ML19347F313

Amend 33 to Application for Ol.Contains Revision 4 to Emergency Plan

ML19347F313
Person / Time
Site:	Susquehanna
Issue date:	05/15/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML18030A282	List: ML18030A281 ML19347F313
References
NUDOCS 8105180339
Download: ML19347F313 (225)

Text

BEFORE THE (o~;

UNITED STATES NUCLEAR REGULATORY COMMISSION 4

In tholStter of PENNSYLVANIA F0WER & ,

Docket Nos. 50-387 and 50-388

, LIGHT COMPANY AMENDMENT NO.33 APPLICATION FOR CLASS 103 OPERATING LICENSES FOR THE SUSQUEHANNA STEAM ELECTRIC STATION UNITS NO. 1 AND NO. 2 Applicant, Pennsylvania Power & Light Company, hereby files Amendment No. 33 to its Operating License Application dated July 31, 19/9.

This amendment contains Revision No. 4 to the Susquehanna SES Emergency Plan.

PENNSYLVANIA POWER E LIGHT COMPANY

! BY:

A"M) N. W. CURTIS N. W. Curtis Vice President-Engineering & Construction' Sworn to and subscribed before me this e o f May , 1981.

Notary Public My Conunission Expires:

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AMENDMENTS TO

, ('s SUSQUEHANNA SES LICENSE APPLICATION V

AMENDMENT CONTENT 1 , Revision No. 1-FSAR

' A.

2 Revision No. 2-FSAR 3 Revision No. 3-FSAR 4 Revision No. 1-ER-OL U S Revision No.'4-FSAR 6 Revision No. B-Security Plan 7 Revision No. 5-FSAR 8 Revision No. 6-FFAR J

9 Revision No. 7-FSAR 10 Revision No.' 8-FSAR.

t (Proprietary) 11 Revision No. 9-FSAR 4

. 12 Revision No. 2-ER j 13 Revision No. 10-FSAR

() 14-15 Revision No. 11-FSAR Revision No. C-Security Plan

'16 Revision No. 12-FSAR 17 Revision No. D-Security Plan l :'

18 Revision No. 13-FSAR

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19 Revision No. 1-Emergency Plan 20- f# Vision No. 14-FSAR i 21' Revision No. 15-FSAR 3 22 Revision No. 16-FSAR 23 Revision No. E-Security Plan 24 Revision No. 17-FSAR j 1

25 Revision No. 2-Emergency Plan f 1-  !

l 26 Revision No. 18-FSAR l 27- Revision No. 19-FSAR l- l

28 Revision No. 3-Emergency Plan '

1 j 29 Revision No. 20-FSAR  !

l 30 Revision No. 21-FSAR I j -

31- Revision No. 22-FSAR 32 Revision No. F-Security Plan 33 . Revision No. 4-Emergency Plan i

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EMERGENCY PLAN REVISIONS O

The attached Revision 4 pages, tables and figures revise the Susquehanna Steam Electric Station Emergency Plan.

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TAB 9.0 TAB 9.0

-(RECOVERY) (RESTORATION) 1 9-1 9-1 9-2 9-2 Figure 9.1 Figure 9.1 4

APPENDIX A Letters From:

Radiation Management Corporation

Pond liill-Lily Lake Fire Company i Aabulance Service i

livbbic Volunteer Fire Company

, Nescopeck Ambulance Assn.

Institute of Nuclear Power Operations APPENDIX D Enclosure 10 Enclosure 10 (1 Page) (5 Pages)

I APPENDIX I

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Appendix I Appendix I (Text, Tables & Figures) (Text, Tables & Figures)

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O PENNSYLVANIA POWER S LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN REVISION I4 MAY, 1981 O

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's ,/ TABLE OF CONTENTS SECTION TITLE PAGE 1.0 DEFINITIONS 1-1 2.0 SCOPE AND APPLICABILITY 2-1 ,

3.0

SUMMARY

OF EMERGENCY PLAN 3-1 4.0 EMERGENCY CONDITIONS 4-4.1 CLASSIFICATION SYSTEM 4-1 4.2 SPEC 1 RUM OF POSTULATED ACCIDENTS 4-6 i

5.0 ORGANIZATIONAL CONTROL OF EMERGr.NCIES 5-1 5.1 NORMAL OPERATING ORGANIZATION 5-1 5.2 ON-SITE EMERGENCY ORGANIZATION 5-1 5.3 AUGMENTATION OF ON-SITE EMERGENCY 5-8 ORGANIZATION 5.4 COORDINATION WITli PARTICIPATING 5-13 GOVERNMENT AGENCIES 6.0 EMERGENCY MEASURES 6-1 6.1 ACTIVATION OF EMERGENCY ORGANIZATION 6-1 6.2 ASSESSMENT ACTIONS 6-5 6.3 CORRECTIVE ACTIONS 6-Il 6.4 PROTECTIVE ACTIONS 6-12 6.5 AID TO AFFECTED PERSONNEL 6-16 6.6 PUBLIC NOTIFICATION SYSTEM 6-18 7.0 EMERGENCY FACILITIES AND EQUIPMENT 7-1 7.1 ON-SITE EMERGENCY CENTERS 7-1 7.2 PP&L OFF-SITE EMERGENCY CENTERS 7-I a

7.3 COUNTY AND STATE EMERGENCY CENTERS 7-2

( 7.4 ASSESSMENT FACILITIES 7-2 7.5 PROTECTIVE FACILITIES 7-4

)

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/' ', 7.6 COPMUNICATIONS SYSTEMS 7-6 V

7.7 ON-SITE FIRST AID AND MEDICAL FACILITIES 7-6 7.8 DAMAGE CONTROL EQUIPMENT 7-7 8.0 MAINTAINING EMERGENCY PREPAREDNESS 8-1 8.1 ORGANIZATIONAL PREPAREDNESS 8-1 8.2 REVIEW AND UPDATING 8-7

. 8.3 NAINTENANCE AND INVENTORY OF 8-8 EMERGENCY EQUIPMENT AND SUPPLIES 8.4 PUBLIC EDUCATION AND INFORMATION 8-8 9.0 RESTORATION 9-1 10.0 APPENDICES A LETTERS OF AGREEMENT B WIND ROS" AND DOSE / DISTANCE PLOTS n C IMPLEMENTING PROCEDURE LIST U D EQUIPMENT INFORMATION LISTINGS t E CORPORATE POLICY STATEMENT F

F SUPPORT AGENCY EMERGENCY PLANS G DEMOGRAPHY AND EVACUATION EVALUATION i H DOWNSTREAM SUSQUEHANNA RIVER WATER USAGE I EMERGENCY FACILITIES - CONCEPTUAL DESIGN DESCRIPTIONS t 5

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ff~'T LISTING OF TABLES LJ TABLE TITLE 4.1 ACTION LEVEL CRITERIA FOR CLASSIFICATION OF EMERGENCY CONDITION 3 ,

S.1 TYPICAL STATION PERSONNEL EMERGENCY ACTIVITY ASSIGNMENTS 5.2 MINIMUM ON-SITE AND OFF-SITE EMERGENCY ORGANIZATION CAPABILITIES 5.3 ADDITIONAL ASSISTANCE FROM OUTSIDE PP&L 6.1

SUMMARY

OF IMMEDIATE NOTIFICATION AND RESPONSE i 6.2 EMERGENCY EXPOSURE CRITERIA 6.3 CRITERIA FOR EVACUATION OF CONTROLLED ZONE AND/0R EXCLUSION AREA 6.4 PROTECTIVE ACTION RECOMMENDATIONS 8.1 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL I-i t

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[G's LISTING OF FIGURES FIGURE TITLE (

2.1 . MAP OF THE SUSQUEHANNA SES VICINITY ,

2.2 MAP OF SUSQUEHANNA SES 50 MILE INGESTION EXPOSURE ZONE 1

5.1 SUSQUEHANNA SES ORGANIZATION 5.2 ON-SITE EMERGL4CY ORGANIZATION 5.3 PP&L OFF-SITE EMERGENCY ORGANIZATION  !

5.4 EMERGENCY ORGANIZATION INTERFACES 6.1 MAP OF THE SUSQUEHANNA SES EMERGENCY FACILITIES 6.2 SIREN LOCATION 9.1 LONG TERM RECOVERY ORGANIZATION i

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1.0 nyrig1I191s The terms defined in this section are those which are used

(') in special context in this document or are unique to the Susquehanna Steam Electric Station (SSES) .

1.1 AggIp]gT - An unforeseen and unintentional event which may result in an energency.

1.2 ALERT - An Energency Classification, see definition 1.13. l 1.3 AjjE!jgERI_ASIIQ3E - Those actions taken during or after an incident to obtain and process information that is necessary to make decisions to implement specific energency measures.

1.4 CONTRQL_BQp3 - The location of the Control Panels from which the reactor and its auxiliary systems are controlled.

1.5 9pN!dQLLEQ_3QE! - The area enclosed by the outer perimeter of the Turbine, Reactor, and Radwaste Buildings for the l cperating Units.

1.6 gg3TBgLLEQ_ggEJ_EVACUATI(J - Evacuation of nonessential individuals from some or all of the controlled Zone.

1.7 CORPOE ATE _3 AM Ag15ENT COM3ITTgf_Jg3CL - The PPSL Management group which determines major policy commitments for the company. The CMC membership includes the President of the company, and the other top executives.

}

1.8 C9EEECTIV E ACTIONS - Those emergency measures taken to ameliorate or termindt e an emergency situation.

1.9 pg3E_ PROJECT 19N - A calculated estimate of the potential radia tion dose to individuals at a given location, normally offsite, (determined from the quantity of radioactive material released and the appropriate meterological transport and dispersion parameters) .

1.10 DOSE _j ATg - The amount of radiation an individual can poten tially receive per unit of time.

1.11 MMERGENCY ACTION! - Those steps taken, as a result of exceeding an Emergency Action Level in the Emergency Plah, to ensure that the situation is assessed and that the proper corrective and/or protective actions are taken.

1.12 EMERG ENCY ACTION LEVELS JEALL - Operat ional or radiological parameters which, when exceeded, require the implementation of portions of this plan. EAL's for various emergency conditions are specified in Taule 4.1.

1.13 E3 ERG EEC1_CgNDITIgE - The characterization of aeveral classes of emergency situations consist ing of exclusive

() groupings including t he entire spectrum of possible Rev. 4, 5/81 1- 1

radiological emergency situa tions. The f our classes of emergencies, listed in increasing severity, which PPSL has incorporated into this Emergency Plan are as outlined in g Sections 4.0 of this plan. W l.14 EMERG EHCY COORDINATORS - Designated Susquehanna SES staff members responsible for coordinating specific emergency organization functions. These coordinating positions are:

o operations Coordinator o Communications and Records Coordinator o Radia tion Protection Coordinator o operations Support Center coordinator o Security Coordinator o Administrative Coordinator o Technical Support Center Coordinator 1.15 EM ERG EN CY DIR ECTOR - The PPSL ind ividu al responsible for directir,n of onsite activities during an emergency at the Susquehanna SES.

1.16 EngE9 E},g1_QE133IJOES_CE3IEEG - Designa ted State and county civil defense (i . e . , emergency management) headquarters f acilities, especially designed and equipped for the purpose of exercising ef fective coordination and control over disaster operations carried out within their jurisdiction.

1.17 EM ERG ENCY OPER ATIONS FACILITY - PPSL Emergency Response Facility located near the reactor site to provide continuous llh coordination and evaluation of PPSL activities during an emergency having or potentially baving environmental conseguences.

1.18 EnfEQENC1_ELA!_15ELEDEHT1HG_EggCEDUB3S - Specific procedures defining in detail the action to be taken in the event of an emergency condition. The Emergency Plan Implementing Procedures will be separate from, but may incorporate and.

refer to, normal plant operating procedures and instructions.

1.19 EggEGEECl_EL A!!))Q_ ZONE - There are two Emergency Planning Zones. The first is an area, approximately ten (10) miles in radius around the Susquehanna SES, for which emergency planning considera tion of the plume exposure pathway has been given in order to ensure that prompt and effective actions can be taken to protect the public in the event of an accident. The second is an area approxima tely 50 miles in radius around the Sus;uehanna SES, for which emergency planning consideration of the ingestion exposure pathway has been given.

1.2 0 EXCLU SIgE_ AFE A - That area surrounding the Susquehanna SES (also referred to as the site) in which t he reactor licensee (PPSL) has the authority to determine all activities g including exclusion or removal of torsons and property from W Rev. 4, 5/81 1-2

the .a rea. (That area around Susquehanna SES within a radius of 1,800 feet) .

(j 1.21 gjAR - Final Safety Analysis Report, Susquehanna SES, Units l 1 6 2.

1.22 GENER AL EgggGESCI - An Emergency Classification. See l definition 1.13.

1.23 LOW EdgDLATIgj ZONE JLpZL - The area immediately surrounding l the exclusion area which contains residents, the total number and dens,ity of which are such that there is a reasonable probability that appropriate protective acasures could be taken in their behalf in the event of a serious accident. For Susquehanna SES, the LPZ has a defined radius of three siles.

1.24 ggp1A_OfERATIOES.E!! TEE - The designated location from which l news releases, press conferences and other media interfacing can be provided.

1.25 gggjIJE - Any area outside the PPSL site boundary l surrounding the Susquehanna SES. See definition 1.41.

1.26 gfgjIJE_ R A DIgLOGICAL_InCIggNT - Any radiation incident l affecting areas beyond the site boundary and posing a I significant threat to public health and safety.

/) 1.27 ONSITE - The area within the PPSL site boundary surrounding l s/ the Susquehanna SES. See definition 1.41.

1.28 OPERATIggAL SUPP0gT_CENZjg_JggCL - An area for shif t l personnel and any required repair party personnel to meet for subsequent dut y assignrsent in support of the emergency operations.

1.29 PLANT _PggCEDUggj - Those procedures utilized by the plant l operations staff to control and manipulate the plant under both normal and abnormal circumstances. These procedures include Alarm Response, Off-normal, and Emergency Operating Procedures.

1.30 20WER DISEATCHER - Individual manning the PPSL Power Control l Center in the corporate headquarters in Allentown.

1.31 PHOTECT2D AREA - The area within the station inner security l fence (Protected Area Barrier) designated to implement th e requirements of 10CFR73.

1.32 E30TECTIVE_ACTIgNS - Those emergency measures taken af ter an I uncon trolled release of radioactive material, 'for the purpose of preventing or minimizing radiological exposures.

1.33 PROTECTIVE ACTION GUIDES _JPAGL - Projected radiological dose l

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1 or dose commitment values to indiv iduals in the general ,

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population that warrant protective action following a release of radioactive material.

l 1.34 EADI ATIQN_pg)) - The quantity of radiation absorbed by the body or any portion of the body. A rem is a unit of dose measurement.

l 1.35 RADIQ ACTIVE _HAIIEIAL - Any solid, liquid, or gas which emits radiation spontaneously.

l 1.36 B AD10 LOGIC AL_ E3]EGJNCY_ R E!PgNS E__TE Ah_JEERTl - The response team from the Division of Radiological Health, State Board of Health, Pennsylvania Emergency Management Agency, and other State agencies, which will be dispatched to the scene of radiological emergencies. The team provides technical guidance and other services to local governments or an affected nuclear facility.

l 1.37 gjCOVEhY ACTIONS - Those actions taken af ter the emergency to restore the plant as nearly as possible to its pre-emergency condition.

1.38 gjg ( Acronym f or roentgen equivalent man) - A unit of measure of radiation dose in biological tissue.

l 1.39 Eg59TE ASSEMBLY ARE A - A designated area, outside the exclusion area, f or the assembly of evacua ted plant l personnel during a Site Area E vac ua t io n .

1.40 SITE AREA EVACUATION - Evacuation of all nonessential O personnel within the plant site area (t he fenced in area of the Susquehanna SES) , with assembly at the Remote Assembly Area (s) . (Refer to Figure 6.1) .

1.41 SITE _jgUNDARY - The SSES site area is enclosed by an irregular boundary. At its closest point, the site boundary is .341 miles away from the center or the reator buildings, at its farthest point, it is 1.140 miles away. The site boundary is depicted on Figure 6.1.

l 1.42 SITE _ EHERgEECY - An Emergency Classification. See definition 3.13.

1.43 STATE - The Commonwealth of Pennsylvania.

1.44 STATION ASSEMBLY AREA - An area designated for the assembly of specific groups of individuals during a Controlled Zone Evacuation.

1.45 TECHNICAL SUPPORT CENTEE - A designated on-site location where various engineering disciplines can analyze the l conditions within the reactor core during and after an l accident to provide technical assessment of the accident to the Emergency Director.

Rev. 4, 5/ 81 1-4

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1.46 TsigQID DQEE - Radiation exposure to the thyroid through inhalatica or. ingestion of radioactive materials.

O 1.47 UHglyll,,glfjI - An Emergency Classification. .See definition l

1.13.

1.48 NH9kE_jgDY EXfgjjjj - Direct ex'.ernal radiation exposure to the body from airborne radioactive materials or contamination from soi.t, watcr, or other media in a critical i 1

pathway.

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20 E92Lhn hEEM9hMidn

./m The Susquehanna SES includes two 1100 MWe boiling water l q') reactor electrical generating units. The station is located in Sales Township, Luzerne County, in east central PennGylvania, about fire' riles northeast of Berwick, Pennsylanvania (See Figure 2.1) . This Energency Plan applies to the operation of Unit 1 during the construction of Unit 2, and to both units upon completion and operation of Unit 2. A separate construction site Emergency Plan, which identifies actions rela ted to construction emergencies, supplements this plan for the applicable construction period.

This Plan provides guidance for both on-site and off-site energency shtuations. It ranges in scope from relatively minor events and occurrences involving small releases of-radioactive material, up to and including a major nuclear incident having significant of f-site radiological consequences. This Plan, together with the interrelated State and county emergency plans, provides detailed arran90Lents for taking emergency measures from plume exposure out to a radius of approximately ten miles f rom the Susquehanna SES. Additional guidance is provided in State and county plans for ingestion pathway preventative measures out to 50 miles (See Figure 2. 2) . Interrelationships of this Plan with procedures, other plans and emergency arrangements include:

1) Susquehanna SES Plant Procedures provide detailad instructions for the recognition and immediate response to abnormal events. These procedures identify, in particular, initiating events which could lead to degradation in the level of safety of the plant. These procedures are periodically reviewed to ensure compa tibility with the Fmergency Plan and Emergency Implementing Procedures.

2) Emergency Implementing Procedures provide detailed instructions to station personnel for implementing the provisions of this Plan. These Emergency Implementing Procedures interrelate with the Pla nt Procedures and describe subsequent and supplementaty actions to be taken in response to. emergency conditions. A typical listing of Emergency Implementing Procedures is contained in Appendix C.

3) This Plan interfaces with applicable portions of the PPSL Emergency Organization Plan (EOP). Although the E0P is primarily for system emergencies, such as floods, icing and severe weather cond itions, it also provides coordination of PPbL system emergency ,

activities in support of requirements of this Plan.

Section 5.0 outlines the corporate level support Rev. 4, 5/81 2-1 i

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activities which provide an interf ace between this Plan and the E0P.

4) This plan interf aces with applicable portions of the O

Susquehanna SES Physical Security Plan and Security Training and Qualifications Plan.

5) Ihe elements of response to off-site emergency conditions are outlined in the emergency plans and operating procedures of the responsible off-site emergency organizations. Continuing liason with these organizations ensures compatibility and proper interrelationship with this Plan. The following applicable emergency plans are contained in Appendix F:

PENNSYLVANIA EMERGENCY MANAGEMENT AGENCY JEggAL Annex E to Commonwealth of Pennsylvania " Disaster Operations Plan," Nuclear Incidents (fixed Facility)

EEEARTM ENT OZ_EN VIRQEMjpT A L_ RESQU RC[S/jUBE AU _ _O F jfDIATIgy__ragTECTION fpE3/jfPL Bureau of Radiation Protection " Plan for Nuclear Power Generatirg Station Incidents" LUZERNE COUNTY CIVIL DEFENSE _JLCCDL

" Nuclear Facility Emetgency Plan" 0 CO LU M B_I _A COUN_TY_ EMERGENCY MANAGEMENT AGENCY _jCgMAL

" Nuclear Facility Emergency Plan"

6) The coordination and liason with off-site emergency organizations include formal agreements that individual organizations will perform their respective emergency functions in response to requests from the Susquehanna SES. Copies of letters of such agreements are contained in Appendix A from the following organizations:

o Pennsylvania Emergency Management Agency o Department of Environmental Resources / Bureau of Radiation Protection o Columbia County Emergency Management Agency o Luzerne County Civil Defense o US Department of Energy (DOE) o US Nuclear Regulatory Commission (N RC) o The Derwick Hospital o Radiation Management Corporation (backup medical support)

o Shickshinny Area Volunteer Ambulance Association l

Rev. 4, S/81 2-2

0 Shickshinny Fire Department o Pond Hill - Lily Lake Fire Company (Aabulance

() o Service)

Sales Township Fire Company No. 1 o Sales Township Supervisors o East Berwick Hose Company No. 2 o Pennsylvania State Police o Nescopeck Ambulance Association o Hobbie Volunteer Fire Company (Aabulance Service)

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3.0 SUMM A RY OF EMERGENCY _PL AN i )

K_/ The Susquehanna SES Energency Plan describes the total prepa redness program established, implemented and

-coordinated by PPSL, to ensure the capability and readiness for coping with and mitigating both on-site and of f-site consequences of radiological and other emergencies. The Plan covers the spectrum of emergencies from minor incidents to ma jor emergencies involving protective measures by off-site response organizations. Included are guidelines for immediate response, assessment of emergency situations, defined action criteria, and delineation of support functions. Emergency Implemen ting Procedures provide detailed information for individuals who may be involved

.with specific emergency response functions.

This Energency Plan provides for a graded response for distinct classifications of emergency conditions, action within those classifications, and criteria for escalation to another classification. This classification system is also used by Luzerne County Civil Defense, Columbia County l Emergency Management Agency, The Pennsylvania Eme rgency Mana ge men t Agency and the Department ot Environmental Resources / Bureau of Radiation Protection. These Plans use I four categories; Unusual Event, Alert, Site Emergency and General Emergency. l r

(3) The organization for control of emergencies begins with the on-shif t station organization and contains provisions for augmentation and extension to include other station personnel, PPSL corporate personnel, and outside emergency response organizations.

Susquehanna station personnel and PPSL support personnel are responsible for on-site emergency actions and limited off-site activities, such as of f-site radiological surveillance.

The total emergency program includes the support of local, State and Federal emergency organizations. Detailed provisions are made for implementing protective measures against direct radiation exposure and inhalation of l

, radioactive material for members of the public within a l radius of at least ten miles from the Susquehanna SES.

Additional preventive measures may be taken beyond that distance to preclude ingestion pa thwa y exposures, i specific atrnngements and agreements are made with local i off-site support organizations to provide:

c Fire and rascue o Emergency medical transporta tion o Hospital medical treatment o Law enforcement and traf fic control (a~)

Rev. 4, 5/81 3-1 1

County, State and Federal agencies having lead responsibilities specifically related to this Plan are:  ;

h o Luzerne County Civil Defense (LCCD) - The host county emergency response coordinating agency, responsible for implementing off-site action upon either direct I

notification from the Susquehanna SES or from PEMA.

O Columbia County Emergency Management Agency (CEMA) -

The agency having the same emergency response capabilities and responsibilities within Columbia County as does LCCD with Luzerne County.

o Pennsylvania Emergency Management Agency (P EM A) - Th e lead state-agency for radiological emergency planning, response and recovery and for providing guidance to local government for development of radiological emergency plans and programs.

o Cepartment of Environmental Resources / Bureau of Radiation Protection (DER /BH P) - The State-level agency ~

responsible to provide guidance and recommendations for specific of f-site protective measures.

o US Nuclear Regulatory Commission (NR C) -

The Federal agency respoasible for verifying that appropriate emergency plans have been implemented and for conducting investigative activities associated with a g radiological emergency.

o LS Department of Energy (DOE) - The Federal agency responsible to provide assistance in emergency action essential for the control of immediate hazards to public health and safety.

T1.e mechanisms through which this Plan provides for the proper response to emergency conditions at the Susquehanna SES include:

1) Initiation The first station individual who becomes a ware of an emergency condition ensures that notification is made and details are provided to the opera tors in the Control Room. This recognition and the initiation of emergency response may also be f rom Centrol Room instrumentation. Appropriate initial action is taken in accordance with Pla n t Procedures. The Shift Supervisor assumes the role of Susquehanna SES Emergency Director, and continues in that ca pacit y until relieved by the Superintendent of Plant or hia l designated alternate. The Unit Supervisor has the responsibility for plant operating functions while the h Shift Supervisor is acting as Emergency Director.

Rev. 4, 5/81 3-2

-; 2) Agggggggni i

t x/ The Susquehanna SES Energency Director performs assessment action relative to the situation in accordance with Section 6.0 of this Plan and the energency Implementing Procedures listed _in Appendix C.

This assessment and concurrent classification of the energency are based on available information such as verbal communication, Control Room instrumentation, dose projection data, and follow-up monitoring or other supportive information. The assessment and the energency classification designation is updated as new informatica becomes available.

3) -Jagggggcy Action ,

The-Susquehanna SES Emergency Director ensures the ,

activation and alerting of both on-site and off-site -

emergency personnel and organizations. .0ff-site notification for various energency conditions are

- discussed in Section 6.0, and are summarized as follows:

o Requests for assistance, such as fire fighting and medical transportation, from local off-site .

. support groups may be made by telephone to the individual group (s) . Provisions are also made to

(")

s_j contact appropriate groups through the 911 .

emergency telephone system or by message relay through LCCD or CEMA.

, o Notification to of f-site authorities of an Unusual

Event is primarily to encure that those agencies

! are cognizant of the details of events which may arouse public concern. The authorities will be l informed on a timely, but not necessarily on an immediate emergency basis. These notifications of an unusual event will be nade to LCCD, CEMA, PEMA and NRC.

o Notification to the above listed off-site authorities shall commence immediately upon the declaration of an Alert, a Site Emergency or a General Emergency. Section 4.0 describes the time limitations between the first indica tion of an event and declaration of the applicable emergency condition. Direct " hot line" telephone connections are providad for making immediate notifications to each of the agencies.

i On-site protective actions, including criteria and methods, are described in Section 6.0. The primary

]j

'~'

protective action is evacuation of non-essential personnel and the use of protective equipment and clothing for those personnel who are reguired to i

Bev. 4, 5/81 3-3

perform emergency activities. Provision is made for larger areas of evacuation commensurate with existing conditions, ll) o A Controlled Zone Evacuation may be implemented by the Susquehanna SES Emergency Director up to the area within the security fence.

l o A Site Area Evacuation, when implemented by the Susquehanna SES Emergency Director, encompasses the entire site area arount the Susquehanna SES.

Off-site protective actions are addressed in Section 6.4.2 and in Table 4.1. Such actions are primarily the responsibility of State and local emergency organizationc, but may be based on recommendations by the Susquehanna SES Emergency Director.

l 4) jestoration l Provisions are made for establishing a restoration organization commensura te with the scope and magnitude of the emergency condition. These provisions include the assiasment of qualified individuals to fill the following positions as may be appropriate:

l 0 Restoration Manager o Plant Operations Manager o Technical Support Manager o Manager of Radiological Control and Waste Management o Design and Construction Support Manager o Advisory Support a Scheduling / Planning Manager o Administration and Logistics Manager o Public Information Manager Functions of the above responsibilit y areas are described in Section 9.0.

Termination from a severe es".gency involving off-site consequences will be through joint evalua tion by the l RcDtoration Manager, PEMA, DER /BRP, LCCD, CEMA and NRC.

O Bev. 4, 5/81 3-4

c 4.0 REEEGREC1_CgnoITL9Es a

w) .4.1 CLASSIflCATION SJSTED Energency conditions are classified into four' categories which cover the entire spectrum of probable and postulated accidents. These categories, or classifications, are Unusual Event, Alert, Site Emergency and General Energency.

Action level. criteria are specified for determining and -

declaring each energency classification. Planning is coordinated with State and county agencies to ensure that this' classification system is compatible with the system used by those agencies. The system provides for notification of appropriate emergency response organizations dnd for implementation of actions IRRediately applicable to a specific condition. Provisions are included for upgrading the classification level and the corresponding response in the event of a change in the emergency condition.

This section identifies and describes the scope of events which comprise each of the four emergency classifications.

Recognition and action level criteria are based on readily dvailable information such as Control Room instrumentation.

Immediate actions for response to conditions involving plant operating parameters, such as Technical Specification Limiting Conditions for Operation (LCO 's) , are detailed in 7, the Plant Procedures. Other immediate actions and follow-up

(j actions are identified in Section 6.0 and described in detail in applicable Emergency Implementing Procedures.

The e mergency classification system, initiating conditions, and immediate response actions are defined in Table 4.1.

This table demonstrates how an initiating condition leads directly to the appropriate emergency classification based on the magnitude of the event. In many cases, the proper classification is immediately apparent from in-plant instrumentation. In other cases, more extensive assessment is necessary to determine the applicable emergency classification. In any case, con t inuing re-assessment is required to ensure that the classification is consistent with the conditions.

4.1.1 p;.u s ua l _ E ve n t Events within this classifica tion represent abnormal plant conditions, They do not, by themselves, ccnstitute ,

significant emergency conditions and have no off-site  !

radiological conseguences. Some of these events could, however, indicate a potential degradation in the level of plant safety and/or could escalate to a more severe con ". t io n if appropriate action is not taken.

(~)h n

Rev. 4, S/ El 4-1 J

Conditions include:

which constitute the Unusual Eveat classification

1) Radiological effluents exceed Technical Specification limits for instantaneous release EgTg l Off-site dose projections must be made immediately when plant effluent instrumentation indicates that the se limits dre exceeded. This requirement is necessary to ensure that the classification will be escalated if a prolonged release results in projected accumulated doses which exceed dose criteria applicable to higher classificaticas.

2) Any violation of Limiting Condition for Operation (LCO) which results in taking the plant from operating status to a hot shutdown condition

3) Fuel cladding degradation

4) Initiation of Emergency Core Cooling System ( ECC S) , due to either a valid sa fety circuit trip or necessary manuti initiation other than testing

5) acactor inadvertently achieves critical status

6) Nearby or on-site release of potentially harmful guantity of toxic or flammable material lf+k

7) Natural phenomena:

o Totnado warning, with probable impact on station o Hurricane warning, with probable impact on station o Flood warning, with probable closure of designated evacuation routes o Ea r t hq uake, detected on station seismic instrumentation l 8) on-site fire lasting 15 minutes or lenger, requiring dCtiVation of plant fire brigade

9) Explosion inside security protected area, with no significant damage to station facilities

10) Aircraft crash on-site or unusual aircraft activity over facility l 11) Traasportation of injured and contaminated individuals frcc Susquehanna SES for treatment at a hospital

12) Main turbine failure causing casing pe ne t ra tion Rev. 4, S/81 4-2

Conditions within the Unusual Event classification

<3 correspond to the same classifica tion within the LCCD,

() CEMA and PEMA plans. l The Emergency Director shall declare an Unusual Event as soon as it has been indicated and verified. All reasonable efforts shall be implemented to make this verification within 15 minutes of the initial indication of the event. Notification to LCCD, CEMA, PEMA, NRC and PPSL Headquarters shall commence on a timely _ basis upon declaration of an Unusual Event.

4.1.2 Alert This classification is characterized by events which indicate an actual degradation of the level of plant safety.

It requires response by the plant emergency organization, augmentation of on-site emergency resources, and constitutes the lowest level for which off-site agency emergency response may be anticipated.

Conditions which constitute an Alert classification include:

1) Radiological effluents exceed ten times the Technical l Specification limits f or instantaneous release rx 2) Reactor coolant system leak rate exceeds 50 gpa

\'->' 3) Severe fuel cladding degradation

4) Unexpected in-plant high radiation levels or airborne contamination which indicates a severe degradation in the control of radioactive ma teria l (would include a fuel handling accident or other event which results in unexpected and verified increase in radioactivity levels by a factor of more than 1,000 above normal conditions)

5) Loss of all off-site power and all onsite AC power supplies

6) Loss of on-site vital DC power

7) Failure of the reactor protection system to initiate and complete a scram which brings the reactor subcritical

8) Loss of capability to achieve plant cold shetdown

9) Control rccm evacuation required or anticipated, with control of shutdown systems established f rom local stations m

l k) 10) Loss of all Control Room alarms /a nnunciators f Rev. 4, S/81 4-3

11) Entry of toxic or flammable gases intc the facility, with habitability problems

12) Natural phenomena:

o Tornado strikes vital plant structures o Hurricane delivers winds near design basis levels at the station o Earthquake greater than Operating Basis Earthquake level

13) Fire or explosion affecting safety systems

14) Aircraf t or missile strikes a station structure The Susquehanna SES Emerlency Director shall declare an Alett as soon as the event has been indicated and verified.

All reasonable efforts shall be implemented to make this veritication within 15 minutes of the initial indication of the event. Notification to LCCD, CEMA, PEMA, NHC and PPCL Headq uarters shall commence immediately upon declaration of dn Alert.

Events within the Alert classification correspond to the l same classification within the LCCD, CEMA and PEMA plans.

4.1.3 Site Emergency O A Site Emergency is characterized by events involving actual or probable major failures of plant functicas needed for protection of the public. Most events within this classification constitute actual or potential for significant releases of radioactive material to the envircament. Although emergoncy actions involving membe;s of the public may not be necessary, off-site emergency response orge.nizations should be mobilized and ready to implement protective measures.

Conditions which constitute a Site Emergency include:

1) Radiological Effluent releaoe cor respcnds to greater i than 50 mr/hr exposure ra te for a half-hour duration or greater than 500 mr/hr for a two-minute duration at the site area bounda.y.

2) Major damage to spent fuel with actual or clear

! potential f or significant release of radioactive material to the environment

3) Unconticlled decrease in the fuel pool level to below the level of the fuel Rev. 4, 5/El 4-4

4) Known loss of coolant accident greater than makeup pump

.g capacity

~^

5) Main steam line break occurs outside cf containment without isolation

6) Degraded core with possible loss of coolable geometry

7) Loss of fu'nctions needed to bring the reactor

, subcritical with the mode switch in shutdown and temperature greater than 2120F

8) All alarms . (annunciators) lost for more than 15 minutes and plant is not in cold shutdown or plant transient initiatcd while all alarms are lost

9) Required evac.uation of the control room. Shutdown systems contcol at local sta tions not established within (time to be determined during startup testing)

10) Toxic cr flammable gases enter vital areas, restricting access to plant Control stations, with plant not in cold shutdown

11) An on-going adversary event threatens imminent loss of physical control af the plan

(^} 12) Loss of all of fsite power 2nd loss of onsite AC power

's -

capability is sustained longer than 15 minutes

13) Loss of all vital on-site 125 volt DC power sustained for more than 15 minutes

14) Natural phenomena 1

c Tornado or Hurricane with winds in excess of design levels o Saf e Shutdown Earthquake (SS E) occurs

15) Severe damage to safe shutdown equipment from fire, explosicn or aircraf t crash when plant is not in cold shutdown.

The Susquehanna SES Emerjency Director slaall declare a Site

• Emergency as scoli as the event has been indicated and verified; but in no case shall this verification time exceed  :

lb minutes. Notification to LCCD, CEMA, PEMA, NRC and PPLL l l Headquarters shall ccamence immediately upcn declara* ion of l l a Site Emergency.  !

! l l This classification of even ts corresponds to the same t

~

classifica tion within the LCCD, CEM A and P EM A plans. l

\

Rev. 4, 5/81 4-5

4.1.4 fien&l_Z8.eLyencI This emergency class is characterized by events, occurring or having occurred, which involve actual or imminent llh substantial core degradation or melting with potential for loss of containment integrity and/or release of large quantities of radioactive material to the environment.

Total activation of the on-site and of f-site emergency organizations is required for such events. Actions involving off-site populations are probable.

Conditions which constitute a General Emergency are:

1) Radiological effluent release corresponds to greater than 500 mr/hr exposure rate at the site area boundary for a half-hour duration.

2) Loss of 2 out of 3 fission product barriers (fuel cladding, reactor coolant pressure boundary and primary containment), with potential loss of the third barrier -

3) Any combination of initiating events that creat as a situation which may result in the release of 13 ge amounts of radioactivity, as described in accrou criterion 1.

4) Loss of physical control of facility The Susquehanna SES Emergency Director shall declare a General Emergency as soon as an event or comaination of events within this category is indicated and verified.

For indications based on radiolog ical ef fluen ts, the verification time shall not exceed 15 minutes. For less apparent indications, the Emergency Director shall ensure that an appropriate Alert or Site Emergency is in effect and determine the applicability of a General Emergency as soon as possible. Notification to LCCD, CEMA, PEMA, NRC and PPCL Headquarters shall commence immediately upon the declaration of General Emergency.

Accidents of this class correspond to the same l classification within the LCCD, CEMA and PEMA plans.

4.2 SPECTEU3_OF POSTULATED ACCIDENTS The classitication and corresponding protective actions relative to significant emergency conditions are based prima rily on the resultant or potential radiation doses.

Methods are described in this Plan and in Emergency Implementing Procedures for projecting, measuring and evaluating those doses.

The discrete accidents addressed in this section are those which are defined in the Susquehanna Ses Units 1 and 2 PSAR 4h as " design basis accidents". The following discussion of Rev. 4, 5/81 4-6

these posculated accidents and Table 4.1 identify the

instrumentation and other mechanisms f or prompt detection

and continued assessment, and demonstrates how each accident is encompassed within the emergency classification system of this Plan.

The manpower needs for taking immediato action to minimize damage to the plant and equipment, and to initiate protective measures for on-site and of f-site individuals are provided by the normal shift operating crew. The composition of this around-the-clock crew, the emergency assignments for these individuals, and arrangements for dugmenting the emergency support personnel, are described in Secticns 5.2 and 5.3.

4.2.1 [gg1Egl_ggd_DEgp_Accideg1 This accident is postulated to occur with the reactor in hot startup condition, and very conservative calculations indicate in failure of about 770 fuel rods. The main steam line radiation monitors detect the significant increase in activity and initiate closure of the main steam isolation valves (MSIV) . valve closure is ccmpleted in about 5.5 seconds. During that time interval, noble gases and radioiodines are t ra nspor ted with the steam to the condenser. Release of radioactivity to the envi ronment is by wa y of leakage from the turbine building.

p(_) Initial assessment of this accident, perf ormed by the Plant Control Operator under the direction of the Sunquehanna SES Emergency Director, includes evaluation of the source term.

Data available for the evaluation are direct rad ia tion levels at the locations of various turbine building ARMS, and an indication of the airborne radi )a 'tivity concentra tion f rom the turbine buildingfra3vaste building vent exhaust acnitor. Emergency Implementing Procedures provide general guida' s for dose projections based on the turbine building so- e term. Da ta f rom the continuous monitoring devices may be supplemented by information obtained by the radiological monitoring team.

The Susquehanna SES Emergency Director designates protective action commensurate with the projected and/or measured doses. For doses in the range of the maximum estimates shown in Table 15.4-15 of the FSAR, the protective actions l may include:

1) Declare an Alert

2) Implement controlled Zone Evacuation 4.2.2 Ing1_gand113s

['#') This accident is postulated to occur with the reactor in i

shutdown condition with the vessel head removed, and results l

l l

Rev. 4, 5/81 4-7

in failure of about 125 fuel rods. The reactor building ventilation radiation monitoring system alarms, isolates the tentilation syatem, and starts operation of the Standby Gas Treatment System (SGTS) , all within about cne minute. Noble gases and radioiodines are released to the reactor coolant, migrate to the seconda ry containment, and are released to the environment after filtration through the SGTS.

