Text

1995 Annual Emergency Exercise Scenario
	ML20087G037
Person / Time
Site:	Three Mile Island
Issue date:	01/31/1995
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20087G035	List: ML20087G033; ML20087G037;
References
	NUDOCS 9508160204
	Download: ML20087G037 (107)
	v • d • e

1 SM-26-1995 09:W FROM m!40F TO TMI)EP i O2 DRILL 9503 J ANNUAL EXERCISE TABLE OF CONIENTS topic ,1&gL v

Table of Contents 1

- Glossery/ Abbreviations 1.1to1.3 ERF Directions 2.1 to 2.3 Observer Assignments 3.1 to 3.3 Objectives 4.1 to 4.6 l

Scope 5.1 to 5.2 Initial Conditions 6.1 Exercise Guide 8.1to8.6 Observer instructions 9.1to9.35 I

Massages 10.1 to 10.24 Observer Checkbets -11.1 to 11.16 Plant Data Appendix A-Inplant Red Con Data Appendix B Radschemistry Appendix C Dose Projection Data Appendx D RMS Data Appendix E Field Team Data Appendix F Rumor Control AM G in Plant Rover Supplemental Information Packet (in Plant Rovers Only)

wwam i 9508160204 950720 PDR F ADOCK 05000289 PDR L. . .

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ACRONYMS / ABBREVIATIONS ac Alternating Current ADV Atmospheric Dump Valve AEOF Annex to the Emergency Operations Facility A/R As Read ATP Abnormal Transient Procedure B&W Babcock and Wilcox BRP Pennsylvania Bureau of Radiation Protection BWST Borated Water Storage Tank

, CC Cubic Centimeter L C/D Cooldown CFM Cubic Feet per Minute Code of Federal Regulations CFR '

Ci Curie' .

CPM Counts Per Minute CRO Control Room Operator CW Circulating Water DC Direct Current DC Drill Controller DER Pennsylvania Department of Environmental Resources DGI. Digital Graphics Incorporated DHR Decay Heat Removal DOE U. S. Department of Energy DPM Disintegrations Per Minute EAA Emergency Assembly Area EAAC Emergency Assembly Area Coordinator EAC Environmental Assessment Coordinator EACC Environmental Assessment Command Center EAL Emergency Action Level EBS Emergency Broadcast System ECC Emergency Control Center ED Emergency Director EFPD Effective Full Power Day EFW Emergency Feedwater

.EMA Emergency Management Agency ENS NRC Emergency Notification System EOC Emergency Operations Center EOF Emergency Operations Facility EPA U. S. Environmental Protection Agency EPIP Emergency Plan Implementing Procedure EPZ Emergency Planning Zone ERF Emergency Response Facility ES Engineered Safeguards ESAS Engineered Safeguards Activation System ESD Emergency Support Director-ESO Emergency Support Organization FAA Federal Aviation Administration FBTL 1 Fire Brigade Team Leader FEMA Federal Emergency Management Agency FP Full Power FRC Federal Response Center FRERP Federal Radiological Emergency. Response Plan FSAR ' Final Safety Analysis Report GeLi Germanium Lithium (isotopic gamma detection crystal)

GM Geiger Mueller (radiation detection tube)

GPM Gallons Per Minute GPUN GPU Nuclear Corporation ACRONLST 1.1 GPU NUCLEAR CORPORATION MIDDLETOWN, PA COPYRIGHT, 1993 L

7 HP . Health Physics HPI High Pressure Injection HPN NRC Health Physics Network

.IAW In Accordance with' ICS Integrated Control System INPO Institute of Nuclear Power Operations IP In Plant Rover IREO Initial Response Emergency Organization IRAP Interagency Radiological Assistance Plan ITS Important to Safety JIC ' Joint Information Center KI Potassium Iodide kv Kilovolt LOCA Loss of Coolant Accident LPZ Low Population Zone LSA Low Specific Activity t

MAP-5 Post-Accident High Range Iodine Sampler MCF Maintenance, Construction, Facilities MFW Main Feedwater MIDAS Meteorological Information and Dose Acquisition System MS-V/R Main Steam - Valve / Relief MU-P Make-Up Pump N/A Not Applicable NaI Sodium Iodine Gamma Isotopic Detection Crystal NAWAS National Warning System NOAA National Oceanic and Atmospheric Administration NRC U. S. Nuclear Regulatory Commission NWS U. S. National Weather Service O/P Office of the President OOS Out of Service OSC Operations Support Center OSH Off Scale High OTSG Once Through Steam Generator PAG Protective Action Guides PAR Protective Action Recommendation PAS Post-Accident Sample PEMA Pennsylvania Emergency Management Agency PD Plant Data PI Public Information PPB Parts Per Billion PPM Parts Per Million PRS Plant Reference Simulator PTFC Parsippany Technical Functions Center QA Quality Assurance QCL Quality Control List RAA Remote Assembly Area RAC Radiological Assessment Coordinator R&EC Radiological and Environmental Controls RB Reactor Building RCP Reactor Coolant Pump l RCS Reactor Coolant System !

RERP Radiological Emergency Response Plan ;

RM-A Radiation Monitor - Atmospheric l' RMC Radiation Management Corporation RM-L Radiation Monitor - Liquid RM-G Radiation Monitor - General Area RMS Radiation Monitoring System ACRONLST.93 1.2 GPU NUCLEAR CORPORATION MIDDLETOWN, PA !

COPYRIGHT, 1993 j I

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SCBA. Self-Contained Breathing Apparatus SCFM Standard Cubic Feet per Minute SCM Subcooling Margin S/D Shutdown SDD System Design Description SRO Senior Reactor Operator TBV Turbine Bypass Valve TLD Thermoluninescent Dosimeter TMI Three Mile Island Nuc1 car Plant TS Technical Specification TSC Technical Support Center V Volt U-1 TMI Unit 1 ,

7 U-2 TMI Unit 2

, WG Waste Gas I

WHM Warehouse Muster ,

X/O Meteorological Dispersion Factor (Chi /0) l l

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I I ACRONLST.93 1.3 GPU NUCLEAR CORPORATION I MIDDLETOWN, PA l

COPYRIGHT, 1993

TMI EMER. R3SPOXSE FACILITY YA:?

PART 1 to EOF /JIC (see Part 3 of map)

To Rt. 283 JoneswoY

. Plaza

g. 29

~

Middletown E

Middletown

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. MH 3 Susquehanna .

North Gate p River ,

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Mile Island K

TYI EYER. 3ESPONS3 FACILITY MA:?

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---, Phone \ /~ Mile A

I Booth Island H _- i Susquehanna Gate l River N mmuunnunum i

j P i k e S t ., .

Park I

- To access the AEOF:

H

,_,_gr? 1. stop at the gate.

2. Use the phone in the booth to call Susquehanna the AEOF .(it dials automatically).

River 3. When the gate opens, drive through (the gate closes automatically).

TYI EYE 3. :RESPOXSE TAC::LITY MA?

? ART 3 EOF /JIC 2574 Interstate Drive Harrisburg i O

a EOF'

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' I COLONIAL 0 CARLISLE P K a, CHAMBERsBuRG y mtER RT 81S ru

' 83 N. i ' =## ,/ ~

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via the lef t lane.

Harrisburg \NT TO HERSHEY VIA RT. 322 -

PROGRESS AVE.

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Rt. 283

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. DIRECTIONS TO OFF-SITE EMERGENCY RESPONSE FACILITIES NOTE These directions are intended to be used with the TMI Emergency Response Facility Map- parts 1,2 and 3. All directions are written using the TMI North Gate as the starting point.

Emergency Operoflons Facility (EOF), Joint Information Center (JIC) and Environmental Assessment Command Center (EACC)

-From the North Gate, turn left onto Route 441 North.

-Proceed 2.1 miles to the first traffic light in Middletown.

-Go straight through the traffic light and the next traffic light to a stop sign.

-Turn right at the stop sign then bear left to cross the rollroad overpass.

-Turn left at the traffic light just past the railroad overpass onto Route 230 West.

-Proceed West on Route 230 through the next traffic light (at Jamesway Plaza) and turn right onto the entrance ramp for Route 283.

-Proceed to the 283 West) Harrisburg sign. Bear left and continue to the 283 merge area.

-Merge onto Route 283 and continue to the next exit (Interstate 283 North).

-Turn right and merge onto Interstate 283 North and continue to the interchange for 83 North. 81 North and 322 West.

-Proceed straight onto 83 North and continue to the junction of Route 81 South (Carlisle).

-Bear left onto Route 81 South and proceed to the next exit (Exit 24 Progress Ave.).

-Take Exit 24 and proceed to the traffic light.

-Turn left at the traffic light and take the next right turn (Interstate Drive). '

-Follow Interstate Drive for approximately 0.5 miles to the EOF /JIC building. The number on the building is 2574.

-Enter at the rear of the building.

Annex to the Emergency Operations Facility (AEOF)

From the North Gate, turn left onto Route 441 North.

Proceed 2.1 miles to the first traffic light in Middletown.

Turn left onto South Union Street. ~

-Follow South Union Street for approximately 4 blocks and turn right onto Pike Street. 1

-Proceed straight to the security gate at the Middletown Service Center.

-Use the telephone in the booth to the right of the gate to identify yourself and request access (the telephone dials automatically when the receiver is picked up). l

-When the gate opens, proceed to the parking lot and park in the visitor area. The gate '

will close automatically.

The AEOF is located on the first and second floors of the Middletown Service Center building.

Near Site Joint Information Center and Simulator

-From the North Gate, turn right and proceed South on Route 441 for 0.7 miles to the entrance to the TMI Visitor Center parking lot.

-The Near-Site Joint Information Center and the Simulator are in the building behind the Visitor Center.

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DRILL 95-03 Annual Exercise OBSERVER ASSIGNMENT SHEET AREA OF RESPONSIBILITY OBSERVER CONTACT PHONE APPENDICES GROUP 1

50. Drill Coordinator (ECC) ~ G. Simonetti 2059 A,B-S,C,D,E,F,G

51. Plant Data Controller N. Brown 2059 A,E

1. , Simulator Management W. Fraser 2059 NO SCENARIO

52. Console Operator J. Boltz 2059

53. Operations Evaluator B. Ogle 2059

54. Communications S. Cviiic 2059

55. TSC R. Tropasso 8742 A

56. PTFC F. Kenny 7390 A

57. Tech Support at EOF C. Shorts 8966 A GROUP 2

58. EOF Controller R. Harper 8966 A,B-S,C,D,E,F,G

59. AEOF M. Press 944-2922

60. Public Info / Rumor Control S. Molello 540-4900 G GROUP 3 540-4501 E,F

61. EACC Controller D. Merchant i

62. RAC Controller F. Linsenbach 2059 B-S,D,E,F

63. Dose Assess Controller R. Eherts 948-2031

64. Field Team (On Site) E. Houser Radio F

65. Field Team (On Site) D. Lawyer Radio F

66. Field Team (EOF) D. Moyer Radio F

67. Field Team (EOF) M. Eckert Radio F 8164/8737

68. BRP Field Team T. Johnson F

69. BRP Field Team J. Sliter 979-5227 F

70. Chemistry E. Gliot Radio B-S,C 8164/8737 rwmrrgegacerg 3.1

DRILL 95-03 Annual Exercise OBSERVER ASSIGNMENT SHEET AREA OF RESPONSIBILITY OBSERVER CONTACT PHONE APPENDICES C"_O"" .

71. In Plant Controller A. Knoche 8718 B-S

72. In Plt Rov A (Elec.) D. VanNortwick 8718 B-S

73. In Plt Rov B (Ops.) G. Hoek 8718 B-S

74. In Plt Rov C (RC) R. Holmes 8718 B-L

75. In Plt Roy D (Safety) S. Pettinato 8718 B-S

76. In Plt Rov E (Mech) T. Coble 8718 B-S

77. In Plt Rov F (RC) A. Paynter 8718 B-L

78. In Plt Roy G (Mech.) S. Turns 8718 B-S l 1

79. In Plt Rov H (Elec.) P. Bickford 8718 B-S !

80. In Plt Rov I (Elec.) P. Karish 8718 B-S GRSUP 5

81. OSC Controller J. Whitehead 8718 B-L

82. Emergency Assembly E. Gee 8064/5042 i 83. Security / Accountability G. DeHoff Radio l

84. NSCC S. Williams l

85. NSCC E. Hammond l

86. PEMA Controller D. Taylor 783-8192 No Scenario

87. PEMA Controller R. Carto 783-3740 No Scenario

88. Evacuee C. Witmer No Scenario

89. Evacuee W. Duncan No Scenario NRC Inspection Team W. Maier (Team Leader) A,B-S,C,D,E,F,G 88.

89. NRC Inspection Team J. Lusher (EOF) 8966

'90. NRC Inspection Team J. Laughlin (ECC) 2059

91. NRC Inspection Team F. P. Bonnett (TSC) 8742 B-S

92. NRC Inspection Team S. Boynton (RAC) 2059 B-S,D,E,F

93. NRC Ispection Team R. Larson (OSC) 8718 B-S l

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DRILL 95-03 Annual Exarcico I!!E DRILL COORDINATOR has the overall responsibility for the implementation of the drill / exercise. All changes to the scenario are authorized by the DRILL COORDINATOR following approval from the affected CONTROLLERS.

$0NTROLLERS are designated for key areas of scenario implementation and -also have the responsibility of observing the activities of the drill participants. CONTROLLERS are the ONLY individuals that may change the scenario (data, sequence, etc.). The changes are implemented following authorization from the DRILL COORDINATOR.

ESERVERS have the responsibility of monitoring the activities of the drill participants and providing required' information (scenario data, messages, etc.).

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y-l ANNUAL EXERCISE l 4/12/95- 1

.i ATTACHMENT I. ;

OBJECTIVES FOR THE'1995 THREE MILE ISLAND NUCLEAR STATION ANNUAL EXERCISE -i hjointexercisewill'beconductedinordertodemonstratethestateof' emergency :

C-rip 2rcdness of the Three Mile Island Nuclear Station (TMI); the Commonwealth of ,

(PCnnsylvania, the TMI Risk Counties, and'the TMI ' Risk Municipalities. 1This.

demonstration will be accomplished through the implementation'of the emergency.

@lan dadicated to the response of a TMI incident. This is a full participation-Oxarcise. ,

Thh Three Mile Island Station objectives are as follows: 'l s I

NOTE: Bracketed information refers'to the correspondence elements ,

identified in NRC Inspection Procedure 82302, Section-82302-03 y

' Inspection Guidance, Paragraph 03.02. ;

l A. Operational Assessment j (al,2) $

1. Demonstrate the ability of the control room personnel to recognize (by ]

Plant Reference . Simulator indications) that. emergency action levels have j been reached or exceeded, properly classify the emergency and implement j

'the emergency plan within approximately'15 minutes of recognition. -;

2. Demonstrate the ability of the operat$ ors to assess, plant conditions, ,

effectively utilize' engineering support, and implement procedures in' '

order to place the plant in a safe condition, as. indicated by.the Plant l Reference Simulator displays. ," .

t Demonstrate the ability of the plant personnel to mitigate the in-plant 3.

