ML20052H554

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Public Version of Revised Plant Manager Emergency Plan Procedures,Including Procedures PMP 2080 EPP.001 Re Emergency Plan Activation & Condition Classification & PMP 2080 EPP.012 Re Initial Offsite Notification
ML20052H554
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/30/1982
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17319B335 List:
References
PROC-820430-01, NUDOCS 8205210208
Download: ML20052H554 (61)
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PMP EPP INDEX t

INDIANA & MICHIGAN POWER COMPANY CONALD C. COOK NUCLEAR PLANT PLANT MANAGER PROCEDURE Index Identification 79 g ,' RevisionNo.l Cements

.lumcer .*nd Data i i

PMP 2080 EPP.001 Emergency Plan Activation Revision 2 -

and Condition Classification 4-27-82 EPP.002 Unusual Event CANCELLED 10-29-81 EPP.003 Alert CANCELLED 10-29-81 EPP.004 Site Emergency CANCELLED 10-29-81 EPP.005 General Emergency CANCELLED 10-29-81 EPP.006 Initial Dose Assessment lev. 2 (Gaseous) 4-27-82' EPP.007 Initial Release Assessments Revision 0 TP-1,2-23-82 Exp NA (Liquid) 4-1-81 EPP.008 Calling Off-Duty Plant Revision 1 -

Personnel 4-29-82 i

EPP.009 Fire Emergency Guidelines Revision 0 i 4-1-81 i EPP.010 Toxic Gas Release Guidelines Revision 0 4-1-81 EPP.011 Natural Emergency Guidelines Revision 0 ,

4-1-81  ;

EPP.012 Initial Off-Site Notificatioq Revision 1.!  ;

I J-27-82 I  ;

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Pica 1 8205210208 820512 .

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PDR ADOCK 05000315 .

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o o PMP EPP INDEX INDIANA i MICHIGAit POWER CCMPAtlY DCNALD C. CC0K NUCLEAR PLANT PLANT MANAGER PROCEDURE Index I

Revision No.I _

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l Identification Numcer And Oate l j PMP 2080 EPP.013 Outies of the Individual Who Revision 0 Discovers an Emergency 4-1-81 Condition EPP.014 Personnel Injury Revision 0 10-27-81 EPP.015 Responsibility of the On-Site Revision 1 Emergency Coordinator 4-29-82 EPP Appendfx A Telephone Numbers for Key Revision 1 Plant Personnel 3-23-82 EPP Appendix B Hospital Assistance Plan Revision 2 3-31-81 EPP Appendix C Radiological Supplement Revision 0 4-1-81 I

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INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET Procedure No. PMP 2080 EPP.001 Revision No. 2 TrrLE EMERGENCY PLAN ACTIVATION AND CONDITION CLASSIFICATION SCOPE OF REVISION Rev. 1: Complete Revision to clarify Operations responsibilities in case of emergency.

Rev. 2: Incorporated Temporary Sheets. Clarified Emergency Condition categories and activation of emergency centers.

DCR MAY 0 51981 i

SIGNATURES ORIGINAL Rev.1 REV.2 Rev.S l PREPARED BY ,jj b [ /

ASSURANCE ~ U INTERTACING DEPARTMENT (/ U'

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I/ /Il A DEFARTMENT HEAD APPROVAL N.A. A/. 4. M4 PLANT NUCIIAR SAFITY COMMITTEE ]

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DATE OF ISSUE 3-31-81 10-27 9l h"S7~ Ik rarm No PW 2C101- tav. 3 9

O % e PMP 2080 EPP.001 LIST OF EFFECTIVE PAGES Page Number Revision Number And Date Page 1 of 30 Revision 2,4/27/82 Page 2 of 30 Revision 2,4/27/82 Page 3 of 30 EXHIBIT A Revision 2,4/27/82 Page 4 of 30 EXHIBIT A Revision 2,4/27/82 Page 5 of 30 EXHIBIT A Revision 2,4/27/82 Page 6 of 30 EXHIBIT A Revision 2,4/27/82 Page 7 of 30 EXHIBIT A Revision 2,4/27/82 Page 8 of 30 EXHIBIT A Revision 2,4/27/82 Page 9 of 30- EXHIBIT A Revision 2,4/27/82 Page 10 of 30 EXHIBIT A Revision 2,4/27/82 Page 11 of 30 EXHIBIT A Revision 2,4/27/82 Page 12 of 30 EXHIBIT A Revision 2,4/27/82 Page 13 of 30 EXHIBIT A Revision 2,4/27/82 Page 14 of 30 EXHIBIT A Revision 2,4/27/82 Page 15 of 30 EXHIBIT A Revision 2,4/27/82 Page 16 of 30 EXHIBIT A Revision 2,4/27/82 Page 17 of 30 EXHIBIT A Revision 2,4/27/82 Page 18 of 30 EXHIBIT A Revision 2,4/27/82 Page 19 of 30 EXHIBIT A Revision 2,4/27/82 Page 20 of 30 EXHIBIT A Revision 2,4/27/82 Page 21 of 30 EXHIBIT A Revision 2,4/27/82 Page 22 of 30 EXHIBIT A Revision 2,4/27/82 Page 23 of 30 EXHIBIT A Revision 2,4/27/82 Page 24 of 30 EXHIBIT A Revision 2,4/27/82 Page 25 of 30 EXHIBIT A Revision 2,4/27/82 Page 26 of 30 EXHIBIT A Revision 2,4/27/82 Page 27 of 30 EXHIBIT A Revision 2,4/27/82 Page 28 of 30 EXHIBIT A Revision 2,4/27/82 Page 29 of 30 EXHIBIT A Revision 2,4/27/82 Page 30 of 30 EXHIBIT A Revision 2,4/27/82 l

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PMP 2080 EPP.001 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT EMERGENCY PLAN ACTIVATION AND CONDITION CLASSIFICATION 1.0 OBJECTIVES The objectives of this procedure are to ensure that proper actions are taken to place the plant in a safe condition; minimize the hazard to the public and plant personnel; assist injured personnel; and obtain adequate support to cope with the emergency.

2.0 RESPONSIBILITIES 2.1 The Shift Supervisor is responsible for initiation of this pro-cedure.

2.2 The Shift Supervisor shall act as the On-Site Emergency Coordi-nator (OSEC) until relieved of this responsibility as described ' -

in PMP 2080 EPP.015, Responsibilities of the On-Site Emergency Coordinator.

2.3 The Shift Technical Advisor (STA) is responsible for re-i viewing and making an independent diagnosis of plant con-

! ditions. The STA then determines whether operator re-sponses are correct and advises the SS/0SEC accordingly.

3.0 APPLICABILITY This procedure is to be initiated any time the S.S. recognizes the existence of, or potential for, off-normal conditions which may di-rectly lead to, meet, or exceed the Emergency Action Levels shown in Exhibit A.

4.0 INSTRUCTIONS 4.1 Implement Abnormal and/or Emergency Operating Procedures as dictated by plant conditions or indications.

4.2 In the event of:

4.2.1 Radiological Hazard requiring personnel to evacuate their work areas:

4.2.1.1 Evacuate personnel by PA if the condition is local, or 4.2.1.2 Evacuate by use of the Nuclear Emergency Alarm, if the condition includes signifi-cant portions of the plant, and initiate PMP 2081 EPP.005 Personnel Evacuation Page 1 of 3'O Rev. 2, J/27/32

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~?' PMP 2080 EPP.001 4.2.2 Fire or Explosion: Sound the fire alarm and an- l nounce the condition over the P.A. Implement i PMP 2080 EPP.009, Fire Emergency Guidelines.

4.2.3 Personnel Injury: Implement PMP 2080 EPP.014, Personnel Injury.

- 4.2.4 Toxic Gas Release: Implement PMP 2080 EPP.010, i Toxic Gas Release.

4.2.5 Gaseous Release: Determine any off-site dose effects as per PMP-2080 EPP.006. Initial Dose Assessments (Gaseous).

4.2.6 Liquid Release: Notify the Chemical Lab to im-plement PMP 2080 EPP.007, Initial Release As-sessments (Liquid).

t 4.7 . 7 Natural Emergency: Implement PMP 2080 EPP.011, Natural Emergency Guidelines.

4.3 Classify the Emergency Condition, using Exhibit A, according to the highest classification (Unusual Event, Alert, Site Emerge cy or General Emergency) the condition exceeds.

j 4.3.1 In the event of :

4.3.1.1 An Alert condition: Activation of the .

Technical Support Center (TSC) is required.

