ML19331D173

Amend 19 to Restart Rept

ML19331D173
Person / Time
Site:	Three Mile Island
Issue date:	08/04/1980
From:	METROPOLITAN EDISON CO.
To:
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ML19331D171	List: ML19331D170 ML19331D173
References
NUDOCS 8008270416
Download: ML19331D173 (200)

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RE? ORT IN RESPONSE TO NRC STAFF RECOMMENDED REQUIREMENTS FOR RESTART OF THREE MILE ISLAND FJCLEAR STATION UNIT 1 AMENDMENT 19 INSTRUCTIONS Those sheets of the TMI-l Restart Report listed in the left-hand column are to be deleted and, where appropriate, replaced with the revised sheets listed in the culumn on the right.

REMOVE INSERT Section 4 Section 4 Remove Entire Section Insert Entire Section Page 4-1 through Appendix D Page 4-1 through Appendix D through I through I 1

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(, k l 8008270 1 :1

4.0 EMERGENCY PLAN FOR THREE MILE ISLAND NUCLEAR STATION UNIT 1 See report following.

'1 Amendment 19

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J GPU NUCLEAR CORPORATION DiERGENCY PLAN FOR THREE MILE ISLAND NUCLEAR STATION UNIT 1 June 1980 Revision 2 Amendment 19

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, TABLE OF CONTENTS Section Topic Page i

4.1.0 DEFINITIONS 1-1 1

4.2.0 APPLICABILITY AND SCOPE 2-1 4.2.1 Applicability of the Emergency Plan 2-1 4.2.1.1 General Information and Site Description 2-1 l 4.2.1.2 Restricted Area, Exclusion Area, and Low Population Zone 2-2 4 .'2 .1. 3 Population and Population Distribution 2-3 4.2.1.4 Nearby Industri.-l, Transportation, and Military Facilities 2-3 l

4. 2.1.5 Emergency Planning Zone 2-5 '

4.2.2 Scope of the Emergency Plan 2-5 4.2.2.1 Emergency Plan Implementing Document 2-6 4.2.2.2 Related TMI Plans, Programs, and Procedures 2-6 4.2.2 3 Related County and State Plans 2-7 4.3.0

SUMMARY

OF Dil EMERGENCY PLANNING PROGRAM 3-1 4.3.1 The Emergency Plan 3-1 4 3.2 The Implementing Document 3-2 4.4.0 EHERGENCY CONDITIONS 4-1 4.4.1 Licensee Classification System 4-1 4.4.1.1 Unusual Event 4-2 4.4.1.2 Alert 4-3 4.4.1.3 Site Emergency 4-6 4.4.1-4 General Emergency 4-7 4.4.2 State and County Classification System 4-9 4.4.3 Spectrum of Postulated Accidents 4-9 4.4.3.1 Classification of Hypothetical Accidents 4-9 4.4.3.2 Instrumentation capability for Detection 4-9 4.4.3.3 Manpower and Timing Considerations 4-10 4.5.0 ORGANIZATIONAL CONTROL OF DfERGENCIES 5-1 4.5.1 Licensee Organiz__lons 5-1 4.5.1.1 Normal Station Organization 5-2 4.5.1.2 Normal Station Support Organization 5-4 4.5.1.3 Onsite Emeraency Organization 5-5 4.5.1.4 Of fsite Emety:ncy Support Orgsnization 5-12 4.5.1.5 Long-Term Recovery Organization 5-15 4.5.2 Local Services Support 5-17 4.5.2.1 Medical Support Organizations and Personnel 5-17 4.5.2.2 Firefighting Organizations 5-17 4.5.2 3 Law Enforcement Agencies 5-18 4.5.2.4 Miscellaneous Support 5-18 4.5.3 Coordinat*.on with Government Agencies 5-18 4.5.3.1 State Agencies 5-18 4.5.3.2 County Agencies 5-21 4.5.3.3 Federal Agencies 5-24 4.5.3.4 Interagency Communications 5-24 4.5.4 Training of State, County and Local Governments 5-25 Revision 2 1 June 1980 Amendment 19

TABLE OF CONTENTS Section Topic Pagt v

4.6.0 EMERGE)CT MEASURES 6-1 4.6.1 Emergency Notification of Of fsite Agencias 6-1 4.6.2 Mobilization of Emergency Organizations 6-1 4.6.2.1 Shif t Foreman / Control Room Operators 6-2 4.6.2.2 Shif t Supervisor 6-2 4.6.2.3 Duty Section Superintendent 6-3 4.6.2.4 Emergency Director 6-3 4.6.2.5 Dauphin County 6-4 4.6.2.6 Pennsylvania Emergency Management Agency 6-4 4.6.2.7 Bureau of Radiation Protection 6-4 4.6.3 Assessment Actions 6-5 4.6.3.1 Assessment Actions for Unusual Events 6-5 4.6.3.2 Assessment Actions for Alerts 6-5 4.6 3.3 Assessment Actions for Site Emergencies 6-6 4.6.3.4 Assessment Actions for General Emergencies 6-6 4.6.3.5 Radiological Assessment and Of fsite Monitoring 6-7 4.6.4 Corrective Actions 6-11 4.6.5 Protective Actions 6-10 4.6.5.1 Protective Cover, Evacuation, Personnel Accountability 6-10 4.6.5.2 Use of Onsite Protective Equipment and Supplies 6-13 4.6.5.3 Emergency Equipment Readiness 6-15 4.6.5.4 Contamination Control Measures 6-16 4.6.6 Aid to Af fected Personnel 6-16 4.6.6.1 Emergency Personnel Exposure 6-16 4.6.6.2 First Aid and Decontamination 6-17

'" 4.6.6.3 Medical Transportation 6-19

. 4.6.6.4 Medical Treatment 6-20 4.6.7 Early Warning and Information for Transient Areas 6-21 4.6.7.1 Early Warning 6-21 4.6.7.2 Information for Transient Areas 6-22 4.7.0 EMERGENCY FACILITIES AND EQUIPMENT 7-1 I 4.7.1 Licensee Onsite Emergency Centers 7-1 4.7.1.1 Emergency Control Center 7-1 4.7.1.2 Technical Support Center 7-1 )

4.7.1.3 Operations Support Center 7-2 4.7.2 Licensee Of fsite Emergency Centers 7-3 4.7.2.1 Near-site Emergency Operations Facility 7-3

4.7.2.2 Backup Near-site Emergency Operations Facility 7-3 l 4.7.2.3 Environmental Assessment Command Center 7-3 l l 4.7.2.4 Parsippany Technical Punctions Center 7-3 1 4.7.3 County, State, and Federal Emergency Centers 7-4 4.7.3.1 County Emergency Centers 7-4 4.7.3 2 State Emergency Center 7-4 4'.7 3.3 Federal Emergency Center 7-5 4.7.4 Media Center 7-5 4.7.5 Communications Systems 7-5 Revision 2 11 June 1980 Amendment 19

TABLE OF CONTENTS Section Topic ,Pm v

4.7.5.1 Operational Line 7-6 4.7.5.2 Radiological Line 7-6 4.7.5 3 NRC Emergency Notification .*ystem (ENS) 7-6 4.7 5.4 Health Physics Network Line (HPN) 7-7 4.7.5.5 Environmental Assessment Line 7-7 4.7.5.6 Parsippany/B&W Line 7-7 4.7.5.7 Parsippany/TMI Line 7-7 4.7.5.8 National Warning System Line (NAWAS) 7-8 4.7.5.9 Emergency Director's Auto-Dialer Phone 7-8 4.7.5.10 Pennsylvania Bell System 8 4.7.5.11 Microwave System 7-8 4.7.5.12 Radio Communications 7-9 4.7.5.13 Parent County Emergency Operations Center Communicatien 7-9 4.7.5.14 Inter-Control Room Hot-Line 7-9 4.7.5.15 Emergency Director's Hot-Line 7-10 4.7.5.16 Alarms 7-10 4.7.5.17 Plant Paging System 7-10 4.7.5.18 Maintenance and Instrumentation Phone System 7-10 4.7.6 Assessment Facilitics 7-10 4.7.6.1 Onsite Systems and Equipment 7-10 4.7.6.2 Facilities and Equipment for Offsite Monitoring 7-17 4.7.7 Protective Facilities and Equipment 7-21 4.7.8 First Aid and Medical Facilities 7-22 4.7.9 Dansge Control Equipment 7-23 m 4.7.10 Radiological Control Equipment , 7-23 4.3.0 MAINTAINING EMERGENCY PREPAREDNESS 8-1 4.8.1 Organizational Preparedness 8-1 4 . 8 .1.1. Training 8-1 4.8.1.2 Drills and Exercises 8-5

. .. _ 4.8.1.,3. . . .. Emergency . P1 anning Coordinator 8-8 4.8.2 Review and Updating of the Emergency Plan and 8-9 Implementing Document 4.8.3 Maintenance and Inventory of Emergency Equipment 8-9 and Supplies 4.9.0 RECOVERY 9-1 1

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10.0 REFERENCES

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LIST OF FIGUREG Figure No. Title

,, 1 , General Area Map 2 Three Mile Island Nuclear Station Facility Arrangement 3 Three Mile Island Relative Location 4 T'3I Exclusion Ares & Low Population Zone 5 Population Distribution 6 Counties and Communities Within a 50 Mile Radius 7 Industrial and Military Facilities Within a 5 Mile Radius 8 Emergency Planning Zone 9 GPU-Nuclear Unit 1 Station Organization 10 TMI :it 1 Shif t Organization 11 GPU-Nuclear Station Support Organization 12 Onsite Emergency Organization 13 Offsite Emergency Support Organization 14 Long-Term Recovery Organization 15 Notification Network 16 Deleted 17 Deleted 18 Emergency Facilities - General Location 19 communications Systems Interf aces 20 Daergency Response Organization Interrelationships 21 Dose to Thyroid from Inhalation of Iodines 22 Gamma Dose to Whole Body 23 Assumptions Used in Figures 21 and 22 24 Exposure Rate-Dome Monitor Outside Shield (Core Cases) 25 Exposure Rate-Dome Monitor Inside S'aield (Core Cases)  ;

26 Exposure Rate-Dome Monitor Outside. Shield (Gap Gases) 27 Exposure Rate-Dome Monitor Inside Shield (Cap Gases)  !

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Amendment 19

t LIST OF TABLES v Table No. Readinn 1 Major Residential Areas 2

Gehools Located Within a 10-Mile Radius of TMI 3- Bospitals Located Within a 10-Mile Radius of TMI 4 Percent of Land Use By County 5 Typical Major. Industries Within a 10 Mile Radius of TMI 6 Accident Classifications 7 Instruments for Accident Detection 8 Manpower and Timing Considerations for Emergencies 9

Radiation Monitoring System - Summary De4cription a 10 TLD Locations 11 Radiological Emergency Assistance from Offsite Agencies 12 Periodic Training of Emergency Personnel v 13 Inventory of Emergency Kits by General Category 14 Unusual Event Summary 15 Alert Summary 16 Site Emergency Summary 17 General Emergency Summary 18 Communications Network 19 EPIP's ";<! For Each Emergency Class 20 Typical Portable Environmental / Radiological Monitors v Aevision 2 v June 1980 Amendment 19

9 APPENDICES APPENDII TITLE A Emergency Plan Implementing Document Table of Contents 3 Emergency Public Information Plan for Three Mile Island Nuclear Generati g Station C Letters of Agreement and Understanding D Commonwealth of Pennsylvania Disaster Operations Plan, Annex E, Emergency Nuclear Incfdents (Pixed Nuclear Pacility)

Annex H, Communications ,

Annex I, Warning E , Dauphin County Action and Response Plan for Emergency Personnel. and Citizens P York Couttty Evacuation Plan for the Three Mile Island Nuclear lower Plant G Lancaster County Emergency Evacuation Plan H Cumberland County Evacuation Plan 79-1 (For Response to a Nuclear Incident at Three Mile Island Nuclear Station)

I Lebanon Comty Emergency Operations Plan l

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4.1.0 DEFINITIONS

, The following is a list of terms and their definitions which will be used, as appropriate, in the Three Mile Island Nuclear Station (Unit 1)

Emergency Plan and Implementing Document:

411 Access Control Point - An access control point serves as the boundary line between a clean and a radiologically controlled area of the plant. The main access control point is located in the Nuclear Services Area, elevation 306.0', Control Building in Unit 1.

4.1.2 Accident - An unintentional event which may result in an emergency.

4.1.3 Adverse Meteorolony - The 5 percent probable meteorology. (i.e.

Pasquill Stability F,1.5 mph) . For the exclusion area boundary, this corresponds to a X/Q value of 6.8 x 10-4 sec./M3 .

4.1.4 Af fected Persons - Persons who, as the result of an accident, have been or may be radiologically exposed or physically injured to a degree requiring special attention (e.g., evacuation, decontamination, first aid or medical services, etc.) .

4 .1.5 Alert - The occurrence of an event or series of events that indicate and allow recognition of an actual or potential substantial degradation of the level of safety of the plant.

4.1.6 Assessment Actions - Those actions taken during or af ter an accident which are collectively necessary to make decisions to implement specific emergency s- actions.

4.1.7 Control Room - The location at Three Mile Island Nuclear Station (TMI) on elevation 355.0' of the Unit 1 Control Building from which the reactor and its auxiliary systems are controlled.

4.1.8 Clean Area - An area where the contamination levels are below those speci-fled below:

Loose surf ace contamination (Beta-Gamma) < 1000 DPM/100cm2, Loose surf ace contamination ( Alpha) <100 DPM/100cm2 71xed contamination < 0.1 mR/ hour on contact.

4 .1.9 Contaminated Area - An area where the contamination levels are in l excess of those specified for a clean area.

4.1 10 Radiologically Cortrolled Area - All plant areas where radiation or con-tamination has a potential for existing in the amounts above the limits set forth for a clean area.

I 4.1.11 Corrective Actions - Those emergency actions taken to ameliorate or terminate an emergency situation at or near the source of a problem.

4.1.12 Emergenev - That situation or condition which may result in damage l co property and/or may lead to undue risk to the health and safety of the general public and/or site personnel.

l Revision 2 4.1-1 June 1980 Amendment 19

4.1.13 Emergenev Actions - Those measures or steps taken to ensure that an emergency situation is assessed (assessment actions) and that the proper corrective and/or protective actions are taken.

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4.1.14 Emerzenev Action Levels - Predetermined conditions or values, including radiological dose rates; specific contamination levels of airborne, water-borne, or surf ace-deposited concentrations of radioactivt materials; events such as natural disasters or fires; or specific instrument imii-cations dich, den exceeded, :(quire the implementation of the Emergency Plan.

4 1.15 Emergenev Classifications - The characterization of several classes of emergency situations consisting of mutually exclusive groupings including the entire spectrum of all possible emergencies. The four classes of emergencies which have been incorporated into this Baergency Plan are (1) Unusual Event, (2) Alert, (3) Site Energency, and (4) General Emergency.

4.1.16 Energenev Control Center - The designated location from which control and/or coordination of emergency actions is ef fected. The designated Emergency Control Center for M Unit 1 is that area encompassing the Shif ts Supervisor's Of fice and the Control Room both of *1ch are on elevation 355 0' in the Unit 1 Control Building.

4.1.1" Emergenev Core Cooling Svstem - The Emergency Core Cooling System (ECCS) includes the pertinent pumps, piping, valves, etc. of the Decay Heat Removal System, Core Flooding Syste.m, and the makaup portion of the Makeup and Purification System.

m 4.1.18 Emergenev Director - Designated onsite individual having the responsibility and authority for implementing the M Emergency Plan and who will coor-dinate efforts to limit the consequences of the emergency and bring it under control.

4.1.19 Emergenev operations Center - Designated State,. county, and local civil defense headquarters f acilities especially designed and equipped for the purpose of exercising effective coordination and control over disaster e operations carried out within their jurisdiction.

4.1.20 Emergenev Plan - GPU Nuclear Corporation plans for coping with amer-gencies at the M site.

4.1.21 Emergenev Plan Implementing Procedures - Specific procedures in the l

laplementing Document that include emergency action levels and provide step-by-step emergency actions.

4.1.22 Emergenev Planning Zone - There are two Emergency Planning Zones.

The first is an area, apprcximate y 10 miles in radius around the M Nuclear Station, for which emergency planning consideration of the plume exposure pathway has been given in order to assure that prompt and effective actions can be taken to protect the public and property in the event of an accident. This is called the 10 mile EPZ. The second is an area approximately 50 miles in radius around the M Nuclear Station, for which emergency planning consideration of the ingestion exposure pathway has been given. This is called the 50 ile EPZ.

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4.1.23 Emergenev Procedures - Specific procedures that provide step-by-step instructions to guide plant operations during potential or real amer-m gency situations.

4.1.24 Emergency Support Director - Designated GPU Nuclear Corporation employee from the senior management staff who has overall responsi-bility for accident management and for providing direction and support to the Emergency Director.

4.1.25 Exclusion Area - As defined in 10 CFR 100.3, that area surrounding the reactor, in which the licensee has the authority to determine all activities including exclusion or removal of personnel and property

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from the area.

4.1.26 General EmerRency - Accidents which involve actual or imminent substantial core degradation or melting with potential for loss of Reactor Building (containment) integrity, and other accidents that have large radioactive release potential such .3 fuel handling and waste gas system accidents.

4 1.27 Implementing Document - The document containing an abstract of the TMI Emergency Plan, Emergency Plan Implementing Procedures, and other specific information as required.

4.1.28 Ingestion Exnosure Pathway - The means by which a radioactive plume can expose the population-at-risk and/or on-site personnel to internal contamination resulting from ingestion of contaminated water or foods such as milk or fresh vegetables. The time of potential exposure could range in length from v hours to months.

. 4.1.29 Low Population Zone - As defined in 10 CFR 100 3, the area immediately surrcunding the exclusion area which contains residents, the t'otal number and density of which are such that there is a reasonable prob-ability that appropriate protective measures could be taken in their behalf in the event of a serious accident.

4.1. 30. .. 0f fsite. - Any area outside of the owner property boundary of the Three Mile Island Nuclear Station.

4.1.31 Onsite - Any area within the owner property boundary of the Three Mile Island Nuclear Station.

4.1.32 Operable - As defined in Technical Specifications (reference 10.13 1),

a component or system is operable when it is capable of performing its intended function within the required range.

4.1.33 owner controlled Area - That area within the security fence that surrounds the immediate site area (i.e. fence that extends from the south vehicle gate north on both shorelines to the north gate) .

4.1.34 Personnel Mot.itorina Equipment - As defined in 10 CFR 20 202, devices designed to be worn or carried by an individual for the purpose of measuring the dose received (e.g., film badges, pocket dosimeters, thermoluminescent dosimeters, etc.) .

v Revision 2 4.1-3 June 1980 Amendment 19

4.1.35 Not used.

v 4.1 36 Plume Exposure Pathwsv - The means by which a radioactive plume can expose the population-at-risk and/or onsite personnel to radiation.

The time of potential exposure could range from hours to days. The principal exposure sources from this pathway are: (1) whole body external exposure to gsama radiation from the radioactive plume and from deposited material, and (2) inhalation exposure from the passing radioactive plume.

4.1 37 Populatien-At-Risk - Those persons for when protective actions are being or would be taken.

4.1 38 Population Center Distance - The distance frcus the reactor to the nearest boundary of a density populated center containing more than about 25,000 residents. -

4.1 39 .P_r_o_tected Dose - A calculated or estimated dose which the population-at-risk may potentially receive as a result of a radiological essergency.

4.1.40 Protected Area - As defined in 10 CFR 73.2, an area encompassed by physical barriers and to which access is controlled. The TMI Nuclear Station Protected Area includes all areas within the security fence v

that immediately surrounds the major Station structures (i.e. Reactor,

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Auxiliary, Turbine, Service, Puel Handling, and Control Buildings) .

4.1.41 Protective Actions - Those actions taken Asring or af ter an emergency situation that are intended to minimize or eliminate the bazard to the health and safety of the general public and/or onsite personnel.

4.1.42 Protective Action Guides - Projected radiological dose or dose commitment

. values to individuals in the general population that warrant protective - - -

action following a release of radioactive material. Protective actions would be warranted provided the reduction in individual dose expected to be achieved by carrying out the protective action is not offset by excessive risks to individual safety in taking the protective action.

The protective action guide does not include the dose that has unavoid-ably occurred prior to the assessment.

4.1.43 Recoverv Actions - Those actions taken af ter the emergency to restore the plant as nearly as possible to its pre-emergency condition.

4.1.44 Restricted Area - As defined in 10 CFR 20.3, any area access to which is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials. A restricted area shall not include any areas used as residential quarters, although a separate room or rooms in a residential building may be set apart as a restricted area.

Revision 2 4J-4 June 1980 Amendment 19 l

4.1.45 _ Site Emerzenev - Accidents in which actual or likaly major failures of plant functions needed for protection of the public have occurred.

s his emergency class includes accidents whi:.h have a significant radiation release potential.

4.1.46 State - ne Ccanonwealth of Pennsylvania.

4.1.47 Not used.

4.1.48 Unrestricted Area - As defined in 10 CFR 20.3, any area access to which is not controlled by the licensee for the purposes of protection of individuals frem exposure to radiation and radioactive materials, and any area used for residential quarters.

4.1.49 Ususual Event - n e occurrence of an event or events that indicates or allows recognition of a potential degradation of the level of safety of the plant, including contaminated injuries of plant personnel which require offsite emergency treatment.

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t 4.2.0 APPLICABILITT AND SCOPE The prime objectives in emergency planning are to: (1) provide the

' means for nitigating the consequences of emergencies (including very low probability events) in order to protect the health sad safety of the general public and site personnel and to prevent damage to property and (2) develop a plan and implementing procedures that will ensure operational readiness and esergency preparedness.

This Emergency Plan has been developed for the Three Mile Island Nuclear Station (Unit 1) in accordance with the provision of 10 CFR 50 34, and is consistent with the guidelines given in (1) Regulatory Guide 1.70, " Standard Content an/ Format of Saf ety Analysis Reports for Nuclear Power Plants", Revision 3; (2) Regulatory Guide 1 101,

" Emergency Planning for Nuclear Plants", Revision 1 dated March 1977; and (3) " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants", NUREG 0654/FDiA-REP-1, dated January 1,1980. Other guidance and sources of information, which are identified in Section 4.10.0 below, were also used in the development of this Emergency Plan.

Although many of the features and requirements detailed in this Plan are, or will be implemented within a relatively abort period of time following the NRC approval, all aspects of the Plan will be fully implemented prior to the restart of TMI Unit 1.

4.2 1 Apolicability of the Emergency Plan 4.2.1.1. General Information and Site Description Three Mile Island Nuclear Station (Unit 1) is operated by GPU Nuclear Corporation (GPU-Nuclear) .* A general area map, provided as Figure 1, shows the relative location of the f acility within the State of Pennsylvania.

The Three Mile Island (TMI) Nuclear Station has a pressurized

, water type nuclear stesa supply system supplied by the Babcock & Wilcox Company. It uses chemical shim and control rods for reactivity control and generates steam with a small smount of superheat in once-through stesa generators. The arrangement of the major TMI Nuclear Station facilities is shown on Figure 2.

The TMI Nuclear Station is located in an area of low popula-l tion density about 12 miles southeast of Harrisburg, Pennsyl '

vania. It is in Londonderry Township of Dauphin County, about 2 5 miles north of the southern tip of Dauphin County,

'where Dauphin County is coterminal with York and Lancaster ,

Counties. l The TMI Nuclear Station site is part of an 814 acre tract consisting of Three Mile Island and several adjacent islands j l

• The GPU-Nuclear Corporation does not yet formally exist. Licensee intends to establish GPU-Nuclear and to organize its personnel as described in this Emergency Plan. Until such time as GPU-Nuclear is established, references to it should be read in a manner consistent with the organi-zational structure depicted in Section 5.0 of the Restart Report.

Revision 2 4.2-1 June 1980 Amendment 19

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which were purchased by a predecessor company of GPU Nuclear Corporation. These lands are part of the York Haven licensed ,

v power project (FPC 1886' . The TMI Nuclear Station is physi-I cally located on Three Mile Island which is one of the largest or a group of several islands in the Susquehanna River upstream i from York Haven Dam. The island is relatively flat-land and is wooded on the periphery and on the southern portion. Hills on both sides of the river rise to elevations of over 500 feet. Of the 470 acres which comprise Three Mile Island, approximately 200 acres on the northern portion of the island are set aside for the Station.

The island, which is situated about 900 feet from the east bank and approximately one .ile from the west bank of the Susquehanna River, is elongated parallel to the flow of the river with its longest axis oriented approximately due north and south. The island is approximately 3 miles long and 1700 feet vide and is at an elevation of 300 feet. Its location relative to the other islands in the Susquehanna is shown on Figure 3. Upstream, in the vicinity of Middletown, the southeasterly flowing Susquehanna River makes a sharp change in direction to near due south. Af ter this change in direction, which is just north of Three Mile Island, the

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river channel videns to approximately 1.5 miles.

An access bridge now used by site personnel connects State Highway Route 441 with the north end of the island across Sand Beach Island. A wood access bridge connects the south v end of the island with Route 441 as well. Route 441 1s a

- teo lane, black top road which runs north and south parallel to Three Mile Island on the east bank of the Susquehanna River and is more than 2,000 feet from the M Unit I reactor at the closest point.

The IMI Nuclear Station site is surrounded, except along its southern border, by the York Haven Pond which is formed by a low dan east andeouth of the site. "'his das does not have I locks and there is no commercial water transportation on the river adjacent to the site. On the east back of the river there is a Conrail one-track line which runs adjacent and parallel to Route 441. On the west bank of the river, there 1s a multi-track Conrail line at the river's edge about 1.25 l

miles vest of the site and a black top, two lane road that runs parallel to it. There is a one-track railroad spur across the bridge on the north end of the island which is used for site-related activities.

j 4.2.1.2 Restricted Area, Exclusion Area, and iov Population Zone l

I 1. The restricted area for the Three Mile Island Nuclear Station includes all a eas within the owner controlled area. The mini =u= distance to the restricted area (security tence) beundary is measured from the center-line of _ne TMI Unit 2 Reactor Building to a point on N

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the western shoreline of the island and is approximately 560 feet.

2. The exclusion area for the Three Mile Island Nuclear

- Station is a 2,000 foot radius that includes a portion of Three Mile Island, the river surf ace around it, and a portion of Shelly Island. The minimum distance of 2,000 feet occurs on the shore of the mainland in a due easterly direction. All land areas within the exclusion area are owned by the Licensee. A map showing the exclusion area boundary is included as Figure 4.

3. The low population zone for the Three Mile Island Nuclear Station has a minimum distance of 2 miles to its outer boundary. The area of the low population zone is also shown on Figure 4.

4.2.1.3 Population and Populstion Distribution As discussed in the previous subsection, a low population zone with a distance to its outer boundary from the TMI Nuclear Station has been specified to be 2 miles. The nearest population center is Harrisburg, Pennsylvania (1970 population of 68,000) which is loc ted approximately 12 miles northwest of TMI. This distance satisfies the require-ments of 10 CHL 100 with respect to population, center distance. The present and projected population distribution as a function of distance and direction from the TMI Nuclaar Station based on 1970 cencus is shown on Figure 5. The counties and relatively large population centers are further v detailed on Figure 6. The population of surrounding residen-

. tial areas, the enrollment in the various schools, and the number of patients in the hospitals in the area around the Dil Nuclear Station site are tabulated in Tables 1, 2, and 3 respectively.

There are no schools and only one recreational area (Falmouth

_ _ . . . Fish.. Commission) presently within the 2 mile low population zone. There is some seasonal shif t in population within a 5 mile radius of Three Mile island since there are over 100 summer cabins on the islands within the area. Additional i transients participate in boating activities in the vicinity l of the TMI site.

1 4.2.1 4 Nearbv Industrial, Transportation, and Militarv Facilities

1. The Three Mile Island site is currently surrounded by farm lands within a 10 mile radius. Lands are used for dairy cattle, tobacco, poultry, vegetables, fruit, corn, wheat, and other products. A summary of land use for Dauphin County, in which the TMI site is located, and for the two other nearest councies (York and Lancaster) is provided on Table 4. The Susquehanna River is used for sport fishing and boating and is not used for commercial fishing.

Revision 2 4.2-3 June 1980 Amendment 19 l

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2. Manufacturing industries in the region produce clothing, wood products, shoes, electrical wiring devices, steel products, packad meat and other food. These activities, within a 10-m11e radius of the site, are confined chiefly to the cities of Harrisburg, New Cumberland, Stealton, and Middletown. A listing of typical industries within 10 miles of the TMI site and eneir respective employment is summarized in Table 5. Located within a 5 mile radius of the site are approximately 23 industrial firms that employ about 2,400 persons. There are gas and oil transmission lines located at a ministan distance of approximately 2 miles face TMI.

The only power station in the immediate upstream vicinity

'of TMI is the Crawford Station (retired) parts of which are owned by Metropolitan Edison Company. Crawford Station is located about 2.5 miles upstream from the site on the east bank of the Susquehanna River. T==adi-ately downstream from *.he site is the York Haven hydro-electric project, cor_sisting of the main dam which averages approximately 10 feet in height and extends about 4,970 feet across the main river channel to Three

, Mile island; a secondary dam which is about 8 feet high and extends 950 feet across the east channel of the river; a pool extending approximately 3 5 miles upstream from the dam and contains about 10,000 acre-f eet of volume; and a head race wall that is about 20 f est in height extending from the west end of the main das approximately 3000 feet to the plant. The York Haven Station is operated on a "run-of-the-river" basis, and its power output is dependent primarily upon the water available. However, the reservoir is used for peaking op2 ration during periods of low river flow. Brunner Island Station, a large steam-electric generating plant owned by the Pennsylvania Po ser & Light Company is located on the- Susquehanna River approximately one mile downstream from the York Haven project. This station uses water from the river on a "run-through" basis for cooling water. Three other hydroelectric generating stations are also located downstream from TMI, with each project having a dam and reservoir on the Susque-hanna River. The three stations are Safe Harbor, Holtvood, and Conewingo Hydroelectric projects, located approximately 25, 31, and 47 miles south of Three Mile Island, respectively. There is also a coal fired, stesselectric plant at Boltwood, and the Muddy Run Pumped Storage Project is associated with Conewingo station. The Peach Bottom Nuclear Generating Station is located along the west bank of the Susquehanna River, about 41 miles downstream of Three Mile Island, just north of the Maryland-Pennysivania border and is the only nuclear plant within s 50-m11e radius Revision 2 4.2-4 June 1980 Amendment 19

of Three Mile Island.

- 3. There are two airports within 10 miles of the TMI site.

Harrisburg International Airport (formerly Olmsted Air Force Base) is located on the north bank of the Susque-hanna River approximately 2.5 miles northwest of the site. The Capital City Airport is located approzinately 8 miles vest-northwest of the TMI site. The vital areas of the TMI Nuclear Station are designed to withstand a hypothetical aircraf t accident.

Conrail lines are located on both sides of the Susque-hanna River, the closest being the east bank, approzi-mat.ely 2,000 f eet from the Three Mile Island Unit 2 Reactor Building. Routine traffic in liquified petroleum gas was identified on the railroad line which passes along the east shore of the river. Analyses indicate that any missiles generated by this traffic would be less damaging than the postulated aircraf t strike against which the plant is protected and that flammable gases would dissipate before reaching the TMI Nuclear Station.

4. The closest military installation to the site is the Air N ;1onal Guard f acility at Harrisburg International Airport. There are no military firing ranges or missile facilities within a 10 mile radius of TMI.

Other military facilities, however, are Army and Navy depots located respectively at New Cumberland and

+ Mechanicsburg, Pennsylvania.

A map showing the major industrir.1 and =111tary facilities within a 5 mile radius of TMI has been included as Figure 7.

4.2.1.5 Emerzenev Planning Zone

. -- GPU Nuclear. Corporation has, in defining the Emergency l Planning Zones (EPZ) for Three Mile Island Nuclear Station, j taken into consideration the information and data presented above, guidance provided by the Pennsylvania Emergency Manage-( ment Agency, and other important factors such as organiza-i tional capabilites, availability of emergency f acilities and l equipment, and the methods for implementing the TMI Emergency Plan. h such, an EPZ having a minimum taiial distance of 10 miles 'r a the TMI site has been defined. A map of the area around T'.I that shows the boundary of the 10 mile EPZ is provided as Figure 8. An EPZ having a minimum radial distance of 50 miles from the TMI site has been defined. A map of the area around TMI that shows the boundary of the 50 mile EPZ is provided in Figure 1.

4.2.2 Scope of the Emerzenev Plan 1 1

Total emergency prepared;.as requires plans for the emergency response i

Retison 2 4.2-5 June 1980 l A=endment 19 l

of both systems and people. The engineering design of the TMI Nuclear Station ensures that the consequences of major malfunctions will be mitigated by the engineered safety systems. The purpose of the TMI Emergency Plan is to provide the basis for human emergency response in the way that design does for system response.

To further ensure that the response to emergencies is initiated in a timely manner and effectively controlled, the Emergency Plan is coor-dinated with other plans, programs, and procedures, as discussed below.

Emernency Plan Isolementina Document l 4.2.2.1 The TMI Emergency Plan has a separate Implementing Document which is distributed to those individuals, agencies, organiza-tions, and f acilities where M=adiate availability of such information would be required in an emergency. The Imple-menting Document table of contents is attached as Appendix A to allow for review of its organization and the list of Emergency Plan Implementing Procedures. As can be seen by reviewing Appendix A, the Implementing Document is organized to provide:

1. An abstract of the TMI Emergency Plan which will include such specific items as definitions, discussions of emergency organizations and responsibilities, a description of emergency planning related systems and facilities, lists of emergency ' equipment, and other information such as important charts and maps.

2. Detailed Emergency Plan Implementing Procedures will,

~

- as necessary and appropriate, be used to assess condi-tions, classify the emergency, provide directions for making required notifications and for requesting assistance, and provide the step-by-step instructions for initiating protective and corrective actions.

.. . The. Emergency . Plan Implementing Procedures have a direct relationship to the TMI Emergency Plan and are coordinated with several other TMI Nuclear Station plans, programs, and procedures including those discussed in subsection 4.2.2.2 below.

4.2.2.2 Related TMI Plens. Programs, and Procedures

1. The TMI Security Plan and procedures and the TMI Baergency Plan and its Implementing Procedures have been coordinated to ensure that appropriate emergency actions can be taken. For example, the Security Plan and procedures will have provisions for emergency response personnel and vehicle access when required by the Emergency Plan Implementing Procedures.

2. The TMI Radiation Protection Plan defines admini-strative controls and procedures such as radiological control limits and precautions, and personnel Revision 2 4.2-6 June 1980 Amendment 19

I decontamination. In addition, Radiological Controls Procedures provide instructions on performing surveys, w enalyzing samples, and operating health physics / radiation l protection equipment. The pertinent information and l details provided in these doctments either have been incorporated into the TMI Emergency Plan and/or Imple-menting Procedures or have been appropriately referenced.

3. A comprehensive set of Emergency Procedures that are used to control plant operations during abnormal and accident conditions have been prepared. Since there is a direct relationship between emergency operations and emergency planning, the Emergency Prm,ltres and Emergency Plan Implementing Procedures are coort*.nated and compli-mentary. As a result, specific Emerget.cy Procedures will, when appropriate, direct the on-shif t operations personnel to the applicable Emergency Plan Implementing Procedure (s). Conversely, Emergency Plan Implementing Procedures will ensure that applicable Emergency Pro-cedures are utilized when appropriate.

4. GPU Nuclear Corporation has developed an Emergency Public Information Plan for the TMI Nuclear Station. The purpose of this plan is to describe the methods by which GPU-Nuclear will disseminate information to the media and the public in addition to the internal dissemination of information in the event of emergencies at TMI. This Emergency Public Information Plan has been included in

+

the development of the TMI Emergergy Plan and is attached

- as Appendix B.

4.2.2 3 Related County sud State Plans The development of the State plans and the TMI Emergency Plan were closely coordinated. In addition, specific State l . . _.. .-. requirements for reporting of emergencies, providing informa-tion and data, and recommending protective actions, have F been integrated directly into the Emergency Plan Implementing Proc edures. In considering the 10 mile EPZ, there are five county plans (i.e. , Dauphin, York, Lancaster, Cumberland, and Lebanon) that have been factored into the development of the TMI Emergency Plan. Not only is the TMI Emergency Plan

[ coordinated with the State and County plans, but also the l State and County plans are coordinated. The details of the State and County plans are provided in section 4.5 3 Revision 2 4.2-7 June 1980 Amendment 19

i 4.3.0

SUMMARY

OF TMI EMERGENCY PLANNING PROGRAM The TMI Emergency Planning Program, as defined by the GPU Nuclear i Corporation, consists of two separate but totally coordinated I documents. The first document, this Emergency Plan, provides the means for performing advance planning and for defining specific requirements and commitments that will be implemented by other '

documents and procedures (e.g., Administrative Procedures, Surveillance Procedures, and Emergency Plan Implementing Procedures). The seepad document, the Emergency Plan luplementing Document, provides the detailed information and procedures that will be required to implement the M Emergency Plan in the event of an emergency at the M Nuclear Station. These two documents are briefly described below.

431 The Emeraency Plan The TMI %ergency Plan assures that all emergency situations, including those which involve radiation or radioactive material are handled logically and efficiently. It covers the entire spectrum of emergen-cies from minor, localized emergencia; to major emergencias involving action by of f site emergency response ajencies and organiza;1ons. The TMI Emergency Plan includes a scheme for classifying emergencies that

• meets the current guidance (reference 4.10.20) provided by the Nuclear Regulatory Commission (NRC). This classification system is described in detail in Section 4.4.0 below. A summary of each classification, its description, purpose and a list of the actions to be taken by the Licensee and of fsite Authorities is included in Tables 14, 15, 16 and

17. Furthermore, this Plan incorporates specific response criteria (emergency action levels) which will be used in the assessment of emergency situation . Thus, the TMI Emergency Plan provides the overall advance planning required for the development of methods of implementation which will be included in the Implementing Document.

4.3.1.1 In summary, the M Emergency Plan provides: ,

t

. ...l.. A means for. classifying emergency conditions.

2. A means of reclassifying such emergency conditions should the severity increase or decrease.

3. Details of normal and emergency operating organizations.

4. General guidelines as well as specific datails as to which State, county, and federal authorities and agencias and other outside organizations are available for assistance.

5. Information pertaining to the emergency facilities and equipment available both onsite and offsite.

6. Guidance for the preparation of detailed Emergency Plan Implementing Procedures.

I l

Revision 2 4.3-1 June 1980 Anendment 19

7. Requirements, such as train *ng, drills, reviews, and audits, which will result in a high degree of energency preparedness and operational readiness.

8. Y'gures and tables *ich dispisy detailed information and data such as organization charts, ma- and popu-lation distributions.

9. An appendiz detailing specific plans and agreeme. ,s perta*ning to participating offsite organizations and agencies.

10. Appendiz 3 - Imergency Public Information Plan.

4.3.2 3e Isolementinz Document he purpose of the Emergency Plan !aplementing Doctament, a description of which is attached as Appendix A, is to provide a " single source" of pertinent and significan: information and data and the procedures that would be required by or useful to various emergency response agencies and organizations in the event of an emergency at OfI Nuclear S:stion. na Implementing Doctment, therefore, consolidates and integratas specific material detailed in such documents as the O!! Imergency Plan, the State Plans, and the various County Plans.

4.3.2.1 3 e Implementing Document is organized to provide:

- 1. An abstract of the O!! Emergency Plan, including specific items such as definitions, energency organizations, responsibilities, f acilities, equipment, a.wi means of classifying anergencies.

2. Emergency Plan Implementing Procedures that define

, specific emergency action levels which require implemen-

.. :stion of the procedure (s) and the detailed emergency actions (i.e. , step-by-step instructions) to be taken by appropriate plan personnel.

