ML20073J037
| ML20073J037 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/24/1983 |
| From: | Clint Jones, Nix H, Rogers W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20073J000 | List: |
| References | |
| PROC-830324-01, NUDOCS 8304190146 | |
| Download: ML20073J037 (135) | |
Text
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l i APPHCvAL PROCLQUHL NO E. I. HATCH NUCLEAR PLANT HNP-4530 See Title Page a6 vision ~o [bl;
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1 of 1 l i ALERT - OPERATIONS SUPERVISOR l t i A. CONDITION
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Events are in process or have occurred which involve an actual or potential substantial degradation of the lev,el of safety of the - plant. Any releases are expected to be limited to small i fractions of the EPA Protective Action Guideline (P.A.G.) { exposure levels. [ l B. REFERENCE g HNP-4520. l C. ACTION I
- 1. Proceed to control room. . , I i L
- 2. Assume the duties of the Emergency Director until relieved, see HNP-4540 for actions. .
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- 3. a. Evaluate actions of Shift Supervisor and Count'* Room !
Operator to bring emergency under control. C l
- b. Assure correct emergency classification has been f declared as per HNP-4520. l j i
- 4. Consult with Shift Supervisor and STA to determine if a more 1 l severe emergency class should be declared. Refer to lI criteria in HNP-4620, 4720 and 4853. /
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- 5. The Operations Supervisor is responsible for notification of ,
Plant Management and NRC as per Emergency Call List and l other offsite agencies in accordance with notification , I procedures HNP-4861. The actual notification process may be i delegated to other, specifically trained, shift personnel. j 1
- 6. Augment shift resources as needed to assess and respond to i
- the event. !
j 7. Make a safety assessment to determine if personnel not l
- involved in the emergency recovery effort should be i evacuated. If possible, consult with Plant Management l' l concerning this evacuation. -
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- 1 0 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Al e r t - Eme rile._n c1 Director PROCEDURE TITLE Naewio - f. vc..>SU f- .
PROCEDURE NUMBER ] l l L_ab RESPONSIBLE SECTION . NON-SAFETY RELATED ( ) SAFETY RELATED ( X) (-----.--------------------..---------------- APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION HEAD MANAGER 3 Page i
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co_e_ rations __to be__ exceeds'_ as stated,in' Technic _al Soecifica_tions ._____.--__ - _ --
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1 awaov% Paoctovat No l E. I. HATCH NUCLEAR PLANT HNP-4540 l See Title Page atvw ao i
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-.,ee Title Page Georgia Power n 1 of a M i 4
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. ' ALERT - EMERGENCY DIRECTOR
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A. C__ONDTION . Events are in process or have occurred which involve an actual or ; po cential substantial degradation of the level of cafety of the I plant. Any releases are expected to be limited to small Fractions of the EPA Protective Action Guideline (PAG) exposure l levels. l t I B. REFERENCE I HNP-4420 l HNP-4520 , I HNP-4620
. . I
-- HNP-4720 f l
HNP-4853
~
e' I'* l i C. ACTION c I l 1. The Plant Mcinager or his designee will assume the. position l ( of Emergency Director as soon as he can establish himself in [* l an activity center (EOF or TSC). The Emergency Director directs the overall management of the emergency response and l i is directly responsible for recommending protective actions l in accordance with HNP-4854 to SREC/GEMA. The Emergency Director may choose to station himself in the EOF or the I TSC. He assigns personnel as necessary to perform the l duties below.
- 2. Assure that the TSC, OSC and EOF are safe areas through the ;
use of portable survey instruments. i
- 3. Establish communications with the Control Room and the TSC l or EOF, as appropriate, and obtain information on the l
diagnosis and prognosis of the accident condition, the estimates or radioactive material releases, and the l prevailing meteorological conditions. This communication j channel is to remain in use for this information as long as l, necessary. t
- 4. Confirm that all notifications as per Emergency Call List ,
have been completed. , I 1 MANUAL SET :
NM PAUC&,UU+4L NO E. l. HATCH NUCLEAR PLANT HNP-4540 See Title Page sem o.no om 5 Georgia Power ~ ~o s ee Title Page O 2.of 2
- 5. Maintain communication with State Radiation Emergency Coor-dinator and/or GEMA and relate the accident diagnosis and prognosis information necessary for these authorities to implement their emergency plans.
i
- 6. Assure that State and local authorities and the NRC are periodically provided with appropriate meteorological and release data, and dose estimates as per HNP-4861. This task .
should be performed in the EDF normally; the ENN may be used to inform State and local authorities and the HPN may be used to inform the NRC.
- 7. Assure that plant status updates are provided to NRC and ,
State authorities at least every 15 minutes. The PSC may be informed by the use of the ENS and the State may be informed by.the use of a dedicated telephone circuit to the Georgia , Emergency Management Agency (GEMA). ' i l' B. Coordinate rescue effort when required. l
- 9. Assure that all personnel reporting to the EDF, TSC and DSC ['
are surveyed for contamination and possible high radiation ; exposure. ,* ' l: l
- 10. Contact company management for outside assistanceg ;
- 11. Supervise collection of emergency data in the Eme'rgency l Operations Facility or TSC log as appropriate.
l
- 12. Organize personnel and standby to provide further' assistance.
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- 13. When appropriate, in consultation with Control Room, TSC, EDF, and Plant Management, escalate to a more severe class i or close out or reduce emergency class by verbal summary to ;
l offsite authorities followed by written summary within 8 hours of closecut or class reduction. Refer to the procedures listed in section B for emergency class criteria.
- 14. Establish security.
- 15. Develop recovery and mitigation plan.
l - MANIML SET ! l
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I GEORGIA PDWFR COMPANY & HATCH NUCLEAR PLANT _ . . . .. - . PROCEDURE
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Notification of Unusual Event s .-..a . ., PROCEDURE TITLE u , . . . . .
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a M e41j-A ALQy44( 4 8) HNP-4420
.,ee Title Page.
a E. l. HATCH NUCLEAR PLANT % ,,, w j 3 e Title Page Georgia Power d ~~ 1 f7 NOTIFICATION OF UNUSUAL EVENT
."~, '
A. CLASS DESCRIPTION s..._ , Unusual events are in process or have occurred which indicate a potential degradation of the level of safety of the plant, such 4
<,,,., as those noted in Table 1. No releases of radioactive material '
requiring offsite response or monitoring are expected unless i
- m. . . further:6 degradation of safety. systems occurs. . .
., .I ,
D. PURPOSE. = ._ - . _. . Purpose of[offsite notification is to (1) assure that the fi. erst step in any. response later found to be necessary has been carried out, (2) bring the operating staff to a state of readiness, and (3) provide systematic handling of unusual events information and decision. making.
., C. PLANT ACTIONS
=-- . . .
NOTE Ya .,.,v..
. .The Shift Supervisorlor. Opera'tions Supervisor.o.- ~,~ ".'
- 1. i "- -)- I!
(or higher ranking licensed or certified person l present) in consultation with the STA , if feasib'le, recognizes and declares that the plant is in a state of' emergency of Unusual Event Class. The Operations Supervisor assumes the role of Emergency Director until relieved by the Plant . Manager or his designee. - - 3 a
- 1. Inform State and/or local offsite authorites of the nature Q*
of the unusual condition within 15 minutes following recognition.
.f :
- 2. Augment on-shift resources as needed. -
l
- 3. Assess and respond.
- 4. Escalate to a more severe class, if appropriate. ,
O_,8
- 5. Close out with verbal summary to offsite authorities; followed by written summary within 24 hours. r
. - .. y M AH AL SkT. == ; = - - -
Aw**Q VAL PNGLtDU58f 980 HNP-4420 aee Ti.le Page . E. l. HATCH NUCLEAR PLANT m,# w
, 5
~~
3ee Title Page Georgia Power a of 7 D. STATE AND/OR LOCAL OFFSITE AUTHORITY ACTIONS ii, . 1. Provide fire or security assistance, if requested.
- 2. Escalate to a more severe class, if appropriate.
- 3. Stand by until verbal closeout.
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; ., , rigi,p,9, E. l. HATCH NUCLEAR PLANT % >u m m
5 See Title Page Georgia Power 3 o, 7 TABLE __1 NOTIFICATION OF UNUSUAL EVENT v% a INITIATING CONDITION EGUIPMENT STATUS PARAMETER VALUE
- 1. ECCS initiated and dis- Auto initiation of: 1 charged to vessel . - Core spray, or -146.5 inches or 2' g.. . ,
psig drywell
~,4 ... . . . _ . . . -- pressure Wrr.vg - W' " 'kHR'.(LPCI mode)
-146.5 inches or 2 ,
m -
---- . . . _ _ . _ . - - .psig drywell _.._.. _.
.. m . a . . . . .
pressure ,
- 2. Radio 1'ogical. effluent w Main Stack and R'est- Exceeding EiTS technical specifica- tor Bldg Vent monitors 2.1.3a tion limits exceeded u~ Hi-Hi alarm plus
- - monitor readings -
~ . . . . - . . . .
Lic.uid Hadwaste Exceeding ETS
, Effluent Hi alarm plus 2.1.la monitor readings - -pv - . . _ . _ _ . _ - . . _ . , _ _ , _ _ _ , _ , _ _ , _ . _ ,
t .-e a "i 3. Fue1n.damagemu ,, ~ ~ - u r -- - .r . n- , y.;.. . . . , _ . . . . , . . . _ , . -
~
- "- indication 1j, ,
u- ,
- a. .v.;. : -
;- , ...?'
- a. High off gas at - Pretreat Monitor Hi Hi 500,000x Ci/sec pretreat" monitor. .
alarm plus monitor corresponding to readings 16 isotopes de-cayed to 30 minutes; or an in-crease of 100,000
^
JACi/sec within a 30 minute period.
. High coolant Lab sample signifi- > 100.p. C f / gm o f activity sample cantly greater than I-131 equivalent limit for normal opera- _
ting I-131 equivalent
- 4. Abnormal reactor Raactor Vessel High 2 1200 psig pressure Pressure i
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. :- - - _ - . - . _ __._._. ._ _ _- M ANUAL SET .- _-- 4 m J'
. - ~ _ ,-
"""-44 see Title Pa9, E. l. HATCH NUCLEAR PLANT ,-~
e Title Page GeorgiaPower d ~~ 4 ,7 TABLE _1_(CONT.) NOTIFICATION OC UNUSUAL INENT
~-
INITIATING CONDITION EGUIPMENT STATUS PARAMETER VALUE
- 5. Failure of a main steam Failure of valve to Torus and/or DW line relief valve to ~ close -
pressure increase [ close-following a re- Torus Temp > 110*F i duction of applicable Torus Level High w pressure.~e~ -
>153 in. {
2.1.h . ~.+ ALM [ i; d . , , Safety Relief Viv , _ _ _ , . ~ - - _ - _ - --
. ._ . . _ ~ . - . - . .. --Tail Pipe Temp. - -
.- , High > 230 # F G. Loss of offsite power .500 and 230 KV system Zero voltagd on or loss of onsite AC ' failure all incoming out-powar capability or side lines zero
. Loss of all emergency , voltage indicated i
~
diesel generators on all 4.16 kV buses
~
- 7. Loss of containment ---Loss of Primary or - See Table la integrity requiring Secondary Containment ~ ~ ' " ~ ~
~T~
~
5'r.] .q 3 shutdown,bystechnical~/.R Integrity:_ ~ _ specifications t - p -.'- -t c c.~L. m; >. c . --
- 8. Fire within the plant. Fire alarm and obser- Operations lasting more than 70 vation . Supervisor's minutes ,
judgement
- 9. Security threat or Observation or valid Operations !
attempted entry or initiation of security Supervisor's e attempted sabatage alcrms judgement based on advise of Security Shift Supervisor
~
lO. Natural phenomenon Observation or Operations being experienced or notification. Supervisor's projected beyond usual judgement levels. I i e a M ANUAL SET -,_ a
Ak "')
- A L gggg g HNP-4420 a,, 7;11, p,9, E. l. HATCH NUCLEAR PLANT 4. .-
e Title Page Georgia Power d -- 3 ,7 TABLE 1 (CONT.)
@TIFICATION OF UNUSUAL _ EVENT dC.f. It!ITI ATING CONDITIOtj . _ .
EGULPt1ENT_ STATUS PARAMETER VALUE
- a. Any earthquake felt Observation or - Alarm setpoint inplant or detected " Seismic Instrumen- is .005 G on plant seismic tation Triggered" g, - ,
instrumentation Alarm on Unit I Con-
;-.; w .. , . ..~.~...o .. .'
trol panel. This starts
'3.C7 c:.2 M ZL ,da ,7d h
~
,Sthe Time /His+ " cord- 1._ _._,i , . . . . c,
-------J -
=-ers-for Units AE "- = - - - - -
- b. Any tornado onsite Observation. .
causing significant= _ l damage affecting plant operations
- c. Any ht hb cane onsite Observation 775 mph causing significant
, damage.affecting , "~ plant operations._- - -
7;h. j d.' 50TFsa F.!fl~ood causin g G? Ob s e rvat i on .~a,z. . , .,.288. 6; f t. ~ MSL ~~"!- 7,
- ._ e - 2:significant.. damage. - - - - - -
- ;/4; +w o~ . c.
,gg, p
operations -
- e. Low river water ~
Unit 1: Intake Screen 6.62/4 ft. MSL. or Low Water alarm plus observation of level
-indicators Unit 2: Plant Service Water Intake Structure '
Low Level alarm plus observation of level
~ . . indicators ..