4.3.1.2 A Site Emergency: Activation of the Emer-gency Control Center, Joint Public Informa-tion Center, the American Electric Power Emergency Response Organization, and the TSC is required.

4.3.1.3 A General Emergency: Activation of the above centers is required. Additionally, the Berrien County Sheriff's Department and the Michigan State Police should be advised to recommend sheltering within a two mile radius of the plant and five miles downwind.

NOTE See PMP 2080.EPP.015, Exhibit A, Responsibility of the On-Site Emergency Coordinator for a listing of on-site and.off-site actions for each emergency condition.

4.4 Implement PMP 2080 EPP.008, Calling Off-Duty Plant Personnel.

, 4.5 Implement PMP 2080 EPP.012, Initial Off-Site Notifications if the Plant Manager or Operations Superintendent cannot be reached promptly.

Page 2 of 30 Rev. 2, 4/27/82

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e i PMP 2080 EPP.001 q 4.6 Notify the NRC via red telephone within I hour. Be prepared to provide one person full time to communicate information over this phone to the NRC if so requested.

4.7 Be prepared to provide updates or additional information to the Michigan Department of Public Health if so requested.

4.8 Start trend blocks 12 through 16 on the Prodac. Start the TSC printers.

4.9 Upon arrival of support personnel:

4.9.1 Activate the Technical Support Center Operation as per PMP 2081 EPP.020 by designating an interim TSC Manager.

4.9.2 The SS shall continue to act as the On-Site Emer-gency Coordinator until appropriately relieved as per PMP 2080 EPP.015, Responsibilities of the On-Site Emergency Coordinator.

4.10 Continue to monitor plant conditions:

4.10.1 Ensure notification of the Berrien County Sheriff's Department, Michigan State Police, and NRC if emer-gency classification changes.

4.10.2 If significant state, local, and federal sources have been activated, attempt to obtain concurrence between all parties prior to de-escalation and entry into the recovery phase of operations.

4.11 Terminate use of this procedure when plant conditions are safe and/or within normal operating parameters.

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i PMP 2080 EPP.001 ;

EXHIBIT A EMERGENCY CONDITION CATEGORIES ECC-1 Aircraft Crash or Missiles from any source ECC-2 Control Room Evacuation ECC-3 Earthquake ECC-4 Explosion ECC-5 Fire ECC-6 Seiche ECC-7 Security Threat or Compromise ECC-8 Tornado or Severe Winds ECC-9 Toxic Gas ECC-10 Loss of AC Power ECC-11 Loss of DC Power ECC-12 Loss of Plant Shutdown Functions ECC-13 Other Conditions or Systems required by Tech. Specs.

ECC-14 Fission Product) and Loss of Coolant Accident Barriers )

ECC-15 Fuel Damage ECC-16 Loss of Secondary Coolant uCC-17 Steam Generator Tube Rupture ECC-18 Fuel Handling Accident ECC-19 Radiation Releases ECC-20 Personnel Injury ECC-21 Other Hazards ECC-22 Loss of Control Room Annunciators / Alarm ECC-23 Liquid Release l

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PMP 2080 EPP.001 EXHIBIT A ECC-1: AIRCRAFT CRASH OR MISSILES FROM ANY SOURCE Unusual Event

1. Aircraft crash on-site.
2. Unusual aircraf t activity by SS's judgment.

Alert

1. Aircraft crash in the protected area or switchgear 345KV, 765KV or Emergency po-wer yards.
2. Missiles from any source landing in the protected area.

i Site Emergency 4

1. Aircraf t crash which, in the judgment of the SS, affects the Aux. Building or Containment.
2. Missile damage which, in the judgment of the SS, causes damage to safe shutdown equipment such

) that it cannot fulfill its safety function.

General Emergency N/A l

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PMP 2080 EPP.001 EXHIBIT A ECC-2: CONTROL ROOM EVACUATION Unusual Event N/A 1

Alert

1. Evacuation of Control Room is anticipated.
2. Evacuation of Control Room is required with control of unit shutdown systems at local station established within 15 minutes.

Site Emergency

1. The Control Room is evacuated and control of all the following systems or equipment is not esta-blished within 15 minutes:
a. Auxiliary Feedwater and
b. Boric Acid Transfer Pumps and
c. Pressurizer Heaters and
d. Atmospheric Steam Dump Valves and
e. Charging Pumps and
f. Charg ng Flow Control Valve and
g. Letdown Isolation Valves.

General Emergency N/A i

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e s PMP 2080 EPP.001 EXHIBIT A ECC-3: EARTHQUAKE Unusual Event

1. Any actuation of seismic instrumentation that is verified to be the result of an earthquake.

Alert

1. Earthquake that is readily felt but does not cause observable damage to the plant or sur-rounding structures.

Site Emergency

1. Earthquake that is of sufficient magnitude to cause significant damage to the plant or sur-rounding structures. It may cause an auto-matic trip of the reactor and/or turbine due to equipment or instrumentation malfunctions.

General Emergency N/A Page 7 of 30 Rev. 2, a/27/82

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PMP 2080 EPP.001 EXHIBIT A ECC-4: EXPLOSION Unusual Event

1. Any explosion Near or On Site Alert
1. Explosion damage to the plant affecting unit operation or offsite power supplies. ,

Site Emergency

1. Explosion damage which, in the judgment of the SS, causes damage to safe shut-down equipment such that it cannot ful-fill its safety function.

i General Emergency N/A d

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o e PMP 2080 EPP.001 1 EXHIBIT A t i

ECC-5: FIRE Unusual Event

1. Any significant fire lasting more than 10 minutes on plant site (protected area) g switchgear yards.

I Alert

1. Fire potentially affecting safety systems as judged by the SS.

Site Emergency

1. Fire affecting any safety system as judged by i ,

the SS.

General Emergency ,

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PMP 2080 EPP.001 EXHIBIT A ECC-6: SEICHE 4 Unusual Event

. 1. Lake level deviation, from operating levels (on screen house water level monitor) by more than 5 ft. up or down but less than 8 ft. up or down.

l Alert

1. Screen house level indication shows a deviation between 8 ft. and 11 ft.

Site Emergency

1. Screen house level indication shows a deviation greater than 11 ft.

General Emergency N/A 4

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1 PMP 2080 EPP.001 EXHIBIT A ECC-7: SECURITY THREAT OR COMPROMISE ~

l Unusual Event r 1. Security threat, attempted entry, or attempted sabotage in the judgment of the SS and/or shift security supervisor.

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1. Ongoing security compromise in the judgment of ithe SS and/or shift security supervisor. ,

Site Emergency

1. Loss of physical control of the facility is likely

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in the judgment of the SS based on the advice of 1

the shift security supervisor.

General Emergency

1. Loss of physical control of the facility as ceter-mined by the S.S. based on advice from the shift se-curity supervisor.

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PMP 2080 EPP.001 EXHIBIT A l

ECC-8: TORNADO OR SE\E.9E WINDS Unusual Event

1. Any tornado near or on site.

Alert

1. Tornado damage to the plant affecting unit operation or offsite power supplies.
2. Sustained winds in excess of 85 mph.

Site Emergency

1. Sustained winds in excess of 100 mph.

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General Emergency N/A J

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PMP 2080 EPP.001 EXHIBIT A ECC-9: T0XIC GAS Unusual Event

1. Near or on-site toxic or flammable gas re-lease.

Alert

1. Entry into the protected area of lethal or concentrated volumes of toxic or flammable gas.

Site Emergency

1. Entry into vital areas of lethal or con-  ;

centrated volumes of toxic or flammable gas which in the judgment of the SS af-fects operation of the safe shutdown equip-ment.

General Emergency N/A I

Page 13 of 30 Rev. 2, 4/27/82

PMP 2080 EPP.001 EXHIBIT A ECC-10: LOSS OF AC POWER Unusual Event

1. Loss of all off-site power or loss of all on-site AC power supplies.

Alert

1. Loss of all off-site power supplies with a) rapid increase of primary to secondary tube leakage to several gpm, and b) off-scale readings on R-15 (SJAE Monitor), and c) large increase on Steam Generator Blow-down Monitor R-19, and d) confirmation of high radiation levels.
2. Loss of off-site power and loss of on-site AC power capacity as indicated by failure of Emergency Diesel Generators to start, and load ampmeters for buses 1A, IB,1C, ID for Unit I and buses 2A, 2B, 2C, 2D for Unit 2 are at zero.

