ML20072G794

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 5.7.2 Re Notification of Unusual event,5.7.3 Re Alert & 5.7.12 Reemergency Radiation Exposure Control

ML20072G794
Person / Time
Site:	Cooper
Issue date:	02/21/1983
From:	Lessor L, Sayer J, Whitman D NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20072G776	List: ML20072G785 ML20072G794
References
PROC-830221-01, NUDOCS 8303290137
Download: ML20072G794 (58)

Text

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COOPER NUCLEAR STATION OPERATIONS MANUAL EtERCENCY PLAN IMPLEMENTIWC PROCEDURE 5.7.1 CNS EMERGENCY PLAN IMPLEMENTATION I. PURPOSE The purpose of this procedure is to provide a means of classifying an event at CNS into one of four emergency classifications as described in the CNS Energency Plan.

II. DISCUSSION A. Introduction To Modular Concept.

1. Basic module,

a. Four classes of Emergency Action Levels have been established.

The classes are:

1) NOTIFICATION OF UNUSUAL EVGT.

2) ALERT.

3) SITE AREA EMERGENCY.

4) GENERAL EMERGENCY.

b. The rationale for these classes is to provide early and prompt notification of minor events (the BASIC MODULE EVENTS) which could lead to more serious consequences or which might be j

indicative of more serious conditions which are not yet fully realized. A system of modules has been provided to ensure more effective response preparation for more serious indicators.

c. There arc four basic modules which depict the four major types i

of events?

1) Radiological.

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2) Operational.

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3) Fire-Natural-Security.

i 4) Miscellaneous.

, d. The basic modules are subdivided into 13 submodules that are abnormal conditions considered to be those initiating events upon which all emergencies categorized within the Emergency i Action Levels are based. .

l i 8303290137 830317 PDR ADOCK 05000298 F PDR Revised By/Date Reviewed By/Date Approved By/Date Rev. Procedure Page 1 Of D. Whitnan 2/7/83 J. Sayer 2/18/83 3-2( U 2 5.7.1 5 Pages I

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e. Prompt recognition of the occurrence of one or more of these initiating events of the Basic Module may prevent the situation from progressing to either a NOTIFICATION OF UNUSUAL EVENT category or.an Action Level of greater severity.

f. The 13 submodule events are:

1) Release of radiological liquid or gaseous effluent in excess of the Technical Specification limits or abnormal radiation levels.

2) Indications leading to or actual loss of fission product barrier.

3) Steam line break or main steam safety or relief valve failure.

4) Primary reactor coolant leak.

5) Loss of power or alarms.

6) Other limiting conditions for operations.

7) Reactor protection system failure.

8) Fuel handling accident.

9) Control Room evacuation.

10) Fire.

11) Security threat.

12) Natural phenomena. -

13) Other hazards.

g. As can be seen from Attachment "A", an emergency (initiating condition) may progress to a particular Emergency Action Level as a result of a combination of one or more of the submodule events. In most instances, these elements of the submodule will advance to the category of a NOTIFICATION OF UNUSUAL EVENT and, with continued degradation, could escalate to the more severe cir.sses of ALERT, SITE AREA EMERGENCY, or GENERAL E!!ERGENCY.

h. The question may arise as to what is meant by a modularized system of the Emergency Action Levels. As shown in Attachment "A", each of the four classes of the Emergency Action Levels is indicative of nine or more sets of initiating conditions.

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1 Procedure M .or FPTP ".7.1

. nua D r ~ 4 - 4 ~- ? o-~ ' " 5 n-

s The events within each class are either identical to or ate slight modifications of those that exist in Chapter 4 of the CNS Emergency Plan. What the modularized system denotes is a graphic reproduction of Tables 4.1-1 through 4.1-4, in an easy-to-read and understand, readily available flow chart format. This modular format yields three important advantages

1) It affords prompt recognition of the severity of emergency conditions and assists in the timely classification of those conditions into one of the four Emergency Action Levels. ,

2) Prompt recognition leads to prompt action in terms of initial notification, activation of on-site emergency response facilities, and off-site agency response.

3) It enables the reactor operations personnel to effectively move through the emergency procedures and into the EPIPs.

i. The utilization of the modular approach in assessing a radio-logical accident, affords greater probability of responding to a potentially hazardous occurrence in a more timely manner, and time is a critical factor in dealing with all emergency situa-tions.

III. REFERENCE MATERIAL

(

A. Cooper Nuclear Station Emergency Plan.

B. NUREG-0654 Revision 1.

IV. PREREOUISITES A. An Emergency Operation Procedure has been initiated. .

B. An unusual occurrence has taken place at or near the site.

V. LIMITATIONS A. The steps required by this procedure are in addition to the steps required to maintain or restore the station to a safe condition.

B. If conflicts in personnel assignments, or sequence of actions arise, first priority will be given to maintaining or restoring the station to a safe condition.

VI. PRECAUTIONS A. None. ,

VII. EQUIP."ENT A. None.

Procedurc Nenber FPTP 5.7.1 Date Revisicn 2 Page 3 Of 5 P.v:e "

,- e VII

I. PROCEDURE

A. Classification.

1. The Shift Supervisor / Emergency Director selects affected submodules on Classification Checklist (Attachment "B") related to station events or conditions and records the date and time of initial classification.

2. For all submodules selected on Attachment "B"; the Shift Supervisor /-

Emergency Director is to refer to the Classification Guide (Attach-ment "C") and review initiating conditions for emergency classifi-cation.

3. The Shift Supervisor / Emergency Director records the emergency classification.

4. The Accident Classification Flow Chart (Attachment "A") is a tool designed to assist selecting the appropriate portion of the Classi-fication Guide (Attachment "C"). The Accident Classification Guide Flow Chart indicates graphically, for certain combinations of station conditions, which basic module in the guide contains the initiative conditions, EALs, and classification levels.

a. In the Submodule column are listed 13 abnormal conditions that are considered to be those initiating events upon which all emergencies are based. By following a vertical path down this column to the applicable condition and then horizontally across the sheet to the actual event, the Shif t Supervisor / Emergency Director can promptly recognize an emergency classification.

5. The Shift Supervisor / Emergency Director initiates the appropriate EPIP as follows:

a. NOTIFICATION OF UNUSUAL EVENT - EPIP 5.7.2.

b. ALERT - EPIP 5.7.3.

c. SITE AREA EMERGENCY - EPIP 5.7.4.

d. GENERAL EMERGENCY - EPIP 5.7.5.

B. Reclassification.

1. An emergency may escalace to a higher classification as station conditions worsen or additional abnormal station conditions arise.

This could also happen as a result of a combination of two or more of the submodule events.

l 2. An emergency may be initially class'ified at one level and, upon l further investigation or after corrective actions, may be de-esca-lated / reclassified to a less severe class of emergency.

I Prncedure Norber ._EPTP 5.7.1 Date '!\ Revisinn 2 Pace 4 of 5 Eace l

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3. Compare station conditions against the Emergency Action Levels in Attachment "C" and as conditions change re-evaluate the classifi-cation as in Section A; reclassify the event as necessary.

4. Record all emergency classifications and date/ time on Attachment "B".

IX. ATTACHMENTS A. Attachment "A", Accident Classification Guide Flow Chart.

B. Attachment "B", Classification Checklist.

C. Attachment "C", Classification Guide.

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i COOPER NUCLEAR STATION OPERATIONS MANUAL ATT ACliMENT "B" IMRCENCY H.AN IMP!I!!ET. TING PROCEDURE 5.7.1 CNS EMERCENCY PLAN IMPLEMENTATION C1.ASSIFICATION CilECKl.IST INITIAL SUBSEQUENT SUBSEQUENT SUBSEQUENT nertn TO CI ASSIFICATION CLASSIFICATION CLASSIFICATION CLASSIFICATION ATTACHMENT "C" SUBMODUI.E DATE/ TIME DATE/ TIME DATE/ TIME DATE/T1HE PACE (S)

1. Release of radiological liquid or gaseous effluent in excess of Technical Specification limits or abnormal radiation levels. 1, 2

2. Indications leading to or actual loss of a fission product tiarrier. 2,3,4

3. Steam line break or safety or relief valve failure. , _ _ , 4, 5

4. Primary reactor coolant leak. 6,7,8

5. Loss of power or alarms. 8, 9

6. Other limiting conditions for operation. 10, 11

7. Reactor protdction system failure. 11

8. Fuel' handling accident. 12

9. Control Room evacuation. 12, 13

10. Fire. 13

11. Security threat. 13

12. Natural phenomena. 14

13. Other hazards. 15, 16 i

1 Procedure fiumber EPIP 5.7.1 Date  ! I' Revision 2 Page 1 Of 1 ' Pages

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C00PER NUCLEAR STATION OPERATIONS MANUAL II*fACM1ENT "C" PfERGFNCY PLAN It!PID!ENTING PROCEDl'RE 5.7.1 CNS EMERCENCY PLAN IMPI.EMENTATION h

CLASSIFICATION CUIDE StTKOULE INITIATING CONDITIONS EMERCENCY ACTION 1.EVELS EMERCENCY CLASS

1. (Continued) 1.5 Effluent monitors detect levels 1.5.1 Determined by Reactor, Turbine, Rad- CENERAL corresponding to 1 rea/ hour whole waste, and AOC Buildings, Elevated EMERCENCY body (or 5 res/ hour thyroid) at Release Point radiation monitor the site boundary under actual readings, and Control Roca calibra-meteorological conditions. These Lion curves to determine release dose rates are projected based on rates. Dose rate projections per other parameters (e.g. radiation EPIP 5.7.17 or measured dose rates levels in containment with leak by field monitoring teams, rate appropriate for existing containment pressure with some a confirmation from effluent moni-tors) or are measured in the environs.

2. Indications Icading to or actual 2.1 Fuel damage indications. 2.1.1 High off gas at steam Jet air NOTIFICATION OF loss of a fission product barrier, ejector monitors in excess of 5 x UNUSUAL EVENT 10 (5) uCi/sec. or an increase of 10 (5) uC1/sec within a 30-minute period. Determined by observing i Panel 9-10 monitors RMP-RM-150A &

B, Panel 9-2 recorder and annun-clators on Panel 9-4, and through

• use of calibration curves posted in Control Room.

2.1.2 Coolant sample activity exceeds 3.1 uC1/gm dose equivalent 1-131.

2.2 Abnormal coolant parameters ex- 2.2.1 a) Determined by core thermal NOTIFICATION OF ceeding Technical Specification analysis. . UNUSUAL EVENT limits, b) Reactor vesscl dom pressure

, a) Coolant temperature. shall not exceed 1337 psig at i b) Coolant pressure. any time when irradiated fuel c) Fuel temperature. .is present in the vessel on 75 psig any time when operating the RHR pumps in the shutdown cooling mode. Indicated on Panel 9-5 RFC-PI-90A, B, C, or RFC-LR/PR-97 or 98.

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Procedure Number EPIP 5.7.1 Date .") Revision f Page 2 Of 16 Pages .