I
- 11. Other hazards being Operations experienced or . Supervisor's projected judgement
- a. Aircraft crash on- Observation site or unusual aircraft activity [
over facility l
- b. Onsite explosion Observation
=
- -= . - - _ - . - MANUAL SH _,a
t i u%.A mucwum m i 2ee Title Page E.1. HATCH NUCLEAR PLANT m, _ e Title Page GeorgiaPower A ~~ s #7 l 1 TABLE _1 (CONT.) ! NOTIFICATION OF UNUSUAL EVENT
- m. ,
INITIATING CONDITION .m._ EQUIPMENT STATUS PARAMETER VAWE_ g
- c. Significant onsite' C"orine alarm in '
toxic gas release -- Chlorine Bldg. Rupture -
,,.m.,
of chlorine cylinder 6"-
; i '. : .ra t m u cm - ..o.r. chlorine system i
' Z.
. iii.1ZCTC..iem piping or . observation _ , ,, C. ' _ , JJ. . ._.
Significant onsite .
. Observation -
. flammable-gas. release , _l
- d. Turbine rotating Turbine trip,-turbine componant failure internal damage causing rapid plant -
shutdown " -
, 12.Other plant conditions Exceeding any safety Operations exist which warrant in- limit as required in Supervisor's
_ . creased awareness on technical specifica- judgement L
', Nit.3 the' parti.ofEtheTp1 ant 2 ntions' 3.e..J..
~ ~
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- y. ' ' T ~ T ' 7 T '~' '. [ .~
no operating staff-or- ~ ' - ~ ' ' - ~~- ~ ~ ~ - - - - - '~ State and/or local off-site authorities .;;- t
- 13. Transportation of con- High contamination to >10,000 dpm/100cm taminated injured in- injured, individual dividual from site to offsite hospital f
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A'*** 'AL enortDUHEtoo HNP-4420 aee Title Page E. I. HATCH NUCLEAR PLANT ,,_ l e Title Page Georgia Power d ~~ 7 #7 TABLE la HNP-EP
~.1 PARAMETER VALUE FOR LOSS OF CONTAINMENT INTEGRITY REQUIRING SHUTDOWN BY TECHNICAL SPECIFICATIONS Unable to meet one of the following requirements within time limit set forth by technical specifications:
E 1. Al'. non-automatic containment isolation valves on lines connected
"; . ?1 te the. reactor 2 coolant.. system or containment which are not t ..
-= - re,- ired-4o-be-open-during-accident conditions are -closed. -These ----
va. Es.may;beropened..to' perform operational activities. r -.-
- 2. At Jeast one.. door _in the personnel airlock is closed and'sialed.
- 3. All automatic containment isolation valves are operable or deactivated in the isolated position.
. , . , ~ . . .
- 4. All blind. flange and man ways are closed.
- 5. At least one door in each access opening is closed. -
'T}i : --t
~
.i 6. The stafidbyJgssitreatment] system.is operable. , y -.
._ a ; 2 c =. a. e n _. . .. . _ .1 . .. rem ;.. u-
_. d,
- 7. All automatic ventilation system isolation valves are operable ;
and are secured in ,the isolated position. - t j l ll, i l : l
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i
- ).
J. _ _ _ _ _ _ _ _ _ _ M ANUAL SET _. _ i
.~ s
~.
GEORGIA POWER COMPANY HATCH MJCLEAR PLANT PROCEDURE Notification of Unusual Event - Control Room OppratorB-PROCEDURE TITLE
.- . . . -- HNP-44.2.2 _ .
PROCEDURE NUMBER Lab RESPDNSIGLE SECTION g e P wa
. g
~
sSAF_m ET..Y_JRELATED NON-SAFETY RELATED (~ )._.].
...~-4..(.X T. .'.- . . . . _ . . . s
.~_.-.__..~~
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APPROVED APPROVED ~ l REV. '-' DESCRIPTION - ~~ ' DEPT. "'^ PLANT C' DATE
.1 _.. HEAD MANAGER 2 Page N ~ ~ f ,
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PRoccouRE. tio. HNP - _-@%' -- - [
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- . . '3 Revision No._- "2 -- -
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REVISION CHANGES MODE OF . OPERATION OR INTENT AS DEGCRIO'ED IN FSAR: ( )tYes . (X) No - 1 . 3 . w'ww . . CHANGE INVOL.VES:-
' g w. - ( -) An unreviewed Safety Guestion .( ) Tech. Specs. ()() Neither ,
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..' . than inalvzed +- in the FSA~>. d:ss not result from this change _ because,f.
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.;, . 3. The marcin of safety as de9ned in the Technica_l Soe_cifications
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.= -
sa_fet*v l,imit to be excee_ded
-- ------ _--- --- -- o_r to a.l. los a limi ti_nc __c_o_ ndi --
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. . . 3 ee Title Page GeorgiaPower A ~~
1 of 1 ge, NOTIFICATION OF UNUSUAL EVENT - CONTROL ROOM OPERATORS ,
- a:. -. .
A. CONOITIONS.a., u Unusual eDefit's"are'in~ process or have. occurred which indicate a potential degradation of the level of safety of the plant, such p as those noted in HNP-4420, Table 1. No releases of radioactive L am, materialdrequiring offsite response or monitoring are e~pected un1ess%fut,t.herldegradation.of. safety s occurs. ;c,,_. i, ,
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- 8. REFERENCE : i J. . . _ . .
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C. ACTION . :..
- 1. Ta[e appropriate action to place the plant'in a safe -'
condition in accordance with emergency operating proceoures, n ;, Tech., Specs., and annunciator response procedures.
.- u . . . _ . . . _ . _ . -
- 2. Make the following announcement ove{ the PA:
.y p ; _
. - ~ . . . . . . . . - . ,y.. . ~ . - . . . - , . .
~ ~ r.
- ATTENTION,-. ATTENTION: A NOTIFICATION OF UNUSUAL-EVENT - -
=
EXISTS. . (If immediate safety of personnel involved, state the incident.) -INITIATE NOTIFICATION OF UNUSUAL EVENT PROCEDURES. .. NOTE There is no Gai-tronics tone for Notification of Unusual - h' Event. Repeat announcement. ,
- 3. Check the control room instrumentation to determine status of plant as to whether or not a more severe emergency class should be declared. Notify Shift Supervisor of findings. l
- 4. Notify Security.
- 5. Evaluate radiological releases using HNP-4853 and inform Shift Supervisor of results. ! '
- 6. If Shift Supervisor has not reported in to the control room, l initiate his actions as per HNP-4423.
- 7. Announcement of the " Notification of an unusual Event" status should be repeated periodically (approximately every 30 minutes) throughout the duration of the event. .
. _ _ , . M AMIAL SET -
.=~a. =.m t
\
GEORG! A POtFR CC*,PANY HATCH NUCLEAR PLANT PROCEDURE NOTIFICATION OF UNUSUAL EVENT-SHIFT SUPERVISOR
.. PROCEDURE TITLE - ahsay. . 't e. %w buy. e + +-r* ^
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.2 PROCEDURE NUMBER
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__$_20 : i. 3 ' ' Revir. ion No. ---_-----__ -
- 1
. _ - - _ - - _- _- - RFC f:~S__TFD_RY = - - - - - - - - . - - - - - -
D'~P,*.R TMGPIT l-IFr.0 f.PP:<n'.'.:.t . . 1 tu,me ; Dates Signature: .. D*at e : s -
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} A- H3, REVISICN CHM:GES MCCE OF .CPERATIOtt OR INTf.NT AS DEGCRIDED IN FSAR: ' *
( ) ,Yes (.)( ) No -
", . . CHANGE ItWOLNES:-
( ) An unreviewed Safety Guestion ( ()() Neither
~
) Tech. Specs.
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s _____e._____ or malfun:tien _ _ -__ _ __ __ _ _of _ _ ecui- _ _ _ _ _ _snt e. _o i_r:_ ta _n.et__o t _s_aft _e.J' _ _a r e n o t i n.c. _r_e a_s_e d_____ ___ e - _ _ _
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_ than an_a_lvzsd _ in the FS.2.P. d:ss_not result ---- f_ rem _ this chanc_e because; --
.s the s.ystem re_s.c._ond_s_.and .is ::s_ rated as before the chano.e. - -
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_ - = . _e._m.
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-is_.n.ot re_duced d_ue_ to th_i_s_r_e_v_i_s. ion becau_s_e_t_he__revis ion do.e..s. not_m._ ..' ..
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- __anv -li:nited__s.a._fe_ty sys_t_e_-_i settinos which wo_uld al_lo_w ~a -
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l safet'y__l,.i_m_it . - to be e_x_ce_e_d.s..f._o_r_ to allow a limi tinc._condi tion for-- -
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A4oo sa, egn;tpunt No HNP-4423 cee Ti+1e Page E. l. HATCH NUCLEAR PLANT m ~% e Title Page GeorgiaPower A -- ~o 1 ,1 p t NOTIFICATION'OF__ UNUSUAL _ EVENT-SHIFT SUPERVISOR l } j A. CONDITIOL4S l Unusual events are in process or have occurred which indicate a l potential degradation of the level of safety of the plant,_such .
.. as those noted in HNP-4420, Table 1. No releases'of radioactive
.- material requiring offsite response or monitoring are expected'
., s .m unless, fur.ther_. degradation of. safety systems occurrs. __. I_ {
B. REFER _RGE./ - . .a .- HNP.-4420 , i_. , ,, , I C. ACTION .-
- 1. Proceed to control room immediately.
- 2. Classify and declare emergency using HNP-4420, ensure that 1 correct cperator action has been taken to bring. emergency l under control.
34 - . . . _ . . ~ . . - . - - - . ~ - _ . . . . . _ _ _ . . .. 7' 3. a Evaluate conditions-and findings of'the contro broom .. . operator.to see if a more severe emergency class should be declared. Refer to criteria in HNP-4520, 4620, 4720 & 4853 procedures. .
- 4. Activate rescue team if necessary by notifying Health Physics. ;
- 5. Assume the duties and responsibilities of the Operations Supervisor if he does not report to the Control Room,.or is incapacitated, as per HNP-4430.
- 6. Direct onsite actions to bring emergency under control.
i l iI
!4 4
v - %- . _ _ _ _ _ _ _ . _ M ANUAL SET -- b
.- - ._a
, __ e._ v ,
CECRGI A PCtER COMPANY HATCH NUCLEAR PLANT PRDCEDURE , NOTIFICATION _ OF UNUSUAL EVENT . OPERATIONS SIIEERV.lSOR
- , m.4.-
1 PROCEDURE TITLE
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^'t REV. -DESCRIPTION DEPT. PLANT DATE HEAD MANAGER .
_ _ _ _ _ .._____ 3 $ _ _ _ _$_ _ _ . '
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- _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________ y_______. ,i f
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HNP-9 , 1 . v MANUAL SET
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PROCCOURE. t/O. l iNP - @ M__-__
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. _ _ _ ____ _--_ F_0_U_:: - P _T -F_D_R _ _ Y _ __ __ _ __-__ ._. --_O_U_P_AR _TtG_ _I_T t_r_c.0_ _ A_P PWf.'At .
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d 2 - {. _ Q --___---- REVISICM' CHANCES MOCE OF.CPERATION 09 JNTENT AS DESCRIDED IN FSAR:
. ( ) ,Yes
( )( ) No -
.. CHANOE INVOLVES:-
* ~~
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- PHO 3(.cretary l
- 83-38 ,q.
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____________.___ belcu I _ _ _ _ 1_ _ .. Tha _ o_ r_c_ _a. 5 .bili'y _ _ _._ _ . of . .. _occ_ _u_r_r. = _ w" _a _n _d_ the _ - ..c_o_n.,enc a _u e n ces _ _.of _ _an _ _ accidmt_ _ _._ _ _ _ _ _ _ _ _ _ _____ ___o_r__c_al_f_u_r._: t _i_c_n__o _f e.c._u_i: __2_:t _i__:o r_t_a_n.t._to__s_a _ _ _ f_e_t_y__a _r e__n_o._t _i_n.c._r_e a_s_e_d_ _ _ _ _ __. _. ____ _a_'b. .o_v _a_ h.vy _a_n 2a.l_v' n _ in_.N,_~T,e . _a n _d_.u a lo. _Le a rc v'AS_ a_r.ms- a_ __ ___ _
-_---- t_h_e__re_v_i_s_i o_n__d_o_e s__n.o._t. ch 'a_r._: s__t_h_e _ou - - r_co s e__o_r o e_r.f._o r _a= _n_ _c._e
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tha n anal _v_:e_d_.i.n ' the FSA. d:s s_ not re_sul t f_'re_m__t_h- _i s__c_h_ance__b_ec_a_u_
=- - - - _ .
th e s -=ys_t_e_m r_e s._c.o.n_d s_ a n d i s :: e ra t ed a s _ _b e fore t_h_e_ch a n ce . t
- 3. Th e__ra_r_c i_n o_f__s _a f e_t_y _
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See Title Page GeorgiaPower 1 of 1 NOTIFICATION OF UNUSUAL EVENT-OPERATIONS SUPERVISOR A.. CONDITION. . 1 Unusual events are'in process or have occurred which indicate a potential degradation of the level of safety of the plant, such as those noted in HNP-4420, Table 1. No releases'of radioactive g? d , material-requiring offsite response or monitoring are expected' i l$ ._ unless.. fur.therldegradation of safety systems occurs._ _ _ f B. REFERENCE A4 #~_.u.. . . . _ . .
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C. ACTION g u.
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- 1. Proceed to control room immediately.-- ~-
;, 2. Assume the duties as. Emergency Director and take " - responsibility for overall management of emergency response, - -l including declaration and notification of the emergency,
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- a. Evaluate actions cf Shift Supervisor and operators to ~
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- b. Assure correct emergency classification has been declared as per HNP-4420.
- 3. After consultation with Shift Supervisor and Shift Technical l Advisor determine if a more severe emergency class should be declared. Refer to criteria in HNP-4520, 4620, 4720 and 4853.
- 4. The Operations Supervisor is responsible for notification of Plant Management and NRC as per Emergency Call List and -
other offsite agencies in accordance with notification j procedure HNP-4861. The actual notification process may be , delegated to other, specifically trained, shift personnel.
