ML20031F037

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Public Version of Revision 11 to Emergency Plan Implementing Procedure EPIP 200-TI, Classification of Generating Station Emergency Plan Conditions
ML20031F037
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 09/22/1981
From: Blackman L, Brunner E, Cusla T
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20031F029 List:
References
EPIP-200-TI, NUDOCS 8110190086
Download: ML20031F037 (18)


Text

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Commonw:al*b Edison x.

.C76 oresd2n Nuchtr Pousr Station

{"j R.R. di Morns. !!!!nois 60450 Telephone 815/942-2920

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  • ts, ~1 1 f 's. '(;

La ocr ',' ' Q) 1 Mr. Harold R. Denton, Director y,

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/A l' Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission

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  • WC4 ((

Washington, D.C.

20555 1)

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Subject:

Emergency Plan Implementing Procedures for Dresden Statiot Dhb Units 1, 2, and 3; NRC Docket Nos. 50-10, 50-237, and 50-249

References:

(a) D. J. Scott letter to H. R. Denton, dated March 12, 1981 (b) Title 10, Code of Federal Regulations, Appendix E, Part V

Dear Mr. Denton:

4-Enclosed are ten (10) copies of revisions to Dresden Station Emergency Plan Implementing Procedures.

No return of transmittals is necessary.

Sincerely, 7

(h D.

Scott Station Superintendent Dresden Nuclear Power Station "DJS:TGB:mt Enclosures cc:

T. Blackmon File /NRC File / Numerical QO 5t (0 i

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8 8110190086 811009 PDR ADOCK 05000010 F

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DAP 9-2 J DRE.Y0ENSTATIONPROCEDUREROUTING

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Revision 11 PROCEDURESCOORDINATORNOTiFIED

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DATE Index Numoer Unit /2/[

Procedure 88[ AO" O Revision No.

2 I

Title

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8-5~ 5~/

d Reg'd. Coop 1. Date Record Retention Requirements:

Action Item No.

1.

Is a Surveillance affected? #d (Submit DAP 11-2 pgs. 5 or 6)

Modification No.

2.

. Is a Station Record,Tj' pe_,beirg established?

  1. O Draft Review:

a.

If "yes", specify record Deletion?

Md retention requirements.

i Posted Procecure?

A/ g (as per Tech. Spec. Sec.

Posted Location?

N"O 6.5, ANSI N4S.2.9 App. A Typing Required?_

VES or DAP 2-3)-

. Index Change Requirec7 V54 b.

If "yes", obtain record type i

number -

-(see R3 Coordinator)

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J 78 Department Supery sor gech. Staff Supervisor 4

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Verifier

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Surveillance Coor nator /

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Procecures Manager

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TRANSMITTAL RECEIPT Regkter No.

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APPROVED W

REMOVE:

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g'p f, p 9 22'81 D.O.S.R*

I hereby acknowledge receipt of the above.

Signed Date (Sign and return this fann to the Procedures Manager.)

FORM 9-2A 18 of 24 '

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CAP 9-2 Revision 11 O

PROCEDURE HISTORY Procedure BPZf 200 - T/

Rev. no.

2 Description of Procedure Revision or of New Procedure (I) Nf

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APPROVEU SEP22 a; 19 of 24 g.O.S.R.

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r-CAP 9-2 SAFETY EVAll!ATION Revisicn 11 p

(10 CFR 50 53) v Dces this procecure/ revision ccnstitute a change to orecedures as described in Safety Analvsis F.ccort ?

Yes ( )

No Od e

4 l1s a change in ene Tecnnical i Soecification involved?

No ( )

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SAFETt EVALUATiCN: Answer the folicwing questions wien a "yes" cr "no", and provide specific reascns Justifying the decision:

1.

Is the probability of an occurrence, the consequence of an acci-dent, or malfunction of safety related equip:r.ent,-as previously evaluated in the Final Safety Analysis Report, increased?

