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Latest revision as of 04:01, 6 January 2021
| ML20065Q845 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/23/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20065Q830 | List: |
| References | |
| PROC-820923-01, NUDOCS 8210280375 | |
| Download: ML20065Q845 (21) | |
Text
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- l QEP 200-0 1 E
Revician 10 4 . . 4
- September 1982 i
'ID/IE,1L . EMERGENCY CONDITIONS 200 ,
Emergency Conditions -
.Rev. 10 09-10-82 200-1 '
Classification of GSEP Conditions Rev. 3 05-05-82 h' j 200_2 ~ Classification of an Incident , l Involving Hazardous Ifaterials Rev. 2 01-22-82 1 200-T1 Quad-Cities Emergency Action Levels - Rev. 7 09-10-82 I 200-T2 9 Emergency Action Levels a l Procedure Cross Reference Rev. 1 09-23-81 l 200-T3 Hazardous Substances Rev. 1 01-22-82 E
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AK - = ~"^ "*W%%M4 = =&- 'tW:fA i l i f l i 3 . . , i . i 1 -
- APPROVED SEP101982 Q.c.o.s.R 8210280375 821012 fDRADOCK05000 _i_ (gg,,1) -
u
^
- . . -- . ... . . .- .-, _ . ~ - - .- - - - - - - - - - - - - - "
QEP 200-T1 . ': s Revision 7' ; ID/2J QUAD-CITIES EMERGENCY ACTION LEVELS September 1982 [ i
, CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY 7 i Class Events in progress Events in progress Events in progress or Events in progress or .
Description - or have occurred or have occurred have occurred which have occurred schich [' which indicate a which involved involved actual or involve actual or potential degradation an actual or likely major failures faminent substantial of the level of potential substantial of plant functions core degradation or - safety of the plant. degradation of the needed for protection melting with potential level of safety of the public. for loss of containment . {
, of the plant, integrity. .
e 6 4
;E
- 1. Aircraft Impacted on-site (1) Impacted on-site Impacted on-site !
crash or and equipment and equipment described . I. missiles from described in the Technical Specifi-in the Technical Specifications is *
-f
- whatever cations is affected degraded such that '
[ source. 4 such that it is an immediate shutdown .f operated in a is required. ! degraded mode ! permitted by a Limiting Condition - - 1 for Operation. i (2) Turbine failure . [ with casing i penetration. APPROVED f
- 2. Control Evacuation is Evacuation is required i
Room SEP101982 t anticipated or and control is not
- Evacuation required with control established from established from Q.C.O.S.R. f local stations within i
local stations. 15 minutes. .
' 1 In addition to the Unusual Event, Alert, Site Emergency, and General Emergency, a Transportation Accident class exists.
A Transportation Accident condition shall exist if any vehicle transporting radioactive materials or nonradioactive { hnzardous materials from a henerating station is involved in a situation which could possibly breach or has breached j
'ths integrity of a shipping container (s). t 9
i
- l L1 [
7 N j QEP 200-T1 7 QUAD-CITIES EMERGENCY ACTION LEVELS , Revision 7~ . t, CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY i
. . I
- 3. Earthquake Earthquake felt in plant i Equipment described Equipment described had occurr- or detected on
~
in the Technica) in the Technical
- ed or Station seismic Specifications is Specifications is is being instrumentation. [
affected such is degraded such experienced that it is operated that an immediate i in a degraded shutdown is. ~ i mode permitted by
* ~
required.
- a Limiting Condition
' }
. for Operation. .
* [
s 48 f,
-i i
- 4. Unplanned On-site and equipment On-site and equipment i explosion. described 18 the described in the -
Technical Spe)cifications Technical Specifications '- is affected:such that it is degraded such tiiat an . . , is operated in a degraded immediate shutdown is ' ~ mode permitted by a Limiting Condition for required. [ C Operation. i 6
- 5. Fire. Requiring off-site Equipmentdekcribedin Equipment described in - '
assistance. the Technical Specift- the Technical Specifi-cations is affected cations is degraded suchthatitf.isoperated such that an immediate in a degraded mode shutdown is required. ; permitted byja Limiting
- Condition for Operation. t IK I y
- 6. Flood Mississippi River Mississippi Elver i level > 588 ft. MSL.
level >589ft.MSL. APPROVED I 4
. !3 SEP101982 1, 1 Q. c. o. S. R.
e i t' i i ) !,
.s i h
O .
