ML20071A680

Public Version of Annual Emergency Preparedness Exercise 1983

ML20071A680
Person / Time
Site:	Beaver Valley
Issue date:	01/26/1983
From:	Carey J DUQUESNE LIGHT CO.
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Download: ML20071A680 (208)

Text

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Emergency .

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Exercise .

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BVPS 1983 Annual Em3rgency Exercise

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DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION 1983 ANNUAL EMERGENCY PREPAREDNESS EXERCISE FORWARD This exercise package has been developed to provide the basis for the conduct of a simulated radiological accident at the Beaver Valley Power Station Unit 1 facility located in Beaver County, Pennsylvania, through which the capabilities and effec- .

tiveness of the Emergency Response Plans for the Duquesne Light Company, the States of Pennsylvania, Ohio and West Virginia and the associated local counties can be evaluated. This package is to be utilized by the exercise controllers and observers of

'the Federal, State and local agencies, as well as the utility, to initiate, control and evaluate the activities of the parti-cipants in the exercise. -

The Duquesne Light Company approves th.is document as the standard for conduct in performance of the 1983 Annual Emergency Prepared-ness Exercise.'

'J. J. Carey Vice President, Nuclear

. Duquesne Light Company l

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BVPS 1983 Annual Emergency Exercise .

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SECTION I INTRODUGTION O

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. BVPS 1983 Annual Emergency Exe*cise '

INTRODUCTION In the interest of verifying.that the health and safety of the general

, public in the Beaver, Columbiana and Hancock County areas are protected in the event of an accident at the Beaver Valley Power Station (BVPS), it is necessary for the Duquesne Light Company (DLC) to conduct a joint annual emergency. preparedness ex,ercise with the appropriate States and local agencies. The role of the Federal government at such an exercise is to evaluate the capabilities of the utility, States and local governments to provide the necessary protection for ensuring the health and safety of, the public in the event of an accident at the RVPS Facility. In this respect, the Annual Exercise will be obyserved and critiqued by the Federal Emergency Management Agency (FEMA) at the State and local levels and the Nuclear -

Regulatory Commission (NRC) at the utility level.

The Annual Exercise, which is scheduled to be conducted on February 16, 1983, will include the mobilization of DLC', States and local personnel and resources, such that the capability to respond adequately to a simulated accident at the BVPS Facility can be verified. Exercise " players" will not have prior knowledge of. the nature of the ' simulated incident or any parts thereof such as, radiological plume release information including times,

' content, size and wather pattern used. The. exercise itself should allow those individuals and agencies.40 are assigned responsibilities in a radiological emergency to demonstrate 4 ether they are adequately trained' to perform according to current emergency preparedness plans and procedures.

. This package has been developed to assist the exercise controllers and

! observers in the conduct and evaluation of the Annual Exercise. This package

contains all of the information and data necessary to properly conduct the Annual Exercise in an efficient and coordinated manner, and is broken down as sh'own_ in the Table of Contents, page iii.

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BVPS 1983 Annual Emergency Exercise Section I EXERCISE PARTICIPANTS .

• DUQUESNE LIGHT COMPANY, BEAVER VALLEY POWER STATION BEAVER COUNTY EMERGENCY MANAGEMENT AGENCY ,

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HANC0CK COUNTY OFFICE OF EMERGENCY SERVICES COLUMBIANA COUNTY DISASTER SERVICES AGENCY PENNSYLVANIA EMERGENCY MANAGEMENT AGENCY

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DEPARTMENT OF ENVIRONMENTAL RESOURCES / BUREAU OF RADIATION PROTECTION - PENNSYLVANIA OHIO DISASTER SERVICES AGENCY _ '

5 WEST VIRGINIA. OFFICE OF EMERGENCY SERVICES l

Duquesne1.idit Company

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5:ction I BVPS 1983 Annual Emergency Exercise EXERCISE DATE AND TIME In compliance with NUREG-0654/ FEMA - REP-1, Rev.1. an.d associated federal regulations governing continuing evaluation of radiological emergency response plans and preparedness for nuclear po4r plants, Duquesne Light Company will conduct a full scale, joint annu'l emergency preparedness exer-cite on Wednesday, February 16, 1983. In keeping with the criteria to start an exercise between midnight and 6:00 a.m. once every six years, this exercise has been developed to initiate resp,onse actions beginning at 5:30 a.m. on the

. morning of Februar,y 16, 1983. The exercise has been designed to. test most of the major aspects of the stations emergency preparedness program (refer to the exercise objectives,Section II) throughout the course of the day. Antici-

, pated response actions are expecteJ to occupy the exercise participants time througnout the day on F2bruary 16, with the exercise termination point-scheduled to occur at approximately 5:30 p.m.

The date and times associated with the conduct of this exercise have been jointly agreed upon by Duquesne Light Company, the states of Pennsylvania, Ohio and West Virginia, Beaver, Columbiana and Hancock Counties as well as the Nuclear Regulatory Commission and the Federal Emergency Management Agency. .

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BVPS 1983 Secticn I -

Annual Emergency Exerc.ise CONTROLLERS AND LOCATIONS Due to the inherent escalation of events and group involvement in the first few hours of the exercise, some of the controllers or observers will transfer to alter-nate locations as the response escalates. It has been tentatively broken down in the following manner, however, depending on the actual response actions of the participants.and the amount of " free play" allowed by the controllers, some of these positions may alter during the conduct of the exercise.

1. Unusual Event Time Period

a. Control Room

• Controllers K. Grada -

Operations Management -

R. Varley -

Roving G. Reed -

Dose Assessment W. Mahan -

Comunications

• Observers C. Wassel -

Roving F. Pavlechko - Roving R. Caldwell -

. Management __.

• J. Brady -

Roving ,

.i b. Plant Locations

• Controller ,

T..Kuhar -

Pri. Drains Transfer Tank

• Observer Station Vent Switchover

c. Inplant Radcon

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• Controller .

D. Kochman -

Rm-215-A Alarm Investigation

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• Observer K. Winter -

Primary Auxiliary Building

d. 0; C Corporate News Center

• Controller F. Skledar -

Press Release 4Ductuesne @ hlxn/

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7 BVPS 1983 Section I Annual Emerg:ncy Exerc,isa-

e. 'Offsite Locations ,

• Counties

• C. Wike -

Columbiana Hancock ~

• F. Klauss -

Beaver

• States Ohio West Virginia Pennsylvania

2. Alert Time Period

a. Control Room

• Controllers K. Grada -

Operations Management G. Reed -

Roving

• Observer R. Caldwell - Management ^

• J. Brady -

Consnunications ,

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b. Plant Locations .

• Controllers T.-Kuhar - Primary Drain Txfr Pump (8:02)

T. Kuhar -

Cable Tray Mezz. (8:20)

Elec. Cable Repair

• Observers B. Zamule -

'0SC

- Cable Tray /Tagouts

c. Inplai1t Radcon

• Controller D. Kochman -

Isotopic Breakdown

• Observer

• K . Winter -

Primary Auxiliary Building P. Gianatusus - ROC

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BVPS 1983 Secticn I Annual Em2rgency Exerc,ise

d. Chemistry

• Controller l

J. Wenkhous -

Pri. Coolant Sample

e. Technical Support Center

• Controllers R. Varley -

Management .

W. Mahan -

Comunications/CATV C. Wassel -- Dose Assessment -

R. Hruby -

Engineering Assessment

• Field Controllers _

• C. Roszkowski -

Field Monitoring M. Shaw .- Field Monitoring F. Straccia -.

Field Monitoring

• Observers W. Wirth -

Roving J. Peters -

. Roving ___'

F. Pavlechko -

Roving s

• J. Peevey -

Dose Assessment

• G. Randolph -

Engineering Assessment

• H. Stokes --

Admin. and Ligistics.

f. Security

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• Controller A. Middleton -

Roving

• Observer

• C. Lopes -

,Reving (Fire Dept. Entrance)

g. DLC Corporate News Center

• Controller l

F. Skledar -

Press Release /CNC Activation

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• Observer

• K. Schlecker -

CNC Activation -

h. Offsite Locations

• Counties

• C. Wike -

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• F. Klauss -

Beaver

• States Ohio ~

West Virginia Pennsylvania

3. Site Area Emergency Time Period

a. Control Room

• Controller K. Grada -

Operations Management -

Observer R. Caldwell -

Management

• J. Brady -

Communications

b. Plant Locations

• Controllers -

T. Kuhar -

~ Annunciator Fuse Panels Cable Tray Mezz.

• Observers B. 7amule -

OSC Roving c .' Inplant Radcon

• Controller l D. Kochman -

Isotopic Breakdown

• Observer .

l K. Winter -

'Pri. Auxiliary Building P. Gianatusus- - ROC

d. Chemistry l

• Controller .

J. Wenkhous -

Pri. Coolant Sample

• Duquesrae @Cori1 par 1y

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8 BVPS 1983 Secticn I -

Annual Emerg:ncy Exercise

e. Technical Support Center

' Controllers R. Varley - Management W. Mahan -

Communications /CATV R. Hruby -

Engineering Assessment

• Observers -

• J. Peters -

' Roving F. Pavlechko -

Roving

• G. Randolph -

Engineering Assessment

• H. Stokes -

Admin. and Logistics

f. Emergency Operations Facility ,

' Controllers G. Reed -

Management C. Wassel -

Dos'e Assessment W. Etzel - Engineering

• Field Co.ntrollers

• C. Roszkowski - FieldMNit'o ring. s M. Shaw - Field Monitoring F. Straccia -

Field Monitoring ,

• Observers W. Wirth -

Roiting -

. *R. Leddick -

Roving

• J. Peevey -

Dose Assessment

g. Security

• Controller-A. Middleton - Roving

• Observer -

• C. Lopes -

Roving (Fire Dept. Exit)

h. DLC Corporate News Center .

• Observer ,

• K. Schlecker - CNC Deactivation

i. DLC Emergency News' Center

• Controller F. Skledar -

Press Releases / ENC Activation i

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BVPS 1983 Section I Annual Emergency Exerc,ise

j. Offsite Locations

• Counties

• C. Wike - Columbiana Hancock

• F. Klauss -

Beaver .

• States -

Ohio West Virginia

- Pennsylvania .

4.* General Emergency Time Period

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a. Control Room

• Controller K. Grada -

Operations Management

• Observer _

R. Caldwell - . Management _.

• J. Brady -

Communications' s

b. Plant Locations

• Controllers T..Kuhar - PAB Entry ,

B. Haney . Medical Aspects B. Bradley -

Medical Aspects NOTE: A volunteer individual to play the . injured victim will be used.

• Observers B. Zamule -

0SC

- Roving

c. Inplant Radcon .

• Controllers D. Kochman - Inplant s'urveys M. Burke - Inplant surveys

• Observers

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BVPS 1983 Section I Annual Emergency Exerc,ise

d. Chemistry

• Controllers J. Wenkhous -

PASS Analysis G. Weikel -

Roving ,

e. Technical Support Center

• Controllers ,

R. Varley -

Management W. Mahan -

Comunications/CATV R. Hruby -

Engineering Assessment

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' Observers

• J. Peters -

Roving

• G. Randolph -

Engineering Assessment

f. Emergency Operations Facility

• Controllers , _

. G. Reed -

Management -

C. Wassel -

Dose Assessnent -

W. Etzel -

Engineering

• Observers ,

s F.'Pavlechko .i Roving W. Wirth -

Roving

• R. Leddick -

Roving

• J. Peevey -

Dose Assessment

• H. Stokes -

Admin. and Logistics

• Field Controll'rs' e ,

• C. Roszkowsk'i -

Field Monitoring M. Shaw. -

Field Monitoring F. Straccia . Field Monitoring

• News Input Controller W. Conover -

National News Inquiry

g. Security .

• Controller A. Middleton -

Roving Duquesne @ Con 1paq

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.Secti8n I Annual Emergency Exerciso

• Observer I

• C. Lopes -

Accountability / Access Control

• G. Ge11 rich -

Evacuation / Ambulance Entrance NOTE: A volunteer individual to play the role of a news media representative trying to get onto the site will be used.

• W. Conover -

News Media Intruder ,

• G. Brown -

News Media Intruder

h. DLC Emergency News Center

• Controller ,

F. Skledar -

Management-

• Observer

• K. Schlecker -

Roving

i. Offsite Locations .

• Counties , ,

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• C. Wike -

Columbiana

- Hancock

• F. Klauss -

Beaver

• States Ohio

- West Virginia

- Pennsylvania I

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BVPS 1983 Section I Annual Emergency Exercisa OVERALL SCHEDULE'0F EVENTS

• *

• FEBRUARY 15, 1983 * *

• 9:00 a'.m. -

Orientation for station personnel at the SAPS Visitor Center - '

2:00 p.m. -

Exercise Controller.and Observer Briefing at the SAPS Visitor Center (the NRC, States and FEMA me have representatives in attendance)

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• FE'BRUARY 16, 1983 * *

• 5:00 a.m. -

AllOnsiteExerciseControllersandObserversidentifiedin the Unusual Event Exercise Organization (see Section VIII organization charts) assemble in the conferei. e room near the Unit 1 Control Room 5:30 a.m. -

BVPS 1983 Annual Exercise comences (for detailed exercise sequence of events refer to Sections V and VI) 6:15.a.m. -

Offsite EOC.0bservers should be in place 5:25 a.m. -

Declaration of an Unusual Event (approx.)

6:30 a.m. -

PID Controller should be in place at the DLC Corporate News Center 7:30 a.m. -

. All Onsite Exercise Controllers and Observers identified in the Alert Exercise Organization (see Section VIII organization charts) who were not previously involved at the Unusual Event Level, assemble in the Administration Building Conference Room l 7:55 a.m. -

Escalation to an Alert (approx.) ,

10:00 a.m. - All Onsite Exercise Controllers and Observers identified in the l Site Area Emergency Exercise Organization (see Section VIII

- organization charts) who were not previously involved at the Alert Level, assemble in the Administration Building Conference Room 10:38 a.m. - Escalation to a Site Area Emergency (approx.)

! 12:30 p.m. - All Onsite Exercise Controllers and Observers identified in the General Emergency Exercise Organization (see Section VIII organization charts) who were not previously involved at the

- Site Area Emergency level, assemble in the Administration Building Conference Room

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BVPS 1983 Secti@n 1 Annual Emergency Exercise 1:07 p.m. -

Escalation to a General Emergency (approx.)

3:30 p.m. -

De-escalation to an Alert (approx.)

5:30 p.m. -

BVPS 1983 Annual Exercise concludes (approx.)

• *

• FEBRUARY 17, 1983.* *

• 10:00 a.m. - Station critique of the exercise is held at the SAPS Visitor Center (observed by the NRC) 1:00 p.m. -

Columbiana County informal critique is held at the County EOC 2:00 p.m. - NRC critique of the exercise is held at the SAPS Visilor Center (forDLCManagement)

• • • FEBRUARY 18,.1983 * *

• 10:00 a.m. - Formal public critique of the exercise by DLC and FEMA is held at the Willows Motel e N e

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• - BVPS 1983 Section I Annual Emergency Exercise '

EXERCISE ABBREVIATIONS ,

BCEMA Beaver County Emergency Management Agency BVPS ' Beaver salley Power Station CCDSA Columbiana County Dis ~ aster Services Agency CFR Code of Federal Regolations. -

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DBA Design Basis Accident DER /BRP Department of Environmental Resources / Bureau of RadiationProtect. ion (Pennsylvania)

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DLC- Duquesne Light Company DOE Departme'nt of Energy (Us)'

EAL Emergency Action Level ENC Emergency News Center ENS Emergency Notification System Emergency Operations Center EOC EOF Emergency Operations Facility ,

s EPA Environmental Protection Agency EPS Emergency Planning Supervisor EPZ Emergency Planning Zone l

ERC Emergency ~ Response Centerr FEMA Federal Emergency M'anagement Agency FSAR Final Safety Analysis Report .

HCOES Hancock County Office of Emergency Services Agency l

INPO Institute of Nuclear Power Operations l LEARN Law Enforcement Activity Radio Network LCO Limiting Condition for Operations LOCA Loss of Coolant Accident i

LPZ Low Population Zone -

1 NRC Nuclear Regulatory Commis's ion (US)

NWS National Weather Ser. vices ODSA Ohio Disaster. Services Agency .,

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ORC Offsite Review Conmittee -

j OSC Operations Support Center -

OSC Onsite Safety Committee

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BVPS 1983 Sectisn I Annual Emergency Exerc,ise PAG Protective Action Guides PEMA Pennsylvania Emergency Management Agency ROC Radiological Operations Center '

SAPS Shippingport Atomic Power Station SPRING Stationary Particulate, Iodine, Noble Gas Monitoring System TSC Technical Support Center WV0ES West Virginia Office of Emergency Services

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Wind Dispersion Factor (Chi /Q)

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BVPS 1983 Section II Annual Emergency Exerc,ise J

DUQUESNE LIGHT COMPANY _

BEAVER VALLEY POWER STATION

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Exercise Objectives -

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Stction II BVPS 1983.

Annual Emergency Exercise DUQUESNE LIGHT COMPANY Beaver Valley Power Station 1983 Annual Emergency Preparedness Exercise SCOPE:

The 1983 exercise, scheduled for conduct on February 16, 1983 will simu-late accident events culminating in a radi.ological accident and resultant off-site releases from the Reaver Valley Powr St& tion, located in Beaver County the state of Pennsylvania. The exercise will involve events that test the effectiveness of the Stations Emergency Preparedness Program and the inte-grated capabilities of the utilities emergency organization and the state and local agencies in Pennsylvania, Ohio and West Virginia. The exercise will include the mobilization of state and local personnel and resources adequate to verify their capability to respond to an accident.

OBJECTIVES:

• The exercise objectives are provided as separate sections, broken down into the objectives for the station and those of each state / local agency. ~

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4 59ction II BVPS 1983 l Annual Emergerycy Exercise In order to establish the scope and. boundaries of the 1983 RVPS emer-gency exercise scenario,.a definitive set of. objectives had to be developed. l These objectives not only are used to ascertain the required input to the

. exercise. sequence of events, but also to establish evaluation critique areas to be graded by the exercise controllers and observers duri'ng actual conduct i

of the exercise. ' The following objectives are to be used for this purpose. l NOTE

The objectives listed with an asterisk (*) to the right indicates that objective is used as both a scenario development objective and a controller / observer evaluation objective. _ The

{ other listed objectives are strictly to be used as ev'aluation objectives to enhance the grading criteria.

A. Overall Onsite Objectives

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1. Demonstrate the capability to carry out protracted. emergency responso activities through the identification and implemen-tatior, of a shift turnover for all key BVPS emergency response organization members.

2. Demonstrate efficient and reliable communications /information flow from the station ERF's to offsite agencies.

3. Demonstrate the ability to. provide adequate administrative and logistical ~ support for non-Duquesne 1.ight emergency support -

personnel. -

4. Demonstrate the ability to mobilize corporate level support,in i

response to the incident.

5. Demonstrate effective rumor control techniques.

6. Demonstrate'the proper utilization of the BVPS ERF's and that ar; equate emergency response equipment-exists.

7. Demonstrate the BVPS emergency organization's ability to make proper decisions related to emergency radiation exposure guidelines, and the capability to imp.lement these decisions.

8. Demonstrate at all BVPS emergency facilities the ability to establish and maintain solid accident management command and control authority and mai'ntain continuity of authority -

throughout the exercise..

9. Demonstrate the ability to formulate and make protective action recommendations to protect station personnel and the general -

' public based on plant parameters and/or field monitoring information. .

10. Demonstrate station re-entry and recovery capabilities wlth

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respect to immediate emergency re-entry needs and long' term accident de-escalation aspects. ~

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Section 11

. BVPS 1983 Annual Emergency Exercise.

B. Operations Objectives

1. Demonstrate the control rooms ability to recognize operations

• symptoms indicative of degrading plant conditions.

2. Demonstrate proficiency in evaluating parameters, properly

• categorizing the situation utilizing the station's emergency action level scheme,_ and making the requisite emergency.

classification.

3. Demonstrate the opera. ting shift's capability to assemble and

• l dispatch emergency squads in response to in plant problems.

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4. Demonstrate the ability to properly' escalate /de-escalate the

• emergency classification.

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5. nemonstrate efficient and effective notification / alerting procedures and methods.

6. Demonstrate the ability to augment the on-shift emergency organization to support emergency operations in a timely and effective manner.

7. nemonstrate effective communications / informational flow from the control room to supporting locations, s a

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8. Demonstrate the capability to shift authorities-and responsi-bilities from the on-shift emergency' organization to the onsite and offsitie emergency organizations upon their activation. -

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9. Demonstrate the ability of the Shift Technical Advisors to

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conduct accident assessmerit activities, and evaluate plant conditions / stability to_ support the overall accident management objectives.

C. Health Physics Objectives

1. Demonstrat'e the necessary radiological controls to rEnove a

• contaminated injured individual from the accident scene and to assist the medical team in minimizing the consequences of a contaminated individual.

2. Demonstrate the ability to support the recovery of the plant.

3. Demonstrate the capability to perform radiological monitoring

• activities and assessments, and to formulate offsite radio-logical dose projections._

D. Chemistry Objectives

1. Demonstrate the use of the post accident sampling system (with

• currently e'xistant' limitations) to obtain samples in support of accident assessment activities.

Duquesne @hpaw Tar 3 .

Section II BVPS.1983 4

Annual Emergency Exercisa

2. Demonstrate the ability to assess data obtained as a result of the sampling activities, and the ability to factor results into the .overall assessment process.

3. Demonstrate utilization of the mobile radiological van in support of offsite environmental sampling activities.

E. Engineering Objectives -

1. Demonstrate the ability to develop. alternative systems or equip-

• ment alterations in response to accident affected plant systems or components and to formulate respective procedures to accom-pany these required modifications.

2. Demonstrate the capatiility to ascertain and to requisition the

, necessary parts to perform corrective maintenance on darii~ aged equipment.

3. Demonstrate utilization and coordination of non-Duquesne Light engineering support as outlined in current letters of agreement.

F. Licensing Objectives -

1. Demonstrate the ability to develop, obtain approval for, and inplement actions which dictate operatior, of the station outside defined safety boundaries or. normal station technical speci fica.tions.

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2. Demonstrate the ability to respond to NRC inquiries'.regarding

• safety violations.

G. Security Objectives

1. Demonstrate the ability to perform personnel accountability

• utilizing the automated security system.

2. Demonstrate timely and efficient means for allowing onsite access to local offsite supporting agencies. (Fire and ambulancesupport)

3. Demonstrate. maintenance of site security throughout the exercise, and the ability to establish and control security access control points.

4. Demonstrate the ability to cope' with non-authorized intrusions

• to security controlled areas by local media personnel.

5. Demonstrate security escort capabilities. '

H. Public Infonnation Objectives

1. Demonstrate the timely release and distribution of news arinouncements.

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S:ction II BVPS 1983 Annual Em:rgency Exercise

. 2. Demonstrate coordination of news announcements with federal, State and County emergency response. agencies.

3. Demonstrate prompt activation of the Emergency News Center.

. 4. Demonstrate the ability to conduct timely and infdrmative media briefings at the Emergency News Center.

5. Demonstrate the ability to respond to outside news inquiries at

• locations other than the Emergency News Center and the reactive effort required to direct those inquiries to the proper source.