Initial assessment of this accident includes the performance of dose projections in accordance with Emergency Implementing Procedures. Dose projections utilize data from the reactor building vent monitor, the reactor building vent radioiodine monitor, and meteorological instrumen tation.

In the event that projected doses are in the range of the l maximum estimate shown in Table 15.7-16 of the FSAR, the protective actions may include:

1) Declare either an Alert or a Site Emergency

2) Implement Controlled Zone Evacuation l 3) Consider Implementa tion of a Site Area Evacuation 4.2.3 gain _ Steam _ Break This accident is postulated to occur with the reactor in o pera ting status. The steam line break occurs outside the l containment and releases steam for a period of about 5. 5 lll seconds, until complete closure of the MSIVs. Noble gases and radiciodines in the coolan t are assumed to be released directly to the environment.

Due to the short duration and the dir ect release to the environment, there is no feasible mechanism to monitor the actual release. However, an estimate of the resultant doses I

can bc made and ccmpared to those shown in Table 15.6-9 of the FSAR for worst case conditions. Actual doses are proportional to the fission product activit y in the steam, l

ds monitcred by the off gas release ra te, prior to the accident. The doses in Table 15. 6-9 o f t h e FSAR are based on the assumption that the off gas release ra te is at the upper limiting condition for operation. Actual dose estimates, and corresponding protective actions, may be scaled by the Susquehanna SES Emergency Director, based on the of f gas release rate prior to the accident.

Consideration may also be given to the relative benefit from taking or not taking specific protective action, based on the short-term duration of exposure associated with this dCCideDt.

Protective actions for vorst case conditions may include:

1) Decla re either an Alert or a Site Emergency Rev. 4, S/ 81 4-8

2) Implement Controlled Zone Evacuation v)

/ 4. 2. 4 ' Ins 1Enten1_113s_DIsah This accident is postulated to occur with the reactor in i operating status, A small line connected to the primary coolant system ruptures at a location which is outside the drywell, but inside the secondcry containment. Noble gases i and radioiodines are released for about ten minutes prior to shutdown of normal ventilation and initiation of the SGTS.

Operator recognition of the accident is by a combination of alarms or abnormal readings from: area radiation monitors, ventilation process radiation monitors, temperatura monitors, and leak detection systems. l Protective actions which may be specified in response to the dose estimates shown in Table 15.6-4 of the FSAR include: l  !

i

1) Declare an Alert

2) . Implement controlled Zone Evacuation 4.2.5 loss of Coglagt_Accidgnt_fl0 CAL This accident is postualted to involve a cc m plete circumferential break of a recirculating loop pipe inside the primary containment, with the reactor operating at full power. The accident results in release of a significant

(~)N

(. quantity of fission products into the primary con tainment, leakage into the secondary containment, and release to the environment through the SGTS. Containmen t failure, although not likely, must be considered possible.

The occurrence of a design basis LOCA is uniquely identified by low-low reactor water level and high drywell pressure signals from the reactor protective system sensors and high radia tion signal f rom the con tainment accident ra dia tion monitor (s) . The signals result in teactor scram and MSIV closure within 5.5 seconds. Operation of the emergency core cooling system is initiated within about 30 aeconds.

The following protective actions would be taken by the i Susquehanna SES Emergency Director in respcnse to a design '

basis LOCA:

1) Declare a Site Emergency 4.2.6 Of f-Gas Treatment _ System _Eailure This accident is postulated to be initiated by an occurrence such as earthquake (greater than SSE design basis),

explosion, or fire. The accident results in release of the stored inventory of noble Jas in the system, including that

() con ta in e d in the charcoal adsorption beds. In addition to recognition of the initiating event, the operator is Rev. 4, 5/81 4-9 l i

l

provided with recognition and assessment information from alarmed instrumentation such as ARMS, off-gas system loss of flow, and vent release activity.

P;otective actions which may be specified by the Susquehanna SFS Emergency Director, based on the maximum estimated doses l shown in Table 15.7-4 of the PSAH include:

1) Declare a Site Emergency

2) Implement Controlled Zone Evacuation 4.2.7 Air Ejector Line failure This accident is postulated to result from a seismic event (grea ter than SSE) which is more severe than the design basis of the system. The noble gas and radiciodine activity from the air ejector, which is normally processed by the off-gas treatment system, is discharged to the environment via the turbine building ventilation system. The accident is recognized by the sounding of the off-gas system loss ot flow alarm and ARMS. Assessment of the severity includes evaluation of the off-gas activity release rate prior to the accident and results of on-site monitoring.

Protective actions, based on the estimated doses shown in l Table 15.7-4 of the FSAR include:

1) Declare an Alert O

2) Implement Controlled Zone Evacuation 4.2.8 Liguid_Radwaste_Pailure This accident is postulated to be rupture of a concentrates waste tank in the radwa st a enclosure. Airborne radioactivity released during the accident passes directly to the environment via the plant vant. A high water level dl.rm on the radwaste building sump alarms and activates the sump pumps. Radwaste building AdMs and on-site monitoring provide data for assessing the magnitude of the radiological conseguences.

i Protective actions, based on the maximum estimated doses l shown in Table 15.7-10 of the FSAR, may include:

1) Eeclare an Alert

2) Imi,lement Controlled Zone Evacuation 1

O Hev. 4, S/El 4-10

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1 Q, Pigs.1 {d' ~

TABLE 4.1 -

CLASSIFICATION OF DfERGENCY CONDITIONS' (UNUSUAL EVENT)

Initiating Conditions Emergency Action Levels Licensee Actions Of fsite 4aeach Actions .

1. Radiological effluents exceed 1. Reactor ~ Building Refueling Floor . 1. Promptly notify plant emergency ~ 1. Notify key officiala and

. Technical Specification limits.. Ventilation Exhaust Monitor high management personnel of event public if deemed necessary by for instantaneous release. radiation alarm annunciated on , particulars and an assessment of Jcounty/ state Emergency..

panel OC651 and recorded on panel . safety significance of the event Director.

1C600.

or 'and Standby Gas Treatment Ventilation Notify LCCD, CEMA,1PEMA and NRC Exhaust Monitor high radiation of " unusual event".

alarm annunciated on panet OC653 and recorded on panel IC600. 'and ojt If' event is not escalating, notify NRC via LER program prompt notifi-Turbine Building Ventilation cation (24 hr.) provision and pro-Exhaust Monitor high radiation vide-for press releases.

alarm annunciated on panel OC653 and recorded on panel IC600, and oj; If event is not being terminated safely (or has rygt been) escalate Service Water System Discharge to " alert" classification.

Line Monitor high radiation alarm annunciated on panet IC668 and re- and corded on panel 1C600. . -

If action statement (3) above is implemented, a written close out; will be submitted to the NRC in 7 days.

2. Puel cladding degradation 1. Off-gas Pre-treatment Monitor 1. Same as (1) above 1.

high radiation alare annunciated Same as (1) above on panel IC651 and recorded on panel IC601.

E Off-gas Post-treatment Monitor high radiation alarm annunciated ,

on panel OC673 and recorded on p nel IC322.

E High reactor coolant activity as determined by sample analysis; greater than or equal to 2uct/g.

of I-131 equivalent.

Rev. 4. 5/81

/ k /

)

}

w/ d P g1 2 _

TABLE 4.1 CLASSIFICATION OF EMERGENCY CONDITIONS (UNUSUAL EVENT)

Initiating Conditions Emergency Action Levels Licensee Actions Of fsite Agency Actio_n__s_

3. Any violation of Limiting Condi- 1. Implementation of a controlled 1. Same as (1) above 1. Sage as (1) above tion for Operation (LCO) which shutdown due to LCO violation.

results in taking the plant from cpelating status to a hot shut- cg; down condition.

Abnormal coolant temperature and/or pressure or abnormal fuel temperatures outside of Tech. Spec. limits.

2 Fxceeding either primary / secondary leak rate Tech. Spec. or primary

. system leak rate Tech. Spec.

E Loss of containment integrity requiring shutdown by Tech. Spec.

E Loss of engineered safety feature or fire protection system function requiring shutdown by Tech. Spec.

(e.g. , because of malfunct ion, personnel error or procedural inadequacy.)

E Indications or alarms on process or effluent parameters not functional in control room to an extent re-quirin; plant shutdown or other signiticant loss of assessment or comr;nication capability.

(e.g. , plant computer, saf ety para-ater display system, all meteoro-logical instrumentation.)

21 Turbtne rotating component failure causing rapid plant shutdown.

Rev. 4, 5/81

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

. s f

s

( -)

Pzga 3 ' k.h

. TABLE 4.1'

.. a CLASSIFICATION OF ENERCENCY CONDITIONS -

' (UNUSUAL EVENT) >

Initiatina Conditions Fsergency Action Levels Licensee Actions 4

Offsite Aseecy Actions !

4. Initiation of Emergency Core 1. . Initiation of Safeguards Systems 1. . Same as (1) sbove 1.

Cooling System ~Same as (1) above and low reactor water level (-38")

annunciated on panel IC651 E

High Drywe11' Pressure (1.69 pef g) annunciated on panel 1C601.

5. Inadvertent criticality 1.. Unexpected. increasing readings. 1. Same as (1) above 1.

indicated on pan el IC651; neutron Same as (1) above monitoring CRT disp 1&y 68.

6. . Nearby or on-site release of 1. When visually observed or notifi- 1.

potentially harmful quantities Same as (1) above 1. Same as (1) above cation to control room operator of toxic or flammable material. ende.

7. Natural phenomenon occurrence 1. Tornado warning; with probable 1. Same as (1) above 1.

impact on station, Same as (1) above 'l-

_or Hurricane warning; with probable -

ki impact on statis=.

S r, Flood warning; with probable 4

closure of designated evacuation routes.

E Earthquake detected by sei.smic i instrumentation systems.

8. Aircraft crash on-site, unusual 1. When visually observ'ed or when 1. Same as (1) above 1.

aircraf t activity over facility notification received.by control Same as (1) above j .or train derailment on-site. room operator.

a i

e Rev 4, $/3]

- - . . . ~ , . . _m __~ . . .. - _ _ - .

- -..m.m. -

. . ~ . _

'Page 4.

TABLE 4.1 CLASSIFICATION OF EMERCENCY CONDITIONS-(UNUSUAL EVENT)

Initiatina Conditions Emergency Action Levels Licensee Actions Of fsite Aaency Actions

9. TYansport of' injured or contamin- 1. As deemed necessary by Shift 1. Same as (1) above 1. Same'as (1) above-s.ted individual from Susquehanna Supe rvisor.

SES for treatment.at a hospital.

, 10. Significant On-Site Fire 1. Activation of fire brigade by 1. Same as (1) above 1. Same as (1) above Shif t Supervisor.

a,nd Fire lasts longer than 15 minutes after time of notification.

11. Explosion inside security pro- 1. When visually observed or when 1. Same as (1) above 1. Same as (1) above tected area; with no significant notification received by control draage to station facilities. room operator.

12. Failure of a safety or relief 1. Initiation of Safeguards Systems 1. Same as (1) above 1. Same as (1) above .

valve in a safety related system and low reactor water level (-38")

i to close following reduction of annunciated on panel IC651.

applicable pressure.

j ?JE High Drywell Pressure (1.69 psig) annanciated on panel IC601. '

13. Loss of of f-site power or loss 1. When observed on ACR. 1. Same as (1) above 1. . Same as (1) above of on-site AC power capability.

- 14. Security threat or attempted 1. As deemed necessary by 1. Same as (1) above 1. Same as (1) above entry or attempted sabotage. Shif t Supervisor.

I Rev. 4, 5/81

, , ,- - _ m -

q .[

Q y;g 3 '$ V-TABLE 4.1 CLASSIFICATION OF ENERGENCY CONDITIONS (ALERT)

Initiatina Conditions Emergency Action Levels Licensee Actions Offsite Agency Actions

1. Radiological eifluents exceed 1. Reactor Building Refueling Floor 1. Promptly notify LCCD, CEMA, PEMA 1. Provide assistance if re-(10 times the Technical Specifi- Ventilation Exhaust Monitor high- and NRC of Alert status and . quested and able. l cation instantaneous limits. high radiation alarm annunciated reason for alert.

I on panel 0C651 and recorded on and, l.

panel IC600. and Augment resources by activa-g Promptly notify plant emergency' ting EOC and any other pri-management personnel of event mary response centers.

Standby Gas Treatment Ventilation particulars and an assessment of Exhaust Monitor high-high radia- the safety significance of the and, tion alarm annunciated on panel event.

OC653 and recorded on panel 1C600. Alert to standby status key and, emergency personnel including or

~'~ monitoring teams and associa-Activate, TSC and OSC.and dispatch ted communications.

Turbine Building Ventilation Ex- off-site monitoring teams if haust Monitor high-high radiation radioactive effluent release in- and alarm annunciated on panel OC653 volved.

and recorded on panel IC600. Prepare to provide confirma-a,nd tory off-site radiation moni-or_ toring and ingestion pathway Provide hourly plant status up- dose projections if actual Service Water System Discharge dates including meteorological- releases substantially exceed Line Monitor high-high radiation conditions and dose projections technical specification alarm annunciated on panel IC668 to off-site authorities. limits.

and recorded on panel IC600, and and Close out by verbal summary to Maintain alert ustus until -

off-site authorities followed by verbal close-out.

press release within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (in some cases de-escalation to or

~

the " unusual event class" may be appropriate if the initiating Escalate to a more severe conditions cannot be closed out, class.

i but it has lost it's alert class significance).

_o_r Escalate to a more severe emerg-ency class.

2. Reactor coolant system leak rate 1. Drywell floor drain sump A or B 1. Same as (1) above 1.

axceeds 50 gpm. Same as (1) above Hi-Hi alarm en panel IC601 and Drywell floor drain pumps (2 of 4); 1A/IP - 402A, IB/IP-4028 IA/

IP-403A and IB/IP-4038 continu-ously running.

Rev. 4, 5/.81

~

s

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a i 1 j '

,! P:g2 6 P

TAbtE 4.1 CLASSIFICATION OF EMERGENCY CONDITIONS (ALERT)

Initiating Conditions P_mergency Act ion Levels Licensee Actions Of f site Agency Actions 21 .

Drywell equipment drain pump Hi-Hi alarm on panel IC601 and Dry-well equipment drain pumps IA/IP-227A and IB/IP-227B continuously running.

3. Severe fuel cladding degradation 1. Off-gas pre-treatment monitor 1. Same as .(1) above 1. Same as (1) above High-High radiation alarm (5 c'/sec; equivalent to 30 min, decay mix) annunciated on panel IC651 and recorded on panel IC600.

21 Reactor coolant sample exceeds 300 uC1/cc of equivalent I-131.

4. Unexpected in plant high radiation 1. Alarm with indication on recorder 1. Same as (1) above 1. Same as (1) above levels or airborne contamination of increase of 1000 times normal which indicates a severe degrada- of area radiation monitoring system, tion in the control of radioactive annunciated on panel IC601 and material (would include a fuel indicated on panel IC605.

handitag accident).

5. Loss of all of f-eite power and all 1. Turbine generator trip with UATil 1. Same as (1) above 1. Same as (1) above on-site AC power supplies, and UAT12 unavailable for service (one tagged out for maintenance with the other S6T device tripped or both 86T devices tripped) and failure of all diesel generators to start or synchronize.

6. Loss of on-site vital DC power 1. Less than 210 volts on the 250 1. Same as (1) above 1. Same as (1) above Note: Busses are not tripped on VDC main distribution panel undervoltage condition. bus; less than 210 volts on ID650 and ID660 as indicated by trouble alarm on IC651.

Less than 105 volts on the 13610, ID620, 10630 and 1D640 125 volt VDC main distribution panel husses.

Rev. 4. 5/81

(,] V. p,y, 7 \j TABLE 4.1 g.pssIFICATION OF EMERGENCY CONDITIONS (ALERT)

Init,tating Conditions 9mergency Action Levels Licettre Actione Of fsite Agency Actions

7. Failure of the resetor protection 1. Trip of at least one subchannel 1. Same as (1) above 1. Same as (1) above system to initiate s.id complete a in each trip system (RPSA and scram which br11gs the reactor RPSB) as indicated by annunciators subcritical. and trip status lights on panel IC651 with failure of suf ficient control rods to insert, as con-firmed by full core display " full in" lights on panel IC651 and "on-Demand" rod informat ion pro-gram 7 from the process computer f ailing to bring the reactor sub-critical as confirmed by neutron count rate on neutron monitoring CRT display 65 on panel IC651.

8. Loss of capability to achieve 1. Loss of both essential service 1. Same as (1) above 1. Same as (1) above cold shutdawn, water loops.

21 Loss of RHR lonps A and B.

SE Loss of main condenser systems with sissiteneous loss of all relief valve capability and loss of ADS funetton an1 RCIC system.

9. Control Room evacuation reqaired 1. As determined by Shift Supervisor 1. Same as (1) above 1. Same as (1) above or anticipated with control of l shutdown systems established from local stations.

10. Loss of all cont rol room alarms 1. As determined by control room 1. Same as (1) above 1. Same as (1) above and a-aunciators. o.nerator from direct observation.

11. Entry of toxic or flammable 1. Visual obse rvation, direct 1. Same as (1) above 1. Same as (1) above gasses into the f acility, with measorement and notification to subsequent habitability problems. the control room operator.

12. Natural PhenomeTon Occurrene,e 1. Tornado strikes plant vital 1. Same as (1) above 1. Same as (1) above structures.

2.L Hurricane impacts plant structures with winds in excess of design basis levels.

Rev , 5/ag

( .

)

V U(') . uf a F ge 8 iL TABLE 4.1 CLASSIFICATION OF DIERGENCY CONDITIONS (AkERT)

Initiating Conditiens Emergency Action Levels Licensee Actions Offsite Asency Actions

.E Earthquake experienced with greater' than operating basis earthquake levels.

13. Fire or explosion af fecting 1. Direct observation or notification 1. Same as (1) above 1.' ' Same as (1) above eafety related components or -l systems ag fit As determined by Shif t Supervisor.

Aircraft or missile strikes a station structure.

14. Steam'line break with significant 1. Reactor Building Refueling Floor 1. Same as (1) above 1.

~

Same as (1) above release (e.g., greater than 10 gpa) ventilation Exhaust Monitor high or MSIV malfonction causing leakage. radiation alarm annunciated on panel 3C651 and recorded on panel IC600.

E Standby Cas Treatment Ventilation Exhaust Monitor high radiation alarm i annunciated on panel 0C653 and a

recorded on panel IC600.

E Turbine Building Ventilation Moniter high radiation alarm annunciated on . .

q panel OC653 and recorded on panel 1C600.

, 15. Ongoing Security Compromise. 1. As determined by Shif t Supervisor. 1. Same as (1) above 1. Same as (1) above 4

j 16. Tr:bine failure causing casing 1. Direct observation or notification. 1. Same as (1) above 1. Same as (1) above potetration.

17. Other plant conditions erist that 1. As determined by Shif t Supervisor. 1. Same as (1) above 1. Same as (1) above w;rrant precautionary activation

, of Technical Support Center and

! placing near-site Emergency

, Operations Facility and other key

emergency personnel on standby.

A Rev. 4, 5/81 4

__m__ _ _ _ . - S_ . . . , ,

g..

>M ,

fh- f . f Y

.' k- ' Page 9

~'

TABLE 4.1 J ct.ASSIFICATION OF EMERGENCY CONDITIONS (SITE EMERGENCY)

Initiating Conditions Emergency Action Levels Licensee Actions Offsite Agency Actions

1. Radiolo'ical g effluent release 1. Vent exhaust monitor alarm (s) 1. Promptly inform off-site auth- 1. Provide,Lif able, any as-corresponds to 50 ar/hr. exposure orities of site emergency sistance requested.

rate for a half-hour duration or g status and reason for emergency, 500 mr/hr. for a two minute dura-if known. and'~

tion at .the site e es boundary. Off-site radiation measurements-confirms. initiating condition dose. and Aurment resources by activa-

.or . rate, ting primary emergency re-Augment resources by activating sponse centers.

Erdiological ef fluent release g emergency support centers.

results in an off-site dose that is projected to exceed 170 mrem ag In-containment monitor alarm (s) n and, to the whole body or child thyroid .

. Assure that system for pub-due to the event. M . Dispatch on-site and off-site lic notification of emer-monitoring teams and associated .gency status is in standby Dose projection resulting in communications for instances and initiate preparation limiting condition. . where radiation releases appear for subsequent public per-imminent or have occurred. . iodic updates.

and and Provide a dedicated individual Alert to standby status for plant status updates to off- .other emergency personnel site authorities and periodic and dispatch personnel to press briefings. duty stations.

and and '

Make setior technical and manage- Provide off-site monito' ring ment staff on-site available for results to Itcensee and consultation with NRC and state others and jointly assess.

on a periodic basis, them, and- -and Provide meteorological and dos 0 Continuously assess infor-estimates to off-site authorities mation froen licensee and for actual releases via a dedicated off-site monitoring with individual or automated data regard to changes to pro L transmission, tective actions already ini-tiated for public and mo-and, bilizing evacuation rere-sources.

Rev. 4. 5/81

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

,s -

" 'm

( \vl 'lt/ )

'F;ge 10 <

TABLE 4.1 CLASSIFICATION OF DIERGENCY CONDITIONS '

(SITE EMERGENCY)

Initiating Conditions Emergency Actirvn Levels Licensee Actions . Of fsite Asemey Actions Provide release and dose projections based on available plant condition jggi information and foreseeable con-

,tingencies. Recommend placing milk ani-mais within affected area jggi, radius on stored feed and assess need to extend dis-Close out or recommend reduction tance.

in emergency class by briefing of off-site authorities at EOC and ~

and by phone followed by written sun-mary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after close-out. Provide press briefings, perhaps with licensee.

E and Escalate to " General Emergency" class. Maintain site emergency status until close out or reduction of emergency class.

E Escalate to "Ceneral 4

Emergency" class.

2. Major damage to spent fuel due 1. Dropping, bumping or otherwise 1. Same as (1) above ' 1. Same as (1) above to fuel handling accident with rough handling of a new oj; spent sctual or clear potential for fuel bundle.

significant release of radio-retive material to the and environment.

Refueling floor area radiation monitors annunciated on panel IC651 and recorded on IC600.

Reactor Building Refueling Venti-lation Exhaust Monitor alarm high-high annunciated on panel DC651 and recorded on panel IC600.

?

3. Uncontrolled decrease in the 1. Uncovering of spent fuel confirm- 1. Same as (1) above 1. Same as (1) above fusi pool level to below the ed by low water level annuncia-level of the fuel. tion on panel DC211 and a high seal leak flow alarm annunciated on OC211.

1 Rev. 4, 5/g1

,v j s

(,/

e

\

Pcge 11 TABLE 4.1 CLASSIFICATION OF EMERCENCY CONDITIONS (SITE EMERGENCY)

Initiating Conditions Emergency Action Levels Licensee Actions Offsite Agency Actions

4. Known loss of coolant accident 1. Water level below (and failure to 1. Same as (1) above 1. Same as (1) above greater than make-up capacity. return to) top of active fuel as indicated on fuel zone level in-dicator LI-B21-1R604j panel 1C652; following a time delay of three minutes.

a n,,d Low-low reactor water level (-129")

on level pressure recorder PK-821-1R632A and B, panel IC601.

E Primary containment Hi-Pressure trip alarm on panel IC651 high and pressure indication (1.69 psig) on panel IC601.

5. Main steam line break occurs 1. High MSL flow annunciated on 1. Same as (1) above 1. Same as (1) above outside of containment without panel IC601 and indicated ( 124%) l isolation. on flow indicators FJ-C32-1RS3 A.B.C or D; panel 1C652.

E High steam tunnel temperature annunciated on panel IC601 and recorded (later) on tempera-ture recorder TRS-IN604; panel IC614.

o Rev. 4. 5/81

,y ,n, -

( $ ( )

%> 'v ' Fage 12 ~

TABLE 4.1 CLASSIFICATION OF EMERCENCY CONDITIONS (SITE DtERGENCY)

Initiatin- Condit"ons Energet cy Action Levels Lica,asee Actions Of fsite Agency Actions

^$

Failure of both MSIV's in the b oken line to close or isolate 46 indicated by position indica-tion; panel IC601.

H

2. High RCIC steamline pipe routing 1. Same as (1) above 1. Same as (1) above area temperature alars annunciated on panel IC601. recorded on temper-ature recorder TRS - IN604; paael ,

IC614.

H RCIC equipment area high temperature alarm annunciated on panel IC601 and recorded on temperature recorder TRS - IN604; panel IC614.

E RLiC steamline flow high (185"H y0) annunciated cm panel IC601 E

RCIS steamline tunnel ventilation high delta temperature annunciated on panel IC601.

E RCIC turbine erhaust diaphragm pressure high alara annanciated on panel IC601.

• • L-. 5 Failure of steam foolatina 'alve HY-E31-F008 to close or isolate as indicated by position indicator on panel IC601.

Rev. 4, $/gg

p 7 --

(v, i v

e L

P::2e 13 TABLE 4.1 CLASSIFICATION OF ENERCENCY (X)NDITIONS (SITE EMERGENCY)

Initiating Conditions Emergency Action Levels Licensee Actions

• Of fsite Agency Actions

6. Degraded core with possible loss 1. Failure of control rod (s) to 1. Same as above 1. Same as (1) above.

of coolable geometry. fully insert on a scram or shut-down as indicated on full core display, panel IC651.

and L*pscale readings on LPRM strings (greater than 94 watts /ca) adjacent to not-fully inserted rods as indicated by LPRM upscale alars; panel ICb51.

Very high coolant activity ( 300 uCf/cc of equivalent I-131) as determined by sample analysis.

7. Loss of functions needed to bring 1. Inability to insert sufficient 1. Same as (1) above 1. Same as (1) above the reactor subscritical with the contral rods (with either the RD l mode switch in shutdown condition system in normal operation or 4nd temperature greater than 212'F via the scram function) to bring (Hot shutdown operational condition the reactor subcritical as indica-1). ted by count rate on Neutron monitoring CRT display 6B on panel IC651 and steam flow on instrument

1. F1-821 - IR603 A.B,C and D panel 1C651.

a,ni Failure of both loops of standby liquid control to inje-:t into the vessel indicated by zero pressure on instrument PI-C41-1R600 panel IC601; or as indicated by failure of valve C41-7008 position light -

on panel 1C631 to indicate open; or as indicated by failure of ex-plosive valves IF004 A and B post-tion lights to indicate open (fired);

panel 1C601 following manual initta-tion of the system.

Rev. 4, 5/81

T\ , _ j^% .

I '

P,:ge TABLE 4.1 CLASSIFICATION OF FJtERCENCY CONDITIONS (SITE EMERGENCY) ,% . .

Initiatina Conditions Emergency Action Levels Licensee Actions Offsite Aspecy Actions

'8. ~ All alarms lost (no. annunciators) 1. Loss of all alarms for more than 1. Same as (1) above 1. Same as (1) above for more than 15 minutes jgy{ 15 minutes confirmed by direct-plant is not in cold shutdown observation of control room opera-or plant transient initiated while tor.

all alarms are lost.

and, Reactor not in cold shutdown demon-strated by: mode switch not in shutdown and reactor temperature greater than 212*F as indicated on temperature recorder TR-IRD06 on panel ICOO7 or as provided by pro-cess computer.

E a

2. Plant transient initiated while 1. Same as (1) above 1. .Same as (1) above all alarms are lost demonstrated by:

a. Lnw - Low reactor water level l on instrument M1-821-LR/PR 1R623 l on panel IC601 and followed by

' ECCS initiation.

E

b. Reactor temperature change greater than 100*F per hour as indicated on temperature recorder TR-tR306 on panel 1C007.

_o_r. ,

h c. Pressure in excess of ate .-

! pheric as indicated on pres-I sure recorder M1-821-LR/PR-

1R623 on panel IC601,

9. Control Room Evacation 1. As determined by shif t supervisor 1. Same as (1) above 1. Same as (1) above agy!

c Shutdown systems control at local ,

+

stations not established with (later-

• time to be determined during 4 startup testing).

i i

Rev. 4, 5/81

f- s

()

t s

\ h , ~_

Page 15 .

TABLE 4.1 CLASSIFICATION OF D4ERGENCY CONDITIONS (SITE EMERGENCT)

Initiating Conditions Emergency Action Levels Licensee Actions Of fsite Agency Actions

10. Toxic or flammable gasses enter 1. Visual observation, direct mea- 1. Same as (1) above 1. Same as (1) above vital areas, restricting access surement and notification to con-to plant control stations, with t.o1 room operator by on the plant not in cold shutdown. scene personrel.

Si ligh alarm of chlorine detector annunciated on panel DC681 with isolation of primary or alternate air intakes.

a,n{

Mode switch not in shutdown or made switch in shutdown ind re-actor temperature greater than 212*F as indicated on temperature recorder TR-IR006 on panel IC007 or as provided by the process com-puter.

11. An on-going adversary event 1. As determined by shif t supe rviso r 1. Same as (1) above 1.

threatens imminent loss of Same as (1) above physical control of the plant.

12. Loss of all of f-site power and 1. Turbine generator trip annunciated 1. Same as (1) above 1.

loss of on-site AC power capabil- Same as (1) above on IC651 with UAT11 and UAT12 ity is su.tained longer than 15 unavailable for service (one tagged minutes. out for maintenance with the other 86T device tripped or both 86T devices tripped) annunciated on DC653.

• 2$

Failure of all, diesel generators to start or synchrontre as indica-ted and annunciated on DC653.

A 15 minute time lapse.

13. Loss of all vital on-site 125 1. Loss of DC power on 125 VDC 1. Sase as (1) above 1.

volt DC power sustained for more busses (at distribution panel) Same as (1) above than 15 minutes. 1D614 and ID615 on panel OC653.

Rev. 4, 5/81

O O Page 16 O

TABLE 4.1 CLASSIFICATION OF EMERGENCY CONDIT!0M3 (SITE EMERGENCY)

Initiating Conditions Emergency Action Levels Licensee Actions Offsite Agency Actions A 15 minute time lapse.

14. Natural Phunomenon Occurrence 1. Tornado or hurricane is > acts sta- 1. Same as (1) above 1. Same sa (1) above tion with winds in excess of de-sign levels.

E Safe Shutdown Earthquake (SSE) occurs.

15. Severe damage to safe shutdown 1. Aa determined by shift supe rviso r 1. Same as (1) above 1. Same as (1) above 1 equipment from fire erplosion or with plant in operational condi-aircraft crash when plant not in tions I, 2 or 3.

cold shutdown.

16. Other plant conditions exist tha t 1. As determined by shif t 1. Same as (1) above 1. Same as (1) above warrant activation of emergency supervisor.

centers and monitoring teams or a precautionary notification to the public near the site.

Rev. 4, $/81

j'")

(3) u.-

(j Pag 1 17 '--

TABLP 4.1 CLASSIFICATION OF Dir.RCENCY CONDITIONS (GENERAL EMERGENCY)

Initiating Conditions Emereeney Action Levels Licensee Actions Offsite Agency Actione

1. Rat"iological effluent release 1. Vent exhaust monitors alarms 1. Same as (1) for " Site Emergency" 1. Provida requested assistance, corresponds to I remlhr. W.B. Hi-Mi radiation, classification. if able, or 5 ren/hr. thyroid at the site boundary under actual or and meteorological conditions.

Off-site radiation measurements Activate immediate public confirme initiating condition notification of emergency dose rate. status and provide public periodic updates.

0.E.

a.!1d In-containment monitor alarms Ri-Hi raoiation. Recommend protective actions for Emergency Planning Zone population and Emergency Ingestion Zone agricultural products.

Augment resources by activa-ting EOC and any other pri-mary response centers.

Dispatch key emergersey per-sonnel including monitoring teams and associated com-munications, aj3{

Activate other emergency ser-vices eersonnel and dispatch to duty stations.

Provide of f-r.ite monitoring results to license and joint-ly assess these.

a,t,,,{

Continuously assess informa-tion from licensee and off-site monitoring teams with regard to changes to protec-tive actions already ini-tiated for public and evacua-tion resources.

Rev. 4, 5/81

gg ,s P g118

TABLE 4.1 CLASSIFICATION OF EMERGENCY CONDITIONS (CENERAL EMERGENCY)

Initiating Conditions Emergency retton Levels Licensee Actions Of fsite Agency Actions

^$

Maintain General Emergency status until closeout or reduction of emergency class.

2. Loss of 2 out of 3 fission pro- 1. When containt_at post accident 1. Same as (1) above 1. Same as (1) above duct barriors (fuel cladding, monttor (later) nn panel (later) reactor coolant pressure boundary indicates levels corresponding and primary containment) with to greater than 500 mr/hr. for a potential loss of the thirl one half hour duration at the barrier. exclusion area boundary for ad-verse meteorology and the vent exhaust moattors provide contire-ation of increased effluent re-lease.

a, nd, Containment pressure exceeds 40.4 PSIG as indicated on pressure re-corder M1-821-LR/PR - IR6238 on panel 1C601.

8.2.0 A visual inspection of the contate-ment indicates a potential for loss of containment (e.e. a crack in con-tainment concrete at tendon and anchorage on penetration failure).

3. Loss of physical control of 1. Reactor is in shutdown mode and 1. Same as (1) above 1. Same as (1) above facility. the neutron count rate: meters on CRT; panels C651 indicate the reactor is critical or supercritical.

and, Loss of capability to insert any control rod not fully insertel.

8"d Loss of SLC system capability to ,

inj ec t .

Rev. 4. 5/81

__.__ _ _ _ _ ___ .- _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . . _ _ . _ _.___._m..~.___.__________ _

e i

O O Page 19 I

L TABLE 4.1 [

t C1.ASSIFICATION OF EMERGENCY CONDITIONS (GENERAL IMERGENCY) t Initiating Conditions Emergency Action Levele Licensee Actions Offsite Agency Actions '

4. Other plant conditions exist 6 hat 1. The upper bound of the EAL's of 1. Same as (1) above 1. Same as (1) above make release of large amounts of initiating condition 7 or 13 l i radioactivity in a short time of site emergency have j period possible, been reached.

i

2. The upper bound EAL's of 1. Same as (1) above 1. Same as (1) above

' initiating condition 4 of l l " Site Emergency" category

! have been reached.

i and 1

l Containment cooling has not been l automatically or manually initiated '

following a 15 minute time lapse.

25-

3. The emergency action levels of 1. Same as (1) above 1. Same as (1) above initiating conditon 2 of a Site Emergency" category have been reached and are maintained in excess of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

l 9

i i

Rev. 4, 5/81

s. O 9B9hB11hTI9Ehk G9 BIB 96 9E EREB912CIgg r~s The on-site emergency organization and its augmentation and

(

)

extension of f-site are discussed in this section. Included dre the duthorities and responsibilities of Key individuals and groups, and the communication links for notifying, alerting, and mobilizing emergency perscnnel.

PPSL's Emergency Plan is based upon a four phase approach to dCCident response and mitigation.

The first phase involves the immediate response to the emergency condition. This consists of id entif ica tion of the condi tion , initiation of prompt corrective action and initiation of prompt notification to local, state and f ederal agencies. as well as appropriate members of PPSL's Emergency Response organiza tion. This initial phase in implemented by the on-shift organization. The on-ahift organization has been staffed and t ra i ried to be capable of both safely operating the unit and quickly and effectively responding to an emergency condition. Initially, the Shift Supervisor, the. highest rar. king ma nagement individual on-shift, will assume the role of Emergency Director. He in responsible for initiating both corrective action and emergency managemerit activities. He will initta te, through the ccmmunica tions coordina tor, the call-in of selected personnel to assist in these activities. 11e will have the

(~} capability to perform initial dose pro jections and make

\> resulting reconmendations rega rding of f-site protective actions.

The second phase of accilent renponso and mitijntion is the activation of the Emergency (on-site) organization. Upon notification by t ne on-shif t orja n i za tion, the Plant Superintendent or his desijnated alternate, will report to' the site to assume the role of Emergency Director.

Addit io nall y , support managers in areas of technical assessment, radiological auuensmont and operati.onal coord ina t ion will also report to the site alonJ with their supportive staffs. Theno individuals torm the nucleus of the Emergency Director's Team and .ill activate the Technical Suppcrt C e r. t e r . The Technical Support Cen ter will be f ully tunctios.al within a 30 to o0 minute time f rame of ini.tial notification. As the Pla n t Superintendent and his support sanagers attive, they will be brought is p to date by the Shift Supervisor and then will in turn assume responsibility trom the Shitt Super visor f or t heit particular areas of expertise. Thus, within 3d to 60 minutes of notification, the emergency management activities, including communications, will be under the control or the Plant Superintendent, t he dose pro jection and assessmen t activities will be directed by the Radiological Support Coordinator, in the areas of react or esijirieer irig, hs thermal hydraulics, plant design, etc., will be provided by the Tecunical Support Coordinatot and tho a p(+t a t io na l Rev. 4, S/81 5-1

Coordinator will provide a focal point for all damage control activities. Thus, the Emergency Director's organization will take over all emergency management and support activities from the on-shift organization leaving the on-shift organization to devote their entire efforts towards establishing and maintaining the plant in a safe, stable conditicn.

The third phase is the activation of the recovery organization. The recovery is that organization which will man the Emergency Operations Facility and provide in-depth technical support and of f-site radiological assessment. In essence, the recovery organization will assume from the emergency directors organiza cion the responsibilities dealing with i n- d e p t h , e xte nsi ve technical evaluations, detailed radiologica l projection and a ssessmen t activities, and all of f-site communication activities including interaction with the public and the press. Further, this or gan iza tion , headed by the Recovery Manager, will be capable of providing the necessary design modifications to install systems and/or components necessary to assure the sdfe shutdown of the unit. The recove ry organiza tion will be fully functional within four hours of notification.

Following establishment of the recovery organization, the Emergency Directors on-site or gani za t ion will remain intact and will devote its entire a ttention to in-pla n t activities.

The last phase is that of restoration and will be headed by a Restoration Manager. This phase leads ultimately to the g

return to service ot the unit. The orga r,iza tional and philosophical concepts that sill be utilizcd during this phase are highly dependent upon tho nature of the emergency.

The restoration phase sould not begin until there waa complete assurance that the plant was in a stacle shutdown condition and that the;e would be no inadvertent or unplanned significant relea se of radioactivity to the envircament.

From the above, it can be seen there ia a clear succession of responsibility with respect to emergency manajement activities trom the on-shif t o rga n i zJt ion through the On-site Emergency Director to the Recovery Manager. All personnel taking part in these organizations will be properly trained as to their responaibilities under emergency conditions and the authority they have with respect to implementation of same.

5.1 Egf MA L_Op_EE ATIEG_QEg AEJ3 ATig N The Susquehanna SES organization for normal operation is shown in Figure 5.1. This organization is applicable to the operation of Units 1 and 2. The figure shows the levels of responsitiility within the s ta tion and indicates the typical number of personnel in each job category during normal working hours (8 a. m. - 4 p.m. Weekddys, excluding Rev. 4, S/ 81 5-2

holidays) . - The minisua shift crew at all other times e3 consists of:

()

One (1). Shift Supervisor 10ne (1) Unit Supervisor-Two (2) Licensed Operators One (1) Shift Technical Advisor Four (4) Non-Licensed Operators One (1) Health Physics Monitor One (1) Chemistry Analyst One (1) Security Shift Supervisor One (1) Assistant Security Shift Supervisor Twelve (12) Security officers 52 91-3UE E11R9 eel 9E9MBM191 The Susquehanna SES on-site emergency organization is illustrated in Figure 5.2. This organization applies to emergency conditions lasting more than about one hour and up to the implementation of the Restoration Organization l outlined in Section 9.0. An on-call emergency organization Muty roster is maintained by the Shift Supervisor to ensure tue following emergency management positions within the energency. organization can be filled within 30 to 60 minutes.