[ No, because:

g g y.'

Yes 1% J 41 V'

2.

Is the possibility for an4cciden: or tr.al function of a di fieren:

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type than any previously evaluated in the Final Safety Analysis O

O Report created?

Yes No, because:

42, 3

Is the margin of safety, as defined in the basis for any Tech-nical Specification, reduced?

Yes No, because:

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Any Answer

  • Yes ( )

h Ali Answers No h l

I A4 quest anc receive.$tuclear Regulatory Cer:ctission

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APPROVED authorization for change.

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SEP22 '8)

Authorizaticn Received ( )

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  • NOTE:

l Initiate ?rocedure i

Any answer check 2d "yes" i

Imclementaticn sheutd be reported in the Performed 3y annual recert to the nic.

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Cate FO.'L'i 3-2C.

7 20 of 24 l;

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EPIP 200 - Emergency Conditions 200-T1 Classification of GSEP Conditions 4

(Primary Responsibility - Station Director)

Rev. 2 9/81 200-T2 Table of I-131 Equivalents For The Principal Iodine Isotopes On A Reactor Core Rev. 0 7/80 200-1 Declaration of GSEP Condition For Gaseous and Liquid Effluent Releases (Primary Responsibility - Operations Director)

Rev. 0 7/80 200-2 Classification of an Incident Involving Hazardous Material (Primary Responsibility -

Station Director)

Rev. 0 7/80 200-3 Criticality Accident in a Special Nuclear Material Area (Primary Responsibility -

Operations Director)

Rev. 0 7/80 200-4 Fire Fighting (Primary Responsibility - Operations Director)

Bev. 1 9/80 200-5 Security Threat (Primary Responsibility - Operations Director)

Rev. 0 7/80 200-6 Corrective Actions Following An Oil Spill (Primary Responsibility - Operations Director)

Rev. 0 7/80 200-7 Operation During Tornado or Sustained Wind Conditions (Primary Responsibility - Operations Director)

Rev. 0 7/80 200-8 Operation During Earthquake Conditions (Primary Responsibility - Operations Director)

Rev. 0 7/80 200-9 Dresden Dam Failure Rev. 0 7/80 (Piimary Responsibility - Operations Director) 200-10 Probable Maximum Flood of Unit 1 (Primary Responsibility - Operations Director)

Rev. 0 7/80 200-11 Probable Maximum Flood of Unit 2 ard 3 (Primary Responsibility - Operations Director)

Rev. O 6,30 200-12 Area High Radiation (Primary Responsibility - Operations Director)

Rev. 0 7/80 200-13 High Airborne Activity (Primary Responsibility - Operations Director)

Rev. 0 7/80 O

SEP 221981

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EPIP O

200 - Emergency Conditions (cont 'd) 200-14 High Radioactive Surface Contamination (Primary Responsibility - Operations Director)

Rev. 0 7/80 200-15 Emergency Procedure for Obstruction Lights (Primary Responsibility - Operations Director)

Rev. o 9/80 200-16 asusxD NUMBER _

200-17 UNUSED NUMBER 200-18 UNUSED NUMBER 200-19 Unit 1 Control Room Evacuation (Primary Responsibility - Operations Director)

Rev. O 9/80 200-20 Control Room Evacuation / Safe Shutdown Procedure (Primary Responsibility - Operations Director)

Rev. 0 7/80 O

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,1 SEP 221981 O

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O EPIP 200-TC t

Revision 2 September 1981 EPIP TABLE 200-T1 CLASSIFICATION OF GSEP CONDITIONS NOTES If a GSEP declaration is made refer to EPIP 100-C1 or EPIP 300-1 for GSEP rescenses.

It is the prerogative of the Station Director to upgrade the condition classification as he deems necessary.