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BVPS 1983 Stction II Annual Emergency Exerc,ise O

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STATE OF PENNSYLVANIA -

AND BEAVER CO.UNTY EXERCISE OBJECTIVES e

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BVPS 1983 I S:cticn II Ar.nual Emergency Exercise )

I. NOTIFICATION A. Notification of Officials and Staff:

1. To test and evaluate the adequacy of the fixed nuclear facility incident notification and alert procedures in the following

areas: -

a. Notification by the Beaver Valley Power Station facility to three (3) states * (Pennsylvania, Ohio, West Virginia) and appropriate county governments,

b. Notification by the Pennsylvania Emergency Management Agency (PEMA) to Rureau of Radiation Protection (BRP), risk county's emergency operations center, affected states, PEMA' area E0C's selected State agencies, and the Federal Emergency Management Agency (FEMA). RRP notifies Federal Department of Energy (DOE). .

c. Notification by the county's emergency management agency (EMA) to risk municipal EMA's and county emergency response ,

staff personnel,

d. Notifcati'on municipal-EMA's to municipal emergency response staff personnel.- -

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e. Notification by. PEMA area headquarters to support' counties. ,

2. To test and ev_aluate the ability of key emergency response per-sonnel at all levels to implement .nctification procedures for fixed nuclear facility incidents, to include continuing noti-fication an'd coordination.

B. Public Alert / Notification and Infomatidn:

1. To svaluate the ability of State, county and municipal aut! hor-

'ities to alert,and notify the public.of incidents within the plume ' exposure pathay emergency planning zone of the Beaver VaTley Power Station, to include actual use of sirens, EBS announcements, route alerting, and other communications means avail abl.e.

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2. 'To evaluate the ability of. appropriate State and county author-ities to provide the public within the 10 mile EPZ of the plant

. , periodic updates of emergency status. -

l II. EXTERNAL COMMUNICATIONS l .

l A.- To test' and evaluate the adequacy of all planned communications systems among and betwen the participants.

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S:ction II . BVPS 1983 Annual Em:rgency Exercisa B. To evaluate the need for and availability of communications circuits between and among the participants. -

C. To review all primary communications circuits for back-up communi-cations capability. ,

l D. To determine the efficiency and effectiveness of communications  !

circuits such as EBS and RACES.

1 E. To evaluate the availability and effectiveness of the communications j interface with federal agencies and/or contiguous states.

III. EMERGENCY OPERATIONS CENTER (STATE /C0i!NTY/ MUNICIPAL)

A. To test and evaluate the adequacy of the emergency operations centers with respect to space, comfort and function for managing responses to nuclear' facility incidents.

B. To test and evaluate the adequacy, appropriateness, and effective-ness of the internal communications system within the EOC, to include maps and displays.

~

C. To evaluate the adequacy of staffing and competency of the staffs.

D. To test and evaluate the .adequac'y of control into the security of ~

the EOC's.

IV ., DIRECTION AND CONTROL -

l A. To evaluate the ability of key State, county and municipal . emergency r'esponse personnel to initiate and coordinate timely and effective decisions with. respect to fixed nuclear facility incidents.

B. To evaluate the capability of State, county and municipal emergency response agencies to identify and provide for. resource requirements.

To evaluate- the capability of State, county and municipal govern-

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C.

ments in coordinatfng (internally / externally) actions, needs and status of situations between organization for the purpose of l

acquiring support and evoking appropriate decisions.

0. . To evalua't e th'e', level of support and . participation provided by the -

responsible elected / appointed officials.

V. EMERGENCY PL'ANS To evaluate the ad'eq'uacy and capability of implementation of State, risk and support counties, and municipal emergency response plans. ,

r VI. PURLIC INFORMATION.

, To evaluate the adequacy of the interface of State, county and Reaver

! . Valley facility public infonnation systems with the news media, to include news media briefing rooms, rumor control measures, etc. '

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BVPS 1983 Annual Emergency Exerc,ise VII. ACCIDENT ASSESSMENT (BureauofRadiationProtection) , ,

To evaluate the effectiveness of state BRP nuclear facility accident assessment system, to include adequacy of equipment, personnel staffing and competency skills with respect to reporting, dose projection, field measurement, coordination, and communications.

~

VIII. PROTECTIVE MEASURES To evaluate the capability of'the State, county and municipal emergency response systems to make decisions and to implement sheltering cn' evacu-ation and to take actions to activate such support functions as recep-tion centers, mass care / decontamination centers, decontamination sta-tions, risk school district procedure,s, ambulance service, bus operations, and pickup points.

IX. RADIOLOGICAL EXPOSURE CONTROL A. To evaluate the capability of State, county and municipal emergency response personnel to implement access control points and traffic control points.

B. To evaluate methods for distribution, issuance, administering and record keeping of potassium iodide (KI) to emergency workers. -

C. To evaluate methods for distribution of dosimetry to emergency workers. .

D. To evaluate methods and capability of State, county and municipal .

emergency personnel for keeping records of individual radiation exposure doses.

X. RE-ENTRY AND RECOVERY To be evaluated as a separate exercise in CY 1984.

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, STATE OF OHIO ,

AND COLUMSIANA C0tlNTY Exercise Objectives ee.

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Section I'I BVPS 1983 Annual EmergGncy Exercise i

1. Demonstrate that personnel in Ohio can, perform offsite dose projections and accident assessment, for both radioactive noble gases and radioiodine.

2. Demonstrate the field monitoring capability for (1) predeter-mined area radiation le,,vels, and (2) air sampling and analysis for radioiodine and particulates in the plume exposure EPZ for plume exposure rate verification; demonstrate that results can be effectively used in detemining protective action recommen-dations.

3. Demonstrate,that onsite and offsite field monitoring teams <an be dispatched and deployed in a timely manner; that communi-cations are adequate; that radiological monitoring equipment is functional; that simulated data are accurately obtained and transmitted to the field radiological center and to the accident assessment center.

4 nemonstrate that adequate security of emergency facilities can be maintained. -

5. Demonstrate the ability to c6mmunicate with monitoring teams, rescue parties, and other station personnel as needed.

6. Demonstrate that inter-stite; intra-state, and state-federal communication and coordination betwen s'ite and EOC's and bet w en EOC's and EOF exist; that communication and coordination between State and County agencies exist and that communications systems for emergency workers are operaile and adequate. ~

7. Demonstrate that messages are transmitted :n an accurate and timely manner; that messages are properly lojged; that = status boards are accurately maintained and updated that appropriate briefings are held and incoming E0C perso~nnel are briefed and updated. -

8. Demonstrate that public information is coordinated between site.

l State, County, and Federal official ~s; that ~there are accurate and' timely press releases and briefings; that designated public information personnel are implementing their procedures.

9. Demonstrate that the designated State official is in command of the E0C; that officials designated in the plan are actually in charge of the overall coordination of the response; and that designated offsite officials are. presented in the EOF.

10 Demonstrate that decisions are coordinated among State, County and Federal agencies and among those agencies and the site and

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corporate management.

11. Demonstrate, the ability of the site, the EOF and wh state to make decisions on both the taking and relaxing of protective actions.

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SGetion II BVPS 1983 Annual Emerger)cy Exercise I

12. Demonstrate the capability to sample soil & vegetation, trans-port samples and activate state lab.

13. Demonstrate that adequate security of emergency facilities can be maintained. '

14. Demonstrate that adequate public alert / notification exists for proper instruction to the public for protective action recommen-dations.

15. Demonstrate that effective command and control can be' accom-plished for. decision making on protective action' coordination with others in counties, the state, East Liverpool and operational forces.

16. Demonstrate that adequate communication exists to support emer-gency operations, to include communication with the plant, the state, East Liverpool and the Joint Public Information Center.

17. Demonstrate that adequate facilities and capabilities exist for the conduct of decontamination operations during an accident.

18. Demonstrate that adequate facilities and capabilities exist for the conduct of care operations, to include necessary space, supplies, personnel and procedures, s

19. Demonstrate that facilities and capabilities exist for the operation of assembly areas. ,

20 Demonstrate the capability to conduct re-entry and recovery.

operations. '

21. nemo'nstrate ~ effective coordination of public information operations through participation at the Joint Public Information Center.

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Section II .

BVPS 1983 Annual Emergency Exercise d

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HANC0CK COUNTY Exercise Objectives s

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West Virginia Exercise Objectives O

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S::cticn II BVPS 1983 Annual Emergency Exercise I. NOTIFICATION

• A. Notification of Officials and Staff

1. To test and evaluate the adequacy of the fixe'd nuclear facility incident notification and alert procedures in the following areas: .

a. Notification by the Reaver Valley Powr Station facility to Hancock County.

b. Notification of the Hancock County of Emergency Services to risk municipalities and county emergency response staff personnel. .

2. To test and evaluate the ability of any emergency response staff personnel at all levels to implement notification procedures for fixed nuclear facility incidents, to include continuing notification and coordination.

R. Public Alert / Notification and Information:

1. To evaluate the ability of County authorities to alert and ~ ,

notify the public of incidents within the plume exposure pathwy emergency planning zone,-to include actual use of sirens, EBS Announcements, route alerting, and other communications means available. -

2._ To evaluate the ability of County authorities to provide the 4 public within the 10 mile EPZ of the plant periodic update of emergency status.

3* To e. valuate that an adequate public alert / notification exits for proper instruction to the public for prot.ective action recommen-dations.

II. EXTERfML COMMUNICATIONS A. To test and evaluate the adequacy of all planned communications systems between the~ participants.

B. To review all Primary Communications circuits for back-up

' communications capability.

• C. To determine the efficiency and effectiveness of EBS and RACES.

D. To evaluate the availability and effectiveness of communications interface with Federal agencies and/or continguous states.

E. To test and evaluate that interstate, intrastate, and state-federal communications and coordination betwen site and E0C and betwen EOC and EOF exists;.that communication and coordination bet wen State and County agencies exist and that communication by items for emergency workers are operable and adequate.

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Section II .

BVPS 1983 Annual Emergancy Excrcise F. Evaluate the ability to communicate with station personnei as needed.

l G. Evaluate the adequacy of communications to support emergency opera-tions to include communications with the plant, the State, munici- -

palities within the 10 mile EPZ and the Joint Public Information )

Center. j III. EMERGENCY OPERATIONS CENTER A. To test and evaluate the adequacy of the Hancock County Emergency Operations Center with respect to space, comfort, and function for managing responses to nuclear facility incidents.

B. To test and evaluate the adequacy, appropriateness, and effective-ness of the internal communications systems within the EOC, to include maps and displays.

C. To test and evaluate the internal message flow, that messages are properly logged; that status boards are accurately maintained and updated; that appropriate briefings are held and incoming EOC personnel are briefed and updated. .

D. To evaluate the adequacy and-competency of the Hancock County Emergency Response Staff. s E. To test and evaluate the adequacy of control and security into the -

EOC.

IV. DIRECTION AND CONTROL A. To evaluate the ability of key County emergency response personnel to initiate and' coordinate timely and effective decisions.

l B. To evaluate the capability of County eme'rgency response agencies to" identify and provide for resource requirements.

C. To evaluate the capability of County government in coordinating activities (both i'nternal and external), needs and status of situations betwen organizations for the purpose of acquiring support.

I

• D. To evaluate the level of support and participation provided by the i responsible elected officials.

E. To evaluate that effective command and control can be accomplished -

for decision making on protective actions, coordination with other counties, the State and operational groups.

V. EMERGENCY PLANS To evaluate the adequacy and capability of implementation of County emergency response plans.

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5 Stction l'I BVPS 1983 Annual Emergency Exerc,isa VI. PUBLIC-INFORMATION A. To evaluate the adequacy of the interface of State, County and Beaver Valley facility public information systems with the news media to include news media briefing rooms, rumor control measures; etc.

B. To evaluate that public information is coordinated between site, State, County and Federal Officials; that there are timely and accurate press releases and briefings; and that designated public information personnel are implementing their procedures. ,

VII. PROTECTIVE MEASURES-To evaluate the capability of the State and County emergency response systems to make decisions and to . implement sheltering or evacuation and to take actions to activate such support functions as assembly areas, reception centers, mass care / decontamination centers, decontamination stations, risk school district procedures, amublance service, bus operations and pickup points.

VIII. RADIOLOGICAL EXPOSURE CONTROL A. To evaluate the capability of State, County and municipal emergency response personnel to implement access control points and traffic control points. ,

B. To evaluate methods for distribution, issuance, administering.and record keeping of potassium iodide (KI) to emergency workers.

C. To evaluate methods for distribution of dosimetry to emergency herkers.

D. To evaluate the' methods and capability of county emergency personnel for keeping records of individual radiation exposure doses.

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Ssction II BVPS 1983 Annual Emergency Exercise State of West Virginia -

Exercise Objectives s

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Secticn II BVPS 1983

• Annual Emergnncy Exerc,ise I. NOTIFICATION '

A. Notification of Officials and Staff:

1. To test and evaluate the adequacy of the fixe'd nuclear facility incident notification and alert procedures in the following areas: .

a. Notification by Hancock County Emergency Services to West Virginia State Office of Emergency Services (WV0ES).

b. Notification by the Pennsylvania Emergency Maragement Agency (PEMA)toWV0ES.

2. To test and evaluate the ability of key emergency response personnel at the State level to implement notification procedures for fixed nuclear facility incidents, to include continuing notification and coordination.

B. Public Alert / Notification and Information:

1. To evaluate the ability of State authorities in assisting ,

Hancock County Office of Emergency Services in alerting and notifying the,public of incidents within the plume exposure pathway EPZ. s '

2. To evaluate the ability of State authoriti.es in assisting Hancock County Office of Emergency Services in providing t,h.e public within the 10 mile EPZ of the plant periodic ~ updates. of -

emergency status. ,

3'. Evaluate capability of coordinating actions with other States.

II. EXTERNAL COMMUNICATIONS A. To test and evaluate the adequacy of all planned communications systems among and between the participants.

B. To evaluate the ne'e'd for and availability of communications circuits bet wen and among the participants.

C. ' To review all primary communfcations circuits for back-up communi-cations capability. .

. D. To determine the efficiency and effectiveness of communications circuits such as RACES. -

E. To evaluate the availability and effectiveness of the communications interface with federal agencies and/or contiguous states. .

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Secticn II BVPS 1983.

Annual Emergincy Exere,ise III. EMERGENCY OPENATIONS CENTER A. To test and evaluate the adequacy of the emergency operations centers with respect to space, comfort and function for managing responses to nuclear facility incidents. '

8. To test and evaluate the adequacy, appropriateness and effectiveness of the internal communications systems 'within the EOC, to include maps and displays. -

'C . To evaluate the adequacy"and competency of the staff. '

O. To test and evaluate the adequacy of control and security of the EOC.

~

IV. DIRECTION AND CONTROL A. To evaluate the ability of key State emergency response personnel to initiate and coordinate timely and effective decisions with respect to fixed nuclear facility incidents. .

B. To evaluate the capability of State emergency' response agencies to ,

identify and provide for resource. requirements.

'~

C. To evaluate the c5pability o State government in coordinating (internally / externally) actions, needs ~and status of situations ,

between organizations for the purpose of acquiring support and evoking appropriate decisions. ,

V. EMERGENCY PLANS To ev'aluate.the adequacy and capability of implementation of State emergency response plans.

VI.

! PUBLIC INFORMATION A. To evaluate the adequacy of the interface of State, county and RVPS i

facility public inf.onnation systems with ,the news media to include

news media briefin'g rooms, rumor control measures, etc.

j B. To coordinate the release of , press information.

VII. ACCIDENT ASSESSMENT .

To evaluate the effectiveness of the State nuclear-facility accident assessment . system, to include adequacy of equipment, personnel staffing and competency skills with respect to reporting, dose projections, field measurement, coordination and communications.

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Section II BVPS 1983 Annual Emergency Exerc,ise VIII. PROTECTIVE MEASURES A. To evaluate the capability of the State emergency response system to assist Hancock County Office of Emergency Services in making deci-sions and implementing sheltering or evacuation a'nd to take support

, actions for the county's requirements in implementing these decisions.

B. To evaluate the capability of coordinating such actions with other States. . .

IX. RADIOLOGICAL EXPOSURE CONTROL A. To evaluate the capability of the State emergency response personnel in assisting Hancock County Office of Emergency Services to-imple-ment access control points and traffic control points.

R. To evaluate methods for distribution, issuance, administering and record keeping of potassium iodide (KI) to emergency workers.

C. To evaluate methods for distribution of d'osimetry to emergency workers. ,

D. To evaluate the methods and capability of State emergency personnel for keeping records of individual radiation exposure doses.

X. RE-ENTRY AND RECOVERY

. Will not be played in this exercise.

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BVPS 1983 A.inual Emergency Exercise 4

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SGction III BVPS 1983 Annual Emergency Exercise 1 PRECAUTIONS AND LIMITATIONS

i 1

This section provides information for all Exercise Controllers and Observers related to the rules and guidelines t.o be followd throughout the conduct of this exercise. Prior to initiation of the exercise, a pre-exercise briefing will be held to review the entire exercise process with all the -

Exercise Controllers and Observers identified in the Introduction Section of this package. -

~ '

. A. Should, at any time during the course of the conduct of this

! exercise, an actual emergency situation arise, all -activities and 1

comunications related to the exercise will be suspended. It will be the responsibility of any Exercise Controller or Observer that .

becomes aware of an. actual emergency to suspend exercise response in 4

his/her imediate area and to inform the Lead Exercise Controller of the situation. Upon. notification of an actual emergency, the Lead

. Exercise Contr suspend all ex,oller ercisewill notify all other Controllers / Observers to activities.

B. Should, at any time during the course of the conduct of this exercise, an Exercise Controller or Observer witness an exercise participant undertake any action sich muld, in the opinion of the Controller / Observer, place either an individual or component .in an unsafe condition, the Controller / Observer is responsible for intervening in the indiv1' duals actions and terminating the unsafe activity immediately. Upon termination of the activity, the Controller / Observer is responsible for contacting the Lead Exercise Controller and informing him of the situation. The Lead Exercise j controller will make a determination at that point dether to continue, place a' temporary hold on, or terminate the exercise.

C. Pressurization of fire hoses, discharging of -fire extinguishers, or initiation of any fire suppression systems, is not to occur in response to any simulated fires during this exercise. _ _

0. Nanipulation of a'ny plant operating systems, valves, breakers or controls in response to this exercise are only to be simulated.

l There is to be no alteration of any plant operating equipment, i

systems or circuits during the response to this exercise.

E. All telephone communications,' radio transmissions and public address .

announcements related to the ' exercise must begin and end with the statement, "This is an exercise (or drill)." Should a Controller or Observer witness an exercise participant not observing this ,

practice, it is the Controllers / Observers responsibility to remind the individual of the need to follow this procedure.

F. Any motor vehicle response to this exercise,

• ether it be 5 ambulance, fire fighting equipment, polica/ security vehicles or field monitor 1 rig teams, should observe all normal motor vehicle operating laws including posted speed limits, stop lights / signs, one my streets, etc.

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I S:ction 111 BVPS 1983 Annual Emerg:rycy Exerc,ise G. Should any onsite security actions be required in response' to this exercise, exercise participants are to cooperate as directed, and security representatives are to be prudent and tolerant in their actions.

H. Exercise participants are to inject as much realism into the exercise as is consistent with its safe performance, however, caution must be used to prevent overrea,ction.  !

I. Care must be taken to assure that any non-participating individuals who may observe exercise. activities or overhear exercise .communica-tions are not misled into believing that an actual emergency e.~.ists.

Any Exercise Cohtroller or Observer do is aware of an individual or group of individuals-in the immediate vicinity who may have_become alarmed or confused about the situation, should approach that individual or group and explain the nature of the exercise and its intent.

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SUMMARY

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Section IV BVPS 1983 Annual Emergency Exercise

$ EVENTS

SUMMARY

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Any emergency exercise must have a significant effort put forth in I i research and development to ensure that the events depicted are as I realistically possible as can be simulated through the use of cue cards, signs, etc. For discussion purposes,these events can generally be broken down l into two categories:

1. -Human Error, and , ,

, 2. Equipment Malfunction.

The first, human error, is the easiest and more flexible of the two categories to identify in a scenario, however, no one likes to assume that they will make mistakes, especially of the magnitude to cause significant plant damage or offsite consequences. .This does not, however, preclude using this means to provide input into the scenario, since the possibility for human error does exist bas'ed on the amount of human judgement

• involved in ,

implementing emergency response actions for off-normal plant events.

The second category, equipment malfunction, is much harder to .

incorporate into a scenario, especially idiere it is needed to cause plant damage that creates a problem to the offsite environment. This is true

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4

.because of the tremendous effort placed on equipment reliability and

• redundancy during design, fabrication and installation of systems.at nuclear power facilities. The. Safety Analysis Report, written for all nuclear

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facilities, including the Beaver Valley Power Station, an'alyzes the .

j capabilities of plant systems to maintain control over radioactive material within the plant during all types of off-normal plant incidents. Thus, in~

order to in. corporate equipment related problem ~s into the scenario, some unrealistic assumptions must be made.

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Additional.ly, the public's perception of the, exercise scenario often

. times leads them to believe that these events may very wil be probable.

Howver, it should be known that if the events in the exercise' scenario presented within were at all possible, an unanswered safety question would exist and actions would be taken to rectify the situation.

Thus, in order to achieve a sequence of events that will lead to a significant plant problem, the exercise, scenario must contain an incredible plant situation, and unlikely series of equipment failures, or an improbable operator error combined with equipmer't failures. For this scenario in l particular, tne following assumptions have been made in order to force the participants into an unusually high level of response activities that may never normally be required. '

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,Section IV BVPS 1983 Annual Emergency Exercise

. JUSTIFICATION AND BASIS FOR EVENTS

-As is indicated in the written summary (Part B of this Section), the flow of events occurs mainly in response to two in-plant situations. One is derived mainly from excessive leakage of water from the Reactor Coolant System and the other is due to electrical shorts in the plant's power distribution system. Based on these concepts, the following Emergency Action Levels (EAL's) were used to upgrade the Emergency Classification from Unusual Event to a General Emergency.

O Unusual Event'

1. Any hon-isolatable Pressure Boundary Leakage

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2. Unidentified Leakage > 1 gpm '

-> 3. Identified Leakage > 10 gpm

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4. Controlled Leakage > 28 gpm at RCS Pressure 2230 t 20 PSIG

. 5. (See also RCS/ Secondary Leaka'g e)  ;

I O Alert - '

A 1. Leakage Exceeds 50 gpm_ -

, . NOTE There are no instruments which directly measure RCS leakage. -

RSC Leakage'is determined by a leak rate surveillance procedure.

. , The instruments listed below may be indicators that a significant ~

leak exists. ,

RM-LRM-215A Containment Parti'culate Monitor RM-1RM-2158 Containment Gas Monitor i- RM-1RM-201 Containment Low Range Area Monitor

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-RM-1RM-202 Containment High Range Area Monitor TI-RC-463 Pressurizer Pwr. Relief Disch. Temperature TI-RC-465/467/469 '

Pressurizer Safety Relief Disch. Temperature LI-RC-470 Pressurizer Relief Tank Level LI-RC-460/462 Pressurizer Level .

PI-LM-100 Containment Total Pressure TI-LM-100 Containment Temperature A4-25 " Pressurizer Power Relief Disch. Temp. High" A4-26/27/28 " Pressurizer Safety Relief Disch. Temp. High" Al-58 " Containment Pressure High" Al-60/66 " Containment Pressure High High" A4-3 " Pressurizer Control Level Low" A3-96 ~ " React Flange Leakoff Temp. High"

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Section IV BVPS 1983

- Annual Emergency Exercise O'

Site Area Emergency j

--> 1. Loss of All Annunciators > 15 Minutes with Plant Not in Cold S/D

2. Uncontrolled Transient Occurs'While Annunciators are Inoperative O ~

General Emergency

1. LOCA 4 a. Loss of Coolant; Accident with failure of ECCS.

b. Loss of Coolant Accident with subsequent failure of heat removal systems;.likely failure of containment.

c. Loss of Coolant Accident with fuel failure and propable imminent failure of containment.