Site Emergency

1. Loss of off-site power is indicated by all ampmeters for the 4160 buses reading 0 amps; and Steam Generator tube rupture indicated by readingsontheCondenserAirgjectorMoni-tor (R-15) greater than 1 X 10 cpm and these readings have been confirmed; and SI' initiated by the Engineered Safety Fea-l ture Actuation System i
2. Ampmeters for 4160V buses all read 0 amps, and Voltmeters for 4160 V buses read 0 volts, and Above conditions last for more than 15 minutes.

I General Emergency N/A Page 16 of 30 Rev. 2, 4/27/82

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PMP 2080 EPP.001 EXHIBIT A

> ECC-11: LOSS OF DC POWER (A & B TRAIN BATTERIES)

Unusual Event N/A Alert

1. All battery voltmeters read zero, and_

board indicating lights are off.

Site Emergency

1. All battery voltmetars indicate 0 volts and no indication of availability of backup DC voltage, and the condition lasts for more than 15 minutes.

General Emergency N/A Page 15 of 30 1

Rev. 2, 4/27/82

PMP 2080 EPP.001 EXHIBIT A ECC-12: LOSS OF PLANT SHUTDOWN FUNCTIONS Unusual Event

1. Plant shutdown as required by Technical Specification for loss of essential assess-ment or communication capabilities, such as:
a. Reactor trip instrumentation .
b. Engineered Safety Feature Actuation Instrumentation
c. Radiation Monitoring Channels
d. Post Accident Monitoring Channels
e. Essential , communication to off-site authorities including back-up capability.

Alert

1. Loss of all Residual Heat Removal (RHR) pumps, heat exchangers and/or controls, with loss of all auxi-liary feedwater capacity needed.

' Site Emergency

1. Loss of all the following systems, equipment or controls:
a. Auxiliary Feedwater System
b. Boric Acid Transfer Pumps
c. Pressurizer Heaters
d. Atmospheric Steam Dump Valve
e. Charging Pumps
f. Letdown Isolation Valves or Letdown Flow Control General Emergency N/A i

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ECC-13: OTHER CONDITIONS OR SYSTEMS REQUIRED BY TECHNICAL SPECIFICATIONS Unusual Event

1. ECCS initiation by valid signal as listed in Technical Specifications Tables 3.3-3 and 3.3-4.
2. Environmental Technical Specification 2.4.1 (liquid waste effluent limits) or 2.4.3 (gaseous effluent limits) possibly have been exceeded with verification .

by Radiation Protection analysis, as indicated by readings on any of:

a. Condenser air ejector monitor (R-15) 0 exceeds 1 X 10 cpm
b. WDS liquid effluent monitor (R-18) exceeds 1 X 10 cpm
c. Blowdown Liquid Monitor (R-19) 4 exceeds 1 X 10 cpm -
d. ESW monitors (R-20 and R-28) exceed 300 cpm
e. Blowdown treatment monitor (R-24) exceeds 7 X 10' cpm
f. Unit vent air particulate (R-25) exceeds 1.3 X 10' cpm i
g. Unit vent gas monitor (R-26) exceeds

1 1 X 10' cpm (fresh gas) or 1 X 103 cpm (old gas) l l

Page 17 of 30 Rev. 2, 4/27/82 1

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PMP 2080 EPP.001 EXHIBIT A ECC-13: OTHER CONDITIONS OR SYSTEMS REQUIRED BY TECHNICAL SPECIFICATIONS (CONT'D)

Use the "old gas" criterion for:

1, Release originating from a gas decay tank shown by unexplained GDT pressure decrease seen on recorders MR058 or MR059.

2. Release originating from a CVCS holdup tank, shown by unexplained CVCS holdup tank header pressure de-crease (QPA 600) and pos-sibly excessive cover gas demand.

Use " fresh gas" condition for:

1. Releases from sources other than those listed above.
h. Unit vent radio-iodine (R-32) exceeds 2 X 103 cpm NOTE Before applying this criterion, ensure the " window" selector is set to .4, and the " input mode" (iodine) selector is set to N.
3. Abnormal coolant temperature, pressure, and/or abnormal fuel temperatures exceeding Technical Specification 2.1.1 or 2.1.2 safety limits exceeded and exceeding Limiting Safety Systems Settings listed in Technical Specification 2.2.1, without a unit trip, with the excursion confirmed.

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't PMP 2080 EPP.001 i EXHIBIT A ECC-13 OTIER CONDITIONS OR SYSTEMS REQUIRED BY TECHNICAL SPECIFICATIONS (CONT'D)

4. Containment integrity Technical Specifications exceeded with a unit shutdown required by the associated Technical Specification.

, 5. Engineered Safety Features or Fire Protection System causing unit shutdown due to associated action statement in the applicable Technical Specification caused by malfunction, procedural error, or personnel error.

6. Reactor Coolant Leakage exceeds Tech. Spec. 3.4.6.2 and the Unit is shut down for this reason.

Alert

1. Radiation monitoring channels exceed indicated levels with confirmational analysis by radiation protection.
a. R-1 (Control Room Area Monitor) exceeds 10mR/hr.
b. R-3 (Radiochemistry Lab) exceeds 100 mR/hr.
c. R-4 (Charging Pump Room) exceeds 1 R/hr.
d. R-5 (Spent Fuel Area) exceeds 100 mR/hr.
e. R-6 (Nuclear Sampling Room) exceeds 1 R/hr.

, f. R-26 (Unit Vent Gas Monitor) exceeds 10$epm.

2. Failure of the reactor trip logic to provide a reactor trip when a signal is received for a setpoint as listed in Technical Specification Table 2.2-1, with rod indication showing no trip has occurred and ma'nual trip circuitry fails to provide a trip.
3. Analysis of effluent samples confirms that instantaneous limits stated in Environmental Technical Specification 2.4.1 and 2.4.3 have been exceeded by a factor of 10.

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PMP 2080 EPP.001 EXHIBIT A ECC-14: FISSION PRODUCT BARRIERS / LOSS OF COOLANT Unusual Event

1. Technical Specification Limits 3.4.6.2a, b, c, & d are exceeded and the unit is shutdown for these rea-sons.
2. Pressurizer safety valves or power operated relief valves stay open as indicated by temperature in the line and by the acoustic monitor.

Alert

1. Rapid increase of primary to secondary leakage to '

j several gpm with off-scale readings on steam jet air ejector montitor (R-15) and large increase on steam generator blowdown monitor R-19 with confirmation of high radiation levels and with loss of off-site power.

2. Large primary to secondary leak rate likely as indicated i by an increase to maximum of charging flow and off-scale radiation tradings on R-15 and R-19 confirmed.
3. Steam line break as indicated by a Safety Injection (SI) for Technical Specification listed in Table 3.3-4 with primary to secondary leak rate in excess of 10 gpm as calculated by the most recent leak rate.
4. Primary Coolant leak rate is too high for one charging I

pump to maintain level in pressurizer above 22% (leak rate is greater than 50 gpm over that total allowed in

, Technical Specification 3.4.6.2), or a second charging pump has to be started to maintain pressurizer level above 22%.

Site Emergency

1. Safety Injection (SI) initiation followed by contain-ment spray (and Phase B) initia~ tion due to high (2.9 psig) containment pressure, with increasing contain-ment sump levels and increasing radiation levels in containment.

General Emergency i 1. Loss of 2 out of 3 fission product barriers with a

! potential loss of the third barrier.

a. Confirmed loss of core geometry, and
b. Confirmed loss of Reactor Coolant System integrity, alLd i
c. High potential for loss of Containment integrity Page-20 of 30 Rev. 2, 4/27/82

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PMP 2080 EPP.001 EXHIBIT A ECC-15: FUEL DAMAGE Unusual Event

1. Unit is shutdown as required by Tech. Spec. 3.4.8. )
2. An increase in failed fuel detector gross gamma readings to off-scale and by chemical laboratory analysis indicating an increase of greater than

.1% failed fuel within 30 minutes.

Alert

1. Very high coolant activity (exceeds 300 pCi/cc dose equivalent Iodine).
2. A sudden increase in possible failed fuel as indicated by a rapid gross gamma reading in-crease on failed fuel monitor and rapid increase on Charging Pump Room Area Monitor radiation levels.
3. Loss of flow in one or more reactor coolant loops initiates a reactor trip (manual below 50% power) foi. lowed by specific activity of the primary cool-ant increasing to greater than 300 pCi/cc equiva-lent of I-131.

