ML20028F645
| ML20028F645 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/06/1983 |
| From: | Nix H, Rogers W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20028F630 | List: |
| References | |
| PROC-830106, NUDOCS 8302020346 | |
| Download: ML20028F645 (108) | |
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HATCH NUCLEAR PLANT l I
d PROCEDURE 1
Mini Pulser Model MP-1 Goeration and Calibration l*
PROCEDURE TITLE !
i HNP-8116__ . .
PROCEDURE NUNGER f t Lab RESPONSIBLE SECTION f e
SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
APPROVED APPROVED DESCRIPTION DEPT. PLANT DATE REV.
HEAD MANAGER 4 Pages 1 -5 #
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Pl o 1, 1 Revision No. ------ ------ -
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REVISIC' CHt,NGES MODE OF .CPERATION OR INTE 'I~CEGCRIDED IN FSAR:
( ) Yes ( No
. . CHANGE ( Neither
) AnINVOt.VES: ) Tech. Specs.
unreviewed Safety Guestic.n (
(
(Sie back for Safe'y Evaluation if required).
Non-Safety Related ( )
SafetyRe[ated (
) Yes ( j Safety /t:sn-safety Status Change ( .
.- 1 Attach marked up copy of procedure to thi's form.
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- -question- - - - - -as- -explained - - - - - - -belci. -------------------------_-____,._____--_' .
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N!ANUAL SEE v-l t
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'h o Title Pago aEv's'oN No GeorgiaPower A om ...
c See Title Page -
1 of 5 O Y i
MTNI PULSER MODEL MP-1 OPERATTON AND CALIBRATION t t
t A. PURPOSC -
t To ensure that the instrument is calibrated properly and to provide operation guides for the user. l f
B. REFERENCE l t Mini Pulser Model MP-1 Technical Manual, T.D.C. Numbe r T.D. C. -523. l C. SAF' TY I .
Exercise care when connecting coaxial cable to instrument being calibrated. _
l D. TEST EGUIPMENT
- 1. Tectronix Oscilliscope Model 453 or equivalent. -l L
- 2. Hewlitt Packard Universal Counter Model 53258 or equivalent. [
i E.. DESCRIPTTON OF INSTRUMENT -
The model MP-1 Mini Pulser is a pulse generator specifically designed to aid in calibrating or trouble shooting pulse counting instruments. The pulse repetition rate is variable from 10 CPM to 1.6 million CPM in discrete steps of 2 and is accurate to within 0.1%. The pulse shape is tailored to simulate most radiation detectors so the counting electronics will operate ,
proper'ly. The pulse amplitude is continuously variable from less than 1 millivolt to 3 volts and is displayed on the pane,1 meter.
F. DESCRIPTION OF CONTROLS l I
- 1. External controls I
- a. CPM controls - Three controls determine output pulse repetition rate in counts l (pulses) per minute. j s t (1) Base switch - Establishes basic repetition l rate l 4
(2) Mult. switch - Establishes factor which 15*
multiplied by the base nu'm)*er
, to determine output repetition rate. G '
.O P l 3 ss I
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. .' FANUAL SET l c ;
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. a== E. l. Hctch Nucinar Plant ma=n ~o
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'See Title Page tuvision no Georgia Power d ..
(} See Title Pana 2 of 5 (3) Manual pushbutton - Provides manual control of output repetition rate. One pulse out for each actuation.
- b. Amplitude controls - Two controls determine ['
amplitude of output pulses.
(1) Coarse switch - Establishes the amplitude {
range of the output. g (2) Fine control - Controls meter reading and i
.. amplitude over the range I-selected by the Coarse switch. f
- c. Battery Check pushbutton-Indica
1itude specified in the instrument procedure.
l
- 3. Switch Power switch to ON.
- 4. Depress Battery Check pushbutton.
fall within the marks on the meter. The meter reading,g@gould 4 l
- 5. After using Mini Pulser, switch Power switch to OFF gnd disconnect coaxial cable from instrument under test 4, ;
r~ C:
, \_) 6. Plug power cord into a 115 V.A.C. outlet. This wilkfkeep the battery charged. %dh j c$f
. . EANUAL SET
~ '
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-;S2e Title Pcgs nem,o uo
-- GeorgiaPower A .. .
See Title Pace 3 of 5 .
)
H. CALIBRATION OE_ INSTRUMENT i I
- 1. Connect Mini Pulser coaxial cable to Oscilliscope input. i a
~
- 2. Switch Power switch to ON. {
l
- 3. Depress Battery Check pushbutton. The meter reading should ,
fall within the marks on the meter. ,
f
- 4. Turn Coarse switch to 100 MV. Adjust the Fine control for ,
60 millivolt output, as observed on the oscilliscope. .1
- 5. , . Adjust Calibration control (R22) for a meter reading of 60 millivolts. Record the As Found and As Left reading on Data Package 1.
t
- 6. Turn Power switch to OFF,
- 7. Connect Mini Pulser coaxial cable to_ Universal Counter input.
n
- 8. Turn Power switch to ON. . t
- 9. Check that count rates for all CPM control switch positions are accurate to within i O.1% of switch setting. Record on Data Package 1. Period =_60 see-({} ,
Range CPM
- 10. Turn Power switch to OFF and disconnect coaxial cable from Universal Counter.
i
- 11. If instrument checks out properly, complete Data Package 1, replace the calibration sticker with a new one bearing this test date and when the instr'; ment is due for its next routine semi-annual calibration. .c .
- 12. If the instrument cannot be calibrated, initiate repairs.
t
- 13. Repeat Section H when instrument is repaired. !
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. - MANUAL SET
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aa==at ~o a Em E. l. Hctch Nucicar Plant HNP- 8116
- asw5ioa ao See Tit 1o Pag <.-
- Georgia Power b ..
- 4 of 5 See Title Paon t-PROCEDLFE DATA PACWAGE OOctstNT NO: wJP-B116- t
- - SERIAL NO: ROA-l t
PFL Not 021-N I RTYPE: Cis.14 .
XREF:
TOTAI., 9 EETS: 2 .
FREQLKNCV: 9emt-Annua 11v i
COMPLETED BY:
. 1 DATE COMPLETED:
I kWE REVID.EO THIS CATA RACWACE FOR CCD5'LETENES3 ,
AND AGAlwST ACCEPTANCE CRITERIA IN ACCCi30ANCE W:TH Wd*-830. 8 ACCEPTABLE t#44CCEPTABLE I
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' REVIEWED BY:
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- OATE REVIEWED: %
- 6 REMARWS:
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,' Sao Title Pega 3 ms o uo
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See Title Pane 5 of 5
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i gatA _o ACW AGE __1 MINT.#93MER J_ f* t02 Af t0r4 ,
M.P.L. No. Test Equip. Nos.
VCR.TAGE CNECW 4 As Found As Leet !
Input t e 60 MV RANCE CHECW Range Espectes Pulse As Found As Lef t ,
ICPM) Duration (Period) (Pertod) (Period) l 10 X 1 6 Sec i .1 %
20 1 1 3 see i .1 %
40 x 1 1.5 sec i .1 % . +
90 W t 750 ms i .1 % )
160 X 1 375 ms 11% .
10 X 10 600 ms i .1 %
20 V 10 300 ** 1 1 %
j 40 Y to 150 ms i .1 %
g -
80 t 10 75 ms 1 1 % .
160
- 10 3*f.5 as i .1 %
10 t 100 60 ms i .1 %
20 W 100 M ms 1 1 %
40
- 100 15 ms t .1 %
80 t 100 7.5 me i .t %
160 m 100 3.75 es i .1 %
10 Y tw 6 me i .1 %
20 Y tw 3 ms t .1 %
40 X ik 1.5 ms 1 1 %
80 W tW 750 ps i .1 %
160
- tW 375 ut i .1 % . ,
- 10 M TOW 600 ns i .1 % s l EO W TOW 300 us i .1 %
l 40 W tCW 150 ms 1 1 %
80 E LOW 75 us i .1 %
,,.........................i..
160
- TOW 37.5 us 1 %
is a C09t_ETFD GY OATE
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PROCEDURE I k
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PROCEDURE TITLE I.
HNP-8134 ,
PROCEDURE NUMBER f Lab RESPONSIBLE SECTION l.
I SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
l i
- - _ - - - .. - - - - _ - - _ _ _ _ _ _ _ - - - _ - .. - - _ - - _ - _ - - _ - - ~ . - .. _ - _ _ _ _ _ _ _ _ - - _ - - _ ..___--__.
APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER .
3 General Revision ,
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- REVIGIC CHAT:GCS McCE OF.OPERATIOP! ( )OR No INTE T AS DEGCRIDED IN FSA j ,s
( ) Yes . .
. ' l,
. CHANGE IttVOL.VES: ( ) Tech. Specs. ( ) Neither
"*( ) An unreviewed Safety Guestion (Seo'bacl< for Safety Evaluation if required).
- . .}
~
SafetyRe[sted ( ) Non-Safety Related' ( ) ,
( ) Yes ( ) No Safety /Non-safety Status ChanDe * .
5 form.
Attach mariced up copy of procedure to thi's
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N;w; Signature: .
I L s y, fL 9 rp y L ________.10.-11:12=.. .__-_-________---__
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AS DEGCRIDEO IN FSAR:
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- REVISIC CHANGG-'.f. ODE Cr.CPERATION OR INTEt ( ) No ,
( ) Yes .
, , CHANGE ItWOINES: ( ) Tech. Specs. ( ) Neither
( ) An unreviewed SMoty Guestion -
(See .ba cl< for Safety Evaluation if required). . .
SafetyRe[ated %) Non-Safety Reinted' ( ) 5 d
i
) Yes ( ) No Safety /Non-safety Status Change ( .
- ,.t Attach marited up copy of procedure 'to thi's form.
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4
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e c- .;' ___________...________ _________ _____________ _____ Q2.- _ ________________-_-__ . Q . . _ _ _ _ GI y,m.% - Q., HN.-9 ' YANUAL sg
~ ~om E.1. Hatch Nuclear Plant -oceovas ~o (
HNP- 8134 i uwsom o Sn Title Pags om GeorgiaPower A .ms ,.o Se'e Title Page
- i of 14 y i
WHOLE BODY COUNTER SYSTEMS I i A.- PURPOSE - i To provide instructions for the operation and calibration of the Whole Body Counters (W.B.C.). l , t
- 8. REFERENCES Operating and Service Manual:
- 1. " Ortec, Preamplifier, Model 113. ,
- 2. Ortec, Amplifier, Model 485. .
- 3. Bioassay Program HNP-8021.
I
- 4. Nuclear Data Model 66 Multichannel Analyzer.
~
- 5. Ortec Hi Voltage Power Supply Model 456. ,-
- 6. Ortec Mixer-Router Model 577S.
- 7. Ortec Hi Voltage Fanout, Model P1. .
- 8. Ortec Modular Systems Bins, Model 401A.
- 9. Ortec Model 401A Bin Power Supply.
- 10. Harshaw Thallium drifted Na(I) crystal detector 5" X 4" (Torso).
.. 11. Harshaw Thallium drifted Na(I) crystal detector 4"'X 4" (Lungs).
l 12. Harshaw Thallium drifted Na(I) ' crystal detector 1.5" X 2" (Thyroid).
- 13. Hewlett-Packard 98458 calculator.
- 14. Hewlett'-Packard 9885M Flexible disk drive.
- 15. Applied Physical Technology Series 6000 W.B.C. Mechanical l
Operation, Installation and Maintenance Manual.
- 16. Applied Physical Technology W.B.C. Data Analysis Package
, Program Manual.
l () 17. A.N.S.I. N343-1978 American National Standand For Internal Dosimetry For Mixed Fission And Activiation Products.
~
Relerence ()nly
~
FANUAL SET w-M-
. . . . . _ . . . _ _ . v. . -__
+.a= E. l. Hatch Nuclear Plant aoctov'a ~o H N P- 8134
' ISao Titic Pego navision so a..
See Title Paqe . Geor8aPower A l .. e 2 of 14 ,
)
i C. SAFETY
- 1. Observe Radiation Protection Procedures. *
- 2. Refer to Chemical Safety Manual. ;
D. STANDARDS a The W.B.C.'s are checked daily for energy calibration, when in operation. The W.B.C. uses 3 Eu-152 sources. It is checked annually for efficiency using a variety of mixed standards. Some of the isotopes normally used include Na-22, Y-88, Cs-137, Sn-113, I-131, Cs-134, Co-58, 2n-65, Co-60, Mn-54, Fe-59 and Cr-51. Consult Lab Foreman to decide which to use. E. WHOLE BODY COUNTER
- 1. Description of Instrument, i The Whole Body Counter (W.B.C.) systems consists of equipment listed in C., References. The 3 Na(I) Detectors are connected via high voltage coaxial cable to the high ;
voltage fanout. High voltage fanout is fed directly from the high voltage power supply, model 456. Signal is (]) provided to the amplifier input via coaxial cable from the i preamplifiers. The amplifier output is connected to the Mixer Router via coaxial cable and then to the Multichannel l Analyzer Exit 1 over multiconducter cable and then from the ! multichannel analyzer RS-232 interface output to the Hewlett-Packard 98458 Calculator. The amplifiers, high voltage power supply, Mixer-Router and high voltage fanout are mounted in a NIM-BIN chassis.
"r
- 2. Description of Controls. ,
The controls are listed and described in the operating l i manuals for the respective equipment in the sectiono noted.
- a. Na(I) Detectors - No controls.
l b. Preamplifier - See section 2 of reference C.1, Ortec l Preamplifier M,odel 113.
- c. High Voltage Power Supply - See sections 1 and 2 of references C.5, Ortec High Voltage Power Supply Model l 456.
- d. Ortec Mixer Router - No controls, a
() e. Amplifier - See sections 2 and 4 of reference C.2, Ortec Amplifier Model 485.
- - ge\cies* ()QVj VANUAL SET
~a - EN1)_
.i
*awat ~o
.haon E. l. Hatch Nucinar Plant 8134 l
- HNP- g aavision so
'See Title Page om GeorgiaPower d -- ~e i
g , 3 of 14 V See Title Pace I
. i
- f. High Voltage Fanout - Used to supply each detector with !
a constant voltage (1000 volts). l 9 Bih Power Supply - See section 2 and 4 of refere~nce C.9, Ortec Bin Power Supply Model 401 A. l l
- h. Multichannel Analyzer - See section 4 of references i C.4, Nuclear. Data Multichannel Analyzer Model ND66. {
I
- i. APT Whole Body Counter Chair - See section 3 of reference C.15, Applied Physical Technology, Inc.