@ @ 1 I QEP 200-T1 . !
QUAD-CITIES EMERGENCY ACTION LEVELS , Revision 7 - , CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY i GENERAL EMERGENCY i,
'7. Security Security threat, An ongoing s'ecurity Security threat Security thrent. (event)'
f threat-' (event) which also threat (event.) of (event) involving involving a loss of {
. poses a radiological increasing severity, an imminent loss physical control of i threat, or has the or a different of physical control the facility. !
potential for threat, which of the facility. substantial degrada- involves actual - tion of the level or potential' -
, of physical security substantial degrada-
> at the station. tion of the level ,.
(See generic'GSEP of safety of3the 4 i Section9.3.p.) station from,either ! the radiological or I physical security viewpoint.} f
~!
- 8. Tornado or (1) Tornado near (1) Tornado ; strikes l
(1) Sustained winds
.I severe winde facility. l-facilityl of > 110 mph and .,
, being (a) Control Room (2) Sustained winds both units not experienced. informed by Load {
of > 95 mph. in cold shutdown. 3 Dispatcher or j j (b) Control Room i! . : informed by !: , station personnel who have made k ( j i visual sighting or e (c) Shift Supervisor I ! informed by [ Weather Alert, or " l . (2) Sustained winds of >80 mph. . j I APPROVED l 4 (. SEP101982 (' Q. c. o. s. R.
' [t II 5 , I
. .I - 51 l(1 i
QEP 200-Tl - QUAD-CITIES EMERGENCY ACTION LEVELS Revision 7 CONDITION i UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY l
- 9. Toxic or Uncontrolled release Uncontrolled release Uncontrolled release uncontrol- of toxic or uncontrolled of toxic or uncontrolled of toxic or uncontrolled i led flam
- flammable gas at life flammable gas at life flammable gas at life
- l mable gas threat'ening levels threatening levels threatening levels [
(Chlorine, near or on-site. within the protected within the vital areas. Ammonia, area. ' j Hethane, - ' etc.)
> l 5
; i
(
- 10. Loss of Loss of all' pff-site Loss of all off-site Loss of all off-site !
AC power. power or loss of all power and lofs' of all power and loss of all ! Diesel Generators. diesel generators for diesel generators for .
< 15 minutes! > 15 minutes.
-{
t
- 11. Loss of DC power sources Lossofbothf Loss of both 125 VDC DC power. as described in the 125 VDC and 250 VDC and 250 VDC battery f*
Technical Specifica- battery <_ 15 minutes. systems > 15 minutes. tions are degraded l ! such that a Limiting 1 - . Condition for Operation j , requires a shutdown.
- 4 4 :
i li q i ! n J ! l ! i i - APPROVED I ( .: 6 '
. 4 SEP101982 ;, .
Q.c.0. S. R. !
, I j L1 ;
- - . .. . .~- . .
n_ ~~-- m i QEP 200-T1 -
'l QUAD-CITIES EMERGENCY ACTION LEVELS Revision 7' ,
CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY f
- 12. Plant Shutdown l'
. (1) Loss of "all (1) Loss of all systems Functl6ns. systems capable capable of maintain- ,
of maintaining ing hot shutdown or - I cold shutdown. (2) A transient requiring I' (2) Failure'of the Reactor operation of ECCS with f{ Protection System failure to SCRAM. ' r Instrumentation to initiate.and complete !
. a SCRAM which brings .- !
. the reactor subcritical 6 :
once a limiting safety 4 f system s'etting, as specified in the Technical -l Specifications, ..)
" has beeni exceeded. ' -
{ (ATWS) : .i
. L
- 13. Other (1) Equipment described (1) Equipment described Unplanned loss of most i conditions in the Technical in the Technical or all annunciators on !
or systems Specifications is Specifications is either panel 901-3(902-3) - ! required by degraded such that a degraded beyond or 901-5(902-5) for i Technical Limiting Condition the Limiting Conditions. greater than 30 minutes, i
, Specifi- for Operation requires for Operation (as and a plant transient cations (such a shutdown. [
specifiep that require has initiated or is in ( as ECCS, (2) Loss of communi- a shutdown). progress. I fire pro- cations or instru- (2) Technical -
; tection mentation such that Specification i.
system, accident assessment Sofety Limit [ etc.) or off-site dose exceeded. assessment cannot (3) Unplannned loss of lI be made. most or'all annunciators APPROVED .I s on either panel 901-3 k (902-3) or or 901-5 SEP101982 ! (902-5) for greater than- s
' 30 minutes. Q.C.O.S.R. !