Site Emergency

1. Core saturation curve or core subcooling monitor indicates subcooling of 0*F or less and this reading is confirmed.

General Emergency N/A i

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PMP 2080 EPP.001 EXHIBIT A ECC-16: STEAM LINE BREAK Unusual Event

1. Steam generator safety valves, or power operated relief valves stay open with significant gpm primary to second-ary leakage existing as indicated by off-scale readings on condenser air ejector and gland steam seal radiogas monitors.

Alert

1. Steam line break as indicated by a safety injection with primary to secondary leak rate in excess of 10 gpm as per latest calculated rate.
2. Steam line break with failure of steam line isolation valve to close as indicated by continued high steam line flow on the flow meters.

Site Emergency

1. Steam line break as indicated by any of following SI conditions: High steam line flow coincident with steam line pressure or coincident with Low Tavg, or high differential pressure between steam generators (both units), or low pressurizer press (both units) as per Technical Specification Table 3.3-4 setpoints, and
2. Calculated primary to secondary leak of 50 gpm, and
3. Fuel damage as indicated by Reactor Coolant dose equivalent I-131 greater thant 300 pc/g.

General Emergency N/A Page 22 of 30 Rev. 2, 4/27/82

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.i PMP 2080 EPP.001 EXHIBIT A ECC-17: STEAM GENERATOR TUBE RUPTURE Unusual Event

1. Tech. Spec. 3.4.6.2.c exceeded.

Alert

1. Primary to secondary leak rate in excess of 10 gpm as per latest calculated rate with steam line break as indicated by a Safety Injection (SI) for Technical Specification listed in Table 3.3-4.
2. Rapid increase of primary to secondary leakage to several gpm with off-scale readings on Steam Jet Air Ejector Monitor (R-15) and large increase on Steam Generator Blowdown Monitor (R-19) and confirmed high radiation levels with loss of off-site power.
3. Large primary to secondary leak rate likely as in-dicated by an increase to maximum of charging flow and off-scale radiation readings on R-15 and R-19 confirmed.

Site Emergency

1. a. Steam generator tube rupture indicated by read-ing on the Steam Jeg Air Ejector Monitor (R-15) greater than 1 X 10 cpm and these readings have been confirmed; and i
b. SI initiated by the Engineered Safety Feature Actuation System; and
c. Loss of off-site power is indicated by all ampmeters f;r the 4160 volt buses reading 0 amps.
2. a. Calculated primary to secondary leak of 50 gpm; and l

b.

Steam line break as indicated by any of the follow-ing SI initiating conditions: High steam line flow coincident with low steam line pressure or coinci-dnet with Low Tavg, or high differential pressure between steam generators (both units) or low pres-surizer pressure (both units) as per Technical Spec-ification Table 3.3-4 setpoints, and

c. Fuel damage indicated by Reactor Coolant dose equi-valent I-131 greater than 300 pc/g.

General Emergency N/A Page 23 of 30 Rev. 2, 4/27/82

PMP 2080 EPP.001 EXHIBIT A ECC-18 FUEL HANDLING ACCIDENT Unusual Event N/A Alert

1. If an apparent accident occurs and containment area monitor (R-2) shows a reading 100 times .

previous reading while handling fuel during re-fueling, g R-5 (spent fuel area monitor ex-ceeds 100 times previous reading while moving fuel or objects over spent fuel pit. Analysis confirms fuel failure by detection of fission I products.

Site Emergency

1. A heavy object (Technical Specification 3.9.7) impacts spent fuel while the spent fuel is in containment or in the spent fuel pit.
2. Water level in the vessel or spent fuel pit drops below the top of the fuel.

General Emergency N/A Page 24 of 30 Rev. 2, 4/27/82

i PMP 2080 EPP.001 EXHIBIT A ECC-19: RADIATION REI. EASE Unusual Event See also ECC-13 for classifications of specific RMS

, monitor readings.

Alert See also ECC-13 for classifications of specific RMS monitor readings.

1. Measured or projected dose rate of 2 mR/hr whole body at site boundary under existing weather con-ditions.

Site Emergency

1. Measured or projected dose rate of 50 mR/hr whole body or 250 mR/hr thyroid at the site boundary under existing weather conditions.

General Emergency

1. Measured or projected dose rate of 250 mR/hr whole body or 1250 atR/hr thyroid at the site boundary under existing conditions.

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Page 25 of 30 Rev. 2, 4/27/82

PMP 2080 EPP.001 EXHIBIT A ECC-20: PERSONNEL INJURY

Unusual Event
1. Transportation of contaminated individual (s) to off-site hospital.
2. Any fatality, or serious injury occurring on site requiring a stay at a medical facility in excess of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
3. Any serious personnel radioactive contamination requiring extensive on-site decontamination or outside assistance.

Alert i N/A Site Emergency N/A General Emergency N/A i

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PMP 2080 EPP.001 EXHIBIT A ECC-21: OTHER HAZARDS Unusual Event

1. Turbine failure with resulting damage but not penetrating outside turbine housing.
2. Rapid uncontrolled depressurization of the secondary side.
3. Unit is shut down in an uncontrolled manner or conditions exist which might escalate to a more severe class; such as, uncontrolled rod withdrawal, dropped RCCA assembly or bank, uncontrolled dilu-tion, loss of one or more Reactor Coolant Pumps above 50% power, loss of load, loss of normal feed-water or malfunction (overcooling, excessive load increase), inactive RCS loop startup, steam line break.

Alert

1. Other plant conditions exist that warrant pre-cautionary activition of Technical Support Center and near-site emergency operations center, as per SS judgment.
2. Turbine failure causing damage as judged by the SS penetration outside turbine housing.

Site Emergency

1. SS judgment, i.e., a less severe emergency class has escalated to meet Site Emergency criteria.

General Emergency

1. Loss of Coolant Accident (LOCA), (large or small),

with the failure of the Emergency Core Cooling Sys-tem (ECCS) to function leading to severe core degra-dation or melt. With core melt sequences, ultimate containment failure likely with several hours availa-ble for response.

2. Transient due to loss of the Feedwater System or Con-i densate System followed by the failure of the Auxiliary Feedwater System for an extended period. Core melting i

is possible in several hours with ultimate containment i

failure likely if core melts.

i I , (C,nt'd)

! Page 27 of 30 Rev. 2,d/27/82

1 PMP 2080 EPP.001 EXHIBIT A ECC-21: OTHER HAZARDS (CONT'D) i

3. Transient condition requiring operation of Reactor Protection System with a failure to trip the reactor followed by a failure of ECCS and makeup system which would lead to a core melt.
4. Failure of offsite and onsite power along with total loss of emergency feedwater capability for several hours which would lead to eventual core melt and likely containment failure.
5. Small LOCA with initial ECCS actuation success-ful with subsequent failure of containment heat removal systems. Ultimate core melting is likely with probable containment failure.

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PMP 2080 EPP.001 EXHIBIT A ECC-22: ' LOSS OF CONTROL ROOM ANNUNCIATORS / ALARMS 1

Unusual Event a

N/A Alert 3

1. All annunciator panels in Control Room non-functioning.
2. The unit is undergoing a transient while the annunciators are inoperable.

Site Emergency N/A General Emergency N/A 4

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PMP 2080 EPP.001 l EXHIBIT A ECC-23: LIQUID RELEASE Unusual Event

> 1. Environmental Technical Specification 2.4.1 (liquid waste effluent limits) or 2.4.3 (gaseous effluent limits) exceeded with verification by radiation protection analysis.

Alert

1. Radioactive liquid effluent releases which exceed 10 X Technical Specification limits.

Site Emergency

1. Radioactive liquid effluent releases which for a single isotope or mixed isotopes exceeds 50 X MPC in water (averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).

General Emergency

1. Radioactive liquid effluent releases which for a single isotope or mixed isotopes exceeds 500 X MPC in water (averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).

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INDIANA & MICHIGAN 1 ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET Procedure No. PMP 2080.EPP.008 Revision No. 1 TrrLE CALLING 0FF-0UTY PLANT PERSONNEL SCCPE OF REVISION Rev. 1 - Added Graphical Phone Tree. Clarified assembly and call in, activate call list on TSC manning not Nuclear Emergency Alarm.

i DCR MAY 0 51981 i

SIGNATURES ORIGINAL Rev.I REV.2 Rev.3 PREPARED BY T. Duffy R. Keith ggy ,7 QUALITY ASSURANCE REVIEW J. Stietzel ,

INTERFACING DEPARTMENT # '

i/

HEAD CONCURRENCE N,A,  !/ f/j$

DEPARTMENT HEAD APPROVAL i

N.A. /VA PLANT NUCLEAR .