- Mechanical Operation, Installation, and Maintenance Manual Model WBC-6000. ;
Modular System Bins - No controls. j.
- k. 98458 Calculator - See Chapters 1 and 2 of Reference C.13, Hewlett-Packard 9845B calculator. (
- 3. Operation of Instrument '
NOTE ',
' These are standard switch positions. Switch positions may vary,
- a. Standard Switch Positions for Operation.
(1) Verify that power cords from all equipment are connected to a grounded 115 volt line receptacle. (2) Verify settings on Thyroid Amplifier are as i follows: - (a) Coarse Gain Knob: 4.0 , (b) Fine Gain Knob: 6.0 (c) Positive - Negative Toggle Switch: Negative (d) Unipolar - Bipolar Toggle Switch: Bipolar (3) Verify settings on Lung Amplifier are as follows: (a) Coarse Gain Knob: 8.0 , (b) Fine Gain Knob: 5.0 O
~~
(c) eositive - ne2etive Teoste Swit e g esetive (d) Unipolar - Bipolar To % h: Bipolar
MANUAL SET
. . . . _ . . . _ . _e. _ _
-ovE E. l. Hatch Nuclear Plant racetovas ao i H N P- 8134 Sao Title Page z.svisiom uo 3
om Georgia Power d ... See Title Page 4 of 14 {} . (4) Verify settings on Torso Amplifier are as follows: (a) Coarse Gain Knob: 8.0 l (b) Fine Gain Knob: 5.5 (c) Positive - Negative Toggle Switch: Negative (d) Unipolar - Bipolar Toggle Switch: Bipolar (5) Verify settings on Torso, Lungs and Thyroid Preamplifiers are as follows: (a) Input Cap. Knob for Torso: 100 (b) Input Cap. Knob for Lungs: 100 (c) Input Cap. Knob for Thyroid: 100 (6) Verify. settings on High Voltage Power Supply are - as follows:
'(a) Power - Off Switch: Power O (b) Voltage Output Switches:.
- 1. Six-position switch: 1000 l
- 2. Five position switch: O
- 3. Ten-turn potentionmeter: ,n.1.
(c) Polarity Switch (rear panel): Positive f (d) Control Switch (rear panel): 4nternal (7) Verify settings on Multichannel Analyzer are as follows: (a) Power On-Off Switch: On (8) Verify 98458 calculator and 9885M Flexible disk drive are' operable. (9) Verify On-Off Toggl'e Switch on Nim-Bin is on. (10) Verify settings on N0575 ADCs are as follows: (a) Conv Gain - 256 b O (b) Coin-Anti-set to Off f,% cod 1 - VANUAL su
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, nevision so See Title Page 3 GeorgiaPower A ,_ o n om .
5 of 14 (./ See Title Page ' I l } (c) Acq-Strb-set to Acq
- b. Po,wer Up (Ortec High Voltage Power Supply Model 456) , {
(1) Check to see that power switch is in the Off . Position. I I (2) Plug the AC power cord into the appropriate j receptacle. , (3) Set polarity switch on rear panel to positive. ; (4) Verify high voltage cable is connected from the output on the 456 to the input of the High Voltage Fanout. j (5) Set the front panel selector switches and potentiometer as noted in E.3.a.(6).(b). l (6) Turn on the power with the toggle switch on the front panel. Instruments are now ready for use. , Chair Counter Operation (]) c. (1) Ver'ify high voltage is energited and adjusted to the setting as stated in E.3.a.(6).(b). l (2) Note that power (ac) is applied to the NIM DIN, s the multichannel analyzer and the calculator,
'(3) For calibration purposes and for normal counting of people the thyroid detector is normally positioned vertically at marker 21. The '
horizontal position should be as close to the individual or source as possible. 'If this >
position is not reasonable, adjust vertically and l l horizontally so that the detector is positioned just under the individuals chin. (4) The chair has 2 motor driven controls to raise the seat' vertically and move the chair horizontally. The vertical adjustment is normally at marker 14 for calibration and counting, unless the subjects lungs do not appear lined up with the lung detector (located on the back rest of the chair). () i
~ ~ .~.-
p#' FANUAL SET
jm . __ N . _ _ . . _ ._ _ L E. l. Hatch Nuclear Plant
~om aaocw e<~o .
' i- HN P- 8134
' amssoNw See Title Page '
om GeorgiaPower A .. e See Title Page
- 6 of 14 '
(]} , e (5) The horizontal control should be in the normal position so the subject can have control over the forward and reverse motion of the chair by l utilizing the permissive lever located beneath the subjectc right hand. The forward position is n o rma l l',- at marker 3-but adjustments should be made if necessary. i (6) The marker positions should be entered into the l computer program when they are called for. ; t . d. Acquiring Spectrum: (1) Select any one of the four memory segments by pressing the ADC pushbutton and obtain one of four memory segments. Press the ERAS button and INIT button to clear spectrum for each ADC segment of any stored data. Repeat the above process to i clear the other two ADC's.
. i l (2) Type in AU-1 and press RETURN to acquire a l
, spectrum. t'
() e. Analyzing Spectrum (1) Using the 98458 calculator type in LOAD "BCGRAP: F8" and RUN. Input data as required by the l display statements. See program document description for details if needed. l (2) After acquiring the spectrum, input into the computer the ADC number and group (ie(1,1)(1,2)(1,3) or (1,4) and press continue and
., the 9E45 will read the spectrum from the MCA. The 9845B Thermal Printer will provide'a hard copy of the results from the spectrum.
- 4. Interpretation of Results NOTE i Refer to ANSI,N343-1978 for additional details.
The spectrum acquired by the.W.B.C. is printed out by the 98458 Thermal Printer. Both the Torso and Lung Detectors identify (11) eleven isotopes of interest. The isotopes are Ru-lO3, Ba-140, Ru-106, Cs-137, Zr-95, Cs-134, Co-58, Mn-54, Fe-59, Zn-65 and Co-60. These isotopes are of majony3 interest because of their long half life (s) and abun_dence. O sy 6
. . MANUAL SET
7 ma=as ~o i V 9m E. l. Hatch Nuclear Plant H N P- 8134 ~! LEYlSION NO f Sie Title Page " ' Om GeoroiaPower D A -. No 7 of 14 See Title Page
) i*
When the analysis is complete the technician performing the Whole Body Count (W.B.C.) will review the printout for any i isotopes or unknowns which may have been identified or If any were identified the cause will be (1) flagged' investigated. Things to look for might include: possible external contamination on the persons clothes or on l their skin. To confirm this, the person needs to shower and j j get another count in a disposable paper suit or other non-contaminated clothing. (2) Contamination on the Whole + Body Counter itself. To confirm this do a WBC on the empty chair. If an unknown was flagged the technician may run the "BCRAP" , program which allows the technician to identify and quantify ; 1 unknown peaks. Once it has been determined that the contamination was not l external or contamination on the Whole Body Counter itself, I i the contamination should be considered internal and based on the % derived organ burden (% D.O.B.) the following a,ction should be taken. t If % D.O.B. is greater than 10% the results should be stored on the computer and the individual should be recounted to (]) . determine his equivalent 50 year dose in mrem. The individual should return within two weeks for a follow up count and every 2 weeks thereafter until, (1) the % 0.0.8. decreases to less than 5% D.O.B. or, (2) the effective half life has been established. After this the yearly program can be reestablished. In addition, the W.B.C. printout (s) should be reviewed for { accuracy and errors and a bioassay program should be : established (i.e. collection of urine samples) as per HNP-8021. The Lab Foreman or Supervisor shaft be consulted to determine whether work restrictions (i.e., individual should not be allowed in R.W.P. areas) or referrals for therapeutic treatment are required (i.e. greater than 100% D.O.B.) i He should also determine the cause of the contamination (i.e. individual may need additional training, respiratory l protection program may need revising, air sampling program may need revising, etc.) and take corrective action if necessary. r NOTE , a If the % D.O.P. is greater than 10% the individual sho 11 d be g-)g ( immediately surveyed throughly for external contami . h ( .-
# FANUAL SET
- _L
ha' E. l. Hatch Nuclear Plant a=<== ~o
., 8134 HNP.
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'See Title Page See Title Page GeorS a Power sk l ..m ~o 8 of 14 J
i If the individual was externally contaminated then another whole body count should be performed. If the second result is demonstrably less than the first, thereby indicating that external con tamination may have been a contributor, further showering and recounting should continue until two consecutive results indicate no significant change. If the results are still greater than 10% then the deposition must be considered to be partly internal and an indirect bioassay should be followed immediately. If individual is ' terminating or leaving Plant Hatch a Lab Foreman or Supervisor should discuss follow up steps with the
- individual before he leaves.
If %D.O.B. is greater than 1% but less than 10% D.O.B. the results should be stored on the computer and the individual should be recounted to determine his 50 year dose in mrem. The individual should return within 2 weeks for a follow up count and every 2 weeks thereafter until the % 0.0.B. is less than 5% D.O.B. or the effective' half life has been established. After this the yearly program can be . reestablished. . In addition,the W.B.C. printout (s) should be reviewed for g accuracy and errors. The Lab Foreman or Supervisor should (' ') determine if (1) urine samples are necessary, (2) work restrictions are necessary, and (3) retraining of individual is necessary. If % D.O.B. is less than 1% D.O.B., the results should be stored on the computer. The cause for the internal contamination should be determined and corrective actions taken, if necessary, and the individual should be made aware of the contamination. Consult Lab Foreman or Supervisor to ' - see if other than yearly W.B.C.'s should be done. Some low level Cs-137 contamination could be caused by consumption of wild game such as deer, squirrel, quail, etc. that consumed Cs-137 from the fallout of atom bomb blasts in previous years. Normally, the computer printouts are stored in the l individual's dosimetry file. l
- 5. Daily Calibration
- a. Verify that detectors and controls are operating as per section 3., Operation of Instruments. ;
t l t I
~
lo . s
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MANUAL SET y-L_.
%om - E.1. Hatch Nuclear Plant eaoccovac ao H N P- 8134 LEWSON NO
'Sre Title Pagn om GeoroiaD Power d . No See Title Page - 9 of 14
- b. Remove the chair cushions and position the bottom half of the Phantom in the chair. Center one of the Eu-152 calibration sources on the thyroid detector. Position the other two Eu-152 sources on top of the Phantom ,
centered in front of the Torso and Lung Detectors ! respectively. Then position the APT WBC Chair Model 6000 front-to-back at 3, seat height at 12 and thyroid detector at 20. Then acquire spectrum as per section 3.d.(1) and (2) with a count time of 300 seconds. '
- c. Using the 98458 calculator type in LOAD "BCECAL: F8" and RUN. Input data as required by the display -
statements. The purpose of this program is to provide 3 a means by which the energy response of the W.B.C. - 6000 may be calibrated for each detector. After the spectrum has been acquired including five well defined gamma peaks per detector energies being 344 Kev, 779 Kev, 965 Kev, 1100 Kev, and 1408 Kev the calculator , calculates the approximate location of the peaks and the technician is given the chance to correct the peak's centroids by computer entry. These centroids are used as the data points in a linear regression L analysis to determine the energy coefficients (i.e. energy offset (Kev) and energy gain (Kev / channel). The C>) ~ Technician is given a chance to store these energy coefficients for daily use. The print out is stored as the " Daily Energy Calibration Program" of this procedure in Documentation.
~
- 6. Annual Calibration NOTE .
l Normally the WBCs will be calibrated with four# - isotopes; Ce-139, Y-88, Sn-113 and Cs-137. Consult the ! Lab Foreman as to any changes in the above. Refer to l Reference No. 16 for directions to the proper operation of the computer programs,
- a. Verify that detectors and control are operating as per section 3., Operation of Instrument.
l b. Using the 98458 calculator type in Iced "8CEDAT: F8" and RUN. Input data as required by tte display. The purpose of this program is to store data for the calibration standards to be used by the standard calibration program. Data input will consist Isotope Name. Energy, Assay Date, Dis /sec., l Fraction and Half-Life for each source use the O cetibretiom. ik.
. WANUAL SET
Fame E. l. Hatch Nuclear Plant =c t =*
- I
. . H N P- 8134
[ Smo Title Page REWSKA W o.m Georgia Power d .. . See Title Page 10 of 14 O
- c. Remove the chair cushions and load the lower torso of the phantom with three one liter bottles of calibration standard. Set the upper torso part of the phantom on the lower part. Load the phantom with two one. liter b'ottles of calibration standard, insert tops onto the phantom. Insert the thyroid phantom and load with one 15 ml vial of calibration standard. Move chair into standard calibration position.
Acquire a 300 second spectrum for all detectors. NOTE For all counting on the WBC-6000 chair, the front to back should be set at 3, the seat height at 14 and thyroid detector at 21.
- d. Using the 98458 calculator type in LOAD "BCSTND:F8" and l RUN. Input data as required by the display statement.
The purpose of this program is to compare the total observed counts produced by a calibration standard with the known amount of the particular isotope used to generate the spectrum which allows the determination of the efficiency of the system for detection of the () isotope. , [- NOTE (The lower torso and thyroid are counted in conjunction and a seprate count is done for the lung detector without the source being placed in the Phantom Torso and Thyroid, perform section b.c for each). The sources used are from section D Standards. As a result both the efficiency and resolution are stored for each isotope for each detector. s
- e. After completing step c., then type in LOAD "BCEFF:F8" l l and RUN. Input data as required by display statements. The purpcse of this program is to calculate the efficiency results from the efficiency stored in step (d) for each detector (i.e. efficiency l as a function of energy). These efficiency parameters
[ are stored for each detector for use by the "BCGRAP" l program.
- f. After completion of step e., then type in LOAD "BCRES:F8" and RUN. Input data as required by d. play statements. The purpose of this program is to; , l
. . calculate the resolution results from the resp,lution stored in step d. for each detector (i.e. FWHL4*(MEV) as Os a function of energy (KEV)). The resolutigdFparamaters are stored for each detector for use by 1(e'"OCGRAP" program. <dhe -
i VANUAL SET l . p u_.. ._ _ .- , r - -_ _. -
Amac - E. I. Hatch Nuclear Plant =a== ~o
- H N P- 8134 f Sea Title Page LEvtSION NO om Georoia D Power d ..m ~O See Title Pace 11 of 14 .