- 5. ' Augment on shift resources as needed to assess and respond to the event.
l
- 6. Close out after the emergency with verbal summary to offsite i authorities; followed by written summary within 24 hours. l; IY
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- - .- - - - . - ... _ .. -- - . . - - - MANUAL SET -
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PROCEDURE i
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PROCEDL'nE. ?!D. HNP -
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- - - - -- - -- ..-- DrP ARTMENT H.W.O APP:<nw.i.
N/ tw; De't e : Signature: .. Date:
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. REVISICM 'CH5tiCES 'MOCE OF .CPERATIOtt OR INTENT AS DEGCRIDED IN FSAR: .'
. . .- . ( ) ,Yes
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... CHANGE INVOLVES:- .
. ff*'*t * ( ) An unre' viewed Safety.Guestion ( ) Tech. Specs. . ('[s ) Neither .
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C' _ __u q _e s_t_i_o n _a_s_' _e x_p l.a._i n e_d_ _b _e l c_w ._-____ ____ ______________/_______. _______. l .
- _1 T_h_e_ o r_o_b_a..b._i _ l_i_t_y _ o..f.._o_ccu_r_e.s. -"m_a_n d__t_h e rq.y_o_u_e_n_c.e.s. n .
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- . ' chance an.v._'l_i_r.i.t.ed sa fety_. syste i settinos which would allow a l safet'L_l,.i_mi t to be exces_d_s.f._o_r__to _a_llow a limi tinc _c_ondi tion for
_____oc_erations to be exceeded as stated -in' Technical Soecifica_t_ ion _s_._
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n PM.4 PHr.JCLDU R t NO E.1. HATCH NUCLEAR PLANT HNP-4523 See Title Page at m.cwo I m - 4
~ ~o See Title Page - Georgia Power 1 ,, 1 ,
ALERT - SHIFT SUPERVISOR i
.t-m A. CONDITIONS '
6 Events are in process or have. occurred which involve an actual or l potential substantial degradation of the level of sa'ety of the 1 plant. -Any releases are expected to be limited to small 4.;i m fractions'of the EPA Protective Action Guideline (P.A.G.) '
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HNP-4520 :.,.x n . . I
- 1. Proceed to, control room immediately. l
~ . ~ . . . . ~ . . . . -
- 2. Classify and declare the emergency using HNP-4520, and ensure that correct operator action has been taken to bring j.
emergency under control. ( INb. , 3.' Teva 1Ea~te..coI1Iditions[and findings of thWTontrol~ro'om~ ~. ~ ~
~
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~ ~ ~ ' operator to see-if a Site Area or General ~ Emergency should - 9 be declared, based on performance of HNP-4853 and on criteria in HNP-4620 and 4720.
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- 4. Activate Internal Survey Team by contacting Operations .
Support Center' Manager when staffed. Direct Internal Survey l Teams to areas to be surveyed as appropriate. j 9
- 5. Activate Rescue Team as necessary by contacting Operations ]
Support Center Manager when staffed. ,. l
- 6. Establish communications with the Emergency Operations Facility, Security Force, Technical Support Center, and Plant Management as soon as possible and discuss declaring a j' Site Area or General Emergency and/or the need'for outside assistance. ._. . . .
- 7. , Direct onsite actions to bring emergency under control.
1
- 8. Assume the duties and responsibilities of the Operations !
Supervisor if he does not report to the control room, or is { incapacitated, as per HNP-4530. ; i
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. t j-M ant lAL SET
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GECRGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Alert - Internal Survey Team ap , PROCEDURE TITLE
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- HNP-4524 _
PROCEDURE NUMBER
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Y 0-* f .A 4 -V 3 _______ " W_Sb REVISICil CHANGES MODE OF . CPI.Rr, TION OR INTENT AS DEGCRIDED IN FSAR: t )gYes . ()() No -
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than a_n_a_l.yzed in the FS.P._d:es not result _frem this chano._e because -- -- th_e_sys_t_em u resconds and is f:e.r.=ated as before the chan.c.e. _ _ _ _ _ _ __ _ ____= __ _ __ -- - _ _ _ -==___
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GeorgiaPower A ~~ 1 ,, y g ALERT - INTERNAL __ SURVEY TEA!j
. T.D A. CONDITION Events are in process or have occurrea which involve an actual or potential substantial degradation of the level of safety of the 2,, plant. Any releases are expected to be limited to small
%. fractions of the EPA Protection Action Guideline (PAG) exposure levels.t--L--,
- - - +,
V _ 3 B. PEFERENCES~ = - - I H4P-4520 . .a . -. - , C. ACTION --
' ~~ ~ ^
NOTE , This action is to be taken by the. Health Physics Supervisor or designated alternate, whenever possible,
,,, or.by other. trained personnel. _ _ _ _ , , . _ . _ _ , , , , . , ,,
M ^^ t 1.' Obtain the following equipment from the OSC Emergency Kit or -] from the HP office. . l High Range Survey Meter i High Range Dosimeter GM Survey Instrument l MSA Air Pack SCBA I Protective Clothing ! Air Sampler Radio : Wip'es l l 2. Turn instruments on and allow them to' warm up. 1
- 3. Don the protective clothing and the SCBA. Proceed toward j' i area where the emergency exists making survey as you go.
NOTE ,, At all times, follow the guidelines and limits of HNP-48E.6. ', l a. If any of the following readings are observed, retreat and notify the Control Room. l' Beta, Gamma - any reading above 5 R/hr Contamination - 10,000 cpm above background on a wipe . 4
- 4. Take samples with an air sampler if conditions permit. l 4
- l
- .. -- - . . - . - M ANUAL SET ., .,
, W . l
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, E. l. HATCH NUCLEAR PLANT HNP-4524 aee _.tle ii Page me. u au 3 see title Page GeorgiaPower A ~~
g ,, y S. 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.
y ' , ~
, . . 8. - Assist Control Room. personnel, when reouested, in evaluating
.- M theJe.xtent.1of: radioactive material, released or potentidl for . 7 ,
~ release n sing effluent' monitor ~ readings or other~ air ~* - - -*
-samplers"readily available, meterological instrumentation, -
9 and procedure HNP-4853 to estimate dose rates to persons 8 y.
; _. beyond the.. plant _ site _ boundary..... _ . _ _ . . _..g.. y
- 9. Notify-Shift Supervisor if conditions exist that would cause -
a person at or beyond the plant site boundary to receive -l
~
radiation. exposure at action levels in HNP-4853. 3'
- 10. Communicate with the Emergency Operations Facility and/or Technical Support Center in determining extent of sny
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...a.,- 11, Document survey findings on standard health physics' survey forms. (See HNP-8012)
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- 12. Returh to the OSC.when released by the Shift Supervisor or l
HP Supervisor., 4 {
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GErRCIA POWER COFPANY HATCH NUCLEAR PLANT PROCEDURE
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ALERT EMER_CiNCY - RALLY _ POINT LEADER PROCEDURE TITLE
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REVISICN CW-,NGEC MOCE Or .CPERATION OR INTF.NT AS DEGCRIDED IN FSAR:
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?.ee Title Page -ev.s.u ~o l sn 4 Georgia Power See Title Page O
~ ~o 1 of 2 u
Gu ALERT EMERGENCY _,- RALLY POINT LEADER Ma A. CONDITION J Events'are in process or have occureed 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 . ig. fractions'of:the EPA Protective Action Guideline (PAG) exposure . , 2:,w;.. _ _ 1 eve 1s.u * $ : LULL.2ii o - #
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B. REFERENCE-
.t92= L:- - - -
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; 1. .Once the Rally Point Leader.is designated by the OSC manager,--he should appoint approximately three RET members
. .,.y _to_repor_t.with,him to, gate.16,,which..is.the_pr.imary. rally _ . , z:-n, n
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2... .. Determine if the rally point is habitable using survey
'~
~ meters and the following criteria:
- a. area dose' rate less than 0.5 mr/hr, and
' b .- - contamination less than 100 CPM above background.
- 3. If conditions at the primary rally point (gate 16) do not satisfy the criteria in C.2, then proceed to an alternate rally poir.t. The alternate rally point is The Skills Training Building or The Environmental Building.
- 4. Determine if the alternate rally point satisfies the e criteria in step C.2. l t
5.
~ '
Return to gate 16. -
- 6. ' Notify the Control Room of results.
- 7. Prepare for evacuation of plant personnel if the emergency, class should escalate, periodically confirming that j conditions at-the rally point are still acceptable. l e- MANUAL SET -
.-a.e J
. - ~
~
- \
a w vat m ov t ,,oa E. l. HATCH NUCLEAR PLANT WP-4526 See Title Page m,-o a 4 See Title Page 2 of a
- 8. Do not release members of the Radiological Emergency Team,
, except to report to the EOF, until directed to do so by the ~. -
Emergency Director or Operations Supervisor if the Emergency l Director cannot be contacted.
- 9. Assist in routing ambulance to pick up any injured personnel.v-- Assure ambulance driver and attendant are f eL provided with TLD badge and pocket dosimeter on entry. . ;
i 3 . ' ?;t~ z ' *?; * . .:. - . . .
.~ #. i 10. : Assist.EmergencyJDirector **~'-
in bringing emergency under7
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE USE AND CARE OF RESPIRATORS PROCEDURE TITLE i HNP-8010 PROCEDURE NUMBER
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LAB RESPONSIBLE SECTION g5 . . ..
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.. SAFETY RELATED ( X ) NON SAFETY RELATED ( )...
I _-____,________ ___________..______-_________.. _______________i._______. APPROVED APPROVED -g REV. DESCRIPTION DEPT. PLANT DATE l HEAD MAN GER 13 General Revision g _ _ - _ _ _ _ _ _ _ _ . ..___ ___ L _ _ _ _ .._- .. _ __ .. j eg2,_ _ - _ .
'. 14 < s M _ _ - *_4. ' 8_N N__.
(' . - _G_e_n e r_a_l__ _Rev_i_s_i_on _ _ _ _ . . Pages 1-3,6,8,9,14,16, . j
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.. _ _ _ _ _ _ . . _ _ _ _ _17_.- _ _d. d_t' --
' f_ .. _k_ _'_ A_- / __ i 16 General Revision
_ _ _ _ _j __ p -. - _ /' _.[ _ _(p_ _ 3 ______ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ - _ _ _ - - _ _ _ _ _ _ _ _ .. _ _ _ - _ _ _ _ _ - _ _ - _ _ _ ..________ l- _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ .. - - _ - _ - - _ _ _ _ _ - - ..______-- j
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i- REGUFSTFD OY OFPARTMENT HFAO APPleD'JAL'- r- Date; Date: Signature: 1 Name yll$ ; Jhc/j_&c .] O_r Z -?2- W 0
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o i - REVISION CHANGES MODE OF OPERATION OR INTENT ^ DESCRIBED IN FSAR: ( ) Yes ( No - k Lfdti@Kl. ~ . - . - - .... . .s...... i ".-: CHANGE INVOLVES: .
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CHANGE INVOLNES: :
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(See back for Safety Evaluation if required). Safety Related ( Non-Safety Related ( )
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Safi-ty/Non-saf ety Status Change ( ) Yes ( j No ' Attach marked up copy of procedure to this form. REASON FOR REGUEST_lpg__JP Eisn h d,,.,);,ya/ fff Q/ _
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. . - . . WoritDuM N0 HNP-8010 E. l. HATCH NUCLEAR PLANT *w. w 2ee _.tle ii Page
- n 16 (:)Es C GeorgiaPower A, ~~
See Title Page 0 1 of 36 A USE AND CARE OF RESPIRATCRS t A. PURPOSE
'.l T ' To provide instructions for the proper selection, use, maintenance, control and storage of respiratory equipment.
ig' r.4
.~ This procedure covers.the following respiratory devices: ,
~
=-
MSA Ultra Filter Respirator , MSA Pressure Demand Apparatus ( Air Pack) MSA Constant Flow Air Line Respirator , NPO Supplied Air Respirator (Hood)
- 8. REFERENCES f
- 1. 10 CFR2O para. 20.103
- 2. MSA Respirators Instruc'tions for Use and Maintenance a
NPO Supplied Air Respirators Instruction Manual
.) 3.
~#
- 4. A.N.S.I. Z-88.2 (1969) .
C. SA%ETY Observe Radiation Protection Procedures. , D. MANAGEMENT POLICY It is the Georgia Power management policy to minimize the inhalation of airborne radioactive materials to all personnel assigned or visiting Plant E. I. Hatch. For this reason it is
- mandatory that personnel at Plant Hatch adhere to all procedures, e and policies relating to the respiratory protection program.
The management policy will be normally accomplished'by the ! application of engineering controls, including process, containment, and ventilation equipment. Periodic evaluation of i the respiratory protection program will provide the management with the means for determining what additional measures, equipment and controls may be necessary, where practical, to- l further meet the objective, while in turn reduce the need for ; wearing respiratory equipment. 6 I Routine plant operations are planned activities that are , ( generally repetitive and occur with various frequencies. Operations of this nature have been considered in the design of
- the plant and appropriate equipment installed to minimize most
- airborne situations. !.
- i
- n
- n
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Pse OCEDUAE NO E. I. HATCH NUCLEAR PLANT HNP-8010 mee +:tle Page enou w
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Georpia Power A ~~ _ 2ee - : tle Page 0 2 of 36 , *~- , The use of respirators as a substitute for practical engineering controls in routine operations is inappropriate. Therefore the installed process, containment, and ventilation equipment will be utilized, in addition to -preplanning of work, to minimize the use of respiratory equipment. Nonroutine operations are activities that are either j ggog m . nonrepetitive or else occur so infrequently that adequate
't2S?, '
limitation of exposures by engineering controls is impractical. 1,,L. For operations of this type respiratory equipment will bd used where n'eded e to provide protection. Emergency operations are unplanned events characterized by risks sufficient to require immediate action or mitigate an ab'rupt or rapidly deteriorating situation. Procedures have been issued for nandling most emergency situations and are contained in procedure , series HNP-4000-4999. Adequate quantities of and locations for respiratory protection equipment are provided to handle emergency
. situations. Training and retraining of personnel in emergency
; situations requiring respiratory protection is provided.