Revision 2 4.3-2 ?me 1980 Anend=en: 19

4.4.0 EMERGENCY CONDITIONS 4.4.1 Licensee Classification Svsten 4

This Emergency Plan characterizes four classes of emergency situations which consist of autually exclusive groupings covering the entire spectrup of possible emergency situations. Each class is associated with a particular set of immediate actions to be taken to perform:

(1) accident classification, (2) notification of off site agencies and support groups, and (3) sobilization of the applicable portion of the '

amargency organizations to cope with the situation and continue accident assessment functions. These actions are described in detail in Section 4.6.0 of this Plan. The various classes of accidents repre-sent a hierarchy of accidents based on potential or actual hasards presented to the general public. Accidents may be classified in a lower category at first and then escalate to another, higher class if the situation deteriorates.

Each of the four emergency classes are characterized by emergency action levels. These levels consist of specific sets of plant para-meters (i.e., instrument indications, system status, etc.) that will be used to initiate (1) emergency class designation, (2) noti-fication, and (3) emergency organization mobilization. These emergency action levels are used specifically to obtain early readiness status on the part of emergency response persons and organizations. These levels have not been selected so as to infer any immediate need to implenect protective actions but rather to insure a reasonable amount of time is available to confirm in-plant readinge by implementing assessment asasures onsite and of fsite. Once declaration of an emergency class i . requiring possible protective action occurs, dose assesmaents will be j ande by either measurement or projection methods. The dose assessment j values, along with other plant status assessments will be reported to l offsite agency of ficials as inputs for their decision on whether or not i protective actions for the public are to be implemented. The relation-ship of these dose assessment values to the Environmental Protection Agency (EPA) Protective. Action Guides (PAGs) and the possibility of approaching or exceeding the PAGs will specifically be reported.

A specific methodology was used in relating the whole body and thyroid exposure action levels of the Alert, Site and General Emergency classes to the EPA PAGs. The Emergency Action levels were chosen such that exposure to that whole body dose rate or iodine concentration for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> would result in accumulating the following fraction of the lower PAGs (i.e. , 1 Ram whole body or 5 Rea child thyroid):

Praction of PAG Alert .01 Site Emergency .05 General Emergency .1 The philosophy taken for cicssification will always be to promptly Revision 2 4.4-1 June 1980 Amendment 19

declare the highest class for which an emergency action level has been exceeded. For example, a Site Emergency would be declared directly if a Site Emergency action level is exceeded, without having previously been in the lower Alert class. The classification system is designed to permit rapid evaluation of plant conditions against saargency action levels so as to promptly recognize and declare emergencie.s (within 10 minutes of event).

A listing of the Emergency Plan Implementing Procedures normally expected to be c.111:ed for each emergency classification is included as Table 19 Each of the four emergency classes, and the related emergency action levels requiring declaration of each class, are described in the following subsections.

4.4.1.1 Unusual Event The least severe of the four emergency classes defined by this Plan is called an Unusual Event. For the purposes of this Plan, an Unusual Event shall be defined as the occurrence of an event or events that indicate or allow recognition of a potential degradation of the level of saf ety of the plant. For coavenience, this class shall also include contaminated injuries of plant personnel which require offsite emergency treatment. The incident shall be classified as an Unusual Event only if the event is a minor one and no releases of radioactive material requiring offsite response or monitoring are expect ed . Events in this class are selected based upon a potential to legenerate to a more severe situation rather

. than an actua public hazard.

t l' The emergency acrion levels that shall require an Unusual Event declaration include (but are not necessarily limited to) the following:

. ..L. . .A reactor . trip coincident witn either: .

a. Total Loss of Forced Reactor Coolant Flow

b. Total Loss of main and emergency feedwater

2. Any reactor trip followed by an unplanned automatic I ECCS actuation.

3 Reactor Building pressure 12.0 peig.

4. Reactor coolant total activity 150 uCi/ml. '

5. Any unidantified Reactor Coolant System leakage 11 gym or total Reactor Coolant System leakage 110 gym that results in a Technical Specification required shutdown.

6. Sustained loss of all of fsite power which results in a reactor trip.

7. Both Diesel Generators inoperable resulting in a Technical Specification required shutdown.

l Revision 2 4.4-2 June 1080 f

Amendment 19

l

8. Projected river stage > 302 f t. at the River Water Intake Structure. <

9. Any earthquake of a magnitude > .Olg as indicated by the I

" Threshold Seismic Condition" annunciator.

10. Transportation of a contaminated, injured individual from onsite to an offsite hospital.

11. Actual or projected hurricane force winds (175 mph sue-tained).

12. Onsite aircraf t crash outside the protected area fence and not impacting on plant structures.

13. Any near or onsite toxic or flammable gas or lignid release which affects the habitability required for normal plant operations.

14. Valid unanticipated alert alarm on an af fluent radiation monitor gas channel (Monitors RM-A8, RM-A9 and RM-A5).

15 . Any fire in a permanent plant structure which cannot be controlled by the Fire Brigade within 10 minutes of discovery or any fire outside plant stucturcs requiring offsite firefighting assistance.

16. Any valid Reactor Building evacuation alarm.

v The intent of the values noted above is to provide absolute values which, if exceeded, will initiate the Unusual Event emergency class.

In addition to the requirements for declaration of this emergency class that are imposed by the emergency action levels desertbed above, the Unusual Event class can be declared by an action statement in a specific Emergency

. Procedure.or Alarm Response Procedure. Steps in these l procedures state that an Unusual Event has occurred or is l occurring and require that an Unusual Event class of emer-gency be declared. All Emergency Plan related actions (notification, etc.) will be carried out in parallel with the remainder of the Emergency Procedure.

Lastly, the Emergency Director shall declare an Unusual Event any time that, in his judgement, the plant status warrants such a declaration; Training shall stress the need:

(a) to analyze all minor events in light of their potential for further degradation of the -level of safety of the plant and (b) not to hesitate to declare this particular emergency i

class.

4.4.1.2 Alert The next level of emergency class designated in this Plan is Revision 2 4.4-3 June 1980 Amendment 19

called an Alert. An Alert is the occurrence of an event or l series of events that indicate and allow recognition of an )

actual or potential substantial degradation of the level of safety of the plant. As in the case of an Unusual Event, j

- the Alert class includes emergency situations that are  ;

expected to be minor in nature but where it has been deemed  ;

prudent to notify more of the offsite amargency participants and mobilize a larger portion of the emergency organization.

In addition, because of the nature of the Alert class (re-leases of radioactive material possible), broader assessment actions will be started. All of the actions to be taken for each emergency class are described in detail in Section 4.6.0 of this Plan. . Events that will initiate an Alert shall be those with the potential of limited releases of radioactive material to the environment. As before, a situation will only be classified at the Alert level if none of the emergency action levels for a higher class have been exceeded or are expected to be exceeded in the near term.

The emergency action levels that shall require an Alert to

be declared include (but are not necessarily limited to) the following

l

1. Reactor Coolant. System pressure and temperature reach saturation conditions.

2. Reactor Coolant System hot leg temperature 1 6200F-3 Reactor thermal power and reactor power imbalance in excess of the safety limits defined by Figure 2.1-2, " Core v Protection Safety Limits", in reference 4.10 13 1.

4. A measured Reactor Coolant Systss: pressure in excess of 2500 psig.

S., Failure of the Reactor Coolant System power operated relief valve to shut (af ter lif ting to relieve pressure) .

j 6. Reactor Building pressure >_ 4.0 psig .

I

7. Reactor coolant total activity 1130 uC1/ml.

8. Primary to secondary system leakage in excess of 1 gym.

9. More than one control rod known to be untrippable.

10. Loss of all offsite power coincident with the fatiure of both Diesel Generators to start for less than 15 minutes.

11. Loss of all onsite DC power for less than 15 minutes.

12. Secondary system activity (I-131 equivalent) > 1.0 uC1/ml.

I 13 Actual river stage >_ 302 f t. at the River Water Intake Structure.

Revision 2 4.4-4 June 1980 Amendment 19

s

14. Any earthquake of a magnitude _> OBE levels as indicated by an alan:n on the " Operating Basis Earthquaka" annun-ciator.

. 15. Any tornado striking the facility.

16. An streraf t crash within the protected area or onto any per.aanent plant structure. '

17. A fire in any permanent plant structure which requires of fsite firefighting capability.

18. A valid count rate on any gaseous plant affluent

' monitor that would result in a projected dose rate at the exclusion area boundary of > 10 mR/hr (gsama) using adverse meteorolen.

a. EMA-8 2.0 x 104 cym.

b. .RMA-9 4 5 x 104 epa.

c. RMA-5 1.0 x 106 cpm.

19. A valid count rate increase on any plant iodine affluent

- monitor that would result in a projected child thyroid dose at the exclusion area boundary of > 50 mR in one hour using adverse meteorolorv.

a. RMA-8 8.5 x 102 cps / min.

~ b. RMA-9 2.5 x 103 cpm / min.

20. A valid dose rate of 6.0 R/hr on the Reactor Building high range monitor that would result in a projected child thyroid dose at the exclusion area boundary of > 50 mR in one hour or a whole body dose rate > 10 mR/hr (gamma) using adverse meteorolorv and building deeign leakrate.

21. Unanticipated high alarm on any two area and/or process i radiation monitors at the same time.

22. A valid high alarm on the station liquid affluent monitor (RM-L7).

23. Offsite radiological monitoring reports of > 10 mR/hr (gamma) at any location.

Again, the values specified are absolute action levels requiring declarction of the Alert level.

i i l This class of emergency can also be declared by arrival at I an action statement in a specific Emergency Procedure.

Steps in these procedures state that an Alert has occurred or is occurring and require that an Alert class of emergency be declared.

- All Emergency Plan related actions (notification, etc.) will be carried out in parallel with the remainder of the Emergency Procedur e.

Revision 2 4.4-5 June 1980 Amendment 19

As in all cases Emergency Directur shall declare an Alert any time ..a judges the status of the plant to warrant it. He shall specifically consider escalation from the Unusual Event to the Alert class if, in his judgement, the

- situation is not likely to deteriorate.

4.4 1 3 _ Site Emergency The next level of emergency class designated is the Site Emergency. The Site Emergency class includes accidents in which actual or likely major f ailures of plant functions ,

needed for protection of the public have occurred. Although immediate protective actions are not automatically required, i declaration of a Site Emergency will set into motion all personnel onsite and of fsite that would be required to perform actions up to and including the evacuation of near-site areas. All monitoring teams required to make continuing assessments for providing officials with information to decide on protective actions will be dispatched. The Site Emergency class includes accidents which have a signifi-cant radiation release poteacial. Details of all of the emergency measures that will be taken upon declaration of a Site Emergency are cresented in Section 4.6.0 of this Plan.

The emergency action levels that shall require a Site Emergency to be declared sha)1 include (but are not necessarily limited to) the following:

1. Reactor Building pressure 130 psig.

2. Reactor coolant activity 1300 uCi/ml.

,. 3. Primary to secondary leakage 1 50 gym.

4. Loss of all offsite power and loss of both Diesel Gener-acora for amore than 15 minutes.

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

6. River stage 1307 f t. at the River Water Intake Structure.

7. Any earthquake of magnitude 1 SSE levels.

8. Failure of actuated Emergency Core Cooling System components to start and run following an automatic system initiation such that the number of components available is below the minimum assumed for accident analysis.

9. A valid count rate on any gaseous plant ef fluent monitor 1

that would result in projected dose rate at the exclusion area boundary of > 50 mR/hr (gamma) using adverse meteorology.

a. RMA-8 1.0 x 105 ep ,

b. RMA-9 3.0 x 105

10. A valid count rate on any plant iodine effluent monitor

- that would result in a projected child thyroid dose at Revision 2 4.4-6 Jnna 1980 Amendment 19

the exclusion area boundary of > 250 mR in one hour using adverse meteorolomv.

a. EMA-t 4.5 x 103 cpmesin.

b. RNA-9 1.2 x 104 epa / min.

11. A valid dose rate of 28.0 R/hr on the Reactor Building f

high range monitor that would result in a projected child thyroid dose at the exclusion area boundary of > 250 mR _ )

in one hour or a dose rate > 50 mR/hr (gamma) using 1

- adverse meteorolony and building design leakrate. l

12. Incore temperature > 7000F as measured by any two incore thermocouple readings following a reactor trip.

13 Offsite radiological monitoring reports of > 50 mR/hr (gamma) at any location.

This emergency class, as is the case with all classes in this Plan, can also arise from an action statement in a specific Emergency Procedure. As an example, one of the steps in the " Loss of Reactor Coolant / Reactor Coolant 4 Pressure" Bnergency Procedure will trigger declaration of a i

Site Emergency.

In addition, the Emergency Director shall declare a Site Emergency any time that in his judgement plant conditions exist that warrant the activation of emergency centers and precautionary public notification.

It should be noted that, unlike the two previcualy described i classes of emergency, the Site Emergency class is very likely to involve some radiation exposure to the near-site public . Also, many of the accidents included in the class have the potential for degradation to the General Emet;ency class. Although the amargency act:Lon levels for this class e have been selected at values which would result in offsite exposures well below the protective action guides, offsite monitoring team reports and continuing assessment will lead to any final decision on protective actions to be taken. A detailed discussion of the implementation of as.essment

, actions and possible protective actions for the Site Emergency ,

class are provided in Section 4.6.0.

4.4.1.4 General Emeraency The highest, most severe class of emergency defined by this Emergency Plan is called General Emergency. The General Emergency class will contain accidents which involve actual or imminent substantial core degradation or melting with potential for large releases of radioactive material and/or loss of Reactor Building (containment) integrity, and other accidents d

that have large radioactive release potential such as fuel handling and waste gas system accidents.

Revision 2 4.4-7 June 1980 Amendment 19

.-m-e~-, . - .--...--,re ,w--,

o -

t

\

. \

\

in keeping with the philosophy adopted throughout this Plan, the emergency action levels are set at values below the EPA protective action guides so that they may be used to (1) declare the emergency. (2) notif y the appropriate authorities and support groups, and (3) mobilize the applicable portions of the emergency organizations. However, this class of emergency is somewhat different in that some protective actions may be recommended upon declaration of the General Emergency, since, f or this emergency class, the lower limits of the protective action guides are likely to be exceeded.

The emergency action levels have been selected so that time should be available to make some confirmatory measurements in the field prior to implementation of any of the more extensive (i.e. , evacuation) protective actions.

Some of the General Emergency action levels require a dose projection calculation using actual meteorolorv. This differs from the adverse meteorology assumpthos used in the Site Emergency action levels in order to remove this built-in conservatism and to preclude declaring a General Emergency when actual conditions do not warrant that high of an emergency classification. In those cases where radiation nonitors are off scale, the calculations will use contingency dose release factors. A detailed description of the protective actions to be taken for each class of emergency will be presented in Section 4.6.0.

The emergency action levels that shall require declaration of a General Emergency include (but are not necessarily limited to) the following:

1. A projected dose rate at the exclusion area boundary from all sources of 1100 mR/hr (gamma) using actual meteorolorv and Reactor Building design leakrate.

2. A projected child thyroid dose from all sources at the

- exclusion. area boundary of 1500 mR in one hour using actual meteorolorv and Reactor Building design leakrate.

3. Of f site monitoring reports of 1100 mR/hr (gamma) at any location.

4. Reactor Building high range monitor exceeds the level for a Site Emerggey with either (1) a measured Reactor Building pressure 155 psig or (2) a measured hydrogen concentration in the Reactor Building 13% by volume.

Also, the Emergency Director shall declare a General Emergency at any time that in his judgement plant conditions exist that already, or in the near term, warrant the taking of some protective actions for the population-at-risk. Although the emergency action levels are set below values related to the EPA protective action guides to allow time for further assess-ment, it is possible that some protective actions will be required upon declaration. For a complete discussion of these actions ref er to Section 4.6.0.

Revision 2 4.4-8 June 1980 Amendment 19

B 4.4.2 State and County classification Svstem

!be Pennsylvania Emergency Management Agency's Disaster Operations Plan Annex E " Emergency Nuclear Incidents (Fixed Nuclear Facility)", the  !

Department of Environmental Resources, Bureau of Radiation Protection l Plan for Nuclear Power Generating Station Emergencies, and all five '

County plans contain the same emergency classifications as those utilized in this Plan.  !

Since both the State's and GPU-Nuclear's classifications include events which have significant potential for radioactive releases, it is imperative that specific guidance for initiating protective actions be available to the " decision-making" persotmel in emergency response organizations and agencies. The State has, for plann*ng purposes, adopted the Environmental Protection Agency's (EPA) protective action guides (PAG's) that are specified in ref erence 4.10.8. The projected values for dose and dose commitment given as emergency action levels for even then highest class of emergency (i.e. General Emergency) are considerably lower than the EPA PAG's discussed above. Therefore, the declaration of a General Emergency, although an extremely significant event in its own right, should not be construed to mean that the EPA PAG's have been, or even vill, be exceeded.

4.4.3 Spectrum of Postulated Accidents This section of the !MI Emergency Plan shows that each of the discrete accidents that have been hypothesized for the plant is encompassed

_ vithin the preceding emergency characterization classes and provides a summary analysis of their implications for emergency planning.

4.4 3 1 Classification of Evpothetical Accidents All of the events hypothesized in Chapter 14 of the TMI Nucla.ar Station Final Saf ety Analysis Report (75AR) fall into one of the four emergency classes outlined above, with approxima,ely half f alling into the Alert, Site, and General Emergency categories. Table 6 lists each of these events and the emergency class that each would be likely to f all into. A complete discussion of any of these hypothetical events may be found in Chapter 14 of the 75AR. In completing this table, conservative asstseptions with respect to the accidents described in Chapter 14 have been made. Therefore, occurrence of some of these accidents (for example, with no f ailed fuel) may not result in as high a class as noted in Table 6. Also, equipment asstuned to work in the Chapter 14 analysis was assumed to successfully operate for the evalu-ation. Failures of required equipment in any of the accident scenarios nay result in higher classes of eaergencies.

4.4.3 2 Instrumentation Capabilitv for Detection The plant instrunentation that vill be used to promptly Revision 2 4.4-9 June 1980 A=end=ent 19

_ ~

detect accidents at the plant is discussed in detail in the TMI Nuclear Station FSAR. Table 7 lists each hypothe-tical accident, and the important instrumentation that would be expected to detect each of these accidents. Only major, installed equipment is listed.

4.4 3 3 _Mrapower and Timinst Considerations The manpower and timing response during an emergency is depicted in Table 8. This table includes (1) the number of personnel onsite continuously, (2) the number of personnel to be called to report oncite, and ,(3) those that are to be called to report to the Near-site Daergency Operations Facility. Included in Table 8, along with the above infor-nation, is the estimated maximism time for the identified personnel to report to their assigned locatie is.

Revision 2 4.4-10 June 1980 Amendment 19

i 4.5.0 1 ORGANIZATIONAL CONTROL OF EMERGENCIES The planning for and response to a radiological emergency at the TMI Nuclear Station is the joint responsibility of CPU-Nuclur and the state / county / local governmental agencies. GPU-Nuclear is responsible for on-site emergency response. In order to fulfill this responsi-bility, GPU-Nuclear relies on various off-site agencies, both govern-mental and private, to provide assistance beyond that available on-site. The Commonwealth of Pennsylvania, through its vetious state, county and local agencies, is responsible for offsite emergency response. In order to fulfill this responsibility, the Commonwealth of Pennsylvania relies on GPU-Nuclear to provide necessary information l on plant status and radiation releases. Recognizing the joint nature l of their responsiblities, GPU-Nuclear and the relevant governmental l agencies have coordinated their emergency planning and have provided l for adequate and redundant communication systems so as to coordinate their response during an smargency event.

l The TMI Unit 1 Emergency Plan describes the methods and procedures to be used by GPU-Nuclear in satisf ying its on-site responsibilities.

The Emergency Plan describes: (a) the organizations and f acilities to be relied upon in responding to emergencies, (b) the means to be used for initial accident assessment and notification, (c) the resources available for continued monitoring, assesanent and dissemination of information about the emergency, (d) the emergency measures to be l takan, including on-site protective and corrective actions, and (e)

! the procedures to be followed for maintaining anergency preparedness.

Similar offsite responsibilities are describ*1 in Annex E-Fixed Nuclear Facility Incidants to the Commonwealth of Pennsylvania Disaster Operations Plan (State Plan) and in the emergency response plans for the five counties of Dauphin, York, Lancaster, Lebanon and Cumberland (County Plans) . The State Plan designates tne Pennsylvania Emergency Management Agency (PEMA) as the lead state agency for radiological energency response planning and the state agency through which the Governor will exercise coordin tion and control during an emergency. The State Plan is an integrated document setting forth the resources and responsibilities of all relevant state agencies.

Significant plans from the Stats Departments of Agriculture (Appendix l 7), Environmental Resources, Bureau of Radiation Protection (Appendix 8), and Health (Appendix 9) are included in the State Plan.

4.5.1 Licensee organizations GPU-Nuclear is the organization which operates and providen technical support for the TMI Nuclear Station. This organization is staffed by GPU-Nuclear personnel. The following five subsections provide a detailed description of the TMI Station and Station Support Organi-i zations during normal operations and, in addition, a detailed descrip-l tion of the onsite and of f site emergency organizations that can be activated from the normal organizational arrangements. A description l ef a basic organization for long-term recovery operations is also p ovided.

l Revision 2 4.5-1 June 1980 Amendment 19

m .

e I

t. 5 1 1 Normal station organization

1. A block diagram of the M Nuclear Station Organization is provided as Pigure 9 The diagram illustrates the levels of responsibility within the station organ-ization. The personnel staffing the normal station organization are usually onsite from about 8 AM to

. . 5 PM during the normal work week (i.e., weekends and holidays excluded) .

. a. The Vice President-m I has the overall respon-

!* sibility for the day-to-day operation of Unit 1.

, In carrying out his responsibilities he directs the management staff in the execution of their functional responsibilities.

b. The Manager Unit 1 is responsible for the overall operation and maintenance of the Unit. He reports directly to the Vice President-TMI 1 and is directly responsible for operating the unit in a saf e, reliable and af ficient manner.

, c. *he Manags: Plant Engineering is responsible for the coordination of the technical engineering and chemistry staff. The Manager Plant Engineering also reports to the Vice President-TMI 1.

d. The Manager-Training TMI-1 reports to the vice President-Nuclear Assurance through the Director of Training and Operational Safety Support and is responsible for the conduct of all training functions.

e. The Manager Administration and Services is respon-sible for planning, organizing and directing the day-t wday activities of the Personnel, Eudgets ano

! Reports,Securi4v, Facilities, Document Control.

Office Management and Safety fune:1ons. This position reports to the Vice President-TMI 1.

I

f. The Manager Radiological Controls is responsible for all matters affecting the Radiation Protection and Health Physics aspects directly associated with the operation and maintenance of Unit 1. This l

i position reports to the Vice President-Radiological and Environmental Controls.

g. The Public Af fairs RSpresentative is responsible for the coordination and control of the dissemination of information to the public, state, and f ederal l

civil authorities. This position reports to the Vice President-Comm:nications.

2. The Manager Unit i provides operators onsite en a navision 2 4.5-2 June 1980 Amend =ent 19

rotating shif t basis to ensure the safe and proper operation of the plant 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 days per week. In addition, personnel from other departments within the station organization are also assigned to shifts to provide additional capabilities. Require-ments for minimum shif t crews are specified in Section 6.2 of the Technical Specifications (reference 4.10.13.1).

The typical TMI Unit i shift organization is shown in Figure 10. The shif t organ'ization can be augmented, in the event of an emergency with off-duty personnel within 60 minutes.

a. The Shif t Supervisor, who f s on duty at all times, is the immediate onsite position of authority and responsibility for th.e safe and proper operation of the plant. The Shift Super-visor will be responsible for the initial eval-untion of any abnormal or emergency situation, and for directing the appropriate response. If it is determined that an emergency exists, those responsibilities assigned to the Emergency Director will be assumed by the Shif t Supervisor.

Under such circumstances, the Shif t Supervisor 4

. will initiate appropriate actions, implement

proper procedures, notif y appropriate of f site emergency response organizations and agencies (i.e. Dauphin County PEMA, NRC) and the Duty Section Superintendent, and retain such respon-sibilities until relieved by tha Emergency

~

Director. The Shife Supervisor shall, during normal and emergency operations, maintain control over plant operations as the senior licensed operator unless he is properly relieved by another member of the TMI Nuclear Station staff who holds a valid Senior Operator license.

In addition, the Shif t Supervisor shall maintain control over the conduct of operations and personnel in the Control Room.-

b. The Shif t Foranan functions as an assistant to the Shif t Supervisor. In the temporary absence of the Shif t Supervisor, the Shif t Foreman will assume his responsibilities.

c. The Control Room Operators are responsible for the manipulation of controls as necessary to perform plant operations as directed by the Shif t Foreman or Shif t Supervisor. They are responsible to the Shif t Foreman.

d. The Auxiliary Operators are responsible for performing component and/or system operatioas outside the Control Room. Normally they take direction from the Control Room Operators; however, s

Revision 2 4.5-3 June 1980 Amendment 19 I

t

_._-.-,._m_ . - . _ _ , . _ - - . . . - - - . . - - _ _ _ - . - _ , , . . - - . - - _ , _ - _ - , - ,

l they too are responsible to the Shif t Foreman or Shif t Supervisor.

~

a. In addition to the operations personnel assigned to each shif t, a Shif t Technical Advisor will be I assigned to each shif t. He will be responsible for serving in an advisory capacity on plant safety to the Shif t Supervisor. He shall have no duties or responsibilities for manipulation of controls or for command of operations.

f. To meet the Technical Specification (referenes 4 10.1.3 1) requirement for having at least one member of the operating shif t " qualified to implement radiation protection procedures", at least one, and normally three, Radiation Controls Technicians will be assigned to each shift.

These technicians are qualified to determine dnas received by workers during the performance

' of their duties and will be available during emergencies on a 24-hour per day basis to perform related functions.

g. To provide for round-the-clock maintenance coverage, a maintenance crew is assigned to each shift. This crew typically consists of a Maintenance Foreman and several craft personnel providing capability in the mechanical, electri-cal, and instrumentation and controls disciplines.

~

~

h. The Site Security Force provi.ies, on a round-the-clock basis, security services (e.g., access control, surveillance, response, etc.) in accordance with the Security Plan and procedures.

4 5.1.2 Normal Station Support Organization The CPU-Nuclear Normal Station Support Organization is shown in Figure 11. As can be seen in a review of the organization chart, the normal station support organization provides the capabilities described below:

1. The Vice President-Technical Functions is responsible for providing a centralized technical capability to support generating facilities. This includes general mechanical, civil, electrical and instrumentation engineering and design, along with licensing and environ-mental assessment. This Vice President reports to the Executive Vice President of the GPU Nuclear Corporation.

2. The Vice President-Nuclear Assurance is responsible for nuclear safety assessment, quality assurance, training and the operational safety support functions of the System Laboratory, and Emergency Planning Group. This Vice President reports to the Executive Vice President of the GPU Nuclear Corporation.

Revision 2 4.5-4 June 1980 Amendment 19

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3. The Vice President-TMI 1 has the overall responsibility for the day-to-day operation of Unit 1. In carrying out his responsibilities he directs the management staff in the execution of their functional responsibilities.

This Vice President reports to the Executive Vice President of the GPU Nuclear Corporation.

4. The Vice President Radiological and Environmental Controls is responsible for establishing policy, coordination and review of radiation and environmental controls at the nuclear generating stations. This Vice President reports to the Executive Vice President of the GPU Nuclear Corporation.

4.5 1.3 Onsite Emergency Orasnization The Vice President-TMI 1 vill be responsible for assigning TMI Nuclear Station personnel to positions in the onsite amargency organization which is shown as Pigure 12. This responsibility includes the assignment of key TMI Nuclear Station managsment and supervisory personnel to the Duty Section and to the position of Emergency Director. The Manager Unit 1 and the Emergency Planning Coordinator will assist him in making these assignments. The Duty Section assignments will be made and posted in writing (e.g.

memo, duty roster, procedure, etc.) to ensure that full 24

_ hour per day, 7 day per week coverage is provided. In

, addition, provisions will be made to ensure that alternates to key positions are pre-designated.

Additional information regarding the onsite emergency organization is provided below:

1. Direction and Coordination The Vice President-TMI 1 and Vice President-TMI 2 share overall responsibility for site administration as well as for directing and coordinating the activities at TMI to ensure that it functions in a safe, reliable and efficient manner. One of the Vice Presidents or their designated alternates shall assume the overall site responsibilities in an emergency situation by assuming the position of Emergency Support Director.

The Manager Unit 1 is responsible to the Vice Frasident-TMI 1 for the safe, reliable, and efficient opera-tion of the plant in conformance with the Operating License. He, or his designated alternate, shall maintain these responsibilities in an emergency situation.

As mentioned in subsection 4.5.1.1.2.a above, the Shif t Revision 2 4. 5-5 June 1980 Amendment 19

4 Supervisor will, in the event an emergency exists, assume the responsibilities of the Baergency Director.

Until such time as personnel can be recalled to staff the emergency organization (Figure 12), the Shif t Supervisor will assir,n members of the shif t organization to carry out prioritized actions as described in Section 4.6.2 2 and Table 8. In addition, he will notify the Duty Section Superintendent, who will relieve the Shif t i

Supervisor of Emergency Director responsibilities upon his arrival in the Control Room. In case the Shift Supervisor is unavailable or becomes incapacitated for any reason, the Shif t Foreman has the authority to assume l i

the position of Emergency Director until properly relieved l

by the Duty Section Superintendent.

The Emergency Director has the authority and the respon-sibility to immediately and unilaterally initiate any emergency action, including providing protective action i

recommendations to authorities responsible for imple-menting offsite smergency measures.

The Emergency Director, following notification of an existing or potential energency, will respond to the

• emergency as described in Section 4.6.1 below. The Emergency Director will be responsible for final assess-ments of emergency situations, especially whern the emergency presents a real or potential hazard to offsite persons or property. The Emergency Director will imple-

" ment the TMI Emergency Plan through the use of specific

' Emergency Plan Implementing Procedures, activate necessary and/or required portions of the emergency organization and, as appropriate:

a. Estan11sh methods, including communi;:ations with the onsite Technical Support Center and the Near-site .

Emergency Operations Facility, to ensure that he will be kept informed of the status of the emergency.

! b. Provide direction and support to the Shif t Supervisor.

l

c. Provide liaison and communications with the County, State, and Federal governments, and ensure that notification and reports to these agencies are made in a timely manner.

d. Communicate with the of fsite emergency support organization.

e. Request assistance from onsite and offsite personnel, organizations, and agencies.

f. Organize, direct, and coordinate emergency teams.

g. Interpret radiological data obtained in terms of both real-time measurements and, to the extent possible, projected radiological exposures.

h. Ensure that adequate protective measures are taken l by personnel performing emergency efforts. This includes those individuals assigned to the Emergency Control, Technical Support, and Operations Support Centers.

Revision 2 4. 5-6 June 1980 Amendment 19

. 1

1. Ensure that accurate exposure records are maintained.

j. Review and evaluate updated information and data.

k. Relay significant information and data to onsite and offsite organizations, agencies, and response teams.

1. Determine the necessity for onsite evacuation.

Emergency Director responsibilities that may not be delegated include:

z. Decision to notify offsite emergency management agencies.

b. Making protective action recommendations as necessary to of f-site energency management agencies.

c. Classification of Emergency Event.

d. Determining the necessity for on-site evacuation.

e. Authorization for emergency workers to exceed normal radiation exposure limits.

To ensure that proper offsite authorities are kept fully informed of the emergency status and actions in progress, the Emergency Director will ensure that follow-up messages containing the following information, if it is known and appropriate, are transmitted in a timely manner:

a. location of incident and name and telephone number (or cr===mications channel identifications) of caller ,

b. date/ time of incident

c. class of emergency

d. type of actual or projected release

. e. estimate of quantity of radioactive material released or being released and height of release

f. chemical and physical form of released material, including estimates of the relative quantities and concentration of noble gases, iodines and particulates

g. prevailing weather (vind velocity, direction, temper-ature, atmospheric stability data, form of precipita-tion, if any)

h. actual or projected dose rates and integrated dcse at exclusion area boundary and at about 2 and 10 miles, including sectors affected

1. estimate of any surface radioactive contamination J. emergency response actions undervey

k. recommended emergency actions, including protective measures

1. request for any needed onsite support by of" site organizations

m. prognosis for worsening or termination of event based en plant information

2. Plant Staff Emergenev Assignments

a. Conmunicator The Communicator will report to the Emergency Revision 2 4.5-7 June 1980 Amendment 19

_ v

Director. He will function as liaison between tha Emergency Director, of fsite organizations and

- agencies, and onsite organizations and agencies, and the onsite emergency organization (i.e., Technical Support Center Coordinator, Group Leader - Technical Support, NRC-Bethesda, and the Babcock and Wilcox Company). As required, the Communicator will 1 provide, using available e'quipment, reliable and '

- accurate communications iniaccordance with the appropriate Emergency Plan [ Implementing Procedures.

In addition, he is responsible for maintaining records of outgoing and incoming communications.

He will have designated assi.stants that will be utilized in an emergency as!necessary.

b. Technical Sucoort The Technical Support Centej Coordinator and his staf f of engineers will repgrt to the Emergency Director. The technical su;nort personnel will analyze current and projecttfl plant status and, through close communications (via the Communicator) with the Emergency Director, provide technical support and recommendations egarding emergency

• actions. In addition, the T chnical Support Center Coordinator v411, as necessa y, provide a direct interf ace with the Group Les r - Technical Support.

More specifically, the Techn al Support Center Coordinator and his staff wil<:

~ i (1) Analyze mechanical, ele {trical, and instru-ment and control problery; determine alter-nate solutions, design atd coordinate the installation of short-ce y modifications.

(2) Analyze thermohydraulic 4 pd thermodynamic problems and develop prol les resolutions.

(3) Assist in the developmen: of Emargency Procedures, Operating Pro edures, etc. as necessary for conducting < sergency operations.

(4) Analyze conditions and defalop guidance for the Emergency Director ar operations personnel.

(5) Resolve questions concern.ng;0perating License requirements with NRC re resentatives.

\

, c. Plant Operations (1) The Operations Coordincar is responsible for coordinating operations and pintenance activities through the(Shif t Supervisor and the Emergency Maintenacce Coordinagor. The Operations Coordinator ma, not relitve the Shif t Supervisor or speci. '.cally direct plant operations unless he is a lice'used Senior Reactor Operator. ' he Operations Coordinator will report tejtheEmergency Director.

Revision 2 4.5-8 '

June 1980 Amendment 19

' - - - - - - ~ - - -

l (2) The TMI U .it 1 Operations Shif t, under the direction of the Shif t Supervisor, is respon-sible for the safe and proper operation of the plant at all times. Therefore, the operations shif t will respond to all abnormal and emergency situations and take action as necessary to improve and/or terminate any accident.

Ihe shif t organization will be self-reliant for a sufficient period of time to allow for the notification of required personnel and the assembly and integregation of those person-nel into the emergency organization. To ensure the shif t can respond and function in an emergency, the Shif t Supervisor is responsible for the initial assessment and evaluation of the situation and will initiate the necessary immediate actions to limit the consequences of the accident and bring it under control.

In addition, he will assume and carry out the responsibilities of the Emergency Director until relieved by the member of the TMI Staff assigned this duty.

The Shif t Technical Advisor, as discussed in subsection 4.5.1.1 2.e. above, will advise the Shift Supervi sor on activities that impact the safe C proper operation of the plant.

The shif t organization personnel are familiar with the operation of plant systems and the location and use of emergency equipment.

Some members of each shif t are trained in fire fighting, first aid, and the use of

. . . radiation monitoring equipment. In addition, a Radiological Controls Technician is assigned to each shif t to provide 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 day per week coverage.

This technician is available to provide radio-logical control assistance in the determin-ation of emergency exposures, stay times, and methods of dose reduction. He will provide personnel monitoring equipment and techniques (including dosimetry) in accordance with applicable Radiological Controls Procedures and maintain records of personnel exposures as normally required by these procedures.

(3) The Emergency Maintenance Coordinator is responsible for directing the activities of the Emergency Repair Team (s) and for coor-dinating those activities with the Shif t Revision 2 4.5-9 June 1980 A=endment 19

Supervisor through the Operations Coordinator.

The Emergency Repair Team will rective health physics support, if necussary, through the Operations Support Center Coordinator.

d. Security and Personnel Accountability The TMI Site Security Force will operate by the requirements established in the Security Plan and Procedures. The IMI Site Security Force will report to the Security Coordinator in emergency situations. The Security Coordinator, in turn, shall report to the Faergency Director.

The Security Force vill alueys respond and provide assistance as required for security controla.

The responsibilities- associated with personnel accountability will be assmed by Security. Pro-visions have been made in the Security Plan for admitting emergency vehicles when Security is notified, in advance, by the Shif t Supervisor or Emergency Director. In addition, Security will, as

- appropriate, direct such vehicles to the proper location. Requirements for providing advance

-mtification to Security will be detailed in the ppropriate Emergency Plan Implementing and Security Procedures.

e. Radiological Assessment The Radiological Assessment Coordinator is respon-sible for directing the operations Support Center Coordinator and the Radiological Analysis Support Engineers. In addition he is responsible for coordinating

• the activities of several emergency response teams that are within his part of the

! e onsite emergency response organization. As required, i be shall direct the Operations Support Center i

Coordinator to dispatch Of f site and/or Onsite i

Radiological Monitoring Tesas which will report directly back to him. Be shall coordinate initial radiological assessment activities, review results, and report findings and make recommendations to the Emergency Director. In addition, he shall interf ace with the Envirotsmental Assessment Coordinator (See Figure 18) on radiological and environmental matters including requests for RAP and IRAP assistance.

t

! (1) The Radiological Analysis Support Engineers shall perform dose projection calculations, source tezs calculations, and other such calculations or determinations that may be necessary to assess radiological hazards and to minimize personnel exposure.

Revision 2 4.5-10 Juae 1980 ,

Amend =ent 19

i (2) The Operations Support Center Coordinator shall be responsible for and direct the activitias of personnel reporting to the Operationa Support Center. He will specifically direct and coordinate the activities of the Health Physics and Chemistry Coordinators.

These individuals are responsible for in-plant health physics and chemistry controls, respsc-tively. As mentioned above, the Operations Support Center Coordinator will dispatch Offsite and/or Onsite Radiological Monitoring Teams as directed by the Radiological Assess-ment Coordinator.

(3) Once the Environmental Assessment Command Center is manned, radiological assessment activities will be directed from this location.

A complete discussion of dose assessment is contained in section 4.6 3 5.

f. Firefiahtina

Specific personnel on each shif t (Shif t Fire Brigade) are trained in firefighting to ensure such capability will be available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 days per week. The Fire Brigade, under the direction of the Shif t Supervisor or another individual designated by him, shall respond to all fire alarms and report to the location of the fire with assigned equipment. During the normal work week, additional qualified firefighting personnel will, as necessary, be obtained from the normal onsite organization. Assistance will be requested from local fire departments as deemed necessary by the Emergency Director.

g. First Aid and Rescue Medical emergencies and rescue operations will be the responsibility of the First Aid and Rescut Team. Specific personnel on each shif t are trained in first aid techniques to ensure such assistance will be available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 days per week.

Assistance will be requested from outside medical support personnel or organizations as deemed neces-sary by the Emergency Director.

h. Radiological Monitorina Prior to the activation of the entire onsite emergency organization, the Emergency Director may dispatch Offsite and/or Onsite Radiological Monitoring

! Teams via the Operations Support Center Coordinator as well as other personnel to perform radiological Revision 2 4.5-11 June 1980 Amendment 19

monitoring functions. Af ter the Of fsite and Onsite Radiological Monitoring Tasans are dispatched, they shall report directly to the Radiological Assessment Coordinator. The various radiological monitors and monitoring teara are responsible for performing radiation / contamination surveys, for radiological monitoring, and for assisting in decontmaination activities as assigned. A complete discussion of monitoring teams and dose assessment is contained in i

section 4.6 3 5. 1 1

i

1. Repair and Damane Control The Emergency Repair Team (s), under the direction of the Emergency Naintenance Coordinator, provide for the assessment of equipment damage and will effect emergency repairs as required for operations.

4.5.1.4 offsite Emernency Support Ornanization The Off site Emergency Support Organization, shown in Figure 13, vi1*, provide technical and logistics support in the event of

• a serious or potentially serious emergency. This organization will be staffed by personnel from the normal station organiza-tion, the normal technical support organization, and consultants.