AIRCRAFT CRASH Page 11 LOSS OF. FISSION PRODUCT BARRIERS Page 6 t

CONTROL ROOM EVACUATION Page 10 LOSS OF PLANT SYSTEMS Page 3 EARTHQUAKE Page 5 LOSS OF PRIMARY COOLANT Page 5 EXPLOSION Page 4 OTHER CONDITIONS Page 12 FIRE Page 4 PERSONNEL INJURY Page 2' FLOOD Page 11 RADI0 ACTIVITY EFFLUENT RELEASE Page 7 FUEL HANDLING ACCIDENT Page 5 SECURITY THREAT Page 11 HAZARD 0US MATERIAL Page 2 TORNADO OR SUSTAINED WINDS Page 10 LOSS OF AC POWER Page 3 TRANSPORTATION ACCIDENT Page 13 LOSS OF DC POWER Page 4

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Eele2000 R: vision 2 6

SITE GENERAL CONDITION UNUSUAL EVENT ALERT' EisERGENCY' EMERGENCY' t

Class Description.

Events in progress Events in progress Events in progress Events in progress or have occurred which or have occurred which or have occurred which or have occurred which indicate a potential involve an actual or involve actual or involve actual or degradation of the potential substantial likely major failures imminent substantial level of safety of degradation of the of plant functions core degradation or the plant, level of safety of needed for protection melting with potertial

]

the plant, of the public, for loss of cont in-ment integrity.

1)

Personnel Any serious injury

  • or Inju ry.

serious contamination

  • re-quiring transportation to a medical facility.
2) Hazardous Dr.e of the following:

Uncontrolled release of lJncontrolled release of Material.

(1) Uncontrolled release toxic gas at life threaten-toxic gas at life threaten-of toxic gas at life ing levels within the ing levels within the vital threatening levels protected area.

areas.**

near or on site.

(2) Uncontrolled situat-ion involving a substance or material in a quantity and fonn which may pose an unreasonable risk to health and safety or property.

  • Serious injury is an injury that requires admission to a hospital for treatment or observation for a period of more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Serious contamination requires medical treatment for skin tissue removal or involves internal contamination -

it is more than the scrubbing of skin or shaving of hair.

    • Vital areas are: U-1 Sphere, U-1 Turbine Bldg., U-2/3 Reactor Bldg., U-2/3 Turbine Bldg., Control Room, U-1 Cribhouse, U-2/3 Cribhouse, Control Alann Station (CAS), Secondary Alarm Station (SAS), U-1 Fuel Building.

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CONDITION UNUSUAL EVENT' ALERT

' EMERGENCY

' EMERGENCY'~

4

3) Loss of Plant Equipment described in One of the following:

Equipment is degraded Systems.

the Technical Specifica-(1) Equipment is degraded such that neither a Cold tions is degraded such such that a Cold Shut-Shutdown *** condition nor that a Limiting Condition down*** condition can-a Hot Shutdown *** condition for Operation requires not be achieved or can be achieved or main-6 a shutdown.

maintained.

tained; and Safety Limits ***

(2) Technical Specifica-may or will be exceeded.

tions Safety Limit ***

exceeded.

(3) Failure of the Reactor Protection System Instrumentation to initiate and complete a SCRAM which brings the Reactor subcritical once a limiting safety system setting as specified in the Tech-nical Specifications has been exceeded.

4) Loss of AC AC power sources as AC power sources are One of the following:

Power.

described in the Technical degraded such that a (1) AC power sources Specifications are de-Cold Shutdown *** con-are degraded such graded such that a dition cannot be achieved that neither a Cold Limiting Condition for or maintained.

Shutdown *** condi-Operation requires a

. tion nor a Hot Shut-shu tdown.

down*** condition can be achieved or main-M tained; and Safety

,0 $

Limits *** may or will l

ON x be exceeded.

in N O (2) Loss of all AC power N cd <

to Unit 2 or 3 for A

greater than 15 O

minutes.

      • Cold Shutdown Hot Shutdown and Safety Limits are defined by the Technical Specifications.

