ML20062B587

Public Version of Revised Emergency Plan Implementing Procedures,Including Revision 2 to Procedure Ei 1300.00 Re Station Response to Emergencies & Revision 3 to Ei 1300.01 Re Emergency Plan Activation

ML20062B587
Person / Time
Site:	Davis Besse
Issue date:	07/12/1982
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20062B566	List: ML20062B565 ML20062B577 ML20062B587
References
PROC-820712-01, NUDOCS 8208040616
Download: ML20062B587 (154)

Text

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• f a THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION

,, DfERGENCY FIJ.N IMPLMNG PROCEDURES

,g REVISION INDEX m

Q PAGE REVISION PROCEDURES REVISION TEMPORARY MODIFICAT 2IS 1 0 EI 1300.00 2

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EI 1300.01 3 l

, EI 1300.02 1 T-6015 2,

EI 1300.03 F , EI 1300.04 1 T-6060 EI 1300.05

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y EI 1300.06 2 E 1300.07 1 T-6016, T-6074 b -

EI,1300.08 2 T-5849, T-6041, T-6051 l

, , EI 1300.09 0 d

l EI 1300.10 0 T-6017 I

y EI 1300.11 0 T-6018 EI 1300.12 1 T-5850, T-5918

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Revision 12 July, 1982

. 8208040616 820730 PDR ADOCK 05000346 F PDR

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EI 1300.00.0 1 a s

Davis-Besse Nuclear Power S'tation O Unit No. 1 Emergency Plan Implementing Procedure EI 1300.00 Station Response to Emergencies l Record of Approval and Changas Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. Wells 6/13/80 -

Section Head Date Recommended by f/ e -

6 xy/Po

~ SRB Chaffman Date QA Approved (( '

Quality Assurance Manager Date Approved by D 9 ,- @ // 5:f/h StationSuperintendeg Date Revision SRB QA Sta." Supt.

No. Recommendation Date Approved- Date Approved Date

/ h/Ef' V'//N Y Y P/

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1 EI 1300.00.2

1. PURPOSE To present a summary of the DBNPS Emergency Plan.

2. SCOPE To present a summary of Station actions during an amergency and to outline the interface between Station procedures and Emergency Implementing Procedures (EI 1300 series).

3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Davis-Besse Nuclear Power Station Emergency Plan Telephone Directory 3.3 TECo Corporate Radiological Emergency Response Procedure 3.4 Emergency Implementing Procedures EI 1300 series 3.5 Administrative Procedures AD 1827 series ~

3.6 EP 1202.35 F,1,ru Emergency 7-s3 3.7  !!P 1604.01 Personnel Decontamination 3.8 Admin Memos 38', 39, 40

4. DEFINITIONS 4.1 Dose Projection - The calculated estimate of a radiation dose to individuals at a given location (usually offsite),

determined from the quantity of radioactive material released and the appropriate me*eorological transport and disporsion paramotors.

4.2 Emergency Action Levels - Radiological dose rates, specific concentrations of radioactive materials; or specific instrument readings and indications (including their rate of change) that may be used as thresholds for initiating such specific emergency measures as designating a partic-ular classification of emergency, initiating a notifica-tion procedure, or initiating a particular protective ncLion.

4.3 , Emergency Control Center (ECC) - A specifically designated locnLion which is equipped to facilitate the control and coordination of emergency activities'and assessments.

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• 2 EI 1300.00.2 .

4.4 Emergency Duty Officer (EDO) - An assigned individual responsible for direction and coordination of activities ll during an emergency situation at the Station.

4.5 Emergency Operations Center (EOC) - An offsite location utilized by State, County, and other government agencies and organizations to perform assessments of radiological conditions and to coordinate offsite activities (access, evacuation, etc.). f 4.6 Emergency Planning Zones (EPZ) - TVo zones that EPA recommends be established around all nucicar power stations.

Uno zone with a radius of 40 miles (16090 meters) for plume exposure pathway, and the other with a radius of 50 miles (80450 meters) for food ingestion pathway.

In these zones, predetermined protective action plans are needed.

2 4.7 Operations Support Center (OSC) - An area in the Station in close proximity to the Control Room to which Station personnel report and await instructions from the Shift ~

Supervisor, Emergency Duty Officer or Station Operations flan ngn r . ,,

4.8 Projected Exposure Time (PET) - The estimated period of time that the population in the area surrounding DBNPS may f

be exposed to ' radiation as a result of an accidental cirborne radioactive release. PET starts when the air-borne radioactivity release is estimated to cross the Owner-Controlled Area, and ends when the radiation icvels offsite are exper*ad to return to normal.

4.9 Protective Action Guides (PAG's) - Projected radiological dose or dose commitment values to individuals in the general population that warrant protective action follow-Ing a release of radioactive material. Protective actions

' would be warranted provided the reduction in individual dose is NOT offset by excessive risks to individual safety in taking the protective action. The PAG does NOT include the dose that has unavoidably occurred prior to the assessment.

2 4.10 Tnchnical Suppor,t, Centnr (TSC) - An nron within the ownnr controlled area, which hus the capabilities to display and transmit station status information to individuals who are knowledgeable of and responsible for engineering and management support of reactor operations in the event of an emergency situation.

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t 3 EI 1300.00.2 s 5. EMERGENCY PLAN

SUMMARY

5.1 The DBNPS Emergency Plan establishes the concepts, evalu-ation and assessment criteria, and protective actions that are necessary in order to limit and mitigate the consequences of potential or actual radiological emergencies. The plan provides the necessary prearrangements, directions, and organization so that all Station emergencies can be offectively and efficiently resolved in order to safeguard Station personnel, property and the general public.

6. STATION RESPONSE 6.1 The Station Superintendent is ultimately responsible for the assignment of responsibilities in the onsite Emergency Organization. However, the onsite Emergency Organization is predefined, and alternate assignment.= specified.

. 6.2 k' hen an emergency condition is declared, the members of thn normal plant organization assume duties in the onsite Emergency Organization.

6.2.1 The Shift Supervisor's primary responsibility is main,tulning the plant in a safe condition as well as carrying out the initial steps of the EDO:

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a. Verify the existence of an emergency condition.

b. Notify Stat' ion personnel, the Station Superin-tendent, EDO, and offsite support groups as required.

c. Activate emurgency' teams.

2 d. Control access of personnel to Control Room.

c. Initiate immediate protective measures as required.

f. Verify operating status of the Plant and Station.

6.2.2 The Shift Supervisor assumes the role as EDO until properly relieved by the on-call EDO or his alleruute.

6.2.3 The Control Room, during an emergency, will control the power plant to mitigate the effects of the emergency conditions.

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4 EI 1200.00.2 ,

6.2.4 The Assistant Station Superintendent, Operations, or his alternate, the Operations Engineer, becomes the Plant Operations Manager. He is responsible for keeping the Station Operations Manager advised of plant operations. He may assist the Shift Supervisor in directing plant activities and damage control efforts, however, ultimate authority for directing all phases of plant operations lies with the Shift Supervisor. {

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6.2.5 The Radcon Opeations Manager is the Chemist and Health Physicist or the Chemical and Radiation Protection Engineer. He directs and coordinates the radioactive waste and radiological controls aspects of the recovery operation.

6 . 2.- 6 The Operations Engineer, or the Operations Supervisor, becomes the Plant Operations Engineer.

, 2 He supervises Control Room activities, and performs on-the-spot operation analysis as required by the Shift Supervisor. The Shift Supervisor, and through him the operating shift, reports to the Operations Engineer.

6.2.7 Pla*n't Maintenance, during an emergency, is directed by thu Maintenance Engineer, or his y .

alternate, the Lead Maintenance Support Engineer,

! or Lead Instrumentation and Control Engineer.

6.3 The ED0's responsibilities include:

a. Implements appropriate protectivo actions to mitigate I

the effects of tho incident. The Implementing l'rocedures for the plan shall provide necessary guidance. The judgment of the EDO plays a vital role in any emergency and in some cases, may take precedence over previously preplanned actions.

b. The safety and well-being of Station personnel.

c. Determination as to necessity to evacuate the Station and/or the local area.

d. Provides projected dose information.

u. l<nconunends to offsite emergency organizations for implementing effective protective measures for the general public.

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5 EI 1300.00.2

(~' 6.4 Onsite Assessment Teams (OAT)

V 6.4.1 The Onsite Assessment Team is headed by the Nuclear Engineering Manager or his alternate, the Plant Nuclear Systems Engineer.

6.4.2 The Team Manager supervises the analysis efforts of Company engineers, NSSS vendors, and other plant staff.

6.4.3 The location of the OAT is the TSC.

2 6.4.4 The Technical Engineer or his alternate, the Nuclear and Performance Engineer, will be in the TSC to analyze vital plant parameters and plant response.

6.5 Other emergency response personnel provide specialized support:

6.5.1 Radiation Monitoring teams (Admin Memo 42) 6.5.2 First. Aid Team (Admin Memo 38) 6.5.3 Fir"c Brigade (Admin Memo 39)

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6.5.4 Emergcncy Facility Personnel

a. ECC (EI 1300.08)

b. TSC (EI 1300.07)

c. OSC (EI 1300.06) 6.6 When required, additional support is provided by the TED Corporate Emergency Organization in the form of technical, admini.strative, and logistical support to the onsite Emergency Organization.

7. EMERGENCY PLAN STEPS In general, the Emergency Plan encompasses the following basic steps.

u. DeLuction of the emergency

b. Clnssification of the emergency

c. Activation of the responding organization (s)

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6 EI 1300.00.2 ,

d. Assessment of the situation

e. Initiation of protective actions

f. Initiation of corrective actions

g. Aid to affected persons

h. Periodic dissemination of updated information 2 1. Reentry and recovery 7.1 Detection of the Emergency This step of the Emergency Plan relies on the Operating Shift Crew to determine whether an abnormal situation exists based on all plant parameters, visual sitings of problems or scund engineering judgement. This step may also include actions required by Emergency Procedures, Alarm Procedures, or Abnormal Procedures, etc.

7.2 Classification of the Emergency ..

7.2.1 Emergencies are grouped into four (4) class-i fi*c~a t ions Ifsted below in order of increasing severity:

a. Unusual-Event The occurrence of an event or events which indicate a potential degradation of the level of safety of the plant. Unusual Event emer-gencies involve minor situations that have the potential to escalate to more serious emergencies.

b. Alert The occurrence of an event or events which involve an actual or potential substantial degradation of the level of safety of the plant. The consideration is, as in an Unusual Event, to prepare to cope with potentially more serious emergencies. Alert emergencies may involve limited release of radioactive material.

c. Site Emergency e i 1

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7 EI 1300.00.0 The occurrence of an event or events which Os involve actual or likely major failures of plant functions needed for protection of the public. The potential for a situation hazardous to the general public is the major concern of the Site Emergency classification. There also exists a significant actual or potential release of radioactive material.

d. General Emergency The occurrence of an event or events which involve actual or imminent core degradation with the potential for loss of containment integrity. Large amounts of radioactive material, immediately hazardous to the general public, could be released during a General Emergency.

7.2.2 The classification of the emergency is determined by comparing plant conditions with the Emergency Action Levels described in Emergency Plan Activa-tion Procedure EI 1300.01.

7.2.3 Tlic .Shi f t Siipervisor is responsible for dcLarmin-s ing the initial classification of the emergency.

7.3 Activation of 'the Responsible Organization (s) 7.3.1 Upon determination of the appropriate emergency class, the Shift Supervisor shall then refer to the approprinto emergency classification procedures:

a. Unusual Event TI 1300.02

b. Alert EI 1300.03

c. Site Emergency EI 1300.04

d. General Emergency EI 1300.05 7.3.2 The Shift Supervisor assumes the duties as interim Emergency Duty Officer and proceeds with the actions outlined in the EDO check lists provided with the abovo procedures. Ile remains the interim EDO until relieved by the assigned EDO or until the emergency is terminated.

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7.3.3 Part of each checklist is ensuring that proper, timely notifications are made in the event of an emergency.

For example:

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a. Notification should be made to State / Local authorities (via Ottawa County Sheriff) as soon as possible (normally within 15 minutes) following the declaration of an emergency classification, as identified in 10 CFR 50 Appendix E, Section IV.D.3., Domestic Licensing of Production and Utilization Facilities.

b. Notification should be made to the NRC as soon as possible and in all cases within one hour of the occurrence of any significant event as identified in 10 CFR 50.72, Licensing of Production and Utilization Facilities, i 7.3.4 The EDO has some options as to which organiza-tions and/or individuals should be activated. -

l These decisions should be based on obtaining the best sources of information, experience and adv'ico availabin.

7.3.5 The.cxpected degree of involvement of partici-patin~g organizations is shown in Table 1.

7.3.6 The Emergency Organization response to emer-gencies is shown in Table 2.

7.3.7 Thu Emergency Organiz~ation is shown in Figures 1 and 2.

7.3.8 The DBNPS Emergency Call System is shown in Figure 3.

7.4 Assessment of the Situation Effective coordination and direction of all elements of the emergency organization requires continuing accident assessment throughout an emergency situation. Each emergency class shall invoke similar assessment methods, however ench classifinntion imposos n difforent magniLudu ol' nssnssment u f fo rt . In Lho following subsections, assessment actions to be taken for cach emergency class-ification are outlined.

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9 EI 1300.00.0 7.4.1 Assessment Actions for Unusual Events The continuing assessment actions to be performed for this classification consist of the normal monitoring of Control Room and other plant instrumentation and status indication until the situation is resolved. If a fire is the reason for the declaration of an Unusual Event, the Fire Brigade Captain, upon reporting to the fire location will make continuing assessments based on his knowledge and experience and report his findings to the Shift Supervisor on whether offsite fire fighting support is required. In the case of personnel injury and/or illness, the utilization of offsite medical assistance may be cause to declare an Unusual Event if the injury involves personnel

. contamination.

7.4.2 Assessment Actions for Alerts The assessment actions for an Alert shall include:

a. increased surveillance of in plant instru-mentation.

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b. If' possible, the dispatching of shif t per-sonnel to the identified problem area for confirmation and visual assessment of the problem.

c. The dispatch of onsite RadiaLion Monitoring Team's (RMT's) to monitor for possible releases and to provide confirmation of correct accident classification.

d. If a radiological accident is occurring, the in plant instrumentation necessary to obtain meteorological and radiological data for calculating or estimating projected doses will be monitored. This dose assessment activity shall continue until termination of the emergency in order that the updating of initial assnssments may be provided to all concerned of fsite agencies and to the EDO.

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o 10 EI 1300.00.0 ,

7.4.3 Assessment Actions for Site Emergencies l

The assessment actions for the Site Emergency classification are similar to the actions for an Alert, however due to the increased magnitude of the possible release of radioactive material, a significantly larger assessment activity shall occur. The necessary personnel for this assess-ment effort shall be provided by mobilization of the onsite and offsite emergency organizations.

Specifically:

a. An increased amount of plant instrumentation shall be monitored. In particular, indica-tions of core status (e.g., incore thermo-couple readings, etc.) shall be monitored.

b. Monitoring efforts shall be greatly increased.

Onsite and offsite monitoring teams shall be dispatched. In addition to beta gamma field measurements, the change-out of thermolum-inescent dosimeters (TLD's) at frequent intervale may be performed; air sampling and collection of other environmental media for assessment of m'torial a transport and deposition shall be performed.

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c. Dose assessment activities shall be conducted more frequently, with an increased emphasis un dose projection for use as a factor in determin-ing the necessity for protective actions.

Radiological and meteorological instrumentation readings shall be used to project the doso rate various distances from the Station, and to determine the integrated dose received. In reporting the dose projections to the EDO or to offsite agencies, the dose rate, dose, and the basis for the time used for the dose estimate shall always be provided. Any confirmation of dose rates by offsite RMT's shall be reficcted in reporting and/or revising i

dose estimate information provided to offsite and internal organizations.

7.4.4 Assessment Actions for General Emergencies Assessment actions for the General Emergency 9

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11 EI 1300.00.0 r" classification shall be the same as for the Site

(_ Emergency with a shift of emphasis to greater offsite monitoring efforts and dose projection efforts extending to distances further from the plant. Additionally, since the projected doses are likely to be much closer to the EPA PAG's, greater emphasis shall be placed on the assess-ment of release duration. Judgements and assump-tions used for dose assessment shall always be reported.

7.5 Initiation of Protective Actions Protective actions are emergency measures taken during or after an emergency situation that are intended to minimize or eliminate the hazard to the health and safety of the general public and/or Station personnel. Protective actions include the following:

7.5.1 Protective Cover, Evacuation, Personnel Account-ability During an emergency, sheltering may be the most effc.ctive protective action. The relocation of y~' personnel may also be required in order to pre-1 -

vent or minimize exposure to radiation and radio-activ'c materials. In any event, personnel accountability is very important during this time. The following subsections present information on policies applicable to such situations.

a. Plant Site All persons onsite at the time of an Alert, Site, or General Emergency, who do NOT have emergency assignments (nonessential personnel) shall be notified of the emergency classifica-tion by announcement over the public address system. These personnel shall report to assembly areas for accountability, monitoring and possibic evacuation. At the assembly area, members of the emergency organization shall direct and conduct accountability, monitoring and evacuation ufforts,

b. Offsite Areas The responsibility for actions to protect persons in offsite areas rests with the State O

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of Ohio and Ottawa County officials. Respon- g sibilities are described in detail in the W j State Plan and implemented in conjunction with  !

the County Plan. The means to warn or advise  !

persons involved in taking protective actions  !

is the responsibility of the Ottawa County Disaster Services Agency (DSA) Coordinator and the Ottawa County emergency organization.

Ottawa County is responsible, according to the State Plan, for the preparation and dissemina , '

tion of information material on protective actions for the general public.

7.5.2 Use of 0nsite Protective Equipment and Supplies The following onsite locations have been designated as emergency assembly points and areas where emergency teams shall be assembled and equipped.

a. Control Room / Shift Supervisor's Office

b. Radiation Access Controlled Area (RACA) .-

Control Point 2 c. PPF

. d. Operations Support Center

e. Emergency Control Center 7.5.2.1 Emergency equipment and supplies shall be stored in close proximity to the assembly points.

7.5.2.2 A complete list of emergency equipment and supplies can be found in appropriate procedures if the Emergency Plan.

2 7.5.2.3 Emergency response team members have been trained in the use of specific emergency equipment.

7.5.2.4 Emergency celuipment and supplins will'bc used in accordance with Emergency Plan Implementing Procedures or as directed by O

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13 EI 1300.00.2 g2 the Emergency Duty Officer,

() Shift Supervisor, or emergency team leaders.

7.5.3 Contamination Control Measures This section describes provisions for preventing or minimizing direct or subsequent ingestion exposure to radioactive materials deposited on the ground or other surfaces.

a. Station Area Access to the owner-controlled area is con-trolled. In addition, there are no areas for proiucing agricultural products within the own'.r-controlled area.

Station contamination contiol shall be exercised in accordance with .

. appr ved procedures. ,

b. O.isite Arcas It is the responsibility of the State Depart-m,ent of Agriculture, in conjunction with the Department of Health and Environmental Pro-rs tection, to issue guidance and coordinate

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actions to control contaminated agricultural products offsite. The State of Ohio has the responsibility to act on TECo recommendations and to develop their own course of action.

7.6 Initiation of Corrective Actions 7.6.1 Detailed operating procedures are available to the operators for use during emergencies as well as during normal operations. Specific Emergency Procedures are provided to assist the operators in placing Lhc plant in a safe condition and taking the necessary supplemental corrective actions. In addition, operations personnel are capable of taking appropriate corrective actions based on their training, knowledge and experience.

7.6.2 Selected Davis-Besse Nuclear Power Station Staff personnul, including operation, health physics, chemistry and radiochemistry, and maintenance personnel are assigned to emergency teams.

These teams are capable of responding to situa-tions in order to assess conditions and take any D

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h 14 EI 1300.00.1 applicable corrective actions. Maintenance personnel shall provide the necessary crafts l expertise to effect repair and damage control b functions. l 7.6.3 Corrective actions shall normally be planned events that are taken to mitigate the consequences of, or terminate the emergency situation.

Planned radioactive releases or corrective actions that may result in a radioactive release shall be evaluated by the Emergency Duty,0fficer, and his staff, as far in advance of the event as is possible. Such events and data pertaining to the release shall be reported to the appropriate offsite emergency response organization and/or agencies prior to any controlled release during an emergency or post emergency situation.

7.7 Aid to Affected Persons 7.7.1 Emergency Personnel Exposure Emergency measures may warrant the acceptance of above-normal radiation exposures. Saving a life, measures to circumvent substantial exposures to population groups, or even preservation of valua,ble installations, may all be sufficient ,

lh cause for above normal exposures. The following are the guidelines for these emergency activities:

a. Life-saving action 100 rem

b. Correctivo action 25 rem Personnel involved in any of the above actions must be volunteers.

1 The senior Toledo Edison Management individual i

present shall authorize the above exposures and is responsible for maintaining exposures below these values. He shall seek advice from the Radeon Operations Manager (Chemist and Health Physicist) or members of the C&HP staff. He shall assure that measures are taken to minimize other exposures (such as internal exposure) during the conduct of emergency operations.

7.7.2 Thyroid Blocking A ready supply of suitable thyroid blocking agent O

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('] will be maintained and available for use by

(,,/ Toledo Edison employees. Guidance for admin-istration of the blocking agent will be provided by medical advisors and it will be distributed as per AD 1827.12.