In general, the responsibilities of the offsite emergency support organization are to:

o Prwide liaison and communications with the Nuclear Regulatory Commission and the appropriate State and county agencies.

o Provide public relations and make news releases.

o Provide for environmental monitoring and assessment in support of the onsite emelancy organization.

o Provide security support.

i o Support the onsite emergency organization in engineering I

and technical matters.

o Coordinate the restoration and/or operation of all generation, transmission and distribution facilities.

o Procure and dispatch transportation equipment and services.

o Purchase materials, equipment, and services necessitated by the emergency.

o Provide assistance for reentry operations and post-accident planning.

o Assign post-accident investigation and review responsi-bilities.

1. The Emergency Support Director and his Assistant will be responsible for activating and directing the ,of fsite emergency support organization and ensuring that the functional groups provide a coordinated response in n

Revision 2 . 4.5-12 June 1980 Amendment 19

_ _,__ _ ___~ . _ _ ,. - . - _ _ _ _ _ _ _ - - - _ , . _ _ _ _ _

support of the onsite emergency organization. The Emergency Support Director will serve as the senior management representative at or in the vicinity of the ,

IMI site. As such, during emergency operations, the l Faernency Support Director may provide advice and guidance to the Emergency Director; the Emergency l Director, however, will maintain overall responsibility for the operation and control of the plant. As emergency ,

situations tend to stabilize, the Emergency Support Director may relieve the Emergency Director of more and more accident management responsibilities. H is will i provide ,a centrolled means of shif ting to a recovery organization should that type of organizational arrange-ment be deemed necessary.

2. De Emergency Support Communicator and his staff of -

assistants will be responsible for the operation of the er=== icatioc' systems at the Near-site Energsney Opera-tions 7acility and the coordination of requests for outside assistance.

heir duties include, but are not necessarily limited to:

a. D e setup and operation of primary communications systems. i

b. The setup and operation of backup commmications systems.

c. Maintaining records of communications.

,. d. Maintaining the Near-site Emergency Operations Facility status board up-to-date.

a. Coordinating the procurement of outside resources (e.g., technical assistance, manpower, equipment, etc.) with the Group

• eader of Administrative Support. l l 3 The Public Af fairs representative shall report to i the Emergency Support Director in a staff capacity.

His specific responsibilities are detai* JJ it the l Emergency Public Information Plan which is attached to this Plan as Appe ix 5. Briefly, however, hia primary responsibilities ,'ll be to maintain liaison with i GPU-Nuclear management and keep them infoned of all

! onsite developments and prepare news releases. To

i fulfill these responsibilities, he is responsible to the Emergency Support Directo. for the preparation of

technically accurate information for media release.

a. The Group 1.eader-Maintenance Support and his staff will be responsible for coordinating the allocation of i Company (i.e. , GFU-Nuclear) and non-Company maintenance equipment and manpower to support onsite operations and maintenance activities.

Revision 2 4.5-13 June 1980 A=endment 19

-- --.,----.,-.+--...--..-,,-.,,,,..,n-. -----,----,e,- - . . ~ . . . . , . . - , , - , - , - - , - , - . , , , . . - - , , --,,,-.~--e.,,r-, y,--,., . , -y y,- c,,- -, - . , .

i l

l l

5. The Group Leader-Technical Support and his sta.ff will l be responsible for providing technical analysis, eval- l untion, and recommendations to the Emergency Support

' Director and the onsite Technical Support Center Coor-dinator and his staff with respect to plant conditions, reactor core status, and subsequent plant operations.

More specifically they wilb

a. Analyze mechanical, electrical, and instrument

. and control probisms; determine alternate solutions, design and assist in the coordination of the insta!.1-ation of short-term modifications.

b. Analyze thermohydraulic and thermodynamic problems and develop problem resolutions.

c. Assist in the development of Emergency Procedures, Operating Procedures, etc. as necessary for con-ducting emergency operations,

d. Analyze conditions and develop guidance for the Emergency Support Director, the Emergency Director, and operations personnel on protection of the core.

e. Resolve questions concernirg Operating License requirements with NRC representatives.

6. The Group Leader-Security Support will be responsible for the overall security program required to support anergency operations. This includes the coordination of permanent and temporary security forces and the clearance and baciging of emergency response personnel requiring site access. The Group Leader-Security Support will provide a member of the Security Force to the Group Leader-Administrati"e Support to assist him in the processing and clearance of emergency response personnel requiring site access.

, 7. The Group Leader-Health Physics Support and his staff will be responsible for all aspects of health physics and environmental assessment support for the onsite emergency organiza tion. Such support may include, but is not limited to:

a. Overall assessment of the impact of liquid and gaseous effluents with respect to Technical Specifi-cations (reference 4.10.13.2) and protective action guides.

b. Providing a member of the Health Physics Department to the Group Leader-Administrative Support to assist him in the processing (including issuing personnel monitoring devices) of emergency response personnel requiring site access.

c. Personnel dosimetry (whole body and extremity) and l emergency TLD controls and documentation.

l d. Wole body counting and evaluation.

i e. Identification and coordination of required equip-ment and manpower resources.

, f. Assessment of solid waste problems.

Revision 2 4.5-14 June 1980 Amendment 19 l

l . _ _ _ _ . . _ _ _ . _ . __ __ . . - . _ _ _ _ . . _ __ , _ _ . _ .

e

8. The Group Leader-Chemistry Support and his staff will be responsible for all aspects of chemistry support for the onsite emergency organization. Such support may include, but is not limited to:

a. Determination of in-plant sampling requirements based on plant conditions.

b. Coordination of the use of laboratory instrumentation, sample analysis, sample storage, and the interpre-tation and dissemination of analysis results.

c. Identification and coordination of required equipment and manpower resources.

9. The Group Leader-Administrative Support and his staff vill be responsible for administrative and logistics functions required to support the entire of fsite and onsite emergency organizations. The types of support services that might be required include, but are not necessarily limited to: -

a. General Administration (1) Word processing (2) Typing pool -

' (3) Reproduction

b. Transportation (1) Helicopter services (2) Vans, busses, automobiles, shuttle service

c. Personnel Administration and Accommodations (1) Personnel processing (a) Registration (b) Indoctrination and training (c) TLD issuance (d) Security badging (2) Lodging , food ,

d. Outside Plant Support (1) Trailer set-up (2) Janitorial service l (3) Telepho es

e. Commissary

) (1) Temporary facilities and meal delivery

f. Safety (1) Industrial safety (2) First Aid (3) Training

g. Human Resources (1) Manpower (2) Labor relations (3) Payroll

(4) Clerical Support +

1

! 4.5.1.5 Lona-Term Recoverv Ornanization In those cases where post-accident conditions indicate that recovery operations will be either complicated or v111 extend over a relatively long period of time, GPU-Nuclear will Revision 2 4.5-15 June 1980 Amendment 19

- _~ - _ - - -

i shif t from the emargency responsa crganizations (i.e., onsito and of fsite support) to a long-term recovery organization.

The organization itself will, of course, be dependent upon the nature of the accident, post-accident conditions (i.e. ,

plant conditions, radiation / contamination levels, etc.) and other factors to be determined at the time. Prior to initi-ating recovery operations, which are further discussed in Section 4.9 0 below, a specific long-term recovery organiza-tion will be defined. For long term recovery, the GPU organiza-tional structure shown in Figure 14 will be used and is described below:

1. The Of fice of the President GPU-Nuclear is responsible for the overall recovery operation. This includes overseeing the operations of the various functional groups and ensuring that all activities, proposed courses of action, and contingency plans receive proper analysis and coordination and selection of senior personnel to fill the key positions in the long-term recovery organ-ization.

2. The Public/ Government Af f airs Group is responsible for

! coordinating the exchange of information with public and governmental agencies and includes legal counsel as a part of its organization.

3. The Vice President Administration is responsible for providing the necessary administrative / logistics requirements such as communications, manpower, transpor-tation, commissary arrangements, accommodations, clerical suppo rt, and temporary office space and equipment. He sets priorities; develops plans and schedules; coordinates and monitors the status of tasks; and reports the work

(

l progress of all the technical groups. In addition, he

' provides administration support liaison with the Nuclear Regulatory Commission.

4. The Vice President Technical Functions is responsible for providing engineering support, technical planning and analysis, procedure support, control room technical support, data reduction and management, and support relating to licensing requirements. He is responsible for providing the engineering, design, materials and construction necessary to complete required modifications to plant systems, equipment, and structures.

5. The Vice President Unit Operations is responsible for performing all plant operations and maintenance activities, limiting and controlling personnel exposures, in-plant health physics management, terminating or minimizing of f site releases, stabilizing plant conditions, and l restoring the plant's ability to function normally and respond to any further emergencies. He is responsible for safely and effectively managing the quantities of radioactive gases, liquids, and solids that might exist during the initial phases of recovery. Subsequently, he

'- is responsible for the development and implementation of short and long-term plans to manage and process contam-Revision 2 4,5-16 June 1980

. Amendment 19

_ .-_ .._ _ ._..~. _ _ _ _ _ _ .

9 insted solids, liquids, and gases; quantifying the degree of contamination of buildings and systems; and the establishment of processing priorities based on plant needs.

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6. The Vice President Nuclear Assurance is responsible for implementing the Quality Assurance Plan for all recovery activities important to saf ety. He is responsible for implementing all necessary general employee, technical and recovery management training programs. Be provides ongoing development of the Site Emergency Plan and Implementing Document and insures that Emergency Prepared-ness is maintained for potentionally hazardous recovery activities. He assists the Generating Station by providing chemistry and metallurgical analytical services and recommending chemistry requirements and specifications for recovery and plant lay-up activities. He monitors, evaluates and assures that all recovery activities having the potential for compronizing nuclear safety are ade-quately addressed.

7. *he Vice President Radiological and Envirotmental Controls is responsible for establishing policy, coordination and review of radiation and environmental controls at the

, nuclear generating station. He is responsible for providing inplant radiological controls management and monitoring and for quantifying the degree of contamination of buildings and personnel.

8. The Vice President of Maintenance and Construction has the responsibilities for direction of activities associated with major =aintenance tasks and accomplishment of the field work for =ajor modifications. He also provides corporate oversight for all plant =aintenance activities, which is directed toward ec=monality of practices and procedures in these areas.

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l Revision 2 4.5-16A June 1980 l

Amendment 19

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4.5.2 Local Services Support

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The nature of an emergency may require augmenting the onsite emergency organization. Therefore, it may become necessary to request and utilize assistance furnished by local personnel, organizations, and agencies. In order to ensure that suppo rt fro = local law enforcement agencies, fire departments, hospitals, physicians, and ambulance services will be available on relatively short notice, letters of agreement have been made with the following personnel, organizations, and agencies (see Figure 20):

4.5.2.1 Medical Support Ortanizations and Personnel

1. Hershey Medical Center

2. Physicians

3. Radiation Ma agement Corporation

4. Bainbridge Fxre Company (anbulance service)

5. Liberty Fire Company (a=bulance service)

6. Londonderry Township Fire Company (ambulance service)

7. Rescue Rose Cempany No. 3 4.5.2.2 Firefighting Organizations

1. Bainbridge Fire Company

2. Liberty Fire Company .

3. Londonderry Township Fire Co=pany

4. Rescue Rose Company No. 3

5. Union Hose Ce=pany Revision 2 4.5-17 June 1980 Amendment 19

4.5.2 3 Law Enforcement Agencies

1. Pennsylvania State Police

2. Middletown Police Department 4.5.2.4 Miscellaneous Suecort

1. Consolidated Rail Corporation Copies of these letters of agreement are included in Appendix C.

4.5.3 Coordination with Government Agencies GPU Nuclear Corporation has and will continue to work closely with State, county, and f ederal agencies in coordinating emergency planning activities for the Emergency Planning Zone in order to ensure the health and safety of the general public. As a part of this coordin-ation, each participating agency has been assigned specific resrcusi-bilities and authority for both emergency planning and emergency response. Also as a part of this combined effort, specific emergency related notification and information reporting requirements between GFD-Nuclear and the various participating agencies have been defined.

' Additional reporting requirements, which are specified in references 4 10.14 and 4 10.13 1, will also be met. A brief description of the key elements of each of the participating State, county, and federal agencies is provided in the following subsections. Additional infor-mation pertaining to emergency related notification requirements that activate the emargency response organizations and the subsequent information reporting requirements is provided in Section 4.6.1. A diagram of the interrelationship of the various organizations is contained in Figure 20.

4.5 3.1 State Agencies The Pennsylvania Emergebey Management Agency (PEMA) was established under the Commonwealth of Pennsylvania, Public Law 1332 and is, in general, responsible for coordinating emergency services in the State. In order to plan for emergencies in a manner that compleagnt , federal guidelines and implements State directives that are related to emergency l

operations, the Commonwealth of Pennsylvania Disaster Operations Plan was prepared and issued under the authority I of, and in accordance with the provisions of, Public Law 1332.

Annex E, Emergency Nuclear lucidents (Fixed Nuclear Facili-ties), to the Disaster Operations Plan provides guidance to the State, county, local, and f ederal agencies and nuclear power plant facilities in the deveicpment and implementation of emergency plans associated with radiological emergencies.

Annex E is attached to this Plan as Appendix D.

( 1. Pennsv1vania Emergenev Manacement Agenev The Pennsylvania Energency Manage =ent Agency (PEMA) has been assigned as the lead state agency for the coordin-Revision 2 4.5-18 June 1980 Amendment 19

e ation of radiolological emergency response plans prepared by the state, county, and local governments, and the TMI Emergency Plan prepared by GPU-Nuclear. In addition, should a radiological emergency occur at the TMI Nuclear Station that requires the implementation of state, county, and local government radiological emergency response plans, the state agency through

' which the Governor will exercise coordination / control will be PEMA. However, as in all emergencies, the Governor retains directional control.

PEMA exercises authority over all organizations who are a part of the emergency response team both in the 10 and 50 mile EPZ. This authority is based in law under the provisions of Section 7313 of the State of Pennsyl-vania Emergency Management Services Code. Under law, PEMA is authorized to:

a. direct the cooperation and assistance of all state and or local agencies and of ficials.

b. provide emergency direction and control of

, Commonwealth of Pennsylvania and local disaster emergency operations.

c. accept aid and coordinate assistance provided by Federal Agencies under provisions of the Federal Disaster Relief Act of 1974.

Details on emergency response agencies involved in the 10 and 50 mile EPZ is included in Annex E, of Commonwealth of Pennsylvania Disaster Operations Plan.

To ensure that PEMA can provide 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 day per week response to emergencies, PEMA maintains a duty watch of ficer. This communication system allov immediate PEMA response to incoming emergency situation requests. PEMA is responsible for promptly communicating F with af fected counties, and contiguous state and local governments within the 10 and 50 mile EPZ.

2. Department of Environmental Resources The Department of Environmental Resources (DER), under the administration and technical direction of the Secretary, is responsible for gathering and evaluating technical information and for supplying such informa-tion and technical advice and recommendations to PEMA and the State Council of Civil Defense.

Within the DER, the Bureau of Radiation Protection (BRP) has been delegated DER's responsibilities as they apply to radiological emergencies. The Director, BRP, is responsible for meeting these delegated responsi-Revision 2 4.5-19 June 1980 Amendment 19

bilities, however, the Secretary, DER, will maintain overall responsibility. Specific responsibilities assigned to the DER /BRP that are appropriate to radio-logical energencies are defined in Section II A.5 of Annex E to the State's Disaster Operations Plan which is attached as Appendix D.

To provide for emergency response capability, the BRP has made pr w isions for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 7 day per week inter-face with PEMA.

3. Department of Education The Commonwealth of Pennsylvania vill conduct, on a continuing basis, an education progran designed to f amiliarize the public with factual information concerning nuclear radiation. (Appendix D,Section VIII L.) The Department of Education will coordinate with the Department of Invironmental Resources in the development of programs on nuclear radiation and assist DER and The Department of Health in t'se development of an enhanced public information program concerning the effacts of nuclear radiation.

4. Department of Agriculture Upon the request and under the direction of the

~ Pennsylvania Emergency Management Agency, the Department

- of Agriculture will provide for agricultural, dairy and food product control up to 50 miles downwind of a fixed nuclear facility. Details of the concept of operations is contained in the State Plan. The Department of Agriculture Plan for Nuclear Power Generating Stations is Appendix 7 of the State Plan.

5. Department'of Health Upon the direction of PEMA, the Department of Health will activate its comprehensive emergency medical plan to meet the health care needs of the citizens of Pennsylvania during the release of dangerous levels of radioactive material. This shall include the supervision of, stockpiling, distributing and administering thyroid blocking agents and other radiological health materials.

The concept of operations and resources of the Depart-ment of Health are set forth in Section II A.16 of the State Plan. The Radiological Emergency Response Plan is Appendix 9 to the State Plan.

6. Department of Militarv Affairs The Department of Military Af f airs will activate its

_ plan to support county and local government in the Revision 2 4.5-20 June 1980 Amendment 19

risk area upon request from the Pennsylvania Bnergency Management Agency. Military forces under the direction of the Department will assist in security, traf fic

,_. control and evacuation of the 10 =ile plume exposure pathway.

The total concept of operations and resources for the Department of Military Af fairs is contained in Section II.A.7 of the State Plan.

7. Department of Public Welf are In the event of an emergency the Department of Public Welf are vill provide for relocation of patients and institutional 1 zed people. ~he Department also will provide for the care of evacuees requiring special attention and will extend its public welf are assistance to those in need. (Section II. A.10 of the State Plan.)

8. Department of Transpertation The Department of Transportation vill provide guidance and direction to the af fected counties to designate traffic control points, road capacities, and major and feeder routes. *he Department will co-ordinate the marking of evacuation routes, and designate emergency fuel distribution locations. (Section II. A.11 of State Plan.)

~

. 4.5.3.2 County Agencies Public I,av 1332 states that "Each political subdivision of this Commonwealth is directed and authorized to establish a local emergency =anage=ent crganization in accordance with the

, plan and program of the Pennsylvania Emergency Management

! Agency. Each local organization shall have responsibility for

( emergency =anagement, response and recovery within,the terri-terial limits of the political subdivision within which it is organized and, in addition, shall conduct such services outside of its jurisdictional 11=its as =ay be required under this part." Therefore, each County and Local F=ergency Management Coordinator in the State is responsible for estab-lishing a civil defense organization within their respective

! jurisdiction, developing plans and preparing for emergency operations.

With respect to the 10 =ile EPI, the 5 counties identified below have prepared emergency plans that are coordinated not only with the State's Disaster Operations Plan but also with the IM1 E=ergency Plan. Local gover==ent plans are either included directly with their respective County's plan or are maintained as separate, but coordinated doeuents.

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Revision 2 4.5-21 June 1980 A=end=ent 19 i

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1. Dauphin County w The Dauphin Cousty Action and Response Plan for Energency Personnel and Citizens was prepared by the Dauphin County Office of Emergency Preparedness. This plan is attached as Appendix E.

To provide adequate response capability, the County Emergency Operations Center is the location of the County dispatcher for police, fire, and rescue services and is manned by a dispatcher 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 days per week.

2. York County The York County Protective Action Plan for the Three Mile Island Nuclear Power Plant, attached to this Plan as Appendix F, was prepared under direction of the County Commissioners and the County Emergency Management Coordin-ato r.

The York County Emergency Operations Center is the loca-tion of the County dispatcher for police, fire, and rescue services and is =anned by a dispatcher on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 day per week basis.

3. Lancaster County w The Lancaster County E=ergency Evacuation Plan was prepared i by the County Emergency Manage =ent Agency under the direction of the Lancaster County Cc==issioners. This plan is attached to this document as Appendix G.

The Lancaster County Emergency Mangement Agency has made provisions for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 day per week emergency

._ - response coverage.

4. Cumberland Coun:v The Cu berland County Three Mile Island D:ergency Response Plan was prepared under the direction of the Cumberland County Cc=_issioners and Director of E=ergency Preparedness.

A copy of this plan is attached as Appendix E.

The Cu berland County E=ergency Operations Center is the location of the County dispatcher for police, f tre, and rescue services and is =anned by a dispatcher en a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 day per week basis.

5. ' ebanon Coun:v The Lebance County E=ergency Operations Plan, Radiation Incidents - Three Mile Island Nuclear Power Plant, a copy s

Revision 2 4.5-22 June 1980 A=end=ent 19

l I 3 f i

of which is attached as Appendix I, was prepared by the Lebanon County Emergency Management Agency and approved by the County Commissioners. The Lebanon County Emergency Operations Center is the location of the County dispatcher for police, fire, and reserve services and is manned by a dispatcher on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 day per week basis.

4.5 3.3 Federal Agencies Should an emergency situation or accident occur at the TMI site, notification, reports, and requests for assistance may be made to various federal agencies and organizations. j Specific details for notifying and making reports to these  ;

agencies, as well as requesting and obtaining assistance, '

will be provided in the Emergency Plan Implementing Pro-cedures. The following agencies may, as the situation warrants, be contacted:

1. Nuclear Regulatorv Commission The Nuclear Regulatory Commission (hACs requires notification and reports as specified :: references 4.10.14 and 4.10.13.1. In addition, : -ilowing noti-fication by GPU-Nuclear, it is expectts that FEMA will also notify the NRC of emergencies at the TMI Nuclear .

Station. As situations warrant, the NRC Regional l

Of fice will notify the Department of Energy.

1 During a radiation emergency, the primary role of the l NRC is that of conducting investigative activities associated with the incident and verifying that l; emergency plans have been Laplemented and proper I agencies notified. Should NRC personnel be dispatched to the scene, they will, as needed, assist in coordin-l ation with Radiological Assistance Tasms provided by j the Department of Energy, and providing to State and local agencies advisory assistance associated with *

.... . investigating and assessing radiological hazards to the public.

To ensure reports can always be made, the Region 1 NRC Office vf Inspection and Enforcement (I&E) is equipped with a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> emergency telephone number and has assigned duty of ficers. The Region I I&E Of fice is located in King of Prussia, Pennsylvania.

A letter of understanding is provided in Appendix C.

2. Department of Energy The Department of Energy (DOE) has established several l regional coordinating of fices for the purpose of providing radiological emergency assistance to State,

! county, and local governments; nuclear power plant l facilities; and other federal agencies.

To ensure 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 7 day per week emergency response cap 6bility, DOE has established a continuously l Revisien 2 4.5-23 June 1980 l Amendment 19 l l l

i manned Security Operations Center in each of their designated regions. The Security Operations Canter for the region in which the TMI Nuclear Station is located

% is in the Brookhaven Office in Upton, New York. A letter of understanding is provided in Appendix C.

3. U.S. Coast Guard During a radiation emergency which could involve exposure to offaite personnel, the U.S. Coast Guard will provide assistance by maintaining traffic control on the Susquehanna River. By authority of the Pennsyl-vania Emergency Management Agency, the U.S. Coast Guard, as assisted by the Coast Guard Auxiliary, may also be used to keep unauthorized personnel from entering Three Mile Island and adjacent islands until emergency conditions are controlled. Assistance may be obtained by calling the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> emergency telephone number. A letter of understanding is provided in Appendix C.

4. Departnent of the Army The 56th Ordinance Detachment of the Department of

~

the Army will provide Explosive Ordinance Disposal personnel in response to requests for assistance during bomb threats. Additional details of this arrangement are specified in a letter of agreement which is provided in Appendix C.

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- 5. Federal Aviation Administration The Federal Aviation Administratica will ensure air traffic is diverted around the TMI Nuclear Station in the event an emergency situation exists with the potential for a radioactive release. A letter of

. . . . . . . agreement covering this matter is provided in Appen-dix C.

6. National Weather Service The National Weather Service will provide backup meteorological information as necessary, and initiate balloon runs upon request. A letter of agreement is p ovided in Appendix C.

4.5.3.4 Interagenev Communications Sections 4.6.1 and 4.7.5 describe the communications con-cepts and equipment that will be utilized by TMI emergency response personne1.

The Communications section of the State Disaster Operations Plan (included in Appendix D) and Section II, "Communica-Revision 2 4. 5-24 June 1980 Amendment 19

[

l e l tions", of the Department of Environmental Resources Bureau of Radiation Protection Plan for Nuclear Power Generating Station Incidents (included in Appendix D) l l describe the systems and comununication concepts that are l

utilized by the Commonwealth of Pennsylvania in order to l coordinate emergency activities. l The Operations Officer and after normal hours, the Duty Of ficer, are the primary contacts for PEMA. The Emergency i Management Coordinator, his Deputy or Communications l Of ficer are the primary contacts at the county level. The Deergency Management Coordinator at the local level is that political subdivision's principal contact. The Director of the Bureau of Radiation Protection or his designated alternate is the primary contact for the Depart-ment of Environmental Resources.

4.5.4 Trainina of State. Countv and Local Governments The Pennsylvania Emergency Management Agency (PEMA), in accordance:

with Annex E of the Disaster Operations Plan, will conduct and pr_rti-cipate in annual training exercises that involve State, county a d local government agencias and consist of (1) scenario development. (2) reviewing Radiation Emergency Response Plans, procedures, and response capabilities, (3) testing of communications, radiological monitoring instrursentation and warning systems, and (4) critique of the exercises.

PEMA also provides a comprehensive series of courses consisting of home study, seminars / workshops, and formal training programs on subjects such as basic emergency management, basic health physics, operation of radiological survey instrumentation, and county coordinator development courses and conferences. These programs are utilized to provide state emergency monitoring teams with the necessary skills to perform their functions, to provide new County Emergency Management Coordinators with the necessary knowledge to implement radiation emergency response plans and procedures, and to instruct local govern-ment officials, their staf fs, and other key personnel in emergency i

ptaparedness planning. j l

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i Revision 2 4.5-25 June 1980  !

Amendment 19 l i

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,,-,n---a , - - - , - w .- . - - - - - . ~ - - - . , . - - , , - - ,

4.6.0 EMEP.GENCY MEASURES This Section identifies the specific measures that will be taken for each class of emergency defined in Section 4.4.0 of this Plan. The logic presented in this Section is used as the basis for detailed Emergency Plan Implementing Procedures which define the emergency actions to be taken for each emergency class. Emergency measures all begin with (1) the recognition and declaration of an emergency class, l (2) notification of the applicable agencies for each emergency class, and (3) sobilization of the appropriate portions of the emergency organization. The additional measures are organized into assessment actions, corrective actions, protective actions and aid to affected personnel and are described in the sections below for each emergency class.

4.6.1 EMERGENCY NOTIFICATION OF OFFSITE AGENCIES Parameters that establish emergency situations have been predetermined and specified as emergency action levels in procedures contained in the Emergency Plan Implementing Document. When conditions or values specified in one of these procedures are met or exceeded, an emergency situation as defined in Section 4.4.1 exists (i.e., Unusual Event, Alert, Site Emergency or General Emergency). The Ehif t Supervisor must classify and declare the emergency, and ensure that all required notifications are made including those to of fsite emergency response organizations. Messages, developed in conjunction with the Commonwealth and local agencies, have been specified in an Implementing Procedure and in accordance with the Commonwealth Disaster Operations Plan, Annex E, Appendix 3, will be issued to provide information relative to the emergency class, type and magnitude of any actual or potential release, aff ected populace and areas, and any recommendations to take protective actions. Verification of messages believed to be from the facility will be made by a return telephone call from the Commonwealth Department of Environmental Resources.

In addition to the initial notification and verification telephone calls, coinnunications channels will be maintained between the facility and of fsite emergency response organizations to allow for any further dissemination of information and follow up messages concerning the emergency.

4.6.2 FOBII.IZATION OF EMERGENCY ORGANIZATIONS In conjunction with ensuring that the above notifications are made, the Shif t Supervisor will notify the Duty Section Superintendent or his designated alternate. The Duty Section Superintendent working closely with the Shif t Supervisor, will perform an overall assessment of the emergency in order to determine if it is necessary to activate a portion of, or the entire emergency organization. A more detailed discussion of the methodology that is used in activating the emergency organizations during each class of emergency is provided below. In addition, Figures 15,17, and 19 provide a visual display of the communications networks that have been planned for notification requirements, information reporting, and decision making.

l Revision 2 4.6-1 June 1980 Amendment 19 l

( .-- ._ - - - _ _ . - - - - .-.- - _. . - .- - - - . - . _ - -.. . .

4.6.2.1 Shift Foreman / Control Room Operators

1. Should emergency situatione (real or potential) arise, it is expected that the Control Room Operator (s) and/or the Shif t Foreman will be in:tially made aware by alarms, instrument readings, reports,. etc. The Control Room Operator (s) shall ensure chac the Shif t Foreman and/or the Shif t Supervisor are immediately informed. The Shift Foreman shall, if not already accomplished by the Control Room Operator (s), inform the Shif t Supervisor immediately.

4.6.2.2 Shift Supervisor

1. The Shif t Supervisor, when informed of an essergency situation, is responsible for performing the assessment of the emergency (e.g., plant systems and reactor core status, radiological conditions, etc.) . He will determine what immediate actions must be taken (e.g. '

use of Emergency Procedures) to ensure the safe and proper operation of the plant. The Shif t Technical Advisor will advise and assist the Shif t Supervisor on matters pertaining to the safe and proper operation of i

. the plant with regards to nuclear safety. '

2. If the situation requires implementation of the TMI Emergency Plan, the Shif t Supervisor shall:

a. Initially classify the emergency as an Unusual Event, Alert, Site Emergency, or General Emergency as appropriate and implement the applicable Emergency Plan Implementing Procedure.

b. Ensure notification of the following agencies and personnel of the emergency declaration:

(1) Dauphin County EOC (2) PEMA EOC (3) NRC Of fice - Bethesda, Maryland (4) Duty Section Superintendent (5) Unaffected Control Room (6) Public Af fairs Representative The initial notification messages shall contain information about the class of emergency, whether a release is taking place, potentially affected population and areas, and whether protective measures may be necessary.

c. The Shif t Supervisor may, if deemed necessary, have the unaf fected unit's on-shif t duty roster and emergency duty section manned. If manned, they will not necessarily implement the Emergency Plan for the unaffected plant but report to their watchstations and await further instructions from Revision 2 4.6-2 June 1980 Amendment 19

from their Shif t Supervisor s

3. Due to the numerous responsibilities assigned to the s_

Shift Supervisor at the onset of an emergency, he shall prioritize his actions to (1) ensure the safe operation of the plant, (2) ensure that immediate notificacion requirements are met, (3) dispatch, in the event of rad 1= logical emergencies, Radiological Monitorirc Teams, and (4) perform additional emergency actions as time and conditions permit.

4.6.2.3 Duty section Superintendent

1. The Duty Section Superintendent, upon being informed cf an emergency declaration by the Shif t Supervisor, shall:

a. Evaluate the information, data, and methods used by the Shif t Supervisor in order to ensure that the proper emergency classification has been made.

b. Determinc to what extent the offsite and onsite emergency organizations shall be activated within the following guidelines:

• (1) For an Unusual Event, all or part of the Duty Section shall be activated as necessary.

(2) For an Alert, the Duty Section shall be activated along with all or portions of the onsite emergency organization. The Technical Support Center and the Operations Support s- Center will be activated.

1 (3) For a Site Emergency, the entire onsite acergency organization shall be activated.

A major portion, if not all of the of fsite emergency organization shall also be activated .

(4) For a General Daargency, the entire onsite and offsite emergency organizations shall be e ac tivated .

c. Inform the support rember of the Duty Section of  ;

dae emergency and direct him to activate the of fsite and/or onsite emergency organizations as l determined bnmediately above. I

d. Report to the Emergency Control Center and assume the position of Emergency Director in the onsite emergency organization.

NOTE: The Shif t Supervisor shall assume the responsibilities l assigned to the Emergency Director until properly I relieved by the Duty Section Superintendent.

4.6.2.4 Emergency Director

1. The Emergency Director shall locate himself in the Emergency Control Center and assume the responsibili-ties specified in subsection 4.5.1 3 1 above.

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Revision 2 46-3 June 1980 Amendment 19

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I' 4.6,2.5 Dauphin County

l. The dispatcher at the Dauphin County EOC shall notify the Dauphin County Emergency Management Coordinator or his designated alternate.  ;

2. The Dauphin County Emergency Management Agency (EMA) l shall, through area and local civil defense personr.el  !

and other means, notify local municipalities with priority f avoring those nearest TMI.

4 6 2.6 Pennsylvania Emergency Management Agency j

1. The PEMA Duty Officer or Operations Officer at the State EOC shall, upon receiving notification of an emergency at the TMI Nuclear Station, immediately notify the Bureau of Radiation Protection.

2. PEMA shall, in accordance with standard operating procedures, notify the following personnel, organi-zations, and agencies as appropriate:

a. Dauphin Ccunty EMA

b. Other af fected county emergency management organiza-tions (e.g., York, Lancaster, Cumberland, Lebanon)

c. Other af fected states (i.e., Maryland)

d. Selected State agencies such as the:

(1) Department of Environmental Resources s_ (2) Department of Agriculture

_ (3) Department of Health (4) State Police (5) Department of Transportation

e. Selected Federal agencies.,

t 4.6.2.7 Bureau of Radiation Protection

1. The Bureau of Radiation Protection employee (i.e.

Incident Manager) who receives the notification from PEMA that an emergency exists at the TMI Nuclear Station shall:

a. Call the TMI Nuclear Station Emergency Control l Center to:

(1) Verify actual origin of the emergency message from TMI Nuclear Station (2) Determine the classification of the emergency (3) Obtain information and data pertaining to the emergency.

b. Initiate activation of the BRP emergency response organization.

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l Revision 2 4.6-4 June 1980 Amendment 19 i

L_ _ _ . . . ._. _

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c. Advise the PEMA Duty Officer er Operations Officer of the BRP's initial assessment of the emergency.

s_ d. Notify selected Federal agencies.

4.6 3 Assessment Actions

• Ef fective coordination and direction of all elements of the emergency ,

organization requires continuing accident assessment throughout '

an emergency situation. Each emergency class will invoka similar  ;

assessment methods, however, each class imposes a different magnitude of assessment af fort. In the following subsections assessment actions to be taken for each emergency class are outlined.

4.6 3 1 Assessment Actions for Unusual Events The detection of an Unusual Event will arise from either exceeding a specific emergency action level for this class (see Subsection 4.4.1.1) or by an action statement in an Emergency Procedure. Detection of the event in either case vill come as the result of alarms, instrument readings, .

recognition through experience or a combination thereof.

The continuing assessment actions to be performed for this -

• class of emergency will be in accordance with the Emergency Plan Implementing Procedure for an Unusual Event and will consist of the normal monitoring of Control Room and .

other plant instrumentation and status indicaticus until the situation is resolved. If a fire was the reason for the declaration of an Unusual Event, the Fire Brigade leader who will have reported to the fire location will make continuing assessments based on his experience and report to the Emergency Director on whether offsite firefighting assistance is required.

4.6.3.2 Assessment Actions for Alerts Once an accident has been classified as an Alert by the Emergency Director, assessment actions will be performed l in accordance with the Emergency Plan Implementing Pro-cedure for an Alert. 'Ihese actions will include:

1. Increast d surveillance of in-plant instrumentation.

2. If possible, the dispatching of an Emergency Repair l

Team to the identified problem area for confirmation and visual assessment of the problem.

3. The dispatch of onsite radiological monitoring team (s) to monitor for possible reae.ases and provide rapid confirmation of correct accident classification.

i 4. Dose Assessnent -- If a radiological accident is occuring, surveillance of the in-plant instrumentation necessary to obtain meteorological and radiological data required for calculating or estimating projected Revision 2 4.6-5 June 1980 Amendment 19

e doses will commence. The dose assessment activity will continue until termination of the emergency in order that updating of initial assessments may be provided to all concerned offsite agencies and to the Emergency Director. Emergency Plan Implementing Procedures are provided to allow rapid, consistent projection of doses. A complete discussion of moni-toring teams and dose assessment 1; contained in section 4.6 3.5.

4.6.3.3 Assessment Actions for Site Emergencies The assessment act' ions for the Site Emergency class are similar to the actions for an Alert, however, due to the increased magnitude of the possible release of radioactive material, a significantly larger assessment activity will occur. The necessary personnel for this assessment effort will be provided by mobilization of the onsite and offsite emergency organizations. Specifically,

1. An increased amount of plant instrumentation vill be monitored. In particular, indications of core status (e.g., incoro thermocouple readings) will be monitored closely.

2. Monitoring ef forts will be greatly increased. Onsite and offsite monitoring teams will be dispatched.

In addition to beta and gsama field measurements, the s, changeout of hermoluminescent dosimeters (TLD's) at

_ frequent intervals will be done, air sampling and collection of other environmental media for assessment of material transport and deposition will be performed.

3. Dose assessment activities will be conducted more frequently, with an increased emphasis on dose projection for use as a factor in determining the necessity for protective actions. Radiological and i meteorological instrumentation readings shall be used I

to project (1) dose rate at predetermined distances from the plant, and (2) an integrated dose. In reporting the dose projection to the Emergency Director or offsite agencies, the dose rate, dose, and the basis for the time used for the dose estimate will always be pr ovided . Any confirmation of dose rates by of fsite teams will be reflected in reporting or revising dose estimate information proviced to applicable of f site agencies. A complete discussion of monitoring teams and dose assessment is contained in Section 4.6 3 5.

4.6.3.4 Assessment Actions for General Emergencies As ses sment actions for the General Emergency Class will be the same as for the Site Emergency class with some possible shif t of emphasis to greater offsite monitoring Revision 2 4.6-6 June 1980 I Amendment 19 i

l

efforts and dose projection efforts extending to distances farther from the plant. Additionally, since the projected doses are likely to be much closer to EPA PAG's, greater t emphasis shall be placed on the assessment of release -

duration. Judgements and assumptions used for dose assessment will always be reported. A complete discussich of monitoring teams and dose assessment is contained in '

section 4.6.3.5.

Time distance dose plots for specified gamma whole body dose and thyroid dose for a TID-14844 accident with engi- '

neared safety features operable are included in Figures 21, 22, and 23. Time versus exposure rate plots for the Dome Manitor with 100% of Gap and Core Noble Gases and Iodine in Containment atmosphere are included in Figures 24, 25. 26 and 27.

4.6.3.5 Radiological Assessment and Off-Site Monitorina Prior to the activation of the entire On-site Emergency Organization, the Emergency Director may dispatch of f-site radiological monitoring teams via the Operations Support Center Coordinator. These teams will consist of one to

- two persons per team, trained in the use of portable radiation monitoring equipment. When dispatched, the teams will proceed to the Processing Center where they will pick up emergency kits containing portable monitoring equipment (see Table 13) and portable radios. After an operational check of the equipment, they will pick up an s

emergency vehicle and proceed to their first monitoring location. They will be controlled by the Radiological Assessment Coordinator and will report all readings to him.

The plant has the capability to dispatch two radiation monitoring teams and receive initial monitoring data within one-half hour of the emergency declaration.

_. - .... In-plant Radiological Controls procedures have been modified to reflect the ability to measure and detect r.n borne radioiodine and particulates under field conditions in the presense of noble gases and background radia d.on.

These procedures incorporate the use of both charcoal and silver zeolite cartridges, as necessary, with a Nal crystal connected to a single or dual channel analyzer.

For gaseous releases, the first step in the assessment process is to estimate the noble gas and the iodine source rele ase terms in curies per second . To do this, the radi-at$ en monitoring system readings for all the monitored gaseous effluent release paths are factored into combined source release terms for noble gas and iodine by applying the appropriate ventilation flow rates, meter conversion factors, containment building design leak rate, etc. Whole body dose rates and iodine concentrations are then projected by applying *he appropriate meteorological dispersi,n factor s

Revision 2 4.6-7 June 1980 Amendment 14

(I/Q) for the location of interest. Once the projections are made, the radiation monitoring teams can be directed to

~

the location of interest to take readings and confirm the projection. Based on the difference in actual versus projected values, source release terms are corrected and used for further projection. This iterative process is continued in order to determine the actual source release terms as accurately as possible. As soon as initial projected whole body dose rates and iodine concentrations are determined, they will be integrated to determine whole body and child thyroid dose based on the expected duration of the release or a nominal time of two hours if the duration of the release cannot be estimated. These integrated doses will be compared to the lower limit protective action guides and communicated to the Bureau of Radiation Protection.

