ML17319A852

Forwards Public Version of Addl Info to Be Inserted in 810102 Revised Emergency Plan

ML17319A852
Person / Time
Site:	Cook
Issue date:	03/02/1981
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17319A851	List: ML17319A850 ML17319A852
References
AEP:NRC:00308F, AEP:NRC:308F, NUDOCS 8105140231
Download: ML17319A852 (31)

Text

INDIANA 5 MICHIGAN ELECTRIC COMPANY P. 0. BOX 18 BOWLING .GREEN STATION NEW YORK, N. Y. 10004 March 2, 1981 AEP:NRC:00308F Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. OPR-58 and DPR-74 EMERGENCY PLAN INSERTS Mt . Harold R. Oenton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

The attachments to this letter transmit the additional information committed to by the submittal of our Emergency Plan under AEP:NRC:00308B, dated January 26, 1981. Since this information is an insert to the original documents we have transmitted to you, we are not treating this as a formal revision or change to the documents you now have. One control copy and nine additional copies of the inserts are being sent to you. Three copies of the inserts are also being transmitted to the NRC Region III Office of Inspection and Enforcement under separate cover.

Very truly yours,

. S. Hunter Vice President cc: John E. Dolan R. W. Jurgensen R. C. Callen G. Charnoff yDC5 D. V. Shaller - Bridgman NRC Region III Resident Inspector - Bridgman NRC Region III Office of Inspection and Enforcement i/(o INPORIATION PERSONAL PRIVACY 5ITH THE DELETED IN ACCORDANCE ACX FREEDOM Or XmZOZ,mTION

ATTACHMENT 1 TO AEP:NRC;0308F PERSONAL PRIVACY INFORMATION DELETED IN ACCORDANCE WITH THE ZBEMOM OF INFORMATIONACT

TABLE OF CONTENTS (cont'd.)

Title Pacae 12.3 ' EMERGENCY RESPONSE SUPPORT AND RESOURCES 12. 3-48 12.3.4.1 Interagency Radiological Assistance 12. 3-49 Plan (IRAP)

'12.3.4.2 Off-Site Representatives 12.3-52 12.3.4.3 Off-Site Agencies and Organizations 12.3-52

12. 3. 5 EMERGENCY CLASSIFICATION SYSTEM 12.3-54 12.3.5.1 Emergency Action Levels 12.3-55 12.3.5.2 Protective Actions 12.3-56 12.3.5.3 Emergency Protective Action 12.3-58 Guidelines All Classifications Gaseous Release (Four Charts) 12.3.5.4 Emergency Protective Action 12. 3-62 Guidelines All Clc.ssifications-Liquid Releases 12.3.5.5 Initiating Conditions 12.3-63 12.3.5.6 Example Events 12.3-68 12.3.5.7 Emergency Classification of FSAR 12. 3-74 Postulated Transients 12.3.6 NOTIFICATION METHODS AND PROCEDURES 12.3-92 12.3.6.1 Notification of Emergency Response 12.3-93 Personnel and Organizations 12.3.6.1.1 On-Site 12. 3-93 12.3.6.1.2 Off-Site (Plant Staff) 12. 3-94 12.3.6.1.3 Off-Site Response 12. 3-95 Organizations

12. 3. 6. 2 Levels of Implementation for 12. 3-97 Alerting, Notifying and Mobilizing Response Personnel Revision 0 March 1, 1981

12.3.5.5 Initiatin Conditions 12.3.5.5.1 Unusual Event Initiatin Criteria

1. ECCS initiated

2. Radiological effluent technical specification limits exceeded

3. Fuel damage indication. Examples:

a. High coolant activity sample (e.g., exceed-ing coolant technical specifications for iodine spike)

b. Failed fuel monitor (PWR) indicates increase greater than 0.1% equivalent fuel failures within 30 minutes.

4. 'Abnormal coolant temperature and/or pressure or abnormal fuel temperatures

5. Exceeding either primary/secondary leak rate technical specification or primary system leak rate technical specification.

