ML18017A292

1997 Nrc/Fema Observed Exercise.

ML18017A292
Person / Time
Site:	Susquehanna
Issue date:	10/28/1997
From:	Byram R, Jones G, Kuczynski G PENNSYLVANIA POWER & LIGHT CO.
To:
References
NUDOCS 9712050072
Download: ML18017A292 (265)

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.DOC.DATE: 97/10/28 EOTARTEED: EO DOCKET 0 FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 JTH.NAME AUTHOR AFFILIATION RAM,R.G Pennsylvania Power & Light Co.

JONES,G.T. Pennsylvania Power E Light Co.

KUCZYNSKI,G.J. Pennsylvania Power 8 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

1997 NRC/FEMA Observed Exercise." A DISTRIBUTION CODE: IE35D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Emergency Preparedness-Appraisal/Confirmatory Action Ltr/Exercise Rep T E

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10/28/97 NRC Exercise Manual

FORWARD This exercise package has been developed to provide the basis for conduct of the simulated radiological accident at the Susquehanna Steam Electric Station Unit ¹1, located in Luzeme County, the'state of Pennsylvania.

The exercise will test and evaluate the effectiveness and capabilities of the Emergency Preparedness Response Program for the Pennsylvania Power and Light Company.

This package is to be utilized by the Exercise controllers to initiate, control, and.

evaluate the activities of the participants in the 1997 NRC Observed Exercise.

10/28/97 NRC Exercise Manual

TABLE OF CONTENTS SECTION I INTRODUCTION A. Major Exercise Event Schedule I-3 B. Exercise Development Philosophy I-5 SECTION II 'BJECTIVES SECTION III GUIDELINES FOR CONDUCT OF EMERGENCY EXERCISE SECTION IV CONTROLLER LOCATION AND TELEPHONE NUMBERS IV-1 SECTION V TIMELINE V-1 A. Summary V-1 B. Detailed Timeline V-7 C. Basis of Timeline Events V-21

1. Basis arid Detailed Discussion for Fire Adjacent to V-21 D/G Building

2. Basis and Detailed Discussion for RPS Quarter V-25 Scram and Fuel Damage

3. Basis and Detailed Discussion for Fuel Damage and V-30 General Emergency Trigger

4. Basis and Detailed. Discussion Radiological V-36 Conditions SECTION VI INITIALCONDITIONS VI-1 A. ISES Daily Report VI-1 B. Operator Turnover Sheets VI-9 10/28/97 NRC Exercise Manual

SECTION Vll RADIOLOGICALCONDITIONS VII-1 A. Offsite Release Data VII-1

'I. Weather and Met Data Log VII-1

2. Plume Trajectory and Field Monitoring Team Data Vll-6

3. Release Rate Data VII-32 B. Reactor Water Isotopic VII-36 C. Suppression Pool Water Isotopic VII-38'IIQO D. Drywell Air Isotopic E. Wetwell Air Isotopic VII%2 F. Reactor Building ARM Readings Vll~ .

G. Reactor Building Hi Range ARM Readings VII47 H. Control Structure ARM Readings Vll-50 I. Turbine Building ARM Readings VII-52 J. PASS Sample.Information VII-54 K. In-Plant Radiological Conditions Vll1

1. Turbine Building Rad Conditions VII1

2. Reactor Building Rad Conditions VII45 SECTION Vill MESSAGE INFORMATION SHEETS VIII-1 SECTION IX SIMULATOR INFORMATION. IX-I SECTION X FORMS A. Controller Logs B. Drill/Exercise Rosters .

C. Participant Initial Conditions D. Exercise Phone Numbers 10/28/97 NRC Exercise Manual

SECTION I INTRODUCTION 10/28/97 NRC Exercise Manual

INTRODUCTION This exercise package has been developed to provide the basis for conduct of a simulated radiological accident at the Susquehanna Steam. Electric Station (SSES) Unit

¹1, located in Luzeme County, within the Commonwealth of Pennsylvania. The exercise is scheduled to be conducted on October 28, 1997. This exercise is the biannual Nuclear Regulatory Commission (NRC) observed exercise to satisfy NUREG 0654 requirements. The exercise will have participation by both risk counties, all support counties, all 27 risk municipalities, and the appropriate State agencies. A Federal Emergency Management Agency (FEMA) Radiological (REP) exercise evaluation will be performed concurrently with this Emergency'reparedness

. exercise.

The exercise will test and evaluate the effectiveness and capabilities of the Emergency Preparedness Program for the Pennsylvania Power and Light Company. The exercise has been developed to test most of the major aspects of the SSES Emergency Preparedness Program as indicated in the exercise objectives, (Section II).

This package is to 'be utilized by the exercise controllers to initiate, control, and evaluate the activities of the participants in the exercise. It contains the information and data necessary, along with the plant specific simulator, to properly conduct the exercise in an efficient and coordinated manner.

Exercise participants will not have prior knowledge of the nature of the exercise scenario.

The Exercise will allow individuals and agencies who are assigned responsibilities in an emergency to demonstrate they are adequately trained and capable of providing for the protection of the health and safety of the general public. The Exercise will allow individuals and agencies who are assigned responsibilities in an emergency to train and demonstrate they are adequately trained and capable of responding.

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SECTION I J

PART A - MAJOR EXERCISE EVENT SCHEDULE I-3 10/28/97 NRC Exercise Manual

1997 NRC EXERCISE SCHEDULE October 24, 1997 Controller Training Time: 0830-1200 Location: 'est Building LCR Attendees: All Controllers and Observers

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October 27, 1997 NRC Entrance Meeting for NRC Exercise Time: 1300 Location: West Building Attendees: NRC Inspectors and SSES Emergency Pla'nning

'RC October 28, 1997 Exercise Time: Afternoon Shift Location: Simulator and all ERFs .

Attendees: All Players, Controllers, and Observers October 29, 1997 Critique Preparation Time: 0900-1200 Location: West Building LCR Attendees: Lead Facility Controllers.

October 30, 1997 Critique Presentation Time: 1000-1200 Location: SBA Video Conf Rm Attendees: NRC Evaluators and Lead Controllers, Lead Coordinators and Managers 10/28/97 NRC Exeruse Manual

SECTION I PART B - EXERCISE DEVELOPlNENT PHILOSOPHY l-5 10/28/97 NRC Exercise Manual

EXERCISE DEVELOPMENT PHILOSOPHY NUREG N.3 This Controller Handbook contains essential information pertinent to the conduct and control. of the Exercise. It contains an overview of the Exercise purpose and scope, defines the Exercise control concept and organization, and the staffing functions and responsibilities of individual controllers. In addition, it provides instructions for controllers on the pro'cedures they should follow to manage and document Exercise participation. This document is for the exclusive use of designated controllers during exercise planning and execution. The contents of this Controller Handbook will not be

. divulged to players prior to the end of the exercise.

The NRC Observed Exercise will provide the Nuclear Emergency Response .

Organization (NERO) the opportunity to train and review the individual and overall radiological emergency response procedures.

The purpose of the exercise scenario is to create an emergency situation requiring the'ERO organization to activate using their planned response actions. Exercise control is the process which guides the progress of the simulated activities and provides for the infusion of information. from,non-participating personnel and from nonwbservable, scripted events. The interactions of the various. response elements will provide an opportunity to demonstrate and confirm the adequacy of the plans and procedures currently in place. The dialogue associated with the reviews are expected to result in initiatives to refine and improve plans and procedures and to ultimately facilitate a timely and efficient response to an actual disaster.

INTERFACE WITH OFFSITE AGENCIES There will be limited offsite'participation. The offsite participation will consist of the agencies accepting phone notifications of the simulated events occurring at the power plant. The scenario will include simulated events.and injects from control cells which would likely occur during an actual event.

The Exercise is designed to give players an opportunity to react to situations as they would in an actual radiological emergency. The technical aspects of the scenario and the involvement of the public will be simulated through the use of the training simulator, scripted technical data, and exercise messages. Controllers also will simulate various types of interested parties such as legislators, media, and various government and private sector principals. A major exercise design consideration'is that simulations will be conducted only to the extent needed to facilitate dynamic interactions among the players.

Controllers at the TSC, MOC, and EOF will stimulate player actions by providing information and data, or injecting scripted messages in accordance with specific 10/28/97 NRC Exercise Manual

directions, The Facility Controllers will notify the Lead Controller of any event or player action that may prevent meeting one of the major goals of the Exercise. The Lead Controller will take the appropriate actions to assure the Exercise objectives are met (e.g., prompt an action by a player).

ROLE OF PLAYERS Participants will respond to scenario situations in accordance with their respective procedures. Players or participants in the Exercise are expected to carry out, as authentically as possible, the response functions required of their positions. Although.

the date and location of the exercise will be known to players in advance, the details of the scenario will not. To the extent possible, players will participate as they would in the event of an actual radiological emergency. Players will be drawn into the exercise throughout the notification process in accordance with established plans or procedures and through spontaneous communication initiated by other players.

Once engaged in the exercise, a player may act in response to a scenario simulation, other player interaction, or the requirement of a procedure check list item. Players are expected to respond with the breadth and depth of activity appropriate for'the scenario situations presented. Controllers will inform players when and if an action should be simulated instead of being spontaneously played out in the "context of the Exercise.

See Section ill for more information on Controllers and Conduct of Exercises.

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SECTION II OBJECTIVES It-1 10/28/97 NRC Exercise Manual

1997 NRC/FEMA Observed Exercise .

Objectives, Scope, and Extent'of Participation

SUMMARY

The Objectives, Scope, and Extent of Participation of the NRCIFEMA Observed Exercise are based on meetings held with the State, FEMA, and counties at the West Building on May 20, 1997. The exercise in October will be a normal plume phase, biennial exercise for the PP8L Nuclear Emergency Response Organization (NERO). A mini-drill will be conducted to test the ability of the NERO to support a shift change in the EOF during the course of the exercise.

BACKGROUND A biannual exercise is performed to meet federal requirements for the State, PP8L, the local municipalities, the risk counties located within 10 miles of the plant, and the support counties. The involved entities are required to demonstiate emergency preparedness by mobilizing, communicating, and taking necessary actions to protect the public in the event of an incident at the Susquehanna Steam Electric Station (SSES). The duration of the exercise is expected to be between 4 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to allow sufficient time for all parties to demonstrate the applicable requii'ements or objectives.

During a plume phase biennial exercise, FEMA is charged with evaluating the emergency preparedness of the off-site agencies and the NRC is responsible for evaluating the preparedness of PP&L. Satisfactory demonstration. by the off-site agencies and PP8L are conditions of the operating license for the Susquehanna station. A poor performance by any of the off-site organizations or PP8L places operation of SSES at risk. the'ontinued Every 6 years all emergency response organizations are required to demonstrate the capability to man the response facilities around the clock. The EOF 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing mini-drill will test the EOF's ability to support 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> operation. All involved municipalities and risk counties will also demonstrate a shift change during the course of the exercise.

The attached is a list of objectives based on the 10 CFR 50.47 and NUREG-0654 which will provide the basis for evaluation of the PP8L emergency response organization..

The listed objectives will be demonstrated by PP8L, and a similar set of objectives will be demonstrated by the State, the risk and support counties, and the. municipalities during the exercise.

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1997 NRC/FEMA Observed Exercise Objectives e Objectives which support the 1997 NRC Observed Exercise have been reviewed and approved by PP&L upper management as indicated below.

Approved:

Robe . yram, Approved:

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Ge T. Jones Approved:

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OB JECTIVES

~ The following objectives establish the scope of the October 28, 1997 Emergency Exercise.

The objectives establish the extent of play and ensure that required events are induded within the exercise scenario.

Demonstrate the ability to notify, mobilize, activate, and sustain the Pennsylvania Power & Light (PPBL) Emergency Response Organization.

Extent of Play:

For the 1997 Annual Exercise, PP&L will activate the Control Room (Simulator),

OSC, TSC, EOF, and the Media Operations Center. The Nuclear Emergency Response Organization (NERO) will be notified using the TelenotNcation System (TNS), with the exception of the Simulator Control Room, which will be pre-staged.

2. Demonstrate the capability to perform accident assessment to support dassification, protective action recommendations (PAR), and protective measures decision processes.

Extent of Play:

Accident assessment will be demonstrated by personnel in the Control Room (Simulator), TSC, and EOF as required by the scenario.

3. Demonstrate the capability to dassify emergency conditions utilizing appropriate emergency action levels (EALs) criteria.

Extent of Play:

Classifications will be made by the Control Room (Simulator), TSC, and EOF as required by the scenario using appropriate EAL criteria.

4, Demonstrate the capability to determine and initiate appropriate PARs based upon plant/site conditions, dose assessments, plant/field measurements, and weather conditions.

Extent of Play:

Protective action recommendations may be initiated by the Control Room (Smulator),

TSC, or EOF, dependent on the scenario. Protective action recommendations will be presented to the State for applicable emergency action levels. Protective actions will be simulated by the State/at-risk counties.

Demonstrate the ability to assess conditions and implement appropriate protective measures for emergency response personnel, habitability, including site access control, contamination control, exposure control, use of protective devices, and, as appropriate, the process for authorizing the use of potassium iodide (Kl).

Extent of Play:

Protective measures will be considered for all PP&L'mergency response workers.

The erst team dispatched from the OSC/TSC will be expected to demonstrate the use of protective clothing. Other teams will not be required to dress out. Habitability surveys will be conducted by the emergency responders. The need for potassium iodide will be evaluated. If scenario conditions warrant the use of KI, distribution will be simulated. Exposure control will be maintained for all personnel dispatched into controlled areas.

Demonstrate the capability to determine and initiate appropriate mitigation measures to place the plant in a safe condition and reduce the effects of the source term.

Extent of Play:

Primary responsibility for placing the unit(s) in a safe condition will be with the Control Room (Simulator). The Operations Coordinator in the TSC will also assist in this effort, using TSC staff as necessary. EOF personnel may also be. called upon to assist in mitigating the effects of the accident.

Demonstrate the capability to maintain command and control of the emergency response effort.

Extent of Play:

Command and control of the emergency will be demonstrated by the actions of the emergency response organization. Management personnel are expected to establish and dearly communicate plant priorities. Supervisory 'personnel are expected to implement mitigation strategies and communicate results to management.

Demonstrate the ability to notify the state, local governments, and the NRC within established time constraints.

Extent of Play: r During the exercise PP&L will notify the State and risk counties as required by the scenario. The NRC will be notified at the beginning and end of the exercise..

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9. Demonstrate the ability to establish and maintain effective communications, within and outside PP8L.

Extent of Play:

.. Communications will be maintained between PPB L emergency facilities and the State t

and risk counties throughout the exercise. Communications will also be iriitiated to INPO and ANI. All other communications will be simulated using control cells.

Back-up communications will be tested as required by procedures during activation of the emergency facilities. Back-up communications equipment will be used in. the event of an actual equipment failure.

10. Demonstrate the ability to coordinate preparation, review, and release of timely and .

accurate information to the public.

Extent of Play:

PP8 L will activate the Media Operations Center for the exercise. Press releases and news releases will be prepared by MOC personnel. PP8L emergency management 11.

personnel will review and approve press releases.

Demonstrate the ability to establish and maintain rumor control.

I Extent of Play:

Media Operations Center personnel will perform rumor control for PPBL. The scenario will include messages which will result in the performance of this objective.

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12. Demonstrate the ability to conduct assembly and accountability of personnel within the protected area.

Extent of Play:

Assembly and accountability will be performed for plant personnel during the exercise.

13 Demonstrate the ability to conduct site evacuation of non-essential personnel.

Extent of Play:

Site evacuation will be simulated for the exercise.

14. Demonstrate that facility layout and equipment support emergency response activities in each facility.

Extent of Play:

The adequacy of each emergency response facility will be evaluated by the controllers for each facility. Controllers are expected to observe the overall facility, equipment, method of operation, and position specific procedures for their facility.

'5. Demonstrate the capability to'deal with an on-site medical emergency and transport a contaminated injured person'to an off-site medical facility..'xtent of Play:

This obJective will not be demonstrated during the exercise.

16. Demonstrate'the capability of the on-site fire brigade to handle an on-site fire emergency and coordinate with off-site support as required..

Extent of Play:

This obJectlve will not be demonstrated during the exercise.

17.~ Demonstrate the capability to provide for continuous staffing of PP&L emergency

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facilities.

Extent of Play:

This objective will be demonstrated by preparing and Implementing shift tumovers for the EOF.

18. Demonstrate the. ability to establish a Recovery Organization and to develop a Recovery Plan.

Extent of Play:

Demonstration of this objective will be limited to brief discussions In the TSC and the.

EOF concerning the addition of personnel and organizations to aid in the recovery from the accident:

19. Demonstrate the ability to conduct a self-critique and to identify areas for improvement.

Extent of Play:

Critiques will be conducted in each emergency response facility. Controllers will record comments at the critique. Areas for improvement will be noted and included in the formal exercise report.

SECTION III I GUIDELINES FOR CONDUCT OF EMERGENCY EXERCISE 10/28/97 NRC Exercise Manual

INTRODUCTION This exercise is a means by which Pennsylvania Power 8 Light. along with the Commonwealth of Pennsylvania and local government authorities will demonstrate

. emergency preparedness operations. The previous section set forth the objectives of

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this demonstration. Then it defined the extent of'play to accomplish those exercise objectives. Here we establish the boundaries within which the participants and controllers may operate while performing this demonstration. The scenario has been designed by the state and the licensee to support the listed extent of play. The intent of the scenario is to allow maximum free play. The scenario drives participant play for demonstration of the objectives. The following section describes how maximum free

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play is supported while ensuring adequate opportunity to demonstrate objectives.,

The Guidelines for Conduct (Section III) is divided into five parts:

Termination or Delay of the Exercise Controller Guidelines Participant Guidelines Observer Guidelines Simulations These parts establish the envelope of exercise play and control. The scenario is designed with a success path. It will allow the participants to mitigate the consequences of the simulated accident while providing accomplishment of the objectives. Providing the initiating actions to the participating off-site agencies is also within the scenario design.

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TERMINATIONOR DELAY OF THE EXERCISE

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1. Actual Emergency at SSES or any

~ of the response facilities During any exercise, an actual emergency might occur. An incident at the plant or any facility which could be life threatening may justify any player or controller to suspend play. Any natural or technological hazard'hat threatens, or carries the

'otential to threaten, life or improved property can be reason for controllers to halt play. In the event of a real emergency, notify the Exercise Lead Controller. The Exercise Lead Controller will make the determination to postpone, suspend, or.

restart the exercise. The Exercise Lead Controller will ensure that information is disseminated to all locations through the controller organization.

2. Inclement Weather The Lead Controller has the authority to suspend parts or all of the'exercise due to inclement weather. Weather conditions that cause a weather.warning to be

'roadcast over the Emergency Broadcast System (EBS) are sufAcient to cause a delay or postponement of the exercise.

3. Completion of Exercise Play The Lead Controller in conjunction with the State Lead Controller will make the determination when to stop exercise play for all facilities and disseminate that

', information to all locations through the controller organization. Consideration will begin when all objectives have been accomplished. Exercise play may be stopped in a facility when all their objectives have been met and they are not needed for external communication or support of other emergency response facilities.

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CONTROLLER GUIDELINES All controllers are required to perform both as a controller and a evaluator. These guidelines were developed to help controllers perform those tasks.

The exercise will be held on October 28,1997. The exercise operations crew will report to the Training Center Simulator room at 1500. AII other emergency responders will report to theil'acilities upon notification through standard emergency call-out procedures.

Exercise play will start at 1500. All controllers will be in their respective facility at least 30 minutes prior to their respective facility being activated.

The Facility Lead Controller for all facilities will call the Exercise Lead Controller as soon as all of his controllers are on location. A brief update on exercise status will be conducted.

All controllers are responsible for immediately notifying the lead controller if they can' be in their required location on time.

. Controllers must ensure that all communications (written and verbal) begin and end with "THIS IS A DRILL."

Radios should not be used by players or controllers in sensitive areas of the'plant.

This is a formally evaluated exercise. Any prompt, assist, or inject must be recorded'in the evaluation package.

Facility lead controllers must keep the exercise lead controller informed.

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All controllers are required to maintain a record of the pertinent activities in their area (time of event included). Controller logs are provided with this manual.'ake additional copies if needed. Also, list observations of any program or process deficiencies that occurred. Turn in all controller logs to the Lead Controller.

All controllers must know the scenario time line. Identify all deviations from the scenario time line. Record and notif'y exercise lead controller immediately.

Get approval from the exercise lead controller prior to injecting a contingency message to players.

All controllers must know the exercise objectives and evaluation criteria for their area.

Document accomplishment of the evaluation criteria and objectives. Some objectives will include more than one facility.

10/28/97 NRC Exercise Manual

CONTROLLER GUIDELINES Facility lead controllers are responsible for the post exercise facility critique.

The Exercise Lead Controller will be located in the Simulator Control Room and will be responsible for coordination of the other controllers at that facility and overall exercise control. The Exercise Lead Controller will ensure that all messages and data are appropriately assigned to a controller. The Exercise Lead Controller has the authority to resolve unexpected situations at all the response facilities to ensure the exercise meets the expected objectives'. At the end of the exercise, the Lead Controller will ensure that critique information is collected prior to controllers and players leaving, the exercise area.

Control Cells will be located at the MOC in the East Mountain Business Center. Control Cell personnel will introduce scenario events over the telephone, simulating roles of individuals or groups not participating in the exercise.

Facility Controllers have the authority to interject messages to support free play as necessary. Facility Controllers are familiar with the exercise scenario and have the responsibility to assure that. the activities at their assigned location are consistent with the exercise objectives.

Actors will be assigned to simulate roles.,of individuals or groups not participating in the

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exercise, but who could become involved in a real event. The MOC will have "media

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actors" not familiar with the scenario, who are responsible for questioning public affairs personnel and press briefers.

Field Controllers will accompany emergency field team personnel as they are deployed.

from the EOF or OSC.

Controllers have direct responsibility for presenting or communicating a condition to players through the use of pre-scrtpted information. They must provide the required information without prompting players. Control Cell Controllers will respond to player requests by simulating the various roles needed, primarily for non-participating agencies.

Facility Lead Controllers will produce a chronological report of the exercise activities in their area. It will contain as a minimum, a facility event time line, final status of evaluation criteria and objectives, other pertinent data. It will be presented at the combined facilities critique along with all logs and other forms.

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PARTICIPANT GUIDELINES

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These guidelines will be issued to each of the participants in their participant notification package.

The exercise will be held on October 28,1997. The exercise operations crew will report to

'the Training Center Simulator room at 1500. All other emergency.responders will report to their facilities upon notification through standard emergency call-out procedures.

All communications shall begin and end with the notice: "THIS IS A DRILL."

Players are not to communicate with controllers during the exercise except to obtain or clarify data. Exercise information will be provided according to'the exercise ti'me line.

Do not request information that would not be available to you in a real emergency.

Players are encouraged to be demonstrative in the conduct of their responsibilities. Let controllers and evaluators know how you are responding to the scenario events and-what the expected results are.

DO not take any action that may endanger personnel or plant safety.'f you have a question regarding an action, ask a controller.

If you cannot understand a PA announcement during the exercise due to equipment problems, notifjj th'e controller in your area.

If an actual emergency occurs during the exercise, notify the exercise lead'controller immediately. The exercise lead controller may suspend exercise play, terminate the exercise, or take other appropriate action.

The Site Emergency alarm will be used to call for assembly and accountability.

The off-site emergency siren system will not be used during the exercise.

Radios should not be used in'sensitive areas of the plant.

Following the exercise, a critique will be held in your emergency response facility. If you identify items that need to be improved, make sure controllers record your comments at the critique. Submit a completed Emergency Planning Improvement Recommendation form for each'item.

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OBSERVER GUIDELINES

.All observers must be pre-approved by the Supervisor Nuclear Emergency Planning and will be physically Identified as.a observer.

These guidelines are to be issued to observers'by the facility lead controller.

Upon your arrival at an emergency response facility, request specNc instructions from the controller in the area that you will be observing. Some areas may be restricted to observers due to crowding. 'C Observers will not communicate with players during the exercise.

Do not block aisles, status boards, computer display terminals, or clocks.

Do not use telephones that may be needed for the exercise.

If you observe any actions that may be a threat to the plant or personnel safety, notify a controller.

lf you have any comments or recommendations for improving emergency preparedness at SSES, please communicate this information to the Emergency Planning staff or controllers.

Thank you for your cooperation, 1

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SIMULATIONS

.Exercise artificialities are situations that would not exist in an actual accident, Certain artificialities or simulations are expected in any exercise. Some are induced by the design of the exercise; and some are. actions that are intentionally precluded. It is not acceptable to actually damage plant equipment or place plant personnel (or the public) at hazard for the sake of an exercise. Intentional artificialities and simulatioris include:

1. Plant Condition There will be no manipulation of actual plant controls and equipment. The actual operating condition of the Susquehanna Steam Electric Station (SSES) will not be altered during the exercise. The Control Room Simulator will be used as the Control Room. An exercise operating crew will conduct the exercise in the .

simulator. Message injects or live data from the PICSY will provide information concerning all plant parameters that would be observed if the simulated accident had actually occurred. The exercise operators in the simulator control room will respond to the simulator. indications and messages as 'hough the parameters/messages had been observed/received in the control room.

2. Weather Real time meteorological conditions will not be used during the exercise.

3. ~Free Pla Controllers will ensure that the exercise progresses on schedule while enabling the participants as much opportunity as possible to respond to the scenario as they would in an actual radiological eveht.

4. Off-site E ui ment/Dress Wearing of protective clothing (including respirators and gloves) will be simulated by all off-site emergency responders. Emergency Monitoring teams. will be required to perform surveys and collect air samples. Controllers will guide field participants on how to respond to queries from the public.

5. ALARA Entering actual contaminated and/or high radiation or greater areas to'simulate repair of damaged equipment or conduct surveys is prohibited.

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6. ~ Potassium Iodide KI Issuing and distributing Kl will be simulated. ~

. 7. Res irato Protection If required by the scenario, at least one team will demonstrate how to don SCBA units; however, wearing of the facepiece, will be simulated. All other use of .

respirators will be simulated. The participant must initially describe how to obtain, don and use the equipment. Also, wearing of facepieces for other types of respiratory protection will be simulated.

8. Fire E ui ment/Dress If needed, fire fighting activities will . be simulated. Simulations include pressurizing hoses, discharging of extinguishers, and 'ctuation suppression systems. If temperatures are too hot, turn-out gear may be

'f simulated. This judgement will be made by, the Lead Controller prior to the start of the exercise.

9. Site Evacuation Site evacuation of non-essential personnel will not be conducted.

10 ~NERO S rt The procurement of food for emergency personnel will be pre-staged. Procuring additional personnel or equipment for site support and/or field monitoring activities will be simulated.

11. Communications Selected off-site communications are simulated. See the "Controllers Section (IV) for a list of the replacement telephone numbers.

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SECTION IV CONTROLLER LOCATION AND TELEPHONE NUMBERS I.

~ I IV-1 10/14/97 NRC Exercise Manual

EXERCISE TELEPHONE NUMBERS Partici atin A enc Numbers:

PP&L AGENCY NETWORK 'UTSIDE NUMBER (Reference PEIIA 8-(717) 651-2001 Emergency'elephone Directory.

CCDES "191" ,. 8-(717) 389-5720 for additional LCEIIA 8-(717) 820-4400 telephone numbers)

DEP/BRP RADIOLOGICAL 4964 8-(717) 75M964 DEP/BRP TECHNICAL'965 8-(717) 75M965 Mock Numbers:

AGENCY NETWORK OUTSIDE NUMBER PLAYER NRC/HPN 8-321217 8-(717) 831-6217 Bill Neidermeyer NRC/ENS 8-321-6220 8-(717) 831%220 Frank Gruscavage INPO ANI '-321-6237 8-321-6244 8-(717) 831237 8-(717) 831<244 Debra McDermott Debra McDermott ALLEGHENYELECTRIC 8-321-6236 8-(717) 831-6236 Debra McDermott TRANSMISSION POWER 8-321-6243 8-(717) 831-6243 Donna Roth DISPATCHER NATIONALWEATHER 8-321-6257 8-(717) 831-6257 Donna Roth SERVICE CORPORATE 8-321-6249 8-(717) 831%249 Donna Roth COMMUNICATIONS IV-2 10/14/97 NRC Exercise Manual

Facility Controllers POSITION 10/28/97 NRC Exercise Telephone Extension Control Room Simulator Instructor C. Hess 8-254-1613 Lead Control Room Controller W. DiDomenico 8-254-1 613 Lead Controller R. Halm 8-254-3782 OSC OSC Lead Controller F. Calabrese 8-254-3907 OSCAR Controller M. Micca 8-254-3907 Rad Controller D. McGarry

'SC 8-254-3907 In-Plant Team (HP) R. Hock 8-254-3907

.In-Plant Team (HP) C. Madara . 8-254-3907 In-Plant Team (Eng) S. Daderko 8-254-3907 In-Plant Team (Ops) T. Maruca 8-254-3907 In-Plant Team (Ops) J. Paisley 8-254-3907 In-Plant Team (Ops) T. Kinsey 8-254-3907 In-Plant Team (Ops) A. Ulitchney 8-254-3907 TSC TSC Lead Controller K. Chambliss '.