7.7.3 Decontamination and First Aid Personnel found to be contaminated shall undergo decontamination by Health Physics personnel (or other qualified personnel as specified in HP Procedures). It is preferred that personnel decontamination be performed by trained Health Physics personnel, however other TECo personnel are instructed in both decontamination and first aid procedures. Measures shall be taken to prevent the spread of contamination.

Emergency first aid and medical treatment shall be given to injured personnel who are contaminated.

Station personnel, trained in first aid, shall assist contaminated personnel either at the scene of the accident or in the First Aid Room.

Prov.isions have been made to ensure contaminated and injured personnel receive specialized medical g treatment if necessary. The Magruder Memorial

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Hospi,tal has agreed to accept contaminated patients for emergency medical and surgical treatment and/or observation. If affected personnel must be transported, measures shall be taken to prevent the spread of contamination.

7.7.4 Medical Transportation Ambulance service for Davis-Besse is provided for by the Carroll Township Emergency Medical Service.

7.7.5 Medical Treatment Arrangements for hospital and medical services for injured or contaminated /over-exposed per-sonnel are provided for by the Magruder Memorial 2 llospital, REMS Corporation, the Peter Bent Brigham Memorial Hospital in Boston, Mass., and local physicians.

7.8 Reentry and Recovery 7.8.1 The Emergency Duty Officer and the Station Opera-tions Manager have the joint responsibility for D

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16 EI 1300.00.0 i determining and declaring when an emergency situation is stable and the Station is ready to e

enter the reentry and recovery phase.

7.8.2 The reentry and recovery phase of the Emergency Plan consists of planned and deliberate actions taken to return the plant to pre-accident levels of radiation and contamination or to conditions which are acceptable and controllable for an extended period of time.

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17 EI 1300.00.1 Table 1 v) EMERGENCY CIJ.SSIFICATIONS AND THE DEGREE OF INVOLVEMENT BY PARTICIPATING GROUPS Necessity for Necessity Degree of Participation Emergency Protective Actions for By Various Organizations Classification Corrective TECo Offsite Onsite Offsite Actions *** Onsite Offsite Agencies Notifi- Notifica- Notifica-1 Unusual Event None None Possible cation tion tion

Status

• Status Status **

Alert Possible None Possible St'ndby a Standby Standby Status ** Status Status Site Emergency I'robable Possible Probable Action Action Action I

General Emer- !

r,nni:y I l'roliala l u l'robable i<cciu i red Action Action Action 1 I

• Notification Status: Organization informed of situation onsite.

• • Standby Status: Organization staffs preplanned centers, establishes communications, and assembles emergency teams.

l *** Action might include local fire support, ambulance service, medical

! assistance, or radiological assessment.

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, , El 1300. 01, Davis-Besse Nucl. ear Power Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.01 Emergency Plan Activation I

1 Record of Approval and Changes Prepared by_ '

G. J. Reed S/30/80 Date Submitted by C. E. Wells Section Head _

6/13/80 "

Recommended by Date M8c/ #_

h /3!N SR3 Chairtin _

Date

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QA Approved s ef/ /9 Quality Assurance Manager _

Date I. A PProved by_ 'y Y"> h =g f[/ &/,g Sta'tionSuperintendeQ poce I Revision SRS I No.

J Recommendation M. L) Poudw Aho/6)

Date QA Approved Date Sta. Supt.

Approved p N// W Daty#?'

W' I .;S &$ 'I~I

, , ,,1y - v y en lplh I "" -.. b q/ Ih I

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1 EI 1300.01.3

1. PURPOSE I 3 To provide guidelines for conditions at which specific emergency classifications must be declared.

2. SCOPE 3

To specify emergency action levels and personnel judgments that t are consistent with the emergency classification scheme depicted in Appendix 1 of NUREG-0654, Rev. 1.

3. REFERENCES 3.1 The Davis-Besse Nuclear Power Station Emergency Plan 3.2 Final Safety Analysis Report, DBNPS 3.3 Technical Specifications, DBNPS Unit No. 1, Appendix A I 3.4 and B to License No. NPF3 Station Response to Emergencies, EI 1300.00

4. DMINITIONS 4.1 Unusual Everd - Event (s) are in progress or which have

- occurred that indicate a potential degradation of the

, level of safety of DBNPS.

4.2 Alert - Events are in progress or have occurred which

'Eol've i an actual or substantial degradation of the level of safety of DBNPS.

I 4.3 Site Emergency - Events are in progress or have occurred which involve actual or likely major failures of DBNPS functions needed for the protection of the public. There also exists a s_ign_ificant actual or pcLential release of

.I radioactive materiai.

4.4 I General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degrada-Lion or meiLing with Lhe potential for loss of containment integrity, and/or involve the potential for a release of radioactive particulates or gases of fsite of a magnitude to exceed regulatory limits.

I 4.5 Emergency Action Levels (EAL's) - Radiological dose rates, speci fic contamination levels of airborne, waterborne, or surface-deposited concentrations of radioactive materials; I or specific instrument readings and indications (including their rate of change) that may be used as thresholds for initiating such specific emergency measures as designating

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2 EI 1300.01.3 a particular classification' of emergency, initiating a notification procedure, or initiating a particular protec-tive action.

S. EMEHCENCY MEASURES 5.1 The Shift Supervisor, when informed that abnormal or emer- I gency conditions (real or potential) have arisen, shall perform the necessary actions in the priority listed B*l below:

5.1.1 Ensure that the immediate actions (e.g., use of Emergency Procedures) are taken for the safe and proper operation of the plant. l 5.1.2 Assess the information available from valid indication and using Table 1, initially classify the situation with the following considerations:

a. The specific emergency action levels described in Table I are not all inclusive. The Shift I ' Supervisor or Emergency Duty Officer shall declare an appropriate emergency classification Ghenever, in his judgment, the station status warrants such a declaration. (Refer to Step

) . 5.2.2 for guidance.)

b. Reaching these levels over a period of days I rather than hours is not sufficient to declare the appropriate classification.

i I c. Some of the emergency action levels described are not, by their very nature, intended to be used during maintenance and/or testing situa-tions where abnormal temperature, pressure,

! equipment status, etc. is expected.

d. All of the emergency action levels shall be considered if the plant is, or was (immediately prior to the emergency condition) in Mode 1 operating at a high power level, except for I those conditions noted in the Index of Emer-gency Action Level Conditions, Page 4.

'g 5.I.3 Use the appropriate che'cklist from either the l 3 Unusual Event (EI 1300.02), Alert (EI 1300.03),

l Site Emergency (EI 1300.04), or General Emergency l 3 (EI 1300.05) procedure to ensure that immediate notification requirements are met and the proper Emergency Plan response is taken.

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, 3 EI 1300.01.3 5.1.4 Perform additional, emergency actions as time and conditions permit.

5.2 Operator judgment plays an important role in ensuring that during any specific event the appropriate actions a re performed.

5.2.1 Exampics

ll a. For an abnormally high lake level, operator i3 judgment should take into consideration the lake level, wind direction, weather con-ditions, etc. , before announcing a flood lI warning and initiating personnel evacuation.

During a previous incident, personnel were evacuated during flood warning conditions, however it was found that this was unnecessary since the weather then cleared and no flood or hazardous situation occurred.

b. For localized incidents that may affect only small areas, operator judgment should take -

3 into consideration that an alarm, when sounded,

,5 could be followed by some amplifying instruc-i I. ions to aid personnel response. Duriny, u

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-~m previous incident, an individual was injured requiring medical assistance. The Initiate Emergency Procedures .ilarm was sounded, however verbal instructions via the gai-tronics system could have been used to prevent unneeded personnel involvement and assembly.

EJ 5.2.2 For abnormal plant conditions that are not

.5 specifically covered in the Table 1 emergency action levels, the following criteria shall be IE used to assist the Shift Supervisor or Emergency E Guty Officer in classifying the event based on their judgment.

a. Unusual Event - Other plant conditions exist that warrant increased awareness on the part of the plant operations staff or State and/or local offsite authorities which are not  ;

covered under any other existing station procedure.

b. Alert - Other plant conditions exist that  !

. warrant precautionary activation of the i I g Technical Support Center and Emergency Control Center and placing other key emergency per-sonnel on standby.

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4 EI 1300.01.3

) c. Site Emergency - Other plant conditions exist that warrant activation of emergency centers and monitoring teams or a precautionary notification to the public near the site.

E d. General Emergency - Other plant conditions 3 exist, from whatever source, that make release of large amounts of radioactivity in a short time period possible, I situation.

e.g., any core melt 5.3 Plant conditions should be continually evaluated to ensure 1

the proper emergency classification is being utilized and the classification upgraded or downgraded by the Shift Supervisor and Emergency Duty Officer as conditions dictate i per Table I and Steps 5.1.2 and 5.2.2 above.

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5 EI 1300.01.3 INDEX OF EMERGENCY ACTION LEVEL CONDITIONS Condition Page No(s).

3

• Safety System Functions 6-7 Plant Shutdown Functions 8 Coolant Pump Seizure I Loss of Assessment functions 9

10 Control Room Evacuation 11

• Abnormal Coolant Temperatures 12 I'l

• Abnormal Primary Leak Rate 13-14 Abnormal to Primary / Secondary Leak Rate 15-16 3l

• Core Vuel Damage 17-18 Loss of Fission Product Barriers 19

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• Fuel llandling Accident 20

-m Abnormal Containment Atmosphere 21

• Abnormal Effluent Release 22 I. *High Radiation Levels in Plant 23 kAbuurmal Itadiation f.evels at Site 11oundary 24-26

• Contaminated Personnel 27 Major Steam Leak 28-29 Major Electrical Failures 30

• Fire 31

• Security Threat 32

• llazards to Station Operation I *iMural F. vents (Wi thin OLLawa County) 33-35 36-38

?NOTF.: When evaluating the EAL's in Table 1, the plant must be in Mode 1 or had been in Mode 1 operating at a high power level when the

) event initiated, except for those annotated conditions above which have been broken down and noted, as applicable, in their respective sections of Table 1.

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6 EI 1300.01.3

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TABLE 1 SAFETY SYSTEM FUNCTIONS Emergency Condition Indication (s) Classification 3l Unplanned Initiation Any three of the four fol- Unusual Event

• I of ECCS with Flow into Core Indicated loving with flow indicated:

1. HPI low flow alarm (EI 1300.02) and/or LPI low flow I 2.

alarm (on then off)

HPI and/or LPI pump status lights indicate Pump (s) running

3. HPI and/or LPI pump current meters indicate pump (s) running I 4. HPI and/or LPI pump discharge valves indicate '

open I t.uss of Contairunent Any One of the four following

,r integrity Unusual Event requiring plant shutdown per

> [yg , T.S. 3.6.1.1:

(EI 1300.02) 1.. Any penetrations required to be closed during accident I' conditions that are not:

A. Capable of being closed by the Safety Features I Actuation System, OR B. Closed by manual valves, I blind flanges, or de-activated automaLic valves secured in their closed position except jI as provided in T.S.

3.6.3.1 Table 3.6-2

2. An equipment hatch is not closed and sealed

3. An airlock is not operable per T.S. 3.6.1.3 I 4. A sealing mechan' ism assoc-iated with a penetration (e.g., welds, bellows, or 0-rings) becomes inoperable NOTE: For the above asterisked (*) classification (s) the plant can be in any Mode for the listed EAL's to be applicable.

~7 EI 1300.01.1 TABLE 1 SAFETY SYSTEM FUNCTIONS (Con't) iEE Emergency Condition Indication (s) Classification

. Loss of Engineered 1. A Safety Features Unusual Event Safety Feature Actuation System (SFAS) (EI 1300.02) functional unit shown in T.S. Table 3.3-3 becomes inoperable per T.S.

3.3.2.1 and requires plant I shutdown OR

2. The Boron Injection Flow I Path (operating) or Borated Water Sources (operating) becone. in- ..

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operable and require plant shutdown per T.S. 3.1.2.2 and 3.1.2.9 Fai lure of Sa fety 1. - Reactor Coolant System: Unusual Event Helated Safety or Helief A. Indication of flow (EI 1300.02)

. Valve to Close through Pressurizer I1 Reliefs (red light on Panel C5798 or I B.

C5799)

AND RCS Pressure drop lg to <1600 psig i g 2. Main Steam System:

(any 2 of 3)

A. Hapid and continuing j decrease in Steam Cen-erator pressure to <500 Psig i

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C.

Rapid RCS cooldown rate Audible steam relief noise in the Control I . . . _ . . . . . . .

Hoom lasting >10 minutes

. . . . . . . . ~ . . . . . . . . . . . . .

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8 EI 1300.01.1 TABLE 1 PLANT SHUTDOWN FUNCTION Emergency Condition Indication (s) Classification Loss of any system which 1. Any of the following Alert

, E precindes placing the systems become inoperable: (EI 1300.03)

El plant in cold shutdown A. Service Water System (both trains) l I B.

C.

Decay Heat System (both trains)

Component Cooling Water (both trains)

Loss of any system which 1. The following systems Site Emergency lEW precludes placing the plant in hot shutdown become inoperable: (EI 1300.04)

A. Makeup System and HPI System ,,

l g OR g B. Main Feedwater System

.- and Auxiliary Feed-water System Failure of Reactor Pro- 1.' Any time plant parameters Alert I, Lection System to initiate and complete a trip meet conditions requiring a trip and RPS fails to (EI 1300.03) initiate and complete a I trip which brings the reactor subcritical I

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EI 1300.01.0 9

TABLE 1 C00LA'4T PUMP SEIZURE

)

Emergency J Condition Indication (s) Classification Coolant pump seizure with 1. Reactor Coolant System Alert luel elamay,e inelicated flow indication decreases ley lueline sample > T.S. (EI 1300.03) rapidly 3.4.8 AND

2. Confirmed Primary Coolant I sample results indicate

>1.0 pCi/ Gram dose equiv-alent I-131 I

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10 EI 1300.01.3 TAB'LE 1 i LOSS OF ASSESSMENT FUNCTIONS l Emergency Condition Indication (s) Classification Control Room Indications Any of the Following: Unusual Event I or Alarms on Process or F.TfIuent Parameters NOT Innetional to an extent

1. Radiation monitoring instrumentation < min-imum channels operable (EI 1300.02) j reepairing plant shutdown I 3 or other significant loss of assessment or communica-requiring shutdown per T.S.

requirements OR Lion capability 2. RE2024A, B & C, RE2025A ,B

& C and Backup Crab Sample capability become in-operable I 3.

OR Meteorological monitoring instrumentation < min-I imum necessary to perform offsite dose calculations (i.e. wind speed, wind direction, and stability l L. - ***}

4. Post-accident instrument-I, ation < minimum channels operable requiring plant shutdown per T.S.

I 5.

requirements (T.S. 3.3.3.6)

OR Complete failure of the I plant telephone system and Gai-tronics system All annunciator alarms 1. Any simultaneous loss Alert and station computer of all annunciator (EI 1300.03) lost alarms and the station computer l

All annunciator alarms 1. Complete loss of ali Site Emergency lE5 and station compulcr lost

>15 minutes during plant annunciator alarms (EI 1300.04) and station computer

,g transient lasting more than 15-I 3 minutes AND

2. Plant transient initiated or in progress I

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11 EI 1300.01.0 TABLE I CONTROL ROOM EVACUATION i

Emergency Condition Indication (s)

Classification Evacuation of Control Room 1. Any evacuation of the Alert required Control Room with shut-I down control established locally within 15 minutes (EI 1300.03)

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Evacuation of Control Room 1. Any evacuation of the Site Emergency and Control NOT estab- Control Room with shut- (EI 1300.04)

I listicd locally within 15 minutes down control NOT estab-lished locally within 15 minutes I

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12 EI 1300.01.3 TABLE 1 ABNORMAL COOLANT TEMPERATURES Emergency Condition Indication (s) Classification 3 Core Subcooling is 1. As determined by Sub- Unusual Event

• I Determined to be less Cooling graph or T (EI 1300.02) than normal (10*) Meter Indication (TD14950 or TD14951)

AND

2. As indicated by the difference between Pres-surizer Temperature and I3 Th (use incore thermo-couples temperature if Th "***' i* ff-8C'l*)

3 Coolant Temperatures 1. As determined by the Unusual Event

• combination of Reactor I

and/or pressures outside (EI 1300.01) of Technical Specification Coolant Core Outlet Iimits .. Pressure and/or Outlet Temperature exceeding the safety limits of

, T.S. 2.1.1 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any mode for the listed EAL's to be applicable.

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13 EI 1300.01.3 TABLE 1 ABNORMAL PRIMARY LEAK RATE Emergency Condition Indication (s) Classification I.cak Rate Requiring 1. RCS Water Inventory Unusual Event Plant Shutilown by I TS Section 3.4.6.2 Balance indicates

>l GPM unidentified leakage or >10 GPM (El 1300.02) identified leakage I 2.

OR Measurement of controlled leakage from the Reactor I Coolant Pump seals is >10 GPM total OR j3 3. Leakage from any RCS pres-g sure isolation valve >5 gpm as listed in TS Table -

1.cak Rate >50 GPM but Any Two of the Four Following: Alert

• withirt liigh Pressure 1. Makeup Tank level (EI 1300.03)

Injection' system - decreasing approximately capacity two inches per minute I- while RCS temperature remains steady

2. Increased activity on Con-I tainment Vessel Airborne Monitor (s) RE 4597AAA, AAB AAC, or RE 4597BAA, BAB, I 3.

BAC Increase in Normal Sump level on level instruments LI 1546 A or B

4. RCS Water Inventory Balance indicates

>50 GPM leakage

,I i.oss of Coolant Aerialent 1. Pressurizer level anil Site Emergency I liigh I'ressu re lujection system capacity pressure decreasing rapidly without an associated change in RCS (El 1300.04)

I temperature (RCS tempera-ture/ pressure reach saturation conditiont.) e OR t

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14 EI 1300.01.3 TABII 1 ABNORMAL PRIMARY LEAK RATE Emergency Condition Indication (s) Classification l

2. Containment pressure >38.4 l g psia and Reacte- Coolant i

g System pressure s ~ 3 psig 3 NOTE: For the above asterisked (*) classificatior.(s), the plant can be in any Mode for the listed EAL's to be applicable.

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IS EI 1300.01.3 TABLE 1 ABNORMAL PRIMARY TO SECONDARY LEAK RATE Emergency Condition Indication (s) Classification Leak Rate Requiring RCS Water Inventory Unusual Event Plant Shutdown by Balance indicates >1 TS 3.4.6.2 (EI 1300.02)

GPM total Primary to Secondary leakage And the Following:

1. Main Steam Line Radiation 3

monitor (s) (RE 600 and/or RE 609) in the " Analyze I Mode" to detect N-16 indicate increas:d activity

)

OR I 2. Condenser Vacuum dis-charge radiation monitor (s)

(RE 1003A (B)) indicate -

increased activity I ..

3.

AND Unexplained Makeup tank level decrease while Reactor N} -

Coolant System temperature remains constant Rapid failure of Steam Main Steam Line Radiation Alert Generator tubes (e.g., monitor (s) (RE 600 and/or (EI 1300.03)

I .seve ra l hnndred gpm primary to secondary leak rate!)

RE 609) in the "Arialyze Mode" to detect N-16 indicate increased activity, or Con-denser Vacuum discharge radia-I tion monitor (s) (RE 1003 A (B)) indicate increased activity I , And One of the Following:

1. Rapid drop in RCS pressure I 2. Rapid decrease in Pres-surizer and Makeup Tank levels I 3. Sa fety Features Actuation System (SrAS) Level 2 activates il 1

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, 16 EI 1300.01.3 TABLE I I ABNORMAL PRIMARY TO SECONDARY LEAX RATE Emergency Condition Indication (s) Classification 3' 4. Main Steam line radiation monitors in the " Gross Mode" I indicating more than 15000 epa net; background equals 1000 cpm I Hapid failure of one Steam 1. Noticable drop in Alert Generator tube and loss of I offsite power RCS pressure and pres-surizer level AND (EI 1300.03)

2. The 13.8 XV BUSES are deenergized -

AND 3 3. Main Steam line radia- ~

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tion monitors in the

" Cross Mode" indicating more than 15000 cpm net; y background equals 1000

) -

cpm 3 Rapid failure of Steam 1. Indications for leak Site Emergency Generator tubes (several rate of 400-700 GPM (EI 1300.04) hundred GPM leak rate AND indicated) and loss of 2. The 13.8 KV BUSES are offsite power deenergized I

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$7 EI 1300.01.3 TABLE 1 CORE FUEL DAMAGE Emergency Condition Indication (s) Classification

.g 53 liigh Coolant activity 1. Failed Fuel Detector (RSH Unusual Event sample Requiring Plant 1998) alarm with confirmed (EI 1300.02)

I Shutdown by Technical Specifications for Iodine (T.S. 3.4.8) sample results indicating

>1.0 pCi/ Gram Dose Equiv-alent I-131 I 2.

Aht Plant Shutdown required I3 Very liigh Coolant activity

1. Failed Fuel Detector (RSH 1998) "RC Letdown Activity Alert High" alarm (EI 1300.03)

AND

2. Confirmed sample results indicate >300 pCi/ Gram I-131 '-

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Core damay,e with in-

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1. Confirmed primary coolant y adequate core cooling Site Emergency sample results indicate:

determined A.