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6. Failure of a safety or relief valve to close

7. Loss of offsite power or loss of onsite AC power capability

8. Loss of containment integrity requiring shut-down by technical specifications

9. Loss of engineered safety feature or fire protection system function requiring shutdown by technical specifications (e.g., because of 12.3-63 Revision 0 March 1, 1981

malfunction, personnel error or procedural inadequacy)

10. Fire lasting more than 10 minutes

11. Indications or alarms on process or effluent parameters not functional in control room to an extent requiring plant shutdown or other significant loss of assessment or communication capability (e.g., plant computer, all meteoro-logical instrumentation)

12. Security threat or attempted entry or attempted sabotage

13. Uncontrolled rod 'withdrawal from a subcritical condition

14. .Uncontrolled rod withdrawal at power

15. Dropped RCCA assembly.: or bank

16. Uncontrolled dilution

17. Loss of one or more reactor coolant pumps above 50% power

18. Excessive Tavg-Tref Deviation

19. Natural phenomenon M.ing experienced or projected beyond usual levels

a. Any earthquake

b. 50 year flood or low water, t'sunami, hurricane surge, seiche c., Any tornado near site

d. Any hurricane

12. 3-64 Revision 0 March 1, 1981

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20. Other hazards being experienced or projected

a. Aircraft crash on-site or unusual aircraft activity over facility

b. Train derailment on-site

c. Near or on-site explosion

d. Near or on-site toxic or flammable gas release

e. Turbine failure

21. Other plant conditions exist that warrant increased awareness on the part, of State and/or local offsite authorities or require plant shut-down under technical specification requirements or involve other than normal controlled shutdown (e.g., cooldown rate exceeding technical specifi-cation limits, pipe cracking found during oper-ation)

22. Transportation of contaminated injured individual from site to offsite hospital

23. Rapid depressurization of PWR secondary side.

12.3.5.5.2 Alert Initiatin Criteria

1. Loss of one fission product barrier

a. ~ 300 ~Ci/cc I-131 coolant sample

b. ~50 gpm Primary Coolant Leak Rate

c. Loss of containment integrity

12. 3-65 Revision 0 March 1, 1981

2. Inoperability of a single complete safety system and which cannot be returned to operable within 15 minutes

a. ECCS subsystems

b. Containment Spray

c. Diesels

d. Control Room Evacuation

e. Batteries

3. O 2 mR/hr at Site Boundary under actual conditions

4. Other hazards, occurrences, or natural phenomena experienced on-site warranting activation of off-site response forces 12.3.5.5.3 Site Emer enc Initiatin Criteria

1. Loss of or potential loss of two fission prod~et barriers

. a. ~ 300 ~Ci/cc coolant sample (I-131)

b. ~ 50 gpm primary coolant. leak

c. Loss of containment integrity

2. Loss of one fission product barrier as above combined with inoperability of a single complete safety system when needed, or which cannot be restored operable within 1S minutes

a. ECCS subsystem

b. Containment Spray

c. Diesels

12. 3-66 Revision 0 March 1, 1981

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d. Control Room Evacuated

e. Batteries OR inoperability of two complete safety systems when needed

3. ~ 50 mR/hr whole body at site boundary under existing conditions

~250 mR/hr thyroid at site boundary under existing conditions

4. Natural phenomena experienced beyond design basis levels. Other hazards:

Winds, tornado, Earthquake

5. Other conditions occurring on-site warranting notification of the public to take precautionary measures or prepare to take such measures.

12.3.5.5.4 General Emer enc Xnitiatinq Criteria

1. Loss of or potential loss of' fission product.

barriers

a. ~300 aCi/cc I-131 coolant sample

b. ~50 gpm primary leak rate

c. Loss of containment integrity

2. Loss of two fission product barriers combined with inoperability of single complete safety system, when needed or which cannot be restored to operable within 15 minutes

a. ECCS subsystem

b. Containment Spray

12. 3-67 Revision 0 March.l, 1981

c. Diesel s

d. Control Room Evacuated

e. Batteries

3. N1 R/hr whole body at site boundary under existing conditions

~5 R/hr thyroid at site boundary under existing conditions

4. Other plant conditions exist that make release of large amounts of radioactivity in a short time possible.

12. 3.5. 6 Exam le Events 12.3.5.6.1 Exam le Alert Initiatin Events

1. Severe loss of fuel cladding

a. Very high coolan'ctivity sample (e.g.,

300wCi/cc equivalent of I-131)

b. Failed fuel monitor. (PWR) indicates increase greater than 1% fuel failures within 30 minutes or 5% total fuel failures

