ML20112G377
ML20112G377 | |
Person / Time | |
---|---|
Site: | North Anna |
Issue date: | 11/15/1984 |
From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | |
References | |
PROC-841115, NUDOCS 8501160321 | |
Download: ML20112G377 (400) | |
Text
{{#Wiki_filter:. go-33 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY EXERCISE l NOVEMBER 15, 1984 EXERCISE MANUAL MANUAL NO. 20- ) f a , 8501160321 841115 PDR ADOCK 05000338 F PDR N ff35 _-
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9 O INDEX
- 3
- 1. References
- 2. List of Simulations
, 3. Useful Information
- 4. Scope
. 5. Objectives
- 6. Emergency Exercise Scenario Narrative
- 7. Emergency Exercise Scenario Events
- 8. Participants
- 9. Messages
- 10. Controller Data
- 11. Diagrams of Facilities
- 12. Controller and Observer Information
- 13. Observer Critique Sheets
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- 14. Critiques - >
- 15. VOPEX 2-84 %
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NAEE Saction 1 Page 1 of 1 10-10-84 REFERENCES
- 1. Corporate Emergency Response Plan
- 2. Corporate Plan Implementing Procedures
- 3. North Anna Power Station Emergency Plan
- 4. North Anna Power Station Emergency Plan Implementing Procedures
- 5. Commonwealth of Virginia Radiological Emergency Response Plan
- 6. County Radiological Emergency Response Plan for the counties of Louisa, Spotsylvania, Orange, Caroline and Hanover
- 7. NUREG - 0654
- 8. Virginia Operations Plan Exercise No. 2 1984 (VOPEX 2-84),
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- 2. LIST OF SIMULATIONS I
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NAEE Section 2 Page 1 of 1 10-10-84 sQ V LIST OF SIMULATIONS
- 1. Simulate a request for assistance for additional field monit'oring personnel from Surry Power Station.
- 2. Simulato a request for food and bedding supplies for station personnel.
- 3. Account for station employees on vacation and simulate the recall of as many as possible.
- 4. Simulate the following calls for assistance:
- a. Westinghouse
- b. INPO
- 5. Simulate the wearing of PC's except in actual contamination areas.
.b 6. Simulate &ctivation of the North Anna Early Warning System.
Monthly scheduled activation will occur on November 21. i k-9- t n i' a if l
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NAEE Section 3 Page 2 of 5 10-10-84 ( USEFUL INFORMATION ROUTE TO NORTH ANNA POWER STATION BY AIR: Byrd International Airport - Richmond, Virginia BY CAR: Refer to the map below. The station is % proximately 60 miles North of Richmond. Take Interstate 64 West to the Shannon Bill Exit (Exit #29). Take Route 605 North to U.S. Highway 522. Take U.S. 522 North (left) to Route 700 on the Right. Take Route 700 to North Anna Power Station. BY TRAIN: AM-TRAK with a connection in Richmond. I O - p kNORTH ANNA
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NAEE Section 3 Page 1 of 5 L 70-10-84 + F i r h i USEFUL INFORMATION
- 1. Route to North Anna Power Station
- 2. Map to locate Vepco's Corporate Office
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- 3. Map to locate the Commonwealth of Virginia's Emergency L Operations Facility
- 4. Nearby accommodations i' s 4
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i INTERSTATE Si l 5 NAEE section 3 Page 3 of 5 8 l-COLISEUM 10-10-84 2-aowa =^asaau aarE' O ) 3- VEPCO' 4-WBACCO COMPANY Rest P- PARKING .
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- 3. USEFUL INFORMATION l
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l NAEE Section 3 Page 5 of 5 10-10-84 1 y NEARBY ACCOMMODATIONS ,
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l Richmond (approximately 60 miles from station) . 1 Holiday Inns 6531 West Broad Street 3 Locations on 804/285-0051 , West Broad Street Richmond, VA 2000 Staples Mill Road
- 804/359-6061 3200 West Broad Street 804/359-4061 1
Fredericksburg (approximately 30 ..les from station) Ramada Inn Fredericksburg, VA 703/786-8361 . Sheraton Inn Fredericksburg, VA O 703/786-8321 Charlottesville (approximately 45 minutes from station) Holiday Inn - North Charlottesville VA 804/293-9111 Holiday Inn - South Charlottesville. VA 804/977-5100 ' Ramada Inn Charlottesville. VA 804/977-7700 0
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- 4. SCOPE l A
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NAEE Section 4 Pags 1 of 2 10-10-84 SCOPE OF EXERCISE On November 15, 1984, the Virginia Electric and Power Company (VEPCO) intends to demonstrate its capability to effectively implement the North Anna Power Station (NAPS) Emergency Plan. The purpose of this exercise is to activate and evaluate anjor portions of the Energency Plan, associated Implementing Procedures, and selected portions of the VEPCO Corporate Emergency Response Plan in accordace with Nuclear Regulatory Commission Regulation 10CFR50.47(b)(14), and to participate in the implementation of State and local government emergency response plans as required by the . Federal Emergency Management Agency. This exercise will be held in conjunction with full scale emergency response demonstrations by the Commonwealth of Virginia and the Counties of Louisa, Spotsylvania Orange, Caroline, and Hanover. Simulations of response will be performed with supporting Federal agencies, and volunteer groups, as well as other supporting organisations. The exercise shall demonstrate that those individuals.and agencies who are assigned responsibilities in a radiological V emergency are capable of providing the necessary protective measures to ensure the health and safety of the public in the event of an accident at the NAPS facility. The exercise is intended to initiate responses for all four categories of emergencies as outlined in NUREG-0654. A scenario shall be prepared to accomplish a successive escalation of the emergency from the " Notification of Unusual Event" to a " General Emergency". Free play is encouraged and controllers will only interfe~e with the play if the exercise less behind schedule, if emergency response personnel take 1-correct actions to carry them to the next exercise event, or - if action is taken that would correct the expected simulated response earlier than scheduled by the scenario. At no time will the exercise be permitted' to _ interfere with the routine safe, operation of the station, and station annagement asy, at their discretion, suspend the esercise for any period of time necessary to ensure this goal. Exercise " players" will not have prior knowledge of the simulated incident or any parts thereof. O . jej/SP4/123
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l I NAEE Section 4 i 3 Page 2 of 2 10-10-84 J VEPCO also intends to activate the Corporate Emergency Response Plan at its , General Office Building in Richmond, Virginia, to demonstrate the Corporate Bnergency Responce (, enter's capability to interact with the Local Emergency , ' Operations Facility at North Anna. 1 { O jej/SP4/123
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- 5. OBJECTIVES !
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NAEE S2ction 5 Page 1 of 6 10-10-84 CBJECTIVES OF EXERCISE The objectives of this exercise are to demonstrate by actual performance a number of key emergency preparedness functions as they relate to the North Anna Power Station (NAPS) Emergency Plan. The simulated accident will involve response and subsequent recovery actions to include: emergency classification, notification of company personnel and off-site organizations, simulated actions to correct the emergency condition, and initiation of accident assessment and protective actions as necessary to cope with the event. In addition, the exercise will simulate an emergency that results in off-site radiological releases which require response by off-site authorities. Simulations of some aspects of
"# emergency preparedness, without actual demonstrations by the Station or Corporate entities, may oc.:ur where it is deemed impractical to call for personnel involvement.
The following objectives have been developed in order to establish the scope and boundaries of the 1984 NAPS emergency exercise. These will be used to ensure that required events are included in the exercise scenario, and to establish critique areas to be evaluated by controllers and observers during the actual conduct of the exercise. rT
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NAEE Ssction 5 Pags 2 of 6 10-10-84 { A. OVERALL STATION OBJECTIVES j 1. Demonstrate the emergency organization's ability to make proper } -decisions related to emergency radiation exposure guidelines, and j the capability to implement these decisions.
- 2. Demonstrate at all emergency facilities the ability to establish i
- and maintain emergency management command and control authority, 1
and maintain continuity of authority throughout the exercise. i i i ! 3. Demonstrate the ability to formulate and make protective action
- recommendations to protect station personnel and the general
- i. public based on plant parameters and/or field monitoring information.
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- 4. Demonstrate the ability to classify actual or potential emergencies in accordance with ITAPS Emergency Plan Implementation Procedures with respect to:
i Notification of Unusual Event Alert Site Area Emergency General Emergency 2
- 5. Demonstrate the ability to develop alternative systear or equipment alterations. in response to accident affected plant systems or components and to formulate respective procedures to accompany these required modifications.
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- 6. Demonstrate the capability to ascertain and to requisitior. the !
necessary parts to perfore corrective maintenance on damaged equipment. ! i 7. Demonstrate the ability to develop, obtain . approval for, and > implement actions which dictate operation of the station outside defined safety boundaries or normal station Technical Specifications. jaj /SP4/122
NAEE Saction 5 Pags 3 of 6 10-10-84 O y A. OVERA1.1. STATION OBJECTIVES (continued)
- 8. Demonstrate the ability to evacuate non-essential personnel from the site.
- 9. Simulate transition into the recovery mode. Requests for simulated technical support will be made, as well as transmitting information to the facilities needed for recovery support.
- 10. Demonstrate the ability to augment. the on-shift emergency organization to support emergency operations in a timely and effective manner.
B. OPERATIONS OBJECTIVES
- 1. Demonstrate the control room operator's ability to recognize operational symptoms indicative of degrading plant conditions.
- 2. Demonstrate proficiency in evaluating parameters, properly categorizing the situation utilizing the station's emergency action level scheme, and making the requisite emergency classification.
- 3. Demonstrate the ability to properly escalate /de-escalate the emergency classification.