8, d h]j
. . - . _ , _ _ , _ - _ _ ~ _ _ . - .- - - . - - . . - . * = = , - - -
1 i O O{ 0 ~1 c
' QEP 200-T1 . *i QUAD-CITIES EMERGENCY ACTION LEVELS Revision 7' ,
CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY
. 14. Loss or (1) ECCS Initiation (1) A 2 50 spa (1) A 1 500 gym Imminent core melt.
Primary (not spurious). leakagefrate leakage rate Coolant - (2) Failure of a increase as increase as i Primary System indicated by indicated by " Safety or Relief 'surveill'ance. surveillance. Valve to close. (2) A main steam line (2) A main steam line (3) Total leakage rate break outside break outside* *
. to primary containment containment with containment without is greater than 25 spa. automatic -[
the capability of .- t
. isolation. (FSAR effecting 4
'g }
sectionjl4.2 3) isolation. j p (3) Circumferential p l break of a reactor - t jj coolant recircu- -
;'t '
lation line.
'{
..f
' }' (LOCA; FSAR '-
5' d Section 14.2.4.) .-
-. b n >
- 15. Fuel Handling . Standbygasjtreatment Standby gas treatment t Accident. system operational .
system not operational - f. (Fuel Handlers and secondary contain- or secondary contain-ment isolation report damage to ment isolation
. irradiated fuel effective okecapable incapable of being {
assemblies and of being effected, effected. ; Refuel Floor ARM (Refueling accident; ' reads 100 ar/hr.) FSAR Sectioni14.2.2) i > hy
+
I s. 1 i-1 e ir s APPROVED - p t t SEP101982 i
' e . !
f
-6,1 Q. C. O. S. H.
6 t 4 ; f i b h
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-_ _ _- _. . - . - - _ - -- - - _ _ --. ~mn-ma
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QEP 200-T1 . i QUAD-CITIES EMERGENCY ACTION LEVELS Revision 7 , P CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY 0
. t 2 2 3 -
- 8
- 14. Loss of Coolant activitey A. 1primarycontain,[
2 x 10 R/hr A. 1 4 x 10 R/hr A. 1 2 x 10 R/hr l, fissio'n sample 1 5 uCi of primary contain- primary contain- j product I-131 dose equi- ment activity, or ment activity, or ment activity, and ( barriers. valent per gram B. Loss of I of the B. Loss of 2 of the imminent loss of of water. following 3 fission following 3 fission primary containment, product barriers': product barriers: or h (1) Cladding: grab (1) Cladding: grab B. Loss of 2 of the
. sample > 300:pci/cc sample > 300 pCi/cc following 3 fission {
, equivalent of equivalent of product barriers, ,- !
. I-131. (Control I-131. with an immisent j
'4 Rod Drop Accident; (2) Reactor coolant loss of the 3rd [
FSARSectionl sys: > +2 psig fission product i 14.2.1) 1 drywell pressure barrier:. [ (2) Reactor coolant & < -59 in:hes (1) Cladding: grab ~l sys: > +2 psig . vessel level.
- sample > 300 pCi/cc .: .)
drywell pressure (3) Primary Containment: equivalent of I-131. f,
& < -59 inches (a) > 56 psig (2) Reactor coolant ?
vessellevelk ment gressure, or sys: > +2 psig f. (3) Primary l (b) > 281 F contain- drywell pressure p Containment:j ment temperature, & < -59 inches } (a) > 56 psig (c) Loss of primary vessel Jevel.