SAM COWNE R. Keith l

! PLANT MANAGER APPROVAL B. Svensson h DATE OF ISSUE 3-31-81 4-2# d h Form No PMI 20104. asv. 2

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P'fP 2080 EPP.008  !

3 LIST OF EFFECTIVE PAGES Page Number Revision Number And Date Page 1 of 6 Revision 1,4-29-82 Page 2 of 6 Revision 1,4-29-82 Page 3 of 6 EXHIBIT A Revision 1,4-29-82 Page_4 of 6 EXHIBIT A Revision 1,4-29-82 Page 5 of 6 EXHIBIT A Revision 1, 4-29-82 Page 6 of 6 EXHIBIT B Revision 1, 4-29-82 i

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Revision 1, 4-29-82 1

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PMP 2080 EPP.008 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT CALLING OFF-DUTY PLANT PERSONNEL 1.0 OBJECTIVES The objective of this procedure is to provide the information that is necessary to summon off-duty plant personnel during emergency conditions.

2.0 RESPONSIBILITIES The Shift Supervisor (SS)/On-Site Emergency Coordinator (OSEC) is responsible for initiating the emergency call list and providing the required information to the parties called in.

3.0 APPLICABILITY This procedure applies to any plant emergency event which requires off-duty plant personnel notification. The procedure may be imple-mented anytime the SS/0SEC determines that it is necessary that on-site emergency personnel resources be augmented by off-duty plant personnel.

4.0 INSTRUCTIONS 4.I Identify the appropriate assembly location for reporting off-duty personnel. This would normally be the Technical Support Center and Control Room.

NOTE: THE PRIMARY ASSEMBLY AREA FOR OFF-DUTY REPORTING, IN THE EVENT OF RADIOLOGICAL EMERGENCIES, IS TE GUARD HOUSE AT I-94 ON THE PLANT ACCESS ROAD. THE ALTERNATE ASSEMBLY AREA IS AT THE STEVENSVILLE SUB-STATION.

4.2 Identify appropriate reporting routes.

4.3 Determine any immediate requirements for off-duty personnel.

4.4 Initiate the predetermined calling sequences for off-duty plant personnel.

NOTE: CALL SEQUENCES ARE SHOWN ON: EXHIBIT A, EMERGENCY CALL LIST FOR EMERGENCIES REQUIRING ACTIVATION OF THE TECHNICAL SUPPORT CENTER. TELEPHONE NUMBERS ARE IN APPPENDIX A. EXHIBIT A ALSO CONTAINS A GRAPHICAL REPRESENTATION OF THE PHONE TREE.

[ Page 1 of 6 l

Revision 1, a-29-82 l

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l PMP 2080 EPP.008 4.5 Items 1 thru 5 on attached checklist in EXHIBIT B should be used as a guide regarding the information to be supplied.

4.6 Alert plant security to set up the Assembly Area for immediate processing of the arriving off-duty personnel if needed.

NOTE: TO PROVIDE RAPID NOTIFICATION OF DEPARTMENTAL PERSONNEL, DEPARTMENT SUPERVISORS MAY ESTABLISH DEPARTMILNTAL CALL TREES OR DELEGATE NOTIFICATION TO OTHER DEPARTMILNTAL PERSONNEL.

i Page 2 of 6 Revision 1,4-29-82

PMP 2080 EPP.008 EXHIBIT A '

EMERGENCY CALL LIST FOR EMERGENCIES REQURING ACTIVATION OF THE TSC When the individuals listed below are notified of an emergency, they in turn will notify other personnel who have been aesigned emergency functions or are needed to combat the emergency; for example, ffter the Shift Supervisor is no-tified, he will notify either the Plant Manager or the Operations Superintendent who in turn will notify the others. When the caller cannot reach the person called, he must assume responsibility for calling those persons in the next level of the telephone chain.

NOTE: TELEPHONE AND CALL NUMBERS aRE IN APPENDIX A.

Person to Make Call Persons To Be Called Shift Supervisor Plant Manager or Operations Superintendent NOTE: PERSON RECEIVING THE CALL NOTIFIES THE OTHER.

Plant Manager

  • Berrien County Sheriff's Dept.
  • NRC (Resident Inspector)

Public Affairs AEPSC (Asst. V.P. & Chief Nuc. Eng.)

I & M Elect. Co. (Executive Assistant to the Pres.)

NOTE: *May be delegated to S.S. or S.S. may initiate if, in his judgement, the Plant Manager will not be able to promptly notify these agen-cies. The S.S. will make the initial NRC notification via the

" Red Phone".

Operations Assistant Plant Manager (APM)

Superintendent (Technical Support Center, Manager)

Production Supervisors (Ops.)

Technical Superintendent Board Writer and C.R. Talker NOTE: THE ALERTED APM NOTIFIES THE REMAINING APM. THE OPERATIONS SUPER-INTENDENT WILL INDICATE TO APM AND THE TECHNICAL SUPERINTENDENT THE

! EXTENT OF CALL LIST TO BE ACTIVATED BASED ON EMERGENCY CONDITIONS l AND NEEDS.

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PMP 2080 EPP.008 EXHIBIT A EMERGENCY CALL LIST (CONT'D)

FOR EMERGENCIES REQURING ACTIVATION OF THE TSC Person to Make Call Persons To Be Called Assistant Plant Manager (APM) Assistant Plant Manager Maintenance Superintendent Chief Security Supervisor Training Coordinator Technical Superintendent Production Supervisor Technical Performance Supervising Engineer Plant R. P. Supervisor Environmental Coordinator i C & I Engineer Computer Nuclear Supervisor Plant Chemical Supervisor Communicators NOTE: EACH TECHNICAL DEPARTENT SECTION HEAD WILL CALL IN NECESSARY PERSONNEL FROM THEIR RESPECTIVE SECTION. THE TRAINING COORDINATOR WILL CALL ON NECESSARY PERSONNEL TO ADEQUATELY OPERATE NECESSARY COMMUNICATION LINKS.

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PMP 2080.EPP.008 .

E MIBIT A GRAPilICAL Pil0NE TREE S.S.

OF _ _ _ _ _ . _

OPS. PLANT SUPT. MANTGER

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or TECll. NECESSARY DEPT. PROD. PUBLIC AEPSC I&M NRC PSP BCSD .

SUPT. PERSONNEL SUPV. AFFAIRS ELECT.

APM APM (B0ARD WRITER)

OPS' 'MI NT *  !

(CR TALKER) i-ENV. . PERF. PROD. SilPV. C&I TRAINING MAINT' SUPV. T ECil.

R.'.

SilPV.

CHEM.

SUPV.

NUC.. EAR f CNbF . SUPV. COORD. ENG. SUPV.

SUPV.  !

COMM.

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PMP 2080 EPP.008 EXHIBIT B 0FF-DUTY NOTIFICATION CHECKLIST Plant Manager or Operations Superintendent notified of the following information:

~ Information given to responding personnel: -

1. Emergency was declared at .

(Classification) (Time) 2.

(Nature of incident and status of plant) l

3. Personnel resources needed on high priority .
4. A release to the environment has not occurred  ; has occurred  : is occurring  ; may occur .
5. Project Lose Rates at or near the site boundary are
6. Report to: Security Control Center  ; I-94 Guard House  ;

Stevensville Substation  ; Operations Staging Area  ; Technical Support Center  ; via .

(Route) l l

Page 6 of 6 Revision 1,4-29-82

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INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR Pt. ANT PROCEDURE COVER SHEET Pawe No. PMP 2080 EPP.012 Revisen No. 1 TITII INITIAL OFF-SITE NOTIFICATIONS SCOPE OF REVISION Rev. 1: Incorporated Temporary Sheets. Revised Exhibit A and B.

p/ V :.m O1 j

Ef 0 5;331 l i SIGNATURES ORIGINAL Rev.I REV.2 Rev.3 PREPARED BY J/ A,pr [ /b QU ASSURANCE INTERFACING DEPARTMENT /['

U

/ /' I) (-

HEAD CONCURRENCE ( N.A. (,,

/ 4/, .4.

DEPARTMENT HEAD APPROVAL N.A. A/, 4, l PLANT NUCLEAR SATETY COMMITTEE [p[ .