O Plant Superintendent or designated alternate o Radia tion Protection Coordinator O o Operations Coordinator o Trchnical Support Coordinator The on-site emergency organization may begin with the minimum shift crew and expand to include others as they are needed and available. Additional available manning is detailed in Table 5.2.

The Emergency Director will have available, via duty rosters and call-in procedures, personnel with collective expertise in radiological macaurement and control, damage control, of f-site radiological measurement, plant engineering and emergency management. The areas o f expertise, numbers of personnel available, reporting location and time availability are delineated in p1ble_S z2. Required Personnel will be in the TSC or on-call 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day during the emergency.

This section describes the positions and responsibilities of the on-site emergency organization. Ta ble 5.1 nummarizes i typical emergency activity assignments f or station 4

personnel. Actual assignments will be addressed in the Emergency Implementing Procedures.

l (~

l'G) 1

! Rev. 4, 5/01 5-3

5.2.1 ImergencLRirgsto r The Shift Supervisor shall assume the role of tho l Susquehanna SES Emergency Director until such time as he is relieved of that responsibility by the Superintendent of Plant, or his designated alternate. Typical alternates are the Assistant Superintendent of Plant, the Supervisor of Operations, the Technical Supervisor, or an Of f-duty Shif t Supervisor.

The Shift Supervisor shall ensure that the Superintendent of Plant, or designated alternate, is promptly notified of an emergency condition.

The Susquehanna SES Emergency Director shall assume full responsibility for the implementation and administration of the Emergency Plan and is responsible for assuring continuity of resources until he relingaishes those responsibilities to the Recovery Manager. The responsibility anu authority of the Sasquehanna SES Emergency Director are set forth in Appendix E.

The Emergency Director cannot relinquish any of the above responsibilities until the arrival of and assumption of responsibilities by the Hecovery Manager at the Emergency Operations facility. At that time, he may relinquish, to the Rccovery Manager, any of the above responsibilities except those related to the responsibility to maintain the Unit in a safe shutdown condition with adeguate coro cooling lll and no uncontrolled radioactive matetial releases.

Functional responsibilities of the Emergency Director include:

1) Immediately upon notification or an existing or poten tial emergency, report to the Control Room and initiate assessment activities, incluling classification of the emergency and dcse projections if appropriate.

2) Unilaterally implement the immediate en-site corrective and protective actions to bring the incident under control and mitigate its effects.

3) Assure that appropriate notifications and recommendations to off-site organizations are made within 15 minutes.

4) Appoint Emergency Coordinators for assistance with current and continuing emergency control, but assume those responsibilities until the positions are filled.

5) ' Augment the on-site emergency organization with duty 3 l

roster perscnnel anl other available station staff members as dictated by the emergency ccadition.

W Rev. 4, S/81 5-4

6)' continue re-assessment of emergency status and make 7s appropriate' recommendations including protective

( ,) actions.to off-site organizations.

7) Ensure that information released is accurate and released through the proper channels.

r

8) Activate Energency Control Pacilities described in Section~7.0.

9) Assign technical' liaison to Emerguncy,0peration Centers, if requested. l ,

10) Communicate with and provide inf ormation to the Secovery Manager.

11) Issuance of Radioprotective Drugs in accordance with prescribed procedures.

5. 2. 2- 'gggIgliggg_Cgggdingagg This position may apply to both short-term and long-ters

• energencies, and will be filled by the Supervisor of  ;

operations or a designated alternate. Typical alternates are a Shift Supervisor or a Senior Hesults Engineer. primary responsibilities of the Operations Coordinator are:  ;

's 1) cirect Control Room and in-plant operational  ;

activities, through the Shift Supervisor and the Opera tions. Su pport Cen ter Coordinator.

f

2) Advise the Emergency Director on mat ters concerning <

f plant operations.

S.2.3 Cgamunicatiggs_and_ggegedg_Cggrdinatg1  !

A plant Control Operator will be a ppointed, if plant conditions permit, for short-term responsibilities. Por a ,

long-term emergency, the position of Coordinator will be filled by simulator Instructor. A typical alternate for l this position is a member of the Susquehanna Training Staf f.

Responsibilities of the Communications and Records  !

Coordinator include:

1)_ Make proper notification to off-site ctganizations.-

-2). Initiate call-in procedures as requested by the  ;

Emergency Director. '

3) Functic9 as. liaison for emergency-related communications between the Emergency Director and on-site and off-site emergency groups.

(~E)

4) Maintain records concerning the emergency.  !

L 5/81 Rev. 4, 5-5 r

t

, . . , _ . . . _ . _ - _ . _ , , _ . ,_ ._.____...o. .m_ .

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

5.2.4 33diat i on Ptgtection_CooIdiDaloE This position will be filled by the Health Physics l Supervisor. Typical alternates for the position of Radiation Protection Coordinator are the Radiological Support Supervisor and the Health Physics Foreman.

Responsibilities of the Radia tion Protectica Coordinator include:

1) Perform initial dose projection and of f-site environmental assessment until these functions are l performed by the of f-site Radiation Support Manager.

2) Frovide technical advice to the Emergency Director and the Operations coordinator on radiological aspects of on-site emergency activities.

3) Provide technical advice to the Emergency Director concerning recommendations for off-site protective actions.

4) Maintain Communication with and provide inf ormation to the off-site Radiation Emergency Manager.

5) Prov i.de on-site radiation monitoring personnel for efficent release assessment.

6) Provide radiation monitoring personnel for emergency team efforts.

ggg

7) Assist in personnel decontamination efforts.

5.2.5 Jechnical_ Support Coordinator This position vill be filled by the Technical Supervisor.

l Typical alternates are the Plant Engineering Supervisor or the Heactor Enginer.,ng Supervisor.

desponsibilities of the Technical Support Center Coordinator include:

1) Analyze mechanical, electrical, a nd instrument and control problems; determine alternate solutions, design and coordinate the installation of short-term modifications.

2) Analyze thermohydraulic and thermodynamic problems and develop solutions.

3) Assist in the developmen t of Emergency Procedures, Cpe14 ting Procedures, etc., as necessary for conducting emergency operations.

4) Analyze conditions and develop guidance for the Emergency Director and opera tions personnel. lh Rev. 4, 5/81 5-6 t

5) Resolve questions concerning Operating License gr) . requirements with NRC representatives.

'V 5.2.6 Adminis1EA11Ys_G99Idinat9I This position vill be filled by the Personnel and Administrative Supervisor. Typical alternates are the Administrative Supervisor or the Supervisor-Nuclear Records Systems.

I Responsibilities of the Administrative Coordinator include:

1) Coordinate provisions for transportation, food and other logistical support for emergency personnel.

2) Provide personnel and work schedules for relieving emergency personnel.

3) Act as liaison with oatside groups in providing additional resources such as manpower, equipment, supplies and transportation.

5.2.7 jecurily_Cogrdinatgg This position will be filled by the Supervisor of Security.

4 Typical alternates are the Security Training Supervisor, a Security Shi'.t Supervisor or an Assistant Security Shift Supervisor.

[]_s Responsibilities of the Security Coordinator include:

1) Maintain plant security and institute appropriate contingency measurea.

2) Account for personnel in accordance with Emergency Implementing Procedurcs.

3) Provide access and traf fic control for of f-aite PPSL locations such as the EOF and Remote Assembly Areas. l 5.2.8 operations _gurport Cen ter coordina tor t

This position will be filled by the-Supervisor of Maintenance. Typical alternates are the Mcchanical l Maintenance Supervisor, Electrical Maintenance Supervisor ,

and the Maintenance Supp 3rt Coordinator. Responsibilie.ies j of the Operaticns Support Center coordinatcr are: l

1) Direct the activities of the in-plant Emergency Teams i such as damage control, fire brigado and first aid and  ;

rescue.

- A N.]

Rev. 4, 5/81 5-7

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

E9IE l The fire brigade has a fire brigade leader (Assistant Unit Supervisor of the unaffected unit) who actually directs t he lh fire fighting efforts in accordance with the Susquehanna SES FSAR and Fire Protection Review Report. However, the coordination of various team activities will be the i responsibility of the operations support Center coordinator.

2) Responsible for coordinating the availability and assignment of personnel supporting activities for the Emergency Director and other emergency organization sanagers.

5.3 ggg;gIIg_ggggggc3g_6_ACIly1Tigg Necessary management and technical resources to support the on-site staff in the event of an accident will be provided in a time frame commensurate with the need for such I resources. The Emergency Plan Implementing Procedures provide specific plans for contacting and activating these resources which includes call-out coste rs and communications capabilities.

5.3.1 Iggrgency_gperations_Zacility The Susquehanna Emergency Operations Facility (EOF) is located offsite but near the Susquehanna site. The Off-Site g Emergency Organization manning the EOF is illustrated in W Figure 5.3. The following personnel are notified of all levels of emergencies.

o Becovery Manager o Public Information Manager Manning of the EOF is required for a Site Emergency or General Emergency'only. Manning of the EOF for an Unusual Event or Alert is the decision of the Recovery Manager, The personnel who, at the direction of the Recovery Manajer, will man the EOF are:

5.3.1.1 fecovery_nanaler The Vice President-Muclear Operations shall assume the role of PP&L Recovery Manager. Typical alternates for this position are Manager-Nuclear Support and Manager-Nuclear Plant Engineering.

The Recovery Manager is responsible for providing continuous coordination and evaluation of PPSL activities during an emergency having or potentially having environmental consequences. He is the individual in charge of the PP6L emergency response and is responsible for asauring continuity of resources.

lll Rev. 4, 5/81 5-8

l I

Other functions of the EOF under the direction of the Recovery Manager are the following:

/ i

'J o Evaluate the magnitude and ef fects of actual or potential radioactive releases from the plant o Recommend appropriate offsite protective measures o Manage all PPSL emergency resources o Coordinate emergency response organizations, including the NP.C and PEMA (interf ace with government authority) o Provide currrent information on conditions potentially affecting the public to the NRC and to State and local emergency response agencies E91E The Energency Director assumes all this responsibility until the EOF is manned and he is released by the Recovery Manager Recovery Manager will be available to report to the EOF within four hours of notification

5. 3.1. 2 Technical Support Manager The Manager-Nuclear Plant Engineering shall assume the role g~)g q_ of Technical Support Manager. Typical alternates for this l position are Assistant Man 49er-Nuclear Pldnt Engineering and Nuclear Plant Engineering Mechanical Group Superviso'r.

[

Responsibilities of the Technical Support Manager include: l o Writing esorgency and contingency procedures o Providing design and analysis information ta the onsite Technical Support Center o Coordinating taska with other organizations o Providing additional personnel to the Technical Support Center, if required o Support for planning and re-entry restoration l operations The Technical dupport Manager will be available to report to l the EOF within four hours of notification. The Technical Support Manager shall have a staff that is capable of l f unctioning within four hours af ter initia tion of the emergency condition and will be available on-call until the Recovery Manager determines this level of support is no f')

v longer needed.

Rev. 4, S/61 5-9 y e -

--er

5.3.1.3 Jitg_Syrpgr1_Managsg The Manager-Nuclear Support shall assume the role of Site Support Manager. Typical alternates f or this position are Ih Supv.-Nuclear Operations Support and Supv.-Nuclear Maihtenance Support.

Responsibilities of the Site Support Manager include:

o Prov ide liaison between the Site Technical Support Center and remainder of the offsite emergency resources o Provide personnel to work onsite, if required o Communicating with the Technical Support Center The Site Support Manager will be available to report to the EOF within f our hours of notifica tion.

The Site Support Manager shall have a staf f that is capable of functioning within four hours a f ter the accident and will be available on-call until the Recovery Manager determines this level of support is no longer needed.

5.3.1.4 Adginigtgative Suppopt_Managgp The Project Consturction Manager shall assume the role of Administrative Support Ma na ger. Typical alterna tes for this position are Senior Project Engineer within the Project Construction Organization.

Responsibilities of the Administrative Support Manager include:

o Establishing communicationa for the offsite support personnel o Notification of of f site support personnel to assemble o Providing housing, food, of fice equipment, etc., for offsite support personnel o Making necessary contractual arrangements for the emergency response efforts o Procuring equipment, supplies, and additional personnel needed to support the emergency resycnse efforts.

o Providing additional aanpower for scheduling activities deemed appropriate by the recovery manager The Administrative Support Manager will De available to report to the EOF within four hours of notification.

The Administrative Support Manager shall have a staff that h is capable of functioning within four hours af ter the Rev. 4, 5/61 5-10

accident and should be available on-call until the Recovery Manager determines this level of support is no longer ,

(~)l

\_ needed.

5.3.1.5 jadia11gg_ SEER 9It_Mangger The Radiological and Environmental Services Supervisor shall assume the role of Radiation Support Manager. A typical alternate for this position is the Staff Health Physicist.  ;

Responsibilitics of the Radiation Support Manager include: l 0 Evaluating the magnitude and effects of actual or potential radioactive releases from the plant o Recommending appropriate offsite protective seasures

• o Communicating with the Radiation Protection Coordinator in the TSC o Assigning offsite monitoring teams The Radiation Support Manager will be available to report to l the EOF within fcur hours of notification.

The Radiation Support Manager shall have a staff that is l capable of f unctioning within four hours af ter the accident

() and should be available on-call until the Recovery Manager determins this level of support is no longer needed.

5.3.2 gedia_opgratiggs_ Center The Susquehanna Media operations center will be located at the Berwick YMCA. Activities at the center will be managed l by the Public Information Manager. The Special Assistant to the President-Susquehanna shall assume the role of Public Information Manager. Typical alternates for this position l are the Public Information Director-Susquehanna SES, the Bloomsburg Area Manager, or a Public Information Specialist-Susguehanna.

Responsibilities of the Public Information Manager include:

o Serving as official company spokesman for emergency news releases o Preparing and disseminating information to the public via the news media by PPSL

. o Interpreting plant status information for dissemination I to news media and other agencies o Arranging for news media conferences Rev. 4, S/81 5-11 l

The Public Information Manager will be available to report to the EOF within four hours of notificaticn.

The Public Information Manager shall have a staff that is O

capable of functioning within four hours af ter the accident and should be available on-call until the Recovery Manager determines this level of support is no longer needed.

l 5. 3.3 Lgca l __ o f f-S ite_ Suppo rt Grougs The nature of an emergency may require augmenting on-site response groups with local services, personnel and equipment. Support from local organizaticns may be obtained as necessary from the following organizations-o The Derwick Hospital o Shickshinny Area Volunteer Ambulance Association o Shickshinny Fire Department o Fond dill-Lily Late Fire Co. (Ambulance Service) l 0 Nescopeck Ambulance Association o Salem Township Fire Co. No. 1 o Hobbie Volunteer fire Co. ( A mbu.a nce Service) o East Berwick liose Co. No. 2 o Pennsylvania State Police .

Specific methods for notification of these organizations ara contained in Emergency Implementing Procedures. Letters of agreement from each organization to provide their respective emergency assistance to the Susquehanna SES are contained in Appendix A.

5.3.4 Off-site SuppgIt_S 3Evicgs An emergency at the Susquehanna SES may require additional technical services and equipment. This type of assistance may be obtained from the following organizations, e Radiation Management Corporation o Bechtel Power Corp.

., General Electric Company o PJM Nuclear Utility Support Group l o Institute of Nuclear Fower Operations Specific methods f'or notification of these organizations are contained in the Emergency Implementing Procedures. A h Rev. 4, 5/81 5-12

listing of these organizations, their support capabilities and availability is f ound in Table 5.3.

/

i

'/- S.4 sagspIHAIlgE_!IIf_EARI191EAII!c agIIE!!E!I_AEI!sIIs 5.4.1 jigte_ggd_Issal_Ausas19s This section identifies the principal State and local governmental agencies having action responsibilities for radiological energency in the vicinity of the Susquehanna SES. The radiological emergency response plans of these agencies describe their respective responsibilities, authorities, capabilities and emergency f unctions, and are included as part of this Plan. The emergency organizational interfacing between PP&L, local and State agencies and Federal government groups la outlined in Figure 5.4.

Initial notification to each agency, via 24-hour por day manned "Ifotline" telephonen, will include, but not be limited to, the following information:

o caller's Name o Emergency Classification o Erief Description of Emergency Condition o Secommended Agency Pesponse

() As additional information becomes available, this information will be directed to all responsible ageacies.

The Implementing Procedurea provide a format for providing initial and folicw-on informa tion. Following is a summary of the provisions for preparedness and response to radiological emergencies by each organization, as well as the primary and alternate methods of emergency notification:

LMISIDd_999D1Y_GlIll_ggigggs (LCCD) is the lead governmertal dgency for of f-site Coordination and response in LuZerre County. The LCCD emergency plan is entiticd " Nuclear Facility Emergency Response Plan," and is contained in Appendix F.

The LCCD plan includes provision for:

o Planning ard coordination with local, Stato and Federal authorities o Initial response to notification by Susquehanna SES.

o Alert and warning of local populations o Evacuation and other protective measures for local populations ,

(~) j K/ o Emergency services l Rev. 4, S/81 S-13 i

o Situation analysis The LCCD plan also contains emergency procedures for the local organizaticns which are assigned acticu or support lll responsibilities under that plan.

The primary method of notification to LCCD is a direct telephone " hot line". Secondary methods are radio and regular telephone. A copy of the agreement letter from the LCCD is contained in Appendix A.

Columbia _ County _ Emergency _ gag 39ement_ Agency (C EM A) is the lead governmental agency for of f-site coordination and response in Columbia County. The CEMA emergency plan is entitled " Nuclear Facility Emergency Respcase Plan," and is contained in Appendix F.

The CEMA plan includes provision for:

o Planning and coordination with local, State and Federal authorities o Initial response to notification by Susquehanna SES o Alert and warning of local populations o Evacuation and other protective measures for local populations o Emergency services o Situation analysis The CEMA plan also contains emergency proccdures for the local organizations which are assigned action or support responsibilities under that plan.

The primary method of notification to CEMA is a direct telephone " hot line". Secondary methods are radis and regular telephcne. A copy of the agreement letter from the CEMA is contained in Appendix A.

ESEDUYlvani4_gmgtgency_3angggggat_Aggncy (PE1A) is the lead governmental agency f or coordination and response of emergency activities at the S ta te level. The PEMA emergency plan is entitled " Annex E to Commonwealth of Pennsylvania Disaster Operations Plan," and is contained in Appendix F.

The PEMA plan includes provision for:

o Issuance of planning guidance o Coordination of State response to nuclear incidents o Coordination of multi-county Emergency desponse Plan tiing lll 4

Bev. 4, 5 /1 6 5-14 s

o Operation of energency operations center

() o Provision for energency public information o coordination of State agencies and departments The primary method of notification to PEMA is by direct telephone " hot line". A second0 ry method is by regular telephone. A copy of the agreement letter from PEMA is contained in Appendix A.

ESEAItsent of Envigggaental_pesogrggg/ Bureau of Egdia11gg PI glegtign (D ER/B HP) is the lead governmental agency for providing technical advice and consultation to State and local organizations in evaluation of appropriate off-site preventive and protective measures. The DER /3RP energency plan is entitled " Plan for Nuclear Power Generating Station Incidents," and is contained in Appendix F. The DER /BRP plan Frovides for:

o Technical consultation o Accident assessment o Recommendations for protective actions o Recommendations for protection of potable water and

~D food V

o Recommendations for recovery and re-entry (of f-site) l The initial notification to DER /DRP will be made by PEMA.

Direc t ': hot line" communications are also established l betwc en Susquehanna SES and DER /BRP for transmitting technical inf ormaticn and/or recommendaticns. A copy of the agreement letter from DER / BHP is contained in Appendix A.

S.4.2 federal _3ggggies The principal Federal government agencies having emergency responsibilities relative to the Susquehanna SES, and a summary of those responsibilities are:

HE_Enslest_Ess91019tI_Cgmalagigg (u nC) , Region I, is '

responsible for conducting investigative activities associated with a radiological emergency, and verifying that emergency plans have been implemented and the proper agencies notified.

t The primary method of notification to NRC is by " hot line" telephone. A secondary method is by regular telephone. A copy of the agreement letter f rom NRC is contained in Appendix A. Facilities are available at the TSC and EOF for (s) NBC use.

Rev. 4, S/El 5-15

US De part agat_g1_Engggy (DO E) , Brookhaven Area Office, will respond to requests f rom the Susquehanna SES and provide assistance which is limited to advice and emergency action essential for control of the immediate hazards to public lll health and safety.

The primary method of notificati.on to DOE is by telephone, in accordance with the provisions of the agreement letter, contained in Appendix A. Notification may also be made through NRC. DOE assistance will arrive a t the EOF within eight (8) hours of their notification. Facilities are available at the EOF for DOE use.

ES$2E31 .332Egggcy_g333gement Agency (FEM A) , FEMA has the primary role in coordinating the Federal response to a commercial nuclear power plant accident by serving as the primary point of contact for requests f or Federal assistance from state and local officials and other Federal agencies.

FEMA is responsible f or coordinating all ncn-technical response activities of the Federal government.

9 O

Rev. 4, 5/81 5-16

TABLE 5.1 TYPICAL ,

STATION PERSONNEL EMERGENCY ACTIVITY ASSIGNMENTS EMERGENCY NORMAL WORKING HOURS ALL OTHER ITEMS FUNCTION FULL STAFF; 8am-4pm (SHIFT CREW)*

EXCLUDING WEEKENDS & HOLIDAYS

1. Plant System All station personnel on duty 1 - Shift Supervisor Operations 1 - Unit Supervisor 1 - Shift Technical Advisor 2 - Licensed Operators 4 - Non-Licensed Operators

2. Radiological 1 - Health Physics Supervisor 1 - Health Physics Monitor Survey & 1 - Health Physics Foreman 1 - Chemistry Analyst Monitoring 1 - Assistant Health Pinysics Foreman 5 - Health Physics Monitors 2 - Chemistry Analysts

3. Fire Fighting 1 - Assistant Unit Supervisor 1 - Assistant Unit Supervisor l (Unaffected Unit) (leader) (Unaffected Unit) (leader) 2 - Non-Licensed Operators 2 - Non-Licensed Operators

( ) 2 - Security Officers 2 - Security Officers v

4. Rescue 1 - Non-Licensed Operator 1 - Non-Licensed Operator Operations 1 - Health Physics Monitor 1 - Health Physics Monitor Other station personnel 1 - Chemistry Analyst l as needed

5. First Aid 1 - Health Fhysics Monitor 1 - Non-Licensed Operator Other station personnel 1 - Security Officer as needed 1 - Chemistry Analyst l

6. Decontamination 1 - Health Physics Supervisor 1 - Non-Licens'ed Operator 1 - Assistant Health Physics 1 - Chemistry Analyst l Foreman 2 - Health Physics Monitors 2 - Chemistry Analysts

7. Security 1 - Security saift Supervisor 1 - Security Shift Supervisor Plant and Site 1 - Assistant Security Shift 1 - Assistant Security Shift access control Supe rvisor Supervisor 12 - Security Officers 12 - Security Officers Lj Rev. 4, 5/81

Page 2 i TABLE 5.1 TYPICAL STATION PERSONNEL EMERGENCY ACTIVITY ASSIGNMENTS EMERGENCY NORMAL WORKING HOURS ALL OTHER TIMES FUNCTION FULL STAFF; 8am-4pm (SHIFT CREW)*

EXCLUDING WEEKENDS & HOLIDAYS

8. Repair and 1 - Supervisor-Maintenance 2 - Non-Licensed Operators Damage Control 1 - Sr. Results Engineer 1 - Mechanical Maintenance Supv.

1 - Electrical Maintenance Supv.

1 - Mechanical Repair Foreman 1 - Electrical Repair Foreman 12 - Maintenance Workers

9. Personnel 1 - Security Shif t Supervisor 1 - Security Shif t Supervisor Accountability 1 - Plant Control Operator 2 - Non-Licensed Operators 2 - Nuclear Plant Operator or 1 - Health Physics Monitor Auxiliary Systems Operator

10. Record Keeping 1 - Supervisor-Nuclear 1 - Licensed Operator Records / Materials 1 - Plant Training Supervisor 1 - Non-Licensed Operator g, 2 - Simulator Training

(_) Instructors 1 - Plant Control Operator

11. Communications 1 - Supervisor-Nuclear 1 - Licensed Operator Records / Materials 1 - Plant Training Supervisor 1 - Non-Licensed Operator 2 - Simulator Training Instructors 1 - Plant Control Operator

12. Dose 1 - Health Physics Supervisor 1 - Shift Supervisor Projection 1 - Radiological Support 1 - Unit Supervisor Supervisor 1 - Health Physics Specialist 1 - Licensed Operator 1 - Shift Supervisor 1 - Non-Licensed Operator 1 - Unit Supervisor 1 - Chemistry Analyst l

1 - Asst. Unit Supervisor o Additional Station personnel can normally be available within one hour.

959699 R:v. 4, S/81 I l

.y

' N, . N

()  %,)

Page 1 TABLE 5.2 MINIE'M ON-SITE AND OFF-SITE DiERCENCT ORCANIZATION CAPABILITIES

• MAJOR FUNCTIONAL IACATION MAJOR TASKS POSITION TITLE AVAILABILITT AREA OR EXPERTISE ON SHIFr 30-60 MIN 4 NRS Plant Operations Control Room Establish and Shift Supv. (SRO) 1 (nd Assessment of and/or maintain safe Unit Supv. (SRO) 1 Operational Aspects Plant Proper shutdown condition Control Room Operator (RO) 2 Auxiliary Operator 4 EmergIncy Direction Control Room Overall Emergency Shift Supv. 1 cud Control TSC Mangement & Emergency Director 5 1

EOF Coordination Recovery Mgr. C 1

Notification / Control Room Notify PP&L, State, Communicator L A

Communication TSC Local & Federal Comm. & Records Coord. 1 EOF personnel & maintain Communicator 1 Power Control communication Comm. & Records Coord. 1 Center E System Operator 1 Radiological Accident TSC overall Management Rad. Protection Coordinator 1

• A:seccment & Support & Coordination of Operational EOF Rad. Support Mgr. F 1

AccidInt Assessment Operations Support Inplant Surveys HP Technicians 1 2 Center (OSC)

EOF Cn-Site Surveys Survey Team Personnel 2 2 Off-Site Surveys Survey Team Personnel 2 4 OSC Radiation Protection Health Physics 4 2 2 2 o Ac'ess Control Trained Personnel o He Coverage o Personnel Monitoring o Dosimetry OSC Radiochemistry / Chemistry Chemistry Technician 1 1 Analysis Rev. 4, 5/81

_ _ _ . _ _ _ _ _ . _ . _ . - . _ _ _ . . - - . _ . _ . . .m - - _ - - - . . . . - = - - -- - -- *

~

-p b

'\

- % ):;

Page 2 TABLE 5.2 MINIMUM ON-SITE AND OFF-SITE EMERGENCY ORGANIZATION CAPABILITIES *

-MAJOR FUNCTIONAL LOCATION MAJOR TASKS ' POSITION TITLE AVAILABILITY AREA OR

-EXPERTISE ON SHIFT 30-60 MIN -4 HRS Damage Control OSC Overall Coordination OSC Coordinator 1 A

Mechanical Repair Mech. Maintenance lg i Electrical Repair Elec. Maintenance 1 '

I&C Repair A I&C Tech. I

'mdwaste Operations A Radwaste Operator 1 1 h; cue & First Aid A 2 Local Support Fire Fighting 5 Local Support.'

' Site Access Control On Station eert r.. Communications, Security SS 1'

& Parsonnel Accountability r :- iccountability Security Ass't SS 1 Security Controller 2 Security Officers . 10 TSC . Emergency Security Mgmt. Security Coordinator 1 T4chnical Assessment Control Room EtQineering & Eval. Shift Tech. Adv. 1 and Operations TSC Mgmt. of Support Resources Tech. Support Center 1 Support Coordinator Operations Coordinater 1 EOF Tech.: Support Mgr. 1 Site Support Mgr. 1 TSC Engineering Eval. Reactor Engr./ Thermal 1

. & Operations Support Hydraulics I&C Engr. 1 Chemistry / Radiochemistry 1 Mechanical Engr. 1 Overall Plant Design 1 Electrical Systems 1 EOF Plant Operations / Refueling Ops 1 Fire Protection 1 Chemical Engr./ Radiochemistry 1 Radwaste Mgat./ Decontamination / 1 Rad Control /HP Plant Maintenance 1 TOTAL 26 27 19 Rev. 4, 5/81

g

)

i 'p)

J Page 3 TABLE 5.1 MINIMUM ON-SITE AND OFF-SITE DfERGENCY ORGANIZATION CAPABILITIES

• NOTES A- Will be provided by Shif t Personnel normally assigned other functions.

B- Plant Superintendent, or his designated alternate, will assume the role of Emergency Director vpon arrival on-site.

Kangement activities sill be carried out from the Technical Support Center. At that time Emergency C- Overall management of the emergency response will be assumed by the Recovery Manager upon his arrival at that Emergency Operations Facilit- '.

However, minute-to-minute in-plant activities remain under the control of the Emergency Director.

D- The Communicator originally located in the TSC shif ts to the EOF af ter the EOF is activated.

E-The System Operator in the Power Control Center (Allentown) is responsible for activation of the off-site emergency organization and corporate notifications.

F-Overall management of Radiological Accident Assessment will be assumed by the Rad. Support Manager upon his arrival at the EOF. However, the Rad. Prntection Coordinator will remain in charge of in-plant activities.

The personnel listed on this table are the nucleus of the PP&L emergency manpower resources (with one unit operational) that will be available to respond to an emergency in the time frame indicated. Additional personnel will be available to augment this nucleus. Areas of significant suppo rt not listed on this table include: Public Information Personnel in the Media Center, Technical Support Personnel located in the General Of fice in A11entoen, and Administrative and Logistics Support Personnel loctied on-site and of f-site.

NOTE:

Activation of the PP&L Emergency on-site and of f-site organizations is the responsibility of the Shif t Supervisor / Emergency Director. The details are specified in " Emergency Plan - Implementing Procedure - 018 (EP-IP-018), Emergency Organization and Notification". Personnel assigned responsibilities in these organizations are listed on duty ros ter s maintained in the Plant Control Room and the Allentown Power Control Center. All on-call station personnel can be paged via the 150 Mhz VHF radio paging system with control stations in the Plant Control Raom, Technical Support Center, and Emergency Operations Facility. A separate paging system is available to contact those per-sonnel stationed in the Corporate Offices. Management positions requiring early communication capability with the Emergency Director will be assignedOperations Emergency vehicles equipped Facility. with 150 Mhz VHF mobil radios for direct contact with the Plant Control Room, Technical Support Center, or Rev. 4, 5/81

n TABLE 5.3 ADDITIONAL ASSISTANCE FROM OUTSIDE PP&L N:me/ Emergency Availability Reporting Address Function (Hours) Location

1. Committed Resources o General Electric Engineering advice & N/A GE facilities 175 Curtne.r Ave. Analysis for NSSS equip. in San Jose San Jose, (s 95125 (408) 925-3005 Operations and Maintenance 48 EOF (Site expertise on NSSS equipaent Support Mgr.)

o. Bechtel Engineering & Analysis N/A Bechtel P.O. Box 3965 Facilities in San Francisco, CA 94119 San Francisco

. (415) 768-2760 Engineering expertise 48 EOF (Technical Support Mgr.)

fN Radiation Mgmt. Corp. HP & Environmental N/A RMC facilities (s_) 3508 Market Street Calculations & Analysis in Philadelphia Suite 400 Philadelphia, PA 19104 HP/ Environmental 4 EOF (215) 243-2970 expertise (Rad Support Mgr.)

a INPO Operations & Maintenance on call EOF 1820 Water Place expertise 24 hrs. (Technical Atlanta, CA 30339 a day Support Mgr.)

. (404) 953-0904 Dissemination of N/A INPO HQ info rmation in Atlanta o PJM Nuclear Utility Operations, Maintenance 4 EOF Support Group Rad con personnel for (Site Support augmenting emergency Mgr.)

staffing

-s

~. ,

Rev. 4, 5/81

Pcg3 2-e TABLE 5.3 77-~)C 3,

ADDITIONAL ASSISTANCE FROM OUTSIDE PP&L 5'

lN:me/- Emergency Availability Reporting

' Address- Function (Hours) Location

-2.' Available Resources  !

o Quadrex, Corp._ Engineering 24 hrs.* EOF 1700 Dell Ave. expertise (Tech.

Campbell, CA 95008 Support Mgr.)

, '(408) 866-4510 i

Operations Expertise 24 hrs.*- EOF l (Site Support. I

Mgr.)-

o Gilbert Associates' Engineering 4 hrs.* EOF ~ l P.O. Box 1498 expertise. (Tech. l Reading, PA 19603 Support Mgr.) }

(215) 775-2600 ,

i o Nuclear Safety Assess- _ Analysis &' Engineering N/A NSAC facilities i ment Center Evaluation in Palo Alto ,

3412 Hillview Ave. -

P.O. Box 10412 i

-O

~ \-)

Palo Alto, CA - 94303 (415) 855-2000 .

i' o Cooper Bessemer Expertise on 24 hrs.* EOF  !

North.Sandusky St. Diesel Generators (Tech.  !

, Mount Vernon, Ohio 43050- Support Mgr.) l (614) 397-0121  !

4 o . Rad Services Expertise on Nuclear 24 hrs.* EOF 500 Penn Center Instrumentation (Tech.

Pittsburgh, PA 15235 '

Support Mgr.)

o' Keystone Helicopter Transportation & 4 hrs.* EOF 1420 Phoenixville Pike Helicopter Service (Recovery Mgr.)  !

l ~ West Chester, PA 19?80

! [

(215) 644-4430 '

i

• Time after initial notification which could only be made during normal working hours.

f r

l i  ;

.I L

! L(~T s-< '

t

' Rev. 4. 5/81:

4 --e - --- , ,,- -- 7 ,.-,---r - . , . ,--- , ,-. ..n,, , ,.- , . . ,,. w--,,, - -- , ,

O v rd a

(;

PP&L OFF-SITE EMERGENCY ORGANIZATION CORPORATE LEVEL UTILITY MANAGEMENT (E.G. - SENIOR V.P. - NUCLEAR)

---

q l

l CORPORATE OFFICE l EMERGENCY OPERATIONS FACILITY MEDIA OPERATIONS CENTER l

I Ih0h (E.G. - V.h. - NUCLEAR)

PUllic INF0 5ATitel EA808EI TECHNICAL SITE ACMINISTRATIVE RADIATION SUPPORT SUPPORT SUPPORT SUPPORT MANAGER MANAGER MANAGER MANAGER

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CEMA LIASON PEMA DER /BRP l FEMA r

Rev. 4, S/81 1

PEMA/BRP SUS 00EHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 EOC EMERGENCY PLAN EMERGENCY ORGANIZATION GOVERNOR'S INTERFACES /

OFFICE f FIGURE 5.4

6.0 EMERGEECI_jj}SURgj-fs Energency actions are initia ted .primarily in response to

~,1 _ alarmed instrumentation, but may be through-notification _to the Control Roca by the .first individual at the Susquehanna SES to become aware of an apparent emergency situation. The Unit' Supervisor must take the necessary, immediate action and ensure that the Shift Supervisor is promptly notified.

'The Shift Supervisor assumes the role of Susquehanna SES Energency Director until he is relieved of that responsibility by the Superintendent of Plant or his designated alternate. The Emergency Director assesses and classifies the condition, initiates the appropriate corrective and protective actions and ensures activation of the necessary segments of the total emergency organization.

6.1 ACTIVjTION OF_EDERGEECY ORGANIZATICE This section describes the provisions for notifying or activating groups within the emergency organization in response to emergency ~ events at the Susquehanna SES. Action levels.are recognition criteria which dictate the appropriate emergency classifications described in Section

4. 0. More detailed methodology for each classification is described in Emergency Implementing Procedures. This includes message authentica tion requirements.

Table 6.1 summarizes the notification / activation cf both the c on-site and the of f-site emergenc y organization and ks} designates immediate action requirements f or each emergency classification.

6.1.1 9n-Site Emergency _grga nization Upon' being informed of an emergency event, as defined in Section 4.0, the Shift Supervisor will assess the condition.

he will ensure that appropriate actions have been initiated to maintain the safe and proper operation of the plant. If the event requires implementa tion of this Plan, the Shift Supervisor shall assume the role of Emergency Director and:

1) Classify.the condition as an Unusual Event, Alert, Site Emergency or General Emergency as appropriate.

2) -Implement immediate actions in accordance with this Plan and the applicable Emergency implementing Erocedures.

3) Ensure that on-site emergency response individuals and groups are notified, using the pA system or diract communications. Depending on the nature and severity of the condition, these individuals with their respective groups may include:

o operations Coordinator Rev. 4, 5/81 6-1

o Communications and Records Coordinator o Radiation Protection Coordinator o Technical Support Coordinator o Administrative Coordinator llh o Security Coordinator o Operations Support Center Coordinator l

4) Notify affected individuals at the plant as required l for Local Area, Controlled Zone or Site Area Evacuation. These notifications will be made over the PA system or the plant emergency ala rm vstem.

5) Notify the Superintendent of Plant or his designated alternate, apprise him of the situation, and request that he relieve the Shift Supervisor as Emergency Director if appropriate. For conditicas within the Unusual Event classifica tion, the rola of Emergency Director is likely to remain with the Shift Supervisor through termination of the condition, due to probable short duration or low severity of the event.

6) Ensure that off-duty station personnel are notified to assist as necessary with emergency activities. These notifications will be made, via the radio paging system or by telephone backup, to individuals designated for off-duty availability status to fill key emergency response positions. Those key positicus are identifiLd in Section 5.0. Other off-duty personnel vill be called in as required. g 6 .1.1.1 secggity and Accountanility Accountability of on-site personnel during an emergency will be acccmplished through the use cf the ph ysical security system and personnel accountability procedures. The physical security system clearly establishes who, by name, is within the protected ar ea.

l Personnel will be summoned to accountability areas during an emergency via an alert signal transmitted over the public address sytem. The names of the personnel reporting in will be compared to those logged through the security system in order to ensure either total accountability or identification of potentially missing personnel. The specifics of the accoun tability process are identified in the Emergency Plan Implementation Procedures.

6.1.2 Off-Site _Emeggency_gggagizatign 6.1.2.1 Jmergency_Synnggt_Groggg the Emergency Director shall ensure that appropriate off-site emergency support groups a re con tacted to provide the type and level of assistance which may be necessary to deal with the existing emergency lh Rev. 4, 5/81 6-2

condition. The organizations listed below may be

' contacted for assistance. Methods available for

(^-)

• contacting these support groups include direct telephone communications with individual organizations, use of the 911 telephone system for emergency services and message relay through LCCD, or CEM A.

c Salem Township Fire Company No. 1 (fire and rescue) o- East Berwick Hose Company No. 2 (fire and rescue) o Shickshinny Area Volunteer Ambulance Association (ambulance service) o Shickshinny Fire Department O Nescopeck Aminulance Association o Hobbie Volunteer Fire Company (ambulance service) o Pond Hill-Lily Lake Fire Company (ambulance service) o Berwick Hospital (medical tr eat ment) o Radiation Management Corporation (backup medical

(')s

\- support) o Pennsylvania State Police (traf fic control and othdr assistance) 6.1.2.2 Off-Site Authorities The Emergency Director shall ensure that off-site authorities are notified and apprised of emergency events at the Susquehanna SES. Notifications shall be made to:

o LCCD o CEMA o PEMA c NRC J Notification of an Unusual Event is primarily to ensure that the authorities are cognizant of the details of events which may arouse public concern and initiate inquiries by news media or members of the public.