- 4. Demonstrate efficient and effective notification / alerting procedures and methods.
- 5. Demonstrate effective communications / informational flow from the control room to supporting locations.
C. SECURITY OBJECTIVES
- 1. Demonstrate the adequacy of access control and security for O emergency response facilities.
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t NAEE Section 5 Page 4 of 6 l 10-10-84 C. SECURITY OBJECTIVES (continued)
; 2. Demonstrate station employee accountability.
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- 3. Demonstrate the ability to implement site evacuation and access procedures.
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- 4. Demonstrate call-out of off-duty station personnel, i
- 5. Demonstrate Security escort capabilities.
j D. HEA1.TH PHYSICS AND CHEMISTRY OBJECTIVES i i
- 1. Demonstrate the necessary radiological controls to remove a !
contaminated injured individual from the accident scene and to j- assist the medical team in minimizing the consequences of a 1 contaminated individual. i. !b 2. Demonstrate the capability to perform radiological monitoring 4 activities and assessments, and to formulate offsite radiological } dose projections.
- 3. Demonstrate the use of the Foot Accident Sampling System (with currently existent limitations) to obtain samples in support of .;
accident assessesnt activities. This shall include the sampling l and analysis of liquids with actual elevated activity levels. i
- 4. Demonstrate . collection and analysis of water, vegetation, soil, and air samples both on-site and off-site, as appropriate..
- 5. Demonstrate use of comunications by the monitoring teams, to includesending, receiving,andunderstandingmessagecontent.
- 6. Demonstrate response to and analysis of simulated elevated airborne and/or liquid activity levels (as appropriate), and of l simulated elevated area radiation levels.
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NAEE Saction 5 Page 5 of 6 10-10-84 D. HEALTH PHYSICS AND CHEMISTRY OBJECTIVES (continued)
- 7. Demonstrate initiation and use of appropriate procedures for the collection, analysis, and documentation of Post-Accident and Environmental Monitoring samples, and for Radiological Monitoring evaluation.
- 8. Demonstrate the ability to assess data obtained as a result of sampling activities, and the ability to factor results into the overall assessment process.
E. HEALTH & SAFETY OBJECTIVES
- 1. Simulate the injury and contamination of one etaployee and demonstrate the following:
a) Transportation to an offsite medical facility; and b) Participation (subsequent simulated medical treatment) by the offsite medical facility.
- 2. Demonstrate that surrounding Volunteer Rescue Squads and Fire Departments can send supporting units to the station and simulate successful fire fighting and life support missions in coordination with station personnel assigned to the tasks.
- 3. Simulate a fire in accordance with the requirements of the NAFS Fire Protection Program.
F. EMERCENCY RESPONSE FACILITY OBJECTIVES
- 1. Demonstrate the staffing of the following Emergency Response Facilitiest Technical Support Center (TSC)
Operational Support Center (OSC) Local Emergency Operations Facility (LEOF) Corporate Emergency Response Center (CERC) jaj/SP4/122
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NAEE Section 5
, Page 6 of 6 10-10-84 l
F. EMERGENCY RESPONSE FACILITY OBJECTIVES (continued)
- 2. Demonstrate the communications capabilities between the Control Room. TSC, OSC, LEOF, and CERC, and the ability to maintain these communications with Federal. State, and local governments. This shall include sending, receiving, and understanding the content of i messages involved.
- 3. Demonstrate the. proper utilization of the Emergency Response Facilities and that adequate emergency response equipment exists.
G. CORPORATE OBJECTIVES , 1. Demonstrate that the LEOF can be adequately staffed and communications properly established.
- 2. Demonstrate that the CERC can be adequately staffed and made functional (e.g., maintain communications, interface with the Stat's Emergency Operations Center, provide engineering assistance, provide logistic support, and establish a Rumor Ccutrol group).
- 3. Demonstrate the activation of the Media Center.
- 4. Demonstrate the timely release and distribution of news announcements.
- 5. Demonstrate coordination of news announcements with off-site emergency response agencies.
. 6. Demonstrate the ability to conduct timely and informative media briefings.
- 7. Demonstrate the ability'to respond to outside news inquiries.
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- 6. EMERGENCY EXERCISE SCENARIO NARRATIVE l
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_~ - _ _ - - . -. - -- - . _ - - - _ _ - _ - . .- i NAEE Section 6
. Page 1 of 2 10-10-84 i VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY EXERCISE SCENARIO NARRATIVE A. full scale joint emergency exercise has been scheduled for the North Anna Power Station on November 15, 1984. Unit 2 has been designated as the affected unit.
Units .1 and 2 are operating at 100% full power equilibrium. The Unit 2 reactor core is at midlife and fission product coolant inventory is considered to be normal. l - In the early stages of the scenario, a simulated maintenance proj ect is scheduled to take place on the top elevation of the Unit 2 electrical ; penetration area. Mechanical maintenance personnel notify the Control Room staff that repairs are required on MOV-HV-200B. A Maintenance Work Order, Welding and Flame Permit, and Radiation Work Permit shall be issued to support this task. Failure of a pump motor causes an electrical fire in a motor control center located in the Waste Disposal Building (Clarifier Building). The fire will , spread -and involve combustible LSA wood and 10 - 55 gallon drums ot contaminated waste oil stored there. After te, minutes, the fire is
} -% / considered out of control. Offsite fire assistance shall be requested. A' " Notification 'of Unusual Event" will be declared based on E.A.L. . Tab I, Condition 1.
Mechanical and electrical maintenance personnel will be requested to restors operability to the damaged pump motor and associated motor cont rol center. Two employees receive injuries during post-fire cleanup activities. Oily floors cause one individual to slip and receive a bleeding head injury while the other breaks his leg. Both individuals will be contaminated and the latter will have accidentally been exposed to a Cobalt-60 radiographic source stored in the area. The Station Emergency Manager will be notified of the event and offsite rescue squad assistance will be requested. A leak through the containment purge system into the Containment Building will-occur causing containment internal air pressure to increase. Operations personnel receive data.from the annunciator alarm system indicating increasing containment pressure with no increased containment temperature 'or radiation.' The leakage inte containment continually' increases for approximately 30 minutes.- Unit shutdown will, in one hour, he mandated due to operation outside acceptable ranges of: 1) the applicable RWST water temperature limit
' lines and 2) bulk air temperature limit lines per T.S. 3.6.1.4. A normal shutdown is initiated in order that the unit will be in Mode 3 within 6 hours.
jaj /LM6-249
b NAEE Section 6
- Page 2 of 2 10-10-84 Shortly thereafter, Letdown Radiation Monitor RM-228 will indicate 1.0 x 10' cpm (Hi alarm). AP-5 shall be initiated in response to this event. A gradual increase in counts per minute will be noted by Control Room personnel. Loose parts will be detecteg in the reactor vessel, immediately followed by a RM-228 Hi-Hi alarm (2.0 x 10 cpm).
' 6 An " Alert" will be declared when Letdown coolant activity exceeds 1.0 x 10 cpm for greater than 15 minutes (RE: E.A.L. Tab C, Condition 2), which is indicative of severe clad damage. Samples should then be taken from Reactor Coolant System (RCS) Letdown. Analysis will indicate a slight increase in Dose Equivalent (D.E.) I-131 but not in excess of T.S. 3.4.8 limits for s,pecific activity.
Coolant Specific Activity and Letdown Activity continue to increase over a period of hours while the unit is being removed from service (RE: inability to maintain containment vacuum). It is anticipated that the SRO may escalate rampdown rates but this will be blocked by i.he controller as thermal shock may cause additional fuel failure. 6 A " Site Area Emergency" should be declared when RM-228 exceeds 1.0 x 10 cpm and confirming RCS samples are in the range, of 65 uCi/ gram D.E. I-131. Although loss of RCS cooling is not indicated as per E. A.L. Tab C, Condition 3(b), the Station Emergency Manager should declare the " Site Area Emergency" as per E.A.L. Tab M. Condition 3 because:
- 1) Fuel failure has occurred due to icose parts, and V 2) Containment has a known leak due to increasing pressure with no increase in temperature or area radiation indicated.
Rampdown continues until the RCS fails. Pressurizer level and pressure begin to decrease while containment temperature, humidity, and radiation increase. A non-isolable leak develops at the Letdown line in "A" Loop Room, upstream of LCV-2460A and B. The leak escalates to 600 spm, and automatic Safety Injection occurs on low pressurizer pressure. A " General Emergency" condition now exists based on the loss of two of three fission product barriers with a potential loss of the third (E.A.L. Tab B, Condition 11).
- A release to the atmosphere occurs when containment pressure increases to ~. . approximately 5 psig (20 psia). A welders torch causes an explosion whereby MOV-HV-200B will become dislodged from its piping and MOV-HV-200A fails open.
' No fire or personnel injury will occur. Radioactive effluent will escape i through the faulted containment ventilation piping resulting in an unplanned / uncontrolled release across the Site Boundary and ultimately to the general public. . The leak to the atmosphere will be terminated when containment is returned to the sub-atmospheric condition. RCS leakage will continue until plant operations personnel depressurize and cool down the primary plant in accordance with applicable Emergency Operating
'O Procedures.
The exercise will terminate, followed by an exercise critique.