8-254-3223 TSC Rad Controller Kessler ., 8-353%932 TSC Engineering Controller S. Kuhn Security Controller R. Kishbaugh 8-254-3115 PASS/Chem Controller P. Treier 8-353Q932 EOF Lead EOF Controller A. Male 8-321%201 Engineering Controller J. Rothe 8-35~928 EOF Support Controller S. Denson 8-353<920 Lead EOF Rad S. Ingram 8-3534910 Field Team Controller T. Furler Radio Field Team Controller W. Hill Radio MOC Lead MOC Controller J. Sco lliti 8-321%293 MOC Rumor Control(Site En ) B. Neidermeyer 8-321 W218 MOC Rumor Control(Site En ) F. Gruscava e 8-321%218 MOC Rumor Control(GO En ) D. Roth 8-321%218 MOC Rumor Control(GO Eng) D. McDermott 8-321-6218 IV-3 10/14/97 NRC Exercise Manual

EXERCISE EMERGENCY PHONE DIRECTORY

'ONSITEIPP&L NRC EXERCISE For October 28, 1997 SIMULATOR CONTROL ROOM PHONE NUMBERS SHIFT SUPERVISOR ETN 25¹3867 CTN 353-4973 OPS COMMUNICATOR CTN 353-4916 UNIT SUPERVISORS DESK ETN 254-3868 STA DESK ETN 254-3859 CONTROL ROOM REFEREE ETN 254-1613 LEAD REFEREE ETN 254-3782 EOF RECOVERY MANAGER CELL PHONE RECOVERY MANAGER (G. D. Miller) Cell Phone (610) 703-7633 EOF ENGINEERING SUPPORT SUPERVISOR CELL PHONE'ngineering Support Supervisor (M. Detamore) Cell Phone (610) 703-7427 SECURITY ASCC ETN 254-3115 IVX 10/14/97 NRC Exen:ise Manual

EOF Control Cell Location Ext 8243, 6257, 8249 Ext 6237, 6244, 6238 Q

Ext. 8218, 8235 Ext. 8217 Ext. 6220 IV-5 10/14/97 NRC Exercise Manual

~To NRC Conference ~a~~

oom Admtn.

Coonfin ster 4930 Securtty Coordnstor 4931 TSC Dose Cstcutstor 4932 O

O K

O Red. Protecdon Cooidlnstor 4933 V

0 TSC Layout and Telephones.

C%

TSC Commun@ster 4933 Opersttons Coordtnstor 493tt TSC Coordtnstor 4939 GETARS 542~

4941 542'ispatch 7 940 Elevator T5 944 To Library 10/14/97 NRC Exercise Manual

SECTION V - TIMELINE PART A - Summary V-1 10/28/97 NRC Exercise Manual

1997 NRC OBSERVED EXERCISE

SUMMARY

The following is an overview describing the events of the detailed timeline and predicted response of the Emergency Response Organization.

INITIALCONDITIONS Susquehanna Steam Electric Station Unit 1 has been at 100% power since the refuel outage with the exception of the normal surveillance testing (MSIV and Turbine Valve testing, rod swaps, etc.) and power reductions due to minimum generation alerts. The plant has been operating since the last refueling outage with minimal problems.

A problem that has been recurring is reactor water level spikes on both units that are attributed to the ringing phenomena.

Two momentary reactor water level spikes were experienced yesterday, one at 1635 and one at 2325. GETARS was manually initiated on both occasions. 'o operator actions were required since the plant responded quickly and level was restored to 35" within 5 seconds. No other anomalies were observed.

Another problem which has not been resolved is the ability of Service Air to back up Instrument Air through the cross tie. System Engineering is continUing to pursue resolution to the Service/Instrument Air cross-tie pressure control issue.

A leak has develo ed on the 'B'HR.Service Water Heat Exchan er shell side relief inlet flan e that needs to be leak sealed. The work is scheduled to be initiated when the work acka e has been reviewed and a roved. The room floor drains are bein drained a roximatel once er shift.

Additional items/problems that the plant is working/investigating are listed on the Daily Report which is attached.

SHIFT TURNOVER The above listed information will be given to Operations during a turnover process. The Operators will be given a shift turnover by the Control Room controllers. The turnover will discuss the status of the above items as shown on the Station Priority List and supported with Control Room logs.

V-2 10/28/97 NRC Exercise Manual

SCENARiO SVMMARY Source Term The initial fuel damage assumed for development of the scenario data is approximately 420% clad failure. The cause of the fuel failure is attributed to uneven power l distribution on a failure to scram.

h As the scenario develops, additional fuel failure is attributed to a stuck control rod which will not insert into the core. The additional fuel failure is to drive containment radiation levels and cause a General Emergency classification.

The scenario has two different leak paths, one is from the Turbine Building Vent and the other is from the Reactor Building/Standby Gas Treatment Vent.

Release Paths The exercise has two different release paths for the participants to evaluate:

'T~li ~ lldl .Tk I khtkl I tk t I,d tk into the main condenser and out of the main condenser when vacuum is lost.

The leak rate is based on nominal leak rate values (35 SCFM).

As found LLRT data is used as the basis for leakage through the. Main Steam Isolation Valves to the Main Condenser. The gases which collect in the main condenser are released to the turbine building as condenser vacuum is lost via the turbine seals.

The Turbine Building flow path is not a treated flowpath but is monitored for a period of time. As the scenario progresses, the release from the Turbine Building will become unmonitored due to high background radiation at the vent monitor detector. The high radiation levels will mask the release from the Turbine Building Vent.

Reactor Buildin /SBGTS - A ten gallon per minute leak of Suppression Pool water into the Reactor Building is assumed to be ongoing unless investigated and mitigated by the organization.

The Suppression Pool water that is discharged into the Reactor Building has a significant amount of activity. The high activity is due to continual blowdown of reactor steam from the reactor vessel to the Suppression Pool via a stuck open relief valve.

The leak of suppression pool water into the Reactor Building will end up in the Reactor Building sump which will be pumped to the Rad Waste Building. For V-3 10/28/97 NRC Exercise Manual

Scenario development, it is assumed that most of the noble gases contained in the suppression pool water which leaks into the Reactor Building are released to the Reactor Building Sump. The Reactor Building Sump is vented to the Reactor Building Ventilation system.

The organization will be provided a success path for the Reactor Building leak.

See the radiological description section for a detailed explanation.

Classification and PARs ALERT - The initial event is a vehicle fire between the Service and and the 'D'iesel Generator Building.

Administrative'uilding

'I SITE AREA EMERGENCY - The second event is a plant transient which causes fuel

'damage (204.% clad failure) to drive a Site Area Emergency Classification. I The transient is a partial failure to scram which causes fuel damage. The fuel damage is the trigger for the classification to the Site Area Emergency.

A slight radioactive release begins as a result of the plant transient, (RHR room) and will continue until mitigated by the organization.

GENERAL EMERGENCY - An increase in containment rad monitors will be the trigger to upgrade the classification to a General. There will be several indicators to review to determine if a General Emergency classification'is warranted. There is not a large amount of fuel damage and not a catastrophic failure of the coolant or primary containment barriers but a continuing release of radioactive material and no mechanism for decay heat removal.

SCENARIO OVERVIEW ALERT The initial classification will be an ALERT and it will be at approximately 1700. The otential exists that an UNUSUAL EVENT will be declared first and shortl thereafter an ALERT. The UNUSUAL Event classification will be based on a fire lastin lon er than 15 minutes and activation of the Fire Bri ade EAL 14.1 ONSITE FIRE/EXPLOSION.

The EAL for the classification will be ONSITE FIRE/EXPLOSION EAL 14.2 based on a fire in a tractor trailer engine compartment which spreads to engulf the entire cab. The fire will last longer than 15 minutes with the potential to affect safety related equipment.

Information during the fire scenario will be forwarded to the Control Room by the Fire Brigade Leader. Information transmitted to the Control Room will also provide indications that a Toxic/Flammable Gas {EAL0 19} has entered the facility.

V-4 10/28/97 NRC Exercise Manual

This portion of the exercise is not to demonstrate onsite/offsite fire brigade response and any offsite or onsite response will be simulated. A controller will accompany any operator dispatched to investigate the "fire" and a controller will accompany the OSC Coordinator/Fire Brigade Leader when the Fire Brigade is activated. This portion of the scenario is to trigger the ALERT classification.

SITE AREA EMERGENCY At 1815 the SITE AREA EMERGENCY classification is to be declared. The

. 'lassification is due to fuel damage resulting from a failure to scram.

The plant transient results from a 1/4 scram initiated by an i&BC surveillance which has

[

been in progress and a blown fuse. The quarter scram fills the Scram Discharge volume which prevents insertion of the remaining rods when the full scram signaI is generated.

'I The fuel damage is a result of the uneven rod pattern at the time of the scram. The fuel damage initiates a containment isolation which isolates the, normal heat sink (main Condenser).

During the Control Room operators'esponse to the plant transient, a piping failure will occur which will cause a loss of decay heat removal for the unit.

There are two release paths both of which are monitored, one via the Turbine Building Vent and the other from the Reactor Building vent. As the scenario progresses the monitored release paths will become unmonitored.. The change from monitored to unmonitored occurs as a result of increasing radiation levels in the Reactor Building.

The increased background radiation level around the vent monitor detectors causes the detectors to read high.

GENERAL EMERGENCY The General Emergency Classification is expected to occur at 1900. The General

(

Emergency classification will be triggered by high containment radiation resulting from fuel damage which occurred due the failure to scram and the stuck control rod.

There will be several indicators of degraded coolant and primary boundaries prior to the containment radiation level reaching the trigger point for the General Emergency classification. The indications of the degraded boundaries are:

Suppression pool temperature increasing as a result of no decay heat removal (Stuck open relief valve - Primary Coolant boundary).

The Reactor Building and Turbine Building general area radiation levels will be increasing, V-5 10/28/97 NRC Exercise Manuai

(MSIV leakage and RHR Relief valve - Primary containment boundary)

The Turbine and Reactor/SBGT vent monitors will indicate increasing release rates (MSIV leakage and RHR Relief valve - Primary containment boundary)and, Field team readings of 20 to 30 mr/hr at two miles will be an indicator of the failed boundaries, A Protective Action Recommendation should be made to the State after the declaration of a General Emergency. It is expected that the PAR will be to evacuate from 0 to 2 miles and shelter from 2 to 10 miles.'he exercise will be terminated after the State, counties, municipalities, and utility have completed demonstration of their objectives.

A debriefing will be held in each facility at the end of the NRC OBSERVED EXERCISE by the lead Controllers. The formal critique preparation will be with the lead Controllers at the West Building on October 29, 1997.'UMMARY TIMELINE 1500- -Control Room Setup 1625-1700-Alarms received in Control Room indicating a fire near the S&A Building.

ALERT classification by Control Room based on a fire with potential to impact safety related equipment.

l

~

1800- TSC in control of emergency management.

180 - Plant transient causing fuel damage and trigger for a Site Area Emergency.

1800- TSC in control of emergency management.'815-ClassiTication by the TSC at a Site Area Emergency level based on (

containment radiation'evels.

18390- EOF activated and prepared for turnover of emergency management l responsibilities.

I 930-1 Increasing containment radiation levels reach the trigger point for a General l Emergency classification by the EOF Staff.

1945 - The EOF Staff recommends to the State that a protective action be initiated. l

~

V-6 10/28/97 NRC Exercise Manual

2100 - Turnover of EOF facility to "second shift".

2130- The 1997 NRC OBSERVED EXERCISE is terminated.

2130- EOF Discussion of recovery issues.

V-7 10/28/97 NRC Exercise Manual

SECTION V - TIMELINE PART B - Detailed Timeline V-8 10/28/97 NRC Exercise Manual

APP E 0 INITIATINGEVENT EXPECTED SEQUENCE OF EVENT -.

1500 Controller Messa e - Control Room Controllers to set The Control Room Controllers will review the following for set up of the IS-1 up initial conditions for the scenario in the simulator. simulator

1. Operations turnover sheets

2. ISES Daily Report NOTE: The above material is located in the INITIALCONDITIONS of the CONTROLLER MANUAL. 'ECTION 1500 Controller Messa e - Equipment set up, initiate Phone company personnel to perform switching in the Service and IS-2 activation of the emergency exercise phones, radio, Administration Building phone room and hook up in the simulator Control and plant page for the simulator Control Room. Room.

Lead Controller to swap simulator radio and check if the NRC phone is activated.

1500 Controller Messa e - Simulator Instructor initialize the .The initial plant conditions contain the following files: IS-3 (B.1, B.2, B.3, simulator to IC-XXX.

B.5) QXKMM-One of the conditions that is a part of the scenario is l8 C performing half scram surveillances in the plant. The Sl-XXX-XXX-XXwill be part of the turnover process. SEE IS-X at 1645.

An additional initial condition is the SDV Hydraulic lock which is IMF RD155017 See SECTION IX SIMULATOR INFORMATION for data contained in these files.

1530 Controller Messa e - Plant page announcement for Plant page announcement to be made from Control Room indicating the start ISO start of 1997 NRC Observed Exercise. cf the 1997 NRC Observed Exercise.

1620 ControllerMessa e-The ReactorBuildin NPOcalls TheControlRoom rants ermissionforthedrainin ofthefloordrains. IS-5 the Control Room re uestin ermission to drain the RHR room floor drains.

1625 Controller Messa e - The Fire Scene Controller The Control Room will receive information of a fire outside Unit 1 East Turbine . ISA (I.1, 1.2) initiates information for the fire scenario. Building Trackway between S8A Building and Diesel Generator Building. The

'driver of the truck is calling the Control Room on the plant page (PA722 on the SBA Loading Dock).

1625 Simulator Control Room Operators will respond to the The Control Room Operators will review the fireplan and send an operator to (I.1, I.2) information received. investigate the report. r V-9 10/28/97 NRC Exercise Manual

APPX TIME OF DAY INITIATINGEVENT EXPECTED SEQUENCE OF-EVENT', ',., ,-;

1625 Controller Messa e - Shift Supervisor activates the . The fire brigade response will be simulated. The Fire Brigade Leader (FBL) IS-79 fire brigade. will be provided information by a Fire Controller. The information provided by the controller will be reported back to the Control Room.

If offsite fire fighting support is requested it will be simulated. The Security Controller will provide the offsite response times to the officer in the ASCC for transmission to the Control Room.

1630 Duty Manager and Operations Coordinator report to Shift Supervisor provides status of the fire event, actions taken, and plans for (A.1, A.3, A.4, Control Room for briefing of incident. future actions.

B.7, B.8, B.9) 1630 Controller Messa e - Simulator Instructor initiates The Simplex Panel alarm received in the Control Room (Fire Detection X232 IS Z7) will indicate a panel alarm for the S&A fire protection panel OC707.

The alarm on the SBA local panel (OC707) is a smoke alarm.

1635 Controller Messa e - The fire brigade arrives on The FBL reports back to the Control Room from the scene the indications IS-98 scene and reports status to the Control Room. observed.

At the fire scene the tractor engine compartment is engulfed in flames with indications diesel fuel is on fire and smoke.

1635 Controller Messa e - Simulator Instructor initiates The Simplex Panel alarm (Fire Suppression X234 Z7 ) is received in the IS-108 simplex alarm and fire pump start aiarm~lMF .Control Room will indicate a fire suppression alarm for the S&A drypipe fire YCF13510 & MRF:FD013014 .. protection. S&A Building Lpcal Fire Panel alarm (OC707) will be Zone 8.

The alarm on the simplex panel is caused by activation of the diypipe system and subsequent auto start of the fire pump as indicated by Fire Suppression Alarm on panel OC650.

1640 Controller Messa e - The fire brigade reports status to The FBL reports that the fuel tank on the tractor is now involved with the IS-110 the Control Room. tractor's front tires on fire producing large quantities of smoke.

0 10/28/97 NRC Exe cise Manual

APP OF INITIATINGEVENT EXPECTED SEQUENCE OF EVENT 1640 Shift Supervisor reviews information received and The classification is based on the fire/explosion EAL: 14.1:

declares a NOTIFICATION OF UNUSUAL EVENT (A or B) classification. A. (1 and 2)

Fire within the plant, indicated by:

1. Activation of fire brigade by Shift Supervisor.

and

2. Duration of fire longer than 15 minutes after time of notification.

or B. (1 and 2 )

Actions initiated include; Notification of the off-site agencies.

1641 Controller Messa e- The fire bri ade re orts status to The FBL re orts that several corn ressed as tanks sittin on the Ioadin IS-121 the Control Room. dock are relievin throu h their ru ture discs. It is unknown what the com ressed as c linders contain but it does not a ear to be flammable.

The Fire Bri ade Leader re orts that the fiire is contained and under control.

1645 Controller Messa e - Chemistry Tech in chem lab The report is to simulate the intake of smoke from the fire scene into the IS-13R calls Control Room to report very strong fire smell and Turbine Building ventilation intake.

a smoky haze.

1650 Controller Messa e - Simulated worker on Turbine The report is to simulate the intake of smoke from the fire scene into the IS-148 Deck calls Control Room to report very strong fire Turbine Building ventilation intake.

smell and a smoky haze.

1655 The Control Room Communicator completes The communicator has provided all the required information to the offsite (E.1, E.2, E.3, notifications to the off-site agencies for the NOUE agencies so that they will be able to take actions as required by their J.1) classification. emergency plans.

1655 Controller Messa e - The fire brigade reports status to The Fire Brigade Leader reports that two of the compressed gas tanks sitting IS-154 the Control Room. on the loading dock are Freon. The Fire Protection Engineer on scene reports that Freon and high temperatures can produce phosgene gas which can be lethal. It also appears that smoke is being drawn into the Turbine Building Intake.

The Fire Brigade Leader reports that the fire is contained and under controf, the S&A Sprinkler system is cooling the compressed gas cylinders.

V-11 10/28/97 NRC Exercise Manual

APPX TIME OF DAY INITIATINGEVENT EXPECTED SEQUENCE OF. EVENT. g, 1700 Shift Supervisor reviews information received and The classification is based on the fire/explosion and or Toxic/Flammable declares an ALERT classification. Gases EAL.

Fire I4.2 (A or B)

A. (1and2and3)

1. Fire lasting more than 15 minutes after notification.

and

2. Fire is in the vicinity of equipment required for safe shutdown.

and

3. Fire is damaging or is threatening to damage equipment due to heat, smoke, fiame, or other hazard.

OI'.

(1 and 2)

Explosion damage to facility affecting plant operation, determined by:

1. Direct observation or notification received by Control Room operator.

and

.2. Shift Supervisor evaluation.

TOXtC/FLAMMABLEGASES EAL ¹19.2 Entry of toxic or flammable gases into the facility, with subsequent habitability problem indicated by, Visual observation, direct measurement, or notification received by the Control Room operator.

Actions initiated based on classification level: Call out of NERO, local area evacuation of D/G building, S&A Buildin'g and Turbine Building, Accountability, and investigation of event. A check will be made of the generator building and the SBA building to ensure that there is no

'D'iesel collateral damage as a result of the fire.

1705 Controller Messa e - The lead controller will prompt The scenario must support the time line agreed upon with the State and the SS to classify the situation as an ALERT if not FEMA. If the ALERT classification is not declared by 1700 the SS will be done by this time. prompted to make the classification.

The prompt will be noted on the evaluation sheet for the critique process.

APP E 0 INITIATINGEVENT NT 1705 Security will be notified by the Control Room The activation of the Telenotifiication System by the Security Controller in the (E.1, E.2, E.3, Communicator to initiate call out of the NERO. ASCC will begin the activation process of the PP&L NERO. The TSC, EOF, J.1) and MOC will report to their respective duty stations as assigned.

1705 Shift Supervisor directs CREOASS placed in service The Shift Supervisor recognizes the potential of drawing smoke and gases into the Control Structure.

1705 Shift Supervisor directs shut down of Turbine. Building The Shift Supervisor recognizes the potential of drawing additional smoke HVAC. and gases into the Turbine Building.

1710 Controller Messa e - i&BC Control Cell calls Control The Plant Control Operator places the SI on hold and informs the Shift IS-176 Room to initiate Step XX of Sl-158-303XXX4XX4X Supervisor of the IBC request.

1715 Shift Supervisor gives directions for I&BC to secure The Shift Supervisor recognizes the impact of performing the IBC Sl at this conduct of Sl-1 58-303XXX4XYAK. time and places the Sl on hold.

1715 Controller Messa e - The fire brigade reports status to The Fire Brigade Leader reports that the fire is out. IS-187-the Control Room.

Fire Brigade Leader requests permission to isolate DPS-001 (close OS&Y) will cause trouble alarm from OC707 trbl pnt X234 Z2 (AR-SP403). 'hich Fire Brigade Leader to report that a check for fire extension will be initiated for the S&A and D/G Building, a fire watch is being set and the fire pump can be shut down when the OS&Y is shut.

1715 The Control Room Communicator completes The communicator has provided all the required information to the offsite (E.1, E.2, E.3, notifications to the off-site agencies for the ALERT agencies so that they will be able to take actions as required by their J.1) classification. emergency plans.

1715 Shift Supervisor requests Safety to check habitability Safety will recommend to the Shift Supervisor that Turbine Ventilation be of the Turbine Building. started to help clear out the building. Safety will check habitability of the Turbine and the S&A Buildings.

1730 Controller Messa e - The fire brigade reports status to The Fire Brigade Leader reports that check of S&A, D/G building complete for IS-198 the Control Room. fire extension.

1730 Responders arrive at the OSC/TSC and begin The OSC and the TSC begin to set up their respective facilities and muster (A.1, A.3, A.4, turnover process. the people arriving for accountability reporting. The designated OSC B.7, B.8, B.9) Coordinator is briefed by the Control Room and in turn briefs the OSC responders. The TSC people start to check communication links, start up equipment, and determine plant status in preparation for turnover.

Plant conditions at this point in time are Both units at 100% power, Fire Brigade closing out S&A fire, V-13 10/28/97 NRC Exercise Manual

APPX TIME OF DAY INITIATINGEVENT EXPECTED SEQUENCE OF, EVENT 1730 Controller Messa e - Security reports results of site Security compiles the information required for the accountability and takes IS-accountability to the Operations Shift Supervisor. required action for any missing individuals. Review with the Security 1209 Controller the complications arising due to fire brigade activation and the simulation of same.

1730 Controller Messa e - When the accountability has been The Emergency Director will release everyone from their accountability stations. IS-210 completed prompt the Emergency Director to release the people from their accountability stations.

1730 Site based individuals begin reporting to EOF and start The site based EOF responders will contact their counterparts in the TSC and set up of facility. be updated on the plant status, actions in progress, and support required.

These individuals will update the status boards and will provide updated information to the responding managers when they begin to arrive.

1800 TSC takes control of emergency. The TSC Emergency Director completes briefing the respective Coordinators, receives updates, and announces the TSC has management responsibility of the event. The information that the TSC is in control is passed over the plant page.

The focus of the TSC is to determine the extent of damage resulting from the fire at the S8A building.

10/28/97 NRC Exercise Manual 0

APP E 0 INITIATINGEVENT EXPECTED SEQUENCE OF- EVENT 1805 Controller Messa e - Simulator instructor to initiate The first indication in the Control Room will be a half scram. The half scram IS-2+.

(I.1, I.2) %ANXXXXW is a result of IBC restoring from the SI-XXX-XX-XX.

1C609 F18A OUT) blown fuse, and (IMF RR179003 (trigger 0 0) 100 5:00 0) fuel damage, and Stuck Shortly after the half scram is received, a fuse in the RPS power supply to the Control Rod 22-35 (IMF XXXXXXX)with LPRII high scram solenoid valves blows causing a quarter scram and subsequent full alarms NM17816B2433 100, and (IMF MC143001 scram signal.

SCFM), and (IMF XXXXXXXXXX) condenser air The 1/4 scram caused a hydraulic lock of the Scram Discharge Volume lnleakage, and ramp of the Containment radiation preventing a portion of the control rods to insert at the time of the full scram monitors such that they will exceed 2000 rR/hr at signal which causes fuel damage.

1930(EPLAN95IPEPC).

The fuel damage is manifested by high radiation in the main steam lines and The file will initiate indication of a partial scram. This closure of the MSIVs.

event will cause fuel damage and be the trigger for a SITE AREA EMERGENCY classification based on The loss of Reactivity Control will coincide with an ALERT classification, the EAL 3.3 Fuel Clad failure. fuel damage will trigger a Site Area Emergency based on containment radiation levels exceeding 400 Rlhr.

The reactor pressure will increase due to the plant being at power and the MSIVs closed which will result The immediate operator action will be to initiate Standby Liquid Control to in SRVs discharging to the suppression pool. The shut down the reactor and the ES procedure to drain the Scram discharge suppression pool pressure will increase due to the volume and rescram the plant.

non condensables and periodically relieve back to the Drywell. The leak back will cause alarm annunciation The operators will pay close attention to the Main Steam Line Radiation for the Drywell vacuum breakers. Monitors, the vent stack monitors, Area Radiation Monitors (ARMs), and room temperatures to determine the severity and spread of activity.

1805 Controller Messa e - The OSCAR Monitoring team The OSCAR Monitoring team will receive direction from the TSC HPQSCAR IS-23R (A.1, A.3, A.4, will be dispatched from the TSC if not already Radioman B.7, B.8, B.9) dispatched.

1815 Controller Messa e - Simulator instructor to initiate When the Drywell/Suppression Pool vacuum breakers lift the increased IS-248 FILE EPLANXXXXXto simulate the suction relief on pressure will lift the suction relief. The lifting relief valve will cause an the 'B'r 'D'HR pump lifting and failing to reseat. increase in the Reactor Building vent monitor.

When the Control Room personnel note the increased release rate from the Reactor Building Vent Monitor, they will place SBGT in service V-15 10/28/97 NRC Exercise Manual

APPX TIME OF DAY INITIATINGEVENT EXPECTED SEQUENCE OF EVENT;,"",,;..'.',".'.;,",:

1815 Allentown individuals begin reporting to EOF and The EOF responders will contact their counterparts irt the TSC and be updated complete set up of facility started by the initial on the plant status, actions in progress, and support required. The EOF staff responders. will update the status boards and will provide updated information to the responding managers and when they will be ready to take over the emergency responsibilities.

1820 Shift Supervisor will direct SBGT system to be placed in The release rate from the Reactor Building will change as a result of the swap of service. ventilation flow paths to SBGTS.

The Reactor Building radiation levels will increase due to the Unit 1 being placed in recirc.

1820 The TSC will classify the event as a SITE AREA The Emergency Director will classify (Containment Radiation level >400R/hr)

(D.1 D.2)

~ EMERGENCY. the emergency based on the EAL, Fuel Cladding degradation, which states:,

EAL ¹3.3 (A or B)

A. Reactor coolant activity greater than 1,000 uCi/cc of equivalent l-131 as determined by sample analysis..

OR B. Valid containment post accident monitor indication on panel 1C601 greater than 400 R/hr.

The Emergency Director will initiate upgrade notifications to offsite and internal, and initiate evacuation of non-essential personnel.

1820 Controller Messa e - There will NOT be an The Security Coordinator will be instructed to initiate a site evacuation. The IS-254 evacuation of any site personnel. The evacuation will Security Coordinator will acknowledge the request and after an appropriate be simulated. period of time will report the status of the evacuation.

1820 Controller Messa e - The Control Room will request The Chemistry Coordinator will respond to the sample request by initiating IS-265 (B.1, B.2, B.3, Chemistry to obtain a reactor coolant sample. setup of the Chem Lab and a briefing for the Chemists for obtaining a coolant B.5) sample.

1820 ~ Controller Messa e - The portal monitors and friskers The plume from the Reactor Building release is passing over the Unit 2 IS-276 (I.1, 1.2) at the South Gatehouse and at the Unit Two Access Turbine Buildin and the atehouse.

Control Point alarm.

Th'e portal monitors are sensitive enough that they will see the plume passage.

APP E 0 INITIATING 1825 Controller Messa e - The lead TSC controller will The scenario must support the time line agreed upon with the State and IS-2P prompt the TSC ED to classify the situation as a Site FEMA. If the Site Area Emergency classification is not declared by 1825 the Area Emergency if not done by this time. ED will be prompted to make the classification.

The prompt will be noted on the evaluation sheet for the critique process 1825 Conference call between the Recovery Manager, Discussion of plant status, what caused the emergency, actions being taken (F.1, F.2, E.2, Emergency Director, Engineering Support to minimize release or future releases, actions for recovery of the plant.

E.4, H.6) ~Su ervisorMeeeger, and Public Information Manager established. The conference call is in preparation for turnover of the emergency management responsibilities to the EOF.

1825 Controller Messa e - Simulator instructor to initiate The Control Room while following the containment control EOP will start RHR IS-298 FILE: XXXXXXrunout indication on the 'B'HRSW and RHRSW for Suppression Pool cooling. After the pump has been started for pump. a few minutes fluctuating current is observed. The high current is due to run out of the pump due to the broken discharge line.

This file is initiated when the Control Room operators place RHRSW in service to support suppression pool The Control Room will recognize that failure of the RHRSW pump leaves them cooling. with no decay heat removal which is covered by EAL ¹10 Loss of Decay Heat Removal Capability.

1830 Controller Messa e - Security reports a sink hole on Security calls the Control Room to report a hole has formed on the north side IS-the north side of the S&A Building. of the S&A Building and a large amount of water is flowing onto the roadway. 3020 Note that this message will be directed to be provided by the simulator instructor after the broken pipe indications are initiated.

1830 The Emergency Response organization will recognize The Reactor Building vent monitor is showing an increase due to the stuck open the increase in release rate from the Reactor Building relief valve on the RHR suction, discharging suppression pool water into the Ventilation, if SBGT not already initiated. RHR Room floor drains, and'into the Reactor Building sump.

To reduce the total release, SBGT will need to be placed in service if it hasn' already.

1830 Controller Messa e - The OSCAR monitoring team Data supplied to the monitoring team personnel will be consistent with the IS-310 (I.1, 1.2) will report the field data. actions taken.

1830(A.1, A.3, The EOF Staff takes control of the emergency. The EOF Staff takes over the radiological and notification responsibilities for the A.4, B.7, B.8, emerge'ncy.

B.9)

NOTE: The TSC is most likely in the midst of Notification for the Site Area Emergency and turnover will occur when the TSC has completed notification.

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APPX TIME OF DAY INITIATINGEVENT EXPECTED SEQUENCE OF. EVENT .

1835 The TSC Communicator completes upgrade The TSC communicator has informed the off-site agencies of the upgrade of (E.1, E.2, E.3, notifications to the off-site agencies for the SITE the emergency classification so that the agencies may respond as required J.1) AREA EMERGENCY classification. by their Emergency Plans.

1835 Controller Messa e -The Simulator instructor to The initiation of the file will cause all of the vent monitors on the refuel floor to IS-324.

Activate Malfunction File: "XXXXXXXXX" begin to show an increase. The increase is due to the background radiation masking the vent monitors.