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5) Loss of DC DC power sources as DC power sources are One of the following:

~

eower.

described in the Technical degraded such that a (1) DC power sources Specifications are de-Cold Shutdown *** con-are degraded such graded such that a dition cannot be achieved that neither a Cold Limiting Condition for or maintained.

Shutdown *** condi-Operation requires a tion nur a Hot Shut-shutdown.

down*** condition can

)

be achieved or main-tained; and Safety 1

Limits *** may or will i

be exceeded.

(2) Loss of all DC power to Unit 2 or 3 for greater than 15 minutes.

6) Fire.

One of the following:

Equipment is degraded Equipnent is degraded such (1) Requiring off-site such that a Cold Shut-that neither a Cold Shut-assistance, down*** condition cannot down*** condition nor a Hot (2) Equipment described in be achieved or main-Shutdown *** condition can be the Technical Specifi-tained.

achieved or maintained; cations is degraded and Safety Limits *** may such that a Limiting or will be exceeded.

Condition for Operation requires a shutdown.

7) Explosion One of the following:

Equipment is degraded Equipnent is degraded such causing damage. (1) Requiring off-site such that a Cold Shut-that neither a Cold Shut-assistance.

down*** condition cannot down*** condition nor a (2) Equipment described in be achieved or main-llot Shutdown *** condition the Technical Specifi-tained.

can be achieved or main-cations is degraded tained; and Safety Limits ***

such that a Limiting may or will be exceeded.

Condition for Operation requires a shutdown.

      • Cold Shutdown, Hot Shutdown and Safety Limits are defined by the Technical Specifications.

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' ALERT EMERGENCY'

' EMERGENCY'

8) Earthquake has Equipment described in Equipnent is degraded Equipment is degraded such occurred or the Technical Specifica-such that a Cold Shut-that neither a Cold Shut-

~

is being tions is degraded such down*** condition cannot down*** condition nor a Hot experienced, that a Limiting Condition be achieved or main-Shutdown *** condition can be for Operation requires a tained.

achieved or maintained; shu tdown, and Safety Limits *** may or will be exceeded.

l 9)

Fuel Handling Standby Gas Treatment Standby Gas Treatment Accident.

System operational and System not operational or (Fuel Handlers Secondary Containment Secondary Containment report damage Isolation effective Isolation incapable to irradiated or capable of being of being effected within fuel assemblies effected within 15 15 minutes, and Refuel Floor minutes.

ARM reads > 100 mR/hr).

10) Loss of Primary (1) ECCS initiation (not A > 50 gpn-leakage rate (1) A > 100 gpm leakage Imminent core melt.

Coolant.

spurious).

increase in'an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rate increase in an (2) Failure of a Primary period as indicated by 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period as indi-System Safety or surveillance.

cated by surveillance.

l Re','ef Valve to close.

(2) A Main Steam Line (3) Total leakage rate to break outside contain-Primary Containment is ment without the capa-W greater than Technical bility of effecting Specifications Limiting isolation.

Condition for Operation.

      • Cold Shutdown, Hot Shutdown and Safety Limits are defined by the Technical Specifications.

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EPIP200-T[]

Revision 2 5ITE GENERAL CONDITION UNUSUAL EVENT ALERT EMERGENCY'

' EMERGENCY ~

11) Loss of (1) Loss of one of the (1) Loss of two of the (1) Loss of 2 of the Fission followinD Fission followinD Fission following 3 Fission -

Product Barriers.

Product Barriers.

Product Barriers.

Product Barriers (a) Cladding.

(a) Cladding.

with imminent loss Grab sample activity Grab sample of the third equivalent to activity equival-Fission Product

& 300 pCi/ml of ent to > 300 Barrier.

I-131.

pCi/ml of I-12.

(a) Cladding.

(b) Reactor Coolant (b)

Reactor Coolant Grab sample System.