- and off-site consequences of a radiological release through operational :

manipulations. ;

t 4.- Exh'ibit the coordination and adequacy =of the TMI. Emergency Operating !

Procedures and Emergency Plan Implementing Procedures. l4 B.e Radiolocical Controls and Environmantal Assessment )

[a5,6; bl4] l 3 Satisfactorily perform radiological and environmental monitoring. I 1.

activities in accordance with prescribed procedures. !

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ANNUAL EXERCISE 1 4/12/95 RpJir>1ocical Controls and Environmental Assessment (CONTINUED)

2. Properly assess the monitoring data to formulate accurate off-site radiological dose projection.

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3. Demonstrate the ability to evaluate monitoring data, off-site radiological dose projections, and plant conditions to . arrive at appropriate protective action recommendations within approximately 15 minutes of the G.E. declaration, j I

.4. Demonstrate the ability to support the radiological protection assessment process while maintaining personnel radiation exposure as low as reasonably achievable.

5. Demonstrate that sufficient radiological protection exists for emergency personnel to properly carry out assigned roles and responsibilities in all facilities. !

4

6. Demonstrate the ability to obtain and analyze appropriate samples (e.g. ,

grab samples, etc.).

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7. Exhibit the proper use of appropriate sample results (e.g., grab samples, etc. ) for dose assessment and radiological controls activities. ,

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8. Demonstrate the effective coordination of the radiological and 1 environmental assessment process with the Bureau of Radiation Protection.

9. Demonstrate the capability to dispatch a field monitoring team from the facility within 30 minutes of the declaration of an emergency when a release is in progress. ,

10. Exhibit the ability to develop the initial dose, projection within 30 ;

minutes of process initiation and subsequently within approximately 15 minutes as needed. -

C. Emercency Oraanization

[a7,8; b6)

1. Demonstrate that sufficient emergency personnel are available to properly mitigate the consequences of an emergency and support the emergency on a round-the-clock schedule.

2. Exhibit proper response of the emergency personnel to activate emergency response facilities and carry out assigned roles and responsibilities within their allotted 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months response time. Note: Response time starts with the activation of the EP Pagers.

ANNUAL EXERCISE 4/12/95 Emercency Orcanization (CONTINUED)

3. Display proper transfer of responsibility between onshift personnel and incoming emergency personnel.

4. Demonstrate timely briefing and dispatch of Emergency Teams at the OSC.

$. Emercency Response Facilities

1. Demonstrate that sufficient and adequate emergency equipment exists to effectively perform all necessary emergency actions.

2. Demonstrate a viable means of access control exists that restricts entry to authorized personnel only.

3. Show that sufficient space is dedicated in all facilities to allow for proper emergency response.

4. Demonstrate the ability to screen and/or process personnel for access to emergency' response facilities.

8. Communications (e3,4]

1. Demonstrate that reliable communications systems exist to accomplish notification of off-site agencies within the 15 ninute (State.and Risk Counties) or 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (NRC) time limits and to communicate with the Bureau of Radiation Protection.

2. Demonstrate that adequate emergency communications systems are in place-to facilitate transmittal of data among emergency response facilities.

3. Exhibit the ability to effectively utilize emergency communications systems. .

4. Demonstrate the ability to adequately alert station personnel of an.

emergency through the use of alarms and public address systems.

5. Demonstrate that adequate call out procedures exist to provide for mobilization of emergency response personnel within approximately 30 minutes of the event declaration.

6. Demonstrate the ability to effectively communicate with emergency teams on-site and off-site.

i 7. Exhibit data display at each facility which is adequate to support the facilities' mission.

t 6- -.__ ___ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _

e ANNUAL EXERCISE 4/12/95 4 Jersonnel Protection (bl4~,17]-

1. Demonstrate that initial accountability can_ be accomplished within L

thirty _ minutes , and final accountability' can be accomplished within l sixty minutes from'the-request.

2. Demonstrate :the ability .to muster non-. essential. personnel onisite and l l .that adequate provisions ' exist to carry ' out an orderly. evacuation.

NOTE: A maximum of.4_ personnel will demonstrate evacuation.of1non-essential personnel. ,.

3. Demonstrate proper-adherence to personnel protection / safety' rules.

4. Demonstrate the capability _ to radiologically monitor and, if necessary,

~ decontaminate personnel onsite or offsite.

5. Demonstrate that search and rescue can be implemented following ,

accountability, if. required.

6. Demonstrate the ability to control access to changing; radiological . _]

conditions in-plant and around the site.

L Public Information (b2,9] .

1. Demonstrate the ability to develop and disseminate. accurate news '.

releases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from the time that a l major plant event l has i occurred.

- 2.- Exhibit proper activation of the Joint Information' Center.

'3. Demonstrate effective rumor control techniques. -

4. Demonstrate the ability to conduct news briefings and interface with~ the news media and concerned citizens on a frequency of at least 1 per hour, as required.

3. 'Criticue (d]- ,

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~1. Demonstrate that previously identified deficiencies have been corrected.

NRC Inspection Report 50-289/94-09 Resident Safety Inspection (5/17/94 - 6/27/94) t

ANNUAL EXERCISE 4/12/95 Criticue (CONTINUED)

Exercise weakness:

o The licensee initially f ailed to recognize that the high range condenser offgas radiacion monitor for gaseous activity, RM-A-5 HI Gaseous, was greater than the high alarm setpoint, which is a condition which requires the licensee to declare an Alert. The Operations Coordinator (Plant Operations Director) noted the condition and the licensee declared an Alert approximately one hour after receiving the radiation monitor alarm.

Areas for potential improvement:

C There were several instances where ECC communications to other d facilities could be improved. For example, the ECC and the Emergency Offsite Facility (EOF) were aware that in addition to the primary-to-secondary leak, there were indications of reactor coolant leaking into the Reactor Building [there das a simulated main steam line leak in the

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affected OTSG]. However, the OSF and TSC were not aware of the reactor coolant leak. Though the OSF and TSC actions were still correct in ,

attempting to close the open Reactor Building purge valves, the work l crews should have known to expect the high radiation levels at the purge valves, o At the start of the drill, the computer on the Shift Supervisor's desk displayed a recently installed screen' that is designed to provide radiological assessment information from the RAC. The screen is a good licensee initiative because it provides up-to-date radiological information to the ED. However, this screen was not functional in the.

actual Control Room. The concern is that Control Room personnel would become accustomed to using equipment during drills that would not be available during an actual event. The emergency preparedness personnel thought the screen was functional in the Control Room as of April 25, 1994, but on May 20, 1994, the inspector found that the screen was not functional. The Shift Supervisor at the Simulator was aware that'the screen would not be available in the actual control Room and therefore, he would have to use the RAC computer. However, discussions with other licensee personnel indicated that they thought the computer screen was available in the Control Room. The licensee did not make the screen functional until June 15, 1994, o The OSC repair team assigned to perform mechanical repairs to close the Reactor Building outer purge valve did not have the procedures, technical manuals or drawings at the work site. Although this information was being reviewed at the OSC and although the individuals were very familiar with the purge valve, the information should also be at the work site to assist in their troubleshooting efforts.

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ATTACHMENT II I

. NOTE: This list of items denotes the level of participants that may result if such actions are taken by the participants in response

to scenario situations (i.e., if search and rescue is deemed i appropriate by the participants, they will be required to actually l perform this action rather than simulating it.) 'It is NOT intended to be an absolute list of actions that will be taken. Actions which affect normal Plant Operation WILL NOT be permitted.

t I SIMULATION EVENT ACTUAL

1. Declaration of Emergency X

2. Notification of Off-Site Agencies X

3. Emergency Announcements X

4. Activation of' Initial Response X ;

Emergency Organization l 5. Activation of Emergency Support X Organization

6. Protected Area Accountability X l

7. Sample and Analysis X l

8. Evacuation of Site Personnel X* .

9. Monitoring at Assembly Area X

10. Decontamination of Contaminated '

X**

Person (s)

11. Power Plant Operation P.***

12. Dispatching of Response Teams X (e.g., Radiation Monitoring, Repair, etc.)

13. Public Information (e.g., Rumor X Control, News Releases, Joint Information Center Activation, etc.)

14. Search and Rescue (e.g., Trapped Person, Missing Person)

15. Evaluate Emergency Responder (s) to X meet Fitness for Duty Requirements

A maximum of 4 personne'l will be evacuated to demonstrate the effectiveness of the evacuation process.

- Contamination is simulated by using Lantern mantles. Simulated decontamination is done by following applicable plant procedure (s).

- - Control switches may be operated in the Plant Reference Simulator. All controls in the Plant will not be operated. ( ACTUAL PLANT CONFIGURATION WILL NOT BE ALTERED.)

DRILL 95-03 ANNUAL EXERCISE 1995 SCOPE The Annual Emergency Exercise is a Player reactive event run from the Plant Reference Simulator (PRS) using REAL TIME dose assessment. Real Time dose assessment involves actual field monitoring team data transmissions and the use of actual time of day meteorological conditions. Using the Simulator and Real Time dose casessment adds an important degree of realism to the response of the drill participants. The drill encourages a player reactive response to the scenario which in turn enhances the awareness of the plant conditions by the Emergency Organization, especially when their recommendations are implemented. Back up information is available if the simulator malfunctions.

The Initial Conditions for this drill are on the Initial Conditions Sheet (Page 6.1). There is one time clock in effect for this drill. A 30 day Administrative time clock per AP1038 because MU-P-1C is out of service. An additional item is that the pressurizer spray valve is leaking and stuck in the open position with the block valve closed. The block valve is scheduled to be cycled open and closed to provide boron mixing. The drill is started by the Drill Coordinator with an announcement for all drill participants to use radio channel 5.

Shortly after the drill starts the operators attempt to cycle RC-V-3 and find that it is stuck in the closed position. Procedure (EP1202-29) guidance directs that power changes be limited to less than 1% per minute. After the valve is found failed the OTSGs (Once Through Steam Generators) start to leak. The total leakage will be cpproximately 80 gpm split 70 % to 'A' and 30% to the 'B' generator. The operating et ff will quantify the magnitude of the leak and direct the following: 1) Plant Shutdown and 2) Declaration of an Alert.

NOTE: The Operations Evaluator will insure that the shutdown rate is:1 %Iminute.

Following the controlled plant shutdown a system cooldown will be initiated.

This will be controlled by the Operations Evaluate to be at 90 10 *Flhour. During the cooldown several failures will occur: CF-T-1A will lose its nitrogen overpressure.

CF-V-4B will be failed closed, and the total OTSG leakage will increase to about 650 gpm. The operators will attempt to increase the makeup to the RCS by starting a second Makeup pump, which falls to start. Additionally when the 'B' Decay Heat Removal pump attempts to start it will also fail. The leak rate is more than the capacity of one pump and sub-cooling margin will decrease to less than 25 *. This condition warrants declaration of a Site Area Emergency. The Site Area Emergency activates the entire Emergency Organization (The Initial Response Emergency Organization {IREO} and the Emergency Support Organization {ESO}). Additionally this level of emergency initiates the Accountability / Mustering / Evacuation activitice.

The evacuation will be demonstrated by a few select employees in lieu of a full site evecuation.

DRILL 95-03 ANNUAL EXERCISE 1995 One aspect of this particular exercise is that the core heat will be controlled to allow exercise objectives to be met within the time limits of the exercise. Personnel .

responsible for evaluating heat removal and plant response will be informed that e.bnormal response can be expected. The manipulation of the core heat will allow a rapid RCS heatup, at the desired time, and fuel cladding failure.

After several hours into the cooldown and about the time that Decay Removal cperations will begin, several failures occur: 1) The OTSG leakage increases, and 2)

The remaining pumps (MUP sud DHR) controlling RCS inventory are lost. The RCS heats up and suffers fuel clad damage warranting declaration of a General Emergency. ,

A General Emergency declaration requires that a Protective Action Recommendation)

PAR be developed and given to the state within approximately 15 minutes. The plant will restore inventory control and evaluate entry into Recovery. (NOTE: De-escalation 13 not an appropriate alternative following a General Emergency Declaration.)

The drill will end with concurrence from the State and GPU management.

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DRILL 95-03 ANNUAL EXERCISE 1995 DRILL DRILL DRILL I

DATE 04/12/95 TIME 0530 TMI-1 PLANT STATUS PRIMARY PLANT SECONDARY PLANT i

MO33: POWER OPERATIONS GENERATION: 878 MWe; ACT-PRED: +2.1 MWe !

POWER: 99.66 % 2559.3 MWth CNDNSR VAC 26.7" Hg; CW TEMPS 74 F BURNUP:525 EFPD; BORON: 16 ppmB OTSG A/B PRESSURE: 911 / 911 PSIG PRE 2SURE 2156 PSIG; TAVE: 579 F OTSG A/B LEVEL: 58% / 57% Op Range RC PUMPS: 4 RC FLON: 144.4 Mlb/hr FW A/B FLOWS: 5.35 / 5.30 (MLB/HR)

RCS LEAK RATE: MS Drains Feeding Forward: 4 Laakage + Losses: .0768 GPM Total Leakage: .0801 GPM RC TOTAL ACTIVITY: 2.994 uCi/ml ;

Unidentified: .0801 GPM DOSE EQUIV IODINE: 4.49 E-3 uCi/ml f Mathod A P-S Leakege: 0.14 GPH CONDENSER OFFGAS: 10025 CPM @ 24 SCFM Method B P-S Leakage: 0.17 GPH Lithium: 0.43 ppm RCS hot pH: 7.8 I

CONTINUOUS DAYS ONLINE:516 CHEMISTRY & THERMOHYDRAULIC ABNORMALITIES: .

SICNIFICANT EVENTS:

The Met recorders (Direction, Speed and Temperature) are OOS use the ED/ESD screen on the computer, if information is needed.

MAJ R EQUIPMENT OUT OF SERVICE / PROBLEM AREAS:

MUPIC is OOS. ADMIN 1038 30 day time clock in effect, started 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months 4/10/95. The pump shaft is cracked. The unit is disassembled and awaiting a replacement shaft. The shaft is expreted to arrive on site within the next week to 10 days.

RCV1 is leaking. RCV3 is closed. In accordance with EP1202-29 RCV3 is cycled to maintain boron and spray line temperature. The valve is cycled every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at 35 minutes after the hour.

MAJ R PLANNED ACTIVITIES AND TESTING FOR THE NEXT 24 HOURS:

NONE. ,

PDMS:

NONE.

COMMENTS:

RB Purge in progress for non-routine safety related corrective maintenance (check RB ;

coolers).