The increase in effect causes an unmonitored release since what is leaving the Turbine Building Vent and the Standby Gas Vent is not monitored until vent sample monitors are taken.

The field readings will be increasing.

The indications shown will prompt discussions for a General Emergency classification.

1835 Controller Messa e - The Simulator Instructor to The vapor released from the Main Turbine Seals due to vacuum being broken IS-33R (I.1, I.2) initiate the Turbine Building Area Radiation Monitor will migrate into the Turbine Building ventilation, causing the building to go and SPING Files for data generation from the airborne.

simulator to the other emergency fycilities. '

The indication on the Turbine Building SPING will increase as a result of the Activate Malfunction File: "EPLAN95IPERAD" vapor in the main condenser leaking past the seals.

1840 Controller Messa e - TSC assembles and directs a The OSC Control Cell will provide the necessary data to indicate the IS-34 (K.1, K.2, K.3, damage control team to investigate and complete appropriate actions doses and times to complete the work at the RHR heat K.5, K.6, J.3, repairs to the 'A'HR heat exchanger. exchanger.

J.6) 1845 Controller Messa e - The portal monitors, friskers, A portion of the radioactive vapor released from the Main Turbine seals due IS-354 (I.1, I.2) and portable air samplers in the Turbine Building go to the loss of condenser vacuum will be recirculated by the Turbine Building into alarm. ventilation.

All the sensitive radiation monitoring instruments in Turbine Building and first floor of the Control Structure go into alarm. The Count Rooms in the Control Structure first floor are inoperable as a result of high back ground.

Multiple PCRs are reported by Health pPhysics.

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APP E 0 Nl IA IN EXPECTED SEQUENCE OF EVENT- - .-

1845 Controller Messa e - Control Room directs a NPO The OSC Control Cell will provide the necessary data to indicate the IS-3%

(K.1, K.2, K.3, and a HP Tech to investigate the increase ARM appropriate rad levels and plant conditions for the time of dispatch, if proper K.5, K.6, J.3, readings in the Turbine Building. investigation conducted. The report back to the Control Room will indicate J.6) increased radiation and airborne levels throughout the Turbine Building. The operator will report back to the Control Room the results of the investigation.

1845 Controller Messa e - Control Room directs a NPO to The OSC Control Cell will provide the necessary data to indicate the IS-376 (K.1, K.2, K.3, upper relay room to investigate the increase ARM appropriate rad levels and plant conditions for the time of dispatch, if proper K.5, K.6, J.3, readings in the Turbine Building. investigation conducted. The report back to the Control Room from the relay J.6) room will indicate increased radiation and airborne levels throughout the Turbine Building.

1845 Controller Messa e - Control Room directs a NPO The OSC Control Cell will provide the necessary data to indicate the IS-387-(K.1, K.2, K.3, and a HP Tech to investigate the increase ARM appropriate rad levels and plant conditions for the time of dispatch, if proper K.5, K.6, J.3, readings in the Reactor Building. investigation conducted. The report back to the Control Room will indicate J.6) increased radiation and airborne levels throughout the Reactor Building.

If the operator and the HP Tech go into the 'B'HR room, they will determine,

>~p/~ due to water flow noise, that the 'A'HR suction relief is lifting and discharging to the Reactor Building Sump.

The operator will report back to the Control Room the results of the investigation.

1915 Conference call between the Recovery Manager, Discussion of plant status, what caused the emergency, actions being taken

'su (F.1, F.2, E.2, E.4, H.6)

Emergency Director, Engineering Support ervisorMsssrisr, and Public Information Manager established.

to minimize release or future releases, actions for recovery of the plant.

1930 The Containment Radiation Monitors will indicate The high containment radiation level is the trigger to go to the General

~

. 2000'R/hr at this time. Emergency classification level.

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APPX TIME OF DAY INITIATINGEVENT EXPECTED SEQUENCE OF, EVENT, 1945 The EOF declares a GENERAL EMERGENCY and The Recovery Manager will classif'y the emergency based on the EAL, FUEL (D.1, D.2) begins consideration of Protective Action CLADDING DEGRADATIONat the General Emergency level, the FUEL Recommendations. DEGRADATION EAL states:

EAL 3b B. Valid containment post accident monitor indication on panel 1C601 (2C601) greater than 2000 R/hr.

and Containment high pressure indication or annunciation on panel 1C601.

The ED will initiate upgrade notifications to offsite and internal, review the radiological consequences of the emergency, and make a Protective Action Recommendation.

1950 Public Information Manager briefed as to extent of The Public Information Manager will need to have the required details for (F.1, F.2, E.2, events. preparation and distribution of information concerning,the events at the plant.

E.4, H.6) 1950 Controller Messa e - The lead controller will prompt The scenario must support the time line agreed upon with the State and IS-398 the Recovery Manager to classify the situation as a FEMA. If the General Emergency classification is not declared by 1950 the General Emergency if not done by this time. Recovery Manager will be prompted to make the classification.

The prompt will be noted on the evaluation sheet for the critique process.

1955 Licensee, State, and Federal agencies confer The radiological data received from the field will not support evacuation and (E.1, E.2, E.3, concerning Protective Action Recommendations to use of Kl for emergency workers.

J.1) the Governor.

. The expected recommendation to be made to the state is evacuate 0 to 2 miles and shelter 2 to 10 miles.

2000 The Recovery Manager will make a Protective Action The Recovery Manager will discuss with the radiological and technical staffs (J.7) Recommendation. in the EOF the conditions supporting a Protective Action Recommendation.

When the PAR decision process is completed, the Recovery Manager'will the recommendation to the EOC in Harrisburg. 'ommunicate 2000 The EOF Communicator completes upgrade The communicator has informed the offsite agencies of the upgrade of the (E.1 E.2, E.3,

~

notifications to the offsite agencies for the GENERAL emergency classification so that the agencies may respond as required by J.1) EMERGENCY classifiication. their Emergency Plans.

10/28/97 NRC Exercise Manual

APP E 0 INITIATINGEVENT . EXPECTED SEQVENCE OF EVENT ;

s 2005 Controller Messa e - The lead controller will prompt The scenario must support the time line agreed upon with the State and IS-the Recovery Manager to initiate a PAR if not done by FEMA. If the PAR is not declared by 2005 the Recovery Manager will be 4%8 this time. prompted to make the PAR.

The prompt will be noted on the evaluation sheet for the critique process 2005 . Conference call between the Recovery Manager, The conference call will cover the major events that have occurred to this (F.1, F.2, E.2, Emergency Director, Engineering Support point in the timeline and all issues should be identified with priorities set and E.4, H.6) ~gu ervisorManager, and Public tntormaUon Manager. action plans established and understood by the entire NERO.

The managers will discuss the status of the plant and the radiological conditions on- and off-site. They will discuss their short and long term goals and strategy.

2100 Controller Messa e - The PP&L Lead Controller and The State and PP8L review that the opportunity to demonstrate the applicable IS410 the State Lead Controller confer for termination time objectives has been provided and that all the participating agencies and of the exercise. groups have completed their required actions.

After conference a time will be set for termination of the exercise.

2200 Controller Messa e - The 1997 NRC Observed A page announcement is made in all the facilities by the Lead Controller that ISA'he Exercise is terminated. exercise is terminated.

All participants to collect emergency plan records and submit to them the facility lead Controller.

The Facility Lead Controller will conduct a debriefing in their area and collect the Controller Observation Sheets.

The Lead Controller to contact the phone company personnel at 3999 to restore the phone and page system to normal.

The Control Room Controller to restore the simulator radio system to normal training status.

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SECTION V - TIMELINE PART C - Basis of Timeline Events Section 1 - Fire Adjacent to D/G Building V-22 10/28/97 NRC Drill Exercise

BASls AND DETAILED DISCUSSlON FOR Fire Adjacent to D/G Building ALERT TRIGGER

SUMMARY

The ALERT classification should be made at approximately 1700.

The EAL for the classification will be ONSITE FIRE/EXPLOSION EAL 14.2, based on a fire adjacent to the 'D'iesel Generator Building lasting longer than 15 minutes. The ',

fire is in tractor trailer engine compartment escalating to engulf the cab of tractor.

Smoke from the fire will enter the Service & Administrative and Turbine Buildings which will result in a habitability concern and subsequent classification at the ALERT level.

This portion of the exercise is not to demonstrate onsite/offsite fire brigade response.

The offsite and onsite response will be simulated. 'A controller will accompany any operator dispatched to investigate the "fire" and a controller will accompany the OSC Coordinator/Fire Brigade Leader when the Fire Brigade is activated. This portion of the scenario is to trigger the ALERT classification.

DETAILED DESCRIPTION At 1625 a call will come into the Control Room from a simulated tractor trailer driver'.

saying that his rig, parked by the 'S8A Building has caught on fire in the engine compartment. Shortly after the call, the Control Room will receive fire alarms on the simplex panel indicating smoke and then activation of the drypipe fire protection system associated with the loading dock area of the SBA Building along with auto start of the fire pump.

The fire is postulated to engulf the cab of the tractor producing significant quantities of smoke and heat. Several compressed gas cylinders stored on the loading dock in close proximity to the fire will relieve on over pressure.

The chiller refrigerant which will decompose when exposed to heat to phosgene gas which is lethal. The Control Room will be informed of the hazardous gas that is involved with the fire. I Additional information will be received in the Control Room from an actor simulating a worker on the Turbine floor. The simulated worker will call the Control Room and report a heavy smell of smoke and a haze on the turbine deck. The information will be recognized in the Control Room as smoke from the fire being inducted into the Turbine Building. The information concerning the smoke in conjunction with the hazardous gas will cause a classification at an ALERT level.

V-23 10/28/97 NRC Drill Exercise

No on-site or off-site fire assistance will be active for this scenario. All fire fighting will be simulated. Information will be supplied to the Control Room via the Fire Brigade Leader who will receive information from a fire controller.

The fire will be reported out shortly after the classification is made. It is expected that the organization will investigate the possible extent of the fire and determine if any nearby. safety equipment might have been affected.

EXPECTED RESPONSE The Control Room Operators will dispatch an operator to investigate the area that was reported on. The'Shift Supervisor will dispatch the Fire Brigade. The Shift Supervisor will review the EALs to check what is required to make a classiTication. The Onsite Explosion/Fire EAL for an ALERT is as follows:

Onsite Explosion/Fire EAL I4.1 A. (1 and 2 and 3)

1. Fire lasting more than 15 minutes after notification.

and

2. Fire is in the vicinity of equipment required for safe shutdown.

and

3. Fire is damaging or is threatening to damage equipment due to heat, smoke, flame, or other hazard.

It is expected that the Shift Supervisor will classify the fire initially as a Notification of an Unusual Event level based on the fire will have lasted 15 minutes. When additional information is received by the Shift Supervisor showing the extent of the fire impact and the hazar'dous gas involved, a classification at the alert level will be made.

EVALUATIONPOINTS The conduct of the initial investigation and Fire Brigade Leader will be evaluated against procedures and policies for fire investigation and suppression by the on-scene controller. Additional points to consider will be the conduct of the Fire Brigade Leader when the ALERT classification is made for the accountability and activation of the OSC.

The Fire Brigade Leader is the OSC Coordinator and his absence from the OSC at time of declaration will cause some difficulties that the OSC organization will need to work through. How the OSC organization addresses the abserice of the OSC coordinator will be evaluated by the Lead OSC Controller.

V-24 10/28/97 NRC Drill Exercise

The evaluation of the classification decision making process will be the responsibility of the Lead Control Room Controller.

The potential impact to safety related equipment needs to be investigated to ensure problems from the fire do not extend into other areas such as the Diesel Generator Building.

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SECTION V - TIMELINE PART C - Basis of Timeline Events Section 2- RPS Quarter Scram and Fuel Damage V-26 10/28/97 NRC Drill Exercise

BASIS AND DETAILED DISCUSSION FOR RPS QUARTER SCRAM SAE TRIGGER

SUMMARY

The SITE AREA EMERGENCY classification is to be at approximately 1815.

N The EAL for the classification will be based on EAL 3.3 Fuel Clad degradation. The indications will be containment and Main Steam Line radiation levels.

Th i 2D'/, I dfil initially as the basis for the i radiological data.

There is no signiTicant radioactive release at this time of the scenario.

The plant transient is a partial failure to scram which precipitates fuel damage and the source term for the future release. The operators will be able to shutdown the reactor using alternate means but not until after the fuel damage has occurred. As part of the scenario a control rod will fail to completely insert and be found to be stuck when attempts are made to move it. This stuck control rod in conjunction with the failure to scram will cause the containment radiation levels to continually increase, requiring a' General Emergency Classification at approximately 1930.

DETAILED DESCRIPTION At 1805 the Simulator instructor will initiate a file which will cause a half scram to occur and shortly thereafter will cause a blown fuse in the RPS power supply to the Scram Solenoid valves.

The initial conditions and part of the shift turnover process'rovided information that l8C was performing a surveillance in the field which would cause half scrams and would require the operators to reset the RPS after the appropriate steps in the procedures. At this time in the scenario, an I8C control cell will call the Control Room and will state the step and inform the Control Room of an impending half scram. The Shift Supervisor will inform 18C to secure from the surveillance testing due to the fire situation. The scenario postulates that as I8C is restoring from the surveillance there is a half scram. Shortly after the half scram occurs, there is a blown fuse for the scram solenoid valves in the other RPS channel.

The result of the half scram on one RPS channel and a blown scram solenoid fuse on the other RPS channel is a quarter scram. One quarter of the control rods drive into the core. When the control rods drive into the core water is discharged into the Scram Discharge Volume (SDVj.

V-27 10/28/97 NRC Drill Exercise

When the quarter scram occurs reactor power decreases rapidly and sever flux peaks are caused which is the basis for the clad failure. A full scram signal is generated when the Scram Discharge Volume (SDV) High Level setpoint is reached, but because of the quarter scram, the SDV is full of water and a hydraulic lock exists preventing a full scram.

The fuel damage is manifested by high radiation in the containment and the main steam lines. The increased radiation in the main steam lines will initiate an automatic closure of the Main Steam Isolation Valves (MSIVs). The Main Steam Isolation Valve (MSIVs)

Closure will cut off the normal heat sink which is the Main Condenser.

The reactor pressure will increase due to the plant still being at power and the MSIVs closed. Reactor pressure will increase to the point of the Safety Relief Valve (SRV) setpoint. When the set pressure of the SRV's are reached they will open and discharge to the Suppression Pool as necessary to control reactor pressure.

The scenario causes one of the SRVs to stick open which will provide a path for to leak into the containment (suppression pool).

primary'oolant

. The containment response for the failure to scream, with the plant initially at approximately 12% power decreasing, with the MSIVs closed is:

~ SRVs discharging to the suppression pool

~ Suppression Pool pressure will increase due to the non condensables which will vent back to the Drywell

~ Suppression Pool Temperature will increase

~ Containment radiation levels will increase

~ Containment noble gas, Iodine, and particulate levels will increase Two release paths are initiated at this point in the scenario. One release path depicts typical leakage through the Main Steam Isolation Valves and the other leak path is from a RHR Suppression Pool Suction relief valve lifting and sticking open. The release paths are described in detail in the Radiological consequences section.

After the initial flurry of activity due to the failure to scram, the plant will be shutdown with fuel failure and two leak paths from the reactor vessel and no direct method of decay heat removal.

EXPECTED RESPONSE The Control Room operators will recognize immediately that there has been a failure to scram and the immediate operator action will be to initiate Standby Liquid Control to shut down the reactor and commence the ES procedure to drain the Scram Discharge Volume and rescram the plant.

V-28 10/28/97 NRC Drill Exercise

The operators will pay close attention to the main steam line radiation monitors, the vent stack monitors, area radiation monitors, and room temperatures to determine the severity and.spread of the source term.

The TSC will have taken over from the Control Room at this point in the scenario and will be responsible for classifications and Protective Action Recommendations (PARs).

The TSC Emergency Director will be provided with information from the Control Room and the TSC Staff and will classify the plant transient as a SITE AREA EMERGENCY.

The classification will be based on the EAL ¹3.3, Fuel Cladding degradation, which states:

(A or B)

A. Reactor coolant activity'greater than 1,000 uCi/cc of equivalent I-131 as determined by sample analysis. ~

OR B. Valid containment post accident monitor indication on panel 1C601 greater than 400 R/hr.

The Emergency Director will initiate upgrade notifications to offsite agencies and the NERO, and initiate evacuation of non-essential personnel ~

When the operators attempt to'place 'B'HRSW in service for Suppression Pool Cooling, the RHRSW pump will indicate a run-out condition. The run-out condition is due to a broken pipe in the SW pump discharge rendering the system inoperable.

With the 'B'HRSW loop inoperable and the 'A'oop out of service for maintenance there is no decay heat removal available for the containment. The normal heat sink of the condenser is isolated due to high radiation in the steam lines leaving no decay heat removal capability.

With no decay heat removal available, one of the main priorities of the TSC will be to restore the 'A'oop of RHR SW for decay heat removal The TSC Staff will need to set

~

aside the resources to perform the required restoration prior to the evacuation of the non-essential personnel. In addition the TSC will need to plan the work based on changing radiological conditions which may require dose extensions.

Another expected action at this time will be to place the Standby Gas Treatment System (SBGT) in service. As mentioned previously, the relief valve on the RHR

~

suction is stuck open. The relief is discharging suppression pool water to the Reactor Building ventilation via the Reactor Building sump which will cause an indicated increase of activity from the Reactor Building vent monitor. The increased release rate will prompt placing SBGT in service.

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EVALUATIONPOINTS The evaluation of the classification decision making process will be the responsibility of the TSC Lead Controller.

The TSC staff should recognize the type of fuel damage, the mechanism which caused the fuel damage, the potential leak paths and the threats to the barriers, specifically the primary containment with no decay heat removal available.

The TSC Staff will be looking to turnover management of the emergency to the EOF which at this time is beginning the activation process.

The TSC Health Physics function will be characterizing the source term and the potential effects offsite.

V-30 10/28/97 NRC Drill Exercise

.SECTION V - TIMELINE PART C - Basis of Timeline Events Section 3 - Fuel Damage and General Emergency Trigger V-31 10/28/97 NRC Drill Exercise

BASIS AND DETAILED DISCUSSION FOR FUEL DAMAGE GENERAL EMERGENCY TRIGGER

SUMMARY

The GENERAL EMERGENCY classification is to be at approximately 1930.

The EAL for the classification will be based on EAL 3.4 Fuel Clad degradation. The indications will be containment radiation levels in conjunction with field team readings,.

threat of loss of primary containment, and increased radiation levels in the Turbine and Building. 'eactor The scenario uses a 204% clad failure initially as the basis for the radiological data with l an increasing containment radiation level depicting core problems due to the stuck control rod.

The control rod which had failed to completely insert and was found to be stuck when attempts are made to move it is the source off the containment radiation level increase and the resultant trigger for a General Emergency Classification.

The radioactive releases from the Reactor Building and the Turbine Building will provide an increasing trend. The increasing release trend indicates a degradation of the fuel, primary coolant, and primary containment barriers. With a degradation of all the barriers and the start of an unmonitored release the organization will be monitoring the containment radiation levels very closely to. determine if a General Emergency classiTication is warranted. When containment radiation continues to increase to the 2000 R/Hr level the General Emergency classification will be declared.

The EOF staff will have responsibility for management of the emergency at this time and will be responsible to make the GENERAL EMERGENCY classification and the Protective Action Recommendation (PAR).

DETAILED DESCRIPTION The final portion of the scenario is the manifestation of the leakage which began earlier.

I TURBINE BUILDING The leakage through the MSIVs to the main condenser did not show until later in the scenario because there was still condenser vacuum. The loss of condenser vacuum is a result of the MSIV closure and resultant loss of steam jet air ejector motive steam:

With a total loss of the condenser vacuum the radioactive gases that have leaked through the MSIVs will now leak out of the turbine seals and into the Turbine Building V-32 10/28/97 NRC Drill Exercise

atmosphere. A small portion of the radioactive gas will be recirculated in the Turbine Building and a portion will be discharged out the Turbine Building vent.

The radioactive gases that are recirculated will cause an increase of the general area dose rates. The Turbine Building Area Radiation Monitors (ARMs) will increase, and the CAMs, friskers, and portal monitors will increase to the alarm points.

The Chemistry count lab will show an increased background due to the recirculation of the Turbine Building atmosphere into the chem Iab.

The only mechanism to reduce the leakage through the MSIVs is to reduce the ~

pressure difference across the valves which will require the plant to'be depressurized with no mechanism to remove the heat from the Suppression Pool.

REACTOR BUILDING The source of the increased radiation into the Reactor. Building is the RHR suction relief that has lifted and is stuck open. The relief valve is discharging Suppression Pool water into the floor drains which is dumped into the Reactor Building Sump which pumps over to the LRW collection system.

The Reactor Building Sump is vented directly to the Reactor Building Ventilation System so all the noble gases which are being carried into the sump from the stuck open relief valve. are vented to the HVAC and discharged to the environment. When it is noted that the Reactor Building vent monitor is increasing, the Control Room will place the Standby Gas Treatment system into recirculation as outlined in the procedures.

When the Reactor Building atmosphere is placed in recirc, -the release rate to the environment will be decreased but the Reactor Building General Area radiation levels will increase.

As the Reactor Building radiation levels increase the SPING monitors located on the refuel floor will see an increased background level and display an increasing release rate from ALL the vents. The vent monitors for the Unit 1 8 2 Turbine and Reactor Buildings will show an increase, as will the SBGT vent monitor.

The organization will have an opportunity to mitigate the'elease from the reactor building and possibly prevent an unmonitored release. The organization will have the opportunity to assess the indications, determine the source of the RB leakage, walk down the Reactor Building, find the RHR room where the stuck open relief valve is located and mitigate the release.

V-33 10/28/97 NRC Drill Exercise

Containment The containment response for the failure to scram, with the plant initially at approximately 12% power decreasing, with the MSIVs closed is:

~ SRVs discharging to the suppression pool

~ Suppression Pool pressure will increase due to the non condensables which will vent back to the Drywell

~ Suppression Pool Temperature will increase

~ Containment radiation levels will increase Containment noble gas, Iodine and particulate levels will increase All the above mentioned parameters indicate a threat to the primary containment. The crucial point to include with the above information is the inability to remove decay heat from the Suppression Pool. The consequences of the RHRSW line break and the initial conditions having the 'A'HRSW Heat exchanger out of service result in no mechanism to remove decay heat from the Suppression Pool. No decay heat, removal for the suppression pool indicates another threat to the primary containment.

Conclusion After the initial transient due to the failure to scram, the plant will be shutdown, there will be indicated fuel damage, two leak paths from the reactor vessel, and no direct method of decay heat removal ~

EXPECTED RESPONSE The NERO should recognize that there are indications that all of the barriers are degraded based on field team data indicating radiation readings in the field. The organization will recognize the difference between a General Emergency classification and a Site Area Emergency classification is based on the amount of fuel damage. The only indication that the organization has at this time of amount of fuel damage is the containment radiation monitors.

It is expected that the NERO will be monitoring the containment rad monitors closely.

Any change noted by the NERO will prompt a revaluation of the amount of fuel damage and the classification.

The major threat that can change the amount of fuel damage is the decay heat removal capability. The organization will be focusing on returning a loop of decay heat removal to eliminate this threat.

The EOF will be in charge of mangemaent of the emergency at this time and will be )

responsible for classification and PARs.

V-34 10/28/97 NRC Drill Exercise

The trigger for the General Emergency classification will be the containment radiation monitors which will show an increase and require an upgrade of the emergency level.

The upgrade will be based on EAL 0 3.4 FUEL CLADDING DEGRADATION EAL03.4A (A or 8)

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

'A. (1 and 2) Valid containment post accident monitor indication on panel 1C601 (2C601) greater than 400 R/hr.

'nd

2. (aorborc)

a. Containment pressure greater than 40.4 PSIG, indicated on panel 1C601 (2C601).

or

b. A visual inspection of the containment indicates a potential for loss of containment (e.g. a crack in containment concrete at tendon and anchorage or pehetration failure).

or

c. Other indications of potential or actual loss of primary containment.

OR B. (1 and 2)

J

1. Reactor Coolant activity greater than 1000 uCilcc of equivalent I-131 as determined by sample analysis.

and

2. Actual or potential failure of Reactor coolant isolation valves to isolate a coolant.

leak outside containment as determined by valve position indication on panel 1C601 (2C601) or visual inspection.

V-35 10/28/97 NRC Drill Exercise

EAL3 3.4b (A and B)

Core melt indicated by:

A. Valid containment post accident monitor indication on panel 1C601 greater than 2000 R/hr.

AND B. Containment high pressure indication or annunciation on panel 1C601.

The Recovery Manager will initiate upgrade notifications to. offsite and internal, and initiate the PAR decision process.

Based on the information available the PAR will. be to evauate 0 to 2 miles and shelter from 2 to 10 miles.

EVALUATIONPOINTS The evaluation of the classification and PAR decision making process will be the responsibility of the EOF Lead Controller.

The EOF staff should recognize the type of fuel damage, the mechanism which caused the fuel damage, the potential leak paths, and the threats to the barriers, specifically the primary containment with no decay heat removal mechanism.

The TSC and EOF Health Physics function will be characterizing the source term and the potential effects offsite.

Restoration of the RHR SW for decay heat removal will be a top priority.

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SECTION V - TIMELINE PART C - Basis of Timeline Events Section 4 - Radiological Conditions V-37, 10/28/97 NRC Drill Exercise

BASIS AND DETAILED DISCUSSION FOR RADIOLOGICALCONDITIONS GENERAL Tt ditv I i~ i b d pp i tly20% I dfil drive dose rates of approximately 20 mr/hr at 2 miles to the south of the plant for the State field teams. There is to be slight indications of Iodine for the field teams.

Field radiological conditions and release rates will not drive the General Emergency classification. The General Emergency classification will be driven by plant conditions with the resultant PAR based on plant conditions in conjunction with field team monitoring data.

The organization will have a success path available to mitigate the Reactor Building release if the proper investigation, assessment and mitigating actions are pursued.

WEATHER The direction of plume travel will be toward the south southwesteast-. The weather l conditions used for this exercise will be based on actual weather conditions which occurred on July 10, 1997. The deposition and the airborne activity levels will be variable depending on the actions taken by the TSC to investigate and mitigate the release. Since the release will be going toward the south, there will be portal alarms at the South Gatehouse indicated at the appropriate time in the scenario.

SOURCE TERM The source term for the accident is approximately 420% clad failure at the onset of the (

Site Area Emergency. The fuel damage will be indicated by an increased containment rad level, and increased area radiation monitor readings in areas such as the CRD HCU, RCIC, and the HPCI room.

The initial transient which is the basis for the fuel damage is an over-power condition which is postulated to cause'ellet clad interaction and a noble gas and iodine release.

The release of the noble gases cause the containment radiation monitors to increase to approximately 400 R/hr and the Main Steam Isolation Valves to close on high radiation.

The plant scenario is a failure to completely scram which causes fuel damage and an isolation of the MSIVs which means Reactor Pressure will increase to the point of opening Safety Relief Valves (SRVs). The SRVs discharge reactor vessel steam/noble gases to the Suppression Pool. During the early portion of the scenario, the SRVs are discharging at a rate of approximately 12% power which equates to 2.0E06 LBM/HR.

The SRVs are used continually there-after, for reactor pressure/temperature control. It V-38 10/28/97 NRC Drill Exercise

is assumed that approximately 250,000 LBM/HR are discharged for the remainder of the scenario.

Toward the later part of the exercise it will become obvious that containment radiation levels have been continually increasing. The fuel damage is attributed to one of the fuel bundles in the four bundle array associated with the Control Rod which did not insert completely at the time of the plant scram. The continual increase of the radiation monitor will eventually be the trigger for a General Emergency classification.

RELEASE PATHS The exercise has two different release paths for the participants to evaluate:

T~ti B ilCh -Th I kp thi f tt t I,d th into the main condenser. The radioactive gases will leak out of the main condenser when vacuum is lost. The leak rate through the MSIVs used for data generation is approximately 35 SCFM.

As found LLRT data is used as the basis for leakage through the Main Steam Isolation Valves to the Main Condenser. The gases which collect in the main condenser and are released to the Turbine Building as condenser vacuum is lost are mostly noble gases.

The Turbine Building flow path is not a treated flowpath but is monitored for a period of time. As the scenario progresses, the release from the Turbine Building will become unmonitored as high background radiation at the vent monitor detectors marks the vent readings.

Reactor Buildin /SBGTs - A ten gallon per minute leak of. Suppression Pool water into the Reactor Building is assumed to be ongoing unless investigated and mitigated by the organization.

The Suppression Pool water that is discharged into the Reactor Building has a significant amount of radioactivity. The high activity is due to continual blowdown of reactor steam from the reactor vessel to the Suppression Pool via a stuck open relief valve.

The leak of suppression pool water will end up in the Reactor Building sump which will be pumped to the Rad Waste Building. For Scenario development, it is assumed that most of the noble gases contained in the suppression pool water leaked into the Reactor Building are released to the Reactor Building ventilation.

V-39 10/28/97 NRC Drill Exercise

REACTOR BUILDING The source of the increased radiation into the Reactor Building is the RHR suction relief that has lifted as suppression pool temperature and pressure increased. The relief valve will remain stuck open for the duration of the exercise. The water discharged from the relief valve is Ssuppression Pool water flowing into the floor drains. The floor )

drains end up in the Reactor Building Sump which pumps over to the LRW collection system.

The Reactor Building Sump is vented directly to the Reactor Building Ventilation System so all the noble gases which are being carried into the sump from the stuck relief valve are vented to the HVAC and discharged to the environment. When it 'pen is noted that the Reactor Building vent monitor is increasing the Control Room will place the Standby Gas Treatment system into recirculation as outlined in the procedures.

The normal lineu for the floor drains in the RHR room is isolated. The RHR floor drains are normall isolated based on floodin anal sis. To su ort the Reactor Buildin release from the RHR Suction Relief Valve the floor drains from the room to the Reactor Buildin sum need to be o en. The initial conditions have an ent which states the 'B'HR room drains are eriodicall bein o ened due to an RHR SW leak.