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l l NAEE Section 7 i Page 1 of 2 10-10-84 NORTH ANNA POWER STATION D(ERGENCY EXERCISE SCENARIO NOVEMBER 15, 1984 NOTE: Times are approximate. TIME EVENT 1200 Exercise begins. Low volume air leakage into the containment building occurs when maintenance personnel unknowingly crack MOV-HV-200B, the outside containment Purge Isolation Valve. MOV-HV-200A, the inside containment Purge Isolation Valve, has seating surface damage allowing air to leak into containment. 1203 Annunciator F2 Panel J sounds indicating actual containment pressure exceeds setpoint pressure by +0.1 psi. 1205 Control Room personnal start a containment vacuum pump. 1230 Hi Alarm occurs on Letdown Radiation Monitor RM-228, 1.0 x 10' cpm. 1232- 2-AP-5 is initiated (Radiation Monitoring System). rw Shif t Supervisor requests coolant samples to aid in verifying alarm. 1235 1240 " Loose Parts" annunciator sounds. 1242 Lower reactor vessel loose parts observed at LPMS (Loose Parts Monitoring System) panel by control room personnel. i 1245 Engineering is requested to evaluate loose parts noise. 1300 Annunciator Hi-Hi Alarm occurs on RM-228, 2.0 x 10' cym. Annunciator G1 Panel J sounds indicating actual containment pressure exceeds setpoint pressure by +0.25 psi. The second containment vacuum pump is started by the Control Room operator. 1305 An electrical fire is caused by a faulted motor on Clarifier- 4 Discharge Pump 1-LW-P-12A. Breaker A2 in MCC-1B1-1A explodes, igniting LSA wood storage boxes and waste oil drums filled with contaminated lube oil. 1307 Smoke Alarm Zone 25 (Waste Disposal Building) is received in the Control Room. Clarifier Hi Level Alarm occurs. 1308- Fire is reported in the Clarifier (Waste Disposal) Building. . Lir 1315 Fire out of control in the Clarifier Building.
-1320 Declaration of " Notification of Unusual Event".
Offsite fire-fighting assistance is requested. j i l
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r NAEE Section 7 Page 2 of 2 10-10-84 (~') (j TIME EVENT 1330 Shift Supervisor receives coolant sample results: D.E. 1-131 = 0.6 uCi gram. Unit rampdown commences at 0.3%/ minute due to operation outside limits of T.S.3.6.1.4. 6 1345 RM-228 indicates 1.0 x 10 cpm. 1400 Fire under control. RM-228 indicates 1.0 x 106cpm for greater than 15 minutes.
" Alert" is declared: Severe clad damage E.A.L. is exceeded.
Post-fire cleanup begins. 1410 Control Room receives notification of personnel injuries. 1430 Control Room receives notification of injured personnel overexposure. Offsite rescue squac assistance is requested. Shift Supervisor receives coolant sample results: D.E. I-131 = 30.0 uCi gram' Projected increase in coolant activity approximately 23.5 uCi per hour. gram ('T (_) 1600 6 RM-228 indicates 2.0 x 10 cpm. Coolant sample indicates greater than 65.0 uCi D.E. 1-131. gram
" Site Area Emergency" should be declared.
1700 A slight RCS leak begins. Leak cannot be isolated. The source of the leak will not be identifiable. 1730 Automatic S T. and Reactor Trip occurs from low pressurizer pressure.
" General Emergency" fission product barrier E.A.L. exceeded.
1745 Containment pressure positive. 1755 An explosion is reported in the vicin.ity of-containment Purge Valves. Containment integrity is lost and steam is reported escaping from the Rod Drive Room. Attempts by Control Roon personnel to reduce containment pressure are limited by failed or unavailable Containment Depressurizing System equipment. 1930 containment Depressurization System equipment operable. Radioactive effluent will continue to escape until approximately 2000. 2000 Containment pressure is sub-atmospheric. Recovery Phase begins. I 2100 Exercise Terminates.
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- 8. PARTICIPANTS A
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ll NAEE Section 8 Page 1 of 1 10-10-84 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA EMERGENCY EXERCISE i LIST OF PARTICIPANTS I The . following organizations, agencies, and political subdivisions will participate in the North Anna Power Station Emergency Exercise: A. Virginia Electric and Power Company (VEPCO)
- 1. Corporate Headquarters (804) 771-3000
- 2. North Anna Power Station (NAPS) (703) 894-5151
- 3. North Anna Power Station News Media Center (703) 894-4826/4662 B. State Agencies, Commonwealth of Virginia 4
- 1. Emergency and Energy Services, Office of (804) 323-2300
- 2. Health, Department of (804) 323-2300 (State EOC)
- 3. State Police, Department of (804) 323-2014/2000
- 4. Other State agencies: See Vopex 2-84, Administrative Instructions, for more details.
C. Local Governments
- 1. Caroline County (804) 633-9831 4 2. Hanover County (804) 798-6081 Ext. 217
- 3. Louisa County (703) 967-0401
- 4. Orange County (703) 672-3313
- 5. Spotsylvania County (703) 582-5676/6384 D. Civf Air Patrol (CAP), Virginia Wing -
Through State EOC
; (804) 323-2300 E. Radio Amateur Civil Emergency Services (RACES) - Through State ' EOC (804) 323-2300 F. American National Red Cross (804) 748-2262 G. Institutions - within ten miles of the NAPS A
V - H. Nuclear Regulatory Commission (NRC) I. Federal Emergency Management Agency (FEMA) e-++- w Y --e.- ,+-.g9,--- g>=w,- gw+,%4 -,.,-'wy e- qw ,-e,, g ----<igeg -.mggv-.i-gg.,---*y,wi-g--.ee.g.,e,ygy..,+y--g,yeaq g gw w 9. --
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- 9. MESSAGES 5
4 l t 9 1 1 l l
- , e-w,,ww.e,n-.--,,. <---.- , ... rem--,-m-w .m.ew-.-,,-.e-e-ew--wwww.-,,-eg.rw.-.s-w- w.=v,-- em.-,-----,-we-- -
NAEE Section 9 4 Page 1 of 3 10-10-84 NORTH ANNA POWER STATION t 1984 EMERGENCY EXERCISE INITIAL CONDITIONS SHIFT SUPERVISOR STATION MANAGER NOTE: Unit 2 is the unit designated to be exercised for the purpose of the drill. NOTE: If at any time, in the judgement of the shif t supervisor, the emergoney drill interferes with the safe operation of the unit, the drill will be suspended until station conditions are returned to normal. PLANT CONDITIONS
- 1. REACTOR A. Unit 2 at 100% power (Equilibrium)
B.' Unit 1 at 100% power
-C. Burnup Unit 2: 7,500 MWD /MTU
! D. 572 ppm Boron E. 'D' Control Bank at 224 steps II . - MAINTENANCE A. Quench Spray Pump B (2-QSrP-1B) OOC - tagged out to the mechanical maintenance department. Pump undergoing inspection due to low' delta P discovered during monthly PT. No work in progress, awaiting spara parts delivery. B. Mechanical maintenance personnel are working in the upper ' level
' elevation of the Unit 2 electrical penetration area. A broken hand-wheel or bent valve stem on MOV-HV-200B is hindering valve . stroke. . .C. 'C' Containment Air Recire. Fan is 000 (Blade imbalance).
D. No other major maintenance projects are being conducted. All other plant equipment is as per the " Turnover Check List". [ III. RADIOACTIVE RELEASES A. Liquid waste-is being processed via the Chem. Nuc. IX, Clarifier and Clarifier Ion Exchanger. B. No gaseous releases are in progress except for normal flow via 'A' and 'B' stacks. i IV. RADIOACTIVITY OF RCS~
!-A A. - Fission product - coolant inventory is at a level equal to what has-been projected for this time-in core life, t
1 -
, , - . , -. , _ - - - - . . , . . vy. . . , - - ,4, - , - , . - ,, ..,,-,w.-,,,-,-.- m ,- ,,,,,,m - - ,w,.-,,,, ,,,,----y-.,,4,s..,--,.--N,,-mw,",
NAEE Section 9 Page 2 of 3 10-10-84
.. m V. SYSTEM LINE UP AND FLOW PATHS A. Normal charging and letdown; 'A' charging pump running.
B. All main steam PROV's, steam dumps, decay heat release valves, and safeties are operable. . C. Pressurizer PROV's and safeties are operable with block MOVs open. i D. Station service, reserve, and emergency busses are operable. Both diesels in automatic, and 'H' and 'J' 4160 busses being fed from reserve station service. 7 VI. VENTILATION A. Vent stack 'A' flow is g 65,000 cfm. 2 central and 1 general exhaust fan in service. B. Vent stack 'B' flow is W 65,000 cfm. 2 fuel building, 1 decon building, and 2 safeguards exhaust fans in service. Charcoal iodine filter system is operable but not in service. b
- h r
1._ _. . . . _ . . . . _ . . . _ , , . . . . - , - . - . _ . ,_ . -~~.a.u~ .---- - - -- . - - - - - - --- -
NAEE Section 9 Page 3 of 3 10-10-84 NORTH ANNA POWER STATION 1984 EMERGENCY EXERCISE SHIFT SUPERVISOR EXERCISE GUIDELINES ,
- 1. Select personnel to continue routine duties.
NOTE: These personnel should not be involved with this exercise.
- 2. Select personnel to participate in exercisc: (Personnel will be designated in advance by Operations Superintendent)
- a. Shift Supervisor -1
- b. Control Room Operator -1
- c. Emergency Consnucicatoe -2 d.' Exercise Support -2 (Optional)
- 3. Ensure all exercise data flow into or cut of the control room funnels through the controller (i.e., Andy Neufer or Tom Chaffee).
- 4. This exercise is not to interfere with the operation of Unit No. 1 or 2.
- 5. Ensure the word " DRILL" is used for exercise related communication within the station. -
- 6. Ensure the phrase "THIS IS A V0PEX MESSAGE" preceeds all off station 6 cornunication.
NOTE: This identifies to State / local authorities that it is exercise related communication.
- 7. lThis is NOT an operational exercise but an emergency response exercise.