MET RECORDERS are OOS. ** Use ED Display on computer for current data. **

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BLANK 1

ANNUAL EXERCISE ]'

April'12,.1994 TIME MAJOR EVENT MESSAGE MESSAGE DETAILS / DETAILS / EXPECTED ACTIONS CONTENT NUMBER MESSAGE MESSAGE SCENARIO CLOCK (PAGE) DELIVERED BY DELIVERED TO T = -30 1500 Initial N/A None Plant Data Senior Inform drill Conditions Controller / Management / participants of ,

OSC Controller Shift drill plant Supervisor / conditions.

Shift Foreman /

Group Rad Con Supervisor T=0 1530 Exercise The time is DC-1 Drill Drill Start the Begins now T = 0. (10,5) Coordinator Observers / exercise. Change Drill radios to Channel Participants 5.

T=5 1535 Drill Cycle RC-V-3. OE-l* Operations Control Room Cycle RC-V-3.

Control (10.6) Evaluator Staff Feature T=5 1535 RC-V-3 Fails N/A None Plant Data Control Room Investigate.

Closed Staff -

T = 15 1545 Primary to N/A None Plant Data Control Room Attempt to Secondary Staff quantify leak Leak of 80 rate.

to 100 gpm.

(70%-A/30-B)

T = 25 1555 Plant Shut down at OE-2* Operations Control Room Shut down at 1%

shut down 1% per (10.7) Evaluator Staff per minute.

initiated. minute.

O Indicates a Contingency Message. Refer to the Observer Instructions. ,

cursse 8.1 d EaWi,E

ANNUAL EXERCISE April 12, 199.4-TIME MAJOR EVENT MESSAGE MESSAGE DETAILS / DETAILS / EXPECTED ACTIONS-CONTENT NUMBER MESSAGE MESSAGE CLOCK (PAGE) DELIVERED BY DELIVERED TO SCENARIO T = 25 1555 Leak Rate N/A None Plant Data Control Room Declare an ALERT.

Quantified Staff at =80 gpm.

T = 45 1615 Alert Declare an DC-2* Drill Emergency Declare an Alert.

Declaration Alert. (10.8) Coordinator Director T = 60 1630 Information TRAFFAX PI-1 Public ECC Staff Refer caller to Request reporter (10.9) Information Member Public Information requesting Observer Department.

information.

T= 120 1730 Information Request for PI-2 Public ECC Staff Refer caller to Request television (10.10) Information Member the Communications coverage. Observer Division.

T= 150 1800 Plant Cool Cool Down-at OE-3* Operations ECC Staff Cool dawn plant at Down 90*i10*/ Hour. (10.11) Evaluator 90*110'/ Hour.

Initiated.

T= 155 1805 CF-T-1A N 2 N/A None Plant Data ECC Staff Dispatch an Pressure Emergency Repair Loss. Team to CF-V-4B investigate when Fails Shut. discovered.

T= 160 1810 Plant Decay Heat is OE-4 Operations ECC Staff Allow for control Parameter being (10.12) Evaluator feature while Information controlled. performing calculations.

O Indicates a Contingency Message. Refer to the Observer Instructions. ,

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ANNUAL EXERCISE April 12 0 1994

-m /

TIME MAJOR EVENT MESSAGE MESSAGE DETAILS / DETAILS / EXPECTED ACTIONS CONTENT NUMBER MESSAGE MESSAGE SCENARIO CLOCK {PAGE) DELIVERED BY DELIVERED TO T = 160 1810 Plant Decay Heat is TSC-1 TSC Observer TSC Staff Allow for control Parameter being (10.13) feature while Information controlled. performing calculations.

T= 160 1810 Plant Decay Heat is TS-1 EOF Tech EOF Tech Allow for control i Parameter being (10.14) Support Support feature while Information controlled. Observer Staff performing i calculations.

T= 160 1810 Plant Decay Heat is TF-1 PTFC Observer PTFC Staff Allow for control Parameter being (10.15) feature while Information controlled. performing calculations.

T = 165 1815 MU-P-1A N/A None Plant Data ECC Staff Dispatch Emergency Failure. Repair Team.

DH-P-1B Attempt to recover Failure. sub cooling Decreasing margin. Declare a Sub Cooling SITE AREA Margin. EMERGENCY.

T= 165 1815 OTSG Leakage N/A None Plant Data ECC Staff Continue cool

~

Increases to down.

=650 gpm.

T = 180 1830 Site Area Declare a DC-3* Drill Emergency Declare a Site Emergency Site Area (10.16) Coordinator Director Area Emergency.

Declaration. Emergency.

l O Indicates a Contingency Message. Refer to the Observer Instructions.

e m es 8. 3* E8EE271,E

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-ANNUAL EXERCISE April-12, 1994 DETAILS / DETAILS / EXPECTED' ACTIONS

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TIME MAJOR EVENT MESSAGE MESSAGE CONTENT NUMBER MESSAGE MESSAGE SCENARIO CLOCK (PAGE) DELIVERED BY DELIVERED TO T= 185 1835 RCS Pressure N/A None Plant Data ECC Staff Investigate at 600 psi. and/or dispatch CF-T-1B . Emergency Repair problem Team.

discovered.

T= 190 1840 Muster Select three EA-1 Emergency Emergency Comply with Complete. individuals (10.17) Assembly and Assembly direction.

to Site Area NOTE: The three -

demonstrate Evacuation Coordinator evacuees are the Observer pre-designated.

evacuation process.

T = 200 1850 Account- N/A None Security and Site Repotu status to ability Accountability Security Emergency Complete. Observer Director. Commence One person Search and Rescue.

missing.

T = 210 1900 Fitness for Individual EOF-1 EOF Controller Emergency Test BAC I.A.W.

Duty Testing consumed (10.18) Support- EPIP-TMI .27.

at EOF. alcoholic Director i beverages.

T = 215 1905' Missing N/A None In Plant Rover Search and Extricate and Injured Rescue Staff treat individual.

Person Located.

t T = 220 1910 Evacuation Initiate a DC-4 Drill Emergency Commence the mini (10.19) Coordinator Director evacuation.

evacuation O Indicates a Contingency Message. Refer to the Observer Instructions. , , , ,

~

ANNUAL EXERCISE April 12, 1994 TIME MAJOR EVENT MESSAGE MESSAGE DETAILS / DETAILS / EXPECTED ACTIONS CONTENT NUMBER MESSAGE MESSAGE ECENARIO CLOCK (PAGE) DELIVERED BY DELIVERED TO T = 240 1930 Information Conrail Yard PI-3 Public EOF Staff Refer caller to Request Master asking (10.20) Informatica Member the Communications about rail Observer Division.

safety near TMI.

T = 265 1955 MU-P-1B N/A None Plant Data ECC Staff Dispatch Emergency Failure. Repair Team.

DH-P-1A Failure.

T = 265 1955 OTSG Leak N/A None Plant Data ECC Staff Continue cool Rate down.

Increases.

T = 280 2010 Evacuees N/A None AEOF Observer AEOF Staff Decontaminate arrive at personnel. Utilize the AEOF. manpower as needed.

T = 295 2025 Sub Cooling N/A None Plant Data ECC Staff Attempt to recover Margin Sub Cooling Negative. Margin. Declare a GENERAL EMERGENCY.

Make a PAR within 15 minutes.

T = 300 2030 General Declare a DC-5* Drill Emergency Declare a General Emergency General- (10.21) Coordinator Director Emergency.

Declaration Emergency 0 Indicates a Contingency Message. Refer to the Observer Instructions. ,

0412950 8.5 "[

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ANNUAL EXERCISE April 12, 1994

~

-TIME MAJOR EVENT MESSAGE MESSAGE DETAILS / DETAILS / EXPECTED ACTIONS' CONTENT NUMBER MESSAGE MESSAGS SCENARIO CLOCK (PAGE) DELIVERED BY DELIVERED TO T = 301 2031 Intermediate N/A None In Plant Plant Staff Monitor and and Turbine Rovers Decontaminate.

Building Personnel Contamin-ations.

T = 305 2035 MU-P-1A N/A None In Plant Rover Emergency Report status to-Returned to Repair Teams OSC and ECC.

Service.

DH-P-1A Returned to Service T = 320 2050 Sub Cooling N/A None Plant Data ECC Staff Continue recovery Margin operations.

Recovered.

T = 330 2100 Information Fuel oil PI-4 Public EOF Staff Refer caller to Request truck driver (10.22) Information Member the Communications concerned Observer Division.

about making a delivery to TMI.

T = 345 2115 AEOF Support Obtain a AE-1 AEOF Observer Site Identify source of Request mobil (10.23) Services supply.

breathing air Coordinator compressor.

Indicates a Contingency Message. Refer to the Observer Instructions. ,

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' ANNUAL-EXERCISE-April 12,-1994 TIME' MAJOR EVENT MESSAGE MESSAGE DETAILS / D'ETAILS/~ EXPECTED' ACTIONS:

CONTENT NUMBER MESSAGE MESSAGE SCENARIO CLOCK '(PAGE) DELIVERED BY DELIVERED TO T = 390 2200 Drill Ends The drill is DC-6 Drill Drill Terminate the terminated. (10.24) Coordinator Observers & drill.

with ED & ESD Participants concurrence.

Indicates a Contingency Message. Refer to the Observer Instructions. ,,, ,,ct,,,co,,g,,,,,,

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ANNUAL EXERCISE April 12, 1994 DRILL COORDINATOR INSTRUCTIONS

1. When all personnel have been briefed (i.e., watch turnover) and the Plant Reference Simulator is lined up for the drill, read Message DC-1 over the plant page system.

2. Several events will occur during the course of the drill that, in reality, could require off site assistance. Calls are to be simulated with the exception of the Emergency Off Site Notification process and calls to PEMA regarding the site evacuation process. A similar instruction is included in the Communications Observer Instructions.

3. At T = 45 (1615 hours0.0187 days 0.449 hours 0.00267 weeks 6.145075e-4 months ), if the Emergency Director has not declared an Alert or is not preparing to declare an Alert,

. read Contingency Message DC-2 to him. This message will ensure the drill follows the time line approved by the Pennsylvania Emergency Management Agency and that off-site activities are not adversely affected.

4. The Public Information Observer will call the ECC with Message PI-1 at T = 60 (1630 hrs.) and Message PI-2 at T = 120 (1730 hrs.). See the Public Information Observer Instructions for the specific messages. These calls will test the ability of the ECC personnel to deal with distractions and outside agencies during a stressful situation. Monitor the response to these calls.

5. At T = 180 (1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months ), if the Emergency Director has not declared a Site Area Emergency or is not preparing to declare a Site Area Emergency, read Contingency Message DC-3 to him. This message will ensure the drill follows the time line approved by the Pennsylvania Emergency Management Agency and that off site activities are not adversely affected.

6. At T = 220 (1910 hrs.) or when muster is complete, direct the Emergency Director to initiate the mini evacuation by reading message DC-4 to him. Verify the Emergency Director consults with the Radiological Assessment Coordinator to consider radiological exposure implications relative to the evacuation route. Provide the Emergency Director with the modified Emergency Report Form for Site Evacuation.

GPU NUCIZAR CORPORATION A \041295, 9.1 EIEEEEE"i,E

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ANNUAL EXERCISE April.12, 1994 i DRILL COORDINATOR INSTRUCTIONS (Continued) t

7. The U.S. Nuclear Regulatory Agency has indicated that they will actually send an Incident Response Team as part of this drill. If they elect to do so, actual NRC personnel could i arrive at the TMI emergency response facilities. Response to team activities should be in accordance with established procedures. Individuals requiring site access who do not presently possess a TMI security badge should be processed through the AEOF. Should~the team require assistance in obtaining site entry processing or clearance, ensure the Emergency Director and staff support the team's visit / site '

entry as necessary. Monitor the interaction between the Incident Response Team and the ECC staff and record comments in your Observer Comments.

8. At T = 300 (2030. hours), if the Emergency Director has not declared a General Emergency or is not' preparing to declare a General Emergency, read Contingency Message DC-5 to him. l This message will' ensure the drill follows the time line approved by the Pennsylvania Emergency Management Agency and that off site activities are not adversely affected.

9. At T = 390 (2200 hrs.) with the drill objectives satisfied and with Emergency Director and Emergency Support Director concurrence, end the drill by reading Message DC-5 over the .

plant page system. Then read Message DC-5 to the EOF,-AEOF, j Joint Information Center, and PTFC using commercial or ;

emergency telephones. l

10. Contact the Shift Supervisor / Shift Foreman at extension 8070 j or 8071 and inform him of the completion of the drill. !

11. At the completion of the drill, ensure all equipment is )

returned to the proper storage location and the Simulator 1 Control Room is returned to pre-drill conditions. ,

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CPU NUCLEAR CORPORATION xisouas, 9.2 E$EEcE"i,E l

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ANNUAL EXERCISE April 12, 1994 COMMUNICATIONS OBSERVER INSTRUCTIONS

1. During the course of the drill, various events will take place which, in reality, could require off-site assistance.

All calls to off-site entities shall be simulated with the exception of the emergency off-site notification process.

L Also, calls to PEMA regarding the site evacuation process (refer to EPIP-TMI .02) should not be simulated. In all other cases, allow the drill participants to produce 4 applicable telephone numbers and explain the contact method, but stop the process at the point that the call would be placed. ,

2. Off- site notifications are to be performed as specified in a the applicable communications Emergency Plan Implementing Procedure.

o The initial notifications shall be performed in their entirety in accordance with the Emergency Notifications ;

and call Outs procedure, EPIP-TMI .03. i o Reclassification notifications shall be performed in i their entirety in accordance with the Emergency )

Notifications and Call Outs procedure, EPIP-TMI .03. 1 o Closeout notifications shall be performed in their entirety in accordance with the Emergency Notifications and Call Outs procedure, EPIP-TMI .03.

o The call out of emergency personnel shall be in accordance with the Emergency Notifications and Call Outs procedure, EPIP-TMI .03.

3. Ensure drill demands placed upon state and county emergency management agencies are held to a minimum. For example, if I the communicator fails to cancel the ring tone on the Notification Line, intervene and cancel the ring tone yourself. Any intervention performed ~by the observer to lessen the drill impact on state / county dispatch centers should be noted in your Observer Checklists.

4. Should the USNRC elect not to participate in this drill relative to the use of the Emergency Response Data System (ERDS), the Plant Data Controller will turn off the ERDS GPU NUCLEAR CORPORATION At\0412959 9.3 E$$5$7idi

ANNUAL EXERCISE April 12, 1994 COMMUNICATIONS OBSERVER INSTRUCTIONS (Continued) modem. The Communicator should perform the steps in Procedure EPIP-TMI .03, Emergency Notifications and Call D outs regardless of the NRC's decision. If the modem is i turned off, the CRT indications will differ from those specified in the procedure as follows:

Modem Status: Fail Link Status: Fail ,

ERDS Status: Inactive !