System.

activity

> +2 psig drywell

>, +2 psig drywell equivalent to pressure and/or (-59 pressure and/or4-59

> 300 pCi/ml inches vessel level inches vessel level of I-131..

during other than during other than (b) Reactor Coolant controlled evolutions.

controlled evolutions.

System.

(c)

Primary Containment.

(c)

Primary Containment.

> +2 ps ig dry-Containment pressure Containment pressure well pressure

> 62 psig and/or

>, 62 psig and/or and/or 4 -59 Containment tempera-Containment tempera-inches vessel ture > 281*F.

ture > 281*F.

level during other than controlled evolutions.

(c) Primary Con-tainment. Con-tainment press-ure >,62 psig and/or Con-tainment temperature

> 281 F.

cn

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"U 2

2 3

(2) > 2 x 10 R/hr (2) >, 4 x 10 R/hr (2) > 2 x 10 R/hr

.O y Z but but Primary Containment 2

3 P

< 4 x 10 R/hr

<.2 x 10 R/hr activity.

g

  • U "

rn Primary Containment Primary Containment g

O activity.

activity.

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EPIP200-Th

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' EMERGENCY' I

12) Radioactivity Effluent Release fraa the plant.

A. Noble gas releases.

1. Unit 1 Chimney. Gaseous effluent instant-Unit 1 is currently See Alert.

See Alert.

aneous release rate undergoing an extensive exceeds Technical modification and Specifications Limits decontamination outage.

as measured by Wide Range Noble Gas Radiation Monitoring Monitoring Instrumen-Instrumentation:

tation will be installed Release cate and Emergency Action

> 5.6 x 10s C1/sec Levels will be defined, p

or prior to unit start-up.

Monitor off scale due to a noble gas release.

2. Unit 2/3 Chimney.****

Gaseous effluent Gaseous effluent Gaseous effluent Gaseous effluent instantaneous release instantaneous release release as monitored release as monitored rate exceeds Technical rate > 10 times the by Radiation Detection by Radiation Detection Specifications Lt. nits Technical Specifications Instrumentation Instrumentation as measured by Limits as measured corresponds to corresponds to Radiation Monitoring by Radiation Monitor-

>,50 mR/hr for h

> 1 Rem /hr whole Instrumentation:

ing Instrumentation:

hour or ;,r 500 mR/hr body at the site

        • High Range Noble Gas Monitoring Instrumentation capable of monitoring and providing control room indication of the release rates corresponding to the Alert, Site Emergency and General Emergency categories will be installed by 1/1/82. Release rate detenninatior.s in the interim period will be detennined procedurally by local monitoring of effluent sample line exposure rates and conversion of results to gaseous effluent release rates.

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EMERGENCY'

' EMERGENCY ~

12) (cont'd) g

)

Unit 2 or Unit 3 Unit 2 or Unit 3 whole body for 2 boundary (actual only (not both) only(notboth) minutes at the meteorology).

site boundary for This condition Effluent release Effluent release adverse meteorology.

exists when rate > 7.0 x 105 7

rate 4 7.0 x 106 Q/p 3 4.5 x 10 pCi/sec pC1/sec Effluent release rate where 7

Both Units 2 and Both Units 2 and

>,1.3 x 10 pCi/sec Q = release 3 operating 3 operating for ><30 minutes rate in pCi/sec Release rate Release rate or p = mean wind

> 9.0 x 105

><9.0 x 106 Release rate speed in mph l

8 l

pCi/sec pCi/sec

>1.3 x 10 pCi/sec or j

for 12 minutes.

Q/p > 1 x 108 where l

Q = release rate l

in pC1/sec p = mean wind speed in meters /sec.

3.