Ri ht before the start of the fire outside the SBA Buildin a messa e will be in'ected to the control room that an o erator is o enin the floor drains in the 'B'HR room for the eriodic drainin of the RHR SW leak. The RHR room drain isolation will remain o en due the confusion caused b the fire activation of the fire bri ade and subse uent ALERT classification.

At the time that the Reactor Building atmosphere is placed in recirc, the release rate to

. the environment will be decreased, but the Reactor Building general area radiation levels will increase.

As the Reactor Building radiation levels increase, the SPING vent monitors located on the refuel floor will see an increased background level and display an increasing release rate from ALL the vents. The vent monitors for the Unit 1 8 2 Turbine and Reactor Buildings will show an increase as will the SBGT vent monitor.

The organization will have an opportunity to mitigate the release from the reactor building and prevent an unmonitored release. The organization will need to initiate an investigation to determine the source of the leakage and walk down the Reactor Building, find the RHR room where the stuck open relief valve is located, and initiate mitigating actions.

See the attached for a schematic diagram representing the possible releases based on the actions of the organization..

0 V-40 10/28/97 NRC Drill Exercise

e 1997 Annual Exercise RadiologIcal Release Model for Reactor Building Release Reactor Gap Activity (1% at B:15 PM)

'eactor Coolant System (peak gross activity 1.23e+

uCVml) 250000 Ibm/hr Suppression Pool (peak gross activity 1.35e+

uCVrnl) yes Relief Valve lsolsted2 no Reactor Bulldlng Sump Reactor Building Sump (valve dosed -1 gpm leak (valve open - 10 gpm leak from Suppression Pool) from Suppression Pool) 0 no Use Standby Gas2 yes Recirculation, alrbome Exhaust, no airborne actlvty In Reactor activity In Reactor Bulldlng. Masks vent Building monitors.

Atmosphere Ground Deposition (uCI/hP) (uCI/hF)

L V-41 10/28/97 NRC Drill Exercise

TURBINE BUILDING The leakage through the MSIVs to the main condenser is delayed until condenser vacuum decays. The loss of condenser vacuum is a result of the MSIV closure and the resultant loss of steam jet air ejector motive steam.

With a total loss of the condenser vacuum the radioactive gases that have leaked through the MSIVs will now leak out of the turbine seals and into the Turbine Building atmosphere. A small portion of the radioactive gas will be recirculated in the Turbine Building and eventually discharged out the Turbine Building vent.

The radioactive gases that are recirculated will cause an increase of the general area dose rates. The Turbine Building Area Radiation Monitors (ARMs) will increase, and the CAMs, friskers, and portal monitors will increase to the alarm points.

The Chemistry count lab will show an increased background due to the recirculation of the Turbine Building atmosphere into the chem lab.

The only mechanism to reduce the leakage through the MSIVs is to reduce the pressure difference across the valves which will require the plant to be depressurized.

The depressurization of the plant will depend on the restoration of a decay heat removal mechanism for the suppression pool.

TEAMS

'IELD The Field Monitoring Teams will have an opportunity to see an increase of activity as the releases from the plant increase. The OSCAR monitoring team will be on station first and be able to provide trending to the TSC.

The field teams, if properly located, will be able to monitor cloud shine, some iodine among the noble gas, decay particulates, and minor amounts of ground contamination due to the decay of the noble gases.

The direction of the plume travel will cause a challenging scenario for the Field Team Director. The Field Team Director will need to get the teams in position as soon as possible and continually deal with the teams having to criss-cross the river to locate the plume.

Field team data will be critical to understand the magnitude of the release if the'ent monitors become masked due to high background on the Refuel floor.

The dose projections should reflect the change in plant conditions indicated by the increased radiation readings in the containment. The protective action recommendation will be made on plant conditions and supported by the dose projections.

V-42 10/28/97 NRC Drill Exercise

See the attached for a schematic diagram representing the Turbine Building releases.

V-43 10/28/97 NRC Drill Exercise

1997 Annual Exercise Radiological Release Model Reactor Gap Activity Turbine Building Release (14k at 6.'15 PM)

Reactor Coolant System Matri Steam Lines Condenser (from leak from steam lines Turbine Building (from leaking Turbine Generator seals)

Turbine Building Exhaust System (Vent)

(150,000 scfm)

Atmosphere (uCI/M')

I I

I I

Ground Deposition (uCIIM')

V-44 10/28/97 NRC Drill Exercise

SECTION Vl - INITIALCONDITIONS PART A -.DAILYREPORT VI-1 10/28/97 NRC Exercise Manual

PPSL INDEPENDENT SAFETY 'EVALUATIONSERVICES SUSQUEHANNA STEAM ELECTRIC STATION DAILYREPORT DATE: 10/28/97 Report Period: 0800 hr. 10/27/97 to 0800 hr. 10/28/97 Unit 1 Plant Parameters:

Plant Condition-1 Power-100% Megawatts Gross-1148 Total Core Flow - 104.3 Million Ibs/hr Reactor Water Conductivity - 0.11 pmho/cm Reactor Water Sulfates -4.2 ppb HP Condenser Backpressure -3.1 inches Hga Offgas Pretreatment Rate - 192 pCi/sec Flow - 25 scfm Number of- Control Room Alarms Lit - 8 Days on Line.- 134 Unit 2 Plant Parameters:

Plant Condition -1 Power-100% Megawatts Gross-1144 Total Core Flow - 98.5 Million Ibs/hr Reactor Water Conductivity - 0.11 pmho/cm Reactor Water Sulfates - 5.1 ppb HP Condenser Backpressure-2.9 inches Hga Offgas Pretreatment Rate - 111 pCi/sec Flow - 18 scfm Number of Control Room Alarms Lit - 7 Days on Line -80 Unit Common Plant Parameters:

Number of Control Room Alarms Lit - 8 lma or Work in Pro ress/Com leted and Problems - Unit 1:

1. Two momentary Reactor water level spikes were experienced yesterday, one at 1635 and one at 2325. GETARS was manually initiated on both occasions. No operator actions were required since the plant responded quickly and level was restored to 35" within 5 seconds. No other anomalies were observed.

(SS log, Unit log, CR 97-2471, CR 97-2474)

VI-2 10/28/97 NRC Exercise Manual

Ma or Work in Pro ress/Com leted and Problems - Unit1 cont.:

At 0839, an out of service annunciator came in for the RCIC system. A failed alarm relay was identified as the cause. The RCIC system was inoperable during the period when repairs were being made. Following replacement of the alarm relay, the RCIC system was restored to operability. The LCO was cleared at 1655.

(SS log, Unit log, LCO log, CR 97-2462)

The Reactor Building SPING remains out of service for l&C and Chemistry calibrations. The LCO has been in effect since Monday (10/27/97) at 0910.

(LCO log, Priority List)

The 'A'HRSW on-line work window continues. The LCO has been in effect since Monday (10/27/97) at 0700. (LCO log, Priority List)

5. System Engineering is continuing to pursue resolution to the Service Air/

Instrument Air cross-tie pressure control issue. (0730 mtg.)

Ma or Work in Pro ress/Com leted and Problems - Unit 2:

The Common Offgas recombiner remains in service. Investigation/troubleshooting of the Unit 2 Offgas recombiner problem is in progress around-the-clock.

(0730 mtg.)

At 1014 the Control Room received the REACTOR WATER LEVEL HIGH/LOW LEVEL TRIP alarm. TRA was manually tripped to capture the event. Reactor water level returned to normal without any operator action.

(SS log, Unit log, CR 97-2465)

3. The 'A'eactor Water Cleanup filter demineralizer was removed from service at 1443 for backwashing and precoating activities. The demin was returned to service at 1642 the same day. (Unit'log)

The 'C'ondensate Demineralizer vessel was removed from service for cleaning at 2318. Reactor water sulfates have started to trend downward (currently at 5.1 ppb down from 6.4 ppb yesterday). (0730 mtg., Unit log)

At 2350,LPRM 16-17B was bypassed due to drifting tow. The minimum number of inputs to the 'E'PRM have been maintained without this LPRM and therefore the APRM remains operable. (SS log, Unit log, CR 97-2475)

The RCIC on-line maintenance work continues. On Wednesday, the turbine failed to trip on mechanical overspeed on its third overspeed test after successfully tripping on the first two tests. Another mechanical overspeed test is scheduled for today. (0730 mtg, Unit log)

VI-3 10/28/97 NRC Exercise Manual

Ma or Work in Pro ress/Com leted and Problems - Unit Common:

1. The 'E'iesel Generator remains substituted for the '8'hich is undergoing an 18 month overhaul. 'At 0515 this morning, the 'E'/G was started for a monthly

. operability run. At 1630 yesterday, the 'D'iesel LCO was cleared following jacket water heater replacement. The 'D'/G was run from 1703 until 1719 for a surveillance associated with the ECCS override of Test Mode.

(0730 mtg., Unit logs, LCO logs)

2. Spray Pond Cooling has been in effect. The Unit 2 8 RHRSW pump was placed in service at 0747 to support Unit 2 RCIC testing. (Unit logs)

3. At 0456, Unit 2 Zone III ventilation was removed from service for scheduled maintenance. Unit 1 HVAC is in service carrying all the load for Zone III.

(Unit log, Priority List)

4. The fourth River Water Makeup pump remains in service in support of Cooling Tower chemistry problems. (0730 mtg.)

5. Investigation of the inability to cross tie instrument air continues with a TP scheduled for 10/29/97. (0730 mtg.)

Short Term Schedule - Unit 1: 1. Continue Full Power Operation.

Short Term Schedule - Unit 2: 1. Continue Full Power Operation.

ISES Management Attention: A two week NRC inspection commenced Monday.

This inspection is focusing on the details of our operation, maintenance, engineering and support activities.

All of the Condition Reports presented at the Corrective Action Team meeting for the report period are included in the attached charts and tables.

Tom Ryder / Rick Dixson Written by Reviewed by Vl-4 10/28/97 NRC Exercise Manual

Priinary Coolant SUlfates Trend Note: These data are obtained from the Daily Chemistry Report.

0 ng ~ b 15 Sulfates In PPB 10 1997 Department Goal ~ c 4 ppb average

~Unit1

~Unit 2 24 25 '8 30 DATE VI-5 10/28/97 NRC Exercise Manual

Today's Condition Reports Significance Summary Numbers of CRs shown by Significance Level 16

'4'2 16 V 10 O

6 a 6 R 4 0, 0 Significance Level (Level 1 ls highest)

Today's Condition Reports Disposition (Workload) Summary 7,

6 4>>

i 3

2>>

p I

ERT RCA CD CC CL Event Root Cause Correct Close Review Cause Determination Condition at Team Analysis CAT VI-6 10/28/97 NRC Exercise Manual

Condition Reports Presented to CAT During the Report Period CR Unit Date Description Level rape*

97-2427 10/24/97 A VALIDSQRT BINDER DOES NOT EXIST FOR THE RHR INJECTION THROTTLE CD VALVES.THE ORIGINALVALVES WERE REPlACED AND THE SQRT BINDERS WERE NEVER REVISED.

97-2432 10/24/97 THE LOAD TABULATIONS IN CALCUlATIONEC417-0001 FOR INSTRUMENT AC VITAL CD UPS LIGHTING PANELS (2Y629 AND 1Y629) ARE BASED ON REVISION 6 TO DRAWING E-64 SH 19. CURRENT REVISION NUMBER OF THE DRAWING IS 26.

97-2434 10/23/97 THE REACTOR VESSEL LEVEUPRESSURE RECORDER (LR/PR 14201B) HAS AN INPUT CD VOLTAGE LESS THAN.THE MANUFACTURER'S RECOMMENDED MINIMUMOF 22 VDC.

THE PROBLEM WAS DISCOVERED DURING TROUBLE SHOOTING OF WHY THE CHART PAPER WAS NOT ADVANCING.

97-2403 10/22/97 SOME LDCNs WHICH SHOULD HAVE REQUIRED A SAFETY EVALUATIONTO BE CD WRITTEN WERE INCORPORATED INTO CHAPTER 9 OF THE FSAR WITHOUT A SAFETY EVALUATIONBEING WRITTEN.

97-2452 10/27/97 THE MYLARCONTAINED WITHIN THE UNIT 1 REACTOR BUILDINGSPING LOW RANGE CD NOBLE GAS DETECTOR AND THE PARTICULATE DETECTOR WAS FOUND DAMAGED.

97-2397 10/21/97 WORKERS OBSERVED NOT WEARING PROPER EYE PROTECTION, CONTRARY TO CD SIGN POSTED AT THE JOB SITE. THE ORIGINATOR DISCUSSED THIS WITH THE FOREMAN AT THE JOB SITE AS WELL AS WITH SITE SAFETY.

97-2451 10/27/97 TECHNICAL SPECIFICATION FIRE DOOR (E-10) WAS OPEN FOR GREATER THAN 1 CD HOUR WITHOUT POSTING OF THE REQUIRED FIRE PROTECTION FORMS. THE DOOR OPENING WAS MONITORED BY A QUALIFIED FIRE WATCH.

97-2435 0 10/24/97 A SPURIOUS C DIESEL GENERATOR FUEL OIL STORAGE TANK LOW LEVELAlARM CC WAS RECEIVED AND THEN IMMEDIATELYCLEARED.

97-2448 10/27/97 THE UNIT 182 FEEDWATER SYSTEMS WERE NOT BEING OPERATED IN ACCORDANCE CC WITH GENERAL OPERATING PROCEDURE FOR POWER OPERATION. THE PROCEDURE DIRECTS THAT THE LEVEL CONTROLLER TAPE SET BE SET AT 35 INCHES.

97-2429 10/24/97 THE TLD PROCESSING PROGRAM QUALITYMANUALCONFLICTS WITH THE NATIONAL CC VOLUNTARYLABORATORYACCREDITATION PROGRAM RELATIVETO ORGANIZATION OF THE TLD PROCESSING lABORATORYSTAFF. (AUDIT97428) 97-2399 10/21/97 LIFTING DEVICE ATTACHEDTO MANHOLEAT ESW VAULTHAS A BROKEN SAFETY CC lATCH AND THE SLINGS ARE NOT ATTACHED PER PROCEDURE PQSQ 12 REV 0.

97-2418 10/23/97 POST ACCIDENT VENT STACK MONITORINGAND SAMPLE LINE HEAT TRACE OUTPUT CC DOES NOT MEET THE DESIGN OF 1174 WATTS, THE PAVSS SYSTEM REMAINS OPERABLE.

97-2455 10/27/97 UNIT 1 EXPERIENCED A MOMENTARYREACTOR WATER LEVEL SPIKE TO 39 INCHES. CL THE DATAWAS ANALYZEDBY THE SYSTEM ENGINEER AND ATTRIBUTEDTO VESSEL RINGING PHENOMENA.

97-2440 0 10/26/97 THE ESW HEAT EXCHANGER OUTLET TEMPERATURE INDICATOR FROM THE 'E'/G CL (SUBSTITUTING FOR B) PEGGED UPSCALE FOR SOME UNKNOWN REASON. THE ESW SYSTEM WAS NOT INSERVICE AT THE TIME.-

VI-7 10/28/97 NRC Exercise Manual

Condition Reports Presented to CAT During the Report Period CR Unit Date Description Level TJ'pe*

97-2454 10/27/97 UNIT 2 RECEIVED A REACTOR VESSEL WATER LEVEL HIGH/LOWALARM. NO CL EVOLUTIONS WERE IN PROGRESS THAT WOULD HAVE AFFECTED WATER LEVEL REACTOR VESSEL WATER LEVEL RETURNED TO NORMALWITHOUTANY OPERATOR ACTION.

97-2437 10/25/97 THE UNIT 2 D APRM COULD NOT BE RESET FOLLOWING THE PERFORMANCE OF THE CL DAILYVERIFICATIONOF APRM SCRAM AND ROD BLOCK SETTING SURVEILLANCE.

INVESTIGATION BY IS C REVEALED FAULTYTERMINATIONAT J45 CONNECTOR.

TERMINATIONWAS REWORKED PER WA V72612.

97-2431 10/21/97 A TURBINE BUILDINGUNIT ¹2 SPING ALPHA DETECTOR CABLE WAS FOUND TO BE CL BROKEN OFF.

97-2430 10/22/97 CHEMISTRY WAS UNABLE TO OBTAIN A STABLE BACKGROUND COUNT RATE DURING CL THE TURBINE BUILDINGUNIT ¹2 SPING PARTICULATE CH. CALIBRATION.

'Abbreviations: CD - Cause Determination CC - Correct Condition CL - Closure RCA - Root Cause Analysis 10/28/97 NRC Exercise Manual

SECTION Vl - INITIALCONDITIONS PART B - OPERATOR TURNOVER SHEETS (Need alarm window log)

VI-9 10/28/97 NRC Exercise Manual

UNIT SUPERVISOR TURNOVER SHEET UNIT: Date: October z 1997 SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE MODE POWER LEVEL 100 POWER LEVEL GENERATOR OUTPUT 1148 MWe GENERATOR OUTPUT MWe REMARKS:

1. DW/SP vac bkr PSV-15704B1 alarm problem - Bypass (1-97-015) installed & PCAF to SO-100-006

2. "S" SRV Acoustic Monitor inop- Bypass applied -Tech Spec discretionary letter

3. SA/IA X-tie unreliable

4. "A" RHRSW loop o/s for planned maint.- LCO

5. RB SPING o/s- LCO 7.

8.

9.

10.

12.

13.

14.

COMMON:

1. "E" Diesel sub for "B"

2. Green Sand Filter bypassed line blockage restricting flow

3. Spray Pond Clg in effect,

4. U-2 Zone 3 HVAC s/d, U-1 Zone 3 carrying the load 8.

)

FORM OP-AD-003-7, Rev. 5. DUPLEX, Page 1 of 2 (File Number R5-5)

Vl- IO

UNIT SUPERVISOR TURNOVER SHEET UNIT: 2 .

HIFT 1900 to 0700 SHIFT 0700 ta 1000 start End Start Ead MODE MODE POWER LEVEL 100 POWER LEVEL GENERATOR OUTPUT 1144 MWe GENERATOR OUTPUT MWe REMARKS

1.LPRM 16-17B bypassed- drifting low RE notified

2. Installed bypass on Main Turbine TG, will always stay on low speed.

3. "B" RRP Bentley-Nevada Instrumentation is working spuriously

4. )Pcs b /7~& i Serrvice

5. "C" Cond Demin o/s for URC

6. RCIC o/s for work window -LCO 12.

13.

COMMON:.

1. "E" Diesel sub for "B"

2. Green Sand Filter bypassed line blockage restricting flow

3. Spray Pond Clg in effect

4. U-2 Zone 3 HVAC s/d, U-1 Zone 3 carrying the load ~

10.

FORM OP-AD-003-7, Rev. 5, DUPLEX, Page 2 of 2 (File Number R5-5)

VJ-ti

LCO LOG UNIT DATE /a ~J V7 SYSTEM O.O.S IMPACT REASON:

Date/Time Date/Time T.S. SECTION OPER, COND. REFERENCE FORMS ACTION REQUIREMENTS (OPS): RETURN Date/Time SYSTEM O.O.S IMPACT REASON:

Date/Time Date/Time T.s. SECTION OPER. COND. REFERENCEFORMS ACTION REQUIREMENTS (OPS): RETURN Date/Time SYSTEM O.O.S IMPACT REASON:

Date/Time Date/Time T.S. SECTION OPER. COND. REFERENCE 20RMS ACTION REQUIREMENTS (OPS): RETURN Date/Time SYSTEM O.O.S IMPACT REASON:

Date/Time Date/Time T.S. SECTION OPER. COND. REFERENCE FORMS ACTION REQUIREMENTS (OPS): RETURN Date/lime Daily Review Reviewed

'nitials I a ~ ir n e n

~ nano e 0 ~ ~ 1 tauten 4 ef ) Ill IDI PX /Clio 1

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DatefTime Date/Time /Cidf/ IC /d+S~ /f g< +<ac c/, ~cc1~7, T.S. SECTION S.S,INIT

/c:.27- g7 /e- $ o Y7

$ 7c <

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7P ctc7iy,1 c'ti f

//Cf j,V/~ J Z'055 t SYSTEM O.O.S IMPACT T.S. SECTION S.S. INIT Dale/Time Dalefrlme

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~ /te SS Daily Review Reviewed Initials Day Shift Supervisor I Date FORM NDAP-QA-0302-5, Rev. 2, Paqe 1 of 2 DUPLEX (File R5-4)

PENNSYLVANIAPOWER 8 'LIGHT COMPANY SUSQUEHANNA SES UNIT I SYSTEM AND EQUIPMENT STATUS Date /~ -2'~'/ 7 Shift SHIFT INITIALCONDITIONS Power Level (MW~) Shift Responsible PCO Mode Additional PCO Mode Switch Position Completed by Reviewed by (Unit Supervisor)

Reviewed by (Shift Supervisor) 1C668 SYSTEM . STATUS PROBLEIIS 8 COMMENTS EHC10111*1PO*11t ~ 4 I/S avl unavl, auto hydraulic fluid pp A h draulic flu'id pp 8 filter pp turbine vapor extr STEAM SEALING i

• I/S avl unavl aligned packing exhauster A packing exhauster 8 main steam supply aux steam supply COND DEMIN I/S S/8 unavi recy cond demin A demin 8 'ond cond demin C cond demin D cond demin E cond demin F cond demin.G MIN FLOW

• auto man unavl G PM FV-10508 RFPT AUX e a e e o e 1 ~ a i ~

I/S avl un avl auto turning ear A turning gear 8 turning gear C A mn L-0 pp A A mn L-0 pp 8 8 mn L-0'pp C 8 mn L-0 pp D C mn L-0 pp E C mn L-0 pp F A vapor extr 8 vapor extr C vapor extr V FORM OP-AD-003-1, Rev. 9, DUPLEX, Page 1 of 12 (File Number N/A)

Vl-ld

UNIT 0 SYSTEM AND EQUIPMENT STATUS'1C668 SYSTEM STATUS PROBLEMS & COMMENTS pFF GAS ee* ~ e ~ eeeee I/S avl unavl main aux SJAE MVP CIRC WATER ***

• I/O'vl unavl min full-pump A pump 8 pump C pump D SERVICE WATER * *

• I/S avl unavl auto pump A r pump 8 pump C RBCCW e e * *

• e e

• e e e I/S'vl un avl pump A pump 8 BCCW eeeeeeeeeee I/S avl unavl mpA pump'. 8 INSTAIR eeee*ee ~ eee auto unavl compressor A compressor 8 dryer A 58/4 8 X-7ir vere lr~$ )<

dryer 8 dryer C SERVAIR eeee ~ eeeee auto unavl compressor A compressor B FORM OP-AD403-1, Rev. 9, DUPLEX,.Page 2 of 12 (File Number N/A)'

UNIT 'I SYSTEM AND EQUIPMENT STATUS 1C651 SYSTEM STATUS PROBLEMS 8 COMMENTS RWCU e e **~ 4 e e e ~ ~ I/S avl unavl pump A pump 8 filter dern A filter dern 8 CONDENSATE

• I/S avl unavl pump A pump 8 pump C pump D RFPT ~~*~*e~e**~ I/S avl unavl auto man turb/pump A turb/pump C

8'urb/pump Iow load bypass DC L-0 ppA DC L-0 pp8 DCLOppC RX RECIRC *

• I/S avl unavl drive motor/pp A drive motor/pp 8 RECIRC AUXILIARIES I/S avl unavl auto vent fan A vent fan 8 AC L-0 pp A-1 AC L-0 pp A-2 AC L-0 pp 8-1 AC L-0 pp-8-2 DC L-0 pp A DC L-0 pp 8 RECIRC CONTROL

• auto controller A dd  % Speed controller 8 S 7  % Speed FORM OP-AD@03-1, Rev. 9, DUPLEX, Page 3 of 12 (File Number N/A)

Vl-u

UNIT 1 SYSTEM AND EQUIPMENT STATUS 1C651 SYSTEM STATUS PROBLEMS & COMMENTS BYPASS SWITCH POS norm inst byp list bypassed instrument in inst column RBM A/8 APRM A/C/E ~

V flow 'A/C IRM A/C/E/G APRM B/D/F flow B/D e

IRM B/D/F/H SRM A/8/C/D

• auto RMCS * ~ Pooo*1 *P44 I/S B/P inop RBM RSCS list rods bypassed MAIN TURB EHC i A B pressure set in control MAIN TURB *

• I'S avl unavl auto lift pumps uming ge OIL SYSTEMS ~**~~*~ I/S avl unavl auto 'lock TGOP Mn L-.O suet pp EBOP ESOP GEN EXCITATION

• auto man voltage regulator FORM OP-AD403-1, Rev. 9, DUPLEX, Page 4 of 12 (Fite Number N/A)

Vi-l7

UNIT 1 SYSTEM AND EQUI PlVlENT STATUS 1C601 STATUS PROBLEMS 8 COMMENTS SYSTEM'RP,1 PIP 1 1PP* ~ ~ PP I/S avl pump A unavl'ut pump B flow contr A

. flow contr B

$ BLC )I

• I 'I I I 'I

• I

• I 'I squib continuity squib A squib B D/W FLOOR SUMPS avl unavl sump A pump A sump A pump B.

sump B pumpA sump B pump B RCIC 1 1*1111***11 I/S avl unavl turb/pump status RCIC control auto man controller

• V' 'ape setpoint value < ~ ~ . GPM CORE SPRAY DIV I I/S avl unavl pump A pump C DIVI ***11**11 I/S avl unavl pump A pump C RHR SW DIV I I/S avl unavl A

• 'ump

~ g',k M/WA~

AP$ 1 *I ~ P ~ I ~ I ~ IIIIII avl unavl system

$ POTMO$ I I I I P ~ I I P I/S unavl system A system 8 MSIV STATUS LIGHT ' off light, indication TIPI I I I I I I I I P ~ III close open valve indication

. FORM OP-AD403-1, Rev. 9, DUPLEX, Page 5 of 12 (File Number N/A)

Vl-IQ

/

UNIT I

'YSTEM AND EQUIPMENT STATUS 1C601 SYSTEM STATUS PROBLEMS 8 COMMENTS CONTAINMENTHg/Og H% 02%

AR15746A AR1 57468 5 TO S(6 SUPP POOL FILTER PP* I/S avl unavl pLlrn p INST GAS>> <<<<<<<<** <<>> auto unavl compressor A compressor 8 STORAGE BOTTLES"

• dose open SV-12643 SV-12648 CORE SPRAY DIV II 'I/S avl unavl pump 8 pump D RHR DIV II'<<*<<<<<<<< I/S avl unavl pump D

8'ump RHRSW DIV II'* **<< I/S avl unavl 8

HPCI>> ******>>*>>>>>>>>>> 'I/S avl unavl turb/pump status HPCI control* <<<<* <<<<<<<< auto controller tapesetpointvalue 5/~< GPM OOS ECCS/BIS STATUS'os yes no lights tested all oos lights off list oos systems ORM OP-AD-003-1, Rev. 9, DUPLEX, Page 6 of 12 (File Number N/A)

VI-19

UNIT 1 SYSTEM AND EQUIPMENT STATUS T-10 11A 118 12A 128 T-20 BUS 10 X BUS 20 13;8KV k L ~ b.

Q ~

p ~ p ~ Q ~ 6 '.A ~ ol P4 o

)C 'pC )C ~4'VA p ~ g g 0

0 1A 1C 18 10 2A 2C ~

28 'O ~

0 0

10 20 8

4.16KV Use an "X" in the applicable boxes to represent closed breaker positions Circle those boxes which represent unavailable breakers.

FORM OP-AD403-1, Rev. 9, DUPLEX,. Page 7 of 12 (File Number N/A)

Yj-ZQ

UNIT 1 SYSTEM AND EQUIPMENT STATUS OC653 SYSTEM STATUS PROBLEMS 8 COMMENTS COND TRANSFER I/S avl unavl pump A pump B REFUEL TRANSF

• I/S avl unavl pump A pump 8 MAKE-UP DEMIN

• I/S avl unavl pump A pump B jockey pp AUX BOILER, * * 'I/S avl unavl boiler A boiler B RIVER WATER M-U

• I/S avl unavl pump A pump B ump C ump D ESWJ*%i1Po ~ 0 ~ ' P ~ ~

I/S avl unavl pump A pump C pump B pump D DIESEL GENERATOR I/S avl unavl DGA DG B DG. C DGD DG E

• If substituted, aligned to ORM OP-AD<03-1, Rev. 9, DUPLEX, Page 8 of 12 (File Number N/A)

~

Yl-2j

UNIT 1 SYSTEM AND EQUIPMENT STATUS HVAC Systems OC681 SYSTEM 'STATUS PROBLEMS 8 COMMENTS CREOASS '* I/S avl 'unavl stop S/B lead start OV101A OV1018 ESW PP HSE'FANS ' I/S avl un avl OV521A OV521C OV5218 OV521D CONT STR CHILLWATER I/S avl unavl

'P171A OP1718 DG BLDG VENT FAN ' ' I/S avl un avl OV512A OV512C OV5128 OV512D CONT STR VENT FAN OV103A

" '/S avl unavl OV1038 CONIP ROOM FAN ' ~ << ~ ~ " ~ ~ ~

I/S avl unavl OV115A OV1 158 CONT ROOM FAN " I/S avl unavl OV117A OV117B BATTRMEXH<<'.'<<'""'<<>> I/S avl unavl OV116A OV1 168 SBGT SYS EQUIP FAN I/S avl unavl OV118A OV1 188 SBGT RM HEAT FAN OV144A

'/S avl unavl OV1448 RB RECIRC FAN OV201A

' '/S avl unavl stop S/B lead start OV2018 CHILL WIR CIRC pp OP162A

' ' '/S avl unavl OP 1628 SBGTSYS EXHFAN>><<>>'V109A I/S avl unavl stop S/8 lead start OV1098 SGTS CLG OA DMP ' ' CLOSED HD-07555A HO<75558 SEC CONT ISO PWR OFF FU-5 FU-7 FU-6 FU.8 LER-94415-00.