1 (y Prior to issuing a respirator to an individual, he/she will be
*S.?P informed of the following policy: Persons wearing respirators may leave the area at any time for relief from resparator use in the event of equipment malfunction, physical or psychological distress, procedural or communication failure, significant deterioration of operating conditions, or any other condition that might require such relief.
E. FEGULATORY REGUIREMENTS 10 CFR2O paragraph 20.103 specifies regulations regarding exposure of individuals to concentrations of radioactive materials in air in restricted areas. This procedure has been written to carry out the regulations. F. DESCRIPTION OF RESPIRATORS
- 1. Ultra FJ1ter Full Facepiece Respirator Thi.s respirator is a full facepiece unit with a single or double cartridge providing protection factor of 50 against dust, fumes, and mists having a time weighted average less than 0.05 milligram per cubic meter. The respirator with the rectangular ultra filter cartridge has an approval No.
TC 21C-150. The respirator with the round ultra filter Type H cartridge has an approval No. TC 21C-155. - ( MANUAL SET _, a e m.m . 4 - - _ . _ . . , - . . _ _ _
ha . PROCEDuett NO HNP-8010 mee _. istle Page-E.1. HATCH NUCLEAR PLANT aueo u:. 16 Georgia Power dz b1 ee. Title Page 0 3 of-36 2 NOTE This respiratur removes only dispersoids from the air. .It gives no protection against gases, vapors, or oxygen deficiency ~(less than 19.5% O ). 2
^
pgy 2. Pressure Demand Apparatus (Air Pack)-
;b.b.' The Pressure Deman'd. Apparatus (Air Pack) , consists of 5 high pressure cylinder, a' pressure demand regulator connected by a high pressure tube-to the cylinder, a facepiece and tube assemoly with an exhalation valve, and a harness assemoly for mounting the complete apparatus on the body. . Thd unit maintains a slight positive pressure inside the facepiece during innalation, thus minimizing potential-air in-leakage into the facepiece. The unit contains-an audible signal device to indicate when the breathing supply has dropped to a point where the user must return to f resh air. The unit
/ is rated for 30.minutas' service. Actual service time will
} depend on the user and his level of exertion.- The unit has an approval No. .TC13F-29. It can be used in oxygen
_7
.yjf deficient and in-toxic atmospheric' conditions and-has a .
protection factor of 10,000 for particulates, gases.and vapors.
- 2. Constant Flow Air Line Respirator.- Full facepiece The Constant Flow Air Line Respirator is a respirator.
approved for use in atmospheres not immediately hazardous to life or health. The unit-consists of a facepiece and tube assembly, low pressure control valve, from 25-300 feet of air ~ hose, and a portable air filter and regulator.
' Breathing air for this unit is provided by the plant service
- air! compressors. :The service air is filtered and reduced in j pressure to 35-40 psig by the portable air filter and regulator to meet the requirements-of the respirator. With this respirator, a continuous flow of breathable air is supplied to the facepiece and provides a cooling effect as it meets the respiratory requirements of the wearer. The unit has an approval No. TC19C-78 and provides a protection Factor of 2000 for particulates, gases and vapors.
- 4. Hoods
. The Supplied-Air. Hood is approved for respiratory protection against atmospheres.not immediately dangerous to life or . health a'nd contains 2_ 19.5% oxygen. The unit consists of a (- hood, cape, air distribution unit, belt, air line hose and l [ source of clean respirable air (Class D or higher quality).' The respirator has a MSHA-N105H approval TC-19C-140.
- s. .
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9 of 36 s._ a prctecti:n factor c up to 2000 may only be used when the air flow is maintained at the manufacturer's recommended maximum rate of 15 SCFM. The following Table will be used to estselish pressure settings for the Air Supplied Hood. PRESSURE RANGE (PSIG) LEMOTH (FEET) NO OF SECTIONS MINIMUM MAXIMUM l j hMMh.ye; ________________________________________________________ _____________.
~
25-50 1 ~o r 2 20 34 (28*) 7~-100 1 -4 25 45 125-175. 2-6 30 '50 3.~O-E75 2-6 38 55
- Maximum Pressure of 28 PSIG will Hansen (B) and snap-tite (D) 9 fittings.
NOTE
#^h A protection factor of 2000 may only be used when the pressure is regulated at the maximum pressure settings-listed in the above Table. Pressure settings less than tha maximum range and greater than minimum range will drop the protection factor to 1000. Never set pressure below the minimum range nor higher than the maximum range.
G. SELECTION OF PESPIRATORS FOR USE NOTE
, Respiratory protection devices may be required in any situation arising from plant operations where the potential for airborne radioactivity, oxygen deficiency,, or' toxic atmospheres exists. In such cases, the air will be monitored by Health Physics or other qualified personn'el and the necessary protective devices specified according to the concentration and type of airborne contaminants present. It is the responsibility of the individual and his supervisor to notify Health Physics personnel when working with radioactive or hazardous. material that are likely to become airborne. Every precaution should be taken to keep air contamination to a minimum through use of proper ventilation and prior decontamination of equipment or work areas. -
(O s_J f M ANU AL SET _, .;
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1 4""- ' PREEUUMt NO
. E. I. HATCH NUCLEAR PLANT HNP-8010 we _.tle
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- 1. Regulatory limits and rules.
Respiratory protective equipment will be selected to provide a protection factor greater than the multiple by which peak concentrations of radioactive materials are expected to I j 1(( . exceed the values specified in Table I Column 1 of Appendix B to 10 CFR20. The equipment selected is to be used so that-ji m c. the average concentration of radioactive material in the air IT?/$( m. that is inhaled ,during ar-y period of uninterrupted use in an LJ4C; airborne radioactiv'ity area, on any day, by any individual us'ing the equipment, will not exceed the values specified in Table I, Column 1 of Appendix B to 10CFR20. For purposes of this procedure, the concentration o'f radio-active material in the air that is inhaled when respirators are worn may be initially estimated by dividing the ambient ' concentration in air by the protection factor specified in 10 CFR 20.103 Appendix A. If a respirator user's intake of radioactive materials is later determined by other l i g measurements to have been greater than that expected from
'. initial estimates of radioactive materials in the air the user inhales, the greater quantity is to be used in w,ky.
evaluating exposures. If it is less than that initially
. estimated, the lesser quantity may be used in evaluating exposures.
- 2. Administrative rules and limits.
- a. Section E and paragraph G.1 prescribe rules and regulations which shall not be exceeded. For administrative purposes Table 1 will be used for selecting respirators.
- b. If airborne conditions exist which require consideration toward exceeding the administrative limits in Table 1, a laboratory supervisor must be consulted and his approval received before using greater values.
- 3. Selection procedure.
- a. Determine the radiological (external radiation an'd airborne) conditions-in.the work area using the procedures HNP-8005, 8012, 8013. Air samples should be taken as near the breathing zone where the work will be performed as possible. (Also if the worker has to pass through an airborne area to get to the w 'k place). - 1 l (
i b. If air sampling conf'irms that an airborne condition, as defined in HNP-8003, exists in the work area, * !, respiratory protection equipment, increased surveillance, or limitation of working times is warranted. .
? M ANUAL SET __j t .. e. o ... _ . _ . _ ...-..-_m
- . - - emovpt No
. E. I. HATCH NUCLEAR PLANT HNP-8010 See Title Page *vum w h- See _.tiv : Page Geo biaPower A ~~
6 of 36
- c. Consider the type of work, work hazards and locations, time to complete the work, ambient conditions at the work location,* equipment to be used by the worker, and the potential for airborne conditions to develop during the work period (i.e. highly contaminated areas and
; 4-~ equipment, opening of equipment during the work, air movement in the work location, cutting and welding j gq work, etc.). . m. J.. d. Consult with a laboratory supervisor or designated 4*-~ ~ "--
alternate and select the proper respirator for the work conditions using Table 1 and paragraph b and c above.
- e. Issue the respiratory eqi nment per Section H.'
The worker, after proper training, will wear the respirator using Section I as guidance for-donning the equipment.
.I' 4. Determination of Airborne Radiation Exposure.
(~4 a. Anytime an individual is likely to inhale, for any two
- A hours in a day or ten hours in one week, radioactive nf'*' - materials in uniform concentrations as specified in Appendix B. Table 1 Column 1 of 10C;3R20, the following calculations shall be made to determine levels of airborne radiation exposure.
- b. From the data on HNP-8013 Data Package 1, Data Sheet 1 and HNP-8003 Figure 2, calculate the exposure to airborne radioactive materials as lollows:
K MPC - HRS = Hours in Area multiplied by Activity _N (PF) MPC N=1 N N WHERE K = Number of nuclides in the air th Activity = Activity of the N Nuclide in uci/cc N th PF = Protection factor of the respirator for the N N Nuclide (See 10CFR 20.103 Appendix A) th MPC = MPC of the N Nuclide in u ci/cc - h' N Hours in Area = Stay time in the airborne area in hours
- c. Log the airborne exposure in MPC HRS for the appropriate day on Form 5 (Data Package 3) using the results obtained from G.4.b. .
MANUAL SET ! f i. & 4 a.... _ .. _ -c __ M
4*** ~ PROClouHt NO E. I. HATCH NUCLEAR PLANT HNP-8010 See Title Page
- us4w uo A 16 Om.. Georgia Power A ~ ~o see _':tle Page~ O 7 of 36 NOTE If an individual's airborne-exposure exceeds 2 MPC HRS in any one day or 10 MPC - HRS in any one week then that individual's intake will be assessed by
[C. appropriate methods as outlined in Section L and all his exposure to airborne radioactive materials will be j e a c.t . documented on Form 5 (Data Package 3) for the current
- 1777; calendar qua.r.ter including those cmounts of exposure 15;
- below 2 MPC - Hrs. in a day or 10 MPC - Hrs. in a week..
H. CONTPOL. ISSUANCE1 PROPER USE AND RETURN OF RESPIRATORY EGUIPMENT
- 1. The Health Physics staff centrols the issuance, prop'er use, inspection, cleaning and repair, testing and fitting, spare parts, and quantities of respirator equipment required.
(The Regulatory Specialist handles special training for the fire brigaoe team on SCOA). Training is conducted by the Training Department.
- f .~., -
e 2. Respiratory equipment will be issued only to. N-A.gf.y a. Those persons who have been trained, fitted and tested-d' for that type equipment.
- b. Those persons whose facial hair does not interfere with the seal of the respirator.
- c. Those persons who have received medical approval by a physician to wear respirators.
3
- 3. Only MSHA/N10SH approved equipment will be used when taking credit for the use of respirators in protecting personnel from airborne activity.
- 4. ' Respiratory equipment will be issued using a Radiation Work Permit procedure, ex cept dt ring emergency conditions.
- 5. Adequate surveillance and surveys of the work activity by the Health Physics staff will assure proper use of the equipment.
- 6. The Health Physics etaff will. conduct an adequate number of air surveys during the work period to verify and assess radiological conditions and exposure to personnel.
- 7. Facelets will not be used for protection against airborn .-
() radionuclides. .
. 8. Equipment will be used within the limitations for its type and make of use as described in this procedure.
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. E. I. HATCH NUCLEAR PLANT HNP-8010 See Title Page aeve m ~o A~ .-e 16 U. dee
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~ ~o 8 of 36 B. Only the SCBA equipment is to be used as emergency devices.
.:. Wneae 'ecuired, spectacle kits will be furnished to permanent plant personnel.
3727
~ ~ ~
- 11. Where r'equired, goggles, anti-fog compounds and communication gear will be furnished to respiratory users.
, n . . _-
1353*'
. m .-
- 12. Contact lenses are not to be worn with full-facepiece.
a,.s _ ., respirators.
- 13. Air purifying respirators are not to be used in oxygen ocficient atmosoneres or atmospheres immediately haz,ardous to life or health.
- 14. No credit will be taken for use of sorbent cartridges against radioactive materials.
- 15. Only high efficiency cartridges, as described in Section F f will be used in air pur.ifying respirators when making allowance for the use of respiratory equipment in estimating (sq exposures of individuals to airborne radioactive materials.
w' *
- 16. Filter cartridges on air purifying respirators must be replaced with a fresh cartridge after one work day's use by one individual.
- 17. Respiratory equipment except energency equipment, will be issued by and returned to .the Health Physics staff.
Issuance will be controlled through an RWP permit, a Respirator Clearance List (or Respirator. Clearance Card), and the use of Form 6 (Data Package 4). The normal method of issuance will be through the use of the clearance card unless exempted by the H.P. Superintendent or designee. In lieu of Form 6 (Data Package 4), Health Physics may control issuance and re'a.rn of respirators at established control points by the worker surrendering the respirator clearance card to the Health Physics technician upon issuance. This card will be retained until the respirators are returned. I. USING THE RESDIRATORS
- 1. Health Phycies will issue the proper respirator for the work to be performed.
NOTE Each respirator user.is emphatically advised that he (~) a. should immediately leave the area for relief from *
- respirator use in case of equipment malfunction, physical or psychological discomfort, or any other condition that might cause reduction in the protection
. afforded the user. .
* - M ANU AL SET - ;
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- b. Respiratory protective devices should never be worn when a satisfactory face seal cannot be obtained.
s
- c. Custom Comfo Aerosol - half face respirator will not be
,_ used for respiratory protection.
4
- 2. Full facepiece w/ type H Ultra Filter Cartridge. ,
Y, 2$,$kNIS
- a. Perform Steps I.6. For donning the facepiece.
