ML20063M489
ML20063M489 | |
Person / Time | |
---|---|
Site: | Quad Cities ![]() |
Issue date: | 08/16/1982 |
From: | COMMONWEALTH EDISON CO. |
To: | |
Shared Package | |
ML20063M480 | List: |
References | |
PROC-820816-02, NUDOCS 8209140404 | |
Download: ML20063M489 (15) | |
Text
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QEP 200-0 -
9 Revision 9 ,
- ID/1K,IL EMERGENCY CONDITIONS' 200-0 Emergency Conditions Rev. 9 08-16-82 200-1 Classification of GSEP Conditions Rev. 3 05-05-82 200-2 Classification of an Incident Involving Hazardous Materials Rev. 2 01-22-82 200-T1 Quad-Cities Emergency Action Levels Rev. 6 08-16-82 .
200-T2 Emergency Action Levels -
Procedure Cross Reference Rev. 1 09-23-81 200-T3 Hazardous Substances '
Rev. 1 01-22-82 L.)
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l acPROVED
@ AUG 161982
-- -Q. C. O. S. H~
8209140404 820826 PDR ADOCK 05000254 F PDR (final)
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QEP 200-Tl Revision 6 :
ID/2J QUAD-CITIEC EMERGENCY ACTION LEVELS August 1982 ,;
CONDITION UNUSUAL EVENT ALERT I$
SITE EMERGENCY GENERAL EMERGENCY 'i Class Events in progress Description Events in progress Events in progress or Events'in progress or [!
or have occurred or have occurred have occurred which have occurred which which indicate a which involved involved actual or involve actual or ..
potential degradation an actual ca likely major failures imminent substhntial h of the level of potential ubstantial of plant functions core degradation or M safety of the plant. degradation of the needed for protection melting with potential t level of safety of the public. for loss.of containment 1 of the plant. integrity. *
- 1. Aircraft Impacted on-site (1) Impacted on-site Impacted on-site crash or and equipment and equipment described missiles described in the in the Technical from Technical Specifi- Specifications is #
whatever cations is affected degraded such that p.
source. such that it is an immediate shutdown operated in a is required.
degraded mode p
4 permitted by a, )
Limiting Condition for Operation. *
(2) Turbine failure 1 with casing j penetration.
APPROVED (
i
- 2. Control Room Evacuation is Evacuation is required gyG1 6 601 b anticipated or and control is not ~
Evacuation required with control established from Q.C.O.S.R. ;
established from local stations within local stations.
Q 15 minutes. '
.F. '
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 (
hazardous materials from a generating station is involved in a situation which could possibly breach or has breached [,.
the integrity of a shipping container (s). F
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g QEP 200-Tl l-QUAD-CITIES EMERGENCY ACTION LEVELS Revision 6 .
CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY ff
- 3. Earthquake Earthquake felt in plant Equipment. described b
Equipment described ?
had occurr- or detected on in the Technical in the Technical c ed or Station seismic Specifications is Specifications is is being' instrumentation. affected such is degraded such k,
experienced that it is operated that an immediate t in a degraded shutdown is mode permitted by required. j.
, a Limiting Condition .
for Operation. L
- 4. Unplanned On-site and equipment On-site and equipment 6
explosion. described in the described in the Technical Specifications Technical Specifications ,
is affected such that it is degraded such that an
~
. is operated in a degraded immediate shutdown is mode permitted by a required. tj Limiting Condition for Operation.
, y
- I S. Fire. Requiring off-site Equipment described in Equipment described in .
assistance. the Technic'al Specifi- the Technical Specifi- .
cations is affected cations is degraded a such that it is operated such that an immediate t in a degraded mode shutdown is required. .
permitted by a Limiting Condition for Operation.
)
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- 6. Flood Mississippi River Misaissippi River h level > 588 ft. MSL. level > 589 ft.. MSL. ppl10VED
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- QEP 200-T1 QUAD-CITIES EMERGENCY ACTION LEVELS Revision 6 -
s CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY (
I.