' Of course, the final plant condition, which leads to the General Emergency, also creates (through assumptions and simulation) a significant radiological problem that requires offsite protective action responses.-

Knowing this type of information, as well as having an understanding of the -

concepts involved in the application of this scenario, including any misnomers, is important to,the overall outcome of the exercise because of the -

attitude generated when the exercise irbeing conducted and observed.

. s First, it is important to realize (especially for the plant participants '

and observers) that the scenario is not there'to' test the Operators knowledge.

of the plant. It definitely s,hould be as realistic and as comprehensive as l

possible, however, no scenario can provide the detailed information or exact time sequence that will actually occur during a-similar plant event, .unless the exercise is run using a Control Room simulator. Even then, much of the data and observations mus't come from in-plant locations other than the Control Room, where again cue cards or signs must be used.and thus the simulation is far from realistic. What the scenario should do is to provide enough impetus to test not only the Operators, but also the rest of the response organiza-tions on their knowledge of the Emergency Plans, Implementing and/or Standard Operating Procedures, and how each must interface with the other.

Second, it should be understood that many varied conditions must be assumed initially in order to provide answers to expected Operator or Engineering responses .that will occur following each event in the scenario.

This is important, since their attitude during the exercise can effect the attitude and perception of the overall response organization - onsite as well '

as offsite. In order words, if they are given an exact or detailed summary of why their suggestion won't work to mitigate the event, they will react as if the situation is more realistic and armed with this new information attack the problem more eagerly. This eagerness and willingness to respond attitude has proven in the past to be transferred to the offsite participants. On the other hand, if they are given a "no, this won't work" answer, they get disgruntled and disgusted with the scenario, won't know where to look next and won't care since they'll expect the same answer, and this definitely has a l

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Section IV BVPS'l983 Annual Emergency Exercise detrimental transfer effect on how communications flow and how the interface with offsite agencies occurs. For this reason, a comprehensive set of initial plant conditions have been developed and no matter how unrealistic it appears to be in the beginning of the exercise, this will soon be forgotten once they are into the exercise and each of these in turn plays an active role in providing input into Operator and Engineering response actions.

Several of the initial plant conditions place design safety systems in a .

"not presently available" category, one of which (for example) would change the outcome of the exercise events drastically. This is the condition concerning the floating ring seals of the Keactor Coolant Pumps. In the scenario, a failure of a Reactor Cool-ant Pump seal is the source of the loss of coolant accident which creates serious offsite consequences. In reality, the floating ring seals are in place and if a Reactor Coolant Pump seal should fail, they would limit the loss of coolant to approximately 75 gpm rather than the 300 gpm assumed during this exercise scenario. ~

The last-aspect which should be addressed is the significant electrical problems that are assumed to occur during this exercise. These normally would q not be a problem for the following reasons:

1. Constru:: tion or maintenance personnel would not be permitted to -

perform major repairs or conduct circuit testing evolutions when the plant is in an Alert emergency (unless it was directly related to

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the cause of the Alert). ,

2. A voltage surge through the plant's power distribution system is highly unlikely and the possibility of it tripping ~ open breakers on several different panels is even more unlikely.

3. The electrical systems at Beaver Valley were designed with alternate power systems,,each with independence, redundancy, capacity, and testability to ensure that the capability exists for performing the functions required for engineered safety features (i.e., Reactor Coolant Pump, Charging Pump operation, etc.).

However, to instill some realism into the exercise-response Key Exercise Controllers (licensed or, plant or an engineer) will prompt specific actions '

and provide explanatory comments beyond the scope of i;he cue cards. This will be limited, however, and will remain within the bounds of the scenario and shall not inhibit or preclude the free play to be demonstrated by the participants in the exercise.

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Stction IV BVPS 1983 Annual Emergrncy Exerc,ise

. WRITTEN

SUMMARY

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Note: The following is a synopsis or summary of the detailed

, sequence of events listed in Sections V and VI of this e package.

- The Beaver Valley Power Station Unit I has been operating at 1007. power with only minor equipment problems identified and operationally addressed through surveillance activities. During the midnight shift, however, Operations personnel discover leakage from the Reector Coolant System in excess of Technical Specification

-limits. Later in the shift, a Containment Air Radiation Monitor alarm is received. An Unusual Event is declared at approximately

. 6:25 in the morning.

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The Operating shift crew take steps to investigate and respond to the situation, as well as to notify station personnel, Station Management, the Nuclear Regulatory Commission, and State and local authorities. Additional minor events occur in the plant, however, they do not warrant escalation of the emergency.

7 Pl' ant conditions begin changing, indicating a Reactor Coolant System leak rate of greater than 50 gpm. Upon verification, the l emergency is escalated to an_ Alert classification at approximately 7:55 that same morning. , s The Operators take actions to respond to the abnormal plant

' condition and. notify Duquesne Light personnel, the NRC, and offsite authorities. The Technical Support Center at the plant'is activated. Other emergency response personnel go on standby.

Partial activation of the local- Emergency Operations Centers occur.

The Shift Supervisor directs activities to begin shutting the plant dom. (Note that this action as well as many of the others is only simulated.) Shortly thereafter,- an electrical fire breaks out in the plants-cable tray mezzanine during electrical modification

testing. The onsite Fire Brigade is activated and offsite j assistance from the Shippingport Fire Department is requested. .

The plant is brought down to a hot standby (Mode 3) condition l and, with the assistance of the local Fire Department, the fire is extinguished. A fire watch is stationed and assessma nt and .

corrective actions for the situation begin.

A short dile later during the electrical corrective actions, a voltage transient occurs causing breakers to trip open and a loss of power to all Control Room annunciators.

Fifteen minutes later, power still has not been regained to the Control Room annunciators and a Site Area Emergency is declared at approximately '10:38. Offsite notifications are made by the Technical Support Center. The Duquesne Light Emergency Operations T#

Siction IV BVPS 1983

- Annual Emergency Exercise l

Facility and Emergency News Center are activated. T'he State Emergency Operations Centers are activated.

Actions are taken onsite to repair plant systems necessary to ensure that control of the plant can be maintained. Necessary ,

repair actions are completed to return the Control Room annunciators to service. However, a short dile later, Charging System operation is lost causing severe damage to.a Reactor Coolant Pump seal. The l -seal fails causing a ~ major loss of coolant accident and a General

Emergency is declared at approximately 1

07. Offsite notifications

] are made by the Emergency Operations Facility.

i Over a period of time, plant conditions worsen and core degradation cuases a release of radioactive material to the environment. Offsite authorities are notified and public ptotective actions are recommended. The early warning system sirens and Emergency Broadcast System are utilized to notify the public.

Plant personnel enter t' he Primary Auxiliary Building-in an attempt to isolate the source 'of the leak den one individual falls, j- injuring himself in a contaminated environment. The plant first aid personnel respond, Atle notifications are made offsite for ambulance support anu to prepare the Beaver County Medical Center-for receipt of a contaminated _ injured victim.

Plant security restricts access to the' site to non-essential personnel and provides entrance assistance,to emergency response

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personnel from the utility, local support agencies, the State and Federal governments, and requested support organizations. Two personnel are apprehended in an attempt to make an unauthorized entry.

Due to the (simulated) long duration of the event, a turnover '

between onsite response personnel occurs to provide a rest period for those initial responders'do directed the early phases of the emergency response effort.

Plant personnel-later succeed in isolating the leak in the Primary Auxiliary Building and begin stabilizing plant conditions on long term recirculation cooling. After a period of time, the radiological aspects appear to be under control and the emergency is de-escalated to an Alert at approximately 3:30 in the afternoon (per .

simulated time this is 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> and 40 minutes into the event).

Efforts continue to stabilize and improve plant conditions and over a period of time, the event is de-escalated from an emergency condition to a recovery operation. -

Following requisite reentry and recovery activities, the plant is returned to a pre-emergency status and the event response is terminated. (The time is now approximately 5:30 in the afternoon or 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> and 40 minutes into the simulated event time chronology.)

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BVPS 1983 Annual Emergency Exercise -

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SECTION V ONSITE SEQUENCE OF EVENTS ,

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f Section V BVPS 1983 Annual Emergency' Exerc,ise i INITIAL PLANT CONDITIONS A significant difficulty to overcome in any exercise scenario is preventing the exercise participants from resolving simul,ated problems prior to allowing the response from organizations both onsite and offsite from occurring. To  :

alleviate this situation to some extent is the purpose for developing compre- '

i hensive initial plant conditions. To set the stage for the 1983 Beaver Valley Emergency Exercise, the following initial plant condi'tions will be used: i

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0 Plant operating at 100% powen for t.he last six months.

O Both containment vacuum pumps are operating due to abnormal air leakage to containment placing the plant in an action statement of the plant Tech Specs (T.S. 3.6.5.2). -

0 No Steam Generator tube leaks exist.

0- Reactor Vessel head vent and Pressurizer vent are still out of service due to NRC ongoing review of procedures.

O Primary Coolant activity of < 100/E' uci/gm and 1 uct/gm I-131' identified -

earlier in the 00-0800 Operations shift. _

0 Only one Charging Pump is operable clacing the plant in an action state-

. ment of the plant Tech Specs (T. S. 3.1.2.4'for the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) with

. CH-P-1B inoperabl-e due to a broken speed ' increaser and CH-P-1C inoperable

. due to a rotor change out. .

0 One Primary Drain Transfer' Pump not operable with identified leakage into the Primary Drains Transfer Tank (DG-TK-2) at 9.8 gpm.

0 One Main Filter Bank 'of the Reactor Building and Suppl. Leak Collection System is inoperable due to problems with the. filter sprinkler system placing the plant in an action statement of the plant Tech Specs (T.S.

3.7.14.2 for the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).

O Containmen't air monitors RM-1RM-215A and B are. operating.

O Both Boron Recovery System degasification recire. pumps and systems are in service.

- 0 All three Pressurizer Power Operated . Relief Valves (PORV's) are isolated due to:

l' i -- Broken limitorque casing on MOV-RC-535.

-- Excess valve stem leakoff on PCV-RC-456 and excess closing time.

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-- MOV-RC-537 is jammed into its seat.

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Section-V BVPS 1983 Annual Em:rgency Exerc,ise INITIAL PLANT CONDITIONS (cont'd.)

placing the plant into an action statement of the plant Tech Specs (T.S. l 3.4.11).

- 0 Pressurizer Spray valve PCV-RC-455A is on its backseat due to excessive valve stem leakoff.- ..

O All 3 Reactor Coolant Pumps are operating without the floating. ring seals which were removed during the.last refueling and are scheduled to be replaced at next refueling.

0 The Special Particulate, Iodine and Noble Gas (SPING) monitoring system may not be used pending completion of NRC review of procedures. -

0 Construction personnel are performing' electrical modifications in the plants cable tray mezzanine. ~

NOTE: The sequence of events incorporates a cue numbering system as follows:

CC - Cue Card -- A 3" by 5" card with single initiating event instructions or -

data.

CS - Cue Sign -- An 81/2" by 11" or larger sheet of ~ paper indicating condi-tions in that area'of the plant or piece of' equipment.

CIS - Cue Inf'o rmation Sheet -- An 81/2" by 11" sheet of paper in a format for relaying specified and changing plant operating parameters. -

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Secticn V BVPS 1983 Annual Emergency Exerc,ise Approx. Planned Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No.'s

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. 5:30 a.m. -00/50 Plant is simulated to have been operating CIS-1

. at 1007, power. The 00-08 Operating Shift CS-1 noted a 9.8 gpm leak into the primary .

Drains. Transfer Tank DG-TK-2, source not identified except as valve stem leakoff. -

NOTE: The actual Operating Shift personnel will not be participating in the t.xercise due to plant operation safety concerns, how-ever additional operations personnel will tie present to perform the actions necessary to respond to the simulated plant conditions and

' will be briefed on the initial conditions at this time.

5:50 -00/30 The reactor cont'ainment sump level alarm- 'CC-1 is received from LAH-DA-200. The sump CS-2 i

pump flow integrator FTO-DA-102 indicates an 11 gpm lidk rate and is being pumped -

into the High Level Waste Tank which is '

currently at 94 inches..

6:20 00/00 CC-2 A Hi alarm is received from RM-1RM-2g5A Containment Air anonitor reading 3X10 cpm above background. RM-1GW-108A and B of the Gaseous Waste Process Vent System indicates increased activity levels.

6:25 00/05 Upon verification, the Plant Operators

, should use procedure EPP/I-1 to classify the situation as an Unusual Event based on exceeding Tech Spec leakage limits.

6:27 00/07 The Operators take action to identify the source of the leakage and to notify Station Personnel, Station Management, the NRC, and offsite authorities per EPP/I-2. -

6:45 00/25 Radcon personnel should be directed to CC-3 l

investigate the RM-215-A alarm.

l l NOTE: At 7:00, the actual Operating Shift crew will begin a shift change with oncoming Operation: personnel. No major scenario events should occur or otherwise t

interface with this normal shift change l operation. .

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Section V BVPS 1983 Annual Emergency Exercise Approx. Planned . .

Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events- No.'s 7:10 00/50 Annunciator window A3-121 alarms on CC-4 Abnormal. Primary Drain Transfer tank level. CS-3 DG-P-28 (Primary Drain Transfer Pump) has .

tripped and cannot be restarted. DG-TK-2

, pressure is oscillating at 65 psig. ,

7:15 00/55 The Aux. Bldg. Southwest Sump (Well Sump) - CC-5 Level Alarm is received in the Control Room.

Operations personnel take actions such as reducing the degassifier pressure to get -

below the Primary Drains Transfer Tank relief valve set point in order to stop this

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release. Investigation indicates the initial .

source of water was from valve PCV-CH-145 CS-4 leak off into DG-TK-2 at approximately 9.5 gpm.

7:16 00/56 RM-VS-102 alarms and initiates an auto- CC-6 '

matic safety features switchover of the CS-5 Station Ventpath to the filtered flow path. Operators should verify this and Radcon personnel should calculate initial dose projections for the event.

Meteorological information at this time is CC-7

,- as f611ows:

Wind Speed 2.6 mph

. ' Wind Direction 90*

150'-35' Temperature .8'F Precipitation None l

7:20 01/00 Operators should review the emergency action levels in EPP/I-1 and determine that escala-tion of the emergency is'not required.

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! NOTE: Exercise controllers shall ensure that I escalation to an Alert does not occur at

• this point.

7:30 01/10 Due to radiation levels in the Primary CS-6 Auxili_ary Building this area becomes a local limited evacuation area with access controlled to essential personnel only.

7:50 01/30 Plant conditions begin changing, including *CIS-2 makeup frequency and charging flow with a i

steady Reactor Coolant System (RCS) tempera-

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-Ssction V. '

. BVPS 1983 Annual Emergency Exercisa -

Approx. Planned ,

Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No.'s ture, and slowly increasing radiation levels as seen on RM-1RM-215A and B, the Containment Gas.and Particulate Monitors. The Operators -

should perform a RCS leak rate surveillance .

using the RCS Water Inventory Balance pro- CC-8 cedure,.OST 1.6.2.

.7:55 01/35 Based on the indicated plant conditions

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that a primary leak rate of > 50 gpm exists, the plant operators escalate to an ,

Alert emergency classification.

7:57 01/37 The Operators take action to assess and control the plant per the Abnormal Operating Procedures, AH Chapter 538 Excessive Plant Leakage. Additional actions are taken per EPP/I-2 to notify Station Personnel, Station ,

Management, the NRC and offsite authorities.

P.lant assessment activities increase and

. Technical Support Center (TSC) activation begins at this time. ,

! NOTE: Field monitoring teams may be dis- ,

patched to verify that not significant.

radiation releases have occurred.

. 7:59 01/39 The Shift Supervisor directs the plant to

' be shut down to Mode 3, until the primary leak can be properly investigated and resolved.

NOTE: If notifications are made to the Load Dispatcher, they sh.ould be annotated with "This is a drill" both before and l after the message information.

l 8:00 01/40 Radcon begins to develop the isotopic CC-9

• breakdown for the release source term.

Chemistry personnel may sample and analyze i -

the primary coolant for deviation in 1 7

chemistry specifications.

NOTE: The Post Accident Sampling System should not be used for this sample.

8:02 01/42 Operations personnel succeed in restarting CC-10 DG-P-28 which terminates the release from .

the Primary Drain Transfer Tank to the Aux.

Bldg. Southwest Sump.

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, Secticn V . BVPS 1983 Annual Emergency Exerc,ise 1

Approx. Planned 2

Time of Exercised Time .

Cue  ;

Day Hours / Minutes Onsite Sequence of Events No.'s l NOTE: Radiation levels in the Auxiliary )

Building begin decreasing.

8:10* 01/50 The Public Information Dep5rtment acti- ~

vates the Corporate News Center. .

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l 8:20 02/00 Construction workers performing electrical . CC-11 i modifications in the plant Cable Tray CC-11a l

Mezzanine re-energize a circuit that in-advertently shorts and creates severe flares and arcs. *o . one is injured however the breaker trip was not fast enough and an electrical fire ensues in the cable Tray ,CC-12 Mezzanine. The 1C Reactor Coolant Pump trips.

8:25 02/05 The Control Room is informed of the event ~

and steps are taken to activate the onsite Fire BrigadC - .

8:30 02/10 Upon arrival at the Ca'le b Tray Mezzanine, CC-13 the Fire Brigade Chief assesses the situa-

, . tion and reports to the Control Room that .

offsite assistance is required.

8:31 02/11 Operations personnel discover several CC-14 burned and damaged cables in a tray that was in the vicinity of the fire. The TSC engineering staff is requested to CC-14a identify the components powered by these cables and to evaluate potential losses of functions.

8:32 02/12 The Control Room contacts the Beaver County Communications Center to request local Fire

D,epartment response.

8:35 02/15 .The TSC is fully activated and performing engineering assessment and offsite dose projection activities.

' NOTE: No excessive offsite dose rates'are possible at this time and recommendations for protective actions should be that none are required.

Exact time may vary dependent on time of notif'ication or other factors.

, Secticn V BVPS 1983 Annual Emergency Exercise Approx. Planned '

Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No. 's 8:40 02/20 The Control Room Opdrators complete the CIS-3 plant shutdown. The plant is now in Mode 3. ,,

8:50 02/30 The fire at this point is being contained.

Station. Electricians are requested to begin CC-15

} preparation to splice the IC Reactor CC-16 Coolant Pump Cable to permit depressurization.

NOTE: The 1A Reactor Coolant Pump on the -

Charging Pump through the Chemical and Volume Control System could provide pressurizer spray flow for depressurization, however, '

, 1C Reactor Coolant Pump is a preferred method providing better flow. Also, if an attempt is made through the use of the Pressurizer PORY PCV-RC-456 to depressurize, -

this valve will fail to open. Use of the other two PORV's is already restricted (see initial plant condition,s).s .

9:15 02/55 With the assistance'of 'the local Fire CC-17 Department, the fire is extinguished and .

cleariup efforts are initiated. A fire ~

watch is stationed until such time that the proper electrical configuration is

. restored. Station emergency repair team pe'rsonnel work'on installation of a 4160 Ky cable link to restore the 1C Reactor Coolant Pump.

! NOTE: Clearance tags should be prepared l .

~ for, this and a Exercise Observer should evaluate the Tagout Procedure, however, no tags should actually be hung and no

. . equipment should be tampered with. All

. repair actions should be simulated.

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l 9;30 03/10 Plant conditions and indications are again CIS-4 assessed by the Plan ~t Operators and TSC personnel.

I 9:35- 03/15 TSC Engineering personnel identify one CC-18 of the cables as that belonging to the 1A Charging Pump (minor insulation damage).

The Shift Supervisor requests the TSC to evaluate the amount of time it would take Yf A .

S ction V BVPS 1983 Annual Emergency Exerc,ise i

i Approx. -Planned I Time of Exercised Time Cue  !

Day Hours / Minutes Onsite Sequence of Events No.'s l to reach Accumulator injection should the CC-19 1A Charging Pump trip with the present 50 gpm leak. He also requests that a 1 method be developed to' install a temporary -

backup pump for the Charging System or ,

alternate electrical feed to Charging .

l Pump 1A. and procedures for system operation.

During Anytime The Public Information Department prepares news releases concerning the accident conditions at Beaver Valley. ,

9:55 03/35 Assessment oft' he primary coolant leak and Charging Pump operation continue. The NRC_ -

and offsite authorities continue to receive updates on plant conditions from the Control Room and TSC.

10:05 03/45 The repair team members at the Cable Tray CC-20

. Mezzanine complete the temporary restoration .

of the electrical cabling system and are . , ,

ready to're-energize circuits as soon as -

repair tags are removed. ,

10:20 ' 04/00 Approval is received to remove the repair

, tags and re-energize the circuit. Repair team personnel complete the tag removal

, expeditiously..

10:23 04/03 The previously damaged Cable Tray Mezzanine circuits are re-energized, CC-21 however, a voltage transient occurs causing a current surge through the electrical busses. Several breakers in CC-21a the 125 VDC and 120 VAC power supply trip open, an alarm for loss of Vital Buss 2

, . occurs and all Control Room annunciators are lost. .

10:25 04/05 The damaged Cable Tray Mezzanine circuits are opened and again tagged. Plant Operators are dispatched to the switch boards to're-close affected breakers.

10:27 04/07 All breakers are successfully reclosed, CC-22 however, Reactor Coolant Pump (RCP) 1A has lost thermal barrier cooling water and Control Room annunicators have not CIS-5 returned. Additionally, operators become aware of a faint odor of the electrical Ducluesne @ hpa.g Tars -

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Section V . BVPS 1983 Annual Emergency Exercise

. Approx. Planned Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No.'s arcing at the Annunciator breakers. . A repair

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repair team should be dispatched to investigate.

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10:38 04/18 'Through investigation, it is discovered CC-23 -

that the power supply cables from Vital ,

Buss 2 to the plant annunciators has shorted; and must be repaired. The Emergency Director in the TSC declares a Site Area Emergency due to the annunciatort being lost for more than 15 minutes. .

10:40* 04/20 Offsite notifications are made by the TSC and actions taken per EPP/I-4. The -

Emergency Operations Facility -(EOF) initial activation begins and the Public Information Department activates the local Emergency News Center. .

-10:45 04/25 The affected cables are located and C'C-24 carefully jumpered to return the plant annunciators to servic6.

NOTE: Exercise controllers shall ensure that .

jumpers are hot actually installed during demonstration of this activity.

11:00 04/40 . . Attemp'ts are made to acquire the necessary CC-25 parts to return the IB Charging Pump to service, since the speed increaser parts that are required are not available on site.

Once the EOF is activated, the Emergency Director requests EOF assistance in acquir-ing these parts.- .

NOTE: If notifications are made to offsite

. . . manufacturers or suppliers, they should be simulated or annotated with "This is a drill" .

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both before and after the message information.

• 11:30 05/10 Offsite agencies are updated by the TSC. ,

11:40 05/20 The E0F is fully activated.

12:00 p.m. 05/40 The NRC and offsite authorities continue to receive updates from the Control Room and EOF .

• Exact time may vary dependent on time of notification or other factors.

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SectiCn V BVPS 1983 Annual Emergency Exercise Approx. Planned Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No.'s 12:20 06/00 The TSC engineers complete a design draft of l a temporary backup system to the Charging i

System. They request Nuclear Engineering -

Department approval and acquisition of needed material for installation. Pro-cedures, continue to be developed for its' ,

operation.

12:30 06/10 The NRC and offsite authorities receive plant status updates from the,TSC.and E0F _

respectively.

12:40 06/20 Relatively minor plant condition changes CIS-6 have occurred over the past hour.