2. Rapid gross failure of one or more steam generator tubes with or without 3,oss of offsite power

3. Steam line break with significant (e.g.,

greater than 10 gpm) primary to secondary leak rate or with MS'XV malfunction

4. Primary coolant leak rate greater than 50 gpm

12. 3-68 Revision 0 March 1, 1981

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5. High radiation levels or high airborne con-tamination which indicate a severe degradation in the control of radioactive materials (e.g.,

increase of factor of 1000 in direct radiation readings)

6. Loss of offsite power and loss of all onsite AC power

7. Loss of all onsite DC power

8. Coolant pump seizure leading to fuel failure

9. Loss of functions needed for plant cold shutdown

10. Fuel damage accident with release of radio-activity to containment or fuel handling building

11. Fire potentially affecting safety systems

12. All alarms (annunciators) lost

13. Radiological effluents'greater than 10 times technical specification instantaneous limits (an instantaneous rate which, if continued over 2 hours, would result in about 1 mR at the site boundary under average meteorological conditions)

14. Ongoing security compromise

15. Severe natural phenomena being experienced or projected

a. Earthquake greater than OBE levels

b. Flood, low water, tsunami, hurricane surge, seiche near design levels 12.3-69 Revision 0 March 1, 1981

I

c. Any tornado striking facility

d. Hurricane winds near design basis level

16. Other hazards being experienced or projected

a. Aircraft crash on facility

b. Missile impacts from whatever source on facility

c. Known explosion damage to facility affect-ing plant operation

d. Entry into facility environs of toxic or flammable gases

e. Turbine failure causing casing penetration

17. Other plant conditions exist that warrant.

precautionary activation of technical support center and near-site emergency operations center

18. Evacuation of control room anticipated or required with control of shutdown systems established from local stations 12.3.5.6.2 Exam le Site Emer enc Initiatin Events

1. Degraded core with possible loss of eoolable

.geometry (indicators should include instru-mentation to detect inadequate core cooling, coolant activity and/or containment radio-activity levels)

2. Rapid failure of more than 10 steam generator tubes with loss of offsite power

12. 3-70 Revision 0 March 1, 1981

3. PWR steam line break with greater than 50 gpm primary to secondary leakage and significant indication of fuel damage

4. Loss of offsite power and loss of onsite AC power for more than 15 minutes

5. Loss of all vital onsite DC power for more than 15 minutes

6. Loss of functions needed for plant hot shut-down

7. Fire affecting safety systems

8. All alarms (annunciators) lost for'ore than 15 minutes and plant is not in cold shutdown or plant transient initiated while all alarms lost

9. a. Effluent monitors detect levels correspond-ing to greater than 50 mR/hr for 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or greater than 500 mR/hr W.B. for two minutes (or five times these. levels to the thyroid) at 'the site boundary for existing meteorology

b. These dose rates're projected based on other plant parameters (e.g., radiation level in containment. with leak rate appro-priate for existing containment pressure) or are measured in the environs

10. Imminent loss of physical control of the plant

12. 3-71 Revision 0 March 1, 1981

11. Severe natural phenomena being experienced or projected with plant not in cold shutdown

a. Earthquake greater than SSE levels

b. Flood, low water, tsunami, hurricane surge, seiche greater than design levels or failure of protection of vital equipment at lower levels

c. Winds in excess of design levels

12. Other hazards being experienced or projected with plant not in cold shutdown

a. Aircraft crash affecting vital structures by impact or fire

b. Severe damage to safe shutdown equipment from missiles or explosion

c. Entry of toxic or flammable gases vital areas

13. Other plant conditions exist that warrant activation of emergency centers and monitor-ing teams and a precautionary public notifi-cation

14. Evacuation of control room and control of shutdown systems not established from local stations in 15 minutes 12.3.5.6.3 Exam le General Emer enc Initiatin Events

1. Small and large LOCA's with failure of ECCS to perform leading to severe core degradation 12.3-72 Revision 0 March 1, 1981

or melt. Ultimate failure of containment likely for melt sequences. (Several hours available for response)

2. Transient initiated by loss of feedwater and condensate systems (principal heat removal system) followed by failure of emergency feed-water system for extended period. Core melting possible in several hours. Ultimate failure of containment likely if core melts.

3. Transient requiring operation of shutdown systems with failure to scram. Core damage for some designs. Additional failure of core cooling and makeup systems would lead to core melt.