- g. The calibration data will be a computer printout titled ,
(Daily Energy Calibration Program) and stored in documentation after the Lab Foreman okays its release
~
f to documentation. 4
! i
- 7. Source Check ; ,
i The Torso a'nd Lung detectors will be source checked on a l routine basis. The activity detected by the detectors will be compared with actual activity. The rotation and calibration of standards will be maintained by the Dosimetry Staff. The standard calibration sources are the isotopes listed in section D., Standards. t
- 8. Guarterly Crosscheck Analysis
- a. On a quarterly basis, a vendor will ship us an unknown sample to be loaded and counted in our whole body 4 p
phantom.
- b. The phantom will be counted, with sources loaded, in the routine fashion (see section E.3, Operation of -
Instrument). Upon completion of measurement of these unmarked
~
c. sources, the plant personnel will report by Figure 1 (Crosscheck Report) the results for the source values to the vendor.
- d. The sources will also be returned to the vendor upon completion of the measurements.
- e. The vendor will compare the reported values to the actual source values to determine if the reported values are in agreement with the actual' values.
- f. The basis for this agreement will be the NRC's
" Criteria for Comparing Analytical Measurements",
Figure 2. ,
- g. Afterthehvaluationoftheplantreport, the vendor will write a letter report to the plant certifying the agreement or non-agreement with the known source values.
- h. This letter from the vendor will serve as evidence of calibration and procedure verification and stored in ,
Documentation as the "Crosscheck Report".
~
- 1. Thisprocedurewillberepeatedeachtimethatk) I
, () verification is required.
. NUAL SET l . 78M 8 8, . _ _ _ . _ _ _ , . _ _ _ . ,,,...m.___ _ - _ . _ _ . _ _ . , , . , , _ _ , . _ _ _ _ _ . _ . _ _ _ _ , _ . -
+ _, _ .. - . . _ _ _-_
W moa E. l. Hatch Nuclear Plant aw a =ae~O HNP- 8134
'S2s Title Pag 2 LEvissON NO om Georgia Power sk O See Title Page '
12 of 14 - O G. FREGUENCY OF WHOLE BODY COUNTS All personnel assigned to Plant Hatch should have a whole body count as soon as practicable following assignment. This w'ill be the baseline count. A final count should be performed prior to termination or transfer from Plant Hatch. All personnel should have additional Whole Body Counts on a yearly basis. However, if internal contamination is suspected more frequent Whole Body Counting should be done as recommended by a Lab Foreman or Supervisor. All,.nonfacility personnel (i.e. not assigned to Plant Hatch) including visitors and contractors personnel who enter bio-assay areas (i.e. R.W.C.U. pump rooms, Radwaste drum lines, Airborne Areas, etc.) should have a preliminary count (before e".tering the area) and a final count (after leaving the area for the last time) unless otherwise directed by a Lab Foreman or Supervisor. Any visitors or contractors personnel not' bio-assay areas do not f ' need a Whole Body Count. .
. NOTK See Management Memo #45 for clarification of whole body counting requirements.
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I"**v4 E. I. Hatch Nuclear Plant e=u== ~o i H N P- 8134
,Sne Title Pego s.evisio= ~o om GeorgiaPower A. ..o. ~o See Title Page . 13 of 14 FIGURE 1 CROSSCHECK REPORT '
I i
)
i i SOURCES USED; ( )Co60 ( )Cs137 ( )Other f. I 1 I i RESULTS:
~
Lungs and GI .uc i Thyroid uti i i t COMPARISON: ( ) Agreement ( )Non-Agreement 1 c-I REMARKS: s i s ,- COMPLETED BY o. DATE___
- l. O i, , MANUAL SET l PtBGG A S
. .. _ - --- . . ~ . . _ , . - . . , . . . . . . . . - . . . - . - . , _ . _ __ . _ _ , _
1"rc E. l. Hatch Nuclear Plant =ctov= ~o
' HN P- 8134 +
umio= ~o ; Sao Title Paga ' om See Title Page - GeorS i a Power 1 - ~o 14 of 14 O
- FIGURE 2 ,
t CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS ; i This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program. In thes'e' criteria, the judgment limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated uncertainty. As the ratio, referred to in this program as
" Resolution" increases, the acceptability of a licensee's measurement should be more selective. Conversely, poorer agreement must be considered acceptable as the resolution decreases.
~
LICENSEE VALUE [
. RATIO = ------------------- g-NRC REFERENCE VALUE POSSIBLE . POSSIBLE RESOLUTION AGREEMENT AGREEMENT A AGREEMENT 8 - 3 0.4 - 2.5 0.3 - 3.0 No Comparison 4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 ,
8 - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 16 - 50 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 ' 51 - 200 0.80 - 1.25 0.75 - 1.25 0.6 - 1.66 200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33 (
- e. s "A" criteria are applied to the following analyses: {
Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Kev. , Tritium analyses of liquid samples. s "B" criteria are applied to the following analyses: Gamma Spectrometry where principal gamma energy used for . identification is less than 250 Kev. 89 90 o .. O se emo se oeter-i= tioae-same
- Gross Beta where samples are counted on the same date using'hhe Cv reference nuclide. %,tf chkuAL su
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.i J GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Alert - Shift Sugervisor PROCEDURE TITLE .
HNP-4530 PROCEDURE NUMBER Lab RESPONSIBLE SECTION NON-SAFETY RELATED ( ) SAFETY RELATED ( X) APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION HEAD MANAGER p---__--. -------- 3 Page i [ g J g 4 . -P_a.ae -- _1 _ - _ - _ - _ - _ _ _ _ - .___ _ _- < - M _--_-_- - _- -_. . /- -[ [-
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Revision No. _ 3 RFCU: P.TFD GY Dr P.^.R T'fINT HF,' O P P: <OW.r . ) Nr.me; Date; Signature: Date: l Y M O' IM ' r['t'ide . E. > Y 2-
- REVISION CH.^,NGES MODE DF .CPERAT3DM OR JNTENT AS DEGCRIDED IN FSAR:
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( K) No . CHANGE 1NVOLVES: ) Neither
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) An unrevi.ewed Sefety Guestion 4 J Tech. Specs t 4
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(See back for Safety Evaluation if required)..
.SafetyRe[ated (Y) Nnn-Safety Related ' ( ) ,
Safety /Non-saf ety Status Change ( ) Yes ( h No -
-Atkarh marked up copy of procedure -to -this form.
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l E..**./.A.. :..t ;.'.T..i.r..W GA..f..r.I..T.Y_ The revision of this orocedure does not constitute an unrevie.7ed : 2fetv ..'
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- question as exclained belcw. -
1._ The nro_5_a.5ility of occurrence __and thg_g.o.ngquencas _of an accid _ent or ralfuncticn of eaui- ent imoortant to safety ara not increased 2bove th--a analyz_eJ;l in the F.S AR'du_e_1g_1.bfS.e. rbanges be.cAuse the revision does_not chance the ourcose or perfor ance of the system. - Th'e oossibility of an accident or malfunction of a different tvoe
~
2. than analyzed in the FSAR does not result from this chana._ebecause _, the sys_ tem resconds and is operated as before the chance.
~
.__, 3. The marcin of safet.y as _defin_e_d in the Technical Soecifications is not reduced due to this revision because the revision does not - -
b,-n
- - - - chance anv limited safety system settinos which would allow a __
safet'y limit to be exceeded or to allo.r a limitino condition for ocerations to be exceeded as stated in' Technical Soecifications.
~ *
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< ~om E. l. Hatch Nuclear Plant moaan ~o
- H N P- 4530 Sne Titio Page uvisio~ ~o
... Georgia Power d ..m ~o gj See Title Page . 1 of 1 ALERT - SHIFT SUPERVISOR A. CONDITION-Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline (P.A.G.)
exposure levels.-
~
B. REFERENCE . HP-4520. C. ACTION
- 1. Proceed to control room.
- 2. Assume the duties of the Emergency Director until relieved, see HNP-4540 for actions.
m 3. a. Evaluate actions of Shif t Foreman and operator to bring
.j emergency under control.
- b. Assure correct emergency classification has been g declared as per HNP-4520.
- 4. Consult with Shift Foreman and STA to determine if a more severe emergency class should be declared. Refer to g
- criteria in HNP-4620, 4720 and 4853.
- 5. The Shift Supervisor is responsible for notification of Plant Management and NRC as per emergency call list and other offsite agencies in accordance with notification l procedures HNP-4861. The actual notification process may be l, delegated to other, specifically, trained, shift personnel.
l.
- 6. Augment shift resources as needed to assess and respond to the event.
~
- 7. Make .a safety assessment to determine if personnel not ihvolved in the emergency recovery effort should be
. . . evacuated. If possible, consult with Plant Management concerning this evacuation. ,
') .. 4 9 -[,. -
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a GEORGIA POWER-COMPANY HATCH NUCLEAR PLANT PROCEDURE SITE ARFA EMERGENCY - RADIhLOGICAL FMERGFNCY TEAM PROCEDURE TITLE HNP-4623 PROCEDURE NUMBER LAB RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 1 Page 1 (, y 3} fs)-
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A-PROCEDURE N'0". IINP - _8ge_2]-__- --__ i e m Revision No.____1_________ _-________--__---__--_ ---__--_--_____1.______----__. , Of_P_AR_TM_E_N_ _ T _t_-tF_,' _-- 0 A_P_P_:--< OV_ A_t . ________-__R FOUF.F.T-- F_D D_Y - - Date:
- Datel Name*
Signature: l _eL..____. # ESW
.-.,., ____R ic_k ~GTh_______--__1_zi
/7 - - _ - - -
I REVISICM CHANGr.O MODE OF .CPERATION OR INTENT AS DEGCR.OCO .IN FSA ( ) Yes . (g) No ' '
'. CHANGE INVOtNES: ) Tech. Specs. ( M Neither f.
'C ) An unreviewed Safety Guestion (- '
(See back for Safety Evaluation if required). . .
~
SafetyRe[ated Non-Safety Related' ( ) - e. No Safety /Non-safety Status Change ( ) Yes ( k) . a
. Attach marked up copy of procedure to thi s form. .
REASON FOR REGUEST _ -- -_ fe5Cw De_%. M N & 4.
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[ .. i - - - =t i ed :.1fety The_r_e_v_is_i_o_n of _this o.r_oced.u._re_ does n.o_t const tu e an unrev ew _--ques_ti on ---- a s. .e.xpl.a..i.ne_d _b el ow ._--__ 1.----Th e probability of occurrsncq and ths c.qn..Secuences o.f.-an _acc.i. dent d f eauicment importan -------.t. to - - sa- - fe _- tJi a re no t i ncrea.s e _-_ --- m.--_un.c.- or al f - tion_.o.---- - ---- m above those ana.l'Jm zed in-mthe_F.S. AB d_ua 10. th.aS.a CbAD. CSS _b.cW" Se. ' e _ _ _
------- the revision does not_. chance the nurnose or_p_, rformance of the - -
- sX. stem.
- 2. Th'e possibility of an accident or_ malfunction of _a different tvoe than analyzed in the FSAR does not result from t_his chance because -
- - - ~ _
the system responds and is coerated as before the chance.__ __-- -_---___ -- ~
~
The marcin of _ safety as defined in the Technical Soecifications s 3.
- - - - - no.t.-----
h, . ____i_s_not _ reduced due to this revision beca_u_se the revision doe
--- U- .__
chance - ------_ any limited safetL' system sett.inos which would all.o.w a
-- - -- - - - =-
safet'Y._l,_i_mit to b_e exceeded or to allow a limitino condition fo_r___ o.Lerations to__b_e_ exceed _ed _as state _d in' Techni_ cal Soe -- - s . - t _--_---------------------------------------Qnu-- t-
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hom E. l. Hatch Nuclear Plant aaoa = = ~o l H N P- 4629
, Sao Titlo Page r ewsio= ~o om Georgia Power d ..
See Title Page - 1 of 1 g SITE AREA EMERGENbY - RADIOLOGICAL EMERGENCY TEAM NOTE This proced'ure supercedes HNP-4609 Revision 3 dated 8-31-79. A. CONDITION Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed PAG exposure levels, except near the site boundary.
'B. REFEHENCE HNP-4620. _
C. ACTION .
- 1. Report to the Operations Support Center, carrying as many survey instruments, friskers, and air samplers as you can.
a NOTE It is extremely important that you move as expeditiously as possible.
- 2. The Operations Support Center Manager will choose a Rally Point Leader.
- 3. The remaining members of the Radiological Emergency Team will, by assignment of the Operations Support Center Manager:
- a. Assist the Rally Point Leader in performing Rally Point or Personnel Surveys,
- b. Serve as Rescue Team Leader's, and rescue team members. l l c. Serve as Internal or External Survey Team Leaders, and Survey Team members, d'. Standby to give other assistance as directed.
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o Q GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE - SITE AREA EMERGENCY - SHIFT SUPERVISOR _ PROCEDURE TITLE HNP-4630 -. PROCEDURE NUMBER LAB RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( ) F APPROVED APPROVED DESCRIPTION DEPT. PLANT DATE REV. HEAD MANAGER e
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PROCCDL'RE td. H.'P _*((z 3n , b. 2. Revision No. ----------_ --
-------- ----- ------ _ - - - - - _ J~ _ ----------
R TME, NT HF, .O t.P Pu nV.:.t . RFCU::STFD GY ----------
.--------t DPP.--- - - - - - - - - - - - - - - - - - - - -
.--.---_--------------- Date; Signature: Date:
N;.me ; NJA'~ ____t. L-_ u h -- _ _ _ _ - n/q$t --- ---- _-- g w ---- -- - - - - - - . . - REVISICil CHr-.N. GCO.. MODE 0F .CPERATICtl (OR INTENT No AS DESCRIDED IN FSAR: . ( ) Yes . t . .