(EI 1300.04)

, >1.0 pCi/ Gram Dose equivalent I-131, and B. >100/E pCi/ Gram I* specific activity, AND

2. Reactor Coolant System

,g llot Leg temperature >620*F 3 OR

3. Incort thermocouple temper-I atureu increasing to >700*F Core damage with other 1. Confirmed primary coolant Il3 a plant conditions making release of large amounts of radioactivity sample results indicate

>300 pCi/ Gram I-131 AND General Emergency (EI 1300.05) l po.ssibic 2. Incore thermocouple temper-atures indicate >2000*F AND

3. Containment radiation level I3 is > 101 R/hr OR I 4. Contain$ent pressure is

>40 psia I

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18 EI 1300.01.3 TABLE 1 CORE FUEL DAMAGE Emergency Condition Indication (s) Classification 3 Core melt situations Any one of the following General Emergency sequences occurs with a concurrent likely failure of (EI 1300.05) containment imminent:

1. Either a small or large I LOCA occurs with a con-current failure of the ECCS to perform leading I 2.

to severe core degradation or melting A transient is initiated I by a loss of the main feedwater system followed by a failure of the emer-gency feedwater system '-

for an extended period with

.. core melting resulting

3. A transient occurs requiring operation of shutdown systems with

, failure to trip which results in core damage, or additional failures of core cooling and makeup I 4.

systems occur which lead to a core melt A failure of offsite and onsite power along with total loss of emer-gency feedwater makeup capability occurs for several hours which leads to a core melt

5. A small LOCA occurs with l3 initially successful ECCS, t E however a subsequent fail- 1 ure of RCS heat removal I systems over a period of several hours leads to a core melt

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19 EI 1300.01.3

. TABLE 1 LOSS OF FISSION PRODUCT BARRIERS Emergency l Condition Indication (s) Classi'ication Loss of 2 of 3 fission Any Two of the following General Emergency product barriers wills a conditions exist and the (EI 1300.05)

I potential loss of Llie 3rd barrier Third is inaninent:

1. Fuel clad is ruptured as indicated by grab sample results

2. A rupture of the RCS has been confirmed

3. Containment integrity has I been breached and cannot be restored 3 NOTE:

Ollier sections of Table I can be used for guidance in determining the above three conditions, as follows:

a. For i tein 1, refer to " Core Fuel Damage" at the Alert and Site Emergency levels for sample result values and indi-cations.

Nh b.

For item 2, refer to " Abnormal Primary Leak Rate" at the Alert and Site Emergency levels for indications of a loss of primary coolant.

c. For item 3, refer to " Safety System Functions" a Loss of Containment Integrity condition at the Unusual Event II level for indications of a breach in Containment integrity.

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20 EI 1300.01.3 TANLE 1 FUEL HANDLING ACCIDENT Emergency Condition Indication (s) Classification Fuel llandling Accident 1. Direct information from Alert

• which results in the fuel handling personnel (EI 1300.03) release of radioactivity indicating that an to Containment or Spent irradiated fuel assembly Fuel Pool area I has been damaged and radioactive gases are escaping AND I3 2. Fire Detection System /

Radiation Monitoring System (FDS/RMS) alarms I with high radiation monitor reading printed out on data logger -

I 3.

OR Local Radiation Monitoring Alarm Station alarms both I, audibly (horn) and visually 6

(green light goes OFF and

- red light comes ON) and is reported to the Control Room Fuel llandt ing Accident 1. Indications of fuel hand- Site Emergency

• I which results in SFAS uetuation ling accident which results in the release of radio-activity to Containment (El 1300.04) or Spent Fuel Pool area AND

2. SFAS incident level one actuation on radiation in Containment or isola-tion of ventilation in fuel handling area based on radiation E3 NOTE: For the above asterisked (*) classification (s), the plant can be in 5 any Mode for the listed EAL's to be applicabic.

2'1 El 1300.01.1 TABLE 1 ABNORMAL CONTAINMENT ATMOSPHERE Emergency l Condition Indication (s) Classification increasing Containment Any Two of the Following: Alert radiation, pressure, and 1. Containment high range (EI 1300.03)

I temperature monitor (s) (RE 2387 and/or RE 2389) indicate >104 mR/hr I 2.

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Containment pressure (P1 2000, PI2001, PI2002, PI 2003) indicates >17 psia

3. Containment average air temperature (TI1356, TI 1357, TI1358) indicates

>170*F

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liigh Containment radia- Any Two of the Following: Site Emergency tion, pressure and ,1,. Containment high range (EI 1300.04)

Lemin rature radiation monitor (s)

(RE 2387 and/or RE 2389) indicate >106 mR/hr 2.' Containment pressure (PI 2000, PI2001, PI2002, PI

, I 2003) indicates >20 psia

3. Containment average air temperature (TI1356, TI I 4.

1357, Til358) indicates

>200*F Safety Features Actuation I System (SFAS) functions have activated Very liigh Containment AnLTwo_,of the Following: Cencral Emergency radiation and pressure 1. Containment high range (EI 1300.05) radiation monitor (s)

I (RE 2387 and/or RE 2389) indicate >107 mmR/hr 1 2. Containment pressure (PI 2000, P12001, PI2002, P1 2003) indicates >40 psia

3. Safety Features Actuation I System (SFAS) functions have activated and Con-tainment Spray is operating I

l 22 EI 1300.01.3 TABLE 1 ABNORMAL EFFLUENT RELEASE Emergency Condition Indication (s) Classification 3l Effluent Release > limits Confirmed analysis results Unusual Event

• allowed by E.T.S. 2.4.1 or for a gaseous or liquid (EI 1300.02)

E.T.S. 2.4.3 release indicates > the limits given in the Environ-mental Technical Specifica-tions Effluent release >10 Confirmed analysis results Alert times instantaneous, for a gaseous or liquid (EI 1300.03) linits allowed by E.T.S. release indicates >10 2.4.1 or E.T.S. 2.4.3 times the instantaneous limits given in the Environ-mental Technical Specifica- -

tions

) NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

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TABLE 1 l HIGH RADIATION LEVELS IN PLANT Emergency Condition Indication (s) Classification General area radiation 1. Fire Detection System / Alert

• Icvels or high airhorne Radiation Monitoring radioactivity >1000 times (EI 1300.03)

System (FDS/RMS) Console normal from an unidentified Alarm with high radiation 3 source, lasting more than 30 monitor reading displayed minutes on CRT and printed out on I 2.

data logger OR Local Radiation Monitoring I Alarm Station alarms both audibly (Horn) and visually (green light goes off and I red light comes on) and is reported to the Control Roon ~

AND I 3. An irca radiation survey or airborne radioactivity sample indicates activity

, levels >1000 times normal 3 NOTE: For the above asterisked (*) classification (s) the plant can be in 1 any Mode for the listed EAL's tc be applicable.

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l 24 EI 1300.01.3 TABLE 1 I ABNORMAL RADIATION LEVELS AT SITE BOUNDARY Emergency Condition Indication (s) Classification Projected or actual 1. Station Vent Monitor Alert

• radiation readings that I indicate a potential dose of 100 mR Whole Body or 500 mR Child Thyroid at (RE2024C or 2025C) read-ing >0.1 pCi/cc Xe-133*

for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or readings (EI 1300.03)

NOTE: (These are which will give an equiv-I 3 the Site Boundary using adverse meteorology. 2.

valent dose in <2 hours Station Vent Monitor the appli-cable con-centrations, (RE2024B or 2025B) read- however they I ing >7.2 x 10-S pCi/cc I-131 for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or readings which will give an equivalent can not be obtained from the dose in <2 hours presently

• NOTE: This concentra- 3. Radiation Monitoring Team installed tion is based on reports radiation levels at instrumenta-a stability class Site Boundary <50 mR/hr for tioE.

I of F and wind speed of 2 mph; if actual ..

meteorology is used, an incident projected to last 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reports of read-are to be They used when the ings which will give an Kamen High I

this concentration equivalent dose in <2 hours range non-inay be higher 4. . Radiation Monitoring Team itors are reports I-131 concentrations installed.

• >1.1 x 10-7 pCi/cc at Site Boundary Projected or actual radia- 1. Grab sample, or Station tion readings that indi-Site Energency*

Vent Monitor (RE2024C or (EI 1300.04) cate a potential dose of 2025C) reading >1.0 pCi/cc

'I 3 1 rem Whole Body or 5 rem Child Thyroid at the Site Doundary using adverse Xe-133* for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or readings which will give an NOTE: (These are the appli-equivalent dose in <2 hours cable con-I meteorology. 2. Station Vent Monitor (RE2024B or 2025B) > 7.2 x 10-5 pCi/cc I-131 for centrations, however they can not be I 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or readings which will give an equivalent dose in <2 hours obtained from the presently

• NOTE: This concentra- 3. Radiation Monitoring Team I tion is based on a stability class reports radiation levels

>500 mR/hr at the site installed ins t rumer.t:-

tion. They of F and wind speed boundary for an incident are to be I of 2 mph; if actual meteorology is used, this concentration projected to last 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or which will give an equiv-used when the Kamen

{

) alent dose in <2 hours High range I

. ', i5 El 1300.01.3 TABLE 1 ABNORMAL RADIATION LEVELS AT SITE BOUNDARY Condition Emergency Indication (s) Classification may be higher 4. Radiation Monitoring Team monitors reports I-131 concentrations are in-

>1.1 x 10~' pCi/cc at the stalled.

Site Boundary NOTE:

13 For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

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26 EI 1300.01.3 TABLE 1 ABNORMAL RADIATION LEVELS AT SITE BOUNDARY Emergency Condition Indication (s) Classification Projected or actual site A radiological puff release Site Emergency

• boundary radiation readings (short instantaneous release (EI 1300.04)

I3 corresponding to a whole body dose of 50 mr/hr for from a non-continuous source) occurs with:

1/2 hour or 500 mr/hr for I 2 minutes using adverse meteorology or five times

1. Station vent monitor RE 2024C or 2025C readings and analysis indicating these levels for a thyroid 9.6 x 10-2 pCi/cc* for 1/2 I dose. hour or .96 pCi/cc* for 2 min.

• NOTE: These are the ap- OR I plicable concen-trations, however they cannot be ob-

2. Station vent monitor RE 2024B or 20253 readings and analysis indicate tained from the pre-I 7.2 x 10-s pCi/cc* for sently installed in- for 1/2 hour or 7.2 x stalled instrumenta- - 7.2 x 10-5 pCi/cc* for tion. They are to 2 min.

) used when the Kamen liigh range monitors .

are installed in

, the near future.

I Projected or actual site boundary radiation read-ing corresponding to a A radiological release occurs with:

1. Projected doses at the General Emergency *

(EI 1300.5) whole body dose of 1 R/hr site boundary equate to or a thyroid dose of 5 1 R/hr whole body or 5 R/hr using actual R/hr thyroid (or higher) '

meteorology. using actual meteoroligi-1 I cal data.

OR

2. A Radiation Monitori'ng 7eam '

s*

I at the site b'ounda'ty 4

• reports radiaT.i.on,levqls <. . . . . , .

at 1 R/hr or~ 2.27 x

• i

, g 10-5 pCi/cc~I-231 (or ,.

g higher). 6 -

NOTE: For the above asterisked (*) classification (s), the plant can be in 4 , any Mode for the listed EAL's to beLapplicable. ,

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57 EI 1300.01.3 TABLE 1 CONTAMINATED PERSONNEL Emergency Condition Indication (s) Classification Transportation of con- 1. Any event which requires Laminated injured in- Unusual Event

• transportation of a con- (EI 1300.02) dividual(s) offsite I taminated injured indi-vidual to an offsite medical facility I 3 NOTE:

For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

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28 EI 1300.01.3 TM 1 MAJOR STEAM LEAK Emergency Condition Indication (s) Classification Major Steam Leak with Increasing Containment pres-

,NO Primary to Secondary Unusual Event sure (if leak is inside Con- (EI 1300.02)

I leakage tainment) or unusually loud noise outside Containment And One of the Following:

I 1. Steam and Feedwater Rupture Control System (SFRCS) initiates

2. Main Steam Pressure (s) and/or Steam Generator Pressure (s) drop to <300 PSIG

\

Major Steam Leak with 1. Indication of a Major ~~

Alert I >10 CPM Primary to Secondary 1.cak Ra te ..

2.

Steam Leak AND Main Steam Line Radiation (EI 1300.03)

D - Monitor (s) (RE 600 and/or

, RE 609) in the " Analyze Mode" to detect N-16 indicate increased I* activity,

'AND

3. RCS Water Inventory Balance I3 4.

indicates >10 GPM Primary to Secondary leakage {

Main Steam line radiation monitors in the " Gross Mode" indicating more than I 15000 cpm net; background I equals 1000 cpm i Hajor Stesa Leak with 1. Indication of a Major Site Emergency

>50 GPM Primary to Steam Leak Secondary leak rate and (EI 1300.04) l AND fuel damage indicated 2. Main Steam Line radiation

E monitor (s) (RE 600 and/or E RE 609) in the " Analyze Mode" to detect N-16 i indicate increased j activity l AND I

0 El 1300,01,3 TABLE I I HMOR STEAM y Emergency Condition Indication (s) Classification

3. RCS Vater Inventory Balance indicates >50 GPM Primary I 4.

to Secondary Leak rate AND Confirmed Primary Coolant ,

j sample results indicate  :

Dose Equivalent'I-131 above acceptable limits of T.S. Figure 3.4-1 AND I3 5. Main steam line radiation monitors in the " Gross I Mode" indicating more than 150,000 cpm net; background equals 1,000 -

I cpm.

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30 EI 1300.01.3 TABLE 1 MAJOR ELECTRICAL FAILURES Emernency

! Condition Indication (s) Classification 3l Loss of offsite power 1. Both Emergency Diecel Unusual Event or of (nsite AC power Generators and the Main (EI 1300.02)

I capability Generator out of service simultaneously OR g 2. Loss of all three 345 XV E transmission lines 3l Loss of offsite power 1. All AC buses deenergized Site Emergency and all oasite.AC power more than 15 minutes for more than 15 rainutes (EI 1300.04) 3 Loss of all onsite 1. All DC buses deen- Alert 8l DC isower ergized as determined by breaker positions, and (EI 1300.03) i line voltage or amperage meters '

I Loss of all onsite DC 1. All DC buses deenergized Site Emergency power for more than 15 for more than 15 minutes i minutes (EI 1300.04) ll

!I

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r- - -

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31 EI 1300.01.3 TABLE 1 FIRE Emergency g Condition Indication (s) Classification Uncontrolled fire NOT 1. Any fire at the Station Unusual Event

• involving a safety that requires offsite system, but requiring (EI 1300.02) support offsite support I Uncontrolled fire potentially affecting sa fety systems and

1. Any fire at the Station that requires offsite Alert (EI 1300.03) support I requiring offsite support 2.

AND Has the potential to damage or degrade a safety system 3 Fire resulting in the 1. Observation of a major Site Emergency loss of redundant .. fire that defeats the (EI 1300.04) safety system trains capability of redundant or functions safety system trains Ni

. which includes both trains or functions

~

3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

o l

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32 EI 1300.01.3 TABLE 1 SECURITY THREAT Emergency Condition Indication (s) Classification Security Threat, Attempted 1. Report by a senior Unusual Event

• Entry, or Attempted member of the Security (EI 1300.02)

I Sabotage Force of an Attempted Entry, Attempted Sabotage, or a Security I Threat Ongoing Security 1. Report by a senior Alert

• Compromise member of the Security (EI 1300.03)

Force that a Security Emergency is in progress -

Imminent loss of physical 1. Physical attack on the Site Emergincy*

Il plant involving imminent control of the plant (EI 1300.04) '

.. occupancy of the Control 3

Room or local shutdown r

~

stations i ..

u Loss of physical control 1. Physical attack on the General Emergency

• I* of the facility plant which has resulted in occupation of the (EI 1300.05) 3l Control Room or local shutdown stations by unauthorized personnel 3 NOTE: For the above asterisked (*) classification (s), the plant can be in t

any Mode for the listed EAL's to be applicable.

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33 EI 1300.01.3 TABLE 1 HAZARDS TO STATION OPERATIONS Emergency Condition Indication (s)

I Aircraft crash onsite or 1. Control Room informed by Classification Unusual Event

• unusual aircraft activity Station personnel who have (EI 1300.02) over facility made a visual siting Aircraft crash affect- 1. Control Room informed Alert ing plant structures by Station personnel who (EI 1300.03) have made a visual siting I Aircraf t crash da= aging 1. Control Room informed by Site Emergency vital plant systems I Station personnel who have made a visual siting AND (EI 1300.04)

2. Instrumentation readings

'E on vital systems indicate 5

• equipment problems Train de'railment onsite 1. Control Room informed by Unusual Event

• Station personnel who have (EI 1300.02) made a visual siting I 3 2.

=

Station Structures have been damaged I 3.

OR Danger or potential danger to Station personnel exists I Onsite explosion Control Room informed by Unusual Event

• I Station personnel who have made a visual siting (EI 1300.02)

Onsite explosion affect- 1. Control Room informed by Alert ing plant operations Station personnel who have (EI 1300.03) made a visual siting I 2.

AND Instrumentation readings on plant systems indicate equipment problems NOTE: For the above asterisked (*) classification (s), the plant can be in gg any Mode for the listed EAL's to be applicable.

l .

34 EI 1300.01.3 TABLE 1 HAZARDS TO STATION OPERATIONS (Con't)

I Condition Indication (s)

Emergency Classification Explosion causing severe 1. Explosion causing either I damage to hot shutdown equipment of the following combina-tions of systems to become Site Emergency (EI 1300.04) inoperable:

I A. Makeup System and HPI System OR I B. Main Feedwater System and Auxiliary Feed water System 3 Toxic or flammable gas 1. Control Room informed by Unusual Event

• release from its con- Station personnel who (EI 1300.01) tainer to atmosphere at have discovered it life threatening levels ..

near or onsite Uncont' rolled toxic or 1. " Control Room informed by Alert flammable gas release Station personnel who have I' at life threatening levels within plant facilities made a visual siting OR (EI 1300.03)

2. Chlorination System Trouble Alarm initiates and Station i

personnel verify a signifi-cant release

.I Uncontrolled toxic or 1. Control Room informed by Site Emergency I flammable gas release at life threatening Icvels within plant vital areas Station personnel who have made a visual siting AND (EI 1300.04)

I 2. Chlorination System Trouble Alarm initiates and Station personnel verify a signifi-I 3.

cant release OR The Control Room Ventila-tion System automatically shuts down e

NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

EI 1300.01.0

'35 TABI.E 1 HAZARDS TO STATION OPERATIONS (Con't)

Emergency Condition Indication (s) Classification

~

Turbine damage causing Control Room informed by Alert casing penetration Station personnel who have (EI 1300.03) made a visual inspection of turbine casing Missile impact on plant Control Room informed by Alert structures Station personnel of any (EI 1300.03) miscile I Missile impact causing 1. Control Room informed by Site Emergency I severe damage to llot Shutdown equipment Station personnel of any missile impact on Hot Shut-down equipment (EI 1300.04)

~

I 2.

AND Instrumentation readings on Hot Shutdown equipment p .

indicate equipment problems 8

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36 EI 1300.01.3 TABLE 1 I NATURAL EVENTS (WITHIN OTTAWA COUNTY)

Emergency Condition Indication (s) Classification Any earthquake 1. Confirmed Station Seismic Unusual Event

• Instrumentation Alarm (EI 1300.02)

I 3 Earthquake > Operating 1. Procedure for Earthquake Alert Basis Earthquake (OBE)

I Icvels Evaluation (SP 1105.17) indicates earthquake >.08 g (EI 1300.03)

Earthquake > Safe 1. Procedure for Earthquake Site Emergency Shutdown Earthquake Evaluation (SP 1105.17)

(SSE) levels (EI 1300.04) indicates earthquake l

>.15 g I Any Tornado onsite 1.

Control Room informed by Station personnel who have made a visual siting of a Unusual Event.*

(EI 1300.02) p ,

Tornado crossing'the

, site boundary Tornado striking 1. Control Room informed by I~ facility Station personnel who have Alert (EI 1300.03) made a visual siting I 11urricane 1. Control Room informed Unusual Event *

!g l by Load Dispatcher of (EI 1300.02)

E Hurricane Watch for Ottawa County 3l l!urricane force winds up 1. Control Room informed by Alert to Design Basis Levels Load Dispatcher of (EI 1300.03) i I Hurricane striking Ottawa County AND

2. Wind speed indication from the station meteorological tower is of sustained winds approaching 90 mph 1I g NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

I

E *

. 37 EI 1300.01.4 TABLE 1 NATURAL EVENTS (WITHIN OTTAWA COUNTY) (Con't) .

Emergency Condition Indication (s) Classification 3l Hurricane force winds 1. Control Room informed by Site Emergency

> Design Basis Levels Load Dispatcher of (EI 1300.04)

Hurricane striking Ottawa I County AND

2. Wind speed indication from I the station meteorological tower of sustained winds above 90 mph 50 year flood or low 1. Control Room informed by Unusual Event

• 3 water, surge or Load Dispatcher seiche (EI 1300.02)

OR

2. Control Room informed by -

Station personnel who have

,, made visual siting AND

3. High Forebay level alarm p -

or lake level indication Ls ' oscillating with readings high (>580 feet I.G.L.D.)

or low (<565 Feet I.G.L.D.)