Actual operation of equipment is not desired. However, actual use of procedures is desirable, e.g., EPIP's, EP's, AP's, OP's, SRO/CR0 logs, etc..
- 8. Ask the . controller for any information/ data you desire. Alarms will be given to you verbally by the controller.
- 9. Ideas / solutions you. may have are encouraged. The success of the' ideas / solutions will be determined by the Lead Controller or his designee.
- 10. If you have any questions at' any time, please feel free to ask the controllers.
r 3
t ) j 10. CONTROLLER DATA 4 9 se -..,-,em+-yses y,--- I,s,w9-u.-'p4y.y _9 y,e' W PTF* y 4 W-46e W 'w T=
.. - - _ . . - . ~ _ .
NAEE Section 10 Page 1 of 190 10-10-84
' NOTE: Times are approximate.
TIME EVENT 1200 Exercise begins. Low volume air leakage into the containment building occurs when maintenance personnel unknowingly crack MOV-HV-200B, the outside containment Purge Isolation Valve. MOV-HV-200A, the inside containment Purge Isolation Valve, has seating surface damage allowing air to leak into containment. 1203 Annunciator F2 Panel J scunds indicating actual containment pressure
- exceeds setpoint pressure by +0.1 psi.
1205 Control Room personnel start a containment vacuum pump. 4 1230 Hi Alarm occurs on Letdown Radiation Monitor RM-228, 1.0 x 10 , 1232 2-AP-5 is initiated (Radiation Monitoring System). 1235 Shift Supervisor requests coolant samples to aid in verifying alarm. 1 h 7 1240 " Loose Parts" annunciator sounds. 1242 Lower reactor vessel loose parts observed at LPMS (Loose Parts Monitoring System) panel by control room personnel. 1245 Engineering is requested to evaluate loose parts noise. o l l -
i NAEE Section 10 i Page 2 of 190 10-10-84 l TIME EVENT
.1300 Annunciator Hi-Hi Alarm occurs on KM-228, 2.0 x 100 cpm.
Annunciator G1 Panel J sounds indicating actual containment pressure exceeds setpoint pressure by +0.25 psi. The second containment vacuum pump is started by the Control Room operator. 1305 An electrical fire is caused by a faulted motor on Clarifier Discharge Pump 1-LW-P-12A. Breaker A2 in MCC-1B1-1A explodes, igniting LSA wood storage boxes and waste oil drums filled with . contaminated lube oil. 1307 Smoke Alatu Zone 25 (Waste Disposal Building) is received in the Control Room. Clarifier Hi Level Alarm occurs. 1308 Fire is reported in the Clarifier (Waste Disposal) Building. 1315 Fire out of control in the Clarifier Building. b 1320 Declaration of " Notification of Unusual Event". Offsite fire-fighting assistance is requested. 1330 Shift Supervisor receives coolant sample results: D.E. 1-131 = 0.6 uCi gram. Unit rampdown commences at 0.3%/ minute due to operation outside limits of T.S.3.6.1.4. 1345 RM-228 indicates 1.0 x 100 cpm. i g , !b
NAEE Section 10 Page 3 of 190 10-10-84 TIME EVENT 1400 Fire under control. 6 RM-228 indicates 1.0 x 10 cpm for greater than 15 minutes.
" Alert" is declared: Severe clad damage E.A.L. is exceeded.
Post-fire cleanup begins. 1410 Control Room receives notification of personnel injuries. 1430 Control Room receives notification of injured personnel overexposure. Offsite rescue squad assistance is requested. Shift Supervisor receives coolant sample results: D.E. 1-131 = 30.0 uCi gram Projected increase in coolant activity approximately 23.5 uCi per hour. gram 0 1600 RM-228 indicates 2.0 x 10 cpm. Coolant sample indicates greater than 65.0 uCi D.E. I-131. gram
" Site Area Emergency" should be declared.
NAEE Section 10 Page 4 of 190 10-10-84 O TIME' EVENT
'd 1700 A slight RCS leak begins. Leak cannot be isolated. The source of the leak will not be identifiable.
1730 Automatic S.I. and Reactor Trip occurs from low pressurizer pressure.
" General Emergency" fission product barrier E.A.L. exceeded.
1745 Containment pressure positive. 1755 An explosion is reported in the vicinity of containment Purge Valves. Containment integrity is lost and steam is reported escaping from the Rod Drive Room. Attempts by Control Room personnel to reduce containment pressure are limited by failed or unavailable Containment Depressurizing System equipment. 1930 Containment Depressurization System equipment operable. Radioactive effluent will continue to escape until approximately
.2000.
2000 Containment pressure is sub-atmospheric. Recovery Phase begins. 2100 Exercise Terminates.
.p G
NAEE Section 10 Page 5 of 190 10-10-84 1 O CONTROLLER INSTRUCTION NCRTH ANNA POWER STATION OPS-1 NO.: 4 EMERGENCT EZZRCISE NOVEMBER 15, 1984 + TO: ..CO.NTROLLER ~ LEAD CONTROLLER (CR) TIME: 1155 . - - INSTRUCTION: At the time designated, perform the following:
- 1. Give INITIAL CONDITIONS TO THE SHIFT SUPERVISOR ,, ,
- 2. Maintain the Exercise Scenario by: .
I l l . If necessary, give Message NO. to i ADDITIONAL INFORMATION: For further clarification, consider the following: l l l l i l 10
i NAEE Section 10 Page 6 of 190 10-10-84 ! CONTROLLIR INSTRUCTION NORTH ANNA POWER STATION NO.: OPS-2A EMERGENCT FT N ISE NOVEMBER 15, 1984 i TQ:. ,, CONTROLI 'R LEAD CONTROLLER (CR) 73; 1200 INSTRUCTION: At the time designated, perform the following: PLANT STATUS SHEETS TO SHIFT SUPV. OR EMER. COIC4UNICATOR
- 1. Give -
- 2. Maintain the Exercise Scenario by:
PROVIDING THE FOLLOWING PLANT STATUS SHEETS TO OPS PERSONNEL III THE CORRECT ORDER AND AT THE PROPER TI'4E AS INDICATED ON EACH ( SHEET. , If necessary, give Message NO. to ADDITIONAL.INFORMATION: For further clarification, consider the following: 9
NAEE Section 10 Page 7 of 190 10-10-84 O CONTROLLER INSTRUCTION NORTH ANNA POWER STATION NO.: Ops-2B
; EMERGENCT EIERCISE NOVEMBER 15, 1984 TO: ...C.O. NT. ROLLER CONTROL ROOM - II.AD CONTROLLER'S ASSISTANT TI3g 1200 INSTRUCTION: At the C M designated, perform the following:
J
- 1. Give ME"'EROLOGICAL AND RADIOLOGICAL PARAMETERS TO OPS AS REQUESTED.