4. Failure of offsite and onsite power along with total loss of emergency feedwater makeup capability for several hours would lead to eventual core melt and likely failure of con-tainment.

5.. Small LOCA and initially successful ECCS.

Subsequent failure of containment heat removal systems over several hours could lead to core melt and likely failure of containment.

12 ~ 3 73 Revision 0 March 1, 1981

12.3.5.7 Emergency Classification of FSAR Postulated Transients The FSAR postulated transients are classified into emergency event categories as indicated below. The transients are bounded by the conditions set forth in Chapter 14 of the FSAR. Reference to the applic-able FSAR section is indicated by the number in

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Emergency Example FSAR Event Descri tion Classification No.

1. Uncontrolled Rod Withdrawal Unusual Event 13 (subcritical)

(14.1.1).

2. Uncontrolled Rod Withdrawal Unusual Event 14 (at power)

(14.'1.2)

3. RCCA Misalignment Unu'sual Event (14.1. 3) or (14.1. 4)

4. CVCS Malfunction Unusual Event (14.1.5')

5. Loss of Reactor Coolant Unusual Event 17 Flow (14.1.6)

6. Inactive Loop Startup (14.1.7)

7. Loss of Load (14.1.8)

8. Loss of,-Normal Feedwater (14.1.9)

• Not classified as an Emergency Condition 12.3-74 Revision 0 March 1, 1981

Emergency Example FSAR Event Descri tion Classification No.

9. Feedwater System Unusual Event 18 Malfunction (14.1.10)

10. Excessive Load Xncrease Unusual Event (14.1.11)

11. Loss of All AC Power to Unusual Event.

Station (14.1.12)

12. Turbine Generator Accident Unusual Event (14.1.12)

13. Fuel Handling Accident Alert 10 (14.2.1)

14. Accidental Licpxid Release Alert 13 (14.2.2)

15. Accidental Gaseous Relesae Alert 13 (14.2.3)

16. S.G. Tube Rupture Alert (14. 2. 4 )

17. Steam Line Break Unusual Event 18, 1, 21 (14.2.5)

18. Control Rod Ejection Alert (14. 2. 6)

19. Secondary Side Release Unusual Event 3 (14.2.7) Alert 1

20. LOCA Alert (14. 3)

NOTE: Majority of these examples could be classified more or less severely depending on actual conditions present at the time.

12.3-75 Revision 0 March 1, 1981

Pages 12.3-76 through 12.3-91 have been left blank intentionally.

ATTACHMENT 3 TO AEP:NRC'0308F

INSERT TO APPENDIX A

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INDIANA 5 MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT PLANT MANAGER PROCEDURE Index Ident> scat>on evssson No Number Title And Date Comments PMP 2080 EPP.001 Emergency Plan Activation Revision 0 and Condition Classification 4-1-81 EPP.002 Unusual Evept Revision 0 4-1-81 EP P.003 Al crt Revision 0 4-1-81

. EPP.004 Site Emergency Revision 0 4-1-81 EPP.005 General Emergency Revision 0 4-1-81 EPP.006 Initial Dose Assessments and "

Revision 0 Veri f ication (Gaseous) - ~ 4-1-81 EPP.007 Initial Release Assessments Revision

. 4-1-81 0

and Verification (Liquid)

EPP.008 Calling Of f-Duty Plant Revision 0 Personnel 4-1-81 EPP.009 Fire Emergency Guidelines . Revision 0 4-1-81 EPP.010 Chl orine Gas Release Revision 0 Gu idel ines 4-1-81 EPP.Oll Natural Emergency Guidelines Revision 0 4-1-81 EPP.012 Initial Of f-Site Revision 0 No tifications 4-1-81 EPP.013 Duties of the Individual Who Revision 0 Discovers an Emergency 4-1-81 Condition Page 1 .

Rev. Date 4-1-81

INDIAN'A 5 MICHIGAN POHER COMPANY DONALD C. COOK NUCLEAR PLANT PLANT MANAGER PROCEDURE Index ent1 1 cation evasion No.