Explain'to the Communicator that the NRC is not !

participating via ERDS and give the drill participant credit l if the steps were performed properly. The steps in EPIP-TMI .03 should actually be performed. Do nqt allow the ;

Communicator to report the system out of service; simulate "

that the ERDS system is in service and operating.

5. Before securing from the drill, ensure closeout ;

notifications have been completed in accordance with ,

procedures EPIP-TMI .03 and EPIP-TMI .27. Verify I completion with the EOF Communications Coordinator or .

j Communicators as well as the ECC Communications Coordinator -l or Communicators. ~j I

6. If problems are encountered with any communications !

hardware, ensure you record all relevant information so that repairs can be arranged following the drill. Do not allow the ECC Communications Coordinator to actually call off site companies for communications repairs during the drill. Bell of Pennsylvania, AT&T, Communications Systems Specialists, etc. will be contacted through normal channels following the drill.

1 I

l CPU NUCLEAR CORPORATION At\0412959 9.4 E85557l"i9E

ANNUAL EXERCISE-3 April 12, 1994 OPERATIONS EVALUATOR INSTRUCTIONS

1. Arrive at the Plant Reference Simulator in sufficient time to allow for simulator start up and set up. Initial Conditions will be provided to the drill participants in the simulator at T = -30 (1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months ).

2. Because this drill is a full participation exercise, a number of outside agencies will be participating. To allow for a proper evaluation of outside. agencies, this scenario ~

must closely follow a time line agreeable to regulatory agencies, as well as GPU Nuclear. In order to comply with the selected time line, certain contingency messages and scenario control features are necessary for this drill.

3. As part of the initial conditions, the control room staff will be informed that block valve RC-V-3 is closed to compensate for leakage past Pressurizer Spray Valve RC-V-1..

A schedule for cycling RC-V-3 will be provided to them identifying that RC-V-3 must be cycled at 1535 hours0.0178 days 0.426 hours 0.00254 weeks 5.840675e-4 months .

Should the control room staff. neglect to cycle RC-V-3 at the specified time (T = 5 /1535 hours), read Contingency Message OE-1 to them. This message serves to identify a plant component failure and provides a scenario control function.

4. At.approximately T = 25 (1555 hours0.018 days 0.432 hours 0.00257 weeks 5.916775e-4 months ), the Control Room staff should decide to shut down the plant once the primary to secondary leak rate is determined to be of sufficient magnitude to require such an action. If a shut down rate other than 1 % per minute is selected or if the decision is not made to shut down, read contingency Message OE-2 to the Emergency Director.

5. In order to control the drill parameters and the drill time line, read contingency Message OE-3 to the ECC staff at T = 150 (1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months ) if a cool down rate other than 90 degrees per hour is selected. This will specify a cool down rate of 90 i 10 degrees per hour.

6. After the plant cool down is initiated at approximately T = 160 (1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months ), read Message OE-4 to the ECC staff.

This message will inform them that decay heat is being controlled (frozen at 4%) and will not be at expected levels to allow the drill to meet exercise objectives.

i GPU N'JCLEAR CORPORATION As\0412,5, 9.5 EEEEEi,E L

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ANNUAL EXERCISE

' April 12,'1994 i OPERATIONS EVALUATOR INSTRUCTIONS.(Continued) ,

7. At the completion of.the drill, ensure all equipment is '

returned to the proper storage location.and the Simulator Control Room'is returned to'. pre-drill. conditions.

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CPU MUCLEAR CORPORATION i MIDDLETOWN, P t As\041295, 9.6 corralcar is,As i

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ANNUAL EXERCISE April 12, 1994 4

IN PLANT ROVER INSTRUCTIONS Note 1: Do not allow drill' participants to enter actual contamination, airborne, or high radiation areas.

Entry into a radiation. area is acceptable provided the ALARA program is observed and entry into the area will enhance drill continuity and realism. Ensure all drill participants'are signed on to a valid Radiation Work Permit before entering any actual RWP areas. Ensure observers and participants do not violate site radiological practices.

Note 2: Do not allow drill participants to actually manipulate, disassemble, or take readings on plant equipment.

However, drill participants will be expected to work on

" mock-ups" if provided.

Note 3: Ensure extreme caution is exercised in the vicinity of energized, rotating, moving, or hot equipment. Obey all safety rules. ,

Note 4: Applicable drawings _and tech manual pages are provided only for the observers in_the In Plant Rover Supplemental Information Package. Do'not supply this

'information to drill participants unless otherwise directed.

Note 5: Do not allow drill participants to simulate procurement of tools, drawings, spare parts, etc.

1. INITIAL CONDITIONS A. A reactor building purge is in progress.

B. Pressurizer Spray Block Valve RC-V-3 is closed due to leakage through the Spray valve RC-V-1. While this condition exists, the block valve is cycled every four hours to confirm operability. The next scheduled cycling of RC-V-3 is at T = 3 (1535 hours0.0178 days 0.426 hours 0.00254 weeks 5.840675e-4 months ).

C. "A" Make Up pump MU-P-1A is off but available, s

GPU NUCII.AR CORPORATION

-Anouris, 9.7 EENIEEi,E

ANNUAL EXERCISE April 12, 1994~

IN PLANT ROVER INSTRUCTIONS (Continued)

D. "B" Make Up pump MU-P-1B is running and powered from the lE 4160 volt bus.

E. "C" Make Up pump MU-P-lC is out of service due to the discovery'of a cracked shaft-on the pump on April 04-10-94 at 0800. The pump is disassembled and a replacement shaft is being shipped to the site.

Because two other Make Up pumps were available when MU-P-lC was taken out of service, the plant did not enter a Tech. Spec. time clock but a 30 day administrative time clock is in affect.

2. PRESSURIZER SPRAY LINE ISOLATION VALVE RC-V-3 In accordance with the Initial Conditions, the Pressurizer Spray Line Block Valve is closed due to leakage through Spray Valve RC-V-1. In accordance with Technical Specifications, RC-V-3 is required to be cycled to ensure operability every four hours. The block valve was last cycled successfully at 1135 hours0.0131 days 0.315 hours 0.00188 weeks 4.318675e-4 months . At T = 5 (1535 hours0.0178 days 0.426 hours 0.00254 weeks 5.840675e-4 months ),

the Control Room Operators will be informed that the time to cycle RC-V-3 has elapsed and it must again be verified operable.

When Operations attempts to cycle RC-V-3, it will not respond. When an Emergency Repair Team is assembled to address the probleia. follow them through the briefing, preparation and work crocess. All tools, parts, test equipment, and documentation (including prints, drawings, technical manuals, and procsdures) that would be needed to actually trouble shoot the system must be produced at the job site by the Emergency Repair Team. Do not allow the team to actually open, troubleshoot, or take readings on the in-service switch gear.

Discussions regarding the motor operated valve control circuitry should take place at the 1B ES Control Center, Unit 10B. Have the Emergency Repair Team explain their trouble shooting process in detail using the applicable prints and drawings provided by the drill participants.

If the Emergency Repair Team takes the. proper actions to CPU NUCI. EAR CORPORATION A:\041293, 9.8 EEEEE7i,E

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d ANNUAL EXERCISE

. April 12, 1994 j t

IN PLANT ROVER INSTRUCTIONS (Continued) ;

investigate the failure of the block valve to open, inform them.that the control circuit is tripping on torque ;

overload. Jammed valve internals are the source of the problem but this problem would not be detectable by the ,

Emergency Repair Team without a reactor building. entry and physically disassembling the valve. ;

3. PRIMARY TO SECONDARY LEAK ,

A Primary to Secondary leak will commence in both Steam -

Generators at.T = 15 (1545 hrs.).

The leak rate is between 80 and 100 gallons per minute with 70% coming from the "A" ;

OTSG and 30% coming from the "B" OTSG. The leak rate will be quantified at approximately 80 gallons per minute and a plant shut down will be initiated between T = 15 and T = 25.

The steam generator leakage will increase to = 650 gpm at :

T = 165 (1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months ) and the Sub Cooling Margin will , ,

decrease to less than 25 degrees. At T = 265 (2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ),

the leak rate increases. The Sub Cooling Margin will become negative at T = 295 (2025 hours0.0234 days 0.563 hours 0.00335 weeks 7.705125e-4 months ). The Sub Cooling Margin will be recovered (less than saturation temperature) at T =

320 (2050 hours0.0237 days 0.569 hours 0.00339 weeks 7.80025e-4 months ). .,

4. MAKE UP PUMP MU-P-1A When Operations attempts to start the "A" Make Up Pump at T= 165 (1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months ), it will not start. .If it is already ,

running, it will trip at T = 165. Repeat attempts to start -

or restart the pump will not be successful.

If an Auxiliary Operator or Emergency Repair Team is tasked with investigating or rectifying the pump start failure, [

monitor the briefing and any preparations for the assignment. Any items needed to accomplish the task such as hand tools, test equipment, supplemental lighting, protective clothing, documentation (including drawings, ,

prints, procedures, and technical manuals), or keys must be i produced at the job site. Do D2t allow drill participants to actually manipulate, adjust, disassemble, open, take readings on, or work on plant equipment. Have the-individuals involved explain in detail what they would do to investigate the problem. If they must operate a component, CPU HUCLEAR CORPORATION Ai\041295, 9.9 EEN5EEi,E I t

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ANNUAL EXERCISE.

April 12,.1994 J

IN PLANT ROVER INSTRUCTIONS (Continued) ,

the staff must be able to locate the device.

Discussions concerning the control circuit should take place at the 1D 4160 volt Switch Gear on the 338 foot 6 inch elevation of the Control Building. The "A" Make Up Pump is Unit ID7.

Have the Emergency Repair Team explain their troubleshooting process in detail using the appliccble prints and drawings provided by the drill participants. Any electrical test readings taken will result in normal values. As tho team progresses through the trouble shooting process, they should investigate the possibility of a circuit breaker malfunction. When this avenue is investigated, inform the Emergency Repair Team that the breaker is mechanically binding if their actions / explanation would have ' revealed such a problem.

The Emergency Repair Team may elect to repair the circuit breaker, or replace it with a compatible unit. Possible sources for a replacement 1 breaker include Unit' 1D8 (for MU-P-1C which is presently powered from the 1E bus) or 1E 4160 volt Unit 1E8 (for the out of service MU-P-1C).

If the time is T = 305 (2035 hours0.0236 days 0.565 hours 0.00336 weeks 7.743175e-4 months ) or later, repairs or replacements performed by the Emergency Repair Team will return the "A" Make Up Pump to service. If necessary to delay repair efforts until T = 305, contingency failures must be used. Difficulties in removing the circuit breaker from, or inserting the replacement breaker into the cabinet can be used. Misalignment, binding, or stripped rack-in components are some of the possibilities. Select contingency failures only as necessary to prevent the Make Up Pump from a return to service time earlier than T = 305.

See " Miscellaneous" in these In-Plant Rover Instructions.

5. DECAY HEAT REMOVAL PUMP DH-P-1B At T = 165 (1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months ), the "B" Decay Heat Pump will also trip and attempts to restart the unit will be unsuccessful.

Shortly after the trip, AMS-3 alarms will be received in the Auxiliary Building.

GPU NUC12AR CORPORATION Aiu uz,s, 9.10 EEEc'E"i,E

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ANNUAL EXERCISE April 12, 1994 IN PLANT ROVER INSTRUCTIONS (Continued)

When an Emergency Repair Team is assembled to investigate the loss of the "B" Decay Heat Pump, accompany them during their briefing and preparatory activities as well as on the job. All tools, test equipment, and documentation (such as prints, drawings, procedures, and technical manuals) necessary to actually perform the task must be produced by the team at the job site. Do ngt allow the participants to actually work on or take readings.on the equipment.

Investigation of the control circuit should take place at the lE 4160 Volt switch gear on the 338 foot 6 inch elevation of the control Building. DH-P-1B is Unit lE7.

Teams may already be in the area for work involving MU-P-1A.

Have the Emergency Repair Team explain in detail the process by which they would troubleshoot the problem. Prints and drawings, supplied by the drill participants, should be used. If they check the indicator flags, the unit will be discovered to have tripped on overload. Electrical readings will show normal voltage to be available. $ to $ readings will reveal normal resistance readings, as will $ to ground resistance readings. To obtain this information, the personnel must have the appropriate test equipment with leads, and the test equipment must be selected to the correct function and scale.

When the "B" Decay Heat Pump vault is approached, radiation levels will increase. Steam is seen issuing from the "B" Decay Heat Pump vault, significant enough to preclude the possibility of approach. This condition will exist for approximately ten minutes, or until the pump is successfully isolated by Operations. After pump isolation and steam dissipation, it may be decided to inspect the vault. Review Note 1 at the beginning of the In-Plant Rover Instructions.

The entrance to DH-P-1B vault is located in an actual High Radiation Area and cannot be entered for drill purposes. If inspected, use prints and drawings and have the Emergency Repair Team explain their investigation. Obvious mechanical damage will be discovered at the pump. Bearing failure will have resulted in failure of the pump seals. Damage is obviously severe and cannot be repaired during the drill time frame GPU NUCIZAR CORPORATION Aamme 9.I1 SEE"ioE

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l ANNUAL EXERCISE April 12, 1994 IN PLANT ROVER INSTRUCTIONS (Continued)

6. CORE FLOOD TANK CF-T-1A NITROGEN At T = 155 (1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months ), nitrogen pressure will be lost on the "A" Core Flood Tank. This will reduce the amount of water available to replace the reactor coolant volume which is lost due to cool down.

If an Auxiliary Operator or Emergency Repair Team is tasked with investigating or rectifying the loss of pressure, monitor the briefing and any preparations for the assignment. Any items needed to accomplish the task such as hand tools, test equipment, supplemental lighting, protective clothing, documentation (including drawings, prints, procedures, and. technical manuals), keys, or ladders must be produced at the job site. Do not allow drill participants to actually manipulate, adjust, disassemble, open, take readings on, or work on plant equipment. Have the individuals involved explain in detail what they would do to investigate the loss of CF-T-1A pressure. If they must adjust a valve, the staff must demonstrate the ability to locate the valve. Increasing the nitrogen flow to the tank will not cause pressure to be regained in CF-T-1A, indicating that the nitrogen is being lost at a rate greater than can be made up. Because the nitrogen supply piping and leak in the piping cn: associated components are located inside the Reactor Building, it will not be probable that an entry into the reactor building will be made to determine the exact location of the leak.

Although unlikely, the staff may decide to send an Emergency Repair Team into the Reactor Building to attempt to find and correct the cause of the Core Flood Tank depressurization.

If this is done, all preparatory actions must be performed by the support and entry teams. After donning the required protective clothing, stop the entry at the step-off pad at the entrance to the Reactor Building air lock. Then have the team explain the location of the valves and piping to be investigated. If this is done to your satisfaction, inform the individual (s) that the one inch nitrogen piping has sheared between valve CF-V-26A and CF-V-27A. Any further action will be discussed by the team and Observer but repairs will not be completed during the drill time frame.