- 2.' Maintain the Exercise Scenario by:
ENSURING TIMELY UPDATES ARE PROVIDED AS NECESSARY. If necessary, give Message NO. to ADDITION /J., INFORMATION: For further clarification, consider the following: _- - , - , . . _ - 4%--,_, , . . , , _ , - - - . , , - - - - , - -
-.4,- , - - - ,,
NAEE Saction 10 Page 8 of 190 10-10-84 PLANT PARAMETERS
,U RCS PZR REACTOR TIME TAVG Th Te PRESS LEVEL POWER 1200 589 618 560 2235 67 100 1230 589 618 560 2235 69 100 1300 589 618 560 2235 68 100 1330 589 618 560 2235 68 100 1400 584 610 558 2235 65 90 1415 583 607 558 2235 64 84 1430 581 605 557 2235 61 78 1445 580 603 557 2235 60 74 1500 578 600 556 2235 58 70 1515 577 597 556 2235 56 68 1530 575 593 556 2235 54 61 1545 573 590 556 2235 52 57 1600 571 586 556 2235 48 52 1615 570 '585 555 2235 47 48 1630 567 580 554 2235 45 44 1645 565 576 553 2235 43 40 1700 564 574 553 2235 39 34 1715 561 570 552 2235 36 30 1730 559 567 550 2235 20 24 1745- 535 540 530 1350 0 0 1800 .515 515 515 1100 0 0 1815 500 500 500 1050 0 0 r- g _ .1830 '479 480 477 1025 0 0 1845 468 468 467 1025 0 0
NAEE Section 10 Page 9 of 190 l' l 10-10-84 RCS PZR REACTOR TIME TAVG Th Tc PRESS LEVEL POWER ' 1900 460 460 460 900 15 0 1915 455 455 455 930 50 0 : 1930 450 450 450 1000 75 0 1945 378 380 375 1100 62 0 2000 378 380 375 1100 67 0 O. : f I
~
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wt-
. _. . . _ .._ .. - - .. . - _ . _ _ ~ -. . - . . - _ _ .- . __ -
NAEE Section 10 Page 10 of 190 10-10-84 , METEROLOGICAL DATA c TIME AT 79 Wind Direction Wind Speed (MPH) (from) 1200 + 2.00 3.0 137.0 5 1215 + 1.95 3.1 136.9 5 1230 + 1.95 3.1 136.8 5 1245 + 1,92 3.2 136.7 5 1300 + 1.92 3.3 136.5 5 1315 + 1.90 1.3 136.4 5 1330 + 1.90 0.4 136.3 5 1345 + 1.90 3.3 136.2 5 1400 + 1.90 3.3 136.1 5 1415 + 1.90 3.2 136.0 5 1430 + 1.91 3.2 136.0 5 1445 + 1.92 3.1 136.0 5 1500 + 1.93 3.1 135.9 5 1515 + 1.94 3.0 135.8 5 1530 + 1.95 3.0 135.6 5 1545 + 1.96 3.0 135.4 5 1600 + 1.97 3.0 135.3 5 1615 + 1.98 2.9 135.2 5 1630 + 1.99 2.8 135.0 5 1645 + 1.99 2.7 135.0 5 O 1700 1715 1730
+ 2.00 + 2.00 + 2.00 2.7 2.6 2.5 135.0 135.0 135.0 5
5 5 1745 + 2.01 2.5 135.0 '5 1800 + 2.02 2.5 . 135.0 5 1815 + 2.03 2.5 135.0 5 1830 + 2.03 2.5 135.0 5 1845 + 2.03 2.5 135.0 5 1900 + 2.03 2.5 135.0 5 1915 + 2.02 2.5 135.0 5 1930 + 2.01 2.5 135.0 5-1945 + 2.00 2.4 135.0 5 2000 + 2.00 2.4 134.9 5
- 2015 + 2.00 2.4 . 134.8 5 2030 + 2.00 2.4 134.8 5 2045 + 2.00 2.4 134.6 5 2100 + 1.98 2.4 134.5 5 4 O
J
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O . O O RADIOLOGICAL PARAMETERS AUX. BLDC. CHEM. LAB LETDOWN CONT. PART. CONT. CAS HATCH MANIP. CRANE CRANE WALL INCORE RM-154 RM-158 RM-CH-228 RM-259 RM-260 RM-261 RM-262 RM-263 RM-264 TIME R/hr R/hr CPM CPM CPM R/hr R/hr R/hr R/hr 1200 NORMAL NORMAL 8.0 E+3 NORMAL NORMAL NORMAL NORMAL NORMAL NORMAL 1230 NORMAL. NORMAL 1.0 E+4 NORMAL NORMAL NORMAL NORMAL NORMAL NORMAL 1300 NORMAL NORMAL 2.5 E+4 HH NORMAL NORMAL NORMAL NORMAL NORMAL NORMAL 1330 NORMAL N0i< MAL 1.0 E+5 NORMAL NORMAL NORMAL NORMAL NORMAL NORMAL 1400 NORMAL NORMAL 1.0 E+6 NORMAL NORMAL NORMAL NORMAL NORMAL NORMAL 1430 ' NORMAL NORMAL 3.0 E+6 NORMAL NORMAL NORMAL NORMAL NORMAL EORMAL 1500 NORMAL NORMAL 2.8 E+6 NORMAL NORMAL NORMAL NORMAL NORMAL NORMAL 1530 NORMAL NORMAL 2.7 E+6 NORMAL NORMAL NORMAL NORMAL NORMAL NORMAL 1600 NORMAL NORMAL 2.5 E+6 NORMAL NORMAL NORMAL NORMAL NORMAL NORMAL 1630 NORMAL NORMAL 2.5 E+6 NORMAL NORMAL NORMAL NORMAL NORMAL NORMAL
" I "
1700 1.2 E-4 1.5 E-2 2.5 E+6 6.0 E+3 g 1.2 E+3 g NORMAL 1.2 E-3 1.2 E-3 1.2 E-3 1715 1.2 E-4 1.5 E-2 2.5 E+6 3.0 E+4 0FFSCALE NORMAL 1.0 E-3 1.0 E-3 1.1 E-3 1730 1.2 E-4 1.5 h-2 2.5 E+6 1.8 E+5 0FFSCALE 1.0 E-1 1.3 E-3 1.3 E-3 1.2 E-3 H~ M 1745 2.5 E-4 1.5 E-2 2.5 E+6 4.0 E+4 0FFSCALE 1.0 E-0 1.0 E+1 6.0 E-2 1.4 E-2 IIH MH H 1800 2.5 E-1 nuH 3.8 E-0 2.5 E+6 2.5 E+3 0FFSCALE 1.5 E42 OFFSCALE 7.0 E-0 "1.3 E-0 llH HH 1815 1.3 E-0 5.0 E-0 2.5 E+6 1.0 E+4 0FFSCALE 3.0 E+2 0FFSCALE OFFSCALE 2.8 E-0 1830 2.5 E-0 2.8 E-0 2.5 E+6 2.0 E+4 0FFSCALE 4.0 E42 0FFSCALE OFFSCALE 4.2 E-0
- m v2 z; ?$$N H = HI AIARM E
- 0, M
/n ~. O HH = HI HI ALARM o-mo b
O
\ '(
w %) O' RADIOLOGICAL PARAMETERS AUX. BLDG. CHEM. LAB LETDOWN CONT, PART. CONT. CAS ILATCH MANIP. CRANE CRANE WALL INCORE RM-154 , RM-158 RM-CH-228 RM-259 RM-260 RM-261 RM-262 RM-263 RM-264 TIME R/hr R/hr CPM CPM CPM R/hr R/hr R/hr R/hr 1845 4.0 E-0 7.5 E-0 2.5 E+6 3.4 E+4 OFFSCALE 5.0 E+2 0FFSCALE OFFSCALE 6.0 E-0 1900 6.0 E-0 OFFS'CALE 2.5 E+6 4.8 E+4 0FFSCALE 6.0 Ef2 0FFSCALE OFFSCALE 7.0 E-0 , 1915 8.0 E-0 0FFSCALE 2.5 E+6 6.2 E+4 0FFSCALE 7.0 Et2 0FFSCALE OFFSCALE 6.0 E-0 1930 1.0 E+1 3.8 E+0 2.5 E+6 8.0 E+4 0FFSCALE 8.0 E+2 0FFSCALE OFFSCALE 9.0 E-0 1945 0FFSCALE 2.4 E+0 2.5 E+6 9.0 E+4 0FFSCALE 8.4 E+2 0FFSCALE OFFSCALE 9.5 E-0 2000 0FFSCALE 1.0 E-2 2.5 E+6 1.0 E+5 0FFSCALE 8.4 E+2 0FFSCALE OFFSCALE 9.5 E-0 l ALARM SET POINTS: E III III RM-154 (AUX BLDG) 2.Ox10~ 5.OxlO~ R/hr , RM-158 (CI!EM LAB) 1.OxlO~ 5.0xlO~ R/hr RM-228 (LETDOWN) 1.0xlO 2.0xlO cpm RM-259 (CONTAIN. PARTIC.) 1.6x10 4.8xlO cpm f ) RM-260 (CONTAIN. GAS) 5.0xlO 1.6xlO cpm i RM-261 (HA'ICH) 1.DxlO 1.0xlO R/hr RM-262 (MANIP. CRANE) 1.0xlO~ 4.Ox10~ R/hr i Rm-263 (CRANE WALL) 2.0xlO~ 5.0xlO~ R/hr -mz i ~ RM-264 (INCORE) 2.Ox10 5.0xlO~ R/hr i$ $ i gmm a 0 %' O rt
'8
, G" l 5
NAEE Section 10 Page 13 of 190 10-10-84 0 SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: ops-1 1 EMERGENCY EXERCISE I NOVEMBER 15, 1984 TO: SHIFT SUPERVISOR TIME: 1200 For the purposes of this exercise, you have observed or been informed of the following. MESSAGE: THIS IS A DRILL EXERCISE BEGINS.
- REPAIRS ARE IN PROGRESS ON !!OV-HV-200B.
s' k' THIS IS A DRILL ADDITIONAL INFORMATION:
PLANT STATUS NAEE section 10 /200 NORTH ANNA POWER STATION Page 14 of 190 10-10-84 UNIT e IMARY' SYSTEM pd REACTOR COOLANT SYSTEM (T = Temperature - HOTTEST TH (/8 F HOTTEST TC 50 F LOOP"I AT SP F LOOP "2 AT 59 F LOOP "3 AT 59 F ! PRESSURE 2%75 PSIG PRESSURIZER LEVEL (7 % REACTOR COOLANT PUMP A: A, ($) 00C B: A, @ 00C C: A. @ GOC CORE PARAMETERS CORE EXIT THERMOCOUPLE 82 3 F MARGIN TO SATURATION Ch A - 2T F Ch 8 - 29 F SOURCE RANGE COUNTS N 31 '- C N 32 - O INTERMEDIATE RANGE AMPS N 35 - /,O x /d~3 N 36 - /,0 ae /o ~ 8 CONTAINMENT TEMP. -O F PRESS. 7, 7 PSIA SUMP LEVEL d8 N SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A VS % B V.S* X C U % AUX. FEEDWATER AUX FEED' FLOW C (GPM)1-CN-TK-2 LEVEL 25 % 3A: C R, 00C 38: @ R. 00C FW-P-2 A ENGINEERED SAFEGUARDS - RWST SP N SI FLOW C (GPM) HHSI A: A,$ 00C B: O R. 00C C: (A) R. 00C OSRS A: (% R, 00C B: (kJ R. 00C LHSI A:(O R, 00C B:(Q R. 00C ~ ISRS A: /%t R, 00C B: 4) R. 00C OS A:(A7 R, 00C B: A, R. Q Cssmj C,,/, ,7 72 77 g ELECTRICAL DISTRIBUTION "r 4 f/ f.O/ W lE EMER ENCY BUS (SUPPLY)
. 5 DIESEL, . DEAD, BACKFEED h DIESEL, DEAD, BACKFEED EMERGENC DIESEL GENERATOR (EDG)
H: OP, ,00C J:OP h .00C RESERVE STATION SERVICE l A:50T) DEAD B h 0EAD Cah0EAD HIGH RANGE EFFLUENT RAD MONITORS l VENT VENT l FROCESS VENT l MAIN STEAM A B C REMARKS O LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSILE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY 05 - CUENCH SPRAY RSS - RESERVE STATION SERV!CE
NAEE Section 10 Page 15 of 190 10-10-84
'O
[ SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: OPS-2 EMERGENCY EXERCISE NOVEMBER 15, 1984 TO: SHIFT SUPERVISOR TIME: 1203 For the purposes of this exercise, you have observed or been informed of the following. MESSAGE: THIS IS A DRILL ANNUNCIATOR F2 PANEL J S NDS, INDICATING ACTUAL CONTAINMENT PRESSURE EXCEEDS SETPOINT PRESSURE BY +0.1 psi. THIS IS A DRILL ..