', . CHANGE IrlVOt.VES:
( ) An unreviewed Safety Guestic.n (See back for Safety Evaluation if required). ( ) Tech. Specs. ( f Neither 5 SafetyRe[ated (h Nnn-Safety Related ( ) . Safety /Non-safety Status Change ( ) Yes (g) No .
~
Attach inarked up copy of procedure to thi's form. REASON FOR RECT.'EST_J1[ b,dncu - jf,_ t/3 [ -- - b_ _ C . 3 _ a, h. l A .
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. .u.e_s_t_i_o.n _ a.s.__e x_pl_a_i n_e_d__b e_l o_w ._______
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-- _ - _ . _fe_ty a._re__no t i nc_r_ea s
_a.hpve _t.hgn._a.naly.ut d _in .thg_U3Ehu.e_19._ttne..chaosas_hecusa . _ _ _ _ _ _ _ _ the _r_ev__is_i_o_n d_oes not__c_h_ ance the nur.9ose or nerformance of the s_ys tem.
- 2. T_h_'e possibili ty o_f__an accid _ en_t or mal _ fun _ction of_a_ __di ffere_n.t._tvoe than_a_n_a_l,yzed in the FSAR does not result from this c,ance_because
- - =-
a. the sy= stem resconds and is ooerat__ed__a_s_b_e_f_o_re the chan.c.e.- - - _
-- =
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- 3. The marcin of safety as defined in the Technica_l So_e_cifications -
is not reduced due to this_r_e_v_ision beca_use the_.r.evision___does no.t______-
- - - - _.__ chan_ce_.a.n.y.__ limited _ safet'L_s_ _-ystem
-- sett.i.nos_
- _- which would all_o_w a ___
_ safetL_l,.imit to be_ exceeded or to lal ow a limitino_ condition for o_oe. rations to b_e exceede_d__as stated _in' Technic _a_l _Soecification __ -_ ___ _ ________n_ . M _ _ __.._______ _ ______________________________________ q =___-_- _ s__ ~._ _ __ _a ' 9'
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-E E. l. Hr.tch Nuclear Plant HNP- 4630
, uvmon ao See Title Page ~ 3 J om Geor8 a Power d l
1 of 1 g's See Title Page SITE AREA EMERGENCY - SHIFT SUPERVISOR _ A. CONDITION ) Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed PAG exposure levels, except near the site boundary. B. REFERENCE HNP-4620. HNP-4720. HNP-4740. HNP-1. C. ACTION
- 1. Proceed to control room.
room, ensuring
- 2. Take control of all activities in the control
~~~ that proper coordination of all activities is carried out.
l
- 3. a.
Assume the duties of the Emergency Director until relieved. Assure that those actionsroom in HNP-4640 which are accomplished. can be performed from the control
- b. Assure correct emergency classification has been declared as per HNP-4620.
4. Evaluate actions of Shift Foreman and operator to bring emergency under control. 5. The Shift Supervisor is responsible for notification of Plant Management and NRC as per emergency call list and in accordance with notification other offsite agenciesThe actual nofitication process may be procedure delegated toHNP-4861. other, specifically trained, shift personnel.
- 6. Consult with the Technical Support Center and Emergency D.irector'to determine any outside assistance needed.
- 7. Assure that personnel are assigned to maintain an open line to NRC, T.S.C. and E.O.F. and inform these groups of significant plant changes. -
B. Escalate to general emergency class (refer to HNP-4720/and f 4853), if appropriate. []pF6 9. ProvideinformationtotheEmergencyDirectortoffksistin his determination of close out or reduction of$the emergency class.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT -
. PROCEDURE General Emergency - Radiological Emergency __ Team PROCEDURE TITLE HNP- 4729 PROCEDURE NUMBER Lab RESPONSIBLE SECTION NON-SAFETY RELATED ( )
SAFETY RELATED ( X) (-----..------------------- APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION HEAD MANAGER 1 Page 1 Deletion of page 2 A p [-[ o*f hg;
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ft1 2~ _ V c2= -W--- -_____ AS DEGCRIDED IN FSAR: REv.tSIC': CM.*GES MODE O. .CPERATICM OR INT.. ( ) Yes . ( ) No
.- CHANGE INVOL.VES: ) Tech. Specs. ( R) Neither
'( ) An unreviewed Safety Guestion (See back for Safety Evaluation if required).
( 7 Non-Safety Related . (
)
Safety Related p) ( ) Yes ( ) No
' Safety /Non-safety Status Change -
Attach marked up copy of procedure to this form. REASON #CR REGUEST _ d .'5. 6 4,l )-- d.v.ar_W_ Tce_ Me nt.bcG __ CL!
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___ue_s_t_i.o._n_a_s expl ained belcu. 1_.__T_h.e_2r_o_b_a.b._i l_i_t.'l_o..f _o_ccu_r_renc_a _- .a._nd_ t_h.e. c_q.n.w.a_u_e_n_c.e.s o o_f_a n__a_c_c_i d_e_n_t__ -_ or mal fun'ction o f eau $' omen _t_i_m.por_t_a_n.t. t_o__s_a_fe_ty-__are__not increased abo.n_t_h.n.e ana1v::nd._in_.tha_Es33_d_u.e_to._t;tne..rAcoras_he.cssa- =-- . ____ - t_he__revis_ ion does n_o_t_c_h_a_n.c.e_ the ourcose_or oerformance of the system. t .
~
- 2. Th'e nossibilit.y of an accident __o_r.m. alfunct_ ion of a differe_n_t_t_yce . _
than analyzed -n in the FSAP, does not result from this chanc_e because the system responds and is onerated as before the chance.
=.--%
- 3. The n'arcin of safety as defined in the Technical Soecifications -_
e is not reduced due to_this revision because the revision ___does not
- 1- . chance anv limited safety _ system set _tinos which would _a_1_1_ow a safet'l'__l,.imit to be exceeded or to
--_. allow
-- a .l.imitino condition for ooerations to be__ exceeded as stated in' Technical Soecifica_tions.__---_--_ - _ _ - - - _
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1 HNP *3 l ;J - , , . . ji . MANUAL SET l .E,, (.L." .n ._g , -
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E.'I. Hatch Nuclear Plant raou wasao 1 H N P- 4729
.- Sue Title Page , newsio= ~o om .
Georgia Power d m mo See Title Page , 1 op 1 l GENERAL EMERGENCY - RADIOLOGICAL EMERGENCY TEAM
~
NOTE This procedure supercedes HNP-4709 Rev. 3 dated 5-13-78. A. CONDITION Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Release can be reascnably expected to exceed PAG exposure levels off site for more than the immediate site area. B. REFERENCE V%F-4720. C. ACTION
~~~
- 1. Report to the Operations Support Center, carrying as many survey instruments, friskers, air samplers as you can.
s NOTE It is extremely important that you move as expediciously as possible.
- 2. The Operations Support Center Manager will choose a Rally Point Leader.
- 3. The remaining members of the Radiological Emergency Team will, by assignment of the OSC Manager:
- a. Assist the Rally Point Leader in performing Rally Point or Personnel Surveys. '
- b. Serve as Rescue Team Leaders, and Rescue Team Members.
l
- c. Serve as Internal or External Survey Team Leaders, and
' Survey Team Members. ' ~
- d. Standby to give other assistance as directed.
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d a GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDLIRE General EmprS_en__eZ - Shift'SuD.ervisor
, PROCEDURE TITLE HNP-4730 PROCEDURE NUMBER Lab -.
RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )
- - _ _ - - . . _ - - - - - _ - - - _ - - _ _ _ _ _ - - . .-----_------_-_- L------_---__----, ,--_----
APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 2 Page 1 . f f'~ g .--,--
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( ) An unreviewed Safety Guestion ( ) Tech. Specs. (,() Neither (See bacl< for Saf ety Evaluation if required).
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- 2. The possibili_t.'i_o_f an accident _ or ma.l. function' of a different tyce . -_ _.
than ana_lyzed in the FSA_R__do_e.s..not result from t.h.is chanc_e because the _s1.st.e.m. resconds and is _c_oerated a.s. before the chan_.ce._
- 3. The marc _i.n. of .s._afety -- ----- as _d_e. fin.e._d in the Technic _a_ l_Soecific_at, ion _s__
is not reduced due to this revision beca_u_se the revision _. don _n_oc__ ___ chance __a_n_y limited safet_y system settinas
--- _which would allo.r a_ _ _ _ _ _ _ _ .
s a f.e.t'y.nl -- i.mi t_ _to b e e_ _xc ee d e_ _d or to a l l o.-t a limitino condition for _
.o_Perations to b_e exceede.d. as stated _._in' Technical Snec 9 -
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a E. I. Hatch Nuclear Plant ae aom raxe==< ~o
, HN P- 4730 Sto Title Pegn '5 *
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3 o.,, Georgia Power d .... . See Title Pa'e a ' 1 of 1
. GENERAL EMERGENCY - SHIFT SUPERVISOR A. CONDITION.
Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Release can be reasonably expected to exceec PAG exposure levels offsite for more than the immediate site a'rea. B. REFERENCE HNP-4720. HNP-4740. HNP-1. C. ACTION
- 1. Procede to control room.
- 2. Take control of all activities in the control room, ensuring
~--
that proper coordination of all activities is carried out.
- 3. a. Assume the duties of the Emergency Director until the l E.O.F. is established. Assure that those actions in HNP-4740 which can be performed from the control room are accomplished.
- b. Assure that correct emergency classification has been declared as per HNP-4720.
- 4. Evaluate actions of Shift Foreman and operators to bring emergency under control.
- 5. The Shift Supervisor is responsible for notification of Plant Management and NRC as per . emergency call list and other offsite agencies in accordance with notification procedures HNP-4861. The actual notification process may be delegated to other, specifically trained, shift personnel.
- 6. Consult with the Technical Support Center and Emergency Director to determine any outside assistance needed.
- 7. Assure that personnel are assigned to maintain open line to NRC, T.S.C. and E.O.F. and inform these groups of $\
(j)*J
.significant plant changes.
- .q,
. 8. Provide information to the Emergency Director togassist in
- he emergency hisdeterminationofcloseoutorreductiono{g$
class, as per HNP-4720. l 43S,L
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{ NOTE 4 1, %^ ll g This procedoro supercades HNP-4503 Revision 6 dated 2-23-81. i. f A. rnMn1TTnN s> [ An sM alarms or local dose rates as indicated by other
,- .m +-"mants are about 10 times higher than expected or air Q~ activity is greater than 1 MPC (particulates and iodines and
'? ' " access is uncontrolled).
. . ~ ,
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. N.OTF.
- . = - .
e This action is to be taken by Health P,hysics (HP) personnel e, whenauer possible or by other trained personnel when HP is y not available, u d 1. Obtain the following equipment as necessary: 6
- High range dose rate meter ,
'j High range dosimeter f GM survey instrument and wipes g Full face respirator g Protective clothing p( Air sampler
.} P. Turn instruments on and allow them to warm up.
7 Proceed toward area where the Radiological Event exists f making survey as you 90. If survey indicates the need to do y
? so, don the protective clothing and the respi'ator if S necessary,
,)
- sa y NOTE v:
, t all times adhere to the limits and guidelines in
- HNP-4866, a, r F,}f3: _
t "
- dc a. If any of the following readings are observed, retreat
'L' immediately and notify the Control Room; f.VMp; . ,
;$4 Beta, Gamma - Any reading above 5 r/hr.
'4
- Contamination - 10,000 cpm above background on a wipe,
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'M y MANUAL SET
-s 700820
- 44 wv= E. l. Hatch Nuclear Plant .=u=a= ~o 4324 ' ' .,~ .
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- wn ';+1e Pnao nevision wo Georgia Powerkn i -- N' 2 I e m ..- ~e
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4 rawe samples taith an air sampler if conditions permit. 1 x 5, Determine cause of high local activity and notify Control [ Room, 'TG conditions indicate that a higher emergency A- classificatinn avis +s notify the Shift Foreman and discuss x declaring the upgraded emergency M j $, F. . Rope O H- and post areas of high air activity or radiation as
; .; n .ci tons permit and clear area of personnel vaere 1
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~' Jr ..;- _. 7. .Using HNP-8005 and HNP-8006 procedures to control local l I'/Z[. ~ contemination and radiation when recurning to normal.
J[g a,et. ianen requaetad, the Shift Fo: eman in evaluating
.[ , r ; any to determina 4.f any radioactive material released 3
! .. 'm -he olant will cause the action levels in HNP-4853 to l I .W, .w .o c e e o'e o , ,
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Mw h HATCH NUCLEAR PLANT - 9...
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. :N . Notification of Unusual Event-Rescue Team l .
PROCEDURE TITLE s 1 1 HNP-4428 i i PROCEDURE NUMBER
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Lab l, ' RESPONSIBLE SECTION s.o. . ,-..m-n a . .~ . . 3 0.; . . - 4., SAFETY RELATED ( X ) NON-SAFETY RELATED (' )
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.t.
REV. DESCRIPTION DEPT. PLANT DATE
- o. HEAD , .ER 4 - _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .__ _____ _______
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.. R EV C : GN C H ,N .C MOC.I CF .CP ER AT I OM OR INT'ENT A" CEGCRIDED IN FSAP.:
l E ( ( ) Yes . i .-
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l M- CHANC.E INVCtNES:
) An unreviewed Safety Guestion ( ) Tech. Specs. ( L-t'~NN the r
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i f.Y;[ 14 '.-' R e l a t e d ( <_ -) Non-Safety Related ( ) s.
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) Yes ( 40 i 3;E,,, ty/Non-safety Status Change (
W !,*r . Attach marked up copy of procedure to this f o't m . - u RE/,5CN FOR REG!.'EST - - _ --
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i __,______the revision does not chance the nurgose or p_erformance of the -
,7 ,. -
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n . w w N- 2. The nossib.ilit.y of an accide_nt or malfunc_t_ ion of a differe_nt tvoc_ g .---- ---- -
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than a_nalyzed in the FSAP. does not result from this chanc._e_becau._s_e___ -- - - . .