Normally dosed if system not in service. Initiate / WA, and notify NSE if open when should be dosed. Refer to FORM OP-AD-003-1, Rev. 9, DUPLEX. Page 9 of 12 (File Number N/A) vl-22

UNIT 1 SYSTEM AND EQUIPMENT STATUS HVAC SYSTEMS OC681 SYSTEM STATUS PROBLEMS 8 COMMENTS DRYWELL COOLERS'V414A l/S avl unavl 1V416A 1V415A 1V411A 1V412A 1V413A 1V417A 1V418A 1Y4148 1V4168 1V4158 1V4118 1V4128 1V4138 1V4178 1V4188 HR PP ROOM CLR

' ' IIS avl unavl

'210A 1Y210C

~ 1V2108 1V210D RClC PP ROOM CLR ' l/S avl unavl

'V208A-1V2088 CORE SPRAY ROOM CLR l/S unavl 1V211A 1V211C 1Y2118 1V211D HPCI PP ROOM Cl l/S avl unavl R'Y209A 1V2098 EMERG SW CLR ' ' 1/S unavl 1V222A 1V2'228 .

RHRSW PP ROOM CLR ' I/S , avl unavl 1V506A

'1 V5068 ORM OP-AD-003-1, Rev. 9. DUPLEX, Page 10 of 12 (File Number N/A)

UNIT 1 SYSTEM AND EQUIPMENT STATUS Miscellaneous MISCELL SYSTEM STATUS PROBLEMS 8 COMMENTS RP$ 404'PI4*40441 I/S avl unavl A gen feed

'es 8 gen feed A alt feed 8 alt feed EXCESS FLOW CH no all vlv open GEN LOCKOUTS ~ ' ' ' ~ " 'es no lockouts reset no relay flags CONT ATMOS MON ' anal S/8 off samp zero span

'C690B 1C690A PASS SYS ~ ~ I ~ ~ ~ ~ * ~ ~ ~ 0 ~ ~ ~ ~

off isol vlv permiss switch CONT RAD avl unavl MONT'P262A1 1P262A2 1P26281 1P26282

'/S FIRE PROTECT I/S avl unavl pp 'iesel AC pp smoke rem fan A smoke rem fan 8 OC697 MOV BYPASS '

switches in normal RECOMBINER unit 1

'/S avl unavl unit 2 common unit select switch position-unit CCW pp 1P145 CCW pp 2P145 CCW pp OP145 FORM OP-AD%03-1. Rev. 9, DUPLEX, Page 11 of 12 (File Number N/A)

'C Vl-2V'

UN)T 1

. SYSTElN AND EQUlPIVlENT STATUS IVliscellaneous MISC ELL SYSTEM STATUS PROBLEMS & COMMENTS

~ ~ ~ ~ P ~ ~ ~ ~ 0 UNIT 2 ECC$ I/S avl unavl U-2 RCIC U-2 core spray pp A U-2 core spray pp C U-2 RHR pp A U-2 RHR pp C U-2 RHR swppA U-2 core spray pp B U-2 core spray pp D U-2 RHR pp B U-2 RHR pp D U-2 RHR sw pp B U-2 HPCI CRQSSTIED SYS 0 i 0 ~ ~ ~ ~ i ~ no yes common S.W. from U-2 CRD U-1/U-2 IA U-1/U-2 SA U-1/U-2 CST U-1/U-2 ANNUNCIATOR TEST'IGHT no yes SHIFT ONLY Control Room Annunciators tested I~ ~ 1 ~~ ~ ~ ~

~ ~ ~ ~ ~ Check no for each Panel on Dayshift satisfactory for the following Panels 1C668 1C651 1C601 OC653 OC681 DIV 1 OC681 DIV 2 1C681 DIV 1 1C681 DIV 2 1C692 Excess Flow Check Vlvs Test DIV1 1C692 Excess Flow Check Vlvs Test DIV2 1C692 1C694 DIV 1 1C694 Dlv 2 1C644 1C645 1C693 OC693

'C650 OC673 OC659 FORM OP-AD-003-1, Rev. 9, DUPLEX, Page 12 of 12 (File Number N/A) vl-25

SECTION Vll - RADIOLOGICALCONDITIONS PART A - Offsite Release Data Section 1 - Weather arid Met Data Log VII-1 10/28/97 NRC Exercise Manual

SYSTEM WEATHER FORECAST FOR 10/28/97 ISSUED: 0145 HOURS FROM TCC TUESDAY - MORNING CLOUDS GIVING WAY TO AFTERNOON SUN. WINDS N 12 MPH TEMPERATURES Wednesday Thursday 1100 Max Time 1100 Min Time Max Time Allentown 68 73 1600 70 57 0500 74 1600 Harrisburg/Lancaster 70 75 1600 70 59 0600 77 1500 Hazleton/Scranton 65 71 . 1600 68 55 0600 77 1500 Williamsport 65 71 1700 65 56 0600 73 1500 Wednesday - Sunny throughout the day. Clear to partly cloudy overnight. Winds N 5 mph.

VII-2 . 10/28/97 NRC Exercise Manual

SYSTEM WEATHER FORECAST FOR 10/28/97 PDATE ISSUED: 1134 HOURS OM PCC Tuesday - Mostly sunny and pleas'ant this afternoon. Clear and quite cool tonight.

Wednesday - Sunny throughout the day. Clear to partly cloudy at night.

TEMPERATURES Wednesday Thursday Winds

@ 1100 0400 1100 Min Time Max Time Max Time Allentown 58 70 57 0500 74 1600 N6 Harrisburg/Lancaster 61 71 59 0600 '77 1500 N5 Hazleton/Scranton 55 65 53 0600 78 '500 W4 Williamsport 55 66 53 0600 .1500 W5 ursday - Mostly sunny through the day. Clear to partly cloudy at night.

Average Max Temp 76 min 53 1

Friday - Mostly sunny during the day." Clear to partly cloudy at night.

Average Max Temp 77 min 55 VII-3 10/28/97 NRC Exercise Manual

Weather Data (Taken from July 10, 1997)

VMS01B VMX01B VMX03B VMT08A VMS02B VMX02B VMX04B VMA01 Time Value Value Value Value Value Value Value Value Sig. 10M 10M WS 10M WD Sig Theta 60M WS 60M WD Theta Amb 2 min 2 imn 60M 2 2 min 2 min 10M 2 Temp avg avg min avg Delta T avg avg min avg 14:55 9.25438 349.051 22.5876 74.743 8.71318 337.467 16.2788 -0.82 15:10 13.8764 388.137 21.4389 74.011 8.98267 378.954 14.4691 '1.02

~ 15:25 13.8764 388.137 21.4389 75.8368 8.98267 378.954 14.4691 -1.02 15:40 13.8764 388.137 21.4389 75.7698 8.98267 378.954 14.4691 -1.02 15:55 13.8764 388.137 21.4389 75.744 8.98267 378.954 14.4691 -1.02 16:10 12.0554 378.343 32A252 75.5396 8.28634 383.981 21.4162 -0.97 16:25 12.0554 378.343 32.4252 76.1875 8.28634 383.981 21.4162 -0.97 16:40 12.0554 378.343 32.4252 76.2486 8.28634 383.981 21.4162 -0.97 16:55 12.0554 378.343 32.4252 76.3592 8.28634 383.981 21.4162 -0.97 17:10 9.7014 353.22 23.1898 76..1 557 7.15337 354.161 20.6993 .-0.71 17:25 9.7014 353.22 23.1898 75.8968 7.15337 354.16'l 20.6993 -0.71 17:40 9.7014 353.22 23.1898 76.1906 7.15337 354.16.1 20.6993 -0.71 17:55 9.7014 '53.22 23.1898 76.2623 '.15337 354.161 20.6993 -0.71 NOTE: The above weather conditions are that which existed July 10, 1997. The weather data has been loaded into the simulator for display on the various computer displays used by the emergency responders.

Vll-4 10/28/97 NRC Exercise Manual

Weather Data (Cont.)

(Taken from July 10, 1997)

VMS01B VMX01B VMX03B VMT08A VMS02B VMX02B VMX04B VMA01 Time Value Value Value Value Value Value Value Value Sig 10M 10M WD Sig Theta 60M WS 60M WD Theta Amb. 10M WS 2 imn 60M 2 2 min 2 min 10M 2 Temp 2 min avg min avg Delta T avg avg min avg avg 18:10 7.94777 387.901 22.0469 75.4927 7.17745 368.73 16.5026 -0.76 18:25 7.94777 387.901 22.0469 75.2679 7.17745 368.73 16.5026 -0.76 18:40 7.94777 387.901 22.0469 74.9303 7.17745 368.73 16.5026 -0.76 18:55 7.94777 387:901 22.0469 74.5533 7.17745 368.73 16.5026 -0.76 19:10 7.35226 366.746 15.0612 74.4391 6.05441 365.092 9.15248 -0.48 19:25 7.35226 366.746 15.0612 74.1099 6.05441 365.092 9.15248 -0.48 19:40 7.35226 366.746 15.0612 73.7664 6.05441 365.092 9.15248 -0.48 19:55 7.35226 366.746 15.0612 73.2271 6.05441 365.092 9.15248 -0.39 20:10 9.7922 356.495 12.8387 72.5737 4.98654 345.663 10.0878 -0.24 20:25 9.7922 356.495 12.8387 71.811 4.98654 345.663 10.0878 -0.24 20:40 9.7922 356.495 12.8387 71.0533 4.98654 345.663 10.0878 -0.24 20:55 9.7922 356.495 12.8387 70.3933 4.98654 345.663 10.0878 0.11488 4

21:10 9.9348 366.144 6.98064 69.7015 4.5188 358.54 5.48274 0.30739 5

21:25 9.9348 366.144 6.98064 68.5707 4.5188 358.54 5.48274 0.6301 21:40 9.9348 366.144 6.98064 66.7612 4.5188 358.54 5.48274 1.14154 21:55 9.9348 366.144 6.98064 65.3702 4.5188 358.54 5.48274 1.64396 22:10 8.28123 369.428 12.2223 63.5825 2.67866 418.909 4.89502 2.24062 22:25 8.28123 369.428 12.2223 61.7824 2.67866 418.909 4.89502 2.76015 22:40 8.28123 369.428 12.2223 60.8251 2.67866 418.909 4.89502 2.76015 NOTE: The above weather conditions are that which existed July 10, 1997. The weather data has been loaded into the simulator for display on the various computer displays used by the emergency responders.

VII-5 10/28/97 NRC Exercise Manual

SECTION Vll - RADIOLOGICALCONDITIONS PART A - Offsite Release Data Section 2 - Plume Trajectory and Field Monitoring Team Data VII-6 10/28/97 NRC Exercise Manual

tume Information (OSCAR): AirS lodi Time (conect for release start time): iso cpm Scenario Release 0 Time Start Time = Clock Time 0 For Reactor Building 0:00 0 Release Only D 0 0

T AIS Survey Readings (mr/hr): Particulate:

oh. 5TDRAIR OHIO ~~If~l I lsopleth Open Window Closed Window Isopfeth cpm

'.AKE 5 2

~ ~~~

e/ I SITE SERVICEI 8 8

~ ~ Ll Was HOUSE C 5PRAT D D 0

~ ~'tttttt 'I war~ E 0

~; CATKHOUSE

~ 'l J

IWt I ~ ~-

~ 5ECURITT TIIOL~

C3 COOLIHS t'N~~wra 0 I

COH CEHIER TOWER I LASORATORV i A(XlCfLOIWS EL I

eh SEIKQKHT

~ POND C I TOOK-A-WHILE tt

~ CIRC.- WATER E Il O

C [

ACCESS tl C

OW LEVEL RADWASTE UIST t O.

~~

ltlt

~ t L TOWER SEMOR

~ t I'E

~ t A WATRS TRKATI4EHT PLAHT tIt I j tl t/

tttl tt

/tt A

~+

SUSOUEHANRA B C P ec Ht p IKVEh STAKE RIVER

~) 5lhUC IUhE OO KV C

~ T STAT ~

I ~he I%$ 0 r

0 Iume Information (OSCAR): AirS iodine.

Time (correct for release start time): lsopleth cpm Scenario Release Time Start Time = . Clock Time 0:10 D

E TAIS

~ STORAGE TOlRNTIR Re Sunny Readings (mrlhr):

lsopleth Open VNndow Closed VNndow Particulate:

lsopleth e~~ 20 16 cpm SITE SERVIf WAIRHOLN C C SfllAT I D

~ uu mesc weft tl;IIATEHOUSE D E 0 0 E Ii t

I SECURIfr CIITROL~

Cl un' cooLRN TONER I

i. "" EIIYNONJKNTAL LARORA1 ORV I 0 CERIER AC@I CIEOWC SEL SEOOEHT

., LAIIE tND C-I fOOII-A-NIIILE II I

~ CIRC..NITER Il

[ /I

-LOW LEVEL ~~

/

II RAOWASTE ~

~

/

lowEh ~ )

SENSE

~ /

A TREATIKHT //I/

WATS BAHT /I I ////

//

//

////

~+

SU50UEHAIIIIA

~E hf /l P IIVER NfAIIE RIVER S I INJC1URE oo Kv

~ f SfAT - ~

1 Waar Ra TRIO f B C; P E

0

'lume Information (OSCAR): AirSar 5:

lodi Time (conect for release start time): iso cpnl Scenario Release 20 Time Start Time = . Clock Time 5 0:40 C 3 D 1 0

Survey Readings (mr/hr): Particulate:

Oh, glohAOL lONRSR t RO lsopleth Open Window Closed Window lsopleth cpm 100 80 e~ 0 25 20 B users aoi SllE SERVICE wNSHousl 17 13 C D

~ IWp HOLNK ISfllH OAlKHOUSE-

~

l I

~ SECNIIl V E3 COOLNO

~

~ 0 AREA EHVIROHMENlAt I I

Q

)I

~

I CON fhO~ lOWE1 I 0

tASORArohv I CENIER ACID CICOOIO SEL .t 0

~ SE LAKE tOHO C-I lOOK-A-WIIILK

~

II ~

Il CIRC. WAlER II ACCESS ~ I

-loW LEVEL I t

~

II LNlf hAOWASlE

~l~~$~g

~ S COOLIHO lOWE1 SEW'hEAlIIKHl

~

~

II I

I II

'LAHf

~

WAISI Il II li ~ I ~

~ ~ 0

~

IIII II gs l ~ ~

II lH ~A 5U50UEHARHA

~ M OA E RIVER SE Nl P NVER IHIAKE A

SSRUC lURE OO KV C t..

S lAl l IISIUt 10 ASS E u C O E

~me Information (OSCAR): AirSa iodine.

ime (correct for release start time): lsopleth cpm Scenario Release A 19 Time Start Time = Clock Time 1:10 D

E AIS i1~ . T Survey Readings (mrlhr): Particulate:

ON. STORAGE I OCIIS ~ i~g

~

lsopleth Open Window Closed Window iso pleth cpm 93 74 SITS SQ' 23 19 16 12

. anAT I

~ CND ~TH D ~ D I i,ICATKHOU E

'1 I'

EHvllNISIEggpg

~ SKCURITT K3 COOLNO LASORATORY I COHTRCL~ lOWKR CENTER Qe ACNl CINONl4 SKL SKOSH T LANK tOHD C-I TOOli-A-WHN.K I~

lI CIAC. WllER II O ACCESS II II II LOWLEVEL RADWASTK I'llt ~

II

~I I

X

~ ~a~i~g COOLNO TOWER WELL SKULK TRKATIAKHT I

~I II tlAHT IlII P

WATER li IJ IJ IIIl IJ II TH I 5USOUEHAHHA

~

~

~ ~ RiVER

~ SK HT P IIVER NTAKE 5 IRUCIUhE C

Oo NV STAT I IC5NP hh T~S ~

f-8 CD VII-10

me Information (OSCAR): AirSa lodin me (correct for release start time):: lsopl . cpm Scenario Release 18 Time Start Time = Clock Time 1:40 C D

Survey Readings (mrlhr): ParticLliate:

1S TAI tsopleth Open Window Closed Window lsopleth cpm

~ ~~g ~ ~~ 0 88 70

~0~0 22 18 5PAAy g) I I

Sla Illll ~ C D

15 12 C D

/

rural HOUSE il

~ Hah TH 0SATEHOUI 1

LEANT I

~ ~ 0ii M LWKMI 0'IIII AREA I I

5ECURITT CQHTROL~

Ej COOUHO TOWER EMnMHMENlAl LASORATORy, I Ij I CEHTEh AC%I CN.OSIS SEL 0

0M. 5ENLAEHT LAKE lr tOHD C-I TOOK.A- WIULE II I CIRC. WATER u l II ACCESS ~~

II

-LOW LEVEL RADWASTE LNIT COOUNQ t ~ /

///

~

TOWER SEWN%

/ ~I

~

A TREATQOIT //

////

WATER tLAHT

////

~ ~ ~ 0 //

//

~ ~ //

TH ~

/// SUSOUEHANRA SA E RIVER MVTR NTAKE 5'IMJC I IKIE OO KV

~ T STAT ~

l NSNIP hh T<IO I B c D

lume Infol'mation (OSCAR): Air lod Time (conect for release start time): ~

iso cpm Scenario Release 17 ~

Time Start Time = . Clock Time 2:10 D

E 1 AI$

OR, ~ TORAH III~ Survey Readings (mrlhr): ParticUlate:

1 OWN$

lsopleth Open Window Closed Window Isopleth cpm I 84 67

$ ITE $ ERVICE 8 17 B C 14 5%I AY I D

,+ OATEHOUSE- E 0 ACKET lt LRRT I

$ ECURITT COH THOL~

CEHTER C} COOUHO TOWER I LNVIMlalalgAg LA$ORATORy t fl Ctkl8%4 I 0 I

aw.

CNC. WATER

~g Ir'CCE$

~

A

$ ENQEHT tOHD C-I LAKE lOOK. A-WlIILE U I/

/I

-LOW LEVEL ~~

/

I( $ $ NO ~

RAOWA$TE ///

LL ~

~ ~I~

~ ~) TOWE1 ACKITY

$ EWAOE I/

~/

//

TREAT~T ~ /

/

////

. tLAHT A ~ /

.c

$T ~ ~ //////

//

/

r' $ USOUEHANHA

~

OINT n MVER IH TAKE RIVER

$ 1 RUCI UhE K

~ $ l TAI WN5HIP T4$ ~ x. u L

C D E

~lume Information (OSCAR): AirSa ~s:

lo Time (conect for refease start time): Is cpnl Scenario Release -16

=

Start Time =

'ime Clock Time 4 2:40 C D

1AI Survey Readings (mr/br): Particulate:.

Oa NORAH'OWRER' ONO Isopleth Open Window Closed Window Isopleth cpm A 80 64 NTE SERVICE 20 16 WNRNOUEE 13 0 NOW i D D tUQt NOUEK eefN i,iOAT EHOUSE-

~

'1.I lhhf I 5ECURITT Cl COOUNO ENVIRONMENTAL I O

COH THOL~ TOWER LARORA OR<f I CEHIEh 0

A e

~-

~ LOO. <<Q ACKI CILOSt4 EEOeENT PND C-I

~y LAKK fOOK-A-WHILE II CIRC..WAfER II O

R II ACCEES I

-LOW.LEVEL MOWASTS LAIT t COOLINO lERIO ACLITY

~

~

~

I I

LL~ ~ ~Q TOWER II II

~ I

/ SEW'REATNENT ~I I

IIll A.ANT A II

'c ~

0

~ II II Q II tI r'V OQKN f N-t MVER hlfAKE OlhUCI UhE

~

5USOUEHAHHA RIVER

~ E f III WN5HIP I I TABOO L ~ 2 C D VII-13

'Iume Information (OSCAR): AirSar. s:

lod Time (conect for release start time): fso cpm Scenario Time .. Release Start Time = Clock Time

':10 15 C

D OL ITORAOL OTIC+~~

ai Survey Readings (mr/br): Particulate:

T

~I~ Isopleth Open Window Closed Window Isopleth cpm

~ ~I~~

~ ~~~ 77 62 A GITE IERVICEI 19 15 8 13 10 ~

C

!) ~AT I D D 0 ll lhif I ~

+ AIICgl

~~HMlNEAl COOLIHO Towfa i LAIORAfORV i 0 CENTER 0

(@)

ACO ACORNE

~ LOO. <>ouSI t

I LRIT I

~ SECURIT Y K3 COOLI>>0 CO>>TRCL~ TOWER 'ARORATORY CE>>TER ACO MON%~ EL 0

SEORAE>>l LAKE to>>O C-l lOOK.A.WIIILE O

I tlc: outs tt tl OR ACCESS ~~

LOW LEVEL LN T R tROC555RIO ~ I ltI

~

X RAOWAST5 cooLT>>e fACLITY TOWER lt

~

I tttt SEIRAOE TREATIIENT NA tI IIII tLANT ti

'c ST s I A .,/

I NANT n

~

It I

II IIII III

~

SUSOUENAHHA RIVER I-a *4-IKVTR I>>TAKE STRUCl LIE 500 V c SWIT Il NWI ~

l TRIO L. . .J B C D E

Plume Information (OSCAR): Air ss:

lo Time (conect for release start time): ls cpm Scenario Release 14.

Time Start Time = . Clock Time 4:10 C D

SO I A IS Survey Readings (mrlhr): Particulate:

Oh, STORAOL ON4 I OgKQilf .Isopleth Open Window Closed Window Isopleth cpm

~ ~I~ 74 19 59 15 B SITE SERVICES C 12 10

. ~AT i D D

[I I E

<:eATfexsf I) LAIT I MOW Sf CURITT Cl COOLRN ENVSIOIIMEIITAL4.

TOWER I Q I CONTROL~

CEIITE1 LASORA TORT II 0

~ I ~ IOO. <( ( ~

o I( ~ ~

) Xr t w A

I> ~

O

~ ~

/t ~j h getkgllgaQ i

~ ~

, ~, C.

I 0/

/

go ~ -AIVPB ~

Hoch I 0

I I I Plume Irmation: AirSamples: + "

II Igl. "

todine:

Time Scenar o ct for. release start time):

Release tsopleth A

~

c~ ~

~

r@:g,::-..

o,

)

Time Statt Ttme = Clock Time t' ~ o I 0:25 c 0 'SI tI

) (

'urvey Readings

~

(mrrhr): Particutate: o tsopleth Open Window Closed Window tsopleth cpm 30 24 lj 10 (

I 0

I 0 ~

ll IS z I I)i I

I( ..-

7(I

~f iVli

~

I

)

rC

r. J

. 'ewe s g ~ (l (Il l -.J II~. l.l I:=-

f(

7

%s I

I A

s ~

/,

eLt Ir

//

s

) J~( ~,( .c g

'I .).

~l..

('~ ) II

/: A pea,c&gai C

~ ~ ~

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SECTION Vll'- RADIOLOGICALCONDITIONS PART A - Offsite Release Data Section 3 - Release Data VII-32 10/28/97 NRC Exercise Manual

Release Rate Summary Note: Scenario is free play, times are approximate.

18:16 Reactor Reactor Building with Building Turbine Combined Combined SBGT without SBGT Building with SBGT without SBGT pCi/Min pCi/Min pCi/Min pCi/Min- pCi/Min Total - NG 1.26E+05 5.72E+06 1.12E+08 1.12E+08 1.18E+08 Total - lod. 5.20E+00 2.37E+05 8.75E+03 8:75E+03 2.46E+05 Total- 4.63E-04 2.11E+01 2.41E+00 2.41E+00 2.35E+01 Part.

Total 1.26E+05 5.96E+06 1.12E+08 1.12E+08 1.18E+08 18:46 Reactor Reactor Building with Building Turbine Combined Combined SBGT without SBGT Building with SBGT without SBGT Total - NG 2.02E+05 9.20E+06 5.85E+08 5.85E+08 5.94E+08 Total - lod. 5.79E+00 2.64E+05 4A9E+04 4.49E+04 3.08E+05 Total- 2.35E-03 1.07E+02 1A5E+01 1.45E+01 1.21E+02 Part.

Total 2.02E+05 9.46E+06 8.85E+08 5.85E+08 5.95E+08 19:15 Reactor Reactor Building with Building Turbine Combined Combined SBGT without SBGT Building with SBGT without SBGT Total - NG 2.73E+05 1.24E+07 5.45E+08 5.45E+08 5.57E+08 Total - lod. 6.30E+00 . 2.87E+05 3.91E+04 3.92E+04 3.26E+05 Total- 4.23E-03 '1.93E+02 1.45E+01 1.45E+01 2.07E+02 Part.

Total 2.73E+05 1.27E+07 5.45E+08 5.45E+08 5.58E+08 VII-33 10/28/97 NRC Exercise Manual

19:46 Reactor Reactor Building with Building Turbine Combined Combined SBGT without SBGT Building with SBGT without SBGT Total - NG 3.40E+05 1.55E+07 5.17E+08 5.17E+08 5.32E+08 Total - lod. 6.75E+00 3.08E+05 3.49E+04 3.49E+04 3.43E+05 Total.- 6.12E-03 2.79E+02 1.45E+01 1.45E+01 2.93E+02 Part.

Total 3.40E+05 1.58E+07 5.17E+08 5.17E+08 5.33E+08 20:15 Reactor Reactor Building with Building Turbine Combined Combined

'SBGT without SBGT Building with SBGT without SBGT Total - NG 4.04E+05 1.84E+07 4.92E+08 4.93E+08 5.11E+08 Total - lod. 7.17E+00 3.26E+05 3.17E+04 3.17E+04 3.58E+05 Total- 8.01E-03 3.65E+02 1.45E+01 1.45E+01 '.79E+02 Part.

Total 4.04E+05 1.87E+07 4.92E+08 4.93E+08 5.11E+08 20:45 Reactor Reactor Building with Building Turbine Combined Combined without SBGT'BGT Building with SBGT without SBGT Total - NG 4.66E+05 2.12E+07 4.71E+08 4.71E+08 4.92E+08 Total-lod. 7.55E+00 3.44E+05 2.93E+04 2.93E+04 3.73E+05 Total- 9.89E-03 4.51E+02 1.45E+01 1.45E+01 4.65E+02 Part.

Total 4.66E+05 2.16E+07 4.71E+08 4.71E+08 4.92E+08 VII-34 10/28/97 NRC Exercise Manual

21 15 Reactor Reactor Building with Building Turbine Combined Combined SBGT without SBGT Building with SBGT without SBGT Total - NG 5.25E+05 2.39E+07 4.53E+08 4.53E+08 4.77E+08 Total - lod. 7.90E+00 3.60E+05 2.73E+04 2.73E+04 3.87E+05 Total - . 1.18E-02 5.37E+02 1.45E+01 1.45E+01 5.51E+02 Part Total 5.25E+05 2.43E+07 4.53E+08 4.53E+08 4.77E+08 20:45 Reactor Reactor Building with Building Turbine Combined "Combined SBGT without SBGT Building with SBGT without SBGT Total - NG 5.82E+05 2.65E+07 4.36E+08 4.37E+08 4.63E+08 Total - lod. 8.24E+00 3.75E+05 2.57E+04 2.57E+04 4.01E+05 Total- 1.37E-02 6.22E+02 1.4'5E+01 1.45E+01 6.37E+02 Part.