-ADDITIONAL INFORMATION:
O . g , -
, ,, ~yy-, --,,,---..-g ., --,y ,,m -g,-~-,m,-, ,.,-+r .,-ay s.wy .n.- , n, -
PLANT STATUS NORTH ANNA POWER STATION M E Se d on I M4 W ged6 of 19gNIT 1 pIMARY' SYSTEM d REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST THf8 F HOTTEST'TC S(0 F LOOP =1 AT 58 F LOOP "2 AT S? F LOOP "3 AT SP F PRESSURE E2JS PSIG PRESSURIZER LEVEL C7 % REACTOR COOLANT PUMP A: A.
@ 00C s: o 6 00C C: A, (ID 00C CORE PARAMETERS CORE EXIT THCRM0 COUPLE 823 F MARGIN TO SATURATION Ch A - 2.1 F Ch 8 - 2,9 F SOURCE RANGE COUNTS l{ 31 '- _
C N 32 - C INTERMEDIATE RANGE AMPS N 35 - /,4 x t'O ~3 N 36 - /,0.x /0~J CONTAINMENT TEMP.
~e j F PRESS. /O 8 PSIA SUMP LEVEL N SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
. A 6 % B YI % C 6 % AUX. FEEDWATER AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL 2S % g 3A: hR 00C 38: h R. 00C FW-P'-2 A~
, ENGINEERED SAFEGUARDS - RWST ff T SIFLOW D (GPM)
HHSI A: A, @ 00C 8: @ R. DOC C: G2 R, 00C OSRS A: /DD R. 00C g:/A) R 00C LHSI A d]D R. 00C B: OR 00C ISRS A: (A) R 00C B: #) R. 00C OS A: 69 R, 00C _ _8: A R. M CE mf Coausp72- 9Fg ELECTRICAL DISTRIBUTION "A j g g,gj4 EMERGENCY BUS (SUPPLY) Hi@IESEL, DEAD, BACKFEED h DIESEL, DEAD. BACKFEED EMERGENCY DIESEL DENERATOR (EDG) H: OP, @ 00C J: OPh. 00C RESERVE STATION SERVICE B- / DEAD C:h/ DEAD A:@ DEAD HIGH RANGE EFFLUENT RAD h0NITORS VENT VENT ,_ PROCESS VENT HAIN STEAM A- - B C' REMARXS O'a
. LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE
- m. - _ - _ . -. , _- .
NAEE Section 10 Page 17 of 190 10-10-84 l i
\
SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: OPS-3 EMERGENCT EXERCISE NOVEMBER 15, 1984 TO: SHIFT SUPERVISOR TIME: 1230 For the purposes of this exercise, you have observed or been informed of the
.fo11owing.
s MESSAGE: THIS IS A DRILL HI ALARM OCCURS ON RM-CH-228: 1,0x10 cpm THIS IS A DRILL i-1 ADDITIONAL INFORMATION: The HI and HI-HI SETPOINTS FOR RM-CH-228 ARE AS FOLLOWS 4 ' HI: 1.0x10 HI-HI: 2.0x10 , RESET AFTER THE MOST RECENT CUTAGE.
.V .
W
'm . 2 .r, , , , , , _ e --e gy --. . - . , .ywo.. ,c,,w.-- - ,%-- ,vy-w.-.---w---,w.m,-e- ,e,= -e,--r,--y ,%mm_., *f-,, ,,w--- -,-w-, ,e . - -- - ,
NAEE Section 10 Page 18 of 190 10-10-84 0 . SCENARIO MESSAGE 4 NORTH ANNA POWER STATION NO.: OPS-4 EMERGENCY EXERCISE NOVEMBER 15, 1984 1 9 TO: SHIFT SUPERVISOR TIME: 1240 For the purposes of this exercise, you have observed or been informed of the following. o MESSAGE: THIS IS A DRILL ~ LOOSE PARTS ANNUNCIATOR SOUNDS. 9 t 4 1 THIS IS A DRILL ADDITIONAL INFORMATION: e
NAEE Section 10 Page 19 of 190 10-10-84 0 SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: OPS-5 EMERGENCY EXERCISE NOVEMBER 15, 1984 TO: SHIFT SUPERVISOR TIME: 1242 For the purposes of this exercise, you hcve observed or been informed of the ' following. MESSAGE: THIS IS A DRILL LOWER REACTOR VESSEL LOOSE PARTS OBSERVED AT LPMS PANEL BY OPS PERSONNEL. t THIS IS A DRILL t ADDITIONAL INFORMATION:
+
- r
_~ -
PLANT STATUS NORTH ANNA POWER STATION [g 6o $9 > 10-10-84 NIT ~ O MARY' l SYSTEM REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH (/E F HOTTEST TC SM F LOOP =1 AT 58 F LOOP "2 AT SP F LOOP "3 AT 58 F PRESSURE 22,35 PSIG PRESSURIZER LEVEL 68 % REACTOR COOLANT PUMP A A, (19 00C B: A, 8 00C C: A, N 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 623 F MARGIN TO SATURATION Ch A - 29 F Ch B - 24 F SOURCE RANGE COUNTS N 31' - O N 32 - O INTERMEDIATE RANGE AMPS N 3S - /, 0.x /0 ~ 3 N 36 - /, d.X /0 ' 3 CONTAINMENT TEMP. O F PRESS. /O, 7 PSIA SUMP LEVEL de SECONDARY SYSTEM STEAM GENERATOR (LEVEL) . A k.S % B VI % C VI % 0 AUX. FEEDWATER AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL .25 % ( a 3A: S R, 00C 3B: /5') R. 00C FW-P-2 M ENGINEERED SAFEGUARDS - RWST 98 6 SI FLOW O (GPM) HHSI A A.[R) 00C B:$ R. 00C C: $ R. 00C OSRS As @ R, 00C B:dl7 R, 00C LHSI' As /O R. 00C B: @ R. 00C ISRS A @ R 00C 8:(157 R. 00C OS A:4, R, 00C B: A, R,(6@ dffag c,sup n fg g
^
ELECTRICAL DISTRIBUTION " A ,.,,,s ,4 f g Ava//d44. EMER ENCY BUS (SUPPLY) S DIESEL, DEAD, BACKFEED Jh DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR ;EDG) H:OP AI 00C J: OP,h,00C
. RESERVE STATION SERVICE A: dIOD' DEAD C h 0EAD B @ DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIM STEAM A B C ' REMARKS LEGEND: HHSI -~ HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE
NAEE Section 10 Page 21 of 190 10-10-84 i O l -Q i SCENARIO MESSAGE NORTH ANNA. POWER STATION NO.: OPS-6 EMERGENCY EXERCISE NOVEMBER 15, 1984 TO: SHIFT SUPERVISOR TIME: 00 For the purposes of this exercise, you have observed or been informed of the following. MESSAGE: THIS IS A DRILL ANNUNCIATOR HI-HI ALARM OCCURS ON RM-CH-223 2.0x10 . ANNUNCIATOR Gl PANEL J SOUNDS INDICATING ACTUAL CONTAINMENT PRESSURE EXCEEDS SETPOINT PRESSURE BY +0.25 psi. THIS IS A DRILL ADDITIONAL INFORMATION: 9 e L- -
. NAEE Section 10 l Page 22 of 190 10-10-84 CONTROLLER INSTRUCTION NORTH ANNA POWER STATION NO.: OPS-3 EMERGENCT EXERCISE NOVEMBER 15, 1984 LEAD CONTROLLER 7g; 1305 TO: _,C,0_NTROLLER INSTRUCTION: At the time designated, perform the following:
- 1. Give
- 2. Maintain the Exercise Scenario by:
ENSURING SCENARIO IS MAINTAINED (CHRONOLOGICALLY) THROUGH THE FIRE AND MEDICAL INCIDENT. MESSAGES SHOULD BE REACHING THE SHIFT SUPERVISOR FROM THE ACCIDENT SCENES DIRECTLY. IF NOT, ATTEMPT TL DETERMINE THE DELAY SO THAT THE EXERCISE WILL CONTINUE ON SCHEDULE. If necessary, give Message NO. to ADDITIONAL INFORMATION: For further clarification, consider the following: z) i
)
NAEE Section 10 Page 23 of 190 10-10-84 O l SCENARIO MESSAGE f NORTH ANNA POWER STATION NO.: Ops-7 ^ EMERGENCY EXERCISE NOVEMBER 15, 1984 TO: AMTFT SUPERVISOR TIME: 1307 4 For the purposes of this exercise, you have observed or been informed of the following. MESSAGE: THIS IS A DRILL SMOKE ALAIW ZONE 25 IS RECEIVED IN THE CONTROL ROOM. CLARIFIER HI LEVEL ALARM OCCURS. f J !~ THIS IS A DRILL
~
ADDITIONAL INFORMATION: e O .