NOTE: With the. plant annunciators back and conditions fairly controlled, the ,

, EOF Director may elect to de-escalate to a,n Alert. They,should be allowed to do so if they so desire, however, Exercise

• Controllers should keep EOF personne'l on station to support the latter portions of , '

the scenario when conditions require , ,

further escalation. '

1:00 d6/40 Charging Pump 1A trips, severe degrada- CC-26

. tion is indicated at the 1A RCP seal, and

'several additional plant parameters begin CIS-7 changing, indicating a loss of coolant

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accident.

l NOTE: The 1A Charging Pump trips, due to a fault or short in its electrical circuitry, causing a rapid rise in current rate which is picked up by relay i

1. 50, motor electrical protection trip.

l 1:05 06/45 Based on the indicated plant conditions, I the Operators. identify the problem as a l

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major loss of coolant accident from the 1A RCP seal. They immediately inform the TSC and EOF. They also inform the

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NRC over the ENS circuit and trip the 1A Reactor Coolant Pump.

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S;ction V- BVPS 1983 Annual Emergency Exercise Approx. Planned Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No. 's NOTE: Reactor Coolant System Loop

. isolation valves exist, however, the emergency operating procedures state .

and the Plant Operators are trained to not use these valves. Should they take action to shut the "A" Reactor Coolant -

Loop isolation valves, the electric -

motor operator on valve MOV-RC-590 fails to operate properly and the valve remains open. ,

1:06* 06/46 Reactor Coolant System pressure drops to CIS-8 1845 psi activating the engineered safety .

features systems for automatic safety injection.

NOTE: Safety In'jection Flow will not .

occur due to 'the inoperability of the ~

charging pumps. One pump will be regained at 1:29. During this time, Accumulator

, Injection will not occur unless the CC-27 operators attempt to depressurize the plant by cooling down the Primary System.~ This can be done by drawing steam from the Steam

• Gener'ators through the Atmospheric Dump

valves. Accumulator injection would then l . ,

occur at approximately 650 psi RCS pressure.

1:07 06/47 Based on the information from the Control Room, the EOF Director declares a General

. Emergency. Offsite authorities are notified.

1:08 06/48 Pressurizer level and RCS pressure con- CIS-9 tinue to drop rapidly.

1:09 06/49 Pressurizer level fluctuates and increases CIS-10 while surge line temperature decreases -

indicating possible bubble formation in -

the reactor vessel head.

1:10 06/50 Technical personnel (Engineers) are dis-patched to the State and local Emergency Operations Centers (E0C's) to provide i

• Exact time may vary dependent on Operator action and controller judgment.

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Secticn V BVPS 1983 .

Annual Emergency Exercise Approx. Planned Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No.'s technical understanding of plant condition reports., ,

NOTE: This may' occur earlier at the Site ,'

Area Emergency level if offsite authorities i request them. -

. CC-28 1:15 08/55 The reactor plant has reached saturated CIS-11 Note: Jump in conditions.

exercise time. ,

1:16 08/56 Containment Area Radiation Monitors CC-29

, indicate increased activity levels inside .

, containment.

1:17 08/57 Reactor Containment Building pressure _CIS-12

. reaches 10 psi a'ctivating the engineered safety features systems for automatic -

t Containment _ Spray.

1:20 , 09/00 The NP.C and offsite authorities are updated on plant conditions by the TSC and E0F.

CC-30 1:25 10/35 . Indications are received that core de . CIS.-13

! Note: Jump in gradation is possible. Low RWST level

! . exercise time. initiates a safety injection transfer l , to the recirculation mode.

N0'TE: Chemistry personnel should sample the primary coolant using the Post Accident

. Sampling System (PASS) some time during the next few sequence of events.

1:28 -

10/38 The NRC and offsite authorities are updated on plant conditions.

1:29 10/39 The 1A Charging Pump is successfully re- CC-31

- started. -

l 1:30 10/40 Radiation levels in the Primary Auxiliary CC-32

- Building (PAB) begin increasing rapidly. CIS-14 Sump alarms are received on the north and south sumps. RM-2178, location 9 shows increased activity. Also VS-1028 alarr.s and realigns the ventilation to the Reactor Building and Supplemental Leak Collection System. An Operator I

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Secticn V BVPS 1983 '

- Annual Emergency Exerc,ise l

Approx. Planned Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No.'s and Radeon Technician suit up, don respira- CS-7

, tors and enter the PAB to investigate the situation. .

1:40 10/50 Offsite dose projections are stepped up by the EOF. . Field monitoring activi' ties.

4 are initiated. An onsite evacuation is

.. ordered, including accountability of per-

, sonnel in the protected area. Security

restricts access to the site. -

1:45 10/55 VS-1078 alarms on station ventilation CC-33 discharge requiring offsite dose pro- ,

, jections. ,

1:50 11/00 From the PAB, the Operator reports leaks CC-34 from the Boron Injection Tank -(BIT) inlet isolation valve and inlet flange totaling -

approximately 20 gpm. Water from the leaks is reading well-above nocmal radiation .

levels due to it being, water recirculated -

from the containment sump.

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, NOTE: Requests should be made to gain.. -

authorization for exceeding emergency exposure limits for personnel working in the PAB.

i; 1:55 11/05 Sam Donaldson of the national news network CC-35 calls the EOF and requests an update on activities and what Duquesne Light plans to do.

NOTE: The EOF should not answer any of his questions, but politely refer him to the Public Information Department.

1:56 11/06 Plant parameters continue to be assessed CIS-15 by the Control Room Operators. -

2:00 11/10 The NRC and offsite authorities are updated I

on plant conditions. Offsite protective actions are recommended.

NOTE: Initial offsite protective action recommendations may be to shelter personnel in a 2 mile radius and 5 mile downwind dis-tance from the plant.

2:05 11/15 A second report c6mes in from the PAB, this time from the Radcon Technician g stating that during an attempt to decrease 74 M USSne M M P. T -

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Section V BVPS 1983 Annual Emergency Exercise Approx. Planned- l Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No.'s i

the leak from the BIT inlet valve, the l Operator had slipped and broken his leg.

Assistance is needed to remove him from ,

the area. . .,

2:06 11/16 The Stiift Supervisor requests an -

CS-8 Emergency Squad from the Operations

, SupportCenter(OSC)torespondto,

• the injured victim. The Beaver County Communications Center is called to provide ambulance service and notifi- "'

cation is made to Beaver County Medical Center to prepare for receipt of a con-taminated injured individual.

2:07 11/17 Parts are received on site for repair CC-36' of the 1B Charging' Pump. ,

2:15* '-

11/25 The EOF Director provides recommenda-tions for protective actions to the offsite -

authorities. Doses of.1 Rem whole body and 5 Rem thyroid are projected out to 7 miles from the site into the State of Ohio.

NOTE: Protective action recommendations at this point may be to evacuate personnel -

in a 2 mile radius and 5 mile downwind dis-tance from the plant and shelter from 5 out 1

to 10 miles downwind of the plant.

2:26 , 11/36 Plant parameters continue to be assessed CIS-16 by the Control Room Operators.

2 28 11/38 Isotopic results'from VS 112 are available CC-37 for evaluation.

2:29 .11/39 Attempts to isolate the source of the CC-38 release succeed in reducing the BIT -

leakage down to 2 gpm.

2:30 - 11/40 The NRC and offsite authorities are updated on plant conditions. The EOF Director makes offsite protective action reconnendations.

• Exact-time may vary dependent on personnel response and controller judgment.

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Secticn V BVPS 1983 Annual Emergency Exerc,ise Approx. Planned Time of ' Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events No.'s NOTE: The EOF Director should maintain the previous offsite protective action reconnenda-tions until field monitoring readings verify .

that radiation levels offsite are. below pro-tective action guide valves.

Afternoon Anytime Simulated members of the news media atte[npt to penetrate the site security access control. ~

2:40 11/50 The engineering approach has been approved _by the EOF and TSC staff for installation of

~

. . additional Charging System components. - Loca-tion of desired material has been completed .

with the Assistance of the Institute of Nuclear Power Operations (INPO) and is on its way. ,

. 2:45 11/55 Due to personnel in the TSC and EOF being on

• duty for nearly ten hours, a shift change of key management positions in these two -

facilities occurs. .

2:52 12/02 ~ The Plant Operators are able to initiate CIS-17

. long term recirculation on the Reactor. -

Coolant System.

~

3:00 12/10 TheNRCandofhsiteauthoritiescontinu'e

.' to be updated on plant conditions. The EOF Director continues making recommenda-

~

tions for offsite protective actions based

. on incoming data from the plant and field

. monitoring teams.

NOTEi Based on field monitoring readings and plant conditions,'all requirements for offsite' protective actions are relaxed, how-ever personnel should not be permitted to enter the evacuated areas until reentry -

operations permit it.

3:10* 12/20 Chemistry personnel' report post accident CC-39 sample results from PASS.

• Exact time may vary depending on personnel response, see note at 1:25.

Af -

Section V .

BVPS 1983 .  !

Annual Emergency Exerejse l Approx. Planned Time of Exercised Time Cue Day Hours / Minutes Onsite Sequence of Events- No.'s CC-40 3:15 14/25 Plant conditions appear to be improving CIS-18 Note: Jump in on long term recirculation with Radio-exercise time. logical aspects under surveillance.

NOTE: At this point, Exerdise' Controllers -

should lead exercise participants toward.

. de-escalation of the emergency. ,

3:30* 14/40 The NRC and offsite authorities are updated on plant conditions and that the emergency is being de-escalated to an -

. Al ert.-

. . 3:45 14/55

• Efforts continue to stabilize and improve 'CC- 41 plant conditions. Additional radwaste pro-cessing and storage facilities are acquired to provide for necessary Radwaste control.

Engineering evaluations are made on how -

these systems can be utilized and how they -

should be physically installed. .

4:00 15/10 The NRCa 'nd offsite au' thor ties are updated on plant conditions.

l-4:15 15/25 Plant conditions appear to be stable with CIS-19 continued cooldown, control of radiological releases and in-plant' radiation levels

. decreasing.

4:25 15/35 The emergency condition.is closed out and reentry efforts begin under the formation

(

of a Recovery Organization.

4:30 15/40 The NRC and offsite authorities are updated

. on plant conditions. Certain factions of both the offsite and onsite organizations l are disbanded as conditions permit.

l ..

All initial onsite reentry measures are com-5:00 _16/10 pleted and full-scale recovery efforts

. commence.

5:30 16/40 All basic recovery efforts are discussed or simulated. The. exercise is then terminated. _

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BVPS 1983 Annual Emergency Exercise 1

i 4

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SECTION VI OFFSITE SEQUENCE OF EVENTS, O

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S:ction VI BVPS 1983 Annual Emergency Exerc,ise Approx. Planned Time of Exercise Time Day Hours / Minutes Offsite Sequence of Events 1

6:20 T=0 Reactor coolant leakage in excess of Plant  :

Technical Sp'ecifications initiates the declaration of an Unusual Event by the .

Beaver Valley Power Station Control Room Staff.

6:25 00/05 - 00/35 ~ Beaver Valley Control Room notif'ies the Beaver Co. Communications Center, PEMA, Columbiana Co. Sheriff's Office, the-Communications Dispatcher at Hancock Co.

and the NRC of an Unusual Event at RVPS.

The NRC is notified via the " Red Phone" while all other notifications are completed over the BVPS Emergency Communications System.

NOTE: Due to the nature of the Unusual Event, these calls are made in a timely .

manner.

Beaver Co. -communicator logs the mess' age on the Initial No'tification Form and then contacts the BCEMA coordinator or his .

designee. .

PEMA - Communicator logs call - Notifies BRP of the Unusual Event at BVPS. PEMA notifies NV0ES and ODSA. BRP makes follow-up verification call to BVPS.

Hancock County communications dispatcher receives Initial Notification and logs on form. Notifies designated County officials and the Mayor of. Chester. Hancock Co. also receives follow up verification call to BVPS.

Colu'mbiana County Sheriff's dispatcher at -

Columbiana Co. jail receives call the logs message. Notifies CCDSA Coordinator and .

. relays message. Verification call is made and instructions to dispatcher are given.

ODSA and East Liverpool Police are noti fied. -

6:25 00/05 - 00/35 ODSA - No action will ta taken by CDSA at ,

this level. '

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dection vi BVPS 1983 Annual Emergency Exercise Approx. Planned .

Time of Exercise Time Day Hours /Mi nutes Offsite Sequence of Events NRC - logs call and remains in stand-by mode.-

n0TE: Unusual. Event notification to the NRC done-in a timely manner, within one hour.

7:55 01/35 . Based on the indicated plant conditions-that a primary leak rate of greater than 50 gpm exists, the plant operators escalate to an Alert.

7:57 01/35 - 02/07 BVPS Control Room notifies ~ BCEMS, BRP, CCDSA, HCOES and NRC the situation has '

i -

escalated to an Alert.

BCEMA Communicator logs message and relays-info to Coordinator. -Verification call is made and selected key personnel designated -

by the emergency management' coordinator

~

repiirt to the EOC. The Beaver Co. Public Information Of.ficer is notified and remains

! on stand-by. RACES is notified, alert health care, prisons and other public or, private institutions inside the risk a',rea. ,'

BRP - logs message, performs call back and l ,

notifies PEMA. BRP alerts monitoring teams. PEMA notifies BCEMA, 00SA, WV0ES, PEMA western office 'and designated State and Federal agencies.

Hancock Co. dispatcher receives call and.

logs message. Verifi~ cation call is made and State EOC contacted. The Hancock Co.

EOC is activated as are designated elected officials and government agencies.

7:57 01/37 - 02/07 Coltunbiana Co. dispatcher logs call and relays info. Verification call is made.

Adjacent counties.as wil as State Officials are contacted. Columbiana Co. -

requests Communications Officer, EOC

. Controller and East Liverpool r.epresenta-tive come to EOC. Security is also requested. The High wy Patrol, local

. school boards, municipalities and the EOC staff' are activated.

ADuquesneIidit ComparTf

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Sectionyk BVPS 1983 Anne 21 Emergsncy Exerc,ise Approx. Planned Time of Exercise Time Day Hours / Minutes Offsite Sequence of Events ODSA - will notify th'e Governor's Office, Ohio Dept. of Health, Ohio EPA and ODSA staff. The above (except Governor) will man the assessment room of State EOC. ODSA field monitoring teams and communications team (van) will be dispatched to county.

Ohio's EOF rep and PIO for Publi*c Information' Center will be in route at the Alert stage. Any future notifications should be made to EOC.

3 NOTE: Duquesne Light ' Company's Public TnTormation Dept. will provide timely new releases for the Unusual Event and Alert.

NRC - Updated via " Red Phone" from this point on the line will be continually manned and assessment will be constcnt. ,

8:32 02/12 ,

TheJVPS Emergency Organization contacts the Bea'ver Co. Communications Center to request offsite fire support. ,

The Communications Center contacts the.

Shippingport Volunteer Fire Dept. and .

reports assistance is needed at RVPS.

8:47 -

02/27 '

Offsite fire support arrives and is met by Security and Radcon.. Fire support personnel are issued proper dosimetry and escorted to the' Cable Vault.

9:15 02/55 The Fire is extinguished and clean up efforts are init.iated.

State and County EOC's are becoming staffed and operable, communications among eme.#gency organizations are established and tested. EOC support personnel are brought to stand-by. Appropriate notifications are

.made to jails, hospitals, si:hools, nursing homes and day care centers. -

9:55 03/35 Assessment of plant conditions.onsite continue. The NRC and offsite authoriti.es continue to receive updates on olant conditions from the TSC.

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S;ction VI BVPS 1983 Annual Emergency Excrc,ise Appro.x. Planned Time of Exercise Time Day Hours / Minutes Offsite Sequence of Events 10:35 04/18 As a result of electr'ica'l malfunctions.

experienced during recovery from the electrical fire, powr to the Control Room Plant Annunciator System has been lost for greater than 15 minutes necessitating the

, declaration of a Site Area Emergency.

Offsite notifications are made and the Public Infonnation Center (PIC) is activated. Public Infonnation Stafft are mobilized, rumor control and future-EBS announcements are coordinated.

, 10:40 04/18 - 04/43 BCEMA - Mobilize monitoring teams and activate transportation pick-up points.

Distribute dosimetry and KI to emergency workers. Activate decontamination stations and decon tenters, distribute survey meters .

and forms. RACES network opens and

. reception centers and mass care centers are placed on stand-by status within the county.

. BRP-PEMA - BRP dispatches monitoring team and continues assessment. PEMA - coordi-nates with Facility, Governor's office and county PIO's for news release. Dosimetry

, and KI along with report forms are issued to emergency workers. Coordinates with the risk counties and specifies the time to sound the sirens. BRP instructs to remove farm animals from pasture feed. State E0C fully activated.

~

HCOES - Continued monitoring and assessment actions and coordinates public wrning actipns with State and PEMA. Issues -

dosimetry and report forms to emergency workers.

. CCDSA - Continues appropriate call-out procedures and notification to appropriate agencies. PIO Officer is added to PIC.

CCDSA E0C is fully activated. Assembly

. . areas and care centers are activated.

l

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S:cticn VI BVPS 1983 l Annual Emergency Exerciss Approx. Planned .

Time of Exercise Time Day Hours / Minutes Offsite Sequence of Events ODSA - Ohio EOC w 'ill -be fully activated. and request for utility liaison will be made.

State EOF liaison will be in route.

NOTE: Updates from Public Information center will be provided on a timely basis. ,

11:30 05/10 , . Offsite'. agencies"an'd' NRC updated period-12:00 05/40- ically. State and county assessment actions and monitoring continue. l 12:40 06/20 BVPS Emergency Organization may elect to de-escalate to an Alert due to stabilizing conditions. If this occurs, Controllers /

Monitors should keep EOC personnel to support later portions Wien conditions require, further escalation.

1:07 06/47 A rapidly occurring loss of coolant ~

accident results in the declaration of a General Emergency being issued by the BVPS Emergency Organization. NRC and offsite agencies are notified. ,

' NOTE: Jump in exercise time from 06/Sh to

3550. During this period the following j has occurred..

BCEMA - County recep' tion and mass care centers activated. Full use of RACES

, network - to the maximum extent possible.

Receives instructions from PEMA concerning any protective actions.

1:07* 06/50 - 08/55 -

PEMA - Supplies ' direct informational i Time Jump support to West Virginia, Ohio, and risk l

counties concerning protective actions.

Arrival of Federal Response Teams. Status of supplies for mass care centers are checked.

l 1

• The jumps in the scenario are al. located to facilitate onsite accident events to occur in a realistic manner offsite actions should not be altered by these time jumps.

'Af xz. - -.-- m ,,_ ---.-._.---,_m- - - - -.

Section VI BVPS 1983 Annual Emergency Exerc,ise Approx. Planned Time of Exercise Time Day Hours / Minutes Offsite Sequence of Events HCOES and CCDSA - Following the direction of State agencies, continue offsite

. monitoring and assessment actions and

. activate response organizations.

1:20* 9/00 - 10/35 NOTE: Time jump in exercise. During this period many generic actions will be

. occurri'ng. Some of these include:

Assessing requirements for special population areas. ,

Support resource needs are assessed, and any ' unmet needs at the county level are reported to the State E0C's.

Traffic and access control points established at predetermined p'oints.

Agriculture and Water Sampling.

Constant update fr'om the BVPS Emergency Organization to the NRC and offsite agenci'es. ,

1:40 10/50 Offsite monitoring is stepped up by ali states in response to updated infonnation

, that an onsite evacuation has.been. ordered.

2:06 11/16 The Beaver County Communications Center is called to provide ambulance support at the Beaver Valley Pour Station.

Notification is made by Communications Center to local ' ambulance service that there is need for an ambulance at BVPS.

2:15 11/25 Ambulance arrives at site and escorted by Security and Radeon to injured person.

• The jumps in the scenario are allocated to facilitate onsite accident events to-occur in a realistic manner, offsite actions should not be altered by these time jumps.

• Vg .

'A@

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S:ction VI BVPS 1983 Annual Emergency Exerc,ise Approx. Planned .

Time of Exercise Time

• Day Hours / Minutes Offsite Seauence of Events Beaver County Medical' Center is notified and informed to prepare for receipt of a contaminated / injured individual. Rad Tech accompanies ' ambulance to hospital.

, , NOTE: Public.Infomation Center conducts.

. press briefings and . issues media' statements as appropriate, . .

2:30 11/40 The Emergency / Recovery managtr in the EOF makes offsite protective actions recon-mendations. NRC and offsi.te agencies are.

noti fied.

PEMA - Because of unstable plant conditions an evacuation is recommended. Traffic and access control points are established. EBS messages are released. -

BCE_MA - Under the cognizance of PEMA activates public/ alert notification system and comence appropriate EBS announcements.

. Schools, prisons, etc., are notified to evacuate.-

ODSA-CCDSA - Message is verified and aiert system is activated. Readings by offsite monitoring teams combined with BVPS recomendations lead, to ODSA evacuation recomendation. Traffic control and access

, control points are established and radiation monitoring is increased.

3:00 12/10 NRC and offsit'e authoiities continue to be updated based on' continued plant assessment and field monitoring. Offsite protective

, actions are still recommended.

EBS messages indicate appropriate actions to be taken in Pennsylvania, Ohio and West Vi rginia.

3:15 12/20 - 14/25. NOTE: Jump in exercise time.

3:30 14/40' NRC and-offsite agencies authorities are, updated on plant ~conditins and that the emergency is being de-escalated to an Al ert.

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SIction V1 BVPS 1983 Annual Emergency Exercise Approx. Planned Time of Exercise Time Day Hours / Minutes Offsite Sequence of Events Rad monitoring continues in all states.

4:25 15/35 The emergency condition is closed out and reentry efforts begin on site.

NRC and offsite authorities are updated on

. .. .. ~

plant conditions... Certain factions of

~

offsite organizatic'ns are~ disbanded as .

, conditions permit. s * <

Pennsylvania and West Virginia 9d11, end participation in the exercise at this -

point. ' -

00SA-CCDSA - Recovery / Reentry Technical Advisory Group is formed under the '

direction of the Ohio Department of Health. Recommendations of this group go to the Governor who then recommends to the

• Board of Commissioners for the final -

decision. .

l 5:30 16/40 All basic recovery efforts are discussed or simulated. The exercise is then terminated.

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BVPS 1983 Annual Emergency Exercise O

/

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SECTION VII

~

PROMPTING MATERIAL 4

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BVPS 1983 Section VII Annual Emergency Exercise 1

PROMPTING MATERIAL The use of the prompting material provided in this section is predicated on the need to incorporate into this exercise the 1atitude to allow as much

" free play" and " undirected response" on the part of the exercise participants, consistent with the ability to stage an emergency situation on the scale necessary to satisfy the objectives of all agencies involved. To this ex-tent, the use of Cue Cards, Cue Signs and. Cue Information Sheets, has been adopted to provide the necessary vital information to the exercise participants, ,

minimizing the questions and answer interactions between Exercise Controllers -

and the exercise participants.

CC -

Cue Card - A 3" x 5" card with single event initiating.

instructions or data.

CS -

Cue Sign - An 81" x 11" or larger sheet of paper, posted to indicate conditions in a particular area of the plant '

or on a piece of equipment.

CIS - Cue Information Sheet - An 8t" x 11" or larger sheet of paper, handed to an exercise participant to reflect a sequence o'f changing plant parameters over a given period of time.- ' -

s .

When disseminating the prompting material, each Exercise Controller should follow the writteri exercise scenario to ensure that the material being provided is given at th'e app'ropriate time in relation to the other exercise events. .

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1 l

BVPS 1983 Secticn VII Annual Emergency Exercisa l

1 CUE CARDS thmber Time Location To WW

• CC-1 5:50 Control Reactor , Al-49, Contaimment Sung Ievel High and 1

(-00/30) Roan Operator A6-25, Primary Hater Supply Pressure Iow, Alarms have just occurred.