-l.
containment pressure, or containment
. integrity when (3) Primary Containment:
[' ('
, (b) > 281 F required. (a) > 56 psig containment ccatainment temperature. pressure, or -
(c) Loss of primary (b) > 281*F ; ) containment containment y l integrit.y when temperature. required 3 l l (c) Loss of i l g Primary j. containment ,
? jll APPROVED integrity i
, when g 4 SEP 101982 re9uired. !
j i
- g. c. o. s. R. 3 ld( 9 y d ll1 '
a _ _ _ _ _ _ _ _ _ _ _ . _ _ __ _ r.
t G O
~
i QEP 200-T1 - QUAD-CITIES EMERGENCY ACTION LEVELS Revision 7 . f CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMEltGENCY
- 17. Radio , A. Gaseous Effluents: (
A. Gaseous ' Effluents: A. Gaseous Effluent: A. Gaseous Effluent: activity i Technical Specifi- Effluent release Effluent monitors Monitors detect . Effluent
- cation instantaneous > 10 times the detect levels levels corresponding !
release release limits. Technical Specifi- corresponding to to > 1 res/hr whole ! from the exceeded as cation J plant. measured by instantaneous >30ar/hr(1.3x 10 pei/sec) for 1/2 body at the site boundary. This [ effluent radiation release. limits as hour or >g500'mR/hr condition exists j monitoring and measured,by (1.3 x 10 pei/sec) ,when: ; counting- radiatioh 7 for 2 minutes at t'he Q/U > 4.5 x 10 .- instrumentation. monitoring and where
'{ counting. instrumentation site boundary. 8 (Adverse Meteorology.) Q = release rate in j.
(1) Noble Gases - (1) Noble' Gases - pei/sec i (a) Main Chimney: (a)iMain Chimney: U = mean wind speed Unit 1 or Unit 2 :' Unit 1 or Unit 2 in sph ' (not both) !.(not both)' ' OR .-)
, Releaserage Release rgte Q/U > 1.0 x 10 [
> 2.1 x 10 pCi/sec > 21 x 10 pCi/sec where Ey j u Ey Q = release rate in Both Units 1 and 2 Both Units 1 and 2 [
pci/sec > Rele.sserage ijRelease rgte U = mean wind speed
> 2.6 x 10 pCi/sec 'j > 26 x 10 pCi/see in meters per second - (;
Ey { Ey (b) Reactor Bldg (b).jReactor Bldg , , Vent Stack: JVent Stack: , Release rage jReleasergte (
> 2.3 x 10 pCi/sec pCi/sec 1.3Ey + ES }g>23x10 l 1.3Ey + Ep i-c whwre: Ey = average gamma energy per disintegration (MeV/p'is).
I ES = average beta energy per disintegration (MeV/dia). [ l These quantities are determined monthly and are prominently posted in the Control Room. j
' h APPROVED :
' e ;
9 SEP101982 b .
, y q.c.o.s. w. ;
9 t
-8 .! l (
dh! _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ r
i fU QEP 200-T1 QUAD-CITIES EMERGENCY ACTION LEVELS Revision 7 T t CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY t
- 17. (Cont.) (2) Iodine.and (2) Iodine and '
Particulates - Particulates - Susanation of Suassatjo a o( ! release rate for release rate for i halogens and halogens and particulates with particulates with [' (
-half-lives > 8 daysj 3 half-lives > 8 daysio I 7.3Qv + 2.6Qc > 10 7.3Qv + 2.6Qc > 10 !
e v '
. i where: Qv = relense rate from the reactor p[ 4 building vent stgack in pCi/sec.
Qc = release rate from the main I( f I,i , chimeny in pCi/sec. L ki 'I B. Liquid effluents B Liquid dffluents: B. Liquid effluents: B. Liquid effluents: ., concentratiori of: g (1) Gross beta activity (1) Coheatrationof grces beta activity Estimated activity Estimated activit'y ; of liquid release of liquid release .) (above background) inhhedischarge is > 2000 Ci but is > 2.4 x 10' ri. E in the discharge baf,i> 10 times the 1 20,000 C1. ' bay in excess of TepnicalSpecifi- : the Technical cationLiegt -
-[,
Specification (>!! x 10 pei/ml) limit (> 1 x 10 _7 unless discharge is l i
. pci/ml) unless co5 trolled on a '
discharge is radionuclide basis ' controlled on a in accordance with radionuclide basis Appendix B Table II , , in accordance with Colden 2 of 10 CFR Appendix B, Table II, 20 and note 1 thereto. j Column 2 of 10 CFR 20 OR . ' I and note 1 thereto. (2) Etimated activity of liquid release
> 40 Curies but pp g .f.
s 2000 Curtes. SEP101982 i Q.C.O.S.K l ! L, ti 1
'Ihf
_-- 7 ' _ . _ _ - - - a---.-=---- -"w l 0 I .y QEP 200-T1 QUAD-CITIES EMERGENCY ACTION LEVELS Revision 7 t h CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY .
)'
i 18. Personnel Transportation of i
}
Injuqr radioactivity contami-
' t nated injured person j, !
to hospital. i. t
# I y 5
- 19. Hazardous As a direct result of (1) Warrants Warrants activation 8 Materials hazardous materials a precautionary of emergency cente'rs
.' person is killed or activation of the and monitoring teams,
=
I hospitalized or TSC and placing or a precautionary . i
- estimated psoperty the EOF and other notification to the
- g damage exceqds $50,000. keyemergency public near the site.
3 persoanel on k standby. - I (2) ARN readings (a) ' [. indicate a severe
- dedradationinthe control of radio-l' active material. !
- 20. Any other Warrants increased Imminent core melt.
conditious awareness on the i f of equivalent part of the state magnitude to ll f and/or local off-site i I
. the criteria officials. . I used to define i i the accident as di determined by 1.1 APPROVED !
- Station Director
- d
- cro 1 n MM t Other emergency conditions that require an emergency rssponse are those involving: d ' * ' " ' -
{
- a. Incident reporting per 10 CFR 50.72.
- b. Hazardous material incident reporting per P.A. 79-14424 g,g,g,3, g, !
- c. Oil discharges to waterways per the SPCC Plan. j -
.f.
l d. Security contingency events per the Station Security Plan. ( The Station Director may, at his discretion, categorize th) above situations as GSEP emergencies, depending upon the
, seriousness of the situation. (Refer to Section 9.3 of thE generic plan for additional information.)
{
-10 (final) 9
.L '
j dI.O A
3 . . ! I. T
~l N
]1-
,1 s -
, ,3 ENTON QAP lico-I5 Revision 6 k \QG .
STATION PROCEDUKE REVISION COVER SHEET October 1981 4 *V ID/12 L Revision Des ption 1, . ' a & otsriduit u a OGP 330-3 -
.' b r 5 e m r,. c d 2t;;f .
l 7** ********* A Ori Restsion
!E .
2 i -
~
j This proced tre is required to be implementad prior to -
} Dsta DeC3ESS of_
, 13tAFT REVIEW !
FINAL
?[ OVAI. , 'm . r. Tech. Staff Supervisor Date u
I l
/
Dept.
=dsCn M46 C#Eh ens Data r_
?
^) ._ DePa. w t. Hand
- Mb .-a th, 2.
_ . ,._,,,,_ Data .f=^ . 3 ervisor- '
- .*Inta- -
' 7 Originator
/Ltd h-b .
23 - i y . Date Asst. Sapt. .A OA /41 Data 4J un0N - - L i l h Sta*_ ion Superistandant' Effettive Date vn/n . p, INSTRUCTIONS FOR REVISION INSERTION REMOVE' INEERT QEP 350-0 MEV l'.S OEP th e-<* MV IV QEb 330 3 2W V -
.. REVISION RECEIPT FORM L
,. C
( j j< Please Quad sign Station. Citie;g and date below, and return this sheet to the Officer Supervisor - Your Station Procedure copy number is ' ~ '. - Signature ~
. Data *
(final) ,
!!OV 8, Jssi -
, O.C.O.S o
{ n _n.,
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y .-r~~-~~-i"---"----~-~~.-----R quP 330 0 .- T i . Revicion 14 September 1982
. . ID/10,1P ASSESSMENT ACTIONS 330 ,
j Assessment Actions " Rev. 14 09-23-82 1 ! 330-1 i 4 Abnormal Personnel Exposure Rev. 3 08-10-81
- I l 330-2 I j Accidental Release of Radioactivity
- i Within the Site Boundary Rev. 2 02-22-81 e
i 330-3 SPING. Control Terminal Operation Rev. 4 09-23-82 1 4 330-4 l Estimation of Off-Site Dose from an Unplanned Release of Radioactive Effluents Rev. I 12-17-80 330-5 Estimating High Activity Reisases during Accident Conditions Rev. 1 12-17-80 4 330-6 . Air Sampling Under Accident -*-
. .g Cor.ditions Rev. 2 03-10-82
'%) c- n ; :,:.w ~ ;;;= ::. =:y:xwa.a.t:=d=:- w.w r.a uu.m sunww w.omeu 330-7 - - - - -~~ ~ -- ~
In-Plant Iodine-131 Messurement During Post-Accident Conditions Rev. 4 03-10-82 330-8 Handling and Analysis of Post Accident Reactor Coolant Samples Rev. 4 08-23-82 ' 330-9 Estimating Plant Releass Using the Stack Gas Monitors Rev. I 12-17-80 l 330-10 . On-Site Sampling During * *
- Emergency Situations Rev. 1 06-01-82 ..