I PLANT MANAGER 7 APPROVAL M- r: g, DATE OF ISSUE 3-31-81 Y- 67-8 %

Form Na ?WITC10-1 tzv. 2

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PMP 2080 EPP.012 LIST OF EFFECTIVE PAGES Page Number Revision Number And Date Page 1 of 3 Revision 1, 4-27-82 Page 2 of 3 EXHIBIT A Revision 1, 4-27-82

! Page 3 of 3 EXHIBIT B Revision 1, 4-27-82 i

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Page 1 of.1 Rev. 1, 4-27-82

, PMP 2080 EPP.012 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT 1.0 OBJECTIVE This procedure prov'. des guidance to the Plant Manager or Shif t Super-visor regarding initial information supplied to off-site support groups.

This information is to be supplied upon declaration of an Unusual Event, Alert, Site Emergency, or General Emergency condition.

2.0 RESPONSIBILITIES 2.1 The Plant Manager is responsible for the accomplishment of initial off-site notifications to individuals or agencies specified in this procedure.

2.2 The Shift Supervisor is responsible for the initial notifications to individuals or agencies specified in this procedure if:

a. In the Shift Supervisor's judgement, the Plant Manager will be unable to complete the notifications in a time-ly manner, o_r,
b. The Shift Supervisor is delegated this responsibility by the Plant Manager.

3.0 LIMITATIONS 3.1 Initial notification to the Michigan State Police and the Berrien County Sheriff's Dep.rtment of an Unusual Event is expected to be completed within 60 minutes of event classification.

3.2 Initial notifications to the Michigan State Police and the Berrien County Sheriffs Department shall be immediate upon classification of an Alert, Site Emergency or General Emergency Condition and no-tification of the NRC and appropriate AEP personnel.

4.0 INSTRUCTIONS 4.1 Upon declaration of an Unusual Event, Alert, Site Emergency or General Emergency the Plant Manager or SS shall provide all inusediately available information from EXHIBIT A, ACCIDENT INFORMATION REPORTING DATA SHEET, to those listed on EXHIBIT B, INITIAL OFF-SITE NOTIFICATION LIST.

NOTE: EXHIBIT A AND EXHIBIT B SHOULD BE COMPLETED AND ROUTED TO -

THE PLANT MANAGER'S OFFICE UPON EVENT CLOSE-0UT.

NOTE: PHONE NUMBERS FOR ALL PERSONNEL ARE CONTAINED IN APPENDIX A 0F THESE EMERGENCY PLAN PROCEDURES.

NOTE: IF PUBLIC AFFAIRS AND NRC AGREE A NEWS RELEASE IS TO BE MADE, THE NUCLEAR CENTER WILL PROVIDE THE RELEASE TO THE MICHIGAN .

STATE POLICE, THE BERRIEN COUNTY SHERIFF'S DEPARTMENT AND THE NEWS MEDIA.

Page 1 of 3 Revision 14-27-c2

O O PMP 2080 EPP.012 EXKIBIT A ACCIDENT INFORMATION REPORTING DATA SHEET D.C. Cook Unit Date Time Classified Classification Classified By Description of Event Time of Actual Or Projected Release Estimation Of Duration Of Release Release Involved: Yes No Release Rate: Noble Gas Ci/sec Release Height: Groun.* Level Iodine Ci/sec Meteorological Conditions: Wind Speed (mph)

Wind Direction: From To Stability Class: ST Pasquill Cat.

Precipitation Projected Dose At:

Site Boundary 2 Miles 5 Miles 10 Miles Dose Rate, Whole Body Integrated Dose, Whole Body Dose Rate, Thyroid Integrated Dose, Thyroid Sectors Affected Injured Personnel Radioactivity Contaminated Off-Site Emergency Protective Actions Recommended Off-Site Support Requested Type Prognosis For Termination Or Worsening Page 2 of 3 Revision 1,1-27-82

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PMP 2080 EPP.012 EXHIBIT B INITIAL OFF-SITE NOTIFICATION LIST Event Classification: Unusual Event Alert Site Emergency General Emergency Event Closed-Out Event Notification Or Upgraded Initials / Time Initials / Time Berrien County Sheriff's Department REQUEST CALL BACK VERIFICATION Michigan State Police, Benton Harbor REQUEST CALL BACK VERIFICATION Assistant V.P. and Chief Nuclear Engineer Alternate: Assistant Chief Nuclear Engineer Alternate: Executive V.P. - Construction and New York Engineering

  • Executive Assistant to the I&MEco President Alte rnate : I&MECo President Alternate: I&MEco V.P.
  • NRC Resident Inspector Alternate: Assistant NRC Resident Inspector NRC Region III/ Washington Energy Information Center Manager Alte rnate: Public Affairs Director Alternate: Information Services Manager
  • 0ptional For Unusual Event Page 3 of 3 Revision 1,4-27-82

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INDIANA & MICHIGAN 1 ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT i PROCEDURE COVER SHEET Procedure No. PMP-2080 EPP.015 Revisiert No.1 TITLE RESPONSIBILITIES OF THE ON-SITE EMERGENCY COORDINATOR SCOPE OF REVISION Revision 1 - Clarified the responsibilities of the OSEC to include activation of emergency cantars. Alen referenced PMP 2080 EPP.006, Initi al 0%e /4s! smeni, and PMP 2080 EPP.012, Initial Off-Si te Noji(if a!. ons. Added Exhibit A.

MAY 0 51961 l

.I SIGNATURES ORIGINAL Rev.I REV.2 Rev.3 PREPARED BY j]

QUALITY ASS *!RANCE ()

REVIEW ,p INTERFAC'NG DEPARTMENT U/ v' HEAD CCNCURRENCE A/, 4 , s g',A,

! DEPARTMENT HEAD l APPROVAL A/, 4 , it/, A.

! PLANT NUCLEAR SATETY COMMITTEE $jr - r '

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! "## "^"^ '" a s: L f L E f i u 's DATE Or [SSUE /0- D ?I A 8A Tonn No. PMI:010-1 nav. 2

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PMP 2080 EPP.015 LIST OF EFFECTIVE PAGES Page Number Revision Number And Date

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Page 1 of 13 Revision 1, 4 29-82 Page 2 of 13 Revision 1, 4 29 82 Page 3 of 13 Revision 1, 4 29 82 Page 4 of 13 Revision 1, 4 29 32 Page 5 of 13 Exhibit A Revision 1, 4 29-82 Page 6 of 13 Exhibit A Revision 1, 4-29-82 Page 7 of 13 Exhibit A Revision 1, 4 29 32 Page 8 of 13 Exhibit A Revision 1, 4-29-82 i

Page 9 of 13 Exhibit A Revision 1, 4-29-82 Page 10 of 13 Exhibit A Revision 1, 4-29-82 Page 11 of 13 Exhibit A Revision 1, 4-29-82 Page 12 of 13 Exhibit A Revision 1, 4-29-82 Page 13 of 13 Exhibit A Revision 1, 4-29-82 Page 1 of 1 Revision 1, 1-29-82 l

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e 0 PMP 2080 EPP.015 INDIANA &MICHIGANELECTRICCOMPAhY DONALD C. COOK NUCLEAR PLANI RESPONSIBILITIES OF THE ON-SITE EMERGENCY COORDINATOR 1.0 OBJECTIVES This procedure describes the responsibilities of and line of succession to the On-Site Emergency Coordinator.

2.0 RESPONSIBILITY The On-Site Emergency Coordinator (OSEC) is responsible for overall plant emergency response functions. As such, the OSEC is responsi-ble for:

Declaration of an Emergency Condition Determination of Protective Actions Ensuring Prompt Notification of emergency classification and appropriate protective actions to off-site author-ities.

Overall management of site resources in response to the emergency Declaration of entry into a recovery phase (de-escalation of event classification of operationsh The OSEC is additionally responsible for ensuring activation of:

The Technical Support Center for an Alert Classification.

The Joint Public Information Center, the American Electric Power Emergency Response Organization, and the Emergency Control Center for a Site Emergency Classification The S.S. is the individual on site at all times who has the responsibility and authority to carry out the functions of the OSEC. The SS is super-seded as the OSEC by senior company personnel as they arrive on site, as follows:

Executive Vice President - Construction and New York Engineering Assistant Vice President and Chief Nuclear Engineer D. C. Cook Plant Manager Assistant Plant Manager in order of Seniority Operations Superintendent Production Supervisor of Affected Unit 3.0 APPLICABILITY This procedure is applicable upon activation of the Emergency Plan.