GPU NUCLEAR CORPORATION Ai\0412,5, 9.12 Es$$$5"i,$

ANNUAL EXERCISE April 12, 1994 IN PLANT ROVER INSTRUCTIONS (Continued)

7. CORE FLOOD VALVE CF-V-4B At approximately T = 155 (1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months ) or when needed, the "B" Core Flood Tank check valve will fail to open. This will reduce the amount of water available to replace the reactor coolant which is lost because of the cool down. Although the valve will fail at T = 155, the plant staff will not be aware of a problem until RCS pressure is reduced to 600 psi.

When CF-T-1B fails to flow water, it should be apparent that a problem exists with the check or block-valve.

If an Auxiliary Operator or Emergency Repair Team is tasked !

with investigating or rectifying the inability to use the contents of CF-T-1B, monitor the briefing and any preparations for the assignment. Any items needed to accomplish the task such as hand tools, test equipment, supplemental lighting, protective clothing, documentation (including drawings, prints, procedures, and technical manuals), keys, or ladders must be produced at the job site. !

Do npf allow drill participants to actually manipulate, adjust, disassemble, open, take readings on, or work on plant equipment.

Have the individuals involved explain in detail what they would do to investigate the lack of flow from CF-T-1B. Any troubleshooting outside the reactor building must include the ability to locate the components involved. Because the piping and components associated with the failure are located inside the Reactor Building, it will not be readily accessible. Although unlikely, the staff may decide to send an individual into the Reactor Building to attempt to investigate. If this is done, all preparatory actions must be performed by the support and entry teams. After donning the required protective clothing, stop the entry at the step-off pad at the entrance to the Reactor Building air lock. Then have the team explain the location of the relevant valves and procedures necessary to open them.

Despite their best efforts, check valve CF-V-4B cannot be opened during the drill time frame. J l

CPU NUCLEJJL CORPORATION m o m es, 9.13 EINU5E"i,E

l ANNUAL EXERCISE April 12, 1994

( IN PLANT ROVER INSTRUCTIONS (Continued)

8. SEARCH AND RESCUE When the accountability process is completed, one individual will be discovered to be missing. The individual will be found to be injured in the turbine building. Monitor the Search and Rescue Process. Due to the person's injuries, the plant staff will need to extricate him from a cat-walk.

Personnel should be dispatched from the OSC to perform and/or assist with the resc'ue. The Safety and First Aid Observer will the have responsibility for monitoring the rescue evolution.

9. MAKE UP PUMP MU-P-1B At T = 265 (1955 hours0.0226 days 0.543 hours 0.00323 weeks 7.438775e-4 months ), the "B" Make Up Pump will trip.

Attempts to restart the pump, powered from either the 1E 4160 Volt bus or the ID 4160 volt bus, will be unsuccessful.

When an Emergency Repair Team is assembled to investigate the loss of the "B" Make Up Pump, accompany them during j their briefing and preparatory activities as well as on the '

job. All tools, test equipment, and documentation (such as prints, drawings, procedures, and technical manuals) ;

necessary to actually perform the task must be produced by ;

the team at the job site. Do not allow the drill participants to actually work on or take readings-on the equipment.

1 Investigation of the control circuit should take place at the 1E 4160 Volt switch gear on the 338 foot 6 inch ;

elevation of the Control Building. MU-P-1B is Unit 1E9 on j the lE 4160 (Unit 1D8 on ID 4160). Teams may already be in i the area due to continuing work on MU-P-1A and DH-P-1B.

Have the Repair Team explain in detail the process by which they would troubleshoot the problem. Prints and drawings, supplied by the drill participants, should be used. If checked, the unit will be discovered to have tripped on over current. Electrical readings will show normal voltage to be available. Phase to ground readings will reveal normal resistance readings. Phase to phase resistance readings, however, will indicate a direct short between two phases.

GPU NUCLEAR COFJ ORATION ,

A:soum, 9.14 E$ ERNE 71,E

ANNUAL EXERCISE April 12, 1994 IN PLANT ROVER INSTRUCTIONS (Continued) l 1

l To obtain this information, personnel must have appropriate l test equipment with leads, and the test equipment must be selected to the correct function and scale.

Pursuing the $ to p short will reveal that the problem is not in the switch gear. Through a process of elimination, if the proper actions are explained in detail, the insulation break down will be traced to the motor itself.

Testing at the motor lead connection box will confirm the motor to be unusable. As a motor rewind would not be possible during the drill time frame, MU-P-1B will not be e returned to service. W

10. DECAY HEAT REMOVAL PUMP DH-P-1A When Operations attempts to start the "A" Decay Heat Pump at T = 265 (1955 hours0.0226 days 0.543 hours 0.00323 weeks 7.438775e-4 months ), it will not start. Repeat attempts to start the pump will result in no response.

If an Auxiliary Operator or Emergency Repair Team is tasked with investigating or rectifying the pump start failure, monitor the briefing and any preparations for the assignment. Any items needed to accomplish the task such as hand tools, test equipment, supplemental lighting, protective clothing, documentation (including drawings, prints procedures, and technical manuals), or keys must be produced at the job site. Do act allow drill participants to actually manipulate, adjust, disassemble, open, take readings on, or work on plant equipment. Review Note 1 at the beginning of the In-Plant Rover Instructions.

Have the individuals involved explain in detail what they would do to investigate the problem. If they must operate a component, the staff must be able to demonstrate the ability to locate the device.

Discussions concerning the control circuit should take place at the 1D 4160 volt Switch Gear on the 338 foot 6 inch elevation of the Control Building. The "A" Decay Heat Pump is Unit 1D6. A team may also be working in the adjacent breaker cubicle in an attempt to return MU-P-1A to service.

CPU NUCLUJL CORPORATION A:\0412959 9.15 $UEE?"i,E

ANNUAL EXERCISE April 12, 1994 IN PLANT ROVER INSTRUCTIONS (Continued)

Have the Emergency Repair Team explain their troubleshooting process in detail using the applicable prints and drawings provided by the drill participants. Any electrical test readings taken will result in normal values with the exception of the circuit down stream of the control fuses.

The fuses will be found to be blown if the Emergency Repair Team has the relevant test equipment and test leads, the test equipment is selected to the correct function and scale, and describes the method used to check the fuse.

If the Repair Team can produce a compatible replacement fuse i and the time is T = 305 (2035 hours0.0236 days 0.565 hours 0.00336 weeks 7.743175e-4 months ) or later, the "A" Decay l Heat Pump can be returned to service. If the Emergency l Repair Team does not take any action to discover and correct the problem, DH-P-1A will remain out of service. If the repairs will be completed prior to T = 305, it will be l necessary to introduce contingency delays. If si l time remains, the fuse holder can be broken when.gnificant installing the replacement fuse. If a short time remains, the down I

stream fuse can also be found to be blown. A defective replacement fuse can also be discovered. Review the l

" Miscellaneous" section in these In-Plant Rover Instructions.

11. TURBINE BUILDING Because of the Primary to Secondary Leak, any personnel l entering or traversing the Turbine Building without proper protective clothing after T = 301 (2031 hours0.0235 days 0.564 hours 0.00336 weeks 7.727955e-4 months ) will become contaminated in accordance with the Worker Contamination Report on page 9.18. AMS-3 alarms will activate in the building at T = 301 (2031) . If evaluating personnel passing through the Turbine Building without the correct personnel protective clothing after T = 301, wait until they l are monitored before informing them of their contamination.

l l 12. INTERMEDIATE BUILDING Because of the Primary to Secondary Leak, any personnel entering or traversing the Intermediate Building without proper protective clothing after T = 301 (2031 hours0.0235 days 0.564 hours 0.00336 weeks 7.727955e-4 months ) will become contaminated in accordance with' the Worker CPU NUCLEAR CORPORATION Ai\0412959 9.16 EEUcEEitE

l

. r ANNUAL EXERCISE !

April 12, 1994 i

IN PLANT ROVER INSTRUCTIONS ~ (Continued)

Contamination Report on page 9.18. AMS-3 alarms will activate in the building T = 301-(2031 hours0.0235 days 0.564 hours 0.00336 weeks 7.727955e-4 months ). If evaluating personnel passing through the Intermediate Building without the correct personnel ~ protective-clothing after T.= 301, wait until they are' monitored before. !

. informing them of their contamination. ;

13. MISCELLANEOUS:

In order.to drive the drill toward the desired result.and.

satisfy the drill objectives, it may be necessary to fail certain components and either prevent or further delay their :

return to service. To realistically control the Emergency Repair Team's progress toward success, the In-Plant. Rover may need to resort to contingency situations. .These'can. ;

~

include but are not limited to, tools breaking or missing, torn protective clothing, failed respiratory protection . .

equipment, rounded nut or bolt flats, sheared bolts, etc.

Do not allow any failed component to be returned to service earlier than specified in the drill: time line without ,

specific app r~ oval from the Plant Data Controller'. However, 1' due to extraordinary' Emergency Repair Team efforts, it may be necessary to give the repair team' credit for an ,

expeditious repair and.not allow the Simulator. Control Room , I (ECC) or Operations Support Center-to-know ofvthe component's availability until permitted by the drill time :

line or Drill Coordinator. !

l l

l CPU NUCLEkR CORPORATION At\0412959 9.17 EINUEisE l l

6

=m

Annual Exercise l 4/12/95 E TMI-1 WORKER CONTAMINATION REPORT O TMi-2 Name Date Inplant Worker E** 2031 hrs 4/12/95 Describe cause of contamination-

)

Use this data if a worksr enters the Turbine or ,

Interrnediate Buldings without proper protective clothing ;

after 2031 hrs.

I SURVEY DATA By Date Time Inst.

SURVEY RESULTS (CPM) 2031-2050 2051- 2115 2116-2130 l 2131-END 1 2 3

@ 150 180 200 200 h 150 170 180 180 i h 120 150 180 150 y k5

y h,[

@ o h 150 120 180 150 200 120 180

, , @ .120 150 180 200

@ 250 350 450 500 h 400 500 600 650 Remarks:

h 500 700 800 800 9.18

l ANNUAL EXERCISE April 12, 1994 SAFETY-AND FIRST AID OBSERVER INSTRUCTIONS

1. This evolution will have two observers assigned. The primary observer will evaluate the response and the victim's comments will also be reviewed.

2. When the mustering and accountability process is completed, one individual will be discovered to be missing. This individual will be staged in the turbine building on the platform at the 344 foot 10 inch elevation, accessible from the ladder north-west of the high pressure turbine on the 355 foot elevation. The reason the person does not comply with the muster and accountability instructions is because he has a possible fracture of the right fibula. There is no page phone at this location and the person is unable to climb the ladder.

3. The estimated time the person will be found is at T = 215 (1905 hours0.022 days 0.529 hours 0.00315 weeks 7.248525e-4 months ). At this time, the Medical Department and TMI volunteer EMS personnel should be dispatched to assist in the treatment of the injured worker. The worker will inform the plant staff that he slipped while descending the ladder and will complain of severe pain in his right lower leg, radiating to above the knee. Extreme tenderness is present at the injury site with discoloration noted. All other signs and symptoms, including vital signs, will be as read /seen. The patient is ngt contaminated and all measurements will be as read.

4. The patient will need to be extricated from the platform.

At least three personnel on each shift have been trained in the use of the confined space rescue equipment, and the fire brigade has been trained to assist. The use of this equipment would be a logical choice ahen deciding how to extricate the victim. Other possibilities exist including use of the over-head crane, or even pure manpower. What ever method is selected, patient care must be the priority factor in its application.

5. The observer is not to assist the rescue personnel in the decision or implementation process. Personnel skills and equipment capabilities.will be evaluated, as will the ability to actually perform the task. Because of the nature of the evolution, either Observer (Safety Observer or CPU NUC12.AR CORPORATION Anona,3, 9.19 E8EEESEi,E

P i

ANNUAL EXERCISE April 12, 1994 !

I SAFETY AND FIRST AID OBSERVER INSTRUCTIONS (Continued) victim) will have absolute authority and responsibility to stop the evolution if the safety of any person, or the l integrity of any plant component is about to be compromised. ;

6. Once the patient is extricated and packaged for transport, he is to be transported to a gate or door an ambulance would i be able to access. Off-site EMS-response will not be a part i of this drill and the ambulance will be simulated. Once the patient reaches a protected area gate, this mini scenario is ,

complete.

t f

i

?

t I

r 3

CPU NUCLEAR CORPORATION h Anour,s, 9.20 E$$557i,E l

ANNUAL EXERCISE April 12, 1994 PUBLIC INFORMATION OBSERVER INSTRUCTIONS

1. When personnel respond to the Joint Information Center, provide the video tape for simulated Media Broadcast monitoring.

2. At T = 60 (1630 hrs.), call the ECC at 948-2069, 948-2070, or 948-2071 and read Message PI-1 to the individual answering the telephone. The caller is seeking information for a Traffax report. Record the instructions or response from the ECC staff member who should refer the caller to the Communications Division.

3. At T = 120 (1730 hrs.), call the ECC at 948-2070, 948-2071, or 948-2069 and read Massage PI-2 to the individual answering the telephone, The caller is a television news show producer requesting permission to place a camera on site for real time footage of the emergency. The caller should be referred to the Communications Division.

4. At T = 240 (1930 hrs.), call the EOF at 948-8903, 657-0739, or 657-0471 and read Message PI-3 to the individual answering the phone. The caller is the Yard Master at the Summerdale Conrail Yard inquiring if his trains can safely t pass the plant along the east shore rail lines. The Yard Master should be directed to contact the TMI communications <

Division or County Emergency Management Agency.

5. At T = 330 (2100 hrs.), call the EOF at 657-0739, 657-0471,

or 948-8903 and read Message PI-4 to the individual answering the telephone. The caller is a truck driver tasked with delivering fuel oil to Three Mile Island for the Auxiliary Boilers. He is concerned with his safety if he l comes on the island. The caller should be directed to contact the Communications Division. -

6. At the completion of the exercise, ensure the Joint Information Center is returned to pre-drill conditions.

l CPU NUCLEAR CORPORATION A:so4:res, 9.21 EiE$ill?"i,E l

ANNUAL EXERCISE April 12, 1994 L

SECURITY AND ACCOUNTABILITY OBSERVER INSTRUCTIONS (Continued) this or other security related activities as you see fit.

If the individual has been located prior to the initiation of the accountability process, restage the individual so that Search and Rescue is demonstrated.

5. Personnel comp'leting their normal work day who are not directly involved in the drill will be allowed to exit the island.

6. The Emergency Assembly Area muster sheets will be given to a Site Protection Officer in accordance with the Emergency Assembly and Site Evacuation procedure (EPIP-TMI .36).

Collect the muster sheets from Site Security and turn them in with your observer comments following the drill.