CC-2 6:20 Ocntrol ,Beactor A4-71, Radiation Monitorig High (bl%215A]

(00/0,0) Roan Operator Alarm p just mcurred. Monitor readig is l 3 x 10 cpm above background.

CC-3 6:45 Primary Radoon A spurious alarm is indicated.

'(00/25) Auxiliary IV.rsonnel

. Buildig CC-4 7:10 Control Reactor A3-121, Primary Drain Transfer Tank 2 (00/50) Roan OperdL u; Ievel High-Low and .

--'A3-105, Primary Drain Transfer Tank 2 4

Punp 'r%==1 overload, alarms

, have just occurred. '

CC-5 7:15 (bntrol Reactor All-21, Auxiliary Building Southwest Simp (00/55) Boom Operator (well Sung) Ievel High Alarm has just occurred.

CC-6 7:16 Centrol Reactor A4-71, Radiation Monitoring High (%VS-102B)

(00/56) Roan Operator A4-72, Radiation Monitorig High-High

( % VS-102B), Alarms have just occurred.

CC-7 7:16 Control Reacter Meteorological Information:

(00/56) Boan Operator Wind Speed 26 nph Wind Direction 90' 150'-35' Temperature -0.8'F Precipitation Ibne CC-8 7:50 Control Plant For tratpting purposes only, a Water (01/30) Iban Operators Inventory Balance should be performed.

%t5

BVPS 1983 Section VII Annual Emergency Exercisa CUE CARDS FAznber Time Locatim To Message CC-9 8:00 Oan Radoon Fbr ptanpting purposes cnly, Radeon personnel (01/40) Iab Personnel should develop an Isotopic breakdown for the release source term.

CC-10 8:02 Primary Auxiliary DG-P-2B has been restarted terminating the (01/42) Auxiliary Operator release fran the Primary Drain Transfer Tank.

Building CC-ll 8:20 Cable Construction Inform Control Roan of severe flares and arcs (02/00) Tray Workers which have occurred in the cable Tray Mezzanine Mezzanine due to the circuit re-energization.

CC-11a 8:20 Control Reactor All-67, Cable Tray Mezzanine Fire, and -

(02/00) Iban Operator A3-120, Reactor Coolant Pump 1C flow low alarms have just occurred.

CC-12 8:20 Control Beactor All-75, Cable Tray mezzanine CD2 Discharge (02A)0)- Iban- Operator Alarm has'just occurred.

CC-13 8:30 Cable Fire Brigade Offsite Assistance is required to put out fire.

. (02/10) 'nay Chief Mezzanine CC-14 8:31 Cable A.O. in Inform Ccntrol Roan of burned and damaged cables (02/11) Tray Fire Brigade in nearby tray.

Mezzanine CC-14a 8:31 Ocntrol Shift For Iranpting purposes cnly, request the (02/11) Iban Supervisor TSC' engineering staff to identify the canponents powered by cables in the affected tray and to evaluate potential loss of functims.

CC-15 8:50 Cable Fire Brigade 'Ihe fire is being contained.

(02/30) Tray. Chief -

Mezzanine Tars M MMP8T

d BVPS 1983 l Section VII . Annual Emergency Exerc,ise l l

l i

CUE CARDS Locatim Ntznber Time To Message CC-16 8:50 control Operations Begin preparations to splice the 1C Reactor (02/30) a:x2n Support Coolant Pump Cable to allow for plant Center Depressurization.

CC-17 9:15 Cable Fire Brigade Iocal Fire Department has assisted in (02/55) Tray. Olief extinguishing fire. The area is now Mezzanine clear to permit energency repair team access.

CC-18 9:35 Tecinical TSC For prmptire purposes mly cne damaged cable (03/15) Sup crt Engineers belongs to the 1A Charging Punp (minor Center insulation damage).

CC-19 9:35 Cmtrol Shift For pronpting purposes mly, request the TSC (03/15) Rocrn Supervisor personnel to evaluate the time to reach amhilator injection should the 1A Charging

, Pump trip with a 50 gpm leak. Also, request the TSC to develop a rpethod to install a taimmy backup punp for the Charging System.

OC-20 10:05 Cable Electrical You have conpleted tayvray restoration of the

.~ (03/45) t ay aepair Electrical Cabling System. Make a request to Mezzanine Team remove repair tags and re-energize the affected circuits.

CC-21 10:25 Cable Electrical For pwyLing purposes only, you have just re-(04/05) Tray Repair energized the Ireviously damaged circuits.

m nine Team Indications are that the circuit is still damaged, because the breaker trips cpen.

OC-21a '10:23 centrol asactor Al-11, Vital Bus II trouble and -

(04/03) Ibcrn Operator Al-19, Vital Bus II Battery Operation alarms have just cxx:urred. All annunciators go dark.

CC-22 10:27 Elec- Plant All affected are successfully reclosed, (04/07) trical Operators however, a faint odor of electrical arcing is Busses apparent at the Annunciator breakers.

4Duquesne @ hpany

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BVPS 1983 SGction VII Annual Emergency Exercise CUE CARDS Nunber Time Tocation To Message CC-23 10:38 Plant Eladrical Power supply cables from Vital Buss 2 (04/18) Annunciator Repair to the plant Annunciators have shorted out. I Breaker Team Panel CC-24 10:45- Plant Electrical , 'Ihe Annunciator power supply ables are (04/25) Annunciator Repair junpered out, all plant Annunciators return

~

Breaker Team to service.

Panel -

CC-25 11:00 Control Shift For pecnipting plum only, request the (04/40) Ibczn Supervisor TSC to determine if in fact the parts nW to repair the IB Charging Punp are not cost and if not, dere they can be .

located.

CC-26 *1:00 0:ntrol Beactor Charging,Punp'1A has just tripped and will

'(06/40) Ibczn Operator not restart.

CC-27 1:06 Control Shift For scenario purposes onlh, depressurizing (06/46) accan Supervisor the plant by drawing steam off the' Steam Generators through the A: w?+ric Dunps will not be permitted.

CC-28_ 1:15 All All For scenario plupOses, a two hour time jung (08/55) has just occurred. During this period, the loss of coolant accident has not been stopped and the plant has reached saturated conditions.

CC-29 1:16 Control Reactor Cortainmant Area Radiation Monitors indicate (08/56) Rocan Operator incraa=v1 activity levels.

6

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BVPS 1983 Section VII Annual Emergency Exercise CUE CARDS Ihrnber Time Iccation To Messwe CC-30 1:25 All All For scenario purposes, a one hour and 30 (10/35) minute time junp has erred. During this time period, Ccntainment Spray has punged down the RHST and placed safety injection in the recirculation node. It has also been identified that protracted emergency organization cperation wi11 be necessary. For purposes of this emercise to demonstrate a shift change in organization capabilities, the following key management positions should identify their reliefs who may be currently in the facilities. 'Ihese positions should be released from the exercise activities to return at 2:45 pm for relief turnover.

They are:

Emergency Direct.or TSC Technical Support Coordinator 'ISC

' EA & DP Cxxrdinators TSC Radiological Cmtrols Coordinator TSC Emergency /Remvery Manager IDF Support Services Manager IDF Offsite Agency TA=4<rn EOF Engineering nanager EOF CC-31 1:29 Control Reactor IA Charging Pump is successfully restarted.

(10/39) Roczn Operator CC-32 1:30 Ocntrol Reactor Primary Auxiliary Building Radiaticn levels (10/40) Rocm Operator are rapidly increasing.

CC-33 1:45 Ocntrol Reactor .

VS-107B Station Ventilation Discharge Alarm (10/55) Ibczn Operator has just occurred.

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BVPS 1983 Section VII Annual Emergency Exerc,ise l

CUE CARDS thaber Time Tecaticm - To Message CC-34 1:50 Primary Beactor N1== from Boron Injection tank Inlet (11/00) Auxiliary Operator Isolation valve and inlet flange totals Building aan.wdmately 20 gpm.

Above normal radiation levels are observed in water from the leaks.

CC-35 1:55 Exercise Dnergency 'lhis is Sam Donaldson of the Natimal (11/05) Controller Operations News Network. I have a few questions to Facility *ask you. First,1diat has Ire 51piategl the event. W at are the present plant conditions' and what are you planning to do to protect the public?

CC-36 2:07 Security Security Delivery van with repair parts for the 1B (11/17) ,

Guard Charging Pung have just arrived.

l ~

CC-37 '2:28

, Cnem Chemistry VS-112 Isotopic results are ready for (11/38) Iab Cocedinator evaluation. ~

CC-38 2:29 .

Prbnary Beactor Baron Injecticn Tank leakage has been reduced (11/39) Auxiliary Operater down to cerwdmately 2 gpm after several Building at 6 ets to isolate the source of the release.

CC-39 3:10 Chen Chemistry Pest M4nt sanple results frczn pass are (12/20) Iab Coordinator reported.

CC-40 3:15 All All For scenario purposes, a two hour time (14/25) jung has just occurred. During this period, plant conditions ingrove on long-term recirculations.

i CC-41 3:45 Bnergency Bnergency/ For prwviing purposes (mly, radwaste (14/55) Operations Recovery 1:rocessing and storage facilities should Facility Mar ==2 be assumed to have been required.

- Engineering evaluatiora should be nede on how radwaste facilities can be used and'

- how they should be physically installed.

Ductuesne Lidrt pany

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1 BVPS 1983 S:ction VII Annual . Emergency Exercise l

1 l

CUE SIGNS r,W Ia:ation Message CS-1 Primary Auxiliary Valve stem leakoff is drainirg into Building Elev. 714' DG-TK-2.

i CS-2 Containment Sump FIO-DA-102 indicates 11 gpn. .

Integrator .

CS-3 Primary Drains DG-TK-2 pressure is oscillating around Trae fer Tank 65 psig.

CS-4 Control Rocrn, PCV-OI-145 leakoff into DG-TK-2 is 9.5 gpm.

CS-5 Control Roan Normal Station Ventilation has switched tn the nain filter banks thru the Reactor Building and Supplemental Ieak Collection System.

CS-6 Primary Auxiliary General Area Radiation levels are 100 i Building times normal.

, - CS-7 Primary Auxiliary General Area Radiaticn levels are 1000 times Building normal.

. CS-8 Primary Auxiliary Victim is conscious. Has a broken left leg Building between the knee and foot. Has a contusion on left shoulder. Radiation levels of 24,000 cpm on the left leg and 13,000 cpn around the contusion.

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BVPS 1983 g Annual Emerg;ncy Exercise 3

CUE INFORMATION SHEETS Nurrber Time Message CIS-1 5:30 Plant is cperating at 100% power, normal (00/50) temperat21res and pressures.

CIS-2 7:50 A3-58, 01aring Pump Discharge Flcw High-Im (01/30) A6-25, Primary Water Supply Pressure Im A4-4, Pressurizer Control I m Ievel Deviaticn.

Al-49, Contaiment Sunp Level High.

CIS-3 8:40 Plant is shutdown, cperating in Mode 3, (02/20) hot standby conditions.

CIS-4 9:30 Plant in hot standby conditions, 1C Beactor (03/10) Coolant Pump incperable.

CIS-5 10:27 Control Rocm annunciators are still dark.

(04/07) Valves TV-CC-105El and TV-CC-107A and 107E2 remain closed.

CIS-6 12:40 Plant in hot standby, annunciators cperating, (Q6/20) conditicos relatively stable.

CIS-7 1:00 A3-49, Olarging Pump Auto Start-Stcp, (06/40) A3-50, Clarging Pump Discharge Pressure .Im, A3-58, 01arging Pump Discharge Flcw High-Im, A3-78, Reactor Coolant Pump Seal Injecticn l

Flow Im, A3-ll5, Regenerative Heat Exchanger Ietdown Outlet 'IWnperature High, A4-35, Pressurizer Control Heater Group Auto Trip, A3-86, Reactor Coolant Pump No. 1 Seal Leakoff Tenperature High, A3-91, Non-Regenerative Heat Dcchanger Discharge Tenperature High, ,

A3-55, Volume Control Tank Discharge Temperature High, Al-49, Containment Sunp Ievel High, Al-35/43, Containment Air Partial Pressure High-Im OII/II, l

Al-36/44, Containment Air Partial Pressure Hiah-Hiah Of I/II.

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BVPS 1983 Annual Emergency Exercise g

l CUE INFORMATION SHEETS j Number Time Message CIS-7 CONTINUED 1:00 A4-3, Pressurizer Control Ievel Icw, (06/40) A4-12, Pressurizer Control Im Pressure Deviation, A4-18, Pressurizer Pressure Icw, A4-23, Pressurizer 2/3 Pressure Relief Block A3-79, Reactor Coolant. Pump Seal Isakoff Flow Im, A3-88, Reactor Coolant Pump No. 1 Seal Differentail Pressure Iow, and A3-103, Reactor Coolant Pung 1K Seal Vent Pot Ievel Iow Alarms have just occurred CIS-8 1:0'6 A5-31, Pressurizer Pressure Iow-Reactor Trip (06/46) and Safety Injecticn, A4-21, Pressurizer Im Pressure-Safety Injecticn Setpoint,

~A3-49, Charging Punp Auto Start-Stcp, Al-61, Baron Injecticn Tank Recirculaticn Flow Im, ,

Al-70, Boron Injection. Tank Tenperature Icw, Al-80, Safety Injection Planp Auto Start-Stop, Al-82, River Water Pump Auto Start-Stop, ,

A6-128, Auxiliary Feed Ptznp Auto Start-Stop,

. A7-37, Steam Generator Feed Punp Auto Stop, A6-20, Refueling Water Storage Tank Below Normal Ievel, Alarms have just occurred.

Reactor Coolant Systen Pressure 1845 psi.

i CIS-9 1:08 Pressurizer Ievel and RSC pressure dropping (06/48) rapidly.

CIS-10 1:09 ' Pressurizer level fluctuates, then increases.

(06/49) Surge line tenperature decramaaa.

CIS-11 1:15 A4-43, Reactor Core Margin to Saturaticn l (08/55) I m or Processor Failure.

A4-44, Beactor Core Margin to Saturaticn I m -I m .

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BVPS 1983 yg Annual Emergency Exercise 3

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CUE INFORMATION SHEETS Nunfoer Time Message CIS-12 1

17 Al-35/43, Containment Air Partial Pressure (08/57) High-Lew GI/II, Al-36/44, Ctritainment Air Partial Pressure High-High GI/II, Al-58, Containment Pressure High (1/3),

Al-60, Containment Pressure Intermediate High-High (1/3),

Al-66, Cartmia=nt Pressure Higti-High (1/4),

Al-72, Containment Isolation Phase B, Al-81/89, Inside RecirculationW Ptmp 1A/B Auto Start-Stop, Al-88, Spray Actuation, Al-109/ll7, Quench PLup 1A/B Auto Start-Stop, and Al-121, outside Recirculation Spray Ptmp Auto Start-Stop, Alarms have just occurred.

CIS-13 1:25 A6-22/30, nefueling Water Storage Tank Ievel

.Iow m 1/2,

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Al-26 1/4 Refuel Water _ Storage Tank Ievel Iow Al-25 2/4 Rust Io Ievel & SI Auto XPER SI Itu to Recire Initiated.

i CIS-14 1:30 All-30, Auxiliary Building, South Simp (10/40) Ievel High, A4-71, Radiaticn Monitcring High, A4-72, Radiation Monitoring High-High (RM-VS-102B), and A11-22, Auxiliary Building North Sunp Ievel High, Alarms have just occurred.

CIS-15 1:56 High Irimary cx:clant activity levels, (11A)6) recirculation continues, RCS Iressure steadily increasing.

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BVPS 1983 .

i Annual Emerg:ncy Excrcise Ssetion VII CUE INFORMATION SHEETS Number Time Message CIS-16 2:26

• Primary coolant activity levels above (11/36) normal, recirculation continues, RCS pressure steady.

CIS-17 2:52 Icng term recirculation initiated, cooldown (12/02) in progress.

CIS-18 3:15 Primary coolant activity levelf near normal, (14 /25) long term recirculation cperating properly.

CIS-19 4:15 In-plant radiation levels decreasing, control (15 /25) of radiological rel=== maintained, pIant ocmditions stable with cooldown in progress.

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Sectitn VII Annual Emergency Exerciso DOSE ASSESSMENT DATA NOTE:

The dose assessment information contained in 'this package was developed based on existing dose assessment procedures, since'the development effort, new procedures have been put into effect at th'e station. The effects of the new procedure on the dose assessment information is presently being evaluated and will be adju'sted accordingly, prior to the exercise.

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'g TIME - 1330-1430 Activity (uC1/cc) Activity (uC/cc)

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I j Kr-85 84.3 I-131 81.2 Br-84 0.7 H-3 161.0 Kr-85e 40.3 I-132 23.9 Sr-89 0.2 l Kr-87 21.4 1-133 102.2 Sr-90 0.1 f Kr-88 71.8 I-134 9.7 Y-90 0.8 Rb-88 71.8 216.0 Y-91 0.8

! ' LU Xe-131m 40.3 Y-91n 0.1 Xe-133 5778.7 Sr-91 0.1 l Xe-135m 21.4 Zr-95 0.2

'l Xe-135 160.0 Ho-99 38.3 Ke-138 9.0 Ru-103 0.2 1 .

j 6299.0 Ru-106 0.1 l Te-129 0.8 Co-60 0.1 3, , Fe-59 0.1 4

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Co-58 0.5 Te-132 11.0 s

Co-134 2.6

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Co-136 0.5 >:s

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Ba-140 0.2 ' D La-140 0.2 Pr-143 0.2 E' E' o

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FE8RUARY 1983 ANNUAL EMERCENCY PREPAREDNESS EXENCliE

.j POST ACCIDENT SAMPLE IMTA SHEEf a

EFFLUENT ISOTOPIC ANALYSIS TIME 1400-1430

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Kr-85 6.6E-3 I-131 9.6E-4 Br-84 1.0E-9 pp Kr-85e 3.IE-3 I-132 2.8 E-4 Sr-89

} 2.9E-10

',i Kr-87 1.6E-3 I-133 1.0E-3 Sr-90 1.4E-10 Kr-88 5.6E-3 I-134 1.lE-4 Y-90 1.4E-10 i Rb-88 5.6E-3 Totsi 2.3E-3 Y-91 1.2E-9

. Xe-131m 3.lE-3 Y-91m 1.4E-10 Xe-133 4.5E-1 St-91 1.4 E-10 Xe-135m 1.6E-3 Zr-95 2.8 E-10 Xe-135 1.2E-2 No-99 5.6E-S Xe-138 7.OE-4 Ru-103 2.8 E-10 Ru-106 1. 4 E-10 Total 4.9E-2 Te-129 1.2E-9 4

• Co-60 1.4E-10 f Noble cas Source Terat .

Fe-59 1.4E-10 Co-58 7.3E-10 j 4.94E-1 uC1/cc x 1.7E7 cc/See x 1.0 C1/1.0E6 uC1'= 8.4 C1/Sec Te-132 1.6E-8 Cs-134 3.8E-9

.) Iodine Source Term Cs-136 i 7.3E-10 3m

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Cs-137 1.6E-8 2.3E-3 uC1/cc x 1.7E7 cc/See x 1.0 C1/1.0E6 uCi = 4.0E-2 C1/See Ba-140 2.8E-10

) s 1.a-140 2.8 E-10

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Particulate Source Terms Pr-143 mN 2.8E-10 M$

Ce-144 2.8 E-10 Ea 1.0E-7 uC1/cc x 1.7EF cc/SEC x 1.0 C1/1.0E6uC1=1./E-6 fin-54 Cr-51 1.4E-10 $$

1. 4 E-10 k Total , 1.0E-7 p m

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^{ RADIATON MDNITORING SYSTDI DATA SitEET Time 01-108 CW-110 VS 217A(9) VS217s(9) VS-1028 VS-107A VS-1078 VS-112(LR) VS-112(HR) 0620 1.0E6 - 1.1E2 I 0715 7.OE4 1.8E4 6.4E3 - 1.6E3 - -

-f 1330 5.5E5 3.4E5 .1.2E5 5.0E2 9.9E4 1.3E1 -

1 I 4 1345 Of f Scale off Scale off Scalei 1.6E5 off Scale 4.3E5 1.2E2 1400 Off Scale off Scale off Scale' 2.6E5 off Scale 7.0E5 1.9E2 1415 Off Scale Off Scale Off Scale 2.6E5 Off Scale 7.0E5 1.9E2 l .

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, METEOROLOGICAL DATA SHEET s

Time Wind Speed Wind Directica Wind Direction T . T Stab 111ty Class Stability Class h w= 35' 35' 500' 150'-35' 500'-35' 150'-35' 500'-35' N

0530 3.6 15 280 -1.3 -3.5 ABC D -

E 0545 3.2 20 275 -1.3 -3.8 ABC D 0600 2.7 10 290 -1,2 -2.7 AAC D

. 0615 2.8 . 15 285 -1.1 -2.1

• ABC D 1 0630 3.8 25 275 -1.1 -2.4 ABC D t) 0645 2.5 10 290 -0.9 -1.7 D D i 1

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q. 0715 2.6 15 305 -0.8 -1.5 0 D j 0730 2.0 30 300 -0.7 -0.8 D ~E

j 0745 1.8 40 310 -.0. 5 -0.9 D E

$ 0800 2.0 45 305 -0.4 -1.0 D E 4

1300 3.6 105 0.8

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2.5 E E 1315 3.8 110 160 0.8 3.7 E E 1345 4.0 105 155 0.9 4.1 E r 1 1400 1415 4.6 4.2 120 125 150 1.1 4.6 FC F g 145 1.3 5.1 FC F

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! 105 160 1.4 5.6 FG F h N 1500 4.2 115 170 1.5 5.7 FC F to e/s 1515 4.4 105 175 1.5 5.2 FG F Ed re to j 1545 4.6 110 165' 1.6 6.2 n:

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FEBRUARY 1983 ANNUAL F.9ENCF.NCY PREPAREDNESS EXERCISE .

j ,8 POST RELEASE SAMPLE DATA SilEEf q , EFFLUENT ISOTOPIC ANALYSIS p- p T1HE 0715-0745 Noble Cases Activity (uC1/cc) todine Activity (uC1/cc) Pa rt icula te Activity (uC1/cc)

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Er-83m 2.2E-8 1-130 4.2E-10 Cr-51 5.3E-14 g

Kr-85m 1.2E-7 1-131 6.0r.-8 In-54 9.2E-14 2

Kr-85 2.5E-7 , 1-132 -

1.0E-8 Fe-55 4.7E-14

- Kr-87 6. 5 E-8 1-133 7.4E-8 Fe-59 2.8E-14 Kr-88 2.2E-8 1-134 6.9E-9 Co-58 4.6 E-13 Kr-89 5.1E-9 1-135 2.8E-8 Co-60 5.9E-13 j Total 1.7E-7  ; 8r-83 9.9E-14 j Xe-131m 1.3E-7 +

Sr-89 1.0E-14 1 Xe-133m 2.4E-7 T-91 5.9E-14 x

Xe-133 2.0E-3 Mo-99 1.2E-11 .