I-3 Flood, low water, surge 1. Control Room informed by I or seiche at Design Levels Load Dispatcher OR Alert (EI 1300.03)

2. Control Room informed by I Station personnel who have made visual siting AND

3. High Forebay level alarm or lake level oscillating with readings at Design Levels high (584 feet I.G.L.D.) or low 562.1 feet I.G.L.D.)

3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

f

EI 1300.01.3 3'8

TABLE 1 i q NATURAL EVENTS (WITHIN OTTAWA COUNTY) (Con't) f Emergency Condition Indication (s) Classification 3 Flood, low water, surge 1. Control Room informed Site Emergency or seiche > Design Levels by Load Dispatcher (EI 1300.04)

I .

,',2 .

OR Control Room informed by Station personnel who have made a visual siting

AND -

.3. High Forebay level alarm or lake level indication occillating with readings

> Design Levels high (>584 feet I.G.L.D.) or low l t (<562.1 feet I.G.L.D.)

ID .

\

END

EI 1300.03.0 Davis-Besse Nuclear Power Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.03 Alert

• Record of Approval and Changes I Prepared by~ G. J. Reed 5/30/80 Date i

Submitted by C. E. Wells 6/13/80 Section Head Date Recommended by

((Me~ h /3

, ERB Chairian 'Date QA Approved I/

({uality Assurance Manager Date Approved.by NO W 'M!hO StationSuperintendj4t Date j Revision SRB QA Sta. Supt.

No. Recommendation Date Approved Date Approved Da e

. / k Z y &/9 iv/r Wh" '+'et 3 Ae = _ _ g G/uja. gg Ton"= d

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l EI 1300.03.2

k. PURPOSE To outline the course of action and protective measures required to mitigate the consequences of Station emergency at the Alert level to safeguard Station personnel and the general public.

2. SCOPE Describes the actions and responsibilities of Davis-Besse per-I sonnel and offsite support groups in the event the Shift Supervisor declares an Alert as identified in the Emergency Plan Activation procedure, El 1300.01.

3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Station Response to Emergencies, EI 1300.00 3.3 Emergency Plan Activation, EI 1300.01 3.4 Protective Action Guidelines, AD 1827.12

4. DEFINITIONS 4.1 Alert - Events are in progress or have occurred which involve an actual or substantial degradation of the level of safety of DBNPS.

5. EMERGENCY MEASURES 5.1 Shift Supervisor The Shift Supervisor, having assumed the role of interim Emergency Duty Officer and having classified the emer-gency as an Alert, shall assure the following actions are taken as required (See Attachment 1):

5.1.1 Mdke the appropriate notifications or sound the appropriate alarm as necessary:

a. Fire

b. Containment Evacuation

c. Initiate Emergency Procedures 2 NOTE: The station alarm need not be sounded if downgrading from a higher classification.

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2 EI 1300.03.2 5.1.2 Announce the location, type and classification of the emergency on the Station public address system twice and make the appropriate announce- g ment as to the need for perscnnel assembly, a non-assembly, evacuation, or non-evacuation as the conditions dictate.

5.1.3 Notify the following individuals:

2 a. Nuclear Security Supervisor ,

b. Station Superintendent

1. During normal working hours, the Station Superintendent should be reached over the Station gai-tronics or telephone or by g utilizing his " beeper" pager. During off g normal working hours, manually telephone his office and home using the numbers a listed in Administrative Memorandum No. g

37. If there is no answer, then attempt a page. Upon being notified, the Station Superintendent shall then confer with the Shift Supervisor and ascertain the degree of response that may be necessitated by a plant event.

NOTE: If the Station Superintendent does NOT respond within five minutes, re-initiate the page.

2 If he fails to respond to a second page, the Assistant Station Superintendent, Opera- l tions, should be contacted. 5 If neither can be contacted, the Shift Supervisor should exercise his own judgement in dealing with the situation.

2. The Station Superintendent can then authorize the Shift Supervisor to tape an announcement on the Telephone Pager located in the Shift Supervisor's office.

(The Station Superintendent may elect to perform this evolution himself over the telephone. If so, the Station Superin- g tendent should call the Edison Operator 3 and request to be connected to the Telephone Pager.)

.F l

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3' EI 1300.03.2 NOTE: The announcement should include; 1) the Emergency Action Level classification,

2) the level of response required, and 3) a brief description of plant con-ditions.

3. The Shift Supervisor or his designee shall then activate the pagers of the key emergency response personnel as listed in Administrative Memorandum No. 37.

4. When paged (beeped), those individuals must telephone the Edison Operator who shall connect them with the Telephone I Pager thus allowing them to hear the recorded message.

I 5. Those individuals shall then " call in" or notify additional personnel as required to provide adequate response to the event by using Administrative Memorandum No.

37.

NOTE: The NRC resident inspector can be telephoned or paged in accordance with AD 1827.17 if necessary.

5.1.4 Notification of the following agencies must 2 occur:

NOTE: When notifying an outside agency, record the name of the individual contacted and request a return telephone call from the agency to verify notification 2 a. Sheriff's Department, Ottawa County, as soon as possible after the declaration is made (normal notification time is approximately 15 minutes)

b. NRC Region III, Office of Inspection and Enforcement; NRC, NRR, Emergency Incident Response Center, Bethesda, Maryland (This is I2 accomplished by the NRC Emergency Notifi-cation System - Red Phone) within one hour.

5.1.5 Continue in the capacity of interim Emergency Duty Officer until relieved by the assigned Emergency Duty Officer.

I I

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. II 4 EI 1300.03.0 '

5.1.6 Assessment actions which shall include:

a. Increased surveillance of in plant instru-mentation.

b. The dispatching of shift personnel to the identified problem area for confirmation and visual assessment of the problem.

c. The dispatching of onsite RMT's to monitor ,

for possible releases and to provide con-firmation of correct accident classification.

d. Surveillance (if a radiological accident is occurring) of the in plant instrumentation necessary to obtain meteorological and radio-logical data required for calculating or estimating projected doses. This dose assess-ment activity shall continue until termina-tion of the emergency in order that the updating of initial assessments may be pro-vided to all concerned offsite agencies and to the EDO.

5.1.7 Corrective actions by plant operators shall be according to established procedures that place the plant in a safe condition.

5.2 Emergency Duty Officer (EDO)

The Emergency Duty Officer, upon being informed that an Alert has been declared, shall:

5.2.1 Report to the Emergency Control Center and assume the position of Emergency Duty Officer in 3 the onsite emergency organization, relieving the g Shift Supervisor of this duty.

5.2.2 Evaluate the information, data, and methods utilized by the Shift Supervisor in making his determination in order to ensure that the proper emergency classification has been made.

5.2.3 Determine to what extent the offsite and onsite emergency organizations shall be activated.

a. For an Alert, the emergency teams shall be activated along with all or portions of the onsite emergency organization.

I

5' EI 1300.03.1 5.2.4 If the onsite organization is required and the need exists, activate the ECC according to the Emergency Control Center Activation Procedure, EI 1300.08.

5.2.5 Continue assessment actions initiated by the Shift Supervisor.

5.2.6 Recommend protective actions to the Ottawa I County Sheriff as required by assessment results per AD 1827.12, Protective Action Guidelines.

5.3 Shift Operations Personnel 5.3.1 Control Room operators shall maintain safe I operations of the Station and minimize the potential hazards to Station personnel and the general public as directed by the Shift Supervisor.

5.3.2 In the event that the Shift Supervisor is incapacitated, his duties and responsibilities indicated in Step 5.1 shall be assumed by the Assistant Shift Supervisor in the Control Room until relieved by a qualified Shift Supervisor.

p 5.3.3 Equipment and auxiliaries operators shall main-tain safe operations of the plant as directed by the Shift Supervisor.

5.3.4 The Shift Technical Advisor shall provide tech-nical and analytical support in the diagnosis of off-normal events. He shall also advise and assist the Shift Supervisor on matters per-taining to the safe and proper operation of the plant with regards to nuclear safety.

5.4 Shift Chemistry and Radiation Tester (C&RT)

I 5.4.1 The shift C&RT shall report immediately to the Health Physics Monitoring Room to await instruc-tions from the Shift Supervisor or Chemist and I

Health Physicist.

5.4.2 The shift C&RT shall provide radiological monitoring for the Fire Brigade in the event of a fire in RACA.

A 5.4.3 The shift C&RT shall monitor all injured per-sonnel before they leave the site. An off-shift C&RT shall accompany or meet the contaminated l personnel at the offsite medical facilities.

I 5.5 Fire Brigade 5.5.1 The Fire Brigade Captain shall respond to any I announced fire, evaluate the situation, direct 5 the Fire Brigade, and keep the Shift Supervisor infor=cd of the status of the fire.

5.5.2 Personnel assigned to the Fire Brigade shall respond to any announced fire with appropriate fire fighting and protective equipment and ,

extinguish the fire as directed by the Fire Brigade Captain.

5.5.3 The first Fire Brigade Captain arriving on the scene should remain in charge of the fire until termination of the emergency or relieved by the g Fire Chief or Assistant Fire Chief. g 5.6 First Aid Team 5.6.1 The First Aid Team Leader shall respond to any announced personnel injuries, evaluate the situation, direct the First Aid Team and keep the Shift Supervisor informed of the status of the injured individual (s).

5.6.2 Personnel assigned to the First Aid Team shall respond to any announced personnel injury with appropriato first aid supplies and provide the E necessary first aid treatment.

g 2 5.7 Nuclear Security Forco 5.7.1 The Nuclear Security Supervisor, upon notifica-tion by the Shift Supervisor that an Alert oxists, shall implement the Industrial Security g Plan Procedure, AD 1808.00. g 2 5.7.2 Nuclear Security Officers shall maintain security of the Station as directed by the Guard Supervisor.

5.8 Radiation Monitoring Team (RMT) 5.8.1 Normally only one RMT member should be from the C&HP Section.

5.8.2 During normal working hours:

2

1. Qualified RMT members who are not involved in immediate corrective actions shall report to the Radiological Testing Laboratory (RTL) or

7 EI 1300.03.2 the Emergency Control Center (ECC) for specific assignments.

2. RMT members are designated by the OSC Manager (Maintenance Engineer).

3. Onsite RMT's from the Chemistry & Health Physics Section should standby at the Health Physics Monitor Room for instructions from the Chemist & Health Physicist or his designee.

They should use the survey equipment and air samplers located adjacent to the Health Physics Monitor Room, if requested to do onsite surveys.

2 l3 4. Offsite RMT's requested by the Emergency Duty

,5 Officer (EDO) should report to the Emergency Control Center (ECC). They should then check

out the monitoring equipment in the Radiological Testing Laboratory and standby for further 4

instructions from the EDO.

5.8.3 During off-normal hours:

1. RMT member.s called in during an emergency p report to the Chemist & Health Physicist or EDO in the Davis-Besse Administration Building for assignment to an onsite or offsite RMT.

2. Check out the monitoring equipment and standby in the Radiological Testing Laboratory for further directions.

5.9 Onsite Personnel jg 5.9.1 Personnel, who do NOT have specifically assigned

E duties during an Alert, shall proceed to the fc11owing areas:

a. Personnel inside RACA shall proceed to the Health Physics Monitoring Room area and wait for further instructions.

b. Personnel in the Protected Area shall proceed to the Operations Support Center and wait for further instructions.

I

c. Personnel outside the Protected Area shall proceed to the Construction Office Build-ing and wait for further instructions.

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8 EI 1300.03.2 5.10 Offsite Personnel 5.10.1 Personnel offsite that are notified to report to the site shall proceed to the Emergency Control Center and then to their specifically assigned locations as required and conditions permit.

5.11 Offsite Agencies and Organizations 5.11.1 The Carroll Township Ambulance Service shall ,

provide transportation service as required for offsite medical treatment.

5.11.2 The H. B. Magruder Memorial Hospital shall provide offsite medical treatment for personnel I

as required.

5.11.3 The Carroll Township Fire Department shall provide primary response to fire alarms onsite at required,

a. The Village of Oak Harbor Fire Department shall provide alternate response to fire alarms onsite as required through mutual aid with Cerro11 Township.

1 5.11.4 The Ottawa County Sheriff's Department is experienced in providing area control, com-munications assistance, and direct handling of g the local population, including evacuation, g should it become necessary. The Sheriff's Department provides 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radio communication coverage with the Shift Supervisor at DBNPS and is the lead offsite governmental agency contacted in the event of an emergency at the site.

6. TERMINATION 6.1 The Emergency Duty Officer and Station Operations Manager have joint responsibility for determining and declar-ing when the emergency situation is stable.

6.2 The Emergency Duty Officer shall assure notification of all offsite organizations and TECo personnel that the emergency has terminated.

2 6.3 A written summary will follow notification of termination within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

JI

I

, . 9. El 1300.03.2 ED0/ SHIFT SUPERVISOR CHECKLIST FOR ALERT NITACHMEhT 1 NOTE: If changing from a prior emergency classification checklist, com-plate str.ps NOT already accomplished by the previous checklist.

Then attach all the previous checklists used to this one. Place N/A in stops that are not applicable.

ACTION COMPLETED M,"I'!ON REQUIRED DATE TIME INITIALS

1. Initiate corrective action as required

2. Make the appropriate announce-ment or sound the appropriate alarm I 2 NOTE: This step may be omitted when dcwngrading from a higher classification.

3. Announco locnLion, type of .

omurgency cn Gui-tronics twice and make the appropriate announce-ment as to personnel assembly as required

4. Confirm Emergency Classification (See El 1300.01)

5. Conduct necessary notification:

2 a. Nuclear Security Super-visor (Ext. 556 or 557)

NOTE: 'In the event of a fire, the Nuclear Security Supervisor notifies the Ottawa County Sheriff who notifies the appropriate department.

b. Edison Controx Operator (Ext.88-000 or 259-5000)

'E NOTE: In the event of a medical emergency, the Edison

,3 Operator notifies the medical authorities and appropriate company management.

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. . 10 EI 1300.03.2 EDO/ SHIFT SUPERVISOR CHICKLIST FOR ll ALERT (Con't)

ATTACHMENT 1 ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS

c. Station Management ,

(See Step 5.1.3(b) of this procedure)

1. Station Superin-l tendent NOTE: The Station Superintendent or his designee is responsible for notifying the Ottawa County Sheriff upon declaration of an Emergency Action Level.

2. The Key Emergency Response Personn.1:

Emorgency Duty Officer, Assistant Station Superin-Londent Operations, Chemist and Health Physicist, Nuclear Services Director, Emergency Planning Super-visor, Nuclear Security Manager, News Media Relations Supervisor, Technical Engineer, Maintenance Engineer, -

~

and Operations Engineer.

d. *NRC (use the Emergency Notification System

- Red Phone) 2

• NOTE: NRC notification must be made within one hour I and should be made by station management. Health physics information should be transmitted using the NRC Health Physics Network by the Chemist and Health Physicist or his designee. (Dial 22 for NRC Headquarters - 23 for NRC Region 3 Office.)

6. Perform applicable steps of the ECC checklist (Attachment 3 of EI 1300.08 Emorgency Control Centor Activation)

7. Cantor Activation

a. Emergency Control Center (EI 1300.08)

l 11 EI 1300.03.1 1

ED0/ SHIFT SUPERVISOR CHECKLIST FOR ALERT (Con't)

ATTACHMEST 1 ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS 1 b. Operations Support Center (EI 1300.06)

Technical Support I

c.

Center (EI 1300.07)

8. Conduct Periodic Updates for:

a. TECo Personnel

b. NRC

c. Ottawa County Sheriff

9. As conditions change, check EI 1300.01 to dotermino if reclassificat. ion is appro-priate

10. When the condition is resolved notify:

a. TECo Personnel

b. NRC

c. Ottawa County Shoriff l

l l

Reviewed by Filed by l Station Superintendent Emergency Planning Supervisor END J

EI 1300.05.0 Davis-Besse Nuclear Power Station Unit No. 1 i

Emergency Plan Implementing Procedure EI 1300.05 General Emergency '

Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date I Submitted by C. E. Wells 6/13/80 Section Head Date Recommended by '

388v+r h/ h ,

SRB Chairc.af 'Date QA Approved //!8 Qua*Litj Assurance Manager Date Approved.by M N < ' b/N Station Superintendent d Date Revision SRB QA Sta. Supt.

No. Recommendation Date Approved Date Approved Date

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1 EI 1300.05.0 '

1. PURPOSE To outline the course of action and protective measures required to mitigate the consequences of a station emergency at the General Emergency level to safeguard Station personnel and the general public.

2. SCOPE Describes the actions and responsibilities of Davis-Besse per-sonnel and offsite support groups in the event of the Shift Super-visor declares a General Emergency in accordance with the Emergency Plan Activation procedure, EI 1300.01.

3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Station Response to Emergencies, EI 1300.00 3.3 Emergency Plan Activation, EI 1300.01 3.4 Emergency Offsite Dose Estimates, AD 1827.10 3.5 Protoctivu Action Guidelines, AD 1827.12

4. DEFINITIONS 4.1 General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degrada-tion or melting with the potential for loss of contain-ment integrity, and/or involve the potential release of radioactive particulates or gases offsite of a magnitude to exceed regulatory limits.

5. Et!ERGENCY t!EASURES 5.1 Shift Supervisor The Shift Supervisor, having assumed the role of interim Emergency Duty Officer and having classified the emer-gency as a General Emergency, shall assure the following actions are taken as required (See Attachment 1).

I 5.1.1 Make the appropriate notificat ions or sound the appropriate alarm as necessary:

I a. Fire i b. Containment Evacuation

c. Initiate Emergency Procedures

2 EI 1300.05.2

• 2 NOTE: The station alarm need not be sounded if downgrading from a high classification.

5.1.2 Announce the location, type and classification of the emergency on the Station public address system twice and make the appropriate announce-ment as to the need for personnel assembly, non-assembly, evacuation, or non-evacuation as the conditions dictate. ,

5.1.3 Notify the following individuals:

2 a. Nuclear Security Supervisor

b. Station Superintendent l

1. During normal working hours, the Station Superintendent should be reached over the Station gai-tronics or by utilizing his a

" beeper" pager. During of f normal work-ing hours, manually telephone his office [

and home using the numbers listed in Administrative Memorandum No. 37. If there is no answer, then attempt a page.

Upon being notified, the Station Super-intendent shall then confer with the Shift Supervisor and ascertain the degree of response that may be necessitated by the plant event.

NOTE: If the Station Superintendent does NOT respond within five 2

minute, re-initiate the page.

If he does not respond to a second page, the Assistant Station Supervisor, Operations, g should be contacted. If E neither respond, the Shift Supervi.or should use his own judgment to deal with the situation.

2. The Station Superintendent can then authorize the Shift Supervisor to tape an announcement on the Telephone pager located in the Shift Supervisor's office. g (The Station Superintendent may elect to g perform this evolution himself over the telephone. If so, the Station Superin-i

I 3 EI 1300.05.2 tendent should call the Edison Operator and request to be connected to the Telephone Pager.)

I NOTE: The announcement should include; 1) the Emergency I Action Level classification,

2) the level of response required, and 3) a brief I description of plant con-ditions.

I 3. The Shift Supervisor or his designee shall then activate the pagers of the key emergency response personnel as listed in Administrative Memorandum No. 37.

4. When paged (beeped), those individuals must telephone the Edison Operator who I shall connect them with the Telephone Pager thus allowing them to hear the recorded message.

5. These individuals shall then " call in" or notify additional personnel as required l to provide adequate response to the event

! by using Administrative Memorandum No.

l 37.

I NOTE: The NRC resident insepctor can be telephoned or paged in accordance with AD 1827.17 if necessary.

5.1.4 Notification of the following agencies must 2 occur:

lE NOTE: When notifying an outside agency, record i

the name of the individual contacted and request a return telephone call from the agency to verify notification.

2 a. Sheriff's Department, Ottawa County, as soon as possible after a declaration is made (normal time is approximately 15 minutes)

I b. NRC Region III, Office of Inspection and Enforcement; NRC, NRR, Emergency Incident Response Center, Bethesda, Maryland (This is accomplished by the NRC Emergency Notifica-tion System - Red Phone) within one hour.

I

. g

. . . m 4 EI 1300.05.0 5.1.5 Continue in the capacity of interim Emergency Duty Officer until relieved by the assigned l Emergency Duty Officer.

5.1.6 Assessment actions which shall include:

a. Increased surveillance of in plant instru-mentation.

b. Dispatching of shift personnel to the identi-fied problem area for confirmation and visual l)

Bi assessment of the problem.

)

c. Dispatching of onsite RMT's to monitor for  !

possible releases.

d. If a radiological accident is occurring, surveillance of the in plant instrumentation necessary to obtain meteorological and radio-logical data required for calculating or estimating projected doses. This dose assess-ment activity shall continue until termina-tion of the emergency in order that the updating of initial assessments may be pro-vided to all concerned offsite agencies and .

y to ths EDO.

I t

e. Greater emphasis on offsite monitoring  ;

efforts and dose projection efforts extending to distances much further from the plant.

Additionally, since the projected doses are likely to be much closer to the EPA PAG's, greater emphasis shall be placed on the g assessment of release duration. g Dose assessment shall be in accordance with the Emergency Offsite Dose Estimates Pro-cedure, AD 1827.10.

f. Should any potential danger to the general public be determined, a precautionary evacua-tion out to two (2) miles may be recommended.

5.1.7 Corrective actions by plant operators shall be according to established procedures that place the plant in a safe condition.