I
;.f""'~ b. Remove the facepiece after use per subsection I.7.
- 3. Constant flow air line respirators (full facepiece).
- a. Inspect equipment as per Step N.1 and N.4.
- b. Bleed off the house service air line to remove any condensate which may have formed in the system prior tc connecting the portable filter and regulator to the service air line. .
I gs c. Connect the portable filter and regulator unit to a
, (,)(.
house service air line, using the air hose provided. Attention should be made to keep the unit out of the contaminated area; but if this is not possible, it should be wrapped in plastic. Operate the unit in the upright position only.
- d. Tag the service air outlet with a "To Be Operated by-H.P. only" Tag.
- e. Adjust the regulator for 35-40 psi. Bleed off the filter trap for moisture.
- f. Place the control valve on a belt or loop on the left side of the body.
- g. Put on the facepiece as in subsection I.6.
- h. Connect 25-300 ft. of MSA air hose from portable filter regulator unit to the control valve. Then connect facepiece breathing tube to the control valve.
- i. After leaving the airborne or work area, do not remove the facepiece until outer pair of gloves, coveralls and shoecovers are removed. (This may not be possible in all cases). -
O j. Disconnect breathing tube and air line hose from the control valve. Disconnect air line hose at outlet of
- filter regulator unit.
1
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- k. Remove facepiece as in subsection I.7.
- 1. Shut off air sQpply to filter-regulator unit and disconnect hose.
$2 NOTE j pogggg. , Do not perform this step until all persons are pfgf. - throug.h. using the filter-regulator unit. ,
axu_ .
- m. Place all equipment in designated place for sunveying and cleanup.
- n. The plant service air compressors are equipped'with a Control Room annunciated high temperature alarm. If the Control Room recieves a high temperature alarm, they will announce over the P.A. system that high temperature conditions exist in the Unit 1 and/or Unit 2 service air compressors. They will also announce that all personnel using in-line air respirators _are to remove their respirators and exit the work area '
(~'t following proper undressing procedures. The Control
' fj
+3 Room will also notify the Health Physics Foreman who
'~
will assure that all persons using air line resp,irators have removed their respirators and exited the work area.
- 4. Constant Flow - Air Line Respirator (Hood)
- a. Follow Steps I.3.b., c., d.
- b. Adjust the regulator pressure according to F.4.b.
- c. After hood is inflated, place headpiece over head seating lower edge of headpiece securely on shoulders.
- d. Place inner cape against body and smooth out folds and wrinkles. Tape inner bib together at sides.
~
- e. Fold inner cape at shoulders to e.liminate the excess material extending over shoulder.
- f. Put on outer protective clothing and smooth out folds and wrinkles of outer. cape against outer P.C.'s.
- g. Tape outer capes together at sides. Tighten belt over outer cape and connect air line to belt. Adjust hood assembly for minimum restriction of head movement. -
b
'"C ' Reset p.ressure regul'a tor as necessary to assure h.
. adequate air flow (See F.4.b.).
M ANUAL SET ,, j
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- 5. MSA Air Pack Model 401-pressure demand
- a. Check the pressure gauge in the cylinder valve to insure that the cylinder is full (2216 psi pressure).
If there is less pressure, the service life will be a reduced accordingly.
- b. Put on the apparatus using either of the following i methods:
DIf^[ - , (1) Open the lid of the case and extend the shoulder straps to their full length. Lean forwardi grasp the cylinder and backplate firmly, with both hands, between the cylinder clamp and thd waist belt. Lift the. apparatus straight up and over the head and rest it on your back. The shoulder straps will fall into place over the shoulders. Adjust straps before straightening up. Fasten waist belt snugly. Should further adjustment be necessary, lean forward and adjust straps. Use of chest strap is optional. r"s Extend narrow shoulder straps. Don the apparatus 4 *g (2)
. like a vest. Lean forward while the shoulder straps are being adjusted. Fasten waist be1~t securely and snap chest strap if desired.
- c. Open the cylinder valve handwheel fully (at least 3 turns) and close the By-Pass (red) handwheel on the Demand Regulator.
- d. Place palm of hand over the Pressure Demand Regulator outlet-firmly to block it leaktight. This is necessry as the pressure Demand Regulator is spring loaded and
,. air will flow automatically if the outlet is not blocked.
- e. Open the Main Line (yellow) handwheel fQlly and observe the pressure gauge on the Regulator. This gauge ~
indicates the pressure in the cylinder and shou'd read 2216 psig i 100 psig if fully charged. If there is less pressure in the cylinder the service life will be reduced accordingly. Turn off the cylinder valve and watch the pressure gauge on the regulator. There should be no drop in pressure if the equipment is leaktight. If there is noticeable deflection of the needle the equipment should be checked and the leak , ($ (> corrected before entering a toxic atmospher'e. Shut off Main-Line Valve.
- f. Put on respirator as per subsection I.6.
MANUAL SET ,,; .. , i i e.'. _ J _ _ - - . -' ~ ' '"*** ' ~~^
PRCOkOUpt P.O
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- g. Cennect mask hose to regulator. Open Main-Line Valve fully.
l h. Breathe normally as the apparatus au.tomatically ( satisfies any breathing requirement. I ! NOTE l t' 'Me , It is necessary to periodically check the pressure
. . . . , gauge on the Pressure Demand Regulator as it continually indicates the pressure in the cylinder.
When the needle reaches approximately 540 psi on the pressure gauge, the Audi-Larm Signal will begi,n ringing. When the bell starts ringing, or when the pressure reaches 540 psi, it is time to return to fresh air. NOTE During normal use the Oy-Pass (red) valve is closed and is used only if the Pressure Demand Regulator becomes
?% inoperative. It provides a continuous flow and should I
( l, y be opened and the By-Pass valve adjusted to provide the l flow desired. Leave hazardous area immediately since life of apparatus is greatly diminished when By-Pass valve is being used.
- i. After leaving the airborne area, do not remove the facepiece until outer pair of gloves is removed. If high contamination conditions exists in the work area, then two pair of rubber gloves should be worn to prevent spreading of contamination to the hands. All practical efforts should be made to keep the regulator tank and harness from becoming contaminated.
- j. Unlock the lever on the cylinder valve and close the.
valve. Do not use excessive force as the valve closes leaktight with little effort. .
- k. Release pressure in high pressure hose by breathing until air is exhausted.
NOTE Do NOT use Oy-Pass valve to exhaust air pressure.
- 1. Remove facepiece as in subsection I.7. -
( s M ANUAL SET , . _
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*. 4
- 6. Donning the facepiece
- a. Inspect the facepiece to be sure that all parts are in good condition and installed properly. Rubber parts should be pliable and not cracked. See section N for details.
- b. Pull out the facepiece headband straps so that the ends g ;.gggg,y are at the b.utkles and grip facepiece between the thumb and fingers. Insert chin well into the lower p' art of
+ - - -
the facepiece and pull the headbands back over t.he head. To obtain a firm and comfortable fit against the facepiece at all points, adjust headbands as f,ollows: (1) See that straps lie flat against head. (2) Tighten lower or neck straps. (3) Tighten the side straps (do not touch forehead or j front strap). (^3 , (4) Place both hands on headband pad and push in
%,f. .. ,
toward the neck. (5) Tighten forehead or front straps a few notth'es if necessary. (6) Check for proper seal using the field testing procedure in subsection J.2.
- 7. Removing the facepiece
- a. After using the respirator remove the outer pair of contaminated gloves. Bend your body forward at the waist until the chest is parallel to the floor. Then remove the facepiece by grasping the cartridge housing and lifting outward. (For airline respirators and SCDA's, grasp breathing tube connection at the ..
facepiece). CAUTION Care should be taken when removing respirator to insure that open areas of the face do not become ~ contaminated from contact with the equipment. AVOID UNNECESSARY JERKY MOTIONS WITH THE FACEPIECE AS ANY CONTAMINATION MAY DE SHAKEN OFF AND ON TO YOU. If high contamination
/~}
L' conditions exist in the work area, then two pair of rubber gloves should be worn to prevent the possible spread of contamination. *
?
r MANUAL SET _,__
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~ . . PAOCtOuHE NO E. l. HATCH NUCLEAR PLANT HNP-80lO cee ...tle it Page aev s w w y .n 16 b Georgia Power dA ~~
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- b. Place facepiece along with all associated respiratory equipment in a deisgnated location for survey and cleanup. DO NOT place in contaminated clothing storage drums.
WARNING i l DWReg.. Respiratory equipment is a personnel safety device and
"'. should not.be mistreated (i.e. thrown, kicked, dropped, mutilated). ' Personnel found abusing this equip, ment
~~'~"
will receive disciplinary action. .,
- c. Survey yourself for contamination, making a very thorough survey of the face and head. If cont' amination is found contact Health Physics immediately.
J. FITTING AND TESTING J
- 1. Initial Fitting and Testing f a. Each person requiring the use of a respirator will be
(~} . individually fittad for the particular facepiece prior S y. Y to being allowed use of the respirator equipment. No person with facial hair interfering with the respirator ' seal area will be fitted and tested. b.- Any facial abnormalities will be documented on Form 2 and will assist in identifying those persons who might have more difficulty.in obtaining a' good seal with a respirator.
- c. A qualitative or quantitative test will be performed for each type of facepiece. Quantitative test results, (if employed) will be documented on the strip chart
- - paper and filed with the Form a in the individuals dosimetry file. See HNP-8033. The qualitative test' will be performed as follows:
~
(1) The person dans the respirator with an organ'ic cartridge attached. (2) The person checks the facepiece seal using the negative pressure test as described in J.2.b. (3) The instructor will test the fit during normal breathing by waving a cotton or stencil brush f- filled with isoamyl acetate gently near.the (j - periphery of the facepiece. Smoke tubes, when availabic, may also be used. If odor is detected,
- the wearer must re-adjust the facepiece and the*
test redone. -
.)
1 MANUAL SET ., ...y
- % . s. . . . _, _
x . - PM1DVMt PeO HNP-8010 dee +t.tle Page E. l. HATCH NUCLEAR PLANT aimsm uo p ;c 16 V Georgia Power d, ~ ~ ~o see .. istle Page o 15 of 36 NOTE When practical; a test chamber will be used in lieu of the cotton or stencil brush. Evaporate about 173 milliliters of isoamyl acetate for each 1000 cubic feet of room volume. (Do not use heat for evaporation). l 4gme .., (4) The instructor may then have the wearer perform
~. the following movements: ,
~ " - - - *
(a) deep breathing ., (b) moving head from side to side (slowly) (c) moving head up and down (slowly) (d) frown
. (e) talking (e.g., speaking a short passage aloud)
(f) normal breathing.
~~'
'[ (5) The instructor will then re-check the seal with isoamyl acetate or smoke tube.
(6) If the tests are acceptable (no leakage) it will be documented on Form 2.
- 2. Field Testing
- a. Where practical, respirators will be tested in the field using either amyl acetate or irritant smoke.
- b. Where it is impractical, a negative pressure test will
- be performed as follows:
(1) Close off the inlet opening of the. canister or breathing tube by covering it with the palw of the ' hand (2) Gently inhale so that facepiece collapses slightly. (3) Hold breath for 10 seconds. (4) If facepiece remains in slightly collapsed condition and no inward leakage of air is detected, the tightness of the respirator is
,-)
i t. satisfactory. (5) If unsatisf actory do no t use the respirator and* contact Health Physics. MANUAL SET .j .
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- . *: PwoCEDURE NQ E. I. HATCH NUCLEAR PLANT HNP-EOlO Sea title Page aevmm ao C
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See ..itle Page Geo ia Power d ~ ~o 16 of 36 K. PSDICAL REGUIREMENT All personnel who wear re'spirators will be evaluated by competent medical personnel prior to an assignment requiring such use. The evaluation will determine if the individual is physically able to perform the work and use the respiratory protective equipment. A physician will determine what health and physical conditions are l3ggayyn pertinent. The medical status of each respirator user will be
. . revsewed annually. ,
L. BIOA99AV9 AND SURVEYS .,
- 1. Air sampling and contamination surveys ,
A comprenensive air sampling and contamination survey program is in effect to identify radioactive hazards to evaluate individual exposures, and to permit proper selection of respiratory protective equipment. Surveys are performed on a routine and special basis per the use of procedures HNP-8013, 8012, 8008, 8005, 8050 and applicable
- instrument operating procedures. High-efficiency (greater
/'i than 99%) filter media are used to measure airborne kq //
particulate concentrations. Activated charcoal is used to determine radio-iodine concentrations.
- 2. Bioassays NOTE r
Refer to HNP-8021 and 8009
- a. Whole body counting -
(1) It is the intent to obtain a whole body count or
- - urinalysis on each G.P.C. employee who may have been exposed to airborne radioactivity at least once each year.
(2) Whole body counts will also be made where suspect internal contamination has occurred.
- b. Urinalysis (1) A fission product and tritium analysi's will be performed on selected personnel who may have been exposed to airborne radioactivity.
r~s (2) The above analysis will also be made, when deemed t'~'j necessary, where suspect internal contamination has occurred.
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17 of 36 s_ c. Nasal, throat swabs or washings and breath samples will be performed as necessary on suspect inhalation cases to serve as a qualitative exposure index for , radionuclides. d. Follow up sampling (Whole body, urinalysis, nasal throat swabs, breath samples, etc.) will be performed
- l 9?4Qm,r and will be frequent enough to evaluate the uptake of radionuclides after an incident. The sample co,11ection will be appropriately timed to permit accurate'
; ,, _ evaluation of the total intake and the resultant, dose.
NOTE e It is noted that there are extenuating circumstances which may prevent whole body counting of all personnel affected by this procedure. Such situations as persons leaving the plant site without proper notification to the management, whcle body counting equipment malfunction at critical counting times and scheduling
' impossibilities will prevent a 100% whole body counting program. The frequency of these events, should not
[~)[, diminish the overall effectiveness of the bioassay
^% program however.