=- --
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is _not r.e.duced due to this re.v. ision becau.se t'h.e .r.evision do.e.s. not chance-- any -_l_imited safety system settines which would allo'.s a
=
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h safet'y, l,.im.it _to be exceeded or to al_ low a limitine co_ndi.. tion fo_r
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e HW -9 i W i MANUAL SU , m )- - \
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M*-'.pmova E.1. Hatch Nuclear Plant a = =ai a HNP- 4428 ' [ I' h Ti+1a ' Panpl KEvi$10N NO
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g NOTTFTCATTOM OF UNU5UAL FUENT-RESCUE TEAM
,",~ A, ('nNOTT1ONS t ,, i
- g. 1 Jnu su a l avants ara in process or have occurred which indicate a
@ notential degradation of the level of safety of the plant, such f- % v, n nn+nd in HNP-44PO, Table 1. No releases of radioactive j ,.
n.s t e r i a l requiring offsite response or monitoring are expected
, f, . .,,,.3, atrther degradation o& safety systems occurs.
l Q'h
! p '_ . 'O. PrFERENCE -
L _. 5 8NA-4420 y c,_. -N f U ~~t r m descue Team;
*h,J-J'b a, Laboratory fornman or supervisor' designates a member of f the Health Physics staff to be Rescue Team Captain.
I .. b. The Rescue Team will comprise the following; j Survey Man , g.- I J ., Stretcher Bearer 4 1
.p.
7 Stretcher Bearer 42
., Stretcher Bearer # 3 w
# ;. c. Rescue Team Captain leads team in the rescue effort.
; i.--
?,
(~ Orass out in protective clothing located in the assembly 6 room (Service Building), if time and the situation permits. J' ' Ant'i-C Coveralls.
-g. Shoe Covers A ., Rubbers
/ Hood l' 5, s. , Respirator (self-contained)
'((
M1
-j High Range Pencil Dosimeter TLD Badge
.44
,6 3. Survay Man carries GM survey meter and high range survey NC meter, Team Captain carries walkie-talkie and remains in r L', contact With Laboratory forman or supervisor and/or Shift t Fnroman, ,
( ,O . , h . cy :
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, A., Oetermine nenhabla location of victim from Shift Foreman.
I s, { } 5, Procead with rascue. l 3 .* a. Stretchar bearars carry: l T Stretchar
,f none and tackle, if requirad for rescue Pinch bar, if required for rescue
..' ' '- t ar e t aid kit s.
*^
. b. Start using respirator while approaching building.
- w:
}
; j Retreat if dosimeter reaches 2 R and victim has not
; i. _ been located.
;r3
- d. Limit dose to membe rs o 4- Rescue Team to limits and g, guidelinas in HNP-4812 and HNP-4866 in effecting rescue.
d
- e. Perform necessary first. aid measures for victim but L, '
move rapidly when dose rates are high. Move victim j into Oecon Room and decontaminate if possible, as per NNP-4802 and HNP-4803.
.4 R 6, Inform Control Room of condition of victim. Assure that
, *i. Shift Foreman has notified hospital that the victim is or is
? not contaminated.
4 7, Move victim to ambulance.
-[
7: a, g- Arrange for radiation technician to accompany victim to
.- hospital in ambulance.
lh j.'c 7 Notify a laboratory supervisor as soon as possible.
- f, 10, Taka necessary measures to limit spread of contamination and
,.[' report to the Laloratory 2 Forema'n or Supervisor and Shift i
py Foreman when completad, e.yo ..
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s 7"w. %TCH NUCLEAR PLANT fL' .
..' PROCEDURE k;
n r40'rIFICATION OF UNUSUAL EVENT-SHIFT SUPERVISOS -
.. PROCEDURE TITLE W: .-
E' - HNP-4430 PROCEDURE NUMBER 4 ..
." LAB = ! M '~ REEPONSIBLE SECTION j ..o
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M.7 C % dSAFETY;RELATED DX.). .. NON-SAFETY RELATED ( i )
- . - _ ~ . .. . . .
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.F R' .v ' c. ; C : CM. NG:.^. McCE O' .CPERr, TION OR INTENT AS DEGCRIDED IN FSAR:
~
( ) Yes ( ,X1 No .
.T .
M.,. . CIW:0E JMVC1.VFS: ( ( ) An unreview.d Safety Guestic.n ( ) Tech. Specs. M Neither j,f (See back f,'r Safety Evaluation if required). .
*o )
Nnn-Sofety Related (
,- G rety Related (f )
- u. ) Yes ( No 4 Gafety/Non-safety Status Change ( .
w., y, Attach marked up copy of procedure to thi~s fo'rm. i RE/5ON FOR RECUEST Q.4. h.__ m I- __9 2. - 4 Z </, .. _ 4,17..m. c _. _t _ a h ._"_ , n_a_t & _ 9 _. w _ s_ _ a_ _,1 ,o d _:L L -
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- i i' . H N P- 4430 Y ***
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-l- NOTIFICATION OF UNUSUAL EVENT-SHIFT SUPERVISOR 5
l $ A. CONDITION i 6 usual events are in process or have occurred which indicate a 4 1 potential degradation of the level of safety of the plant, such T as those noted in HNP-4420, Table 1. No releases of radioactive I naterial requiring offsite response or monitoring are expected 2
.i-, unless further degradation of safety systems occurs.
,ir . i a -8. REEERENCE s
- p. .
'7 mP~4420.
.... C. ACTTON p ,
r} ,' 1. Proceed to control room immediately.
- 2. Assume the duties as Emergency Director and take
,- responsibility for overall management of emergency response, i' including declaration and notification of the emergency, y until relieved by Plant Manager or his designee.
y h l'f"
- a. Evaluate actions of Shift Foreman and operators to bring emergency under control.
[ 4
- b. Assure correct emergency classification has been declared as per HNP-4420.
~e n
- 3. Afer consultation with Shift Foreman and Shift Technical Advisor determine if a more severe emergency class should be k, T declared. Refer to criteria in HNP-4520, 4620, 4720 and l, fp, X:
4853. l ' jf~ 4. The Shift Supervisor is responsible for notification of i14 Plant Management and NRC as per emergency call list and hy[~ other offsite agencies.in accordance with notification procedure HNP-4861. The actual notification process may be V -de169 ated to other, specifically trained, shift personnel. l W 5. Augment on shift resources as needed to assess and respond to the event.
- 6. Close out after the emergency with verbal summary to offsite
~
authorities; followed by written summary within 24 hours. L -
}
4- ~ . de# l 2 MANUAL SET l . &._b .. - w p, - -- 700930
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^"i HNP-4524 E- PROCEDURE NUMBER
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- - -RELATED ( X)
; NON-SAFETY RELATED (i )
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HEAD PLANT ER DATE [* ------. .--------------------..----------------. .-- --_ ----- --. .- --- 2 Pages 1 and 2. - - <
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-J REVISICM CHANGEC MOCE OF.CPERATICM OR INTEN
- y. . ( ) Yos . (d) No i * *
~+ - CHANGE INVOL.VES:
$; " ( ,) An unrevisned Safety Guestion (- ) Tech. Specs. (d() Neither b (See back for Safety Evaluation if required). -
e .. .
' Safety Related (N Non-Safety Related' ( )
;;[ Safety /Nc.n-safety Status Change (
) Yes (k ) No
. S E -
- g- Attach marked up copy of procedure to thi's' form,, .
a ~ A REASON FOR REGUEST 9,ftresu O fr ~6qi kg3__tifg__ ' l
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question as exclained belcw. = _ - - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ n 5 1_. The probability of occurrsn_ce _a_nd t_hs con.Seo_u_e_n_c_es__o_f_an__a_c_c_id_e_nt or malfunction of eauipment im.oortant t to safetJ* are not increased
; 2cve th e ana 1 v7ed j_n__thg_F,$1bp_e_10._t.bRSr . CHAD 90R5_b.tCAUSE_______
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- 2. The cossibility of an acc_ident or ma_l_func.t._ ion of a different tyce -
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6, _ _ _ . than ana.l..yzed in the FSAR edo s_not result from this chance because re the sys_t_em resconds and is -operated as before the_c_h_a_n_ce.
~ - - -
wt y ___ h 3. The marain of safet as defined in the Technical Soecifications .--- T is not reduced due to this_r_e_ vision b_ec_a_u_se the _re_v_i_s_ ion __d_oes not -
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.-F chance _an.y l_imited_ safety system s_e_t_t_inas which would allo.w. a z_ - . _
s a limitino condition for C sa_f.e.t'y l,.i_m_it__t_o be exceeded or to allo.r __a
'. op-erations to be exceeded as stated in' Technical Saecifications. -
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J EN ue== E. l. Hatch Nucl:ar Plant a===as ~o I W ^ ' HNP. 4524 [( See Title Page amsson no e a
; ft ' om Georgia Power n . ..- ~o i
, See Title Page 1 of 2 F *~t , . ALERT - INTERNAL SURVEY TEAM l
7 2,. - A. CONDITION b}*.;; k Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the
- g. plant. Any releases are expected to be limited to small fractions of the EPA Protection Action Guideline (PAG) exposure d
_% . levels. m s .. VM B. REFERENCES Ys .
. .t 8 'NP-4CEO s'
ur sy uy v. -CTION [s NOTE ,
, ,a This action is to be taken by the Health Physics 3Q Supervisor or designated alternate, whenever possible, 4 or by other trained personnel.
g'b. 1. Obtain the following equipment from the OSC Emergency Kit or from the HP office.
~
<NJ High Range Survey Meter High Range Dosimeter
'97
!,p{;) GM Survey Instrument and Wipes MSA Air Pack SCBA
,xt[p
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4.g . Protective Clothing Air Sampler W:: - Radio
~. 2. Turn instruments on and allow them to warm up.
- 3. ' Don' the protective clothing and- the SCBA. Proceed toward area where the emergency exists making survey as you go.
7 7. . NOTE Y ' At all times, follow the guidelines and t limits of HNP-4866.
- a. If any of the following readings are observed, retreat immediately and notify the Control Room.
~
[ Beta, Gamma - any reading above 5 R/hr .
, Contamination - 10,000 cpm above background on a wipe j /*
N.) 4. Take samples with an air sampler if conditions permit.
'e N -
m4 .. MANUAL SET
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; 5. Determine cause of high activity and notify Control Room.
p 6. Rope off and post areas of high air activity or radiation as conditions permit. d5
- 7. Determine habitability of Health Physics, Laboratory, and Countino Room areas.' Notify the Control Room.
l W-
- 8. 4siat Control Room personnel, when requested, in evaluating a the extent of radioactive material released or potential for l ' ~ ~ ~'
~
release, using effluent monitor readings or other air l } Mi. n ..
"._ - -' , _,- ~!Kand7 samplers readily available, meterological instrumentation, procedure HNP-4853 to estimate dose rates to persons
?~
~
. . ~~~~beyond the plant site boundary. w.
, s fm 9. Notify Shift Foreman if conditions exist that would cause a ', D person at or beyond the plant site boundary to receive T' ~ radiation exposure at action levels in HNP-4853.
a a '? 10. Communicate with the Emergency Operations Facility and/or r Technical Support Center in determining extent of any 1 -
~" activity release.
f 7" 11. Document survey findings on standard health physics survey f forms. (See HNP-8012) g3 P"~ 12. Return to the OSC when released by the Shift Foreman or HP
.f~ Supervisor.
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GEORGIA POWER COMPANY A Yw .. HATCH NUCLEAR PLANT 44 T" PROCEDURE m.s. ALERT - RESCUE TEAM c PROCEDURE TITLE
%. t-HNP-4528 PROCEDURE NUMBER m
, " LAB y_
RESPONSIBLE SECTION _n z . . m.,
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.L.. OiSA.FETY RELATED ( X) _'NON-SAFETY RELATED ( 1 )
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#. . . . t APPROVED APPROVED E
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~V HEAD ' MANAGER ,
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M* . [ ,- .
- PROCI~Ot clE Rf ~V T G f ON Gi~Ot uT.T a2 .
- . PRCCCO's'RE t.N. IIMP - 'l s' 7. ?
Revision No. ----_2. -- - -- , py -- . - _ _ _ _ _ _ _ _ _ _ _____ ____ D_F P .'.R TMEN_ T _t_-6_,'.0__,* P P_N_OW. . -___-
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; .- REVISIC;! CIC NCE". MODE OF .CPERATICr! OR INTENT AS DESCRIDEO IN FSAR:
. ( ) Yes . (.\') No
~ **
- T CHANGE INVOLNFS:
~-. '
( ) An unreviewed Safety Guestion (- ) Tech. Specs. ( X) Neither [i. n (See bacic for Safety Evaluation if required). {, Safety Related (K ) Non-Safety Related ~ ( )
]
Safety /Ncn-safety Status Change ( ) Yes (X) No Attach marl <ed up copy of procedure to this form. h ' - 5-
-. u' ' . REASON FOR RECL'EST .
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_-----=. h-ab6ve those anali zed J _in__t_h.e FSAP_d_u,a
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< + __=_
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",. [ .
n the system resoonds and is oper_a_ted as before'_the chance.
- _=_ - -_
u - -----.
~ - - - _ _.
t4 ud - 3. The marcin of safet.'L_a_s_ define _d_ _ in the Technical Soeci.f.ications is__not_ reduced du_e to thi__s_revisi_on be_cause the_ revision _does not_
.y l(
chance --- any limited safety system settinas which would all_ow a - g :p -
."' _ safeti l,.i.mit to be exceed.ed or to allo.r a limitino condition for t
- q. .,.. .
l UE g 2, p coerations to be exceede_d
- -- -- as_ stated in'Technica_l Soecifications.
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iw 3 Q*SMANUAL
%cfSET 9
M A . S, y_ N .
-~,~- -
- : ~
t~ ova E.1. Hatch Nuclear Plant axt=xa ao e &s -t t H N P- 4528
.V See Title Page REVGCN W 3
y'-r **..om Georm. D a Power n- . ~me J '~ See Title Page 1 of 2 pp:. .
, 'Ti . ALERT - RESCUE TEAM h.a i
A. CONDITION _
- Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small frac-
,- tions of the EPA Protective Action Guideline (PAG) exposure g .,, c leveIs.-- ,
f
..v-*' B. REFERENCE
~~
I Y HNP-4520 t [C s C. ACTION P , 4 1. Form Rescue Team:
..[
*~
- a. OSC Manager designates a member of the Radiological Emergency Team to be Rescue Team Captain.
h;; b. Radiological Emergency Team members are assigned to
'W" complete Rescue Team as follows:
Id 2f" Survey Man Stretcher Bearer # 1 3 I Stretcher Bearer # 2 gh Stretcher Be'=rer # 3 yr g}j[ c. Rescue Team Captain leads team in the rescue effort.