Number Title And Date Comments PMP 2081 EPP.001 Emergency Communications Revision 0 4-1-81 EPP.002 Barring of the PBX Revision 0 4-1-81 EPP.003 Follow-Up Off-Site Revision 0 Comnunications 4-1-81 EPP.004 Protective Action Guides Revision 0 (PAGs) and Protective Actions 4-1-81 EPP.005 Personnel Accountability and Revision 0 Site Evacuation 4-1-81 EPP.006 Activation of the Reentry Revision 0 and Rescue Team 4-1-81 EPP.007 Security Actions During Revision 0 Emergency Conditions 4-1-81 EPP.008 Emergency Medical Plan Revision 0 Guidelines 4-1-81 EPP.009 Health Physics Procedures Revision 0 4-1-81 EPP.010 Activation of Radiation Revision 0 Monitoring Teams 4-1-81 EPP.011 On-Site Radiological Revision 0 Monitoring 4-1-81 EPP.012 Of f-Site Radiological Revision 0 Monitoring 4-1-81 EPP.013 Environmental Monitoring Revision 0 and Analysis 4-1-81 Page 2 Rev. Date 4-1-81

INDIANA 5 MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT PLANT MANAGER PROCEDURE Index Ident> >cation ev>sson No.

Number Title . And Date Comments PHP 2081 EPP.014 Off-Site Dose Assessments Revision 0 4-1-81 EPP.015 Sampling and Analysis of Revision 0 Waterborne Releases 4-1-81 EPP.016 Collection and Analysis of Revision 0.

Liquid and Gaseous Samples 4-1-81 EPP.017 Interpretation of Liquid Revision 0 and Gaseous Samples 4-1-81 EPP.018 Transportation Accidents Revision 0 Involving Radioactive 4-1-81 Material EPP.019 AEP Emergency Response Revision 0 Organization Activation and 4-1-81 Management EPP.020 Activation and Operation of Revision 0 .

the Technical Support Center 4-1-81 (TSC)

EPP.021 Activation and Operation of Revision 0 the Operations Staging Area 4-1-81 (OSA)

EPP.022 Activation and Operation of Revision 0 the Recovery Center (RC) (An 4-1-81 Emergency Operations Facility)

EPP.023 Activation and Operation of Revision 0 the Emergency Control Center 4-1-81 (ECC) (An Emergency Operations Facility)

EPP.024 Activation and Operation of 'evision 0 the Joint Public Information 4-1-81 Center (JPIC) (An Emergency Operations Facility)

Page 3 Rev. Date 4-1-81

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Iki&JANA 5 tlICHIGAN POHF.R COMPANY

~HALD C. COOK NUCLEAR PLANT PLANT flANAGER PROCEDURE Index Identification Revision No.

Number Title And Date Comments PblP 2081 EPP.025 Activation and Operation of Revision 0 the Emergency Hews (ENS) 4-1-81 (An Emergency Source Operations Facility)

EPP.026 Personnel Assignment to Revision 0 Off-Site Centers 4-1-81 EPP.027 Off-Site Support and Revision 0 Assistance 4-1-81

'PP.028 Damage Control, Repair and Revision 0 Recovery 4-1-81 Page 4 Rev. Date 4-1-81

~, e' &. <<

~ I "I ANA 5 MICilIGAN PO>lER COMPANY DONALD C. COOK NUCLFAR PLANT PLANT MANAGER PROCEDURE Index Identif ication. Revision No.

Number Title And Date Comments PMP 2082 EPP.001 Emergency Exposure Guidelines Revision 0 4-1-81 EPP.002 Public Information Revision 0 Dissemination 4-1-81 EPP.003 Maintenance of Emergency Revision 0 Records 4-1-81 EPP.004 Emergency Per sonne 1 Revision 0 As s ignments 4-1-81 EPP.005 Tests, Drills and Exercises Revision 0 4-1-81 EPP.006 Training Revision 0 4-1-81 EPP.007 Emergency Equipment and Revision 0 Supplies 4-1-81 EPP.008 Maps and Forms Revision 0 4-1-81 EPP.009 Maintenance of the Emergency Revision 0 Plan Procedures 4-1-81 EPP Appendix A Telephone and Call Numbers Revision 0 4-1-81 EPP Appendix 8 Memorial Hospital Plan Revision 0 4-1-81 Page 5 Rev. Date 4-1-81

'APPENDIX B The AEP Emergency Response Organization Procedures will be incorporated into a single document entitled the AEP Emergency Response Manual. This manual will contain subsections which provide the procedures outlining the job functions and responsibilities of each AEP-ERO manager designated on the organization chart Figure 12.3-4 as well as identification of the specific individuals who fill position in the AEP-ERO by title.,