If the instrumentation used for radiological assessment is of f-scale or inoperative, the Radiological Assessment Coordinator must utilize contingency dose calculation procedur es. These conservative calculational methods utilize dose release factors which are based upon the expected plant source release terms for several accident classifications. The Radiological Assessment Coordinator must first select the accident class which most closely fits the current plant conditions. He must then apply the I/Q for the location of interest to the dose release factor to proj ect whole body and child thyroid exposures. Con-currently, radiation monitoring teams are sent to those locations of interest to take actual field measurements in

. order to refine the projections and to correlate projected versus actual results. These detailed calculational tech-niques are included in an Emergency Plan Implementing Procedure.

For liquid releases, the radionuclide concentration at any downstream location is determined by taking the radia-tion monitoring system readieng on the plant liquid effluent monitor and applying the af fluent flow rate, a meter conver-sion f actor and river volumetric flow rate. The detailed calculational technique is included in an Emergency Plan Implementing Procedure. Downstream users will be notified to curtail intake if the projected concentration is above the level specified in the procedures.

Once the of f-site emergency organization is manned, and )

the Environmental Assessment Coordinator announces his 1 readiness, the responsibility for of f-site radiological I assessment will be transferred to the Environmental Assess-ment Coordinator. The decision to transfer responsiblity for of fsite radiological monitoring will be made by the Radiological Assessment Coordinator. The Radiological Assessment Coordinator will notify the Environmental Assessment Coordinator of this transfer via a dedicated Revision 2 4 6-8 June 1980 Amendment 19

I line. Additionally, a formal radio announcement at the time of this transfer will be made to all offsite monitoring teams. In carrying out his responsibilities the E2viron-mental Assessment Coordinator will utilize the Environmental Assessment Command Center and its support staff. The Radiological Assessment Coordinator will maintain control of the on-site radiation monitoring team (s) and onsite assess-ment. Communications to the Bureau of Radiation Protection regarding off-site dose projection will now originate from the Environmental Assessment Coordinator.

The Environmental Assessment Coordinator and his staff at the Environmental Assessment Command Center have the following capabilities.

Four one-aan teams and a two-man mobile monitoring lab can be dispatched during an emergency situation. This can be backed-up by three additional one-man teams, should it become necessary. The portable equipment that is available and the mobile van are described in Table 20. The mobile environmental laboratory obtains additional meteorological information from its portable tower. The laboratory's tower is outfitted with

' instrumentation to measure ambient temperature, wind speed and wind direction at the 33 f t. level. This information is recorded on strip charts located inside the lab. Communications between field teams and the Environmental Assessment Command Center will be via twr-way radios with CB and Tone activated pagers as m 1.ekup. Field data can be relayed to both the Control Room and Near-site Emergency Operations Facility via separate dedicated phone lines from the Environmental Assessment Command Center.

Ef fluent monitoring data is relayed to the Envircumental Assessment Command Center by the Radiological Assessment -

Coordinator. This information is then fed to a computer based in Bethesda, Md., which also receives direct meteorological data from the site's meteorological tower to be used in making dose calculations and proj ections. Verification and alterations in the model projections are corrected upon receipt of field mon-itoring data.

In addition, effluent monitors will be tied directly into a computer along with the meteorological data.

Dose calculations and plume projections can then be called up at will thrwgh the Environmental Assessment Command Center's CRT unit. Corrections to the model projections will be accomplished through field moni-toring teams and real time garma detectors.

The sof tware package associated with this system, referred to as MIDAS (Meteorological Information and Revision 2 4.6-9 June 1980 Amendment 19

s t

Dose Acquisition System), provides, the following primary functions:

a) Collection and s orage of data f from the meteorological system on site, plant ef fluent monitors and of f-site radiation monitors. g (b) Real time atmospheric dispersion, dose calculations

- will be based on the above datak (c) Retrieval and processing of hist;orical data for af fluent reports and environmental dose calculations required by Appendix I Technica Specifications.

(d) Remote interrogation by governme{nt agencies for disp ofresultsinprintedorCRTgryhicsformat.

(e) Miscellaneous routines to facilitate data checking, archiving , maintenance, editing , etc.

4.6.4 Corrective Actions Data 11ed operating procedures are available to the charators for use during emergencies as well as normal operations. Sp acific Emergency Procedures are provided to assist the operators in placing the plant in a safe condition and taking the necessary supplemental corrective actions. In addition, operations personnel are trained in the operation of plant systems and their associated proegdures and will, therefore, be capable of taking appropriate corrective actions.

Selected TMI Nuclear Station Staff personnel, includingyperations, health physics, and maintenance personnel, are trained atd assigned to emergency teams. These teams will be able to respond as het forth in the Emergency Plan Implementing Procedures in order to asgess condi-tions and take any available corrective actions. Maintenance per-sonnel will provide the necessary craf ts expertise to ef fe'tt repair and damage control functions. I Corrective actions will normally be planned events that are aken to ameliorate or terminate the emergency situation. Planned rai ioactive releases or corrective actions that may result in a radioacti e release will be evaluat'ed by the Emergency Director and his s aff as far in advance of the event as is possible. Such events and d ta pertaining to the release will, if at all possible, be reporte- to the appropriate of fsite emergency response organizations and at ncies.

l 4.6.5 Protective Actions l

Protective actions are emergency measures taken during or af ter .jn emergency situation that are intended to minimize or eliminate ele hazard to the health and safety of the general public and/or site personnel. Such actions taken onsite a- e the responsibility of GPU Nuclear Corporation while those taken cf f aite fall under the jurisdiction of the Commonwealth of Pennsylvania and other of fsite response agencies. All visitors to the site will be either escortid

by an employee knowledgeable as to emergency plan response or will !

l receive training on actions required by them during an emergency.

Revision 2 4.6-10 June 1980k Amendment 9 i

4.6.5.1 Protective Cover. Evacuation. Personnel Accountability During an emergency, the relocation of persons may be required in order to prevent or minimize exposure to radiation and radioactive materials. The following subsections discuss the policies applying to such situ-ations.

1. Plant Site At the time an emergency is declared, an announcement is made on the site public address system to all persons within the Owner Controlled area. The announce- ,

ment will include the classification of the event, a brief description of the event, and actions to be taken on-site if required. Station shif t personnel will proceed to their respective emergency assignments.

At the discretion of the Emergency Director, all non-essential personnel within the Protected Area vill be individually accounted for at a predesignated assembly area. All non-essential personnel outside, the Protected Area will muster at different predesignated assembly areas, and will be accounted for if time pe rmit s .

Upon declaration of a Site Emergency, or at the dio-cretion of the Emergency Director, all non-essential personnel will report as described above. Thereaf ter,

- these people will be evacuated from the site in accor-dance with applicable Emergency Plan Implementing Procedures and Security Procedures. This evacuation will be by private vehicle out to FA 441 and then north to the Crawford Station.

l Upon declaration of a General Emergency, or at the discretion of the Emergency Director, all non-essential personnel within the Protected Area vill be accounted for and evacuated from the site as described above.

Non-essential personnel Outside the Protected Area, however, will be directed to proceed to their vehicles and to evacuate to the Crawford Station tamediately.

In support of these operations, Site Security Personnel will direct a search of all buildings, trailers, and other areas of the Owner Controlled area to ensure that all persons have assembled and/or evacuated the site.

Search and rescue operations will be implemented to locate any missing persons.

Once at the Crawford Station, all personnel will be accounted for and radiation worker trained personnel will monitor persons and vehicles for radioactive contamination. Individuals found to be contaminated Revision 2 4.6-11 June 1980 Amendment 19 i

l

(i.e. , greater than 1000 dpm) will be decontaminated in accordanca with applicable Health Physics Procedures.

Vehicles found to be contaminated vill be impounded until they can be taken to a suitable site for decon-tamination. In the event that Crawford Station is inaccessable due to plume passage, the 500kv substation east of the site will be used as an alternate off-site assembly and holding area. Inclement weather will not affect the direction of the traffic flow, but may increase evacuation times. Righ traf fic density results only from traffic to and from TMI.

2. Offsite Areas The responsibility for actions to protect persons in of f site areas rests with the Commonwealth of Pennsyl-vania and is described in detail in Annex E (attached as Appendix D) to the Commonwealth of Pennsylvania Disaster Operations Plan and implemented in conjunc-tion with the county emergency plans.

The Department of Environmental Resources, Bureau of Radiation Protection (BRP) is the specific agency

~

responsible for evaluating information from the plant staff and all other sources and recommending to PEMA that protective actions be taken. The 3RP has a number of protective action options such as evacuation, sheltering and thyroid prophylaxis. The most appro-priate protective action for a particular situation

_ vill depend on the magnitude of the release, duration of the release, vind speed, vind direction, time of day and transportation constraints. In the case of a General Emergency, circumstances may indicate the immediate need to initiate some precautionary protective action . This judgment is the responsibility of the 3RP and should be based on an evaluation of the current plant conditions, dose projections relative to the PAG's and expected subsequent plant operations /evalu-acions. Examples of such precautionary measures are (1) immediate sheltering within a certain radial distance from the plant, (2) evacuation within a certain radial distance from the plant, (3) evacuation of a certain sector based on vind speed and direction, i

etc.

GPU-Nuclear through the TMI Emergency Director shall remain ready throughout an emergency to provide protective action recommendations to State of ficials (see also Assessment Actions, Section 4.6.3) by way of the Radiological Line. The Emergency Director will make his reconmendations consistent with the

protective action options outlined in the State Plan Annex E, Appendix 8 (Bureau of Radiation Protection) .

l Revision 2 4,6-12 June 1980 Amendment 19

l

a. Consideration shall be given to sheltering if:

1) Release time is expected to be short (puff release

<2 hours)

2) Evacuation could not be well under way prior to expected plume arrival due to short warning time, high wind speeds and/or foul weather.

l

~

b. Consideration will be given to evacuation if:

1) A release is expected to occur with projected doses approaching or exceeding:

1 Ram Wole Body and/or 5 Rem child thyroid

2) Release time is expected to be long (>2 hours)

3) Evacuation can be well underway prior to plume arrival for above release, based on wind speed and travel conditions.

The means to warn or advise persons involved is desig-nated a responsibility of the " Risk County" in Annex E of the State's Disaster Operations Plan.

Annex E also designates the " Risk County" as respon-sible for the preparation and dissemination of infor-mation material on protective actions to the general

'. public and includes necessary information (evacuation routes , mapa, e tc.) for the implementation of protec-tive measures in the plume exposure pathway.

4.6.5.2 Use of Onsite Protective Equipment and Supplies l

The following onsite locations have been designated as l

i emergency assembly points and areas where emergency teams I will be assembled in accordance with the Emergency Plan Implementing Procedures or as directed by the Emergency Director or his representatives. Such representatives may be the Shif t Supervisor, or emergency team leaders.

1. Control Room / Shift Supervisor's Of fice The Control Room and Shift Supervisor's of fice are designed to be habitable under accident conditions and will serve as the primary onsite Emergency Control Center (ECC). Emergency lighting, power, air filtra-tion-ventilation system, and shielding walls enable operators to remain in the Control Room to ensure that the reactor will be maintained in a safe condition. In addition, the operators will be able to evaluate plant l

Revision 2 44-13 June 1980 i

Amendment 19 I _ . _ - _ _ _ _ _ _ - - _ _ .___ _- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ ___ __

B conditions and relay pertinent information and data to appropriate onsite and of fsite personnel, organi-

_ aations, and agencies during all emergencies. To ensure the operations shift and other personnel assen-bled at the location can remain self-sufficient, emergency equipment and supplies will be stored in or near the Control Room. The exact location and the type and quantity of emergency equipment and supplies available vill be specified in the Implementing Document.

However, as a general gu'f e, the following will be available:

a. High and low range dosimeters,

b. Dosimeter charger,

c. Dose rate survey meter (s),

d. Contamination survey meter (s),

e. Protective clothing,

f. Respirators and/or masks,

g. Air sampler (s),

h. Portable lanter=s and/or flashlights,

1. Walkie-calkie( s) ,

j. Site sector map and map overlays,

k. Map of environmental monitoring stations,

l. Copy of the Implementing Doctament,

m. Station floor plan drawings and piping and instrument diagrama,

n. Resuscitator,

o. First aid kit, and

_ p. Miscellaneous supplies and equipment.

2. Access Control Point / Operations Support Center During normal operation this area serves as the access control point for personnel entering the controlled areas. Health Physics equipment will normally be on hand in this area to support daily operation and maintenance activities. However, to ensure that an l adequate inventory of equipment and supplies will be

! available, additional emergency equipment and supplies I

vill be maintained in this area. The exact location and the type and quantity of emergency equipment and supplies will be specified in the Implementing Document.

However, as a general guide, the following vill be available:

a. High and low range dosimeters,

b. Dosimeter charger,

c. Dose rate survey meter (s),

d. Contamination survey meter (s),

e. Protective clothing,

f. Respiraters and/or = asks,

g. Air sampler (s),

h. Neutron survey =eter(s).

1. Portable lanterns and/or flashlights, Revision 2 4 6-14 June 1980 A=end=ent 19

j. Copy of the Implementing Document,

k. Decontamination chemicals,

1. Self-contained breathing apparatus,

m. Resuscitator,

n. First aid kit, and

o. Miscellaneous supplies and equipment

3. Processing Center The Processing Center vill be continuously manned by Site Security force personnel. Emergency equipment and supplies will be maintained in this facility to support such tasks as reentry efforts, performing onsite radiation surveys or collecting samples. The exact location and the type and quantity of emergency equip ,

ment and supplies will be specified in the laplementing Document. However, as a general guide, the following vill be available:

a. High and low range dosimeters,

b. Dosimeter charger,

c. Dose rate survey meters),

d. Contamination survey meter (s),

e. Protective clothing,

f. Respirators and/or masks,

g. Air sampler (s),

h. Portable analyzer,

1. Portable power inverter,

j. Portable lanterns and/or flashlights,

k. Site sector map and map overlays,

1. Map of environmental monitoring stations,

m. Walkie-talkie ( s) ,

n. Copy of the Implementing Document,

o. First aid kit, and

p. Miscellaneous supplies and equipment.

l l

4. - Unit 1 Service Building Auditorium Emergency equipment and supplies, which are located in lockers in the vicinity of the auditorium are maintained for such tasks as personnel monitoring, and readying l

contaminated, injured personnel for transporting to the hospital. The exact location and the type and quantity of emergency equipment and supplies will be specified in the Implementing Document. However, as a general Suide, the following will be available:

a. Poly sheeting,

b. Protective clothing,

c. Monitoring equipment.

4.6.5.3 Emergenev Equipment Readiness To insure that the necessary emergency equipment is maintafned and available for use during emergency situations, readiness Revision 2 4.6-15 June 1980 Amendment 19 l

checklists have been developed and incorporated in the Health Physics procedures. These checklists provide for detailed inventory and calibration / functional checks of equipment contained in the emergency kits / lockers. The inventory checklists will be performed on a quarterly basis and to insure interim readiness, all kits / lockers are sealed or locked as appropriate. Table 13 lists emergency kits by General Category.

contamination control Measures

~

4.6.5.4 This section describes provisions for preventing or minimizing ?,irect or subsequent ing7stion exposure to radioactive materials deposited on the ground or other surfaces.

1. Plant Site All land areas within the exclusion area are owned by the Licensee and will, therefore, be controlled. In addition, there are no areas for producing agricultural products within the exclusion area. In plant contamin-ation control vill be controlled in accordance with

. approved Radiological Controls procedures.

2. Offsite Areas

• Offsite, it is the responsibility of the State Depart-ment of Agriculture in conjunction with the Departments m

of Environmental Resources and Health to issue guidance and coordinate actions to control contaminated agricul-tural products (See Annex E, Appendix T, of the Common-wealth of Pennsylvania Disaster Operations Plan) .

4.6.6 Aid to Affected Personnel This section of the plan describes the measures that vill be used by the Licensee to provide necessary assistance to persons injured or exposed to radiation and radioactive material.

4.6.6.1 Enerzenev Personnel Exnosure 1

Emergency personnel, including those involved in removal of injured persons, undertaking corrective actions, per-forming assessment actions, providing first aid, perforv.ing personnel decontamination, providing ambulance service, and I

providing medical treatment services, vill have their exposures controlled to the limits specified in 10 CTR 20

( for radiation workers. This is accomplished through normal health ~ physics practices on site. Wen personnel are called in from of f-site, qualified health physics technicians are provided to support the offsite teams. For example,

, a health physics technician is assigned to the of fsite fire j teams to monitor and control radiation exposures and evaluats-radiological hazards.

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l j Revision 2 4.6-16 June 1980 Amendment 19 l _ _ _ _ _ ._. .__ . _ _ _ _ _ . . -

O

)

1 Faergency sensures may warrant the acceptance of above-

~

normal radiation exposures (doses). Saving of life, measures to circumvent substantial exposures to population groups or even preservation of valuable installations may all be sufficient cause for above normal esposures. De

. following are the exposure guidelines for these emergency activities :

Life saving action -

100 Rem Wole Body -

No Syroid Limit  !

Corrective action - 25 Rem W ole Body or 125 Rea nyroid

'i ne Emergency Director is the designated individual who can authorize emergency workers to receive doses as defined above in excess of 10 CFR 20 limits. Rose workers must be volunteers and vill be required to closely adhere to the l controls specified in applicable procedures. In authorizing

! onsite voltsiteers to receive radiation exposure in the course of carrying out lifesaving activities, the Emergency Director shall balance the risks from such esposures against the benefits to be received from the lifesaving activities.

l 11sks are determined and decisions are made to expedite i lifesaving activities, based upon advance radiation surveys done at the affected areas to determine stay times, shielding

, requirements, or the possibility of dispatching a " scouting" team to assess actual conditions. Measures will be utilized to aid in exposure reduction and the Emergency Director, in consideration of advice from the Radiological Assessment

. Coordinator, shall assure that all possible measures are taken to minimize other exposures (such as internal exposures) during the activities.

4.6.6.2 First Aid and Decontamination i 1. First Aid l

l Emergency first aid and medical treatment will be given to injured personnel who are contaminated. Shift i personnel, trained in first aid, will be available l en-site on a 24-hour per day basis and will assist I contaminated personnel wither at the scene of the accident or in the first aid room located at the 305' elevation of the Service Building. Provisions have been made, through agreements, to ensure contaminated and injured personnel vill receive specialized medical treatment if necessary. n e Hershey Medical Center '

i has agreed to accept contaminated patients for emergency medical and surgical treatment and/or observation.

(See letter cf agreement, Appendix C.)

Radiation Management Corporation (RMC), in conjunction with Hershey Medical Center, has developed a comprehen-sive program of Radiological Control for injured Revision 2 4.6-17 June 1980 A=endment 19

contaminated personnel and vill institute this program

~

when necessary during an emergency. The primary '

emphasis will be to initially address tramatic or life-threatening injuries since radiation injuries are not immediately life threatening. RMC will also provide j on-site consultation and supervision of contaminated injuries and aid in preparation of affected persousel  ;

for transport to of f-site treatment / decontamination facilities. (See letter of Agreement, Appendia C.)

Transportation will be arranged and provided for as discussed in subsection 4.6.6.3. If affected personnel sust be transported, measures will be taken to prevent

! the spread of contamination. Such seasures will include placing affected personnel in " clean" protective clothing or wrapping in blankats. The bergency Director will insure that the organizations who will provide the transportation and treatment are alerted.

If necessary, a physician will be requested to provide medical assistance on-site. Detailed instructions for treatment and trasportation of contaminated and injured -

personnel are specified in the Implementing Document.

l 2. Decontamination Personnel and equipment decontamination will be ini-

~ tially accomplished at the Unit I Bealth Physics Access control point where specialized equipment and supplies are available. Procedures are written with specific details for the accomplishment of decontamination.

by the Licensee, and by Radiation Management Corporation.

For personnel within the 2rotecte Area, emergency i situations which require decontamination will be handled in accordance with these procedures and the implementing document.

1 l All personnel leaving the Protected Area will be l nonitored for contamination by use of portal monitors, I and/or hand and foot counters, and/or friskers.

Any individual found to have contamination levels in l

excess of 1000 disintegrations per minute as measured by an RM-14 friskar with HP 210 probe (or equivalent instrument), will be considered to be contaminated.

Perst ael found to be contaminated will undergo decon-tami ation by radiological controls personnel (or other l qualified personnel as specified in Radiological Controls Procedures). Measures will be taken to prevent the spread of contamination. Such measures may include isolating af fected areas, placing contaminated person-nel in " clean" protective clothing before moving, and Revision 2 4.6-18 June 1980 Anendnent 19

decontaminating affected personnel, their clothing, and

' equipment p-ior to release, in accordance with appli-cable station Radiological Controls Precedures.

In the event that a release of contaminants has occurred

~

or is occurring, in-plant potable water systems will be secured to prevent possible contamination. For emergency personnel who remain on-site, water and food supplies will be brought in using sealed containers and will be monitored by Radiological Controls personnel prior to use or consumption, and then on a normal routine basis to validate their safety from con-tamination. Any food or water supplies discovered to be contaminated will immediately be disposed of as waste and will not be used. Upon the receipt of infor-macion that the energency is ended and a recovery phase has started, in-plant facilities and areas will be surveyed, sampled, and cleared for use or controlled as necessary in accordance with applicable Radiological Controls procedures.

If it becomes necessary to declare an on-site evacu-ation, personnel from outside the Protected Area vill be directed to proceed to Crawford Station. Upon errival at Crawford Station, personnel accountability will be performed and individuals for contamination.

If anyone is found to be contaminated, showers, sinks

~ and decontamination supplies are available at Crawford Station. Equipment for decontaminating personnel will be in Emergency Supply Kits. Included are such items as absorbent material (atomic swipes), scrub brushes, soap, shampoo, decontaminant chemicals, wash bottles, cotton-cipped applicators, surgical gauze and gloves, protective clothing, and other assorted equipment to be used in preparing for decontamination and waste control.

Portable survey instruments are available and kept under current calibration for use in decontamination operations. All skin contamination prob 1r:.s will be handled by using normally accepted health physics practic es.

For contaminated personnel inside the Protected Area, the preferred decontamination facilities will be chose on site at the Health Physics Control Access Point if accessible; otherwise the Crawford Station will be used.

4.6.6 3 Medical Transportation Ambulance service for the site is provided f or by letters of agreement with neighboring first aid squads. See Appendix C for actual agreement letters. Off-site emergency squads will include squad members with a minimum of Red Cross l

Revision 2 4.6-19 June 1980 Anendment 19

advanced first aid certification. GPU-Nuclear will provide training to the squad members in the treatment and transpor-tation of containated injured individuals. GPU-Nuclear will provide radiological control technicians if available to assist the squads enroute to the hospital.

4.6.6.4 Medical Treatment Arrangements for hospital and medical services for injured or contaminated / overexposed personnel are provided for by letters of agreement with the Hershey Medical Center, Radiation Management Corporation and local physicians.

See Appendix C for actual agreement letters.

The first level of treatment can be given on-site, either within the controlled area (if necessary), or in the First Aid Room. Onsite emergency medical services will be rendered by site personnel who are Red Cross multi-media First Aid Certified. GPU-Nuclear has agreements with local private physicians for medical services when needed. If the  :

severity of the injury requires more extensive or prolonged tr ea tment, the patient will be transported to the second level of assistance. For conventional inj uries (that is, non-radiation related), the patient will be transported to the Harrisburg Hospital.

The Hershey Medical Center receives contaminated / injured personnel in a special area designated as the Radiation

~ Bnergency Area. The Medical Center has detailed plans and procedures for the decontamination and treatment of contaminated patients. A brief ".ist of the equipment available at the Radiation Emergency Area includes l

i o GM and Ion Chamber Instruments o Respirators o Dosimeters

. _.....o. Anti-Contamination Clothing o Radioactive Waste Containers o Portable Shielding o Decontamination Table o Decontamination Kits o Sample Taking Kits o Thermoluminescent Desimeters The Hershey Medical Center employs a prof essional staf f consisting of a certified health physicist, a master's level health physicist and radiation protection techno-logists. The Center has over two hundred radioisotope laboratories, receives thousands of radioactive shipments l

each year and conducts radiation therapy using Cobalt 60 and a linear accelerator. The staf f is routinely involved in operations requiring radiological controls.

Radiation Management Corporation's f acilities and services include a radiation chemistry laboratory, exposure Revision 2 4.6-20 June 1980 Amendment 19

evaluation services including a whole body mobile counter, a radiation emergency medical team, and a special van designed to transport contaminated patients. Radiation Management Corporation also has access to and use of the Hospital of the University of Pennsylvania special engency medical accident plan facility which includes a radiosurgery decontamination suite with auxiliary traffic flow and contamination control features.

RMC is under the direction of a physician, certified in both radiology and nuclear medicine, who is also the Asso-ciste Professor of Clinical Radiology at the University of Pennsylvania School of Medicine. The RMC Staff is comprised of approximately 150 people, skilled in health physics, radiation physics and measurement, radiochemistry, environ-mental sciences, biology and ecology. Staff members include individuals with doctoral degrees and Certified Health Physicists.

4.6.7 Early Warning and Information for Transient Areas 4.6.7.1 Early Warning Early warning and instructions to the population at risk are accomplished by the PEMA and its af fected county emergency l management organizations. Prompt notification by the l Licensee is the vital first link in this process and is described in Sections 4.4.1, 4.6.0, 4.6.1, 4.6.2.2.2.b and i 4.7.5.

Once Commonwealth of Pennsylvania authorities have been notified, several methods to warn the population-at-risk can be utilized. The method used will depend on the severity of the situation. The methods available are:

1. Emergency Broadcast System (EES) - PEMA and the counties have the capability to broadcast bulletins over the EBS f rom their emergency operations I centers.

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2. Siren Alert System - The counties can selectively activate warning sirens.

3. Each county can notify its local Emergency Management Coordinators by telephone.

4. Each county has central dispatching manned on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> basis with radio communications with police, fire departments, etc.

5. Vehicles with loudspeakers can be dispatched to broadcast warning messages.

Additional information concerning warning capability is Revision 2 4,6-21 June 1980 l Amendment 19

I detailed in Annex E to the State Disaster Operations Plan.

4.6.7.2 Information for Transient Areas Annex E of the State Disaster Operations Plan directs the counties to develop and post information and appropriate advisories to the public, including transient areas such as motels, hotels, parks; etc., concerning be actions to be taken during an amargency. These acticas include evacuation.

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Revision 2 4.6-22 June 1980 Amendment 19 l

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4.7.0 EMERGENCY FACILITIES AND EQUIPMENT This section describes the equipment and f acilities that are utilized to:

o Assess the extent of accident hazards.

o Mobilize the resources required to mitigate the consequences of an accident.

Provide protection to plant personnel.

o Support accident mitigation operations.

o Provide immediate care for injured personnel.

o Effeet damage control.

A diagram identifying the major emergency f acilities and their general location relative to each other is attached as figure 18.

Many of the GPU-Nuclear facilities and much of the equipment are normally used for routine plant operations. Other items are reserved for use only on an "as needed" basis.

4.7.1 Licensee Onsite Emerzenev Centers 4.7.1.1 Emernency Control Center The designated location for the Emergency Control Center is in the Unit 1 Control Room and the adjacent Shif t Supervisor's Office. These areas are designed to protect personnel from radiation hazards and natural phenomenon. Command and control of all site-related emergency efforts originate from this center.

4.7.1 2 Technical Suovert Center

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'. The Technical Support Center (TSC) is located in close proximity to the TM1 Unit 1 Control Room. It is an area below the Control Room on the 322' elevation of the Control Building (Remote Shutdown Station) . This area contains the necessary controls to bring the reactor to a safe shutdown.

A display unit and patch board provide ac:ess to over 100 key plant parameters that may be used for assevsing accident conditions. Records and drawings which de scribe the as-built l conditions and layout of structures, systems, and components i

are contained in fireproof filing cabinets inside the TS C.

The TSC contains a Victoreen VAMP gamma monitor and an AMS-3 continuous air monitor, each having alarm capability.

In addition, the TSC is within the boundary of the Control Room Ventilation System, hence back-up air monitoring is available. If any monitor indicates a significant increase, Radiological Controls is notified and protective measures are taken based on recommendations from Radiological Controls. Full-f ace filter respirators, sufficient for the number of people to be assigned to the TSC, are available in the TSC should they be required. The TSC is well shielded from outside sources of radiation since the control building is aircraf t hardened with about 4 feet of reinforced concrete for external valls.

Revision 2 4.7-1 June 1980 A=endment 19 1

The TSC is activated during an Alert, Site, General Emergency or when directed by the Emergency Director. Once activated, Procedures requires the setting up of tables and chairs stored in the TSC, arranging prints, technical manuals, and other information sources for availability, and manning the Operational Line. Should the TSC become uninhabitable, procedures direct that the TSC Coordinator move to the computer room and the engineers move to the Instrument and Control Shop where room is available for them to work.

Personnel reporting to the TSC are established by the 1MI-l Emergency Plan Duty Section Schedule.

The purpose of the Technical Support Center is to provide an area outside of the Control Room that can accommodate 25 personnel acting in support of the command and control functions by furnishing more indepth diagnostic and cor-rective engineering assistance.

Future additions to the TSC will include permanent gamma and airborne radiation monitors, as well as a Cathode Ray Tube Monitoring System (CRT) with an attached printer. This CRT System will be capable of monitoring the plant computer and required radiological information on a "not to interfere with the operator" basis. This will increase the TSC engineering staf fs access to plant parameters. This CRT will be powered from a vital bus. Power f ailure will not cause a loss of information since the plant computer will be on an uninterruptable power supply.

4.7.1.3 Operations Support Center

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The primary location for the Operations Support Center (OCS) is in the area of the Health Physics Access Control Point on the 306' elevation of the Control Building . The secondary location for this Center is in the Instrument Control Shop and Instrument Supervisor's Of fice which are both adj ac ent to the Control Room.

There is adequate room for all required shif t personnel and those workers who may be in the radiologically controlled area. Emergency equipment available in the OSC is described in 4.6.5.2 part 2. The OSC is well shielded from outside sources of radiation due to the control building being aircraft hardened. The OSC is normally within the Auxiliary Building ventilation system. However, on detection of airborne activity, the OSC area is isolated from the re-mainder of the Auxiliary Building ventilation system and can be placed in a recirculation mode of operation through a charcoal filter system.

The purpose of establishing an Operations Support Center is to provide an area for shif t personnel to muster for subsequent assignment to duties in support of emergency ope rations .

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Revision 2 4.7-2 June 1980 Amendment 19 l l

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4.7.2 Licensee Offsite Emernencv Centers 4.7.2 1 Near-site Enernency Ooerations Facility The TMI Observation Center fIwting on Highway 441 east of the M site vill house the primary Near-site Emergency i Operations Facility (EOF) . This facility is normally manned j l as a public relations center and is a well built permanent structure with adjacent parking areas. Sufficient area for helicopter landing is available in close proximity to the TMI Observation Center. The TMI Observation Center l will house the key technical groups of the offsite emer- <

gency organization. In addition the BRP will send a liaison representative and the NRC will locate their senior site amargency team at this location. The Near-site EOF has a Cathode Ray Tube Monitoring System (CET) as described for the Technical Support Center (Section 4.7.1.2).

Depending upon the logistics requirement, certain non-technical functions will be located either at the Crawford Station or the 500kV Substan, south of the TMI observation Center. (See Figure 13) 4.7.2.2 Backun Near-site Emergency 0serations Facility The Crawford Station, which is located approximately three miles north of the TMI site, serves as the backup location for the Near-site Energency Operations Facility.

4.7.2.3 The Environmental Assessment Command Canter The Environmental Assessment Cr== mad Center will be located in of fices at the Olmsted Airport and will be made opera-tional concurrent with the Near-Site EOF. Once operat$onal, the command center will be responsible for the assessment of all off site radiological impacts. This includes offsite dose calculations, of fsite monitoring of releases via all major pathways, and the receipt and dissemination of all data received from offsite emergency teams to the Environ-l mental Assessment Coordinator located at the Environmental Assessment Command Center.

l 4.7.2.4 P arsippany Technical Functions Center This center will be located at the GPU headquarters building in Parsippany, NJ. The Group Leader-Techni al Support and his staff will report to this center within four hours of notification of an anergency at TMI. A representative of this group designated as the Assistant Group Leader -

Technical Support, will be dispatched to the Near-site EOF f or the purpose of giving recommendations to the Emer-gency Support. Director. This center will have a dedicated phone line to Babcock and Wilcox in Lynchburg, Va., called

! the Parsippany/B&W line, and a dedicated phone line to the Near-site EOF and the TSC called the Parsippany/TMI l

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Revision 2 4.7-3 fune 1980

! Amendment 19 '

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line. This center vill also have access to in-plant parameters via a CRT system similar to that described in Section s 4.7.1.2.

4.7.3 County. State, and Federal Emergency Centers 4.7.3.1 County Emernancy Centers Potential TMI-related emergencies could impact the people in Dauphin, Lancaster, York, Cumberland, and Lebanon counties. Each of these jurisdictions has Energency Oper-ations Centers (EOC's) that meet or exceed the minimum federal criteria for suf ficient space, communications, warning systems, self sufficiency in supplies and accomo-l dations, and a protection factor of 40 or more. All counties maintain at least two full time employees to coordinate emergency planning. County EOC's are located in the following places:

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1. Dauphin County EOC Dauphin County Court House Front & Market Streets Harrisburg, Pennsylvania 17101

2. Lancaster County EOC

-- Lancaster County Court House

. 50 North Duke Street Lancaster, Pennsylvania 17602

3. York County EOC York County Court House

• 28 East Market Street l York, Pennsylvania 17401 l 4. Cumberland County EOC l

l Cumberland County Court House High and Hanover Streets Carlisle, Pennsylvania 17013

5. Lebanon County EOC Lebanon County Municipal Building 400 South Sch Street Lebanon, Pennsylvania 17042 4.7.3.2 State Emergenev Center The State Emergency Operations Center (PEMA headquarters) is located in the Transportation Building in Harrisburg.

Revision 2 4.7-4 June 1980 Amendment 19

It contains provisions, accomodations, and its own water supply to support State operations people. A reliable communications system ties all area and county emergency operations centers into the State center. During an emergency, representatives from selected State agencias assemble in the State EOC to manage the response efforts.

The State EOC also has the capability to transmit over the l

Emergency Broadcasting System.

4.7 3 3 Federal Emergency Center i

l The Federal Emergency Center will be located at the Capital City Airport. This center will have communications ties with the State Bureau of Radiation Prctection. Both the Department of Energy and the Environmental Protection Agency radiation assistance teams will operate out of this location.

4.7.4 Media Center '

The Media Center will be located in a trailer parked adjacent to the TMI Observation Center. Equipment and facilities are designed to l,

support timely communications and information dissemination on plant conditions and emergency operations. Large press conferences will be i

held in the Hershey Hotor Lodge Convention Center. Additional information on the media center is provided in the Emergency Public i Information Plan for the Three Mile Island Nuclear Generating Station which is attached as Arpeudix B.

l-i 4.7.5 COMMUNICATIONS SYSTEFJi The TMI communications system is designed to ensure the reliable, timely flow of information and action directives between all parties having jurisdiction and a role to play in the mitigation of energen-cies at the TMI Nuclear Station. Reliability is provided via (1) extensive redundancy, (2) alternative communications methods, (3) dedicated cofbunication equipment to preclude delays due to system swamping, and (4) routine use of many of the systems which lovers the probability of undetected system failures. Timeliness of information flow is achieved by (1) prompt notification, (2) predefined lines of communication, (3) predefined emergency action levels, and (4) predefined levels of authority and responsibility.

Figures 19 is a block diagram showing the physical relationship and fundamental communications paths between all parties involved in accident mitigation. The Unit 1 Control Room is the primary source of plant information. Information originating in the Control Room can be classified into two maj or catagories: operational data and radio-logical data. The TMI communications network is formulated around this basic concept and is designed to channel information directly to the key parties having closely related f unctions thus eliminating errors of ten associated with second hand information. By providing well defined and dedicated communication links, better accident manage-ment from physically separate control and support centers can be achieved .

1 Revis1on 2 4.7-5 June Ir80 ,

Amendment 19 i

9 4.7 5 1 Operational Line The " Operational Line" is special telephone located in the Shif t Supervisor's Office that has dedicated telephone lines connecting it with (1) the Babcock & Wilcox Company in l Lynchburg, Virginia, (2) the DEI Technical Support Center,

! and (3) the Near-site Emergency Operations Facility, and (4) l the alternate Near-site EOF. The " Operational Line" permits l

an unimpeded flow of plant parameters, system status data, reactor core conditions, and any other information needed by the involved parties to resolve problems in accident mitiga tion. Conference capability also permits discussions involving all parties and timely decisions on subsequent plant operations. The Cr==micator is responsible for establiahing and controlling this special line of cr==mi-

cations. The next available individual in the appropriate l functional group may act as an alternata for the Commamicator on instruction of the Emergency Director. (See Table 18, number 1).

4.7.5.2 Radiological Line i

The " Radiological Line" is a special telephone located in the Control Room which has dedicated telephone lines connecting it with (1) the State Bureau of Radiation Protection. (2) the Near-site Emergency Operations Facility, and (3) the alternate Near-site IOF. The " Radiological Line" permits the transmission of plant conditions, dose projec-tions, of fsite monitoring results, and liquid affluent release data to all parties involved with accident assessment.

- The Radiological Assessment Coordinator, located in the Control Room area, is responsible for establishing and controlling this special line of cr==mications. Conference capability also permits discussions involving all parties.

The Radiological Assessment Coordinator may appoiv. the next available individual in the appropriate functiona.. group as an alternate Cr==micator on the " Radiological Line" . The State 3RP Incident Manager may appoint a Radiological Line alternate per the procedures established in the BRP plan.

(See Table 18, number 2).

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l 4.7.5.3 NRC Emergenev Notification System (ENS)

The NRC Emergency Notification System het line is a dedi-cated telephone system that connects TMI with NRC head-i quarters in Bethesda, Maryland. It is to be used for reporting emergencies. Commercial telephone lines should be used as backup communications. Transmittal of operation-ally related data should be done over this system. The purpose of this line is to provide reliable cr==mications with the NRC. The ENS hotline phones are located in the Control Room, the Shif t Supervisor's Of fice, Operations Support Center, Technical Support Center, and the Near-site EOF. The Emergency Director, the Emergency Support Director, s

Revision 2 4.7-6 June 1980 Anendnent 19

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(. and the Technical Support Center Coordinator asy, in cases i

where it is necessary, appoint the next available individ4a1 in the appropriate functional group to act as a LNS hotline alternate communicator. (See Table 18, number 3).

4.7.5.4 Health Physics Network Line (HFN)

• In the event of a site emergency, this HFN network line will j

be activated by NRC Operations center in Bethesda, Maryland.

This phone is part of a network that includes all nuclear

, power plants, the NRC Regional Offica and the NRC Operations l headquarters in Bethesda, Maryland. The HFN is a restricted l network and should not be used by non-government employees at any time unless used to report a significant event when both the INS and the commercial telephone lines are out of service. This system is dedicated to the tra-4 ttal of radiological information by NRC personnel on site to NRC personnel at the Bethesda office and Regional office.

HPN phones are located in the Shif t Supervisor's office and Near-site Bsergency Operations Facility. (See Table 18, number 4) .

4.7.5.5 Environmental Assessment Line The Envirotusental Assessment Line is a dedicated telephone line that connects the RAC in the Control Room and the EAC at the Environmental Assessment Command Center at Olmsted Airport. Through this line, the EAC will receive radiological assessments from the Environ-mental Assessment Command Center and the Control Room.

Monitoring teams will radio all findings to the Environ-mental Assessment Command Center for transfer to the EAC.

The EAC say , if necessary, appoint an alternate ommunicator for this line. The alternate should be chosen from the next available individual from the appropriate function group.

(See Table 18, number 12) .

4.7.5.6 Parsippanv/B & W Line This dedicated line connects the GPU-Nuclear Technical Functions Group in Parsippany, New Jersey with the Babcock and Wilcox technical function group in Lynchburg, Virginia.