- 2. Dress out in protective clothin'g located in the Operations
'.wg~i - Support Center, if time and the situation. permits.
5.f.. Y Anti-C Coveralls
- .fiC , - Shoe Covers 47 Rubbers ce
, g;'+- Hood Respirator (self-contained)
$~ High Range Pencil Dosimeter .
% TLD Badge Is i 1.- -
l .iC n R[g . y} ,
, 7 j ,. w .
S .< . ' MANUAL SET
= =
footao
= .,n'
- f~o=
- . E. l. Hatch Nuclear Plcnt aaxt= ~o H N P- 4528 '
. . E f[ See Title Page WSON NO t 4 - Georgia Power d , .m No 2 of 2 l ~ 2,, See Title Pace
[, ?. .
"g
- 3. Survey Man carries GM survey meter and high range survey
.2?: meter. Team Captain carries walkie-talkie and remains in contact with Rally Point Leader and/or Shift Foreman.
p 4. Determine probable location of victim from OSC Manager. P: . Proceed with rescue,
-- [ -
t ,. a. Stretcher bearers carry:
; x. ' ._ . Stretcher
.jyn Rope and tackle, if required for rescue
] _r T:.. :. ~ Pinch bar, if required for rescue
, '?v First aid kit
[ ! '*;
- b. Start using resoirator while approaching building.
ce g6 c. Retreat if dosimeter reaches 2 R,and victim has not been located. mE
., rg;- d. Limit dose to members of Rescue Team to limits in gL. -
HNP-4812 in effeeting rescue. ( M e. Perform necessary first aid measures for victim but
#11 move rapidly when dose rates are high. Move victim
~
"L into Medical Room and decontaminate if possible (as per
'; HNP-4802 and HNP-4803.).
19 M 6. Inform Control Room of condition of victim. Assure that
""gg Shift Foreman has notified hospital that the victim is or is gp not contaminated.
Wf[
'dag QW
- 7. Contact Technical Support Center or Control Room by radio or phone for ambulance pickup of victim in the upwind direction of victim's location.
N., s K ?; 8. Move victim to ambulance.
- -:C,n .
416 9. Arrange for radiation technician to accompany victim to
.T~ W- .
hospital in ambulance. N$;. 10. Notify the TSC as soon as possible. W M 11. Take necessary measures to limit spread of contamination and y report to the OSC Manager when rescue effort is completed. m - t .
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HATCH NUCLEAR PLANT s, w e
,; . PROCEDURE .'
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*..,9 ' _ _ _Site Area Em_e_rflency - Rescue Team , 1 PROCEDURE TITLE rM #
W' HNP- 4628 - i i t.._ PROCEDURE NUMBER i
;tg Lab " I.
- RESPONSIBLE SECTION
. ,m
. . g w, . .
._ca ,., .
I CJ SAFETY RELATED ' ( ~X ~ ) NON-SAFETY RELATED ( ')
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- l. _ _ _____
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______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________ p_______. w -
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HNP-9~ 4 <c MANUAL SET
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___________L_Or_c1LL_el___________._____ g-a _ _udiusu _ _ _tJ _u'_ __U,, ,c, ,a _ _____ Date: r ru.tw ; D&te; Signature: A. 4/nin. ______9 k_#__- #6 P I. . . .._pj_, g_th r., _- 7 A. REVISICM CM.*,NGEG MODE OF .CPERATICM OR INTENT AS DEGCRIDEO IN FSAR: l ( )( ) No ( ) Yes l e . 1
; 5. ~ CHANGE INVOLNES: ) Tech. Specs. (X) Neither
_.r ; .( ) An unreviewed Safety Guestion ( (See-.back for Safety Evaluation if required).
- v. Non-Safety Related ( )
J. S.dt:.ty Related (X)
?,, .
Safety /Non-safety Status Change ( ) Yes ( k) No
]p -
Attach marked up c o py o f p r o c e d u r e t o th i's f o'rm. g '
~~
REASON FOR REGUEST - - p fh '_C1--__tsl.iR._ " wim_%_ms(. k mi u Es_ny.') -_AJ " c,o_emN-_-_ [ .y s4ptr c,4u-
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---_.W ann. i.vre_d in the FSAR does_not resul t from t.h.is chance because M+ .
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-~ - _ - -
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d e fi ned i n .t..h.e. T e ch.n i c a_l S c e c i _f i_c a t i o n s_
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4ly: - . - - . - - s a.f..e._t'v
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MANilAl SET e . . . . . , , , , w.
1 3 5A.Pa ao.= E. l. Hatch Nuclear Plant ax ouae ~O
~~ .
H N P- 4628
,d Sao Title Page aEvissON NO om Georgia c Power A . ~ ~O (
-. See Title Page 1 of 2 f
n SITE AREA EMERGENCY - RESCUE TEAM
, v. .
i k4 NOTE
; 'y This procedure supercedes HNP-4607 Revision 6 dated 8-31-79. , s i
b A. CONDITION g Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of
~~;rj; the public. Any releases are not expected to exceed PAG exposure
+} ; levels, except near the site boundary.
; O. %-i-RENCE r
g HNP-46EO. M C. ACTION , k
~
- 1. Form Rescue Team:
97 OSC Manager designates a member of the Radiological l .f h a. Emergency Team to be Rescue Team Captain. t g . giJ b. Radiological Emergency Team members are assigned to
.: complete Rescue Team as follows:
N Rescue Team as follows:
?g .1*c ef iph Survey Man
?9 Stretcher Bearer #1 C
f' Stretcher Bearer #2 l it. .
,4g Stretcher Bearer #3 ,
.'$/ c. Rescue Team Captain leads team in the rescue effort.
-- E. Dress out in Protective clothing located in the Operations ge Support Center, if time and the situation permits.
b W -- Anti-C Coveralls EA Shoe Covers - i dQ l
-C Rubbers i N__ -
~
;C Hood Respirator (self contained)
A=.- MANUAL SET
*Qu-700820
r d4-aes E. I. Hatch Nucl0ar Plant aaociou:= ~o A % ,1 - HNP. 4628 r [" See Title Page r:svision so
~j Georgia Powerkn 2
I
/M =m . . .m ~o 3ee Title Pace l 2 of 2 i
l , High Range Pencil Dosimeter i 1. : i , l j.y TLD Badge a. g 3. Survey Man carries GM survey meter and high range survey W meter. Team Captain carries walkie-talkie and remains in i9 contact with Emergency Operations Facility and/or Shift Foreman. r-g -+. Determine probable location of victim from OSC Manager. 1; @+ l "l2p . n . . 5.- Proceed with rescue. 7, a. Stretcher bearers carry: es
.}j{ 5tretcher i Rope and tackle, if required for, rescue.
SJ. g
}Z Pinch bar, if required for rescue.
[ First aid kit 3,b b. Start using respirator while approaching building. q J, c. Retreat if dosimeter reaches ER and victim has not been 1 located. l I v; I d. Limit dose to mer. tiers of Rescue Team to limits in HNP-4812 in effecting rescue. d.v. ..
'Q~
- e. Perform necessary first aid measures for victim but c- move rapidly when dose rates are high. Move vict'im
-Q into Medical Room and decontaminate if possible (as per TE W.%
HNP-4802 and HNP-4803.) I k 6. Inform Control Room of conditidn of victim. Assure that M.
*/
Shift Foreman has notified hospital that the victim is or is not contaminated.
$5.l
- 7. Contact' Emergency Operations Facility or Control Room by radio or phone for ambulance pickup of victim in the upwind M- -
direction of victim's location. l :3 l L* ' 8. Move victim to ambulance. , ll ,__'s l
- 9. Arrange for radiation technician to accompany victim to hospital in ambulance. ,
ei m 3'6,}
- 10. Notify the Technical Support Center as soon as possitsle
..O - .
O c l
*- 11. Take necessary measures to limit spread of _contami' nation and y y report to the OSC when rescue effort is complet'ed.
'g4 A.s. ,
MANUAL SET w ^2 30
r.y , 9__ , q . GEORGIA POWER COMPANY t y " ' g HATCH NUCLEAR PLANT
, .g< -
1 ,i,y' PROCEDURE s _ i I f General Emer_qency - Rescue Team PROCEDURE TITLE
.t
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1 7? HNP-4728
>i
, PROCEDURE NUMBER
";-~_
l Lab i ""._4 RESPONSIBLE SECTION w:~. _..
~
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.- m... . , v I, MT [- . P SAFETY RELATED ( X ) NON-SAFETY RELATED (- t )
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c- ______+____________________, . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , .________________m________ w
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l APPROVED APPROVED EJ REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER c-g 1 Pages 1, 2&3 p M
. - _M 7g __ _____.._
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# 2 Pag 1, 2, & 3 ' / N__h,__
3 - _ _ _ _ _ . .____e_s__._____________. . _ _ _ __. ._____ __ _ _ _ - . W 1 p -_____ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________ \ w
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- . -~ *' Revision No.,___f _
*'~ ,_____-.--- Dr- P_AR
-- -- TMENT t-tF,'.O A_PPN_O_V,:.r_._-_
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I Signature: Date: Sn. p;,me ; ab-- -$ O Mf _ __ be _ _- a 9
.s INTENT AS DEGCRIDED IN FSAR:
1REVISICN CM.",N0; . 7 ODE OF .CPERATICM CR
. g . ( ) Yes . (b) No .
i %'* r,. - * '
- T" LCHANGE .) An INVOLNES:unreviewed Safety Guestion ( ) Tech. Specs. ( Jh. Neither
.C (
(See>back for Safety Evaluation if required).
' {54 ,-
i
'Ge.fety Related (h Non-Safety Related' ( )
- a ,- ,
,ft Safe ^y/Non-safety Status Change ( ) Yes (A) No a 5fn
- Attach marked up copy of procedure to thi's form. -
~
y- . 9:1 REASON FOR REGUEST ,, , .
~.
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{ . __qu e s_t.i_o _ ._ n _a_s__e x_p l_a_i n e_d__b e l ow . ----_ _ - =- --_ ____ _. 1.__T_h__e_gr.o_b_a_b.il_i_ty of occurrenc_e__a_nd__t_hs c_o_n5.ea_u_e_n_c_es o._f._an__a_c_c.i d _ . _ _
}b ' .__
or mal fu.n._cti_o_n__of. e.9_uic_m_e_n_t_i_mLor_t._a_n_t_t_o s_a_fet.L' are
- - - =- --- ] y(. _ a.b.p.g_t. h 012_a.p.alyled_in_ thg_F.Mbu_e_.to._tbR5.C. Ch.aD.9RS_hCC.!WSP _____
a . [ the revision does 'n_ot chance the nurnos_e_or_p.erformance of the -_
- w. -
N's system. -- it' . 7; m ,- ?. _T_h_e cossibilit.y of an accident or ma_l_fu_nc_ tion of a different tvoe rw .I .
~^c.~
v,. than ana_lyzed -m-in the FSAR does_not result from this chan_c_e becau_se
- - =
the sys_ tem resconds and is operated a_s_b_efore the chance. w..___ .
~
n_ _______ C
- 3. The marcin of safety- - - -as define _-J _in th_e_ Technical-= Soecificat_io_n_ s - - - -,
4 = e is not reduced due to this revision b_ec_a.us.e the _ revision __d_o_es not -
.w chance anv limited safety svstem settinos which would allow a -
- - ei'p.
g ' bd a limitina condition for ._
%gW. safet'v_l,i.m._it__to be exceeded or to allot ooerations_to be exceeded as stated _i_n Technical Sne_c_i_fic_a_tions.___. -
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3.5NAL SET N.
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l A.*1 d FPR%V4 E. l. Hatch Nuclcar Plant =ct=as ao HN P- 4728 I See Title Page l F.EviS.ON NO O c. m GeorgiaPower A , ..-~O ( 9ee Title Paga 1 of 3 c. b GENERAL EMERGENCY - RESCUE TEAM 7f ,
,e r-NOTE This procedure supercedes HNP-4707 Rev. 3 dated 5-13-78.
'n A. CONDITION y
a i ~", . ~ Events are in process or have occurred which involve actual or
%.- imminent substantial core degradation or melting with potential for ' loss of containment integrity. Release can be reasonably
]#f- ~
_ . . expected to exceed PAG exposure levels offsite for more than the 47, . 11-mediate site area. v..
.MT 8. EEFERENCE
[. HNP-4720. .
.1
?- C. ACTION W
t' 1. Form Rescue Team:
?
3 a. OSC Manager. designated a member qf the Radiological
- h. Emergency Team to be rescue Team Captain.
i. g/^ b. Radiological Emergency Team members are assigned to 7F complete Rescue Team as follows:
. Survey Mat.
J
,+-
Stretcher Bearer #1 ,
'.*hf,tY Stretcher Bearer #2 Stretcher Bearer #3 s it y . 'Y' c. Rescue Team Captain leads Team in the rescue effort.
47
'f~'
- 2. Dress out in Protective clothing located in the Operational fi Support Center, if time permits. ~
n Anti-C Coveralls v v Shoe Covers . [ - Rubbers t Hood o
.m 1f *a MANUAL SET
$m%.-4 9
- a
' ~ d u~ao= E. I. Hatch Nuclear Plant accamae ~o i d , H N P- 4728 m s See Tit 1e Page - nevisiou mo. u
. - Georgia Power n , -- ~o
- c. See Title Page 2 of 3
, S. Respirator (self-contained)
.c. ,
I :L High Range Pencil Dosimeter
; t
^
! TLD Badge
% 3. Survey Man carries GM survey meter and high range survey
% meter Team Captain carriers walkie-talkie and remains in
}[
contact with Emergency Operations Facility and/or Shift
, , ,*r Foreman.
dJ' 4. Determine probable location of victim from OSC Manager. j g"~ 5. Proceed with rescue.
, 5; a. Stretcher bearer's carry:
Q x; Stretcher , g} Rope and tackle, if required for rescue Pinch bar, if required for rescue 7
- 2. First Aid Kit *
(
$v..
- b. Start using respirator while approaching building.