Notification to the above listed off-site authorities shall commence immedia tely upon the declaration of an

, Alert, a Site Emergency or a General Emergency. Direct

( ')

" hot line" telephone connections are provided to each cf these agencies for this purpose. Section 4.0 Rev. 4, S/81 6-3

describes the time limitations between the first indication of an event and declaration of the applicable emergency condition. llh Each of the of f-site agencies will activa te the appropriate segments of their emergency organization, based on information provided from the Susquehanna SES

&nd in accordance with their respective agency emergency plans. The DER / BHP will be notimied initially by PEMA. Following the initial notification for events involving a significant release of radioactive material, direct and continuing communications will be maintained between DER /BRP and the Susquehanna SES.

Backup radiological emergency assistance for a General Emergency may be provided by the U. S. Department of Energy in Brookhaven, NY. Notificaticn to request this assistance may be made by telephone to DOE or message relay through NRC.

6.1.2.3 PPSL Of f-Site Organization Notification of tne Recovery Manager will be made for all levels of emetgencies.

The method for notifying the Recovery Manager f rom Sasquehanna SES is via the Power Dispatcher in the Power Control Center. The Power Dispatcher will be g notified of all levels of emergencies via a hotline connection between the SSES Control Room and the Power Control Center. Backup radio communications are also available. An on-call dut roster tot all off-site positions will be kept in "the Power Ccntrol Cen ter f or use by the Power Dispatcher.

For an Unusual Event or Alert, the Recovery Manager will determine what additional off-site resources should be notified and where the off-site support resources should report. The Power Dispitcher will notify all required personnel via telephone or paging system, and instruct them where to report.

For a Site or General Emergency, the Emergency Cperations Facility will be manned by the offsite emergency managers listed below and a ny additional support, personnel deemed necessary by the Recovery Manager. The Power Dispa tcher will nctify all required personnel via telephone or paging system and instruct them where to report.

o Recovery Manager l o Technical Support Manager o

o Administrative Support Manager Radiation Support Manager lh Rev. 4, S/ s1 6-4

O Site Support Manager cs

()

The ED will provide recommendations for initial countv actions to CEMA and LCCD personnel. These recommendations will be made to enable the county agencies to begin activation of their energency organizations until the final recommendations are received from DER / BHP. The recommendation that key officials of the county be notified will follow an

" Unusual Event" notification. The reccamendation that key officials of the county be notified or county emergency services elements be placed on stand-by will follow an " Alert" no ti fication. The recommendation that key officials of the county be notified, county emergency services elements be placed on stand-by or protectave actions for the public be issued will follow a " Site 2aergency" or " General Emergency" notification.

Emergt:ncy Implementing Procedures and Training shall provide specific guidance on recommendated. actions taking into account the nature of the incident, weather conditions, and projected doses.

6.1.2.4 jnecial O ffice_ of _ the_Prgside nt Ihe Susquehanna SES Emergency Director shall ensure that the rPSL Special Office of the President in Berwick is promptly notified and provided with

(~}

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available details of any Unusual Event, Alert, Site Emergency or General Emergency. The staff of that office will transmit information regarding the emergency and items of potential interest to municipal groups, initiate appropriate news releases and respond to questions from public information representatives.

After activation of the EOF, all public information will come from the Recovery Manager via the Public Information Manager, t

6.2 ASSESjgENT ACTIONS Provisions are made for assessment th roug h cu t the course of an emergency to ensure effective coordination, direction and upgrading of emergency activities in a timely manner. The assessment actions are '~mribed in detail in Emergency Implementing Procedures. ;e assessment f unctions and the general methodology and te iniques utilized are identified ,

in this section. Initial a ssessments are made solely by the on-site emergency organization. Upon activation of the EOF, off-site support personnel will be used to aid in these assessments.

6.2.1 Sausual_ Event f3 continuous assessment of the status of plant systems and

()_ radiological conditions is provided by plant instrumentation  ;

and is supplemented by routine surveillance functions. The l

Rev. 4, 5/81 6-5 1 1

l

occurrence of an Unusual Event will be reccgnized by instrument alarms or indications, surveillance results or other observation of an of f-normal conditicn by an g individual at the station.

Many events within this classification invc1ve exceeding the LCO for plant operating parameters. For these cases, assessment and corrective actions are described in detail in Planc Proceduras. Supplementary assessment actions are described, where appropriate, in Emergency Implementing Procedures.

For events which require dispatching of or-egency teams, such as fire or first aid, the initial and continuing assessment will be performed by the team leader. His training and experience enable him to evaluate the condi tion , implement the proper corrective action and escalate the response as necessary.

Off site dose projections will be performed if the event involves radiological effluents exceeding the Technical Specification limits for instantaneous release. These dose projections are based on the rate and estimated duration of the release, and the current meteorological parameters.

They will be continually re 3ated throughout the duration of the release to reflect any significant changes. Methods for performing rapid dose projections include the use of 4 nomographs and map overlays which are described in detail in "

Emergency Implementing Procedures.

6.2.2 Alggt Assessment actions f or an Alert include upgrading of the functions performed for an Unusual Event based on the condition. Examples are:

o Increase surveillance of in plant instrumentation.

o Cbtain additional assistance from of f-dut y personnel and/or of f-site support groups.

o Assemble of f-site radiological monitoring teams.

o Intensify dose projection activities.

6.2.3 Site _Emgrgency Assessment actions f or a Site Emergency will be responsive to the increased probabilit y of major failure of plant safe functions and release of significant quantities of ran saactive material. Examples include:

o Increase surveillance of in s t ru me n ta t ion which may provide information on the status of the core and g reactor ccolant system.

Rev. 4, S/81 6-6

o Deploy off-site monitoring teams to perform direct radiation measurements, sampling and analysis of air

_y and other environmental media and perform evaluation of l

environmental thermolumineesent dosimeters (TLD).

o Correlate dose projection results with of f-site monitoring data, o Coordinate off-site dose assessment activies with DER / BHP.

o- -Increase reactor coolant sampling and analysis frequency.

6.2.4 _Ggng;;1_ggggggagy The emphasis _ of assessment actions for a General Emergency will te placed on the likelihood of substantial core degradation, potential loss of containment integrity and release of large quantities of radioactive material.

Surveillance of instrumentation relative tc the core condition, reactor coolant system activity, containment pressure and radiation level, and radioactive effluents will be increased. Dose projection and off-site monitorir.g efforts will be increased and continuous communications will be maintained with DER / BHP to ensure that cff-site dose assessments are based on the best available information.

(q ,j 6.2.5 off-site _Dgse_frgjegtign in the event of an accident at the Susquehanna SES, the Emergency Director will be respcnsible for initiating off-site dose projection and assessment activities. This activity will initially be performed from the Control Room. Available in the Control Room is data from the effluent monitors, vent stack flow monitoring stations, and the meteorological tower. This information will serve as inputs for computerized off-site doce projections. As a backup, Manual Calculations can be performed.

A Radiation Protection Technician will assist in making off-site dose projections and report results to the Emergency Director.

The Control Room, ISC and EOF are provided with site and county Edps for use in conjunction with isopleths for manual calculation of off-site dose. The thytoid and w ho le body dose isopleths serve as a backup to the computerized dose project ion system.

Concurrently, the Brergency Director will call in assistance to the TSC to solely handle the off-site dose projection activities.

The Health Physics Supervisor will report to the TSC within 30-60 mintues. Subsequently, . the of f- aite dose projection activities at the TSC will be turned over to the Radiation Support Manager at the EOF. The Radiatica Support Manager will report to the

,_ Becovery Manager at the EOF within tour hours of notification.

s r V

Rev. 4, S/81 6-7

The dose pro' :tions are verified by the off-site monitoring teams who att directed to selected monitoring icca tion (s) by the Emergency Director via radio communication. The results of the off-site monitoring teams surveys are used to up-date projected ll) doses and dose calculational assumptions. This process will be reiterated throughout the duration of the release in order to maintain an updated status of dose rates and accumulated dose within the pathway of the plume.

The initial of f-site monitoring team (s) will be staffed as required within 30-60 minutes. Additional team (s) will be dispatched within one to four hours.

Each off-site monitoring team will be supplied with an ionization survey meter, low volume air sampler, noble gas monitor and iodine analysis capability. In addition, four pressurized ion chambers will be positioned in the north, south, east and west sectors frcm the site at pre-determined locations supplied with electrical service. TLD's are located at 16 sites around the station to provide early information on accumulated off-site.

doses. Three sets of TLD's are provided at each of these sites; one set for ve :y early collection /exchangu >.a readout, one set f or dose accumalaticn during the period or release and one set for the total dose assessment due to the accident. The latter set has 66 TLD's at as many loca tions extending from the station to a dista nce of 92 miles.

The Emergency Director, and subsequently the Recovery Manager, will recommend appropriate protective actions tc the loca, state and f ederal agencies based upon the results of the off-site dose projection activities.

As described above, the emergency management activities are organized to facilitate rapid assessment of the off-site dose consequences of effluents from the station. All personnel assig ned to of f-site dose monitoring f unctions Will bP properly trained as to their technical areas of expertise and responsibilities under emergency conditions.

6.2.5.1 3e teorology The Susquehanna SES on-site meteorological measurement prog ra m is defined in Section 2.3.3 of the Susquehanna SES FSAH. In order to provide backu p f or this system, an agreement will be established with the Wilkes-Earre/Avoca Airport Weather Service Station for providing necessary weather informaticn for of f-site dose projection capabilities. The prima ry on-site metectological system will feed selected information to the Plant Process Computer f or of f-site dose projection calculations. The primary on-site meteorological system data is also available within the Control Room to sun. ort manual of f-site dose projection calculaticns. llg aev. 4, 5/81 6-8

A comparison'of the Susquehanna SES primary on-site

, 'seteorological system and the backup system at the

(  ; Wilkes-Darre Scranton Airport at Avoca, about 30 miles

^~' northeast of the Susquehanna site, for wind, temperature and atmospheric water vapor, precipitation, fog and saog, and stability is found in Sectin 2.3.2 of the Susquehanna SES FSAR. Due to their close proximity and similar topography, it is reasonable to assume the Avoca data is' representative of the site meteorological conditions.

The primary on-site meteorological system consists of a 300 foot tower located about 340 m to the southeast of the nearest station structures. This tower is instrumented to provide continuous data to the Plant Process Ccaputer ' and the Emergency Response Computer System to define the stability and movement of the air layer into which the effluent from the facility could to released for close assessment purpcses.

6.2.5.2 gganutgr_jgthgds

'A computer program called the Radiatica Dose Projection Service will be used to produce initial transport and dif f usion estimates within 15 minutes following classification of an accident. This service is available from the process computers used in the n Advanced Centrcl Hoom (Aca).

(o) o Inputs (1) Meteorological tower da ta (2) Vent monitor data (3) Grab sample data o Outputs (1) Whole body doses (2) Thyroid doses c Calculational Features (1) The program wilI calculate doses in the middle of each sector at pre-determined j

distance. Flexibility exists to also l calculate dose at user specified grid coordiantes.

(2) Nine Design Basis Accidents (DBA's) can be selected for as cicse as porsible

(~) approximation of the type of accident

\> occurring. The selection of a DBA allows the Rev. 4, 5/81 6-9

? +r--- e n e

1 computer to calculate the relative percentages of isotopes contributing to the gross vent monitor readings.

(3) The whole body dose equaticn accounts for external radiation from both noble gases and iodines.

(4) The thyroid dose equation accounts for ooth dry deposition and wet deposition as a f unction of distance downwind.

(5) Doses for eight concentric distances are Cdlculated for every run. Two of these distances are the boundary cf the Low Population Zone (LPZ) and the boundary of the Exclusion Area. Doses f or a number of points including site boundary limits and local high population areas such as Nescopeck, Hazleton, and Berwick are also calculated for every run. Additiona l concentric distances and pcints may be evaluated as necessary.

(6) 'The decay of radioisotopes as a function of the time it takes for the plume to travel to the point of interest is accoun ted for.

(7) The concentrations of each isotope can be entered as derived from grab sample data llg instead of using the air monitor gross readings.

o Operational Features (1) Accessible from all computer consoles through d dedicated keyboard pushbutton.

(2) Provides whole body and thyroid dose projections on a cumulative basis for coordinates specified at initiation time.

(3) Provides the ability to car ry out study case runs without affecting the o n-line data nor interrupting the periodic real time runs. As an example, this feature could be used to evaluate the consequences frcm the release of the containment source term indicateri by the containment monitor.

(4) Provides a detailed printout including all inputs for each dose calculation run.

(5) Can be used to calculate doses even if the vent monitors and meteorological tower are out of service using use r-supplied input.

Rev. 4, S/81 6-10

'6.2.5.3 _jggggl_5gthgdg

~~'

sanual methods are used as backup to the computer programs.

o Airborne Release Data from the meteorological tower and radiological monitors such as the containment monitor and vent monitors will be used together with isopleths and noaographs to project whole body and thyroid doses. These estimates will necessarily be conservative since parameters such as wet and dry deposition and radioactive decay are not taken into account. By knowing the type of accident, this procedure can also be utilized to project doses should the vent monitors or meteorological tower be out of service.

O Liquid Release Estimates of downstream river wa ter concentrations will be made by employing discharge monitor data, discharge flow ra tes and river eleva tion readings.

The river elevation will be used to estimate the travel time to the point of interest. The degree

^ of mixing, obtained from a graph will be utilized,

(~J N- together with the discharge monitor da ta, and the discharge flow rates to calculate downstream concentrations.

6.3 CORREg]IJE_ACTJgE Detailed operating procedures and Plant Procedures are utilized by the plant opera ting personnel to assist them in recognizing emergency events and taking the corrective actions necessary to place the plant in a safe condition.

Additionally, Emergency Implementing Procedures describe subsoguent and supplemental corrective actions for the scope of potential situations within each of the emergency classifications. These procedures are designed to guide the actions of the personnel to correct or mitigate t he condition as early and. as near to the source of the problem as teasible. Actions are specified, for example, which may prevent or significantly reduce a potential release of radioactive material, provide prompt fire control and repair. The Emergency Implementing Procedures are also utilized as emergency training media and are the basis for response during periodic emergency drills.

Some essential corrective actions may involve the risk of higher-than-normal radiation exposure to emergency response (s) personnel. Such actions could involve preventing the release of large guantities of radioactive material, reducing damage to ma jor equipment or life saving actions.

Rev. 4, 5/81 6-11

Table 6.2 and Section b.5.1 specify the limits for such emergency radiation exposure and other relevant criteria to be considered. The Emergency Director is responsible for all corrective actions taken to mitigate the consequences of the accident on-site, even after the EOF is activated.

6.4 PROTECTIVj_ ACTIONS Protective actions are implemented to prevent or mitigate conseguences to individuals during or af ter a radiological incident. Protective actions within the Susquehanr.a SES site boundary are the responsibility of the Susquehanna SES Emergency Director, but may include assistance by of f-sit e organizations. Protective actions outside the Susquehanna SES site boundary are primarily the responsibility of State and 1ccal emergency organiza tions, but may include coordination of activities, dissemination of appropriate data, and recommendations by the Susquehanna SES Emergency Director or Recovery Manager.

b.4.1 Cn-Site Protective Actions The primary protective measure for on-site personnel in an emergency is prompt evacuation f rom areas which may oe c5fected by significant radiation, contamination or airborne radioactivity.

Respiratory protective equipment and clot'hing are provided h at the plant and in the various emergency equipment kits for all personnel who may be required to perform emergency dCtiVities.

Control of in-plant contamination is in accordance with Susquehanna SES Health Physics procedures. In the event of radioactive contamination outside fenced security areas, but within the exclusion area, access to such areas shall be contrclled by PPSL.

There are no pctentially atfected agricultural products or water supplies within the Susquehanna S ES exclusion area.

Following are some significant aspects of the evacuation categories for implementation of protective actions for on-site p e rs or.n e l:

6.4.1.1 Local Area Evacuation This ca tegory refers to evacuation frcm one area to another area within the same building. The initiation cf a Local Area Evacua tiori results frcm ARM or CAM alarm (s) Sounding in the same area within a building or from observed conditions such as smoke or toxic gas, which may indicate a possible habitability problem.

The initial restonse for irid iv id ua ls is to evacuate to g

an' unaffected area of the building, notify the plant Rev. 4, S/81 6-12

,. Control Rcca of the conditions and avait further t instruction. The Emergency Director shall-assess the situation, activate d'ppropriate procedures to rectify the condition and inform, via the PA system, the personnel when to return to their resractive work area.

6.4.1.2 Controlled Zone Evacuation This category refers to evacuation f rcn areas within the protected area boundary.

~

A Controlled Zone Evacuation requires that all non-essential individuals i within specified areas of the controlled zone assemble in their respective Station Assembly Areas. These ,

Station Assembly Areas are located in the Service and Administration Building and in the Ccnstruction Office l Euilding. Personnel who enter the plant through the  ;

north security gate will assemble in the Service and Administration Building area. These are station ,

personnel, visitors and non-construction contractors.  ?

Construction-related personnel and others who enter the plant via the south security gate will assemble at the Construction Office Building. The Security Section shall maintain the appropriate security posture, including access control as defined by the Susquehanna SES Physical Security Plan and Implementing Procedures.

<- The initiation of a controlled Zone Evacuation results

(,S) from ARM, C AM or otner applicable monitor alarms, (i. e. , fire alarms) . Notification for personnel to proceed with a controlled Zone Evacuation shall be announced over the plant PA system or the emergency alarm system. The initial mandatory response by individuals is the same as for a Local Area Evacuation; namely, e vacuation to an una f f ected area. In this case, however, the nea rest such area may not be in the same building, and multiple ARM, CAM or fire alarms are probable.

The actual decision to implement a Controlled Zone Evacuation is the responsibility of the Susquehanna SES Emergency Director. This decision is based largely on his evaluation and judgement of the nagnitude and severity of the particular situation. Factors to be considered must include the apparent levels of radiation and/or airborne radioactivity involved, the exposure to personnel that would result from evacuating as well as not evacuating to the S ta tion Assembly Areas. In the event of multiple fire alarms within the Controlled Zone, with no potential hazard to personnel, such as construction workers in unaffected areas, the Susquehanna 3ES Emergency Director may leem it prudent not to evac Jate such personnel and allow work to continue.

\.]

5 Rev. 4, 5/El 6-13

A Controlled Zone Evacuation shall be implemented within the times specified in Table 6.3 for each range of dose rates or radiciodine concentrations prevailing within the affected areas. These times at the specified levels correspond approximately to radiation doses of 5,000 mrem to the whole body, ot 25,000 mrem to the thyroid. Personnel accountability of station personnel, visitors and non-construction contractors is made at the Station Assembly Area. Accountability of evacuated and non-evacuated personnel will be performed in accordance with emergency Implementing Procedures and the results transmitted to the Susquehanna SES Emergency Director.

l 6.4.1.3 jitg_Agga_ Evacuation Site Area Evacuation requires that all indi vid uals within the Susquehanna SCS site area, except for Control Rcom operations personnel and others with specific emergency assignments, evacuate and proceed to the designated Remote Assembly Area. The primary Femote Assembly Area is located at the PPSL structure known as the Pelton liouse, to the southwest of the plant, as shown in Figure 6.1. The alternate Remote Assembly Area is the Susquehanna SES Simulator Building. Security personnel will be advised of the designated area, will help to ensure tha t all personnel proceed to the designated location, will provide access l control, and will provide f or per.;onnel accountability.

l Implementation of a Site Area Evacuation is the responsibility of the Susquuhanna SES Emergency Director. That decision is based on the severity of th e incident, the likelihood of e ;calation, and the radiation and airborne radioactivit y levels throughout the station, particularly at the Station Assembly Areas. Station Assembly Area dose rates and concentrations are determined by radiation monitors and air sample collection devices which a re loca ted in the l vicinity of each asaembly area. A Site Area Evacuation shall be implemented within the times specified in Table 6.I for each range of dose rates or radiciodine concentrations at aither Station Assembly Area.

l Notification of a Site Area Evacuation is made via the plant emergency alarm system, consisting of evacuation siren and message announcement.

Accountability is accomplished in passage through the security gate and supervisor y checks a t the assembly area. Personnel and vehicle contamination surveys are performed at the Remote Assembly Area, using portable survey instruments.

6.4.2 gli;211g_Eggigglign_Aglichs Rev. 4, 5/El 6-14

,s The responsibility f or actions to protect o f f-sit e

) individuals rests with the Commonwealth of Pennsylvania, as

'> described in Annex E of the Commonwealth of Pennsylvania Disaster Operations' Plan. PEMA is responsible.for implementa tion of that plan.

DER /BRP is responsible f or evaluating inf orration obtained from the Susquehanna SES and other sources and recommending appropriate of f-site protective actions to PEM A. Such recommendations, based on all available data, local constraints and other considerations may include:

o Shelter f or af fected populations o Evacuation within a specitied radial distance o Administration of thyroid prophylaxis o Control of contaminated agricultural p rod uc ts The principal off-site local coordinating agencies for providing response to radiological emergencies in the vicinity of the Susquehanna SES are LCCD and CEMA. Since the area and population inside the ten-mile emergency planning zone are partially within Columbia County, parallel emergency response functions are provided by CEMA. Upon

('N notification by the Susquehanna SES Emergency Director or

(. ) PEMA of a situation which may require protective actions for o f f- s ite populations, LCCD and CEMA will initiate appropriate actions in accordance with specific instructions from the notif ying party, and within the guidelines of the LCCD and CEMA emergency plans. If time permits, LCCD and CEMA will obtain a review and verification by PEMA of recommendation made by the Susquehanna SFS Emergency Director or Recovery Manager.

LCCD and CEMA have the capability and detailed plans for impicaenting protective actions which include:

o Implement prompt notification of the population within ten miles of the Susquehanna SES t hr ough the use of the Public Notification Sy stem described in Section 6.6.

o Transmit specific instructions to potentially affected populations o Provide assistance for evacuation of the pop ula tion within the ten-mile emergency planning zone l 0 Provide reception and mass care centers f or evacuated individ uals b'#

Occupants within the ten-mile emergenc y planning zone of the Suaguehanna SES will be provided with information regarding l

emergency planning. This inf orma tion will describe the Rev. 4, 5/81 6-15

method by which they will be notified of an emergency and wi_1 provide specific instructions to f ollcw upon receiving such notification. Additional discussion of the content and method of distribution of this information is contained in Sectica 8.0.

A detailed study has been conducted of the status and capacities of roads, traffic patterns and demography within the ten-mile emergency planning zone. This study includes the estimated times to evacuate all or segments of the population, identifies potential problem a reas and provides contingencies for dealing with adverse conditions. This study was utilized in the development of detailed evacuation plans by LCCD and CEMA. A summary of this study is presented in Appendix G.

6.5 AID _TC_AfEECTED_PERSGNNEL Established procedures provide for control of emergency exposure, perscnnel contamination, and for assistance to injured persons including situations involving complications due to the presence of radiation or radioactive contaminction.

6.5.1 Jmergency_Expgsure All reasonable measures shall be taken to maintain the radiation exposure ot emergency personnel who provide llh rescue, first aid, decontamination, ambulance or medical treatment services within applicable quarterly liaits s peci fied in 10CFR20. Table 6.2 summarizes the emergency exposure criteria for entry or re-entry into areas for purposes of undertaking protective or corrective actions, such as fire control, minimizing damage to facilities and reducing the release of effluents, and for carrying out life saving activities. Methods and conditions for permitting volunteers to receive emergency radiation exposures are described in Emergency Implementing Procedures, and provide for expeditious decisions with consideration to known cad reasonable balance of associa ted risks.

6.5.2 Eece n ta m ina tion _a n d_Ei rst_ A id personnel contamination in emergency situations shall be ccatrolled to the extent feasible by the normal methods of using protective clothing and surveying f or contamination following the removal of such clothing. Personnel decontamination areas, consisting cf sh owe rs and sinks which drain to the radwaste system, are available for either routine or emergency use. Sta tion employees a re instructed in the proper methods of removal of minor contamination from skin s u r fa ce s. Decontamina tion ef f orts involving significant amounts of contamination, particularly in the vicinity of facial openings, however, shall normally be g

performed under the direction of Health Physics personnel.

Rev. 4, 5/81 6-16

Detailed methods for personnel decontamination are described in health Physics procedures. A listing of typical

("}__ decontamination equipment located at the personnel decontamination areas is provided in Enclosure 1 of Appendix D. (Appendix D lists equipment and supplies relative to this Plan.)

At least two persons who are qualified in first aid methods shall be on-site at all times. First aid to injured personnel can normally be performed in canjunction with any necessary decontamination methods. However, if immediate treatment of the injury is vital, that treatment shall take precedence over decontamination. This philosophy also extends to off-site emergency assistance involing radioactive contamination. For that purpose, measures are established to ensure timely of f-site medical treatment, as described in Sections 6. 5. 3 and 6.5.4.

6.5.3 gedic,1_

3 Transportation Arrangements have been made for the tra nspcrta tion of patients from the Susquehanna SES, who may have injuries complicated with radioactive contamination or who may have been involved in radiation incident, to a medical treatment facility. Organizations with which these arrangements have been sade are:

()'

Shickshinny Area Volunteer Ambulance Association Shickshinny, PA Pond Hill-Lily Lake Fire Co.

Pond Hill, PA Nescopeck Ambulance Association Nescopeck, PA Hobbie Volunteer Fire Co.

Hobbie, PA Copies of agreements to provide emergency services from these organizations are contained in A ppendix A. Ambulance emergency supply kits, which typically contain items shown in Enclosure 2 of Appendix D, are available for use.

6.5.4 Medical Treatment Arrangements have been mado for medica l trea tmen t of f patients from the Susquehanna SES, who may have injuries complicated with radioactive contamination at:

The Berwick Hospital Berwick, PA r

\J Similar arraugements have been made, through Radiation Management Corporation, Philadelphia, P A, for medical Hev. 4, S/81 6-17

treataent of contamination injuries and significant over-exposures to radiation, and for evaluation of radioactive material uptakes at:

Radiation Medicine Center Hospital of the University of Pennsylvania Philadelphia, PA The arrangements with Radiation Management Corporation also include provision f or consultation with experts in radiation and nuclear medicine.

Copies of agreements to provide medical treatment from these organizations are contained in Appendix A.

The Radiation Medicine Center is adequately supplied and equipped to receive and treat contaminated patients. A set of contamination control supplies are provided at the Berwick llospital. A typical list of this equipment is shown in Enclosure 3 to Appendix D.

6.6 PUBLIC NOTIFICATION SYSTEM An early alert siren system consisting of 105 sirens ranging from 107 db to 125 db exists within the ten-mile Emergency Planning Zone (EPZ) around Susquehanna SES. Siren location Wds determined by a detailed study including field surveys, actial determination of average 1.ackground noise level, and llg considera tion of population distribution within the ten-mile EPZ.

Activation of the Siren System is via radic control from Luzerne County Civil Defense and Columbia County Emergency Management Agency EOC. Activation by either County ECC will dCtiVate the entire siren system.

The Nuclear Emergency Alert sig na l is a steady 3-5 minute wail. This enunciation will occur three times within the first 15 minutes of activation. Public response is to procecd indoors and tune their radio or television to the Emergency broadcast System Network serving their local area for appropriate additional information.

This public notification system provides a means to alert the pcpulation within the ten-uile EPZ within 15 minutes of an energency condition. Testing of the system will take place annually and will include independent verification of the system's ability to alert the ge ne ra l public. Figure 6.2 shows the location, coverage area and size of the sirens that make up the public notitication systes.

O Rev. 4, 5/P1 o-18

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• TABLE 6.1 SUMMART OF IMMEDIATE NOTIFICATION AND RESPONSE EMERGENCY - CRITERIA IMMEDIATE NOTIFICATIONS IKMEDIATE ACTIONS -

CLASS ON-SITE OFF-SITE ON-SITE PERSONNEL OFF-SITE PERSONNEL UNUSUAL Off-Normal Events o Fire Brigade o Fire Units o Fight Fire o Provide Fire' Fighting Assistance EVENT Which By Themselves o Damage Control Teams o Rescue Assis- o Perform Emergency Repairs o Assist in Rescue Operations Do Not Constitute o Surveillance Watches .tance o Designated Surveillance o Provide Medical Transportatloa Significant Events, o First Aid Teams o Ambulance Ser- Functions But Could Indi- o Rescue Teams o Provide Hospital Medical Treatment vice o Adataister First Aid o Assist in Damage Control cate a Potential o Monitoring Teams o Hospital o Conduct Rescue Operations o Provide Info to the Public via the Degradation in the o Security Force o LCCD o On-Site Monitoring & Dose media

, Level of Safety o Dose Projection Personnel o CEMA projection of the Plant 4 o PEMA o Appropriate Security Mea-o NRC sures As May Be Required' -l o PP&L Head- o Perform Cor.tinuing Assess .

quarters ment a Special Office Of The fresident ALERT Events Which Indi- o Fire Brigade o Approptiate o Activate TSC as Appro-cate an Actuel o Damage Control Teams [o Provide On-Site Assistance as Local Assis- priate required Degradation in the o Monitoring Teams tance o Fight Fire Level of Safety o Dose Projection Personnel

-o Alert Key Persona =1 to Standby o LCCD o Perform Emergency Repairs o Conduct Confirmatory Dose Projections of the Plant o Security Force o CEMA 3 o On-site and Off-site o Maintain Emergency Communications o PEMA ' Monitoring o Provide Info to the Public via the o NRC o Off-site Dose Projections media 1

o PP&L Head- o ApproprLate Security quarters Measures o Special Office o Augment Onshift Resources Of The President o Perform Continuing Assess-ment Rev, 4, $/81 4

n -

e - aA

_ pg f% >

() ("}\

\

TABLE 6.1 (Cont'd).

StrMMARY OF IMMEDIATE NOTIFICATION AND RESPONSE EMERGENCY CRITERIA - IMMEDIATE NOTIFICATIONS .IMMEDIATE ACTIONS CLASS- ON-SITE OFF-SITE ON-SITE PERSONNEL OFF-SITE PERSONNEL SITE Events A ich in- o Appropriate Emergency o Appropriate o Alert Total Emergency-DtERGENCT o Provide info to the Public via the media volve Actaal or Teams local Assistance Organization o Provide On-site Assistance as Required Likely Major o Security Force o LCCD o Take Appropriate Correc-. o Activate and Man Response Centers Failures of o All other Station Personnel o CEMA 3

tive Action o Mobilize Emergency Response Personnel Plant Functions o PEMA o On-site Monitoring o Place Public Notification System and Needed for Pro- o NRC o Provide info for offsite Procedures in Standby Status tection of the o PP&L Head-Public dose proj. o Implement Appropriate Near-Site quarters o Appropriate Security -Emergency Protective Measures o Special Office Measures o Maintain Emergency Communications Of The President o Augment Resources / o Offsite Monitoring & Dose Projections Activate Emergency Centers o Recommend Off-site Action o Personnel Evacuation as Appropriate o Perform Continuing Assess-ment CENERAL Events Which o Appropriate Emergency o Appropriate o Activate Total Emergency DtERGENCY Involve Actual or Teams o Provide info to Public via Media local Assistance Organization 'o Provide On-site Assistance as Imminent Substan- o Security Force o LCCD o Take Appropriate Correc- Required.

tial Core Degrada- o All Other Station Personnel o CEMA tive Action tion er Melting 3 o Fully Staff Response Centers o PEMA o On-site Monitoring o Activate all Emergency Response with Potential for o NRC o Appropriate Security Loss of Contain- Personnel o DOE Measures- o Implement Public Notification Proce-ment Integrity o PP&L Head- o Augment Resources / dures qurters Activate Emergency Organ- o Continuously Evaluate Dose Projections o Special Office ization o Implemes.t Appropriate Off-site Emer-Of the Presi- o Personnel Evacuation as gency Protective Measures Appropriate o Maintain Emergency Commmuunications -

o Perform Continuing o Recommend Off-site Action Assessment-On-site notification is normally by plant PA system.

Allmessage offsite notifications except those made via " hot line" or through the PP&L system operator require authentication.

Rev. 4, $/81 3 4 Notification is required within 15 minutes of indication and verification cf the event.

Timely, but not necessarily immediate, notification.

l

Table 6.3

(~')

SEJIEEll_f0R EVACUATION _Qf 99EIE911ER_39El_132293_EIII 3EI!' l Whole Body Dose Implement Radioiodine Rate Reachest Evacuation concentration Reaches 2

__Jgggs/hrl_______ __ Within__ _____J_91/cg1________

Up to 600 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Up to 1 X 10-5 600 to 1000 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 1 X 10-5 to 2 X 10-5 1000 to 2500 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 1 10-5 to 4 I 10-5 2500 to 5000 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 X 10-5 to 7 X 10-5 5000 to 10,000 30 minutes 7 x 10-5 to 1 X 10-*

10,000 to 20,000 15 minutes 1 X 10-* to 3 X 10-*

>20,000 IMMEDIATELY >3X 10-*

1. Whole body dose to non-emergency personnel not to exceed 5000 mrem frcm the event.

2. Maximum concentration for specified time ccrresponds to approximately 25,000 mrem gdult thyroid dose commitment.

Radioiodine concentration vs. adult thyroid dose commitment based on July, 1977 Draft, Appendix D, to USEPA Manual of Protective Action Guides. Radioiodine nuclide distribution g-) corresponds to T+4 hours following reactor shutdown.

U

3. In using Table 6.3, it is impo rta nt to reccgnize tha t there is no direct correllation between the whole body dose rates and the radioiodine concentrations; and the measurements or projections of each must be performed 'inde penden tly. In the event that only a direct radiation determination is dVa11dble, with no Corresponding knowledge of th e concentra tion or fraction of the total which is attributable to radioiodine, the most conserva tive assumption s specified in the USEPA Manual for Protective Action Guides would be required. Such assumptions, based only on direct radiation deter mina tions, would likely result in gross over-estimation of thyroid dose cormitment.

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t.s TABLE 6.4 ' ; Pzgs 1' ('"4

' PROTECTIVE ACTION RECOMMENDATIONS A. Caseous Release PP&L Actions PP&L Recommendations I. General Public Determine the following: Recommend Sheltering if:

1 Length of time release 1. Projected doses are~ expected to

.in progress. approach 1 Rem Whole Body or 5 Rea i to infant thyroid but not to exceed

2. Anticipated length of time 5 Rea or 25 Rem respectively and release will continue. +

2. The combination of warning time,

, 3. Rats of release plume arrival time and release time is not long enough to effect evacua-

4. Stability of release rate. tion; 33;

5. Meteorological Conditions 3. , Af ter evaluating time of day, weather and road conditions, evacuation cannot

a. Wind Speed be effected so as to avoid a significant b.

Precipitation fraction of expected ' exposure; and/or

c. Stability Cissa,

d. Wind Direction 4. Sheltering appears to be the best option available.

6. Quantity of release.

Recommend Evacuation if:

7. Calculate projected dose.

1. A core melt accident is underway which involves or expects to involve a loss of containment integrity by melting through or direct release to the atmosphere; $3;

2. Projected doses are expected to approach or exceed 1 Rem Whole Bcdy or 5 Rem to the infant thyroid; and 4

a) Release time is expected to be.long.

b) Evacuation could be well under way before plume arrival based on vind.

speed and travel conditions.

c) Substantial dose savings can be made by avoiding exposure to surface de-position of radioactivity.

3. After evalur, ting all condi.tions, evacua .

tion appears to be the best option avail-able.

Rev. 4, 5/81 s

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(' C 'v Pega 2 TABLE 6.4 PROTECTIVE ACTION RECOMMENDATIONS Gaseous Reicase (Cont,) PP&L Action Results PP&L Recommendations II. Dairy Cows 1. Determine the following:

a. Projected or Actual a. Equal to or ggeater integratedagconcen- than 14 X 10 (Ci-See) tration of I ,3

b. Meteorological Conditions b. Known sectors DER /BRP to recommend potentially affected appropriate protective (1) Wind Speed action to affected (2) Precipitation farmer w (3) Stability Class (4) Wind Direction

c. Project deposition c. Equal or greater than concentration 14 LCi ,

M Rev. 4. 5/81

s w i

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'P:gt 3 TA3LE 6.4 PROTECTIVE ACTION RECOPCENDATIONS 4

Emergency Conditions PP&L Action Results PP&L Recommendations B. . Liquid Radioactive 1. Dete m ine the following: If the: 1. Assess Danville Release into Water Authority ~

Susquehanna River a. Source of release a. . Limits specified in in-line monitor

b. Quantity of release 10CFR20 Appendix B reading,

c. Anticipated length of are exceeded:

time release will continue. 2. Based on above, consider termination

2. Notify: of user intake of all i

downstream users.

a. DER /BRP

b. Danville Water Authority

c. NRC

3. Initiate sampling of:

a. release reint

b. Susquehanna River C. Plant in a degraded 1. Evaluate potential source (s) 1. If exceed limits 1. Protective actioca condition with po- and quantity of release specified for gaseous based on the criteria tential for signifi

• or liquid release for the type of cant release of 2. Perform Dose Projection release.

radioactive -

based on potential - - ' '

{ material. release, i

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      ;        Emergency facilities and equipment are provided to ensure the capabilities.for prompt, efficient assessment and control of situations o'ver the entire spectrum of probable and postulated emergency conditions. The facilities and associated equipsent, and their e9ergency f unctions, are described in this section. Conceptual design descriptions for the TSC, OSC, EOF, SPDS, NDL and ERCS are included in Appendix I.

7.1 gy-SI))_jgj3 G EJCI_C]NTfgS 7.1.1 Jtatign_ggniggl_ Boom The station control Room is the primary location for the initial assessment and coordination of corrective actions for essentially all emergency conditions. The Control Room is equipped with the readout and controls for all critical plant systems, the readout and assessment aids related to radiological and meteorological monitoring systems, and access to all station CommuPiCation systems. A typical listing of Contrcl Room emergency equipment is provided in Enclosure 4 of Appendix D. Of f-site emergency coordina tion f unctions initially served by the control Rocm will be transferred to the Technial (s Support Center or Emergency operations Facility for a Site (,) or a General Emergency as deemed appropriate by the Susquehai.7a SES Emergency Director. The p ri ma ry consideration is to ensure that the number of peraonnel involved with the emergency in tne Control Room shall not impair the safe and orderly shutdown of the reactor or the operation of plant safety systems.

;       7.1. 2       Technical SuragIt_Cggter Heference Appendix 1, Section 2.0 for conceptual design descriptions of the TSC.

7.1.3 922Iations Sgyport_ Center Reference Appendix I, Section 4.0 for conceptual design descriptions of the OSC. 4 7.2 ffEl_Sff:!IIf_fgEEjjpCl_gERIjpg 7.2.1 fndig_gyerations contor The Media operations Center (MOC) will be utilized for all news conferences. The Berwick YMCA, Berwick, pA, is the designated Media Operations Center with dedicated space to accommodate nebs Conferences for 500 people. Appropriate (~) v facilities will be provided for news media personnel. R e v. 4, S/El 7-1

7.2.2 Jaergsagy_9Bsrali9as_facilitt Reference Appendix I, Section 3.0 for conceptual design descriptions of the EOF. 7.3 C9EET1_AEp_STATj_ggggGggC1_CSETjgS 7.3.1 C9un ty_ Egeggeggy_Centygs The ten-mile emergency planning zone for the Susquehanna SES includes areas and populations in Luzerne and Columbia Counties. Each of these county jurisdictions has Emergency Operations Centers which meet or exceed the einimum Federal criteria for sufficient space, communicaticns, warning systems, self-suf ficiency in supplies and accommodations and radiological protection factor. Both counties maintain I f ull-time employees, providing 24-hour per day coverage at their EOC, to coordina te emergency planning and evaluation.

       " Hotline" telephcne connections between Sus.juehanna SES and each County EOC ensures prompt notification capability during all Emergency Classifications.