330-T1
- Quad-Cities Station Environs l Monitoring-Dairy Farms Rev. 1 06-20-80 .
330-T2 1 Dese Factors,for Gaseous Releases Rev. 2 03-10-82 i _ 330-T3 : APPROVED i
' PO ~ Dose Factors for Liquid , Releases
- Rev. I 12-17-80 SEP 2 31982 Q.c.o. s. a
, 1 .
s + -
- ,.n p-m -
-,--;9 ___._Q.
V l_. a_- .w . . . . . . . - - . . . . - -
.. ,- ~.
.---~---~~~-w.n'
~
y o l, a QEP 330-0
~
T Revicies 14 j
; - 330-T4 .
i Main Chimney Release Rate Table' Rev. I 12-17-80
]' .
<:. 330-T5 ,
, , Typical Gas Stack Monitor .
3 Calibration curve Rev. I 12-17-80 330-T6 - 1 Sample Cave Rev. 1 05-18-81
! 330-77 Sample Dilution Equipment Rev. 1 05-18-81 ] 330-T8 .
j On-Site Environmental Sampling I,ocations Rev. 1 06-01-82 t i
.i .
is
% - e, 4
4 o t i ! t , h L l* . 5 i l
- 1
. 1 I
APPROVED i ;& 8: r SEP 2 31982 Q. C. O. S. H. (final) .. . 9 _e .
.P. _ . _ _
1 7..
- . +-
-....--- -- A N
- -~
.2 q
'l n . 1 I QEP 330-3 .) N,) '
, Revision 4 4 SPING CONTROL TERMINAL OPERATION September 1982 1,
j ID/5G A. PUkPOSE j ) , The purpose of this procedure is to provide inscructions for operating the SPING control terminal. ] B. REFERENCES } 1. Eberline CT-2 Technical Manual. 1 C. PREREQUISITES l
- 1. Obtain a keybcard key from the Shift Engineer.
j D. PRECAUTIONS _
~
i
- 1. The keys on the keyboard are touch sensitive. There is no need to a
press hard when entering data. E. LIMITATIONS AND ACTIONS
- 1. The calibration constants in the noble gas rhannels are based on Xe-133 calibrations.
F. _ PROCEDURE
- 1. The keypad has two keypad subgroups. The upper keypad group is the
], instruction pad, while the lower keypad group is the data pad. An j entry of both an instruction and data is then a command. All commands j begin with a single entry via the instruction pad, followed by an entry or entries via the data pad, and thrainate with the ENTER key. j 2. The instruction pad is color-keyed according to function. The blue i keys are for inquiries of ds',a or parameters. The green keys are for J control functions. The blau key (edit) is used to coemand changes of l parasseters in the channel files. The red key (print) is used to print j the status of all channels and to perform calculations on history data. ..
~
4 . i I 1 l APPROVED SEP 2 31982 Q.C.O.S.R
,- _ m
-._.-....u.. . - - . , . ~ . - . L . . a. .~. . . . . . . . . . . . . - . . n :. . w . .
- n. l
. . e g
, QEP 330-3 Revision 4 f .
f . 3.' An address is the complete numerical identification of a detector and i;, . comprises the fiefd unit address plus th,e channel number of the detector. }J The addresses are as follows. Rx Vent Low Range Noble Gas - 0105 J) Rx Vent Mid Range Noble Gas - 0107 j Rx Vent High Range Noble Gas - 0109 i Rx Vent Area Monitor - 0106 APPROVED i Rx Vent Background - 0108 { SEP 2 31982 j Main Chimney Low Range Noble Gas - 0305 d 4 Main Chimney Mid Range Noble Gas - 0307 Q.C.O.S.H. Main Chimney High Range Noble Gas - 0309 j Main Chimney Area Monitor - 0306 1 Main Chimney Background - 0308 l 4. To have information output from the control terminal the following i; commands should be performed. 3 a. Open the control terminal drawer, insert the key in the keyboard
! slot and turn it on.