5.2 Emergency Duty Officer (EDO)  !

l The Emergency Duty Officer, upon being informed that an l General Emergency has been declared, shall-  !

l 1

I '

I 3 EI 1300.05.1 5.2.1 Report to the Emergency Control Center and assume the position of Emergency Duty Officer in i the onsite emergency organization, relieving the '

Shift Supervisor of this duty.

5.2.2 Evaluate the information, data, and methods utilized by the Shift Supervisor in making his I determination in order to ensure that the proper emergency classification has been made.

I 5.2.3 Activate the ECC according to the Emergency Control Center Activation procedure, EI 1300.08.

I 5.2.4 Continue assessment actions initiated by the Shift Supervisor.

I 1 5.2.5 Confer with the Emergency Operations Manager concerning distribution of a thyroid blocking agent to those TECo emergency workers involved in the Station response as specified in AD 1827.12, Protective Action Guidelines.

5.2.6 Recommend protective actions to the Ottawa I County Shoriff as required by assessment results per AD 1627.12, Protective Action Gaidelines.

5.3 Shift Operations Personnel 5.3.1 Control Room operators shall maintain safe operations of the Station and minimize the I potential hazards to Station personnel and the general public as directed by the Shift Super-visor.

5.3.2 In the event that the Shift Supervisor is 1

incapacitated, his duties and responsibilities indicated in Step 5.1 shall be assumed by the I Assistant Shift Supervisor in the Control Room until relieved by a qualified Shift Supervisor.

5.3.3 Equipment and auxiliaries operators shall main-tain safe operations of the plant as directed by the Shift Supervisor.

5.3.4 The Shift Technical Advisor shall provide tech-nical and analytical support in the diagnosis of off-normal events. He shall also advise and assist the Shift Supervisor on matters per-taining to the safe and proper operation of the plant with regards to nuclear safety.

5.4 Shift Chemistry and Radiation Tester (C&RT) lI I

6 EI 1300.05.2

• 5.4.1 The shift C&RT shall report immediately to the Health Physics Monitoring Room to await instruc-tions from the Shift Supervisor or Chemist and Health Physicist.

5.4.2 The shift C&RT shall provide radiological monitoring for the Fire Brigade in the event of a fire in RACA.

5.4.3 The shift C&RT shall monitor all injured per- ,

sonnel before they leave the site. An off-shift C&RT shall accompany or meet the contaminated personnel at the offsite medical facilities.

5.5 Fire Brigade 5.5.1 The Fire Brigade Captain shall respond to any g announced fire, evaluate the situation, direct 3 the Fire Brigade, and keep the Shift Supervisor informed of the status of the fire.

5.5.2 Personnel assigned to the Fire Brigade shall respond to any announced fire with appropriate I fire fighting and protectivo equipment and extinguish the fire as directed by the Fire Brigade Captain.

5.5.3 The first Fire Brigade Captain arriving on the scene should remain in charge of the fire until termination of the emergency or relieved by the Fire Chief or Assistant Fire Chief.

5.6 First Aid Team 5.6.1 The First Aid Team Leader shall respond to any announced personnel injuries, evaluato the situation, direct the First Aid Team and keep g the Shift Supervisor informed of the status of g the injured individual (s).

5.6.2 Personnel assigned to the First Aid Team shall respond to any announced personnel injury with appropriate first aid supplies and provide the necessary first aid treatment.

2 5.7 Nuclear Security Force 5.7.1 The Nuclear Security Supervisor, upon notifica-tion by the Shift Supervisor that a General Emergency exists, shall implement the Industrial Security Plan Procedure, AD 1808.00.

I I

. 7 EI 1300.05.2 l 5.7.2 Nuclear Security Officers shall maintain security of the Station as directed by the Guard Super-visor.

5.8 Radiation Monitoring Team (RMT) 5.8.1 Normally only one RMT member should be from the C&HP Section.

5.8.2 During normal working hours:

1. Qaalified RMT members who are not involved in I immediate corrective actions shall report to the Radiological Testing Laboratory (RTL) or the Emergency Control Center (ECC) for specific assignments.

2. RMT members are designated by the OSC Manager (Maintenance Engineer).

3. Onsite RMT's from the Chemistry & Health l

Physics Section should standby at the Health Physics Monitor Room for instructions from the Chemist & Health Physicist or his designee.

They should use the survey equipment and air samplers located adjacent to the Health Physics Monitor' Room, if requested to do onsite surveys.

2

4. Offsite RMT's requested by the Emergency Duty Officer (EDO) should report to the Emergency i Control Center (ECC). They should then check I out the monitoring equipment in the Radiological l Testing Laboratory and standby for further instructions from the EDO.

5.8.3 During off-normal hours:

! 1. RMT members called in during an emergency report to the Chemist & Health Physicist or EDO in the Davis-Besse Administration Building for assignment to an onsite or offsite RMT.

I i

2. Check out the monitoring equipment and standby in the Radiological Testing Laboratory for 3 further directions.

l l 5.9 Plant Staff Members of the plant staff that have been informed of a Site Emergency shall proceed to their designated loca-tions and perform their assigned functions.

t I

8 EI 1300.05.0 5.9.1 The Plant Operations Manager shall proceed to the Control Room. He shall direct plant opera-tions and plant damage control efforts. He shall g also keep the Station Operations Manager advised W of plant operations and plant damage control efforts.

I 5.9.2 The Operations Engineer shall proceed to the Control Room. His functicns are to supervise control room activities, to perform on-the-spot operational analysis as required to assist the Shift Supervisor, and keep the Plant Operations Manager informed of current plant conditions.

5.10 Onsite Personnel 5.10.1 Personnel, who do NOT have specifically assigned duties during'a Site Emergency, shall proceed to the following areas:

1

a. Personnel inside RACA shall proceed to the Health Physics Monitoring Room area and wait for further instructions.

b. Personnel in the Protected Area shall proceed to the Operations Support Center and wait for further instructions.

c. Personnel outside the Protected Area shall proceed to the Construction Office Building and wait for further instructions.

5.11 Offsite Personnel 5.11.1 Personnel offsite that are notified to report to the site shall proceed to the Emergency Con- g trol Center and then to their specifically 3 assigned locations as required and conditions permit.

5.12 Offsite Agencies and Organizations 5.12.1 The Carroll Township Ambulance Service shall provide transportation service as required for offsite medical treatment.

5.12.2 The H. B. Magruder Memorial Hospital shall provide offsite medical treatment for personnel as required.

JI I

I .

. .9 EI 1300.05.2 5.12.3 The Carroll Township Fire Department shall '

provide primary response to fire alar =s onsite '

as required.

a. The Villago of Oak Harbor Firo Department shall provide alternate response tc fire alarms onsite as required through mutual aid with Carroll Township.

5.12.4 The Ottawa County Sheriff's Department is experienced in providing area control, com-munications assistance, and direct handling of the local population, including evacuation, should it become necessary. The Sheriff's Department provides 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radio communication coverage with the Shift Supervisor at DBNPS and is I the lead offsite governmental agency contacted in the event of an emergency at the site.

6. TERMINATION 6.1 The Emergency Duty Officer and Station Operations Manager have joint responsibility for determining and declar-ing when the emergency situation is stable.

6.2 The Emergency Duty Officur shall assuro notification

[_ of all offsite organizations and TECo personnel that L- the emergency has terminated.

6.3 A written s"--ary will follow notification of termination I2 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

I

[

l

, ,10 EI 1300.05.2 ED0/ SHIFT SUPERVISOR CHECKLIST FOR GENERAI. EMERGENCY ATTAC}DIENT 1 NOTE: If changing from a prior emergency classification checklist, com-place steps NOT already accomplished by the previous checklist.

Then attach all the previous checklists used to this one. Place N/A in steps that are not applicable. ,

ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS

1. Initiate corrective action as required

2. Make the appropriate announce-ment or sound the appropriate g alarm l

2 NOTE: This step may be omitted when downgrading from a higher clos.sification.

'J . Announco location, typo of omorgency on Gai-tronics twice and make the appropriate announce-mont as to personnel assembly as 2 required. Announco no eating, drinking, or smoking until further notico.

4 Confirm Emergency Classification (See EI 1300.01) ,

S. Conduct necessary notification:

2 a. Nuclear Security Super-visor (Ext. 556 or 557) l l

NOTE: In the event of a fire, the Nuclear Security 1

, Supervisor notifics the Ottawa County Sheriff who I l

I notifies the appropriate department.

E b. Edison Contrex Operator 2 (Ext.88-000 or 259-5000)

NOTE: In the event of a medical emergency, the Edison l Operator notifies the medical authorities and appropriate company manage =ent.

l

o I '

c

, ,l a El 1300.05.2 ED0/SHIIT SUPERVISOR CHECKLIST FOR GENERAL EXERGESCY ATTAC101ENT 1 (Con' t)

ACTION COMPLETED .

ACTION REQUIRED DATE TIME INITIALS

c. Station Management I (See Step 5.1.3(b) of this procedure)

I 1. Station Superin-tendent NOTE: The Station Superintendent or his designee is responsible for notifying the Ottawa County Sheriff upon declaration of an Emergency Action Level.

2. The Key Emergency Response Personnel:

I 't F.morgency Duty Officor, Assistant Station Superin-Lundant Operations, Chemist and Health qhysicist, Nuclear Services Director, Emergency Planning Super-visor, Nuclear Security Manager, News Media Relations Supervisor, Technical Engineer, Maintenance Engineer, .

and Operations Engineer.

d. *NRC (uso the Emorgency Notification System

- Red Phone) 2

• NOTE: The NRC notification must be made within one I hour and should be nado by station management.

Health physics information should bo transmitted using the NRC Health Physics Network by the Chemist and Health Physicist or his designee.

I (Dial 22 for NRC Headquarters - 23 for NRC Region 3 Office.)

I 6. Perform applicable steps of the ECC chocklist (Attachment 3 o f F.1 1300.06, Emorgency Control Center Activation)

7. Center Activation Confirmation

~

, , . 12 EI 1300.06.0 ED0/ SHIFT SUPERVISOR CHECKLIST FOR GENERAL EMERGENCY NITACHMENT 1 (Con't)

ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS

a. Emergency Control Center ,

(EI 1300.08)

b. Operations Support Center (EI 1300.06)

c. Technical Support Center E

(EI 1300.07) E

d. Emergency Support Center E (EI 1300.09) E

8. Conduct Periodic Updates for:

a. TED Personnel

b. NRC

c. Ottawa County Sheriff

9. As conditions change, check EI 1300.01 to determine if reclassification is appro-priato

10. When the condition is resolved notify:

a. TED Personnel

b. NRC

c. Ottawa County Sheriff E

Reviewed by Filed by -

~

Station Superintendent Emergency Planning -

Supervisor END

l f s l s 1

.' I DAVIS-BESSE REVISION COVER SHEET b( g July 12, 1982 DATE TO: fho &/ Wut, be FYUt%

(/ V FROM: EMERGENCY PLANNING & PREPAREDNESS SUPV,

SUBJECT:

Davis-Besse EMERGENCY PLAN IMPLEMENTING PROCEDURES Manual Changes This letter transmits additions and revisions to the Davis-Besse EMERGENCY PLAN IMPLEMENTING PROCEDURES Manual. Control Copy d .

Instructions for the material are as follows:

REMOVE AND RETURN INSERT Revision Index, Revision 12 Revision Index, Revision 13 EI 1300.02.1 EI 1300.02.2 - -

T-6015 EI 1300.04.1 EI 1300.04.2 T-6060 EI 1300.07.1 EI 1300.07.2 T-6074 T-6016 EI 1300.08.2 EI 1300.08c3 T-6051 T-6041 T-5849 EI 1300.10.0 EI 1300.10.1 T-6017 Date Revision Entered Addressee Signature RETURN TO THE OFFICE MANAGER - STOP#30h0

%(. .

T 7~

THE TOLEDO EDISON CCMPANY

. DAVIS-BESSE NUCLEAR POWER STATICN

,, EERGENCY PLAN IMPLEMENTING PROCEDURES REVISION INDEX 4

m PAGE REVISION PROCEDURES REVISICN TDfPORARY MODIFICAT':NS i 0 EI 1300.00 2 3

EI 1300.01

, EI 1300.02 2 2

EI 1300.03 ,

EI 1300.04 2 2

EI 1300.05 EI 1300.06 2

~

ms EI 1300.07 2 EI 1300.08 3 EI 1300.09 0 m .

EI 1300.10 1 y EI 1300.11 0 T-6018 EI 1300.12 1 T-5850, T-5918 0

3 i i U

, Revision 13 L July, 1982

, El 1300.02.0 Davis-Besse Nuclear Power Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.02 ,

Unusual Event

• I .

I .

Record of Approval and Changes I

Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. Wells 6/13/80 -

Section Head D te Recommended by

~ '

[ /d Chair 6.an h M [0 S Date ,

QA Approved

~

[

Quality Assurance Manager Date Approved.by C / &/N

\f 9 StationSuperintenden$ Date I Revision No.

SRB Recommendation Date QA Approved Date Sta. Supt.

A roved Date

/ f Nf" $f/ &

l p png Giuln $ fr T" "' " s ' '

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i 1 EI 1300.02.2

1. PURPOSE J

To outline the course of action and protective measures required to mitigate the consequences of a Station emergency at the Unusual Event level to safeguard Station personnel and the general public.

2. SCOPE Describes the actions and responsibilities of Davis-Besse per-sonnel and offsite support groups in the event the Shift Super- ,

visor declares an Unusual Event in accordance with the Emergency Plan Activation procedure, EI 1300.01.

3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Station Response to Emergencies, EI 1300.00 3.3 Emergency Plan Activation, EI 1300.01 3.4 First Aid Response, AD 1827.02 '-

3.5 Protective Action Guidelines, AD 1827.12

4. DEFINITIONS

, 4.1 Unusual E~ents v - Event (s) are in progress or which occurred that indicate a potential degradation of the level of safety of DBNPS.

5. EMERGENCY MEASURES 5.1 Shift Supervisor The Shift Supervisor, having assumed the role of interim Emergency Duty Officer and having classified the emer-gency as an Unusual Event, shall assure the following actions are taken as required (See Attachment 1):

5.1.1 Make the appropriate notifications or sound the appropriate alarm as necessary:

I a. Fire

b. Containment Evacuation

, c. Initiate Emergency Procedures

-2 NOTE: The station alarm need not be sounded if downgrading from a higher classification.

~ ~

. V .

2 EI 1300.02.2 '

5.1.2 Announce the location, type and classification of the emergency on the Station public address i

system twice and make the appropriate announce-ment as to the need for personnel assembly, non-assembly, evacuation, or non-evacuation as the conditions dictate.

5.1.3 Notify the following individuals: 1 2 a. Nuclear Security Supervisor I

b. Station Superintendent

, 1. During normal working hours, the Station Superintendent should be reached over the Station gai-tronics or telephone or by utilizing his " beeper" pager. During off normal working hours, manually telephone his office and home using the numbers listed in Administration Memorandum No.

37. If there is no answer, then attempt a page. Upon being notified, the Station. g Superintendent shall then confer with the g Shift Supervisor and ascertain the degree of response that may be necessitated by a plant event.

NOTE: If the Station Superintendent does NOT respond within five minutes, re-initiate the page.

2 If a second page fails, the Assistant Station Superintendent, Operations', should be contacted.

In the event that neither can be contacted the Shift Super-i visor should exercise his own judgement in dealing with the situation.

2. The Station Superintendent can then l authorize the Shift Supervisor to tape an announcement on the Telephone Pager g located in the Shift Supervisor's office.

(The Station Superintendent may elect to g

perform this evolution himself over the telephone. If so, the Station Superin-l tendent should call the Edison Operator l E

[ and request to be connected to the Telephone Pager.)

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3 EI 1300.02.2  :

Im NOTE: The announcement should include; 1) the Emergency I Action Level classification,

2) the level of response required, and 3) a brief description of plant con-ditions.

3. The Shift Supervisor or his designee I shall then activate the pagers of the key emergency response personnel as listed in Administrative . Memorandum No. 37.

4. When paged (beeped), those individuals must telephone the Edison Operator who shall connect them with the Telephone

.I Pager thus allowing them to hear the recorded message.

i

5. These individuals shall then " call in" c:

notify additional personnel as required to provide adequate response to the event I .

by using Administrative Memorandum No.

37.

NOTE: The NRC resident inspector can be telephoned or paged in accordance with AD 1827.17 if necessary.

5.1.4 Notification of the following agencies must 2 occur:

NOTE: When notifying an outside agency, record the name of the individual contacted and I request a return telephone call from the agency to verify notification.

2 a. Sheriff's Department, Ottawa County, as soon I as possibic after the declaration is made (normal time is approximately 15 minutes)

I b. NRC Region III, Office of Inspection and Enforcement; NRC, NRR, Emergency Incident Response Center, Bethesda, Maryland (This is accomplished by the'NRC Emergency Notifi-2 cation System - Red Phone) within one hour.

5.1.5 Continue in the capacity of interim Emergency I Duty Officer until relieved by the assigned Emergency Duty Officer.

. v

+

4 EI 1300.02.2 -

5.1.6 Assess the situation by monitoring Control Room  ;

and other plant instrumentation; e

a. Assessment of a fire shall be performed by E' the individual discovering it. Confirmation should be made by the Fire Brigade Captain with recommendations to the Shift Supervisor 2 or Emergency Duty Officer. Refer to EP 1202.35

. g

b. Assessment of the condition of an injured E individual and recommendations for care shall be made by the First Aid Team Leader in g accordance with First Aid Response, AD gl'

, 18'7.02.

5.1.7 Corrective actions by plant operators shall be according to established procedures that place the plant in a safe condition.

. 5.2 Emergency Duty Officer (EDO)

The Emergency Duty Officer, upon being informed than an.

Unusual Event has been declare, shall:

5.2.1 EvaTuate the information, data, and methods utilized by the Shift Supervisor in making his determination in order to ensure that the proper emergency classification has been made.

5.2.2 Determine to what extent the offsite and onsite E emergency organizations shall'bc activated.

a. For an Unusua) Svent, part of the onsite emergency ortanization and' emergency teams may be activ.ted or, depending on the cir-cumstances, notification of key individuals may be all that is required.

5.2.3 Report to the Emergency Control Center if required and assume the position of Emergency Duty Officer in the onsite emergency organiza-tion, relieving the Shif t Supervisor of this duty.

5.2.4 If the need exists, activate the ECC according to the Emergency Control Center Activation Procedure, EI 1300.08.

5.2.5 Continue radiological assessment actions 3 initiated by the Shift Supervisor.

E

F .

5 EI 1300.02.1 5.2.6 Recommend protective actions to the Ottawa County Sheriff if required by assessment results per AD 1827.12, Protective Action Guidelines.

5.3 Shift Operations Personnel 5.3.1 Control Room operators shall maintain safe operations of the Station and minimize the potential hazards to Station personnel and the I 5.3.2 general public as , directed by the Shift Supervisor.

In the event that the Shift Supervisor is incapacitated, his' duties and responsibilities I ' indicated in Step 5.1 shall be assumed by the Assistant Shift Supervisor in the Control Room until relieved by a qualified Shift Supervisor.

5.3.3 Equipment and auxiliaries operators shall main-tain safe operations of the Station as directed

_ by the Shift Supervisor.

5.3.4 The Shift Technical Advisor shall provide tech-nical and analytical support in the diagnosis of off-normal events. He shall also advise and as'slst the Shift Supervisor on matters per-taining to the safe and proper operation of the

. plant with regards to nuclear safety.

5.4 Shift Chemistry and Radiation Tester (C&RT) 5.4.1 The shift C&RT shall repor't immediately to the Health Physics Monitoring Room to await instruc-I tion from the Shift Supervisor or Chemist and Health Physicist.

5.4.2 The shift C&RT shall provide radiological I monitoring for the Fire Brigade in the event of a fire in RACA.

5.4.3 The shift C&RT shall monitor all injured per-I1 sonnel before they leave the site. An off-shift C&RT shall accompany or meet the contaminated personnel at the offsite medical facilities.

5.5 Fire Brigade I

• 5.5.1 The Fire Brigade Captain shall respond to any announced fire, evalucte the situation, direct the Fire Brigade, and keep the Shift Supervisor informed of the status of the fire.

~- 9 m

. 1 6 EI 1300.02.2 .

5.5.2 Personnel assigned to the Fire Brigade shall respond to any.. announced fire with appropriate fire fighting and protective equipment and extinguish the fire as directed by the Fire Brigade Captain.

5.5.3 The first Fire Brigade Captain arriving on the scene should remain in charge of the fire until termination of the emergency or relieved by the Fire Chief or Assistant Fire Chief.

5.6 First Aid Team 5.6.1 The First Aid Team Leader shall respond to any announced personnel injuries, evaluate the I

situation, direct the First Aid Team and keep l the Shift Supervisor informed of the status of the E injured individual (s).

. 5.6.2 Personnel assigned to the First Aid Team shall respond to any announced personnel injury with appropriate first aid supplies and provide the-necessary first aid treatment.

2 5.7 Nuclear Secu'r'ity Force

. 5.7.1 The Nuclear Security Supervisor shall implement the Industrial Security Plan, AD 1808.00, upon notification of a security threat, attempted unauthorized entry, or attempted sabotage.

2 5.7.2 Nuclear Security Officers shall maintain security of the Station as directed by the Nuclear Security Supervisor.

l 5.8 Onsite Personnel Onsite personnel, who do NOT have specifically assigned duties during an Unusual Event, shall proceed according to the directions given by the Shift Supervisor over the Station public address system.