E c. Retreat if dosimeter reaches 2 R and victim has not f been located. U [J d. Limit dose to members of Rescue Team to the limits in HNP-4812 in effecting rescue. h{i : e. Perform necessary first aid measures for victim but h move rapidly when dose rates are high. Move victim into Medical Room and decontaminate if possible (as per
- y~
HNP-4802 an<j HNP-4BO3. )
<A'
?'E J Jea 6. Inform Control Room of condition of victim. Assure that VW Shift Foreman has notified hospital that the victim is or is d
h,q. .not-contaminated. h 7. Contact Emergency Operations Facility or Control Room by radio or phone and arrange for ambulance pickup of victim in ig gW. the upwind direction of victim's . location. 6 8. Move victim to ambulance. g tei p ;y
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, -t - E. l. Hatch Nuclear Plant 1
~ I*AP*aOVAL aaoct=as ~o
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# . HN P- 4728 E See Title Page REUISON W 2
% c.,e Georgia Power n , ..e. ~o See Title Page 3 of 3 i p',. 9. Arrange for a radiation technician to accompany victim to
- hosp. ital in ambulance.
1 A , i
- 10. Notify Technical Support Center as soon as possible. l
-l 7' i -l
- 11. Take necessary measures to limit spread of contamination and r' report to the OSC Manager when rescue effort is completed.
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First Aidr Decontamination and Evacuation e-of ExEosed and/or Contaminated In.iured Individual p.. n PROCEDURE TITLE s-4 4
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HNP-4802
' l. . PROCEDURE NUMBER I. ~*'
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PLANT DATE
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y, 7 7 .* , n 4.. . . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______.
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2
" < M MANUAL SET
'.\ 9 %' O ==~ -
_ . _ _ . . . . _ _ . _ . _ . _ _ _ _ . _ _ - HNP .9 - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ s
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REVISICN Char:GES MCCE OF .CPERATION OR INTENT AS DESCRIDED IN FSAR: . f ._ .. . . ( ) ,Yes
. ( /C ) No
~
Cl%NOE INVOlNES:
- 7. @* " ( ) An unreviewed Safety Guestion ( ) Tech. Specs. ( >4 Neithe r e (Sen back for Saf ety Evaluation if required).
.\ i~. . *- .
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- y. S.,Fety Related ( j. ..-. Non .Sa f et-,y..R .e.l .a .t e. d. .. ..(. ,._-.).
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, - , . -- . _ -. :w. .u .u u . w_ .. . .. . . .; - ~ -
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! .; Safety /Non-safety Status Change ( -) Yes (A) No -
-*' Attach marked up copy of procedure to this form., .
=- .
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- REASON FOR REGUEST O b u N $2 2,-N O '
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< _ , . Pl<0 39erotary Y.. --_-_.._..._kk,2_C_f______________ -
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- - - - = = = _ _ - - - - . - _ - - - - - --------------.-------
1 __c.u.e ---- - s t i o n a s__e x_c_l ---- a i n e d_ _b e l_cw .
! . 1_.__T_h e_ Erob ab i l i_t_y o f occu rej _ _s, a -nd_ th -3 ..C.o_n.gc_u_e_n_c_es__o_ f _ a_ _n _a_c_c_i d_e_n_t__ _
--- _- or mal fur.:tien of ecuir s
------------- - _t_'-----corta_n_t to_sa - --- fety ----- are not increa_s_e_d-- _- - - -
.c_ 09.n_t_h.cn_a.n a l yz_qLin._tii_:.jjbu_e_10._tt.es.e. Chmas_b.e. css a_---_-
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J _the revisio_.n = - - - -- -- _does_ no.t c_h,jtr._:e the our.c._ose or pe_r_formance of the 7 - system.
>v . ... .
e- .. . . _ .. The rossibility of an accirs-t or ralfunction of a different tvoe '
- - 2. _
T-- ..... ~ ..-._. .. ... . = ........ . . .
- -- - --.-- -- - ~ ~. ...
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than analv:sd in the FS.2.R d:ss not result frem this chance because -
~ "
the systs: resconds and is ::srated as before the chance.
- w. . .
- s. .
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- 3. The marcin of s.afety as dsr.ed in the Technical Scecifica_tions
- ---- -----_ - -- - ---- --- - = = - - - _. -
(r v . 7- -- is not__ reduced due to this revision because the . revision does not
=--- ,
4, chance anv linite'd_ safety s'ests 1_ settincs which would al_l_ow a (c w y s.n. safet'y -- m - l.i.mit to be excesd9.f or to allo _w a limitinc condition for G. v~ Q o_cerations to_b_e_e_x_ceeded is stated in' Technical Soecifications. - p~.~ . qY O ' Y[* * - t 1 . .' ,.i, .b'ik -
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-s. a bov - E. l. Hatch Nuclear Plcnt ====: s ~o .
ut ~' - H N P- 4802 - _.r See Title Page ty m > ~o 2 - Georgia Power d . ..- ~o 5 l 5ee Title Page 1 of 6 l, Si-3 FIRST AID 1 DECONTAMINATION AND EVACUATION
'jt QF_ EXPOSED AND/OR CONTAMINATED INJURED INDIVIDUAL b A. PURPOSE
- 1. To specify how the usual first aid and decontamination
,,.7;" procedures should be modified when the victim is both l ,
injured and contaminated. l, u ?- 2. To specifv the priority of actions to be taken in evacuating
! /9 ;.an exposed and/or contaminated injured individual.
kc. i 8."REFERENCESf
.T . . EMERGENCY FIRST AID MEASURES - Georgia Power Company ks. .. ADVANCED FIRST AID AND EMERGENCY CARE - American National
.P Rec Cross b
& 3. HNP-8006 PERSONNEL DECONTAMINATION k
. . . . 4. HNP-4810 FIRST AID TREATMENT GUIDELINES v*
,1 .
F C. GENERAL ' sI g3 1. Under all circumstances, unnecessary exposure to radiation should be avoided. x' j; 2. In rescue and first aid operations, the NRC Regulatory
.. limits of exposure are not binding (See Paragraph F.6. below i EMERGENCY EXPOSURE RISK).
n-
- 3. When it is known or suspected that an individual has i$$rr received a serious injury, summon the ambulance and Plant pg Medical Consultant without delay.
rn< .
,@?g - 4. When a casualty i_s to be sent t'o the hospital, a member of IC " the Health Physics staff will complete the form attached to 17/ - this procedure.
7/2 Q'g , D. FIRST AIQ er. dbk 1. Preferentially, first aid will be administered by plant Qy personnel who have been trained in first aid courses
;fu presented or sponsored by the Safety Department.
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See Title Pags See Title Pace Georgia Power d , uvisioN NO mm ~e 2 of 6 1
- z. 2. An important aspect of first aid is self-aid. If the
.@ injured individual is capable, he should apply self-aid
? -i procedures and assist those who come to his rescue,
$"v particularly with regard to preventing blood loss.
.T.n 2 3. Life-saving first aid should never be withheld because of
_f ~ the radiation hazard to the rescuer arising solely from the radiological condition of the injured individual (See gf paragraph F.5.a. below). A
,7.{ ' E. DECONTAMINATION 1 Jep r-- "I',"fjb~econtaminationwillalwaysbeasecondpriorityactivity;
, g; first priority goes to first aid.
Yh 2 Never remove a dressing or splint for purposes of decontamination; this will be done as indicated by a doctor.
.,3 R
, 3. Never decontaminate a serious wound; this will be done by a
~s ,e, doctor.
r..
, i 4. Conduct personnel decontamination using procedures and w($ materials identified in HNP-8006 or RMC Decon Kit, when such
',y procedures and materials can be used without aggravation of
@, .- the individual's injuries or causing him discomfort.
, pr'! l' . 5. To avoid aggravation and discomfort, remove grossly
$ $hF C.k contaminated items of apparel by use of scissors.
I Wa d ;_ 6. Do not, by excessive decontamination, cause the injured MC~ individual to become unduly apprehensive about his state of s contamination. His state of contamination is of minor,
@$l gM medical significance.
mw l Sf., i Wy F. EVACUATION OF THE NON-AMBULATORY INJURED INDIVIDUAL MTk 1. General _ 4
;2 '~ T4 a. A prompt and realistic comparison of the hazard to the f victim if he is not evacuated vs. if he is evacuated,
$p- , - will be made.
YiE b. The hazards incurred by leaving the victim at the site W W of his injury may be conventional hazards (fire, steam, etc.) or radiolcgical hazard.s or a combination. N{
- c. The radiological hazards are external radiation,
_ airborne radioactivity and personnel contamination.3
;r r s.
g , d. The hazard of evacuating the injured individual'i's the aggravation of his injury. , j%" 5 -
, . , Xp aw
., .%A. . ^ MANUAL SET
~
r
- 1. - .
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- $ ^ =va E. I. Hatch Nucitar Plant axsou= ~o H N P- 4802
_E See Title Pega avisio= =o 1 e
~
See Title Page Geor8 a Power d l -
~o ~o 3 of 6 , y .
f J' . we 2. Guidance for Evacuation 1' A ff a. "If continued occupation of the accident site presents a
,e threat to the health and safety of the injured man that
!i exceeds the threat of possible aggravation of his injury by evacuation, evacuate him.
j ,,: (1) With respect to external radiation exposure, a j 9;- " threat to health and safety" is a cumulative ll , exposure in excess of 50 R. l
}"
9
~"'~~ (2) Personnel contamination will never present a serious threat to the health and safety of the +
jt. Injured man, f~ (3) As a rule of thumb, if external radiation does not Ny present a threat to health and safety at the T; accident site, the airborne radioactivity will not 9 present a threat to health and safety. y b. If adequate first aid cannot be provided at the 1: accident site, evacuate the injured individual to an
, J: area (e.g., the Medical Room) where this first aid can 5" be applied. ,
- 0. '.
g c. If adequate first aid can be provided at the accident M site and the victim's health and safety is not threatened at the accident site, provide first aid at the accident site, and await the arrival of the r i ambulance personnel or the doctor.
.C or
;i" 3. Evacuation Procedures 2f
?$,$ f; a. Evacuation from the accident site to the Medical Room 7f will be conducted in accordance with " Emergency First
'$,f-'
yi Aid Measures" and " Advance.d First Aid and Emergency Care". . I?C b. When possible the scoop stretcher will be used.
}$ji?s 4. Protecting the Victim f rom Exposure
-in
??f[ a. If the victim is not moved from the accident site every 3%r reasonable precaution should be taken to protect him
{p from significant exposure. . C1 (1) Shields will be interposed to protect him from
% ,__ external radiation.
(2) If his injury permits, he will be fitted with a respiratory control device. ' 5 _ . , AL 4T
, 700330
-~~~
- _ _ _ _ _ _.2
. 1
~
4*. amm E. l. Hatch Nuclear Plant moct== ~o l H N P- 4802 l 5$ Sne Title Paga KEYtSioN NO j j ,i -. Georgia Power d . ~e No l 3 See Title Page 4 of 6
- a-l' w.;'
(3) If personnel decontamination is practicable, he
. will be decontaminated at the accident site.
5s . 5,. 5. The Victim as a Source of Radiological Hazard
- m. . .
y;m a. Life-saving first aid should never be withheld because 3 ^^ of exaggeration of the hazard to the rescuer arising l 47 solely from the radiological condition of the victim. j :
, ,k (1) A beta-gamma irradiated victim present no hazard 7!; . -
to his rescuer. Eli ..
"3'. (2) A grosely contaminated victim presents a slight 3 contact.and some respiratory hazard to the rescuer.
;F (3) A victim who has radioactive material imbedded in ypp his body could present a significant hazard.
37 However, if one assumes that, life-saving first aid RT could be administered to a victim in six minutes, j-r the exposure rate would have to be 750 R/hr.
#U before he would exceed the limit of 75 R proposed
( as a limit for life-saving operations. 0
- f" b. If the victim is evacuated from the accident site to 43 the Medical Room, the stretcher-shield and/or the lead
%, glass shield will be used to shield the attendants, if
, y* the radiation levels warrant the use of these devices.
! sUr l
>f 6. Emergency Exposure Risk l ":?f?.
(3$p a. A comprehensive presentation of the medical 4 Esp; significance of radiation doses received under yyyj emergency conditions is given in Reference 3 to this procedure.
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- b. In brief, the rescuer should be aware of these facts:
7Tr Without treatment, it is v'ery likely that a man who
$r? receives an acute whole body exposure of greater than
["' 600 R will die. It is very unlikely that a man who "F receives an acute whole body exposure of less than 200 i 4 z. . - R will die. It is also unlikely that he will
?"- experience any symptoms of radiation sickness. There I#A are no credible conditions under which radioactive
?E contamination deposited on the skin or inhaled could a present a threat to a man's life. Gross external
_ contamination (approximately or equal to 10' dpm/cm2) L _ in contact with the skin for one hour may produce an l ___ erythema similar to a mila sunburn. Breathing.g'
.C contaminated with approximately or equal to 10-l /N uCi/ml of 131 I for one hour would cause sericag amage l- ^:<# to the thyroid. 6 - e, I.)
py e = ANUAL SET 700210
- f. - .
- A
- p ova E. l. Hatch Nuclear Plant a=ct=a= =o HN P- 4802
,T Seo Titlo Page rev s oa ao.
2 cm See Title Page Georgia Power d . .m ~o 5 of 6
] 7. Health Physics Support for_the Ambulance Attendants
, a. ..A member of the Health Physics staff will meet the
- u. ambulance attendants at the plant entrance. He will
@,. brief them on radiation protection procedures to be n
0 followed. He will provide each attendant with a respiratory control device, if the use of such device 3;' is necessary for his protection, and a TLD badge and a a
.is- pocket dosimeter of suitable range.
l l
; $'gp., . b. The member of the Health Physics staff will remain with
'r , the ambulance attendants from the time of their entry Q'qR
^ -
until they have delivered the victim to the hospital.
.._ _ . He will:not. release the ambulance or the attendants
?
@ m until they have been monitored and decontaminated.
.7" p c. The member of the Health Physics staff will be yl% responsible for assuring that the internal and external
.}
; exposure incurred by the attendants is maintained as y low as practicable under the circumstances that prevail.