M. EESPIRABLE AIR REGUIREMENT
- 1. All~ breathing air supplied by air compressors and bottled air will meet the minimum requirements of Grade D air as prescribed by the Compressed Gas Association or better. If
' high temperature alarm is received for service air compressors, then air quality can no longer be guaranteed due to possible CD concentrations. See Section I.3.n. for details. ~-
- 2. Samples of air from air supply sources will be taken quarterly and mailed to an outside laboratory .for testing.
- 3. Oxygen and breathing air are not to be used in the samP apparatus.
4. Proper fittings will be used with supplied air equipment. 5. Oxygen shall never be used with air line respirators.
- 6. All air cylinders used in the MSA 401 units will have the
_. words "Dreathing Air" on the cylinder. . u t
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. E.1. HATCH NUCLEAR PLANT HNP-80lO dea .:tle Page anum uu et 16 U .
Georgia Power d, - 29 ::le Page O l 18 of 3G N. IUjP_gCTION AND__ MAINTENANCE
.; raspient rs shall be' inspected routinely before and cif ter eacn use. A respirator that is not routinely used but it kept ready for emergency use shall be inspected after each use and at least monthly to insure that it is in satisfactory working condition. All routinely used respirators shall be inspected j y pggs, before and after use and at least monthly and shall have an
'~. inspection sticker. , ,
An inspection sticker shall be attached to the outside and inside of each emergency respirator container and a record of inspection Hept on Form 3 (Data Package 1), Respirator Monthly Inspection Peport. Any respirator not meeting inspection acceptanc'e shall be repaired or replaced. Respirators will be repaired only by personnel designatec by a laboratory supervisor.
- 1. Facepiece and breathing tube (SCBA & Constant Air Flow)
- a. Inspect the facepiece and breathing tube for signs of mechanical damage, deterioration, cracking or rupture.
', Tears occur most frequently about strap attachments, jf outlet valves and hose. Discard equipment damaged in this manner.
- b. Check the protective tape and metal band bindings for
. deterioration. Replace as necessary.
- c. Inspect the tab assemblies on the facepiece used for attaching head straps. All buckles should be present and in good operating condition.
- d. Check the lens for looseness and damage. Discolored or damaged lens should be replaced.
- e. Inspect the exhaust valve for proper sealing of the rubber diaphragm. Replace as necessary..
- f. Check breathing tube connections for deteriorat oh and damage and tightness. Repair or replace as necessary.
- 2. Ultra Filter Respirator-Full facepiece. In addition to Step 1, just prior to use:
- a. Check that the type of cartridge is correct and that the cartridge is couplec to the respirator securely.
- b. Examine the cartridge for damage and check that the inlet seal has not been removed.
- MANUAL SET _ _ .
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- 3. Pressure Demand Apparatus (Air Pack)
In addstion to Step 1, perform the following:
- a. Check for proper operation of cylinder valve assembly.
- b. Check main pressure gauge for proper operation and that j paggy. - air cylinder is full (2216 1 100 psig). If cylinder
- f. , pressure is less than 2116 psig, remove air pack ,from
- m. service and recharge.
. . ~ .
- c. Inspect condition of hose connection and hose to cylinder valve assembly. If hose is cracked replace it.
- d. Check operation of Main Line (yellow) valve by operating it.
- e. Check operation of low pressure alarm monthly by
,, closing cylinder valve and cracking the Main Line (yellow) valve open. This should let the pressure decay off so the alarm should sound at about 540 psi.
- L,XJ "'
- f. Check operation of regulator bypass (red) valve by operating it.
- g. Inspect all belts for signs of fraying. Inspect,around side strap buckles.
- 4. Constant Flow Air Line Respirator-In addition to Step 1 perform the following:
1
- a. Check the operation of all couplings by mating them to working couplings.
. b. Check all hoses for cracks and leaks.
- c. Connect the portable air filter regulator tp an' air supply and check operation of the gauge, filter, regulator and inlet and outlet. couplings. Check the filter trap for moisture. Pressure gauge should read 35-40 psig.
NOTE Filter media for filters will be changed after each refueling outage for the units used during the. outage. ( )- 5. MGA 401'SCGA. Inspection Checklist
. a. Refer to the checklist while performing the monthly
- inspection. Comply with each-item listed. See Form 1 (Figure 1).-
-) . mo&% .i . MAHAL SET _,_j
HNP-8010 cae Tii.,e Page E. I. HATCH NUCLEAR PLANT % , %, w C 3, w , , . g, , Georgia Power.A ~- ao 33 l
- 6. S.C.B.A. Dreathing Air Tanks (Model 401 Air Pack). l t
- e. Ea:n steel tank will be hydrostatically tested to 3360 ?
pstg. on a 5 year frequency. !
- b. Each aluminum and fiberglass tank will be hydrostatically tested to 3360 psig on a 3 year w, , frequency.
' Form 4 (Data' Package 2) will be used as a master 1ist
- c. 8
- for determining when the testing will be performe.d.
- d. Testing documents will be filed in the Document Room.
- 7. Semi-Annual MSA 401 Regulator Testing.
- a. Each regulator will be tested every six months using the MSA Portable Regulator Tester.
- b. Once the regulacor passes all the tests as described in the MSA Portable Regulator Tester Manual an inspection
(~T sticker will be placed on the regulator bearing the 6;g[ date it was tested. .
- c. In the remarks section of the monthly respirator -
inspection sheet FORM 3 (Data Package 1) for the
.particular MSA 401 that is being tested, note it was tested and that it passed or failed its test.
B. Regulator testing for Manifold-Filter System (continuous flow respirator)
- a. Regulators will be tested annually using a calibrated 150 psig test gauge or equivalent. Test gauge can be
- obtained from the Test Shop.
- b. The regulator gauge must read plus or minus 15% of the test gauge before it is acceptable for use. ,
- c. Regulators acceptable for use will have an inspeciton sticker placed on the regulator bearing the date it was tested.
NOTE Only personnel trained and certified by MSA will be .
,4 approved to repair MSA 401 Regulators.
b, t
? llAMllAL SET M
+ . . _ _., _ _ . _
... _ __ .,_ _ _ _ _~;
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21 of 36 O. CLEANING AND SANITIZING
- 1. Menitor entire equipment as soon as possible after use to ,
cetermine level of contamination. Pay particular attention to filters, exhaust valve housing and straps. s NOTE f.*A '
~
Ik 7" ~ If necessary, facepieces may be re-issued to the same person on the'same day if the following limits'are not
.121.,__ exceeded on any surface of the facepiece. Alpha surveys are not required unless alpha contamination is suspected.
9
- a. Fixed contamination:
Beta-gamma-0.2 millirad per hour above background at contact.
.. Alpha-50 d/m/ probe area
- b. Smearable contamination:
'M No detectable. removable activity using a standard swipe technique (disc smear over 100 cm A).
- 2. Facemask and breathing tube.
The facepiece and breathing tube assembly of respirators must be cleaned, sanitized, dried, surveyed and inspected after each day's use as follows:
- a. Add one package of powdered MSA Cleaner-Sanitizer per gallon of warm water (about 120 degrees F.).
- b. Immerse equipment in the solution and scrub gently with a soft brush until clean. Take care to, clean the exhalation valve in the facepiece and all other parts that exhaled air contacts. A dishwasher may be used in lieu of hand cleaning.
. c. Rinse in plain warm water (about 120 degrees F.) and then air dry. .
NOTE (. Do not fold head straps in front of face piece for - storage. .
- M ANUAL SET _,_____!
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- d. Survey the equipment for radioactive contaminetion.
The facepiece and breathing tube (s) must have no datectable removable activity using a standard smear survey technique. Fixed contamination shall not exceed 0.2 millirad / hour at contact beta-gamma and 50 dpm/ probe area alpha. Alpha surveys are not required unless alpha contamination is suspected. d '*40N e.
~ Place routinely used facepieces after inspectiog in a clean plasti ~c'
_ bag and store in their assigned storage _, z locations. (During periods of high usage it will,be acceptable to delete the clean plastic bag storage requirement). Place respirators assigned for emergency use only, after inspecting, in the compartments' built for them and return them to their storage locations. NOTE Respirators should be packed or stored so that the
~
facepiece and exhalation valve will rest in a normal position and function will not be impaired by the f- elastomer setting in an abnormal pukition. (g)> J' 3. Other equipment (harness, regulator, air cylinder, hose).
- a. Remove the used air cylinder from the Pressure Demand
. Apparatus (Air Pack) and decontaminate by wiping with a wet pad of Cleaner-Sanitizer solution and then with a dry pad.
- b. Wipe down harness, breathing bags, regulator and hose with wet pads as necessary to reduce the transferable contamination to le,ss than 1000 dpm/100 cm#-beta-ganma and 100 dpm/100 cm- alpha. Alpha surveys are not required unless alpha contamination is suspected.
- c. Survey equipment after drying to verify captamination levels do not exceed those in Step O.3.b. .,
- d. Attach a fully charged cylinder to the harness and regulator assembly of the Pressure Demand Apparatus (Air Pack).
- e. Store equipment in their designated areas.
P. REVIEWS AND RECORDS ("N (Z
- 1. A laboratory foreman will routinely review respiratory practices and procedures to assess the program effectiveness. .
e
. ~ . . . - -
MANUAL SET _, , __M
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- 2. Timely assesements of a particular individual's intake will be made'if and when required and adequate records will be j maintained for summary review and evaluation.
1 I 3. If an individual's intake exceeds 40 MPC hrs. in seven consecutive days an evaluation will be made and action taken j to assure against recurrence. Records of.the occurrence, evaluations and actions taken will be kept in a clear and g g g' ' '" . .' ", readily identifiable form suitable for summary review and evaluation. Radiation Occurrance Forms (HNP-SOO5),' 1 Personnel Contamination Report (HNP-8009), Radiation Work Permits (HNP-8008) in addition to survey records, bioassay results, etc. maHe up most of these recoros. , f-r*. f., I I ,i' - e 6 m . e l! 7 M ANU AL SET ;
^
- n a ~ ' =- ._
4
"" . "HOGLDuHt NO
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=ee r t:le Page Ueoria 24 of 36 APPENDIX __I__
---------- a------------------------------------------------..---------
SECTICN TITLE PAGE NO. A Purpose 1 B Safety 1 C References 1 g qp~g..
. D Management Policy ,
1
~ ~ - - - -
E Regulatory Requirements , 2 F Description of Respirators , 2 G Selection of Respirators for Use 5 H Control Issuance, Proper use, and Return of Respiratory Equipment 7 I Using the Respirators' 9 J Fitting and Testing 15 (~N),, ----------.. --_-----------------------_--------------------..----------
.w %.
~
K Medical Requirement 17 L Bioassays and Surveys 17 M Respirable Air Requirement 18 N Inspection and Maintenance 19 C Cleaning and Sanitizing 22 P Reviews and Records 23 Tables:
- 1. Airborne concentration limits for respirators , 26 Forms:
_ _ 1. Insgections of 401 SCBA 29
- 2. Respiratory Protection Training Form 2A 28 Raspiratory Protection Training Form 29 29
- 3. Respirator Monthly Inspection Report 30
- 4. MSA Respirator (Model 401) SCBA g 32
(_) ~ (Tank Hydrostatic Test Master List)
. 5. MPC-HR tracking (Yearly) 34'
- 6. Respiratory Issuance 36 I m---------. .-------------m----mm-----------m----------------..---------e 9 i
MANUAL SET _~ - ~s n .x ; _ , -- -
e r4 ,. PROCtDuett NO HNP-8010
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~~~
TABLE 1 AIP9_ORNE CONCENIRATION LIMITS FOR RESPIRATORS i AIR PURIFYING RESPIRATORS
- AIRBORNE CONCENTRATION Full facepiece w/ type H Particulate activity less than j jgggg.g Ultra filter cartridge 40 times MPC n '
_ ,,.i ? ATMOSPHERE SUPPLYING RESP.*'
- 1. Air line respirators Full facepiece-constant flow - Particulate, gas and vapor activity less than 1600 times MPC Hood-constant flow - Particulate, gas and vapor activity less than 1600 times MPC when pressure is maintained
- at manufacturer's maximum rate (See F.4.)
) ,
Suit - constant flow - No credit allowed unless suit
~ ' ' '
is MSHA/N10SH approved. See a laboratory supervisor -
- Air line and air purifying respirators can only be used in a nospheres not immediately hazardous to life or health.
- 2. Self-Contained Dreathing Apparatus (SCOA)
- MSA Air Pack Model 401 Pressure - demand Particulates, gas and vapor activity less than 10,000 times MPC. However, may be used in emergency conditions in unknown concentrations of airborne acti-vity. Must-also consider external radiation hazards and other limi-tations (skin absorption, etc.).
e 4 .
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a 1 . MANUAL SET ,, ' n d. = .a _ e . _- .; . , _ __
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- E. I. HATCH NUCLEAR PLANT HNP-8010 s e r. Title Page ec~ ~o
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*~r FIGURE _1 FORM 1 INSPECTION OF 401 SCGA FORM FORM 1 INSPECTION CF 401 SCBA g 5 -- - - 1. Items of inspection on f acepiece and breathing tube. .
- a. Insure f acepiece is a 401 mask with spring loaded eshaust valve. t
- b. Mechanical damage.
- c. Cracwang or ruptures.
- d. Tears around strap attachments, outlet valve and hoses.
- e. Detersoratson metal band osndings.
- f. Stuck ethaust valve.
- g. Damaged ennaust valve.
- h. Detersoratson, damage, taghtness of breathing tube.
- i. Mtsstng clips on face lens.
. j.
Cracking or detertoratson of gaskets between facepiece, hose, regulator and hose.
- k. Insure all straps on facepiece are adjusted fLily out.
, (h .