Location Of the county Emergency Operations Centers are-o kyggggg_gguggy_ggggggggy_gggggtiggg_gggtyg Luzerno County Office of Civil Defense Luzerne County Court liouse Wilkes-Barre, Pennsylvania g o ggl u g bla_ggyn ty_ Egerse ngy_ og era t iggg_ge n t er Columbia County Emergency Management Agency Columbia County Court House Bloomsburg, Penn s ylva n ia 7.3.2 S tg t g_im egge ngy_g en t gg The S tate Emergency Operations Center is lccatad at the PEMA head g ua r ters, in the Transportation duilding, in Harrisburg. This center is equipped with a reliable c cu m u nica tion s system which ties all area and county emergency operations centers with PEMA h eadqua rters. During an emergency, representatives f rom appropriate State agencies will assemble at the State Emergency operations Center to manage and support the emergency responoe activities. Facilities dre a Vailable at the near-site EOF f or P2M A personnel. Twent y-f our hour per day co verage at their EOC and maintenance of the PEMA call-out duty roster is described in Annex E of the PEMA Disaster Ope & ation; Plan. - 7.4 ASSESSMENT FACILITIES O Hev. 4, 5/61 7-2

The primary energency assessment facility is the station Centrol Room. Supplementary and complimentary assessment fhnctions are performed in the EOF and the TSC. (x s) In addition to the systems, equipment and instrumentation for assessing plant status, the followin9 Frovide for both initial and continuing assessment of emergency conditions. 7.4.1 jadiati2D_d9Dit9E Dg_gyptgm i This cn-site system, consisting of ARMS, CAMS and process monitcrs, contributes to personnel protection, equipment monitoring and accident assessment by measuring and recording radiation levels and concentraticns of radioactive material at strategically selected locations throughout the station. A listing of these radiological monitors is contained in Enclosure 8 to Appendix D. 7.4 2 figg_pgiggligg_gyptgan Fire protection at the Susquehanna SES is provided by a complete network of fire suppression and extinguishing systems. These systems and associated fire alarms are activated by a variety of fire and smoke detection devices which are located throughout the plant. These fire detection systems are identified in the Susquehanna SES FSAR and Fire Protection Heview Report. k> 7.4 3 Batural_Ehengmgna_3onitogg Monitors are provided for detecting and recording natural phenomena events that could result in plant damage due to ground motion or structural vibration. These monitoring systems are identified in Enclosure 7 to Appendix D. 7.4.4 Environmental Monitoring , The primary functions of the environmental radiological monitoring program are to establish the pre-operational background levels, detect any gradual buildup of long-lived radionuclides, and verify that operation of the plant has no detrimental effect on the health and safety of the public or the environment. Sampling media from the environmental monitoring locations may, however, be utilized to obtain valuable assessment data in the event of an accident involving the release of a signif icant amount of radioactive material. Enclosure 10 to Appendix D identifies the I enviroamental monitoring systems. 7.4.5 Emergency _3gnitgrinj_ Team _g2uinagnt l A listing of equipment provided for use by cn-site and off-site radiological monitoring teams to aid in emergency

   ,_s assessment is contained in Enclosure 5 to Appendix D.

(J i Rev. 4, S/81 7-3 l

1 7.5 fjgTEGTIyj_ffg]GIIIES l l Facilities and designated assembly locations are provided which ensure adequate radiological protection for personnel lll assigned to emergency duties in the plant, and for the dCComBodation of other personnel evacuated from areas that may be affected by radiation and/or airborne radioactivity. 7.5.1 Control Room In addition to serving as the first-line centrol for emergency situations, the Control Room has the following features which provide protection for perscnnel who may have emergency or operational duties throughout the course of any emergency:

1) Adeq ua te shielding by concrete walls to permit continuous occupancy under severe accident conditions.

2) An emergency air supply system, cJuipped with IIEPA and activated charcoal filters.

3 Continuous monitoring of radiation levels in the Control Room and throughout the plant by the AR1 system, with readout in the Control Recm.

4) Emergency and essential lighting a nd power.

5) Basic protection equipment for emergency teams (Appendix C) , and listings of emergency supplies / equipment, and their locations within the station.

b) Communications systems, as described in Section 7.6. Additional details regatding the desig n and inherent protective capabilities of the station Control Room are discussed in the Susquehanna SES Units 1 and 2 FSAR.

7. 5. 2 Statioy_ Assembly _ Areas Specific locations are designated f or assembly of personnel dt the station in the event of a Controlled Zone Evacuation.

These areas provide space to accommodate all personnel who may be at the station. They are located on the b.tsis 'o f logical access routes and physical separa tion from likely dreds of radiation and/or airborne radioactivity. "' h e locations and the individuals assigned a re:

1) service and Administritive Building Personnel who have entered the pla nt via tha north security gate will normally report to this area. This includes FPT,L employees, visitors and non-construction l contractors. The responsibility to ensure that an Rev. 4, 5/81 7-4

escorted visitor evacuates to the proper area is that of the individual escorting the visitor at the time () evacuation cccurs. In isolated cases, construction-related contractor personnel say enter the plant via the north security gate. In such cases, those individuals will also report to the SSA Building in response to a Controlled Zone Evacuation.

2) Cggsitsg11gn_giligs_an11ging All personnel who have entered plant via the south security gate will report to the Const ruction of fice Building. This includes all construction-related contractor personnel, with the exception identified immediately above.

3) Jegsgity_fggsggngl Security Section Personnel will perform duties at locations specified in the Susquehanni SES Security Procedures.

7.5.3 Bemote Assembil _Arg3s These areas are designated for assembly of personnel from

 /~         within the site area in the event of a Site Area Evacuation.

(-)' The primary location is the vicinity of the PPSL-owned EOF, The location of the Remote Assembly Area was selected on the basis of:

1) Space is available for all personnel who may be within the exclusion area at the time of an evacuation.

2) This locatica provides reasonable assurance of a controlled area, and for control of ing ress/ egress f or contamination surveys and for posaible establishment of decontamination stations.

An alternate Remote Assembly Area, in a different wind sector from the EOF, is the Susquehanna SES Simulator Parking Lot (See Figure 6.1) . If, based on radiological measurements at the Remote Assembly Areas and/or data from the Contrcl Room, neither of  ; those locations is deemed by the Susquehanna Sns Emergency Director to be appropriate, provisions can be made for the i movement of evacuees to an unaf fected area. In such an l i unlikely event, the location for reassembly is the PPSL I l Service Center at Hazleton, PA. l l i l l Rev. 4, S/81 7-5  ; i

i 7.6 Connus1CAIIgys_sysIgns Reference Appendix 1, Sections 2.7, 3. 7, 4.5 and 8.3 for conceptual design descriptions of systems except for the lll following:

1) Cgagonwealth/pell_Tglgphogg_Sygtgg Locations of Extensions include, o Contrcl Room o Operations Support Center / Technical Support Center o Emergency Operations Facility o Station Assembly Areas o Remote Assembly Areas o Remote Shutdown Panel o Media Operations Center

2) flant_ Egg 132ncy_Aldgg_jygigg

• A plant emergency alarm system provides audible warning of emergency conditions to plant perscnnel. The system consists of a multi-tone siren, tone selector switch, area selector switch, and message tape recorder. The Emergency Alarm System is integral to the PA System and is powered via the Vital AC UPS. The Plant Emergency Alarm System shall be testei at least mon thl y.

7.7 gy-SIJE_{IEST_AIC_ App _MEpICAL_ FACILITIES First aid treatment facilities, equipped with normal industrial first aid siipplies, ar e loca ted near the Access contrcl Area and near the machine shop. Standard first aid kits are at designated locations throughout the station, including: o Control acom o Access ont r ol A rea o Machine Shop o Instrument Shop o Chemistry Labotatory o Health Physics office o North and South Security Gates o Technical Support Center o Operations Support Center The first aid kits a re checked periodically, in accordance with statica procedures, and replenished as necessary. Stretchers are stoted at designated locaticus in the following arras: o o lurbine Operating Floor Heactor Duilding (2 loca t ions) lh Bev. 4, 5/81 7-6

o Access Control Area

 , r"y      o    Radwaste Building LJ 7.8  pagAg]_CQ!TEgl_j$UIPMENT Damage control equipment consists of normal and special purpose tools and devices used for maintenance functions throughout the station. Personnel assigned to damage control teams are cognizant of the locations of specific equipment which sa'   9 required in an emergency. The Susquehanna SES Ear ancy Director has access to keys . for maintenance tool cribs, shops and other locations where appropriate damage control equipment may be stored.

Implementing Procedures provide guidance for damage control teams, and include inventory check lists for designated damage contrcl equipment. Heavy duty and specialized equipment, and trained equipment operators, will be provided, if necessary, through the PPSL Recovery Manager. O \ Rev. 4, S/El 7-7

80 Dh151h1E159 E5EE9EEGX EEEEAELEEEGG

 .,)

(_ A concept of in-depth preparedness is empicyed regarding the Susquehanna SES emergency ptogram. This concept is emphasized in the training prograi and in p repa redness drills and exercises. Personnel shall be trained to provide an in-depth response capability for required actions in an energency situation. This section includes the means to achieve and maintain preparedness and to ensure maintenance of an ef fective emergency program. 8.1 gygAHJ3AIlgEAl_fhjgfEjp!f33 8.1.1 IId1Bing The Supervisor-Nuclear Emergency Planning is responsible for Emergency Plan Training. Emergency training vill include:

1) All unescorted personnel entering or working within the Susquehanna SES Protected Area will receive as a minimum, the following. instruction.

o Orientation in the content of the Susquehanna SES Emergency Plati_ arid the Emergency Implementing

    -                      Procedures.

D' o Orientation in the implementation of the - Su sg ueh a rina SES Emergency Pla n, including the assignment of luties and responsibilities, location of emergency centers and assembly areas, and the location oi emergency equipment and supplies, where a pplicable. o orientation in individual employee responsibilities with rogard to the use of emergency facilities and equipment, t amiliarization w ith sta tion alarms and personnel

                           ,t e m pon se, and the use of applicable station communications systems.                                ,

o otientation in instructions and requirements associated with personnel accoun tability, evacuation, arid radiation exposure criteria. o O rie nta tioni its radiation protection with emphasis on the principles and use of protective clothing, equipment, a nd personne l dosi.me t ry.

2) Those individuals working on the Sus q ue hantia SES site, but outside the Ptotected Area, will to provided with instructions on warning signals, assembly areas and

 . s_

p/ evacuation routos. i l Hev. 4, 5/81 8-1 l

3) Personnel assigned to the PPSL emergency organization with specific Emerjency Plan duties and responsibilities shall receive specialized training for their respective assignments. Table 8.1 delineates lll which personnel will receive specialized training, the type of training and the required f requency of such training.

4) The Pennsylvania Emergency Management Agency develops, conducts, coordinates, and promotes a training program throughout the State and assists the counties in developing training policy for disaster operational readiness. The county and local Civil Defense Directors are responsible for planning and conducting disaster preparedness training of respective emergency response personnel. PPSL will work closely with PEMA and the county Civil Defense Directors in coo-dinating training prog rapis. In addition, orienta tion and training State and county agencies and personnel involved in Susquehanna SES emergency planning efforts will be made available by PP&L.

5) The civil defense organizations listed below will be invited, on at least an annual basis, to pa rticioate in a training program at the Susquehanna SES. The program will relate the importance of effective planninJ for emergency situations and interfaces between the PPSL emergency organizations and the off-site (i.e., State, g county, and Feder al) emergency organizations. The W program will also include a review of the Susquehanna SES Emergency Plan and appropriate Emergency Implementing Procedures, with particular emphasis given to the classification of emergencies; emergency action levels; reporting requirements; assessment, protective, dnd Corrective dCtion3; and Communica tions networks.

c Pennsylvania Emergency Management Agency o Luzerne County Civil Defense o Columbia County Emergency Management Agency o Ten Mile EPZ Municipal / Township Emergency Management Coordinators

6) At least annually, the Depar t ment of Environmen tal Resources / Bureau or Radiation Protection will be l invited tc participate in a training p r og ra m a t the Susquehanna SES. The program will, as does the program for the civil defense organizations, relate the

importance of ef fective planning f or emergency situations, the intertace between the PP6L emergency organizations and the offsite (i . e . , State, county, and Federal) em(rgency organizations. The program will include a review of the Susquehanna SES Emergency Plan and appropriate Emergency Impleme nting Procedures, with particular emphasis given to the classification of emergencies; emergency action levels; reporting llh Rev. 4, S/El 8-2

requirements; assessment, protective, and corrective ( ) actions; and communica tions networks. In addition, N/- specific review of dose calculations / projections, protective actions guides, a nd reportable information till also be conducted.

7) The State Police will, on at least an annual basis, be invited tc participate in a training program and dppropriate Emergency Implementing Procedures, with emphasis on the classification of emergencies, communications, and specific areas of responsibility.

8) PPSL will provide orientation and training to local off-site support organizations 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 l Susquehanna SES emergency organization. These local organizations and personnel who may provide on-site emergency assistance will be encouraged to become familiar with the Susquehanna SES (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 PPSL. Such training will be provided on at least an alinual basis to the appLopriate organizations and

  <w                personnel as follows:

U 1he local fire and rescue companies will be invited to participate in a training program tha t will include: o Interface with the Site Security Force during emergencies o Basic Health physics indoctrination and training c Susquehanna SES facility layout o On-site fire protection system equipment [permanont and portable) o Differences between on-site firefighting equipment and fire ccmpany supplied squipment o communications system o Review of appropriate sections of the Susquehartna Emergency Plan and Emergency Implementing Proceuures o The en-site emergency organiza ticn with specific

emphasis on the interface between the

, Susquehanna SES fire brigade and fire company perscnnel The local medical support organizations and peraonnel will be invited to pa rticipa te in a training program that will include as applicable: I o Interface with the Site Security Force during (~N emergencies

 \-)               o      basic health physics indoctrina ticn and training o      Susquehanna SES facility layout l

Bev. 4, 5/81 8-3

l o Communications systems o The on-site emergency organization with specific g emphasis on the interface between the W Susquehanna first aid and rescue team (s) , the local medical support personnel, and Radiation Management Corporation o Hadiological aspects of emergency medical treatment o Susquehanna SES Health Physics Procedures tor decontamination a Detwick Hospital radiation emergency procedurea 8.1.2 Drills and Exe,Icigeg Periodic drills and exercises will be conducte1 in oruer to test the state of emergency preparedness of all participa ting personnel, organizations, and agencies. Each drill or exercise will be conducted t o: (1) ensure that the participants are familiar with their respective duties and responsibilities, (2) verif y the adeluacy cf the Susquenaanna SES Emergency Plan and the methods used in the Emergency Implementing Procedures, (3) test communications networks and systems, (4) check the availability of emergency cupplies and equipment, (5) verif y the operability l of emergency equipment, and ( 6) verify the adeluacy of the interrelationship with off-site agency plans. The Supervisor-Nuclear E;oergency Pla nn ing is responsible for planning, scheduling, and coordinating all emerJency planning-related drills and exercises. All drills and h exercisen at e subject to the approval of the Superintendent of Plant. Drills and exercises will be conducted to aimulate actual umergency conditions as closely as possible and may be scheduled such that more than one drill or excercise can be conducted simultaneously. Drill scena rios will be prepared that involve participation of several emergency teams and all or specitic parts of the on-site and off-site emergency or Ja n iza tions includinj varying degrees of participation of State, county and Federal agencies and organizations and local off-site support personnel and organizations. The Supervisor-Nuclear Emergency Planning will notity the off-l site e.nergency response organizations and agencies at least thirty days in advance of the scheduled date of the drill or exercise. Recommendations for revisions to the Susquchanna SES Emergency Plan and the Emergency Implementing Procedures and/or the upgrading of emergency equipment and supplies, as a result of a drill or exercise, shall be f o rwa rded to the Supervisor-Nuclear Emergency Planning by observers or participdnts. The Supervisor-Nuclear Emergency Planning will submit such recommendations to the Superintendent of a Plant for review. Recommended changes that are approved by W the Superintendent of Plant shall be incorForated under the Rev. 4, 5/dl 8-4

direction of the Supervisor-Nuclear Emergency Planning. 7- s Records will be saintained on each najor drill, such as

  ;     )      described below:

v

1) ' ggdjgal_De1;ggggy_ Drill o At least one drill por calendar year shall be conducted. The drill will invcive the participation of some, if not all, of the local medical support personnel and organiza tions (e. g. ,

physician, as;bulance service, hospital, etc.) and will involve casos of contaminated / injured

• personnel and/or possiblo radiation ovoroxposure.

2) figs _fs2ESSDGI_DEill o At least one drill shall be conducted per calendar quarter. ,

o At least one drill in the calendar year shall involve the participation of a 1ccal fire department.

3) Eddigli2D_E89EddDEI_DElli o A major drill appropriate to a Site or General Emergency shall be conducted at least once per calendar yeat.

o The drill shall provide for the coo r.lin a tion with and participation by off .2ite emergency reponse personnel, organizations, and agencies including those of Stato and count y gover nmenta. o At 1 cast once overy five years a joint exerciso appropriate to a Site or General Emergency that involves Federal, State, and county emergency t osponso personnel, organiza *. ions, and agencies till be conducted. Tha scopa of the exercise will test the respect ive emergency plans to the extent which is reasonably achievable. The degree of public participation in this exercisa shall be determined by the appropriate State and local agencies.

4) C9EMuiGdli9DU_DElil o Telephone and Radio Communications Drills will be conducted with pa rticipa tion of PEMA, LCCD, C E tt A ,

and NHC on a monthly basis. o Annually, a f ull-scale drill will be conducted with the off-sito monitoring team radio communications ne twork. Thia may be held in Rev. 4, 5/El 8-5 j

conjunction with the annual Radiation Emergency Drill. o Annually, a full-scale test and verification of O the Public Notification System will be conducted.

5) Edd iglggica l_ggvilgngen ta l_no nit ori ng_pIllis An annual drill requiring the collection and analysis of environmental sa mple media (e.g., wa ter, vegetation, soil and air) will be conducted. Provisions for record-keeping and comm unica tions will be monitored.

6) Egalth_Ehysics_ppills Semi-annual drills involving response to and analysis of simulated elevated airborne and legend samples and i direct radiation mea surements will ne conducted.

Ar.nually, a drill including the usage of the post-dCCident sampling system will be conducted. Simulated elevated samples will be used during the conduct of this drill. Following the conduct of drills, critiques will be hel.1 to clearly identily deficiencies and action plans for resolution of same. All agencien, county, State and Federal, who participated in said drills will be invited to participate in the critiques. Procedures will ne g established to assure the timely inplementation of corrective actions. d.1.3 Synery ingI- y gelegg_ E m gIgggef _ P la gg i ng,JUE EEL The responsibilities of the Supervisor-Ncolear Emergency Planning shall include, but not necessarily be limited to:

1) E n s u r. i n g the coordination ot the Susquehanna SES Emergency Plan with:

o State plans o county plans a Susquehanna SES Physica l Secu rity Plan a Sasquehanna SES FSAR and Fire Protection iteview Report

2) Ensuring that the in fo r ma tion , data, and proceduros detailed in the Emergency Implementing Procedures are consistent with the Susquehanna SdS Emergency Plan J) En2uring that the Emergency Implementing P:. >ced ur es are coordinated and interface properly with other procedures, including Administrative P roced u res ,

Security Procedute.5, liealt h Physics Procedure.5, Plant Procedures and Training Procedures h Rev. 4, 5/81 6-6

4) Assisting the Plant Training Group in coordinating s and/or providing emergency plannirig-related specialty

( ) training

    ~/

5) Coordinating emergency planning-related drills and exercises

6) Coordinating the review and updating of the Susquehanna Emergency Plan and Emergency Implementing Procedures

7) Ensuring the maintenance and inventory of emergency equipment and supplies

8) Keeping abecast or changes in Federal regula tions and guidanco that may atfect emergency planning

9) Ensure that SSES support groups provide for the training of individuals responsible fcr the planning effort.

B2 BELIR3 hED 92DhTIR9 Heviewing and updating the Susquahanna SES Emergency Plan and Erergency Im[:lementing Procedures are primarily the responsibility of the SNEP. Annual reviews of the Plan will be conducted by the Plant operations Review Committee (POPC) dnd the Corporate Susguehanna Review Commit tee (S RC) . The ("N PORC and the SRC membership compositions are specified in (_) the Susquehanna SES Technical Specificaticns. The SRC is responsible to ensure independent and documented reviews of the Susquehanna SES emergency preparedness proJram. This shall include an annual review and audit of emergency drills, exercises, procedures and capabilities. The SNEP presents recommendations to the PORC for changing, updating and improving the Plan, which may result from exercises, drills, changes in operating precedurea or conditions, or chsnyes in regulatory or other requirements. The P0HC reviews and submits appropriate changes for approval by the Plant Superintendent. Holders of official copies of the Su sq ueh a r,na SES Emergency Plan shall be apprised of revisions and ahall maintain their copies current. Organizations or groups having assigned responsibilities under the Plan, but who are not holders of otticial copies, shall be apprised of applicable changes in a timely manner hy the SNEP. 29TE Revised pages shall be dated and marked to show where l changes have been made. ) O- ^t te et 4 ="4ttr the s"8e 111 eree t- " et t== revert including a listing of char.ges made since the previous Rev. 4, 5/81 6-7 l l

r report, and a summary of emergency exercises and drills conducted during that period. The SNEP shall 'nsAre tnat lettera of agreement from all O participating organizations are updated a nd renewed at least every two years. a.3 5htNTEEAE9E hED 181EET981 9E EREB9 ERG 1 E291EB122 hED spgELigs The SNEP is responsible for planning and scheduling the guarterly inventory and inspection of designated emergency equipment and supplies. Tolephone numbers listed in the Emergency Plan IP's will be reviewed and updated qua r terl y, lie will ensure that personnel are assigned to per for m these activities. Designated emergency equipment and supplies and their storage locations will be listed in emergency Implementing Procedures. Such equipment and supplies will be maintained in accordance with a pproved Susquehanna SES procedures. Equipnent, supplies, and parts having limited Thelf-lives will be checked and replaced as necessary. Any deficiencies found durinj the inventory and inspection will be either cleared immediately or documented for corrective action. A report of each inventory and inspection, including documented deficiencies, will be prepared and submitted to the SNEP. The SNEP will ensure that identified deficiencies are corrected in a timely manner. In addition to any other requirements relating to communications, the SNEP shall develop with each aloney having dedicated communicationa linkc provisiona for testing of those links on a monthly basis. 6.4 E2BLIG EDUGhTIGE ABD IBE9B5hTIGE

         'nder the direction of the Supervisor, Nuclear Energency Planning, tho following methods will t>e utilized to ensure th at emergency planning edaca tion and information is provided and transmitted to resilents and transients in the Emergency Planning Zone:

o A full-page ad in the local newspapers, s'immarizing the actions to 1e taken by resilents, will ne published on an annuai Lasis, o Printed instructions and evacuation maps will be distributed to EPZ reuidents on at letst an annual basis. These instructions sill inclu le educati1nal information on radiation and instructicns tu contact the SNEP for additional information, o Printed instructions will be included in the local telephone directory. g Rev. 4, S/81 d-8

o Printed instructions and evacuation maps vill be r3 distributed to notels, hotels, and recreation areas on

 !s_)              at least an annual basis.

Under the direction of the Special Assistant to the President-Susquehanna: In the event of an actual emergency, initial public statosents by PPSL will be via pre-drafted news releases contained in tS9 public information implementing procedures. These releases will provide initial information as to the nature of the emergency and the status of the plant. Subsequent news releases will be coordinated with ' appropriato authorities. Public Information Ptocedures provide the specific details and responsibilities for who, how, and when information is teleashd. These procedurea alao establaih a mechaniam whereby rumors can be controlled, that is, phone contact with knowledgeable public information people. The actual phone number will have wide-spread distribution. Ccsduct r rograms annually to acquaint the news media with the emergency plan, inf orma tion. concerning radia tion, and points :- contact for telease of public information in the event of an emergency.

 /~)/        Educational training programa on emergency planning will he made available to the general public and groups through the PPSL Nuclear Speakers Bureau.

k [} s-i Rev. 4, S/81 8-9  ;

[x

         !n) v                                                       (v)                                                      $

u Pcg2 1 TABLE 8.1 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL Personnel Category Involved Personnel Initial Training and Periodic Retraining

1. Emergency Directors Superintendent of Plant; Asst. Initial training will consist of instruction on the Supt. of Plant; Supervisor of scope and functioning of the Emergency Plan and l Operations; Shift Supervisors Implementing Procedures.

Retraining will be on an annual basis and vill include a review of the basic plan with any changes since the last training period.

2. Personnel responsible for Emergency Director; Emergency Initial training will consist of instruction on the accident assessment and/or Coordinators; and alternates Susquehanna SES Emergency Plan and Implementing accident management Procedures germane to their particular assessment /

management function. Retraining vill he on an annual basis and will include a review of the basic plan with any changes since the last training period.

3. Radiation Monitoring Teams Health Physics Supervision; Licensed personnel and E1alth Physics Monitors receive Licensed Operations Personnel; substantial training in radiation monitoring.

Non-Licensed Operators; Chemistry Analysts; Health Initia_ training for all personnel performing radia-Physics Monitors tion monitoring duties will consist of instruction in the on-site and off-site radiation monitoring Implementing Procedures. In addition, the Health Physics procedures utilt. zed for normal operating conditions will be reviewed. Retraining will be on an annuS1 hasis with hand-on instrumentation usage with emphasis on interpretation of results. Rev. 4. 5/81

              ?

i (

                                                                          ~

Pr g? 2 TABLE 8.1 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSOVNEL Personnel Category Involved Personnel Initial Training and Periodic Retraining

4. Fire Brigade Assistant Unit Supe rviso r, Training and retraining are outlined in the Susque-Non-Licensed Operators; Secu- hanna SES FSER.

rity Of ficers; Maintenance Personnel

5. Damage Control Teams Non-Licensed Operators; Repair and Damage Control are considered a normal part Maintenance Supervision; of the job functions of the listed personnel.

Maintenance Personnel Initial training for emergency planning purposes will include responsibilities during an emergency radiological considerations, availability of damage control equipment use of systems, and interfaces with other emergency teams. Retraining will consist of a review of the above topics and will be conducted annually.

6. First Aid and Rescue Teams Non-Licensed Operators; llealth Each member of the First Aid and Rescue Team will Physics Monitors receive the Standard Red Cross Multimedia First Aid Course. In addition, each team member will also be instructed on the availability of on-site medical treatment supplies and equipment; communication system, radiological hazards; and interfaces and responsibilities with local medical support personnel (e.g. ambulance and hospital personnel).

7. Fire Support Personnel Local Fire Companies Training and retraining requirements are outlined in the Susquehanna SES Emergency Plan.

'l. Rev. 4, 5/81

rm Pega 3 TABLE 8.1 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL Personnel Category Involved Personnel Initial Training and Periodic Retraining

8. Medical Support Personnel Berwick Hospital Staf f; Radiation Management Corporation has extensive experi-Ambulance Companies; Radiatlon ence in the treatment of contaminated / injured personnel.

Management Corporation Training shall include individual attendance at appro-priate seminars and training courses. Initial training of the Berwick Hospital staff and Ambulance Corps shall be conducted by RMC and the Nuclear Emergency Planning Group. This instruction shall include treatment and handling of contaminated / injured personnel, communication systems, radiological hazards and interfaces with Susquehanna Security and Operations Procedures. Retraining shall be conducted on an annual basis.

9. Corporate Support Personnel Corporate Management Personnel; Initial training shall consist of a review of the including Nuclear Fuels. - Emergency Plan and appropriate Implementing Procedures Nuclear Plant Engineering with specific emphasis on PP&L interface with government and Nuclear Support agencies and methods of communication.

Retraining shall be conducted on an annual basis.

10. Security Personnel Supervisor of Security; Security Training and retraining requirements are outlined in Training Supervisor; Shif t the Susquehanna SES Training and Qualification Plan.

Supervisor-Security; Asst. Shift Supervisor-Security; Security Officers / Controllers

11. Public Information Special Office of the President; Initial training vill consist of instruction of scope, Personnel Information Services Personnel responsibilities and functioning of the Emergency Plan and Public Information Procedures.

Rev. 4, 5/81

              .,-        . , , - . . + . -                                    -

7__... , , -

                                                                                                                                       ,,m    -
                                                                                                                                                  , . - _ _      _m . .-.-- -

                                             %D   BEGI9BA119B
 ~-n

[') The Susquehanna SES and PP&L Off-Situ Support omorgency organizations shall continue to provido a ppropria to emergency response functions until such timo aa th6 omorgency has been terminatoil or the PPr,L Corporate Management Cottitten (C MC) has approved the implumontation of a long-range rest oration organization. The Vico l Fronident-Nuclear operations shall requent that the CMC establiah a rostoration organization when the following l guidolinen have boon met: o In- p la n t radiation levola are utable or are decreasing with time. o 11oleases of radioactive matorial to the environment aro l under contrcl or have ceased. o Any fire, flooding or similar omorgency conditions are under contrcl or have coaaed. Although planning for todtoration will vary according to the l nature of the specific omergoney situation, a long-term teatoration organization that la genoLal in natuto has been defincd. The testoration organization uhall be a pro ject-type cryanization with theit major activities conducted from the near-cito rol. This organiza tion in depicted in Figuro l p 9.1 and majot responsibilitica are defined below. O o BCU19fd119B_Ud!!dSSI - A dea tgnated officer or nonior l manager LIom PP&L who has tho toquiuito authority, ma na ge me n t ability, and technica'- knowledge to aanage the Suuguchanna SES rostoration operations. l o IldD1 0Eeld11989_5duducE - A designatad manager from EPfL with the requisito authority, plant operating experience, and qualit ica tions to con t rol plant operations includinJ accurity. o 10GhuiEdl_E9fE9El_ddudiffg - A desig nated mariagor f roin PP&L with the requinito authority, nuclea r experience, and technical exportian to manage a technical group in support of [ lant opora tions and reatoca tion. l o tendueE_9f_Edd1919919dl_ centi 91_ dud _L!]te_udaduemeni - A doctynated managur who han the requiaite authority, nuclear experience and technical expertino to manage the radioactive wanto and radiological control aspects of the rosto. .s c i on opera t ions. l 0 DCD19u_dDi_G9BD1EM911Hu_ l S MEE9Il_5dudilSI - A designated manager who coordina tos the activities of PPGL, NSSS s supplier and construction torces on proposed plant modifications or other doaign and construction support required for the rostoration. l li e v.  % 5/ 81 9-1

                                                                         ~- -         -     -

0 AdI14911_SSIE951 fSEGli2D - Advisory support should consist of senior representatives of the NSSS supplier l and the NBC, and special consultants as necessary who would meet at least daily with the Restoration Manager lll and his staff. O 59h2dSliHSZPlanning_3andger - A designated mana Jer, with a staft from PP&L, who has the requiaite authorit y to coordinate and expedite plans and schedules for t he l Restoraticn Manager. O AdaiDAMlIdli9D_ dud _19did119d_3dB19fE - A designated officer or senior manager from PP&L who is responsible for providing administrative, logistic, communications and personnel support for the restoration operation. l O EMhl19_ LEA 9EHdl19D_ddudSSE - A desig na ted manager, with a staft from PPSL, who has the responsibilities as described in Section 5.3.2 of this Plan. l During restoration operations, the radiatica exposure limits of 10 CFR 20 shall apply. Compliance with those limits l shall be tne responsibility of the Restoration operations Manager via the applicable llealth Physics crganization at i the time of restoration. At the time of dcclaring that an emergency has entored the l restoration phase, the Restoration Manager shall be responsible tor t rovidin j notification to all applicable agencies (e . g . , Federal, State, and county agencies, etc.) l that the emergency has shitted to a restoration phase. Restoration actions that plan tor, or nay tesult in, radioactive release will be evaluated by the Rostoration Manager and his 9taff as far in advance of the event as is [ossible. Such ever.ta and data pertaining to the release will be reported to the appropria te of f-site emergency response organizations and agencica. Termination tros an emergency cond ition will be through joint evaluation by the organizatioris involved. In the case of a severe emergency involving off-site ccusequences, this l would include Ros toration Managet , DER /BRP, P EM A, LCCD, C EM A dnd NBC. The Offuite Support Organization described in Section 5.3 may function as the destora tion organizat icn until such time ds the CMC approves the long-term restoratica oper1tions. All Ccntrol Room activities will be conducte1 by the normal l operating shift. Should events occur during the restoration that are deemed an emergency, all emergency centers and staffs sill be reactivated as apt-opriate. O Rev. 4, 5/01 9-2 m

O O O PP & L CORPORATE HEADQUARTERS d 1 I I PUBLIC INFORMATION RESTORATION ADMIN / LOG 7S11CS MANAGER MANAGER MANAGER ADVISORY SCHEDULING SUPPORT PLANNING MANAGER J d TECHNICAL PLANT M AN AGER OF DESIGN & SUPPORT OPERATIONS RADCON/ WASTE CONSTRUC110N MANAGER MANAGER M ANAGEM ENT SUPPORT M ANAGER m w c  ? a - < c = 8 - E E f

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I ltg January 15, 1931 J l4r. Harley L. Collins Vice President, System Power & Engineering Susquehanna Steam Electric Station Pennsylvania Power & Light Company Two North flinth Street Allentown, PA 18102

SUBJECT:

Emergency liedical Assistance Program

Dear fir. Collins:

This confirms an agreement between Radiation lianagement Corporation (Rf1C) and Pennsylvania Power S Light Company, wherein R!iC agrees to furnish certain services to nuclear generating stations operated by Pennsylvania Power & Light Company. These services comprise a pro-gram that is identified by Ri4C as an Emergency iledical Assistance Program (EliAP). With regard to Susquehanna Steam Electric Station, n the El4AP contains the following provisions: 'O

1. Semi-annual review of plant and hospital procedures, equipment and supplies; one of these audits will be in conjunction with (6.) below;

2. Twenty-four-hour-per-day availability of expert consultation on mnagement of radiation accidents;

3. Availability of Bioassay Laborator~v for evaluation of radiation flh ll  % accidents; gg g 4. Twenty-four-hour-per-day access to a Radiation Emergency tiedical Team consisting of a physician, certified health physicist, and pnnnnpg nn technicians with portable instrumentation to location of accident UUIWUIu Ull victim;

5. Availability and access to a medical center equipped for the definitive evaluation and treatment of radiation injuries; UNIVER$17Y CITY scauct cruren 6. Annual training for the plant, ambulance and hospital personnel who may be directly or indirectly involved in the execution of the radiation medical emergency program; 3504 MARKET STREET PHILADELPHIA. PA 69 04 7, preparatjon of an " accident" Scenario for use as a training

, d' ' 6 '* aid in a radiation medical emergency drill; i)- continued. . . . .

b Susquehanna Steam Electric Station Page Two

8. Coordination of a radiation medical emergency drill based on the scenario; umpired, video-taped and critiqued by Rl4C;

9. Submission of two Drill Evaluation Reports; one relating to the observations made at the station, and another relating to observations made at the hospital; and ...

10. Participation in an annual one-day seminar in Philadelphia on the management of radiation accidents for physicians.

Each plant site may seni one person, and each utility conpany may send one person. Accident Resoonse Consultation and laboratory services by RllC personnel are at no charge, except incremental costs associated with consulta-tive activities, such as travel, lodging and other related A)

 's_   expenses.

1011 I4AllAGE!!EllT CORPORATI0ll

                                                 )    ~         MP~

l e . Linnemann,ii.D. RES EllT 1 REL:tm

     'cc: Charles Wike i

O L l

                               -                            .g.

  .f TWO Notf H NINYM 5fatti,AlttNf0WN. PA. 1410i   P M O N t r (213) 5 21 3131.
   'v/           ,-
         . January 7, 1980 Pond Hill-Lily Lake Fire Company Ambulance Service R.D. ill Wapwallopen, PA-       18660' Attn: Mr. Leonard Pyzia, President Gentlemen:

R *he interest of verifying the agreement that exists between our

         .orgcnizations, please confirm the conditions in our letter of May 23, 1977. Attached is a copy of that agreement for your convenience. You may indicate your concurrence by signing the statement below and returning the original copy to me.       (You may keep the second copy for your files.)

O If you have questions concerning the conditions of our original agreement, please contact Peter Collopy, Staff Health Physicist, at 215-821-5636 as soon as possible. Thank you for your cooperation in this matter. b / B. D. Keny Assistant Vice President-Nuclear Operations Attachment

         'PC:lf 4761 l

I e N (name), / LW he-[ (title), an l authorized representative of the Pond Hill-Lily Lake Fire Company Ambulance

l. Service on this // day of AM , (_ , 1980 concur with the provisions- of our original agreement.

1 PENN$YLVANIA POWit & tlGHT COMPANY

PPaL []; SUSQUEHANNA STEAM ELECTRIC STATION P.O. BOX 467 BERWICK, PA 18603 Hobbie Volunteer Fire Co. . R.D.#2 Wapwallopen, PA 18660 Attn: Mr. Dennis Moyer

Dear Mr. Mayor:

This letter will serve as an agreement between the Hobbie Volunteer Fire Co:pany and Pennsylvania Power and Light Co=pany concerning the transportation of persennel from the Susquehanna Steas Electric Station. This agreement is =ade pursuant to the Federal Require:ents cited in Attach =ent 1. Hobbie Volunteer Fire Company agrees to transport patients from the Susquehanna Steam Electric Station, who may have injuries complicated with radioactive () N/ contamination or who cay have been involved in a radiation incident, to the Berwick Eespital. Pennsylvania Power and Light Company agrees to pay all reasonable fees and charges associated with such services. Pennsylvania Pcwer and Light Company also agrees to provide appropriate training for these ambulance personnel as designated by an authorized representative of the Hobbie Volunteer Fire Company. This agree ant will remain in effect indefinitely unless terminated by either party giving thirty (30) days advance written notice of termination to the other party. Please signify acceptance of the provisions of this letter by executing the agreement and returning the original copy to me. (You =ay keep the second copy for your files). Very truly yours,

               /
       . (bluv B. D. Kenyod ]s,I Vice President-Nuclear Operations
                                                        -7             _ . _

I. (name) (title), an authorized representative of Hobbie Volunteer Fire Company, on the day of (~} , 1981, agree to the provisions contained herein.

%-)                                                                  '

PENNSYLVANIA POwet & LIGNT COMPANY

w) TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE: (215) 821-5151 Nescopeck Ambulance Assn. Warren Street Nescopeck, PA. 18635 ATTN: Mr. Henry Woodeshick

Dear Mr. Woodeshick:

This letter will serve as an agreement between the Nescopeck Ambulance Assn. and Pennsylvania Power and Light Company concerning the transportation of personnel

     -from the Susquehanna Steam Electric Station. This agreement is made pursuant to the Federal requirements cited in Attachment 1.

Nescopeck Ambulance Assn. agrees to transport patients from the Susquehanna Steam ("f Electric Station, who may have injuries complicated with radioactive contamination or who may have been involved in a radiation incident, to the Berwick Hospital. Pennsylvania Power and Light Company agrees to pay all reasonable fees and charges associated wich such services. Pennsylvania Power and Light Company also agrees to provide appropriate training for those ambulance personnel as designated by an authorized representative of the Nescopeck Ambulance Assn. This agreement will remain in effect indefinitely unless terminated by either party giving thirty (30) days advance written notice of termination to the other party. Please signify acceptance of the provisions of this letter by executing the agreement and returning the original copy to me. (You may keep the second copy for your_ files). Very truly yours, I

         . d'    GW B. D. Kenyo Vice Pre'sident-Huclear Operations
               /

u n/ e.e (name) M s- e" >r (title), an aathor ked/ representative of Nescopeck Ambulance Assn. , on the /Fday of l , -0f wmi/ , 1981 agree to the provisions contained herein.