A
; b. Determine the system status as follows.
(1) Check the lights located above the pull-out drawer. I {"pI (2) The lights and their associated meaning are, from left to
} '- -- right. ] NORMAL (green) - normal status.
Q MAINTENANCE (white)-aunitisinflush,chrecksource,or [ calibrate. i FAIL (amber) - a unit has failed on low flow, low counts, j communication, or loss of power. a ] TREND (amber) - a unit has trend alarm status. Trend alarm is a condition that relates present values with past values, y A preset percentage difference, high or low, causes an alarm. 1 . ALERT (amper) - high alarm condition exists. l HIGH ALARM (red) - high-high alarm condition exists. By 4 pressing the high alarm light the red light to the right of it will go off. RED LIGHT - this will light with any change in status of any j unit or on a high-high alarm condition. I c. ' Type in PRINT, ALL STAT, ENTER. This will give you the day and L time, the other control terminal communication status (Bro) and l A the status of all initialized channels in each SPING unit. Channels not initialized will have a star in front of them and no status.
. . - . . _ ,. . ..-- -..~
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'- Revision 4 5.' Determine the present pei/cc value for each channel of the reactor vent and main chidney monitors. ,
- s. Type in DATA, 0105, RNTER. This will give you the present value of the low range noble gas channel of the reactor vent monitor and '
its status.
- b. Repeat the DATA, XXXX, ENTER command for each of the desired noble I gas channels listed in Step F.3.
- 6. Determine-the history data for each desired channel.
- a. Type in HIST MIN, 0105, ENTER. This will give the last 23 ten-minute averages of the reactor vent low range noble' gas with the present value printed last to give 24 data points.
- b. Type in HIST HR, 0105, ENTER. This will give the last 24 one-hour averages for the reactor vent low range acble gas with the most j recent value printed last. '
i
- c. Type in HIST DAY, 010'5, ENTER. This will give the last 24 day I averages for the reactor vent low range noble gas with the most i
recent value printed last. - f
- d. Repeat the appropriate history command for the desired noble gas
- channels listed in Step F.3.
! 7. To turn .the pump of any: unit- ON or-OFF, type as follows: l .
- a. For main chimney; PUMP, ON (OFF), 030, ENTER l ,
t ! b. For reactor vent; PUMP, ON (OFF), 015, ENTER. . 8. To take any unit IN or OUT of flush, type as follows: } a. For main chimney; FLUSH, ON (OFF), 030, ENTER.
- b. For reactor vent; FLUSH, ON (OFF), 010, ENTER.
- 9. To clear an alarm on any unit, type as follows:
i . NOTE l l Value must be 780% of alare value to clear. l
- a. For main chimney; ALMCLR, 030, ENTER. l
- b. For reactor vent; ALMCLR, 010, EITTER.
APPROVED I Unit-channel numbers are listed in Step F.3. 23M g.c.o. s. x.
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p QEP 330-3 f Revision 4 j 10 . ' To check a detectors response, type in: CKSRC, unit channel #, ENTER. j . NOTE I l Only channels 5, 6, and 9 have checksources.
- 11. To print the parameter file for acy channel, type in: FILE, f
unit-channel 9, ENTIR. l i
- 12. If power is. lost to any field unit (SPING), the unit will need to be re-initialized as follows: I
- a. Type in FILE, UNIT-CHANNEL #, ENTER. This will cause the printout of the channel parameter file for the specified unit and channel.
- b. All of the calibration constants and units will have to be edited in.
g c. To type in any value type: RDIT, line number (2 digits), data 1 (either numerical value, channel number, or yes/no), ENTER. EXAMPLE: A calibration constant is #4.08e-03. To input this number find the line number associated with it (ie 03). The command, EDIT, 03, +4.08 - 08, ENTER will cause the value to be input into the file. Note the format for numbers. To check the value, turning the edit key off will cause the channel parameter j;)- g file to be printed again with the new value. w-w
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- d. Any other 'significant data should be edited in a similar manner. ~
, 13. If power is lost to a CT-2 terminal a FILE O command will need to be
- executed.