- 7. Security Security threat An ongoing security Security threat Security threat (event) threat (event) which also threat (event) of (event) involving involving a loss of poses a radiological increasing severity, an imminent loss physical control of 1 threat, or has the or a different of physical control the facility.
potential for threat, which ' fl 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 of the Section 10.3.2.) station from either ,
the radiological or physical security -
view point. :
g
- 8. Tornado or (1) Tornado near .(1) Tornado st.rikes (1) Sustained winds c severe winds facility. facility, of > 110 mph and ,
y[
being (a) Control Room (2) Sustained winds both units not F experienced. informed by Load of > 95 mph. in cold shutdown. :3 Dispatcher or I (b) Control Room F informed by .
station personnel who have made
[
visual sighting or [5 (c) Shift Supervisor "
informed by '
Weather Alert, or (2) Sustained winds '
of >80 mph.
f APPROvFD (i
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QEP 200-Tl QUAD-CITIES EMERGENCY ACTION LEVELS Revision 6 C
, r CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY '
- 9. Toxic or Uncontrolled release Uncontrolled release Uncon2 rolled release uncontrol- of toxic or uncontrolled of toxic or uncontrolled of toxic or uncontrolled j led flam- flammable gas at life flammable gas at life flammable gas at life (c.
mahle gas threatening levels threatening levels threatening levels E.
(Chlorine, near or on-site, within the protected within the vital areas.
- Ammonia, area.
Methane, etc.)
- 10. Loss of Loss of all of f-site Loss of all off-site Loss of all off-site AC power. power or loss of all power and loss of all power and loss of all ;
Diesel Generators. diesel generators for diesel generators for
$ 15 minutes. > 15 minutes.
.i
y as described in the 125 VDC and 250 VDC and.250 VDC battery Technical Specifica- battery 5 15 minutes. systems > 15 minutes, 4
tions are degraded '
such that a Limiting Condit. ion for Operation '
requires a shutdown.
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r APPROVED 2 i-AUG 161962 P 1
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UNUSUAL EVENT :
- 12. Plant Shutdown ALERT LEVELS (Jactions. k.'
^' ,QEP 0-Tl -
(1) Loss Revision 6.
systems of all SITE EffERGENCY "
capable (1) Loss fi of maintainin of all systems R55. EMERGENC W (2) Failurecold shdtdown.g capable of maintain- "
i't' Protection Systemof the(2) A transient req iing hot shutd Reactor u ring Instrumentation to initiate failure to SCRAMoperation of EC 1 and complete . ff a SCRAM which brings the reactor ,-
~~ -
once a limiting safetsuberitical system y C
specifiedsetting, as in the Technical
7
- 13. dther Speci fica tions , -
i has been exceeded conditions or (1) Equipment describ (ATWS) .
systems ed required by in the Technical (1) Equipment describ 6 Specifications is ed Technical degraded such that Speci fi- in the Technical Limiting Condition a Specifications is Unplanned loss of most or cations (such as ECCS afor Operation requir es degraded b g either panelall annunciators on
]{
J fire pro,- shutdown. the Limiting Conditi ons o (2) Loss i tection cations of communi- for Operation (as speci fied th r 901-5(902-5) for901-3(902-3) ~
system,' a greater and than 30 minute a plant s, mentationor instru- shutdown).at require etc.) such that (2) Technical has initi transient accident or assessment Speci fica tion progress. ated or is in ^
off site dose assessment Safety Limit ,
be made. cannot exceeded, }
(3) Unplannned lossof b E
most or on ,
either panel 901-3all annunciators (902-3) or k
or 901-5 h
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- 30 minutes.(902-5) an for greater th , , p g g, n 'g p
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QEP 200-Tl QUAD-CITIES EMERGENCY ACTION LEVELS Revision 6 . >
CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY l 1
- 14. Loss or (1) ECCS Initiation (1) A 1 50 gpm (1) A 2 500 gpm Imminent core melt. I Primary (not spurious). leakage rate leakage rate ,
Coolant (2) Failure of a increase as increa::e as p Primary System indicated by indicated by Safety or Relief, h-surveillance. 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 gpm. automatic .the , capability of isolation. (FSAR effecting section 14.2.3) isolation. !
(3) Circumferential Y break of a reactor coolant recircu-
If iS
- 15. Fuel llandling Standby gas treatment Standby gas treatment Accident. t system operational system not operational ty (Fuel llandlers and secondary contain- or secondary contain- ;
report damage to ment isolation ment isolation irradiated fuel assemblies and effective or capable of being effected.
incapable of being effected.