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o COOPER NUCLEAR STATION OPERATIONS MANUAL ,

ITTXCIiMEt.T "C" FMERf fNCY P!AN IMPt.EMENTING PROCFDi'RE 5.7.1 CNS DIERCENCY PIAN IMPLEME!!TATION h

CLASSIFICATION CUIDE SUEM0DULE INITIATING CONDITIONS EMERCENCY ACTION LEVELS EMERCFECY C1. ASS

2. (Continued) 2.6 (Continued) 2.6.1 b) Primary coolant boundary.

1) liigh drywell pressure.

2) Low vessel level.

3) ECCS initiation.

4) Reactor scram.

5) Containment activity, sump level humidity, and temper-ature increasing, c) Containment integrity. ,

1) Inability to isolate primary containment.

2) Suppression pool water volume 7 cannot be maintained between 87,650 cu ft .and 91,000 cu fe or temperature cannot be main-tained below 90*F or 95'F for periods not ,to exceed 45 days wherever river water temperature is such that 90*F cannot be maintained. Temperature and volume displayed on CR-VBD-J.

3) Unable to maintain drywell to suppression chamber differ- ,

ential pressure.

4) Loss of contairvient struc-tural integrity.

5) Containment pressure ex-ceeding design.

3. Steam line break or safety or 3.1 Failure of a safety or relief 3.1.1 Failure of blue Indicating lights NOTIFICATION OF (Panel 9-3) to illusinate after relief valve failure. valve in a safety-related system llNUSl'A1. EVENT to close following a reduction safety relief valve (s) closes and of applicable pressure, suppression chamber temperature continues to increase as noted on Control Room Panel 9-21 recorder, ADS-TR-166.

i 3.2 Main steam line break in primary 3.2.1 Indication may include: ALERT containment with MSIV or other a) High drywell pressure.

valve malfunction causing leakage b) 14w vessel level.

to secondary containment. c) ECCS initiation.

d) Reactor scram.

e) High Reactor Building activity.

(ARMS, CAMS, or ventilation monitors).

Procedure Number EPIP 5.7.1 Date U ' . I N $ Revision 2 Page 4 Cf 16 Pages !

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COOPER NUCLEAR STATION OPERATIONS MANUAL ATTACICIU;I "C" T!'ERCE!;CY PIAf; IMPLDtlf; Tit;C PROCElokE

• 5.7.1 CNS EMERCENCY PLAN 4MPLEMENTATION h

Cl SSIFICATION CUIDE /

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INITIATING CONDITIONS ,,

EMERCENCY Af' lion LEVELS EMERCENCY CLASS

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3. (Continued) 3.2 L> atinued) '

f 3.2.1 f) Containment sump level, humidity, and temperature increases.

g) Failure to isolace containment.

( , , 1) Observe cont'airent Asolation 7h 4 ,

' ,- mimic on Control R Panel 9-3 /

b i 3.1 ' Hain ste-tm line break outside 3.3.1 Indications may include  ! SITE AREA /"

> / icontaireent without isolation. a) Low vessel level. , EMERCENCt

/ b) ECCS initiation.

", c) Reactor scram. . ,-

. > d) Failure of HSIVs to isolate as ,#

',  ;, evidenced by mimic display on 1

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Control Room Psael 9-3.

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< e) liigh Reactor /Torbine Building i g' d

activity levels (ARHs, CAHs, e ,

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,- f) High temperature alarms on area , . ( ,j-t

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temperature monitoring system.

g) Steam line high flow indication."7

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.< j 3.4 Small or large treak'14CAs, 3.4.1 Indicatione are:

CENERAL /(

accompanied by failure of ECCS a) High drywell pressure. ENERGi.NCY -

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to perf4rm,, leading to severe b) Low vessel level, f1

1. , c ' core degradation or melt in from c) Lack of ECCS initiation.

/- minutes to hours. Breach of d) Containment activity, sump containment likely. level humidity, and temperature ,

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/ increase.

e) Reactor scram.

/ f) Area temperature monitor increases. ,

g) High eff gas at steam jet air ji,

- ejector monitors greater than 5

/ C1/sec.

< h) Primary coolant sample indicates

, activity levels exceeding 310 g ( , uCi/ge.

> () Containmer t unisolable. .

j , j) Suppressioin poo) vater volume can-(<

not be mairtsined between 87,650 c2 f t and 91,000 cu ft or temper-j

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,atore ceinno be maint.ilned below an*F or 95'T for peptods not to -

.. ' ' , ,! exceed 45 days whenever river water

/' (, , temperatur4 is such that 90*F cannot be maintained. Temperature 4f* t , / and volume displayed on CR-VBD-J.

r. - k) Containment. pressure exceeding design.

Procedure Number EPIP 5.7.1 Date .J-DI' Revisinn 1 Page 5 Of 16 Pages

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i COOPER NUCLEAR STATION OPERATIONS MANUAL d ATI ACE ElsT "C" .

EMFRCLNCY PLA*! DIPLFMENTINC PRCCEDlSE 5.7.1 CNS EHERGENCY PLAN IMPLEMENTATION d

CLASSIFICATION CUIDE SlVDDULE INITIATING CONDITIONS EMERCENCY ACTION 1.EVELS EMERCENCY CLASS

3. (Continued) 3.5 Small or large break LOCA occurs 3.5.1 Indications are: CENERAL and containment performance is a) High drywell pressure. EMERCENCY unsuccessful, affecting longer b) Low vessel level.

' term success of the ECCS. Could c) Lack of EEC initiation.

lead to core degradation or melt d) Containment activity, sump in several hours without benefit level, humidity, and temper-of containment boundary, ature increase.

e) Reactor scram.

f) Area temperature monitor in-

. creases. .

) g) High off gas at steam jet air ejector monitors greater than 5 C1/ge.

h) Primary coolant sample indicates activity levels exceeding 310 uCf/ge.

1) Containment unisolable, j) Suppression pool water volume cannot be maintained between 87,650 cu ft and 91,000 cu ft or temperature cannot be main-tained below 90*F or 95*F for periods not to exceed 45 days whenever river water temperature is such that 90*F cannot be maintained. Temperature and volume displayed on CR-VBD-J, k) Containment pressure exceeding design.

4. Primary leak. 4.1 Primary leak rate Technical. 4.1.1 Li'it of 5 gpa unidentified flow, NOTIFICATION OF Specification exceeded. 25 gpa identified flow with no UNUSUAL EVENT .

capability to isolate and shut down required. Indicated by drywell floor and equipment sump integrator located on Control Room Panel 9-19 and annunciated on Panel-9-4 4.2 Primary leak rate Technical 4.2.1 Unidentified leak greater than 50 ALERT Specification exceeded. gpm as indicated by drywell floor -

and equipment sump integrators located on Control Room Panel 9-19 and annunciated on Panel 9-4 l'rocedure Number EPIP 5.7.1 Date '. ) ~ 2) I ' ^

• Revision 2 Page 6 Of 16 Pages .

s COOPER NUCLEAR STATION OPERATIONS MANUAL e Tl'IALW C T "C" EMERCit:CY PL AN IWlD*ENTING PROCEDURE 5.7.1 CNS EMtHCENCY Pt.AN IMPLEMENTATION h

CLASSIFICATION CUIDE SUBNODULE INITyTINCCONDITIONS EMERCENCY ACTION LEVELS EMERCENCY CLASS 4 (Continued) 4.3 Known loss of coolant accident 4.3.1 Observation of ECCS initiation and SITE AREA greater than make-up capacity. Control Room or local rack indication of failure to maintain vessel level above -145.5".

4.4 Small or large break LOCAs, 4.4.1 Indications are: CENERAL accompa, ed by failure of ECCS a) High drywell pressure. EMERCENCY to perform, leading to severe b) Low vessel level.

core degradation or melt in frcai c) Lack of ECCS initiation.

minutes to hours. Breach of d) Containment activity, sump level containment likely. humidity, and temperature-increase.

e) Reactor scram.

f) Area temperature monitor increases.

, g) High off gas at steam jet air ejector monitors greater than 5 C1/sec.

h) Primary coolant sample indicates activity levels exceeding 310 r

uC1/ge.

1) Containment unisolable.

j) Suppression pool water volume cannot be maintained between 87,650 cu ft and 91,000 cu ft or temperature cannot be maintained below 90'F or 95'F for periods not to exceed 45 days whenever river water

temperature is such that 90*F can-not be maintained. Temperature displayed on CR-VBD-J; level dis-played on Panels 9-3 and 9-4.

k) Containment pressure exceeding design.

4.5 Small or large break LOCA occurs 4.5.1 Indications are: CENERAL and containment performance is a) liigh drywell pressure. EMERGENCY unsuccessful, affecting longer b) Low vessel level.

term success of the ECCS. Could c) Lack of EEC initiation.

leaJ to core degradation or melt d) Containment activity, sump level, in several hours without benefit humidity, and temperature increase, of containment boundary. e) Reactor scram.

f) Area temperature monitor increases.

g) High off gas at steam jet air ejector monitors greater than 5 C1/ge.

h) Primary coolant sample indicates

activity levels exceeding 310 uCi/gm 1-131.

Procedure NumLer EPIP 5.7.1 .Date ,

l1 $ Revision 2 Page - 7 of 16 Pages

e, COOPER NUCLEAR STATION OPERATIONS MANUAL

• A'lTACle!Ef4T "C" IttfECFriCY PIAN UtPLE!!EtTING PROCFDt*E 5.7.1 CNS EMERCENCY PLAN IMPLEMENTATION f

CLASSIFICATION CIIIDE SUBHODULE INITIATING CONDITIONS ENEPCENCY ACTION I.EVELS EMERCENCY CLASS 4 (Continued) 4.5 (Continued) 4.5.1 i) Containment unisojable. CENERAL j) Suppression pool water volume EttERGENCY cannot be maintained between 87,650 cu f t and 91,000 cu f t' or temperature cannot be main-tained below 90*F or 95'F for periods not to exceed 45 days whenever river water temperature is such that 90'F cannot be.

maintained. Temperature and volume displayed on CR-VBD-J.

k) Containment pressure exceeding design.

5. Loss of power or alarms. 5.1 Loss of all off-site power or loss 5.1.1 Indications: NOTIFICATION OF of all on-site AC power capability, a) Loss of normal Control Room UNUSUAL EVfNT lighting, b) Startup transformer under-voltage.

c) Emergency transformer under-voltage.

d) Associated alarms on Control Room VBD-A, VBD-B, VBD-C, generator trip, or scram, e) Both diesels inoperative, may annunciate on Control Room VBD-C.

5.2 Loss of off-site power and loss 5.2 1 Indications: ALERT of all on-site AC power Tor a a) Loss of station AC lighting.

period of less than 15 minutes. b) Generator trip.

c) Reactor scram.

d) Failure of startup station transformer, e) Both diesels inoperative.

f) Subsequent failure of all AC powered equipment.

5.3 Loss of all on-site DC power for 5.3.1 Indications: ALERT less than 15 minutes. a) Reactor scram, b) Loss of Control Room indi-cati.g lights on 4160 and 480 equipment.

c) loss of annunciators.

d) Loss of control power.