This line serves to provide a reliable channel of communi-cation for more in-depth diagnostic and corrective engin-sering assistance between the operator and the supplier of the nuclear steam supply system. (See Table 18, number 9).

4.7.5.7 Parsippanv/TMI Line This dedicated line corycts GPU-Nuclear Technical Functions group in Parsippany, New Jersey with the Near-site Emergency Operations Facility and the TMI Technical Support Center.

This allows for rapid exchange of technical data between Revision 2 4.7-7 June 1980 Amendment 19

the Technical Support Center Coordinator and the Group Leader - Technical Support at TMI and the Assistant Group Leader-Technical Support in Parsippany. Phone lines are located in the Near-site EOF, TSC, and Technical Functions Center in Parsippany, New Jersey. (See Table 18, number 10).

4.7.5 8 National Warning System (NAWAS) Line A National Warning System (NAWAS) telephone connecting the Control Room directly to the Penesylvania Emergency Henage-ment Agency operations center in Harrisburg, Pennsyl-vania ensures a reliable means for prompt notification of an emergency and, as appropriate, ch'e subsequent exchange of information. In the event of communication difficulties, the Emergency Control Centet may initiate a tone-activated pager. This radio device can be used for transmission of messages from the Emergency Control Center to the Pennsyl-vania Emergency Managenaent Agency (PEMA) . (See Table 18, number 5).

4.7.5 9 Emeraency Director's Auto-Dialer Phone (Pive Af f ected Counties) l' l The Shif t Supervisor's Office has been supplied with a telephone equipped with an auto dialing system. The following essential numbers are listed on the auto log: PEKA duty of ficer, the five county EOC's, state police, DOE RAP Team, Hershey Medical Center, NRC, Harrisburg Hospital,

. Duty Supervisors and essential staff members. This phone system allows rapid notification of all essential parties and organizations in the amergency response network.

Backup communications to the Dauphin, Lebanon, Lancaster,

, Cumberland and York County EOC is provided with open channel

! tone activated pagers on the operations frequency. (See Table 18, number 11).

4.7.5.10 Pennsylvania Bell System THI is served by the Pennsylvania Bell System for normal telephone service. This system is expected to function during emergencies as it does during normal plant oper-ations . GPU-Nuclear leases tie lines that ensure reliable access to other locations. These tie lines preclude local phone activity from swamping calls into and out of the TMI Nuclear Station.

4.7.5.11 Microwave System TMI maintains telephone communication with the entire GPU system via a company owned microwave transmission system.

Access to this mode of transmission is made via the plant telephone system.

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l Revision 2 4.7-8 June 1980 Amendment 19

t 4.7.5.12 Radio Communications Radio communication equipesnt used in normal plant oper-ations will be used in an emergency to comarnicate with mobile units and to provide backup to the tulephone system if necessary. Radio capability includes the following:

1. TMI Operations Frequency

2. TMI Security Frequency

3. Met-Ed System (Lebanon Frequency)

Radio transmission capabilities are as follows:

GPU Security transmits from a) central alarm station (service building), b) secondary alarm station (Frocessing Center), c) Operations Support Center, d) Unit One Emergency Control Center, e) Near-site EOF, and f) Environmental Assessment Command Center.

h TMI Operations Frequency transmits from a) Unit 1 Emergency Control Center b) Operations Support Center, c) Near-site EOF, and d) Environmental Assessment Command Center.

Met-Ed Frequency transmits from a) centrrl alarm station, and b) Unit 1 Control Room.

The environmental and radiological field assessment teams will use the Operations and Security frequency during emergency operations.

4.7.5.13 Parent (Dauphin) County Emernency Operations Center Communication:

i The Control Room is equipped with a device that can trigger  !

a signal to be transmitted that will result in the Dauphin County EOC scanner locking into the TMI Operations Frequency.

Radio communications can then proceed with TMI transmitting on the Operations Frequency and receiving on a scanner which monitors the Dauphin County EOC frequency. In the event of cerec. ication difficulties, the Emergency Control Center may I init.iate the tone-activated pager. This radio device can be  ;

used for the transmission of messages from the Emergency '

Control Center to the Dauphin County EOC (See Table 18, 1 number 6).

j 4.7.5.14 Inter-Control Room Hot-Line I A direct line between the Unit 1 Control Room and Unit 2 l Control Room provides a reliable path for communications between Control Rooms. This keeps the adjacent unit fully cognizant of adjoining unit contitions. (See Table 18, number 8.) l Revision 2 4.7-9 June 1980 l Amendment 19  ;

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l 4.7.5.15 Emerzenev Director's Hot-Line A dedicated phone line has been established between the Emergency Control Center of Unit 1 and the Near-site Emer-gency Operations Facility. This phone is located in the Shift Supervisor's office. (See Table 18, number 7.) This phone is to be used by the Emergency Director and the Emergency Support Director for direct en-mications.

4.7 5 16 Alarms i

Audible alarms are a quick and ef fective means of com-municating emergency warnings on the TMI site. Alarms currently installed at IMI include the:

1. Radiation Emergency Alarm

2. Fire Alarm

3. Reactor Building Evacuation Alarm -

Each alarm provides a distinctive sound that all TMI Nuclear Station personnel and contractors are trained to recogniza.

4.7.5.17 Plant Paging System The plant paging system will provide immediate warning or advice to onsite personnel in the event of an amerseccy.

The plant paging system has two subsystems: the Intra-Plant Communications Subsystem and the Redundant Communi-cation Subsystem. The Intra-Plant Communications Subsystem

- links permanent plant structures through a network of phone stations and speakers. This subsystem provides four channels of communication, one page channel and three party channels.

The Redundant Communication Subsystem serves as a separate, independent system in the event of f ailure of the Intra-Plant Communications Subsystem. Phone stations and speakerb of this subsystem are located in vital plant areas.

e 4.7.5.18 Maintenance and Instrumentation Phone System The Maintenance and Instrumentation Phone System consists of three essentially independent circuits: the Nuclear i Subsystem, the Turbine Subsystem, and the Fuel Handling Subsystem. These circuits are for use between two or more locations during operations when direct communications between operators and/or maintenance personnel is required.

Handsets and headsets are provided. The system is operable when headsets and/or handsets are plugged into the various stations of the three subsystems. (See Table 18, number 15.)

4.7.6 Assessment Facilities 4.7.6.1 Onsite Systems and Equipment

1. Radiation Monitoring Svstr_

n Revision 2 4.7-10 June 1980

, Amendment 19

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The onsite Radiation Monitoring System contributes to personnel protection, equipment monitoring, regulatory compliance, data gathering, and accident assessment by measuring and recording radiation levels and concentre-tions of radioactive material at selected locations within the plant. The Radiation Monitoring System detects, alarms, and initiates, if required, emergency actions een radiation levels or radionuclide concentra-tions exceed predetermined levels. To perform these functions, area, liquid, and atmospheric monitor 1L; subsystems are required.

The data from these subsystems are displayed by readouts in the Control Room and are recorded by strip chart recorders Wich are also located in the Control Roca. A summary description of individual radiation monitor channels, dich are generally described below, is provided in Table 9.

In general the radiation monitoring equipment is designed in accordance with the following:

o' Each monitoring sention has adjustable, high trip, low trip, and power supply failure alarms.

o Solid-state circuitry is used ex ept for primary detectors.

o All AC operated radiation monitoring equipment.,

except for the pump assemblies, is provided with power from the battery-backed, inverter-f ed

. vital power supply bus. The sampling station pumps are fed from the engineered safeguards power systems.

o Each radiation monitor is capable of being checked periodically vich solenoid actuated check l sources.

I o A pulse generator or current source is used for electrically checking each monitor or sub-system. Electrical input tests measure the functional operation of the t.onitoring system from the detector output thrcugh the readout devices.

o The modules are designed so that an alarm and/or indication is initiated when failure occurs anywhere in the channel.

a. Area Radiation Monitoring The area radiation monitoring subsystem is coa.prisee of channels which utilize an ionization chamber type detector housed in a weatherproof container j and equipped with a remote controlled check source.

The local alarm and readout for each of these channels is separate from the detector and is also housed in a weatherproof container.

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Revision ? 4.7-11 June 1980 l Amendment 19

One channel is provided to monitor the high le7el of radiation thac would be characteristic of the post-accident atmosphere in the containment. The detector is densensitized by a 3esd shield.

The Control Room readout modules tra located in the radiation monitoring panel in the control room.

Atmospheric Radiation Monitoring b.

The atmospheric radiation monitoring subsystem is comprised of monitors of the fixed and movable type.

Each fixed atmospheric monitor (except the condensor of f-gas and waste gas monitor) - is comprised of a particulace measuring channel, iodine acasuring channel, and a gaseous sensuring channal. The air sample that passes through each of these channels is obtained by means of an isokinetic sampler and a pump assembly. Samples are obtained by means of a sampling head placed in a ventilation duct. The sampling heads are equipped with one or more isokinetic nozzles such that, with a sample flow of I cfa, the velocity of the air sampled is the same as the velocity of the air in the duct.

Movable atmospheric monitors on carts are typi-cally used in the spent fuel handling area during refueling operations and in the radiochemical laboratory during laboratory sample preparation operations. These monitors are also supplemented by various portable radiation monitoring equipment.

Each monitor contains three channels for particu-late, iodine, and gaseous monitoring, respectively.

Visual high-radiation alert / low-level alaras are provided for each channel at the local monitor sampling station for all atmospheric monitors.

Each channel shares 'an audible alara at the local monitor sampling station.

c. Liquid Radiation Monitoring The liquid radiation monitoring subsystem con-sists of monitors each of which consists of a sampler, scintillation detector, and Control Roon ratemeter module. The monitors indicata in the Control Room on the individual rateseter modules and two common recorders. The Primary Coolant Letdown monitor also contains a high range channel consisting of a GM detector that monitors the same sample but uses a separate Control Room

, .atemeter module.

1 Revision 2 4.7-12 June 1980 Amend =ent 19

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2. Fire Detection Devices Fire protection at TMI is provided by (1) the Fire Service Water System, (2) ths Halogenated Fire Suppree-sion Systen, and (3) the CO2 Fire Extinguishing System. j l

The Fire Service Water System is a full-loop, piped system that supplies water for (1) sprinklers, (2) I deluge water spray, (3) fire hydrants and (4) hose l connections that are located such that they provide fire protection for all major areas of thei plant and site. A 100,000 gallon Altitude Tank pro' ides the source of water to maintain system piping full and pressurized . This provides a method of monitoring system piping integrity and provides an initial

supply of water for suppressing a fire. In the

! event a fire occurs, and either an automatic or l manual system is initiated, the Fire Service Water System piping pressure will decrease which will

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cause, sequentially, one electric and two diesel fire pumps to start as necessary to meet system flow requirements.

l l- The Halogenated Fire Suppression System is provided l

in the plant ventilating air intake and tunnel to j inhibit combustion of any fuel / air mixture which I might enter the intake structure. Detection of an l anbryonic explosion releases Halon 1301 gas into the

- mixture in auf ficient quantity to render it incom-

. bustible within a fraction of the time required for the explosion to reach destructive proportions.

The CO2 Fire Extinguishing System provides fire protection for the 338 foot Elevation Relay Room. A i supply of low pressure CO2 is maintained in a refrigerated storage unit. The CO2 is discharged into the Relay room, af ter a time delay, when a i manual pushbutton is depressed or when a thermostat indicates high room temperature. .

a. The above systems are actuated either manually or automatically in response to signals from detectors monitoring conditions in the protected area. The following is a list of detectors used in various systems discussed above:

(1) Thermostats Thermostats are used to monitor the tempera-ture in the protected area. When the temperature in the area exceeds the setpoint of the thermostat, a signal is either sent to an automatic control circuit which will function to suppress the fire or sound an m

Revision 2 4,7-13 June 1980 Amendment 19

, N alarm causing an operator to activate a suppression system, or both.

(2) Embryonic Explosion Detectors The embryonic explosion detectors consist of a photocell and a pressure detector. The

, photocell will sense the initial flash of a flame front, and the pressure detector will sense the pressure wave as the flama propo-gates. This detector will react to an explosion before the explosion has time to reach destructive proportions. This signal is sent to the Balogenated Fire Suppression System, and will alarm in the Control Room.

(3) Temperature Rise Detectors Temperature rise detectors will monitor the protected area, and send a signal to either an automatic control circuit or an alarm in

. the Control Room, or both, if the rise in temperature reaches a setpoint.

(4) Fusible Links

,  % Fusible links are used in sprinkler systems

. to hold the sprinkler heads closed. When

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the temperature at the sprinkler head rises to a preset temperature, the link melts releasing the sprinkler head which then opens. In the case of a wat sprinkler system, veter is then discharged through the sprinkler. p suppress the fire. In the case of a dry sprinkler system, air is bled out through the sprinkler head, which depressurizes the sprinkler header and causes a water supply valve to open thereby supplying water to the sprinkler.

(5) Flow Datectors Flow detectors are used in the sprinkler systems (refer to (4) above), to sense the flow of unter through a header supplying a sprinkler system, there-by indicating that the sprinkler system has been actuated. This flow detector will send a signal to an alarm in the Control Room to alert the operator as to the status of that sprinkler system.

(6) Smoke and vapor Detectors Ionization type smoke and products of combustion m detectors are installed in the Control Building Revision 2 4.7-14 June 1980 Amendment 19

air return ducts. When smoke or products of combustion are detected, an alarm will sound in the Control Room and the ventilation system will automatically shutdown. Combustible vapor detectors are used to monitor Auxiliary Building plant ventilation exhaust ducts.

3. Seismic Monitorina Strong action recording systems at the 'DfI Nuclear Station measure ground motion and structural vibra-ting response caused by an earthquake occurring in the vicinity of the site. A cassette magnetic tape recorder located in the Unit 1 Control Roon receives information supplied by the triaxial sensor units which are firmly mounted on the Reactor Building.

l Ons trioxial sensor unit is attached immediately outside of the containment vall at the base of the Reactor Building. A oecond triaxial sensor is situated along the same Reactor Building axis, but is attached to the Reactor Building ring girder. The triaxial sensor units begin to supply seismic datu to the magnetic tape recorder af ter a signal is sent to the sensors by a remote starter unit. A remote starter unit attached to the base of the Reactor Building provides a signal for its systems sensor units when the starter unit detects a ground accelera-tion greater than a preset threshold level. The remote starter also actuates an annunciator labeled

. " Threshold Seismic Condition". If the ground accelera-tion exceeds the horizontal or vertical setpoints, a I

seismic trigger, also mounted on the base of the

( Reactor Building, will cause a Control Room annunciator l labeled " Operating Basis Earthquake" to actuate. The time history of a ground motion and resulting vibrating response can be displayed by using magnetic tape cassettes containing the recorded data, and the magnetic tape playback system in the Control Room.

The magnetic tape playback system produces visual playouts of selected magnetically recorded data.

This is accomplished with a strip chart recorder built into the playback system. A visual playout allows quick analysis of the earthquake. The magnetic tapes are available also for detailed analysis.

Peak reading accelerographs are anchored in the Station to Class I selected items. These accelete graphs will produce a permanent record of the peak amplitude of the low frequency accelerations caused by seismic disturbances. This record is in the form of magnetic erasure clips which must be developed, using the magnetic developer kit. Af ter developing, these clips can be examined to verify seismic response which had been determined analytically. ,

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l Revision 2 4.7-15 June 1980  ;

l Amendment 19 )

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1

4. Meteorolonical Monitors - Onsite

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At TMI, basic meteorological information is obtained from a weather tower maintained at the north end of the Island. Meteorological information has been collected at the site since May 1967. Real time information can be obtained from the mini-computer at the site.

The meteorological measurement system is deployed on a 150 f t. tower. It measures wind speed and wind direction at the 100 f t. level. There are redundant speed and direction sensors at this level. Temperature is measured at both 33 f t. and 150 f t. from two sets of platinum sensors. Temperature difference ( AT) is also derived and recorded. Dew point is measured at the 150 ft. level from the two cooled mirror type systems installed on the tower, while precipitation is measured at ground level. Strip charts located inside the meteorological building adjacent to the weather tower record all of the above information. The Control Room is also provided with strip charts of wind speed, direction, temperature, and a measure of atmospheric stability.

The mini-computer system located in the meteorological building is capable of making real-time of f-site estimates of atmospheric ef fluent transport and dif-

' fusion following an accidental airborne radioactive release from the plant. Real time meteorological information is obtained from the mini-computer at the site by telephone line or direct connection of input-output equipment. Computations based on information which is not "real time" are available by calling the data storage facility (DGI). DGI provides maintenance of a file on a disc which includes (1) data received from the meteorological tower every four hours, (2) radioactive release data, and (3) various model parmasters which can be updated at the user's option.

5. Process Monitors Process monitors measure appropriate parameters that are indicative of the status of various plant systems and the reactor itself. In addition, these parameters are displayed in the Control Room.

6. Laboratorv Facilities The TMI Unit i laboratory f acility is equipped to provide the water chemistry and radiochemical analysis support required during normal plant operations.

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4.7-16 June 1980 Revision 2 Amendment 19

7. Systes and Equipment Required bv NUREG 0578 Engineering analyses are currently in progress to determine the design, technical feasibility and installation requirements for equipment required by NUREG 0578. This equipment and crose-ref erence to the applicable section of the Restart Report are listed below:

a. Instrumentation for detection of inadequate core cooling. (Restart Report Section 2.1.1.6)

b. High range effluent monitors. (Restart Report Sections 2 1.2.1 and 2 1.2.7)

c. Post accident sampling capability. (Restart Report Section 2.1.2.4)

d. In-plant iodine instrumentation. (Restart Report Section 2.1.2.1)

In addition, procedures are being developed to better utilize existing instrumentation.

4*.7.6.2 Facilities and Equipment for Offsite Monitoring

1. Radiolonical Enviromiental Monitorina Pronram (REMP)

A complete Radiological Environment Monitoring Program (R1!MP) for the Three Mile Island Nuclear Station has been established by GPU Nuclear Corporation. Itach of the program has been in ef fect since June 1969.

The objectives of the REMP ares o To fulfill the obligations of the radiological l environmentra surveillance sections of the l Environmental Technical Specifications (refer-ence 4.10.13.2) .

o To determine whether any statistically signifi-cant increase occurs in the concentration of radionuclides in critical pathways.

o To detect any bui' dup of long-lived radio-nuclides in the environment.

o To detect any change in ambient gamma radiation levels.

o To verify that radioactive releases are within allovable limits and that plant operations have no detrimental ef fects on the health and safety of the public or on the environment.

I Revision 2 4.7-17 June 1980 l Amendment 19

I Samples for the REMP are taken from the aquatic, atmospheric, and terrestrial environments. Sample types are based on (1) established critical pathways for the transfer of radionuclides through the enviroment to man, and (2) experience gained during the preoperational and initial operational phases of the RDiP. Sampling locations were determined from site meteorology, Susquehanna River hydrology, local demography, and land uses.

Sampling locations are divided into two classes: indicator and control. Indicator stations are those which are expected to monitor plant ef fects, if any exist; control samples are collected at locations which are believed to be unaf fected by plant operations. Fluctuations in the levels of radionuclides and direct rr.diation at indicator stations are evaluated with respect to analogous fluctua-tions at control stations. Indicator station data is also evaluated relative to background characteristics estab-11shed prior to station operation.

Tha media sampled are:

o AI = Air Iodine o FPL = Green Leaf y Vegetables o AP = Air Particulates o ID =

Immersion Dose (TLD) o AQF = Fish o M = Milk o AQP = Aquatic Plants o RW = Precipitation o AQS = Sediment o SW = Surface Water o E = Soil o V = Fodder Crops o FPF = Fruit o NG =

Milk (Goats)

The thermoluminescent dosimeter (TLD) program used by GPU-Nuclear meets the requirements set forth in the TMI Environmental Technical Specifications.

The TLDs are located such that at least two are situated in each 221/20 sector surrounding the TMI site, with one on the site boundary and the other 4 to 5 miles out from the site, for a total of 32. Additional TLDs are located in areas of interest (i.e., near more densely populated areas, etc.) . TLD identification nomenclature is based on both sector position and distance from the TMI site. During normal operations, accurate measures of the environmental dose can be made; during an accident situation time incremental and time integrated dose measurement can be made. Table 10 lists TLD locations.

2. National Weather Service (NWS)

The NWS will provide backup meteorological information (i.e., wind speed, direction and probability of upper air inversion) from several locations in the vicinity of the TMI Nuclear Station as listed below:

Revision 2 4.7-18 June 1980 Amendment 19

o Capital City Airport o Harrisburg International Airport o State Turnpike Authority - Harrisburg The NU$ will also institute emergency balloon runs to collect data upon request. Air stability determinations are also provided, with information received from

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weather stations in Pittsburgh; Washington, D.C.; Bing-hamton, NY; and Atlantic City, NJ.

3. Department of Enerav (DOE) Interanenev Radiolonical Assistance Plan l

The Interagency Radiological Assistance Plan (IRAF) was developed as a means for providing rapid and effec-l tive radiological assistance in the event of a peacetime

~

radiological incident. The IRAP provides a means whereby the participating Pederal agencies may coordinate

' their radiological emergency related activities with those of state and local health, police, fire and civil defense agencies.

To the extent that assistance under this plan is needed, requests for IRAP assistance vill be coordinated through the Bureau of Radiation Protection. Requests for this assistance will be initiated by the Emergency Director, Radiological Assessment Coordinator or Emergency Support Director. When notified of an emergency, IRAP will

- respond with equipment and personnel as required to' t

l assist in the performance of assessment actions. The resources available consists of, but are not limited to, the following:

o Portable radiation survey instrumentation o Mobile laboratory facilities o Personnel for supporting functions o Special transportation activities o Envirotunental monitoring teams

4. Bureau of Radistion Protection (BRP)

(a) The BRP maintains laboratory f acilities in Harrie-burg consisting of the following instruments or their equivalent:

o Gsama Spectroscopy - ND-4420 with NaI and Geli detectors.

o Proportional Counters - (1) Bechman Wide Beta, (2) Gamma products and (3) NMC-PC-4 o Liquid Scintillation - Becha'an LS-133 o Thermoluminescent Dosimetry - Panasonic UD-702D Reader 4.7-19 June 1980 Revision 2 Amendment 19

o The following additional instruments, or their equi-valent, are expected to be purchased in the near futures o Gamma Spectroscopy - ND-6620 (or equitalent) with 5 Intrinsic Germanium detectors o Thermoltatinescent Dosimetry - a second Panasonic UD-702D Reader (b) The ERP also maintains the following portable instruments and equipment, or their equivalant, for field use:

o Routine / emergency mobile laboratory with analyser.

o Routine monitoring van used for collecting Tlf s in the field.

o Eberline SAH-2 o Beta-gamma survey instruments o Air samplers o Respiratory Protection (c) Environmental monitoring is performed by the BRP as follows:

(1) TLD monitoring is performed at twelve (12) locations in the area of TMI. (Additional stations are planned for future install-ation.) These TLD's are routinely read either monthly or quarterly, depending on

. location; the frequency is increased during an emergency situation in which a radiological release is involved.

(2) Water samples are collected at three (3) locations on the Susquehanna River and t

analyzed on a monthly basis.

I (3) Milk samples are collected at two (2) local dairies and analyzed on a quarterly basis.

(4) Air samples are collected at two (2) locations and analyzed on a weekly basis.

(5) Fish and vegetable samples are collected and analyzed annually (July).

5. Offsite Emergency Radiological Assistance See Table 11 for additional emergency radiological assistance to Three Mile island from companies, util-ities and governmental agencies.

w Revision 2 4.7-20 June 1980 Amendment 19

4.7.7 Protective Facilities and Eculosen:

Persoucal protective action at IMI is a fune:1on of the nature of the hazard (i.e., preparing for a hurricane is somewhat different from preparing for radiological hazards). Preplanned responses to

' the basic hazards, high wind, flooding, earthquahms, and radiation exposure, are an integral part of the "X1 Emergency Plan and are detailed in other sections. A f undamental concept in personnel pro-tection is the immediate release and removal of all individuals not essential to the operation, safety, security, and damage control of the plant. Obviously some hazards can occur before asy significant protective sezion can be applied; an ea.:hquake for example. Men the situation permits positive action, the appropriate alarma are sounded and all personnel en the site either assume their assigned emergency responsibilities or prepara for evacuation.

The ~MI Uni: 1 Varehouse is the normal assembly point for all non-essential personnel outside the Protected Area in Unit 1. h is struc-ture is a pre-engineered metal building with a conventional ventilation system. 1: is normally zanned at all times. Respirators, protective clothing, and most other protective equipment for the plant are stored i= this warehouse. If required, personnel assembled at this point

' could be issued protective equipment from stored supplies. *darehouse yo. 2, located ves: of the Unit 2 Turbine Su11 ding is the normal aseeably p.res for all non-essential personnel outside the Protected Area in Outt 2.

' Protective facilities include the "MI Uni: 1 Control Room. D ia area is located in a seismically rated structure and has adequate shialding to permit safe occupation for extended periods of time without exceeding an exposure limit of 3 Rom. The Control Roca ventilation system has redundant fans and chillers and is provided with radiation and sacke detectors with appropriate alarms and in:erlocks. Provisions have been made for the Control Room air to be recirculated through high efficiency particulate (HEPA) and activiated charcoal filters. Tresh air is drawn

. through an underground ventilation :tz:nel which has been provided with protection against ccmbustible vapers, incipien: explosions or fires.

~he tunnel is Seismic Class 1 and is also designed for a hypothetical aircraf t accidest.

Scott air packs and respirators are located in the Control Room to perzir continued occupancy if ventilation systems fail. An extensive medical aid f acility is loca:ed belov the Con::cl Roca in the Health l Physics 1.ab.

4.7.8 71rs: Aid and Medical 7acilities First aid f acilities a: IXI are designed to support a vide range of 4===*iate care ranging from simple f t:st aid up to and including procedures requiri=g a physician. *he nos: readily available first aid is provided by s=all kits placed throu1;hout the plant. "hase kits contain 16 ite=s typically needed :o care for siner injuries. he next level of firs: aid equi; men: is found at firs: aid stations located in the folleving areas:

i Revision 2 4.7-21 June 1980 Amend =ent 19

A~ -- - .a, - - -4 .m. - - - - --, m-+- s.i --m-a'-- ,-a,.-.

o Unit 1 Circulating Puep House o Training Department Hallway o Unit 1 Health Physics area hallway o Unit 1 River Water Pump House o Industrial Waste Building o Warehouse No.1 north end at the receiving dock o Hallway in the Unit 1 Control Building These stations are equipped with sufficle' ; quantities of the following .

supplies to serve the expected needs of 100 employees o Stretcher l o ' Inflatable Arm Splint o Inflatable Les Splint o Utility Blanket ,

o Large Plastic Sheet o 100 Employee Size First Aid Kits Three specific areas in the TNI Nuclear Station have been set aside as first aid f acilities. In a medical amargency the particular facility used would depend upon (1) its proximity to the injured party, (2) the nature of the injury, and (3) the extent of the injury. An unmanned 4

• room is located in Unit 1 at the 305' elevation in the east hallway in the Service Building. This room is usually unlocked and is typically outfitted to support the aid that can be administered by personnel-qualified to the multi-media level of Red Cross training.

A first aid f acility is located in a trailer on the west side of the main roadway adjacent to the Unit 1 Air Intake. A State registered emergency medical technician sans this facility during normal working hours.

A special medical f acility is located in the Unit 1 health physics area at the 306' elevation to permit the treatment of contaminated /

I injured personnel. This f acility is normally lockad with keys main-

.tained at the Access Control Point and in the Control Room.

4.7 9 Damane Control Eautonent The TMI Nuclear Station is extensively equipped to conduct preventive maintenance and repairs on mechanical, structural, electrical, and instrumentation and controls equipment found in the plant. Operational policy provides a minimum maintenance crew assigned to the onsite shift organizations at all times. Each individual assigned to the maintenance crew is qualified and, when required, certified to perform the tasks associated with his craf t in the working environment of a nuclear plant.

In addition to the equipment and materials required for normal maintenance, other items are.available to handle extraordinary maintance jobs that might arise in damage control.

Selection of damage control equipment inventory is based upon (a)

Revision 2 4.7-22 June 1980 Amendment 19

I mitigating the consequences of flooding, (b) personnel rescue, (c) checking the uncontrolled flow of fluids from process systems, and (d) elimination of electrical hazards.

4.7.10 Radiological Control Equipment The 1MI Nuclear Station maintains an inventory of protective clothing, respiratory equipment, survey instruments and supplies to provide adequate contamination control for all personnel expected to be on-site who might be affected in the event of an emergency.

The supplies are maintained, updated, irrentoried and calibrated on a regular basis in accordance with applicable Health Physics pro-cedures. These emergency supplies, so :e in kit form, are stored:

1) in the Control Room /Shif t Supervisor's Office

2) at the Health Physics Lab / Access Control Point

3) in the Processing in Center

4) at Crawford Station

5) on the Fire Brigade Vehicle

6) in the Health Physics Vehicle

7) in the Service Building Auditorissa B) in the Unit 1 and Unit 2 Warehouses M

l 1

Revision 2 4,7-23 June 1980 Amendment 19 i

i 4.8.0 MAINTAINING DERGINCY PREPAREDNESS GPU Nuclear Corporation will mainta%n, as two separate documents, this Emergency Plan and the Emergency Plan Implementing Document. It is intended that this Plan, although considered a part of the Three Mile Island Nuclear Station Unit 1 Final Safety Analysis Report (FSAR), will be maintained as a separate document as suggested by the guidance provided in reference 4.10.4.

Efforts will be made to assure continuous emergency preparedness and operational readiness among GPU-Nuclear personnel and the of fsite response agencies and organizations. The Vice President-TMI 1 and Vice President-TMI 2 have been assigned overall responsibility for emergency planning related to the TMI Nuclear Station. This responsibility i

includes not only the TMI Esergency Plan and Implementing Document but also includes its interrelationship with State, federal, and county plans; agreement letters; corporate policy and plans; and other related plans, programs, and procedures. To assist the Vice President-TMI 1 and Vice President-TMI 2 in meeting their assigned responsibilities, an Emergency Planning Coordinator has been designated. The specific responsibilities delegated to the individual assigned as the Emergency Planning Coordinator are described in the following subsections and in particular, subsection 4 8.1.3.

4 8.1 Ornanizational Preparedness 4.8.1.1 Training All personnel at the Three Mile Island Nuclear Station will take part in a formal training program under the l

direction of the Manager-Training IMI-1. In general, this training program provides for the indoctrination of CPU-Nuclear employees and contractors in addition to providing specialized training for licensed operators, health physics / radiation protection personnel, and persotinel assigned specific responsibilities in the emergency organization.

P The Manager-Training TMI-1 is responsible for ensuring that personnel in each department receive the appropriate training. He may delegate specialty training responsi-bilities to personnel qualified to perform such training.

The training program for the TMI Nuclear Station with regards to the TMI Emergency Plan will include the following:

1. All Three Mile Island staff personnel, except personnel in the Operations Department, are required to attend the General Employee Training Program at least once per calendar year. In addition, the prompt ind octrin-ation ci new employees and contractor personnel is provided for in the Health Physics Training Program which they are required to attend prior to receiving  ;

the privilege of unescorted access onsite. With '

i

- Revision 2 4 8-1 June 1980 Anendment 19

o these programs are to: regard to essergency plannin a.

Pamiliarize personnel with the scope , applica-Plan and implementing Document.bility, ency

- b.

Teach the general duties and responsibiliti assigned to all M personnel. es c.

Keep personnel informed-of any changes e in th TMI Emergency Plan and/or the Implementing Document.

d.

levels of the TMI Nuclear Station on.

or To meet these objectives, each TMI Nuclear ation St receive, as a minimum, the following a.

and the Implementing Document. encyOrientatio Plan b.

of the W Emergency PlanOrientation a on in the im ment of duties and respons,ibilities, location ofinc emergency centers and assembly facilities , and the location where of emergency eqaipment and applicable. supplies, c.

with regard to the use of emergency and equipment, s ities fandiarization with station alarms and personnel response, and the use of <

. general station com=mications systems.

d.

Orientation in instructions and requirement s associated with personnel accountability ,

evacuation, and exposure criteria. ,

e.

Orientation in radiation protection with pem h asis equipment, and personnel dosimetry.on th ,

2.

GPU-Nuclear TMI Station and Station Support Organization personnel assigned to the ncy emerg responsibilities will receive specialized their respective assignments. or which personnel vill receive specialized traininTable 12 deli g, the 1

type of such training, and the mini:num require d f training.

- requency of l Revision 2 4.S-2 June 1980 Asend=ent 19

- - , - - - ~

3. Ihe Pennsylvania Emergency Management Agency (PEMA) develops, conducts, coordinates, and promotes a training program throughout the State and assists the l counties in developing training policy for disaster operational readiness. The county and local EMA Coordinators are responsible for planning and conduct- ~

ing di'saster preparedness training of respective emergency response personnel. GPU-Nuclear will work 4

~

closely with PEMA and the county and local Emergency '

Management Directors in coordinating training programs.

In addition, orientation and training of State and county agencies and personnel involved in TMI emergency planning afforts will be made available by GPU-Nuclear.

a. The energency management organizations listed below will be invited, on at least an annual basis, to participate in a training program at the TMI Nuclear Station. The program will relate

' the importance of effective planning for emergency situations and interfaces between the Lices.see's emergency organizations and the of fsite (i.e.,

State, county, and federal) emergency organiza-tions. The program will also include a review

• of the TMI Emergency Plan and Implementing Document with particular emphasis given to the classification of emergencies; reporting requirements; assessment, protective, and corrective actions; and communications networks.

(1) Pennsylvania Emergency Management Agency 1 (2) Dauphin County EMA (3) York County ENA (4) Lancaster County EMA (5) Cumberland County EMA (6) Lebanon County EMA

. b. At least annually, the State Bureau of Radiation Protection will be invited to participate in a l training program at the TMI Nuclear Station.

The program will, as does the program for the civil defense organizations, relate the importance of effective planning for emergency situations, the interf ace between the Licensee's emergency organizations and the offsite (i.e., State,

[

county, and f ederal) emergency organizations.

The program will include a review of the DiI Encrgenc.y Plan and Implementing Document with particular emphasis given to the classifica-tion of emergencies; reporting requirements; assessment, protective, and corrective actions; and communications networks. In addition, w Revision 2 4.8-3 June 1980 Amendment 19

e specific training on dose calculations / projections, protective action guides, and reportable informa-tion will also be prwided.

c. The State Police will, on at least an annual basis, be invited to participate in a training program that will include a review of the applicable parts of the M Baergency Plan and Implementing Document with emphasis on the classification of emergencies, communications, and specific areas of responsibility.

4. GPU-Nuclear will also provide orientation and training to local services support organizat' ions as specified in respective letters of agreement and as required to ensure a high state of emergency preparedness and response capability between these organizations and the M Nuclear Station emergency organization.

The local services support organizations and personnel who may provide onsite emergency assistance will be encouraged to become familiar with the M Nuclear Station (including the physical plant layout) and key station personnel, and will be invited to attend

• Emergency Plan orientation and training courses conducted by or for GPU-Nuclear. It is anticipated that such training will be provided on at least an annual basis and will be made availaBle to the appropriate personnel of the following organizations and certain specified individuals.

v

a. Middletown Police Department The Middletown Police Department will be invited to participate in a t. raining program that will include a review of the applicable parts of the M Emergency Plan and Implementing Document with emphasis on the classification of emergencies, communications, and specific areas of respon-sibility.

b. Fire Companies The local fire and rescue companies will be invited to participate in a training program that will, as a minimum, include the following topics:

(1) Interf ace with the Site Security Force during emergencies.

(2) Basic health physics indoctrination and tr aining .

Revision 2 4.8-4 June 1980

_ Amendment 19

i (3) TMI Nuclear Station facility layout.

(4) Onsite fire protection system equipment (permanent and portable).

(5) Differences between onsite firefighting equipment m and fire company supplied equipment.

(6) Communications systems.

(7) Review of applicable parts of the TMI hersency Plan and Implementing Doceent.

(8) The onsite emergency organization with specific emphasis on the interf ace between the TMI Fire Brigade and Fire Company personnel.

c. Barshey Medical Center, Local Physicians, and Fire Company (listed above) Ambulance Services The local medical support organisations and personnel vill also be invited to participate in a training program that will, as a minimum and as applicable, include the following topics:

(1) Interface with the Site Security Force during emergencias.

(2) Basic health physics indoctrination and training (3) TMI Nuclear Station facility layout (4) Onsite medical treatment facilities, equipment, and supplies (5) Communicatioca systems (6) The onsite emergency organization with specific emphasis on the interf ace between the TMI Pirst Aid and Rescue Team (s), the local medical support v personnel, and Radiation Management Corporation.

(7) Radiological aspects of emergency medical treatment.

l (8) TMI Nuclear Station procedures for decontamination.

l (9) Hershey Medical Center radiation emergency procedures.

(10) Training in first aid and transportation techniques for contaminated injured individuals.

4.8.1.2 Drills and Exercises Periodic drills and exercises will be conducted in order to test the state of meergency preparedness. The prime objective of this form of training is to verify the amargency preparedness of all participating personnel, organizations, and agencies. Each drill or exercise will be conducted to: (1) ensure that the participants are familiar with their respective duties and responsibilities, (2) verify the adequacy of the TMI hersency Plan and the methods used in the Emergency Plan Implementing Procedures, (3) test communications networks and systems, (4) check the availability of emergency supplies and equipment, and (5) verify the operability of emergency equipment.

The Ehergency Planning Coordinator will be responsible for the planning, scheduling. and coordinating of all emergency w

Revision 2 4.8-5 June 1980 Amendment 19 i

i l

planning related drills and exercises. The Manager-Training TMI-l will assist the Emergency Planning Coordinator in carrying out these responsibilities. However, all drills

, and exercises are subject to the approval of the Manager Unit 1. In addition the Vice President-TMI 1 shall approve the nunual Radiation Emergency Exercise.

When a major drill or exercise is to be conducted, the Emergency Plannfrg Coordinator will:

1. Assign personnel to prepare a scenario.

2. Coordinate af forts with other participating emergency i' personnel, organizations, and agencies.

3. Obtain the approval of the Manager Unit 1 and (for the annual Radiation Emergency Exercise) the Vice President-TMI 1.

4. Schedule a date for drill execution and arrange for qualified observers.

5. Critique the results of the drill. -

6. Assign personnel to correct any deficiencies.

7. Ensure that deficiencies are corrected.

8. Prepare and submit documentation to the Training Department for recordkeeping.

Scheduled drills and exercises will be held involving appropriate of fsite as well as onsite emergency personnel, organizations, and agencies. These drills and excercises will be conducted, simulaties as closely as possible, actual emergency conditions and may be scheduled such that

_ one or more drills or excercises can be conducted simulta-

. neously. Drill scenarios will be prepared that involve participation of several emergency teams and all or specific parts of the onsite and of f aite emergency organizations including varying degrees of participation of State, county, and federal agencies and organizations and local services support personnel and organizations. The scenarios will include the basic objective of each drill and exercise, dates, places and times of participating organizastons, simulated events and a time schedule of real and simulated initiating events. Additionally, the scenario shall contain a narrative stammary describing the conduct of the exercises or drille to include such things as simulated casualties, of fsite fire department's assistance, r uscue of personnel, use of protective clothing, deployment of radiological monitoring teams, and public information activities, i

The Emergency Planning Coordinator will normally notify the of fsite emergency response organizations and agencies at least thirty days in advance of the the scheduled date

(

of the drill or exercise.

A critique shall be scheduled and held as soon as practical af ter securing from a drill or exercise. Observer and participant comments will be given to the Emergency Planning Revision 2 4. 8-6 June 1980 Amendment 19

I Coordinator, who is responsible for coordinating proposed revisions to the TMI F:nergency Plan and the Implementing Document, and the upgrading of emergency equipment and supplies. The Es'ergency Planning Coordinator will submit such recommendations to the Vice President TMI-1 for review.

Recommended changes that are approved by the Vice President TMI-1 shall be incorporated into the Emergency Planning Program under the direction of the Emergency Planning ,

Coordinator. A formal evaluation will be prepared from each '

critique and will be maintained on each drill listed below.