L(
Refuel Floor ARM (Refueling accident; .
reads 100 mr/hr.) FSAR Section 14.2.2) ,
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QUAD-CITIES EMERGENCY ACTION LEVELS Revision 6 -
CONDITION UNUSUAL EVENT ALERT 6 SITE EMERGENCY GENERAL EMERGENCY y
- 14. Loss of 2 Coolant activity A. > 2 x 10 R/hr A. > 4 x 10 R/hr A. 1 2 x 10 R/hr fission sample > 5 uCi of _prirnary contain- primary contain- primary contain- :
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 f ouninent loss of k3
. of water. following 3 fission following 3 fission primary containment, product barriers: product barriers: or i (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, 1-131. (Control I-131. with an imminent :'
Rod Drop Accident; (2) Reactor coolant loss of the 3rd FSAR Section sys: > +2 psig fission product 5 14.2.1) drywell pressure barrier:
(2) Reactor coolant & < -59 inches (1) Cladding: grab sys: > +2 psig vessel level. sample > 300 pCi/cc drywell paessure (3) Primary Conr.aisunent: equivalent of I-131.
& < -59 inches (a) > 56 psig (2) Reactor coolant u vessel level.
(3) primary ment gressure, (b) > 281 F contain-or sys: > +2 psig drywell pressure *
(i Containment: ment temperature. & < -59 inches f (a) > 56 psig (c) Lot.:s of primary vessel level. y contaisunent conta irunent (3) Primary -
pressure, or integrity when Containment: 9
' (b) > 281 F required. (a) > 56 psig , [
containment containment R temperature. pressure, or 4 (c) Loss of primary (b) > 281 F s.
containment containment ;
l integrity when temperature. -
i required. (c) Loss of prima ry
[1 containment is APPROVED integiity p g when :
M1 b required.
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QEP 200-T '
j Revision 6 QUAD-CITIES EMERGENCY ACTION LEVELS ,
s UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY d d
CONDITION
- a'-
Gaseous Effluents: A. Gaseous Effluent: A. Gaseous Effluent: (I Gaseous Effluents:
A. A.
- 17. Radio- Effluent monitors Monitors detect :
activity Technical Specifi- Effluent release -
levels corresponding Effluent cation instantaneous > 10 times the detect levels '
Technical Specifi- corresponding to to > 1 rem /hr whole release release limits body at the site from the exceeded as cation >30mr/hr(1.3x 10 pci/sec) for 1/2 boundary. This plant. measured by instantaneous '
condition exists effluent radiation release limits as hour or >8500 mR/hr (1.3 x 10 pci/sec) when:
monitoring and measured by -7 counting radiation for 2 minutes at the Q/U > 4.5 x 10 .
monitoring'and site boundary. where [
instrumentation.
counting instrumentation (Adverse Meteorology.) Q = release rate in ,
pei/sec (1) Noble Cases - (1) Noble Gases - U = mean wind speed 3
K (a) Main Chimney: (a) Main Chimney:
Unit 1 or Unit 2 in mph 4 Unit 1 or Unit 2 OR (not both) g ij
. (not both) Q/U > I.0 x 10 - y Release rage Release rgte where
?
> 2.1 x 10 pCi/sec > 21 x 10 pCi/sec Ey Ey Q = release rate in }
Both Units 1 and 2 pei/see p, Both Units I and 2 U = mean wind speed Release rage Release rgte ' in meters per second
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> 2.6 x 10 pCi/sec > 26 x 10 pCi/sec Ey ?
Ey - 4 (b) Reactor Bldg (b) Reactor Bldg Vent Stack: Vent Stack: [g Release rage Release rgte (
> 2.3 x 10 pCi/sec > 23 x 10 pCi/sec 1.3EY + Ep 1.3Ey + Ep t
where: Ey = average gamma energy per disintegration (MeV/ dis).
Ep = average beta energy per disintegration (MeV/ dis).
These quantities are determined monthly and are prominently posted in the Control Room.
z l APPROVED '
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', 9.1 QEP 200-T1 QUAD-CITIES EMERGENCY ACTION LEVELS Revision 6 -
CONDITION UNUSUAL EVENT ALERT ~ SITE EMERGENCY GENERAL EMERGENCY I Q
f:
Sununation of Summation of ;d release rat.e for release rate for Y halogens and halogens and '
particulates with particulates with half-lives > 8 daysy half-lives > 8 daysiO '
7.3Qv + 2.6Qc > 10 7.3Qv + 2.6Qc > 10 where: Qv = release rate from the reactor building vent stack in pCi/sec.
c Qc = release rate from the main '
, chimeny in pCi/ cec.