CPU NUCLEAR ColtPORATION Aneur,3, 9.23 Es$5cTi,E

ANNUAL EXERCISE I April 12, 1994 SECURITY AND ACCOUNTABILITY OBSERVER INSTRUCTIONS

1. An. individual has been pre-designated to act as the missing person. He will wait in the turbine building on the platform at the 344 foot 10 inch elevation, accessible _from the ladder north-west of the high pressure turbine on the 355 foot elevation. This person has been instructed not to manipulate any plant equipment and he is to remain inconspicuous. The individual will not respond to the muster and accountability instructions provided over the plant page '

system. He further understands the following items:

a. The person is not to respond to muster and accountability instructions.

b. The person should not answer if paged. :

c. The person is not to evade security but stay in the location given above,

d. The individual is not to violate any security regulations such as piggybacking through key-carded i doors.

2. The person staged to be the missing person will also test the " rescue" aspect of the Search and Rescue process. He will simulate a victim with a broken leg who is unable to climb the platform's exit ladder. It will be necessary for the plant staff to effect an extrication using the confined space rescue equipment. The Safety and First Aid Observer t will be responsible for monitoring this process. ;

3. When a Site Area Emergency Accountability / Mustering is announced, observe the accountability process. Record the ;

response of the Security Officer and if the information is forwarded to the AEOF.

. 4. The Accountability process should be completed around T = l 200 (1850 hrs.). When the individual staged in the first instruction is discovered to be missing, observe Security's l involvement in the Search and Rescue process. Once the individual has been located, the Safety Observer takes the _'

lead responsibility for monitoring the rescue process. As the Security and Accountability Observer, you may monitor i

GPU NUCLEAR CORPORATION Anem,s, 9.22 EIEl$5E"i,E l

s

l r

ANNUAL EXERCISE Apri1=12, 1994 i .

L OSC OBSERVER. INSTRUCTIONS l

1. At T = -30 (1500 hrs.), arrive at the OSC and review the Drill Ground Rules and Initial Conditions with the OSC personnel that are to be Drill Participants.

2. During this drill, a number of major plant components will L fail. Monitor the response of the OSC staff in dealing.with !

the multiple failures, .the ability to devote appropriate-resources to the situation, and the application of the .

correct priorities to each incident as set by.the Emergency Director.

NOTE: Do not allow the staff'to actually call out bargaining unit personnel.

3. At'the completion of the exercise, collect all applicable drill paperwork (completed procedures, training attendance forms, etc.). Ensure all equipment is returned to the proper storage location and that-the OSC is returned to pre-

.. drill conditions.

GPU NUCLEAR CORPORATION Ar\0412,5, 9.24 ElsNlE!!"i,E

ANNUAL EXERCISE April 12, 1994 EMERGENCY ASSEMBLY AND SITE EVACUATION OBSERVER INSTRUCTIONS

1. Obtain a vehicle from Transportation before 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on Wednesday, April 12, 1995. Scheduled pick up time is 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months on Wednesday.

2. Proceed to Warehouse 1 with the vehicle at T = 0 to observe the activation of the Emergency Assembly Area in accordance with procedure EPIP-TMI .36. If the Emergency Director chooses Warehouse 3, proceed to Warehouse 3.

3. All nonessential personnel in Unit 1 and Unit 2 who are not exempt from the drill will participate in the muster and accountability process. Upon completion of the accountability process, the sweep of the outlying areas, and the mustering process, personnel not selected as evacuees for the drill may return to their normal duties with the exception of personnel working in the protected area.

Instruct the Emergency Assembly Area Coordinator to hold those personnel who work inside the protected area until J released by the Drill Coordinator.

4. Before any individuals mustering at the Warehouse are released, read Message EA-1 to the Emergency Assembly Area Coordinator (EAAC). In order to ensure personnel are available to demonstrate the evacuation process, three individuals are provided for this purpose.

5. When the muster is complete, the muster sheets will be given to the Site Protection Officer in accordance with the !

Emergency Assembly and Site Evacuation procedure (EPIP-TMI-

.36). When the EAAC is finished with this procedure, collect the signed off copy of EPIP-IMP .36 minus the muster sheets.

6. When the mini-evacuation is ordered by the Emergency Director, accompany the evacuees to the designated Remote j Assembly Area. j i

GPU NUCLEAR CORPORATION Aiseat2,s, 9.25 5$EIEEi,E

ANNUAL EXERCISE April 12, 1994 EMERGENCY ASSEMBLY AND SITE EVACUATION OBSERVER INSTRUCTIONS (Continued)

7. The evacuees will be monitored at the designated monitoring station in accordance.with.EPIP-IMP .36. Two individuals :

will be found to be contaminated in accordance.with the ,

diagrams on pages 9.27 and 9.28 .

Note 1: The observer will place sealed radioactive sources (Coleman lantern mantles) on two-of the evacuees !

to simulate contamination in accordance with the diagrams on pages 9.27 and 9.28 (where practicable).

Note 2: Provide the information on pages 9.27 and 9.28 as the monitoring is performed. Do not give these l sheets to the monitors. Forms from the emergency kit are to be used by the drill participants.

8. The two contaminated individuals will be decontaminated at the AEC' in accordance with EPIP-TMI .36. Observe the decontamination process in cooperation with the AEOF Observer.

9. Individuals acting in the capacity of the pre-designated ,

evacuees may remain at the AEOF for the duration of the drill after the monitoring process is complete, or they may ;

go home at their option. The Emergency Assembly and Site Evacuation Observer should assist the AEOF Observer in monitoring AEOF staff activities.

10. Return the company vehicle to Transportation after completion of the drill (scheduled for return no later than .,

~

1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months Thursday, April 13, 1995).

L GPU NUC1. EAR CORPORATION Aneuzn, 9.26 E!EEc'E"i,E t

1 ANNUAL EXERCISE 4/12/95 S TMl-1 Personnel Contamination Report O Tui-2 l Nome Time Date .

Evacuee #1 1915 hrs 4/12/es ,

Describe cause of contamination: ,

Evocuee traversed plume during evacuation.

.i l

SURVEY DATA By Date Time inst. t SURVEY RESULTS (CPM)

Initial Decon 1 Decon 2 Decon 3 ,

1 2 3

@ 200 180 130 <100 !

,, I @ 150 120 <100 e 4

evr , ,5 @

n 200 ,50 <100 l

+

W 5 130 <100 !

V}7}j - Q L

@ 140 <100 I hj,f@@ 4 -

h/b @ g

, @ @ @ l Remarks: -

l I

9.27 j

ANNUAL EXERCISE 4/12/95 MTMI-1 Personnel Contamination Report O Tui-2

" ** Evacuee #2 *1915 hrs DY/$2/es !

Describe cause of contamination:

Evacuee traversed plume during evacuation. :

) i SURVEY DATA By Date Time l Inst.

SURVEY RESULTS (CPM)

Initial Decon 1 Decon 2 Decon 3

@ 2 3

@ 900 400 230 <100

@ 400 250 120 <100

[v [ r

,,hl

@ 800 400 wo 180 200

<100

<100 i Vp/-Q@57 M @ 450 200 <100

,f '

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Remarks:

I 9.28

ANNUAL EXERCISE April 12, 1994 AEOF OBSERVER INSTRUCTIONS

1. Proceed to the AEOF at Crawford Station at T = 0 (1530 hrs.)

to observe the activation process. Unless specifically requested by the Emergency Director, personnel should not begin to man the facility until a Site Area Emergency is declared at approximately T = 150 (1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months ).

2. Do not assist responding staff members with entrance to the facility through the motorized gate or locked front door.

The AEOF staff members must demonstrate the ability to enter independent of help by non-AEOF staff members. The three Site Services Coordinators.all have gate openers and keys for this purpose.

3. The U.S. Nuclear Regulatory Agency has indicated that they will actually send an Incident Response Team as part of this drill. For that reason, testing of the site access process by the AEOF Observer will not be performed. Should the NRC Incident Response Team arrive at the AEOF and require processing and badging, all activities by the AEOF staff are to be in accordance with EPIP-TMI .32 and other applicable procedures. Monitor the process and record comments in your Observer Comments.

4. Any time around T = 280 (2010 hrs.), depending on the Remote Assembly Area selected, the contaminated evacuees from the plant should arrive at the AEOF. Monitor the decontamination process to ensure compliance with procedure 6610-ADM-4330.02, " Personnel Contamination Monitoring and Decontamination". The Emergency Assembly and Site Evacuation Observer is available to monitor the decontamination process if other AEOF activities require your attention.

Note 1: All parts of the decontamination process must be performed except showering and the actual removal of clothing.

Note 2: Refer to pages 9.27 and 9.28 for the number of times each person must be decontaminated and the ,

levels of contamination involved.

i l

GPU NUCLEAR CORPORATION A no m ,3, 9.29 E8EEcE"i,E l

l 1

I

ANNUAL EXERCISE.

April 12, 1994 AEOF OBSERVER INSTRUCTIONS (Continued)

Note 3: Coleman lantern mantles are used (where appropriate) to simulate contamination.

5. At T = 345 (2115 hours0.0245 days 0.588 hours 0.0035 weeks 8.047575e-4 months ), read Message AE-1 to the Site Services Coordinator. The Emergency Support Director is' requesting the AEOF staff to obtain a mobil unit capable of filling Self Contained Breathing Apparatus cylinders.

Monitor the ability of the staff to locate such a unit.

Most businesses will be closed by this time and the staff will not be able to make contact with a vendor. .The most likely source would be to forward the request to.the Dauphin County Emergency Management Agency. They have a listing of resources and control dispatch fire department units capable of satisfying the need. Do ant allow AEOF staff personnel to actually contact businesses, the Dauphin County Emergency Management Agency,-or fire companies for the compressor unit. Have the staff explain how they would obtain a mobil compressor unit capable of supplying breathing air. Ensure the AEOF staff does not contact the EOF or Emergency Support Director with the results of their search as this mini scenario affects only the AEOF.

6. Numerous plant components will fail during this drill which may exhaust the supply of on-site. personnel available for Emergency Repair Teams. The AEOF staff should be expected to be requested to supply supplemental personnel for repair activities. Verify the staff's knowledge of the location of the personnel telephone number listing at the AEOF. Do ngt allow bargaining unit personnel to be contacted or called out for this drill.

7. The Emergency Assembly and Site Evacuation Observer is available to assist you in monitoring AEOF activities once the evacuees have been decontaminated.

8. At the completion of the exercise, ensure all equipment is returned to the proper storage location and the AEOF-is returned to pre-drill conditions. Ensure all personnel have exited the facility and it is secured. Ensure the automatic gate closes before departing the area.

i GPU NtM".E.AR CORPORATION Aneur,s, 9.30 $$EE71,E t

m

l

. 1 ANNUAL EXERCISE April 12, 1994 TSC OBSERVER INSTRUCTIONS !

1. Arrive at the Technical Support Center at T = -30 (1500-hrs.) to set up the data link to the Simulator. Observe the TSC activation process when the Initial Response Emergency Organization is called out. Depending on the time required to identify and declare the event, the TSC personnel could ,

begin to man the facility any time around T = 25 (1555 l hours.). l l

2. During the course of the drill, multiple equipment failures !

will be experienced. As well as taxing the personnel manning the Emergency Repair Teams, TSC' Engineers will undoubtedly be requested to assist in returning equipment to service or provide suggestions for backup equipment.

Monitor the response to these demands. '

3. After the plant cool down is initiated at approximately T= 160 (1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months ), read Message TSC-1 to the TSC staff.

This message will inform them that decay heat is being controlled (frozen at 4%) and will not be-at expected levels to allow the drill to meet exercise objectives.

4. At the completion of the drill, ensure all equipment is returned to its proper storage location and the TSC is returned to pre-drill conditions.

l GPU NUCLEAR CORPOPATION anoensse 9.31 Es$$""id"

ANNUAL EXERCISE April 12, 1994 EOF CONTROLLER INSTRUCTIONS i

1. Arrive at the EOF any time around T = 0 (1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months ), to observe the activation process. Personnel should not man the facility until they are called out upon declaration of the Site Area Emergency at approximately T = 150 (1800 hrs.) -

unless the Emergency Director orders an earlier activation.

2. During the course of the drill, several events will occur, that, in reality, could require off-site assistance. Calls are to be simulated with the exception of the emergency off site notification process and calls to PEMA regarding the site evacuation process. A similar instruction is included in the Communications observer Instructions.

3. At T = 210 (1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months ), read Message EOF-1 to the Emergency Support Director. You will be playing the part of a member of the Emergency Support Organization whose fitness-for-duty status is questionable. The Emergency Support Director should direct the Emergency Preparedness Representative to administer a blood alcohol concentration test in accordance with Procedure EPIP-TMI .27, Exhibit 9A, " Emergency Operations Facility Fitness for Duty Determination Instructions". For the purposes of the drill,.all tests administered will result in a zero percent blood alcohol concentration.

4. The Public Information Observer will call the EOF at T = 240 i (1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months ) with Message PI-3. The caller will play the l role of Summerdale Conrail Yard Master. The yard master is j calling to inquire if it is safe to send rail cars down the j tracks along the east side of the river near Three Mile !

Island. The caller should be directed to the Communications !

Division or the Dauphin County Emergency Management Agency.

5. At T = 330 (2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months ), the Public Information Observer will call the EOF with Message PI-4 in the role of.an oil truck driver. The driver is assigned a delivery of fuel oil the Three Mile Island for the boilers but is concerned for i his safety. Monitor the conversation to see if the caller l is properly directed to the Communications Division or is given guidance regarding site access.

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ANNUAL EXERCISE April 12, 1994 EOF CONTROLLER INSTRUCTIONS (Continued)

6. The U.S. Nuclear Regulatory Agency has indicated that they will actually send an Incident Response Team as part of this drill. If they elect to do so, actual NRC personnel could arrive at the TMI emergency response facilities. Response to team activities should be in accordance with established procedures. Individuals requiring site access who do not possess a TMI security badge should be processed through the AEOF. Monitor the interaction between the Incident Response Team and the EOF-staff and record comments in your Observer Comments.

7. If dose projections, Protective Action Recommendations, etc.

are in progress, do not allow items 3, 4, and 5 to reduce your attention to the monitoring of the more significant items in the drill. Regardless of the items being observed however, do nQt allow calls to be placed to outside entities as specified in the instructions above.

8. At the completion of the drill, ensure all equipment is' returned to its proper storage location and the EOF is returned to pre-drill conditions.

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ANNUAL EXERCISE.

April 12, 1994 EOF TECHNICAL SUPPORT OBSERVER INSTRUCTIONS

1. Arrive at the Emergency Operations Facility at T = -30 (1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months ) to set up the data link to the Simulator.

Observe the EOF activation process when the Emergency Support organization is called out. Depending on the time required to identify and declare an event, the EOF personnel could begin to man the facility any time after T = 150 (1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months ), or sooner if the Emergency Director so directs.