'4 ,- ;$ 2. Items of inspection on Pressure Demand Apparatus (Air Pack).
- a. Insure cylinder is full. *
- b. Inspect cylinder for physical damage.
- c. Damage and proper operatson of cylinder valve assembly.
- d. Damage and proper operation of low pressure alarm. (540 PSI)
- e. Damage to connections on hose from cylinder to regulator.
- f. Damage and proper operation of pressure gauge on tank.
- g. Cracks in hose frcm regulator to cylinder.
- h. Operation of main line (Yellow).
s
- i. Operation of bypass line (Red). i J. Check air tightness by pressure drop (see section I.S.d.&
e.).
- k. Linusual sounds in the regulator (whistling, chattering, clicksng, or rattling).
- 1. Damage and proper operation of the pressure gauge on the regulator.
- m. Physical or mechanical damage to the regulator. i
- n. Fraying of belts and straps on harness.
- o. Insure all belts and straps are adjusted fully out.
- p. Insure all buckles ws11 work properly. '
- q. Insure cylinder is in the harress correct. .
O W -8010 R16 i' = i q& MANilAL SET _ -j
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-4 FORM 2A
~1 d RESPIRATORY PROTECTION TRAINING _ FORM l i i
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F RE?pIRATORY Pa0TECTICN TRAININC 1 ' g - INITIAL TRAINit4 DATE: l tWE (last, +1rst, maddle anattal) GPC DEPT. BADGE # S.S. # CR CO. ' I 1 have receaved snstructtons in respiratory protection, and I have been advised that 1 may leave an area when using a respirator at any time f or relsef ' rom respirator use in the event of equipme it malfunc.
' tson, phystcal or psychological distress, procedural or commun catton failure, s Snificant deterioration of operatsng condations, or any ,
. Other condition that asght requare such relief.
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TRAltEE SIGNATURE 2 Fit Test Results: Acceptable Unacceptable Written Test Results: Acceptable Unat:eptable The above individual has been trained to use the f ollowing
,. respiratory systems:
- 1. C MSA Ultra Filter .
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- 2. C Constant Flow i 3.
C PGA 401 Air Pack m COrPLETED BY: DATE:
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! F CD PLETED BY. DATE: *
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DOCtPENT PC: _ N-8010-1 s EERIAL NO: _Rt6-I PFL, ?C: N/A RTYPE: _ C15.1 A , XREF: N/A TOTAL SWETS: 2
)' I' FREQUENCY:. Monthly CCretITED BY:
DATE COMPLETED: 1 I HAW REV! EKED THIS DATA PACKAGE FOR COMPLETENESS 1 i MC AGAltGT ACCEPTANCE CRITERIA IN ACCORDArCE WITH Hre-930. ACCEPTABLE t.NACCEPTABLE REVIEED BY: ' l
.DATE REVIEWED:
REP %RKS: _- __ - . . . . . j Page 1 of 2 M -8010 R16 , . FIGURE 3 Page 1 of 2
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DOCt. PENT NO: M -9010-2 I
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SERIN. NO: Rl6-t ppt. NO: N/A i RTYPE: C15.14 ( XREF: N/A ; i
, TOTAL SKETS: 2 O}g t FREQUENCY: Armual l y D* .
C0rPLETED.BY: DATE COPPLETED: , I HAW REVIEWED THIS DATA PACKAGE FOR CCPJETDESS NO ACAlfGT ACCEPTNCE CRITERIA IN ACCORDANCE WITH HNP-830. ACCEPTABLE UNACCEPTABLE I REVIEWED BY: DATE REVIEWED: !
~
REMARKS:
........- - _ _.-------- - ....-- .===-
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- WP-8010 R16
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CEI?OER DATE DATE SENT DATE
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PROCEDURE DATA PACMACE l { " M1"*
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RTYPE: C15.16 XREF: N/A TOTAL SEETS: a FREQWNCY: As Required kd.i.. CCrPLETED BY: DATE CorPLETED: I HAW REVIEWD THIS DATA PACKAGE FOR COMPLETENESS MO ACAltGT ACCEPTAPCE CRITERIA IN ACCCRDAt<E WITH HP-830. i ACCDTACLE ! LNACCEPTABLE i REVIEED BY:_
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XREF: N/A TOTAL EHEETS:_ A I FREQUENCY: As Recuired '
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CorPLETED BY: DATE CorPLETED: I HAVE REVIEWED TMIS DATA PACKACE FOR COMPLETEPESS MO AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH Hre-830. t i ACCEPTABE LNACCEPTMILE REVIEWED BY: f DATE REVIEWED:
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FO1 ARKS: Page 1 of C .
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Geiger Counter Model E-1EO_.Op_eration and Calibration PROCEDURE TITLE HNP-8120 -- PROCEDURE NUMBER Lab RESPONSIBLE SECTION
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" ~ " ^ SAFETY RELATED ( X) NON-SAFETY RELATED ( )'
APPROVED APPROVED P E/. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER p.---. .--------
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4 Pages 1-3 and 5-6 . 2..,w. F AL;
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.. REVISION CHANCES McCE O.7.CPERATION OR INTENT A3 CESCRIGED IN FSAR: .
. . . ( ) Yes . ( No t- .
'.- CHANGE INVOLVES: * .
' i %** * ( ) An unreviewed Se 7ety Guestion (
) Tech. Specs. ( ) Neither
- . u '.- (See back for S fety Evaluation if required). I
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Safety Related ( ,
) Non-Safety Related' ( ) - Y Safety /Non-safety Status Change ( ) Yes ( No 8 e.
. . Attach marked up copy of procedure to this f,orm. -
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REASON FOR REGLEST ~ , 1 . .
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The revisien of _-------------.t.his oroced.u.red.o..es not consti tute an . -- - -------- unreviewe d safe . - ty ------ - [
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.. -__ues ti_ca as__exclain_ed ---- ----- below.- -------_- _ -_-----__-
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1.- ---Th e prob a.b.il- -- -- i ty o f occurr.e. =s a.n.d. t;.h_e g.on.S eoue_n_ca.s_ o_f a n_ _ a_c_c_i d_e_n t____--- or calfunction .o.f equipment iccort_ ant to sa_fetJ.are not increased ab o.ve_t_h.on_a.p. glyd2.!L _in__tM_F.3N_dp_e_.tq_t;bndgg gS_he caus g __ the revision d_oes n.o.t chance _ the our.2ose or oerformanc_e_o_f the
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s i J than analyzed in the FSAo. does not result fr.om this chano_e_,because E _ , the system resconds and is c:erated as before the chanoe. ____
. . '. 3. The maroin of safe.t.y as defined in the Technical Soecifications . _ - - - - - - - -
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s"- is not reduced due to this r_evision because the revision does not g i
- - - - . chance any limited safety system settinos which wo_uld allow a -
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- ~ . saf.et'v l,.imit to be exceeded or to alloir a limitino condition for operations to__ be exceeded as stated in' Techn_ical_Soecification_s.
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- E. l. HATCH NUCLEAR PLANT HNP-8120 nee ..t1 ,e Page
_ a v. w I . m.e 1,,e. P.n e Geof3iaPower A ~~ 1 of 6 GEIGER COUNTER MODEL E-120 OPERATION AND CALIBRATION i A. P_L_SP_O_S_E_ To' provide instructions for operation and calibration of the mocel E-120 portable survey meter with a Geiger-Muller type detector, normally used with a HP-250 hand probe. bNN B. SAFETY - 8 i -.._-
;- -- Observe radiation protection procedures. ,
C. di E9EHCES I
- 1. Geiger Counter Model E-120 Technical Manual
- 2. Mini-Pulser Procedure ,HNP-8116 D. TEST EOUIPMENT
- 1. Mint-Pulser with coaxial cable.
.-(N, , 2. Gamina Check Sc,urce. (Portal Monitor Check Source)
E. D fCRIPTION OF INSTRUMENT
- 1. The E-120 is a portable battery operated instrument used for the detection and measurement of beta or gamma radiation.
It has a geiger tube detector and the count rate is read out-on a linear scale. -s
- 2. The full range of the instrument is 50 mR/hr or 70 K CPM.
- 3. The battery pack uses two standard D size batteries of any
. type commercially available.
F. DESCPIPTION OF CONTROLS
- 1. External controls
- a. Switch - Five position switch turns instrument OFF, B A T T ,' XO.1, X1, and X10 scales.
1 . MANUAL SET 4 s a a .. . - .. , .
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- 3. Response - Controls response time of meter to most desirable compromise between speed and fluctuation for the particular range.
- c. Reset - Discharges integrating capacitor, bringing meter to zero rapidly.
g g ,gg g d. Phone - Pulse output for use with earphone, speaker or
..m -
ex ternal s ca.l.er. ,
, .7 T ~ J- - 2. Internal controls Cclibration controls - one control for each range which incividually calibrates that range to agree with the' Mini-pulser input.
G. CP$ RATION _DF INSTRUMENT
- 1. To start instrument turn the switch to the BATT position.
The me ter should indicate within the BATT OK area, if not I tag the instrument out with a TO SHOP tag. n(; 2. Place.a check source in a repeatable position adjacent to the detector and move the switch to the X10 scale. Compare reading on the meter to the correct value of the , source. Using an 8 microcurie CS 137 check source reading should be between 20,000 & 40,000 cpm. If instrument does not read within above values, tag it out with a TO SHOP tag.
- 3. Push the RESET button and the reading should drop to zero rapidly, then climb back to the source reading in step 2 when the REEET is released. The RESPONSE may be adjusted to get the most desirable comprcmise between speed of response and meter fluctuation.
- 4. Interpretation of readings:
NOTE All E-120's are calibrated to read in C.P.M. unless otherwise stated on the instrument case.
- a. Th'e meter reading must be multiplied by the scale multiplier to obtain the proper reading. The fluctuation of the meter is normal and i s caused by the random nature of radioactive decay.
~
- b. Th'e E-120, used with an HP-210 or HP-260 probe, has been calibrated using a mini pulser (pulse generator) and should be used principally for contamination survey work. They should NOT be used to measure dose rates.
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. 'e-eve the instrument frem the case.
- 2. Turn the control switch to BATT position and check battery condition. Replace if necessary.
4 ,g. g y3, 3. Connect the Mini-pulser into the probe connector.
'[ 4. Set' Mini pulser for negative pulses at O.25 volt ampiitude.
- 5. Set the Mini pulser to 400 cpm, 4,000 cpm, and 40,00d' cpm successively and check and record readings on Instrument Calierstion Data Sheet (Figure 1) in the As Found c61umn.
- 5. If readings are within i 5% of full scale, turn instrument C.:F , remove Mini-pulser cable, place instrument in case, reconnect cetector and cable, and proceed to step H.12.
NOTE i 5% of full scale
,fl_ -------------------
X O.1 scale 35 cpm X1 scale 350 cpm X 10 scale 3500 cpm
- 7. If reading are not within 1 5% proceed to Step H.8.
- 8. Set the Mini pulser to 400 cpm and adjust the XO.1 control for 400 cpm on the meter. .
- 9. Set the Mini pulser to 4,000 cpm and adjust the X1 control for 4,000 cpm on the meter.
~
- 10. Set the Mini-pulser to 40,000 cpm and adjust the X10 control for 40,000 cpm on the meter.
- 11. Proceed to step H.5 but record readings in the As Leff*
column of Figure 1 if readings are now acceptable. If instrument cannot be calibrated, initiate repairs and repeat Section H.
- 12. Place the portal moni' tor check source on contact with the detector, reading should be about 20,000 cpm._ Record results in the As Found column and, if within i 20% of actual count rate, record also in the As Left column. Count
( . rate of the portal monitor check source is about 20,000 cpm contact with G.M. detector. i - s M ANUAL SET 4 a ~ 'Lu . . . . . . . . - . . :-- - ^ ~~ 7 - - a
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PRCOLDURE NO E. I. HATCH NUCLEAR PLANT HNP-8120 3 ,71,1,g,9, ,..-~~0 g 4
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,, with the instrument on X.1 scale.
- 13. If results in H.12 are not within the limits specified, replace GM detector and repeat.
- ~, --
I NZ
- 14. If the instrument, checks out properly, complete Instrument Calibration Data Sheet, replace calibration sticker,with a
. - - - new one bearing the test date and when'the instrument is due for its next routine semi annual calibration.
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NP-8120 g, 3 g ,g39, E l. HATCH NUCLEAR PLANT atvwore m) { b,...,g,9
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,,. CCMPLETED BY:
DATE COTLETED: .-
- 1 HAVE REVIE%ED THIS DATA PACHAGE FOR CorfLETDESS A*o ACAltST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HP-830.
ACCEPTABLE UNACCEPTABLE . 1 i REVIEWED BY: DATE REVIEMD: i REPARMS: 3
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. GEORGIA POWER COMPANY H ATr. u " '.'..' F.A A. PLn^NT
(. 9P.o_rGDUR.E Victoneen G-M Area Monitor Model 856-20 PROCEDURE TITLE HNP-8127 PROCEDURE NUM9ER Lab _ y 8p, m.o. m RESPONSIBLE SECTION
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SAFETY RELATED ( X) NON-SAFETY RELATED ( ) . 6
. . _ _ _ _ _ . ___________________ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..____ __________m_______.
APPROVED APPROVED P.EV . DEECRIPTION DEPT. PLANT DATE HEAD MANAGER' g 2 Pages 16.4 w - __r y 3_ v.g ( . _ _ - - -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._____ ___ ______+ ______.
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,. .. REVISICN CP.?-?dE3 .v.OCE C.' .CPERATICM OR INTENT AS DEGCRIDEO IN FSAR:
( >() No ( ) Yes .
' ' P. . ,. ..*W." CHANGE INVOLVES: * *
-( ) An unreviewed Safety d'ueition (- ) Tech. Specs. ()() Neither (Sen back for Safety Evaluation if required). ..