                         /

1O P E N N $ Y L V A NI A POWER a LIGH T COM P ANY

5 f3 's_)-' Nescopeck Ambulance Assn. Mr._ Henry Woodeshick-ATTACHMENT 1

              . United States Nuclear Regulatory Commission Rules and Regulations, Title 10, Chapter 1, Code of Federal Regulations, Part 50 (10CFR50),
              . Appendix E, requires thatlthe applicant for a license to operate a
              -nuclear power-facility submit an Emergency Plan which includes a
               ' description of specific elements to an extent sufficient to demonstrate that the plans provide reasonable assurance that appropriate measures can and will be taken in the event of an emergency.

10CFR50, Appendix E Section IV specifically requires arrangements for transportation of injured or contaminated-individuals to treatment facilities outside the site boundary. Provisions are also required for the training of other (of f-site) persons whose assistance may be needed, ' and for testing of the plans by periodic drills. United States Nuclear Regulatory Commission Regulatory Guide 1.101,

                " Emergency Planning.for Nuclear Power Plants" specifies that the license applicant's Emergency Plan should describe the coordination of the

(Nl arrangements between the licensee.and off-site emergency supporting N-s organizations; and should include copies of agreement letters with these organizations and copies or summaries of interfacing emergency plans. l. t i u

w. _ _ - -

                                                                   ~
                                               ~

IN STITUTE OF NUCLE AR POWER OPER ATIONS

<-   1820 Water Place                                  .

Acanta GA 30339 August 27, 1980 (404) 953 3600

Dear ,

                                                     ~

one of the roles of INPO is to ashis't the affected utility in quickly applying the resourcespof,:the nuclear industry to meet the needs of the emergency..'~ INPO , when notified2 of an emergency situation at a nuclear plant, will provide emergency response as requested. Such situations are equivalent to the " alert", " site," and " general" emergency conditions as defined by NRC. Utility emergency response planning should include notification of INPO via the

,_        dedicated Emergency Call Number for these situations..

I t# INPO will be able to provide the following emergency support l functions:

a. Assistancetotheaffectedut'il}tyinlocatingsources of emergency manpower and equipment.

b. Analysis of the operational aspects of the incident,

c. Dissemination to member utilities of information '

concerning the incident that is applicable to their operations.

d. Organization of industry experts who could advise the utility on technical matters.

To support these functions, INPO shall maintain the following emergency support capabilities:

a. Dedicated Emergency Call Number capable of reaching designated INPO staff and activating INPO support f unctio'ns twenty-four hours per day, seven days per week.

I~) b. Designated INPO representative (s) who can be quickly dispatched to the utility emergency response organiza- , tion to coordinate INPO support activities and infor-mation flow.

c. Twenty-four hour-a-day operation of an Emergency Response Center at INPO.

(~ /') INPO Emergency Response Capability , Page 2 . The_ dedicated Emergency Call Number is (404) 953-0904. An INPO Duty Person will respond to th'e call and the Emergency Response Center at INPO will be activated as necessary. When you call ~the emergency number after hours, an automatic dialing system will answer and give you the message on

         -Attachment      A'.
        ' If requested by the utility, or.when deemed appropriate, one or more suitably qualified members 'of INPO technical staf f will report to the Recover #fanIger, and will assist his staff in coordinating INPO's response l..to the emergency as follows:

a. Staffing a single positi,on responsible to the appropri-ate utility manager as liaison for all INPO matters,

b. Working with the INPO Duty Person in htlantd to coordinate all requests for assistance, INPO Lesponso

(~)

 '-                   and related communications.

c. Assisting the utility as requested in initiating ' .

and updating entries into industry information . systems (such as NOTEFAD) concerning the accident

• status and related information of value to other utilities.

d. Ensuring that all information concerning the emergency which is released by the INPO liaison is properly and formally cleared through appropriate utility channels.

. nn INPO representative shall normally be capable of being dispatched on approximately four hour. notice. Upon request in an emergency, INPO will provide assistance to the affected utility in locating and arranging additional emergency manpower, equipment, and the services of various technical _ experts from industry sources. i Analysis of operational factors relating to plant incidents ' will be initiated as directed in an' emergency by the President of INPO. On-site activities, when undertaken, will be coor-dinated with the On-site INPO Representative. ( })

        .                                                                                                      l l

INPO Emergency Response Capability ' (~}

  \_/

Page Three In Srder to assist the utility as indicated above, INPO requires the following action and/or information from the utility:

a. Copy of the utility's Emergency Plan

b. Add INPO to your emergency notification list for actual emergencies and exercises at the " Alert" and above action levels

c. Prior notification of emergency drills and exercises in order that INPO may send observe'rs to the drill or exercise , f .:y3;l, -

                                       ..           L.

If you have any q.-uestions or'2' comments concerning INPO's role in an emergency, please let me know. Sincer.ely,

< ()                                                                                                .

PWL:sf cc: Routine Contaci i l l

                   ,                 -          -        . , .     , , ,              n , - - ,
                                                                                                . = .- ,   ~

Q U CODAPHONE MESSAGE 1-2 INPO, EMERGENCY RESPONSE CENTER -

?;?.p;'-

THE DUTY OFFICER IS NOT PR'ESENT AT THIS TIME;  ;

_ HOWEVER, THE AUTOMATIC DIALING S'f STEM WILL PAGE

{ HIM AND YOUR CALL WILL BE RETURNED AS SOONAS POSSIBLE. O AT THE SOUND OF THE TONE, PLEASE LEAVE YOUR NAME

• TELEPHONE NUMBER, COMPANY AND PLANT NAME, THE ,

i l I NATURE OF THE EMERGENCY AND HC74 INPO CAN HELP YOU l j AT THIS TIME.  ! THANK YOU. i I I. G I t i O - ATTACHMENT A

+ J-ENCLOSURE'10

RADIOLOGICAL ENVIRONMENTAL MONITORING INSTRUMENTATION i

f Table 1 - Offsite Fixed Monitors (attached) Table;2 - Offsite Monitoring Team Instrumentation (attached) In-Plant Fixed Monitoring Equipment - see Table 11.2.of the Susquehanna~SES FSAR , Health Physics Survey Instruments - see PP&L response to NRC FSAR Review Question i EO 1 4 J ( i T i l P O Rev.'4, 5/81- _ _ _ _ _ _ . . _ _ . . - . 7- , .. _ _.. _ ..__.,, _ _ _ _. _ _ r . . . _ _ _ _ _ , . _ . , _ _ . , _ , _ _ . , _ . . , _ . .

O O O TABLE 1 Operational Radiological Environmental Monitoring Program

            . Exposure Pathway             Number of Sam'les p                         . Sampling and            Type and Frequency and/or Sample                 and Locations                     _ Collection Frequency           and Analysis Airborne
            'Redioiodine and     1152 (0.43 mi SW - Golomb House)          Continual sampler operation .Radioiodine Canister:

Particulates 9B1 (1.28 mi S - Transmission Line) with sample collection -analyze weekly for 1131 SS4 (0.76 mi E - W of Bio Consult) . weekly 12El (4.68 mi WSW - Berwick Hospital) 7G1 (13.51 mi SE - PP&L Hazleton Particulate. Sampler: Chem. Lab) Analyze for gross beta radioactivity > 24

                                                                                                         -hours following filter change. Perform ganuna isotopic analysis on composite sample (by -

location) at least once. per 92 days.

           . Direct Radiation    IS2 Security Fence - 0.24 mi N            Quarterly                    Camma Dose. At least ID2 Mocanaqua Substation -                                               once per 92 days.

3.97 mi N 2S3 Security Fence - 0.22 mi NNE 2B3 12: erne Outerwear - 1.31 mi NNE - 2F1 St. Adalberts Cemetery - 5.88 mi NNE 3S4 Security Fence .0.30 mi NE 3D1 Pond Hill - 3.38 mi NE - 3F1 Valania Resident (Nanticoke) - 9.10 mi NE 3H1 Wilkes-Barre-Horton St. . Substation - 15.80 mi NE 4S3 Security Fence - 0.23 mi ENE 4El Pole (#) 46422 N35-197 - 4.75 mi ENE 4C1 Mountain Top-Industrial Park - 13.91 mi ENE SS7 Security Fence - 0.22 mi E

                               -SE2 Bloss Farm - 4.51 mi E 6S4 Security Fence - 0.18 mi ESE Rev. 4, 5/81

              /m                                                    (-                                           ,
                 ,                                                     j                                    ~

TABLE 1 (Page 2) Exposure Pathway Number of Samples Sampling and Type and Frequency and/or Sample and Locations Collection Frequency and Analysis 6A3 State Police - 0.55 mi ESE 6El St. James Church 4.74 mi ESE 7S3 Security Fence - 0.20 mi SE 7El Harwood Transmission Line ~ Pole #2 - 4.22 mi SE 7Cl Hazleton Chem. Lab - 13.51 mi SE 8S2 Security Fence - 0.22 mi SSE 8BI Cale Residence - 1.40 mi SSE

                     'D2  Mowry Residence - 3.95 mi SSE 9S1 Security Fence - 0.26 mi S 9D1 Smith Farm - 3.64 mi S 10S1 Security Fence - 0.43 mi SSW 10D2 Ross Ryman Residence -

3.00 mi SSW 11S3 Security Fence - 0.34 mi SW llEl Jacobsen - 4.74 mi SW 12S3 Security Fence - 0.36 mi WSW 12El Berwick Hospital - 4.68 mi WSW 12G1 Bloomsburg - 14.57 mi WSW 13S2 Security Fence - 0.38 mi W 13E4 Kessler Farm - 4.10 mi W 14S2 Security Fence - 0.43 mi WNW 14El Knouse Farm - 4.11 mi WNW 15S3 Security Fence - 0.34 mi NW 15F1 Zawatski Farm - 5.37 mi NW 16S1 Security Fence - 0.29 mi NNW 16F1 Hidlay Residence (Huntington Mills) -7.81 mi NNW Waterborne Surface SS8 intake area

• Grab sample over Gamma isotopic analysis 6S5 nutfall area
• month period monthly. Composite tritium analysis at least once per 92 days.

Drinking 12H2 Danville Water Co. Monthly composite Cross beta and gamma (App. 30 miles downstream) isotopic analyses monthly Composite for tritium analysis quarterly. Rev. 4, 5/81

TABLE I (Page 3) Exposure Pathway Number of Samples Sampling and Type and' Frequency-

       'ind/or Sample                     .and Locations                  Collection Frequency               'and Analysis Stdiment from          7B1 Bell Bend - 1.2 mi SE                Semiannually                    Camma isotopic analysis Shoreline                                                                                      semiannually.

Ingestion Milk 12B2 Shultz Farm - 1.69 mi WSW Semi monthly when animals Gamma isotopic and 1131 13E3 Dent Farm - 4.9 mi W are on pasture, monthly analysis of each sample SE1 Bloss Farm - 4.4 mi E at other times 10G1 Davis Farm - 14 mi SSW***

     . Fish and              Outfall area                              Sample in season                Gamma isotopic on edible
         -Invertebrates      2G1 Falls, Pa. (Approx.                   One sample of each of the         portions.

30 mi NNE)*** following species **:

1. Walleye

2. Catfish Food Products 12B1 Kisner Farm - 1.15 WSW At time of harvest- Gamma isotopic on edible vegetable portions.

11DI Zehner Farm - 4.3 mi SW vegetable 7B2 Heller's Farm - 1.5 mi SE Fruit 2H1 Yalick's Produce - 21 mi NNE*** vegetable

         *remporary locations until compositor is installed in intake and discharge lines, then frequency changes to composite
  ,-      sample collected over one-month period, and location changes to 6S6 intake _line, 6S7 discharge line.
        **other species in the same family may be sampled instead of the stated species if deemed desirable by the biological consultants.
     *** Control sample location.

Rev. 4, 5/81

_ _ . . - - ~ _ _ . _ _ _ _ _ _ . . . _ . . - . _ . _ . _ _ . . . . _ _ _ _ _ _ _ . . _ _ . . _ . . _ _ . . _ . _ _ . ._ _ ... _ _ . _ i-4 s a 4- ) . 1 l- } TABLE 2 I 0FF-SITE MONITORING TEAM INSTRUMENTATION Available Storage  ; i. Instrument: Number ~ Location 1-

1. Ionization Survey Meter 6 EOF l 2. Low Volume Air' Sampler 6 EOF i.

j 3. Noble Gas Monitor 6 EOF 1 4 i A. Iodine Monitor 6 EOF 1 f 4 4 1 i-1 i ' \ 4 l 2 g-

1. l l

4 l l, LO 4 1 Rev. 4, 5/81 i I.,.._.,,_. . . . . . . .... ....__ . m ,. .-.._,,,,,_ ,_,. _ ,_ _,.. ,,... _ ,.- -,____.,.___ _ _._ _ ,_ _ ,. . .,________________.___I

i l APPENDIX I EMERGENCY FACILITIES - CONCEPTUAL DESIGN DESCRIPTIONS l l l l l l i  : t l l 1 i l l t t Rev. 4. 5/81 , i l, I t

                                                                                ~

r y1 )- i >,

~ l       i V                                            Table of Contents Section            Title                                          Page 1.0 SCOPE AND OBJECTIVE                                          l-1 2.0 TECHNICAL SUPPORT CENTER                                      2-1 2.1 FUNCTION                                                      2-1
,               2.1.1      During Emergency                                       2-1 2.1.1.1    Notification of Unusual Event                          2-1 2.1.1.2    Alert, Site Emergency, General Emergency               2-1 2.1.2      During Non-Emergency                                   2-1 2.1.3       Limiting Conditions                                   2-2 2.2 LOCATION                                                      2-2 2.3 STAFFING                                                      2-2 2.3.1       During Emergency                                      2-2 2.3.1.1    Notification of U:asual Event                          2-2 2.3.1.2    Alert, Site Emergency, General Emergency               2-2 2.3.1.3   Task Functions of Personnel 2-3 2.3.2      During Non-Emergency                                  2-3
      ,q        2.4 ARCllITECTURE                                                 2-3 V          2.4.1      Spacial Layout Descrf;.cion                           2-3 2.4.2      Lighting                                              2-4 2.4.3      Finishes-                                             2-4 2.4.4      Fire Detection                                        2-5 2.4.5       Fire Protection                                       2-5 2.5 STRUCTURAL DESIGN CRITERIA                                    2-5 2.6 HABITABILITY                                                 2-5 2.6.1        Post-Accident Radiation Doses                        2-5 2.6.1.1     Allowable                                             2-5 2.6.1.2    Postulated                                            2                   2.6.1.3    Radiation Monitoring                                  2-6 2.6.2      IIVAC                                                 2-6 2.6.3      Shielding                                             2-6 I                 2.6.4      Occupant Accommodations                               2-6 i

2.7 COMMUNICATION LINKS 2-7 2.7.1 Telephone 2-7 2.7.2 Ilotlines 2-7 2.7.3 Radio 2-8 2.7.4 Pager 2-8 2.7.5 Public Address System 2-8 2.7.6 - Facsimile 2-8 2.8 POWER SUPPLY 2-8 2.8.1 Station Service 2-8 2.8.2 Diesel Generator 2-9 Rev. 4, 5/81

            . . ~ . _      - . . _ , -

    /     k r          )
      ~

2.8.3 TUninterruptable Power Supply 2-9 , 2.9 INSTRUMENTATION 2-9 2.10 TSC DATA PRESENTATION 2-10 2.10.1 Equipment 2-10 2.10.2 Display 2-11 ) 2.11 RECORDS AND DOCUMENTS 2-11 2.11.1 Available Records and Documents 2-11 , 2.11.2 Records Management System 2-11 2.12 SECURITY 2-12 2.13 INTERIM TECHNICAL SUPPORT CENTER 2-12 3.0 EMERGENCY OPERATIONS FACILITY 3-1 3.1 FUNCTION 3-1 3.1.1 During Emergency 3-1 3.1.1.1 Notification of Unusual Event, Alert 3-1 3.1.1.2 Site _ Area Emergency, General Emergency 3-1 3.1.2 During Non-Emergency 3-1 3.1.3 Limiting Conditions 3-1 3.2 LOCATION 3-2 3.3 STAFFING 3-2 3.3.1 During Emergency 3-2 3.3.1.1 Notification of Unusual Event or Alert 3-2 3.3.1.2 Site Emergency or General Emergency 3-2 3.3.1.3 Task Functions of Personnel 3-3 3.3.2 During Non-Emergency 3-3 3.4' ARCHITECTURE 3-4 3.4.1 Spacial Layout Description 3-4 3.4.2 Lighting ~ 3-5 3.4.3 Finishes 3-7 3.4.4 Fire Detection 3-7 3.4.5 Fire Protection 3-8 3.5 STRUCTURAL DES;GN CRITERIA 3-8 3.5.1 Governing Codes and Regulations 3-8 3.5.2 Structural Classification 3-8 3.5.3 Design Loads 3-9 3.5.4 Materials and Design Methods 3-9 3.6 HABITABILITY 3-9 3.6.1 Post Accident Radiation Shielding 3-10 3.6.2 HVAC 3-10 g(_ g,) ~ 3.6.2.1 Design Basis 3-10 i 3.6.2.2 System Description- 3-11 3.6.2.3 Safety Evaluation 3-11 l Rev. 4, 5/81 l

A

    / h
    'd    3.6.2.4 Tests and Inspection                      3-12 3.6.2.5 Instrumentation Requirements              3-12 3.6.3       Radiation Monitoring                  3-13 3.6.4       Occupant Accommodations               3-14 3.7 COMMUNICATION                                 3-14 3.7.1       Telephone                             3-14 3.7.2       Hotlines                              3-14 3.7.3       Radio                                 3-15 3.7.4       Paging                                3-15 3.7.5       Public Address System                 3-15 3.7.6       Facsimile                .            3-15 3.8 POWER SUPPLY                                  3-16

• 3.8.1 PL Distribution - Normal Service 3-16 3.8.2 Emergency Generator 3-16 3.8.3 Uninterruptable Power Supply (UPS) 3-16 3.9 INSTRUMENTATION 3-16 l 3.10 EOF DATA PRESENTATION 3-16 3.10.1 Equipment 3-16 3.10.2 Data 3-16 A

() , 3.11 RECORDS AND DOCUMENTS 3-17 3.11.1 Available Records and Documents 3-17 3.11.2 Records Management System 3-18 3.12 SECURITY CONTROLS 3-18 3.13 BACKUP EMERGENCY OPERATIONS FACILITY 3-18 3.13.1 Function 3-18 3.13.2 Location 3-18 3.13.3 Staffing 3-19 3.13.4 Spacial Layout Description 3-19 3.13.5 Communication 3-19 3.13.6 Backup EOF Data Display 3-19 3.13.7 Records and Documents 3-20 3.14 INTERIM EMERGENCY OPERATIONS FACILITY 3-20 I 4.0 OPERATIONAL SUPPORT CENTER 4-1 , . 4.1 FUNCTION 4-1 4.1.1 During Emergency 4-1 4.1.1.1 Notification of Unusual Event 4-1 4.1.1 2 Alert, Site Emergency, General Emergency 4-1

          ~4.1.2      During Non-Emergency                  4-1 i

i 4.2 LOCATION 4-1 4.3 STAFFING 4-2 4.3.1 During Emergency 4-2 Rev. 4, 5/81

1 / 4.3.1.1 Notification of Unusual Event 4-2 4.3.1.2 Alert, Site Emergency, General Emergency 4-2 4.3.1.3 Task Functions of Personnel 4-2 4.3.2 During Non-Emergency 4-2 4.4 HABITABILITY 4-2 4.4.1 Post Accident Radiation Doses 4-2 4.4.1.1 Allowable 4-2 4.4.1.2 Postulated 4-2 4.4.1.3 Radiation Monitoring 4-3 4.4.2 NVAC 4-3 4.4.3 Shielding 4-3 4.4.4 Occupant Accommodations 4-3 4.5 COMMUNICATIONS 4-3 4.5.1 Telephone 4-3 4.5.2 Hotlines 4-4 4.5.3 Public Address System 4-4 5.0 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) 5-1 6.0 NUCLEAR DATA LINK (NDL) 6-1 7.0 EMERGENCY RESPONSE COMPUTER SYSTEM (ERCS) 7-1 () O 7.1 ULTIMATE ERCS 7.1.1 Integrated Computer System 7-1 7-1 7.1.1.1 Data Acquisition 7-3 7.1.1.2 Data Preparation 7-3 7.1.1.3 Data Presentation 7-4 7.1.2 Seismic SPDS 7-5 7.1.2.1 Data Acquisition 7-6 7.1.2.2 Data Preparation 7-6 7.1.2.3 Data Presentation 7-6

;         7.1.3      Availability                                 7-7 7.2 Interim ERCS                                        7-7 7.2.1      Utilization of the Plant Computer System     7-7 7.2.1.1    Data Acquisition                             7-8 7.2.1.2    Data Preparation                             7-8 7.2.1.3    Data Presentation                            7-9 7.2.2      Seismic SPDS                                 7-9 7.2.3      Availability                                 7-10

6.0 EMERGENCY FACILITIES INTERFACE 8-1 i.1 DATA 8-1 6.1.1 Data in the Ultimate ERCS 8-1 8.1.1.1 Data Provided by the Integrated Computer System 8-1

[ 8.1.1.2 Data Provided by the Seismic SPDS 8-3 ~ b' 8.1.1.3' Data Exceptions in the Ultimate ERCS 8.1.2 Data in the Interim ERCS 8-3 8-3 l i i i Rev. 4, 5/81

I) V 8.2 DATA TRANSMISSION 8-4 8.3 COMMUNICATIONS 8-4 8.3.1 Telephone .8-4 8.3.2 Hotlines 8-4 8.3.3 Radio 8-4 8.3.3.1 VHF Radio System , 8-4 8.3.3.2 UHF Radio System 8-5 8.3.4 Public Address System 8-5 . 8.4 RELATIVE LOCATIONS 8-5 9.0 DESIGN, DEVELOPMENT, QUALIFICATION, AND 9-1 INSTALLATION VERIFICATION PROGRAMS 9.1 TECHNICAL SUPPORT CENTER (TSC) 9-1 9.2 EMERGENCY OPERATIONS FACILITY 9-1 9.3 tjiRGENCY RESPONSE COMPUTER SYSTEM (ERCS), 9-2 sal'ETY PARAMETER DISPLAY SYSTEM (SPDS), ANI) NUCLEAR DATA LINK (NDL) O b L l f

{

               .                                           l

!O r Rev. 4, 5/81

     +

7.s . APPENDIX I EMERGENCY FACILITIES - CONCEPTUAL DESIGN DESCRI:TIONS List of Figures-and Tables a Figure 2.14.1- TECHNICAL SUPPORT CENTER LOCATION PLAN Figure 2.14.2 TECHNICAL SUPPORT CENTER BUILDING SECTION Figure 2.14.3 TECHNICAL SUPPORT CENTER FLOOR PLAN  ; Figure 3.15.1 LOCATION OF THE EMERGENCY OPERATIONS FACILITY Figure 3.15.2 EMERGENCY OPERATIONS FACILITY SITE PLAN Figure 3.15.3 EMERGENCY OPERATIONS FACILITY FLOOR PLAN Figure 3.15.4 EMERGENCY OPERATIONS FACILITY FURNITURE AND DATA DISPLAY LAYOUT Figure 3.15.5 EMERGENCY OPERATIONS FACILITY HVAC LAYOUT Figure 3.15.6 EMERGENCY OPERATIONS FACILITY POWER SUPPLY Figure 3.15.7 LOCATION OF BACKUP EMERGENCY OPERATIONS FACILITY Figure 7.1 ERCS FUNCTIONAL OVERVIEW Figure 7.2 ERCS CONFIGURATION Figure 7.3 INTERIM ERCS Table 8-1 SPDS SAFETY PARAMETER SET Table 8-2 PARAMETERS NOT MONITORED BY INTERIM ERCS Figure 8.4.1 RELATIVE LOCATIONS OF THE EMERGENCY RESPONSE FACILITIES 1 9 Rev. 4, 5/81 l

l.0 ECtJEj_AND_9EJjgTIYS t') The purpose of this appendix is to provide conceptual design l descriptions for emergency f acilities in accordance with criteria , specified in NUREG-0696- Final Report, " Functional Criteria for l Emergency Response Facilities". Information on " interim" facilities, required by NUREG 0694 is also provided. The l following items are contained within the scope of this document:

1) Technical Suppcrt Center (TSC)

2) Interim Techntcal Support Center (ITSC)

3) Emergency operations Facility (EO F)

4) Backup Emergency Operations Facility ( B EO F)

5) Interim Emergency Op,ia . ions Facility ( I EO F) b) Opera tional Suppcrt Center (OSC)

7) Safet y Parameter Display Ssystem (SPDS)

8) Nuclear Da ta Link (N D L)

9) Emergency Response Computer System (ERCS)

  /~T  10)  Interim Emergency Response Computer System (IERCS)

( ,/

11) Emergency Facility Interface

12) Design, Develcpment, Qualification, and Installation Verification Programa i

l Rev. 4, 5/81 1-1

                                                                          --ar   -W

2s9__ZEGUEIGhk_B9229Er Cgyzgy i i E 23J FUNCTION 22121__EMIind_f!"IMSESI The Technical Support Center (TS C) provides a location for plant management and technical support personnel to assemble to advise l Plant operations personnel during an emergency. The TSC personnel will provide guidance for management of emergency conditions and accident mitigation. 2212121__Estitisati9n_9f_Enssaal_ Event The TSC will not be manned during an unusual Event. 2212122__Al2Itt_Si&g_13gggggcy,_ggngIgl_jggggeggy 1be ISC will serve as an emergency response facility during an alert, site emergency and general emergency. The TSC shall r~N perform the functions of the Emergency Operations Facility (EOF) (_) until the EOF is manned. The technical personnel manning the TSC have access to analytical programs needed to effectively analj ze conditions in the plant. The TSC loca tion on the observa tion

gallery overlooking the control room permits visual contact and easy access to information in the Contrcl Room which migh t not be dVailable in the ISC.

The TSC will serve as the communica tion center through which information is veritied for quality, accuracy and conciseness to minimize any error in interpreta tion. This inf ctma tion concerning plant systems is provided co offsite support staff and Nuclear Hegulatory Commission (NHC) personnel lccated in the EOF. Prior to manning of the EOF, the TSC will coordinate all information and communication between the site and offsite support ag encies. 22122_ During_No_n-Emgigency the ISC facilities may be use1 for normal daily activities provider these activities do not degrade the TSC emergency responsiveness or reliability. During normal operating conditions, the ISC will provide office space for the Supervisor at operations, operations Staff Engineers and Shift Technical Advisors. 'The facilities may also be used as a research or [_,] reference area by other station personnel because of the

        -extensive information located here.

Rev. 4, S/81 2-1

2.1.3 Lim it in g---------ns Conditio - The Limiting Conditions for operation of the TSC are under review dnd will be incorporated into the plant technical specifications. 212__1gCATIgE The TSC is located in the existing Control Room mez zan ine above the Centrol Room at elevation 741'-1" of the control structure. The TSC is within approximately two minutes travel time of the Control Roca by elevate- or stairs. Reference Figures 2.14.1 and 2.14.2. 211- gThyyJyg 21211- DuLiuu E2eEuggcy The ISC shall be staffed with gualified individuals to fulfill both management and technical support f unctions. The TSC staff assignments are contained in Section S.2 of the Emergency Plan. 23 J2131__3ctificg11gn_g1_Ungsygl_gvegl O The TSC will not be activated during an unusual event. 23 J3132__hlgI1 ,_gilg_fgggggggy ,_geggggl_3ggggggcy The ISC will be activated during an alert, site emergency and general emergency. The TSC 1 designed to provide working space and facilities for zS people and is a controlled access area. The Emergency Director (ED) and the on-site emerJency response team will be located in the TSC. The on-site emergency response team, as discussed in the Emergency Plan, includes the dD, Technica l Suppctt Coo rd i n a to r , dddiation Protection Coordindtor, Administrative Coordinator and Communications and Records Coordinator. The responnu team shall also include staff members for each coordinator to ensure adequate performance in each area. The responsibilities of each of these ccordinators is listed in the Emergency Plan. The Nuclear Hegula troy Commission Em ergency Responsa Team , consisting at five individuals, sill also be located in the TSC. lll Rev. 4, S/dl 2-2

    ,,     241sizl___1dsh_func11cgg_gf_pygsonnel i
         The task functions of'the emergocny response team personnel are
          . listed in Section 5.2 of the Emergency Plan.

Iz)s2__DMElH9_HQD-EISISSECX During normal operating conditions, the TSC will serve as the offices for the Supervisor of operations (1) , Opera tions Staf f Ergineers (2- 3) , and Shift Technical Advisors (1-3) . The TSC may also be used f rom time-to-time as a reseatch or reference area by other station engineering and operating personnel, due to the information provided in this area. 2.4 A HCilI TEC1pB E The TSC, about 2,250 square feet in size, is designed as a work aLea occupying the existing Control Room mezzanine space and adjacent three rocms. The areas in tront of the Transien t Monitoring Panels 1C/2C 670 r- havc been Ereviously designated for use during startup tosting, a (_S / period at approximately one year a f ter fuel loa d . This is a temporary arrangement which requires the space be availanle for data recording equipment, a CRT, a printer / plotter, startup test l equipment, and-perscnnel. T here fore, during the periods of startup testing of Unit 1, the facilitics indicated for the area in the immediate vicinity of panel IC G70 will not he available. Likewise, during startup testing of Unit 2, the facilities on that side will not to available. 4 241 SEdkill_Ld1091_pngcgiption The 1SC includes the following spaces (Reference Fijure 2.14. 3) :

1) Work Areas:

The work areas adjoin the Monitoring Area. The work areas acccamodate modular tables and cubicle-type work spaces. The Plant Technical Specifications, Plant Operating Procedures, Emergency Operating Procedures and Final Safety Analysis Report are to be located in bookcases in these work areas. I l /~') fV 2) honitoring Area: Rev. 4, S/81 2-3 j

The monitoring area houses the Safety Parameter Display l Unit, Emergency Response Computer System Displ.ty Unit, Unit lg Monitoring Console, printer / plotter, and stack monitoring panel.

3) Conference Room:

The ccnference room is planned to accommodate 16 people grouped around a confetence table composed of several modular reference tables.

4) daergency Director's Office:

The emergency director's of fice is separated from the conterence room by a folding partition.

5) Document Control Area:

This area houses al.! the document reptoduction f acilities l such as a copy machine, telecopy machine, and microfilm and tictofiche reader printers. Alro located in this area is the vertical stick file for selected as-built drawings. Under-counter cabinets are provided for stoiage of administrative supplies. Records (d uplica te copies, not originals) will be stored l within the ISC in this area. Hecords stored in the T3C will include design documents as required to diagnose plant problems at the system level. Documents such as a s- buil t drawing in the f orm of microfilm /m icrofiche, will be stored in metal cabinets.

6) NHC Conference Rcom:

This tcom is provided for NHC consultation. 11S 619htkLq The TSC is designed tcr approxima tely 100 f ootcandles at desk top level. Fully-recessed fluorescent lijht fixtures will be installed in the TSC. Lighting in the monitoring area shall be controlled by a dimmer switch. 2.4.3 Finishes The architectural finish tor the TSC is the same as that specified for offices in the balance of the plant, i.e., resilient flooring, painted walls, and suspended accoustical tile l ceiling. ggg Rev. 4, 5/81 2-4

21EzE-_f1Ee Detectign ()x,

     \_

The halon system shall incorporate a cross-zone ionization detector system. A single detector release shall actuate a predischarge alarm within the space and at the fire protection panel C-650 in t!.9 Control Room. The halon shall be released by the activa tion of two cr more detectors. 21212- ELE 9 EL9599&i92 A halon system shall be provided, designed in accordance with NFPA 12A and shall provido a concentration of 5 to 7 percent flooding. The halon system shall provide fire damper releases for all duct openings located in the perimeter of the protected space. Esk- 21BEC1EEbb DgSJGy_CyJJgyff 1he TSC is located on the mezzanine floor, EL. 741'-1", above the Control Roca in the centrol structure which is a Seismic Category I structure, as defined in NRC Regulatory Guide 1.29, " Seismic Design Classification". This structure la designed in accordanco (~ with Chapter 3.0 of the Final Safety A % lysis Report. 216 g3pII391LIII 23h21__ P951- Acc id e n t :'adiation Doses 21h1111- Allex1kle TSC personnel shall be protected from radiological hazards, including direct shine and airborne activition for postulated dCCident conditions to the SaiSe degree as contecl roon: peraonnel. Applicable criteria are specified in General Design Criterion 19, Standard Review Plan 6.4, and NUREG-0737, Item II.B.2. 2.6.1.2 Pcatulgted i The radiation dose to personnel occupying the TSC is the same as the control Room personnel. The doses trom controlling accidents , are _ammarized in Chapter 15.0 of the Final Safety Analysis Report. Bev. 4, 5/81 2-5

115 11]- Esdi2Li2C E9BiL9EiDU G To ensure adequate radiological protection of the TSC personnel, permanent commercial grade monitors shall be provided to alarm on high gross gamma radiation dose ra tes. In addition, airborne radioactivity concentrations will be monitored by portable monitors. The monit oring system s shall include local ala rms with trip levels set to provide eatly warning to TSC personnel of adverse Conditions. neans to dist.inguish the presence or absence of iodine will be provide 1. 11h12- LilhC The TSC llVAC system is a part of the Control Room HVAC system and is designed to accomplish the folle:. sing ob jectives during normal opera tion as well at undet emergency conditions:

a. Maintai!! room te5peraturv of 730F t 50P.

b. Maintain a positive pressure above atmospheric pressure to inhibit air leakage into the TSC at all t i ai e s.

c. Fupply a quantity of outaide air and tecirculate conditioned air to maintain the design room tempera tu re .lu ring normal operation. When h gh radi: tion is detectei in the outside '

air, the outJide air supply is diverted through the emerjeucy.outside ait filter systet,

d. Isolate the space when chlorine is detected in the outside air.

The Control hoom tiV A C s ys t e:s is described in FSAR Sectiu ' l. l 21hel- Glniellih2 Shielding requirement for the TSC is the same as for the Contr.1 Hoom tor tctal dose to occupa nt; from direct shino and airborne. Activity will not exceed 5 R e.n whole body tor the duration of the accident. This is in accordanc- with General Design criterion 19, U SMC Standard ac.fiew Plan o.4, and N UR EG- 0 7 37, item I I . D. 2. Duration of occupancy and method of saalysis is the same as that used for the centrol room. 2 Sz3__ggguB2B1 SES9EE9dd119hd No sleepin g accom:nodations or to ile t facilities are proviled in the Tsc. Use of the plant 's existing facilities at grade level ot the control atructura for washing ani toilet accommo la tions is g Hev. 4, S/El 2-6

(~^ planned. There is a unit kitchen with electric range, under-k ^) counter refrigerator and sink in the TSC. Potassium iodide and l self-contained breathing apparatus will be provided in the TSC. 211- 995B92LGA1192 kIDED The TSC cosaunication system is comprised of priority accesa voice links-hotlines, telephone lines tied through the plant switchboard, local outside commercial lines, VilF and UHF radio, l pagers and the plant public address aystem. These facilties provide reliable normal and emergency, primary and backup communicat. ion links between the TSC and the Control Hoom, the EOF, the 14BC and all the communication functions required in the ECF f or initial notification and early recommendations to on- and of f-site a uthorities prior to staf fing the EOF. The description of the communica tion f acilities in the TSC is as follows. 1 21111- 1cl22henc Norma l telephone service for the TSC will use the plant Private ( Automatic Branch E xr.h a ng e (PABX) system and local outaide commercial lines. Lirect Allentown General Office branch exchange telephone service is also provided. 2.7.2 Ilot line s 4 Priority accesa voice communication links with automatic signaling is provided at several Inca t ions in the TSC. The hotline f acilities have the capability for individual or conference calling between the TSC arid the follcwing:

d. E2ergGHCy OPHrations Facility (EOF)

b. Contrcl Hoom (CR)

c. Luzerne County Civil Defense ( LCC D)

d. Columbia County Emergency Management Agency (CCEM A)

e. Pennsylvania Emergency Management Agency (P EM A)

f. Nuclear Regulatory Ccemission, Emergency Nctifica tion System (ENS)

{

g. Nuclear Regulatory Commission, llealth Physics Network (hPN)

Rev. 4, S/El 2-7

o

h. Department of Environmental Hogulation/Dureau of Radiation Protection (D ED/ PitP)

1. Opera tional Sul: port Center (OSC) l 222 J__1!dd 19 The TSC has both a four-channel 450 Mliz UllF and a two-channel 150 Milz Vilf Ladio system.

The t wo-channel VilF radio is contained in a single .lesktop centrol console. This syntem i; used as an emetgency backup to l the telephcne s p tem, to communicate with the field monitoring teama, and as an otf-site pager. The f our-c ha nnel UllF radio is opetated from a single lesk top control condole. The UllF radio will provido primary and b a ck il p securit", caergency, operational and maintenance communica tion links. 2:22S__EdGSE l The ISO Milz Vilf radio system is elutpped with a page encoder which is used to locate key person ne l on- a nd off-sito. 221sS__fMhlic_AddESED_SYrdfB T 1. e system .s h d 1 ptcvide two-way communacation facilities for speech in;;o t at handset stations. Each stat ion shall betocapable of originating and receiving communica tion by switching either

 } a   pager enannel or to one of five non-interCacing party-lino channels.