Procedure Number EPIP 5.7.1 Date ) ./ l ' )( I$ hevision 2 Page 8 Of 16 Page s

=

COOPER NUCLEAR STATION OPERATIONS MANUAL AITACHMENT "C" FMERGEt;CY l'LAN IMPLEME . TING PROCEDURE 5.7.1 CNS EttERCENCY PLAN IMPLEMENTATION h

CLASSIFICATION ClllDE SUBMOINLE INITIATING CONDITIONS EMERCENCY ACTION LEVELS EMERCENCY CLASS

5. (Continued) 5.4 Host or all alarms (annunci- 5.4.1 Control Room observation. ALERT ators) non-functional and reactor is not shut down!

5.5 Loss of of f-site power and 5.5.1 Evidenced by: SITE AREA loss of on-site AC power Tor a) Loss of station AC lighting. ENERCENCY more than 15 minutes. b) Generator trip.

c) Reactor scram, d) Failure of station startup transformer.

e) Failure of station service transformer.

f) Failure of both diesel generators to start.

g) Subsequent failure of all AC pcuered equipment.

h) Inability to recover within 15 minutes.

5.6 Loss of all vital on-site 5.6.1 Indications: SITE AREA DC power for more than 15 a) Reactor scram. ENERCENCY minutes. b) Loss of voltage and amperage indication on Control Room Panel VBD-C.

c) loss of Control Room iridi-cating lights on 4160 and 480 equipment, d) Loss of annunciators.

• e) Loss of equipment control power.

f) Inability to recover within 15 minutes.

5.7 Host or all alarms (annun- 5.7.1 As observed by Control Room SITE AREA clators) lost and station Operators. EMERCENCY transient initiated or in progress.

5.8 Failure of off-site and on site 5.8.1 As observed by Control Room ' CENERAL power with loss of emergency Operators. EMERCENCY cooling capabilities for an extended period.

Procedure Number EPIP 5.7.1 Date Revision 2 Page 9 Of 16 Pages

COOPER NUCf. EAR STATION OPERATIONS HANUAL

• ATTACliMENT "C" EMERCFr:CY Pl.A!! IMPIIMENTING PROCEDUIT S.7.1 CNS EMERCENCY Pi.AN IMPLEMENTATION h

CLASSIFICATION CUIDE S0EMODULE INITIATING CONDITIONS ENERCENCY ACTION LEVELS EMERCENCY CLASS

6. Other limiting conj 1 tion for 6.1 Any Technical Specification 6.1.1 As detailed in Technical Specif1- NOTIFICATION OF operation. LCOs resulting in immediate cation LCOs. UNUSUAL EVENT shutdown. Indications or alarms on process or effluent 6.1.2 All meteorological instrumentation parameter not functional in inoperative.

Control Room to an extent re-quiring station shutdown 6.1.3 Inability to compute Core Thermal or other significant loss of Limits.

assessment or communications capability.

6.2 Loss of primary containment 6.2.1 Suppression pool water volume can- NOTIFICATION OF integrity to the extent re- not be maintained between 87,650 cu UNUSUAL EVENT quiring shutdown by Technical ft and 91,000 cu 't, or temperature Specifications, cannot be maintahad below 90'F or 95'F for periods tot to exceed 45 days whenever river water tempera-ture is such that 90'F cannot be maintained. Temperature and volume displayed on Control Room VBD-J.

6.2.2 Unable to maintain drywell to sup-pression chamber dif f erential pres-sure. Instrument indication on Control Room VBD-J.

• 6.2.3 Loss of containment structural integrity.

6.3 Loss of engineered safety 6.3.1 LCOs for engineered safety features NOTIFICATION OF feature to the extent re- exceeded. UNUSUAL EVENT quiring shutdown by Tech-nical Specifications. 6.3.2 LCOs for fire protection system exceeded.

6.4 Emergency Core Cooling 6.4.1 Hanuel or automatic activation NOTIFICATION OF System (ECCS) initiated and involving a valid indication of a UNUSUAL EVENT discharged to vessel. safety problem with an emergency core cooling paraneter not being maintained.

6.5 Any serious radiological ex- 6.5.1 As situations occur. NOTIFICATION OF posure of plant personnel i r UNUSUAL EVENT the transportation to off-site facilities of contami-nated injured personnel.

Procedure Number I PIP 5. 7.1 Date . >! b$ Revision 2 Page 10 Of 16 Pages 4

COOPER NUCLEAR STATION OPEHATIONS MANUAL .-

AI'I ACIC LEl.T "C" l>tERCFl:CY PIRJ IMitEMENTING PROCEDL'RE 5.7.1 CNS EMERCENCY PLAN IMPLEMENTATION h

CLASSIFICATION CUIDE SUEHODULE INITIATING CONDITIONS EMERCENCY. ACTION LEVELS EMERCENCY CLASS

6. (Continued) 6.6 Complete loss of any function 6.6.1 Inability to condense steam,(loss ALERT needed for plant cold shutdown. of condensar, circulating water).

6.6.2 Loss of RCIC.

6.6.3 Unable to place RilR in shutdown cooling mode.

6./ Complete loss of any function 6.7.1 Inability to control recirculating SITE AREA needed for plant hot shutdM:n. water pumps er control rods and loss of heat sink (i.e. Riik ste2m condensing water).

7. Reactor protection system 7.1 Failure of the reacter protec- 7.1.1 Indication of reactor scram ALERT failure. tion system to initiate and Panel 9-5 without corresponding:

complete a scram, which brings a) Valid scram signal and computer the reactor subcritical. printout indicates not all rods scrammeu.

b) Computer printout indicates not all rods full in.

c) Nuclear instruments do not re-gister expected decreases in power . level .

7.2 Transient requiring operation 7.2.1 Any Control Room Panel 9-5 RED SITE AREA of shutdown systems with fail- annunciator indicating a fuTT scram EMERGENCY ure to scram (continued power signal without full in rod indica-generation with no core damage tion en Panel 9-5 full core display.

Immediately evident).

7.2.2 No decrease in reactor power level.

7.2.3 No increase observed on steam jet air ejector monitors, RMP-RM-150A

& B. Coolant sample activity does not exceed equilibrium value of 3.1 uCi/ga.

7.3 Transient plus failure of re- 7.3.1 Any Control Room Panel 9-5 RED GENERAL quisite core shutdown system annunciator, without scram Tnaica- . EHERCCNCY (e.g., scram). Could result tion on Panel 9-5 full core display in core melt down after or no decrease in reactor power several hours with subsequent level, containment failure likely. a) Subsequent increase to greater than 5 C1/sec. activity at steam jet air ejectors, b) Primary coolant activity ex-ceeds 310 uC1/gm 1-131.

Procedure Number EPIP 5.7.1 Date */-bl~sd5 Revision 2 Page 11 Of 16 Pages

e COOPER NUCLEAR STATION OPERATIONS MANUAL ITIACHNL!iT "C" IFU ltGI'NCY PIAN IMPt FMEFTflNG PROCFDL:RE 5.7.1 CNS EMERCENCY PLAN IMPLEMENTATION h .

CLASSIFICATION CUIDE SUBMODUI.E INITIATING CONDITIONS EMERGENCY ACTION LEVELS ENERCENCY CLASS

8. Fuel handling accident. 8.1 Fuel handling accident on 8.1.1 Refueling floor area radiation ALERT refueling floor, monitor alarms on Control Room Panel 9-3.

8.1.2 Refueling floor continuous air monitors in alarm.

8.1.3 Reactor But. ding ventilation monitors in alarm.

8.1.4 Initiation of standby gas treat-ment system.

8.1.5 Verbal reports from personnel on refueling floor.

8.2 Major damage to spent fuel 8.2.1 Verbal reports or annunciation of: SITE AREA on refueling floor, a) Refueling floor area radiation EHERCENCY monitor, b) Refueling floor continuous air monitor.

c) Reactor Building ventilation exhaust monitor, d) Low spent fuel pool water level (Control Room Panel 9-4).

8.2.2 Initiation of:

a) Reactor Building isolation standby gas treatment.

9 Control Room evacuation. 9.1 Evacuation of Control Room 0.1.1 As deemed necessary by the Emer- ALERT required or anticipated with gency Director or Shift Supervisor.

control of shutdown systems established from local sta-tions.

9.2 Evacuation of Control Room 9.2.1 Control Room evacuation accom- SITE AREA accompanied by the inability panied by lack of access to EMERCENCY to locally control shutdown local shutdown system controls, systems within 15 minutes.

Procedure Numtwr Ll'IP 5.7.1 Date .) sI)..

';

• Revision 2- Page 12 Of 16 Pages 4

COOPER NUCLEAR STATION OPERATIONS MANUAI.

ATTAClitlENT "C"

• FMFRGLt:CY PLAN IMPLFMENTING PRfCFDLRE 5.7.1 CNS EMFRCENCY PLAN 1HPLEMENTAT10N CLASSIFICATION CUIDE Siff.!!0DUI.E INITIATING CONDITIONS EMERCENCY ACTION LEVF S EMERCENCY CLASS

9. (Continued) 9.3 Any major internal or external 9.3.1 Situation evident. CENERAL events (e.g., fires, earth- ENERCENCY

. quakes, substantially beyond design basis) which could cause massive common damage to plant systems.

10. Fire. 10.1 Fire at the plant exceeding 10.1.1 As determined by the Shift Fire NOTIFICATION OF short-term capabilities of Brigade Leader. UNUSUAL EVENT immediate on-site fire fighting teams.

10.2 Serious fire with potential to 10.2.1 Fire Protection Syste: alarm and ALERT cause degradation of plant visual confirmation safety systems. a) ECCS compartments.

b) Cable Spreading Room.

c) Diesel Generator Room, d) Verbal reports.

10.3 Fire compromising the function 10.3.1 Inability to initiate a safety SITE AREA of safety systems. system due to fire when a safety E1ERGENCY system is needed to maintain the station in a safe condition. Equip-ment failure or inaccessibility.

11. Security threat. 11.1 Security threat, attempted 11.1.1 As observed or reported by: NOTIFICATION OF entry, or attempted sabotage. a) Security Force. UNUSUAL EVENT b) CAS.

c) SAS.

11.2 On going security compromise. 11.2.1 As observed or reported by: ALERT a) Security Force.

b) CAS.

c) SAS.

11.3 Imminent loss of physical 11.3.1 As observed or reported by: SITE AREA control of the station. a) Security Force. EMERCENCY b) CAS.

c) SAS.

11.4 Loss of physical control of 11.4.1 As observed or reported by: CENERAL the facility. a) Security Force. EMERCENCY b) CAS. '

c) SAS.

d) Other station personnel.