Unit 2/3 Reactor Gaseous effluent Gaseous effluent Building Vent-release yields a release yields a 11ation Stack.*****

monitor off-scale monitor off-scale high response as high response as indicated by indicated by recorder, with recorder, with Standby Gas Standby Gas Og]

Treatment System Treatment System

  • oy m operational and not operational l

yN o Secondary Contain-or Secondary ment Isolation Containment

.N e6 rr1 capable of being Isolation not O.

effected within capable of 15 minutes.

being effected (cont'd) within 15 minutes.

w**** Reactor Building Ventilation System automatically isolates at release rates more conservative than unusual event levels (4 9.0 x 104 pC1/sec). Reactor Building is then vented through the Standby Gas Treatment System to the Dait 2/3 Chimney.

However High Range Noble Gas Monitoring Iritrumentation will be installed on the Unit 2/3 Reactor Building Ventilation Stack prior to 1/1/82.

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12) (cont'd)

B. Particulate and I

iodine releases.

]

1. Unit 1 Chimney.

Sunnation of release Summation of release rates for halogens rates fa. halogens and particulates and particulates with hcif lives with half lives greater than 8 days greater than 8 days

> 2.4 pC1/sec.

>,,,24 pCi/sec.

2. Unit 2/3 Chimney. U'it 2 or Unit 3 only Unit 2 or Unit 3 only I at both)

(not both)

Sunnation of release Sunnation of release l

rates for halogens rates for halogens I

and particulates and particulates with half lives with half lives greater than 8 days greater than 8 days

> 3.5 pCi/sec.

7 35 pCi/sec.

Both Units 2 and 3 Both Units 2 and 3 operating operating Release rate Release rate l

7 4.3 pCi/sec.

> 43 pCi/sec.

3. Unit 2/3 Reactor Summation of release Summation of release Building rates for halogens rates for halogens Ventilation and particulates and particulates Stack.

with half lives with half lives greater than 8 days greater than 8 days

> 0.12 pC1/sec.

>,1.2 pC1/.sec.

l l

C.

Liquid effluents.

(cont'd) l

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12) (cont'd)

All Units Concentration of gross Concentration of gross Estimated activity Estimated activity (1, 2 and 3) beta activity in dis-beta activity in dis-of liquid release of liquid release charge canal (above charge canal (above

> 2,000 Ci but

>,20,000 Cf.

background) in excess background) in excess

<20,000 C1.

of the Technical of 10 times the Specifications Limits Technical Specifications i

(> 1 x 10 7pC1/ml) unless Limits (4 1 x 10 6pCi/ml) discharge is controlled unless discharge is con-on a radionuclide basis trolled on a radionuclide in accordance with basis in accordance with Appendix D, Table II, Appendix B. Table II, Column 2 of 10 CFR Column 2 of 10 CFR 20 and note 1 thereto.

20 'and note 1 thereto.

or Estimated activity of a liquid release

> 40 Ci but

< 2,000 C1.

i

13) Control Room Evacuation is anticipated Evacuation is required Evacuation, or required with control and control is not established from local esti.blished from local stations.

stations within 15 min.

14) Tornado or Tornado within sighting One of the following:

One of the following:

severe winds distance (5 5 miles) of (1) Tornado strikes or (1) Tornado strikes or being exper-the facility, crosses within the crosses vital areas of ienced.

(1) Control Room protected area.

facili ty, informed by (2) Sustained Winds of (2) Sustained Winds of Load Dispatcher; or

> 100 mph.

(100 mph

>f 110 mph as confimed (2) Control Room is max. metro tower by Weather Bureau.

.2>

infomed by capability.)

C g O O

Station personnel

+

&-)

who have made m g yN O visual sighting; or N" e6 <

(3) Shift Supervisor l

rn infomed by Weather O

Alert.

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EPIP 200-TJ V

,h, R:visienh-O SITE GENERAL CONDITION UNUSUAL EVEN1 ALERT' ENERGENCY EMERGENCY'

15) Flood.

(1) Rupture of cooling Illinois River Level >,508' Illinois River Level

  • 510' pond dike affecting (based on Unit 1 Cribhouse (based on 100 year flood levels off-site property, elevation 508'6").

of elevation 510'6").