SafMy Re[sted (I) Non-Safety Related ( ) i i
, Safety,'Non-safety Status Change ( ) Yes h No A :a:n markt:0 up copy of procedura to tr.is form. -
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questien as exclained belcu. -- -- -_-- ----- a-- --
- 1. The orobability of occurranGA._and a the.cQ.n.Mcuences
- ------- of'an accident ---- ------
or calfunction of eguipment i,mportant to safet.y are not increased -- ab,pyg t.hpg_a.nalud 10..thg_ESjB_d.u2 10. tbSS.2..sbADIAS_he.CAUSe._-- -- 1 4- the revision does not chance the ournose or oerformance of the -
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- 2. Th'e cossibility of an accident or malfunction' of a different tvoe i
-----_n tha a_nalyzed - - - - -_- in the FSAP. does_not result from _this chance because -----_ - - _ . -- --
the system rescond_s and is operated as before the chan.ce.
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--=The rarcin of safety as defined in the Technical Soecifications
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- 3. .
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. E. I. HATCH NUCLEAR PLANT HNP-9127 399 ~.719 PaQ9 atv4vN NO
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2 ( g99 .,.i- M Pace Georgia Power A ~ ~o VICTOREEN G-M AREA MONITOR MODEL 856-20 A. PURPO9E To establish a standard technique for the operation and calioration of the Victoreen G-M area monitoring system model j g y_ usG-20.
.%.c .. B. SAFETY 05seeve raoiation protection procedures.
C. M~;gRELC5 vi:toreen G-M area monitoring system model 856-20 Instruction Manua1. } O. QE9CRIPTION OF INSTRUMENT I
- 1. The Victoreen G-M area monitor, model 856-20, consists of a
(. Wall mounted Geiger Muller detector and readout module. Accuracy is within i 20% of reading. Type of radiation detected is Gamma. Energy dependence is i 15% from 100 KEV to 2.5 MEV. The instrument power can be 120 VAC or 230 VAC or 18 VOC. NOTE The Victoreen G-M monitor has been modified witn an audible alarm as well as with its visual alarm. The audible alarm will come on when the alarm setpoint is reached. Tc reset the audible alarm as well as the visual press the ALARM RESET button.
- 2. The readout consist of a logarithmic five deca.de meter
(.1mR/hr to 10 R/hr). ,
- 3. The alarm system consists of a front panel red push button high alarm and a green fail safe alarm. An internal check source is activated on front panel to check meter operation and alarm if setpoint is lower than source' dose rate.
, v 3
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- 1. HATCH NUCLEAR PLANT HNP-8127 tmivou 3 e .:. :-le Mace 2ee ;
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- 1. -xternal Controls.
l
- a. Function Selector Switch. f This rotary switch turns the instrument."on and off" 1 36ws.o selects the operating conditions and high alarm set !
T. point (indicat.ed by meter deflection). , r 1.w.
- b. .' Green Push-Button Light. ,
Green pusn custon is a fail / safe indicator for power
- supply to the instrument or detector. Depression of this button activatee insturments internal check source.
i I
- c. Red Push-Button Light.
Red' push button light indicates high alarm and audible.
- c. Setpoint is fixed by internal controls. Depression of this button will reset alarm.
/
*pe, g 2. Internal Controls. ,
- n. Computer output calibration potentiometer. R-41 is l used to calibrate the computer output to the i specificied accuracy. I l
- b. Alarm setpoint potentiometer. R-37 allows high alarm set point to be set..
I
- c. Alarm meter calibration, R-53 allows calibration of alarm circuit.
- d. Alarm calibration 10-end R-54 allows low alarm setpoint to be set.
- e. Middle range calibration potentiometer R21' adjustment '
for middle range approximately 1R/hr.
- f. Low range calibration potentiometer R12 adjustment for low range approximately 10 mR/hr. {
- g. High range calibration potentiometer C23 adjustment for high range approximately 10 R/hr.
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_. E. l. HATCH NUCLEAR PLANT HNP-9127 y
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.. Functs:n Gelector S4 itch.
j i' To turn the system "ON" turn the selector switch from OFF to OJER. ggg. 2. Operate Position.
.s =. ..
This position selects the full five-decade ranges wfaich is 1 _, Z _ i- read directly on the scale of the meter.
- 3. Alarm Positten I The alarm setpoint level will be indicated by the meter oeflection in this position. It is also spring loaded so as to return back to the operate position automatically.
- 4. Check Source.
. To activate the check source, depress and hold the green 2 ; pusn button light. The meter will be deflected because of
' % c.' the dose rate produced by the ~ check sauce. The check source
; is electrically positioned to irradiate the detector and consists of radium paint covered with clear lacquer on the end of the pointer in the check source assembly (857-1-17).
In the Model 857-1 there is approximately 0.02 microcuries of racium and in the E57-2 tnere is approximately 0.08 microcuries of radium. As the check source is de-energized, the red pushbutton light should be depressed to avoid activating the High alarm in the event that this alarm is set below the reading of the check source. Remember that since the check source provides actual radiation to the detector, this check is not only thorough, but will produco'an appropriate output on any recorders in the system.
- 5. High Alarm.
The red alarm light will turn "ON" when the radiation intensity exceeds the alarm setpoint. The preset level will be indicated by the meter deflection when the Function Selector switch is rotated to the' alarm position. ([ is . 1 7 M ANUAL SET 4
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- 5. -Alarm Reset.
~
A manual alarm reset mode is used in this G-M Area Monitoring System. In this mode the.High alarm will lock-in after it exceeds its preset level. Depressing the red (High Alarm) push button light will reset the High Alarm. Automatic reset mode is also available by removing a jumper j .;ag+y. . . located on the printed circuit board of the readout module.
. J ~. In this mode, the..High Alarm will respond to radiation
..f,i_ . . exceeding the preset levels and automatically reset below the preset levels. .
G. CALD3 RATION OF INSTRUMENT g
- 1. With instrument power supply on and in the operate position, place G-M detector in Gamna fields of 10 mR/hr, 1R/hr and 10 R/hr. Record observations for each of the three fields in the As Found Column of Figure 1.
7 2. If the instrument readings of Step G.1 are within 1 20% of the true dose rate, complete Figure 1, replace the 7 calibration sticker with a new one 'oearing this test date
*gs.
and when the instrument is next due for its semi-annual ' calibration.
?. If the readings are not within i 20% of the true dose rate, proceed to Step G.4.
4 Place instrument in 10 mR/hr Gamma field and adjust R12 adjustment to obtain a reading i 20% of 10 mR/hr.
- 5. Repeat Step G.4 for 1 R/hr field using R21 adjustment.
Recheck 10 mR/hr until both are reading within i 20%. Use same method for 10 R/hr using C23 adjustment.
- 6. Repeat Steps G.1 and G.2 but recording results in Figure 1-in the As Left column, if within i 20% of true dose rate.
- 7. If instrument cannot be calibrated, initiate repairs ahd recalibrate by repeating Section G.
H. . ALARM 9ETPOINTS
- 1. Raise Cs-137.well source to upper ' level, open the door and shield. Turn setpoint adjustment until monitor alarms.
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- c. l. HATCH NUCLEAR PLANT AiVISW NQ s2e riue g,;, GeorgiaPower A ~ ~o 5 of 6 PROCENRE DATA PACKAGE A.
- I { %-e r4 DOCtffNT NO: HNP-9127 i
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"^j- CCrPLETED BY:
DATE CCePLETED: I tMVE REVIE4D THIS DATA PACKAGE FOR COMPLETDESS 40 AGAINST ACCEPTANCE CRITERIA IN ACCCRDANCE WITH HP-830. LNACCEPTABLE ACCEPTABLE l REVIEWED BY:
'I OATE REVIEWED:
- l REr%RKS:
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9 eta.C_ounter Model GC-4 - - . - - PROCED'J7E TITLE _. _ _ HNP-8136 PROCEDURE NUMBER
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Lab RESPONSIBLE SECTION
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.. SAFETY RELATED ( X) NON-SAFETY RELATED ( )
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APPROVED APPROVED AE1 DESCRIPTION DEPT. PLANT DATE HEAD MANAGER e Pages 1 thru 6 . n ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .____c_f_.<._____,._ _ _ _ &_ _ C_ _ _ __ __Q $ s . I i l i b D e l
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unreviewed Safety Guestion (- ) Tech. Specs. ( [) Neither
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Safety Related ( ) Non-Safety Related' ( , fks W,)F h Safety /Non-safety Status Change ( ( d No I Attacn raarked up copy of procedure to thi's form. REASON FOR REGUF.ST_. he r ',yg, v gg gd. fp[ /ggd ede(_
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- - - - . - - - .an unreviewed - - - . - - :sfety ------
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(. .. asp a i nl e___ dbl questien -------.e.x ----- e ow .- - _ . -- -- ------..- -_ -- -----_
---------.e.- 1. Th probability of occurrence and t'h.e. g.onceouences
- -- ----- of an accident----
or calfu_nction
--------- f ecu.i.rm.ent-im.n.ortan.t.
-. ---. --- --to-- safety __are not increased----
a_b.on_t.Apsg_a.p.aly2.d in..the_EMBhu_e_?o._tbas.e._chnoms_b.ersn--- the revision does not chance _ the curaose or oerforman.c._e_- of the - j-
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- 2. Th'e cassibility of an- accident or malfunction of a different tyce than analyzed in the FSAP does not res_ ult from this chance because _
the system resconds and is operated as _ h_efore the chance. Th car of safety as defined in the_ Technical S_oecifications -- - - --- 3 --.e.---.cin
=- --- -
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._is not reduce _d due_,t.o this revision because the revisi
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- - - _ - - - - -.settines__which
- - would allow a .
safet'v' limit to be_ exceeded or to a_llow a limitino condition fo_r
---- _ --- -ices ocerat - to be exceeded as state _d _in' Technical Soecifications.
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(> _ nee trie Dage Georg,ia 0 Power o ~~ 1 or 7 9 ETA COUNTER MODEL 0C-4 A. SW7POCZ To insure the instrument is calibrated properly and to provide operation instructions for the user. 4 gg ,. B . REFERENCE l 4 _ ! iud'. BETA COUNTER MODEL BC-4'te'chnical manual.
--~ . .. .
C. SAFE 1Y Ooserve radiation protection procedures. ' O. O EC9IPTION OC INSTPUMENT The Model GC-4 Beta Counter is a system consisting of a two-inch doioctor, hign voltage pcwer supply, pulse amplifier, timer and
; six decade readout. All circuits are solid state with use of
_ integrated circuits.
=
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E. OsSCPIPTION OF CONTROLS
- 1. EXTERNAL
- a. . Count Mode - Selects timed or manual counting mode. ll
- b. Reset-Start - Resets.all appropriate' circuitry to zero l1 5-and starts a timed counting sequence.
- c. Count Time In Minutes - Selects desired counting time. l
- d. Power - Supplies power to the instrument. l
- e. 115 or 230 VAC Switch-Selects either 115V, 60 Hz, or 230V, 50 Hz. ,
- 2. INTERNAL
- l
- a. Time Base.(Timer Board) - Control for adjusting time base of the timer when instrument is used with a battery.
F. OPEPATION OF INSTRUMENT
- 1. Turn Power Switch to CN. -
( 2. Position Count Mode switch to desired mode. 4 e M ANUAL SET
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- 2. Position Count Time-In Minutes switch to counting time ces: rec.
- 4. Press Reset-Start switch and release. Instrument should l-5sg:n counting.
E. Daily Celibration. 1 FM" e- . a. Set Count Mode switch to Manual. Instrument should l I
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begin to counY. ' Record results in Man. CK column
- of w----- ' Data Package 1 (Data Sheet 1). ,
I
- . Set Count Mode switen to TIMED.
I
- c. Perform a 10 minute background count and record tne -
bacxground counts in C.P.M. on Data Package 1 (Data Sheet 1).
- d. Place a radioactive standard in position for counting and count for 5 minutes. Record results on Data i
Package 1 (Data Sheet 1) in C.P.M. and on graph developed from chi-square test.
,k1f NOTE A TC-99m beta source centered in a stainless c
. steel plachet should be usec. /
- e. The reading should be.within 1 3 sigma of the source's known count rate and should be distributed arouno the mean count line.
F. Calculate the counter efficiency for the geometry in j step d and record on Data Package 1 (Data Sheet 1). l Efficiency = Net C.P.M. X 100 D.P.M. I G. Call?PATION 0: INSTRUMENT
- l. Adjust-H.V. to 900 Volts. Refer to technical manual.
CAUTION Do not over-voltage the GM tube. (900 volts) l
- 2. Chi-Square test (Guarterly test). -
l (
- a. Perform a one minute background count and record the
- background counts in BKG. CPM on Data Package 2.(Data Sheet 2). .
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3 ot-7 D. Place a radioactive standard in position for counting. , Use t%e same standard which will be used in the daily
, calibration.
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'c. Count the source for one minute durations twenty times and record net count results on Data Package 2 (Data t
. Sheet 2).
$ G nid h w d. Calculate chi-square. If results is between 7,and 35, ..[, yj __, the instrum'ent'should be functioning properly j- - 4.s;_- - . ' - e .' Calcualte ld , av and 3a error. Develope a graph for aaily calibration checks. ,
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i i PROCEDL9E CATA PACKAGE
. COC'.raceT NO: HND *1M -1
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a. f_ . sEnAt No: - no2 i,
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MPt. PO: RTYPE: 015.1'* 8 XREF: TOTAL SHEETS: 2 FREOLENCY: Mont%Iy
.a l' CCrPLETED BY:
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a CATE COMPLETED: , I HAVE REVIEWD THIS DATA PACKAGE FCR CCa*PLETCESS NO AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH Hre-830. ACCESTAOLE tr4 ACCEPTABLE 1$ REVIEWED BY: DATE REVIEED: REMARKS: 1 1 Page 1 of 2 f
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