Page 1 of 13 Rev. 1, 4-29-82

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PMP 2080 EPP.015 EXHIBIT A 4.0 ACTIONS NOTE: See Exhibit A for a summary of each emergency classification; including definition, dose levels, Cook Plant actions, and offsite authority actions.

4.1 The S.S. shall act as the On-Site Emergency Coordinator until relieved of this responsibility by the Plant Manager or his designated alternate, or the emergency condition terminated.

4.1.1 The SS/0SEC shall implement PMP 2080 EPP.001.

4.1.2 If protective actions of the public are appropriate, as determined by PMP 2080 EPP.006, the SS/0SEC shall ensure immediate notification of the Michigan State Police and the Berrien County Sheriff's Department.

4.1.3 The SS/OSEC shall insure implementation of PMP 2080.

EPP.012, Initial Off-Site Notifications.

4.2 The Plant Manager or his designated alternate shall replace the SS as OSEC until relieved by the Vice President - Construction and New York Engineering, or the emergency condition terminated.

4.2.1 The PM/OSEC shall additionally implement the below listed procedures as appropriate:

4.2.2 The PM/OSEC shall, after consultation with Federal, State, and County officials, de-escalate emergency classifications thereby entering the recovery stage of operations.

4.2.1.1 PMP 2081 EPP.001 Emergency Telephone Communi-cations 4.2.1.2 PMP 2081 EPP.002 Barring of the PABX 4.2.1.3 PMP 2081 EPP.003 Follow-Up of Off-Site Communi-cations 4.2.1.4 PMP 2081 EPP.004 Protective Action Guides (PAGs) and Protective Actions l 4.2.1.5 PMP 2081 EPP.005 Personnel Evacuation l

4.2.1.6 PMP 2081 EPP.006 Activation of the Re-entry and Rescue Team 4.2.1.7 PMP 2081 EPP.007 Security Actions During Emer-gency Conditions f 4.2.1.3 PMP 2081 EPP.008 Emergency Medical Plan Guide-

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r PMP 2080 EPP.015 EXHIBIT A l l

4.2.1.9 PMP 2081 EPP.009 Health Physics Procedures 4.2.1.10 PMP 2081 EPP.010 Activation of Radiation Moni-toring Teams

'4.2.1.11 PMP 2081 EPP.011 On-Site Radiological Monitor-ing 4.2.1.12 PMP 2081 EPP.012 Off-Site Radiological Moni-toring 4.2.1.13 PMP 2081 EPP.013 Environmental Monitoring and Analysis 4.2.1.14 PMP 2081 EPP.014 Off-Site Dose Assessments 4.2.1.15 PMP 2081 EPP.015 Sampling and Analysis of Water-borne Releases 4.2.1.16 PMP 2081 EPP.016 Collection and Analysis of Li-quid and Gaseous Samples 4.2.1.17 PMP 2081 EPP.017 Interpretation of Liquid and Gaseous Samples 4.2.1.18 PMP 2081 EPP.018 Transportation Accidents In-volving Radioactive Material 4.2.1.19 PMP 2081 EPP.019 AEP Emergency Response Organ-ization Activation and Management 4.2.1.20 PMP 2081 EPP.020 Activation and Operation of the Technical Support Center (TSC) 4.2.1.21 PMP 2081 EPP.021 Activation and Operation of the Operation Staging Area (0SA) and Personnel Accountability 4.2.1.22 PMP 2081 EPP.023 Activation and Operation of the Emergency Control Center (ECC)

(An Emergency Operations Faci-lity) 4.2.1.23 PMP 2081 EPP.024 Activation and Operation of the Joint Public Information Cen-ter (JPIC) (An Emergency Oper-ations Facility) 4.2.1.24 PMP 2081.EPP.026 Use of Stable Iodine for Thyroid Blocking During A Radiation Emergency -

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PMP 2080 EPP.015 4.3 The Vice President - Construction and New York Engineering or his designated alternate shall replace the Plant Manager as On-Site Emergency Coordinator, upon his arrival on site and until the emergency condition is terminated.

4.3.1 The VP/OSEC shall additionally implement the following procedures as appropriate:

4.3.1.1 PMP 2081 EPP.022 Activation and Operation of The Recovery Center (RC)

(An Emergency Operations Facility) 4.3.2 The VP/OSEC shall, after consultation with Federal, State, and County officials, de-escalate emergency classifications thereby entering the recovery stage of operations.

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PMP 2080 EPP.015 EXHIBIT A UNUSUAL EVENT 1.0 Description 1.1 Events are in process or have occurred which are defined as an in-Plant occurrence requiring only in-Plant action to mitigate the event. The event does not affect the health and safety of the public.

2.0 Purpose 2.1 Assure Plant staff members are notified.

2.2 Activate appropriate emergency response.

3.0 Radiological Emergency Action Level at Site Boundary 3.1 No radiological releases.

4.0 Protective Action Guide (Limiting Values) 4.1 To population due to external and inhalation exposure - none.

4.2 For contaminated human and animal food - none.

5.0 Cook Plant Action 5.1 Promptly inform State and County Authorities and Plant Staff in accordance with PMP 2080.EPP.012, Initial Off-Site Notifi-cations, and PMP 2080.EPP.008, Calling Off-Duty Plant Person-nel.

5.2 Verbally notify the NRC. Follow with written notification as required by Technical Specifications and significant events.

(10CFR 50.72) 5.3 Assess and respond.

5.4 Close out by verbal summary to NRC, State / County Authorities, as required.

(or) 5.5 Escalate to a more serious level.

6.0 Off-Site Authority Action 6.1 Provide assistance, as requested, in accordance with established agreements and emergency plans.

6.2 County will notify appropriate State and Local agencie,s as required.

Page 5 of 13 Rev. 1,A_29 82

Y 0 8 PMP 2080 EPP.015 EXHIBIT A ALERT 1.0 Description 1.1 Events are in process or have occurred which involve an ac-tual or potential substantial degradation of the level of safety of the Plant. The alert could possibly affect the health and safety of the public.

2.0 Pu rpose 2.1 Assure that emergency personnel are readily available to re-spond, if the situation becomes more serious, or to perform confirmatory radiation monitoring if required.

2.2 Provide offsite authorities with current status information.

3.0 Radiological Emergency Action Level at Site Boundary 3.1 2t.R in one hour.

(or) 3.2 Liquid effluent concentrations greater than 10 times Technical Specification limits for a mixture of radioisotopes or a single isotope.

4.0 Protective Action Guide (Limiting Values) 4.1 To population due to external and inhalation exposure:

Whole body dose < 0.5R Thyroid dose < SR 4.2 For contaminated human and animal food:

Whole body dose < 0.5R Thyroid dose < 1.5R 5.0 Cook Plant Action 5.1 Promptly inform State and County Authorities and Plant Staff in accordance with PMP 2080.EPP.012, Initial Off-Site Notifi-cations, and PMP 2080.EPP.008, Calling Off-Duty Plant Personnel.

5.2 Verbally notify the NRC. Follow with written notification as required by Technical Specifications and significant events.

(10 CFR 50.72)

5.3 Assess and respond.

Page 6 of 13 Rev. 1, 4-29-82

4

. o i PMP 2080 EPP.015 EXHIBIT A ALERT - Continued 5.4 Activate the Technical Support Center.

5.5 Activate other emergency functions / resources as required.

5.6 Alert appropriate members of the AEP Emergency Respouse Organization to standby only (not to travel to Cook Plant).

5.7 Dispatch on-site monitoring teams and assocated communica-tions if necessary.

5.3 Provide periodic Plant status updates to off-site authorities.

5.9 Provide meteorological and dose estimates to off-site authori-ties for actual releases, and dose projections on forseeable contingencies.

5.10 Close out by verbal summary to NRC and off-site State / County Authorities.

(or) 5.11 Escalate to a more severe level.

6.0 Off-Site Authority Action 6.1 Provide assitance as requested in accordance with established agreements and emergency plans.

6.2 County will notify appropriate State and Local agencies as re-quired.

6.3 Augment State and County EOC's as appropriate.

6.4 No protective actions are required for levels below those listed in the Protective Action Guide (Section 3.0 and 4.0 above).

6.5 Michigan Department of Public Health (DPH) will monitor and in-vestigate the cause of radiation levels and assure that correc-tive action measures are progressing. ,,

6.6 DPH will consider issuing an advisory to seek shelter or to evacuate.

6.7 DPH and Department of Agriculture (DA) will monitor food and milk as required.

6.8 Alert to standby status additional resources as appropriate.

6.9 Escalate to a more severe level, if necessary.

Page 7 of 13 Rev. 1, 4-29-82

- .. .... 2 a

i

! PMP 2080 EPP.015 EXHIBIT A SITE EMERGENCY 1.0 Description 1.1 Events are in process or have occurred which involve actual failures of Plant functions needed to mitigate the events for protection of the public.