--n r- -, , . -,-.o-, w , ,-e, -, , -,- e.,---,-we ,- ,---s,--- + - ower e .a-nv.--, ,e, , ,w s -~--,4 , me.g , , - , - - y , e_,-.s -y ee-,<~e e +
_. _ . __ = .-. .. _ _. NAEE Section 10 Page 24 of 190 10-10-84 4 SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: OPS-8 EMERGENCY EXERCISE NOVEMBER 15,'1984
'TO: SHIFT SUPERVISOR TIME. 1308 For the purposes of this exercise, you have observed or been informed of the following.
l MESSAGE: THIS IS A DRILL < FIRE IS REPORTED IN THE CLARIFIER BUILDING.
- 1. ~
f J f d THIS IS A DRILL ADDITIONAL INFORMATION: O .
PLANT STATUS l NORTH ANNA POWER STATION p) !foN $9bM 10-10-84 UNIT L l l A ! MARY' SYSTEM jREACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH (/P F HOTTEST'TC W # F . LOOP =I AT SP F LOOP "2 AT SP F LOOP "3 AT SF F l PRESSURE 2_23S PSIG PRESSURIZER LEVEL 88 % REACTOR COOLANT PUMP A: A. N 00C 8: A. h 00C C: A. 89 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 623 F MARGIN TO SATURATION Ch A - 19 F Ch B - 2,9 F SOURCE RANGE COUNTS N 31 '- O N 32 - () INTERMEDIATE RANGE AMPS N 35 - /* d X W3 N 36 - /. O x /0 ~ J CONTAINMENT TEMP. fg F PRESS. /O. 7 PSIA SUMP LEVEL W fo SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A V5 % B V5 % C $ % AUX. FEEDWATER AUX. FEED FLOW C (GPM) 1-CN-TK-2 LEVEL 2 S~ % 3A: h R. 00C 38:_ h R. 00C FW-P-2 A GINEERED SAFEGUARDS - RWST 78 T SIFLOW O (GPM) HHSI A2 A. $ 00C B: @ R. 00C C: /T) R. 00C OSRS A: (T) R. 00C 8:($) R. 00C LHSI A:(O R. 00C B:/A) R. 00C - ISRS A: (i92 R. 0 0 C B: 4Q R. 00C 05 A:@ R, 00C B: 1. R.(tS@ Cg,9 g. 7g _ pg y ELECTRICAL DISTRIBUTION " "p , g fg4ff,gfi EMERGENCY BUS (SUPPLY) H- . DIESEL, DEAD, BACKFEED J h DIESEL, OEAD, BACKFEED l EM rt ENCY DIESEL GENERATOR (EDG) H: OP,@ 00C J: OPh,00C i< RESERVE STATION SERVICE i A:M / DEAD B DEAD C h / DEAD HIGH RANGE EFFLUENT RAD MONITORS l VENT VENT PROCESS VENT l MAIN STEAM A B C REMARKS ( x.s LEGEND: HriSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY 05 - QUENCH SPRAY RSS - RESERVE STATION SERVICE Jh a M
NAEE Section 10 Page 26 of 190 10-10-84 O SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: OPS-9 EMERGENCY EXERCISE NOVEMBER 15, 1984
'TO: SHIFT SUPERVISOR TIME: 1330 For the purposes of this exercise, you have observed or been informed of the following.
MESSAGE: THIS IS A DRILL COOLANT SAMPLE RESULTS: D.E. I-131 0 0.C uCi . Os , gram THIS IS A DRILL ADDITIONAL INFORMATION: f O .
NAEE Section 10 Page 27 of 190 , 10-10-84 SCENARIO MESSAGE NORTH ANNA POWER STATIOE NO.: OPS-10 EMERGENCY EXERCISE NOVEMBER 15, 1984 TO: SHIFT SUPERVISOR TIME: 1345 For the purposes of this exercise, you have observed or been informed of the following. i MESSAGE: THIS IS A DRILL ! R!!-CH-228 INDICATES 1.0x10 . THIS IS A DRILL ADDITIONAL INFORMATION: + I
'd .
n ~,- -- -
,w, , -mymr-ww, , , , - , , a s -en-w,-p-- , -w,r. - - ~ , ,ww,<-,-ww-vcwe-+m-,r--msw n ne-s m ~ w---rw-w>w*w~~*',m,,**--~-r~vww-+-
PLANT STATUS l NORTH ANNA POWER STATION p) ion $9[ /Foo 10-10-84 UNIT L
- IMARY' SYSTEM REACTOR COOLANT SYSTEM (T = Temper eture)- HOTTEST TH M _F, HOTTEST TC SSI F i LOOPal AT S 2. F LOOP "2 AT S* 2_ *F LOOP "3 AT S2 0F PRESSURE 2.22S PSIG PRESSURIZER LEVEL (5 % i REACTOR COOLANT PUMP A: A. @ 00C B: A.
h 00C C: A, S 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 6/S F MARGIN TO SATURATION Ch A - 37 F Ch 8 - 37 F SOURCE RANGE COUNTS N 31 '- o N 32 - O INTERMEDIATE RANGE AMPS N 3S - 9,8 X /B~E N 36 - 9. O x /0 ~ Y CONTAINMENT TEMP. fg F PRESS. /0,7 PSIA SUMP LEVEL 53 PI SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A D % B YI % C kI % AUX. FEEDWATER AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL 2 < %
,q 3A: $ R, 00C 38:' @ R. 00C FW-P-2 A 't.$INEERED SAFEGUARDS - RWST 77f5 SIFLOW D (GPM)
HHSI A: A,(1900C 8: (9 R. 00C C: $R, 00C OSRS As db R, 00C B: 67 R, 00C LHS! A:M R, 00C 8:(19 R. 00C ISRS A: dk R, 00C B:(D R. 00C OS A:/iD R, 00C B: A R,/ CUD gg, Q/, , 7j , y o y y ELECTRICAL DISTRIBUTION ,e EMERGENCY BUS a g Y , jyg,g,,gg, (SUPPLY) H@ DIESEL, DEAD, BACXFEED h DIESEL, DEAD, BACXFEED EMERGENCY DIESEL GENERATOR (EDG) H:OP @ ,00C J: OPh. 00C
. RESERVE STATION SERVICE A-@/CEAD B: @ DEAD C @ DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS LEGEN0: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - CUENCH SPRAY RSS - RESERVE STATION SERVICE e (A = Avatleble, R = RunntnFb 00C = Out of Commission)
- l. NAEE Section 10 Page 29 of 190 10-10-84 SCENARIO MESSAGE NORTH ANNA POWER STATION .NO.: OPS-ll EMERGENCY EXERCISE NOVEMBER 15, 1984 TO: SHIFT SUPERVISOR TIME: 1400 For the purposes of this exercise, you have observed or been informed of the following.
. MESSAGE: THIS IS A DRILL FIRE UNDER CONTROL.
' d 6 RM-CH-228 INDICATES 1.0x10 cpm FOR GREATER THAN 15 MINUTES. POST-FIRE CLEA!RJP BEGINS (LABOREkS, HP, ETC.). THIS IS A DRILL ADDITIONAL'INFORMATION: v . 4
+- e . . - . . , , , . -e- . - , ,- - - , ~.s , .,-.y -r.- ,m,,---._.w--, 7_ , _ ,,,, ,, . , , _ %.--.,,.,%-,-,y,--.e,- --v--w-4--w.-- -, ,. ~ ~ - - . , - + - -
PLANT STATUS NORTH ANNA POWER STATION Nge 3b o $9 10-10-84 UNIT b o
/IMARY' SYSTEM C REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST THto7 F HOTTEST TC IIF F LOOP *1 AT 99 F LOOP "2 AT <,e f F LOOP =3 AT 91 F PRESSURE 22.35 PSIG PRESSURIZER LEVEL (9' %
RiACTOR COOLANT PUMP A: A. ("R)R 00C B: A. @ 00C C: A. @ 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE g/2 F MARGIN TO SATURATION Ch A - 9'd F Ch 8 - Yd F SOURCE RANGE COUNTS N 31 '- O N 32 - 6 INTERMEDIATE RANGE AMPS N 35 - P. Sx /0 "Y N 36 - P. 5 2 /o -Y CONTAINMENT TEMP. fg F PRESS. /d, 7 PSIA SUMP LEVEL $3 N SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A VI % B // I % C b % AUX. FEEDWATER AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL 2 9 % g 3A:_$ R, 00C 38: M R. 00C FW-P-2 A INGINEERED SAFEGUARDS - RWST 9P5 SIFLOW O (GPM) - HHSI A A. @ 00C B: $ R. 00C C: T/ )R. 00C OSRS A: ($) R, 00C B:(,5) R, 00C LHSI A:AQ R. 00C B: /K) R. 00C ISRS As /~Q R, 00C 8:rE) R. 00C
~
05 A:/Q R, 00C B: A. R,(GbEl 6sis; 6cs4s$ FL - 99 f ELECTRICAL DISTRIBUTION ^ fa,,g, g g'. A,, ,.g, EMERGENCY BUS (SUPPLY) Hh DIESEL, DEAD, EACKFEED h DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H:OP @ ,00C J:0 % ,00C < RESERVE STATION SERVICE A 4 0EAD B M OEAD C M / DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT _ PROCESS VENT MAIN STEAM A B C REMARKS (D V LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SFRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE
PLANT STATUS NORTH ANNA POWER STATION QE ,3 S oj 1 2 10-10-84 RIMARY' SYSTEM REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH (OS F HOTTEST TC 557 F LOOP =1 AT 4/f F LOOP "2 AT </P F LOOP "3 AT '/8 F PRESSURE 2.235 PSIG PRESSURIZER LEVEL 6/ % REACTOR COOLANT PUMP A: A, @ 00C B: A, @ 00C C: A. /9 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 8/8 F MARGIN TO SATURATION Ch A - 6/ 2.__ F Ch 8 - 9A F SOURCE RANGE COUNTS N 31 '- C N 32 - C INTERMEDIATE RANGE AMPS N 35 - 7 O y /o ~ Y N 36 - P, O x /o - Y CONTAINMENT TEMP. /) F PRESS. /d, 7 PSIA SUMP LEVEL 62_ 7 SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A D % B b % C YI % AUX. FEEDWATER AUX. FEED FLOW O (GPM) I-CN-TK-2 LEVEL 3/% 3A: N R, 00C 38: $ R. 00C FW-P-2 A o CGINEERED SAFEGUAROS - RWST 79 (, SI FLOW O (GPM) HHSI A: A,( O 00C B: SR, 00C C: 8 R. 00C OSRS A': d]?R,00C BS R, 00C LHSI A:Mb R. 00C B:(E7 R. 00C ISRS As dQ R 000 B: (Q R. 00C OS AM R, 00C B: A. R.cGoQ C,pg,9 $/,4 g _ ggf ELECTRICAL DISTRIBUTION '
// g gg,g ,g ,
EMERGENCY BUS duPPLY) Hh DIESEL, DEAD, BACKFEED Jh DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OP@,00C J:OPh 00C RESERVE STATION SERVICE Ax46T)CEAD BM/ DEAD CM/ DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS
\
lU LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave:Imble, R = Running, 00C = Out of Commission)
NAEE Section 10 Page 32 of 190 10-10-84 O a SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: OPC-12 ~ EMERGENCY EXERCISE NOVEMBER 15, 1984 TO: SHIFT SUPERVISOR TIgg; 1430 - For the purposes of this exercise, you have observed or been informed of the following.
