o 5
l' o.m Georgia Power d .. ~o See Title Page 6 of 15 4 O 9. Daily inspect the magnehelic gauge for the HEPA unit associated with the waste sorting tables ventilation system. If the gauge is reading 2 1.5 inches of water, change out i EPA filter and prefilter. Document daily inspection of magnehelic gauge on Data Package 3. M. SEMI Al@AJAL RADWASTE INVENTORY REPORT A semi annual report is necessary to assure that radwaste is not stored at the facility for more than two years. Any waste found during inventory which has a " packaged date" greater than 6 months should be shipped for burial before the next semi annual report due date. Semi annual inventory will be conducted during the first and seventh month each year. Data Package 1 will be
-used to complete this report.
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e a == E.1. Hatch Nuclear Plant a=ct=as ~o HNP- 8430 Sie Title.,Paga atosio= ~o 5 om Georgia Power A .. .. ~o , See Title Pace 7 of 15
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PROCEDURE DATA PACKAGE
" DOCUMENT NO: HrP-8430-1 SERIAL NO: R05-PFL NO: N/A l RTYPE: C15.14 XREF: N/A l TDTAL SHEETS: 5 FREGENCY: As Reauired ,
b ( COPPLETED BY: q DATE COPPLETED: I HAVE REVIEWED THIS DATA PACKAGE FOR COPPLETEPESS APO AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH H @-830. ACCEPTABLE UNACCEPTABLE REVIEbED BY: i DATE REVIEbED: REMARKS:
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- DATA PACKAGE 1 Data Sheet 1 RAD WASTE INVENTORY 5
I. D-25 DOXES gDJ NUMBEg DATE PACKAGEQ STORACE LOCATION E O . l$3: All packages w/ dates 1 6 months in age shou!d be shipped' off site prior.to the next semi annual report.. Page 2 of 5 H@-8430. R05 - f~'y . , .a FIGLRE 1 Page 2 of 5 6 L.
> - ^=cvu E.1. Hdtch Nuclear Plant a*cewai ~o < HNP- 8430 aavisio ~c Sao Title Pags 5 o.m Georgia Power d ..e. ~o See Title Paae 9 of 15 O QATA PACKAGE 1 (CONT) Data Sheet 1 (cont) RAD WASTE INVENTORY
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II. 55 CA'. DRUMS (TRASH) - DRUM NUMBER DATE PACHAC Q STORAGE LOqAl@ s
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w, tEIE: =All packages w/ dates 1 6 months-in age should be shipped oH site prior to the next semi annual report.
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QATA PACKAGE 1 (CONT)_ Data Sheet 1 (cont) RAD WASTE INVENTQR_Y III. ABSORGED SOLIDIFIED OIL DATE PACKAGEQ STORAGE LOCATION DRtJM PAJMBER E O t! gig - ' All packages w/ dates I 6 months should be shipped off site prior to the next semi annual report.- Page 4 of 5-
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"ov4 E. I. Hatch Nucisar Plant aaoamas ~o HNP- 8430 Sao Title Pegs aavisio o 5
oe Georgia Power d .. . ! l See Title Pace 11 o f 15 l l
. DATA PACHACE 1 (CONT)
Data Sheet 1 (cont) RAD WASTE IN'ENTORY
. u TYPE WASTE NUMDER , DATE PACHACED SI,QRACE LOCATIQt!
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9 t!QIE: All packages w/ dates 1 6 months of age should be shipped' off site prior.to the nest semi annual report. Page 5 of 5 W -8430 RO5 j ..,.^s 1- t
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4 - ^~== E.1. Hatch Nuclear Plant
- aouu ~o HNP-8430 Sao Title Pags avisias mo 5
om GeorgiaPower A . . . . . See Title Page 12 of 15 1 PROCECURE DATA PACKAGE u DOCUMENT NO: HNP-8430-2 SERIAL NO: RO5-MPL NO: RTYPE: G15.14 XREF: TOTAL SFEETS: 2 FREGLENCY As Reauired , A COPPLETED BY:
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DATE COPPLETED: I HAVE REVIEWED THIS DATA PACHACE FCR CCPPLETEPESS APO AGAINST ACCEPTANCE CRITERIA IN ACCCRDANCE WITH F9F-830. ACCEPTABLE LNACCEPTABLE REVIEIED BY: DATE REVIEbED: REMARMS: Page 1 of 2 HNP-8430 R05 m - FIGLEtE E Page-1 of 2'
. aaaova' E. I. Hatch Nucicar Plent aaximas ~o HNP- 8430 Sse Title Paga asvisio o 5
om. Georgia c Power d ..o ~o See Title Pace 13 of 15 DATA PACHAGg,g Data Sheet 1 STORACE AREA MONTHLY INSPECTIQN SEET INSPECTOR: DATE: MC,gP_ ELE UNACCEPTADLE TRASH OR DEBRIS DUILDUP (ADDITIONAL EMPHASIS AROUND WORK AREAS) XTERIORATION OF CONTAIERS (i.e. RUST, HOLES, ETC.) PROPER POSTING WHERE APPLICADLE DOSE RATES ARE WITHIN LIMITS POSTED SPILLS (WATEd CR DIL) CEERAL CLEAM.IESS M u IF UNACCEPTABLE, NOTIFY AN . FP FOREMAN IMMEDIATELY. k REMARKS: j Page'2 of 2 He-8430 ROS-(- ( 1 Nd FIGL5tE 2
.-Page 2 of 2
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.- -aoa. E. l. Hatch Nuclear Plant aaoce=as ~o HNP-8430 Sse Title Page aevisio= ~o 5
om GeorgiaPower A a. o See Title Paae 14 of 15 PROCEDURE DATA PACKAGE 5 DOCUMENT NO: HNP-8430-3 SERIAL NO: RO5-MPL NO: RTYPE: G15.14 XREF: TOTAL SHEETS: 2 - FREQUENCY: As Reautred , COPPLETED BY:
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DATE COPPLETED: I HAVE REVIEWED THIS DATA PACHACE FOR COPPLETEESS APO AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 1+P-830. ACCEPTABLE thiACCEPTABLE f REVIEE D BY: DATE REVIE E D: REMARMS: Pee.1: of. a . HPP-s43o Ros-
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I. - aaaac= E. l. Hatch Nuclear Plant aaoct = = = HNP- 8430 Sao Title Pega aiv'5ca w 5 om Georgia Power d .. m o See Title Page 15 of 15
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O t b DATA PACKAGE 3 MAGNE1CLIC SURVEILLANCg
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DATE FERFORMED DY MAGNEHELIC* REMARHS READING
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.= ____ ._-....__-_----_.. . . -______.___--... - _ _ _ . - - _ . _ _ _ . . . - - .
_----- =.. _ = - - - - - - - - . - - - = . . _ -.---.----....___.-_-. _ - _ _ _ . - - _ - - _ . - - . . . . , _ . - - - -.- _--..-__........___._ ..-----...... . __.-- _ = - - . . . . . . _=. _----- _.__ _ _ = _ = = . - - - - -
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........_-..- ....-----....__-- ==.------------..... ---.=- = - -
----.... ===........-_.-_ = = = = = - - - ==.---..== - = _ _ _ . . . . . . . . . . . .
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........................_..- - =----. ..............=---
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- Gauge should indicate < 1.5 inches of water, -if gauge indicates
~
> 1.5 inches of water e then the FEPA filter and profilter should.
be changed. Indicate change out'in remarks. 4 Page 2 of 2-Fer-s4ao nos m 8 .
! I' FIGLRE 3 Page 2 of 2 A---
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