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Xe-135m 1.3E-8 Tc-99m 8.1E-12 j Xe-135 3.8E-7 '

Te-127m 8.1E-15 3 Xe-137 1.0E-9 y Te-127 1.9E-14

s Xe-138 3.5E-9 q Te-129s 4.2E-14 g Total 2. 2 E-5 Te-129 3.3E-14 Te-131m 6.4 -14 @$ '

i Te-132 7.0E-13 1 Noble cas Source Terms 6.7E-14 M 134 gW j 2.2E-5 uct/cc x 1.7EF cc/Sec x 1.0C1 / 1E6 uC1 = 3.8E-4 C1/Sec Total 2.4E-11 ,

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Monitoring Time Noble Cas lodine Particulate X/ Whole Body lodine Conc. Particulate Conc. Charcoal Ag Zeolite Particulate t Location Q(C1/sec) Q(C1/sec) Q (C1/sec) Q (mR/Hr) (uC1/cc) (uC1/cc) Net (CPN) Net (CPH) Net (CPN)

A1.1 1400 8.4 4.0 E-2 1.7 E-6 3.7 E-4 28936 1.5 E-5 6.3 E-10 11111 23006 Q2.1 1400 5.2 2.7 E-2 1.0 E-6 1.0 E-4 5054 2.8 E-6 1.0 E-10 2074 42944

) Q2.1 1430 8.4 4.0 E-2 1.7 E-6 1.0 E-4 7718 4.0 E-6 1.7 E-10 5185 t

61349 Q3.1 1430 8.4 4.0 E-2 1.7 E-6 5.0 E-4 3858 2.0 E-6 8.5 E-10 1481 30674 Q4.1 1430 5.2 2.7 E-2 1.0 E-6 2.8 E-5 1372 7.8 E-7 2.8 E-11 577 11963 g P4.1 1430 5.2 2.7 E-2 1.0 E-6 2.4 E-5 1144 6.6 E-7 2.4 E-!! 488 10122 .

P5.1 1430 1.6 E-2 8.8 E-5 3.3 E-9 1.9 E-5 3, 6.9 E-9 105 Q4.1 1500 8.4 4.0 E-2 1.7 E-6 2.0 E-5 1582 8.2 E-7 3.4 E-11 607 12576 P4.1 1500 8.4 4.0 E-2 1.7 E-6 1.7 E-5 1312 6.8 E-7 2.9 E-11 503 10429 p5.1 1500 8.4 4.0 E-2 1.7 E-6 1.3 E-5 1042 5.2 E-7 2.2 E-11 385 7975 -

N6.1 1500 5.2 2.7 E-2 1.0 E-6 9.0 E-6 432 3 9.0 E-12 177 3680 P6.1 1500 5.2 2.7 E-2 1.0 E-6 9.0 E-6 432 I 244E-7 4 E-7 9.0 E-12 177 3680

) F7.1 1500 1.6 E-2 8.8 E-5 3.3 E-9 8.0 E-6 1 / 7.0 E-10

/4 N7.1 1500 1.6 E-2 8.8 E-5 3.3 E-9 7.5 E-6 1 6.6 E-10 y N7.2 1500 1.6 E-2 8.8 E-5 3.3 E-9 7.0 E-6 1 6.2 E-10 j F5.1 1530 8.4 4.0 E-2 1.7E-6 1.4 E-5 1080 9.6 E-7 2.4 E-11 711 14723 Q5.1 1530 8.4 4.0 E-2 1.7 E-6 1.2 E-5 926 8.8 E-7 2.0 E-11 651 13496

] R5.2 1530 8.4 4.0 E-2 1.7 E-6 1.2 E-5 968 / 5.0 E-7 2.1 E-11 370 7668 y fj N6.1 1530 8.4 1.7 E-6 9.5 E-6 '733 3.8 E-7 4.0 E-2 281' 5828 5 f P6.1 1530 8.4 4.0 E-2 1.7 E-6 9.5 P-6 733 3.8 E-7 281 5828 cp P7.1 1530 5.2 2.7 E-2 1.0 E-6 8.0 E-6 385 2.2 E-7

• 162 3374 M7.1 1530 5.2 2.7 E-2 1.0 E-6 8.0 E-6 385 2.2 E-7 162 3374

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S:cticn VIII BVPS'1983 Annual Emergency Exerc,ise EXERCISE CONTROLLER /0BSERVER CONDUCT A. Each controller / observer should be familiar with the following:

1. The basic objectives of the exercise.

2. The assumptions and precautions being taken.

~

3. The exercise scenario, including the initiating events and the expected course of action to be taken. *

4. The various locations that wili be involved and the specific items to be observed when at those locations.

5. The purpose and importance of the evaluation checklists and chronological record sheets.

8. A summary and description of the controller's/ observers's assigned location, including an onsite exercise organization chart, exercise evaluation checklist, and chronological recor,d, sheet is provided.

within this packet.

C. Controllers / observers are assigned to various lo' cations and are to '

be at their initial locations as' indicated in Section I "Overall Schedule of Events." -

D. If controllers are to provide information via " cue cards," (e.g.,

initiating events, instrument readings, monitoririg results, etc'.).to ,

the exerci.se participants, the information must be provided exactly as and when prescribed. Failure to provide information appro-priately,may invalidate the results of the exercise. -

E. Controllers / observers shall maintain an accur' ate chronological record of activities for the locations observed. . The record should show the actual start and stop time, brief description of the event or occurrence with the result or action. taken..and pertinent comments or suggestions.

F. Controllers / observers should offer no.information, advice or assistance to the exercise participants. Any-such requests should

'be respectfully declined. Controllers shall only interpose them-selves if the participants are taking an action that will cause the exercise to go far afield of the anticipated time schedule and/or outcome.

Examples or problems requiring such interpositions may include: an engineering. calculation / projection that is so grossly inaccurate that an action level other than the one postulated for the scenario would be~ instituted, or an activity is taking so much longer than predicted that:the exercise scenario is in danger of not progressing as postulated, etc.

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Section VIII.

BVPS 1983 Annual Emergency Exerc,ise EXERCISE CONTROLLER /0BSERVER CONDUCT (CONT'D.)

Notes have been placed in the body of the scenario that direct the  ;

controller to be aware of these types of situations.

A lead exercise controller has been d'esignated for the On-site Exercise Organization. Those controllers _ responsible for " Cue Cards" or " Cue Signs" should coordinate their action times closely with the Lead Controller. Provisions will be available for necessary communications with this designated individual should scenario variations warrant. - '

1 G. The controller / observer must remain congizant of all the events and circumstances at their assigned locations. These should include but not be limited to: Participants' actions and reactions, communi-cations methods and record keeping, chain of command, equipment performance and the overall ability to interface with other emergency facilities.

H. Controllers / observers should record all times (both start and finish), actions and comments or. suggestions, as complete and precise as possible, in a chronological order ~on the Chronological ,

Record Sheet.

I. Significant items 'both major deficiencies and strong performan'ce points, should be highlighted upon occu'rence and condensed for presentation in the subsequent critique. -

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Scction MII BVPS 1983 Annual Em:rgency Exercise

, EXERCISE EVALUATION CRITERIA To ensure validity of the evaluation, alk exercise controllers / observers must utilize the same grading criteria. The followin,g grading standards should be utilized:

A. Recording Times of Actions

1. For calculating elapsed times, evaluators will be given the actual time the exercise is initiated. This will be T = 0 on

~

all reports. All ela'psed time calculations will be ' based on this time regardless of den the' separate evaluated activities '

are initiated.

2. An emergency center will be deemed to be in service when-its personnel accountability check is completed and reported or when the center has sufficient. manpowr present to carry out its

, mission. (NOTE: A fomal announcement should be made.)

3. Controllers / observers shall use the Chronological Events Summary during the course of the exercise to take notes on the time and events and shal'1 be the primary evaluatiori record. It is .

intended to be used to compliment the evaluation forms upon completion of.the exercise. ~The form calls for the actual and elapsed times, the initial discoveries,-the resultant acti'v ity, and evaluator comments.

B. Evaluation Standards .

The sequence and numbering below should be used by the con; roller /

observer to evaluate assigned areas pertaining to the eme gency response. A dual purpose will be served by this rating ntem.

First, the capability of each facility or response area will be evaluated and second, the system will provide a vehicle for guiding and directing improvement. The rating scale is as follows:

1. "5" = Excelle'nt - Personnel and equipment almys functioned without error the first time, every t.ime. Th're wre no pro-blems encountered and all personnel and equipment functioned at a level much greater than could reasonably by anticipated.

l

2. "4" = Good - Personnel an'd equipment generally performed better than expected. Any errors or problems were minor and easily l correctable.

3. "3" = Satisfactory - Personnel and equipment performed according to expectations, with 'few minor exceptions. Any errors noted were not severe and could be corrected without undue labor or

. expense. .

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Section VIII BVPS 1983 Annual Emergency Exerc,ise EXERCISE EVALUATION CRITERIA (CONT'D.)

4. "2" = Poor - Personnel and equipment generally performed below expectations and there were several significant deficiencies noted. The area's ability to carry out it's functions was

~

diminished.

5. "1" = Failure - Personnel and equipment consistently failed to perform as required and there were serious deficiencies noted which severely impaired the ability of the area to carry out its functions.

6. "N" = Not Observed - Through no fault of the exercise.

Categories for Evaluation These A number of areas have been designated for monitor evaluation. Each areas will be further definded in the various location packets.

controller /otserver will be , required to rate pertinent actions in the following areas:

A. Activation and Response B. Communications / Dis, semination-of Infonnation C. Procedures .

D. Direction and Control E. Material and Equipment F. Protective Measures G. Access Control H. Summary

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Section VIII i BVPS 1983 Annual Emergency Exercise 1

EXERCISE EVALUATION CRITERIA FOR PLANT C6ATROL ROOM Location:

Beaver Valley Power Station -

Reactor Auxiliary Building Functions: .

1. Perform immediate actions for the safe and proper operation of the plant.

2. Assess information available from valid indications and initially classify the situation.

3. Provide initial notifications and maintain information flow to ,

emergency support centers, when they are established.

4 Perform offsite dose projection and provide directions for offsite monitoring until the TSC/ EOF is activated. ,

S. Make recommendations to offsRe agencies regarding protective and other actions. s

6. Perform supplenientary actions to regain control of the plant.

Personnel and Duties: -

1. Nuclear Shift Supervisor - NSS 'As senior licensed operator on shift, performs all functions in accordance with approved admini-strative proceddres. During an emergency, the NSS assumes the role of the Emergency Director until properly relieved by the designated

~

Emergency Director.

2. Nuclear Shift Operating Foreman - NSOF - Performs the duties of the Operations Coordinator during the initial. stages of an emergency.

3. Nuclear Shift Supervisor Administrative Assistant _- During the initial stages of an emergency serves as the Communications and Records Coordinator.

4. Radcon Technician - Initial dose projections will be calculated

. during the early stages of an accident.

5. Other Personnel l

a. Nuclear Control Operators (2) l Ductuesne @hpaq

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-Section VIII BVPS 1983 Annual Emergency Exerc,ise EXERCISE EVAltlATION CRITERIA FOR PLANT CONTROL 1 0M (CONT'D.) -

b. Nuclear Operators (2) ,

c. Shift Technical Advisor

d. _ Chemistry Technician O

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.Section VIII BVPS 1933 Annual Emergency Exercise CONTROL ROOM EVALUATION Area Evaluated Monitors Rating A. Activation and Response

1. Was activation / initiation efficient an'd 5 4 3 2 1 N organi zed?

l 2. Were personnel familiar with their respon- 5 4 3 2 1 N  !

sibilities and did they respond in a timely manner?

3. Was the person in charge clearly identifiable? 5 4 3 2 _1 N

4. Was the transfer of responsibilities accom- 5 4 3 2 1 N plished efficiently and effectively?

5. Were all persons made aware Wien transfers 5 4 3' 2 1 N were completed?

8. Communications / Dissemination of Information -

1. Were all required and specified coidunication 5 4 3 2 1 N circuits operable?

2. Were personnel familiar with communications 5 4 3 2 1 N' available and the intended use of each? -

3. Were communications adequate? 5 4 3 2 1 N Were there sufficient personnel to conduct

4. 5 4 3 2 1 N communications tasks?

5. Was incoming infc nation effectively and 5 4 3 2 1 N efficiently distributed, to appropriate personnel? -

( 6. Were periodic update announcements made via 5 4 3 2 1 N j Page Party or face-to-face?

l .

7. Did communicators keep accurate log,s? 5 4 3 2 1 N l 8. Were the status boards kept updated? 5 4 3 2 1 N

9. Did persons in charge spend an inordinate 5 4 3 2 1 N amount of time on communigations, such that '

their attention was diverted from the incident?

! 10. Were offsite personne.1 kept infonned of 5 4 3 2 1 N

activities / plant status?

'At5

Siction VIII BVPS 1983 Annual Emergency Exercise Area Evaluated Mor.itors Rating

11. Were logs used effectively by personnel to 5 4 3 2 1 N

. review past events to trend data?

l

12. Were appropriate communications techniques - 5 4 3 2 1 N i (no abbreviations, phonetic alphabet, sign-  !

on, sign-off, etc.) followed? l

13. Was there a two-my exchange of information 5 4- 3 2 1 N such that the personnel observed understood -

the changing situation,and were able to per- l form their tasks in the context of the changing l situation and to effectively contribute to overall l assessment and mitigation?

C. Procedures

1. Were personnel generally familiar with the 5 4 3 2 1 N relevent procedures?

2. Were procedures followd? 5 4 3 2 1 N

3. Were personnel so overselmed with_. procedural 5 4 3 2 1 N requirements that they iere distracted from the appropriate response? (No=5 Yes=1)

4. Were the procedures appropriate? 5 4 3 2 1,N

5. What was your overall assessment of the level 5 4 3 2 -1'N of competency and state of training of the

_. personnb1 observed? (NOTE: If a shortcoming or exceptional performance as observed, pro-vide specific details in the Chronological Event

- Summary Sheet.)

D. Direction and Control -

1. Was the information flow from the plant to 5 4 3 2 1 N senior management, timely, complete and accurate?

2. Did the Emergency Director become too deeply 5 4 3 2 1 N involved in a specific activity to the exclusion of other activities?

3. Could the ' response be categorized as a team 5 4 3 2 1 N effort or a group of individual efforts?

(Team = 5 Individual = 1)

4. Was there an effective mechanism for resolving 5 4 3 2 1 N differences of opinions regarding technical issues or actions to be taken?

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Section V-III ,

BVPS 1983~

Annual Emargency Exerc,ise

~

Area Evaluated Moni+ ors Rating

5. Was there excessive noise and loitering 5. 4 3 2. 1 N in response facilities? (No=5 Yes=1)

Material and Equipment E.

1. Was all of the required materials and equip- 5 4 3 2 1 N ment available?

Was the equipment functional?

2. 5 4 3 2 1 N i

3. Did personnel check to ensure that all 5 4 3'2 1 N equipment as available and functional early in the activation process?

4. If equipment was inoperative or failed in 5 4 3 2 1 N use, were appropriate actions taken to resolve

. deficiency (e.g., spares or backups, etc.)?

5. Were there any situations where the lack of 5 4 3 2 1 N equipment of materials, or inoperative.

equipment, or a lack of ability to operate ,

the equipment, prevent personnel from

performing assigned tasks? (If sorplease

~

detail) '

6. Were there any situations in dich additional 5 4 3 2 'l N equipment or materials, or different types of ,

. equipment could have made the activity more effective?

7. Could the area, support the personnel assigned 5 4' 3 2 1 N to it?

8. Were there resource materials readily availabls 5 4 3 2 1 N to as:sess the emergency situation and to plan l corrective actions (maps, refcrence books, copies of emergency plans and procedures)?

F. Protective Measures

1. Were appropriate protective measures implemented 5 4 3 2 1 N for plant personnel? .

l l 2. Were appropriate contamination controls 5 4 3 2 1 N

' . ,bserved?

3. Were all in-plant activities conducted with 5 4 3 2 1 N c regard to personnel safety, consistent with .

the need to complete.the activity?

Jt:L,l. l ull U111 BVPS 1983 Annual Emergency Exercise l Area Evaluated Monitors Rating I

4. Was the nonnal radiological controls program 5 4 3 2 1 N i appropriately modified to contend with the l

. emergency radiological conditions?  !

G. _

Access Control -

1. Was an~ appropriate security posture 5 4 3 2 1 N established against unauthorized personnel?

2. Were incoming support personnel (fire-fighers, 5 4 3 2 1 N ambuiances, others) provided appropriate access

. in a timely manner?

3. Was there an identification system developed 5,4 3 2 _1 N and used that effectively identified authorized personnel and their. duties?

H. Summary

1. Describe any problems noted by the area being evaluated, a brief description of the problem, its outcome or effect, and any recommended ,

corrective courses of action to mitigate or correct the ' problem;- -

s

2. Completely fill out the evaluation . form, sign it, and promptly return it as directed. ,

3. Critiques of the exercise will be held for all participants, monitors, and NRC personnel (if applicable) that want to attend. Locations and times

.w ill be provided.

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_ BVPS 1983 Annual Emergency Exercise EXERCISE EVALUATION CRITERIA FOR INTERIM TECHNICAL SUPPORT CENTER (TSC)

Location:

Beaver Valley Power Station Basement of the Administration. Building Function: .

1. Provide plant m'a nagement and technical support to the plant operations personnel during emergency conditions.

2. Relieve the reactor operators of peripheral duties and comuni-cations not directly related to reactor system manipulations.

3. Prevent congestion in the control room.

4 Perfonn EOF functions for the Alert Emergency Class and for the Site Area and General Emergency Class' until the EOF is functional.

Personnel and Duties: _

1. Emergency Director - Responsible for the command and control of all accident mitigation actions on site.

2. Radiological Controls Coordinator - Responsible for onsite radiu-logical controls and personnel monitoring.

3. Environmental Assessment and Dose Projection Coordinator - Responsi-ble for' dose projections and offsite monitoring along with radio-logical assessment, sample coordination and the interface with DER /BRP.

4. Operations Coordinator - Acts as management representative in the Control Room. All directives pertaining to operation of the plant, from management will go to the NSS via the Operations Coordinator.

5. Communications and Records Coordinator - Coordinates all communi-cations and maintain records.-

6 Other personnel:

a. Chemistry Coordinator l

b. Security Coordinator i

c. Operations Support Center Coordinator

d. Technical Support Coordinator I

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e. Maintenance Coordinator

f. Assistant to Emergency Director e

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S:ction VIII BVPS 1983 Annual Emergency Exercise TECHNICAL SUPPORT CENTER EVALUATION Area Evaluated Monitors Rating A. Activation and Response

1. Was the activation / initiation efficient and 5 4 3 2 1 N organized?

2. Were personnel familiar with their responsi- 5 4 3 2 1 N bilities and respond in a timely ma,nner?

3. Was the person 1*n charge clearly identifiable? 5 4 3 2 1 N

4. Were the transfers of responsibilities accom- 5 4 3 2 -1 N plished efficiently and effectively?

. 5. Were all participants made awre the transfers 5 4 3 2 1 N had occurred? (NOTE: A formal announcement should be made.)

B. Communications / Dissemination of Information .

1. Were all required and specified connunications 5 4 3 2 1 N circuits operable? '

2. Were all personnel familiar with communications 5 4 3 2 1 N available and the intended use of each? .

3. Were communications adequate? 5 4 3 2 1 N 4 Were there sufficient personnel to conduct 5 4 3 2 1 N communications tasks?'

. 5. Was incominJ information effectively and 5 4 3 2 1 N

! efficiently distributed to appropriate personnel?

6. Were periodic update announcements made via 5 4 3 2 1 N r Page Party or face-to-face?

7. Did communicators keep accurate logs? 5 4 3 2 1 N

8. Were the status boards kept updated? 5 4 3 2 1 N l .

9. nid persons in charge spend an inordinate 5 4 3 2 1 N amount of time on communications, such that their attention as diverted from the incident?

10 Were there periodic reports from the various 5 4 3 2 1 N l

t response facilities to the TSC?

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Section VIII BVPS 1983 Annual Emergency Exercise Area Ev;1uated Monitors Rating

11. Here private and dedicated lines used as 5 4 3 2 1 N effectively as possible?

12. Were logs used effectively by personnel to . S' 4 3 2 1 'N review past events and to trend data?

13. Was information provided to the Emergency 5 4 3 2 1 N News Center in a timely manner?

, 14 Were appropriate communication techniques 5 4 3 2 1 N (no abbreviations, phonetic alphabet, sign-on sign-off, etc.) followd?

15. Was there a tw-way exchange of information 54 3 21 N such that the personnel observed understood the changing situation and were able to perform their tasks in the context of the changing situation and to effectively contribute to overall assessment and mitigation?

C. Procedures .

1. Were personnel generally familiar with the 5 4 3 2 1 N relevant procedures? ,

2. Were procedures followd? 5 4 3 2 1 N

3. Were procedures and' tech specs compatible? 5 4 3 2 1 N 4 Were personnel so overwhelmed with procedural 5 4 3 2 1 N requirements that they were distracted from the appropriate response? (No=5 Yes=1)

5. Were the procedures appropriate? 5 4 3 2 1 N 6 Was the overall level of competency and train- 5 4 3 2 1 N ing satisfactory? (NOTE: Shortcomings or exceptional performance should be detailed in i the Chronological Events Summary.)

D. Direction and Control

1. Was the information flow from the plant to 5 4 3 2 1 N senior management, timely, complete and adequate?

2. Did the individual emergency supervisors keep 5 4 3 2 1 N i the Emergency Director apprised of significant l events within their sphere of concern?

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dection V111 .

BVPS 1983 Annual Emergency Exerc,ise Area Evaluated Monitors Rating

3. Did the Emergeny Director effectively delegate 5 4 3 2 1 N responsibilities to the individual coordinators?

4 Did the Emergency Director become too deeply 5 4 3 2 1 N involved in a specific activity to the exclu-sion of other activities?

5. Could the response be categorized as a team 5 4 3 2 1 N effort or a group of individual efforts?

(Team = 5 Indi.viduals = 1) -

6. Were interfaces with outside technical groups 5 4 3 2 1 N effective?

7. Was there an effective mechanism for resolving 5 4 3 2 1 N differences of opinion regarding technical issues and actions to be taken?

8. Was there excessive noise and loitering in the 5 4 3 2 1 N response facility? (No=5 Yes=1)

Mater.ial and Equipment E.

1. Was all of the required material and equipment s 5 4 3 2 1- N available?

2. Was the equipment functional? 5 4 3 2 1, . N

3. Did the personnel check to ensure that all 5 4 3 2 1 N equipment us available and-functional early in the activation process?

4 If equipment us inoperative or failed in use, '5 4 3 2 1 N wre appropriate actions taken to resolve deficiency (spare and back-ups, etc.)

5., Were there any situations in which the lack of 5 4 3 2 1 N equipment and materials, or inoperative equip-ment, or a lack of ability to operate the equipment prevent personnel from performing assigned tasks? (if so, please detail)

(No=5 Yes = 1) .

6.. Were there are situations in sich additional 5 4 3 2 1 N l equipment or materials, or different types of equipment could have made the activity more effective? (No = 5 Yes = 1)

7. Could the area support the personnel assigned 5 4 3 2 1 N to it?

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Stction VIII -

BUS 1983 Annual Em;rgency Exercise l

Area Evaluated Monitors Rating

8. Were there resource materials readily available 5 4 3 2 1 N to assess the emergency situation and to plan corrective actions - maps, reference books, copies of emergency plans and procedures? .

F. Protective Measures ,

1. Were appropriate protective measures imple- 5 4 3 2 1 N mented for plant personnel? ,

2. Were appropriate contamination controls

• 5 4 3 2 1 N

_ observed?

3. Were TSC personnel kept apprised of in-plant 5 4 3 2 -1 N radiological conditions?

4 Were all in-plant activities conducted with 5 4 3 2 1 N regard to personnel safety, consistent with the need to complete the activity?

5. Was the normal radiological controls program 5 4 3 2 1 N appropriately modified to contend with the emergency radiological conditions? -

s G. Access Control .

1. Was an appropriate security posture established 5 4 3 2 1N against unauthorized personnel?

2. Was there an identification system developed 5 4 3 2 1 N and used that effectively identified author-ized personnel and their duties?