Total 5.82E+05 2.69E+07 4.36E+08 4.37E+08 4.63E+08 VII-35 10/28/97 NRC Exercise Manual

SECTION VII - RADIOLOGICALCONDITIONS PART 8 - Reactor Water Isotopics VII-36 10/28/97 NRC Exercise Manual

RCS Concentrations 18:15 18:45 19:15 19:45 20:15 20:45 21:15 21:45 I-131 2.42E+01 4.83E+01 4.82E+01 4.81E+01 4.80E+01 4.79E+01 4.78E+0.1 4.78E+01 I-132 4.79E+01 8.23E+01 7.07E+01 6.07E+01 5.21E+01 4.48E+01 3.85E+01 3.30E+01 I-133 5.47E+01 1.08E+02 1.06E+02 1.04E+02 1.02E+02 1.01E+02 9.90E+01 9.74E+01 I-134 8.66E+01 1.17E+02 7.84E+01 5.28E+01 3.55E+01 2.39E+01 1.61E+01 1.08E+01 I-135 4.79E+01 9.09E+01 8.62E+01 8.18E+01 7.76E+01 7.37E+01 6.99E+01 6.63E+01 Kr-83m 5.50E+01 9.11E+01 7.54E+01 6.24E+01 5.16E+01 4.27E+01 3.53E+01 2.92E+01 Kr-85m 2.11E+02 3.90E+02 3.61E+02 3.34E+02 3.09E+02 2.86E+02 2.65E+02 2.45E+02 Kr-85 7.26E-01 1.45E+00 1.45E+00 1.45E+00 1.45E+00 1.45E+00 1.45E+00 1.45E+00 Kr-87 2.68E+02 .4.07E+02 3.10E+02 2.36E+02 1.79E+02 1.36E+02 1.04E+02 7.89E+01 Kr-88 4.76E+02 8.44E+02 7.47E+02 6.62E+02 5.86E+02 5.19E+02 4.60E+02 4.08E+02 Kr-89 2.86E+01 8.50E-02 1.27E-04 1.88E-07 2.80E-10 0.00E+00 0.00E+00 0.00E+00 Xe-131m 5.28E+00 1.05E+01 1.05E+01 1.05E+01 1.05E+01 1.05E+01 1.05E+01 1.05E+01 Xe-133m 2.54E+01 5.05E+01 5.01E+01 4.98E+01 4.95E+01 4.91E+01 4.88E+01 4.85E+01 Xe-133 1.06E+03 2.11E+03 2.10E+03 2.10E+03 2.09E+03 2.09E+03 2.08E+03 2.08E+03 Xe-135m 4.87E+01 2.48E+01 6.31E+00 1.61E+00 4.09E-01 1.04E-01 2.65E-02 6.75E-03 Xe-135 9.41E+02 1.81E+03 1.74E+03 1.68E+03 1.62E+03 1.55E+03 1.50E+03 1.44E+03 Xe-137 4.55E+01 3.87E-01 1.65E-03 7.00E-06 2.98E-08 1.27E-10 0.00E+00 0.00E+00 Xe-138 1.88E+02 8.63E+01 1.98E+01 4.54E+00 1.04E+00 2.38E-01 5.47E-02 1.25E-02 Cs-137 7.1 9E+00 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 Total - NG 3.35E+03 5.83E+03 5.42E+03 5.14E+03 4.90E+03 4.69E+03 4.51E+03 4.34E+03 Total - lod. 2.61E+02 4.47E+02 3.90E+02 3.47E+02 3.1 5E+02 2.91E+02 2.71E+02 2.55E+02 Total - Part. 7.19E+00 1.44E+01 1.44E+01 1:44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 Total 3.61E+03 6.27E+03 5.81E+03 5.49E+03 5.21E+03 4.98E+03 4.78E+03 4.60E+03 VII- 10/28/97 NRC Exercise Manual

SECTION Vll - RADIOLOGICALCONDITIONS PART C - Suppression Pool Water Isotopics VII-38 10/28/97 NRC Exercise Manual

Suppression Pool Activities 18:15 18:45 19:15 19:45 20:15 20:45 21:15 21:45 W31 5.80E+00 6.56E+00 7.32E+00 8.08E+00 8.84E+00 9.60E+00 1.04E+01 1.11E+01 I-132 1.15E+01 1.28E+01 1.39E+01 1.49E+01 '1.57E+01 1.64E+01 1.70E+01 '1.75E+01 l-133 1.31E+01 1.48E+01 1.65E+01, 1.81E+01 1.97E+01 2.13E+01 2.29E+01 2.44E+01 1-134 2.08E+01 2.26E+01 2.39E+01 2.47E+01 2.53E+01 2.57E+01 2.59E+01 2.61 E+01 I-135 1.15E+01 1.29E+01 1.43E+01 1.56E+01 1.68E+01 1.80E+01 1.91E+01 2.01E+01 Kr-83m 2.48E+00 3.92E+00 5.11E+00 6.09E+00 6.91E+00 7.58E+00 8.14E+00 8.60E+00 Kr-85m 9.51E+00 1.57E+01 2.14E+01 2.66E+01 3.15E+01 3.60E+01 4.02E+01'.41E+01 Kr-85 3.28E-02 5.57E-02 7.86E-02 1.01E-01 1.24E-01 1.47E-01 1.70E-01 1.93E Kr-87 1.21E+01 1.85E+01 2.34E+01 2.71E+01 3.00E+01 3.21E+01 3.38E+01 3.50E+01 Kr-88 2.1 5E+01 3.48E+01 4.66E+01 5.71E+01 6.63E+01 7.45E+01 8.18E+01 8.82E+01 Kr-89 1.29E+00 1.29E+00 1.29E+00 1.29E+00 1.29E+00 1.29E+00 1.29E+00 1.29E+00 Xe-131m 2.38E-01 4.04E-01 5.69E-01, 7.35E-01 9.01E-01 1.07E+00 1.23E+00 1.40E+00 Xe-133m 1.1 5E+00 1.95E+00 2.74E+00 3.52E+00 4.30E+00 5.08E+00 5.85E+00 6.62E+00 Xe-133 4.78E+01 8.11E+01 1.14E+02 1.47E+02 1.80E+02 2.13E+02 2.46E+02 2.79E+02 Xe-135m 2.20E+00 2.59E+00 2.69E+00 2.72E+00 2.72E+00 2.72E+00 2.72E+00 2.73E+00 Xe-135 4.25E+01 7.11E+01 9.85E+01 1.25E+02 1.51E+02 1.75E+02 1.99E+02 2.21E+02 Xe-137 2.05E+00 2.06E+00 2.06E+00 2.06E+00 2.06E+00 2.06E+00 2.06E+00 2.06E+00 Xe-138 8.50E+00 9.86E+00 1.02E+01 1.02E+01 1.03E+01 1.03E+01 1.03E+01 1.03E+01 Cs-137 5.58E-02 2.83E-01 5.10E-01 7.38E-01 9.65E-01 1.1 9E+00 1.42E+00 1.65E+00 Total - NG 1.51E+02 '2.43E+02 3.29E+02 4.10E+02 4.87E+02 5.61E+02 6.32E+02 7.01E+02 Total - lod. 6.27E+01 6.97E+01 7.59E+01 8.14E+01 8.64E+01 9.09E+01 9.52E+01 . 9.93E+01 Total- 5.58E-02 2.83E-01 5.10E-01 7.38E-01 9.65E-01 1.19E+00 1.42E+00 1.65E+00 Part.

Total 2.14E+02 3.13E+02 4.05E+02 4.92E+02 5.75E+02 6.53E+02 7.29E+02 8.02E+02 Vll- q 10/28/97 NRC Exercise ar ~~al

SECTION Vll '- RADIOLOGICALCONDITIONS PART D - Drywell Isotopics VIICO 10/28/97 NRC Exercise Manual

PENNSYLVANIAPOWER 8 LIGHT COMPANY DRILL: 1997 NRC OBSERVED EXERCISE Drywell Air Space Gas Sample Data (pCI/cc)

Isotope 18:15 18:45 'l9:15 19:45 20:15 ~ 20:46 21:15 21:46 I-131 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 2.32E-03 4.64E-03 6.95E-03 7.11E-03 I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.52E-03 4.33E-03 5.58E-03 4.92E-03 I-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.95E-03 9.75E-03 1.44E-02 1.45E-02 I-134 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 1.72E-03 2.31E-03 2.34E-03 1.61E-03 I-135 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 3.76E-03 7.13E-03 1.02E-02 9.87E-03 Kr-83m 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 8.93E-01 1.48E+00 1.84E+00 1.56E+00 Kr-85m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.35E+00 9.90E+00 1.37E+01 1.30E+01 Kr-86 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 2.51E-02 5.03E-02 7.54E-02 7.73E-02 Kr-87 O.OOE+00'.OOE+00 O.OOE+00 0.00E+00 3.10E+00 4.72E+00 5.39E+00 4.20E+00 Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.02E+01 1.80E+01 2.39E+01 2.17E+01 Kr-89 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-131m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.82E-01 3.63E-01 5.44E-01 5;57E-01 Xe-133m 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 8.56E-01 1.70E+00 2.54E+00 2.58E+00 Xe-133 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 3.62E+01 7.23E+01 . 1.08E+02 1.11E+02 Xe-136m 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 7.08E-03 3.61E-03 1.38E-03 3.60E-04 Xe-135 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 2.80E+01 5.38E+01 7.77E+01 7.67E+01 Xe-137 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 5.16E-10 'O.OOE+00 O.OOE+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.80E-02 8.26E-03 2.84E-03 6.67E-04 Cs-137 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.16E-05 1.63E-04 2.'45E-04 2.51E-04 10/28/97 NRC Exercise Maniacal

SECTION Vll - RADIOLOGICALCONDITIONS PART E - Wetwell Isotopics Vll-42 10/28/97 NRC Exercise Manual

PENNSYLVANIAPOWER & LIGHT COMPANY DRILL: 1997 NRC OBSERVED EXERCISE Wetwell Air Space Gas Sample Data (pCI/cc)

Isotope 18:15 18:45 19:15 19:45 20:15 20:45 21:15 21:45 l-131 1.86E-02 1.86E-02 1.86E-02 1.85E-02 1.48E-02 1.11E-02 7.38E-03 7.09E-03 I-132 3.69E-02 3.17E-02 2.72E-02. 2.34E-02 1.61E-02 1.04E-02 5.93E-03 4.90E-03 I-133 4.21E-02 4.14E-02 4.08E-02 4.01E-02 3.16E-02 2.33E-02 1.53E-02 1.45E-02 1-134 6.68E-02 4.49E-02 3.02E-02 2.03E-02 1.10E-02 5.53E-03 2.48E-03 1.61E-03 I-135 3.69E-02 3.50E-02 3.32E-02 3.15E-02 2.39E-02 1.70E-02 1.08E-02 9.84E-03 Kr-83m 1.52E+01 1.26E+0'I 1.04E+01 8.61E+00 5.70E+00 3.54E+00 1.95E+00 1.55E+00 Kr-85m 5.82E+01 5.38E+01 4.98E+01 4.61E+01 3.41E+01 2.37E+01 1.46E+01 1.30E+01 Kr-85 2.01E-01 2.01E-01 2.01E-01 2.01E-01 'I.60E-01 1.20E-01 8.02E-02 7.72E-02 Kr-87 7.39E+01 5.62E+01 4.28E+01 3.25E+01 1.98E+01 1.13E+01 5.73E+00 4.19E+00 Kr-88 1.32E+02 1.16E+02 1.03E+02 9.14E+01 6.48E+01 4.30E+01 2.54E+01 2.17E+01 Kr-89 7.89E+00 1.17E-02 1.75E-05 2.60E-08 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-131m 1.46E+00 1.46E+00 1.45E+00 '.45E+00 1.16E+00 8.69E-01 5.79E-01 5.56E-01 Xe-133m 7.01E+00 6.97E+00 6.92E+00 6.88E+00 5.46E+00 4.07E+00 2.70E+00 2.58E+00 Xe-1 33 2.92E+02 2.91E+02 2.91E+02 2.90E+02 2.31E+02 1.73E+02 1.15E+02 1.10E+02 Xe-135m 1.34E+01 3.42E+00 8.71E-01 2.22E-01 4.52E-02 8.63E-03 1.47E-03 3.59E-04 Xe-135 2.60E+02 2.50E+02 2.41E+02 2.32E+02 1.78E+02 1.29E+02 8.27E+01 7.66E+01 Xe-137 1.26E+01 5.34E 2.27E-04 9.67E-07 3.29E-09 O.OOE+00 O.OOE+00 0.00E+00 Xe-138 5.20E+01 1;19E+01 2.73E+00 6:27E-01 1.1 5E-01 1.98E-02 3.02E-03 6.66E-04 Cs-137 6.50E-04 6.50E-04 6.50E-04 6.50E-04 5.20E-04 3.90E-04 2.60E-04 2.50E-04 10/28/97 NRC Exercise Maniacal

SECTION Vll - RADIOLOGICALCONDITIONS PART F - Reactor Building ARM Readings VII'0/28/97 NRC Exercise Manual

EL:656 18:15 18:45 19:16 19:46 20:15 20:45 21:16 21:45 RHR Room B B 586 8811 11365 13643 15691 17538 19219 20749 RHR Room A A 568 853 1100 1321 1519 1698 1860 2009 RCIC Room C 586 71223 91875 110290 126842 14177.6 155361 167733 HPCI Room D 557 835 1078 1294 1488 1663 1822 1967 RB/RW Sump E 656 985 1270 1525 1754 1960 2148 2319 Area Core Spray D 563 844 1089 1307 1503 1680 1841 1988 EL 670 18:15 18:45 19:15 19:46 20:16 20:45 21:15 . 21:45 Rem. Shdn Rm B 574 862 1112 1334 1535 1715 1880 2029 U-1 RR Acess A 510 765 987 1185 1362 1523 1669 1802 Bay ELEV 719 18:15 18:45 19:15 19:46 20:15 20:45 21:15 21:45 CRD North A 7208 6677 6308 5991 5718 5488 5282 5070 CRD South A 2754 2551 2410 2289 2185 2097 2018 1937 IGITIP Drive Area AR 586 879 1134 1362 1566 1750 1918 2071 M2 6

CRD Repair B 568 853 1100 1321 1519 1698 1860 2009 Room SwgrRoom 522 783 1009 1212 1394 1558 1707 1843 10/28/97 NRC Exercise Manual

ELEV 749 18:15 18:45 19:15 19:45 20:15 20:45 21:16 21:45 RWCU Recirc A 592 888 1146 1375 '582 1768 1937 2091 Area Fuel Pool PP 545 818 1055 1266 1456 1628 1784 1926 Area

'LEV 779 18:15 18:46 19:15 19:45 20:16 20:45 21:15 21:46 Sample Room 598 897 1157 1389 1597 1785 1956 '112 ELEV 799 18 16 18:45 19:16 19:46 20:15 20:45 21:15 21 45 Recirc Fan Room 650 976 1259 1511 1738 1943 2129 2299 ELEV 818 18'16 18:45 19:15 19:45 20:15 20:45 21 15 21 45 Spnt Fuel Crit 557 835 1078 1294 1488 1663 1822 1967 lion Refuel Flr-North 504 756 975 1171 1347 1505 1650 1781 Samp Cask Stor 533 800 1032 1239 1425 1593 1745 1884 New Fuel Crit 486 730 941 1130 1300 1453 1592 1719 lion.

Refuel Flr-West 522 783 1009 1212 1394 1558 1707 1843 Vll-46 10/28/97 NRC Exercise Manual

SECTION Vll - RADIOLOGICALCONDITIONS PART G - Reactor Building High Range ARM Readings VII-47 10/28/97 NRC Exercise Manual

EL 656 18:15 18:45 19:15 19:45 . 20:15 20:45 21:15 21:45 RHR Room B B 586 8811 11365 13643 15691 17538 19219 20749 RHR Room A A 568 853 1100 1321 ~

1519 1698 1860 2009 RCIC Room C 586 71223 91875 110290 126842 141776 155361 167733 HPCI Room D 557 835 1078 1294 1488 1663 1822 1967 RB/RW Sump E 656 985 1270 1525 1754 1960 2148 2319 Area Core Spray 563 844 1089 1307 1503 1680 1841 1988-EL 670 18:15 18:45 19:15 19:45 20:15 20:45 21:15 21:45 Rem. Shdn Rm B 574 862 1112 1334 1535 1715 1880 2029 U-1 RR Acess A 510 765 . 987 1185 1362 1523 1669 '1802 Bay ELEV?19 18:15 18 45 19:15 19 45 20:15 20 45 21:15 21:45 CRD North A 7208 6677 6308 5991 5718 5488 5282 5070 CRD South A 2754 2551 -

2410 2289 2185 2097 2018 1937 IGITIP Drive Area AR 586 879 . 1134 1362 1566 1750 1918 2071 M2 6

CRD Repair B 568 853 1100 1321 . 1519 1698 1860 2009 Room SwgrRoom 522 783 1009 1212 1394 1558 1707 1843 Vll-48 10/28/97 NRC Exercise Manual

ELEV 749 18 15 18 45 19 15 19 45 20 15 20 45 21:15 21 45 RWCU Recirc A 592 888 1146 1375 1582 1768 1937 2091 Area Fuel Pool PP 545 818 1055 1266 1456 1628 1784 1926 Area ELEV 779 18:15 18:45 19:15 19:45 20 16 20:45 21:15 21:46 Sample Room 598 897 1157 1389 1597 1785 1956 2112-ELEV 799 18:15 18:45 19:15 19:45 20:15 20:45 21 l5 21:46

'129 Recirc Fan Room 650 976 1259 1511 1738 1943 2299 ELEV 818 18 15 18 46 19 15 19 45 20 15 20 45 21 15 21 45 Spnt Fuel Crit 557 835 1078 1294 1488 1663 1822 1967 Mon Refuel Flr-North 504 756 975 1171 1347 1505 1650 1781 Samp Cask Stor 533 800 1032 1239 1425 1593 1745 1884 New Fuel Crit 486 730 941 1130 1300 1453 1592 1719 Mon Refuel Flr-West 522 783 =

1009 1212 1394 1558 1707 1843 10/28/97 NRC Exercise Manual .

SECTION VII - RADIOLOGICALCONDITIONS PART H - Control Structure ARM Readings VII-50 10/28/97 NRC Exercise Manual

PENNSYLVANIAPOWER & LIGHTCOMPANY DRILL: 1997 NRC OBSERVED EXERCISE Control Structure 8 Radwaste Area Radiation Monitors 18:15 18:45 19:15 19:45 20:15 20:45 21:15 21:45

'RM-38 'Rad Chemlab. 0.03 0.20 0.30 .

0.30 0.40 0.30 0.20 0.30

'RM-39 'Control Room 0.20 0.20 0.20 0.20 0.20 0.20 0.20 0.20

'AR-01* Cntm Acc Hi Rad-A 345.00 345.00 356.00 2.00E3 2;10E3 2.00E3 1.90E3 1.70E3

'AR-02* Cntm Acc Hi Rad-B 335.00 355.00 359.00 2.00E3 2.20E3 1.90E3 1.80E3 1.60E3

'ARM-37 'Stby Gas Treat Rm 0.03 0.03 0.03 28.00 40.00 56.00 71.00 83.00

'RM-31 'RW 646 Corr-South 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40

'RM-29 'RW 646 Corr-North 0.30 0.30 0.30 0.30 0.30 0.30 0.30 0.30

'RM-30 'RW 646 Corr-West 0.50 0.50 0.50 0.50 0.50 0.50 0.50 0.50

'RM-32 'Ctrl Zone Shop 0.20 0.20 0.20 0.20 0.20 0.20 0.20 0.20

-'RM-34 'Stor & Equip Area 0.20 0.20 0.20 0.20 0.20 0.20 0.20 0.20.

'RM-33 'Radwaste Ctrl Rm 0.40 0.40 0.40 0.40 0.40 0.40 0.40 0.40

'RM-28 'RW Dr to 2 Fl Sa 0.30 0.30 0.30 0.30 0.30 0.30 0.30 '.30 10/28/97 NRC Exercise Manual

SECTION VII - RADIOLOGICALCONDITIONS PART I - Turbine Building ARM Readings VII-52 10/28/97 NRC Exercise Manual

Turbine Building Area Radiation Monitors 18 00 18 15 18 45.. 19 15 19 45 20 15 20 45 21:15 21 45 ARM-17 COND Pump 0.59 0.59 7.00 12.00 11.00 10.00 9.00 8.00 7.7 Area ARM-07 Offgas 2.00 2.00 6.50 11.70 10.40 9.80 8.50 7.90 7.6 Bypass Area ARM-18 RFPT Area 0.43 0.43 0.80 1.10 1.00 0.90 0.80 0.70 0.68 ARM-40 Turb Bldg 0.05 0.05 0.40 0.90 0.80 0.70 0.60 0.50 .

0.47 Access ARM-19 Air Ejector 102.00 102.00 102.00 102.00 106.00 102.00 102.00 102.00 '02.00 Room ARM-20 Fdwtr Heater 0.20 0.20 3.40 8.70 7.90 7.40 6.80 6.10 5.8 Area ARM-21 Reer Mg Set 0.38 0.38 0.60 0.90 0.80 0.80 0.70 0.60 0.56-Area ARM-27 Turb Access 0.10 0.10 OAO 0.70 0.50 0.50 0.40 0.40 -

0.36 Route ARM-24 Turbine Front 0.12 0.12 0.80 1.30 1.10- 0.90 0.80 0.70 0.64 End ARM-22 Gen Bay Area 0.20 0.20 1.20 1.90 1.30 1.10 0.98 0.70 0.62 ARM-23 HVAC Equip 0.07 0.07 7.00 12.00 28.00 37.00 45.00 48.00 - 51.0 Room

SECTION Vll - RADIOLOGICALCONDITIONS PART J - PASS Sample Information VII-54 10/28/97 NRC Exercise Manval

PENNSYLVANIAPOWER & LIGHT COMPANY DRILL: 1997 NRC OBSERVED EXERCISE FUE PASS Wetwell 15 ml Gas Sample Data mR/hr Monitor Monitor RE-507 RE-704 Unshield Unshield Unshield Unshield Shielded . Shielded Shielded Shielded Time Reading Reading at 2 at 6 at 18" at 36" at 2" at 6" at 18" at 36" 18:15 2.75E+00 1.25E+02 9.19E+02 1.50E+02 1.88E+01 4.88 +00 1.42E+02 2.32E+01 2.90E+00 7.54E-01 18:45 2.10E+00 9.57E+01 7.03E+02 1.15E+02 1.44E+01 3.73E+00 .1.09E+02 1.77E+01 2.22E+00 5.77E-01 19:15 1.81E+00 8.24E+01 6.06E+02 9.89E+01 1.24E+01 3.21E+00 9.36E+0'1 1.53E+01 1.91E+00 4.97E-01 19:45 1.60E+00 7.29E+01 5.36E+02 8.75E+01 1.09E+01 2.84E+00 8.28E+01 1.35E+01 1.69E+00 4.39E-01 20:15 1.15E+00 5.21E+01. 3.83E+02 6.26E+01 7.82E+00 2.03E+00 5.92E+01 9.67E+00 1.21E+00 3.14E-01 20:45 7.73E-01 3.51E+01 2.58E+02 4.22E+01 5.27E+00 1.37E+00 3.99E+01 6.52E+00 8.15E-01 2.12E-01 21:15 4.65E-01 2.11E+01 1.55E+02 2.54E+01 3.17E+00 8.25E-01 2.40E+01 3.92E+00 4.90E-01 1.27E-01 21:45 4.06E-01 1.84E+01 1.36E+02 2.21E+01 2.77E+00 7.19E-01 2.09E+01 3.42E+00 4.27E-01 1.11E-01 Vll- 5 10/28/97 NRC Exercise Ma~ ial

PENNSYLVANIAPOWER & LIGHT COMPANY DRILL: 1997 NRC OBSERVED EXERCISE FUE PASS Wetwell Airborne Iodine Sample Data mR/hr Unshield Unshield Unshield Unshield Shielded Shielded Shielded Shielded Monitor Monitor RE-507 RE-704 Tlllle Reading Reading at 2" at 6" at 18" at 36" at 2" at 6" at 18" at 36" 18:15 2.75E+00 6.25E+02 3.84E+03 7.26E+02 9.88E+01 2.63E+01 NIA N/A N/A N/A 18:45 2.10E+00 4.78E+02 2.94E+03 5.56E+02 7.56E+01 2.01E+01 N/A NIA NIA NIA 19:15 1.81E+00 4.12E+02 2.53E+03 4.79E+02 6.51E+01 1.73E+01 NIA N/A N/A N/A 19:45 1.60E+00 3.65E+02 2.24E+03 4.24E+02 5.76E+01 1.53E+01 NIA N/A NIA N/A 20:15 1.15E+00 2.61E+02 1.60E+03 3.03E+02 4.12E+01 1.09E+01 N/A N/A N/A N/A 20:45 7.73E-01 1.76E+02 1.08E+03 .2.04E+02 2.78E+01 7.38E+00 '/A NIA N/A N/A 21:15 4.65E-01 1.06E+02 6.49E+02 1.23E+02 1.67E+01 4.44E+00 N/A N/A N/A NIA 21:45 4.06E-01 9.22E+01 5;66E+02 'l.07E+02 1.46E+01 3.87E+00 N/A N/A N/A NIA VII-56 10/28/97 NRC Exercise Manual

PENNSYLVANIAPOWER & LIGHT COMPANY DRILL: 1997 NRC OBSERVED EXERCISE FUE PASS Suppression Pool Small Volume Liquid mRlhr Unshield Unshield Unshield Unshield Shielded Shielded Shielded Shielded Monitor Monitor RE-507 RE-704 Time Reading Reading at 2" at 6" at 18" at 36" at 2" at 6" at 18" at 36" 18:15 2.76E-01 1.42E+02 1.83E+00 2.99E-01 3.74E-02 9.71E-03 4.88E-02 7.97E-03 9.96E-04 2.59E-04 18:45 2.17E-01 1.12E+02 1.44E+00 2.35E-01 2.94E-02 7.64E-03 3.84E-02 6.27E-03 7.84E-04 2.04E-04 19:15 1.82E.01 9.33E+01 1.20E+00 1.96E-01 2.46E-02 6.38E-03 3.21E-02 5.24E-03 6.55E-04 1.70E-04 19:45 1.56E-01 7.99E+01 1.03E+00 1.68E-01 2.10E-02 5.47E-03 2.75E-02 4 A9E-03 5.61E-04 1.46E-04 20:15 1.36E-01 6.97E+01 8.98E-01 1.47E-01 1.83E-02 4.77E-03 2.40E-02 3.91E-03 4.89E-04 1.27E-04 20:45 1.20E-01 6.16E+01 7.94E-01 1.30E-01 1.62E-02 4.21E-03 2.12E-02 3.46E-03 4.32E-04 1.12E-04 21:15 1.07E-01 5.50E+01 7.09E-01 1.16E-01 1.45E-02 1.89E-02 '.76E-03 3.09E-03 3.86E-04 1.00E-04 21:45 9.67E-02 4.96E+01 6.40E-01 1.04E-01 1.31E-02 3.40E-03 1.71E-02 2.79E-03 3.48E-04 9.06E-05 VI 10/28/97 NRC Exercise ~ ~al

PENNSYLVANIAPOWER & LIGHT COMPANY DRILL: 1997 NRC OBSERVED EXERCISE FUE PASS Suppression Pool Large Volume Liquid mR/hr Unshield Unshield Unshield Unshield Shielded Shielded Shielded Shielded Monitor Monitor RE-507 RE-704 Time Reading Reading at 2" at 6" at 18" at 36" at 2" at 6." at 18" at 36" 18:15 2.76E-01 1.42E+02 1.83E+02 2.99E+01 3.74E+00 9.71E-01 6.10E-02 9.96E-03 1.25E-03 3.24E-04 18:45 2.17E-01 1.12E+02 1.44E+02 2.35E+01 2.94E+00 7.64E-01 4.80E-02 7.84E-03 9.80E-04 2.55E-04 19:15 1.82E-01 9.33E+01 1.20E+02 1.96E+01 2.46E+00 6.38E-01 4.01E-02 6.55E-03 8.18E-04 2.13E-04 19:45 1.56E-01 7.99E+01 1.03E+02 1.68E+01 2.10E+00 5.47E-01 3.44E-02 5.61E-03 7.01E-04 1.82E-04 20:15 1.36E-01 6.97E+01 8.98E+01 1.47E+01 1.83E+00 4 77E-01 2 99E 02 4.89E-03 6.11E-04 1.59E-04 20:45 1.20E-01 6.'16E+01 7.94E+01 1.30E+01 1.62E+00 4.21E-01 2.65E-02 4.32E-03 5.40E-04 1.40E-04 21:15 1.07E-01 5.50E+01 7.09E+01 1.16E+01 1:45E+00 3.76E-01 2.36E-02 3.86E-03 4.83E-04 1.25E-04 21:45 9.67E-02 4.96E+01 6.40E+01 1.04E+01 1.31E+00 3.40E-01 2.13E-02 3.48E-03 4.35E-04 1.13E-04 VII-58 10/28/97 NRC Exercise Manual

PENNSYLVANIAPOWER & LIGHT COMPANY DRILL: 1997 NRC OBSERVED EXERCISE FUE PASS Reactor Water Small Volume Liquid mRlhr Unshield Unshield Unshield Unshield Shielded Shielded Shielded Shielded Monitor Monitor RE-507 RE-704 Reading Reading at 2" at 6" at 18" at 36" at 2" at 6" at 18" at 36" 8.21E+00 4.22E+03 5.44E+01 8.88E+00 1.11E+00 2.89E-01 1.45E+00 2.37E-01 2.96E-02 7.70E-03 6.34E+00 3.26E+03 4.20E+01 6.86E+00 8.57E-01 2.23E-01 1.12E+00 1.83E-01 2.29E-02 5.94E-03.

5.41E+00. 2.78E+03 3.58E+01 5.85E+00 7.32E-01 1-.90E-01 9.56E-01 1.56E-01 1.95E-02 5.07E-03 4.75E+00 2.44E+03 3.14E+01 5.13E+00 6.41E-01 1.67E-01 8.38E-01 1.37E-01 1.71E-02 4.45E-03 4.21E+00 2.16E+03 2.79E+01 4.55E+00 5.69E-01 1.48E-01 7.44E-01 1.21E-01 1.52E-02 3.95E-03 3.77E+00 1.94E+03 2.50E+01 4.08E+00 5.09E-01 1.32E-01 6.66E-01 1.09E-OI 1.36E-02 3.53E-03 3.39E+00 1.74E+03 2.25E+01 3.67E+00 4.59E-01 1.19E-01 5.99E-01 9.79E-02 1.22E-02 3.18E-03 3.07E+00 1.58E+03 2.03E+01 3.32E+00 4.15E-01 1.08E-01 5.43E-01 8.86E-02 1.11E-02 2.88E-03 VII- 10/28/97 NRC Exercise Maniacal

PENNSYLVANIAPOWER 8 LIGHT COMPANY DRILL: 1997 NRC OBSERVED EXERCISE PASS Reactor Water Large Volume Liquid

, mR/hr Unshield Unshield Unshield Unshield Shielded Shielded Shielded Shielded Monitor Monitor RE-507 RE-704 Time Reading Reading at 2" at 6" at 18" at 36" at 2" at 6" at 18" at 36" 18:15 8.21E+00 4.22E+03 5.44E+03 8.88E+02 1.11E+02 2.89E+01 1.81E+00 2.96E-01 3.70E-02 9.62E-03 18.45 6.34E+00 3.26E+03 4.20E+03 6.86E+02 8.57E+01 2.23E+01 1.40E+00 2.29E-01 2.86E-02 7.43E-03 19:15 5.41E+00. 2.78E+03 3.58E+03 5.85E+02 7.32E+01 1.90E+01 1.19E+00 1.95E-01 2.44E-02 6.34E 19:45 4.75E+00 2.44E+03 3.14E+03 5.13E+02 .6.41E+01 1.67E+01 1.05E+00 1.71E-01 2.14E-02 5.56E-03 20:15 4.21E+00 2.16E+03 2.79E+03 4.55E+02 5.69E+01 1.48E+01 9.30E-01 1.52E-01 1.90E-02 4.93E-03 20:45 3.77E+00 1.94E+03 2.50E+03 4.08E+02 5.09E+01 1.32E+01 8.32E-01 1.36E-01 1.70E-02 4.42E-03 21:15 3.39E+00 1.74E+03 2;25E+03 3.67E+02 4.59E+01 1.1 9E+01 7.49E-01 1.22E-01 1.53E-02 3.98E-03 21:45 3.07E+00 1.58E+03 2.03E+03 3.32E+02 4.15E+01 1.08E+01 6:78E-01 1.11E-01 1.38E-02 3.60E-03 VII-60 10/28/97 NRC Exercise Manual

SECTION Vll - RADIOLOGICALCONDITIONS PART K - In-Plant Radiological Conditions Section 1 -. Turbine Building Rad Conditions VII-61 10/28/97 NRC Exercise Manual

RAD.Chart C1 - TURBINE BUILDING RAD LEVELS When condenser vacuum is lost, a laige portion of the activity that has leaked through the MSIVs and ended up in the condenser will leak out the turbine seals or be drawn out by -the Gland Exhauster. In either case the activity will be discharged to atrriosphere directly by the Turbine Building exhaust ventilation. A very small portion of the activity from the condenser will leak into the contaminated portion of the Turbine Building ventilation and an even smaller portion will end up in the non-contaminated portion of the Turbine Building ventilation.