Major drills and exercises will be conduct.ed as described.

1. Medical Emergenev Drill

a. At least one drill every 12 months (13 months) shall be conducted. TPe drill vill involve the participation of some, if not all, of the local medical support personnel and organizations (e.g., physician, ambulance service, hospital, etc.), and will involve simulated cases of contaminated personnel.

2. Fire Emergenev Drill

a. At least one drill per calendar quarter shall be conducted.

b. At least one drill every 12 months (13 montasi shall involve the participation of at least one, if not all of the local f tre departments.

~. c. Drills shall be in accordance with plant Technir.d Specifications.

3. Repair and Damage Control Drill

a. At least one drill every 12 months (13 months) shall be conducted to exercise the Emergency Repair Team.

4. Communications Links Test

a. At least once per month the communication links with State and local governments within the 10 mile EPZ shall be exercised.

b. At least once every 12 months (t 3 months) the communication links with Federal emergency response organizations and States within the 50 mile EPZ shall be exercised.

c. At least once every 12 months (13 months) the communication links between the nuclear facility, State and local emergency operations centers and field assessment teams shall be exercised.

Revision 2 4.S-7 June 1980 Amendment 19

5. Radiological Monitorina Drill

a. At least one drill every 12 months (i 3 months) shall be conducted. The drill shall include collection and analysis of all appropriate sample media for both onsite and of fsite locations.

6. Health Physics Drill At least one drill shall be conducted semi-annually.

a.

The drill will involve response to, and analysis of, simulated elevated airborne and liquid samples and direct sediation measurements in the environment. The drill shall include analysis of inplant liquid samples with simulated elevated activity levels. -

7. Radiation Emergency Exercise

a. A maj or drill sppropriate to a Site or General Emergency shall be conducted at least once every 12 months (1 3 months).

b. Conduct of the exercise shall include mobilization of on- and off-site emergency response personnel and resources in order to verify the capability to respond ;o an accident scenario. Communications with State and county agencies will be included.

The scenario will be varied from year to year such

+

that all major elements of these plans, personnel.

and resources are tested within a five year period. These annual exercises will be staggered; some will started between 6:00 p.m. and midnight or between midnight and 6:00 a.m.

(1) At the request of the State, the above exercise may be conducted as part of the State's annual exercise which is described in Appendix 14 to'the Commonwealth of Pennsylvania Disaster Operations Plan Annex E, Fixed Nuclear Facility Incidents.

In this case the Pennsylvania Emergency Management Agency can bu expected to be the Lead Agency.

4.8.1.3 Emerzenev Planning Coordinator A member of the TMI Nuclear Station staff will be designated as the Emergency Planning Coordinator. His responsibilities shall include, but not necessarily be limited to:

1. Ensurias the coordication of the TMI Energency Plan with the:

Revision 2 4.8-8 June 1980 Anendment 19

l

a. State plans (reference 4.10.22 and 4.10.23)

b. County plans (reference 4.10.24 through 4 10.28)

c. TMI Security Plan

d. GPU-Nuclear Energency Public Information Plan

2. Ensuring that the information, data, and procedures detailed in the Emergency Plan Implementing Document are consistent with the guidance provided in the TMI Emergency Plan.

~

3. Ensuring that the Emergency Plan Implementtag Procedures  ;

are coordinated and interf ace properly with other procedures (e.g., Administrative Procedures, Security Procedures, Health Physics Procedures, and Training Procedures, etc.) .

4. Assisting the Manager-Training IMI-l in coordinating and/or providing emergency planning related specialty training.

5. Coordinating emergency planning related drills and exercises as described in subsection 4.8.1.2 above.

6. Coordinating the review and updating of the TMI Emergency Plan and Implementing Document as described in Section 4.8.2 below.

7. Ensuring the maintenance and inventory of emergency equipment and supplies .. described in Section 4.8.3 below.

m

,'. 8. Maintaining himself current with respect to changes

( in federal regulations and guidance that impact emergency planning activities.

4.8.2 Review and Updating of the Emergenev Plaft and Implementina Document The TMI Emergency Plan, including appended letters of agreensent and plan of of f site or3anizations and agencies, will be reviewed and updated on at least an annual basis.

The Quality Assurance Department is responsible for the period of activities, and for auditing, at least once every two years, the TMI Emergency Plan and Implementing Document to verify compliance with the l

Operational Quality Assurance Plan, the Fire Protection Program Plan, interne1 rules and procedures, federal regulations, and operating license provisions. This audit vill be conducted pursuant to che procedures and methods set forth in the Operational Quality Assurance Plan. In addition, the Emergency Planning Coordinator will by virtue of his involvement with the it.. Emergency Planning Program, provide an ongoing review. Personnel performing revieva or audits of the TMI Emergency Plan and/or Implementing Document shall take into account l Corporate policy, State policy and plans, county plans, and the various agreements and understcoding with federal, State, county, and local support agencies and organizations.

~

Revision 2 4.8-9 June 1980 Amendment 19

9 As previously mentioned, the TMI Emergency Plan is considered a part of the IMI Nuclear Station Unit 1 FSAR. As such, revisions to the Plan shall be administratively controlled by utilizing existing methods which are used in making amendments to the FSAR.

The TMI Emergency Plan implementing Document will be incorporated into the TMI Nuclear Station procedures program. As such, the Imple-

' menting Document will be prepared, reviewed, approved, concrolled, distributed, and revised in accordance with TMI Nuclear Station Administrative Procedures. Doctament holders (e.g., GPU-Nuclear, State, county, federal agencies, etc.) vill receive revisions to the Emergency Plan Implementing Document in a controlled manner as they are issued.

The Et ergency Planning Coc.dinator is responsible for coordinating the pettodic reviews and audits of de TMI Emergency Plan and Implement-ing Document. In addition, the Emergency Planning Coordinator shall, through letters, meetings, seminars, or other means available, ensure that all elements of the total emergency organization (e.g. GPU-Nuclear, State, federal, county, etc.) are informed of the TMI Emergency Plan, the Implementing Document and revisions thereto.

Results of each annual review and update will be reported to the Vice President-TMI 1.

4.8.3 Maintenance and Inventerv of Emerstenev Equiument and Sucolies Designated emergency equipment and supplies and their storage locations will be listed in the Emergency Plan Implementing Document. Such

~

equipment and supplies will be maintained, inventoried, inspected and calibrated in accordance with approved IMI Nuclear Station procedures.

Equipment, supplies, and parts having shelf-lives will be checked and replaced as necessary.

Any deficiencies found during the inventory and inspection vill be ei-her cleared immediately or documented for corrective actidn.

A report of each inventory and inspection, including documented deficiencies, will be prepared and submitted to the Emergency Planning Coordinator. The Emergency Planning Coordinator will ensure that cognizant department heads assign personnel to correct deficiencies and i

shall ensure that identified deficiencies are corrected in a reasonable period of time.

Revision 2 4.8-10 June 1980 Amendment 19 l

l t

e 490 Rg;OVERY The Emergency Director and Emergency Support Director have the joint responsibility for determining and declaring when an emergency situation is stable and has entered the recovery phase. They will evaluate the status of the emergency by observing monitoring instru-mentation and reviewing all current and pertinent data available from emergency response and/or monitoring teams. They shall consider the emergency under control and in the recovery phase only when the following general guidelines are met:

e Radiation levels in all in-plant areas are stable or are decreasing with time.

e Releases of radioactive materials to the environment from the plant are under control or have ceased.

• Containment pressure is at normal- levels.

e Reactor plant is stable and in a long term safe shutdown condition.

e Any fire, flooding, or similar emergency conditions are controlled or have ceased.

Although planning for recovery will vary according to the specific nature of the emergency situation, a long-term recovery organization that is general in nature has been defined. This organization is w

described in subsection 4.5.1.5 of this Plan.

During recovery operations, the radiation expc:suro limits of 10 CyR 20 shall apply. Compliance with those limits shall be the responsibility of the Recovery Operations Manager via the applicable halth Physics organization at the time of recovery.

• At the time of declaring that an emergency has entered the recovery phase, the Emergency Director shall be responsible for providing noti-fication to all applicable agencies (e.g., federal, State, and county agencies, etc.) that the emergency has shif ted to a recovery phase.

Recovery actions that plan for or may result in radioactive release will be evaluated by the Recovery Operations Manager and his staf f as far in advance of the event as is possible. Such events and data pertaining to the release will be reported to the appropriate of f site emergency response organization and agencies.

Estimates of total population exposure will be made periodically as required. Calculstions for airborne releases will be done in cecordance with Reg. Guide 1.111 and for Liquid releases in accordance with Reg. Guide 1.119. Dose calculations are based on guidance in Reg.

Guide 1.109.

- Revision 2 4.9-1 June 1980 Amendment 19

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4.

10.0 REFERENCES

4.10.1 Title 10, Code of Federal Regulations 4.10.1.1 Part 20, Standards for Protection Against Radiation 4.10.1.2 Part 50, Licensing of Production and Utilization Facilities 4.10.1.3 Part 50, Appendix E, Energency Plans for Production and Utilization Facilities.

4.10.1.4 Part 100, Reactor Site Criteria 4.10.2 USNRC Order and Notice of Hearing, Dockat No. 50-289, dated August 9,1979 4.10.3 Section 13.3, Emergency Planning, of Regulatory Guide 1.70, Revision 3, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants 4.10.4 Regulatory Guide 1.101, Revision 1 da'ted March 1977, Emergency Planning for Nuclear Power Plants 4.10.5 NUREG-75/087, Revision 1 USNRC Standard Review Plan 4.10.5 1 Section 9 5.1, Fire Protection Prograa 4.10.5.2 Section 13.3, Emergency Planning 4.10.6 Regulatory Guide 1 97, Revision 1 dated August 1977, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident 4.10.7 US Environmental Protection Agency Manual EPA-520/1-75-001, September 1975 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 4.10.8 NUREG-0396, EPA 520/1-78-016, November 1978, Planning Basis for the Development of State and Local Government Radiological Emergency Response i

Plans in Support of Light Water Nuclear Power Plants 1

4.10 9 Federal Radiation Council Report No. 7, May 1965, Background Material for the Development of Radiation Protection Standards 4.10.10 National Council on Radiation Protection Report No. 39, January 15, 1971, Basic Radiation Protection Criteria 4.10.11 ANS-3.2/ ANSI N18.7-1976, Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants 4.10.12 Regulatory Guide 1.120 (for comment), Revision 1 dated November 1977, Fire Protection Guidelines for Nuclear Power Plants 4.10.13 Three Mile Island Nuclear Station Operating License No. DPR 50 (Docket No. 50-289), including:

Revision 2 4.10-1 June 1980 Amendment 19

4.10.13.1 Appendix A. Technical Specifications (Safety) 4.10.13 2 Appendix 3, Technical Specifications (Envirotsmental) 4.10.14 Regulatory Guide 1.16, Revision 4 dated August 1975, lepo;; ting of Operating Information - Appendix A, Technical Specifications 4.10.15 NULEG-0578 (extracts), July 1979, T-2 Lessons 1.aarned Task Force Status Report and Short-Tern Recossendations 4.10.16 NURIG-0600 (extracts), Investigation into the March 28, 1979 Three Mile Island Accident by Of fice of Inspection and Ts.dorcement, dated August 1979 4 10.17 nree Mile Island Nuclear Station Final Safety Analysis Report

. 10.18 USNRC Information Repor SECT-79-450, dated July 23, 1979, Actier. Plan for Promptly Improving Emergency Reparedness 4.10.19 NRC Emergency Planning Review Guideline Number One - Revision One -

Emergency Planning Acceptance Criteria for 1.icensed Nuclear Power Plants, dated September 7, 1979 4.10.20 NUREG-0610. USNRC Draft Emergency Action Level Guideldmas for Nuclear Power ?lants, dated September 1979 4.10.21 Proposed :ule change to 10 CPR 50, Appendiz E, ?mergency Planmd,g and Preparedness for Production and Utilization Pacill:1es, published in the Federal Register on August 29, 1979 4.10.22 Commonwealth of Pennsylvania Disaster Operations Plan, Annaz I, Pixed Nuclear Pacility Incidents, dated March 1980 4.10.23 Department of Enviro:ssental Resources, 3nreau of Radiation Proceetion Plan for Nuclear Power Generating Station Incidents, dated January 1980 (Rev. 1) 4.10.24 Dauphin County Of fice of Emergency Preparedness, Action and Response Plan for Emergency Personnel and Citizens, dated March 1980 4.10.25 Tork County Protective Action Plan for the Three Mile Island Nucles:

Power Plant, dated March 1980 4.10.26 ' ancaster County Emergency Evacuation Plan *hree Mile Island, dated March 1980 4.10.27 Cunberland County "hree Mile Island Emergency Response Plan, dated March 1950 4.10.2S Lebanen County Emergency Management Agency, Emergency Operations Plan, 1 Radia:ien Incidents hree Mile Island Nuclear ?over Plant, da:ed March 1950 Revision 2 4.10-2 June 1950 Anendnen: 19

. 4.10.29 Three Mile Island Nuclear Station Procedures i

4.10.29.1 Administrative Procedures 4.10.29.2 Radiological Controls Procedures 4.10.29 3 Emergency Procedures 4.10.29.4 st ..,;ty Procedures 4.10.29.5 Alarm Response Procedures 4.10.30 NUREC-0654 FEMA-REP-1 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, dated January 1980.

4.10.31 Pannsylvania E=ergency Management Agency, U. S. Census Bureau 1970 figures.

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Cit 95)MICAT1suas CEssCT MANACDtf MT -

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g Amendment 19

, .- -. p--..%-,-- , - . . . - . . , ~ . _ - - - . . . - , . - - . . , - . , . . , . . -

w -.y . . - . - - . v.-.- , , . -.,.m- , . - - - . _.%, , . - - . , - - , - , - - - - ,

Cm 3 Assumptiens Used in Calculating Doses in Ficures ti and *2 Power Level (Mwth) 2535 Fraction of ::ccie Oas Inventory Reisased to Containment (T::-143441 1. 0 Fraction of Irdine Inventory Released to Containment ;T:3-14344) 0.5 Fraction of 0:ntaan=ent *cdine Plat =J Cut (T*D-14844) 0.5 Sprayed volume (ft A) 1,430,000.

Unsprayed Volume tf t") 700,000

odine Composition Frac icns Organic 0.04 Particulate 0.05 Elemental 0.91 Spray Removal Rate 0:nstants for cdines (hr *i*)* -

Organic 0.

Particulate 0.4 Ilemental 10.0 Air Flow between Sprayed and *.*nsprayed volumes (cf=) 54,000.

(Value as 2.inL=== cperation value)

Centain=ent LeaX Aate 0 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (percent per day) 0.2

> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (percent per day) 0.1 Dese Model -- R01.109 (Rev 1), intalatten dose based en :tild

ayr:Ad 31spersten n del -- R01.4, A = 2000m*

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Amendment 19 l

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l u. , t o. . . . - Figure U s,,__ w = -_-n -m--~_ =~== , _ = _ = _u_ =-- 1: = n_ w - ==w = = == =~ - = - =

s.... g- :..f R2_K

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- - . - _M- -Fi - _M . . _U._. - . Exposure Rate (R/hr) b 5 .-- l s....

a: "L,-1 De=e ---

Moni:or :.ocation

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• nside Moni:or PR.

= _

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m = m _ -._x---- - _- _ .. - ___

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.... in Con:ain=en:

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p = - w w === =:_ - n = = = =_ j _ eg*#

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(heurs post-3 .e -l shu tdeten) t.

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e e e Amendment 19

~

TA2*.1 1 MA.70R PIS!DICIA*. AEAS

? OPT ATION CECIP3 GPIA'"IK '"HAN 500 k.. .IN A 5-CLI RADIUS OF TEI S!TI AEAS POPT ATION DIS *ANOI AIC DIREC" ION FEDM SITE Goldsboro 576 1.5 miles W York Haven 671 2 miles S Royalton 1040 2.5 miles N Middletown 9080 4 miles N PDPT CION CICERS CEA~IE '"HAR 2000 k*ITEIN A 10-MILE PADIUS OF THE SITE ARIAS POPT ATION DISTANCE AND DIREC ION TROM SITE Middletown 9080 4 miles N S:eelton 8555 6 miles m' Eli:sbethtown 8072 6 miles ISE Highspire 2946 7 miles NW

, POPT ATION CICIRS GEA~IR !":1AN 10.000 WITHIN A 40-F"' RADIUS OF TE ST AEAS POPT ATICN DIS *ANOI AND DIEC" ION TROM SI*I Harrisburg 68,061 12 miles NW York 50,335 14 miles S

, Columbia 11,237 15 miles SE Lebanon 28,572 20 miles NE Lan:as:e: 57,690 25 miles ESE Carlisle 18,079 27 miles W Hanover 15,623 29 miles SSW No:e: Popula:ior. approxi= ate.

See reference (4.10.31)

Revision 2 Page 1 of 1 June. 1980

_ - Amendment 19 I

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

.i~ ,

( ( e TABLE 2 SCIHMil.S I.OCATEI) WITillN A 10 HILE RAlllUS OF THI Al'rRuR illAI E SC1393l. AREA DISTANCE (ill). ENitol.lJIEH F painterlilge Elcmentary Ris inle s-lilge 5.5 2f=2 Falaview Ele =cutary E t i entie t h t owie 7.5 184 East liigli St . Elementary Eli mnhet lit own 6.0 riiplar St. Element nr y 779 Elienhethtuwn 6.0 241 l Ell:.ahi tiet owei liigli School El i zalici +e t owei 6.5 i St . retern School 1817 l

El l e nbe t ht owie 6.5 fe9 Honen t Calvary School Eli anhet let owei 6.5 IIA rilII Honal Element nry El i zalec t ht own 8.0

, Elimnbethtown College 154 El i c alec t ht own 7.5 1732 113 I Ia isle Eleinent ery Hew CumherIanil 9.0 484 New Cumberlanet Hiilille School New Cumberlanel 9.5 686 St. 1herena Elementary New Cussleerlanil 9.5 141 Nor t heng t Scesior liigli School Manchester 7.0 Nor t heng t Junior High School 910 Manchester 7.0 531 Hanrhent er Elcoment ney llanchenter 7.0 124 0: notori Element ery Hancliester 7.0 597 i

York II evesi - Newberry Elesmentary York Havese 3.0 177 i fit . Woll Element nr y Hount Wolf 6.5 313 Conawago Element nry Canawago 7.5 420 Finleing Creek Elementary 1,cwieberry 7.5 622 1 Newberry Elementary Ettere 1.5 504 He. 7.lon Elementary I.ewieberry 7.5 i, 283 Fairview Eleiecntary New Unsherlanil 9.0 251 R 1 1.anil liigli Sclinal f.ewleherry 7.5 132)

See reference (4.10.31)

Revision 2 rage I of 2 June, 1980 u

n 4

i

g .  :

TABl.E 2 SClKMil.S l.0CATED WITil!N A IU Hil.E RADIUS DI' THE ArrstuX1 HATE SClHM)l. AREA DISTANCE (MI) ENNUI.l. HEN T j inwar Blauplain School pintrict lla r r i nInur g 9.5 4t192

! Hilton Hernhey School Hernhey 10.0 1448 ninhop ficilevitt liigle School liarrinburg 9.0 1705 Ilarriphurg School Ipinarict finrrinhurn 9.5 11814fl riiddletown Arca School Hi nt r ict Middletown 2.5 3149 St eciton-Highnpire School llint rict St ee t t on-liighnpi r e 4.0 2 tott Hon t licast Yo k Count y School Dint rIct He. WolI 5.0 3270 St . .lohn's Element ar y Enhant 5.0 109 Holy FamiIy Elementnry HarrInhurn 9.5 305 lloly Hame of .lenus Harrisburg 9.5 393 our I.ady of the Blessed .iaernment Harrinburg 9.5 309 Sacred Hantt H:tr r istner g 9.5 250 St . Catherine f.nhoure Harrisburg 9.5 270 St. Francis of Assini lla r r i nInorg 9.5 288 1he Cathederal School llarrisburg 9.5 184

! Si . Hargaret Hary Harrisburg 9.5 493 St. Joan of Arc Elementary Hershey 10 328 Seven Sorrown R.V.H. Elementary Hiddletown 2.5 246 Anninaptlon of tlie n.V.H. Elementary Steciton 4.0 ISR Dinhnp Neuman Steciton 4.0 19)

St. Peter's Steelton 4.0 81 renn st at e teniverni ty (Capi tol Un= pus) Hiddletown 3.5 2006 tiilton Hernhey Hedical Center Hernhey 3.0 300 llar rinburg Area Comminiit y College Harrinburg 9.5 4400 i

Sec reference (4.10.31) g Revision 2 l' age 2 of 2 June, 1980 0

n.

g -

( l 1

j TABl.E 3 i

ii0SPITALS LOCATED WITilIN A 10 Mll.E RADIUS OF THI Hospital Area Distance (MI) Employment Patients

! Community General Osteopathic Itospital liarrisburg 9.5 400 180

, Milton liershey Medical Center tiershey 10.0 1123 350 Elizabethtown State llospital for Crippled Children Elizabethtown 6.0 250 100 See reference (4.10.31)

)

I g

8 i &

B n

4 i 1

Revision 2 p,g, 3 og g June, 1980

o B

TAB

• I 4 PII*.IK! 0F IJLND USID BY COUNTY USI D4UPHIN YORK 'NR Jo:est 4 Woodland 45.2 22.6 13.7 Crops 31.9 49.8 62.5

. Past-re 4.8 10.1 9.4 Urban 8.6 6.5 7.8

• Ja:er Area .6 .4 4 Tederal .2 .2 .1 Other 8.7 10.4 6.1 l

l See reference (4.10.31) l Revision 2 Page 1 of 1 June, 1980 Amendment 19 s

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

i k

2 l

M m

~

m =-

L ce 4=ge 4 =e => s%

e 4

• 2 w

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ee==o mse o '

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i

. 3 3

I a

=-

2 23 3

.2 M w

I2

. .I 22233g2 33- 2 22 22 2222223232 22222222.2

==

=

3 ....

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• 5 3 3= at - w w g ==5

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==

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532 zz

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• . e .e = = a = .

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S J =, . . : s -.C3 . = S

• 3 *

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su 3 7 3ky L.

=

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t us n  :

• w e w = 3 4 s 2 = a 3= .= * = = t h :  ?

3 = z w= => n u .M ea .% =

m z. s==u J, u : n 3 .E = : : . 3 . w aw= s - 3 : :3 s

.i: *

=

N

=  : u  : = w  : .

>8 2 3 s t h4=J S 24 =J s-  : 3 =- .

3 4

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h 3 : sa- a 3 a a 2 324 .1 a==J t w .

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b 3 J .s Jag=..J~

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.= == - - =

2 = . su- : L.-2 Ta 7  :  : J 3

-

4 . -. . s 3 : s : 4 .

E v -m  := . . A= 7 2T ; J -. s a

^

e T = 3 1 T 1 9 1 m 3 1 g

. L.=4 t o 2 aL : 1 0 J 4. =: = E 1 . 3 3 . >

E S E =3 = L M = = *J = =  %= 1 1 3 . > t == =J s ; = 2  ; . t=  ; '. O s -

%L-= 4 =4 = 4 ====43 2 *M 4 X = Z z 4

A=e=e=e=: 19 l

i

e TA31.E 6 AO:!')IN" O.'.ASSITICA!!ONS ACCIDENT EMERGENCY C;. ASS

1) Uncompensa:ed Opera:ing Reactivity Changes Dausual Event

) Startup Accident i Unusual Event

3) Rod Withdrawal Acciden: at Rated Power Operation Unusual Event

4) Moderator Dilution Accident Unusual Event

5) Loss of Coolan: T1ow Unusual Event

6) Stuck-Out, Stuck-In, or Dropped Con:rol Rod Acciden: Unusual Event

7) Loss of Electric Power Dousual Event

8) Steam Line Failure Aler:

_ 9) Steam Genera:or Tube Tailure Site Emergency l

10) Fuel Hand. ling Acciden:

Site ?mergency

11) Rod Ejec: ion Accident Alert

12) loss of Coolant Acciden: Site Emergency

13) Maximum }!ypothetical Acciden:

General Emergency

14) Waste cas Tank Rupture i

Ceneral Imergency l

l l

l l

l a.

Revision 2 Page 1 of 1 June, 1980 Amendment 19 e

o

f

Tuu

IKa.a.r1.5 TOR A;;'E N* DCTECTION ACCIDEK* INITEUND T5 FOR WTECT205 i 1. Un

ompensated Operating 1. Raaster Average Temp.

Raattivity Changes 2. Bet Leg Temp.

3. Cold Leg Temp.

4. Power Reage Monitor

5. Reacter C 1=at Pressure I

(

! i

2. Startup Accident 1. Source Raage Monitor

2. Ramster Average Temp. s

3. Reacter Coelmat Freneure

4. Eet Lag Temp.

3. Rod Withdrawal Accidust 1. Est Leg Temp.

at Rated Power operation 2. Reacter Pressure 3

3. Power Range nooiter w

4. Moderator Dilution 1. Power Range Monitor Accident 2. Reaster Coolest Pressure

3. Equipment Status Lights (i.a'. Talve Pesities)

4. Pressuriser Level i

5. Loss of Coelent Flov 1. Total naaster Flow

2. Loop T1 w

6. Stuck-out, Stuck-in or 1. Power Range Monitor Dropped Control Rod. 2. Reactor Average Temp.

3. Reactor Pressure

4. Centrol Red Positien ladisaties

- Resision 2 Page 1 of 3 June 1MC Amendment 19 l

,e----. . - - - - , - - - - .,,-,--.-,,-,,--,,,,,,,.,-_-,_,-,-,,-,._,,..-,,,.,,---,,,,,,--w.en__,,,,.-_,,,,,,,,.,,_,,,,.,,,.,,,,---,.,e

,.,,.-,,-,.n. ,,. - , - ,v wgn ,, -m,---,

AI_! -

. !NF 1"MI*: S 70; A001:IC II IO !:K A *.0*OIC IN!*I"MI CS FOR Of*I.T.0K l

7. :. ass of Power 1. != plan: bus vol meters

2. Swit:hyard bus vol: meters L

5. 3:ec :.ine Tailure 1. Mai: S:aan h easure

2. 5:aam Genera:c; *evel

3. Raa ::: kolas: Pressure I. . Power lange honi:::

9. 3:eam Genera:o; 1. Raa:: : solan: h easure Tube Tai 1=e 2. S:sas Genera:or 1evel .

3. Condense: Izhaus: A:mospheric honi:o;

_ 10. Tuel Handli=g A:: ides: 1. Tuel Rand'.ing 1:idte Am.

Radia:ic Moniter

. Fuel hM1ing 3 ridge Main Radia:ie: Moti:or

3. Tuel Eamdling Suilding A:me-spheri: hesite a . A= . & Fuel Handling 31dg. S:s:k

11. Red Ije::le: A:: ice:: 1. Power la=ge accite

2. lea:::: helas: M easure l

3. Press.rize *evel .

i

a. leas:=: 3cilding hasacre

(

1 t

l Revisica 2 Page : ef 3 Ju=e 1930 A=,2 en: 19 s

I

TA1'_I 7

. INS 2"MICI ?OR A:0 SI C DI I:"!!CX A ::DIC IKS*1L" MICE FOR St t: 10N

11. 1.oss of Coolan: 1. Raa::or 3uilding Pressure

1. Raa:to: Coolan: Pressure

3. Raactor luilding 11 lange Radiation Monitor

4. Raatter Building Sta k A:me-shperic Monitor

13. .Maximus Hypo:hetical 1. Reactor Building Pressure

2. Rasetor Building Stack Atmospheri: Monitor

3. Reactor Building Ri lange Radiation Monitor

14. Was:e Oas Tank Rup:ure 1. Area Gmena Monitor -

• Auxiliary Building Entrance

~ Eleva: ion 305 ft.

2. Auxiliary Building Atmospheric Moni:or

3. Waste Gas Sys:aa Ixhaus:

Revision 1 Page 3 of 3 June 1980 A=endment 19

y cr e no c s ef i t s e g n n s s

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c oo d m oS r o c u n Rm rt a FO i i t n q e c or S d u u d a l s oo r q t e . m n oa Cp y o o e r F rr s a h r p .t o r o o s t r y C p y st e m td Cu t t s s) c aa s o i ne SS s i t y e n n s o w os O i l r t ay r S e di A R r C u s m i o i l

N g sc e rl )

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) f Pcg2 2o DUTY SECTION FOR ON-SITE SUPPORT--AVAILABLE WITHIN 60 MINtriES OF NOTIFICATION.

Minimum Number Shift Position Emergency Functions (1) Emergency Director Relieves Shift Supervisors as Emergency Director in the Control Room.

(Duty Section Superintendent) Assumes everall charge of emergency.

(1) Public Affairs Representative Reports to Control Room if EOF is not activated; otherwise, reports to EOF. Activates the Emergency Public Information Plan.

4 NOTE: The Duty Section Superintendent and Public Affairs Representative are notified for any activation of the

! Emergency Plan.

(1) Communicator Reports to Shift Supervisors office and activates the Operational Line.

i Serves as communication link between Emergency Director and the TSC, EOF, and B&W for operational technical data.

(2) Communication Assistants Report to Shift Supervisors office and assist in off-site notifications and communications. Report to Communicator.

(4) Technical Support Center (TSC) Activate TSC and provide expertise on Core, Electrical, Hechanical and Coordinator and Engineers Computer. Provides recommendations to Emergency Director based on assessment of plant conditions.

(1) Radiological Assessment Reports to Control Room. In charge of all in-plant HP and chemistry Coordinator (RAC) and off-site monitoring and dose projections.

(2) Radiological Analysis Support One reports to Control Room and assists the RAC in 11guld and gaseous dose Engineer assessment and one reports to OSC to supervise Rad waste processing.

(1) Operations Support Center Reports to OSC. Responsible for coordinating efforts of HP Coordinator

, Coordinator and Chemistry Coordinator, dispatching monitoring teams and Emergency l Repair Teams.

g. (1) Rad Monitoring Team Reports to OSC. Responsible for radiologically surveying on-site (out on-site & off-site (2-man team)

~

u of plant) and/wr off-site areas.

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I I Tchte 8 Continued Page 3 of 5 Minimum Number Shift Position Emergency Functions (3) IIcalth Physics Technicians Report to OSC. Responsible for in-plant Health Physics Access Control, Ikasinet ry. Surveys, etc.

(1) Operations Coordinator Reports to Control Room, Coordinates Operations and Maintenance activities, under the direction of the Emergency Director.

(1) llcalth Physics Coordinator Reports to OSC and the OSC Coordinator. Coordinates in-plant Health Physics activities.

(1) Chemistry Coordinator Reports to OSC and the OSC Coordinator. Coordinates in-plant chemical

, sampling and analyals.

(1) Emergency Maintenance Reports to OSC. Assigns Emergency Repair Teams and Directs their activities Coordinator as required by the Operations Coordinator.

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Table 8 Continued Pcgs 4 of 5 DUTY FOR OFF-SITE SUPPORT--AVAll.ABLE WITIIIN FOUR ll0URS OF NOTIFICATION Minimum Number Shift Position Emergency Functions (1) Emergency Support 111 rector Assumes over-all direction of t,upport effort from EOF.

(1) Assistant Emergency Support Reports to COF.

Director (1) I'mergency Support Communi- Reports to EOF.

cator (1) Croup 1.eader Technical Sup-port Reports to off-stte Technical Support Center at CPU licadquarters.

Technical Support Staff Reports to off-site Technical Support Center at CPU lleadquarters.

(1) Tech Support Representative Reports to EOF.

(1) Croup I.eader llealth Physics Reports to Crawford Station.

Support (1) Croup Leader Chem'C.1j Reports to EOF, (1) Croup I.eader Mainterc~- - Reports to Crawford Station.

Support (1) Croup 1.cader Admitilst rat ive Reports to Crawford Station.

Support (1) Croup Leader Security Reports to Crawford Station.

Support i

~{ g (1) Personnel Monitoring Reports to EOF.

m p Coo rd i r.a tor g.

g (1) ilcalt5 Physics Hanpower Reports to EOF.

n Support Coordinator w

(1) Environmental Assessment Reports to Environmental Assessment Comumand Center.

Coordinator (EAC)

l Tcble 8 Continued Page 5 of 5 Minimum Number Shift Position Emergency Functions (1) Assistant EAC Reports to EOF.

(Additional Contractor Report to Environmental Personnel to assist in Assessment Commani Center environmental assessment, whole body counting and analysis, and Celi Detec-tor Analysis.)

After the initial manning of the EOF, additional personnel are brought in as required to complete the OFF-SITE EMERGENCY SUPPORT ORGANIZATION as shown in Fig. 13 and to augment the site, Emergency Response Organization as they are required.

cvailable.

Should additional personnel be required, they will be requested from other organizations as GENERAL NOTES:

• Personnel are assigned Emergency Responsi,bilities based on the individual's over-all experience and training as well as their current work position. Individuals will meet or exceed the qualifications of Reg. Guide 1.8

. Rev. 1-R, dtd. 5/77.

Additionally, each individual assigned an Emergency Function will be trained specifically on the Emergency Plan and on Emergency Plan Implementing Procedures as applicable in accordance with Table 12.

(SRO) indicates Senior Reactor Operator License.

(RO) indicates Reactor Operator License.

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TABRI. 9 RAlllATION ft)MI1URING SYS1F.H - StitRIARY DESCRIPTION ItiSIRilHF.Hr CilANNEl, RAlll ATION HuliiTOR ~

2 DESCRIPTION Area Radiatlois Honitors:

i Cl Control Roosa C2 Radloclienical I.nts C3 Sasept ing Norse C/s lhet MacleIne Sliop C5 Reactor Bestiding per ACC Door Cr, Fuel llandling Bridge Aus.

, C1 Fuel finnJilng Bridge Main C8 Reactor Building lil ioR Range C9 Fece1 Ilanelling RrIdge Retuoling snilding CIO Aus. Oldg. Entrance. 58. 305' Cll Weste Decay Tanks Cl2 Solid Weste Ares Atmospheric Radiatios Hoeillor s:

Al FartIctelate-Control Tower Al NN fodine-Cositrof Tower

@ Al Caseous-Controf Tower

.k.

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TABLE 9 RADIATII)H IR)N!TURING SYSTEll - SUttHARY DESCRIPT10M ANSTRilHENT

• RADIATION HON #10R CllANNEL __

_DESCRirTIDM -

Atmospher ic Radiat ion Houitors:

A2 Part iculate-Reactor Building A2 lovline-Reactor Rullding A2 Caseous-Reactor Building A4 Part iculat e-Fuct llandling Ridg.

A4 lodine-Fuct flanilling Bielg.

A4 Caseous-Fret linudling Ridg.

A5 Condenser Exlinust A6 Particulate-Auxil'lary Building A6 lodine-Auxillery Building j A6 Casev,3 Asaillary Building A7 Waste cas System Emleauet A8 Particulate-Aux. & Fuel llandling Building Stack AR Iodine-Aux. & Fuel llandling Ridg. St ack N

g A8 Caseous-Aux. & Fuel llandling

g. Bldg. stack to E Revision 2 g

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TAllt.E 9 RADIATluH HONITORING SYSTP.ti - Sut#1ARY DESCRIPTION INS TRilHF.N f CilANNEl. ~ RADIATION PRINITOR ~ ~'

DESCRIPTION Atmong4:eric Radiation Honitora (Cosit'd):

A-9 Pa r L icie l a t e-Reac t or lhellding St ack g.9 .

Indine-Reactor Building Stack A-9 Caseous-Reactor Building Stack Liquid Redlation Honllora:

I.1 -ill Primary Coolant I.e t domi 1.1 -I.0 Primary Coolant I.c t domi I.2 Decay liest closed Cycle. I.oop A 1.1 Decay Heat Closed cycle, loop 3 IA Nuclear Servicea Closed Cycle 1.5 Spenit Puel I.6 Radioactive Weate Dioclearge I

B u

@ Radioactive Waste Discharge

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Amendment 19

1 TAE( 19 Pare I ' 2 TLD I.0 CATIONS lleight Distance ) Azimuth Location feet miles degrees Description TM-ID-IS2 4 0.4 0 North weather station TH-ID-2S2 3 0.7 25 North bridge TM-In-4S2 35 0.3 71 Top of dike TM-ID-SS2 4 0.2 95 Top of dike TM-ID-8SI 6 0.4 167 Pole #33-ME-T-60 TM-ID-9S2 4 0.8 184 South THI TM-ID-10S2 6 0.4 200 Pole #HE-33-T-28 .

TM-ID-IISI 4 0.1 221 Hechanical draft towers TM-ID-13St 7 0.4 270 Due west on Shelley's Island TM-ID-14S2 3 0.4 293 Shelley's Island TM-ID-ISSI 6 0.5 317 Shelley's Island TM-ID-16S1 4 0.2 340 North boat dock TM-ID-3Al 3 0.6 35 Route 441 TM-fD-4A1 7 0.5 65 Laurel Road TM-ID-sal 3 0.4 86 Observation Center TM-ID-6Al 6 0.5 117 Route 441 On light pole TM-ID-7A3 3 0.6 143 Route 441 TM-ID-IIA 2 6 0.5 221 Beech Island TM-ID-16Al 4 0.4 332 Kohr Island TM-ID-10BI 2 1.1 204 Shelley's Island TM-ID-IIBl 6 1.9 227 Route 262 Pole #HE2890, BK722-306 TM-ID-12BI 4 1.3 253 Coldsboro Air Station TM-ID-13BI 7 1.2 265 Coldsboro Marina on light pole TH-ID-14BI 7 1.4 290 Still flouse Road on tree TM-ID-ISBl 6 1.8 304 Still flouse Road Pole #ME2397NB, 233L-35L TH-ID-ICI 4 2.6 0 Middletown substation i

TM-ID-8CI 4 2.3 159 Falmouth-Collins substation TM-ID-lE4 6 4.3 3 Vine Street exit from route 283, Pole fME2481-LO TH-ID-2El 6 4.8 18 School House Lane & Miller Road, Pole fME782-LO TM-ID-3E3 6 4.5 46 Kennedy Lane, Pole #74-ME-97 TH-ID-4E5 4 4.9 71 Beagle Road

g TM-ID-5El 6 4.6 85 N. Nkrket St. (Rt 230) & Zaeger Road, Pole IPP&L 31084, S30386 g TM-ID-6E6 6 4.6 115 Amosite Road, Pole #PP&L 31016, S29272 g- TM-ID-7E6 6 4.8 131 Bainbridge Road (Route 241) & Risser Road Pole iME825 m TH-ID-8E2 6 4.1 161 Cuard shack at Brunner Island E TM-ID-9El 6 4.9 182 Canal Road, Conewago Heights, Pole #ME497EM, BK244122 g TM-ID-10E3 6 5.0 200 Conewago Creek Road, Strinestown, Pole IME9240E, BANK 231-139 TM-ID-IIE3 6 4.1 228 Stevens & Wtison Roads, Pole #ME252'.N0 Revision 2 l

June, 1980

TABL{'l page 2 c' ?