2. After the plant cool down is initiated at approximately T= 160 (1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months ), read Message TS-1 to the EOF Tech Support staff. This message will inform them that decay heat is being controlled (frozen at 4%) and will not be at expected levels to allow the drill to meet exercise objectives. Ensure all functional areas are_ aware of this control feature.

3. At the completion of the drill, ensure all equipment is returned to its proper storage location and the EOF is returned to pre-drill conditions.

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CPU NUCLEAR CORPORATIOal At\0412959 9.34 EiEEE719E

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ANNUAL EXERCISE :

April 12, 1994 PARSIPPANY TECH FUNCTIONS CENTER OBSERVER INSTRUCTIONS

1. Arrive at the Tech Functions Center any time around T = 15 (1545 hours0.0179 days 0.429 hours 0.00255 weeks 5.878725e-4 months ) to observe the PTFC activation process when the i staff is called out. Depending on the time required to identify and declare an event,,the personnel could begin to man the facility any. time after T = 250 (1555 hrs.).

2. After the plant cool down is initiated at approximately '

T = 160 (1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months ), and as PTFC staff members arrive, read Message TF-1 to the personnel. This message will inform them that decay heat is being controlled (frozen at 4%) and will not be at expected levels to allow certain drill objectives ~to be met. Be certain the various functional areas are all aware of this drill control feature. ;

3. At the completion of the drill, ensure all equipment is returned to its proper storage location and the PTFC is returned to pre-drill conditions.

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ANNUAL EXERCISE c

April 12, 1995

)

MESSAGES / ANNOUNCEMENTS Unless provided in this section, normal plant procedures '!

will be used to make announcements. All announcements and-messages shall be. preceded and ended with the statement: ,

"THIS IS A DRILL. THIS IS A DRILL." !

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EMERGENCY REPORT FORM - TMI I

l J Nuclear (Press Firmly cnd Writ) Clearly) inNUAL ExEncIsr 1PRIL 12, 1995 l CALL OUT '

Z LEVEL 1 Onshift

-~~ LEVEL 2 Initial Response Emergency Organization & Onshift Z LEVEL 3 Emergency Support Organization & Initial Response Emergency Organization & Onshift DRILL USE ONLY - SITE AREA EMERGENCY Q This is a drill. This is a drill. O This is NOT a drill. This is NOT a drill.

l EMERGENCY CLASSIFICAT89N O An Unusual Event has been declared O A Site Area Emergency has been declared O An Alert has been declared O A General Emergency has been declared O The event has been terminated at hours on Emergency Classification Time Emergency Classification Date This represents: An initial Classification Status O An escalation in Classification Status C No change in Classification Status O A reduction in Classification Status EVENT DESCRIPTION There is: GNo abnormal radioactive O An abnormal radioactive airborne O An abnormal radioactive liquid ratasse to the environment as a result of this emergency.

IMUSTER/ EVACUATION i ALL PRE-DESIGNATED EVACUEES l 2_T_~_ _ _ i" _C_ Rem _aig_at_ ypp{ _s_tati_o_n_s a 9p_ await _ f gr_t_h_ef_ipptryS_tions.___ ___ ___ __ _______ _ ___ _ _ ___ _____ __ , ___

O In radiologically controlled areas, report to the Rad-Con access point, and those outside radiologically controlled areas, REPORT TO: u or 6 cr 'f or evacuation C"

. f _C _Y 99! _s_uppfpsoy_a n g _a wait _ fyr_t,hef _ipptrycti,c[ns _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ __ _ _ _ _ _ _ __ _

(Musters r muirea for B C Warehouse 1 O Warehouse 3 *.cno. roui.. n soonca-sit. -r.. cenera.ncv yj _ _____ ___ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

(Ev2cuationi C O AEOF (Crawford Station) O Training Center Reautrea ter eneret yjg gg SCT:De r0UIC)

Entera encsr using the O North Bridge O South Bridge O North and South Bridge Assemole with your supervisor and await further instructions.

l l O Shelter 0 Evacuate PROTECTIVE ACTION RECOMMENDATION -

mile radius I

O Shelter 0 Evacuate miles downwind in the affected and adjacent sectors (circled below): l 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 l METEOROLOGICAL CONDITIONS '

and the wind speedis miles per hour.

l Wind direction is from RADIOLOGICAL INSTRUCTIONS . '

(Reau rco for radiolooicai events) l isa O No smoking, drinking, or eating until further notice.

l O Sound station emergency alarm @

O This is a drill. This is a drill. O This is NOT a drill. This is NOT a drill. ._

5 DZtribution: Green Call Out/ Notification; YeNow . Contact; 1^'*'*- *** Pink Plant Page 5 1008

l EMERGENCY REPORT FORM - TMI ANNUAL EXERCISE N (Press Firmiy and Write Clearty) APRTL 12* 1995 l

l CALL OUT Z LEVEL 1 Onshift

~~'~' LEVEL 2 Initial Response Emergency Organization & Onshift Z LEVEL 3 Emergency Support Organization & Initial Response Emergency Organization & Onshift f

l DRILL USE ONLY - GENERAL EMERGENCY l

O This is a drill. This is a drill. O This is NOT a drill. This is NOT a drill.

l EMERGENCY CLASSIFICATION O An Unusual Event has been declared O A Site Area Emergency has been declared O An Alert has been declared O A General Err.ergency has been declared O The event has been terminated at hours on Emergency Classification Time Emergency Classification Date This represents: An initial Classification Status O An escalation in Classification Status O No change in Classification Status O A reduction in Classification Status EVENT DESCRIPTION Thrre is: CNo abnormal radioactive O An abnormal radioactive airborne O An abnormal radioactive liquid rcl ase to the environment as a result of this emergency. l l MUSTER / EVACUATION -

All non-essentral personnel 9'l " -- _ '_ O,_ Rem _aip_at_ ypyI_statipns_ and a wajt f urt_hef_ipstructsns._ __ ,,,,,_ _ _ _ __ _ __ _ ,,,_,,,,,,,_ _,,,,,,,_

O in radiologically controlled areas, report to the Rad-Con access point, and those outside radiologically controlled areas, REPORT TO: a i er Mr evacuation C"

. 2 C Y991_s_u_ pef v{sor,a n d_a wajt, har_t_h,ef,in sty _u_c_tipn s,_ _ _ _ ,_ _ _ _ _ _ , _ _ _ _ ,, _ _ _ _ _ , _ _ _ _ _ _ ,_ _ ,,,,,,

(Musters , muirea 'o' 9 O Warehouse 1 O Warehouse 3 "5c"o* 'ouur. e aconem, Site -rea cmeroenev yjg Ev:cuation) CC SITE EVACUATION IS NOT REQUIRED FOR THIS DRILL EXCEPT FOR PRE-DESIGNATED EMPLOYEES l(Reauirea nr Genere SITE EVACUATION IS NOT REQUIRED FOR THIS DRILL EXCEPT FOR PRE-DESIGNATED EMPLOYEES I O Shelter 0 Evacuate PROTECTIVE ACTION RECOMMENDATION mile radius !

O Shelter 0 Evacuate miles downwind in the affected and adjacent sectors (circled below):

I l METEOROLOGICAL CONDITIONS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 and the wind speed is miles per hour.

l Wind direction is from i

I (Ranuiren RADIOLOGICAL for radiolootcal eventsk INSTRUCTIONS j O No smoking, drinking, or eating until further notice. '

lt o Sound station emergency alarm O This is a drill. This is a drill. O This is NOT a drill. This is NOT a drill.

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06.wurution: Green - Call Out/ Notification; Ye#ow

Contact:

1 Pink - Plant Page E

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ANNUAL EXERCISE EXHIBIT 6 (Cont'd) APRIL 12, 1995 This form is completed by the Emergency Director Assistant and approved by the Emergency Director. This forms directs the evacuation and informs Dauphin County and PEMA of the evacuation to a Remote Assembly Area (RAA).

Given to Dauphin County and PEMA, before the Evacuation for a Site Area Emergency / or optional evacuation ordered by the Emergency Director.

MESSAGE 1: Approximately non-essential personnel will be evacuating the TMl site (number) to' the (Select one) .O Crawford. Station (AEOF).

C:; Training Centeri using the following route .

)

via'the (Select one) 0; North Bridgei .

Cl South Bridge) !

. Northlan'd South: Bridge Traffic Control will / wilinot be needed.

(Sciect one)

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX PLANT PAGE ANNOUNCEMENT

1. Turn on Whelen speakers.

READ MESSAGE SLOWLY MESSAGE 2: Attention all personnel. Attention all personnel. All non-essential personnel report: ~

(Read shadowed information from"abse)

Assemble with your supervisor and await further instructions.

l REPEAT MESSAGE

2. Turn off Whelen speakers.

Approved: Date:

10.4 2"

I ANNUAL EXERCISE April 12, 1995 MESSAGE: DC-1 T=0 / 1530 Hours Scenario / Clock FROM: Drill Coordinator TO: Drill Controllers. Observers, Participants HOW GIVEN: Plant Pace System MESSAGE: ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

The time is now T = 0. All drill participants issued radios switch to Channel 5. All drill participants issued radios switch to Channel 5.

THIS IS A DRILL. THIS IS A DRILL.

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ANNUAL EXERCISE g April 12,-1995- i i

MESSAGE: .OE-l* T=5 / 1535 Hours .l Scenario / Clock j i

FROM: Ooerations Evaluator !

' TO : ' ' Control Room Staff HOW GIVEN: ' Verbally i

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' MESSAGE: THIS IS A' DRILL.-THIS IS~A DRILL.-

i Cycle RC-V-3.. .;

THIS IS A DRILL. THIS IS A DRILL.

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Denotes a Contingency Message. See your Observer Instructions.-

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ANNUAL EXERCISE April.12, 1995 MESSAGE: OE-2* T = 25 / 1555 Hours Scenario /-Clock FROM: Operations Evaluator TO: Control Room Staff HOW GIVEN: Verbally MESSAGE: THIS IS A DRILL. THIS IS A DRILL.

Commence a reactor shutdown at 1% per minute.

THIS IS A DRILL. THIS IS A DRILL.

Denotes ontingency Message. See your Ob. server Instructions.

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ANNUAL EXERCISE April 12,'1995 MESSAGE: DC-2* T = 45 / 1615 Hours Scenario / Clock FROM: Drill Coordinator TO: Emercency Director HOW GIVEN: Verbally MESSAGE: THIS IS A DRILL. THIS IS A DRILL.

Declare an ALERT.

THIS IS A DRILL. THIS IS A DRILL.

Denotes a Contingency Messege. See your Observer Instructions.

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i ANNUAL EXERCISE 'f April':12,L1995-MESSAGE: PI T = 60 / 1630 Hours- -l Scenario / Clock: -}

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- TO: ECC St"## Member if HOW GIVEN: By Tc - (dial 948-2069. 948-2070, or 948-2071)' .l

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t MESSAGE: .THIS IS A DRILL. THIS IS A DRILL. i Hello.- This is: Charles.Duryea in-the Traffax Command .

Center. We picked .up 'on our monitors that you are having !

an' emergency at Three' Mile Island. Will this-have any-.

effect on traffic along Route 441?

THIS IS-A DRILL. THIS IS.A. DRILL. ;!

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ANNUAL EXERCISE April 12, 1995 :

MESSAGE: PI-2 T= 120 / 1730 Hours Scenario / Clock FROM: Public Information Observer TO: ECC Staff Member i

HOW GIVCi: By Telechone (dial 948-2070. 948-2071, or 948-2069)

MESSAGE: THIS IS A DRILL. THIS IS A DRILL. ,

Hi. My name is Ansel Adams. I'm the news director at television station W-U-P-S. We've been monitoring the emergency at Three Mile Island and would like to give our viewing audience better coverage. Is there some way we could set up at least one camera for a remote feed from inside the plant? If you want, we can set it up and ,

leave, without the need for an operator to be left ;

behind. How soon can we get some live coverage on the air?

, THIS IS A DRILL. THIS IS A DRILL.

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ANNUAL EXERCISE !

April 12, 1995 ,

MESSAGE: OE-3* 'T = 150 / 1800-Hours Scenario / Clock FROM: Operations Evaluator TO: ECC Staff i

IIOW GIVEN: Verbally ;

MESSAGE: THIS IS A DRILL. THIS IS A DRILL.

Cool down at 90* i 10*per hour.

e THIS IS A DRILL. THIS IS A DRILL. . !

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Denotes a Contingency Message. See your Observer Instructions.

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L MESSAGE: OE-4 T'= 160'/ 1810 Hours- '

Scenario / Clock ;

-FROM: Operations Evaluator I i

TO - ECC Staff i

HOW GIVEN: ' Verbally i

MESSAGE: THIS IS A DRILL. THIS IS A' DRILL. !

i Decay Heat -is _ being controlled. It will not be at expected levels. :

I THIS IS A DRILL. THIS IS A DRILL. -l

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A p r i l .1 ,'1 , 1995 :

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' MESSAGE: :TSC-1 T = 160~/ 1810 Hours l Scenario / Clock

,. FROM: TSC Observer TO: TSC Staff

'HOW GIVEN: Verbally. !

MESSAGE: THIS IS A DRILL. THIS IS A DRILL. .

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l Decay Heat is being controlled. It will' not be at j expected levels. '*

THIS IS A DRILL. THIS IS A DRILL. .i!

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~FROM: EOF Tech Sucoort Observer '

TO: EOF Tech Sucoort Staff (all functional arouns)

HOW GIVEN: Verbally

(- MESSAGE: THIS IS A DRILL. THIS IS A DRILL.

Decay Heat is being controlled. It will not be at expected levels.

THIS IS A DRILL. THIS IS A DRILL.

f GPU NUCLEAR CORPORATION MIDDLETOWN, PA C4129510 10.14 coPrucut less j l

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ANNUAL EXERCISE April 12, 1995 MESSAGE: TF-1 T= 160 / 1810 Hours Scenario / Clock ,

FROM: PTFC Observer TO: PTFC Staff (all functional aroups) h HOW GIVEN: Verhally '

MESSAGE: THIS IS A DRILL. THIS IS A DRILL. .

Decay Heat is being controlled. It will not be at expected levels.

THIS IS A DRILL. THIS IS A DRILL.

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April 12, 1995 !!

i, MESSAGE <- DC-3*- T= 180 / 1830' Hours ^!

Scenario / Clock .{

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i, TO: Emercency Director , '! ..

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- HOW GIVEN: Verbally j i

i MESSAGE: THIS IS A DRILL. THIS IS A DRILL. l l

Declare a SITE AREA EMERGENCY. -

THIS IS A DRILL. THIS IS A DRILL.

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ANNUAL EXERCISE April 12, 1995 MESSAGE: EA-1 T= 190 / 1840 Hours Scenario / Clock.

FROM: Emercency Assembly and Site Evacuation Observer TO: Emercency Assembly Area Coordinator ,

HOW GIVEN: Veri

ally MESSAGE: THIS IS A DRILL. THIS IS A DRILL.