2.0 Purpose 2.1 Activate the required response centers.

2.2 Assure that monitoring teams are mobilized.

2.3 Assure that personnel required for taking protective actions tre at duty stations if situation becomes more serious.

2.4 Provide current information for off-site authorities.

. 3.0 Radiological Emergency Action Level at Site Boundary 3.1 50 mR/hr for 30 minutes whole body.

250 mR/hr for 30 minutes thyroid.

(or) 3.2 500 mR/hr for 2 minutes whole body.

2.5 R/hr for 2 minutes thyroid.

(or) 3.3 500 mR/hr in 30 days whole body.

2.5 R in 30 days thyroid.

(or) 0 3.4 Containment reading of 1.03 X 10 R/hr (or) 3.5 Liquid effluent concentrations greater than 50 times Technical Specification limits for a mixture of radioisotopes or a single isotope.

4.0 Protective Action Guide (Limiting Values) 4.1 To population due to external and inhalation exposure:

.5R $ Whole Body Dose < SR - 1.5 5 Thyroid Dose <25R Page 3 of 13 Rev. 1, 4-29-82

j4 PMP 2080 EPP.015 EXHIBIT A 1

SITE EMERGENCY - Continued 4.2 For contaminated human and animal food:

0.5R 5 Whole Body Dose < SR 1.5R S Thyroid Dose <15R 5.0 Cook Plant Action 5.1 Promptly inform State and County Authorities, and Plant Staff in accordance with PMP 2080 EPP.012, Initial Off-Site Notifications, and PMP 2080 EPP.008, Calling Off-Duty Plant Personnel.

5.2 Verbally notify the NRC. Follow with written notification as required by technical specifications and significant events (10CFR 50.72).

5.3 Assess and respond.

5.4 Activate the Technical Support Center, Emergency Control Center, Joint Public Information Center, and the American Electric Power Emergency Response Organization.

5.5 Activate other emergency functions and resources, as required.

5.6 Alert appropriate members of the AEP Emergency Response Organization to standby only (not to travel to Cook Plant).

5.7 Dispatch on-site monitoring teams and associated communications if necessary.

5.8 Provide periodic Plant status updates to off-site authorities.

5.9 Provide meteorological and dose estimates to off-site authorities for actual releases, and dose projections on foreseeable contingencies.

5.10 Make Senior Technical and Management Staff available on-site for consultation with NRC, State and County personnel on a periodic basis.

5.11 Close out or reduce class category. Provide briefing to off-site authorities.

(or) 5.12 Escalate to General Emergency Level.

6.0 Off-Site Authority Action 6.1 Provide assistance as requested in accordance with established agreements and emergency plans.

?

Page 9 of 13 Rev. 1,4 29 82

e 6o PMP 2080 EPP.015 EXHIBIT A SITE EMERGENCY - Continued 6.2 County will notify appropriate State and Local agencies, as required.

6.3 Augment State and County EOC's as appropriate.

6.4 Alert to standby status additional resources as appropriate.

6.5 Michigan Department of Public Health (DPH) will monitor and investigate the cause of radiation levels and assure that corrective action measures are progressing.

6.6 Consult with Cook Plant personnel on results of radiological surveys being conducted.

6.7 Assess information provided by all agencies concerned in monitoring of actual releases.

6.8 Protective action may be required for the public. Public notification may be deemed necessary.

4 6.9 DPH may advise individuals to seek shelter and await further instructions.

6.10 DPH may consider evacuation, particularly for children and pregnant women, based on monitoring results.

6.11 Michigan Department of Agriculture (DA) in conjunction with DPH will divert, condemn or dispose of food and issue i

advisories regarding home grown foods and protective action of animals if necessary.

6.12 DPH and DA will monitor food and especially milk as

  • required.

6.13 State Police will control access to areas affected to avoid unnecessary exposure to individuals if necessary.

6.14 Provide for press briefings and releases.

6.15 Maintain site emergency until closeout or reduction in class.

6.16 Escalate to General Emergency if necessary.

Page 10 of 13 Rev. 1,4-29-82

PMP 2080 EPP.015 i'

GENERAL EMERGENCY 1.0 Description 1.1 Events are in process or have occurred which involve actual substantial core degradation, or melting with imminent potential for loss of containment integrity.

i 2.0 Purpose ,

2.1 Initiate protective actions for public.

2.2 Provide continuous assessment of information from Cook

Plant and off-site measurements. i-2.3 Initiate additional measures as indicated by actual or potential releases.

2.4 Provide current information for off-site authorities.

]

3.0 Radiological Emergency Action Level at Site Boundarz

3.1 Whole body dose 2 500 Kk in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Thyroid dose 2 2.5 R in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

i I

(or) i I

L

3.2 Whole body dose 2 5R in 30 days.

Thyroid dose 2 25 R in 30 days.

i (or) 3.3 Containment reading of 10.4 x 10s R/HR.

i 3.4 Liquid effluent concentrations greater than 500 times Technical Specification Ibaits for a mixture of radioisotopes or a single isotope.

t l 4.0 Protective Action Guide (Limiting Values) -

4.1 To population due to external and inhalation exposure h I'

Whole body dose 2 5R Thyroid dose 2 25 R i

4;2 For contaminated human and animal food ,

Whole body dose 2_ 5R ,

[- Thyroid dose 2 . 15 R I

l -

l Page 11 of 13 Rev. 1, 4-29-82  ;

I

. . 4.  ;

1 PMP 2080 EPP.015 l EXHIBIT A I GENERAL EMERGENCY - Continued 5.0 Cook Plant Action 5.1 Promptly inform State and County Authorities, and Plant Staff in accordance with PMP 2080 EPP.012, Initial Off-Site Notifications, and PMP 2080 EPP.008, Calling Off-Duty Plant Personnel.

5.2 Verbally notify the NRC. Follow with written notification as required by technical specifications and significant events (10CFR 50.72).

5.3 Assess and respond.

5.4 Activate the Technical Support Center, Emergency Control Center, Joint Public Information Center, and the American Electric Power Emergency Response Organization.

5.5 Activate other emergency functions and resources, as required.

5.6 Alert appropriate members of the AEP Emergency Response Organization to standby only (not to travel to Cook Plant).

5.7 Dispatch on-site monitoring teams and associated communications if necessary.

5.8 Provide periodic Plant status updates to off-site authorities.

5.9 Provide meteorological and dose estimates to off-site authorities for actual releases, and dose projections on foreseeable contingencies.

5.10 Make Senior Technical and Management Staff available on-site for consultation with NRC, State and County personnel on a periodic basis.

5.11 Recommend sheltering in a two (2) mile radius and five (5) miles downwind.

5.12 Close out or recommend reduction of emergency class by briefing of off-site authorities.

6.0 Off-Site Authority Action 6.1 Provide assistance as requested in accordance with established agreements and emergency plans.

6.2 County will notify appropriate State and Local agencies, as required.

6.3 Augment State and County EOC's as appropriate.

Page 12 of 13 Rev. 1, 4-29 82

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. y.

PMP 2080 EPP.015 EXHIBIT A GENERAL EMERGENCY - Continued 6.4 Alert to standby status additional resources as appropriate.

6.5 Michigan Department of Public Health (DPH) will monitor and investigate the cause of radiation levels and assume that corrective action seasures are progressing.

6.6 Recommend sheltering in a two (2) mile radius and five (5) miles downwind.

6.7 Consult with Cook Plant personnel on results of radiological surveys being conducted.

6.8 Further protective actions may be required for the public. DPH may consider evacuation, particularly for children and pregnant women, based on monitoring results.

6.9 State Police will control access to areas affected to avoid unnacessary exposure to individuals if necessary.

6.10 Assess information provided by all agencies concerned in monitoring of actual releases.

6.11 DPH will coordinate and perform the monitoring of environmental radiation levels.

6.12 Recommend placing milk animals within LPZ on stored feed.

6.13 Michigan Department of Agriculture (DA) in conjunction with DPH will divert, condemn or dispose of food, and issue advisories regarding home-grown foods and protective action of animals if necessary.

6.14 Provide for press briefings and releases.

6.15 Maintain a General Emergency until closecut or reduction of class.

Page 13 of 13 .

Rev. 1, 4-29-82

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