H. Summary

1. Describe any problems noted by area being evaluated, a description of the problem, its outcome or effect, and any recommended corrective courses of

'ction to mitigate or correct the deficiency.

l I

l 2. Completely fill out the evaluation form, sign it, and promptly return it l as directed.

l

3. Critiques of the exercise will be held for all participants, monitors, and NRC personnel (if applicable) that want to attend. Location and times will be provided.

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Section VIII BVPS 1983 -

Annual Emergtney Exerc,ise EXERCISE EVAltlATION CRITERIA

. FOR OPERATIONAL SUPPTWtT CENTER (OSC) location:

Beaver Valley Powr Station Process Instrument and Rod Position Instrument! Area below Control Room Function: .

1. Provide a location @ere plant logistic support can be coordinated during an emergency.

2. Restrict Control Room access to those support personnel spec 4fically requested by the Shift Supervisor.

Personnel and Duties:

1. Operational Support Center Supervisor - Responsible for the acti-vation and operation of the OSC..

l 2. Other personnel:

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a. Radcon Operations Center - if unstable conditions exist irt the service building.

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S2ction V.III BVPS 1983 Annual Emergerycy Exerc,ise ,

OPERATIONAL SUPPORT CENTER EVALUATION Area Evaluated Monitors Rating Activation and Response _

A. ,

1. Was the activation / initiation efficient and 5 4 3 2 1 N organi zed? .

2. Were personnel familiar with their responsi- 5 4 3 2 1 N bilities and respond in a timely manner? '

3. Was the person in charge clearly identifiable?

R. Communications / Dissemination of Information . -

1. Were all required and specified communications 5 4 3 2 1 N circuits operable?

2. Were personnel familiar with communications 5 4 3 2 1 N available and the intended use of each?

^

3. Were communications adequate? -

5 4 3 2 1 N 4 Were there sufficient pe'rsonnel to conduct '5 4 3 2 l' N communications tasks? -

5. Was incoming information effectively and 5 4 3 2 1.N efficiently distributed to appropriate -

personnel? "

6. Were periodic updates made by the Supervisor? 5 4 3 2 1 N

7. Were accurate logs kept? ,

5 4 3 2 1 N

8. Were the status boards kept updated? 5 4 3 2 1 N

9. Did persons in charge spend an inordinate 5 4 3 2 1 N amount of time on communications, such that their attention was diverted form the inci-dent? (No = 5 Yes = 1)

10. Was the correct private lines used and did 5 4 3 2 1 N non-emergency communications interfere with emergency transmissions? (No=5 Yes=1)

11. Were logs used effectively by personnel to 5 4 3 2 1 N review past events and to trend data?

12. Were. appropriate communications techniques 5 4 3 2 1 N (no abbreviations, phonetic alphabet, sign-on, sign-off, etc.) followed?

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dection vill BVPS 1983 Annual Emerg:ncy Exercise Area Evaluated Monitors Rating C. Procedures

, 1. Were personnel generally familiar with the 5 4 3 2 1 N relevant procedures? -

2. Were procedures followd: ,

5 4 3 2 1 N

3. Were personnel so overwhelmed with procedural 5 4 3 2 1 N requirements that they were distracted from the appropriate response? (No = 5 Yes=1) -

4. Were the procedures appropriate?

5 4 3 2 1 N

5. Was the overall level of competency and 5 4 3 21 N state of training adequate? (NOTE: Any shortcomings or exceptional performance observed should be detailed in the Event Summary Sheets.)

D. Direction and Control

1. Was the information flow from the plant to 5 4 3 2 1 N

- the facilities, timely, complete and accurate?

2. Could the response be categorized as a team . 5 4 3 2 1 N effort or a group of individual efforts?

(Team = 5 Individual = 1)

3. Was there an effective mechanism for re- 5 4 -3 2 1 N solving differences of opinion regarding technical issues and actions to be taken. .

4 Was there excessive noise and loitering in 'S 4 3 2 1 N the response facility? (No = 5 Yes = 1)

E. Material and Equipment

1. Was all of the required material and equip- 5 4 3 2 1 N ment available?

2. Was the equipment functional? 5 4 3 2 1 N

3. Did personnel check to ensure that all equip- 5 4 3 2 1 N ment as available and functional early in the activation process?

4. If equipment us inoperable or failed in use, 5 4 3 2 1 N were appropriate actions taken to resolve the deficiency (spares or back-up equipment)? ,

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S2ction VIII BVPS 1983 Annual Emergency Exere,ise Area Evaluated Monitors Rating

5. Were there any situations in which the lack of 5 4 3 2 1 N equipment and materials, or inoperative equipment, or a lack of ability to operate the equipment, prevent personnel from pre-assigned tasks. (No=5 Yes=1) If so,~

please detail.

6 Were there any. situations in Mich additional 5 4 3 2 1 N equipment or materials, or different types of equipment could have made the activity more -

effective? If so, please detail. (No = 5 Yes=1)

7. Could the area support the personnel assigned 5. 4 3 2-1 N to it?

8. Were there resource materials readily avail- 5 4 3 2 1 N able to access the emergency situation and to plan corrective actions - maps, reference books, copies of the emergency plans and procedures? ,

F. Protective Measures ,

s

1. Were appropriate protective measures imple -

5 4 3 2 1 N mented for plant personnel?

2. nid personnel properly wear protective 5 4 3 2 l' N clothing, dosimetry, respirators?

3. Were appropriate contaminations controls 5 4 3 2 1 N observed?

4'. Were OSC personnel kept apprised of in-plant 5 4 3 2 1 N radiological conditions?

5. Were all in-plant activities conducted with 5 4 3 2 1 N regard to personnel safety, consistent with the need to complete the activity?

6. Was t'he normal radiological controls program 5 4 3 2 1 N appropriately modified to contend with the emergency radiological conditions?

G. Access Control

1. Was an appropriate security posture estab- 5 4 3 2 1 N lished against unauthorized personnel?

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Secticn VIII BVPS 1983-Annual Emergency Exercise Area Evaluated Monitors Rating

2. Was there an identifiable system developed 5 4 3 2 1 N and used that effectively identified auth-orized personnel and their duties? , ,

H. Summary

1. Describe any problems noted by the area being' evaluated, a description of the problem, its outcome or effect, and any recommended corrective courses of action to mitigate or correct the deficiency. ,

2. Completely fill out the evaluation form, sign it, and promptly return it as directed.

3. Critiques of the exercise will be held for all participants, monitors, and NRC personnel (if applicable) that want to attend. Locations and times will be provided. -

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S::ction VIII BVPS 1983 Annual Emergency Exercise EXERCISE EVALUATION CRITERIA

- FOR INTERIM EMERGENCY OPTRXTIONS FACILITY (EOF) location: ,

Beaver Valley Powr Station Basement of the Administration Building Functions: ,

1. Management of overall licensee emergency response.

~

2. Coordination of radiological and environmental assessment.

3, netennination of recommended public protective actions.

4 Coordination of emergency response activities with Federal, State, and local agencies.

Personnel and Duties:

1. Emergency / Recovery Manager - Responsible for the overall activation and operation of t.he EOF and for recommending offsite protective actions. ,

2. Offsite Agency Liaison - Responsible for acting as a liaison with the Nuclear Regulatory Commission concerning Operating License .

commitments and serving as a liaison between the utility and the representatives of the state and local governments in the EOF.

3. Engineer.ing itana.ger - Responsible for directing the engineering efforts related to the emergency response and for short-term l modifications to plant systems to mitigate the accident.

! 4 Support Services Manager - Acts as a liaison with outside groups in l providing transportation, food, manpowr, equipment, supplies and j other logistical support for emergency personnel.

5. Other personnel:

a. Assistant to Emergenc~/y Recovery Manager

b. Environmental Assessment and Dose Projection Coordinator

c. Technical Spokesperson

d. Public Information Manager l

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MCtion V.111 BVPS 1983 Annual Emergency Exercise EMERGENCY OPERATIONS FACILITY EVAltlATION Area Evaluated Monitors Rating A. Activation and Response -

1. Was the activation efficient and organized? 5 4 3 2 1 N

2. Were personnel familiar with their responsi- 5 4 3 2 1 N bilities and respond in a timely manner?

l 3. Was person in charge clearly identifiable? 5 4 3 2 1 N l 4. Were the transfers of responsibilities from the S 4 3 2 1 N TSC accomplished efficiently and effectively? ,

5. Were all personnel made awre transfers had 5 4 3 2 1 N occurred?

B. Communications /nissemination of Information

1. Were all required and specified communication 5 4 3 2 1 N circuits operable? *

2. Were personnel familiar 'with communications ~5 4 3 2 1 N available and the intended use of each? .

3. Were communications adequate? 5 4 3 2 1,N

4. Were the sufficient personnel to conduct 5 4 3 2 1 N communications tasks?

5. Was incoming information effectively and 5 4 3 2 1 N efficiently distributed to appropriate personnel?

6. Were periodic updates provided by the facility 5 4 3 2 1 N director?

7. Did personnel keep accurate logs? 5 4 3 2 1 N

8. Were the status boards kept updated? 5 4 3 2- 1 N

9. Did persons in charge spend an inordinate 5 4 3 2 1 N amount of time on communications, such that

. their attention as diverted from the incidenc? (No = 5 Yes = 1)

10. Were there periodic reports from the various 5 4 3 2 1 N response facilities to the EOF?

T# . _ _ _ _ _ . _ _ _ __ _ _ _ _ . . _ . . _ ,

S;ctico VIII BVPS 1983 Annual Emergency Exercise Area Evaluated Monitors Rating

11. Were offsite personnel kept informed of 5 4 3 2 1 N activities / plant status?

12. Were the private lines used as intended and 5 4 3 2 1 'N did non-emergency communications interfere with emergency transmissions?

13. Were logs and status boards used effectively 5 4 3 2 1 N by personnel to review past events and to -

trend data?

14. Was information provided to the Emergency News 5 4 3 2 1 N Center in a timely manner?

15. Were appropriate communications techniques 5 4 3 2 1 N (no abbreviations, phonetic alphabet, sign-on sign-off, etc.) followd? .

C. Procedures

1. Were personnel generally familiar with the 5 4 3 2 1 N relevant procedures? ,

'. 2. Were procedures follo wd? '5 4 3 2 1 N

3. Were personnel so overNlmed with procedural- 5 4 3 2 1 N requirements that they wre distracted from *

' the appropriate response? (No = 5 Yes = 1)

4. Were the procedures appropriate? 5 4 3 2 1 N

5. Was the overall level of competency and state ~5 4 3 2 1 N of training adequate? (NOTE: Shortcommings and exceptional perfomance observed should be noted in detail in the Event Summary Sheet.) j O. Direction and Control -

1. Was the information flow from the plant to 5 4 3 2 1 N l senior management, timely, compiete and I accurate? .

2. Was adequate and timely guidance provided by 5 4 3 2 1 N the senior management?

3. Did the emergency supervisors keep the Emer- 5 4 3 .2 1 N gency/ Recovery Manager apprised of significant events within their sphere of concern?

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SGetion VIII-BVPS 1983 Annual Emergency Exercise Area Evaluated Monitors Rating

4. Did the Emergenc,y/ Recovery Manager effectively 5 4 3 2 1 N delegate responsibilities to the individual coordinators?

5. Did the Emergency / Recovery Manager become too 5 4 3 2 1 N deeply involved in a specific activity to the.

exclusion of other activities? (No = 5 Yes = 1)

6. Could the response be categorized as a team 5 4 3 ,2 1 N effort or a' group of individual efforts?

(Team = 5 . Individual = 1) ,

7. Were interfaces with outside technical groups 5 4 3 2 1 N effective? -

8. Was there an effective mechanism for resolving 5 4 3 2 1 N

. differences of opinion regarding technical issues and actions to be taken?'

9. Was there excessive noise and loitering in the 5 4 3 2 1 N EOF? .

E. Material and Equipment .

-~ - '

Was all the required material and equipment

1. 5 4 3 2 1 N available? If not, please detail.

2. Was the equipment fdnctional? 5 4 3 2 1 N

3. Did personnel check to ensure that all equipment 5 4 3 2 1 N ms available and functional early in the activation process?

4 If the equipment ws inoperative or failed in 5 4 3 2 1 .N use, wre appropriate actions taken to resolve the deficiency (e.g., spare and back-up equip-ment)?

5. Were there any situations in sich additional 5 4 3 2 1 N equipment or materials, or different types of ,

equipment could have made the activity more effective? If so, please detail. (No = 5 Yes = 1)

6. Were there any situations in Mich the lack of 5 4 3 2 1 N equipment or materials, or inoperative equip-ment, or a lack of ability to operate the equip-ment, prevented personnel from performing assigned tasks? .

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S:cticn VIII BVPS 1983 Annual Emergrncy Exercise Area' Evaluated' Monitors Rating .

7. Could the area support the personnel assigned 5 4 3 2 1 N to it?

8. Were there resource materials readily available 5' '4 3 2 1 'N to assess the energency situation and to plan corrective actions - maps, reference books, copies of emergency plans and procedures?

F, Access Control ,

1. Was an appropriate security posture established 5 4 3 2 1 N against unauthorized personnel?

2. Was there an identification system developed and 5- 4 3 21 N

.used that effectively identified authorized per-sonnel and their duties?

G. Summary

1. Describe any problems noted by the area being evaluated, a description of the problem, its outcome or effect, and any recommended corrective courses .

of action to mitigate or correct the deficiency?

s

2. Completely fill out'the evaluation form, sign it, and promptly return it as directed.

3. Critiques of the exercise will be held for all participants, monitors, and NRC personnel (if applicable) that went to attend. Locations and times will be provided.

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S;ction Vill DVPS 1983 Annual Emergency Exerc,isa EXERCISE EVALUATION CRITERIA FOR ENVIRONMENTAL ' ASSESSMENT ~KRD DOSE PROJECTIONS ROOM Location: l Beaver Valley Power Station -

Basement of the Administration Building Functions: .

1. Assess environmental conditions.

2. Coordinate radiological monitoring activities.

3. Recommend implementation of offsite emergency actions.

Personnel and Duties: ,

1. Environmental Assessment and Dose Projections Coordinator -

Responsible for performing offsite dose calculations and providing the Emergency Director with technical advice concerning radiological assessment and recommendations for offsite protective actions.

2. Othe personnel: ' '

~

. a. Field team ccmmunicator ,

b. Assistant EA and DP Coordinator

c. Status board keepers and communicators G

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S:ction VIII BVPS 1983 Annual Emergency Exercise 4 l

EOF 00SE ASSESSMENT ROOM EVAUJATION Area Evaluated Monitors Rating A. Activations and Response ,

1. Was activation efficient and organized? 5 4 3 2 1 N

2. Were personnel familiar with their responsi- 5 4 3 2 1 N bilities and respond in a timely manner? ,

3. Was person in charge clearly identifiable? 5 4 3 2 1 N 4.' Was the transfer of responsibilities from the 5 4 3 2 1 N CR accomplished efficiently and effectively? -

B. Communications / Dissemination of Information

1. Were all required and specified communication 5 4 3 2 1 N circuits operable? .

2. Were communications adequate? 5 4 3 2 1 N .

3. Was incoming information, effectiveTy and 5 4 3 2 1 N efficiently distributed to appropriate personnel?'

• 4 Were accurat.e logs -kept, and were the status 5 4 3 2 1 N boards kept updated? .

5. Were offsite personnel kept informed of 5 4 3 ~2 1 N activities / plant status?

6. Were appropriate commu'nication techniques 5 4 3 2 1 N (no abbreviations, phonetic alphabet, etc.)

I followed?

7. Was there a tm-way exchange of information 5. A 3 2 1 N such that the personnel observed understood the.

changing situation and wre able to perform

! their tasks in the context of the changing situation and to effectively contribute to overall assessment and mitigation.

C. Procedures

1. Were personnel generally familiar with the 5 4 3 2 1 N relevant procedures?

2. Were procedures followed? 5 4 3 2 1 N l

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Stcticn VIII -

BVPS 1983

Annual Emergency Exercise l Area Evaluated Monitors Rating

3. Were personnel so overdelmed with procedural 5 4 3 '2 1 N requirements that they were distracted from i the. appropriate response? (No = 5 Yes = 1) 4 Were the procedures appropriate? ,

5 4 32 1 N I

5. Was the overall level of competency and state ' S 4 3 2 1 N of training adequate. (NDTE: Any shortcomings of. exceptional performance should be detailed in

• the Event Summary Sheet.)  ;

D. Direction and Control *

1. Was adequate and timely guidance provided by 54 3 2 -1 N the senior management?

. 2. Could the response be categorized as a team 5 4 3 2 1 N effort or a group of~ individual efforts?

(Team = 5 Individual = 1) .

3. 'Was there excessive noise and loitering in 5' 4 3 2 1 N ,

the response facility?

' ~

E. Material and Equipment '

1. Was a,11 the required material and equipment 5 4 3 2 1 N available? ,

2. Was the equipment functional? 5 A 3 2 1 N

.i l 3. Did personnel check to ensure that all equipment 5 4 3 2 1 N

! was available and func'tional early in the activation process? ,

4 If equipment as inoperable or failed in use, 5 4 3 2 1 N were appropriate actions taken to resolve the deficiency?

5. Were there any situations dere the lack of 5 4 3 2 1 N equipment and materials, or inoperable equipment, ,

or a lack of ability to operate the equipmen':,

prevented the personnel from performing assigned tasks? If so, please detail. (No = 5 Yes = 1)

6. Were there any situations in which additional 5 4 3 2 1 N equipment or materials, or different types cf equipment could have made the activity more effective? If so, please detail. (No = 5 i Yes = 1) ,

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Section VIII BVPS 1983 Annual Emergency Exercisa Area Evaluated Monitors Rating

7. Could the area support the personnel assigned 5 4 3 2 1 N to it?

8. Were there resource materials readily available 5 4 3 2 1 .N to assess the emergency situation and to pihn corrective actions - maps, reference books, copies of emergency plans and procedures?

.F. Protective Measures

1. Did personnel properly rar protective clothing, 5 4 3 2 . 1,. - N dosimetry, respirators?

2. Were field monitoring teams periodically reminded 5 4 3 2 -1 N to check their TLD's?

3. Were appropriate contamination controls observed? 5 4 3 2 1 N 4 Was t'he normal radiological controls program 5 4 3 2 1 N appropriately modified to contend with the emer-gency radiological conditions?

G. Access Control ,

1. Was an appropriate security posture established 5 4 3 2 1 N against unauthorized personnel?

2. Was there an identification system developed and 5 4 3 2 l' N used that effectively identified authorized per-sonnel and their duties?

~

H. Summary l'. Describe any problems noted by the area being ' evaluated, a description of the problem, its outcome or effect, and any recommended corre,ctive courses of action to mitig'a te or correct the deficiency.

2. Completely fill out the. evaluation form, sign it, and promptly return it l as directed. .

l l 3. Critiques of the exercise will be held for all participants, monitors, and NRC personnel (if applicable) that want to attend. Locations and times i will be provided.

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S;ction VIII BVPS 1983 Annual Emergency Exercise EXERCISE EVALUATION CRITERIA FOR EMERGENC N S CENTER Location:

Duquesne Light Company - PID Headquarters -

Pittsburgh, PA Willows Motel .

Industry, PA Functions:

1. Serves as focal point for all public information activities.-

2. ,All' media comdiunications by Duquesne Light Company personnel, including press conferences, will be coordinated through the .

Emergency News Center.

Personnel and Duties:

1. Public Information Staff - Ptgviding timely and accurate information to the public via the news media.

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S:ction VIII BVPS 1983 Annual Emerg:ncy Exercise Area Evaluated Monitors Rating

~

A. Activation and Response --

1. Was the activation efficient and organized? 5 4 3 2 1 N

~

2. Were personnel familiar with their responsi- 5 4 3 2 1 N bilities and respond in a timely manner?

3. Was the person in charge clearly identified? 5 4 3 2 1 N B. Communications / Disseminations of Information

1. Were all required and specified communications 5 4 3 2 1 N circuits operable?

2. Were personnel familiar with communications 5 4 3 2 1 N available and the intended use of each?

'3. Were communications adequate? E 4 3 2 1 N 4 Was information provided to the News Center in 5 4 3 2 1 N a timely manner?

5. Were appropriate communi, cation techniques 5 4 3 2 1 N followd? (Noabbreviations, phonetic '

alphabet,etc.) -

C. Direction and Control *

1. Could the response be categorized as a team 5 4 3 2 1 N effort or a group of individual efforts?

2. Was there excessive noise and loitering in the .5 4 3 2 1 N News Center?

3. Were the press briefings conducted in an 5 4 3 2 1 N organized and professional manner?

D. Summary l 1. Describe any problems noted by the area being evaluated, a description of

( the problem, its outcome or effect, and any recommended corrective courses I

of acti.on to mitigate or correct the deficiency.

l

2. Completely fill out the evaluation form, sign it, and promptly return it j as directed.

l 3. Critiqu'es of the exercise will be held for all participants, monitors and l

NRC personnel (if applicable) that want to attend. Locations and times will be provided.

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secuan v.iii BVPS 1983 Annual Emergency Exercise EXERCISE EVALUATION CRITERIA .

FOR REAVET'TOUNTY EMERGENCY OPERATIONS CENTER Location:

East End Avenue Beaver, PA Function: ,

1. direction and control of the emergency response for Reaver County.

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S:ction VIII .

BVPS 1983 Annual Emergqcy Exercise EXERCISE EVAltlATION CRITERIA FOR HANC0 E 0VNTY EMERGENCY OPERATIONS CENTER Location:

Hancock County Courthouse New Cumberland, WV Function:

1. Direction and control of the emergency response for Hancock County. .

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S;cticn VIII BVPS 1983

. Annual Emergency Exercise EXERCISE EVAltlATION CRITERIA FOR COLUMBITRE COUNTY -

EMERGENCY OPERATIONS CENTER Location:

CCDSA Building Richardson Avenue Negley, OH Function: .

Direction ~ and control of the emergency response for Columbiana County.

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section v-111 BVPS 1983 Annual Emergency Exercisa Area Evaluated Monitors Rating A. Activation and Response

1. Was activation efficient and organized? 5 4 3 2 1 N

2. Were personnel familiar with their responsi- 5 4 3 2 1 N bilities and respond in a timely manner?

3. Was person in charge clearly identifiable? 5 4 3 2 1 N

4. Was initial aad subsequent notifications 5 4 3 2 1 N completed in a timely and professional manner?

B. Communications / Dissemination of Information f

1. Were all required and specified communication 5 4 3 2 l N circuits operab7e? .

2. Were personnel familiar with communications 5 4 3 2 1 N available and the latended use of each?

3. Were communications adequate? 5 4 3 2 1 N .

4. Was incoming information, effectivel-y and 5 4 3 2 1 N efficiently distributed to appropriate personnel?

5. Were accurate logs kept, and status boards kept 5 4 3 2 1,N updated? -

l

6. Were the offsite personnel kept informed of 5 4 3 2 1 N activities / plant status?

7. Were appropriate communication techniques '5 4 3 2 1 N followed? (No abbreviations, phonetic alphabet, etc.)

1

8. Were state and federal communication lines 5 4 3 2 1 N available? Did infonnation flow readily?

C. Procedures l 1. Were personnel generally familiar with the 5 4 3 2 1 N l relevant procedures?

i

2. Were procedures followd? 5 4 3 2 1 N

3. Were personnel so overwhelmed with procedural 5 4 3 2 1 N

! requirements that they wre distracted from l the appropriate response?

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BVPS 1983 Annual Emergency Exercise Area Evaluated Monitors Rating

4. Were the procedures appropriate? 5 4 3 2 1 N

' 5. Was the overall level of competency and state 5 4 3 2 1 N of training adequate? (NOTE: Any shortcomings or exceptional performance should be detailed ini the Event Summary Sheet.)