5.9 Offsite Personnel Offsite personnel that are notified to report to the site shall proceed to the Emergency Control Center. Further g

directions will be given upon arrival. E 5.10 Offsite Agencies and Organizations

s

, 7 EI 1300.02.2 5.10.1 The Carroll Township Ambulance Service shall provide transportation service as required for offsite medical treatment. .

5.10.2 The H.B. Magruder Memorial Hospital shall pro-vide offsite medical treatment for personnel as I

required.

5.10.3 The Carroll Township Fire Department shall provide primary response to fire alarms onsite ,

as required. *

a. The Village of Oak Harbor Fire Department I, shall provide alternate response to fire alarms onsite as required through mutual aid with Carroll Township.

• 5.10.4 The Ottawa County Sheriff's Department is noti-fied in order that local authorities may be prepared to answer inquiries generated by the public. The Sheriff's Department is also the main contact for medical and fire support -

agencies who respond to Davis-Besse (See Soctions 5.10.1, 5.10.2 and 5.10.3 above).

6. TElmINATION

~

6.1 The Emergency Duty Officer and Station Operations Manager have joint responsibility for determining and declaring when the emergency situation.is stable.

I 6.2 The Emergency Duty Officer shall assuro notification of all offsite organizations and TECo personnel that the emorgency has terminated.

2 6.3 A written summary will follow notification of termination

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I.

J I  :

' I -

', a

~

8 EI 1300.02.2 ED0/ SHIFT SUPERVISOR I CHECKLIST FOR J UNUSUAL EVEhT ATTACHMEhT 1 I NOTE: If changing from a prior emergency classification checklist, com-plete steps NOT already accomplished by the previous checklist.

Then attach all the previous checklists used to this one. Place N/A in stops that are not applicable.

ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS

1. Initiate' corrective action as required

2. Make the appropriate announce-ment or sound the appropriate alarm 2 NOTE: This step may be omitted when downgrading from a higher classification.

3. Announce location, type of m cmorgoney on Cai-tronics twico

. cad make the appropriate announce-a ment as to personnel assembly as required

4. Confirm Emergency Classification *

(Sco EI 1300.01)

5. Conduct necessary notification:

2 a. Nuclear Security Super-visor (Ext. 556 or 557)

NOTE: In the event of a fire, the Nuclear Security I Supervisor notifies the Ottawa County Sheriff'who notifies the appropriate department.

b. Edison Centrex Operator 2 (Ext.88-000 or 259-5000)

I NOTE: In the event of a medical emergency, the Edison Operator notifies the medical authorities and appropriate company management.

I E

I ~

e .

f g 9 EI 1300.02.2 ED0/ SHIFT SUPERVISOR CHECKLIST FOR '

UNUSUAL EVEhT A'ITACHMENT 1 (Con't) l l

ACTION COMPLETED l ACTION REQUIRED DATE TIME INITIALS I c. Station Management (See Step S.I.3(b) of this procedure)

1. Station Superin-tendent NOTE: The Station Superintendent or his designes is responsible for notifying the Ottawa County Sheriff upon declaration of an Emergency Action Level.

2. The Key Emergency ~

Response Personnel:

~ Emergency Duty Of ficer, Assistant Station Superin-tendent Operations, Chemist and Health Physicist, Nuclear S,ervices Director, Emergency Planning Super-visor, Nuclear Security Manager, News Media Relations Supervisor, Technical Engineer, Maintenance Engineer, I' and Operations Engineer.

d. *NRC (use the Emergency Notification System

- Red Phene)

• NOTE: NRC notification must be m,ade within one hour I2 and should be made by station management. Health physics information should be transmitted using the NRC Health Physics Network by the Chemist and I Health Physicist or his designee. (Dial 22 for NRC Headquarters - 23 for NRC Region 3 Office.)

6. Conduct Periodic Updates for:

a. TECo Personnel

b. NRC Ottawa County Sheriff I

c.

.I ..

t .,

10 EI 1300.02.0 ED0/ SHIFT SUPERVISOR.

J CHECKLIST'FOR UNUSUAL EVENT ATTACHMEhT 1 (Con't)

ACTION COMPLETED ACTION REQUIRED DATE TIME INITIAIS I 7. As conditions change, check EI 1300.01 to determine if reclassification is appropriate

8. When the condition is resolved '

notify:

a. TECo Personnel

b. NRC

c. Ottawa County Sheriff -

1 i

l l

i s

Reviewed by Filed by __

Station Superintendent Emergency Planning -

Supervisor END j 1

i _. _ __

EI 1300.04.0 e ,

6 Davis-Besse Nuclear Power Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.04 Site Emergency

• Record of Approval and Changes I

Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. Wells 6/13/80 Section Head Date Recommended by ,

((d, s -

h[ h SRB Chairgd 'Date QA Approved // [

Qual'it Assurance Manager Date Approved.by Station Superintendent V Y ' U!b

(/ Date Revision SRB QA Sta. Supt.

No. Recommendation Date Approved Date Approved Date l O Y*tf //W/N/ /fh TSWW y Am ajujr pr w w - g 'l' "

I I

h .

e

E -

B* ,

1 EI 1300.04.2

' 1. PURPOSE To outline the course of action and protective measures required to mitigate the consequences of a Station emergency at the Site Emergency level to safeguard Station personnel and the general public.

2. SCOPE Describes the actions and responsibilities of Davis-Besse per-sonnel and offsite support groups in the event the Shift Super-visor declares a Site Emergency in accordance with the Emergency Plan Activation procedure, EI 1300.01.

3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Station Response to Emergencies, EI 1300.00 3.3 Emergency Plan Activation, EI 1300.01 3.4 Protective Action Guidelines, AD 1827.12

4. DEFINITIONS 4.1 Site Emergency - Events are in progress or have occurred E which involve actual or likely major failures of DBNPS functions needed for the protection of the public. There also exists a significant actual or potential release of radioactive material.

5. EMERGENCY MEASURES 5.1 Shift Supervisor I The Shift Supervisor, having assumed the role of interim Emergency Duty Officer and having classified the emer-gency as a Site Emergency, shall assure the following actions are taken as required (See Attachment 1): -

5.1.1 Sound the appropriate alarm:

a. Fire i b. Containment Evacuation

c. Initiate Emergency Procedures 2 NOTE: The station alarm need not be sounded when downgrading from a higher classification.

I

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2 EI 1300.04.2 o 5.1.2 Announce the location, type and classification of the emergency on the Station public address system twice and make the appropriate announce-ment as to the need for personnel assembly, non-assembly, evacuation, or non-evacuation as the conditions dictate.

5.1.3 Notify the following individuals immediately:

2 a. Nuclear Security Supervisor ,

, i

b. Station Superintendent

1. During normal working hours the Station Superintendent should be reached over the g Station gal-tronics or by utilizing his g

" beeper" pager. During off normal work-ing hours, manually telephone his office and home using the numbers listed in Admin-istrative Memorandum No. 37. If there is no answer, then attempt a page. Upon being notified, the Station Superin-tendent shall then confer with the Shift Supervisor and ascertain the degree of response that may be necessitated by the plant event.

NOTE: If the Station Superintendent does NOT respond within five minutes, re-initiate the page.

2 If a second page fails, contact the Assistant Station Superin-tendent, Operations. If neither can be contacted, the Shift Supervisor should exercise his own judgment in dealing with the situation.

2. The Station Superintendent can then authorize the Shift Supervisor to tape an announcement on the Telephone Pager located in the Shift Supervisor's office.

(The Station Superintendent may elect to perform this evolution himself over the telephone. If so, the Station Super-intendent should call the Edison Operator and request to be connected to the Telephone Pager.)

. 3 EI 1300.04.2 NOTE: The announcement should include; 1) the Emergency Action Level classification,

2) the level of response required, and 3) a brief description of plant con-l ditions.

3. The Shift Supervisor or his designee shall then activate the pagers of the key emergency response individuals as listed in Administrative Memorandum No. 37.

4. When paged (beeped), those individuals l must telephone the Edison Operator who lE shall connect them with the Telephone ll Pager thus allowing them to hear the l recorded message.

NOTE: The NRC resident inspector can be telephoned or paged in accordance with AD 1827.17 if l necessary.

5. Those individuals shall then " call in" or notify additional personnel as required to provide adequate response to the event by using Administrative Memorandum No.

37.

( 5.1.4 Notification of the following agencies must 2 occur:

NOTE: When notifying an outside agency, record the name of the individual contacted and l request a return teloptono call from tho l agency to verify notification.

2 a. Sheriff's Department, Ottawa County, as soon as possible after the declaration is made (normal time is approximately 15 minutes)

b. NRC Region III, Office of Inspection and l

l Enforcement; NRC, NRR, Emergency Incident Hosponso ConLor, Bethesda, Maryland (This is I accomplished by the NRC Emergency Notifica-2 tion System - Red Phone) within one hour.

5.1.5 Continue in the capacity of interim Emergency Duty Officer until relieved by the assigned Emergency Duty Officer.

l l

4 EI 1300.04.0 .

5.1.6 Perform assessment actions which shall include:

a. An incraased amount of plant instrumentation shall be monitored, in particular, indica-tions of core status (e.g., incore thermo-couple readings, etc.) shall be monitored.

b. Monitoring efforts shall be greatly increased. Onsite and offsite monitoring g teams shall be dispatched. In addition to , g beta gamma field measurements, the change-out

• of thermoluminescent dosimeters (TLD's) at frequent intervals may be performed; air sampling and collection of other environ- I mental media for assessment of material transport and deposition shall be performed.

c. Dose assessment activities shall be conducted more frequently, with an increased emphasis 3 on dose projection for use as a factor in determining the necessity for protective 3 actions. Radiological and meteorological instrumentation readings shall be used to project the dose rato at predetermined dis-tancos from the Station, and to datormine the integrated dose received. In reporting the dose projections to the EDO or to offsite agencies, the dose rato, dose, and the basis for the time used for the dose estimate shall 3 always be provided. Any confirmation of dose g ratos by offsite R.Tf's shall be refl.2cted in roporting and/or revising dose estinate information provided to applicablo offsite agencies.

5.1.7 Corrective actions by plant operators shall be according to established procedures that place the plant in a safe condition.

5.2 Emergency Duty Officer (EDO)

The Emergency Duty Officer, upon being informed that a Site Emergency has been declared, shall; 5.2.1 Report to the Emergency Control Contor and assume the position of Emergency Duty Officer in the onsite emergency organization, relieving the Shift Supervisor of this duty.

e ,

S EI 1300.04.0 1

5.2.2 Evaluate the information, data, and methods .

utilized by the Shift Supervisor in making his determination in order to ensure that the proper I emergency classification has been made.

5.2.3 Determine to what extent the offsite and onsite a

emergency organizations shall be activated.

a. For a Site Emergency, the emergency teams and the entire onsite emergency organization shall be activated. A major portion, if NOT all, of the offsite emergency organization may be activated.

5.2.4 Activate the ECC according to the Emergency Control Center Activation Procedure, EI 1300.08.

I 5.2.5 Continue assessment actions initiated by the Shift Supervisor.

5.2.6 Recommend protective actions to the Ottawa County Sheriff as required by assessment results per AD 1827.12, Protective Action Guidelines.

5.2.7 Ensure that continuous online phone communica-tions are maintained with the State and County Emergency Operations Centers.

5.3 Shift Operations Personnel 5.3.1 Control room operators shall maintain safe operations of the Station and minimize che potential hazards to Station personnel and the general public as directed by the Shift Super-visor.

5.3.2 In the event that the Shift Supervisor is incapacitated, his duties and responsibilities indicated in Step 5.1 shall be assumed by the I Assistant Shift Supervisor in the Control Room until relieved by a qualified Shift Supervisor.

5.3.3 Equipment and auxiliaries operators shall main-tain safe operations of the plant as directed by the Shift Supervisor.

I 5.3.4 The Shift Technical Advisor shall provide tech-nical and analytical support in the diagnosis of off-normal events. He shall also advise and assist the Shift Supervisor on matters per-taining to the safe and proper operation of the plant with regards to nuclear safety.

I I

g  %

e 6 EI 1300.04.2 5.4 Shift Chemistry and Radiation Tester (C&RT) 5.4.1 The shift C&RT shall report immediately to the E Health Physics Monitoring Room to await instruc- g tions from the Shift Supervisor or Chemist and Health Physicist.

5.4.2 The shift C&RT shall provide radiological monitoring for the Fire Brigade in the event of a fire in RACA. ,

5.4.3 The shift C&RT shall monitor all injured per-sonnel before they leave the site. An off-shift C&RT shall accompany or meet the contaminated personnel at the offsite medical facilities, i 5.5 Fire Brigade 5.5.1 The Fire Brigade Captain shall respond to any announced fire, evaluate the situation, direct the Fire Brigade, and keep the Shift Supervisor informed of the status of the fire.

5.5.2 Personnel assigned to the Fire Brigade shall respond to any announced fire with appropriate fire fighting and protective equipment and extinguish the fire as directed by the Fire Brigade Captain.

5.5.3 The first Fire Brigade Captain arriving on the scene should remain in charge of the fire until termination of the emergency or relieved by the Fire Chief or Assistant Fire Chief. g l

5.6 First Aid Team 3 5.6.1 The First Aid Team Leader shall respond to any announced personnel injuries, evaluate the j

situation, direct the First Aid Team and keep i

the Shift Supervisor informed of the status of the injured individual (s).

5.6.2 Personnel assigned to the First Aid Team shall g respond to any announced personnel injury with 3 appropriate first aid supplies and provide the necessary first aid treatment.

3 5.7 Nuclear Security Force 5.7.1 The Nuclear Security Supervisor, upon notifica-tion by the Shif t Supervisor that a Site Emergency

9. . <

I* ,

EI 1300.04.2 7

exists, shall implement the Industrial Security Plan Procedure, AD 1808.00.

2 5.7.2 Nuclear Security Officers shall maintain security of the Station as directed by the Guard Super-visor.

5.8 Radiation Monitoring Team (RMT) 5.8.1 Normally only one RMT member should be from the C&HP Section.

5.8.2 During normal working hours:

1. Qualified RMT members who are not involved in I immediate corrective actions shall report to the Radiological Testing Laboratory (RTL) or the Emergency Control Center (ECC) for specific assignments.

2. RMT members are designated by the OSC Manager (Maintenance Engineer).

3. Onsito RMT's from the Chemistry & Health Physics Section should standby at the !!calth Physics Monitor Room for instructions from the Chemist & Health Physicist or his designee.

They should use the survey equipment and air samplers located adjacent to the Health Physics Monitor Room, if requested to do onsite surveys. -

2

4. Offsite RMT's requested by the Emergency Duty Officer (EDO) should report to the Emergency l Control Center (ECC). They should then check i

out the monitoring equipment in the Radiological l Testing Laboratory and standby for further instructions from the EDO.

5.8.3 During off-normal hours:

1. Rtff members called in during an emergency l

I report to the Chemist & Health Physicist or EDO in the Davis-Bosse Administration Building for assignment to an onsite or offsite RMT.

2. Check out the monitoring equipment and standby in the Radiological Testing Laboratory for further directions.

I

~,v i

3.*i'.

,r 8 EI 1300.04.0 5.9 Plant Staff Members of the plant staff that have been informed of a g Site Emergency shall proceed to their designated loca- l tions and perform their assigned functions.

5.9.1 The Plant Operations Manager shall proceed to the Control Room. He shall direct plant operations and plant damage control efforts. He shall also keep the Station Opera- ,

tions Manager advised of plant operations.

5.9.2 The Operations Engineer shall proceed to 3 the Control Room. His functions are to super- E vise control room activities, to perform on-the-spot operational analysis as required to E essist the Shift Supervisor, and keep the Plant g Operations Manager informed of current plant conditions.

5.10 Onsite Personnel 5.10.1 Personnel, who do NOT have specifically assigned dutics during a Site Emergency, shall proceed to the following areas:  ?

a. Personnel inside RACA shall proceed to the Health Physics Monitoring Room area and wait for further instructions.

b. Personnel in the Protected Area shall proceed to the Operations Support Center and wait for further instructions,

c. Personnel outside the Protected Area shall "'

proceed to the Construction Office Building ..E and wait for further instructions. , ., ); g 5.11 ~,  ; ',

Offsite Personnel - '

5.11.1 Personnel offsito that are notified to report to ,

the site shall proceed to Emergency Control ,

Center and then to their specifically assigned locations as required and conditions permit.

5.12 Offsite Agencies and Organizations ,

5.12.1 The Carroll Township Ambulance Service stall provide transportation service as required for offsite medical treatment.

9 EI 1300.04.2 5.12.2 The H. 3. Magruder Memorial Hospital shall provide offsite medical treatment for personnel

, as required.

\

5.12.3 The Carroll Township Fire Department shall

._ provida primary response to fire alarms onsite as required.

a. The Village of Oak Harbor Fire Department shall provide alternate response to fire alarms onsite as required through mutual aid with Carroll Township.

5.12.4 The Ottawa County Sheriff's Depart =ent is experienced in providing area control, com-munications assistance, and direct handling of the local population, including evacuation, should it becorne necessary. The Sheriff's M Department provides 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radio co=munication g I coverage with the Shift Supervisor at DBNPS and rs the lead offsite governmental agency contacted in the event of an emergency at the site. >

4

6. TERMINATION p 6.1 Tho Emergency Duty Officer and Station Operations Manager have joint responsibility for determining and declaring when the emergency situation is stable.

6.2 The Emergency Duty Officer shall assure notification e of all offsite organizations and TECo personnel that the emergency has terminated.

2 6.3 A written, suimary will follow notification of termination -

within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

,I i

l l

l

10 EI 1300.04.2 ED0/ SHIFT SUPERVISOR CHECKLIST FOR SITE EMERGENCY ATTACHMENT 1 NOTE: If changing from a prior emergency classification checklist, com-plete steps NOT already accomplished by the previous checklist.

Then attach all the previous checklists used to this one. Place N/A in stops that are not applicable. ,

1 ACTION COMPLETED ACTION REQUIRED DATE TIME INITIA7.S

1. Sound the appropriate alarm t

2. Announce location, type of emergency on Gai-tronics twice ,

2 NOTE: These steps may be omitted when downgrading from a higher classification.

3. Initiate corrective action s -

as required 9

4. Confirm Emorguncy Classification (See EI 1300.01) y

}

5. Conduct necessary notification: .

I2 a. Nuclear Security Super-visor (Ext. 556 or 557)

• NOTE: In the event of a fire, the Nuclear Security Supervisor notified the Ottawa County Sheriff who *9 notified the appropriate department. y

b. Edison Centrcx Operator 2 (Ext.88-000 or

• 259-5000) ,

NOTE: In the event of a medical emergency, the Edison Operator notifies the medical authorities and ,

appropriate Company management.

c. Slutlosi Management (Seo Stop 5.1.3(b) of this procedure) I

1. Station Superin-tendent

2 ll .

11 El 1200.04.2 ED0/ SHIFT SUPERVISOR CHECKLIST FOR SITE EMERGENCY .

ATTACHMENT 1 (Con't)

ACTION COMPLETID ACTION REQUIRED DATE TIME INITIALS NOTE: The Station Superintendent or his designes is responsible for notifying the Ottawa County Sheriff upon declaration of an Emergency Action Level.