TLD LOCATIONS Ileight Distance Azimuth i Location feet miles degrees Description TH-I D- 121:4 6 4.3 245 TH-ID-13E! 6 4.9 Lewisberry & Roxberry Roads, Newberrytown, Pole #ME725NB 268 Yocumtown Road & Old Trail, Pole #MEIO50NB TM-I D-14 E4 6 4.9 281 TH-ID-15El Route 262 & Beinhower Road, Pole fME135FA 6 5.0 313 TM-ID-2FI 6 9.0 Lumber Street, liighspire, Pole #PP&L 26827, S31990 15 TM-ID-5FI 6 6.8 West Areba Ave. & Hill Street, liershey, Pole #PP&L 30383, S34608 89 TM-ID-7FI 4 9.0 linemelstown Street , Elizabethtown, Pole #PP&L 32190, S30207 132 Drager Farm TM-ID-3G1 4 19.7 47 TH-ID-4Gl 6 10.0 68 Cumberland Street (Rt 422) at 16th Street substation, Lebanon Ro:.3e 241 TM-ID-6G2 6 21.1 113 1H-ID-7GI 55 15.0 Steel Way & loop Road, Iancaster, Pole #PP&L 21274,39808,S36930 124 Columbia TM-ID-9Cl 4 13.0 183 TM-ID-14G1 North York substation 6 12.2 300 i TH-ID-ISGI 3 15.0 Ereford Road, Camp 1I111, Pole #PP&L (ATTCli)23347, S33615 308 West Fairview

. TM-ID-15G2 6 11.5 307 TM-ID-16G1 6 11.2 Penn & Forster Streets, liarrisburg, Pole #FF&L 24035, S34066 330 TH-ID-16El 6 4.9 Route 22 & Colonial Road, Colonial Park, Pole #PP&L 25874, S35291 339 Spring Garden Drive & Route 441, Pole #PP&L 27716, S32497 TM-ID-3F1 6 7.16 48 TI-ID-4F1 (Conewago School) HEl039 CW 764/185 on School flouse Rd 6 8.53 72 TI-ID-6F1 6 9.36 113 (Bellaire) PPL 32920 S31503 4 mi. E of Bellaire crossroads (Donegal Springs) PPL 33225 S28173 1/8 mi W of Colebrook &

TI-ID-8FI 6h 7.37 Donegal Springs Rds intersection on Donegal Springs Rd

• 163

. . TI-ID-8GI 6 13.15 157 (Starview) ME193EH 1/8 mi N of Starview Methodist Church TI-ID-9FI 6h 6.48 177 (Wilshire Hills) ME693SE SW corner of Orchard Rd and Stonewood Rd i TI-ID-10FI 6 7.39 196 (Hanchester) C53-LIM HE240MT on Naple St. across from liigh St.

TI-ID-10GI 65 12.69 (Zlon's View) ME1459CF SE corner of Coppenhaffer Rd & RT 295 204 (Weiglestown) EL&P 6632 opp. corner Alta Vista & Fox Run Rds 4 TI-ID-IIFl 6 7.96 225 TI-ID-IIGI 65 11.71 225 (Andersontown) ME611 DO 2017/100 on Andersontown Rd 1/8 mi SW Orr TI-ID-12FI 6 8.56 242 (Mt. Royal) HE3053 DO Bank 321-232 W side Rt 74 at Full Gospel Ch TI-ID-12G2 6 11.94 -

(Maytown) 16E/78/End DJ/63 on Alpine Rd 150 yd S of Rt 177 236 l' TI-ID-13FI 6 7.77 260 (Rossville) ME574 WR Bank 474-100 W side Rt 74 k mi from Rt 177 TI-ID-13G2 6 (Lewisberry) PPL 24599 S29513 W side Rt 382 mi N of Lewisberry 10.4 274 TI-ID-13G1 6 13.19 276 (Lisburn) PPL 23149 S30533 NW corner Lisburn Rd and Main St (RT I lI TI-ID-14FI 6 7.96 292 (Ht. Allen) Attach 21728 S30984 corner Orchard Ln & Hertzler Rd

@ TI-ID-15F1 6 8.49 (Reeser's Summit) Attach 24757 S31644 on Evergreen Rd 308 f

o TI-ID-16FI 7 8.07 340 (Steelton) PPL 21570 S32926 across from Steelton Water Co.

(Rutherford Heights) Attach 27280 S34073 on Derry St at 66th St.

NOTE: All locations current as of 1/11/80 and maintained

!$ as part of REMP program per Plant Technica( Specifications, t

Revision 2 June, 1980

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i Radiological Fmergency Assistance Is om Of fet te Agencies j r' WIPANY/ACEliCV PER Se nNNEl.

_RESUtJECES RESPONSE TIME k m.J.roi L & I) Engineers I

WI h na I) Nolelle Radiochemist ry B.ab

2) Teclenicians 2) Reactor Diagnostic System

3) i RealJent Engineer 3) Other needed eelulpment as available 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

4) Dedicated Couseunication Link from lill to Lynclburg. VA tidard, loue & 8) Nuclear Engineers Carrick t.:onsulting I) Heteorological Tower

' 2) 18ealth rhysics and Cheelstry Teclenicians 2) Computer facilities for Radiological and 3-4 hours 1

)) Heteorotngist Environmental Honitoring

3) Consultation on RsJtological and Environ-i mental Honitoring k jentific Appft- 1) Cleestats catlons Ind. 2) Itealth Physicista ' l) Cermanium Lithium Caanne Spectrometer &

3) Physicists Shield

2) Radiation Monitoring Survey Instruments 6-24 hours

4) Teclenicians (Hechanical. 1) Fortable Sodium loJide Camma Spectrometer f

Electrical) & Shield 1, 4) Air Samplers (lligh and I.aw Volume) 4

5) Completu Cle=tatry Lab () hours away)

{ Radiatlan Hanagement l) Certilled Health Pleysicists Corporation 2) Physicians 4) 24 lor / Jay availability of espert consultation

1) Technicians on management of radiatlan accidents

] 2) Bloassay Lab for radiattoo acclJents j )) RaJlocieemistry Analyses

) hours

4) 24 hr/ Jay access to Radiation Emergency Medical Tese .

i 5) Fortable Radiation Monitoring Instruments

Cantees t a Ind. l} Necessary Engineers to 1 l} Iow background Alpha and Beta Counters assist in set-up and oper- 2) Body Burden Centers k attons of loaned systems 1) Cermanium Lithium Casma Spect rometers 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> i

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Table 18 (continued) 1 i COMPM4Y/AfMY Page 2 of 3 i PER501dNEl.

i _ RESOURCES leershey HeJical BESPONSE TlHE Center 1) Certified and Master llealth l) Hospital equipped for evaluation and treatment Physicists

?) Plah Medical Physicists of gadiation tsjuries available 24 hrs / Jay

2) Bio-Assay lab

3) llealth Physics Technicians 3) Cefger Hueller Counters

4) Chemists 34 45 alinstes

5) Bio-Clienist s 4) Teletectors 3

6) Pharmacists 5) Radioactive Waste Drums

7) College-GrsJuate Research Department ,

.lersey Central

1) Ilealth Physics Technicians I) Air Samplers P&l./ CPU

2) Chemistry Technicians Oyster Cerek riant

3) Fngineers/Tectonicians as 2) Teletectors available. 3) Continuous Air Monitors

4) Thesmolumin8sent Dosleeters & Supply Data

5) High Density Concrete Shteld Blocks

6) Protective Clothing

7) Boots /Balngear 6-8 lumre

8) RaJiation Honitoring Instruments

9) Hobile Vans with Environmental Monitoring Equipment IO) Radiocheatstry Analyses Phila.letplif a Elect ric is lleattle risysics Technicians 1) Radiation Detectors reu h Bottom Plant 2) Cheelstry Technic 8ans 2) Radiochemistry Analyses

3) Engineers as available 3) Liquid Scint'llation Detector 4-6 hours

4) Cernantum Lithium Detector Pennsylvania rea,cr 1) llealth Physics Tece niclans l) Air Saeplers and Associated Equipment

& 3.laht 2) Chemistry Technicians 2) Teletectors susquehanna Plant 3) Technicians (Hecleanical, 3) Radiation Monitoring Instruments Electrical) 4) Protective Clotising

5) Respirators & Canisters k

f"> 6) Self-Contained Brestising Apparatus 4-6 liours U 7) Cernanium Litblian Detectore k

to

8) Hobile Radiological I.sb

9) Dostmeters o

o W

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i i _ Table { (continueJ) page I of 1 f g t_PANY/ACtNCY PERSONNEI. RES0tlRCES RESPONSE TlHE i

Public Service Elec- l) lleattle Pliysics Supervisors trir & C.as (PSE&C) 2) Cl.cmistry Supervisors 1) Cernantum Lithium Detector and Analyser I

Salem Plant 2) Radiochemistry Analyses i

1) llealth Physics & Claemistry 3) Teletectors Tec hnic ians 4) Air Samplers (Illgli and I.ow Volume) l

5) Radiation Honitoring Instruments

6) Silver Zeolate Cartridges

7) Charcoal CartrlJges j 8) Scott Air racks 4-6 liours

9) Portable Air Compressor i 10) full face stespirators witte Charcoal Cantsters and Ferticulate Canisters

' ll) Whole Body Counter

12) Emergency Van equippeJ for Ambulance Service with Radiation Detectors, etc.

1)) Protect ive Clottning (disposables)

14) Dosimeters National Weattier As needed to sug>purt Service (NWS)

Back-up Heteorological Information resources Emergency Balloon Runa b6 hs Depa r t ment of EnerCy As needed to support (isiE) l) Portable Radiation Survey Instrumentatlun l

fesources 2) Fortable Personnel Honitoring Equipment

3) Nbile Lab Facility 12-24 hours 4

Borease of Radiat ion As needed to support j

rsotection (SRPI resources 1) Camma Spectroscopy j

2) Proportional Coesnters i

3) 8.tgtud Scintillation

4) Thermoluminisent Dosfeetry & Eeader t

5) Emergency Hobile I.ab

6) Monitoring Van f, k 7) Beta-Comme Survey Heters I hour

g 8) Air Samples a 9) Resperatory Protection j B m IO) Envirosamental Monitoring o

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, I TABLE 12 PERIODIC TRAINIHC OF FHERGENCY RESPONSE PERSOr.AEl.

l'ersonnel t'nt er,ory Invol vcel l'ernonisel Training and Frequessey -

I.{cesised Operators All Senior Renctor Operatorn aiol Ronct or Operators acid Senior Reactor Operator n receive cateiinive periodic Renctor operatorn on-tlie-job nud coittinuoun formal t ralising an acheduled and conduct ed lay (lie operator requali ficat ion t r aining program. 1his prograai nhall inclisile a coespreisensive review of the 1HI Emergency Plan and impleinent long 1)ocimmeni .

Personnel respon- Dnty Section Super- 1he listed Individuals are responsible for knouledge of tlic current THI sible for accident Int endent s, Einergency a n se ssment and/cr I)irect or, Technical Einergency Plan, Implementing Document, Technical Specifications, nnel cccident manngement. other relat ed Stat ione programs, plans, an.I proceduren. The tinted

, Sug:po r t and Opera- Indviduals attend at least one sneetIng per year to receive training os tions Support Center 1

the THI Emergency Plan and Implementing Documeint. Detailed lust rnet inna Coorelinat o r n , Rndlo-with special attention given to the use of tlie dose projection tecluilepics logical Assessment will also be provided.

i Coorillnntor, Radlo-logical Analynis Siipport Engineer .

Operat ions Coordinator.

Eincrgency anal Assin-Lant Emergesicy Siip-port 111 rectors, Group I easier llealt h lisysica/

(1 cmintry Support ,

Environniental Amness-nient Coord leintor ,

Croesp I.eader Teclinical

• Siippo r t t

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P 00 g I

~TAlit.E I2 PERIulilC TRAIIIING OF EHERGENCY RESPUHSE PERSONilEl, Pe r r.oune l Ca t 'cgory _. ~ ..IsivoUc~d Personnel llealt h 11eynirn/ llenlile Physica Coor-Training said Fregiscucy

=-

Ra.liat ion Pr eit ec- dinat or and Terknt- Ra.llat insi Protect lose pernonnel Init ially receive nei catensive training tion pcrnonnel, cinn1, Oisa it e anel courne and nuhncquent ly receive inst ruct iini nei new sectho In nnd cynigiment Ra.liological Ison- tif fnit e Haillological on nu as-needed basin. %cne I dividuala f aialliarir.e t hesenciven wit h t he itoring and Sur- thinitor tug Team Till l'acrgesicy I' lass and isnpicincot ing Document as an canent ial part of their jobs. Oii at leant an annual banin, detailed instructiose will 1,c veying persoeusel. pe r nosine l , ot he r t enne emonitorn, Heal t le provided on sisch topics ne claneificat lun of emergencien, Interfacca and i responsibillt les of redlological inc:.itoring and senessment pe r noinne l ,

Physica Hanpower Sup-port Coordinat or , persouiet protectiosisluring emergesicien, locat ion and une of cniergency Pei nonnel ihniltoring cigulpment , determinat ion of external and lait ernal radiat ion. caponnec/

Coordinator and Sup- cont aminat ion, decosit aalisat ion of personnel and equipment , snonitor ing tecliniques, and communications.

port St af f Environ-mental Agacenment I

Coordinator and Sop-port Stnif i

First Aid and Rencue Ansillary Operators Te nine( n ) and Radiat ion /Clien- Encle enember of the First Aid and Rescue Tenis will receive the St andaril letry Technicians Red Cross Hultimedia First Aid Course. Set lef actory complet ion of tint a course will certify these as a First Aid and Rescue Tease acaber for a trained in first period of 3 years. Annnelly, a refresher course will be made evallnble nid t echniques inr the teaa escobers and will include a review of the Multiniedla Conrae material. In addit ion, af t er complet ing tlic Standard Red Cronn Courne and during encle of the annual refresher cournes, escle t eene sac = lie r wi l l also be instructed on the availabliity of onnite medical treatment facilities, equipment, ard supplies; conniinilcat ion systenia; radiological har.ards exleting during personinet-related e,ergencies; and interfaces and responelbilitlen ulth local medical support personnel (e.g. n=hininnce personnel, local physicians, etc.)

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TABLE 12 PERIODIC TRAlHING OF EHERCENCY RESPollSE PERSONNEL personnel Category involved Personnel Trairiing and Frettuesicy '

F.mcrgenc y Repair l>n igiant ed fin int eis-Tenes( n )

1he training paogram foi ance licpartment nis i f t not he limited to: Emergency Repair Tenen personniel will leiclesile, lust uns lic a n responalbilit ies during an coergesicy, rnillological cons iderat iosa s , availnhilit y of dnienge contiol equipnient , une of commeens-ication systemn, nod the Interfaces with other essergency tenien. liii n training will he conducted at least asennally.

Sit e Security and Security Supervisor, i Support Security Securit y Coorillnator, lhe personniel list eil to the lef t will receive t raining on at leant i Forces nu annual basin. They in turn will be responalble for training their

' Secur it y Sergeant s, Group I.cader-Security respect ive security of ficers and otlier support personnel. 1he training Support prograin will include at least the following subject s: a review of tlic applicehle parts of the THI Emergency plan and Impleinent iisg Docipacut with emphasis on the classificat loss of einergencies, conununicat ions, and specific areas of responsiblity; personnel accountability; pernonnet l and vehicle access control during emergencien; evacuation cont rol; assil listerfaces wills offsite support organizations.

Fire Brignile Operations Coor-dluntor, Shif t Th i n t raln isit,, wis icle In provided at lenet on ar semi-anisual basin to Siipervinors and each person involveil, la given by Net-Ed instructors tralised In fire Foremen, and assigned fighting. The prograse will incliule, but emot be lisilteit to the types tenne incohers on each of fires and their particular I.asards, equiguneset to be used oss encle shi f t , type of fire, the Installed fire detections anil protection systems, portable fireflghting eqeilpment, respiratory protection devices, and raillological liazards existing during fire essergencies. lie nildit Inn,

! a review of firefighting procedures and techniques will be inc lueled Iri the trainling program. Furtherseure, pract ical dennonstrat ionn of firefigleting will be glvers wisIcle will f aclode the particIpalloin of Fire Brigade persorwiel.

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June, 1980 t

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ptgs 1 of 1 IALLE 13 INVENTORY OF EMERGENCY KITS BY GENERAL CATEGORY I. Radiation Monitoring A. Typical contents

1. Full face respirators with enarcoal canisters

2. Survey instruments--High range GM, Frisker

3. Dosimetry equipment--Dosimeters / chargers, TLD's

4. Pene-at've clothing

5. Support Materials--Paper, pencils, envelops, asps, procedures, etc.

B. Designation / Location -

1. Emergency Monitoring Kits / North Processing Center

2. Control Paint Emergency Lockers / Radiological Controls Lab.

3. Control Room Emergency Lockers / Unit 1 Control Room

4. Emergency rquipment Lockers /Near-site EOF

5. Washdown Area Kits / North Processing Center

5. Emergency Clothing Kit / Access Control Point

7. Ambulance Kit / Machine Shop II. First Aid A. Minor Injury

1. Contain items typically needed for minor injuries

2. Placed throughout plant B. Employee Kits

1. Contain sufficient quantities to serve expected needs of approximately 100 employees.

a. Stretchers ~

b. Inflatable splints

c. Employee size first aid kits

2. Located at twelve first aid stations

a. Unit 1 Circulation Punp House

b. Training department hallway

c. Unit 1 Health Physics area hallway

d. Unit 1 River Water Pump House .

e. Industrial Waste Building

, f. Unit 2 Turbine Building I g. Unit 2-Control Room l h. Unit 2 Reactor Building entrance

1. Unit 2 Auxiliary Building

j. Unit 2 Circulatory Water Pump House I k. Warehouse No. I

1. Unit ' Control Building C. Special Medical Facility

1. Equipment inventory to support professional medical treatment.

D. First Aid Facility

1. Contains equipment necessary for examination of patients

2. Location of sice ambulance III. Damage Control A. Typical equipment available

1. Hand tools

2. Cutting / Welding equipment i 3. Patching materials

4. Portable blowers

5. Submersible pu=ps

6. Electrical equipment

7. Rigging equipment Revision 2 Jane, 1980

page 1 of 1 l

TABLE 14 Unusual Event-Summary State and/or Local Offsite Authority Action Participating Agency i

1. Provide fire or security. a. Security assistance provided by the Penn-assistance if requested. sylvania State Police in conjunction with THI Security Forces,

b. Fires of more than 10 minutes in duration or outside plant structure will receive outside assistance as follows:

FIRE

1. Londonderry Vol. Twp. - Dauphin Co.

2. Rescue Vol. Fire Co. - Middletown

3. Liberty Vol. Fire Co. = Middletown

4. Bainbridge Vol. Fire Co. - Lancaster Co.

AMBULANCE

1. Londonderry Twp. - Dauphin Co.

2. Rescue Life Squad - Middletown

3. Liberty Life Squad - Middletown

4. Bainbridge Ambulance - Lancaster Co.

W Revision 2 June 1980 Amendment 19

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

9 pa;;e 1 of 2 TABLE 15 Alert- Summary State and/or Local Offsite Authority Action Particioating Agency

1. Provide fire or security a. Security assistance provided by Penn-assistance if requested.

sylvania State Police to the TMI Security l B. A fire in whichreqq}anypermanentplantstructure ires offsite firefighting capability.

TMI outside fire assistance vill be received as follows:

FIRE g

1. London lierryTwp.Vol. Fire Dept. - Dauphin Co.

2. Rescue Vol. Fire Co. - Middletown

3. Liberti Vol. Fire Co. - Middletown

4. Bainbrfdge Vol. Fire Co. - Lancaster Co.

AMBULANCE l{

l. Londonderry Twp. - Dauphin Co.

2. RescueiFire Squad - Middletown

3. LiberthLifeSquad-Middletown

4.

• BainbrijgeAmbulance-LancasterCo.

2. I Augment resources by activating near site E.O.F.

Activation df the TMI near site E.O.F.

is achieved' >er section 4.6.1.2 and 4.6.1.3 of

. and any other primary the TMI Estrgency Plan.

response centers. Other prima (y response centers to be notified. 0

1. Dauphin, :ounty (Plan 4.6.1.5)

2. Pennsyldmia Emergency Management Agency @,.6.1.6) and the Bureau of Padiolog1 cal Protection (4.6.1.7)

3. N. R. C.

' site

4. N.R.C.Ok fice - Hot Line - Bethesda, M.D.pm Depending on e situation as evaluated by the Emergegy Director the following agencies may b< called up.

1. Hershey Me ical Center

2. Pennsylvan State Police

3. Department 'f Energy R.A.P. team

4. Radiation M nagement Corporaticn

5. American Nur lear Insurers

'V

3. Alert to standby station key For incidents ig 1ving radioactive emergency personnel including materials, the 0 irations Support Center monitoring teams and associated Coordinator will communications. offsitemonitorin/,ispatchonsiteand teams per Onsite Radiological moni{,oring procedure and the l OffsiteRadiologipimonitoringprocedure to monitor for potsible releases. (Plan 4.7.6.2)

)

Mt Revision 2 June 1980 tj Q Amendment 19 a

Table 15 (Cont'd.)

pa3= 2 of 2 ,

The Bureau of Radiological Protection will 1 provide assist.3nce as outlined by their plan contained in A,.endix 8 of Annex E, the l

Scatc Olan.

4 Provide confirmatory offsite The Radiological Assessment Coordinator and radiation monitoring and in-gestion pathway dose projec- the Environmental Assessment Coordinator shall provide for offsite radiation monitoring and tions if actual releases sub- ingestion pathway dose projections.

stantially xceed technical specificat:en limits.

As outlined in the state plan the B.R.P. will '

provide independent monitoring data and correlate the same with TMI radiological assessment teams.

/

l l

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Amendment 19 Revision 2 June 1980

page 1 of 3 TABLE 16 Site Emergency - Summary State and/or Local Offsite '

Authority Action Participating Agency

1. Provide any assistance The Local Services Support and the requested. Coordinator with Government Agencies sections of the plan (4.5.2. & 3) best describe 'the interface of agenciec providing coordinated assistance in the event of a site emergency.

2. Activate immediate public Upon receipt of report of a site notification of emer- emergency by PEMA from the TMI emergency gency status and provide control centen the initial alert public periodic updates. warning will be disseminated by P.E.M.A.

to the five affected county E.O.F.

Actual activation of sirens will be performed by the affected counties E.O.F.

The National Weather Service will activate the tonal alerts upon receipt of instruction to do so by the PEMA duty officer. The five risk counties will prepare and disseminate public information material or protective actions and event status updates. The National Weather service alert radio will also be used by PEMA as a medium for protective action and update bulletins.

3. Augment resources by Activation of the TMI near site E.O.F.

activating near site E.O.F. is achieved per section 4.6.1.2 and and any other primary response 4.6.1.3 of the emergency plan.

centers. Other primary response centers notified:

1. Dauphin County (4.6.1.5)

2. Pennsylvania Emergency Management Agency (4.6.1.6) - Bureau of Radiological Protection (4.6.1.7)

3. NRC site (4.5.3.3)

4. NRC - Bethesda, Maryland (4.5.3.3)

4. Dispatch key emergency For incidents involving radioactive personnel including moni- materials, the operations support center toring teams and associated coordinator will dispatch onsite and communications. offsite monitoring teams per Onsite and Offsite Radiological monitoring proced7?es to monitor for possible releases (4.7.6.2)

The Bureau of Radiological Protection will provide assistance as outlined by their plan contained in Appendex 8 of Annex E the State Plan.

5. Alert to standby status The five affected counties under the other emergency personnel direction of PEMA will provide rapid (e.g. those needed for notification in priority order, of n..,,,-- , '..- toon Amendment 19

,, Table 16 (Cont'd.) psge 2 of 3 evacuation) and dispatch county and local government heads, key personnel to near site staff, emergency forces, volunteer organiza-duty stations, tions, schools, hospitals, nursing homes

, and business and industry of incident and possible need, for evacuation. The affected counties will select locations for and dispatch emergency services to near site duty stations to include first aid, wrecker, and fuel services.

6. Provide offsite monitoring The Bureau of Radiological Assessment results to licensee and others will conduct incident assessment, determine and jointly assess them. protective actions and recommend to the licensee. The B.R.P. Incident Manager will direct all response team activities, assess and document offsite federal response team data and provide for continued communication of all assessment information to the licensee. Further details available in Appendix 8 of the State Plan.

7. Continuously assess infor- The Bureau of Radiological Protection (BRP) mation from licensee and off- responsibilities include maintaining con-site monitoring with regard tact with the licensee, supplementing to changes to protective environmental sampling and analyses, actions already initiated for situation updating for appropriate state, public and mobilizing evacua- county and local agencies. It will further tion resources, be the responsibility of the BRP to alert and advise PEMA emergency operations center through the bureau representative of the i

need to take protective action, the actions to be taken, the geographic area at risks, and pertinent facility conditions having influence on incident outcome, as well as to recommend withdrawal of pro-tective actions. These alerts and advisories will be issued by PEMA to the five affected counties. The counties will advise local agencies of any further actions to be taken.

8. Recommend placing milk The Department of Agriculture of the State animals within 2 miles or of Pennsylvania will provide advise to stored feed and assess need PEMA, BRP and affected counties on to extend distance. protective actions for livestock including controlled feeding, sheltering and collection and disposal of contaminated farm products.

9. Provide press briefings The Public Affairs representative Vill I

perhaps with licensee. report to the Emergency Support Director l and is responsible to the director for the I

preparation of technically accurate informa-n tion for media release. (4.5.1.4 item 3)

Revision 2 June 1980 Amendment 19

Teble 16 (Cont'd.) paga 3 of 3 The communications Director (Press Secretary to the Governor) will establish a press office as the principal point of contact in the vicinity of the Emergency Operations Facility, utilizing public information personnel from appropriate state agencies. In addition the Press Secretary will serve as a spokesperson who l will have access to all necessary information and who will establish arrangements for timely exchange of information between PEMA, the licensee and all other appropriate information sources. Met Ed will provide a media center to accomodate face to face contact. The Met Ed role is described in I detail in Appendix B of the Emergency Plan.

l

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Amendment 19

, Revision 2 June 1980 t

. page 1 of 4 TABLE 17 General Emergency - Summary

1. Provide any assistance The local Services Support and the Co-needed. ordination with Government Agencies section of the plan (4.5.2 and 4.5.3) best describe the interface of ar,sncies providing coordinated assistance in the event of a general emergency.

2. Activate immediate public Upon receipt of report of a general notification of emergency emergency by PEMA from the TMI emergency Opera-status and provide public tions Facility,the initial alert warning periodic update, will be disseminated by PEMA to the five affected county E.O.C. Actual activation of sirens will be performed by the affected ,

county E.O.C.

The National Weather Service vill activate the tonal alerts upon instruction to do so by the PEMA duty officer. The five risk counties will prepare and disseminate public information material on protective actions and event status updates. The National Weather Service alert radio will also be ased by PEMA as a medium for protective

- action and update bulletins.

3. Recommend sheltering for 2 It is the responsibility of the Bureau of

=ile radius and 5 miles Radiological Protection to alert and advise downwind and assess need to PEMA headquarters through the Bureau extend distances. representative of the need to take' pro-tective action, the actions to be taken, the geographic area at risk and pertinent facilityconditionshavinginfluenceon incident outcome, as well a,s to recommend withdrawal of protective actions. These alerts and advisories will be issued by PEMA to state agencies, county and local government.

The choice to shelter applies where the event involves a sizeable puff release likely to produce offsite consequence equal to or exceeding 1 Rem whole body or 5 Rem to the infant thyroid. This option applies to any severe episode when sufficient time is not available for an orderly evacuation.

4 Augment resources by Activation of the TMI near site E.O.F. is activating near site E.O.F. achieved per section 4.6.1.2 and 4.6.1.3 and any other primary res- cf the TMI Emergency Plan. Other primary pense centers. response centers to be notified:

1. Dauphin County (Plan 4.6.1.5)

2. Pennsylvania E=ergency Management Agency (4.6.1.6) and the Bureau of Radiological Protection (4.6.1.7)

3. N.R.C. - site c..<,-- -

.nentv,,nk ,,pg 1D

4acie A. tvant'w/

page 2 of 4

~

5. Dispatch key emergency For incidents involving radioactive materials personnel including monitoring the operations support center coordinator teams and associated communi- will dispatch onsite and offsite monitoring cations.

teams per Onsite Radiological Monitorf ug procedure and the offsite radiologics'.

ronitoring procedure to monitor for possible releases (Plan 4.7.6.2)

The Bureau of Radiological Protection will provide assistance as outlined by their plan contained in Appendix 8 of Annex E, the State Plan.

The five affected counties under the direction of PEMA will provide for dispatch of emergency personnel as outlined in each of the five county plans attached as appendices to the state plan.

PEMA will act as the emergency broker to meet unmet needs by assigning state resources and requesting the Federal Emer-gency Management Agency to assist in fullfillment of meeting those " unmet needs".

6. Dispatch other emergency PEMA has established the procedure for the personnel to duty stations rapid dissemination of information, the within 5 mile radius and assembly of key personnel and the provision

,, alert all others to standby of equipment, stations.

Upon instruction from PEMA the director of the affected county E.O.C. will order that all police patrol units be advised of the conmition that exists. Secondly, the l

E.O.C. communications will activate Fire and Ambulance Alert tones and sirens and advise

• these personnel of the emergency condition in effect.

Response of emergency personnel to designated duty stations and standby status will be as per contingency plan outlines continued in the county plans submitted to PEMA.

7. Provide offsite monitoring r;sults to licensee and The Bureau of Radiological Protection will conduct incident assessment, determine other and jointly assess protective actions and recommend to the these. 11eensee. The Incident Manager (BRP) will direct all response team activities, assess and document offsite federal response team data and provide for continued communication of all assessment information to the licensee.

Further details available in Appendix 8 State Plan, i

l Revision 2 June 1980 1 Amendment 19

.aat- *, tLont -i 9 page a of 4

8. Continuously assess infor-The Bureau of Radiological Protection (BRP) '

=ation from licensee and responsibilities include maintaining contact offsite monitoring with with the licensee, supplementary environmental, regard to changes to pro- sampling and analysis, situation updating tactive actions already for appropriate state, county and local initiated for public and mobilizing evacuation agencies. It will further be the responsibility of the BRP to alert and resources. advise PEMA emergency operations center through the bureau representative of the need to take protective action, the actions to be taken, the geographic area at risk, and pertinent facility conditions having influence on incident outcome, as well as to recommend withdrawal of protective actions.

These alerts and advisories will be issued by PEMA to the five affected counties.

The counties will advise local agencies of any further actions to be taken.

9. Recommend placing milk The Department of Agriculturs of the State of animals within 10 miles or Pennsylvania vill provide advise to PEMA, i

stored feed and assess need to BRP and affected counties on protective extend distance, actions for livestock including controlled feeding, sheltering and collecting and dis-posal of contaminated farm products.

10. Provide press briefings The public affairs repre entative will perhaps with the

-- report to the Emergency Support Director licensee. and is responsive to the director for the preparation of technically accurate infor-mation for media release (4.3.1.4 item 3).

The Communications Director (Press Secretary-to the Governor) will establish a press office as the principal point of contact in the vicinity of the Emergency Operations Faci-lity, utilizing public information personnel from appropriate state agencies.

In addition the Press Secretary will serve as a spokesperson who will have access to all necessary information and who will establish arrangements for timely exchange of information between PEMA, the licensee and all other appropriate infornation sources. Met Ed will provide a media center to accomodate face to face contact. The Met Ed role is vividly described in Appendix B of the Emergency Plan.

11. Consider relocation to The Crawford Station which is located approxi-alternate E.O.F. if actual mately three miles north after TMI site, dose accumulation in near serves as the backup location for the near site E.O.F. exceeds lower site E.O.F. (Plan 4.7.2.2) bound of E.P.A. PACS.

Revision 2 June 1980

_ . . _ - - - - - Amendment 19 _ _

iasie 4; Wont'u.)

. pago 4 .g 4 ,

The Emergency Support Director will have the authority to initiate a move to the backup near site E.O.F. This initiation will take place upon recommendation of

, the RAC or EAC.

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Cirrutt Plan Reference leication Cossemica t or Estension(s) Information Transnitted Den t ena t ime _ ,

Baciteret t erint es ll) Factgency Direc- Plan 4.7.5.9 m) Shift super- rmer genc y Dir ec t or a) Connecta 38 caergency notificatime system 4) MAWAS l.ine FtJ1A tor's Auto-Dialer visor's Office to appoint a pliones to cont rol b) pauphin Scanner Pimne tFive Affer- Corgeom lra t or tone. Nomhers Mmitor ted Coimt les t listed: r) 5 At lec te.1 Comit ten l) fella dut y of- provided witte tane-ficer. ac t ivat ed open-clie -

2) 5-county , net on operatnt's E.O.C. frequency

3) State police 1) Canvent ional plumes

4) Medical factl-I itlen

5) Other assortee' essentist staff I2) Environmental Plan 4.7.5.5 m) Near-stte uC (r.oF) a) Environmental environmental data entlected frena) operator's base sta-

. Asse ssment Line E.O.F. Control Room (RAC) Asseenment Com- fleid monitoring teams tion and portable h) Control Room Seaf or Staf f itemi er mand Center radios.

. . _ _ _ _ _ _ _ (Comma.nni CentecL.

13) Radiological Field Plan 4.F.5.12 m) Control Room a) fleid rad ammi- transmission of field radiologt- m) conventional plmac j Honttoring IJni t I stAC (FCC) toring teams, viscal information for analysts.

Radin Comummira- b) Near-nite operator's .

IIDIEt Approximately 4-6 Imure tions E.O.F. MC (f 0F) portable radios aTTer initiation of the emer-j c) Unit 2 Contro in contact witti gency response network all com-Room bane stations. mmications will be through the j EA Command Center under the tirection of the E.A.C. (See Finn).

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! 14) Environmental rian 4.7.5.12 .) go,gronmental a) environ = ental transatsolon of environnental i) conventional phonen i

Field nmttoring Assenseent Senior Staff Hembu field membu Perturbation information for 3) C.R. Radian

] Radio Cnewmemtra- Commiand Cnienand Center monitortnr. temma evaluation.

J tfon* Center via operators i por t able- radios

! in contact witta i

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Amendment 19':

t TABLE 19 ,

EMERGENCY PLAN IMPLENENTING PROCEDURES NORMALLY UTILIZED FOR EAcil EMERGENCY CLASS Emergency C'assification Procedure Unusual Number Site General Procedure Title Event Alert Emergency Emergency 1004.1 Unusual Event X 1004.2 Alert -

X 1004.3 Site Emergency X 1004.4 General Emergency X 1004.5 Communications and Record Keeping X X X

1004.6 Assistance and Notification X X X X 1004.7 Projected Dose Calaulations 1004.8 Liquid Release Calculations X X _ X X X _ X 1004.9 II.P. Controls During Emergencies X X X 1004.10 Onsite Radiological Monitoring X X X

1004.11 Offsite Radiological Monitoring X X X i 1004.12 Environmental Monitoring X X 1004.13 Monitoring / Controlling Sump Discharges X X

1004.14 Controlling Liquid Discharges X X 1004.15 Post-Accident In-Plant Sampling X X X 1004.16 Radiation overexposure and Decontamination X 1004.17 Personnel Accountability X X 1004.18 Search and Rescue 1004.19 Evacuation of Onsite Areas X X 1004.20 Personnel / Vehicle Monitoring X X 1004.21 Fire Fighting X X 1004.22 Tornado /Illgh Winds X X 1004.23 Re-entry to Affected Areas X X

$I 1004.24 Recovery Operations X X

$ 1004.25 Training ,

Of lE943 .26 ,Dr, ills h 1004.27

" Activation of Near-site Emergency Operations __ _ _ , , _ _ , ,

.. Facility X X

$ 1004.28 Activation of Technical Support Center X X

X Revision 2 June, 1980

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TABLE 20  !

TYPICAL PORTABLE ENVIRONMENTAL / RADIOLOGICAL MONITORS Instrument and/or Media Sampled Detection Use

1. Mobile Env$ronmental Laboratory (a) Pressurized Ionization Chamber (PIC) Real time gamma radiation, direct readout (b) Noble gas monitors Noble gas detection (c) Meteorological Instrumentation & Wind speed & direction, temperature tcwer (d) Air Samplers (1) Liter grab Noble gas (2) Liter continuous Noble gas (a) Thennoluminiscent Dosimeter (TLD) Beta, ganana radiation (f) Environmental sampling equipment Environmental media sampling

2. Pressurized Ionization Chamber (PIC) Gama radiation

3. Thermoluminiscent Dosimeters (TLD) Beta, gamma radiation

4. Geiger Mueller Detectors Beta, gasma radiation

5. Ge(L1) detector

• Ganana scans

6. Sodium Iodide

• Gamma scans

• - Permanently installed at the Environmental Assessment Command Center I

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Amendment 19 Revision 2 ,_ _ _ June _, l_980 _ _,_ _

9 A P P E .~l D I X A Revision 2 June 1980

-' - - - - - - - - - - - _ _ _ _ . _ .~

APPENDIX B l

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l Amendment 19 Revision 2 June 1980

EMERGENCY PtGLIC INFOR."ATION PLAM FOR TF.E THREE MILE ISLAND NUCLEAR GENERATING STATION June 9, I M O

. b

EMERGENCY PLAN CONTENTS i

.I I. Assignment of Key Responsibilities i

II. Classification of Emergencies '.

III. Unusual Event 1 A. Call-out System )

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B. Information Flow System i C. Information Flow Chart

.I IV. Alert, Site Emergency and General Emergency A. Call-out System B. Information Flow System f l C. Information Flow Chart .

V. Long-term Emergency Response {

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VI. Contingency Plans il VII. Emergency Public Information Plan Continuity i 1

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I. Assignment of Key Responsibilities I

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l Amendment 19 9

I. ASSIGNMENT OF KEY RESPONSIBILITIES This Emergency Public Information Plan requires that several key personnel respond immediately upon notification and accept full responsibility for the operation of the assigned portion of the Emergency Public Information Plan. In this plan, they are designated:

. Public Affairs Manager, who is the primary public information person in the conduct of the Emergency Public Information Plan activities. This, assignment'  ;

is filled' by the (1ana0er-Ti1I Communications. j

. Public Information Writer, to draft official statements and reports, a function to be filled by the Administrator TMI Public Information.

. Community Relations Manager, to assure timely dissemination of public information to government officials, a function performed by the Manager-TMI Public Affairs.

. Information Trailer Supervisor, who serves as the conduit for all approved information from its source to the points of distribution to the various audiences.

This assignment is filled by the Supervisor-TMI Observation Center.

. Public Information Duty Person, who is the public information staff person on call as listed on the respective control room duty lists.

. Director-Governmental Affairs, who is the station's representative to state elected officials in Harrisburg. This position is filled by the Registered l Lobbyist in Harrisburg.

l

. Emergency Public Information Plan Coordinator, who will remain cognizant of

{ all situations and personnel changes that would impact the plan's content and ability to function. This assignment will require regular personal contacts with personnel directly involved and prompt comunication of any l

changes to holders of the Emergency Public Information Plan.

l Amendment 19 l

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I. ASSIGNMENT OF KEY RESPONSIBILITIES (cont'd)

. Senior TMI Official, who will provide senior management's final review of a public statement before its release. This assignment will be filled by an individual at the level of Unit Vice President or above.

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1 Amendment 19.

II. Classification of Emergencies e

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Amend:nent 19

II. CLASSIFICATION OF EMERGENCIES UNUSUAL EVENT: The occurrence of an event or events that indicate or allow recognition of a potential degradation of the level of safety of the plant and shall also include contaminated injuries of plant personnel which require off-site emergency treatment. -

ALERT: The occurrence of an event or series of events that indicate and allow recognition of an actual or potential substantial degradation of the level of safety of the plant.

SITE EMERGENCY: Accidents in which actual or likely major failures of plant

, functions needed for protection of the public have occurred.

This emergency class includes accidents which have a significant radiation release potential.

GENERAL EMERGENCY: Accidents which involve actual or imminent substantial core degradation or melting with potential for loss of reactor building (containment) integrity, and other accidents that have large radioactive release potential such as fuel handling and waste gas system accidents.

1 Amendment 19 l

III. Unusual Event A. Call-out System B. Information Flow System C. Information Flow Chart Amendment 19

III. UNUSUAL. EVENT A. Call-out System With the declaration of an Unusual Event, the Manager-THI Communications or the TMI Public Information Duty Person on call is notified by the control room personnel according to control room emergency notification procedures.

When the TMI Public Information Duty Person on call is notified, he should imediately contact the Manager-TMI Comunications and relate the information passed to him by the control room. If the Manager-TMI Comunications is unavailable or cannot be contacted, his responsibilities will be assumed by the Public Information

'iriter.

When the Manager-TMI Comunications is notified by the control room or the Public Information Duty Person, he will assume his responsibility as Public Affairs Manager and will call:

1. Administrator-Public Informatir,n, or his designated alternate, whose emergency responsibility is che Public Information Writer, assigned to the affected TMI control room during an Unusual Event.

2. The Manager-TMI Public Affairs, or his designated alternate, whose emergency responsibility is Comunity Relations Manager.