Procedure Nun.I,er _ EPIP 5.7.1 Date ;) .) \ '#

Revisa..n 2 P.ir.e 11 Of 16 Pages '

i

I COOPER NUCl. EAR STATION OPERATIONS HAN!!AL -

• AITAQiltENT "C" 1:ttEkCENCY Pl.AN I?tPLFNENTING PROCFDi'RE 5.7.1 CNS FNEHGENCY PLAN IMPLEMENTATION CIAS51F1 CATION ClllDE Sl'EMODULE INITIATING CONDITIONS EMERCENCY ACTION LEVELS EMERCENCY CLASS

12. Natural phenomena. 12.1 Natural phenomenon being exper- 12.1.1 Cround motion greater than .01 g NOTIFICATION OF ienced or projected beyond usual as indicated by Control Room UNUSUAL EVErr.-

levels. Seismic Monitoring Panel, a) Any earthquake.

lg b) 50 year flood. 12.1.2 River level greater than 8978

. ,ge c) Tornado on-site.

12.1.3 As reported or observed.

12.2 Severe natural phenomenon being 12.2.1 Cround acceleration detected in ALERT experienced or projected, such excess of 0.10 g horizontal on as Control Room Seismic, alarm.

a) Earthquake exceeding Oper-ating Basis Earthquake 12.2.2 As reported or observed.

levels.

b) Tornado striking facility. 12.2.3 Winds approaching 100 mph or horizontal velocity detected.

c) Winds near design level.

d) Flood. 12.2.4 Water abose 903' level.

12.3 Severe natural phenomenon being 12.3.1 Cround in excess of 0.1 g hori- SITE AREA experienced or projected with zontal on Control Room Seismic EMERGENCY plant not in cold shutdown, such alarm and if there is safety as: system damaged.

a) Earthquake causing facility damage and core or safety 12.3.2 Anemometers detect sustained system damage, winds in excess of 100 mph.

b) Sustained winds or tornado causing significant damage 12.3.3 Damage to plant safety equip-to vital facilities /struc- ment, tures.

c) Flood waters affecting equip-ment needed for shutdown.

12.4 Any major internal or external 12.4.1 Situation evident. CENERAL events (e.g. fires, earthquakes, EMERGENCY substantially beyond design basis) which could cause massive common damage to plant systems.

Procedure Number EPIP 5.7.1 Date e> .') \ "'ei '#, Revision 2 Page 14 Of 16 Pages 4

o COOPER NUCf. EAR STATION OPERATIONS MANUAL

• ATTACHMENT "C" 1.!!ERCENCY PI Af; IMPLl'Ir!!TIf:G PROCEDURE 5.7.1 CNS EMFRGENCY Pl.AN IMPLEMENTATION Cl.ASSIFICATION CHIDE srb 510DUIE INITIATING CONDITIONS EMERCENCY ACT101 LEVEI.S EMERCENCY CLASS

13. Other hazards. 13.1 Other hazards experienced or 13.1.1 As visually observed by or reported NOTIFICATION OF projected: to CNS personnel. UNUSUAL EVENT a) Aircraf t crash on-site.

b) On-site explosion, c) On-site or near-site related accidents that could result in the release of toxic material or spills of flam-mable materials.

d) Train derailment on-site that may affect plant safety, e) Turbine component failure causing rapid plant S/D.

13.2 Other plant conditions exist that 13.2.1 As situations occur. NOTIFICATION OF warrant increased awareness on UNUSUAL EVENT the part of state / local off-site authorities.

13.3 Other hazards being experienced 13.3.1 As reported by or to station ALERT or projected, such as: personnel.

a) Aircraft crash on facility, b) Missile impact on facility, c) Explosion damage affecting plant operation.

d) Entry into facility environs of uncontrolled toxic or flammable gas, or e) Turbine failure causing cas-ing penetration and resultant radiological effluent releases exceeding 10 times Technical Specifications instantaneous limits.

(Some ef fect on facility exper-lenced or anticipated.)

13.4 Other plant conditions exist 13.4.1 As deemed necessary by the Emer- AIERT warranting precautionary acti- gency Director or Shif t Supervisor, vation of the TSC and other key emergency personnel as well as EOF placed on a standby status.

16 Pages I Procedure Number EP!P 5.7.1 Date - .l ,

Revision 2 Page 15 Of

_,-~  ;

4 r

COOPER NUCLEAR STATION OPERATIONS MANUAL A1TACle1NT C" f f 4 RGFt.CY PI AN IMPI rMFYflNG PROCEDURE 5.7.1 CNS ENERCENCY PLAN IMPI.EMENTATION

'h CLASSIFICATION GUIDE St'bu '00L E INITIATING CONDITIONS EMFRCENCY ACTION LEVELS EMEkCENCY CLASS

13. (Continued) 13.5 Other hazards being experienced 13.5.1 As observed by or reported to station SITE AREA or projected with reactor not personnel. .

In cold shutdown, such as a) Aircraf t crash af fecting vital structures by impact or fire.

b) Severe damage to safe shut-down equipment from missiles or explosion.

c) Entry of uncontrolled flam-mable gas into vital areas; entry of uncontrolled toxic gases into vital areas where lack of access to the area constitutes a safety problem.

13.6 Other plant conditions exist 13.6.1 As deemed necessary by the Emergency SITE AREA warranting activation of emer- Director or Shif t Supervisor.

gency centers and monitoring teams or issuance of a precau-tionary notification to the public near the site.

13.7 Any other plant condition exista 13.7.1 a) All rods scrammed. CENERAL from whatever source that makes b) S/D Margin is achieved. EMERCENCY release of large amounts of c) Inability to condense steam radioactivity in a short time (i.e. loss of condenser, period possible, e.g. shutdowq circulating water).

occurs, but requisite decay heat d) Loss of RCIC.

removal systems (RilR) or non- e) Unable to place RilR in safety systems heat removal shutdown cooling node.

means are rendered unavailable. f) liigh of f gas at steam jet air Core melt could occur in about ejectors greater than 5 C1/sec.

10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with subsequent con- g) Primary coolant sample indicates tainment breach likely. activity levels greater than 310 uCi/gm I-131.

Proca <ture Nun.l.t r I: PIP 5.7.1 tutu .) ) f , k Mo visim 2 Page 16 Of 16 Pages ,

..- .o Lt ovER '.1:LLT.AF FTATinX Gi ER/G IONS TANL'AL -

DIERGENCY PLAN DIPLDIENTING PROCEDURE 5.7.2 NOTIFICATION OF UNUSUAL EVENT I. PURPOSE A. The purpose of this procedure is to _ provide a series of implementing actions to be taken upon declaration of a NOTIFICATION OF UNUSUAL EVENT.

B. This procedure directs personnel to the use of some additional proce-dures to adequately respond to those conditions classified as a NOTI-FICATION OF UNUSUAL EVENT.

II. DISCUSSION A. A NOTIFICATION OF UNUSUAL. EVENT is defined as any station-related event which indicates a potential degradation of station safety margins, but which is not likely to sffect on-site personnel or the public or result in radica.ctive releases requiring of f-site acnitoring. NGTIFICATION OF UNUSUAL EVENT conditions will not have caused serious damage to the station and may not require a change in operation status.

3. In a NOIIFICATION OF UNUSUAL EVENT time is available to take precau-tionary and constructive stcps to prevent a more serious event and/or to mitigate any consequences that may occur.

C. The basic shift complement is able to deal with NOTIFICATION OF UNUSUAL ,

EVENT conditions. Additional station personnel will be notified and will respond at the discretion of the Emergency Director.

D. Appropriate votification of off-site authorities is made.

III. REFERENCE MATERIAL A. CNS Emergency Plan.

B. NUREG 0654, Rev. 1.

IV. PREREOUISITES A. NOTIFICATION OF U'iUSUAL EVENT has been declared in accordance with the provisions of EPIP 5.7.1, Emergene/ Classification.

V. LIMITATIONS ,

A. None.

VI. PRECAUTIONS A. None.

Revised By/Date Reviewed By/Date Aporovep Bv/Date Rev. Procedure Of Page 1 D. Whitnan 12/20/82 J. Sayer 12/29/82 p q . 1 ":E. 1 5.7.2 2 Pages

711. EQUIPMENT A. None.

VII

I. PROCEDURE

A. Immediate Actions.

1. The Shif t Supervisor assumes the function of the Emergency Director.

2. The Shift Supervisor implements EPIP 5.7.6, Notification.

3. The Station S'2perintendent provides necessary direction to the Shift Supervisor or assumes command as the Emergency Director.

B. Subsequent Actions.

The Cmergency Director performs the following:

1. Implement additional EPIPs accerding to the sittation that resulted in the emergency being classified as a NOTIFICATION OF UNUSUAL EVENT and complete the checklist as indicated in Attachment "A",

UOTIFICATION OF UNUSUAL EVENT Implementing Procedure Checklist.

2. Determine the need for any additional p >rsonnel and direct the Operations Communicater to call in additional personnel as needed by e.ontreting the appropriate Department Supervisors.

3. Re-evaluate the emergency classification as conditions change by using EPIP 5.7.1.

4 Upon termination of the NOTIFICATION OF UNUSUAL EVENT close out with verbal summary to off-site authorities, followed by written summary within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

II. ATTACHMENTS A. Attachment "A", NOTIFICATIOM OF UNUSUAL EVENT Implementing Procedures Checklist.

l l

?rocedure Number EPIP S.7.2 Date I- Y- I Revision 1 Page 2 Of 2 Pages

l t .

• ~# s si s t. . . ..s ..t . . s. se.. t r t .. ...e..: . 4 s. . t 151.,

ATTACic!E"T "A" EMERGENCY PT.AN IMPLEMENTING PROCEDURE 5.7.2 NOTIFICATION OF UNUSUAL EVENT l

NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING PROCEDUP2 CHECKLIST REOUIRED COMPLETED PROCEDURE AS l

l NLHBER PROCEDURE YES REOUIRED DATE TIME t

EPIP 5.7.1 Emergency Classification X / /

EPIP 5.7.6 Notification X / /

EPIP 5.7.12 Energency Radiation Exposure Control / /

EPIP 5.7.13 Personnel Monitoring And Decentamina.tien / ,

/

EPIP 5.7.15 Rescue And Re-Ectry / /

E?IP 5.7.18 Of f-Site And Site Boundary Mcnitorit.g ,,

/ _ ,/

EPIP 5.7.19 On-Site Radiological Mr itoring / ,/ _

EP1P 5.7.24 Medical / _/

IMAPKS: _

i l

l l

l l

l l

Procedure Number EPIP 5.7.2 Date  !-N- Revision 1 Page 1 Of 1 Pages

~

woPER NUCLEAR STATION OPERATIONS MANUAL EMERCENCY PLAM IMPLMENTING PROCEDURE 5.7.3 ALERT IMPLEMENTING' PROCEDURE ,

/

1. PURFOSE A. To outline the actions required of station personnel, visitors, and contractors when an ALERT condition is declared.

B.

This procedure directs personnel to the use of some additional proce-dures to adequately respond to those conditions classified as an ALERT.

II. DISCL'SSION A.

An ALERT condition is defined as any condition that involves an actual or potential substantial degradation of the safety level of the station. l At oc.cuthis r . classification level, small releases of radioactivity may Although the releaeas might exceed CNS Technical Soecifications, EPA Protective Action Guidelitas are not expected to be implercnted.