2. The Key Emergency Responso Personnel:

Emergency Duty Officer, Assistant Station Superin-tendent Operations, Chemist and Health Physicist, Nuclear Services Director, Emergency Planning Super-visor, Nuclear Security Manager, News Media Relations Supervisor, Technical Engineer, Maintenance Engineer, and Operations Engineer.

d. *NRC (use the Emergency

~~~'N Notification System L,s l - Red Phone)

• NOTE: NRC notification must be made within one hour I' and should be made by station management.

an incident or abnormal occurrence,-health During physics information should be transmitted using the NRC !!colth Physics Network by the Chemist and Health Physicist or his designee. (Dial 22 for NRC Headquarters - 23 for NRC Region 3 Offico.)

6. Perform applicable stops of .

the ECC checklist'(Attachment 3 of EI 1300.08, Emergency I Control Conter Activation)

7. Center Activation Confirmation

a. Emergency Control Center (EI 1300.06) <

b. Operations Support Center (El 1300.06)

12 EI 1300.04.2 ED0/SHIIT SUPERVISOR CHECKLIST FOR l l SITE EMERGENCY NITACHMEhT 1 (Con't)

ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS 2 c. Technical Support Center ,

(EI 1300.07) ,

d. Emorgency Support Center (EI 1300.09)

8. Conduct Periodic Updates for:

a. TED Personnel

b. NRC

c. Ottawa County Sheriff I 9. As conditions change, check EI 1300.01 to datormino if reclassification is appro-priate

10. When the condition is resolved notify:

a. TED Personnel

b. NRC

c. Ottawa County Sheriff l

I g

i Reviewed by Filed by t

Station Superintendent Emergency Planning Supervisor END

]

u- EI 1300.07.0 Davis-Besse Nuclear Power Station Unit No. 1 I Emergency Plan Implementing Procedure EI 1300.07 Technical Support Center Activation

• Record of Approval and Changes Prepared by

G. J. Reed 5/30/80 Date ,,

Submitted by C. E. Wells 6/13/80

..Section Head Date

,N i

Recommended by

[g M SRB Chai dan

~

b /)

b'a te QA Approved _A/ 8 l Quality Assurance Manager Date Approved.by D @hm p, x s aluja. pg gm ww

'I O

1 EI 1300.07.2

1. PURPOSE To outline the personnel required for activation of the Technical Support Center (TSC) and their responsibilities and actions during an emergency at Davis-Besse Nuclear Power Station.

2. SCOPE Describe the actions of personnel assigned to the TSC when the the need for its activation has been determined.

3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Davis-Besse Nuclear Power Station Emergency Plan Telephone Directory 3.3 Station Response to Emergencies EI 1300.00 3.4 Unusual Event EI 1300.02

~

3.5 Alert . EI 1300.03 3.6 Site Emergency EI 1300.04 3.7 General Emergency EI 1300.05 3.8 Administrative Controls EI 1300.12

4. DEFINITION 4.1 Technical Support Center (TSC) - An area onsite in close proximity to the Control Room which has the capability to display and transmit plant status information to the individuals who are knowledgeable of and responsible for engineering and management support of reactor operations j in the event of an emergency situation.

5. ACTIONS 2 5.1 The Technical Support Center is located at the Davis-Besse site, along Ohio State Route #2, in the Davis-Besse Administration Building. The primary function of the TSC is to house and support an organization that provides management and technical assistance to the Station opera-tions personnel during emergency conditions and to prevent or mitigate the consequences of abnormal plant conditions.

The TSC provides direct voice and data communication with s the Control Room and serves as a primary communications l Il ~-]

1 1

2 El 1300.07.2 2 contact with the offsite emergency organization of Toledo Edison. Visual observation of the Control Room will be available through closed-circuit television (CC'IV). The TSC also contains the DADS to enable the TSC staff to acquire plant data and information necessary for technical evaluations needed to handle emergency conditions and recovery operations. Two communication lines to the NRC are available for direct communication to the NRC Health Physics Network and Emergency Notification System.

The TSC contains work space for up to 25 people, including a main work area for 15 people and 3 conference areas, one of which will accommodate 8 people.

5.2 The TSC shall be activated at the Alert Emergency Classifi-2l cation level.

5.3 The first Station management individual to arrive at the TSC shall notify the Control Room that the TSC is manned.

5.4 Station Operations flanager ~

5.4.1 Tho. primary Station Operations flanager is the Station Superintendent.

5.4.2 The alternate Station Operations ?!anager is the 2

Assistant Station Superintendent, Operations.

5.4.3 The Station Operations t!anager is responsible for assuring the activation of the TSC.

5.4.4 The Station Cperations flanager should proceed to the TSC and, if NOT previously performed, notify the Control Room that the TSC is manned.

5.4.5 The Station Operations t!anager should assure the following individuals arrive at the TSC:

i

a. Nuclear Engineering blanager

b. Technical data communicator

c. Technical Engineer

d. Plant Instrumentation and Control Systems Engineer

c. Plant Nuclear Systems Engineer I

I

. i 3 EI 1300.07.2 5.4.6 The Station Operations Manager may establish the following telephone communications loops as 1 needed per the DBNPS Emergency Plan Telephone Dir-ectory:

)

a. Technical Data Loop

b. Technical Management Loop

c. Policy Management Loop ,

d. Public Relations Loop NOTE: If personnel are required as communicators, requests I should be directad to the Operations Support Center.

5.4.7 The Station Operations Manager should assign an individual (s) to set-up the emergency equip-ment as listed in Attachment 1, as required.

2 5.4.8 Upon arrival, the Onsite Assessment Manager will assume control of the TSC from the Station Operations Manager.

t.m- 5.5 Onsite Assessment Manager 5.5.1 The primary Onsite Assessment Manager is the Nuclear Engineering Manger.

5.5.2 The alternate Onsite Assessment Manager is the Plant Nuclear Systems' Engineer.

2 5.5.3 The Onsite Assessment Manager, upon being informed that an Alert icvel emergency exist, shall proceed to the Technical Support Center (TSC).

The Onsite Assessment Manager's responsibilities

'I 5.5.4 and duties include, but are NOT limited to:

a. Directing the engineering assessment activities of the TSC.

b. Coordinating the enginneritig assessmunL activities of engineering support personnel from the NSSS vendor and the Architect Engineer.

c. Ensuring that adequate mechanical, electrical, instrumentation and control, and technical 1

I 4 EI 1300.07.2 engineers are available to perform engineering assessment, as required.

2

d. Ensuring that adequate support personnel are available to assist in records disposition, g updating status board, and providing communica- l tions to the Control Room and Nuclear Regulatory Commission, as necessary.

e. Reporting to the Station Operations Manager and appraising him of engineering assessment activitics, equipment operation problems and l any alterations in the normal lineup or E operation of plant systems.

5.6 Technical Engineer 5.6.1 The primary technical engineering individual is the Technical Engineer.

5.6.2 The alternate technical engineering individual is the Nuclear Performance Engineer. '-

5.6.3 Tha. Technical Engineer shall assist in coordinat-ing anel performing plant assessment activitics.

~

5.6.4 The T,echnical Engineer shall, as necessary, assure that radiological controls are in place such as:

a. TSC monitored for airborne activity by opera-tion of a portable air activity monitor.

b. A high/ low survey instrument is utilized by personnel leaving the TSC for. entry into the plant.

c. Stepoff pads and contamination survey instru-ments are provided at the entrance to the TSC from the plant when required.

5.6.5 The Technical Engineer shall assure that per-sonnel assembled in the TSC are briefed on conditions and monitoring methods in place while the 7SC is activated.

5.7 Radcon Operations Manager 5.7.1 The Radeon Operations Manager is the Chemist and Health Physicist.

I l

. 5 EI 1300.07.2 5.7.2 The alternate Radcon Operations Manager is the Chemical and Radiation Protection Engineer.

5.7.3 The Radcon Operations Manager directs and I coordinates the radioactive waste and radio-logical controls aspects of Emergency Operations and keeps the Plant Operations Manager informed of radwaste and radcon activities pursuant to the emergency.

5.7.4 The Radcon Operations Manager is re'sponsible for coordinating the activitics of the Health Physics Monitoring Room portion of the Opera-tions Support Center, however he may do this from his office located in the Technical Support Center. He is also responsible for relaying health physics information over the NRC Health Physics Network phone which I is located there.

5.7.5 The Radcon Operations Manager shall supervise -

the onsite radiation surveys and survey results analysis, p) t 5.8 Plant Staff 2 5.8.1 Plant Staff, such as the operations engineering staff, clerical support, etc., who are NOT assigned to other emergency functions, shall (if in protected area) report to the Operations Support Center and be directed to the TSC as needed.

5.8.2 The Technical Engineering staff who are not assigned other emergency functions, shall report directly to the TSC.

5.8.3 The Plant Staff shall assist in accident assess-ment, as required.

5.9 Technical Support Center Activity 5.9.1 Communications with the Control Room, Emergency Support Center, Operations Support Center, Emerg-ency Control Center, and the NRC will be estab-lished as specified by the Onsite Assessment Manager or the Station Operations Manager.

a. The Data Acquisition and Display System (DADS)

I2 terminals in the TSC will provide sufficient station information and data communication for

)

s .

6 EI 1300.07.2 personnel to evaluate and diagnose station conditions and activities so as to conduct emergency operations in an orderly manner.

b. The DADS provide data communication between the ECC, TSC, Control Room and Emergency Support Center.

c. The DADS can monitor plant transients during and following most events expected to occur during the life of the station.

5.9.2 The condition of the reactor and essential safety-related systems shall be assessed and steps taken to assure protection of Station personnel and the public.

5.9.3 Analysis of plant conditions shall be performed to determine reactor core status. Containment Radiation Plots in httachment 2 provide the relationship betweer. containment radiation levels g and the time after plant shutdown for various amounts of fuel inventory released into containment. This E information can be correlated to the approximate source and damage estimates given in Table 1.

5.9.4 Directives issued to the Control Room shall be assessed for potential adverse consequences before. issuance - this includes all offsite directives from government or company management organizations.

a. Directives to the Control Room should be done verbally as long as there is mutual agreement to all parties that the correct action is being taken.

b. If a disagreement occurs between the Control Room and the TSC, a uritten directive from the TSC should be forwarded to the Control 2 Room signed by the Or. site Assessment Manager or Station Operations Manager.

5.9.5 Contact shall be made and support requested as required from the following organizations:

a. Babcock and Wilcox

b. Bechtel g

c. Nuclear Safety Analysis Center (NOTEPAD) g

I . .

I 7 EI 1300.07.2 1

5.9.6 A record of activities of the TSC shall be '

maintained to the best ability of personnel present. Record disposition shall be in accordance with EI 1300.12, Administrative Controls.

5.9.7 The decision to deactivate the TSC shall be made 2 by joint concurrence of the Onsite Assessment Manager, Station Operations Manager, Shift Super-visor and other key plant personnel once accident recovery has reached a point where continuous technical assessment and advisory functions are no longer necessary to mitigate the consequences of plant conditions.

5.10 Procedure for Activation of the Alternate TSC 2 5.10.1 The Onsite Assessment Manager will direct the activation of an alternate TSC if the normal TSC becomes uninhabitable for any reason. .

5.10.2 No more than three (3) persons assigned to -

technical support will be dispatched to the Control Room. The balance of the technical support staff (including vendor, TECo and NRC

'% personnel) will be located at a suitable posi-tion as close to the Control Room as possible.

Communications will be established by telephone, messenger, telecopier, etc. between technical support personnel and the Control. Room. Also, communications'will be established at Icast by telephone or messenger betwcon the relocated TSC and the ECC.

.I P .

8 EI 1300.07.1 .

Technical Support Center Equipment List Attachment 1 l

m I

Equipment Type Quantity Location

1. Portable High-Range Survey Meter 1 ea. *

(1 mr/hr to 1,000 r/hr range

2. Portable Low-Range Survey 1 ca.

• Meter (Frisker) 1 1

3. Portable Air Sampler 1 ea. *

• NOTE: This equipment is available in the Instrument and Calibration Room.

e 1

9 EI 1300.07.1 00 Containment Radiation Plot

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! Attachment 2 l TDE (hours) Page 1 of 2 I

tf 8 10 EI 1300.07.1 Containment Radiation Plot Instructions Theoreticc1 curves of gross gamma dose rate versus time are given for a range of potential source terms. The curves represent direct readings for monitors RE-2004, RE-2005, RE-2006 and RE-2007 located at elevation 585, outside containment. The calculation of monitor response did not include any particulates or iodine since the noble gases are the most significant contributors to dose rate in the containment. At the worst, neglecting the particulates adds a slight amount of conservatism since the actual presence of particulates would result in a higher monitor reading. NOTE: (1) The curves account for the finite containment volume seen by the detector but do not account for any monitor physical or shielding characteristics or calibration un-certainties. (2) The curves assume that only airborne noble gases are significant. Sprays (if used) would make the iodine anti any particulate contribution insignificant. However, particulato plateout on surfaces and direct shine doses from components may make the readings unrelichic. (3) Curve uncertainties are on the order of a factor of 2 to 5. Procedure:

1. Determine the Time after reactor shutdown.

2. Locate the radiation monitor Dose Rate Reading on the graph at the time after shutdown.

l l 3. Tuku the ratio of the measured dose rat.c to the dose rate given on l one of the curves for a known percent inventory. (ic., interpolate l between curves.)

4. Relate the % fuel inventory released to the Approximate Source &

Damage Estimates as given in Table 1. (This value should be compared to the same case number as the curve used in Step 3 above.) Attachment 2 Page 2 of 2 l

L 11 EI 1300.07.1 Table 1 Percent of Fuel Iventory Airborne in the Containment vs. ( Approximate Source and Damage Estimate

                          % Fuel

• l Case Inventory I No. Released Approximate Source and Damage Estimate 1 100 100% Regulatory Guide 1.4, 100% Fuel Damage, potential core melt 2 10 10% Regulatory Guide 1.4, (or 100% NRC Gap I Activity, Regulatory Guide 1.25), total clad failures, core partially uncovered 3 1 1% Regulatory Guide 1.4 (or 10% NRC Gap I Activity), approximately 10% clad failure 4 -

100% coolant release -

         *100% Fuel Inventory = 100% Noble Gas D               -

I . 9 I l END

          ~,                                                                                          ;

EI 1300.08.0 Davis-Besse Nuclear Power Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.08 Emergency Control Center Activation . I. _ Record of Approval and Changes I Prepared by " G. J. Reed 5/30/80 Date I.- Submitted by C. E. Wells 6/13/80 - Section Head Date Recommended by

                                      ,#84/

SRB Chairma ( b /) bate' QA A'pproved .[ A Quality Assurance Manager Date Approved.by V gq Station Superintendent r P/[rd ( Date I

• t Revision SRB j No. QA Sta. Supt.

Recommendation Date Approved Date

 =                                                                     Approved l

z lY$y" fTl8 NA TYSM Date Ax4 p 9iMt # rpm mp,.2 mi

            ) pw~g                          a/m /n jjg              gw                   ,12.n v I

I - I 1 f l I

I e 1 EI 1300.08.3 l

1. PURPOSE To outline the personnel required for activation of the Emergency 1 Control Center (ECC) and their responsibilities and actions during an emergency at Davis-Besse Nuclear Power Station.

2. SCOPE Describe the actions of personnel assigned to the ECC when the need for its activation has been determined.

3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Davis-Besse Nuclear Power Station Emergency Plan Telephone Directory 3.3 Station Response to Emergencies EI 1300.00 I.. 3.4 Unusual Event EI 1300.02 ..

3.5 Alert EI 1300.03 3.6, Sito Emergency EI 1300.04 F% [] 3'. 7 General Emergency EI 1300.05 3.8 Administrative Controls EI 1300.12 I. 3.9 Protective Action Guidelines AD 1827.12 3.10 Emergency Of fsite Dose Estimates AD 1827.10

4. DEFINITION 4.1 Emergency _ Control Center (ECC) - A specifically designated location which is equipped to facilitate the

                    -control and coordination of emergency activities and assessments.

5. ACTIONS 5.1 The ECC is located at the D13NPS site along Ohio State Roulu 2 in thu AdministrnLion fluilding.

a. Command and control of site-related emergency efforts affecting local response within the Emergency Planning Zone originate from this center.

I3 b. The ECC contains communication links necessary for coordination with offsite organizations. I

4 . 2 EI 1300.08.3 -

c. The ECC contains a terminal of the DADS (Data Acquisi-tion and Display System) for acquiring necessary data for dose calculations.

3

d. The ECC will serve as an interface with the TECo Emergency Response Organization and Local, State, and Federal agencies.

5.2 The first Station management individual to arrive at the ECC shall notify the Control Room that the ECC is manned. 5.3 Emergency Duty Officer Activities

 .               5.3.1      The Emergency Duty Officer (EDO) is responsible for determining the need for and assuring the activation of the ECC.

5.3.2 The EDO shall proceed to the ECC and, if NOT previously performed, notify the Control Room that the ECC is manned and perform the steps as indicated in Attachment 3. ~ 5.3.3 The.EDO shall ensure the following individuals arrive at the ECC as needed:

a. Control Room Communicator

b. State and County Communicator

c. Teleprinter Operator

d. Corporate Management Communicator

e. Public Relations Communicator

f. Nuclear Regulatory Commission Communicator I

g. Radiation Monitoring Team Communicator

h. Radiation Monitoring Teams

i. Emergency Operations Manager 3 j. Emergency Planning Supervisor

k. Community Assistance Communicator 5.3.4 The EDO may request to the Station Operations Manager that part or all of the telephone com-munications loops be established.

I

3 EI 1300.08.3 5.3.5 The EDO shall assign an individual (s) to set-up necessary emergency equipment (located in the ECC and Radiological Testing Lab) as listed in Attachment 1. 5.3.6 The EDO shall assign an individual (s) to perform dose calculations and dose assessment, and to 3 operate the CRT terminal for the Data Aquisition and Display System.. 5.3.7 The EDO shall ensure that Attachment 2 is com-pleted correctly and supplied to the State and County Disaster Services Agencies. _ a. This shall be accomplished as soon as pos-sible after the start of the emergency. I b. Updates to Attachment 2 shall be supplied as requested by the State and County Disaster Services Agencies. 3 5.3.8 The EDO shall assume responsibility for distribu-I tion of potassium iodide to station personnel as per,AD 1827.12 and to RMT's as per AD 1850.05. m The EDO shall, when necessary, recommend 5.3.9 "") , protective actions for the plume exposure pathway to thh State and County Disaster Services Agencies per AD 1827.12, Protective Action Guidelines. 5.3.10 The EDO shall assign' Radiation Monitoring Teams and inform Federal,. State and local officials of the affected areas'by sector and zone desig-

                  ,           nators as shown on Attachment 4.

5.4 Emergency Operations Manager I 5.4.1 The primary Emergency Operations Manager is the Nuclear Services Director. 5.4.2 The alternate Emergency Operations Manager is the Staff Assistant Nuclear. 5.4.3 The Emergency Operations Manager, upon being informed that an emergency exists, shall proceed to the ECC. 5.4.4 The Emergency Operations Manager's responsibil-ities and duties include, but are NOT limited to:

4 El 1300.08.3 ,

a. Report to the Operations Director and appraise him of emergency operations and community relations matters,

b. Provide direction and guidance for the EDO.

3 c. Notify the state and local officials that protective action for the injestion pathway may be necessary,

d. Coordinate short term community assistance activities and response to the needs of local government officials.

      ~

3 5.5 Emergency Planning Supervisor 5.5.1 The Emergency P.lanning Supervisor, upon being informed that an emergency exists, shall proceed to the ECC. 5.5.2 The Emergency Planning Supervisor's responsibilities and duties include, but are NOT limited to: ..

a. Report to the Emergency Operations Manager bhd appraise him of emergency response activities.

b. Consult with and provide assistance to the EDO.

c. Provide guidance needed to coordinate the various emergency response activities.

                                                                 .I

d. Ensure contact is made as required to the following agencies (phone numbers are found in Administrative Memorandum No. 37):

l

                                *1. Institute of Nuclear Power Operations I                                       (INPO) 3                             2. REMS Corporation
                                *3. American Nuclear Insurers (ANI)

4. Federal Bureau of Investigation

5. State of Michigan

6. Department of Energy (IRAP)

7. Consumer's Power Company

8. Detroit Edison Company

9. Cleveland Electric Illuminating Co.

10. Cincinnati Gas and Electric Co.

                              *Must be notified at the Alert level or above.

5.6 Radiation Monitoring Teams I F

i 5 EI 1300.08.3 5.6.1 The first RMT to arrive at the ECC shall perform the functions listed below:

a. Using appropriate survey instruments, survey the immediate areas surrounding the ECC.

b. Standby with a Radiation Monitoring Team Kit and Protective Clothing Kit. Protective clothing to be used as directed.

c. Check out equipment for operability.

I . 5.6.2

d. Perform surveys offsite as directed by the EDO.

Other RMT's that arrive at the ECC:

a. During normal working hours:

   ~

1. Standby with a Radiaton Monitoring Team Kit and Protective Clothing Kit to be used as directed. ..

2. Check out equipment for operability.

                                                    .                 3.       Perform surveys offsite as directed by the EDO.

b. During off-normal working hours: '

1. If not needed as an offsite RMT (as deter-mined by EDO), assignment as.onsite RMT's to the Radeon Operations Manager (at the Technical Support Center) or the Shift Supervisor (if the TSC is not as yet manned) will be made by the EDO after it is assured that additional aid is needed onsite.

5.7 Staff Personnel 5.7.1 Staff personnel such as the Nuclear Reliability 3 Manager, and other personnel qualified as EDO who I are NOT assigned to other emergency operations functions shall report to the ECC to assist the EDO, act as conununicators, or perform other duties as directed by the EDO. 5.7.2 The staff will assist in communications as well as in assessment of the data supplied to I the ECC. I