! 1 j a. Type in FILE, 0, ENTER. This will show the day and time and i fbliow with " ENTER DAY TIME". If this needs to be changed, enter a 3-digit number for the day of the year (001-365), a 4-digit number for the time of day (0000-2359) and terminate with enter. This value is then printed. If no change is needed, enter "no" j (-/off key). j b. Next the 24-hour log time will be presented. ~ Enter the time
- desired as is pt,gp F.13.a. or "no" (-/off key).
.i j c. Next tEg 4-hour log will be presented. Answer "yes" (+/on key) or ! "no" (-/off key).
, d. The instrument then asks four quescions (see the CT-2 technical 4
manual for instructions). If nothing is to be added or deleted answer "no" (-/off key) . f E APPROVED 1
@ s SEP 2 31982 Q. C. O. S. M.
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Revision 4 ' 14.' If any log time or time-date needs to be changed follow steps F.13.a. e< to F.13.d. '
, 15. If any problems arise udt covered in this procedure consult the CT-2 technical manual and radiation chemistry supervision.
G. CHECKLISTS [
- 1. None.
i . H. TECHNICAL SPECIFICATION REFERENCES
- 1. None.
d a j i i
- I APPROVED 15 SEP 2 31982 Q. C. O. S. k.
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a Revicica 12 {
' September 1982 )
'ID/IS,1T PROTECTIVE MEASURE FOR
~. s ONSITE PERSONNEL U -
360-0 . Protective Measures for Onsite Personnel Rev. 12 09-03-82 a 360-1 Drywell Evacuation - Rev. 1 06-20-80 1 1 j 360-2 , i Plant Evacuation and Assembly Rev. 8 08-17-82 1 360-3 Site Evacuation Rev. 2 03-02-82 1 I 360-4 Use of Potassium Iodide (KI) } as a Thyroid Blocking Agent Rev. 2 05-1.8-81 ! 360-5 .f Issuance of Emergency Film During 4 GSEP Conditions Rev. 1 05-18-81 3 [ 360-S1
- Emergency Film Distribution Log Rev. 1 05-18-81
?l .s 360-T1 3 S'j ' Evacuation. Assembly Areas for Visitors j and Contractors Rev. 2 03-02-82 9 360-T2 'l
- Evacuation Routes by Wind Direction Rev. 5 09-03-82
] 360-T3 l' Site Evacuation Routes Rev. 1 06-20-80 1 360-T4 Evacuation Relocation Centers Rev. 1 06-20-80 360-T5 Iodine - 131 Dose Equivalent to Thyroid j Reference Reg. Guide 1.109, , Rev. 1 04-01-81 ! 360-T6 , b Iodine - 133 Dose Equivalent to Thyroid l Reference Reg. Guide 1.109 Rev. 1 04-01-81 ? 360-T7 Iodine - 135 Dose Equivalent to Thyroid I Reference Reg. Guide 1.109 Rev. 1 04-01-81 f [kg 360-T8 . APPROVED Q:' Potassium Iodide Distrihntion Record Rev. 1 05-18-81 SEP 0 31982 t Q.C.O.S.M. (final) .. . 9
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o a . D ' l-Q tg . QEP 360-T2 Revision 5 EVACUATION ROUTES BY WIND' DIRECTION August 1982 h ID/IN f WIND DIRECTION SITE EVACUATION RELOCATION t (Determined from Control ROUTE CENTER { Room or Metro Tower) (See QEP 360-T3) (See QEP 360-T4) N (0 ) * . A PARK NNE A PARK l NE (45 ) A PARK ) ENE A PARK 1 E (90 ) A PARg i ESE A RHS SE (135 ) A RHS l } SSE A RHS l S (180 ) A RHS SSW A f RHS 3 SW (225 ) A RHS WSW 3 e A RHS W (270 ) A RHS WNW B PARK i NW (315 ) B PARK NNW A PARK PARK: Proceed north on Route 84 to Albany Road. Turn right on Albany Road. hl).
- Park. is-ondef tchand:sedevoqNetm roudec=cxrR::::c - - -- ~
RHS: (Riverdale High School /COE Elementary School). Proceed south on Route 84 to Hillsdale Road. Turn left on Hillsdale Road. Proceed to 256th Street North. Turn left on 256th Street North. The 2 Riverdale High School and COE Elementary School are en the left h hand side of the road. 3 l EVACUATION ROUTE C: This route may be used :t the discretion of the [ Technical Director or Shift Engineer. I - s
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APPRovrn SEP 0 31982 Q. C. O. S. tt (final) - I
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