Station Operator modification of station operating status is a probable corrective action if such modificatica has not airsady becc accomplished by automatic protection systems.

B.

The decision to make a. immediate initial ALERT declaration rests with the Emergency Director, who, in turn, directs the Operations Communi-cator to perform the necessary notifications. Off-site notification assures that

, the situation becomes more serious. emergency personnel are tradily available to respond if C.

In an ALERT condition the TSC, the Mechanical / Maintenance OSC, the Instrument and Control / Electrical OSC, and the Chemistry and Health Physics OSC will be activated.

personnel may be placed on standby status.In addition, the EOF and key emergency III. REFERENCE MATERIAL A. CNS Emergency Plan.

B. NUREC 0654, Revision 1.

IV. PREREOUISITES -

A.

An dureALERT has been declared in accordance with the provisions of proce-EPIP 5.7.1

. Energency Classification.

V. LIMITATIONS A. None.

Revised By/Date Reviewed By/Date Approved By/ bate Rev. Procedure Page_ 1 Of D. Whitman 2/3/83 J. Sayer 2/17/83 2 5.7.3 3 Pa gras

VI. PRECAUTIONS A. None.

VII. EOUIPMENT A. None.

VII

I. PROCEDURE

A. Immediate Actions.

1. The Shift Supervisor assumes the function of the Emergency Director.

2. The Shift Supervisor implements EPIP 5.7.6, Notification.

3. The Station Superintendent relieves the Shift Supervisor as the

Dmergency Director as soon as possible.

4 The Shift Supervisor directs the Control Room Operator to terivate l the alarm for 10 seconds and make the relieving anncancement:

" ALERT, ALERT!! There is (what) in/at (whete). Emergency personnel report to assigned stations. All other personnel, centractors, and visitcrs report to the CNS Security Btilding. All personnel stay clear of the affected area."

a. Repeat the alarm and announcement.

(

b. Sound the emergency alarm for 1 minute.

B. Subsequent Actions.

1. The Emergency Director performs the following:

a. Implements EPIP 5.7.7, Activation Of TSC.

. b. Places the EOF on standby and implements EPIP 5.7.9, Activation Of EOF (optional).

c. Determines the need for any additional personnel and directs the Operations Communicator to call in additional personnel as needed by contacting the appropriate Department Supervisors, who are listed in the Emergency Telephone Directory.

d. Implements additional EPIPs as required and completes the checklist as indicated in Attachment "A", ALERT Implementing Procedure Checklist.

e. Re-evaluates the emergency classification as conditions change by using EPIP 5.7.1 and provides corresponding information to the on-site Emergency Response Facilities and appropriate governmental agencies.

Procedure Number EPTP 5.7.3 Date O ~' i- '

Fev4cien  ? Paca 2 of 1 Pr s-

f. Closes out or recommends reduction in emergency classification by verbal summary to off-site authorities followed by a written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.of close-out or classification reduction.

2. OSC Activation.

a. The Maintenance and OSC Coordinator and Chemistry and Health Physics Coordinator will implement EPIP 5.7.8, Activation Of-OSCs.

IX. ATTACHMENTS -

A. At.tachment "A", Alert Implementing Procedure Checklist.

h 4

• =W

(/ ,_

'?ros adure Nnal.e r

% - gO* ~s'Ol

FPIP 5.7.1 Dnen . kovisinn 2 P ion 3 or 1 r. -o,.

COOPER NUCI. EAR STATION OPERATIONS MANUAL ATTACHMENT "A" "

EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.7.3 ALERT YMPLEMENTING PROCEDURE ALERT IMPLEMENTING PROCEDURE CHECKLIST REOUIRED COMPLETED PROCEDURE AS NUMBER PROCEDURE YES REOUIRED DATE TIME EPIP 5.7.1 Emergency Classifications X / /

EPIP 5.7.6 Notification X / /

EPIP 5.7.? Activation Ff TSC X / /

EPIE 5.7.8 Activation Of OSCs X / /

EPIP 5.7.9 Accivation Of EOF / /

EPIP 5.7.10 Personnel Assembly And Acccurtability X / _

/

EPIP 3.7,12 Yrtrgercy Radiation Exposure Contral / /

EPIP 5.7.!3 Pers,;anel Monicoring And Decontamination / /

EPIP !.P.?5 Rescue and Re-Entry / /

EPIP 5.7.16 Release Rate Determination / /

EPIP 5.7.17 Dese Assessment / /

EPIP 5.7.18 Off-Site And Site Boundary Monitoring / /

EPIP 5.7.19 On-Site Radiological Monitoring / /

EPIP 5.7.20 Protective Action Guides / /

l EPIP 5.7.23 Media / /

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! EPIP 5.7.24 Medical / /

l REMARKS:

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i Procedure !! umber EPIP 5 7.3 Date ' *Io ~yE Revision 2 Price 1 Of 1 P .1. . -

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COOPER NUCLEAR STATfoi4 OPERATIONS MANUAL EMERGEE4CY PLAN TMPLEMENTING PROCEDURE 5.7.8 ACTIVATTON OF OSCs I. PURPOSE A. This procedure describes the activation and subsequent operation of the three Operations Support Centers (OSCs) in the event of an ALERT, SITE AREA EMERCENCY, or GENERAL EMERGENCY.

B. The topics addressed are:

1. Functions- of the OSCs and their interface with other on-site emergency response facilities.

2. Activation criteria, including and checklists of required actions

to be perf orced.

II. DISCUSSION A. Functiona of 930s.

1. Chewintry and Eesith Physics OSC.

a. The Cbemistry tai Ecalth Physics (C & dP) OSC is the staging area for all Chemistry and Health Physics personntl who may be required to provide chemistry and radiation protection assis-cance.

b. This OSC also serves as a canter where the initial accountabi-lity (heck of all on-duty Chemistry / Health Physics personnel is perfo:ued.

c. Emergency monitoring teams are organized from this point and other radiological or chemical assignments are made here at the direction of the Chemistry / Health Physics Coordinator. -

d. The Chemistry and Health Physics OSC is located on the 918' elevation of the Office Building in the Health Physics Office area.

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2. Mechanical Maintenance OSC.

a. The Mechanical Maintenance OSC serves as a staging area for all Mechanical Maintenance personnel (whose services may be required during the emergency) and from which these personnel are dispatched.

, b. This OSC also serves as the assembly ' area for the initial accountability check of all on-duty mechanical maintenance i personnel. .

l Revised By/Date Reviewed By/Date Approved By/Date Rev. Procedure Page 1 Of D. Whitman 1/28/83 J. Sayer 2/18/83 22/-7_3 2 5.7.9 4 Pages

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c. The Mechanical Maintenance OSC is located on the 903' elevation of the Machine Shop. '

3. I & C/ Electrical OSC.

a. This OSC serves as the staging area for all Electricians and I.

& C Technicians (whose services may be required during the emergency) and from which these personnel are dispatched.

b. The Electrical Shop is the center where initial accountability of all on-duty Electricians and I & C Technicians personnel is pe rfo rmed.

c. The I & C/ Electrical OSC is loested on the 932'6" elsrstien of I the Turbine Building in the F}ectrical Shop. #

B. Staffing Of OSCs.

1. The Chemistry and 3ealth Physics OSC is staffed with the follavirgt

a. Che:istry and Health Physics OSC Supervicor (He&lth Phy-31cist -

ALERT only).

h. Health Physics Technicians as required. -

c. Chemist (OSC Supervisor - SITE AREA AND CENERAL EMERGENCY only).

d. Chemintry Technicians as required.

2. The Mechanical Maintenance OSC is staffed with the folicwing:

a. Mechanical Maintenance OSC Supervisor (Mechanical Supervisor).

b. Mechanical personnel as required.

3. The I & C/ Electrical OSC is staffed with the following:

a. I & C/ Electrical OSC Supervisor (I & C Supervisor).

b. Electrical Foreman.

c. Electricians as required.

d. I & C Technicians as required.

i 4 If activation of the OSCs is required during f other than normal working hours, additional personnel are summoned through call lists and directed to assemble in these . f acilitics for assignments.

Telephone numbers for emergency response personnel are contained in the Emergency Telephone Directory.

Proced*:re Nuuber EPIP 5.7.8 Dnre R..e t ci en 7 psee  ? qi i 8a on -

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III. REFERENCE MATERIAL A. CNS Emergency Plan.

B. NUREC 0654, Revision 1.

IV. PREREOUISITES A. An ALERT or higher level emergency has been declared in accordance with EPIP 5.7.1 Emergency Classification, and actions specified in EPIP 5.7.3, EPIP 5.7.4, or EPIP 5.7.5 are being implemented.

V. LIltITATIONS A. Sin:* no habitability criteria are established for the OSCs, evacuation of OSC personnel may be required as dictated by radiol iical t semergency conditions.

VI. PRECAUTI')NS A. If the Area Alarm Ifonitor and/or the Contintrous Air Monitor plarms, an area Lbitability survey should be conducted. The results of this survey shculd be transmitted to the Chemistry and Health Prysics t Coordinator who will determine the need to evacuate OSC personnel to the Security Building Auditorium.

VII. EQUIPMENT j

A. Communications.

1. A list of communications equipment located in the CS0s and instruc-tions for its use are detailed in EPIP 5.7.22, Communications.

B. Emergency Equipment. -

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1. A list of emergency equipment located in the OSCs and instructions for maintaining the readiness of the equipment are detailed in EPIP 5.7.21, Emergency Equipment Inventory.

VII

I. PROCEDURE

A. Activation Of OSCs. (

1. OSC personnel shall report to respective centers and proceed with check-off lists as follows:

l' a. Chemistry and Health Physics OSC.

1) Chemistry and Health Physic _s OSC Supervisor - Attachment

.'A" .

a) For a SITE AREA EltERCENCY or CENERAL EMERGENCY the Chemist will perform this check-off.

Procedure Nu.mber EPTP.5.7_.8.

Date ) 'I-

?b Revision. 2 Page 3 Of 4 Papes

b. Mechanical Maintenance OSC.

1) Mechanical Maintenance OSC Supervisor - Attachment "B".

c. I & C/ Electrical OSC.

1) I & C/ Electrical OSC Supervisor - Attachment "C".

2. The appropriate OSC Coordinator shall report the status of the OSCs to the Emergency Director.

IX. ATTACHMENTS '

i A. Attachment "A", Chemistry and Health Physics OSC Supervisor Checklist.

B. Attachment "B", Mechanical Maintenance OSC Supervisor Checklist.  !

C. Attachment "C", I & C/ Electrical OSC Supervisor Checklist. ,

a b

Proendure Nuehar FDTD 97A nee. 1. I N *I oc..J-4 . o o--o /. $a 4 o --.

e e COOPER NUCLEAR STATION OPERATIONS MANUAL ATTACHMENT "A" EMERCENCY PLAN IMPLEMENTING PROCEDURE 5.7.8 ACTIVATION OF OSCs CHEMISTRY AND HEALTH PHYSICS OSC SUPERVISOR CHECKLIST ACTION ITEMS' TIME / INITIALS

1. Ensure all communications devices operate in the Chemistry and Health Physics OSC. /

a. Telephone (s): .

b. Gaitronics: .

c. Bonephore: .