2121!1- Elc m iJy A lacsimile machine is 1rovided in the TSC. d.s__EoiBB 31!EE M dad =I__D stken_BerviGc The ISC is an integral part of the existing power block. the ilVAC system f or the- TSC iJ an Since tt>nsion of the Con trol doom g Hev. 4, 5/ 81 2-8

    ~

r3 HVAC systes, its normal power source is taken from the plant (_) class IE 4 80 volt system. Lighting for the TSC is part of the plant essential lighting system which is connected, through isolation devices, to the plant class IE electrical system. Further definition of the Class IE power systes quality, reliability and availability can be found in FSAR Section 8.1. 6. lf a nd 8. 3.1.3. 22e22__ Diesel _9snsIat9E In the event of the loss of normal source of AC power, the Class lE electrical systes is tacked up by the emergency standby diesel generators. Further definition of the diesel generator quality, reliability and availability can be found in FSAR Section 8.1.6.lG and 8.3.1.4. 22S23 Unipietruptd blg_Pgwer_ Supply The TSC instrucentation will be connected to an independent 208/120 volt vital AC uninterruptable power supply (UPS) consisting of an inverter and battery that will provide continuous operation through a loss or of f-alte power. Further () definition of the vital AC UPS system quality, reliability and availauility can be found in FSAR Sec t ion 8. 3.1.8. 222__1ESIE93##TATJgj 1he TSC utilizes the same field sensors and signal conditioning equipment which is prcvided to monitor the nuclear steam supply system and the salance of plant systems. The quality, accuracy, and relianili'a of the TSC instrumen ta tion is therefore identical to the field instrumentation used to operate t he plant. This approach has been taken so that people working in different areas will work with the same data. A detailed description of this instrumentation is provided in Chapter 7.0 of the Final Safety Analysis Report. I The data from these instruments are collected by two data

       .aquisition systems.      One system is the Pla n t computer System and l

the other is the Emergency f<esponse Computer System. The Plant [

is described in Chapter 7.0 of the Final Safety i

Computer Analysis System Report ~and the Emergency Response Computer System is ! described in Section 7.0 of this a ppend ix. Both of these systems ) will present da ta in the TSC as describcd in Section 2.10 of this l appendix. (~) v Rev. 4, 5/81 2-9

2 ,1p__ISiC._IAIA_g g S n I3Il g Ab required by NUR EG-C696, the TSC will include human factors engineered man-machine capabilities to allow personnel to determine: o plant conditions during normal operation o plant s te ad y-s tat e conditions prior tc an accident o tralisient conditions producing an initiating event o plant system dynamic behavior during an accident The man-machine intertace will be p rov ided by devices tied to the Emergency Response Computer System (dHCS) which is described in Section 7 cf this Appendix, and by a Unit MonitorinJ Console tied to the Plaat Computer System (PCS) . 2:1921:__gguinstri The locatica in the TSC of the eqilipment described below is shown in the Monitoring Area of Figure 2. 14.3, Technical Support Center Floot Plan. The ERCS will provide the interface to the t olicwing devices: (1) Two CRTs housed in the SPDS Unit, one CRT normally assigned to Unit 1 and one CRT normally assigned to Unit 2 (both CRTs will be switchable to either Unit 1 or Unit 2) ; these CRTs llh will display information related to the Safety Parametor Display System. (2) A CitT unit Foused in the TSC console, which will provide for the display of general plant sa f et y-relate d da ta contained in the ERCS fot specific TSC functions. (3) A printer and/or printer / plotter for the hard copy output of ERCS data. The plant computer system will provide the interf ace to the Unit Monitoring Console located on the UMC Table. Graphic and patameter displays, depicting the conditions of the plant systems, which are normally used by plant operators will be accessible at the UMC Table. O Rev. 4, S/81 2-10

(~T 2 alas 2__psts (_) In general, safety-related data will be provided by the Smergency Response Computer System and other pla nt operational data will be provided by the Plant computer Systes. Data required to support the SPDS f unctions will be included in the common dRCS data tase and will therefore be available for display in the TSC. The information available here will be the same that is availabic in other SPDS locations. Data required for display at the TSC Console will be contained in the ERCS data base. This will provide, for example, historical data presentations for both pre-event and post-event records. ERCS data is described in Section 8 of this Appendix. The Plant Ccapu ter System is described in the PS AR Section 7.7. 2211_ jECORDS AhD CCCUMENTS 2silzl__3Idilgble_pgggI,qs and Documents The TSC will contain, as specified in the Susquehanna SES Emergency Plan, u p- to- d a to tecords for uso during emergency () conditions. These records include: o Current Plant Technical Specifications o Plant Operating Procedures o Emergency Operating Procedures o Final Safety Analysis Report o Drawings, schematics and diagrams showing current conditions cf plant structures and systems o Dose Calculation Manuals 3:11. 2__ygcord s Ma nagengst_Sygtem The records listed in Section 2.11.1 shall be updated and managed by the Susquehanna SES Document Control Center (CCC) utilizing DCC Administrative Procedures.

 "T (V

Rev. 4, 5/81 2-11

2.12 SECUR[Il Although the TSC contains no vital equipment, it is located within a plant vital area and is subject to the vital area access controls .ns iden t if ied in FSAR Section 13.6. All entrances into the TSC are card Leader controlled. 2212__IEISfid_IfCilNICAL SUPPCRT CEjTEj The interis technical support center is located in the same location as the permanent technical support center (i . e. , EL. l 741'1" of the contrcl struct ure) . The interim technical support center shall have all of the features ot the permanent TSC except for the following data equipment: o Stack Monitoring Panel o Printer / Plotters o Sa f et y Pa ra meter Display Unit l o ERCS Display Unit O O Rev. 4, 5/ 81 2-12

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SUSQUf M ANNA STE And ELECTRIC STATION __

• UNITS I AND 2 goe E hAERGE NCY PLAN x

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TECHNICAL SUPPORT CtuitR l 1 suitoiNo secTioN A; BTRUCTURE v REACTOR BUILDING g

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• NOTE: THE FURNITURE AND TELEPHONE EQUIPMENT LAYOUT PROVIDED IS FOR CONCEPTUAL DESIGN PURPOSES AND sees c ~e-a+ ava/ MAY BE SUBJECT TO CHANLE.

2R Rev. 4, 5/81 , , , ,_,

        ,_                            e sex parer l                                                                                                           SUSQUEHANNA STEAM ELECTRIC STATION y         so. A .                                                                  UNITS I AND 2 e ecc.;m.Ty poon aire cms eeApms g ALLmro.w s= % sew                                                                                            i O          gt;-s C,pggw                                                   TECHNICAL SUPPORT CENTER O-- s.*>cemW w %s                                                                  FLOOR PLAN                 3 l

FIGURE 2.14.3 i

3.0 IEEEGEE91_QEEHAI19Es_fAGILIII

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lzh- 19EG119E 21111__D2Eing_EBSE92ns1 The Emergency Operations Yacility (EOF) is an energency response facility lccated near the site. The EOF will provide continuous coordination and evaluation of PP&L activition during emergencies having or potentially having ervironmental impact. Jmizl:1_E211fiEdlioD_Sf_MEMESdl_EISBt,_31ggi The EOF does not have to be manned during an Unusu'.. Svent or Alert; however, it say be manned at the discretion of the Recovery Manager. 2212122__ Site A r ea_ Eg eggoncy4_Gg n egal_f meggo ncy Manning the EOF in mandatory during a Site Emergency an d 1 General Emergency. During either of these t wo emergenc, (~)h

 \-   class i fica tions , the EOF, under the direction of the Recovery Manager, will provide continuous coordination and evaluation of PPSL activities. Once activa ted , the overall coordination of the emergency will be dcne frcm the EOF.

The EOF will also house various governmental agencies such as NBC, FEMA, PEMA and DOE during these emergencies. Any information on conditions affecting the public will originate from the EOF, however the dissemination of this information will occur at the Media Operations Center. For more detailed inf ormation see Section 7.2.2 of the Emergency Plan. ,

      ),1.2 =_During_Egn-Egggggncy t he non-emergency activities of the EOF are such that its main function, that of an emergency response facility, is not

degraded. During norgal plant operation the EOF will be used to I

provide of fice space for the Nuclear daergency Planning Group and for personnel to maintain the Emergency Response Computer System. In addition, space is provided for plant training pu rpose s. (g] 3.1.3 __Ligiting_ Conditions Bev. 4, S/ 81 3-1

The Limiting Conditions for the operation of the EOF are under g review and will be incorporated in the Plant Technical W Specifications. 3.2 LOCATION l The site lccation for the EOF is in North Central Pennaylvania in Luzerne County approximately 5-1/4 miles north cf the Town of Berwick in Salem Township. The of fsite facility is located approXimately 2,500 feet southwest of the contrcl structure l (Reference Figures 3.15.1 and 3.15. 2) . The site fronts on County Road T-438. Direct access to the site will be maintained over a 12' wide stoned roadway from RtT-438 to the 500 kV Switchyard. 3.3 STAFFING 21111- DSEiD9 EECE92DS1 The EOF, once activated, will provide continuous coordination and evaluation of PP6L activities dQEing emergencief haVing or potentially ha ving en vir onmental consequences. The EOF staff includes personnel who will parform radiolog ica l evalua tions, to interface with otf-site officials and to manage off-site resources. The EOF staf f assignments a re contained in Sectior lll 5.3 or the emergency Plan. 2=11111- EDLLLicatico_gt_ynyggaL_gyout_g;_Alegt The EOF is not required to be activated during either of these emergency levels; however, the aecovery Manager may elect to do so by notifying individuals from the off-Jite support organization to report to the EOF. 3.3.1.2 S ite E me rg en cy_gg_g en er a l_g me rgency The EOF sh all be manned during a Site Emergency and General Emergency. The EOF staff shall consiot of a Recovery Manager who will interface with the plant through the Emergency Director, Technical Support Manager, Site Support Manager, Administrative Support Manager and Radiation Support Manager. The support team shall also include adequate starfing to perform their specific duties. .These duties are specified in the Emergency Plan. Space i t, provided in the EOF for the f ollowing personnel during a Site or beneral Emergency. Rev. 4, S/El 3-2

i i 1 39z 9f EjRSONN EL (U~j 1). Reception Area Receptionist / Switchboard Operation 1 Security Guard 1

2) . Emergency OperattJn Area A. Coordinator's Private Office 1

                  - S taf t Se m i-P riva te Office                         3 D. NGC Office Space                                         S

c. Pennsylvania Emergency Management Agency (FEMA) Federal Emergency Management Agency Office Space 2 D. PFF,L Hadiological and Environ-saental Monitoring Office 1 E. General Staff Work space 35 2121112- ladh E2DGhiSDS 91 EBE22 Duel D

() 1he task functions of the off-site emergency organization are found in Section 5.3 cf the Emergency Plan. # 4 i 213z2__pyging_Non-Emet 32ngy i During Non-Emergency ccaditions the EOF will be staffed by the Nuclear tacrgency Planning Group (NEPG) which will consist of ona supervisor, two staf f members and one secretary / receptionist. In addition, Computer parsonnel may be required for computer equipment maintenance and computer program development. The non-Escrgency use 01 the EOF will not degrade its primary purpose as an Emergency Response Facility. 3.4 ABClilT ECT UR E f the design philosophy developed for this f acility has three ma jor design parameters. First, to provide functional, efficient space to-house the emergency operation requirements if such an event i occurs; second, to create the kind of pleasant and appropriate environment to prcmote the operating ef ficiency of the emergency staff; and third, to express in ita functional architecture the special character of an Emergency Operations facility. i Rev. 4, 5/81 3-3

The 16,500 square feet, one-story buildinj is a rectangular g structure, 167' long by 99' wide. The exterior walls are 12" W reinforced concrete with a brick facin9 The shed roof is a 9-1/2" reinforced concrete slab. The concrete was utilized to provide the required radiological protection. Fifty (50) parking stalls will be provided at the EO F, In addition, parking space for five (5) emergency response monitoring vans will te provided at the side at.d rear of the building. Communication and power hook-ups will be a vailable for each van. hh.1_ _UUd Sid l k d 1921.. E US GIl p ti g r} The area reJuirements for the EOF facility are divided intc three basic ne(ds. These ne++ds are (3eference Figures 3.15. 3 a rid 3.15. 4 ) : A. Eastygygy_9tu5ationy_Bugnonyy This atea is composed of privat 1, semi private and open office areas to assure the scooth flow and evalua tion cf data from th e plant site. The space reijuirem* tats for thi<; operatiori are:

1. A rece>ptionist's area near the ma in entra nce.

g

2. Two offices for off-site Emer gency coordinator and support pertcDuel.

3. One office for the NHC to house five people.

4. One o f fice for PEMA and/or FEMA. (Pennsy1vania Smergency F.cnitoring Agenc y/ Federal Umergency Monitoring Agency) .

5. One o f fice for Radiological Environmental Monitoring personnel,

b. A wor k a red tot 35 people located in a cent ral core a re>a.

Alao included in thi:, area will be a room for maps and documents. In additoin to the desxs in the work r.rea, CRT d it,pla ys a nd hard copy output devices will he pro vided as shown tn Ftgure 3.15.4 A sta tic display board will be mounted on the host wall.

7. One conference rocn for 10 to 15 peopla.

D. ESE1121 t _ A [rg y_1gg_gpffIg e3gy_j!gyngpyn TheJe areas a re provided to accommodate the nce<ls of the dCF atatf durin j an emer Jency con lition. The areas provided are mechanical and electrical equipaent, toilota, kitcher and eatitig Hev. 4, S/81 3-4

t e- facilities, storage areas and a multi purpose meeting room. The (_)' space requirements are:

1. A multi-purpose meeting room.

2. A lunch rcom with kitchen equipment.

i

3. Rest rocas.

4 Mechanical equipment and telephone equipment room.  ;

5. An %sergency generator and uninterruptable power supply.

o. General storage areas. ,

C. ggmguleg_gggg A computer rocm will te located in the EOF to support the Emergency Berponse Ccaputer System. The size of the area will be ' dbout 1,500 square feet. Also, a computer work room of approximately 750 square feet in size, will be coquired to accommodate up to four (4) employees responaible f or the operation and maintenance of the computer equipment. Th i s results in a total requirement of approxiately 2,250 square feet (~)N

  \-   of floor space.        The space reAnirements are:

1. Baised access flooring for computer rccm and computer work rocm.

2. Semi-private office for four (4) com pu ter pornonnel.

3. Inverter back-up poder system to carry electrical load for 15 minutes.

4 Independent cooling system tor computer equipment.

5. Exteriot access to provide for equipment in s ta lla tion.

6. Paper and material storage area. T

       ):dz2__ Lidh ting A. Desig n_ggiteria

1. General Illumination L

() a. Lighting designed to maintain specified footcandle levels in the following loca tio n s: Bev. 4, 5/81 3-5

I (1) Office Areas - 70 to 100 footcandles. (2) Storage Itooms, Lunch itoom, Kitchen and Mechanical Itcoms - 30 to 50 footcandlen. (3) Corridors - 15 footcandles. (4) Toilet Areas & Locker itooins - 20 f oot ca ridl es.

b. Local dimmer switches will be provided in the data dinplay arcan.

2. Stand-by (Emergency illumination)

To be provided as listed under Section 1 - General Illumination. J. External Illumination Liijhting designed to maintain specified footcandle levolu in the following locationu: (1) Parking Area LightinJ 1/2 f o o t ca n:ll e s. (2) Outside Security Lighting - 1/2 footcandle. ( 1) Walkway and Un t rance Lighting - 5 f ootcan llen. U- 111'en o f LighM ng_ fig ung,

1. Interior

a. heneral office: Fully-reconned Iluoroacent light iixturcs.

b. Mechanical and S t o i a g er: Two lamp ItLM f lou r encesit Iixture with porcelain enamel retlectora.

2. Exterior

a. Parking Area: Single luminaires utilizinj high preurute nodium L a ::t p s.

b. Secucit y: Wall mounted luminai res utilizing high 1.tessure sodium l a :n p u.

c. Walkway Lighting: Style of fixtqure to be coo rdi ria ted with architectut.il teatures of the building,

d. Contrcl of exterior fixtures shall be: g

 !< e v . 4,   S/ 61                               3-6

t t' (1) Photocell on and off tot security (2) Photocell on and timeclock off for all other , areas. Jziz2__fiBiehrE

1. Office areas will have vinyl clad gypsum board walls, l

.                      acoustical ceiling tile, carpeted floors, and painted                                ,

trim.  :

2. Toilet areas will have ceramic tile floors and walls [

hith moisture resistant acoustical ceiling tile.

3. Support areas will have exposed concrete floor with hardener, painted block walls, and exposed painted '

ceiling. JzlzS_ =__fite_Delesti9n - A. pggigp_glitrIla *

1. Fire Alarm System

a. The system shall be a class A su pervised s ystem,

       .()                   capabic of performing the followinj functions when a manual or automatic signal initiatir6g device is dCluatEd*                                                                      ;

I. Sound an evacuation alarm.

II. Notifying by leased lines, local, or public fire authorities.

b. Manual operating stations shall be provided at all access doors to the facility with a maximum travel distance of 200 ft. between sta tions.

j'

c. A sprinkler system waterflow switch shall be 7 provided upstream from the alarm check valve.

d. Valve tamper switches shall be provided on each f valve capable of shutting off the sprinnier water  !

supply, , t I f

e. A low building temperature alarm shall bo provided. i l f. The control panel shall annunciate alarm and (

                   -         trouble signals and pro v ido capability of transmitting thoJe signals to a remo te location.                              !

i (~)/ s_ Hev. 4, 5/81 3-7

g. daterflow, manual and halon actuation shall registet as alarm, building temperature and valve tamper shall register as trouble. lll

h. Alarms shall sound throughout the building interior and on the building exterior.

3.4.5 Yitt Protection

1. Automatic wet pipe .iprinklers on an ordinary hazard pipe schedule shall be provided tnroughout the b uildir:g except below the computer room floot and above ceilitigs where no combustible materials are present.

2. Computer Area A total tlooding, automatic halon 1301 syatem shall protect the rcom volumes and the vclume of the spaces Leneath the floors of the computer toca and computer work room with a SX concentration.

3. The halon system shall be actuated by a cross-zoned product of combustion detection system.

11k-_21BEC19?Ah Dhs19h_C21TEBIA 3.5.1 (Joverniga_Codo s_.j gd_hgjula t ioris

1. BOCA "Easic duildinJ Code /lS7d."

2. U3C - " Uniform Buildinj Code /197'd."

3. ASTM - American Standard Testing 1aterials.

4 ACI - American Concrete Institute. Jahz2__31ElJS1HE2_CldEDiliCdtigg building classification: D-5, Non-!!azardous Commercial, Industrial Office. Construction Type: Type III, incombustible, he i-J h t li mit 4-story, maximum floor area allowed 20,000 square foot unsprinklerad. Maximum travel distorice to a n a[ proved oxit is 150 feet. Nuc classification: The 40F is classified as a stracture, the tailure at which sculd not r es ul t in release of significant radioactivity, and is not required for reactor shutdosn. This structure is classificd as Non-Category 1. O dev. 4, S/El 3-8

   <s   JzEsl__Ef212H_k9dda

( )

      /
        - Snow and/or Liveload ..................................                  30 PSF
        - Major Mechanical & Electrical Equipment                ............... Actual
        - Miscella neous Mechanical & R19ctrical .................                  9 PSF
        - Hung Ceiling ..........................................                   3 PSF
        - Dead Load .............................................                  Actual
        - Wind Load .............................................                  25 PSF
        - Uniform Line Load on Floor Slab           .......................       100 P3F
        - Seismic Loads Per UBC Zone 1                                                          1
        - The EOF need not te designed for floods since it is located outside of the flood stage.

225z1__datSIi31h_dDd_E2212B_321h9de The EOF will be a concrete structure designed by the ultimato (,) (~N strength method established by ACI-31d-77. (1) Loadinj Conditiorm I U- 1.4D - 1.7L U= .75 (1. 4 u + 1.7L + 1. 7 W) U= .75 (1. 4 D + 1.7L + 1. 7 W) (2) Notationu U= Ultiniate Strength D= Dead Load L= Live Load V = USC - Seismic Load W= Wind Load 3.6 HA31TABILITY liabitability systems are designed to ensure habitability inside O the EOF during normal and abnormal station operating conditions including post LOCA radiological protection requirements as Rev. 4, 5/ 01 3-9

specified in NUREG C696. Adequate water, santiary facilities and g etdical supplies are provided to meet the reasonable requirements W of normal staffing levels during and a f ter a n acciden t. 3.6.1 Post Accident Radiation Shielding The EOF will be designed to provide auf ficient s h ic id ing to rtduce by a facter of more than 5 the gamma radiation shine from external post accident sources, including both direct shine from the reactor building and from airborne redioactivit y outside the EOF which is released from the reactor building. The walls and ceiling of the EOF are designed to provide a minimum thickness of nine inches of concrete. Based on the attenua tion of 0.7 MeV gamma radiation, this concrete will provide a protection factor at greater than S. In addition, all entrances and exits f rom the building and all penetrations through walls and ceiling will have a labyrinthine design which will prevent direct shine from outside sources into any part of the building which is normally occupied without paraing through at least nine inches of conrete. J.6 22 HVAC 2 - s- 211__ D10114_p A SJs This system provides heating, cooling, ventila tion and control of environmental conditions in the Emergency Operation.; Facility g (EOF) . The system is designed to accomplish the following objectives during nctmal and emergency plant o per at io n : a) Whenever the building is occapied, maintain the apace temperature at 75of 150 for personnel comf ort and to ensure the operability of the equipment a nd inst ruments locate 1 inside the LOF undet normal and emergency [lant operating conditions. b) Maintain a slightly positive pressure above atmosphere inaidc the EOF, in order to inhibit air leakige into the buil d in g. This is not applicable for operation during isolation mode. c) In a p o s t-acc i de n t emergency, the llV AC s ystem is designed to provide radiation protec tion f or occupants of the EOF from airborne fission producta. During emergency mode of o pe ra tiori, outside air shall be fil+ered throujh filter system consisting of High ef ficiency Partiulate Filtars (llEP A ) . The changeover from the nor:nal operation mode to emergency operation mode shall be manual. Capability for tot'al isolation of ilVAC system shall be provided. During this mode a portion of the recirculation air will be tiltered through HEPA filters. Rev. 4, S/e1 3-10

( d) ttaintain airflow from areas of lesser to a reas of greater potential tadioactive contamination. 11.bz212- 2H 125 DH99Eh2119D Figure 3.15.5 shows schematic represantation for this syste giving details of the airflow, duct la yout, instrumentation and equipment rarameters. The system design includes air handling units, filtration unit (including f an) , condensing units, variable air volume boxes, 1 glycol cooling units for computer room air conditioners, exhaust

                        - fans, electric huating coils, rad iant hea t ing panels, intake and j                          exhaust da spers and lcuvers, refrigerant piping, ducting instrumentation and controlu and other components required for proper operation of the system.

Two identical size air handling units provide ccnditioned air through the low pretsure supply duct work and byptsa type variable air volume boxes to supply air outlets located in the various' areas of the tuilding. Area thermoatai.'s are provided for individual control. Electric duct hea ters a re provided in the main supply duct from each ait handler., for providing heating

during cold wea ther. Perimeter a rea heating is provided by ceiling mounted radiant heating panels. Building entrance

;                         vestibules are hea ted using wall insert hea ters.                                 Electrical space heaters are provided in electrical and mechanical equipment                                              ,

j ~ rooms. System air return is provided through the plen um spaco hetween the hung ceiling and tho roof. System cooling is provided by two air ccoled condensing units located outsido the building. Each air handling unit is piped to its condensing unit and refrigerant type direct expansion cooling ccils accomplish the cooling function. Toilet rooms, janitor's closet and shower dreas are providea with ducted exhaust systein using exhaust f a ns.

Separate exhaust will be provided for batter y rcom and exhaust j hood located in t he sample prepf ra tion room.

i j Computer rcom cooling and humidity requirements are provided by a

 ;                       separate system consisting of remote glycol coclers, h umidi fiers, air hdndling units, instrumentation and Controls. Ventilation requirements tor this area ar.+ provided by the central air

handling unitu.

E9E!!hil SEildE_91$Edli9D: 1 The air handliny units provide hea ting or cooling as required. These units ate operated on an economy cycle and maritsum outside air is used tar ,:ooling when the entha lphy of the outside air is 3 lower than the enthalphy of the return air. Mini Aum outaide air and air cocled condensing units are used to provide vo n ti la tion and cooling respectively, when the enthalphy of outaide air is higher than the enthalphy of the return air. Electric heating

,                       -coils, perimeter heating,'and other heaters are used as necessary.                  Area thersometers regulate the a ir flow and Rev.        4,     5/01                                  3-11

therefore, the cocling to the va rious areas. Exhaust systems are operated as required. g fBfEufS1_9ECEdli2B_59de: During this mode of opera tion, the system will cperate with minimum outside air and the building will be slijhtly pressurized. Outside air in filtered through the filter bank consisting of prefilters, ilE P A filters, fan, isclation dampers and controls as required. Outside air flow during this mode shall be limited to 2,000 ctm maximum. System Isolatiot. Mode at opup2tigg: System will also be designed with the feature tc provide total system isolation and partial recirculation through filter units f or operation during emergency requiring total system isolation. This changeover will also be manual. During this mode, al l exhaust tans would be stopped and the building dill not be maintained at a positive pressure. ES9k259D1_Edd9tEU22D52; The equipment and the system components will not be designe i t o meet seismic category I requirements or be qualified as Engineered Satety Features. All llVAC equipment except liEPA f11ters will be commercial grade q ualit y. iiEPA filters shall be suitable fcr nuclear application. 225:22]__2diflX_EYd1 9dli2B The system, a s designed, will meet the LOF f u n c t iorn al requirements as stated in NUREG-Oo96. The system design will include a tie cont.ection between the t wo oupply air system ducts so that partial cooling can be providel la the event one of th e units is nct functicning. 224:22E__1Sdlu_dDd_lB2ESSli2BM All components are tested and inspected as separate components and as integrated system. After the d uctwork system is instdlled, all the air flows Will be meaSitted and adjilstments to meet the design rejuirements will be ma de. All the instruments will be calibtated and set at design conditions. Complete sv2 2 will be pre-operaticnally tested to meet the design requi rma ts. J 5:225__lDd1E9Ethldlio"__E2391E25SE12 All the control s. itches for the control the various system components will be located on a cont; :. panel in the mechanical equipmesnt room. Lccal annunica+ars will be provided in the mecha nical eq uipment room of the E O F. Following abnormal conditions will be alarmed at the loca 1 cont rol pancl: g Rev. 4, S/61 J-12

l r3 a) Air landling unit f an tailures. U Condenser unit f an f ailures. b) c) Filteration system failure (combined alar m) . d) Failure (of battery room exhaust fan. e) Failure of ottet exhaust fans, t) Failure of ccarutar room cooling system (combincl). Filtration syster will be provided with a Iccal panel and following alarms will be provided. a) Higher pressure differential scross the fiEpi filtera. b) Filtration system fan failure. Jakal__Egdiat ion Monitgring to ensure adeguate radiological protection of EOF personnel, the i fcilowing radiation acnitoring aystems will be installed. i

1) Outside Air intake Radiation Monitoring System This system will consist of a GM tube inctvia.i in the

-  f]

outside a - intake duct and connectr5 t.v electronic circuits which will activate both audiM - m.a visual alarms when radia tion levels of outui-A air oxceed a preset trip point. The alarms will be pie"ta in an area whete they can ne heard in normally oc's# WJ areas of the EOF. When the alarm sounds, Pt + Ausly designated personnel will be responsible for m .n ly routing the inlet air thro tgh the emergency air

              < b ;a-up trains (see Section 3.6) .      A low level trip point
'              to indicate malfunctioning or the system will also sound an didra.

t

2) Area Badiation Mcnitors Two wall mounted local radiation monitors will be instal:ed i at opposite ends of the dOF. These monitors will consist of a Gh tubc detector and associated electronics with a range of 0.01 to 100 mt/hr, high and low adjustable trip points, local visual and audible alarms asid a local meter to t

indicate measured radiation levels.

3) lodine Sampling l

The concentration of airbot ne radiciodine during an esorgency will bc determined by use of a portaale low volume Ij3 e air sampler with silver zeolite cartridges (permanently assigned to the EOF) . The cartridJe will te analyzed for (_/ radiciodines by gamma spectrum analysis. Hev. 4, S/El 3-13

3.6.4 O c c u Ea _ _n _t__A _ c_c_o _m _m _o _d _a _t _i _o_n _s Kitchen, sanitary facilities, and medical supplier for minor injuries a re provided for the use of r:0F pet sonnel dur ing normal and accident Conditions. No municipal water supply is available near the EOF; therefore, a well system will be provided with adejuate treatment to make it potable. This well is not within the path wa y of g round wa ter firm from the station and is not anticipated to ever become con t a n. in a t t d . But if an acciden t occurs with tha gt.aut.al te conta mina t e the groundwater, the ca pa bil i t ; lists to s*. ;1e and analyze the well water at the EOF. M__GOM1!E19AI193 Th' s. communicatica system includes priority access voice 2 . n ts- h o t l i n e .;, telephone lines tied th:ough the plant l switchboard, local outside comm e rc ia l lines, VhF and IlliF radio, pagets and an extension of the plant public address system. The combination of these facilities will be used to manage and coordinate on and of f site eaergency response activities and disseminate informatiCn to responsible government agoncie.. The l combination of these facilities forms the redundancy and thus the reliable normal and emergency, primary and backup communiction network. The TSC and Control Room will provide the initial g notif icatica and early recommenda tions to of f site authorities W plior to staffing the EOF. The description of the com mu nica tion tacilities in the EOF are as follows. hM__Td E2 bene l The normal telephone service tot the 60F will use the plant PIivate Automatic Branch Exch.anje (PABX) system and local outside commercial lines. ! Direct Allentown General office branch exchange telephone service l 1s also proviued. J . 7. 2 flot l i ne s Priority access voice communica tions 1 inks with au toma tic sig na li rij is provided at several locations in the EOF. The hotline f acilities have the capa bility for indivilual or l conterence calling hetween the ROF and the followinJ: gl Ecv. 4, S/El 3-14

D- a. Technical Support Center (TSC) d ,3j. b. Contrcl Room (CR)

c. Luzerne County Civil Defense (LCCD) j d. Columbia County Emergency Management Agency (CCEMA)

e. Pennsylvania Energency Management Agency (piM A)

f. Nuclear Regulatory Commission, Emergency Nctifica tion System (EMS) 9 Nuclear Regulatory Commission, Health Physics Network (lip N)

h. Department of Environmental Resources /Dureau of Radiation Protection 3.7.3__EgdJo The EOF has both a four-channel 450 MHz UHF and a two-channel 150 Milz VliF radio system.

The two-charnel VEF radio is contained in a single desktop control ccosole. This system is used as an emergency backup to the telephone system and to communicate with the field monitoring teams and as an off-site pager. The four-channel UHF radio is operated from a single dess top l control console. The Ullf radio will provide primary and backup security, emergency, operational, and maintenance communication links. O 3.7.4_ _ Paging The 150 Milz VHF radio system is equipped with a page encoder which is used to locate key personnel off-site. 3.7.5 Public Address Systeg The public address (PA) system is an extension of the plant PA system. The system shall provide two-way commu nica tions tacilities for speech input at hand-set stations Each station shall be' capable of originating and receiving ccamunications by switching to either a page channel or to one of five non-1 interfering party line channels. 33 7.6 Facsimile A facsimile machine is provided in t t.o EO F. \ 13 o (.) l Rev. 4, 5/81 3-15

_3.a_ p03gg_gURELJ g 3.8.1 PL Cistribution - Normal _ Service The normal electrical service to the EOF will be from the Pennsylvania Power and Light Company distributicn network. The main distribution feeder emanates from the Berwick 66-12 kV substation. The service rating to the EOF is 300 KVA, 480/277 volt, three phase (Be f erence Figure 3.15. 6) . 3.8.2 Emergency _Genelatgr The standby diesel generator is sized for complete operation of the f acility. On loss of utilit y power, automa tic trans f er is made to the standby diesel genera tor which will accept load [ within ten Joconds (Reference Fi .j u r e 3.15.6). 21h12- U DkDt2EEE25dble 292SL E92211 lUEEL The UPS system is completely static design with rectifier, battery and inverter being the main components. The system is sized to carry all critical load and is redundant in design. The critical lead is defined to include computer equipment, security, emergency lighting and telephone systems (Pe ference Figure 3.15.6). 3.9 INSTHUMENTATION nhece required, the EOF utilizes the same tield sensors and signa l conditioning equipment which is proviled to monitor the nuclear steam supply syst. m and the balance of p la n t systems. The quality, accuracy, and reliability of the ECF instrumentation is therefore identical to the field instrumentation used to operate the plant. This approach has been taken ao that people working in ditfetent areas .ill wor k wit h the same data. A detailed description of this instruaentation is provided in Chapter 7.C of the FSAR. The data from these instruments is collected by the Emergency Response Ccmputer System (EPCS) . The EHCS is described in detail in Section 7.0 of this appendix. This system will presen t data to the EOF as described in Section 3.10 of this a ppendix. 3.10 49E LATH ?BRELNThTIDE As required by NUREG-Co96, the EOF wall include human factors engineered man-machine interface capabilities to allow personnel to: gg Hev. 4, 5/81 3-16

 -       o      access environmental conditions

(). o o coordinate radiological sonitoring activities recommend implementation of off-site emergency plans Thu ma n-machine interface in the EOF will be provided by devices tied to the Emergency Response Computer System (ERCS) which is described in Section 7 of this A ppendix. 3.10.1 Eguipment The locatica in the EOF of the equipment described below is shown in Figure 3.15.4, EOF Furniture and Data Displa y Layout. This equipment will be located within the Central of fice Area and in other locations throughout the 80F as required to support the functions being performed at those locations. The ERCS will provide the interface to the following devices: (1) Pvdicated CRTs for the display of information related to the Safety Parameter Display Systou (indicated by "S" in Figure). (2) CRTs for the display of general plant sarety-related data contained in the ERCS for Specific EOF functions (indicated by ' E" in Fig ure) . (~} (3) A printer and/or printer / plotter for the hard copy output of \_/ ERCS data (Not specifically in d ica ted in Figure, but will be provided). 3.10.2 Da ta The data required in the EOF will be ptovided by the Emergency Response Ccaputer System. Da ta required to support the SPDS i tunctions will be included in the common ERCS data boae and will therefore te availabic for display in the EOF. The information d Vdild ble here will be the same that is available in other SPDS locations. Data required for display at the CRTs assigned to specific EOF functions hill be ccntained in the ERCS data base, This will provide, for example, presentation of in plant radiological variables and also, meteorological information. ERCS data is described in Section 8 of this Appendix. 3.11 RECOFDS AND COCUMENTS 3.11.1 Availaule Rocctds an't Document s O) 4 The Eur shall con tain up-to-date records tor use during emergency conditions. These records include: I 1 S/81 Rev. 4, 3-17

o Up-to-date drawings, schematics and diagrams showing current conditions of plant structures and systems. llh o Current plant technical specifications. o Plant Operating Procedures. o Emergency Operating Procedures. o Current Emergency Plans for:

         - Pennsylvania Power & Light Co.
         - Commonwealth of Pennsylvania
         - Luzerne County Civil Defense
         - Columbia County Emergency ManaJesent Agency o     Radiological Records o     o f f-s it e population distribution and evacuation planning.

o off-site Dose Calci 11ation Manual l 2211:2__ EMS 2IdM_UdBadfE2S1_S1sid3 The records listed in Section 3.11.1 sha ll ne updated and managed by the Susqueharitta SES Document Control Centet (CCC) utilizing DCC Administrative Procedures.

   ]:Ad__EEEUE111 During an emergency, eccess to the entire EOF will be limited to only those personnel with proper authorization.      Intrusion detection devices will be located in a nd around the EOF to acnitor the tacility during unoccupied periods.

Jz1]__pASEUE_Anshgthgl_gEgE6Ilggp_EAg11]IX Jellzl__fusetign The Backup EOF p;o vides space and facilities for maintaining the continuity of primary EOF functions, dose projection and senior management dacisica making capability, during emergency conditions that would require EOF personnel to evacuate the primary EOF ot the primary EOF was inaccessible. 2:122$__L953119B The designated location for the dackup EOF is a Conference Room at the PPS L Central Divisiott 3ervice Center ad ministra tion h o f fices a t 344 South Poplar Street, dazleton, PA. This location Eev. 4, S/61 3-18 t

s is 13 air.siles from the Susjuehanna SES (Reference Figure (_) 3.15.7). J,13. 3 Staffing The minimum staffing requirements are those personnel designated as the of f-site emergency organization in Secticn 5.3 of the Emergency Plan. In order to perform the functional requirements sentioned above, this minimum statfing consists of: Recovery Manager, Technical Support Manager, and the Radia tion Support Manager. Other management positions within the off-site emergency organization can perform their f uncticns out of the Allentown Corporate Emergency Control Center at the discretion of the Recovery Manager. The task functions of the minimum staff personnel required to ensure con tinuity of f unctions a t the Backup EOF a re as described in Section 5.3 of the Emergency Plan. Jzl3.4__fEgEisl_LaZggt_Qugsgiptign This approximately 30' by 60' Conference Room can easily be set up in a configuraticn allowin ; easy access and coordination of information necessary to carry on the function of the EOF. Deing located in a main PPSL Service Center provides for ease of access to_ support facilities that may be needed in an emergency O

 \'

situation; this would_ include office equipment and support personnel. Space is available for the sini um PPSL emergency organizatica staft as well as the NBC and other agency staf f that would normally support the activities at the primary EOF. 3.13.5__coggunication The Backup EOF communication system consists cf normal telephone lines capa ble of reaching outside numbers via the Bell Telephone System and also tied into the PPSL Centrex Allentown Exchange System for toll-free calls to all locations within the PP&L Service ARed. Radio communication with the field monitoring teams will be , maintained with portable two-cha nnel 150 mh z VH F radio units. These portable units would also provide a backup reans of commu n ica t ion with the Plant Control 30cm a nd T SC. 2:12rs__pgghyp EOF Data Display A communication link will be established betdeen the EOF building located nearsite and the backup EOF when it is determined that the backup EOF chould be activated. A display . console will be provided in the backup EOF that will be tied to the Emergency Response Computer System. The backup EOF p) (_ will therefore have access to all data CRT displays utilized in the EOF. Rev. 4, S/81 3-19

11klz1- E299ES2 BD$ 999L1929tG The following up-to-date records are maintained at the Central Division Service Center: o Current Emetgency Plans for: Pennsylvania Power and Light Company

             -      Commonwealth of Pennsylvania Luzerne County Civil Defense Columbia County Emergency Management Agency The f ollow ing records will be transported from the primary EOF or the A llentcwn Emergenc y Control Center to the Backup EOF upon activation af this facility:

o Susquehanna SES Oft-Site Doae Calculation Manual o Emergency Plan Implemeting Procedures o Radiological Records o Off-site population distribution and evacuation plannin:) 3.14 INTEBIM EMEHGENCY OPEhATIONS FACILITY Until the Ferranent ECF described above is physically constructed, the Sinulator Butiding will serve as the Interim EOF. The Simulator Building has ill the features described for the permanent EOF excopt the following: lll o Ihe Simulator Building does not provide sufficient shielding to protect against squificant outside radiation. o The Simulator duilding does not ha ve a ventilation system design to p re cl ud e intake of airborne activity. o The Simulator Building radiation moriitors and alarms are not permanently installed. o Voice links to and from the Simulator Build ing are via the notn.al telephone oystem tacked up by portable rtdios. o Data transmission to the Simulator Building is not available. O Dev. 4, 5/81 3-20

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C# Szl__zUNCTIgj S2lal__purigg_gggggensy The operational Support Center is the primary cn-site assembly area for operations support team personnel during an emeriency. This area provides a central Loca tion f or the assembly, accountability, and dispatching'of emergency team perscnnel required tc perform scch functions as: fire fighting, first aid and. rescue, damage ContrCl dnd on-Site radiatiCn monitoring. Eguipment required for these teams to perform their functions, as outlined in Appendix D of the Emergency Plan, will be stored and maintained in this facility. 3 1z121 Nctificati90_9 _UuMEMel_EISDI f During an unosual event, the Emergency Director will activate the OSC with only those teams necessary to handle the emergency condition. Activation of the OSC is at the discretion of the Emergency Director. 321sl:2__ Alert 2_Si te_3mergggcy, Genegal_jmeggency i The OSC is immediately activated under the direction of the OSC

  /~N   Coordinator.      All on-shift duty operations personnel will report

(_) directly to the OSC f or accountability and assignment to team responsibilities at the direction of the OSC Coordinator. The OSC Coordinator will, at all times, be in direct contact with the Emergency Director in order to ensure coordination of emergency conditions with team assignmenta. Salz2__DMElB9_E9D;fB2192LSI 4 During normal plant operations, this arca will servo as an operations staf f work area f or shif t changeover pu rposes as well as shift work assignment area. The Non-Emergency use of the OSC will not degrade its primary purpose as asi Operations Support Center. Sz2__LgCAIIgE The OSC is located in the existing Unit #2 Shift Supervisor's ' Office at the nouth end of the Control Room on EL. 729'-1" of the control structure. The OSC, approximately 340 square teet in size, is asi assembly point for operational support personnct to receive work assignrents. I f i t

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_4_._3___S_T_A_F_F_I_NG t.3.1 During_EgeIgency Operations Support Center staffing is at the direction of the Emergency Director and the Emergency Situation. General staffing dDd responsibilities are outlined in Section 5.2.8 of the Emergency Plan. 313s12 1 Ngtitigation gf_Ugugual_ Event During an unusual e/ent, staffing of the OSC is at the d isc1:etion of the Esergency Director. Eslzlzl__AldIlt_SilS_lB2ESSHEYt_E" emend _EERIGEDSI Upon declaration of an Alert, Site Emergency, or General Emergency, all on-duty shift personnel not assignod direct responsibilities in the Plant Control Room will report to the OSC for accountability and assignment to emergency teams as outlined in Section S.2.8 of the Emergency Plan. 323.1.3 Task Functions ot Eggsggnel The task functions of Emergency Plan versonnel are set forth in Section 5.0 of the Emergency Plan. 9=]1d__ESLIBS_E9D~E29E9"DS1 No specific staff is assigned to this area during non-emergencies. Operaticas staff personnel will use this area as needed. 21S__dhDL1hElkE11 4.4.1 Post-Accident Radiation Doses 2-211:1-_hlk922hle OSC perscnnel shall be protected from radiological hazards, including dirct shire arid airuorne activities f cr postula ted accident conditions to the s ain e degree as Contrcl Room personnel. Applicable criteria are specified in ueberal Design Criterion 19, Standard Review Plan 6.4, and NUREG-0737, Item II.B.2. 4.4.1.2 Pcatulated The radiation dose to personnel occupying the OSC is the same as the Control Room perscnnel. The doses from controlling accidents ggg Bev. 4, 5/81 4-2

i

 -g3  are summariezed in Chapter 15.0 of the Final Safety Analysis

() Report. 3:3213 Radiation MonitcI1DS To ensure adequate radiological protection of the OSC personnel, a permanent commercial grade monitor shall be provided to alarm on high grcss gamma radiation dose rates. Es322__dlA9 The OSC HVAC system, like the TSC HVAC system, is a part of the Control Rocm HVAC system.See Section 2.6.2 f or description of TSC HVAC system. 324.3 _jhigiding Shielding requitement for the OSC is the same as for the control Room f or total dose to occupants from direct shine and airborne. Activity dill not exceed 5 Rem whole body for the duration of the acident. This is in accordance with General Design Criterion 19, T USNRC Standard Review Plan 6.4, and NUREG-0737, Item II.B.2. ('J E- Duration of accupancy and method of analysis is the same as that used for the Control Room. 4.4.4 Occupant Acccamodations No toilet f acilities are provided in the OSC. Use of the Plant's existing facilities at grade level of the control structure for washing and toilet acccmmoda tions is planned. 3: 5 - C 9EEUEIGhllDES The OSC communication system includes priority access voice links-hotlines, the t lant public address system and telephone lines tied through the plant swi tchboa rd. The ccmmunication system will provide a direct voice link between the OSC and the TSC or Control Room and capaDility to reach on- and off-site locations. 3252 1__Iglgghgne The normal telephone service for the OSC will use the plant Private Automatic Branch Eschanje (PABX) system. The PABX han the capability to reach on- and off-site locations. O l Bev. 4, 5/81 4-1 i

21 51 1- 89%)iggy Priority access voice communication links with automatic signaling is provided in the OSC. The OSC hotline has the Capability of Calling the TSC Or the Control roc 3. 4_. 5. 3 Public Address Sygtem The public address (P A) system is an extension cf the plant PA system. The system shall provide two-way cammunication facilities for speech input at hand-set staticns. Each station shall be capable of originating and receiving communications by switching to either a page channel or to one of five non-interfering party line channels. O O l Rev. 4, 5/81 4-4

ho -EH 211_ RARA 5KIER_HsRLAI_EISII5 g/ The Safety Parameter Display System will be developed utilizing the criteria _ contained in NUREG-0696 as applied to a General Electric boiling watet reactor. This system will provide a display of a minimum set of parameters which will indicate the overall safety status of the plant. A BWR nuclear plant is defined to be in a safe state when the following ccnditions are satis fied:

1) The core is adequately cooled.