The portion of activity that leaks into the general area (non-contaminated portion) of the Turbine Building will cause the general areas in the Turbine Building to increase to approximately 1 mr/hr. The levels of airborne and radiation in the uncontrolled areas of the Turbine Building are one tenth the levels in the controlled or contaminated areas of the Turbine Building. See attached chart radiation levels. The increased activity in the Turbine Building will cause any friskers and or PIOPs to alarm and also inop the PCMs due to high background.

The Rad levels in the Control Structure chem lab and first floor will increase to 0.5 - 1.0 mr/hr. This will cause any friskers set up to alarm and inop the PCMs.

The portion of activity that leaks into the controlled areas (contaminated portions) of the Turbine Building will cause the general radiation levels to increase to approximately 15 mr/hr maximum. See the attached chart for radiation levels in the areas of the Turbine Building.

The isotopic concentrations in the Turbine Building are as follows:

The Noble Gas concentration in the controlled area of the Turbine Building is approximately 8.0E-06 pCi/cc and Iodine is approximately 7.0E-10 pCi/cc.

I-131 6.36E-11 Kr-88 1.25E-06 I-132 1.26E-10 Kr-89 7.51E-08 I-133 1.44E-10 . Xe-131m 1.39E-08 I-134 2.28E-10 Xe-133m 6.67E-08 I-135 1.26E-10 Xe-133 2.78E-06 Kr-83M 1.44E-07 Xe-135m 1.28E-07 Kr-85M 5.54E-07 Xe-135 2.47E-06 Kr-85 1.91E-09 Xe-137 1.20E-07 Kr-87 7.04E-07 Xe-138 4.94E-07 Cs-137 1.89E-13 VII-62 10/28/97 NRC Exercise Manual

At 1845 the friskers and CAMs in the Unit 1 Turbine Building'will alarm and the Chemistry count lab will be unavailable to use due to high background. The Health Physics lab in the Unit 2 access area will be unavailable to analyze samples due to shine from the 'plume.

VII-63 10/28/97 NRC Exercise Manual

Chart 51 Turbine Building Controlled Area Radiation and Airborne Levels CONTROLLED AREA OF TB TIIIE 'R/hr IODINE pCI/ML IODINE DAC NG pCI/ML NG DAC 15:00 to 18:15 NORMAL NORMAL NORMAL NORMAL NORMAL 18:15 to 18:45 3.18E+00 6.86E-10 4.58E-02 8.81E-06 8.81E+00 18:45 to 19:15 1.50E+01 3.52E-09 2.35E-01 4.59E-05 4.59E+01 19:15 to 19:45 1.31E+01 3.07E-09 2.35E-01 4.28E-05 4.28E+01 19:45 to 20:15 1.17E+01 2.74E-09 2.05E-01 4.06E-05 4.06E+01 20:15 to 20:45 1.05E+01 2.49E-09 1.83E-01 3.86E-05 3.86E+01 20:45 to 21:15 9.47E+00 2.30E-09 1.66E-01 3.69E-05 3.69E+01 21:15 to 21:45 8.62E+00 2.14E-09 1.53E-01 3.55E-05 3.55E+01 21:45 to 22:15 7.86E+00 2.01E-09 1.43E-01 3.42E-05 3.42E+01 AIR SAMPLE DATA To determine the Turbine Building. isotopic activity of simulated collected air samples, multiply the DAC values listed on the area radiation charts by the percentages listed below for the given isotopes.

ISOTOPE  % X DAC VALUES ON  % X DAC VALUES ON PRESENT SURVEY MAPS ISOTOPE PRESENT SURVEY MAPS I-131 33% KR-85M 1%

I-132 10 KR-85 1%

I-133 33% KR-87 1%

I-134 10% KR-88 1%

I-135 10% XE-133 1%

XE-135 1%

PERSONNEL AND E UIPMENT CONTAMINATION To determine the extent of individual and equipment contamination in the Turbine Building for individu'al and equipment in the area for greater than 10 minutes:

Multiply the DAC as determined from the chart, by 10 for the resultant contamination in CPM.

VII-64 10/28/97 NRC Exercise Manual

SECTION Vll - RADIOLOGICALCONDITIONS PART K - In-Plant Radiological Conditions Section 2 -.Reactor Boilding Rad Conditions VII-65 10/28/97 NRC Exercise Manual

Chart ¹2 Reactor Building Radiation and Airborne Levels REACTOR BUILDING AIR SAMPLE DATA To determine the Reactor Building isotopic activity of simulated collected air samples, multiply the DAC values listed on the area radiation charts by the percentages listed'below for the given isotopes.

'ISOTOPE  % X DAC VALUES ON  % X DAC VALUES ON PRESENT SURVEYIIAPS ISOTOPE PRESENT SURVEY MAPS I-131 33% KR-85M 1%

I-132 10 KR-85 I-133 33% KR-87 l-134 10% KR-88 1%

I-135 10% XE-133 1%

XE-135 1%

PERSONNEL AND E UIPMENT CONTAMINATION To determine the extent of individual and equipment contamination in the Reactor Building for individual and equipment in the area, for greater than 10 minutes:

Multiply the DAC as determined from the survey maps, by 10 for the resultant contamination in CPM.

EXAMPLE: Rx Bldg (except 'B'HR room) af 20:15 4656 (DAC) X 10 = 4.5E5 CPM Notes: AIRBORNE AND DOSE RATES ARE 1/10th IN STAIRWAYS.

Contact door dose rates are 1/10th of room values VII-66 10/28/97 NRC Exercise Manual

Reactor Building Airborne Concentrations and DACs for 10 GPM Leakage Airborne Values for all areas except 'B'HR Rm 18:15 18:45 19:16 19:45 . 20:15 20:46 21:15 21:45 iodine pc/ml 5.99E-05 6.66E-05 7.25E-05 7.77E-05 8.25E-05 8.69E-05 9.10E-05 9.48E-05 iodine DAC 3993 4442 4833 5183 5500 5792 6065 6322 NG NC/ml 1.45E-03 2.32E-03 3.14E-03 3.92E-03 4.66E-03 5.36E-03 6.04E-03 6.70E-03 NG DAC 1446 2324 3142 3917 4656 5362 6041 6696

'irborne Values for

'B'HR Rm 1815 1845 1915 1945 . 2015 2045 21:15 21:45 iodine pc/ml 1.08E-04 1.20E-04 1.31E-04 1.40E-04 1.48E-04 1.56E-04 1.64E-04 1.71E-04 iodine DAC 7188 7996 8700 9329 '899 10426 10917 11379 NG NC/ml 3.05E-03 4.90E-03 6.63E-03 8.26E-03 9.82E-03 1.13E-02 1.27E-02 1.41E-02 NG DAC 3051 - 4904 6629 8265 9823 11314 12747 14128 Note: The above table is for 10 GPM leakage from the RHR suction relief valve. Divide all values by 10 for 1 GPM leakage from the relief valve.

10/28/97 NRC Exercise Manual

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36 EL 670 TIME Map Area 18:15 18:45 19:15 19:45 20:15 20:45 21:15 21:45 Rem. Shdn Rm 574 862 1112 1334 1535 1715 1880 2029 U-1 RR Acess Bay B 510 765 987 1185 1362 1523 1669 1802 HPCl/RCIC Tunnel A 545 818 1055 1266 1456 1628 1784 1926 Oose rate in mRem/hr VII-7;

EL 645 TIME Map Area 18:15 18:45 19:15 19:45 20:15 20:45 21:15 21:45 RHR Room B B 586 8811 11365 13643 15691 17538 19219 20749 RHR Room A A 568 853 1100 1321 1519 1698 1860 2009 RClC Room C 586 71223 91875 '110290 126842 141776 155361 167733 Cl Room, D 557 835 1078 1294 1488 1663 1822 1967

/RW Sump Area E 656 985 1270 1525 1754 1960 2148 2319 Core Spray D $ 63 844 1089 1307 '503 1680 1841 1988 Dose rates in mRem/hr C QPg SPRAT s ~ IC o o OXC %1lT

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~, 18:45 6.66E-05 4442 19:15 7.25E-05 4833 19:45 7.77E-05 5183 20:15 8.25E-05 5500 8.69E-OS 5792 21:15 9.10E-05 6065 21:45 9.48E-05 6322 NG uC/ml 1.45E-03 2.32E-03 3.14E-03 3.92E-03 4.66E-03 5.36E-03 6.04E-03 6.70E-03 NG DAC 1446 2324 3142 3917 4656 5362 6041 6696 Airborne Values for 'B'HR Rm 18:15 18;45 19:15 19:45 20:15 20:45 21:15 21:45

'odine uC/ml 1.08E-04 1.20E-04 1.31E-04 1.40E-04 1.48E-04 1.56E-04 1.64E-04 1.71E-04 iodine DAC 7188 7996 8700 9329 9899 10426 10917 11379 NG uC/ml 3.05E-03 4.90E-03 6.63E-03 8.26E-03 9.82E-03 1.1 3E-02 1.27E-02 1.41E-02 NG DAC 3051 4904 6629 8265 9823 11314 12747 14128

SECTION VIII MESSAGE SHEETS VIII-1 10/28/97 NRC Exercise Manual

IS No. 1 Time: 1500 MESSAGE INFORMATION SHEET MESSAGE FOR: Operations Personnel in Control Room MESSAGE FROM: Control Room Controller LOCATION: Training Center Simulator MESSAGE: "THIS IS A DRILL." The Initial Conditions of the plant are contained in SECTION Vl of the Controller Manual. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: This material provides the initial conditions of the plant for the participants. Included in this section are the ISES Daily Report, previous logs and turnover sheets.

EXPECTED ACTIONS: The Participants will process the information as a normal shift briefing.

VIII-2 10/28/97 NRC Exercise Manual

IS No. 2 Time: 1500 MESSAGE INFORMATION SHEET MESSAGE FOR: Phone Company Personnel MESSAGE FROM: Lead Controller LOCATION: SBA phone room and Simulator Control Room MESSAGE: "THIS IS A DRILL." SBA phone room telephone number-3999. Hook up the Exercise communications equipment in the S8A phone room and the simulator control room, both the page and the telephones.

Ensure the phones are hooked up and the plant radio is activated in the simulator control room.

Test the Plant Page from the Simulator. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY.

CONTROLLER NOTES: The communications equipment needs to be set up prior to the start of the exercise.

EXPECTED ACTIONS: The systems will be checked out prior to the start of the

. exercise.

VIII-3 10/28/97 NRC Exercise Manual

IS No. 3 Time: 1500 MESSAGE INFORMATION SHEET MESSAGE FOR: Simulator Instructor MESSAGE FROM: Controller Manual LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL.." Initialize simulator to IC XXX, FILE: XXX)00( "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The IC sets the initial conditions supported by the annunciator, operator logs, turnover sheets, etc.

EXPECTEDACTIONS: Check the .alarms against the annunciator log, check equipment status of simulator versus status sheets, verif'y SPDS rad points active, verify weather conditions per Radiological section, verify ARMs are active and Unit 2 electrical line up.

Vill-4 10/28/97 NRC Exercise Manual

IS No.4 Time: 1530 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room and Onsite Personnel MESSAGE FROM: Operations in the plant Control Room LOCATION: Control Room MESSAGE: "THIS IS A DRILL." The 1997 NRC Observed Exercise has begun. All exercise communications shall begin with "This is a Drill" and end with "This is a Drill." Line 3 of the plant page system is to be used for the exercise. Exercise Controllers please mark the time as . "THIS IS A DRILL."

REPEAT ABOVE MESSAGE.

FOR CONTROLL'ER USE ONLY CONTROLLER NOTES: This message is to be passed over the Plant PA system by Operations from the on site Control Room to note the beginning of the exercise.

The time should be obtained from the Security Controller at the ASCC.

The Control Room should contact the NRC Operations Center via the ENS and inform them by way of a courtesy call that the site will be doing an NRC Observed emergency exercise.

EXPECTED ACTIONS: Message to be announced over plant page system on line 3.

The message shall be announced from the actual Control Room.

VIII-5 10/28/97 NRC Exercise Manuai

IS No. 5 Time: 1620 MESSAGE INFORMATION SHEET MESSAGE FOR: Simulator Control Room 0 erators MESSAGE FROM: Plant 0 erator LOCATION: Simulated 'B'HR um room MESSAGE: "THIS IS A DRILL." This is down at the 'B'HR Pum room. I will be unisolatin the floor drains to drain the accumulated service water leaka e from the 'B'HR Heat Exchan er. "THIS IS A DRILL" FOR CONTROLLER USE ONLY CONTROLLER NOTES: The drainin of'the RHR Room is to su ort later events in the scenario when the RHR suction relief lifts and remains o en. The RHR room drains will remain o en until the or anization initiates an investi ation or someone remembers that the floor drains are o en.

EXPECTED ACTIONS: The Control Room 0 erator will rant ermission to drain the room.

VIII-6 10/28/97 NRC Exercise Manual

IS No. 65 Time: 1625 MESSAGE INFORMATION SHEET MESSAGE FOR: Simulator Control Room Operators MESSAGE FROM: Fire Controller LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." This is down at the S&A Building loading dock . My tractor is on fire here, I have discharged both of my fire extinguishers on it and I can't get it out, I need some help. "THIS IS A DRILL" Additional information for the control room if requested:

Location of Tractor - preparing to hook up to the water tank parked by the S&A loading dock.

Cause of fire - fuel leak in engine compartment, fire threatening to engulf the entire engine compartment.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The Fire Controller will provide all of the information to the Fire Brigade Leader such that the fire scenario will appear transparent to the personnel in the simulator Control Room. The fire scenario is not a demonstration of the Fire Brigade functions, the scenario is to drive a classification. The Control Room will receive information of a fire outside Unit 1 East Turbine Building Trackway between S&A Building and'Diesel Generator Building from the "simulated" driver of the truck calling the Control Room on the plant page.

EXPECTED ACTIONS: The Control Room Operators will dispatch an operator to investigate the information received. The Shift Supervisor will activate the Fire Brigade and review the EALs to support the decision to make an emergency classification.

VIII-7 10/28/97 NRC Exercise Manual

IS No. 76 Time: 1625 MESSAGE INFORMATION SHEET MESSAGE FOR: AUS/OSC Coordinator/Fire Brigade Leader MESSAGE FROM: Fire Controller LOCATION: S&A Building MESSAGE: "THIS IS A DRILL.". The indications at the scene of the fire are:

Tractor engine compartment on fire due to diesel fuel leak spreading to engulf the cab of the tractor.

Smoke from the fire swirling and rising, filling the area between the Turbine, S&A and Diesel building. A portion of the smoke appears to be entering the Turbine Building via the HVAC intake. Smoke in the S&A, and Turbine Building is simulated for the control room by simplex fire detection alarms being activated.

Activation of the drypipe system will occur at 1635 as simulated for the control room by a simplex alarm and auto start of the fire pump.

Additional information will be provide as needed by the Fire Controller to the Fire Brigade Leader for feedback to the Control Room. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The Fire Brigade Leader will be provided information based on his/hers actions. The Fire Controller will provide the information. The Fire Controller will discuss with the, Fire Brigade Leader what the fire scene is intended to look like and the actions that would be taken. If offsite support is requested, the request will be blocked at Security and it will be simulated by the ASCC. The ASCC will provide information as requested concerning ETA of the fire apparatus.

The Security Lead Controller will provide an ETA of 10 to 15 minutes from the time offside fire support is requested The fire brigade will be simulated and all the information will be provided by the Fire Controller. The fire controller will point out that smoke for this type of fire would be heavy and that it has the potential to enter the D/G building, S&A and Turbine Buildings.

EXPECTEDACTIONS: The Fire Brigade Leader will provide information to the Control Room/Shift Supervisor.

VIII-8 10/28/97 NRC Exercise Manual

IS No. 87-Time: 1630 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operator MESSAGE FROM: Simulator,Instructor.

LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." Simulator instructor to initiate FILE NNXX. The file will initiate indication of a SIMPLEX alarm for the S&A Building fire alarm panel

'Fire Detection X232 Z7).

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The simplex alarm received in the control room will indicate a panel alarm for the S&A fire protection panel OC707 (Fire Detection X232 Z7).

The alarm is being received due to smoke entering the S&A Building.

EXPECTED ACTIONS: The Control Room operators inform the Shift Supervisor of the alarm who will recognize that smoke is entering the S&A Building and will probably enter the Turbine Building.

VIII-9 10/28/97 NRC Exercise Manual

IS No. SS Time: 1635 MESSAGE INFORMATION SHEET MESSAGE FOR: OSC.Coordinator MESSAGE FROM: FIRE CONTROLLER SIMULATINGFire Brigade LOCATION: SBA Building MESSAGE: 'THIS IS A DRILL." The Controller will provide information to the OSC Coordinator/Fire Brigade leader based on actions taken/discussed with the controller.

., "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The elapsed time for different actions will be at the discretion of the controller but will simulate as close as possible the actual elapsed times that could be expected. The time line shows the times of alarms that will be initiated in the Control Room. The intent of this portion of the scenario is to force an ALERT cIassification.

EXPECTEDACTIONS: The Fire Brigade Leader will provide information to the Control Room of what is occurring at the scene.

. VIII-10 10/28/97 NRC Exercise Manual

IS No. 100 Time: 1635 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operator MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." Simulator instructor to initiate FILE )GOOD(. The file will initiate indication of a SIMPLEX Panel alarm for activation of the dry pipe fire protection (DPS-011) (Fire Suppression X234 Z7).

"THIS IS A DRILL."

FOR CONTROL'LER USE ONLY CONTROLLER NOTES: The simplex alarm received in the control room will indicate activation of the drypipe fire protection system and auto start of the fire pump.

EXPECTED ACTIONS: The Control Room operators inform the Shift Supervisor of the alarm.

VIII-11 10/28/97 NRC Exercise Manual

IS No. 110 Time: 1640 MESSAGE INFORMATION SHEET MESSAGE FOR: AUS/OSC Coordinator/Fire Brigade Leader MESSAGE FROM: Fire Controller LOCATION: S&A Building MESSAGE: "THIS IS A DRILL." The indications at the scene of the fire are:

Tractor cab engulfed in flames.

Smoke from the fire swirling and rising, filling the area between the Turbine, S&A and Diesel building. A portion of the smoke appears to be entering the 'D'iesel Generator Building and the Turbine Building via the HVAC intake. Smoke in the S&A has been simulated for the control room by simplex fire detection alarms at this time.

Activation of the drypipe system occurred at 1635 as simulated for the control room by a simplex alarm and auto start of the fire pump.

The tires of the tractor are reported to be burning causing significant smoke at this time. "THIS. IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The Fire Brigade Leader will be provided information based on his/her actions. The Fire Controller will provide the information.

EXPECTEDACTIONS: The Fire Brigade Leader will provide information to the Control Room/Shift Supervisor.

VIII-12 10/28/97 NRC Exercise Manuai

IS No. 124.

Time: 1641 MESSAGE INFORMATION SHEET MESSAGE FOR: AUS/OSC Coordinator/Fire Brigade Leader MESSAGE FROM: Fire Controller LOCATION: SBA Building MESSAGE: "THIS IS A DRILL." The indications at the scene of the fire are:

Several compressed gas cylinders in close proximity to the fire have ruptured their rupture diaphragms.

. It appears that none of the cylinders contain flammable material.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The Fire Brigade Leader will be provided information based on his/her actions. The Fire Controller will provide the information.

EXPECTEDACTIONS: The Fire'Brigade Leader will provide information to the Control Room/Shift Supervisor. The Shift Supervisor will consider isolating building ventilation after already received word of smoke in the Turbine Building.

VIII-13 10/28/97 NRC Exercise Manual

IS No. 132 '

Time: 1645 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operator MESSAGE FROM: Chemistry Controller LOCATION: Control Structure Chem Lab MESSAGE: "THIS IS A DRILL." This is the chem lab. I can smell something burning and there is smoke coming through the HVAC. I think there is a fire somewhere.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The call is to get the Control Room to get the operators to think about smoke intake into the Turbine Building from the fire scene.

EXPECTED ACTIONS: The Control Room operators inform the Shift Supervisor of the call and consider beginning an investigation of the Turbine Building to ensure there is not a fire in the Turbine Building.

Vill-14 10/28/97 NRC Exercise Manual 0

IS No. 148 Time: 1650 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operator MESSAGE FROM: Control Cell Simulating Turbine Building Worker LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." This is I was just on the Turbine Deck on the Unit 1 side by the MG-Sets and I could smell burning rubber and fuel oil, the smoke was pretty heavy up there, looks and smells like there is a fire somewhere up there.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The call is to get the Control Room to think about smoke intake into the Turbine Building from the fire scene.

EXPECTED ACTIONS: The Control Room operators inform the Shift Supervisor of the call and consider beginning an investigation of the Turbine Building to ensure there is not a fire somewhere in the Turbine Building..

VIII-15 10/28/97 NRC Exercise Manual

IS No. 154 Time: 1655 MESSAGE INFORMATION SHEET MESSAGE FOR: AUS/OSC Coordinator/Fire Brigade Leader MESSAGE FROM: Fire Controller LOCATION: SBA Building MESSAGE: "THIS IS A DRILL." The indications at the scene of the fire are:

The Fire Protection Engineer is on station and reports that the gas cylinders on the loading dock are actually chiller refrigerant, which if exposed to high temperatures will become phosgene gas, which can be lethal.

The Fire Protection Engineer also reports that it appears smoke is being drawn into the Turbine Building ventilation intake.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: This specific information is the trigger for an ALERT classification. Information has already been received that there is smoke in the S8A and Turbine Buildings. The new information of hazardous gas will immediately cause the Shift Supervisor to review toxic gases EAL.

EXPECTEDACTIONS: The Fire Brigade Leader will provide information to the Control Room/Shift Supervisor. The Shift Supervisor will declare an ALERT and initiate local area evacuations.

VIII-16 10/28/97 NRC Exercise Manual

IS No. 165 Time: 1705 MESSAGE INFORMATION SHEET MESSAGE FOR: Shift Supervisor MESSAGE FROM: Lead Controller LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The present situation needs to be classified as an ALERT at this time.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The scenario must support the time line agreed upon with the State and FEMA. If the ALERT. classification is not declared by 1700 the SS will be prompted to make the classification.

The prompt will be noted on the evaluation sheet for the critique process.

EXPECTEDACTIONS: The SS will initiate the actions required for an ALERT classification including activation of the NERO.

VIII-17 10/28/97 NRC Exercise Manuai

'S No. 176 Time: 1710 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operator MESSAGE FROM: CONTROL CELL SIMULATINGl8C LOCATION: Reactor Building MESSAGE: "THIS IS A DRILL." The Control Cell will relate the following information:

Control Room, this is in the field performing Sl-000-00 and we are preparing to do step ¹ which will give you a half scram on Channel . Upon completion of the step be prepared to reset the half scram. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The l8C control cell call is preparation for the half scram which will occur later in the exercise to set up the fuel damage. It is not feasible for the control room to entertain performing any surveillances at this time and will inform l8 C of that fact.

A EXPECTED ACTIONS: The control operator will notify the Shift Supervisor and the SS will direct I8 C to not continue with the surveillance.

VIII-18 10/28/97 NRC Exercise Manual 0

IS No. 187-Time: 1715 MESSAGE INFORMATION SHEET MESSAGE FOR: AUS/OSC Coordinator/Fire Brigade Leader MESSAGE FROM: Fire Controller LOCATION: S&A Building MESSAGE: "THIS IS A DRILL.". The indications at the scene of the fire are:

The fire is out.

Fire Brigade Leader requests permission to isolate DPS-001 (close OS&Y) which will cause trouble, alarm from OC707 trbl pnt X234 Z2 (AR-SP-003).

Fire Brigade Leader to report that a check for fire extension will be initiated for the S&A and D/G Building, a fire watch is being set and the fire pump can be shut down when the OS&Y is shut.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: This information wraps up the fire but there needs to be an investigation performed of a potential extension of the fire in the S&A and D/G building. The fire scene will need to be cleaned up with the dry pipe system restored. An investigation of the hazmat situation will also need to be initiated.

EXPECTEDACTIONS: The Fire Brigade Leader will provide information to the Control Room/Shift Supervisor.

VIII-19 10/28/97 NRC Exercise Manual

IS No. 198 Time: 1730 MESSAGE INFORMATION SHEET MESSAGE FOR: AUS/OSC Coordinator/Fire Brigade Leader MESSAGE FROM: Fire Controller LOCATION: S&A Building MESSAGE: "THIS IS A DRILL." The Fire Brigade Leader reports to the Control Room that a check for fire extension has been completed with no additional signs of damage.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: This information wraps up the fire. The investigation of the hazmat situation will need to be completed.

EXPECTEDACTIONS: The Fire Brigade Leader will provide information to the Control Room/Shift Supervisor.

VIII-20 10/28/97 NRC Exercise Manval

IS No. 2049 Time: 1730 MESSAGE INFORMATION SHEET MESSAGE FOR: ASCC Security Controller I

MESSAGE FROM: Lead Security Controller LOCATION: ASCC MESSAGE: "THIS IS A DRILL." There WILL be an actual site accountability. The accountability will be conducted and the results will be reported back to the Control Room.

The Security Controller will need to monitor the activities of the security officers performing the accountability to ensure actions taken do not impede any actual plant operations; Search and Rescue is not an objective to be demonstrated during this exercise. If an individual is found to be missing during the accountability the missing individuals supervisor will be instructed'to locate the individual and report same back to Security. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The objectives for site accountability are required to be fulfilled for this drill.

EXPECTED ACTIONS: The Security Coordinator or ASCC Controller will inform the, Control Room when the accountability is complete.

VIII-21 10/28/97 NRC Exercise Manual

IS No. 210 Time: 1730 MESSAGE INFORMATION SHEET MESSAGE FOR:, Shift Supervisor MESSAGE FROM: Simulator Controller LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." When the accountability is complete allow the people not required for exercise participation to be released back to their normal work assignments. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: With the accouritability complete, the workers may return to their normal assignments.

EXPECTED ACTIONS: The announcement to secure from the accountability will be made.

VIII-22 10/28/97 NRC Exercise Manual

IS No. 224 Time: 1805 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operator MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." Simulator instructor to initiate FILE EPLANXXXXX, kg, d XXXXXXXX) ip f th

~ 2 I,

half'cram and (IMF FU01: 1C609 F18A OUT) blown fuse, and (IMF RR179003 (trigger 0 0) 100 5:00 0) fuel damage, and Stuck Control Rod 22-(IMP~)

33 (INIF XXXX)gtX) ith LPNNI high d

'N't(NNW d (IMP XXXXXXXX)IINIP p

I it kg, p, 3 p d (IMF f th Containment radiation monitors such that they will exceed 2000 r/hr at 1930(EPLAN95IPEPC).

The file will initiate indication of a partial scram. This event will cause fuel damage and be the trigger for a SITE AREA EMERGENCY classification based on EAL 3.3 Fuel Clad Degradation.

"THIS IS A DRILL."

FOR CONTROL'LER USE ONLY CONTROLLER NOTES: The reactor pressure will increase due to the plant being at power and the MSIVs closed which will result in SRVs discharging to the suppression pool. The suppression pool pressure will increase due to the non condensables and periodically relieve back to the Drywell. The leak back will cause alarm annunciation for the Drywell vacuum breakers.

When the Drywell/Suppression Pool vacuum breakers lift, the suction relief on the 'A'HR pump will lift and fail to reseat. The lifting relief valve will cause an increase in the Reactor Building vent monitor.

The first indication in the Control Room will be a half scram. The half scram is a result of I8 C restoring from the Sl-XXX-XX-XXsee message IS-8.

Shortly after the half scram is received, a fuse in the RPS power supply to the scram solenoid valves blows causing a quarter scram and subsequent full scram signal.

VIII-23 10/28/97 NRC Exercise Manual

The 1/4 scram caused a hydraulic lock of the Scram Discharge Volume preventing a portion of the control rods to insert. at the time of the full scram signal which causes fuel damage.

The fuel damage is manifested by high radiation in the main steam lines and closure of the'MSIVs, 35 scfm leakby.

The loss of Reactivity Control is an EAL which is equivalent to an Alert classification; the fuel damage will trigger a Site Area Emergency based on containment radiation levels exceeding 400 R/hr.

The immediate operator action will be to initiate Standby Liquid Control to shut down the reactor and the ES procedure to drain the Scram discharge volume and rescram the plant.

The operators will pay close attention to the Main Steam Line Radiation Monitors, the vent stack monitors, Area Radiation Monitors, and room temperatures to determine the severity and spread of activity.

When the control room personnel note the increased release rate from the Reactor Building Vent Monitor, they will place SBGT in service.

EXPECTED ACTIONS: The operators will follow their emergency operating procedures to place the plant in a safe configuration. The initial actions will be to shutdown the reactor, then address pressure and level, and then the containment integrity.

VIII-24 10/28/97 NRC Exercise Manual

'IS No. 232 Time: 1805 MESSAGE INFORMATION SHEET MESSAGE FOR: OSCAR Monitoring Team MESSAGE FROM: OSCAR Monitoring Team Controller LOCATION: In Field MESSAGE: "THIS IS A DRILL." The radiological data for the OSCAR teams is located in section seven (7) of the exercise manual. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The monitoring teams will be given information (raw data) based on sampling piocedures/techniques, location in the field relative to plume centerline, and questions asked.

The TSC, when dispatching the OSCAR Team, will note any change in the wind direction and the resultant risk to the site. The weather conditions for the exercise are canned. The weather information will be available to the TSC and EOF participants on the PICSY displays. Files have been loaded into the simulator computer based on actual weather conditions on July 10, 1997.