2. Complete the personnel accountability group E checklist and report results to the Chemistry /

Health Physics Coordinator in the TSC.

( /

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3. Dispatch all visitors, contractors, and non-essencial personnel to the Security Building Auditorius. / '

4 Activate the Continsous Air Meritor. /

t 5. Ensure that all Chemistry and Health Physics equipment is in a state of readiness. / _ ,

6. Cher.k emergency kit located in the Chemistry

. and Health Physics OSC and ensure equipment ,

is complete (Inventory List) . /,___ _

7. Check roster list for survey tears assignments. / ~

8. Check personnel decontamination facilities and equipment. /

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9. Check' on any chenistry and radiochemister problems. /

f 10. Check to ensure Chemistry and Health Physics OSC i support is available to perform survey or other assessment functions and notify Chemistry / Health Physics OSC Coordinator in TSC when complete. /

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l Procedure Number EFTP 5.7.8 nare EJ OdI Yb, Revisinn 2 Poco I of 1 P.w a -

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COOPER NUCLEAR STATION OPERATIONS MANUAL ATTACHMENT "B" ,

. EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.7.8 ACTIVATION OF OSCs ,

MECHANICAL MAINTENANCE OSC SUPERVISOR CHECKLIST ACTION ITEMS TIME / INITIALS

1. Ensure all communication devices operate in the Mechanical Maintenance OSC. /

a. Telephone (s): .

b. Gaitronics: .

c. Bonephone: .

Inform the Maintenauca and OSC Coordinator in the TSC of any problems. / i

2. Lispatch s11 visitors, contractors, and non-essential personnel to the Security SAilding Auditoriuc. /

3. Cnmplete the perscnnel acccuntability group check-4 list and report results to the Maintenance and OSC '

Coordinator in the TSC. /

'foth: Request permission from the Maintenance and OSC Coordinatcr to retrieve personnel in work areas.

4. Activate continuous air nonitor, check area radiation tonitor while perforring habitability survey of the Meccanical Mafrtanance OSC, and inform the Chemistry and Health Physics Coordinator in the -

TSC cf ti;e results.

/

5. . Ensure that all emergency equipment and personnel are in a state of readiness. /

a. Maintenance Emergency Response Equipment.

1) Ensure Emergency Rescue Equipment Inventory is available per EPIP 5.7.15 Attachment "B". /

2) Ensure Emergency Equipment Inventory is available per EPIP 5.7.21,-Attachment "C". /

3) Check equipment operability (battery checks). /

b. Health Physics Emergency Response Equipment.

Procadure Nunber FPIP 5.7.8 Dara  ! ' "* Devisinn 2 Pace 1 ne  ? Da"+=

COOPER NUCLEAR STATION OPERATIONS MANUAL ATTACHMENT "B" EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.7.8 ACTIVATION OF OSCs ,

4 MECHANICAL MAINTENANCE OSC SUPERVISOR CHECKLIST ACTION ITEMS TIME / INITIALS

1) Ensure Emergency Equipment Inventory is available per EPIP 5.7.15, Attachment "A". /

2)~ Check equipment operability, a) Battery Checks: .

b) Zero Dcsiroters: ,

c) SCBA's Full: ,

.. 6. Report OSC readiness to the Maintenance and OSC Coordinater in the TSC. ,

/

7. Maintain an OSC Supervisor's Log. /_

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l Procedure Number EPTP 5.7.8 Dare ' 2!' "

Rev4=4nn  ? P49a 2 of 2 P-car l

l COOPER HUCLEAR STATION OPERATIONS MANUAL ATTACHMENT "C" j EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.7.8 ACTIVATION OF OSCs ,

I & C/ELEC1tICAL OSC SUPERVISOR CHECKLIST ACTION ITEMS TIME / INITIALS

1. Ensure all communication devices operate in the I & C/

Elcetrical OSC. /

a. Telephone (s): . /

b. Caitronics(s): .

c. Bonephone: ,

1 Inform the Maintenance and OSC Coordinator in the TSC of any problems. / .

2. Dispatch all visitors, contractors, and non-essential personnel to the Security Building. Auditorium. ,,

/

3. Complete the persontal accountability group checklist and report results te the Maintenance and OSC

. Coordinator. /

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4. Activate continuous air monitor and check ares radia-tion monitor while performing habitability survey of the I & C/ Electrical OSC. Inform the Chemistry and Health Physics Coordinator in the TSC of the results. / ,

5. Ensure that all emergency equipment and personnel are in a state of readiness. /

a. I & C/ Electrical Emergency Response Equipment.

I 1) Ensure Emergency Equipment Inventory is l

i available per EPIP 5.7.21, Attachment "C". /

l 1

2) Check equipment operability (battery checks). /

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b. Health Physics Emergency Response Equipment Inventory.

1) Ensure Emergency Equipment Inventory is available per EPIP 3.7.15, Attachment "A". /

2) Check equipment operability, a) Battery Checks: .

Procedurc Number _,EPIP 5.7.8 Date - ?. l 5' Revisien 2 Paca 1 of 2 P:4can

COOPER NUCLEAR STATION OPERATIONS MANUAL l ATTACHMENT "C"

, EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.7.8 ACTIVATION OF OSCs ,

I & C/ ELECTRICAL OSC SUPERVISOR CHECKLIST ACTION ITEMS TIME / INITIALS b) Zero Dosimeters: .

c) SCBA's Full: .

6. Report OSC readiness to the Maintenance and OSC Coordinator. /

7. Maintain an OSC Supervisor's Log. /

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Procedure Nimber EPTP 5.7.A D,ea .'! ~> p ... < - 4 n., ? p.-n 7 ns 9 3,,.-,

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COOPER NUCLEAR STATION OPERATEGNS MANUAL s, , y. g EMERCENCY PLAN IMPLEMENTING PROCEDURE 5.7.12 .EMERCENCY RADIATION EXPOSURE CONTROI ,

3 s m .

n A

'% + . .

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]. I., PURPOSE 'g . , > s --

The purpose of' this procedure .is to providespolicy guidance, address ,

required authorization, and set forth maximum ' criteria for enorgency .

i 3 - radiation exposure control in the events emergency workers are required to 1

exceed ~eseablished quarterly or annual e.xpcsure limits..-

i.

II. DISCUSSION D --

Under imergency conditions it may become necessary for ettergency workers to ~

receive exposures in excess of Secupational limits established by 10CFR20.

! Emergency dose exposure limits are defined for thras categories (life-saving >

actions, corrective or protective actions, and sampling under emergency

! conditions). These exposure limits are contained in Attachment "A".

The Emergency Director or his designee has the authority to authorize exposures in excess of occupational limits. These exposures are only justifiable.if it is determined that benefits are being achieved, the doses are commensurate with the significance of the objective, and every reason-able effort is being made to maintaidg emergency workers doses As low As Reasonably Achievable (ALARA).

III.' REFERENCES.

A. CNS Esergency Plan.

B. NUREG 0654, Revision 1. -

C. Emergency Exposure Limits, NUREG 0737, November, 1980.

D. NCRP Report 39, 1971; Basic Radiation Protection Criteria.

E. ICRP Report 59; Permissible Dose For Interns 1 Radiation Working Breath-ing Rate.

F. EPA Protective Action Guides, June lh80.

I

IV. PREREOUISITES l A. The Emergency Director may authorize [mergency exposures under the following conditions

1. Life-saving actions.

a. Removal and/or rescue of injured personnel.

s Revised By/Date Reviewed By/Date Approved By/Date Rev. Procedure

• D. Whitman 1/27/83 J. Sayer 2/17/83 ./8 83 2 5.7.12 Pages 4

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< ., , - , - ~ . . . , - . . , . _ _ , . , , , , , , . , - - . . _ . . . , - - - . - . . , - . . . - _. - . - - - _ _ . -- , -

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2. Corrective or protective actions.

a. Providing first aid.

b. Providing ambulance service,

c. Providing medical treatment service. ,

d. Performing personnel decontamination.

e. Undertaking corrective action on station equipment and systems.

3. Sampling under emergency conditions,

s. Collection of in-plant airborne and liquid samples.

b. Use of the post-accident sampling system.

' Note: The above are examples and not an absolute list; the existing situation may dictate additional conditions under which exceeding 10CFR20 limits may be warranted.

V. LIMITATIONS A. Emergency Exposure Limits are contained in Attachment "A".

(-

B. Personnel authorized to receive emergency exposures should meet,the following criteria:

1. Personnel conducting corrective or protective actions or life-saving actions who may receive a whole body dose in excess of 12 rea/ year should be selected on a voluntary basis.

2. Rescue personnel shall be familiar with the hazards of any exposure received under emergency conditions.

3. Women of child bearing age shall not take part in these actions.

i 4 Personnel should not have received previous emergency exposures.

Emergency exposures should be limited to once in a lifetime.

5. Exposures greater than 10CFR20 limits are voluntary.

VI. PRECAUTIONS j A. Protective clothing and/or respirators should be used as appropriate.

B. Potassium Iodide (KI) tablets, if necessary, should be administered in accordance with EPIP 5.7.14, Stable Iodine Thyroid Blocking.

{ C. Administrative methods to minimize personnel exposure (such as ALARA) should remain in force to the extent consistent with timely rescue, corrective, and protective actions.

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Procedure Number _EPIP 5.7.12 Date 3 --),3; - [k Revision 2 _

Page 2 Of _4 Panne

D. Personnel shall wear dosimeters appropriate for measurement of antici-paced exposure levels. These shall include:

1. The most appropriate direct reading pencil dosimeter for whole body exposure:

a. Low range direct reading dosimeter (0 to 200 mR).

b. Medium range direct reading dosimeter (0 to 10 R).

c. High range direct reading dosimeter (0 to 200 R).

2. TLD dosimeter to permanently record whole body exposures'

3. Extremity monitoring, if the anticipated extremity exposure is greater than three times the projected whole body exposure.

VII. EQUIPMENT A. None.

VII

I. PROCEDURE

A. Emergency Radiation Exposure Control.

1. The Emergency Director or his designee has the authority to author-ize whole body doses in excess of 3 rem but not greater than 75 rem.

2. Personnel exposure control.

a. Individuals shall not enter any area where dose rates are unknown or unmeasurable with instruments immediately available.

1) If possible, the following survey instruments should be used:

a) High range portable survey inscrument (0 to 1000 R/hr);

this should be the instrument of choice, b) Low range portable survey instrument (0 to 5 R/hr).

2) Meter use:

l a) Prior to entering any radiation area allow time for the meter to warm up.

b) Check meter response with a check source.

c) Enter suspected radiatio'n areas with the meter set on the high scale and the switch down as necessary.

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Procedure Number EPIP 5.7.12 Date ~ t ',

• i .k Revision 2 Page 3 Of 4 Paces L

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3. The Chemistry and Health Physics Coordinator shall:

a. Obtain initial estimates of the radiation dose of exposed personnel as quickly as possible.

b. 'Immediately report to the NRC exposures in excess of 10CFR20, Occupational Limits. (Attachment "B") per 10CFR20.403 and 10CFR20.405.

c. Update existing Special Work Permits as station conditions change and information becomes available.