C' , Tf~ d. The victim will be wrapped in a blanket or sheet to
~'. S protect the attendants, the stretcher and the ambulance Eh w
from contamination. , w . . l n} e. If the radiation level at one foot from any surface of p,J; the victim is greater than 100 "mc"/hr. as measured by
,C a beta-detecting GM survey meter, the stretcher-shield l fC will be used during transport to.the hospital.
gg
' MP f. The member of the Health Physics staff will remain in the back of the ambulance with the patient. He will F
W assist the attendant in the care or decontamination of
.d":
the victim.
@p g. On arrival at the hospital, the attendants will deliver the casualty to the Radiat, ion Emergency Area (REA).
E gy~ . -
~ , .
l % h. The attendants will return to the ambulance and await hh the member of the Health Physics staff. They will allow no one to enter the ambulance until the member of 7 i Ef' N
- ^ the Health Physics staff returns from the REA and
!' monitors and supervises the decontamination of the N attendants and the ambulance. W
}; 8. Health Physics Support of the Company Physician
- a. A member of the Health Physics staff will meet the u Physician at the plant entrance. He will brief him on iC radiation protection procedures to be followed. He.
will provide him with a TLD badge and a pocket a : ',
?}
[ dosimeter of suitable range. ,'
.' se va nE Ipi
Q*y.pa*** E. l. Hatch Nuclear Plant awawas ~o H N P- 4802 See Title Page asvisioN ao F cm Georoia b Power d ~
..m ~o j'. See Title Page 6 of 6 av '
- b. The member of the Health Physics staff will remain with i ,,- the Physician for the duration of his stay at the plant.'
[ '
- c. He will be responsible for assuring that the internal and external exposure incurred by the Physician is J maintained as low as practicable under the er circumstances that prevail.
9 7
- 9. Health Physics Support at the Hospital L J* a. A member of the Health Physics staff will don surgical f".i. , -
gown provided by the hospital prior to entering the REA. .l
, b. He will advise the doctors concerning the patient's 1 F- radiation and/or contamination status.
I a' , 5,7 c. He will provide such health physics support as is l 7 necessary to assure that exposure to hospital personnel g] is maintained at the lowest practicable level.
- d. He will advise and assist in the decontamination of the patient and hospital personnel.
(' e. He will supervise the decontamination of the REA and it its equipment at the completion 6f use of the area. l l- ,
- f. He will assure that all contaminated items are safely p packaged and taken to the plant for decontamination or
'o disposal.
Wp r g. He will monitor and supervise the decontamination of f the ambulance attendants and the ambulance. If the
? apparel of the attendants is contaminated, he will de collect the apparel and issue scrub clothes from the 1 hospital.
iff 4+
- h. After having effected such decontamination of the ambulance as can be practicably accomplished at the i@P hospital, he will ask the attendants to deliver the fis ambulance to the plant for more complete
}{c_ . decontamination; if there is any residual contamination.
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. GEORGIA POWER. COMPANY
' - , HATCH NUCl. EAR PLANT -
s 4
) PROCEDURE , .
. I Si te Ar ea Fma_r.<w.nc& v - Tnte rna l Survey Team
' PROCEDURE TITLE .
. l HNP-4E.24 PROCEDURE NUMSER .
,I Lab e RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
APPROVED APPROVED . REV. DESCRIPTION DEPT. PLANT DATE . HEAD MANr.ER
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HNP-9 i l F
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Revision No. _[_ _,,, .
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RFCU:rSTFD GY D' P ARTMENT l-GAO APP:<CV.: . Da.e: d Signr.ture: Date: Name;
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- REVISION CHANGES MODE OF .CPERATJON ( DR '^) No J NTENT .AS OF.GCRIDED IN FS j
( ) Yes .
. j
. . g
- CHANGE 7NVO!.VES: ( ,><.) Ne.ither 4 -) An unreviewa<1 c+fety .GuerJtic.n ( ) Tech. Specs.
(Se e ba rJ< f o r b.f ety Ev a l uat ion i f r e qas c i d ) . . Nnn-Safety Related . (
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.Sa f ety Rei a-te d ,
~
Eaf ety/Non-saf e-ty Bta-tus Chr.nge ( -) Yes (&) 'No ..
-~
A$tarh Taarised up copy of procedure -to -this @rm. .
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- t.J. A..T. ..I.Cr t The revision _of this orocedure does _not co_nsti tute an_ unrev_i_ eye,d.;1[eg____,.___ [
-h
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question as explained below.
- 1. The or_oba.b.ilit_.y of_ occur _rence and thn c_o.n..Seauences of an accident cr . lfunctica of ecekemnat icanrt?.nt to raf tv are not increased above thase analyzed in thq.f_SAE_d.u_e_tg_tbSS.0 A nbAnCRS b.CCARSe the revision does not chance the nurpose or performance of the system.
~
- 2. Th'e nossibility of an accident or malfunction of a different tyre -
than analyzed in the FSAR does not result from th.is chance -
- - - - because-_
the sy_s_ tem resconds and is operated as before the chance.
~ "
- 3. The marcin of safety as _ defined in the Technical Soecifications 8 .
Die is not reduced due to this revisi_on be_cause the__ revision does not _
..J chance any limited safety system settinos which frould_ allow a safet'y limit to be exceeded or to allo,r a li_mitina condition for ooerations to be exceeded as stated in' Technical Snecifications.
a. d e - . . . 1 - 1 . l . s 4 l . . 'l 'h. 6 l
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raocewae ~o ; area' E. l.' Hatch Nuclear Plant ' HNP- 4624 nevm on uo ; D2e Titis Pega em Georgia Pon'er d .... 1 of 2 ej See Title Pace
~
SITE AREA EMERGENCY - INTERNAL SURVEY TEAM i
. e NOTE This procedure cupercedes HNP-4603 Revision 4 dated 1-2-81.
,I A. CONDITION i Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed PAG exposure levels, except near the site boundary. ,
B. REFERENCES HNP-4620. , C. ACTION NOTE This- action is to be taken by the Healto Physics Supervisor or
,-((}
designated alternate, whenever possible, or by other trained j ,, personnel. ^
- 1. Obtain the following equipment from the'OSC Emergency Kit or l from the HP Office:
High Range Survey Meter High Range Dosimeter l GM Survey Instrument and Wipes MSA Air Pack SCBA Protective Clothing J Air Sampler f
! Radio l S.
j 2. Turn instruments on and allow them to warm up. Don the protective" clothing and the SCBA. Proceed toward 4 3. area where the emergency exists making survey as you go. i j ,
. LJOTE At all times, follow the guidelines and limits of
. HNP-486G.
t I ,a. If any of the following readings are observed, retreat immediately and notify the Control Room! -
- v. ( }
IN j o .
~
1.- Reference Onh
' MANUAL SU
m- - , g
<reaovat E. l. Hatch Nuclear Plant =c=ne ~o ,
HNP- 4G24 z.smio~ ~o S n Titio Page
- m. Georgia Poker d ..
See Title Paae 2 of 2 O , Beta,' Gamma - any reading above 5 R/hr u j Contamination - 10,000" cpm above background on a wipe I
- 4. Take samples with an air sampler if conditions permit. ,
- 5. Deter $inecauseofhighactivityandnotifyControlRoom.
- 6. Rope off and post areas of high air activity or radiation as conditions permit. .
- 7. Determine habita'bility of health physics, laboratory and counting room areas. Notify the Control Room. f NOTE The primary means of communication with the OSC3 Control I Room, EOF and TSC will be through the use of the plants telephone system. If this system should become inoperable, then the page will act as the backup means
. of communication. - :
- 8. Assist Control Room personnel when requested in evaluating the extent of radioactive material released or potential for
.O
' y release, using effluent monitor readings or other air
~
samplers readily available, meterological instrumentation, and procedure HNP-4853 to estimate dose rates'to persons l beyond the plant site boundary.
- 9. Notify Shift Foreman if conditions exist that would cause a person at or beyond the plant site boundary to receive g
radiation exposure at General Emergency levels or action - j; levels in HNP-4853. l 4 h 10. Communicate with the Emergency Operations Facility and/or Technical Support Center in determining extent of the ,
~
activity release. }} 11. Document survey findings on standbrd health physics survey p' forms; report findings and present completed survey forms to H.P. Supervision for approval and filing.-(See HNP-8012). l i 12. Return.to the O.S.C when released by the Shift Foreman or - H.P. Supervisor.
< l 9.
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- 1. GEORGIA POWER COMPANY HATCH NUCLEAR PLANT -
/3 -
i V PROCEDURE General Emorgency - Internal Survey Team
~~ ~
PiiOCEDURE TITLE HNP-4724
~ PROCEDURE NOMBER Lab RESPONSIBLE SECTION ,
SAFETY RELATED ( X) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MAb uER 1 Page 2 gpp g_ q 3g 2 Pag - 1&2
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- Revision No. . _ _I _ __ _
' V.
______--- ___---____ ______i. ___-________ MF_,' O_AP P N n'.' *.t . _ _- - _D_F_P AR-- T M'D I.T. -----_ - RFCUFST F_D_ -_DV= -__ _____ .__ ---- . cat i,; Signature: onte: Nme;
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REVISICM CH."NGQO MODE O.' .CPERATION OR INTENT AS DEGCRIDED IN FSAR: ( ) Yes . ( X) No -
' ~
CHANGE INVO!.VES: ( ) Tech. Specs. (X) Neither ( ( ) An unreviewed Safety Guestic.n 1 (See bacl< for Safety Evaluation if required).
..t-- Safety Related . .
(%) Non-Sa f e-ty Relat ed ( ) i
+
j Safety /Non-safety Status Change ( ) Yes (X) No . S '. 8 . . - Attach mariced up copy of procedure to this form. 1 - 8f/f.___ _ __.____
- REASON FOR RECLEST b hh_e_qj__@_-@,p,, N __f_2. .
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. - - - -- - --- ------- do_es--- not .-- cons..t.i ---tute --.a.n u_nrevi_ewed :.2 fe tv -
question as explained belcu. p,
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i_t.y o..f o.ccu r_r.gncq. a.n.d _t_h.g e_qn.5 eou_e.n. c.e.s _o_f_ a n_ _a.c. c_i d_e_n_t____ or relf_unctio_n_o_f _e_o.uipment it.2ortant to sa fetJi- are
- ~ --not in.c..r._ ease _d _-- -
a_b_ove those analyzeJ_in_.the_EMB_dus_19.JAes.e..chucas he.cssa_____
'. - ___the revision __does not c_h_a_nge_ the puroose- or_g.erformance o f th_e
= =-
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system. --__-- . -_- _
- c. .- . .i ---___
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- 2. The possibility of an accident or mal.f.u_nction of a d_ifferent_tvoe - -- -- -- = --- -_ -_-- __ -
t
- f. . 1
,i __ - than ana.l.Li zed in the FS_AR does not result from this chance because e.
.- the system responds and is operated as before the change. __
- 3. The margin of safe _ty as defined in the Technical Soecifications
~ ) "
. J is not reduced due to this revision because the revision does no.t.-_ _ _ .
- - =
--- . chan.ce anv li.m._i_te_.d . safety syste_m_se_ttinas which
- =_
-- - - ---- - - - - - would
- - - - allow a safet'y l,.i_m_it to be exceeded or to al_ low a_.l._imitin_c _c_ondition for operations to be exceeded as stated _.in Technical Snecifications.
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MANUAL SET d-----
raou =ac~o ara =e E. I. H'atch Nuclear Plant HNP- 4724 uvisio= ~o Sne Title Page Georeia Power d
..m ~o o.-
1 of 2
. See Title Pao _e O .
{ GENERAL EMERGENCY - INTERNAL SURVEY TEAM i NOTE This procedure supercedes HNP-4703 Rev. 4 dated 5-13-78. l I A. CONDITION Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential l for loss of containment integrity. Release can be reasonably ( expected to exceed PAG exposure levels offsite for more than the i immediate site area.
- 8. REFERENCE HNP-4720 4
C. ACTION 't>
~ (
I NOTE
$ This action is to be taken by the H.P. Supervisor, and
- {- technicians whenever possible, or by other trained personnel.
- 1. Obtain the following equipment from the OSC emergency kit or i from the HP Office:
High Range Survey Meter High Range Dosimeter GM Survey Instrument and Wipes MSA Air Pack SCBA
- t Protective Clothing
'I Air Sampler lj Radio
- 2. Turn instruments on and allow them to warm up.
s b Don the protective clothing and the SCBA. l' 3. I j Proceed toward area where the emergency exists making a
' survey as you go.
ln , NOTE At all times follow the limits and guidelines in i HNP-4866. t If any of the following readings are observed, retreat l:
,J a.
immediately and notify the Control Room:
~
G 9 i
$4:
- h d '
MANUAL SET
. . , . . +wom E. I.' Hatch Nuclear Plant ** ct =at e HNP .4724 newsiow w Sne Title Page e
em . GeoroiaPower D A . _ . _
'See Title Pace 2 of 2 ,
() Beta, Gamma - any~ reading above 5:R/hr. Contamination - 10,000 cpm above background on a wipe.
- 4. Take samples with an air sampler if conditions permit. i i
n !
- 5. Determine cause of high activity and notify Control Room.
- 6. Rope off and post areas of high air activity or radiation as conditions permit.
- 7. Determine habitability of Health Physics, Laboratory, and Counting Room areas. Notify the Control Room.
NOTE The primary means of communication with the OSC, Control Room, EOF and TSC will be through the use of the plants telephone system. If this system should , become inoperable, then the page will be the backup ,i means of communication.
- 8. Assist Control Room personnel, when requested, in evaluating i the extent of radioactive material released or potential for
' {>3 s release using effluent monitor readings or other air samplers readily available, meterological instrumentation, and procedure HNP-4853 to estimate dose rates to persons at and beyond the plant site boundary.
f. l
- 9. Notify Shift Foreman if conditions exist'that would cause a F person at or beyond the plant site boundary to receive
[ radiation exposure at General Emergency levels or at action levels in HNP-4853. I 10. Communication with the Emergency Operations Facility and/or
- Technical Support Center in determining extent of the ,
o activity release. 9, p 11. Document survey findings on standard Health Physics Survey [ Forms; present findings and present survey forms to H.P.
', Supervision for approval and filing. (See HNP-8012).
h Return to the O.S.C. when release by the Shift Foreman or 4 12. M H.P. Supervisor. 4 i 1O
.ui ll -
l[ " (leje!aiYta "' 'l a h . Manunt su}}