2) Beactivity is controlled.

3) Heat sinks and the heat' transfer path from core ard containment to heat sinks are functicning properly.

4) Integrity of f uel, reactor coolant systems, and containment are maintained.

5) In-plant and ef fluent radiation levels are within specified limits.

The SPDS will assist the operators in determining the state of the plant safety rapidly and accurately, even if a plant event is not immediately understood. () The SPD3 will focus on the plant symptom based emergency procedure. The system will track and display the parameters which serve as symptoms for en try to the emergency procedures. This provides an integrated approach to emergency response improvements. The SPDS will be able to trend measured variables, which will facilitate the use of the emergency procedures. The operator will be able to focus attention on the plant instead of on plotting a nd trending variables. Measured variables will be validated by several sethods. SPDS f unctious will be available in the Control Room, the TSC, the EoP, and the Backup EOP. The man-machine interface required for the operation of f.he SPDS will be provided by the Emergency Response Ccaputer System, ERCS (Section 7.0 of this Appendix) . The ERCS will be designed with suf ficient capacity and flexibility to allow for future SPDS changes and modifications as they become necessary. A O Rev. 4, 5/81 5-1

1,0__3pCLEAE_DAIA LINK

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 \-   A Nuclear Data Link (NDL) will be provided which will transmit information to the NRC operations center to aid the NRC in its role of providing advice and support during energencies.

Data required by the ERCS data acquisition system will be formatted for transmission. Specific data to be transmitted has yet to be defined, but it is assumed that for the most part, needed data will cose from Reg. Guide 1.97. The communications protocol, error detectior: and correction for transmission of data also has yet to be defined, however, data will be transmitted once per minute as specified. A review of the hardware required for the NDL will be performed when a specification is issued addressing the subject. O C:') Rev. 4, 5/81 6-1 l

1 9- EREB9 ERG 1 BED 29BBB CDB2 BILE G1ST1B 1LECSL - (_)3 The Emergency Response Compuer System (ERCS) will provide the acquisition, preparation, and display of Unit 1, Unit 2, and common plant data for the Emergrency Response Facilities (ERP) as indicated in the NUREG-0696 guidelines. These facillites include the Technica). Support Center ( TS C) , ths Emergency Operations Facility ( EOF) , the Backup EOF, the Safety Parameter Display System (SP ES) , and the Nuclear Da ta Link (N DL) . The overall design of the PPF,L ERCS is directed toward providing both a dedicated system for the operation of a seismic SPDS, and an integra ted system which will tie together the opera tions of the TSC, EOF, the non-seismic SPDS located in the Control Room, ISC ar.d EOF, and the NDL. During the time period required for design, development, and installaticn of the ERCS, ass interim ERCS will he provided utilizing the Plant Ccaputer System. The conceptual design of both the ultima te ERCS and the interim ERCS is descrioed below. The ERCS description includes diagrams to illustra te the design. Figure 7.1 indicates the basic logic flow of the ERCS, Figure 7.2 , indica tes the ultimate EHCS configuration, and Figure 7.3 indicates the interim ERCS configuration, U t In the design and development phases o f the ERCS Project, examination of human factors engineering criteria and system integration criteria may necessitate changes and improvements to the original design. Therefore, although the design description ccntained herein will serve an a guide f or continuing project i work, the description is not meant to be restrictive. Flexibility must be maintained to ensure a system responsive to the needs cf the people using it. lat- 96TInh1R REGS The ultimate Emergency Respon.ie Computer System will consist of independent computer systems, referred to in this sec tion an, (1) Integrated Computer System and, (2) seismic Sa f ety Parameter Display System. As indicated in Fiqure 7.2, ERCS Configuration, the seismic SPDS will have a dritcated computer which will perform prccessing specificall) 'or the seiamic SPDS in the Control Roc.a. Again Leferring to ?i rre 7.3, the Integra ted Compu ter System will utilize a common computer to perform the SPDS, TSC, d0t, Backup EOF, and NDL functions. 22121_ 1Dl"dId1Ed 90EfS1SI_ Eld 193 In addition to satisfying the seismic SPDS function, the ERCS p must meet functional requirements to ,tcquire data from the field, V to process the data, and to output the data for each of the following: Rev. 4, S/81 7-1

o Safety Parameter Display System o 0 Technical support Center Emergency Operations Facility lll c Backup EOF o Nuclear Data Link To achieve these f unctional requirements, and tc remain consistent with the design intentions of NUREG-0696, the overall Integrated Computer System design philosoph y ovcives f rom the following considerations: (1) The data regt ed for all Emergency Response Facilities is essentially the same. People working in different areas will deal with that data and sometimes communicate with one a nother about the same information. It is desirable that the data come from a ammon source and that no confusion be allowed to develop because of differences in measurement or data acquisitiCn. (2) Just as there should be a single source of data, there enould be a single source 01 results or interpretation of that data. The calculation of a specific variable, even if required in several areas of the Emergency Response facilitry, should only be ccmpu ted in one place and delivered to all areau requiring it. (3) To enhance system availability and tc minimize hardware and software problems, fixes, and associated verification, it is highly desirable to centralize computer processing functions. (4) Cue to the high processing speeds available with toda y's real-time p rocess con t rol com pu te rs, large quantities of data can be presented to users without sacrificing response time. This affords the capability to centralize the several, but common f unctions required of the ERCS. Therefore, a centralized data processing schome serving both plant units is being proposed for implementation of the ERCS whereby a central cceputer, loca ted in the Zmergency Operations Facilities, will handle data processinj associated with all systems excluding the seismic SPDS. Figure 7.2 illastrates this central prccessing concept. The centralized computer system, called the Integrated Computer System, can be categorized into three functional divisions: (1) Ca ta Acquisition (2) Cata Preparation ( 3) Da ta Presentation O Rev. 4, 5/01 7-2

221tl21__ Data Acguisition (n ) Data acquired by the Integrated Computer System will be output to the TSC, EOF, Backup EOF, and SPDS portions of the ERC5. The specific data to be input is detailed in Section 8.0 of this submittal. The pticary source of data for the Integrated Computer system cill come from plant process, meteorological, and radiological equipment. Many of the signals coming from this equipment will be input to common field termination units withia the control structure. These termination urits will be located in a secure area and isolation will be appl ed to all sa fety-rela ted signals. The data acquisition hardware will be designed to obtain all data required by the Integrated Computer system. The sampling frequency chosen will be such that the da ta sampled will be a true representation of the actual processes being monitored. In 4 addition, high speed data communica tin will be provided between the EOF. data acquisition hardware and the centralized computer at the Thus, high data throughput will be achieved f;om da ta scan I to data variables, processing, enabling up-to-date monitoring of syatem  ! l A modular design will be applied to the data ac]uisition system hardware to both acccomodate case of expansion and to ensure t hat the loss of a functional module will not sever the capability to

 ,O         continue tc perform data scan.

Parameters with redundant sensor and status inputs will be monitored on separate input modules to reduce loss of scan of those parameters. User interaction with the system will also be determined by the 1

;          software.          The data system may be used for reviewing an accident i

sequence, to help determine appropriate actions, to help evaluate i

!          the extent of damage, and to help determine the plant stat'as j

during recovery. The I/O proc 7sses for the TSC and the EOF will be executed independently, and transfers between active memory l and archival storage will be made without interrupting the data acquisition and display systems. The software will provide some additional functions such as data preparation for transmittal to the NRC and built-in sof tware protection features against unauthorized data processing, 1 storage, and output. , w 7.1.1. 2 Data Prepara tion once_the data has been acquired, it is prepa red and then sent out for presentation to the Control Room, TSC, EOF, Backup EOP, and , the NBC. Eata from the data acquisition system will be stored in short-term and/or long-term storage, and processed before it is i .rs presented to the varicus facilities. 1 k_ b Rev. 4, S/El 7-3 2

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Equipment for the ERCS will neet size requirements specified in NUSEG-0696, will not interfere with Control Room or TSC operational functions, and will incorporate human factors lll engineering criteria. Existing space and power capacity for the Control Roca and the TSC facilities are limited, and preclude the possibility of locating a large, integrated computer system in the control structure. Thus, the EOF will h ouse the computer and peripheral equiptent associated with the storage and processing of data for use by the Integrated Computer System. This is consistent with the primary function of the EOF as stipulated in NUREG-0696, i.e., that the LOF will ba ve tacilities for the management of overall licensee emergency response. The system to manage the data will be designed such that input / output processing overhead will be minimized. In addition to providing for real-time data s to ra g e, the system will contain sufficient storage capacity to accommodato a t least two hours of p r e-e v e n t data and 12 hours of post-event data, at least two weeks of a dditional post-even t da ta, a rch ival data s to ra g e , and some additional system requirements. The type of data to be stored and processed is described in Section 8.0. System and a pplica tion sof t ware will be developcd to provide tor the following minimum f unc tion s: Da ta manipula tion and storage, data display, programmer input /outptat, devico driving, system security, and NDL handshaking. A data case wil1 include different forms of data such a s raw da ta, data ccnverted to g engineering units, data validated on a real-time basis, and W various types of calcualted da ta. The data will include information to help determine ma jnitude and trends or time derivatives. The system will determine the data to be diaplayed, and the output format that will be available. ihe input / output will be designed tc allow tasks to be performed in a timely manner, to minimize Icss of information during transient conditions, and to satisiy human f actors engineering Critaria. Trenis and time history information will be availaole for display. 211.3 aata crusentation The general purpose of the ERCS is to provide functions for the plant that will help suEport pla n t o pe ra t ion s during an emergency, relieve some of the reactor operator's peripheral duties not directly eclated to reactor system ma nipulations, and prevent conjestion in the Control Room. Section 8.0 describes the ERCS information that will be presented, which generally includes pla n t s ys tem s ' variables, in plant va r iaules , meteorological inf ormation, and radiological information. Integrated Computer System da ta will be prt se n tE d using output devices 4 1 the Control Room, TSC, EOF, and Backup EOF (when necessary) . These output devices will, as a minimum, consist of color CRTs with limited graphicu capabilities to be located in g aus. 4, 5/61 1-4

all of the above places, and printers and/or printer / plotters to (~) \~/ be located in the TSC and EOF. The CRTs located in the EOF will function independently from those in the TSC. The computer, located in the EO F , will process the data for transmission to the output devices. Information desired by the NRC will be sent via the NDL as specified by the NRC. Data will be presented in formats which will be easy to understand and interpret. Unsuccessf ully valida ted variabl es will be presented with an indication of that condition. Alarms will be represented in a f ashion simila r to the plant process computer by using similar color-coding techniques. Output formats will be designed according to human factors engineering criteria, and will include pattern and coding tcchniques. Display tasks will be designed so they are easy to perform and understa;.d. That is, relatively simple keystroke sequences will Cause display of critical information, such as the current status of important plant parameters.

• The purpose of the SPDS is to provide a continuous indication of the safety status of the plant. SPDS data will be presented as described above, and will also include special features as specified by NUhEG-0696. Its function is to aid the operator in rapidly detecting abnormal operating conditions, by enabling the operator to achieve a timely status assessment without surveying

g. the entire Control Room. The SPDS will function during ali

( design basis events. Therefore, parts of the system will be seismic 411y qualified. The seismic portion of the SpDS is described in Section 7.1.2. The SpuS display will be responsive to tra nsient conditions and will be sufficient to indicate the plant status. For individual modes of plant operation, a single primary dic play f orma t will be designed using human factors engineering criteria. The primary display will give an overall system sta tus and will include as a minimum tue following basic safety parameters: Reactivity control, reactor core cooling and heat remova l f.rca prima ry system, reactor coolant system integrity, radioactivity control, and containment integrity. An audible notif ica tion will be included in the contrcl Room to alert personnel of an unsafe operating condition. Any display loca ted in the Control Room sill be of such size and location as to be compatible with the existing space. Human f actors engineering criteria will be ased to determine how to set up a display that. is easily accessible dnd VisiblG. 712 2 Seismic SPDS As indicated in figure 7.2, the seismic Safety Pa rameter Display Syster functions independently of the Integrated Computer System (' dnd Will oFerate if the conventional SPDS f ails to function properly. This seismic system will be able to funct on during Bev. 4, 5/81 7-5 l l 9

dnd following all design basis events for the plant. It will include seismically qualified sensors and signals, da ta acquisition equipment, data preparation equipment, and a data & W display device. Separate seismic SPDS systems will be provided for Unit 1 and Unit 2. Black and white CRTs have been seismically qualified, and will be specified as the data display device. Should seismically qualified color CRTs become availalbe, the black and white CRTs would be replaced with colored CRTs. All equipment for the seismic SPDS will be located within the control structure. 2mlz221__pgtg_Agcgigitip3 j Data acquired for the seismic SPDS will consist of safety rela ted parameters and, therefore, isola tion will be provided for that data. Also, because the seismic SPDS is required to function during and following all design basis events for the plant, all data acquisitio.- equipment will be seismically qualified. Dccause the seismic SPDS will contain a small computer dedicated to performing data acquisition, da ta processing, and data display functions solely for the seismic SPDS, data scan and monitoring of the saf ety para meters will be independently achieved. Because of the importance of the display of seismic SPDS safety O patameters, the data acquisition hardware will te designed to dchieve maximum scanning co:nmtanica tion availability. Expandability cLiteria will also be factored into the data dCguisition design. 2 1 1-2__Dgta_grupgratign once the data has been acquired, it is prepa red and then output to the seismic SPDS display. Data ttom the seismic data dCguisition system Will be stored in 40mOry dnd processed before it is presented to personnel. The type of data to be stored is described in Sect ion 8.0. Software will be d e ve loped to provi.do for data icquisition, preparation, and presentation. The da ta base will include raw data covetted to engineering uni.ts, validated data, and CdlCulated data, which will be used for trends cr time derivatives. 22122 3__ Data _Etusustat19a The seismic SPuS display will be responsive to t ra nsien t conditions and will be sufficient to indicate the plant status. g A simple primary display will be designed, using human factors W Rev. 4, 5/81 7-6

i engineering critoria, to give an overall system status, and will

  '(,,)     include as a minimum the following parameters:               Reactivity control, reactor core cooling and heat removal from primary                         ,

system, reactor coolant system integrity, radioactivity control and containment integrity. The display will be easily accessible dnd visible. An audible notification will be included in the Control Roca to alert personnel of ad unsafe operating condition. 222xl__Ava114hilitz A detailed availability determination has not been performed for the EHCS. From previous experience, it is known tha t systems of this stra'.ght forward design should be able to achieve very high dvailability in the 99% area above cold shutdow n, and 80% area during cold shutdown. During the course of the continuing design  ; and implenetation, aVdilability Will remain one of the primary goals. The desiga will be testeo analytically with availability , calculations an-i modified to improve availability where that is  ! possible. The availablIity of the system will also be enhanced by a comprehensive maintenance program and with built-in f acilities to aid in'that maintenance activity. In addition to achieving high availability through a sound desigr. and through selecting quality I equipment, availability will no further enhanced by minimizing the mean time to repair.

      )

1 22]__ INTERIM EEqS As noted fermerly, at some point in time, a n interim system will te needed to perform the ERCS functions during the time required J for development and installation of the ultimate ERCS (Section l 7.1) . The Plant computer System will be utilized to provide the EhCS Lunctions, as indicated in the configuraticn diagram, Figure 7.3. Ho w e ver , the seismic SPDS util function independently of the plant Computer System, and will have its own da ta dCquisition, preparation, and display systems. In other words, i the seismic SPDS will function as a part of both the interim and the ultima te ERCS configuration. l 222 1 u t i lladiinn_9 f _ the_ flan.t_Cgges t gr_sygie m i The Plant Computer System (PCS) lends itself to utilization in the interim r:RCS configuration f or the following reasons:

o it is a recent-generation plant process computer. '

o It contains spare memory needed to support ERCS. I o It contains excess computational capacity also nouded to support  ! ERCS. [ o It contains CRT graphic and trending ca pabilities, o It provides for historical data recording and retrieval. Rev. 4,

                 . S/81                                  7-7

o It has flexibility to permit inter f a cing to additio nal I/O equipment. o It has a prove n high degr ee o f reliability. lll o It is currently scanning and processing much of the data needed by ERCS. o It is located in a secure area within the control structure. The SPDS functions in the interim ERCS configuration will be provided for by the Seismic SPDS, and no provision will be made for the Nuclear Data Link. The Plant Computer System (PCS) will serve all the other ERCS functions, but with reduced capability, such as: (1) System response times for outputting CRT displays following a display roguest may be icnger in duration than those in the ulthmate ERCS configuration. (2) A variable to be trended on a P la n t Computer System display must be i dentified on a pre-defined display format. There is no d ynamic assignment of a variable for trending. (3) In the interim system, there will be one area in the EOF for viewing displays, whereas in the ultimate ERCS configuration there will be several a reas containing CRTs. 2222121__ Ds.t.g_asguisi t igy llI The data acquisition currently employml by the Plant computer System (PCS)contains many parameters required by the ERF. These pardmeters tre defined in Section 8.0. The EFF data acquired by the PCB undergoes the normal validity and error checking applied to all PCS inputc. Isolation will be appliod tc all safety-relate d signa ls. 2 21122__2did_fL9Eaggtigg Data for the ERCS will be processed and prepared in accordance with the lojistical and proven techniques currently used in the PCS. Display and logging formats needed by the ERF will be generated and stored within the Plant Computer Syatem, using the existing format generators in the PCS. The system to manage the data vill be designed such that input / output processing overhead will be minimized. In addition to providing for real-time data storage, the system contains sufficient storage capacit y to handle pre-event data, post-event data, and archival data storage. Proven system and alplication sof tvare has been developed w hic h performs at least the following functions: Da ta manipula tion and storage, data display, programmer input / output, device driving, llh Rev. 4, 5/81 7-d

c and system security. The data base includes different forms of (3) data such as raw data, data converted to engineering units, data validated en a real-time basis, and various types of calculated data. The data includes informa tion to help determine magnitudes and trends or time derivatives. The system determines the data tha t is displayed and the available cutput format. User interaction with the system will also be determined by the software. The data system may be used for reviewing an accident sequence. Although identical, the I/O processes for data display in the TSC will function independently of those for EOF. 4 2:2212]__Edld_EEE39B131i2D The TSC will contain a display console tied to the Plant Computer System which will provide for display functions in the TSC. Procedures and methods f or keyboard call-up and error indication of TSC functions will be identical to those in use on the Plant Computer System. An interim SPDS CRT (sepa ra t e from the PCS console) will be provided in the TSC but will be tied to the seismic SPDS, which is independent of,the Plant Computer System. The EOF will contain a display console tied to the Plant Computer System which will provide for display functions in the EOF. The ((7 J display consolo in the EOF will he f unctionally identical to that in the TSC, and therefore, EOF I/O request procedures will be ) identical to those of the PCS. An interim SPDS CRT will not be provided in the EOF. There are currently no plans to provide a Nuclear Data Link , Facility in the interim ERCS. It is assumed that the ultimate EBCS (which will contain an NDL) will be oparational before all j interface requirements for the NDL are finalized. Data will be presented in formats which will be easy to understand and interpret. Unauccessfully validated variables will ce presented. with an indica tion of that condition. Alarms will be represented in a fashion aimilar to the plant process computer by using similar color-coding techniques. Output ! formats will be designed according to human factors engineering criteria, and will include pa ttern and coding techniques. 7.2.2 Seismic SPDS The seismic Sa fety Parameter Displa y System will sa tisf y the SPDS l requirements on an interim basis and will serve to meet the i seismic SPES requirements on the ultimate ERCS. A description of l this seismic system is given in Section 7.1.2. The interim ERCS () configuration will contain a CRT in the TSC which will have a l l l l Rev. 4, 5/01 7-9 1

                             -             -     _                 ,  _ _   -. _- 1

direct connection to the seismic data prepa ra tica equipmen t in the Centrol Room for SPDS information. 2z2s]_ Ava ila bility Studies have been conducted by PPSL to determine the feasibility of using the Plant Computer System to fulfill the role of the TSC dDd EOF data system on an interim basis. The purpose for this approach is to allow PPSL additional time beyond the NR equired in-service dates to procute and install a fully integrateu ERCS. System availability of 98% is attainable provided sof tware development is conducted on the Unit 2 system. Once fuel load on Unit 2 begins and until the full ERCS is installed, software development could reduce availability to 97 4. These figures are based on a nalytical calculations and represent the minimum availability figures thdt Cdn be g ua ra n teed . O l O Bev. 4, S/81 7-10

DATA ACQUISITION y HISTORICAL DATA r RECORDING PREPARATION AND RITRIEVAL 4 O e u m TSC/ EOF SPDS

                                                ---+           NDL SYSTEM 1

1 l l

Rev. 4, 5/81

SUSQUEHANNA STEAN ELECTRIC STATION UNITS I AND 2 EMERGENCY PLAN ERCS FUNCTIONAL OVERVIEW FIGURE 7.1

CONTROL ROOM TSC

         /

NON-SAFETY TSC q g SPOS SPOS

          =        SYSTEM                               FUNCil0NAL OlSPLAYS
          $        SIGNALS DISPLAYS               OlSPLAYS I

y SAFETY SAFETY

          "   GRADE     SYSTEM
          = ISOL ATION SIGNALS
          $                         SPOS

( P SEISMIC SPOS T0 csCKUP EOF CONTROL TO NRC l STRUCTURE (~'; \ / un DATA ACQUISITION, STORAGE AND PROCESSING NOL EOF SPOS FUNCTIONAL OlSPLAYS DISPLAYS EOF BUILDING Rev. 4, 5/81 SUSQUEHANNA STEAM ELECTRIC STAil0N UNITS 1 AND 2

 ,s                                                                             EMERGENCY PLAN b

ERCS CONFIGURATION FIGURE 7.2

CONTROL ROOu TSC

 )

TEuPORARY SEISNIC ggg INTERlu SPOS DISPLAY f SIGNALS

   ,    FOR SPOS        $pgs UAIA E                  SElsult
   $                  OlSPLAY 5

SIGNALS FOR PLANT CCEPUTER k PLANT CONSOLE DISPLAY CnuPUTER FOR SYSTEM TSC FUNCil0NS O U CONTROL STRUCTURE 1/ CONSOLE DISPLAY { FOR EOF FUNCTIONS EOF Bull 0 LNG Rev. 4, 5/81 SUSQUEHANNA STEAN ELECTRIC STATION UNITS I AND 2 p v EMERGENCY PLAN l l 1 INTERIM ERCS FIGURE 7.3

8.0 EMERGENCY FACILITIES INTERFACE . ,~ (j The emergency f acilities interface with on- a nd of f-site i locations through data presentation and oral communication systems. These systess include sultiple chahnels and redundanciea which insure the flow of vital information throughout the course of an emergency. B11-_DhTA The paragraphs in this section describe the data set to be i included in the ultimate Emergency Response Computer System i (ERCS) as well as the interim ERCS. 8.1.1 Data in the Ultimate EHCS The ultimate ERCS consists of the Integrated Ccaputer Sfstem with its central processing f acility located at the EO F, and the

,              seismic SPES loca ted within the pla n t.               The pa ragra phs in this subsection describe the data set to be included in these i               components of the ultimate ERCS.

0 lzl21__Dd14_Elg vidgj_hy_t h g_1n t ggggigd_cegegig p_pyg gem i The. integrated portion of the EdCS is designed to acquire and process all of the data needed by the SPDS, TSC, EO F, Backup EOF, and NDL. This computer nystem will provide access to accurate O, and reliable information sufficient to: o determine plant steady-state operating ccnditions prior to the accident, o determine transient conditions producing the event, o determine plant aystems d ynamic tehavior throughout the course of the accident, o assess environmental conditions, o allcw coordination of radiological monitcring activities, o aid in making recommendations for implementing off-site emergency plans, o alled evaluation of the magnitude and ef f ects of actual or potential radicactive releases from the plant, and , o determine off-site dose projections. In order to accomplish the above functions, the data provided will consist of: o plant systems variables, j o in-plant radiological vriables, o meteorological inf orma tion, and o of f-site radiological information

.All of this data will be brought to the EOF buildinJ where the j()

l main this TSC, processing function of the integrated ERCS is loca ted. From point, the data sill be made available for display in the EOF, Dackup EOF, and the NaC Operations Center via the NDL. Rev. 4, 5/81 8-1

The appropriate SPDS dat a vill also be made available for display on SPDS display devices located in the Control Room, TSC, and E0P. g The minimum da ta set tha t will be available includes the following: o Type A, B, C, D, and E variables specified in Regulatory Guide 1.97. See Section 8.1.1.3 for exception. o Meteorological variables specified in Regula tory G uide 1.23, and in NUREG-0654, Revision 1, Appendix 2. See Section 8.1.1.3 fot exceptions. o The SPDS safety parameter set primary variables specified below and in Table 8-1. h0TE: When proposed Reg. Guide 1.23, aev. 1 and aeg. Guide 1.97, Rev. 2 ate finalized, PL will review these locuments and make final commitments to their data requirements. The Susquehanna SES emetgency procedures were developed flom the BWR Emergency Procedure Guidelines (EPG 's) . The EPG's were developed by GE and D 's R O nnet 's Group to comply with Task Action Plan Item I.C.1 item 3 as clarified b / NilhEG- 07 3 7. The Owner'n Group pertormed a comprehensive utudy to identity a minimum set of EPG's which provide coverage of plant satety functions and FSAR Chapter 15 events. found them acceptable forThe trialNRC has evaluated the dPG's and implementation. Table 8-1 presents a list of parameters which have been derived from the plant emergency procedures and will form the safety parameter set for the SPES. Where available, in ut.ts will be taken from redundant sensors, especially for SPDS primary variables. This will allow validatiori of critical parameters on a rea l-t ime ba sis. The accuracy o f the data acquired will be consiatent with acetiracy needed to perform tha various f unctions listed above. The time resolution of eacn sensor signal will dcpend on the potential transient behavior of the variable being measured, and the scan rate for each variable will be determined accordingly. One sample per second will be the fa s tes t that any given variable will be scanned. All Signal interfaces to safety systems will utilize isolation devices to prevent Interference, degradation, or damage to any element of those safety systems as specified in 10 CF3 50 General Desig n Criteria 22, 23, and 24, and in IEEE Standard 279-1971 Sec. 4.7, " Control and Protection System Interaction." Data displayed 1: the ISC, EOF, and Backup EOF need not meet saf ety 9tade or Class IE requirements. Display of Reg. Gu id e 1.97 date need not meet Reg. Guide 1.97 criteria for display of these varia bles in the Control Room. The sensors and signal conditioners will be desig ted and qu$litic d to meet Class IE ll) Rev. 4, S/ 81 8-2

l ('S standards for those SPDS parameters that are also used by safety (,) systems. Also, sensors and signal conditioners for those SPDS parameters identical to the parameters specified in Reg. Guide 1.97 will be des'gned and qualified to the criteria stated in Beg. Guide 1.97 Most of the data signals will be provided in the Control Room, upper rela y room, and lower relay room. Some data, such as the radiation data at plant release points and asppression pool temperature, will be obtained from micrcprocessor based monitoring systems. These microprocessors contain firmware consisting of programmable read only memory which cannot be altered by software. E21zl22 Data _EIovided_by_the Seismic _SEDE The seismic SPDS computer system, described in Section 7.1.2, will acquire and process the prima ry SPDS va riables f rom the parameter set specified in Section 8.1.1.1. All other criteria for the SPDS data mentioned in Section 8.1.1.1 will also be met by the seismic SPDS. E21x1sl__patg_g3cegligng_ig_the_Ultimatg_EECS f () All of the data mentioned in Section 8.1.1.1 will be monitored by the ultimate ERCS, except to the extent that PPSL can justify to the NBC tnat certain parameters need not be monitored, or certain ranges need not be met. These matters will be dealt with when PP&L f ormally responds to the NRC on Reg. Guide 1.97, and Reg. Guide 1.23, and NUREG-0654. For example, BWR ccre thermocouples are not a part of the present GE BWR design, and justification for their deletion must be supplied by GE. 321z2__Date_in_1he_Intsria_EECs The interim ERCS will consist of the seismic SPE discussed previously and the existing Plant Computer System (PCS). Refer to Section 7.2 for a further description of the interim ERCS. The data to be monitored b'y the interim ERCS will consist of the primary SPDS variables (S ec t ion 8.1.1.1) monitored by the seismic SPDS to be installed, and the other data of Section 8.1.1.1 which is already monitored by *he existing PCS. The method of implementing the interim ERCS is cost-effective, but results in some of the parameters specified in Sec tion 8.1.1.1 no t being monitored by at least one component of the interie ERCS. These paraceters are listed in Table 8-2'. Some of the Reg. Guide 1.97 parameters monitored in the interim system will not meet the i apecified ranges until such time as the Reg Guide 1.97 guidelines are Completely met and/or variances are justified to the NRC. O V sev. 4, 5/81 8-3

E1L._Eb1h_1Rh M LEE 10E ERCS data and telecommunication voice links will be transmitted from the main plant to the EOF by way of an underground cable system. 8.3 COMMUNICAIJON! 8.3.1 Telephgne The normal telephone system for the TSC, EOF and Control Room will be part of two Plant Private Automatic Branch Exchange (PABX) systems. The PABX system utilizes Digital Model 1201 and Model 1202 communication units with a ccabined capability of approximately 1,200 lines. The PABX is capable of originating and receiving communications plus conference calling. Power supply to these systems consists of inde penden t chargers and batteries with the capabilit y of operating both telephone systems for approximately eight hours after loss of normal AC supply. E21 2 Hotlines Priority accessvoice communication (hotlines) links are used extensively between the TSC, EOF, OSC, Control Room, NRC and designated Federal, State and local emergency response networks. Signaling is accomplished both a utomatically and selectively. The communication path is through direct point-to point ties. 82 3.3 . Rad ig a.3.J21__ygF Rgaig_ system A VHF radic syr. tem operating in the 150 MHz band provides communication to and around the olant. This system provides communication between the ISC, Control Room, EOF, mobile and portable units operating within a ten-mile radius of the plant and provides emergency communica tions to the PPSL General Office Building in Allentown, PA. Paing is also l accomplished through the VHF radio system. The entire system (repeaters, control stations, mobiles and portables) operate with selectivity in either a digital voice protection or clear voice mode. O Rev. 4, S/81 8-4

All control stations, mobiles and portables are capable of  : (_ _ ') operating through repeaters or, in the event of a repeater

 \/        f ailure, are capable of repeater talk-around.
                                                                                                ?

323.3.2 UB{_padio Sys}en A UHF radio system operating in the 450 MHz Land provides a i communication acans for on- and near-aite activities. The UHF radio is a four-channel network used f or primary and ' backup security, operational, maintenance and emergency plan activities. The control consoles are located in the TSC, Controi Room, EOF, Security Control Center, Alternate Security Control Center, North and South Gatehouses, Pennsylvania State Police Barra cks (Shickshinny) and addi.ional mobile and portable units.

         ; Paging is also accomplished through the UHF radio system.

8 3 4__fublic Address _!ystem The Plant Public Address (PA) system services the EOF, TSC, OSC and Control Room. This systen provides two-way communication facilities for speech input at hand-set stations. Each station is capable of originating and receiving connunication by switching to either a page channel or to one of five non-interfering party-line channels. O p.4 R _E L A T I_VE_ LOC AT IOF S  ; For an overview of the location of each Emergency Response l Facility relative to the Susquehanna Steam Electric Station, see Figure 8.4.1. Rev. 4, S/81 8-5

                  =_-          .                               -

I IABLE 8-1 () SI2s sargII_gagangIgg_gg; i i EfRA5]TER MEASUBED VARIABLg Cote Cooling Reactor Water Level Puel Integrity Off gas Pretreatment Radiation Level Reactivity SBM Log Count Rate Reactor Coolant System Reactor Pressure Integrity Drywell Pressure Drywell Sump Collection Rate RPV Isolation Safety Relief Valve Position Containment Integrity Drywell Pressure Containment Isolation Valve i Positicn Containment Hydrogen Concen-tra tion

   /~\)
   \'/                                            Containment Oxygen Concentrati ?

Suppression Pool Temperature Suppression Pool Level Drytell Temperature Radioactivty Effluent Radiatico Level at Planned to Environment Release Points. i i Rev. 4, S/81

IARLI_3:2 5 EA EAD E T E S!_LOI_u931I9EIR_HI_l!IE!I5_IE C S thBhBEIER *

• RADI0 ACTIVITY CONCENTRATION OR RADIATION LEVEL IN CIRCULATING PRIMARY COOLANT
• BWH CORE THERMOCOUPLES
• MAIN STE AMLINE ISCLATION .V ALVES LEAKAGE CONTROL SYSTEM PRESSURE
• HPCI FLOW
• CORE SPRAY SYSTEM FLOW t
• SLCS PLOW
• SLC S STO R AG E T A N K LEVEL

;

• R11R SERVICE WATER FIOW
• EMERGCHCY SERVICE WATER FLOW O + SPRAY POND POOL 310W
• SPRAY POND TEMPERATURE
• llIGH RADI0 ACTIVITY LIQUID TANK LEVELS
• EMERGENCY VENTILATICN DAMPER POSITION
• liYDRAULIC POWER
• PNEUMATIC POWER
• PRIMARY CONTAINMENT ARE A R ADIATIC N-!!IGil R ANG E
• RADIATION EXPOSURE METERS (CONTINUOUS INDICATION AT FIXLD LOCATIONS) 4 O

1

Rev. 4, 5/81 1

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I NO SC ALE hjMN,"a'J$lTw... O - INTERIM E0F 1 o' i W 2 A - TECHNICAL SUPPORT CENTER / INTERIM TECHNICAL SUPPORT CENTER O- EMERGENCY OPERATIONS FACILITY i g Q-OPERATIONALSUPPORTCENTER I 00

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so l I 44 3 e-yh*' O' l l . v no gp Rev. 4, .i/81 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 5

• g EMERGENCY PLAN Q'. E RELATIVE LOCATIONS 0F THE s

EMERGENCY RESPONSE FACillTIES ' FIGURE 8.4.1

        .     .           .       -       -        . .--      -=      --      - . -  -

t I 9.0 DESIGN, DEVELOPMENT, QUALIFICATION AND INSTALLATION

  ,                     IEEIIJCATION fj0G3Agg____________________________
    )

As required by Section 9.0 of final JUREG-0696, "The SPDS, TSC, EOF and NDL design, development, qualification and installation shall be independently varified by qualified personnel other than

      ~
,         the original designers and developers."        This EUREG-0696-requirement is interpreted to mean that quality plans to verif y that items important to safety and/or reliability be established development of the above energency response systems; verify the qualification of designated systems or structures and/or provide a testing prog ram to validate designated systems and institute an            '

inspection program to assure.the systems have been installed in accordance with the design documents. The quality plans for each of the emergency response systems are summarized as folicws: 9.l_ TECHNICAL SUpp0RT_CENTEE_jTSCL PPGL contractual documents for the TSC will include a quality plan addressing the requirements to verify and validate the design of the TSC and the qualification and installation of designated systems within the TSC. To support these primary verification and validation activities, the quality plan will O include organizational interface control, document control, non-conformance control and audit /surveilla nce activities. 922__jMERG ENCY OP ER AT IONS FAC2LITY JE0ZL PPSL contractual documents for the design and ccnstruction of the off-site EOF will include quality plans for the independent verification and validation activities. The quality plan for the design of the EOF will include requirements for docuritnt control, records an d audit / surveillance activities to support the design verificaticn process. The quality plan for the construction phase of the EOF will provide requirements for qualifica tion verifica tion of designa ted EOF systems and a testing program to assure they will function. The quality plan will also provide requirements for an inspection program to assure designated systems are installed in accordance with the design documents. The quality plan will include 7 organizaticnal interf ace contr ol, document control, non- ' conformance contrcl and audit / surveillance activities to support the qualification and installation verification activities. Rev. 4, 5/81 9-1 c .a

9.3 EMERGENCY RESPCNSE COMPUTER SYSTEM (ERCS) , SAFETY PARAMETER DISPLAY SYSTEM (S PDS) , ANE nyckgsg_pA1A Ling _jup6L____________________ lh PPGL contractual documents including procurement documents for EBCS will include design, qualifica tion and installa tion verification requireaents for the Emergency Response Computer System. To support the design, qualification and installation verification activities, the .guality plans, as applicable will include requiremets f cr organiza tional interf ace control, document control, non-conformance control and audit / surveillance activities. PSAR EPLAN:3 9 i O Rev. 4, 5/81 9-2}}