EXPECTEDACTIONS: The TSC HP Radioman is expected to dispatch OSCAR down wind from the plant which will be in the south sector.

VIII-25 10/28/97 NRC Exercise Manual

IS No. 248 Time: 1815 MESSAGE INFORMATION SHEET ~

MESSAGE FOR: Control Room Operator MESSAGE FROM: Simulator Instructor.

LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." Simulator instructor to initiate FILE EPLANXXXXX,to simulate the suction relief on the 'B'r 'O'HR pump lifting and failing to reseat, "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The Simulator Instructor will initiate the file at the time the control room operators start the RHRSW pump. The lifting relief valve will cause an increase in the Reactor Building vent monitor. The file will cause the Reactor Buildin release rate to increase to the oint of re uirin SBGT to be laced in service Hi Hi vent monitor alarm . The file will also cause the release rate value to decrease to a roximatel S.OE+04 vCi/min release.

EXPECTED ACTIONS: The operators will note the increased release rate from the Reactor Building vent monitor and begin an investigation and eeRsider-plac~

SBGTS in service.

VIII-26 10/28/97 NRC Exercise Manual

IS No. 254 Time: 1820 MESSAGE INFORMATION SHEET MESSAGE FOR: ASCC Security Controller MESSAGE FROM: Security Lead Controller LOCATION: ASCC MESSAGE: "THIS IS A DRILL." There WILL NOT be an actual site evacuation. The site evacuatiori will be simulated. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The TSC should provide information to the ASCC on who, how, and what for evacuation of non-essential personnel from the site. The ASCC will simulate initiating any actions directed by the TSC.

Note: The TSC should have made arrangements prior to the site evacuation'to have maintenance personnel on site to.complete the maintenance initiated on the 'A'HRSW loop.

EXPECTED ACTIONS: The Security Coordinator or,ASCC Controller will inform the TSC or the Control Room when the simulated evacuation is complete.

VIII-27 10/28/97 NRC Exercise IVlanual

IS No. 265 Time: 1820 MESSAGE INFORMATION SHEET MESSAGE FOR: Chemistry PASS Sample Team

.MESSAGE FROM: Chemistry Controller LOCATION: Reactor Building MESSAGE: "THIS IS A DRILL." The PASS information (located in the Rad Section (Vll) of the Exercise Manual) is to be given to the chemistry team when they have demonstrated the ability to obtain a PASS sample.

When the sample is returned to the Chem lab, the chemistry count lab is expected to be contaminated with high background levels. The high background is due to high airborne in the Turbine Building due to leakage from the main condenser.

To obtain results the sample should, be counted by Health Physics or taken to the West Building. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The PASS information can be obtained if the HP or West Building counting equipment is used. There should be a discussion of how the sample is to be transported to the West Building and what if any additional precautions need to be taken. Ensure that any information given out is "earned" by the individuals obtaining the sample. The correct counting time needs to be simulated, the proper procedures and location for obtaining the sample need to be discussed if applicable for training purposes.

EXPECTED ACTIONS: The chem team will report to the TSC for a briefing and simulate proceeding to the Sample Station to obtain a sample. The sample team will proceed to the Training Center and use the PASS to obtain their sample.

VIII-28 10/28/97 NRC Exercise Manual

IS No. 276 Time: 1820 MESSAGE INFORMATION SHEET

- MESSAGE FOR: ASCC Security Controller/TSC RPC MESSAGE FROM: Security Lead Controller/OSC HP Controller LOCATION: ASCC/TSC MESSAGE: "THIS IS A DRILL." This is Officer at the South Gatehouse, we have all of our exit portal monitors alarming at this time, what is going on, and what kind of an exposure are we getting out here'? "THIS IS A DRILL."

"THIS IS A DRILL." This is HP'Tech at the Unit 2 Access Control Point we have all of our ortal monitors and friskers alarmin at this time wh is there hi h radiation here? "THIS IS A DRILL."

~

. FOR CONTROLLER USE ONLY CONTROLLER NOTES: The information concerning the portal monitors will affect the evacuation instructions that have been given by the TSC.

EXPECTEDACTIONS: The ASCC Controller will inform the TSC or the Control Room of the alarms received in the south gatehouse.

The RPC in the TSC will inform the Emer enc Director of alarms.

VIII-29 10/28/97 NRC Exercise Manual

IS No. 287-Time: 1825 MESSAGE INFORMATION SHEET MESSAGE FOR: TSC Emergency Director MESSAGE FROM: TSC Lead Controller LOCATION: TSC MESSAGE: "THIS IS A DRILL." The present situation needs to be classified as a Site Area Emergency at this time.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The scenario must support the time line agreed upon with the State and FEMA. If the SAE classification is not declared by 1825 the TSC ED will be prompted to make the classification.

The prompt will be noted on the evaluation sheet for the critique process.

EXPECTED ACTIONS: The ED will initiate the actions required for a SAE classification.

VIII-30 10/28/97 NRC Exercise Manual

IS No. 298 Time: 1825 MESSAGE INFORMATION SHEET, MESSAGE FOR: Simulator Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." Simulator instructor to initiate FILE XXXXXXXto provide indications of run-out of the Unit 1 'B'HRSW pump. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The indication in'the Control Room will be no flow at the RHR SW Heat Exchan er.

. The indications are to simulate a broken RHRSW line.

EXPECTEDACTIONS: The Control Room will recognize that the RHRSW pump indications are a run-out condition and shut down the pump. The Shift Supervisor will recognize that the loss of the RHRSW pump results in no decay heat removal (EAL 410 Loss of Decay Heat Removal Capability).

The above information will be provided to the TSC.

VIII-31 10/28/97 NRC Exercise Manual

IS No. 3629 Time 1830 MESSAGE INFORMATION SHEET MESSAGE FOR: ASCC Security Controller MESSAGE FROM: Security Lead Controller Note that this messa e is onl to be iven after a call from the lead controller in the control room sa in that the RHR SW um has been laced in o eration'and the messa e can now be called in.

LOCATION: ASCC MESSAGE: "THIS IS A DRILL." This is Officer Mobile 1, I am in front of the North Gatehouse and there is muddy water coming from a hole in the road here on the north side of the SBA. Looks like a bubbling mess, looks like a broken water main. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The information is to coincide with the control room indication of the RHRSW pump in run-out.

EXPECTED ACTIONS: The ASCC Controller will inform the TSC or the Control Room of the information concerning the hole in the roadway.

VIII-32 10/28/97 NRC Exercise Manual

IS No. 310 Time: 1830 MESSAGE INFORMATION SHEET MESSAGE FOR: OSCAR Monitoring Team MESSAGE FROM: OSCAR Monitoring Team Controller LOCATION: In Field MESSAGE: "THIS IS A DRILL." The radiological data for the OSCAR teams is located in section seven (7) of the exercise manual. 'THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The monitoring teams will be given information (raw data) based on sampling procedures/techniques, location in, the field relative to plume centerline, and questions asked.

The Field Team Contioller will need to be in contact with the TSC Rad Controller to know which template to use for the field data. The release from the field is variable based on plant'actions. Ensure it is understood what field readings are applicable.

EXPECTED ACTIONS: The TSC HP Radioman will keep the TSC RPC appraised of information obtained from the field team monitors. The information will also be passed to the EOF Health Physics function. The field team data will be compared to any dose projections that have been performed.

f VIII-33 10/28/97 NRC Exercise Manuai

IS No. 324.

Time: 1835 MESSAGE INFORMATION SHEET MESSAGE FOR: Simulator Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate malfunction file:

XX)000(. The file simulates increasing. Reactor Building general area radiation levels due to the recirculation of the noble gases released from the RHR suction relief. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: This file is initiated when the SBGT System is place in service so the initiation time is variable.

The ongoing release into the Reactor Building will continue until the location of the leak is identified and isolated. Isolation of the leak will be a success path for the organization.

The increasing general area dose rates will eventually cause the SPING Monitors on the refuel floor to show an increase and mask the release in progress from the Turbine Building Vent and the SBGT vent.

EXPECTED ACTIONS: The operators in the Control Room will monitor the radiation levels in the plant and attempt to determine where the increase is originating from. It is expected that an INDIA Team will be dispatched to walk down the Reactor Building to determine the leak location.

VIII-34 10/28/97 NRC Exercise Manual 0

IS No. 332 Time: 1835 MESSAGE INFORMATION SHEET MESSAGE FOR: Simulator Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate file:

"EPLAN95IPERAD". The file provides indication of the Turbine Building SPING increasing as a result of the vapor in the main condenser leaking past the seals.

"THIS IS A DRILL."

(

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The file simulates the loss of condenser vacuum and the release of radioactive gas from the turbine condenser into the Turbine Building.

The major portion of the gases released from the turbine seals will go directly to the Turbine Building exhaust Vent., A minor portion of the gases will be distributed through-out the Turbine Building before being discharged.

The small portion of the leaking radioactive gas in the Turbine Building will cause radiation levels in the general areas of the Turbine Building to increase.

EXPECTED ACTIONS: The Control Room Operators will monitor the SPINGs and ask chemistry to verify and interpret the indications. The organization should recognize that the Chemistry Lab will not be available to count the PASS sample due to increased background and contamination.

VIII-35 10/28/97 NRC Exercise Manual

IS No. 348 Time: 1840 MESSAGE INFORMATION SHEET MESSAGE FOR: India Team

. MESSAGE FROM: In-Plant Team Control Cell LOCATION: Reactor Building MESSAGE: "THIS IS A DRILL." The completion of the maintenance on the RHRSW loop will require maintenance actions in the RHR room. The attached outline of work to be completed will be simulated without compressing the times required to complete the different functions.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The work listed on the attached would take approximately two hours to complete if it were done expeditiously, longer if not made a top priority. The TSC will need to address all the issues of placing a work team in the field during an emergency situation, including dose evaluations and extensions.

When the work is complete, the permit will need to be cleared or emergency actions taken to make the system available for decay heat removal.

EXPECTED ACTIONS: Make the required preparations and conduct the briefings necessary to initiate restoration of the 'A'HRSW loop.

VIII-36 10/28/97 NRC Exercise Manual

IS No. 354 Time: 1845 MESSAGE INFORMATION SHEET MESSAGE FOR: Health Physics Personnel MESSAGE FROM: In-Plant Controllers LOCATION: Turbine Building and First Floor of Control Structure MESSAGE: "THIS IS A DRILL." The portal monitors, friskers, and portable air samplers in the Turbine Building, and Control Structure go into alarm. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: A portion of the leakage from the turbine seals is postulated to leak into the general area of the Turbine Building causing an increased general area airborne causing increased general area radiation levels.

All the sensitive instruments in the Turbine and Control Structure go into alarm.

The Count Rooms in the Control Structure first floor are inoperable as a result of the back ground.

The increased airborne activity in the Control Structure and the Turbine Building occurs after the staffing and activation of the TSC and should not have any adverse affects.

Multiple PCRs are reported by Health Physics.

EXPECTED ACTIONS: The access to the Control Structure will be addressed since the PCM at the entrance will be out of service as will the PCMs for the Unit 1 8 2 access control points.

VIII-37 10/28/97 NRC Exercise Manual

IS No. 365 Time: 1845 MESSAGE INFORIIIIATIONSHEET MESSAGE FOR: Operator/INDIA Team Investigating Turbine Building Rad Levels MESSAGE FROM: In-Plant Team Controller

. LOCATION: Turbine Building 676'ESSAGE:

"THIS IS A DRILL." Investigation of the radiation levels in the Turbine Building will indicate higher than the average levels throughout the building. The increased rad levels are due to leakage from the Turbine Building seals leaking by after the loss of condenser vacuum. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The radiation levels are not a major problem in the Turbine Building other than the contamination and high background in the Chemistry count lab which will require the use of the Health Physics count lab or the West Building sample facilities.

EXPECTED ACTIONS: The INDIA Team will walk down the Turbine Building. The report back to the TSC/Control Room will be an above normal airborne and radiation level for the entire building.

VIII-38 10/28/97 NRC Exercise Manual

IS No. 376 Time: 1845 MESSAGE INFORMATION SHEET MESSAGE FOR: Operator Investigating Turbine Building Rad Levels MESSAGE FROIVl: In-Plant Team Controller LOCATION: Upper Relay Room MESSAGE: "THIS IS A DRILL." Investigation of the ARM readings in the Upper Relay Room for the Turbine Building will indicate 'higher than the average levels throughout the building. The increased rad levels are due to leakage from the condenser seals. The readings are obtained in the Radiological Section of the Controller Manual. "THIS IS A DRILL."

FOR CONTROL'LER USE ONLY CONTROLLER NOTES: The Control Room is expected to dispatch an operator to check out the ARM readings on the local panel in the Upper Relay Room.

W The radiation levels are not a major problem in the Turbine Building other than the contamination and high background in the Chemistry count lab which will require the use of the-Health Physics count lab or the EOF sample facilities.

EXPECTEDACTIONS: The operator will report back to the TSC/Control Room indicating an above normal radiation level for the entire building.

VIII-39 10/28/97 NRC Exercise Manual

IS No. 387 Time: 1845 MESSAGE INFORMATION SHEET MESSAGE FOR: Operator/INDIA Team Investigating Reactor Building Rad Levels MESSAGE FROM: In-Plant Team Controller LOCATION: Reactor Building MESSAGE: "THIS IS A DRILL." Investigation of the radiation levels in the Reactor Building will indicate higher levels throughout the building. The'ncreased rad levels are due to leakage from the leaking relief valve on the RHR suction being recirculated in the Reactor Building by SBGT. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The increasing radiation levels will cause the SPING monitors to indicate high due to increased background levels on the refuel floor.

The participants should recognize that all of the monitors are increasing and check the refuel floor ARMs. The refuel floor ARMs will show that the radiation levels are increasing and the probable cause for the SPING increases.

The organization should recognize that the when the background on the refuel floor affects the SPINGs an unmonitored release is in progress.

EXPECTED ACTIONS: The INDIA Team will walk down the Reactor Building. The report back to the TSC/Control Room will be above normal airborne and radiation level for the entire building.

Unless the team performing the walkdown in the Reactor Building specifically checks the suction relief for RHR they will determine nothing out of the ordinary.

Vill-40 10/28/97 NRC Exercise Manual

IS No. 398 Time: 1950 MESSAGE INFORMATIONSHEET MESSAGE FOR: Recovery Manager MESSAGE FROM: EOF Lead Controller LOCATION: EOF MESSAGE: "THIS IS A DRILL." The present situation needs to be classified as a General Emerge'ncy at this time.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The scenario must support the time line agreed upon with

~

the State and FEMA. If the General Emergency classification is not declared by 1950 the Recovery Manager will be prompted to make the classification.

The prompt will be noted on the evaluation sheet for the critique process.

EXPECTED ACTIONS: The Recovery Manager will initiate the actions required for a SAE classification.

Vill-41 10/28/97 NRC Exercise Manual

IS No. ao Time: 2005 MESSAGE INFORMATION SHEET MESSAGE FOR: Recove Mana er MESSAGE FROM: EOF Lead Controller LOCATION: EOF MESSAGE "THIS IS A DRILL." A PAR needs to be issued at this time.

"THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The scenario must su ort the time line a reed u on with the State and FEMA. If a PAR is not enerated b 2100 the Recove Mana er will be rom ted to make a PAR.

The rom t will be noted on the evaluation sheet for the criti ue rocess.

EXPECTED ACTIONS: The Recove Mana er will initiate the actions re uired b a PAR.

Vill-42 10/28/97 NRC Exercise Manual

IS No. 41089 I

.Time: 2100 MESSAGE INFORMATION SHEET MESSAGE FOR: Lead Controllers MESSAGE FROM: Lead Controllers LOCATION: Simulator Control Room/Harrisburg EOC MESSAGE: "THIS IS A DRILL." The lead controllers from the State and utility confer to review termination of exercise. "THIS IS A DRILL."

FOR CONTROLLER USE ONLY CONTROLLER NOTES: The lead controllers will review that all the required objectives have been demonstrated'and agree upon a time as to when the exercise shall be terminated.

EXPECTED ACTIONS: A termination time will be determined and communicated to appropriate controllers.

Vill-43 10/28/97 NRC Exercise Manual

VIII-44 10/28/97 NRC Exercise Manual IS No. 424 Time: 2200 f

MESSAGE INFORMATION SHEET MESSAGE FOR: AII Areas Via the Plant Page MESSAGE FROM: TSC Communications Controller and All Facility Lead Controllers LOCATION: Plant Control Room and All Emergency Response Facilities MESSAGE: "THIS IS A DRILL." .The following page announcement is to be made from the plant Control Room: "The 1997 NRC Annual Observed Exercise is now terminated; the 1997 NRC Annual Observed Exercise is now terminated."

REPEAT ABOVE MESSAGE.

The Facility Lead Controllers shall ensure that the exercise records are turned in and key individuals attend the area debriefing. Ensure that the telephone system and the plant page system are restored. Transfer the simulator radio back to the training condition and restore the simulator page system and computer to normal operation. Ensure the response facilities are picked up and ready to respond to an actual emergency.'THIS IS A DRILL."

.FOR CONTROLLER USE ONLY CONTROLLER NOTES: The page announcement is to be made in the following areas:

The Simulator Control Room The TSC (ensure chemists in West Building notified)

The Plant The OSC The EOF The MOC Courtesy call to NRC Ops Center to inform them NRC Graded Exercise has been terminated.

EXPECTED ACTIONS: Ensure that all the previously notified offsite agencies are informed that the exercise is terminated.

Vill-45 10/28/97 NRC Exercise Manual

SECTION IX SIMULATOR INFORMATION IX-1 10/28/97 NRC Exercise Manual

66t66t Oct 21 09s25 1997 Page 1 FILE: YPP.EPLAN97 1 NAME: Chuck Hess SCENARIO: NRC Exercise REVISION/DATE: 0, 8/19/97 DESCRIPTION: Sets up sim for drill/graded exercise END restorepref YPP.PRGBUTCLR

'A'HRSW OOS MRF PM131P506A OUT

~

ZMF MVOl:HV11215A ZMF MV01:HV11210A MSL A Leakage past MSIVs ZMF AV05: HV141F022A . 01 IMF AV05:HV141F028A .01 Hydraulic ATWS w/ Stuck Rod IMF RD155017 IMF RD1550062235 48 IMF MV07:PV146F003 (El 0 0) 8 Sets trigger for mode switch in SHUTDOWN TRG E1 RPE.MODESWSD Sets trigger for MSZVs closed TRG E2 MSE.F022ACLS Sets trigger for RHRSW B start TRG E3 EWE.PMPBON Inserts Fuel Damage

, IMF RR179003 (El 0 0) 1000 5$ 00 0 ZMF NM17816B2433 (El 10 15) 100 Inserts Condenser Air Znleakage IMF MC143001 (E2 0 0) 10 20:00 0 Simulates pipe break in B RHRSW system ZMF PM05-'1P506B (E3 2:00 0)

Simulate fire by S6A Building pfs 1 MRF YCF13510 ALARM pfs 2 bat, FDB.SAFIRE Insert when OSGY valve closed pfs 3 MRF YCF13511 ABNORMAL Half Scram on high pressure pfs 4 IMF RL01:C721K5B RPS Scram Solenoid Group Blown Fuse pfs 5 ZMF FU01:1C609F18A Inserts inleakage to RB Sump

Oct 21 09:25 1997 Page 2 pfs 6 MRF LD120010 20 RB SPING readings pfs 7 IMF RD02:RE16512B 1000 5:00 30 pfs 8 MMF RD02:RE16512B 500 5:00 1000 Simulates performance of ES-158-002 pfs 9 bat RPB.DISABLARI pfs 10 bat RPB.ES158002 Clears Hydraulic ATWS pfs 11 DMF RD155017 Shutdown All TB Ventilation pfs 12 CAE+l TBVENTSD Restart TB Ventilation pfs 13 CAE+l TBVENTSU Insert on RHRSW break pfs 14 IMF TR02:FT01204B 1.1E+04 mfs

66t66t ct 22 06:40 1997 Page 1 FILE: 10-28RBSPZNG f Reactor Building SPZNG This file is inserted when the RHR leak begins IF SBGT NOT in service.

IMF RD02:RE16510B 0.8 20:00 IMF RD02:RE16510B1 1.0 20:00 IMF RD02:RE16511B 0.7 20:00 IMF RD02:RE16512B 6.0e3 20:00 IMF RD02:RE16512B1 05:00 7.0 20:00 IMF RD02:RE16513B 02:00 6 20:00 IMF RD02:RE16514B 1.0e4 20:00 IMF RD02:RE16515B 1.0e5 20:00

66t66t Oct 22 06$ 41 1997 Page 1 10-28radl g Reactor Building ARMs xs file is inserted afte r the leak of RHR When SBGT is placed in ser vice.

fZMFElev. 645 TR02$ RZT13701 1000 25$ 00 IMF TR02$ RIT13725 1000 55$ 00 IMF TR02$ RIT13702 100 5$ 00 ZMF TR02$ RIT13703 100 5$ 00 IMF TR02$ RZT13704 1000 50$ 00 f Elev 670 ZMF TR02$ RIT13716 100 5$ 00 IMF TR02$ RIT03708 100 4$ 30 f Elev 719 IMF TR02$ RIT13705 1000 2$ 00 IMF TR02$ RIT13706 1000 2!00 IMF TR02$ RIT13726 1000 50$ 00 IMF TR02$ RZT13741 2 20$ 00 IMF TR02$ RIT13709 1000 60$ 00 P Elev 749 IMF TR02$ RIT13708 100 5$ 00 IMF TR02$ RZT13710 1000 60$ 00 f Elev 779 IMF TR02$ RIT13711 100 6$ 00 f Elev 799 IMF TR02$ RIT13712 100 5$ 00 P Elev 818 TR02$ RZT13713 100 6$ 00 2:RZT13714 1000- 55$ 00 IM $ RIT13715 100 5:00

,ZMF 02$ RZT03707 100 4$ 30 IMF TR02 $ RIT13742 100 5 $ 0 ZMF TR02$ RIT13746 100 4$ 30 IMF TR02$ RIT13747 1000 60$ 00 S Reactor Bldg Hi Range ARMs P Elev 645 IMF TR02$ RIT13756 21 03$ 30$ 00 IMF TR02$ RIT13755 2 03$ 30$ 00 jIMF TR02$ RZT13757 168 03$ 30$ 00 IMF TR02$ RIT13748 2 03:30$ 00 f Elev 670 IMF TR02$ RIT13753 2 03$ 30$ 00 f Elev 719 IMF TR02$ RIT13750 5 03$ 30$ 00 IMF TR02$ RIT13751 3 03$ 30$ 00 P'lev 749 IMF TR02$ RIT13752 2 03$ 30$ 00 IMF TR02$ RIT13754 2 03$ 30$ 00 f Elev 818 IMF TR02$ RZT13749 2 03$ 30$ 00 ZMF TR02$ RIT13747 2 03$ 30$ 00 f Reactor Bldg Process Rad IMF RD02$ RED121N010A 100 5$ 00 IMF RD02$ RED121N010B 100 4$ 30 ZHF RD02$ RED121N015A 100 5$ 00 02$ RED121N015B 100 4$ 30

Oct 22 06:41 1997 Page 2

.: RD02!RED121N016A 100 6-00 ZMF RD02:RED121N016B 100 6s30 IMF TR02:RZTS11216A 100 ZMF TR02:RITS11216B 100 ZMF TR02:RITSD121K606 1.0e3 30:00 P Control Structure ARMs ZMF TR02:RZT03709 56 3:30 P SBGT SPZNG ZMF RD02:RE06510 6 ~ 0 10:00 IMF RD02sRE06510A1 1.0e5 10<00 ZMF RD02:RE06511 7.5 10:00

'ZMF RD02:RE06512 1.0e6 10:00 IMF RD02:RE06512A1 05:00 1.0e4 10:00 IMF RD02:RE06513 02s00 1.0e2 10:00 IMF RD02sRE06514 1.0e4 10:00 ZMF RD02:RE06515 1.0e5 10:00' SBGT Process Rad Mon IMF RD02:RED120N017A 100 ZMF RD02tRED120N017B 100 fZMFTurbine Bld SPZNG RD02:RE16510A 05:00 6.0 20:00 IMF RD02:RE16510A1 05:00 1.0e5 20:00 IMF RD02:RE16511A 05:00 7.5 20:00 ZMF RD02:RE16512A 05:00 1.0e8 20:00 IMF RD02sRE16512A1 10:00 1.0e4 20:00 ZMF RD02:RE16513A 17:00 1.0e2 20:00 IMF RD02:RE16514A 05:00 1.0e4 20:00

'D02:RE16515A 05:00 1.0e5 20:00

66t66t Oct 22 06$ 41 1997 Page 1 E$ 10-28stop F /97 NRC Exercise to be used if RHR releif isolated. File stops ramp.

S Reactor Bldg Hi Range ARMs P Elev 645 IMF TR01$ RZT13756 DMF TR02$ RIT13756 IMF TR01$ RZT13755

.DMF TR02$ RIT13755 IMF TR01$ RIT13757 DMF TR02$ RZT13757 ZMF TR01$ RZT13748 DMF TR02$ RZT13748 fIMFElev 670 TR01$ RIT13753 DMF TR02$ RIT13753 8 Elev 719 IMF TR01$ RZT13750 DMF TR02$ RZT13750 ZMF TR01$ RIT13751 DMF TR02$ RIT13751 f Elev 749 IMF TR01$ RZT13752 DMF TR02$ RZT13752 IMF TR01$ RIT13754 DMF TR02$ RIT13754

'lev 818

$ '01$ RIT13749

$ RIT13749 IM 1$ RZT13747

'DMF R02$ RIT13747

66t66t Oct 22 06:41 1997 Page 1 FILETS 10-28tbrad This file simulates a rad release into the turbine Building from the main condenser. The file is inserted when condenser vacuum is lost.

P Turbine Bldg ARMs IMF- TR02:RIT13707 ZMF TR02cRIT13717 22 5:00 IMF TR020RZT13718 30':00 IMF TR02:RIT13719 ZMF TR02:RIT13720 34 5:00 ZMF TR02:RIT13721 1.0 10:00 ZMF TR02:RZT13722 2.0 12:00 IMF TR02:RIT13723 16.0 15:00 ZMF TR02:RIT13724 2.0 10:00 IMF TR02:RIT03712 2.0 12:00 IMF TR02:RIT03713 2.0 12:00 Control Structure ARMs,.SBGT. The increase is due the Zodine pick up of the charcoal.

IMF TR02:RIT03710 56.0 3:30:00

66t66t oct 22 06<42 1997 Page 1 E: 10-28tbsping

'ne Building SPZNG s file is inserted after the Condenser vacuum is lost ZF SBGT NOT in service.

ZMF RD02:RE16510A 1.3E-5 10s00 ZMF RD02:RE16510A1 1.5E-4 10s00 ZMF RD02:RE16511A 1 1E-1 10)00 ZMF RD02:RE16512A 4.0E6 10:00 ZMF RD02:RE16512A1 05:00 6 ~ 0 10:00 ZMF RD02:RE16513A 10:00 5.5 20:00

66t66t

'Oct 22 06$ 42 1997 Page 1 FZLE$ 10-28weatl Weather file to be initiated at start of exercise and run until 1710.

IMF TR02$ XTT03701 13.87 ZMF TR02$ XTT03702 388.1 IMF TR02$ XTT03706 64 ZMF TR02$ XTT03705A 74.2 IMF TR02$ XTT03708 -1 02 IMF TR02$ XTT03709 14.4 IMF, TR02$ XTT03710 21.4 IMF TR02 XTT03711 0 I IMF TR02$ XTT03703 8 9 IMF TR02$ XTT03704 378-9 IMF TR02$ XTT03707 -1.11 IMF TR02$ XTT03730 8.8 ZMF TR02$ XTT03731 391.0 IMF TR02$ XTT03732 13.6

66t66t Oct 22 06s42 1997 Page 1

~ LE: 10-28weat2 ther file to be initiated at 1710 of exerci'ae run until 1810.

IM R02:XTT03701 9.7 ZMF TR02$ XTT03702 353.1 IMF TR02:XTT03706 62 ZMF TR02:XTT03705A 68 '

ZMF TR02:XTT03708 -0 ZMF TR02!XTT03709 20.6

'1 ZMF TR02!XTT03710 23.1

'IMF TR02:XTT03711 0 ZMF TR02'sXTT03703 7.1 ZMF TR02:XTT03704 354.9 ZMF TR02:XTT03707 -0.83 IMF TR02:XTT03730 8.5 ZMF TR02:XTT03731 345.0 IMF,TR02:XTT03732 19.6

t66t t 22 06:43 1997 Page 1 FILE: 10-28weat3 Weather file to be initiated at 1810 of exercise and run until 2010.

F TR02:XTT03701 7.9' TR02sXTT03702 387.1 F TR02:XTT03706 61 F TR02:XTT03705A 64 2 F TR02:XTT03708 -0.76 F TR02:XTT03709 16.5 F TR02:XTT03710 22 F TR02:XTT03711 0 TR02:XTT03703 7 1 TR02:XTT03704 368.9 TR02$ XTT03707 -0.71 TR02:XTT03730 8.1 TR02:XTT03731 391.0 TR02:XTT03732 14.6

66t66t

)

'Oct 22 06$ 43 1997 'age 1 E$ 10-28weat4 her file to be initiated at 2010 of exercise run until 2155.

ZMF TR02 XTT03701 9.9 IMF TR02$ XTT03702 366.1 ZMF TR02$ XTT03706 55 ZMF TR02$ XTT03705A 60 '

ZMF TR02$ XTT03708 1.6 ZMF TR02$ XTT03709 5.4 IMF TR02$ XTT03710 6.9 IMF TR02$ XTT03711 0 IMF TR02$ XTT03703 4.5 IMF TR02$ XTT03704 358.9 IMF TR02$ XTT03707 1.71 IMF TR02$ XTT03730 3.1 IMF TR02 $ XTT03731 371. 0 IMF TR02$ XTT03732 4.6