• D. Direction and Control-

~

1. Was the infonnation from the pl' ant to the E0C's 5 4 3 2 1 N timely, complete, and accurate?

2. Could the response be categorized as a team 5 4 3 2 1 N effort or a group of individual efforts? -

3.. Was there an effective mech.anism for resolving 5 4 3 2 1 N

. differences of opinion regarding technical issues and actions to be taken?'

4 Was there excessive noise and loitering in the 5 4 3 2 1 'N EOC? .

E. Material and Equipment .

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1. Was all the required material and equipment 5, 4 3 2 1 N available? -

2. 'Was the equipment functional? 5 4 3 2 1 N

3. Did personnel check to ensure that al1 equipment 5 4 3 2 1 N was available and functional early in the acti-l vation process?

4 If equipment was inoperable or failed in use, ' 5 4 3 2 1 N were appropriate actions taken to resolve the deficiency? (e.g., back-ups, spare equipment)

5. Were there any situations in dich the lack of 5 4 3 2 1 N equipment and materials, or inoperative equipment, l or a lack of ability to operate the equipment, pre-vent personnel from performing assigned tasks?

6. Could the area support the personnel assigned to 5 4 3 2 1 N it?

7. Were resource materials readily available to aid 5 4 3 2 1 N in the response actions? (e.g., maps, reference books, copies of emergency plans and procedures, etc.)

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Secticn VIII BVPS 1983 Annual Emergency Exerc,ise Area Evaluated Monitors Rating l

F. Protective Measures

• 1. Was sheltering / evacuation implemented den 5 ,4 3 2 1 N  !

wrranted? ,

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2. Did dose assessment information coincide with 5 4 3 2 1 N ,

those from the site?

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3. Were the E0C's fully awre of dat areas wre 5 4 3 '

2 1 N

, affected bi the accident? .

G. Summary

1. Describe any problems noted in the EDC, a description of the probhm, its outcome or effect, and any recommended corrective courses of action to initigate or correct the deficiency.

2. Completely fill out the evaluation form, sign it, and promptly return it as directed. .

3. Critiques of the exercise will be held for all participants, monitors, and NRC personnel (if applicable) that want to attend. l.ocations and times will be pro,vided.

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52ction VIII BVPS 1983 Annual Emergency Exercise EXERCISE EVALUATION CRITERIA FOR FIELD MONfTORIhTTEAMS EVALUATION Area Evaluated Mo'nitors Rating A. Activation and Response *

1. Was activation efficient and organized? 5 4 3 2 1 N

2. Were perso,nnel familiar with their responsi- 5 4 3 '2 1 .N, lbilities and respond in a timely' manner?1

3. Did one team member assume the role as the 5 4 3 2 1 N team leader? -

B. Communications / Dissemination of Information

1. Were all communication circuits operable? 5 4 3 2 1 N

2. Were communications adequate? .

5 4 3 2 1 -N

~

3. Were accurate logs kept? _

5 4 3 2 1 N 4 Were teams kept informed of activities / plant 5 4 3 2 l' N status?

5. Were appropriate communications techniques 5 4 3 2 1.N

followd? (Noabbreviations,phoneticalphabet "This is a drill," etc.)

6. Was there a tw-my exchange of information such 5 4 3 2 1 N that the personnel obs'erved understood the chang-ing situation and were able to perform their tasks in the coatext of the changing situation?

C. Procedures

1. Were personnel generally familiar with the 5 4 3 2 1 N relevant procedures?

7. Were p' rocedures followed? 5 4 3 2 1 N

3. Were the procedures appropriate? 5 4 3 2 1 N

4. Was the overall level of competency and state 5 4 3 2 1 N of training adequate? (NOTE: Any shortcomings or exceptional performance should be detailed in the E' ~nts Sumary Sheet.)

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Secticn V-III BVPS 1983 Annual Emergency Exerc,isa

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Area Evaluated Monitors Rating D. Direction and Control'

1. Was adequate and timely guidance provided by 5 4 3 2 1 N senior management? ,

2. Were the teams reminded to periodically check 5 4 3 2 1 N their TLD's? -

.E. MateHal and Equipment -

a,1 e 11.g, Was 'all of-.the..r' equi red material'and. eqilipment-~

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.  : avai.lable? . -

, 2.. - Was the equipment functional? 5 4 3 2 -1 N

3. Did the personnel eneck to ensure t. hat all ~

5 4 3 2 1 N equipment was available and functional early in'the activation process? (NOTE: This includes establishing radio contact.)

4. If equipment was inoperable or failed in use, 5 4 3 2 1 N ~

were appropriate actions taken to resolve the deficiency? (e.g.,back,-upsorspares) -

~

Protective Measures F. -

1. Did personnel properly wear protective clothing, 5 4 3 2 1. N dosiriietry, respirators? .

2. Were appropriate contaminations controls 5 4 3 2 1 N observed? .

3. Was the normal radiological controls program ~5 4 3 2 1 N l appropriately modified to contend with the '

emergency radiological conditions?

G. Summary ,

1. Describe any problems noted with the field monitoring teams, a description of the problem, its . outcome or effect, and any recommended corrective cours'es of action to mitigate or correct the deficiency.

2. Completely fill out the evaluation form, sign it, and promptly return it as directed.

3. Critiques of the exercise will be held for all participants, monitors, and NRC personnel (if applicable) that want to attend. Locations and times will be provided.

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S:ction VIII BVPS 1983 Annual Emergency Exercise EXERCISE EVAltlATION CRITERIA FOR RADCON OPERATIONS CENTER Location: ,

Reaver Valley Power Station Radeon Foreman's Office - Turbine Building Functions: ,

1. Central location for coordinating the activities of Radcon technicians within the plant.

Personnel and Duties: -

1. Radcon Foreman - Receives ~ direction from the Radeon Coordinator located in the TSC. Is the liaison betwen the Rad Techs and the TSC.

2. Radcon Technicians - Activated as needed. Rad Techs provide support for input radiation monitoring as well as for emergency squad .

surveys and accompanying offsite support vehicles and personnel.

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S;ction VIII BVPS 1983 Annual Emergency Exerc,he RADCON OPERATORS CENTER ,

Area Evaluated Monitors Rating A. Activation and Response

1. Was activation / initiation efficient and 5 A 3 2 1 N organized? -

2. Were persannel familiar with their responsi- 5 4 3 ,2 1 N bilities and did they respond in.a timely, i manner? ,

3. Was person in charge clearly identifiable? 5 a 3 2 1 N B. Communications / Dissemination of Infonnation

. 1. Were all required and specified communication 5 4 3 2 1 N l

circuits operable?

2. Were personnel familiar with communications 5 4 3 2 1 N available and the intended use of each? .

3. Were communications adequate? - ' S 4 3 2 1 N 4.. Were there sufficient personnel to conduct '

5 4 3 2 1 N .

communication tasks?

^

l l 5. Were periodic updates made? 5 4 3 2 1 N

6. Were logs used effectively by personnel to 5 4 3 2 1 N review past events and to trend data?

7:. Were appropriate communications techniques 5 4 3 2 1 N follo wd? (i.e.,noabbreviations)

C. Procedures l 1. Were personnel generally familiar with the 5 4 3 2 1 N relevant procedures?

2. Were procedures followd? 5 4 3 2 1 N

3. Were the procedures and the tech specs in 5 4 3 2 1 N agreement?

4 Were the procedures appropriate? 5 4 3 2 1 N l

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Secti'on VIII BVPS 1983 Annual Emergency Exerc,ise Area Evaluated Monitors Rating

5. What ws your overall assessment of the level 5 4 3 2 1 N of competency and state of training of the personnel observed? (NOTE: If a shorf:oming .

or exceptional performance us. observed, prpvide specific details in the Chronological Event Summary Sheet)

D. Direction and Control

~

1. Was.information flow from the p'lant to senior 5 4 3 2 1 N management, timely,' complete, and accurate?

2. Could the response be categorized as a team 5 4 3 2 1 N effort as opposed to a group of individual -

efforts?

3. Was there excessive noise a'nd loitering in 5 4 3 2 1 N .

the facilities?

E. Material and Equipment

1. Was all of the required material and equipment 5 4 3 2 1 N available?

~~~

2. Was the equipment functional? 5 '4 3 2 1 N

3. Did personnel check to ensure that all equip- 5 4 3 2 1N ment was available a'nd functional early in' the activation process?

4. If equipment ws inoperable in use, were appro- 5 4 3 2 1 N priate actions taken to resolve the deficiency?

5. Could the area support the personnel assigned " 5 4 3 2 1 N to it?

6. Was there resources'readily available to assess. 5 4 3 2 1 N the emergency situation and to plan corrective actions? .

F. Protective Measures

1. Did personnel properly war protective clothing, 5 4 3 2 1 N dosimetry, respirators?

2. Were appropriate contamination controls observed? 5 4 3 2 1 N

3. Were areas properly surveyed before personnel S 4 3 2 1 N l entered?

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Secticnvi!I BVPS 1983 Annual Emergency Exercise Area Evaluated tionitors Rating Were all in-plant activities conducted with

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4. 5 4 3 2 1 N regard to personnel safety, consistent with the need to complete the activity? ,

5. Was the normal radiological controls program - 5 4 3 2 1 N appropriately modified to contend with the emergency radiological conditions?

G. Access Control

1. Were incoming support personnel (firefighters, 5 4 3 2 1 N ambulances, etc.) provided appropriate' escort.

H. Summary ,

1. nescribe any problems noted in the area heing evaluated, a brief

~

description of the problem, its outcome or effect, and any recommended corrective courses of action to mitigate or correct the problem.

Completely fill out the evaluation fonn, sign it, and promptly return it 2.

as directed. ,

3. Critiques of the exercise will be held for all participants, monitors, and NRC personnel that want to attend. l.ocations and times will be pr,ovided. '

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Soction VIII BVPS 1983

. Annual Emerger,1cy Exerc,ise EXERCISE EVALUATION CRITERIA FOR CHERITTRY location: ,

Reaver Valley Powr S'.;ation Control Room / ROC Function: , ,

~

1. Respons.ble for. conducting all .in ' plant sampling as. requested by the

_ Emergency' Di rector.

2. Also responsible for all chemical analysis done on and offstte,

including environmental samples.

Personnel and Duties:

1. Chemistry Coordinator

2. Chemistry Technicians ,

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Srcticn VIII BVPS 1983 .

Annual Emergency Exerc,ise CHEMISTRY

. Area Evaluated Monitors Rating A. Activation and Response

1. Was activation / initiation efficient and -

5 4 3 2 1- N organized?

2. Were personnel familiar with their respon- 5 4 3 2 1 N sibilities and did they respond in a t'imely manner?

3. Was the person in charge clearly identifible? 5 4 3 . 2 ,1 N B. Communications / Dissemination of Infonnation

1. Were all required and specified communication

. 5 4 3 2 1 N circuits operable?

2. Were personnel familiar with communica'tions 5 4 3 2 1 N available and the intended use of each? -

3. Were communications adeiuate? l s 5 4 3- 2 1 N

4. Were there sufficient personnel to conduct 5 4 3 2 1 N communications tasks? ,

~

5. ~ Was incoming information effectively and 5 4 3 2 1- N efficie,ntly distributed to appropriate personnel?

6. Did communicators keep accurate logs? 5 4 3 2 1 N

7. Were logs used effectively by personnel to 5 4 3 2 1 N review past events to trend data?

8. Were appropriate communications techniques 5 4 3 2 1 N (no abbreviations, phonetic alphabet, sign-on sign-off, etc.) followed?

C. Procedures -

1. Were personnel generally familiar Mth the 5 4 '3 2 1 N relevant procedures?

2. Were procedures followed? 5 4 3 2 1 N

3. Were the procedures appropriate? 5 4 3 2 1 ,N Duquesrae @hpaq

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i SIction VIII '

BVPS 1983 Annual Emergancy Exercisa l

Area Evaluated Monitors Rating

4. What was your overall assessment of the level 5 4 3 2 1 N of competency and state of training of the personnel observed? (NOTE: If shortcomings

)

or exceptional performance was observed, pr.o- l vide specific details in the Chronological Event Summary Sheet.)

D. Direction and Control

. l

1. Could the response he. categorized as a' team 5 4 3 2 1 N effort or a group of individual efforts?

(Team = 5 Individual = 1)

~

2. Was there an effective mechanism for resolving 5' 4- 3 2- 1 N differences of opinions regarding technical issues or actions to be taken?

3. Was there excessive noise and loitering in 5 4 3 2 1 N response facilities? (No = 5 Yes=1)

E. Material and Equipment ,

1. Was all of the required material and' equipment s 5 4 3 2 1- N available?

2. Was the equipment functional? 5 4 3 2 1 N

3. ' Did personnel check to ensure that all equipment 5 4 3 2 1. N was available and functional early in the activa-tion prbcess?

4 Were there any situations in sich additional '5 4 3 2 1 N equipment or materials, or different types of -

equipment could have made the activity more effective? (If so, please detail.)

5. Could the area support the personnel assigned 5 4 3 2 1 N to it?

F. Protective Measures -

1. Were appropriate protective measure's implemented 5 4 3 2 1 N for plant personnel?

2. Were apper;.ciate contamination controls observed? 5 4 3 2 1 N

3. Were all in-plant activities conducted with 5 4 3 2 1 N regard to personnel safety, consistent with the need to complete the. activity?

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Secticn .VIII BVPS 1983 Annual Emsrgency Exerciso Area Evaluated Monitors Rating 4 Was the nonnal radiological controls program 5 4 3 2 1 N appropriately modified to contend with the emergency radiological conditions? .

'G. Summary

1. Describe any problems noted by the area being evaluated, a brief description of the problem, i.ts outcome or effect, and any recommended corrective courses of action tot mitigate or correct the problems?

2. Completely fill out the evaluation form, sign it, and promptly return it as directed.

3. Critiques of the exercise will be held for all participants, monitors and NRC personnel (if applicable) that want to' attend. Locations and times will be provided.

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'S:ction V-III~

BVPS 1983 Annual Emergmcy Exerc,ise EXERCISE EVALUATION CRITERIA FOR SECURITY location: ,

Beaver Valley Powr Staton Guardhouse /Various Functions: -

5 . .

1. Mai.ntain an,appropr_iate pl' ant' security posture and institute.

appropriate contingency measures as necessary. ,

. 2. For unit and site evacuations; receive accountability reports from personnel assembly areas; determine the identity of unaccounted personnel . advise the Emergency Director of the status of personnel accountability, and niaintain accountability of personnel remaining behind during an emergency'.

3. Expeditiously provide for station access for emergency response personnel who do not have current security badging at the Beaver ,

Valley Power.

Personnel and Duties: '

1. Security Coordinator

~

2. Security Representative (TSC)

3. Guards .

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Section Vi!I.

BVPS 1983 Annual Emergtncy Exercise SECURITY 9

Area Evaluated Monitors Rating A. Activation and Response

1. Was activation / initiation efficient and organized? 5 4 3 2 1 N

2. Were personnel familiar with their responsibil- 5 4 3 2 1 N

.ities and did they-respond in a timely manner?

3. Was the person in charge ' clearly ~ identifible? .5 4 3 2 1 N

4. Was the transfer of responsibilities accom- 5 4 3 2 1 N

. plished efficiently ~ and e~ffectively? , -

5. Were all persons made aware den tr.ansfers 5 4 3 2 1 N were completed?

B. Communications / Dissemination of Information

1. Were all required and specified communication 5 4 3 2 1 N ,

circuits operable? -

2. Were personnel familiar'with commu cations 'S 4 3 2 l' N available and the intended use of each? -

3. Were communications adequate? 5 4 3 2 1. N

4. Were there sufficient personnel to conduct 5 4 3 2 1 N communications tasks?

5. Was incoming information effectively and .5 4 3 2 1 N efficiently distributed to appropriate personnel?

6. Were periodic update announcements made via 5 4 3 2 1 N face-to-face?

7. Did communicators keep accurate logs? 5 4 3 2 1 N

8. Were,the status boards kept updated? 5 4 3 2 1 N

9. Did persons in charge spend an inordinate amount 5 4 3 2 1 N of time on communications, such that their atten-

. tion was diverted from the incident?

10. Were logs used effectively by personnel to 5 4 3 2 1 N review past events to trend data? _ .

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11. Were appropriate communications techniques 5 4 3 2 1 N (no abbreviations, phonetic alphabet, sign-on sign-off, etc.) followed?

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BVPS 1983 Annual Emergency Exercise-Area Evaluated Monitors Ra' ting

~

12. Was there a two-my exchange of information 5 4 3 2 1 N such that 'the personnel observed understood the changing situation and wre able to per-form their tasks in the context of the changing situation and to effectively -

contribute to overall assessment and mitigation? -

C. Procedures

1. Were personnel generally familiar with 5 4 3 2 1 N the relevant procedur,es?. .

2. Were procedures followd? 5, 4 3 2_1 N

3. Were the procedures appropriate? 5 4 3 2 1 N

4. What as your overall assessment of the level 5 4 3 2 1 N of competency and state of training of the personnel observed? (NOTE: If a shortcoming or exceptional performance was observed, pro-vide specific details in the Chronological Event - Summary Sheet) . ___ .,

D. ' Direction and Control

1. Was the information flow from the' plant to 5 4 3 2 1 N senior management, timely, complete, and accurate?

2. Could the response be categorized as a . team 5 4 3 2 1 N effort or a group of individual efforts?

(Team = 5 Individual = 1)

3. Was there excessive noise and loitering in 5 4 3 2 1 N respnnse facilities? (No = 5 Yes = 1)

E. Material and Equipment

1. Was all of the required material and equipment 5 4 3 2 1 N available? -

2. Was the equipment functional? 5 4 3 2 1 N

3. Did personnel check to ensure that all equip- 5 4 3 2 1 N ment as available and functional early in the activation process?

'4. If equipment ws inoperative or failed in use, 5 4 3 2_ 1 N were appropriate actions taken tb resolve defi-ciency (e.g., spares or back-ups, etc.-)?

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BVPS 1983 Annual Emergency Exercise Area Evaluated Monitors Rating

5. Were there any situations dere the lack of 5 4 3 2 1 N equipment and materials, or inoperative equip-ment, or a lack of ability to operate the equip-

• ment, prevent' personnel from performing assigned tasks? (If so, please detail.)  ;

l

6. Could the area support the personnel assigned? 5 4 3 2 1 N l F. Protective Measures

1. Were appropriate protective measures ilnplemented 5 4 3 2 1 N for plant personnel?

2. Were all in-plant activities conducted with 5 4 3 2 -1 N regard to personnel safety, consistent with the need to complete the activity?

~.

G Access Control -

1. Was an appropriate security posture established 5 4 3 2 1 N l against unauthorize personnel? ,

2. Were incoming support personnel (firefighters, 5 4 3 2 1 N

. ambulances, others) provided appropriate access -

. i

. in a timely manner? -

y

3. Was there an identification systems developed 5 4 3 2 1. N

..and used that effectively identified authorized '

personnel. and their duties? -

H. Summary

1. Describe any problems noted by the area being evaluated, a brief description of the problem, its outcrane or eff6ct, and any recommended corrective courses of action,to mitigate or correct the problems.

2. Completely fill out the evaluation form, sign it, and promptly return it as directed.

3. Critiques of the exercise will be held for all participants, monitors and NRC personnel (if applicable) that want to attend. Locations and times

, will be provided.

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Siction VIII BVPS 1983 Annual Emergency Exercise EXERCISE CHRONOLOGICAL RECORD SHEET Time

_(Sta7E7?Itop) Event Actions .Taken t

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SIction VIII BVPS 1983 Annual Emergency Exercise EXERCISE CPRON0 LOGICAL RECORD SHEET Time (Start /Stop) Event Actions Taken 9

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Stcti6n VIII BVPS 1983 Annual Emergency Exerc,ise EXERCISE CHRONOLOGICAL RECORD SHEET Time (Start /Stop) Event . Actions Taken e

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S:ctidn VIII BVPS 1983 Annual Emergency Exerc,ise EXERCISE CHRONOLOGICAL RECORD SHEET Time (Start /Stop) Event Actions.Taken i

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Secticn IX BVPS 1983 Annual Emergency Exerc,ise CRITIQUE AGENDA In order to ensure that planning programs are upgraded or problem items addressed, the Nuclear Regulatory Commission and Federal Emergency Management Agency require that a critique be held following each emergency drill or exercise. The critique is a review session normally held in a meeting style format for both the exercise participants and observers. The critique provides a forum for the comments and views of the individuals involved to be openly aired in the form of constru_ctive criticism and suggestions for improvement.

Because of the fullEcale nature of this exercise and since it will be

~

viewed by Federal observers, there w'111 be a Federal critique and public meeting held upon its completion. The exact dates and time for these 1neetings and critiques are as indicated in Section I of this package. The actual agenda and material covered in the critique will remain open to the

. Individuals that lead them, however, the following is a guideline agenda for the station's critiqu'e of the exercise.

Subject:

1983 Beaver Valley Power Station Full-Scale Annual' Emergency Exercise Critique. -

Objective: To allow for discussion End comment on the general outcome.of the exercise and to identify action, items for necessary improvements.

Topi,cs: ,

Introduction - To be given by criti.que chairperson.

Overview of Outcome - Should not exceed 15 minutes for any one area, (Exercisegrade) be it Operations, TSC, E0F, onsite RadCon, etc.

(or the utility, NRC or FEMA at a joint critique).

Specific problems - Should not exceed one-half hour for any one area.

(Facilities and equipment, com-munications, per-sonnel response. .

etc.) .

Scenario problems - Should be brief and to the point.

. (tooshort,too long,-not enough info.)

Summary - To be provided by chairperson.

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Section 1x BVPS 1983 Annual Emerg:ncy Exerc,ise Note: At all critiques, ensure that the notes and materials used by the exercise controllers / observers are collected by a requisite representative of either the utility, Federal, State or local agencies. These should be used not only for documentation purposes, but also to assist in the preparation of formal. wr.itten critiques and scenarios following the open meetings.,

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REFERENCES f

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BVPS 1983

, Annual Emerger, icy Exerc,ise REFERENCES Beaver Valley Power Station, Emergency Preparedness Plan and Implementing Procedures.

• Beaver Valley Power Station, Operating Manua'l -

Emergency operating Fr:cedures P

E-1 Loss of Reactor Coolant. .

. E-14, High Reactor Coolant Activity , ,

E-15 High Activity, Radiation Monitoring  ;.

Abnormal Operating Procedures A0P-10, Malfunction of Chemical and' Volume Control AOP-13, Los's of Containment Integrity A0P-19, Loss of 120V AC Vital Bus 2 Operating Surveillance Test Procedures OST-1.6.2, Reactor. Coolant System Water Inventory Balance -

OST-1.6.4, Measurement of Controlled Leakage 3

~* Duquesne Light Company, Fublic Information Dep.artment - Emergency Preparedness Plan. , .;

' . Beaver County Radiological Emergency Response Plan for Incidents at the Beaver Valley Power Station and 3hippingport Atomic Power Station.

~

, , Commonwealth of Pennsylvania Disaster 0perations Plan, Annex E, " Fixed -

Nuclear Facility Incidents."

• Pennsylvania Emergency Management Agency Standard Operating Procedures, State Emergency Operations Center. -

West Virginia Radiological Plan for a Fixed Nuclear Facility prepared by West Virginia Office of Emergency Services.

! Hancock County Office of Emergency Services - Beaver Valley Site Emergency l Response Plan.

Columbiana County Emergency Plan - Bhaver Valley Site Emergency Response Plan.

l -

State of Ohio Nuclear Power Plant Emergency Response Plan prepared by The l Adjutant General's Department Disaster Services Agency.

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