3. Observation Center Supervisor, or his designated alternate, whose emergency responsibility is Information Trailer Supervisor only if the emergency deteriorates beyond an Unusual Event.

4. Vice President-GPU Service Corp., or his designated alternate, who is responsibile for the emergency comunications among GPU. System management.

A:nendment 19 n

III. UNUSUAL EVENT A. Call-out System (cont'd)

The Community Relations Manager calls personnel who normally function as the TMI Public Affairs staff and the Director-Governmental Affairs. Under Unusual -

Event conditions, the Community Relations staff, based in the Zubey House, will report there to begin contacting public officials representing the TMI area.

The Zubey House is located next to the Collins substation, along Route 441, less than one mile south of the TMI south bridge, and south of Falmouth.

The Information Trailer Supervisor, after being contacted by the Public Affairs Manager, calls the information coordinators normally assigned to the trailer adjacent to the TMI Observation Center.

Upon notification by the Public Affairs Manager, the GPU Service Corp. Vice President Communications notifies GPU officers and his subordinates, who will then contact the Communications Services Departments of the operating companies.

s Amendment 19

. - . . . _ _ . _ _ _ . _ _ . _ _ . . _ . _ _ _ _ A . _ _ _ _ _ _ . . _ . . _ . _ .

\

III. UNUSUAL EVENT _

'l B. Information Flow System With the completion of the Unusual Event call-out procedure, the Public l

Information Writer reports to the Shift Supervisor's Office adjacent to the i

affected control room. The Public Affairs Manager and his staff report to  !

their normal work locations in TMI Trailer 17. I In the Control Room / Shift Supervisor's Office, the Public Infonnation Writer l will:

1. Obtain information available from technical personnel on duty, paying particular attention to radiological controls and environmental assessment activities.

2. Call the Public Affairs Manager to inform him of basic information.

3. Write news statement in or near Shift Supervisor's Office and verify statement's accuracy with appropriate personnel and relay to Trailer 17.

4. Repeat process as events warrant, maintaining contact with Trailer 17 at least every 30 minutes.

When the Public Affairs Manager receives dictated text from the Public Infonnation Writer, he will:

1. Secure statement approval from the Senior TMI Official.

2. Notify GPU Comunications Services office in Parsippany, N.J.

3. Notify Dauphin County Emergency Preparedness Office, the Public Information Officer of the Pennsylvania Emergency Management Agency, and the NRC Region I Public Affairs Officer, noting time of statement. Log these calls.

4. Dictate or telecopy text to Comunity Relations staff in Zubey House, whic.. notifies public officials at direction of Comunity Relations Manager.

Log the calls as necessary.

^ *"d """ 19 III. UNUSUAL EVENT i.

Information Flow System (cont'd) k-B. I

5. Notify local media beginning with wire services based in Harrisburg, noting [

time of statement. Log these calls.

6. Arrange and announce press briefing with Senior TMI Official.

7. Repeat process for each subsequent statement until Unusual Event deteriorates, requiring establishment of the Near-Site Emergency Operations Facility (EOF), or until. the Unusual Event is terminated.

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s' Amendment 19 1

/

III UNUSUAL EVENT C. Information Flow Chart Control Room Public Information Writer g/

TMI Trailer 17 PEMA, NRC

( Public Affairs Manager > Community Relations Dauphin County Staff Public Affairs Offices .

Y Sr GPU Parsippany Media Public Officials I

V l Operating Companies  !

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Amendment 19

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, + , , , - - , ,, ,-a-,-w,, -,-4 - - , , - . - . - ,

i IV. Alert, Site Emergency and General Emergency A. Call-out System B. Information Flow System .

C. Information Flow Chart 4

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i Amendment 19 i

I _ _ _ - , - . . . . . . . - . . - - - . - - - - - - - ~ - - - - - ~ ~ - - - - - - - - - - - - ~ ~ - ' -

IV. ALERT, SITE EMERGENCY _ 1GENERAL _ EMERGENCY A. Call-out System Upon notification from the affected control room, or from the Public Information Duty Person, the Manager-THI Communications or his designated alternate assumes - - -

the responsibilities of the Public Affairs Manager and contacts the Administrator-TMI Public Information or his designated alternate who becomes t Public Infonnation Writer.

The Manager-TMI Communications, who has assumed the Public Affairs Manager duties for the emergency, contacts the Manager-TMI Public Affairs or his designated alternate who becomes Community Relations Manager.

The third call by the Public Affairs Manager goes to the Observation Center Supervisor or his designated alternate who becomes the Information Trailer Supervisor.

The fourth call by the Public Affairs Manager goes to the Vice President-Communications of GPU Service Corp. or his designated alternate.

The Administrator-TMI Public Information, Observation Center Supervisor, Manager-TMI Fublic Affairs and GPUSC Vice President-Communications notify their respective staffs, directing them to their respective work locations.

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_ g, Amendment 19

IV. ALERY, SITE EMERGENCY, GENERAL EMERGENCY B. Information Flow System Under Alert, Site Emergency and General Emergency conditions, information flows from the affected control room to the Near-Site Emergency Operations Facility (EOF) where the Public Affairs Manager and Public Information Writer are assigned.

The Public Affairs Manager and the Public Information Writer will transmit approved statements concerning the emergency to the PEMA Public Information Officer, the NRC Public Affairs Officer and the Dauphin County Emergency Preparedness Office.

The Public Affairs Manager and/or the Public Information Writer will also cooperate with requests for short interviews by news representatives visiting the Information Trailer, located next to the Observation Center. These interview requests will be channeled through the Information Trailer Supervisor. The Public Affairs Manager will determine whether interview requests can be accommodated and whether he or the Public Information Writer will participate in the interviews.

The Public Affairs Manager will assure that the Infonnation Trailer Supervisor has the latest approved statement for designated distribution. He also will assure that the latest approved statement is distributed promptly to the media.

The Public Affairs Manager will counsal the Infonnation Trailer Supervisor periodically on routine and non-routine activities in the EOF.

The Information Trailer Supervisor will transmit the approved statement to the Community Relations Manager at the Zubey House, who insures that the statement is passed to the Director-Governmental Affairs and to designated public officials.

The Information Trailer Supervisor also transmits the approved statement to the Media Center located at Crawford Station, where it is distributed to media respresentatives at that location.

Amendment 19

IV. ALERT, SITE EMERGENCY, GENERAL EMERGENCY B. InformationFlowSystem(cont'd)

The Information Trailer Supervisor also transmits the statement to the GPU Vice President-Comunications office, who in turn relays the information to the GPU officers and Communications Services Departments in the operating companies.

• m O

Amendment 19

% . - _ _ - _ _ . - ~ _ _ _ _ .___ _ _ _ _ _ _ _ _ . _ _ _ _

g .

A_LE a T SITE EMERGENCY, AND CENERAL'EMERCENCY

_C . Information Flow Chart Control Room

+ '

Interviews by PDtA, NRC / u1e a rs h ger, EOF A Dauphin County N e Public Information Writ [

Public Affairs Offices or senior THI official V

Public Information Trailer V

Zubey House

) Covemmental Affairs . Media Center

+

Public Officials g . +

Media 9

V GPU Parsippany V

GPU Officers Communications Services Departments at Operating Co=panies Amendment 19

V. Long-term Emergency Response m.

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oo" Amendment 19

V. LONG TERM EMERGENCY RESPONSE When it becomes apparent that the emergency will become long-term, it will be necessary to plan for the continuation on a 24-hour shift basis for all the same duties and responsibilities to be met.

It will be the responsibility of the GPU Service Corp. Manager of Public Affairs in Parsippany, New Jersey, to coordinate the assignment of personnel from throughout the GPU System Companies to report to Three Mile Island. The GPUSC Manager of Public Affairs, in conjunction with the Public Affairs Manager in the EOF, Community Relations Manager, and the Information Trailer Supervisor will set the time for changing of shifts and assure the notification of personnel to report as relief personnel.

As the emergency becomes long-term, it will be necessary to arrange for informational briefings and tours for appropriate concerned connunity and governmental officials. It will be the responsibility of the Connunity Relations Manager and the Director-Governmental Affairs, to plan and arrange the briefings and to determine the need and advisability for tours. When tours are scheduled, tour arrangements and security clearances will be coordinated by the Information l Trailer Supervisor.

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- _ _ . _ _ - . _ __ ___ -13__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ , _

i VI. Contingency Plans i

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VI. CONTIrlGENCY PLANS j

In the event emergency conditions prevail that eliminate the availability l

of the Observation Center and other locations mentioned in this plan for Emergency Public Information use, all Public Affairs personnel, except the Public Affairs Manager and the Public Information Writer, will report to the Consumer Servic The Public Affairs Manager and the area of the Met-Ed Lebanon Division Office.

Public Information Writer will report to the backup E ergency Operations Facili The first backup facility for the EOF is designated as Crawford Station.

(EOF).

Should conditions such as weather or geographic location of a disastrous eve eliminate access to the Lebanon Division Office, Met-Ed's Western Division O in York will be used for public infm. nation activities.

All facets of the plan will be carried out as defined but at the contingency location.

In the event that Crawford Station is used for certain extraordinary activiti related to an emergency, all personnel not involved with those activities must be allowed to mingle or in any way interfere with those activities.

In such a case, all non-essential traffic between the Media Center and other parts of the building will be prohibited.

1 I

1 Amendment 19

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VII. Emergency Public Information Plan Continuity i

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Amendment 19

i VII. EMERGENCY PUBLIC INFORMATION PLAN CONTINUITY _

Concern for the continuity of this Emergency Public Information Plan is vital.

To assure that all aspects of the plan remain current and viable, the obligation f

to monitor and update the plan continuously will be the responsibility of the  !

j i

&nergency Public Information Plan Coordinator.

The responsibility to carry out this continuing assignment is an integral  :

p:rt of the permanent position description for the Administrator-TMI Public ,

f Information.  ?

RESPONSIBILITIES AND ACTIONS f

1. The Emergency Public Information Plan Coordinator must know the plan's impact  :

on all participants and review the plan once a month to verify its ability to function effectively.

2. The Coordinator, in daily operations, must recognize all events and changes throughout the Company (ies) and question the impact on the Emergency Public Information Plan. Among considerations are changes in:

(a) Policies (b) Personnel (c) Facilities, whether new, retired, altered, etc.

(d) Community officials, services, facilities, etc.

3. A master copy of the Emergency Public Information Plan will be maintained, and necessary changes made immediately upon recognition and confirmation of the need for such changes.

4. A record of all persons having controlled copies of the Emergency Public Information Plan will be maintained.

Amendment 19

m VII. EMERGENCY PUBLIC INFORMATION PLAN CONTINUITY (cont'd)

5. At least annually, the Emergency Public Information Plan Coordinator shall l 1

conduct programs to acquaint the mass media with the Emergency Public Information Plan, infonnation concerning radiation, and points of contact -

for release of public information in the event of an emergency.

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A P P E ;l D I X C t

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Amendment 19 Revision 2 f..n o 1oco

!~

GENERAL f

.TJr PUBLIC UTILITIES CORPORATION 100 Inerpace Pa6way ParsDoany. New Jersey 07054

. 201 263-6500 TELEX 136-4G2 Wrner's Drect Deal Nurnber-January 21, 1980 Mr. Herman M. Dieckamp Acting President, Metropolitan Edison Company P. O. Box 542 Reading, PA 19603

Dear Mr. Dieckamp:

In the licensing of nuclear power plants such as Three Mile Island Generating Station, the Nuclear Regulatory Commission requires the operating utility company to obtain letters of agreement from other organi:ations which are willing to provide assistance in the event of an emergency. .

As Chairman of the Board o'f General Public Utilities Corporation and GPU Service Corporation, President of Jersey Central Power 6 Light Company, and President of Pennsylvania Electric Company, we, the undersigned, hereby agree on behalf of our respective organizations that these organizations will provide assistance upon the request of Metropolitan Edison Company in the event of an emergency at Three Mile Island Generating Station. This assistance will consist of appropriate personnel and equipment to the extent they are available.

j Sincerely, P

GENERAL PUBLIC UTILITIES CORPORATION AND GPU SERVICE CORPORATION By fa airman W. G . KtfEs ,

h-lor the Board JERSEY CENTRAL POWER S LIGHT COMPANY By /Md S. Bartnoff 'Qresident PENNSYLVANIA ELECTRIC COMPANY

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By

%Y,b l W. A. Verrochi, President Jene e Ce~ ,r oce.e $, t 29r Cc-ca~. rr.v cocN3a E: ce C meanc 'Pevmaa a E+- r Com:a

' nacrgancy .R:si:cnse File Original - Iarcy Harding

[l ' :,]I-PENNSYLVANIA EMERGENCY MANAGEMENT AGENCY P.O. SOX 3321 V HARRi$4URG, PENN$YLVANIA 17103 January 3,1980 Mr. J. G. Herbein l* Vice President Metropolitan Edison Company P.O. Box 542 Reading, Pennsylvania 19603

Dear Mr. Herbein:

Pursuant to the provisions of Subchapter B of the Emergency Management Services Code, PL 1332 (Act 1978-323), the Comonwealth i

Government has, in the " Disaster Operations Plan", outlined its

' basic plans for emergency operations to include actions associated with possible radiation accidents occurring at nuclear power stations located within the State.

Insofar as Metropolitan Edison's Three Mile Island Plant is concerned, we are pleased to tell you that the Dauphin, Lebanon, Lancaster, York and Cumberland County emergency management o'ganizations,

.. which are legally recognized governmental agencies established pursuant to the provisions of State law, are actively working with us in the current planning. Further, in consonance with existing statutes, these organizations have pledged full and active assistance in all emergency operations which might be necessitated by nuclear radiation incidents occurring at Three Mile Island.

We appreciate Metropolitan' Edison's assistance in the present planning effort and shall keep you informed of future developments in the matter.

. Sincerely, Oran K. Henderson Director OKH:jmb (717-783-8150)

Amendment 19

i t

Mr. John G. Herbein Vice-President - Met-Ed t

L tropolitan Edison Company ,

P. O. Sc.- 5^2 Reading, Pennsylvania 19603

'l

Dear Mr. Herbein:

I Tn i s is to advise you that, upon notification by you or your designee of an emergency situation existing at the Three Mile Island Nuclear Station, we will provide assist ance as available. Any assistance offered will be in accordance with tnat outlined in the i.enannn i:nunty Lnerxeucy Plan as submitted to the Pennsylvania uercency Mn.7.-eencat Agency.

i Very truly yours, Clyde H. Miller, Director Lebanon County Emergency Management Agency Room #14 Municipal Building Lebanon, Pa. 17042 l

l Da:e: Signed:

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Amendment 19

w; les to:

G. Gicngi/D. BigbO3 G. J. Troffer Original - L. V. Harding copy to emergency response file Mr. John G. Herbein Vice-President - Met-Ed Metropolitan Edison Corepany P. O. Box 542 Raading, Pennsylvania 19603

Dear Mr. Herbein:

his is to advise you that, upon notification by you or your designee of an emergency situation existing at the Three Mile Island Nuclear Station, we will provide assistance as available. Any assistance offered vill be in accordance with that outlined in the Dauphin County Emergency Plan as submitted to the Pennsylvania Emergency Management Agency.

Very truly yours, Kevin J. Molloy Director Office of Emergency Preparedness.. .,

Dste: Signed:

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w-Amendment 19

I l

Mr. John G. Herbein

.Vice-President - Met-Ed Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania 19603-

Dear Mr. Herbein:

This is to advise you that, upon notification by you or your designee of an emergency situation existing at the Three Mile Island Nuclear Station, we will

, provide assistance as available.

Very truly yours, l

Date: Signed:

AYs2/ d_ JW

.:/ Director, Ynr ty Smergency operations Center l Courthouse, York, Pa. 17401 i

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l Amendment 19

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' h Courrty fmeraeru:r thee;;ement Dept 50 N. Dohe Snec Lancaster, PA 17606 I

1 Mr. John G. Herbein Vice-President - Met-Ed Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania 19603

Dear Mr. Herbein:

This is to advise you that, upon notification by you or your designee of an

' emergency situation existing at the Three Mile Island Nuclear Station, we will provide assistance as available.

Very truly yours,

{

Date: Signed:

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Paul L.Leese Director / Coordinator Lancaster County F.:nergency Depart:::en:

.~ 50 ::. Duke St.

lancaster,7a. 17602 Amendment 19

e

tr John G. Herbein Vice-President

letropulitan Edison Company

• O . Bo.v. 542 neading. Pennsylvania 19603

Dear Mr. !!crbain:

This is to advise you that, upon notification by you or your designae of an vmergency situ'ation existing at the Three Mile Island Nuclear Station, we will

, provide assistance as available and out1ined below:

. Approximately .U.'8 b~ men for firefighting and rescue assignments

~ .:. AppruximatelySEE 3&*d pieces of airefighting equipment.

. Approximately C men and _, O ambulances or rescue vehicles for emergency medical services.

. Other specialized services or equipment as listed below:

- ]90 &

l W M

- L.a A c>i .bwlenlA4; M d MJDf J Very truly yours.

D-7 h d N Me o. @'iI *[Ng,c,'

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/ Amendment 19

Mr Jolm C. lierbein Vice-President Metrupulitan Edison Cumpany P.O. Box 542 keading,, Pennsylvania 19603

Dear Mr. Herbein:

This is to advise you that, upon notification by you or your designee of an emergency situation existing at the Three Mile Island Nuclear Station, we vill provide assistance as available and outiined below:

t. Approximately L *>~ mun for firefighting and rescue assignments

. ' . Appruximately 1 pieces of Iirefighting equipment.

J. Appruximately /O men and /

for emergency medical services. 9 ' - -- or rescue vehicles 4 Other specialized services or equipment as listed below:

1.5 c . 7 #l ..

Very truly yours, WLcWw

Title:

6 /1/ 6 d'

.;a t e :

Organization: hsf/ en /MC5 e b6 l

Amendment 19

.Ir John C. lierbein Vice-Presid ent llutropolitan Edison Company P.O. Box 542 Keading, Pennsylvania 19603

Dear Mr. Herbein:

This is to advise you that, upon notification by you or your designae of an emergency situation existing at the Three Mile Island Nuclear Station, we vill provide assistance as available and outiined below:

1. Approximately l_ 5~ men for firefighting and rescue assignments

.! . Approximately 1 pieces of nirefighting equipment.

J. Approximately /O men and / andpu2;sucaw or rescue vehicles for emergency medical services.

4 Other specialized services or equipment as listed below:

l] c ..:.7 #l Very truly yours, WAk,~ckJw

Title:

0 $ /6 d Date: Organization: Osf/on /MOS e do

~.

Amendment 19

I

. MAY 181980 Londonderry Fire Company, No.1 "*'",.

Londonderry Township. Dauphin County A w

oR A D P. O. Box 324 VOLUNTEER MIDDLETGWN. PENNSYLVA NIA 17057 COMPANY MAY 15, 1980 cop ies to:

Mr. John G. Herbein Vice-President Emergency Response Metropolitan Edison Company File P. O. Box 542 S. Polon Readin6, Pennsylvania 19603 original: D. Mitcheli

' J. G. Troffer l!

Dear Mr. Herbein:

This is to advise you that, upon notification by you or your desi5 nee of an emer5ency situation existin6 at the Three Mile Island Nuclear Station, we 'will provide assistance as available and outlined below:

1. Approximately 35 men for firefi 5htin6 and rescue assignments

2. Approximately 4 pieces of firefighting equipment.

3. Approximately 20 men and 1 ambulances or rescue vehicles

. for emer6ency medical services.

4 Other specialized services or equipment as listed below A. Our company has indicated their willin6 ness to render services to radiation contaminated personnel.

B. Our company has access to the services of a foam truck.

i l Ver Trul ours,

~

John L. Dodson Fire Chief Londonderry Township Fire Company Amendment 19

a copies to: G. Giangi/D. Bigbee G. J. Troffer s-S. Polen Original: D. G. Mitchell Mr John G. Herbein Vice-President McCropolitan Edison Company P.O. Box 542 Reading, Pennsylvania 19603 D ear .'Ir . Herbein:

This is to advise you that, upon notification by you or your designee of an emergency situation existing at the Three Mile Island Nuclear Station, we will provide assistance as available and outlined below:

, s-

1. Approximately zo men for firefighting and rescue assignments

2. Approximately $l pieces of firefighting equipment.

3. Approximately _J- men and / ambulances or rescue vehicles

'or emergency medical services.

l I

4 Other specialized services or equipment as listed below:

transcortation of enntaminated iniure! sernnne

. cry truly ycurs, I

T1 Tie: h /@ f.

2 An Date: // Organization: /L i x[ c . / E C(

7

.I y t

l Amendment 19

, ,_ 944.46a4 BOROUGH OF MIDDLETOWN APR 30 ISH COMMUNITY BUILDING. MIDDLETOWN. PENNSYLVANIA 170$7 April 23* 1980

' ** * *

• O'*"8 * "I8 **

G. J. Troffer Emergency Plan File Original: L'. W. Harding Mr. Dennis McClousky P. O. Box 480 Middletown, PA 17057

Dear Sir:

In response to your telephone conversation about a firm comitment from our Department in the event that you need assistance, I would like to state that Middletown has a 13 man department. What this means is that we have 4 men on each shift; with relief days, this comes out to 3 men per shift.

To give you a firm commitment as to how many men and cars we can supply would depend on the type of problem. If the problem is security only, we could commit one car and one man. If the problem would involve the community, then my men would be committed to the town.

Our Department works with the Pennsylvania State Police and if they request assistance, I would do my best to supply any help that I feel would help you, without cutting police protection within the Borough of Middletown.

If you have any questions, feel free to call me.

l Sincerely, BOROUGH OF MIDDLETOWN POLICE DEPARTMENT 1

.' ntf hila l) ) . s-George M. Miller Chief of Police GtWcin l

Amendment 19

A l' y\

G-

.. - _ x y- COMMONWEALTH OF PENNSYLVANIA f)' -

, DEPARTMENT OF ENVIRONMENTAL RESOURCES .7-P. O. Box 2063 W - ~

Harrisburg, Pennsylvania 17120 (717)787-2480 May 23, 1980 Mr. John Herbein Vice President Metropolitan Edison Company P. O. Box 542

Dear Mr. Herbein:

This responds to a recent request for updating our letter of support to your company for the management of off-site consequences of radiation accidents at 'uree Mile Island Nuclear Station Units 1 and 2.-

The role of this agency in the event of such episodes remains unchanged; that role being one of accident consequences assessment and technical advisement to state and local civil defense. This condition will prevail unless and until our staffing should change substantially in a negative directio:a. In that event we will advise you accordingly.

We believe that our response on March 28, 1979, verifies this commitment, i

lj Thank you for your continuing interest and cooperation in

l this matter.

t j Sincerely yours, i

i .' W '

Thomas M. Gerusky, Director Bureau of Radiation Protecti l

l l

l 1

l t

, Amendment 19 1

s

' G. Troffer T)

1. s

"# M S. Polon Original - Roy Harding CoMMoNwCALTH of PENNSYLVANIA PENNSYLVANIA STATE POUCE 8800 cLMcRTON AVtNut

(-

, oANIEL F QUNN H ARRISBURG. PA. t7809 l co==es s eon c a May 22, 1980 Mr. John G. Herbein Vice President, Met-Ed Metropolitan Edison Company Post Office Box 542 Reading, Pennsylvania 19603

Dear Mr. Herbein:

As you are aware, Annex E to the Commonwealth of Pennsylvania Disaster Operations Plan sets forth the Commonwealth's emergency response plans for fixed nuclear facility incidents. The Pennsylvania Emergency Management Agency ("PEMA") has been delegated authority to coordinate development of Annex E, including identification of responsibilities of the various state agencies. Those responsibilities delegated by PEMA to the Pennsylvania State Police are set forth in section IX.A.9 of Annex E.

This is to advise you that, in the event of an emergency at the Three

, Mile Island Nuclear Station, the Pennsylvania Sty.e Police will provide assistance as described in Annex E. Resources available to the State Police in the area of the Three Mile Island Nuclear Station include:

Troop "H" and 500-600 enlisted personnel involving several other Troops.

30-50 civilian personnel (clerks, communicaricus officers, electronic technicians).

275-300 patrol vehicles.

I 1 portable stationary radio.

1 mobile trailer command post.

175-200 portable radios.

3-4 helicopters.

P - % Suu P.4a Amendment 19

Mr. John G. Herbein Page Two May 22, 1980 Rather than constit ourselves to ary specific use of personnel or equipment at this time, I merely wish to say that we would make every effort to cooperate with you. We, of course, must reserve the right to set our own priorities as far as deployment of our personnel and equipment.

Sincerely, l

f

y. M Daniel F. Dunn Conunissioner e

i l

l l

Amendment 19

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- G. Troffer ce uuc:.wtut cr atNwsuv&was ACNNsVLVANIA STATE poLICt . O on isco ctucavow avcusc Emergency Response

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'--- '" Original to: L. W. Harding IC-J/e q May 28, 1980 Mr. John G. Herbein Vice President, Met-Ed Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania 19603

Dear Fr. Herbein:

Please consider this a supplement to my letter to you dated May 22, 1980, outlining the resources available to the Pennsylvania State Police should there be an emergency in the area of the Three Mile Island Nuclear Station.

In response to fear inquiry of this date, please be advised that this department will utilize the amplification system on its helicopters to warn motorists and residents during an emergency. Our intent to use the helicopters for this purpose is, of course, contingent upon the availability of the helicopters. -

As I indicated to you in my May 22, 1980, letter we, of course, must reserve the right to set our own priorities as far as deployment of our personnel and equipment at the time an emergency takes place.

Very truly yours,

/ ( 'Y ^ ('

& j. }&v.y Daniel F. Dunn Commissioner

<. J .,.a s u u =.cae

~

Amendment 19 1

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i DEPARTMENT OF TRANSPORTATION M AhlNG ADDRESS f 1 UNITED STATES COAST GUARD Commander (osr)

' @ .... A 0 Third CG District

'M Copies to: G. Giangi Governors Island G. Troffer New York, NY 10004 Emergency Response File

• Original to: L. W. Harding 3130 22 May 1980 Mr. J.G. Herbein, '

l Vice President Metropolitan Edison Company P.O. Box 480 l

Middletown, PA 17057 Re: Three Mile Island Generating Station Nuclear Plant, Sus-quehanna River, Middletown, Pennsylvania i

i

Dear Mr. Herbein:

This is to ad"ise you tha upon notification by the Station

, Superintendent or his designee of an emergency situation involving a disaster which ha occurred or is impending at the Three Mile Island Generating Station, the Coast Guard will provide its traditional response. It should be under-stood that most of our facilities are located some distance away and are primarily oriented toward response in coastal and maritime arecs. Due to involvement in primary mission areas such as search and rescue, maritime pollution and l fisheries law enforcement, a further delay may be encountered t due to the time that would be involved in recalling and redirecting Coast Guard resources, if warranted, to your area.

I Sincerel ,

R. W. MILLER Captain, U.S. Coast Guard Chief, Search and Rescue Branch Third Coast Guard District By direction of the District Commander I

- e 4

Amendment 19

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,, f :, y , MAY 5 o yggg

• f 6Wl/fN, DEPARTMENT OF THE ARMY G. Giangi g {- g

4TH OCNANCE DETACHMENT (EOD) C. Troffer FCi(T DJDIANTOWN CAP Emergency Response File

-k,1.ye

~; . d.s.//, ANNVI!.LS, PA 17003 Original: Leroy Harding 21 May 1980 Mr. John lierbein -

UP Metropolitan Eddison -

P.O. Box 480 Middletown PA 17057 ATTN: Emergency Planning Dear Mr. Herbein In the event of a bombing or suspected bombing where a specific item is involved, me=bers of the 56th Ord Det (EOD) can respond, after notification by civil authorities, within 90 minutes. A minimum of two technicians are available to render safe any actual or suspected item found. The 56th Ord Det ( F.OD ) and the US Army are not responsible fer destruction of property during render safe procedures. See Inclosure one (Explosive Ordnance Disposal Civil Support Release and Reimbursement Agreement.)

Sincerely. ,

Wk0.

LERUY F.A. DAILEY JR.

e Y-

[

• 2LT, OrdC Commanding l

l i

Amendment 19 l

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... .s..;aK D..ergency Re.sponse File DEPARTI.?ENT OF TRANSPORTATION original to: L. W. iia rding f EDERAL AVIATION AD.'.ilNISTRAll0N AI.RPORT TRAFFIC CCIT.;0L TChTR .

Harrisburg International Ai rport P ;",'."&

213 - Fifth Street if / 7, sh Middletown, Pa. 17057  ?-

' ', .l -w{~f b- o i r

May 20, 1980 . WN I

j Mr. John G. Herbein

. Vice-President - Met-Ed Metropolitan Edison Cor.pany

~

P. O. Box LSO

Middletown, Pennsylvania 17057

Dear Mr. Herbein:

This is to advise you that, upon notification by you or your designee of an ecergency situation existing at the Three Mile Island Nuclear Station, we will provide assistance as follows:

1. Air traffic control to prevent direct over flights of Three Mile Island in case of a radiation release.

Very truly yours, 1=g RAY BYERS 7 Chief of Olmsted Tower file #

w Amendment 19

CONRAIL Original: D. G. Mitchell Copies to: G. Giangi/D. 'digbe

1. _ -- ~ra p- - E EN S. Polon Licensing File April 25, 1980 Mr. J. G. Herbein Vice President Metropolitan Edison Co=pany Post Office Box 480 Middletown, Pennsylvania 17057

Dear Mr. Herbein:

This is in respur.se to your request that Conrail advise you that on a voluntary basis it will, in case of emergency at the Three kile Island Generating Station, cooperate in keeping trains or railroad equipment off the crossing at the entrance to that plant.

_ Upon request by the Station Superintendent, or his designee, that the crossing not be blocked by trains or railroad equip =ent, Conrail will take reasonable steps to cooperate.

Sincerely,

! l

. C. Robins General Manager Eastem Region A=end=ent 19 CCNSoL:

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, Emergency Plan Response Date ,//_ p/ 8.0-cc: :J. .G. Hei tecin, g$i;,> ' , , G. J. Troffer

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%. M, !7 Fi1e: b1.Ut20.0003 Department of Energy drookhaven Atuu Ollico Upton, Now York 11973 516-345-3430 January 4, 1980 ,

Mr. John G. Herbein Vice-President - Met-Ed Metropolitan Edison Company P.O. Box 542 Reading, Pennsylvania 19603

Dear }ir. Herbein:

e

SUBJECT:

METROPOLITAN EDISON COMPANY '

Since your nuclear facility is located in Ruglon L, tla : n s.khaven 'Arca Office is charged with the responsibility for providing i.adiological assistance in the event of an emergency. Sucn assistance can be raquested at all times by calling 516-345-2200 and ask ing for radiological a 4:: 1:at m e c

, indicating the nature of the incident, i hi- I . .c a s i . m . und how to coat.ni

• authorities to coordinate our response.

The Department of Energy (DOE) will respond to requests for radiological assistance from licensees, Federal, state and local agencies, private organizations, or individuals involved in or cognisant of an incident believed to involve source, byproduct, or special nuclear material as defined by the Atomic T.nergy act of A m , a.; amend.d, wr voner ioni:An;-

radiation sources.

Unless the DOE or a DOE contractor is responsible for the activity, ionizing radiation source, or radioactive material involved in an incider.t, DOE radiological assistanc,e will be limited to advice and energencv action essential for the control of'the ic=ediate ha:ards to hesitn and sa:cty.

Radiologic'al emergency assistance will be terninated a: :oon as the ener-gency situation is under control. Therefore, rer.>onsi'1;ity for postincident recovery, including further action .or the protection of individuals and the public health and satcty, should be assumed by the

~

appropriate responsible Federal, state of local government, or private authority as soon as the emergency conditions are stabilized.

Amendment 19

If you feel have free any further to contact me. questions or desire further infor:.stion, Very truly yours, f).. / ,. .

Robert J". Jes.4 Technica Ascistant to the As ca Manager cc:

3. H. Grier, office of Inspection & Enforcement, Nuclear Regulatory Co= mission, Region I G. P. Dix, Division of Operational and Environmental Safety, HQ 6

w Amendment 19

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• UNITED STATES

'o, NUCLEAR REGULATORY Commission 8 3 ,, j REGION I

$ g 531 PARM AvtNUE MING OF PRUSSI A. PENNSYl.V ANI A 19404

\...../ '

Docket Nos. 50-289 JAri 2 81530

~

50-320 e i .

! Metropolitan Edison Company ATTN: Mr. J. G. Herbein l Vice President i P. O. Box 480 i

, Middletown, Pennsylvania 17057 l

Dear Sir:

This is in response to your request for an updated letter regaroing the partici-pation of the Nuclear Regulatory Commission in the event of an energency at the Three Mile Island Nuclear Station.  !

The primary role of the NRC during a radiation emergency is preshtly the conduct of investigative activities associated with the incident, 'terifying that emergency plans and procedures have been implemented, and assuring that the public health and safety are protected. The NRC will also assist in coordination of Federal response resources and provide advisory assistance to State and local agencies concerning investigating and assessing hazards to the public. \

I Various tasks forces, study groups and other ad hoc organizations are reviewing the NRC's role and a different expression may evolve. We will inform you of any changes in our role.

Sincerely, .

l "/

! oyce H. Grier Director cc:

R. C. Arnold, Sr., Senior Vice President G. P. Miller, Manager, Unit 1 J. J. Colitz, Manager Plant Engineering (TMI-1)

R. F. Wilson, Director, TMI-2, l J. J. Barton, Manager Site Operations B. Elam, Manager Plant Engineering (TMI-2)

L. W. Harding, Supervisor of Licensing E. G. Wallace, Licensing Manager I. R. Finfrock, Jr.

R. W. Conrad J. B. Lieberman, Escuire '

. Ms. Mary V. Southard, Chairperson, Citizens for a Safe Environment G. F. Trowbridge, Esquire Amend =ent 19

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WEATHER SERVICE OFFIC4 BOX 1185 HARRISBURG, PA 17100 7 72- 393L Mr. Jahn G. Herbeln *

• Vice-President - Met-Ed Netropolttan Edison Company P. O. hox 54 2 Reading , Pennsylvanta 19603 ,

Dear Mr. Herbeta:

This is to advise you that, upon nettf tcation by you or your designee of an emergency situation existing at the Three Mile Island Nuclear Station, we will provide assistance as available:

1. All severe weather warnings and information.

i l

Very truly yours , -

(f ~e

! C.E. Goodall l Meteorologist in Charge 1

Date: 12/28/79 Sig ned :

1 1

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(/ sn S7 t

Amendment 19

This is to confirm that I agree to the fonoving:

• In the event of an accident at Three Mile Island Nuclear Power Station involving radiation exposure of personnel, I will supply medical assistance on the site and asstse the responsibility for the medical supervision of the patient (s) until he/they arrive (s) at a medical facility such as The Milton S. Hershey Medical Center, Hershey Pennsylvania, or until such time that g services are no longer required; an .

this provided that no other urgent medical duties, in sqr Judgment, preclude air availability for the purpose mentioned above, in which case I will take steps to reduce the period of non-availability to a minimum.

It is understood that a Radiation Emergency Melical' Team vill be dispatched ic=ediately upon notification of a radiation e=argency at the plant by Radiation Management Corporation, Philadelphia, Pennsylvania, and that the physician on this

tes=, upon arrival, will assist me in the duties described above.

Elizabethtown, Pennsv1vania (City and State)

Ill z 9/19 '

(Date) l W %

Miles Newman, M.D.

%_= . As.

Physician Licensed in the State of Pennsylvania, Lic. No. 2 Yg s

t

, Amendment 19

This is to confirm that I agree to the following:

In the event of an accident at Three Mile Island Nuclear Power Star. ion involving radiation exposure of personnel. I vill supply

. medical assistance on the site and assume the responsibility for the medical supervision of the patient (s) until he/they arrive (s) at a medical facility such as The Milton S. Hershey Medical Center, Hershey, Pennsylvania, or until such time that my services are no longer required; all this provided that no other urgent medical duties, in my judgement, preclude my availability for the purpose mentioned above, in which case I will take steps to reduce the period of non-availability to a mini ==.

It is understood that a Radiation Emergency Medical Team vill be e dispatched iz:ssediately upon notification of a radiation emergency

~

at the plant by Radiation Management Corporation, Philadelphia, Pennsylvan,ia, and that the physician on this team, upon arrival, vill assist me in the duties described above.

Highspire, Pennsylvania l

(City and State)

I afi- 49 (Date)

'a w. -w

! William Albright III, M.D.

Physician Licensed in the state of Pennsylvania, Lic. no.

l Amendment 19

I LETTER OF AGREEMENT HERSHEY MEDICAL CENTER E: PRESENTLY BEING DRAFTED BY LEGAL STAFF OF HERSIEY fEDICAL CENTER AM) GPU-NUCLEAR.

SIGNED TO BE SUIMITTED WITHIN l

l Amendment 19

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$h 'k u Keystone November 2, 1979 R

d Mr. J. G. Herbein Vice President 3 Metropolitan Edison Company S

Three Mile Island Nuclear Plant

• N P. O. Box 480 g Middletown, PA 17057 U  ;

Dear Mr. Herbein:

I

< a

', Keystone Helicopter Corporation has been under 5 contract for many years to your company providing G routine and emergency helicopter and airplane service. .

E V We expect to continue to provide this service in the i future. Our current contractual committments are 3

outlined in Purchase Order 61160 C. O. #2 effective April 13, 1979.

\.s As you ara aware the relationship between our companies dates almost twenty years. Through the i years we have provided patrol, survey and personnel y movement in both routine and emergency condition.

% Very truly yours,

@ KEYSTONE HELICOPTER CORPORATION e i k ,

7&bu- /]' W Michael S. D' Aries 8 Vice President / General Manager V

$ MSD/mmd o

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

i

, P cest. 215 893 5353 Page 1 of 2 1

PORTER - GERTZ CONSULTANTS, Inc.

Radiological Protection and Environmental Services 76 RITTENHOUSE PLACE ARDMORE;. PA. 19003 December 3,1979 Mr. Jack Herbein, Vice President Metropolitan Edison Company P.O. Box 542 Reading, Pennsylvania 19640 Re: Porter-Gertz Consultants, Inc. Comitments for Response In The Event of a Serious Emergency at TMI.

Dear Mr. Herbein:

Porter-Gertz Consultants, Inc. can, within three hours of notification, furnish two persons on site at TMI. Then, two additional persons *...a be furnished within another hour. These people would have experier.re in, and could be used immediately for the following task assignmer:,:

- A. On Site

, 1. Radiogas and radioliquid effluent assessment.

2. Assessment of compliance with TMI Tech Specs as far as radioeffluent releases are concerned.

3. Designate and coordinate in-plant sampling requirements, l

4 Coordination of lab instrumentation for effluent assessment.

5. Designa' tion and coordination of required sample analysis for

, effluent assessment.

l

6. Designation and coordination of required effluent sample storage.

7. Interpretation of sample analysis results.

8. Assessment of solid waste radionuclide problems.

9. Special personnel dose assessment studies can be performed.

10. General Health Physics duties, as required, can be performed.

1 Amendment 19

!__ - - - - - - ~ ~~ ~ ~ ~

Mr. Jack Herbein, Vice President Pag 2 2 December 3,1979 B. Off Site Within one hour of a telephone call, the following services can be performed from the Ardmore office of Porter-Gertz Consultants, Inc.:

1. General control of Emergency Radiological Environmental Monitoring Program.

2. Specification of special samples to be taken and special dosimetry to be placed in the field to evaluate the effects of the specific accident.

3. Dissemination of the Emergency Radiological Environmental Monitoring Program data to TMI management, and to the agencies so designated by TMI management.

4. Taking of samples in the TMINS environs (s2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).

5. Coordination, evaluati]n and statistical interpretation of the Emergency Radiological Environmental Monttoring Program data.

Sincerely, NW r r ,

Sydney W. Porter, J .

President SWP:mgh cc: 6 W. Riethie R. DuBiel P. Ruhter S. Gertz Amendment 19

APPENDIX D THROUGH I These sections are available on site.

Revision 2 Amendment 19 June 1980

. _ . -- ._ _-.