Assemble three individuals to demonstrate the site evacuation process. Three individuals have already been ;

recruited to act as the evacuees.

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THIS IS A DRILL. THIS IS A DRILL.

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ANNUAL EXERCISE April ' 12 , . 19 9 5 .-

MESSAGE: EOF T = 210 / 1900 Hours Scenario / Clock 2FROM: EOF Controller

~TO: Emercency Support Director

-HOW GIVEN: Verbally _

' MESSAGE: THIS IS A. DRILL. THIS IS A DRILL.

b Hey. I had a couple of. low alcohol beers when I got home from work. I don't believe I'm impaired, but I know I'm supposed'to '

report this.

,i THIS IS A DRILL. THIS IS A DRILL. l

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April 12, 1995 MESSAGE: DC-4 T = 220 / 1910 Hours !

Scenario / Clock l FROM: Drill Coordinator TO: Emercency Director HOW GIVEN: Verbally l

l MESSAGE: THIS IS A DRILL. THIS IS A DRILL.

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Instruct the Emergency Assembly Area Coordinator to j initiate the mini evacuation.

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ANNUAL EXERCISE April;12, 1995 MESSAGE . PI-3 T = 240 / 1930' Hours .,

Scenario /-Clock FROM: Public Information' Observer _

- TO: EOF' Staff Member HOW GIVEN: By Telechone (dial 948-8903,'657-0739, or 657-0471)

MESSAGE: THIS IS A DRILL. THIS IS A DRILL.

Hi. This is the~ Conrail Yard Master at Summerdale. We understand you're having an emergency.down there and I was wondering it it's safe to send trains down the tracks along the east shore, past your power plant. Is it?.

THIS IS A DRILL. THIS IS A DRILL.

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MESSAGE: T = 300 / 2030 Hours Scenario / Clock j

-FROM: '_Dril1 Coordinator TO : - Emercency Director .,

HOW GIVEN: Verbally -

MESSAGE: THIS IS A DRILL. THIS IS A DRILL. !

Declare a GENERAL EMERGENCY. ;

THIS IS A DRILL. THIS IS.A DRILL.

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Denotes a Contingency Message. See your Observer Instructions. ,

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ANNUAL EXERCISE-April 12, 1995

-MESSAGE: PI-4 T = 330'/ 2100 Hours Scenario / Clock FROM: Public Information Observer l

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,TO: EOF Staff Member _

HOW GIVEN: By Telechone (dial 657-0739. 657-0471, or 948-8903)

MESSAGE: THIS IS A DRILL. THIS IS A DRILL. -

Yeah. My name is Mack Thermodyne. I'm supposed to deliver a load of fuel oil to Three Mile Island but the radio is full.of news about an emergency down' there. ;

Should I deliver my oil? Can you guarantee my safety? :

THIS IS A DRILL. THIS IS A DRILL. l I

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' MESSAGE: AE-1 T = 345-/ 2115 Hours

. Scenario /= Clock _

FROM:' 'AEOF Observer- ,

TO: Site Services Coordinator '

I HOW GIVEN: Verbally' MESSAGE: THIS IS A DRILL. THIS IS A DRILL..

The Emergency Support Director wants you to find a mobil' I unit capable 'of refilling Self Contained Breathing. <

Apparatus tanks' with breathing air. Show me how you would determine a source. Do not call the EOF. 'Give.all )

information to me. 1

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ANNUAL EXERCISE April 12, 1995 MESSAGE: DC-6 T = 390 / 2200 Hours Scenario / Clock FROM: Drill Coordinator TO: Drill Particioants/ Controllers / Observers

!!OW GIVEN: Plant Pace and Telephone (See Observer Instructionsi MESSAGE: ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

The drill is terminated. The drill is terminated.

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DRILL 95-03 ANNUAL EXERCISE 1995 DRILL GROUND RULES

1. Approach and perform all tasks with the same attitude, professionalism, and enihusiasm as if the situation were real. Do not assume that certain actions are unimportant becauso "THIS IS ONLY A DRILL". All actions are to be performed and not simulated, unless the action will result in personnel harm, damage to plant equipment or change the actual plant status.

(For example: i) Procurement of repair parts via a vendor or warehouse,

2) Troubleshooting a failed component by use of test equipment,

3) Checking for a pulse and breathing on a simulated injured unconscious person).

Although a task may appear to be redundant, inconvenient or a waste of materials, the task should still be performed in that it provides a realistic sense of timing and assures the observer that the action can and will be performed during actual accident (emergency) conditions.

2. Actually sign-off procedures as actions are performed, unless otherwise directed.

Used procedures will be replaced following the drill. To minimize confilct between drill conditions and actual plant status precede and end communications with "THIS IS A DRILL! THIS IS A DRILU" (This is to include the plant page, radio and intercom as a minimum.) Off site ,

notifications and emergency personnel call outs are actually performed.

3. Ensure that observers are aware of your activity by verbalizing your actions (For example: procedures used, actions initiated, personnel contacted, decisions made, etc.). Let the observer know WHAT you are doing, WHY you are doing it, HOW you will do it and WHAT procedures you will use. This will promote a more accurate observer evoluotion.

Plant data is provided to selected emergency response facillfles (TSC, EOF, PTFC) via data links to CRT's from the Plont Reference Simulator. If Simulator indications are questionable, check with the facility observer or Plant Data Controller to validate the indications prior to taking actions.

If in doubt. ASK. ;

DRILL 95-03 '

ANNUAL EXERCISE 1995 DRILL GROUND RULES (Continued 1 1

4. Prompting by drill observers is not allowed. Observers will only provide information which is normally available by visible or audible inspection. (For example: meter readings but not historical trends, instruments currently alarming, etc.)

5. Obey all plant page announcements. For example, do not eat, drink or smoke offer the "no eating,-drinking or smoking" announcement is made. Unless otherwise announced, personnel muster and accountability will be performed for nonexempt personnel. Site evacuation will be demonstrated using only 1 designed individuals, unless otherwise announced.

Additionally, Radiological Controls and Security requirements are to be followed.

This means: 1) Do not violate drill Rod Con barriers,

2) Follow Rod Con instructions (e.g., wearing respirators and/or PC's),

3) Do not violate Security procedures (i.e., piggybacking, etc.)

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6. Drills are run from the Simulator. Therefore, calls normally made to the Control i Room are to be directed to the Simulator Control Room, if they pertoln to the drill.

During the drill, the Simulator is accessible by Plant page (use the red button),

radio (Channel 5) and telephone (948-2069,948-2070, 948-2071, or 948-2063

[RAC]).

7. The DRILL RWP for 1995 is # 97380.

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DRILL 95-03 ANNUAL EXERCISE 1995 l l

The following is a breakdown, by discipline and number, of personnel working on a I randomly selected shift for the 1995 First Quarter Drill. This is the maximum number that !

will be allowed to participate at the beginning of the drill. Any number between this maximum and the minimum on-shift staffing level required by the Emergency Plan is

~

acceptable. FOR THIS DRILL' response for "BEEPERipag'ed' Individuals Will be delaye'd j for = 35 min ~u tes, 'simulatinf' a 7:00 PM start time.gThis is an assumed average response ;

ti.me for emergency responders that are)not of work. - Response _ tim _e is from BEEPER activation.

Section Breakdown Total Number Security SPSS Max. number of i SSPO Security Personnel l SPO (SPO) Immediately l available for this 1 drill has been l provided to Security Management 1

Warehouse Stockkeeper B -2 2 TMH Ops SS -1 13 SF -2 CRO -4 l AO-6 l TMH Rod Waste Supr -1 4 l Tech -3 l TMH Chemistry Tech 1 1 TMH Rad Con GRCS-1 5 )

Tech -4 TMH Maintenance Supr -1 11 Tool room 1 l&C -3 l Repair -2 Machine -2 Electric -2 .

Utility Utility -4 4 Util/Jonitor -0 STA STA -1 1 Misc. QA -0 0 l

DRILL 95-03 ANNUAL EXERCISE 1995 i THIS PAGE INTENTIONALLY BLANK i

. s BLACK INK'CNLY. Training AttendEnc3 Form Pags o f __._ ,

1 Office Use Only l

. Received Entered Filed Data Initials Date Initials Date Initials Progrcm No. 10.6,01 Title EMERGENCY PLAN DRILL (95-03)

. Cycle / Week N/A Location TMI Unit 1- Group No.

Course No. .006 Course Occurrence Status.(A/C)

Course Revision Course Completion Date Course Description ANNUAL EMERGENCY EXERCISE L3sson No. AD Taken Date Lesson Status (C/M)

Lesson Revision Lesson Plan No. Instructor SSN - -

Actual Hours Mode DRL Lesson Completion Date 04/12/95 Lesson Description ANNUAL EMERGENCY EXERCISE 1995 DRILL 95-03 Social Exam Security P/F/I/E Grade Printed Name Signature ***

Number (%)

t e e e * * * * * * * * * * * *

- - M.tka entry for this column only if directed by instructor.

Sam reverse for Mode, Date, Status, Grade and Actual hours format. N 2071 11.5

~ Social Exam-

, Security- lP/F/I/E. Grade -Printed Name Signature ***

Number. -(%) ,

5 Method of Evaluation _ _

Attachments

. Entten (Category Type I~ ,, TCR ,, Esam Cover Shut

,, Drel . Blank Enem . 3nting Chart

. Practu:al Factor . Enem Kay - _ Other

_ Oti.et _ Student Eram I..structor Comments I beehr ashasahdem ese es paremme amend se sue fremens Annessees ers he sessnad es endemens e amme as sessmed.

Sihmitted by .

Signature Social Security Number Date

-15 XXX XX XXXX Instructor Signature SSN en front Date MedeFormat Date Format Status Format Bose pro sun - (BPS) On the. gob (DJT) MMfDDIYY Actwo (A)

Corrispondence (CCS) Onginator (ORG) Exemple: 01I21180 Complete (C)

Mril . - (DRL) On-shift tramms (OST) Make up (M)

Eneminettn (EXM) Rephca sim (RPS) Grade Format Fihn (FLM) School (SCH) Pass (P) Acteel Hows Format Lduatery (LAB) Semmar (SEM) foi (F) XXX.X Lceture (LEC) Vuleoispe (VTP) incomplete G) Exemple: 40.0 11.6 u- -

BLAIX INK 04tY Training Attendance Frrm Psca of Offic7 UN,o Only Received Entered Filed D _ta Initials Date Initials Date Initials _

Progrcm No. 10.6.01 Title EMERGENCY PLAN DRILL (95-03)

Cycle / Week J/A Location TMI Unit 1 Group No.

Course No. .006 Course Occurrence Status (A/C)

Course Revision Course Completion Date t

Course Description ANNUAL EMERGENCY EXERCISE l Lesson No. AD 'Taken Date Lesson Status (C/M)

Lesson Revision Lesson Plan No. Instructor SSN - -

l Actual Hours Mode DRL Lesson Completion Date 04/12/95 L:sson Description ANNUAL EMERGENCY EXERCISE 1995. DRILL 95-03 Social Exam Securi ty P/F/I/E Grade Printed Name Signature ***

Number (%) ;

i l

.. _ l l

. - j l

1

e * * * * * * * * * * * *

1

- - Miks entry for this column only if directed by instructor.

Sse reverse for Mode, Date. Status. Grade and Actual hours format. N 2071 11.7

4 1 r Social Exam .

Grade Printed Name

' Security P/F/I/E Signature ***

, Number

(%) ;

s I

t t

?

t i

i Method of Evaluation ._ _ Attachments l I

. Y!rittaa (Category Type i . TCR . Esem Corn Sheet

,, Dral . Blank from .. Seating Chart

,, Practcal f actor . Exam Key _l other Other _ Student Eram i

Instructor Comments

'i j

1 beehy ashameWyn est the parenes heted se thes freemag Anamalamus Fere base stemnded the hudiammad Wesume as epsutes i Subnutted by Signature Social Secunty Number Date OR- i 1

XXX XX XXXX .i instructor Signature SSN en front Date j i

l Modeformat Date Ferinet Status Formet Basic prh sun SPS) On theiob 10JT) MMIDDIYY Active (A) l Correspondence . (CCS) Orginstor (ORG) Enemple: 01121/09 Complete (C)

Dru (DRL) Onitutt tramme (DST) Make up (M) _j

[sommaten (EXM) Replice sun IRPS) Grade Format Fika (FLM) School (SCH) Pass (P) Actual Neurs Format Laboratory (LAB) Sammar (SEM) fab (F) XXX.X Lectars (LEcl VWeetape (VTP) Incomplete (I) Exemple: 40.0 1

11.8

DRILL 95-03 ANNUAL EXERCISE 1995 OBSERVERS NAME:

NOTE: Please take the time to write constructive and positive comments, as well as deficiencies. For each deficiencies write a recommendation to correct the problem and identify the appropriate priority for the deficiency.

PRIORITY i This item is a regulatory or safety issue and must be resolved in no more than 15 working days.

PRIORITY 2 This item involves Emergency Preparedness Program corrections and must be resolved in no more than 45 days.

PRIORITY 3 ' This item involves significant improvements to the Emergency Preparedness Program and is to be resolved in no more than 90 days.

PRIORITY 4 This item involves minor procedure enhancements to the EP program and should be included in ~ the next scheduled substantive '

procedure change or during the annual review, whichever comes first.

DRILL 9503 ANNUAL EXERCISE 1995 COMMENTS / DEFICIENCIES RECOMMENDATIONS / REMARKS PRIORITY t

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DRILL 95-03 ANNUAL EXERCISE.1995 COMMENTS / DEFICIENCIES RECOMMENDATIONS / REMARKS PRIORITY l

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DRILL 95-03 ANNUAL EXERCISE 1995 EMERGENCY DRILL OBSERVER SEQUENCE OF EVENTS SHEET (OPTIONAL)

OBSERVERS NAME: _

TIME SEQUENCE OF EVENTS / ITEMS TO NOTE OR OF INTEREST l

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DRILL 95-03 ANNUAL EXERCISE 1995 EMERGENCY DRILL OBSERVER SEQUENCE OF EVENTS SHEET (OPTIONAL)

OBSERVERS NAME:

TIME SEQUENCE OF EVENTS / ITEMS TO NOTE OR OF INTEREST l

DRILL 95-03 i ANNUAL EXERCISE 1995 {

t EMERGENCY DRILL OBSERVER SEQUENCE OF EVENTS SHEET (OPTIONAL)

OBSERVERS NAME:

TIME SEQUENCE OF EVENTS / ITEMS TO NOTE OR OF INTEREST I

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DRILL 9503 ANNUAL EXERCISE 1995 EMERGENCY DRILL

, t OBSERVER SEQUENCE OF EVENTS SHEET '

(OPTIONAL)

OB3ERVERS NAME:

TIME SEQUENCE OF EVENTS / ITEMS TO NOTE OR OF INTEREST I

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GPU NUCLEAR CORPORATION ,

)

11.46

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ML20087G037

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