B. Liquid effluents B Liquid effluents: B. Liquid effluents: B. Liquid effluents:
concentration of: (1) Concentration of Estimated activity Estimated activity .
(1) Gross beta activity gross beta activity (above background) of liquid release of liquid relgase f:1 ,
in the discharge is > 2000 Ci but is > 2.4 x 10 cf. y in the discharge bay in excess of bay > 10 times the Technical Specifi-5 20,000 Ci. j the Technical cationLimgt Specification
_7 (> 1 x 10 pei/ml) -
limit (> 1 x 10 unless discharge is (p pei/ml) unless discharge is controlled on a radionuclide basis
((
controlled on a in accordance with g(
radionuclide basis Appendix B, Table II
, in accordance with Column 2 of 10 CFR Appendix B, Table II, 20 and note I thereto.
and note 1 thereto. (2) Estimated activity -
(i of liquid release i
> 40 Curies but "
5 2000 Curies. APPROVED AUG161982 ?l e,
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- QEP 200-Tl s QUAD-CITIES EMERGENCY ACTION LEVELS Revision 6 -
f 5
CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY g
- 18. Personnel Transportation of -
Injury radioactivity contami-nated injured person y to hospital. -
. t
- 19. Hazardous As a direct result of (1) Warrants Warrants a'ctivation .
Materials hazardous materials a precautionary of emergency centers .
person is killed or activation of the and monitoring teams, (,
hospitalized or TSC and placing or a precautionary '
e'stimated property the EOF and other notification to the damage exceeds $50,000. key. emergency public near the site.
personnel on standby.
(2) ARM readings (s) indicate a severe degradation in the control of radio-active material. p r
- 20. Any other Warrants increased Inuninent core melt.
conditions awareness on the !, '
l of equivalent part of the state magnitpde to and/or local off-site l
t the criteria officials. ji used to define ,
{e the accident as determined by APPROVED F Station Director * /
Other emergency conditions that require an emergency response are those involving: $Ub16l362 k
- a. Incident reporting per 10 CFR 50.72. l
- b. Ilazardous material incident reporting per P.A. 79-1442. Q.C.O.S.H f
- c. Oil discharges to waterways per the SPCC plan.
- d. f; Security contingency events per the Station Security Plan. . C r
i The Station Director may, at his discretion, categorize the above situations as GSEP emergencies, depending upon the (Refer to Section 9.3 of the generic plan for additional information.)
seriousness of the situation.
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Rtviaica 10
. August 1982
.ID/1S,,1T PROTECTIVE MEASURE FOR' ONSITE PERSONNEL 360-0 Protective Measures for Onsite Personnel Rev. 10 08-12-82 360-1 Drywell Evacuation Rev. 1 06-20-80 360-2 Plant Evacuation and Assembly Rev. 7 08-12-82 360-3 Site Evacuation Rev. 2 03-02-82 360-4 Use of Potassium Iodide (KI) as a Thyroid Blocking Agent Rev. 2 05-18-81 360-5 Issuance of Emergency Film During GSEP Conditions Rev. 1 05-18-81 360-S1 Emergency Film Distribution Log Rev. 1 05-18-81 360-T1 Evacuation Assembly Areas for Visitors and Contractors Rev. 2 03-02-82 360-T2 Evacuation Routes by Wind Direction Rev. 4 03-19-82 360-T3 '
Site Evacuation Routes Rev. 1 06-20-80 360-T4 Evacuation Relocation Centers Rev. 1 06-20-80 360-T5 -
Iodine - 131 Dose Equivalent to Thyroid Reference Reg. Guide 1.109 Rev. 1 04-01-81 360-T6 Iodine - 133 Dose Equivalent to Thyroid Reference Reg. Guide 1.109 Rev. 1 04-01-81 360-T7 Iodine - 135 Dose Equivalent to Thyroid Reference Reg. Guide 1.109 Rev. 1 04-01-81
. 360-T8 ---'
APPROVED Potassium Iodide Distribution Record Rev. 1 05-18-81 AUG 121982 (final)
l-;.