6 EI 1300.08.0 5.7.3 The EDO may designate members of the staff to perform dose calculations and assessments.

a. If a release of radioactive particulates or gases from the plant occurs, dose calcula-tions should be performed in accordance with AD 1827.10, Emergency Offsite Dose Estimates.

b. Total population exposure should be calculated in accordance with the following:

1. Population exposure calculation:

Dose Rate x PET x PPA = man rem Where: Dose Rete = rate of exposure per unit time in rem PET = Projected Exposure Time or af ter ~ the release actual exposure time

                                . PPA = Population in Plume Area
              ~

NOTE: Population values can be

                                    .             derived from Figures 2-4, 2-5 and 2-6 in Section 2.0 of the DBNPS Emergency Plan.

2. Schedule for Calculation or Estimates:

8 hours after release - 1st day 24 hours after release - 1st day every 12 hours thereafter for 3 days daily beginning the 4th day after the incident. 5.7.4 A record of activities of the ECC shall be main-tained to the best ability of personnel present. l Record disposition shall be in accordance with EI 1300.12, Administrat-ive Controls. l 5.8 Responding Personnel l l 5.8.1 Personnel offsite who have been requested to respond to an emergency shall proceed to the Emergency Control Center and then I

7 EI 1300.08.0 to their specifically assigned locations as required and conditions permit. I I I .- I I- .. I~ I , I I I I I P I

I 8 El 1300.08.3 ' DAVIS-BESSE ADMINISTRATION BUILDING RADIOLOGICAL TESTING LABORATORY EQUIPMENT LIST i CABINET "1" Survey Equipment: RM-14 HP 260 Prebe and Power Cord 1 ea. PRM-4A with !if 210 Probe 2 ea. g PIC-6A Ior Chamber 1 ea. E PRM-7 Micro R-Meter 2 ea. Dosimeter Charger 1 ea. g Dosimeter 0-100R Dosimeter 0-5R 5 ea. 5 ea. 3 Dosimeter 0-500mR 25 ea. TLD 25 ea. Check Source, CS-137 (~8pCi) I ca. Air Sampler, DC 4 ea. Batteries: - 12-Volt 35-102 Booster

 ~

1 ea.

                   "D" Cell, 1 1/2 Volt                                                                                             12 ea.                              ~

9-Volt 12 ea. E NEDA 220,15 Volts for SK-1 Speakers 12 ca. g "AA" Penlites . 12 ea. Protective Clothing Kits, Each Contain: 12 ea. 1 Pa'ir Cloth Coveralls - l' Pair Rubber Shoecovers - 1 Cloth Hood - 1 Cloth Cap - l 1 Pair Cottor Liner - E 1 Pair Rubber Gloves - 1 Pair Plastic Booties - g 1 Full Face Respirator Masking Tape 3 Other Protective Clothing: Plastic Shoe Covers . 30 ea. 1)isposable Hubber Gloves 2 Boxes Cotton Giove Liniers 30 ea. Paper Coveralls 30 pairs Miscellaneous: Smears 2 Boxes Smear Folders 2 Boxes Plastic Bags, Swirl Pack - Tweezers - Plastic Bags, Assorted - Extension Cord 1 Radiation Signs and Inserts ' Rope - I Attachment 1 Page 1 of 4

I . .

                 ,                                       9          EI 1300.08.3 DAVIS-BESSE ADMINISTRATION BUILDING RADIOLOGICAL TESTING LABORATORY EQUIPMENT LIST CABINET "2" Ottawa County Maps                                      2 ea.

First Aid Kit 1 ea. Data Sheet #1 for AD 1850.05 25 ea. Data Sheet #1 for AD 1827.10 25 ea. Data Sheet #2 for AD 1827.10 25 ea. Stenographer Pads - I - Bottle of KI Tablets (Approx.1000) Ledger Pencils and Pens - 1 ea. 1 ea. Felt Tip Pen 1 ea. 'I Particulate Filter, 2 1/4" 30 ea. Silver Zeolite Cartridges 30 ea. Duct Tape - Raincoats 12 ea. Radio 2 ca. Radio Charger 2 ea.

l *RMT Kit, Off-Site 2 ea.

'E *RMT Kit, On-Site . 2 ea. Seals - SAM-2 Analyzers 2 ea. Onsite Radiation Monitoring Team Kit PIC-6A Survey Meter 1 ea. E-520 Survey Meter 1 ea. Flashlight 2 ca. I Dosimeter 0-500 mrem 2 ea. Dosimeter 0-1 Rem 2 ea. TLD 2 ea. Smear Swipe NUCON 25 ea. Tweezers I ca. Planchet 10 ea. Pencil 2 ea. Note Paper 1 pad Bag-Plastic 5 ea. Screwdriver 1 ea. RMT Procedure, AD 1850.05 1 set

            *Can he stored outside cabinet, f                                                                 Attachment 1 Page 2 of 4

10 EI 1300.08.3 D5VIS-BESSE ADMINISTRATION BUILDING I RADIOLOGICAL TESTING LABORATORY EQUIPMENT LIST Of fsite Radiation Monitoring Team Kit PRM-7 Micro R-Meter 1 ca. E 520 Survey Meter 1 ea. Flashlight 2 ea. Dosimeter 0-500 mrem 2 ea. TLD 2 ea. Smear Swipe NUCON 25 ea. Tweezer 2 ea. Coins (Dime) 20 ea. Planchet 10 ea. Pencil 2 ea. Note Paper 1 pad Bag - Plastic 5 ea. Screwdriver 1 ea. RMT Procedure, AD 1850.05 1 set County Map - Ottawa 1 ea. I

                   ~

tilli 6 i Attachment 1 Page 3 of 4

11 EI 1300.08.3 DAVIS-BESSE ADMINISTRATION BUILDING EMFJtGENCY C0hTROL CLNTER EQUIPMLNT LIST CABINET "1" TI 57 Calculator 1 ca. TI 59 Calculator 1 ea. Extra Paper for Printer -

• Emergency Plan, Implementing Procedures 2 sets and Supporting Procedures
• Map Board 1 ea.

Ledger 1 ea. Davis-Besse Technical Specifications 1 set State of Ohio, Michigan and Ottawa County 1 set Emergency Plans

         *Can be stored outside cabinet.

D.

                              ~

I I I. P Attachment 1 Page 4 of 4

EI 1300.08.@ 12 DAVIS-BESSE NUCI. EAR POWER STATION Emergency Nuclear Incident

Essential Information Date Time: Sheet No.:

Part I: A.  : Classification of incident l B.  : Time release started or is I expected to start I s

          .                               C.                                                                     to the                   : Wind direction D.                                                                                              m/sec.: Wind speed E.                                                                                            _Ci/sec:    Noble gas release rate F.                                                                                             Ci/sec.:    Radiciodine release rate G.                                                                           '
                                                                                                                                        - : Stability Class                                                -

11 .  : Expected duration of release

                                                                                  ~

1. -

ar/hr. : field monitoring reading

                                                                                                              ~
                                                                                                                                      ~

mr/hr: field monitoring reading mr/hr: field monitoring reading Part II: A. , Sector (s)/ Zone (s) are involved B. mr/hr @ miles; whole body dose (pro-jected value) mr/hr @ miles: thyroid dose (projected value) NOTE: Before acting upon the above information, reverify I the information and ensure that all assumptions being made are known by the utility, State and local officials. C.

Facility recommendations (stay inside or evacuate / distance) f Attachment 2 Page 1 of 2

13 EI 1300.08.2 DAVIS-BESSE NUCLEAR POWER STATION Emergency Nuclear Incident Essential Information D.  : Weather conditions (precipitation) Part III: A.

Plant condition B.

I-.

Cause of incident I NOTE: When disseminating information during an actual event, if a space is skipped, insert "W/F" or "N/A" to indicate that there has NOT been a mis-I take and that the information will be forwarded as soon as possible.

I W/F = will follow N/A = not applicable e *

• 1 I

I I I, . I f Attachment 2

14 EI 1300.08.2 - ECC CHECKLIST lg ACTION COMPLETED l ACTION REQUIRED DATE TIME INITIALS

1. Emergency Duty Officer

2. Perform applicable steps of the ED0/Shif t Supervisor checklist in either El 1300.03 (Alert),

EI 1300.04 (Site), or EI 1300.05

       ~

(General) depending on the action 9 level of the event.

3. Assignment of individuals:

a. Log keeper

b. RMT Offsite Teams

c. Dose Assessment Indi-l2 vidual(s)

d. .

ConLeol Room Communicator

c. NRC Communicator

f. State and County I. Communicator

g. RMT Communicator

                                                                                                  ~

h. Teleprinter Operator

4. Ensure offsite RMT's are sent out in downwind direction for survey per AD 1850.05 _,

5. Ensure offsite dose estimates are being made per AD 1827.10

6. Assign a C&RT individual for air-borne iodine counting and analysis per AD 1850.05 f

                                                                                    .              Attachment 3 Page 1 of 2

                                                .. . 15         EI 1300.08.3 ECC ClfECKLIST (con't)

ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS

7. Evalu.te what protective actions should be taken based on AD 1827.12 for the plume exposure pathway and make tecomendations to the I State and County as necessary.

Affected areas should be desig-nated as shown in Attachment 4. I. 8. Complete the Essential Information form (Attachment 2) and release to the State and County Emergency Operation Centers as needed.

9. Verify that the Shift Supervisor -

has requested the post accident sampling procedure AD 1850.04 be '- put in service per the Station Chemist and llcalth P hsicist

10. Ens 6re total population exposure calculations are made p,er step u .

• 5.7.3(b) of this p'rocedure

11. Coordinate the activities of the I' following individuals as necessary:

a. Community Assistance Com-municator

b. CorporuLc ManagemenL Com-municaLor

c. Public Relation: Com-municator Iteviewed by , Filed by 3l Station Superintendent Emergency Planning Super-s visor Attachment 3 Page 2 of 2

EI 1300.08.2 16 Sector and Zone Designators for Emergency Planning Zones Sector Nomenclature Zone Nomenclature Sector in Degrees True 22 1/2* Miles from i North from Facility Sector Facility Zone' 348.75' to 11.25' A 0-1 1 11.25' to 33.75* B 1-2 2 33.75' to 56.25' C 2-3 3 56.25' to 78.75' D 3-4 4 78.75* to 101.25' E 4-5 5 101.25' to 123.75' 5-6 lI- . 123.75' to 146.25' 146.25* to 168.75' F G H 6-7 7-8 6 7 8 168.75' to 191.25' J 8-9 9 191.25' to 213.75* K 9-10 10 213.75' to 236.25' L 10-15 15 , 236.25' to 258.75* M 15-20 20 f 258.75* to 281.25' N 20-25 25 L 281.25* to 303.75' P 25-30 30 ' 303.75' to 326.25' Q 30-35 35-I 326.25* to 348.75* R 35-40 40-45 45-50 40 45 50 AREA SEGMENT - An area is ' identified by a Sector and zone designator. EXAMPLE - Area F4 is that area which lies between 101.25* to 123.75' - true north from the facility and between 3 and 4 miles out from the facility. I I E I

                                                                                          ^

f Attachment 4 Page 1 of 3

348.75 - R

       \

I 326.25 [,y ,.- s f

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[" Attachment 4 Page 3 of 3 I END L l 1

El 1300.10.0 Davis-Besse Nuclear Power Station l Unit No. 1

Emergency Plan Implementing Procedure EI 1300.10 Reentry .

I . Record of Approval and Changes Prepared by C. J. Reed 5/30/80 Date Submitted by C. E. Wells 6/13/80 Section Head Date , rm Recoc: mended by

                                                                                  " ' RB S
                                                                                            /d/h Chairmati b/3b bate .

QA Approved Quality ' Assurance Manager ^

• Date Approved by 7/ / 52/E<>

Station Superintendent g Date Revision SRB QA Sta. Supt. No. Recommendation Date Approved Date Approved Date i pmg clvl82- nA 9% 'MP'- I I -

 ?                                                                                     -

I

                                                . 1         EI 1300.10.1
        . PURPOSE To outline a course of action and the protective measures required for reentry into Station areas.

1

2. SCOPE l

Describe the actions and responsibilities of Davis-Besse personnel and offsite support groups after the Emergency Duty Officer and the Station Operations Manager have jointly determined and declared the Site or General Emergency situation stable and the Station is ready for reentry phase operations.

3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan

4. DEFINITION Not applicable

5. REENTRY ACTIVITIES 5.1 Initial Coordination ,

fl x 5.1.1 The TECo Engineering Support Director shall - 1, a) develop, coordinate and expedite plans and schedules for the reentry. . d.. .

                                                                                          ,,- a
                                                                                            ^   '

5.1.2 The Company Nuclear Review Board (CNRB) shall 1 oversee the activities of the Engineering Support Director, and the Operations Director, to assure that all nuclear safety aspects of the operations are satisfied. 5.1.3 The Station Operations Manager, under the direction of the Operations Director, shall be responsible at the site for authorizing the start of reentry activities. 5.1.4 Offsite reentry activities will be coordinated I with the State and County Disaster Services Agencies. 5.2 Recatry Requirements The following are actions which shall be considered prior to authorizing reentry. 5.2.1 Assess the need for re-entry and whether the benefits to be gained offset the potential hazards to the re-entry personnel. I

2 EI 1300.10.1 , 5.2.2 Review available radiation surveillance data. i Determine areas potentially affected by radia-tion and/or contamination. 5.2.3 Review radiation exposures of personnel required to participate in the recovery operations. l 5.2.4 Determine the need for additional personnel and the source of these additional personnel. 1 5.2.5 Review the adequacy of radiation survey instrumenta- . tion and equipment for quantity, type, ranges, and calibration. 5.2.6 Pre plan survey team activities to include:

a. Areas to be surveyed

b. Anticipated radiation and contamination levels

c. Radiation survey equipment required

d. Shielding requirements and availability

 -                                                                            e. Protective clothing and equipment required

f. Access control procedures (issuance of new REP's) -

h. Decontamination requirements, and

i. Communications required.

5.2.7 Periodic determination of the estimated total population exposure. 5.3 Reentry Actions 1 The Engineering Support Director and Operations Director shall determine the priority requirements and assure per-formance of the following activities through coordina-tion with the Station Operations Manager. 5.3.1 Determination of the initial required recovery operations (i.e., road blocks, application of locks and safety tags, etc.). 5.3.2 Visual observation of hazards or potential hazards associated with the recovery operations. i

• I..

         ,                                            ,3    EI 1300.10.1 h

5.3.3 Comprehensive radiation surveillance of plant facilities and define radiological problem areas. 5.3.4 Isolate and post areas in the plant with appro-priate warning signs and rope barriers, as Radiation Areas, High Radiation Areas, and Contaminated Areas, as appropriate. 5.3.5 Establish re-entry teams from personnel available in the Operations Support Center (OSC), Technical l Support Center (TSC), or other assembly areas. - ! Re-entry teams shall: I a. Consist of at least a team leader and a communicator.

b. Be briefed on the plan of action.

c. Be authorized emergency exposure limits as necessary and be advised to frequently check direct-reading dosimeters and withdraw to a safe area if assigned exposure limits are approached. .

I d. Be qualified for first aid, plant operations, health physics, and/or maintenance evaluation b and corrective action as necessary for the specific re-entry evolution.

e. Be equipped with, or have avsilable, appro-priate emergency equipment and protection devices. Such equipment shall be tested for I operability prioc to re-entry.

5.3.6 Direct re-entry personnel to withdraw to a safe area if severe unanticipated or unplanned con-ditions are encountered, pending further evalua-tion of the re-entry effort. 5.3.7 Ensure that re-entry teams maintain continuous communication and a continuous status of progress is maintained. I 5.3.8 Coordinate the return of the re-entry teams.

a. Ensure necessary monitoring, decontaminations, and/or first aid is performed as per appropria-te procedures.

b. Debrief team members.

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     ~       _ _ _ _ _

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l . o ) . , ., 4 EI 1300.10.1 ,

c. Report results and status of re-entry teams.

5.3.9 Determine the need for additional re-entries and for initiation of recovery operations per EI 1300.11 Recovery. . 1

6. FINAL CONDITIONS 6.1 Re-entry operations have been completed and all re-entry team members have been accounted for.

6.2 Debriefing of re-entry personnel has been completed and documented. I e V e I I I f < END

                 +

r-C [] 0(9 DAVIS-BESSE REVISION COVER SilEET I July 15, 1982 DATE

.I TO:       )k i     O     l  liL      ( (,

O tA t t - \'"' II > FROM: EMERGENCY PLANNING & PREPAREDNESS SUPV.

SUBJECT:

Davis-Besse EMERGENCY PIAN IMPLEMENTING MANUAL Manual Changes ) l This letter transmits additions and revisions to the Davis-Besse EMERGENCY PLAN IMPLEMENTING MANUAL Manual. Control Copy b. Instructions for the material are as follows: REMOVE AND RETURN INSERT Revision Index 13 Revision Index 14 El 1300.09.0 EI 1300.09.1 J t !I l l l i l l Date Revision Entered Addressee Signature RETURN TO THE OFFICE MANAGER - STOP#30h0 m

T THE IOLEDO EDISON COMPANY

                     ,          DAVIS-BESSE NUCLEAR POWER STATION
  ..                          DfERGLNCY PLAN IMPLEMENTING PROCEDURES REVISION INDEX I
   -f
  "             PAGE REVISION    PROCEDURES           REVISION   TD!PORARY MODIFICAT 3S 1    0        EI 1300.00               2 EI 1300.01               3 EI 1300.02               2 l                             EI 1300.03 2

, EI 1300.04 2 EI 1300.05 EI 1300.06 2 EI 1300.07 2 EI 1300.08 3 EI 1300.09 1 EI 1300.10 1 EI 1300.11 0 T-6018 l, EI 1300.12 1 T-5850, T-5918 l JJ Revision 14 July, 1982

  -O                                     -

a.

EI 1300.09.O Davis-Besse Nuclear Power Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.09 Emergency Support Center Activation . 1 1 Record of Approval and Changes Prepared by G. J. Reed 5/30/80

                                                        .              Date Submitted by                 C. E. Wells                       6/13/80 Section Head                        Date Recommended by I[8M                                     O t -

SR5 Chairaffn Dat5 J QA Approved // M Qual'ity' Assurance Manager Date Approved.by VO Wi -cm MbN Station Superintendent Date 1 Revision SRB QA Sta. Supt. No. Recommendation Date Approved Date Approved Date l MW V/r"f tvA p 9 b 'n u I

I 1 EI 1300.09.0 , 1. PURPOSE To outline the activation of the Emergency Support Center (ESC).

2. SCOPE To describe how the steps are taken for response to an emergency from the ESC.

3. REFERENCES l

3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Davis-Besse Nuclear Power Station Emergency Telephone j Directory 3.3 Station Response to Emergencies EI 1300.00 3.4 Unusual Event EI 1300.02 3.5 Alert EI 1300.03 3.6 Site Emergency EI 1300.04 O 3.7 Ceneral Emergency El 1300.05 Li 3.8 TECo Corporate Radiological Emergency Response Procedures 3.9 Public Relations Policy and Procedures Manual l

4. DEFINITION 4.1 Emergenc :pport Center (ESC) - The TED Edison Plaza Building',moledo, Ohio is designated as the ESC. Key technical and non-technical groups of the offsite emer-gency organization can be housed here.

5. ACTIONS I 5.1 The Station Superintendent shall notify the Operations Director that an emergency exists.

5.2 Upon being informed of the emergency, the Operations Director shalI notify the Emergency Director and the Vice l'renident - l'ubl ic 1(elations. 5.3 The Operations Director shall make reconuendaLions Lo the Emergency Director for activation of the necessary portions of the Offsite Emergency Organization.

2 EI 1300.09.1 5.4

• Those portions of the Offsite Emergency Organization I activated will function as per the TEco Corporate Radio-logical Emergency Response Procedures.

a. To facilitate Corporate emergency response, personnel have been designated a Notification Level number.

1. Level I Directors - those personnel nece:rciy for I immediate response at the declaration of an Alert, Site, or General Emergency.

I 2. Level II Directors - those personnel necessary at the declaration of a Site or General Emergency.

3. Level III Directors - those personnel necessary at the declaration of a General Emergency to assist in a full Corporate response.

I 1 b. Nuclear Support is provided by the Operations Director, who has direct control of the accident management through Station personnel, and the Engineering Support Director (Nuclear Engineering & Construction Director), who is responsible for engineering and recovery planning. I

c. The overall dissemination of information concerning the accident, emergency activities, re-entry, recovery, and on going Corporate activities will be provided by I the Public Relations Mission headed by the Public Relations Director.

d. The Administrative and Logistics Director will be responsible for providing support in the areas of security, personnel, transportation, procurement, and provisions.

c. Legal Support is provided by the Legal Director.

f. Indirect Support is provided by the Finance Director and the Assistant to the Chairman in the form of financial advice and community assistance advice.

5.5 Key Areas of the ESC are:

a. 7th Floor - The Nuclear Engineering & Construction Division (NE&C) is located on the 7th floor of the Edison Plaza. This area includes all engineering departments, as well as the Nuclear Licensing Depart-ment. This group will provide engineering support to l the Technical Support Center (TSC) and Facility

I . l 3 EP 1300.09.1 Engineering Group. A terminal of the Data Acquisi-tion & Display System (DADS) is available in this I area to acquire and transmit current data as necessary between facilities. I b. 8th Floor - The eight floor contaics the Public Relations area which will function at a center for Public Relations and community assistance efforts. I

c. 16th Floor - The Planning Center, located ou the 16th floor, will serve as the Corporate Management Dnergency Response Headquarters. It is equipped with all necessary communications, both radio and telephone, and other necessary emergency planning items.

I S.6 The Operations Director may direct that one or more of the following telephone communications loops be established as needed per the DBNPS Emergency Plan Telephone Directory:

a. Technical Data Loop

b. Technical Management Loop

c. Policy Management Loop

    /~N

d. Public Relations Loop 1 S.7 The V.P. Administrative Services - Nuclear or his designee shall coordinate the response activities of the ESC.

6. EMERGENCY SUPPORT 6.1 When act ^ ted, the ESC will provide Station support for emergenk,perations. This support includes, but is NOT limited to:

a. Operational Data (systems operations, set points, procedure writing, etc.)

b. Technical Data (equipment specifications, etc.)

c. Engineering (in-house, consultants, vendors, etc.)

d. Quality Assurance

e. Public Relations

     .                 f. Personnel (operational, clerical, mutual aid per-sonnel, etc.)

g. Security I

l

h. Transportation

i. Provisions (food, billeting, etc.)

j. Procurement (parts, equipment, etc.)

k. Administrative services 6.2 Requests for offsite support should be transmitted to the res-ponsible TED Department or Mission for action per the TECo Corpor-ate Radiological Emergency Response Procedures.

t l 1 6.3 Refer to the Corporate Radiological Emergency Response Plan for a more detailed description of corporate response and responsibili-l ties. l u' i I END _. ___}}