(2) Flood occurring or projected.

l

16) Aircraft Crash Impacted on site but Impacted within the pro-Impacted within the pro-or missiles outside the protected tected area but not tected area and affecting from whatever area.

affecting vital areas.**

vital areas.**

j sou rce.

l

17) Security The following events Security Threat Imminent loss of physical Loss of physical
Threat, as described in the of increasing control of facility.

control of fa.:1lity.

For other Security Plan:

severity that security events (1) Obvious attempt persists for more see Item 18.

to sabotage.

than 60 minutes.

(2) Internal disturbance (disturbance which is not short lived or is not a hannless outburst involving one or more individuals within the protected area).

(3) Bomb device discovered.

(4)llostage.

(5) Civil disturbance i

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,C (spontaneous collec-a tive group gathering l

l 2n N O which disrupts normal g "cx5 g operations.)

rn (6) Armed or forced pro-U tected area in~ trusion.

(7) Armed or forced, vital l

area intrusion ~**

    • Vital areas are:

U-1 Sphere U-l Turbine fldg., U-2/3 Reactor Bldg., U-2/3 Turbine Bldg., Control Room, U-l Cribhouse, U-2/3 Cribhouse, Control Alann Station (CAS), Secondary Alarm Station (SAS), U-1 Fuel Building.

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/ -

I CONDITION UNUSUAL EVENT -,.

ALERT EMEMENCY EMERGEllCY'

18) Any other con-Warrants increased aware-The following are ex-

~~

Imr:fIIent ccrs 7

ditions of ness on the part. of the amplbs of conditions melt '

equivalent State and/or Local off-that may or may not magnitude to site officials.

warrant classification v

/[

the criteria The following are examples as an Alert under GSEP.

1 e

v-used to define of cor,ditions that may or

'1) Criticality acci-f

~

l the' accident may not warrant classift-dent in a Special

~

category as cation as an Unusual Nuclear Materials f

aetennined by Event under GSEP.

area.

~

the Station (1) Conditions requir-(2) Control rod drop

/

~

~

Director.

,ing Illinois occurs with reactor 4 /'

Department of power less than. 20%

e C-

"Public Health as indicated by j-l Notification per APRM's.

Section D.403 -

(3) Fuel pool level,

/

of the Rulbs and approaches or de-

/

Regulationi for creases below the Protection Against Technical Specifi-Radiation [see cations Limit.

Section B of

'/;

Notifications l

and GSEP

~~

Response

procedure (EPIP300-1)].

(2) Oil Spill.

3>

(3) Bomb Threat.

T (4)AttackThreat.

m IW T (5) Extortion (a O%O message is re-p 4.

ceived which

%g tr) directly states s

O that unless de-mands are followed adverse action will be taken).

(cont'd) 12 of 13 J

EPIP 200-T Revision 2 SITE GRERAL CONDITION UNUSU4L EVENT ALERT" EMERGENCY' IMERGENCY'

18) (cont'd)

(6) Loss of Guard Force (e.g. strike).

(7) Security Communica-tions Failure.

(8) Conditions requiring NRC Notification per 10 CFR 50.72.

[RefertoSectionB.2 3

and B.4 of Initial Noti-l fications and GSEP Response procedure (EPIP300-1)].

Transpertation Accident A.

A vehicle transporting radioactive materials or 'on-radioacti'?e Hazardous materials to or from a Car.monwealth Edison generating station is involved in a situation in which:

1.

Fire, breakage or suspected radioactive contamination occurs involving a shipment of radioactive material or;

(

2.

As a direct result of flazardous materials, (a) A person is killed; or (b) A perscn receives in.i,uries requiring hospitalization; or (c)

Estimated carrier or other property damage exceeds $50,000.

B.

Any other condition involving Hazardous material transportation and equivalent to the criteria in Item A.

.C h o

o~o y) N O

? Ih 13 of 13 (FINAL) 0

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