IX. ATTACHMENTS A. Attachment "A", Emergency Exposure Limits i B. Attachment "B", Maximum Permissible Dose Equivalent For' Occupational Exposure.

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l Prnecilure Number EPTP 5.7.12 Date N -- hI'7 S Revisten 2 Pace 4 Of /* P ic..s

CCOPER NUCf.FAR STATION OPERATIONS MAh'UAL ATTACHMENT "A" EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.7.12 EMERCENCY RADIATION EXPOSURE'CONTROI.

1 EMERGENCY EXPOSURE LIMITS SAMPLING CORRECTIVE UNDER OR ACCIDENT PROTECTIVE LIFE-SAVING CONDITIONS ACTIONS ACTIONS Whole Body (rem) 5 25 75 Thyroid (rem) 15 125 No Limit

• Extremities (rem) 75 100 200

• Thyroid exposure should be minimized to the extent feasible by the use of respir-atory protection and/or thyroid blocking. However, no upper limit is specified for life-saving action.

Procedure Number EPIP 5.7.12 Date -8 *

'. Revision 2 Pace  ! Of 1 Pe=

COOPER NUCLEAR STATION OPERATIONS MANUAL ATTACHMENT "B" EMERCENCY PLAN IMPLEMENTING PROCEDURE 5.7.12 EMERCENCY RADIATION EXPOSURE CONTROL ,

MAXIMLH PERMISSIBLE DOSE EQUIVALENT FOR OCCUPATIONAL EXPOSURE MILLIREMS /. MILLIREMS /

OUARTER YEAR Whole Body; Head And Trunk; Active Blood-Forming Organs; Lens Of Eyes; Or Gonads 3,000 1 12,000 2 Hands 25,000 75,000 Forearms 10,000 30,000 Skin Of Whole Body 7,500 15,000 Other Organs, Tissues, And Organ Systems (Thyroid Included) 5,000 15,000 Fertile Women (With Respect To Fetus) 500 mR/9 months

1. 3,000' millirem is permitted in a calendar quarter as long as the accumulative

( occupational dose to the whole body does not exceed 5,000 millirem X.(Age -

18).

2. Accumulating occupational exposure in excess of 5,000 millirem / year is per-mitted providing Step 1. above is maintained.

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l Proendure Nunber KPTP 5.7.17 Dare D -- l$ -  ?> Revision 2 Pnen 1 Of 1 Pa c.' e

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_ . .. _ ~, _ _ . _ _ _.. m .

C00 pen MI' CLEAR STATION OPERATTONS MANUAL .

' EMERCENCY PLAN IMPLEMEMTING PROCEDURE 5.7.14 STABLE IODIDE THYROID BLOCKING (KI) ,

?

l I. PURPOSE i

The purpose _of'this procedure is to define under what emergency conditions Potassium Iodide (KI) should be administered to station personnel and who has the authority to determine when and at what dosages KI should be i sdministered.

II. DISCUSSION 4

j A. Effectiveness.

KI is an effective means of . blocking radioiodine from the thyroid gland. If possible -it should be administered approximately 1/2 hour-to 1 day before exposure for maximum blockage. Final uptake.is halved if. KI is administered within 3 - to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> af ter exposure. Little benefit is gained if it is administered 10 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after exposure.

1 B. Dosage.

Once taken, and the concentration is verified or estimated by dose calculations, the tablets should be taken for 10 days post-exposure.

Dosage is one (130 mg) tablet; per day. Individuals suspected of

(

inhalation of airborne contaminant should receive thyroid counts on a regular basis throughout the KI treatment period to verify effective-ness of treatment and to estimateLdose commitment.

4 C. Precautions / Side Effects.

Potassium Iodide should not be used by individuals allergic to iodine.

. Usually side effects occur when- the dose is higher than that recom-mended for a long period of time. Possible side effects include skin rashes, swelling of the salivary gland, and iodism (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold, and sometimes stomach upset and diarrhea). If the side effects are severe or if an allergic reaction is experienced, stop taking KI and contact a doctor for further instruction.

III. REFERENCE MATERIAL 4.

A. CNS Emergency Plan.

B. NUREG 0654, Rev 1.

C. NCRP 55, Protection Of The Thyroid Gland In The Event Of Release' Of

• -Radioiodine, National Council on Radiation Protection and Measurements, 1977.

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l Revised By/Date Reviewed By/Date Approved By/Date Rev. Procedure Page 1 Of D. Whitman 1/27/S3 J. Sayer 2/15/83' N.bs 4t-tG S3 2 5.7.14 2 Pa;;es

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1 IV. PREMEOUISITES A. Potassium Iodide is to be administered:

1. Whenever a calculated radiciodine dose of 10 rem or greater to the thyroid is likely to be-received. ,

2. If possible, prior to undertaking a life-saving operation where high levels of radiciodine are suspected and no current air analy-sis is available.

V. LIMITATIONS A. Refer to Section II. for information on effectiveness and dosage.

VI. PRECAUTIONS A. KI should not be administered to personnel allergic to iodine.

B. KI will be administered on a voluntary basis.

VI

I. PROCEDURE

j A. Stable Iodine Thyroid Blocking (KI).

l

\ 1. The Emergency Director, acting on the recommendations of the

, Radiological Manager, will determine when and to whom KI may be administered.

2. The Radiological Manager, or his designee, will:

a. Obtain bottle (s) of 130 mg KI tablets from the Control Room TSC, EOF, AEOF, Chemistry and Health Physics, Instrument and Control / Electrical, or Mechanical / Maintenance OSC.

b. Dispense one tablet to each individual that has an emergency team assignment and may potentially enter a high-level airborne radioiodine environment.

c. Ensure that records (Attachment "A") are maintained for those j individuals who received KI tablets.

l 3. KI tablets may be provided to non-NPPD emergency response organi-l zations (i.e. States, NRC, FEMA, etc.) for distribution to their emergency workers. Administration of KI to non-NPPD personnel will be the responsibility of the organizations to which these personnel

, belong.

i VIII. ATTACHMENTS l

A. Attachment "A", Potassium Iodide Distribution Record.

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Proce< litre Number EPTP 5.7.14 Dare D -13 ' Ab Revision 2 P: ice 2 of 2 Pnc -

• e - a COOPER NUCLEAR STATION OPEP.ATIONS !!ANUAL -

ATTAC101EMT "A" E!!ERGENCY PLAN I!!PLEMENTING PROCEDURE 5.7.14 STABLE IODIDE THYROID BLOCKING (KI)

POTASSIUM IODIDE DISTRIBUTION RECORD SOCIAL SECURITY DATE/ TINE NAME NUMBER ORGANIZATION i

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Precediare Numbor EPIP 5.7.14 Date ) 3 3 c Revision 2 Pace 1 of I p;w,y

a s COOPER NUCLEAR ' STATION OPERATIONS MANUAL EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.7.15 RESdUE AND RE-ENTRY I. PURPOSE A. The purpose of this procedure is to provide the guidance and require-ments necessary to conduct efficient rescue and re-entry operations.

B. Topics covered in this procedure are:

1. Organization and operation of Rescue and Re-Entry Teams.

2. Precauticas observed by Rescue and Re-Entry Teams, including equipment carried during search and rescue operations.

II. DISCUSSION A. During a station emergency, abnormally high levels of radiation and/or radioactivity may be encountered. These levels may range from slightly above those experienced during normal station operation to life-endan-gering levels of several hundred Rem in a short period of time (e.g.

spect fuel cask accident or loss of coolant accident). Under all emergency situations,'whether it is immediate action to regain control of the emergency or for life-saving purposes, care should be taken to minimize personnel exposure from external and/or internal sources of

• radiation whenever practicable.

B. Specific exposure guidelines for entry or re-entry into areas in order to remove injured persons and undertake corrective actions, are defined in Attachment "C". The Emergency Director will authorize emergency dose guidelines consistent with or more restrictive than these limits depending upon emergency conditions. Radiological concerns will be discussed with rescue teams prior to undertaking any rescue mission.

III. REFERENCE MATERIAL A. CNS Energency Plan.

B. NUREG 0654 Revision 1.

C. 10CFR20.

IV. PicGREOUISITES A. Personnel are known to be missing or in need of help.

B. All Rescue and Re-Entry Team members have been briefed on the hazards of radiation exposures in excess of 25 Rem.

Revised By/Date Reviewed By/Date Approved By/Date Rev. Procedure Page 1 Of D. Whitman 2/8/83 J. Sayer 2/18/83 #I ^ 4<' J-2/ 23 2 5.7.15 4 Pages

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V ' LIMITATIONS A. All Rescue and -Re-Entry Team members will participate on a strictly voluntary basis.

B. No team member shall receive a whole body. dose greater than 75 Rem (whole body) while conducting search and rescue operations.

i VI. PRECAUTIONS A. During any emergency involving radiological hazards, exposure to i personnel should be. minimized consistent with the nature of the emer-gency response required.

B. The Radiological Manager will obtain approval from the Emergency Director for team members to obtain doses between 5 Rem and 75 Rem.

C. All planneddExposures in excess of. CNS administrative limits or 10CFR20 l limits shall be approved by the Radiological Manager and the Emergency

Director prior to receiving the- exposure. Radiation exposures of 2

Rescue and Re-Entry Team members are not to exceed 75 Rem whole body under any circumstances, i D. Referring to EPIP 5.7.14, Stable Iodine Thyroid Blocking, the Radio .

logical Manager or Emergency Director . will determine if Potassium

! Iodide should be administered and shall administer it if indicated to the Rescue and Re-Entry Team members in accordance with EPIP 5.7.14.

E. Ensure that a Health Physics Technician is equipped with a high range beta-gamma dose rate meter and monitors radiation levels at all times

! during the search and rescue operations.

VII. EQUIPMENT A. The Rescue and Re-Entry Team Leader will ensure that the team is equipped with the necessary protective equipment as shown in Attachment j "A", Protective Equipment.

i i B. In addition to the emergency fire fighting and protective equipment, a special Rescue Tool Cabinet is maintained in the vicinity of the l

Machine Shop. To assure ready availability, the equipment contained in this cabinet is reserved for EMERGENCY RESCUE USE ONLY. A list of this i equipment is shown in Attachment "B", Emergency Rescue Equipment.

l l VII

I. PROCEDURE

l E A. Personnel Search And/Or Rescue.

i 1. Immediate life-saving rescue required.

!l ' a. Within the limits allowed by the urgency of the situation, make

, every reasonable effort to obtain as much of the following:

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l Procedure Number EPIP 5.7.15 Date ) ~)l ! ~ Revision 2 Page 2 Of 4 Pages t

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1) Pertinent information (i.e. what happened, what may happen, what hazards are present, whac can be done, etc.).

2) Available protective and monitoring equipment and possible rescue devices.