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Revision 7 ,
PLANT EVACUATION AND ASSEMBLY August 1982 ID/1L j A. PURPOSE l The purpose of this procedure is to describe Evacuation and_ Assembly practices.
B. REFERENCES
- 1. Refer to Quad Cities Security Procedures.
t
, 2. GSEP.
i 3. QEP 360-T1, Evacuation Assembly for Visitors and Contractors.
?
i 4. QEP 360-3, Site Evacuation.
I
~
C. PREREQUISITES
- 1. Radiation monitoring devices indicate that radiation from or within the station is such that permissible exposures will be exceeded; or
- 2. A Site or General Emergency is declared; or
- 3. Other dangers exist that present a threat to the safety of onsite j personnel as determined by the Station Director.
D. PRECAUTIONS
- 1. If it becomes necessary to evacuate the gatehouse due to a high radia-tion evacuation, refer to Quad Cities security procedure.
- 2. The units will be shutdown and all personnel, not essential to perform the emergency shutdown, immediately assemble at a safe location.
E. LIMITATIONS AND ACTIONS
- 1. None.
F. PROCEDURE
- 1. The evacuation alarm is sounded when the Station Director has determined that an evacuation is necessary.
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- 2. During a station evacuation, site personnel will assemble at the following locations:
- a. Maintenance personnel (Mechanical, Electrical, and Instrument) will assemble in the machine shop area.
l APPROVED l AUG 121982
, Q. C. O. S. H.
.; e v ra. m , gy. w ...c_ . + _ , .i. .n . > ,- we.n u:.vm e _ + &.%w ;-4ma;ww QEP 360-2 v .
s Revision 7
- b. Operators and Rad / Chem Technicians will assemble in the Operational Support Center (OSC).
- c. Contractors and off-site CECO personnel will assemble in the
! Turbine Building Trackway nearest their work area (either Unit 1 or 2) (see QEP 360-TI).
, d. The Station Director and Operations Director will report to the
[
Control Room. All other GSEP Directors will report to the Technical Support Center (TSC).
- e. Visitors and all other CECO Station assigned personnel will assemble in the lunchroom on the ground floor of the Service Building.
(See QEP 360-T1.)
- f. A security guard will contact a spokesman for the assembled group to determine if any personnel are unaccounted for. The security guard will contact the SAS , operator who will compile a list of unaccounted personnel. This list will be turned over to the Security Director, or Shif t Engineer in his absence, for disposition.
NOTE Normal clothing removal procedures shall be waived. Personnel wearing one layer of protective clothing shall remove only gloves .
and protective footwear when exiting from the radiation zone. Personnel wearing two layers of protective clothing, as required in highly contaminated areas, shall remove gloves , protective footwear and the outer layer of protective clothing. Hand and shoe counts and required personnel surveys should be omitted. Personnel exiting from radiation zones wearing protective clothing during an assembly should make every reasonable effort to avoid contaminating equipment, walls, floors, and other personnel.
- 3. Personnel will remain in these areas until the condition is corrected or instructed to move elsewhere.
- 4. If site evacuation is necessary, the Shift Engineer will designate the evacuation route and off-site assembly area, after consulting with the Technical Director, in accordance with QEP 360-3.
- a. If a site evacuation is required,. the names of non-essential . , , .
personnel will be provided to the Security Director.
APPROVED AU G 121982 Q.c. o. s. a.
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QEP 360-2 -
, .> Revision 7 -
- 5. Upon assembly at the relocation center, preplanned program of in-creased environmental sampling and a radiation survey of the environs are simultaneously initiated as required in the Generating Station Emergency Plan (GSEP). An estimate of the situation based on existing meteorological conditions, the results of the radiation survey, and the condition of the station is made. If, based on this estimate, it is determined that it is necessary to evacuate residents from the Low Population Zone, the GSEP Command Center Director notifies the Illinois ESDA and Iowa Office of Disaster Services in accordance with GSEP. The Station Director will also immediately notify the Rock Island County Communications Center (in Illinois) and the Scott County Sheriff's Office (in Iowa) if prompt off-site evacuation is needed.
- 6. The Rad / Chem Director will make provisions for monitoring personnel at the off-site relocation center, if needed.
G. CEECKLISTS l
l 1. None.
i H. TECHNICAL SPECIFICATION REFERENCES
- 1. None.
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APPROVED AUG121982 (final)
__ . -- , . --