3) Backup assistance from others nearby or request assistance.

b. Evaluate available information and discuss best apparent rescue approach with the Radiological Manager prior to the rescue attempt if practicable.

c. If available, other personnel in the area should render assis-tance and monitor the time rescuer (s) is (are) in a high radiation area.

d. Perform rescue mission consistent with good first aid practices and as dictated by dose rates encountered and the limits discussed above.

Note: Work as quickly and safely as possible while avoiding sources of high dose rates within the rescue area, whenever practicable,

e. Limit exposure of rescuers in accordance with Attachment "C",

Condition 3.

k 2. Organized search and rescue following a personnel accountability check.

a. Upon being notified that personnel are missing, the Security /

l Administration / Logistics Coordinator will page on the Gai-i tronics to determine if missing personnel may be unharmed, but isolated in some area of the plant or plant site,

b. The Emergency Director will direct the Radiological Manager and I the Maintenance and OSC Coordinator to assemble a Rescue and Reentry Team,

c. The Rescue and Re-Entry Team will quickly gather needed equip-ment and assemble at the designated Point of Re-Entry.

d. The Rescue and Re-Entry Team will conduct a search, keeping all members of the team in the same general area (i.e. frequent visual checks, each searching independently).

e. When a victim or victims are located, the team will notify the i Technical Support Center immediately. This should be followed l up with additional relevant information (i.e. nature and extent

! of injuries, dose rates encountered, etc.) as this information

! develops.

Procedure Number EPIP 5.7.15 Date ) - dl' b b Revision 2 Page 3 Of 4 Pages l

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f. The exposure of rescuers shall be limited to as low as reason-ably achievable and not exceed the appropriate level specified in Attachment "C".

g. Treat victims in accordance with EPIP 5.7.24, Medical.

B. Entry And/Or Re-Entry Activities.

1. Actions to correct or mitigate further station degradation,

a. The Control Room or Technical Support Center will request assistance from the Operations Support Centers or the Emergency Operations Facility by specifying:

1) The problem and its location.

2) The corrective actions to be undertaken.

b. The Entry Team will quickly gather needed equipment and assemble at the designated Point of Entry.

c. The Entry Team will preplan activities prior to entry into the problem area and should work as quickly as is consistent with safety and time constraints.

d. The Entry Team should perform only those assigned duties

(' intended to control the emergency, but as dictated by the dose rates encountered and the appropriate emergency exposure limits specified in Attachment "C".

e. The Team will report progress and/or completion of the assigned work to the Control Room or Technical Support Center by radio, Gaitronics, or other available communications.

IX. ATTACHMENTS A. Attachment "A", Protective Equipment.

B. Attachment "B", Emergency Rescue Equipment.

C. Attachment "C", Emergency Dose Limits.

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Procedure Number EPIP 5.7.15 Date ) ~2)l -3 2h Revision 2 Page 4 Of 4 Pages

COOPER NUCLEAR STATION OPERATIONS NANUAL ATTACHMENT "A" EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.7.15 RESCUE AND RE-ENTRY ,

i PROTECTIVE EQUIPMENT J

ITEM DESCRIPTION UNIT QUANTITY

1. High range self-reading dosimeter. Each 1/ Member

2. Personal TLD. . Each 1/ Member

3. Protective clothing, as required. Each 1/ Member 4 Respiratory protection equipment, as required. Each 1/ Member

5. Portable 2-way radio (if necessary). *Each 1/ Team

6. First-aid kit (rescue only). Each 1/ Team e

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COOPER HUCLEAR STATION OPERATIONS MANUAL ATTACHMENT "B" EMERCENCY PLAN IMPLEMENTTNG PROCEDURE 5.7.15 RESCUE AND RE-ENTRY ,

EMERCENCY RESCUE EQUIPMENT ITEM DESCRIPTION UNIT QUANTITY

1. Wrecking bars. Each 2

2. Bolt cutters. Each 2

3. Hacksaw and blades. .

Each 2

4. Ratchet-type chainfall hoist. Each 1

5. Cable sling, 1/2" x 3'. Each 2

6. Cable sling, 1/2" x 6'. Each 2

7. Hydraulic jack, 1 1/2 ton. Each I

8. Hydraulic jack, 5 ton. Each 1

9. Sledge hammer, 6f. Each ,

2

10. Sledge hac:mer,12#. Each 2 k Each 1

11. Porta power.

12. Web slings (2" - 20' long, 2" - 10' long). Each 4

13. Sound powered phones. Fair 1

14. Safety harness and line. Each -1

15. Fire axe. Each 1

16. Crow bar. Each 1

17. 200' - 3 part block and tackle. Each 1

18. Battery lanterns. Each 2

= 0

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COOPER NUCLEAR STATIOt4 OPERATf0NS MANUAL ATTACliMENT "C" EMERCENCY PLAN IMPLEMENTINC PROCEDURE 5.7.15 RESCUE AND RE-ENTRY EMERGENCY DOSE LIMITS CONDITION CRITERIA DOSE LIMIT 1 Dose limit applied to emergency 5 Rem to the whole body response facility personnel.

2 Dose limit applied to in-plant 25 Rem to the whole body activities required to correct or mitigate further station degradation.

3 Immediate evaluation and action 75 Rem to the whole body required for saving of life.

When efforts are completed, revert to limits 1 and 2 above, as appropriate.

NOTE: If the limits specified in Condition 2 or 3 are involved, the following considerations should be made:

1. Female employees of child-bearing age should not be allowed to participate.

2. All practical protective measures available to limit such an exposure should be utilized.

i

3. Concurrence of the individual (s) involved (i.e., voluntary risk acceptance) shall be obtained.

4 The probability of success should be balanced against the exposure limit.

5. The individual's familiarity with the task to be performed should be reviewed.

6. The speed with which the individual can perform the task should be evaluated.

7. The amount of radiation the victim has already received should be estimated.

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Procodore Ne-be- FPTP 5.7 15 Dara ne 4-4-a  ? o -n 1 nr i e-- .

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, . e..e l COOPER NL' CLEAR STATION OPERATIONS MANUAL EMERCENCY PLAN IMPLEMENTING PROCEDURE 5.7.25 RECOVERY OPERATIONS ,

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I. PURPOSE The purpose of this procedure is to prescribe those recovery operations necessary to identify the extent of station damage and radiological conta-mination (if any) and return the station to an operating status in compli-ance with the Technical Specifications.

II. DISCUSSION

. Recovery operations will normally commence once an event has been down-graded to the ALERT level or at such time that conditions are acceptable.

As indicated in the CNS Emergency Plan, recovery -operations will occur in two phases. Phase I activities are performed by the emergency response organization and are designed to terminate the emergency, mitigate or eliminate potential hazards to the public and station personnel, and restore the station to a safe and stable condition.

Phase II recovery operations, which are addressed in this procedure, include the longer term efforts required to return the station to a normal operating status following damage associated with a major emergency. While such damage could occur under an ALERT classification, it is anticipated 7

that Phase II recovery operations would be only following a ' SITE AREA EMERGENCY or a CENERAL EMERGENCY.

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III. REFERENCE MATERIAL A. CNS Emergency Plan.

B. NUREC 0654, Revision 1.

C. NUREG 0737.

IV. PREREOUTSITES A. Radiation levels are stable or decreasing with time.

B. Releases of radioactive materials to the environment have ceased or are controlled within permissible license limits.

C , Fire, flooding, or similar emergency conditions no longer constitute a hazard to the station or station personnel.

D. Measures have been successfully instituted to correct or compensate for malfunctioning equipment.

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s Revised By/Date Reviewed By/Date Approved By/Date Rev. Procedure Page 1 Of D. Whitman 2/3/83 J. Sayer 2/18/83 /(ifd!>4vs 2,2 /. p3 2 5.7.25 3 Pages

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• 1 V. LIMITATIONS 1

A. None.

VI. PRECAUTIONS A. Following any emergency involving radiological hazards, exposure to personnel should be kept as low' as reasonably achievable consistent with the nature of the recovery operation-required.

l B. Recovery operations commence with the station in a controlled, stable condition. No action is to be taken which might jeopardize this condition without the approval of the Recovery Director.

VII. EOUIPMENT A. Recovery operations will be performed-using existing station equipment (which includes the post accident sampling system) to the maximum extent possible. Special and/or additional equipment will be obtained when required to complete the recovery operation in a safe and effi-cient manner.

VII

I. PROCEDURE

A. Determination Of Station Damage And Contamination.

1. Initial station survey.

a. For known or suspected significant station damage, and at the discretion of the Recovery Director, survey teams will be formed consisting of Operations, Engineering, Maintenance, and Health Physics personnel.

These teams, following pertinent guidance contained in EPIP b.

5.7.15, Rescue And Re-Entry, will perform an organized search of the station to ascertain the extent of physical' damage and areas of contamination /high radiation. The results of these surveys will be used by the Recovery Director and the Radio-logical Controls Manager in planning the detailed surveys I described below.

2. Detailed station surveys.

I i

a. Using the.information obtained above, the Radiological Controls j , . . Manager will dispatch properly equipped Health Physics Techni-cians to perform detailed surveys of any areas known to contain l radiological hazards. Each area shall be posted and barriers i

shall be erected. Station Radiological Survey Maps will be i

used to record the boundaries of these areas. Station Chemists may be dispatched to take and analyze a post accident sample should conditions dictate. Provisions have been made to take and analyze coolant and containment samples within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of the time a decision is made that samples are required.

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b. Under the Recovery Director, the Technical Support Manager will evaluate any physical damage found and analyze pertinent station instrumentation to ascertain what station systems /com-ponents are inoperable and, if possible, the cause. Detailed lists of this information will then be generated and made as specific as possible.

B. Repair, Modification, And Decontamination.

1. Planning.

a. Under the direction of the Recovery Director, pertinent recovery organization members, as well as selected off-site personnel, will address the planning and coordination of the recovery effort. Such activities as the repair and maintenance of existing station system / components,' modification, installation, and decontamination, as well as determining the need for portable shielding and special procedures will be discussed,

- prioritized, and planned.

b. The Scheduling / Planning Manager will develop an overall schedule to guide the recovery effort.

2. Training.

a. In consideration of the situation to be handled, special training material will be developed and training conducted for special work tasks to the maximum extent.

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3. Recovery implementation.

a. Once the plant problems are defined, the recovery plan final-ized, special procedures developed, personnel trained, and the necessary equipment allocated, actual recovery operations will begin. Notwithstanding any special requirements in place at the time, wherever practicable, normal station practices will be followed concerning maintenance, repair, modification, decontamination, and personnel exposures control.

j b. During the recovery operation, the Radiological Controls Manager will periodically estimate total population exposure, in coordination with state and federal authorities,

c. As the recovery operation proceeds, any unforeseen problems

! - which are encountered will be evaluated and factored into the

!' recovery plan. The schedule will then be adjusted accordingly.

d. Upon completion of the recovery effort. Technical Specification compliance will be verified prior to recommencing normal station operations.

IX. ATTACHMENTS

/ A. None.

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Preecertu re Nun:1.. r FPIP 5.7.P. Date Ii' :l- 3 Reviifon 2 l':w .' 3 of 3 P. <-