- MESSAGE:- THIS IS A DRILL COOLANT SAMPLE RESULTS: D.E. I-131 0 30.0 uCi . .
gram O PROJECTED INCREASE III COOLANT ACTIVITY APPROXIMATELY 23.S uCi PER HOUR. gram 6 TilIS IS A DRILL ADDITIONAL INFORMATION: O
PLANT STATUS NORTH ANNA POWER STATION Paga 33 of 190 M E Sa d on 10 /yff 10-10-84 UNIT 1 PRIMARY' SYSTEM I REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH 603 F HOTTEST TC Sf7 F LOOPal AT V4 F LOOP "2 AT. 94 F LOOP '3 AT V( F PRESSURE 2235 PSIG PRESSURIZER LEVEL (d % REACTOR COOLANT PUMP A A. (@ 00C B: A. @ 00C C: A. @ 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 867 F MARGIN TO SATURATION Ch A - 94/ F Ch B - t/ V F SOURCE RANGE COUNTS N 31 '- O N 32 - C INTERMEDIATE RANGE AMPS N 35 - 7. S .x /o'I N 36 - 7. L /o ~ V CONTAINMENT TEMP. _ kd?
# F PRESS. /d. 7 PSIA SUMP LEVEL 78 N SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
. A 78 % B [5 % C 78 % AUX. FEEDWATER AUX. FEED FLOW - O (GPM) 1-CN-TK-2 LEVEL (/8 % 3A: @ R, 00C 3B: /1D R. 00C FW-P-2 N O O CJINEERED SAFEOUARDS - RWST 79 E SIFLOW (GPMi HHSI A: A,d900C 8: @ R. 00C C: /lQ R, 00C OSRS A: (1D R, 00C B:/P R, 00C
~
LHSI Arr$3 R. 00C 8: @ R. 00C ISRS A (b R. 00C B: 11b R. 00C B: A, R /UDC) Q, g g g OS A:/@ R. OCC a 44
+
- ELECTRICAL DISTRIBUTION O ~
#~*
EMERGENCY BUS (SUPPLY) H h DIESEL, DEAD, BACKFEED J h DIESEL, DEAD, BACKFEED l EMERGENCY DIESEL GENERATOR (EOG) ! H:OP @ ,00C J: OP@,00C l RESERVE STATION SERVICE A:G / DEAD DEAD C h 0EAD j HIGH RANGE EFFLUENT RAD MONITORS i VENT VENT , PROCESS VENT l MAIN STEAM A B C REMARKS ,' A L] LEGEND: HHSI - HIGH HEAD S.I. OSRS - GUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS'- OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave lable, R = Running. 00C = Out of Commission)
PLANT STATUS NORTH ANNA POWER STATION $ a UNIT '3$ oIS9kM( o 10-10-84
~~
( MARY' SYSTEM V REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH d'oo F HOTTEST TC SS4 F LOOP *1 AT VV F LOOP "2 AT 97 F LOOP "3 AT 99 F PRESSURE 22.35 PSIG PRESSURIZER LEVEL E SP % REACTOR COOLANT PUMP A: A,
@ 00C 8: A, @ 00C C: A. N 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 6d5 F MARGIN TO SATURATION Ch A - 77 F Ch 8 - #/ ~7 F SOURCE RANGE COUNTS N 31 '- C N 32 - C INTERMEDIATE RANGE AMPS N 35 - 7, 5"y /0 ' Y N 38 - ~A .S x /0 - Y CONTAINMENT TEMP. 98 F PRESS. / 0, ""7 PSIA SUMP LEVEL 5O N SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
A VS X B Y$ % C VS % AUX. FEEDWATER AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL 9._'I % g 3A M R, 00C 38: O R, OCC FW-P-2 M ENGINEERED SAFEGUARDS - RWST TF 25 SIFLOW O (GPM) HHSI A A,@ 00C 8: 75)R 00C C:[d)R, 00C
~
OSRS A: (fDR, 00C ggfs? R 00C LHSI A:MQ R, 00C B:@ R. 00C ISRS A: 7J? R 00C B TQ R. 00C OS Ad R 00C B: A. R./UUD Cgy,p 4,g gj - g g ELECTRICAL DISTRIBUTION f/ // g, EMER ~NCY BUS (SUPPLY) Y S DIESEL, DEAD, BACKFEED M DIESEL, OEAD, BACKFEED EMERGENCY DIESEL GENCRATOR (EDG) H:OP @ 00C J: ORM,00C
= RESERV STATION SERVICE A: 0 DEAD B M DEAD C:M DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS v
LEGEN0: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE
PLANT STATUS NORTH ANNA POWER STATION NAEE Ssetion 10 UU Paga 35 of 190 UNIT 2_, 10-10-84
/' MARY' SYSTEM C]PEACTORCOOLANTSYSTEM (T = Temperature)- HOTTEST TH SM F HOTTEST TC 554 F LOOPal AT 9/ F LOOP "2 AT y/ F LOOP "3 AT 9/ F F.V SSURE 2.23'S PSIG PRESSURIZER LEVEL St %
REACTOR COOLANT PUMP A: A.
@ 00C B: A. (fi-) 00C C: A. $ 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 802 F MARGIN TO SATURATION Ch A - Sd F Ch 8 - So F SOURCE RANGE COUNTS N 31 '- O N 32 - C INTERMEDIATE RANGE AMPS N 35 - 7 8 y /O-Y N 36 - 2 8x /O' Y CONTAINMENT TEMP. 6 F PRESS. /0, 7 PSIA SUMP LEVEL 8k SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
A ll.5 % B U % C V$ % AUX. FEEDWATER AUX. FEED FLOW O (GPM) l-CN-TK-2 LEVEL 92 % 3A: @ R, 00C 38: N R. 00C FW-P-2 N h31NEERED SAFEGUARDS - RWST 88 6 SIFLOW O (GPM) HHSI A: A./#)00C B:/5) R. 00C C:/fpR. DOC
~
OSRS As /E7 R. 00C B:CA/ R, 00C LHSI A:d!D R. 00C B: /'@ R. 00C - ISRS A: #R R. 00C B:7@ R. 00C OS A:[R R, 00C 8: A, R/TOO d o,,,jp g j g,y7 ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY)
,v ogW g g ,.g , @ DIESEL, DEAD, BACKFEED J@ DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG)
H: OPg,00C J: OPffhd2,00C < RESERVE STATION SERVICE A @ DEAD B @ / DEAD Ci b OEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT , PROCESS VENT MAIN STEsM A B C REMARKS , O LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE Nn
PLANT STATUS '
.* NORTH ANNA POWER STATION M E Socion 10 / I 3 0 Paga 36 of 190 UNIT 2--
10-10-84 P IMARY' SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH5f3 F HOTTEST TCSSt F LOOP"I AT 37 F LOOP "2 AT 37 F LOOP "3 AT J7 F PRESSURE .12_75 PSIG PRESSURIZER LEVEL Q % REACTOR COOLANT PUMP A: A. $ 00C B: A. / C) 00C C: A. (9 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 5 78' F MARGIN TO SATURATION Ch A - Sy F Ch 8 - S*Y F SOURCE RANGE COUNTS N 31 *- 6 N 32 - 6 INTERMEDIATE RANGE AMPS N 35 - 6,53 /O' Y N 38 - ( .fA /0 ~ f CONTAINMENT TEMP. 90 F PRESS. /0, ~/ PSIA SUMP LEVEL 78 N SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 95* %B N5' % C VI % AUX. FEEDWATER AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL 38 % g 3A: N R, 00C 38: 6 R. 00C FW-P-2 M U INEERED SAFEGUARDS - RWST 97 fl SIFLOW O (GPM) HHSI A A. 6 00C 8: SR. 00C C: NR. 00C OSRS As dDR. 00C Spf R, 00C LHS! A:/OR, 00C B:/@ R. 00C ISRS Ar4T R. 00C 8:N R. 00C 05 AO R, 00C B: 'A. R,(CVCC? C4suf Q,4 yz _ 77 g ELECTRICAL DISTRIBUTION a g_ g,fg jg, , EMERGENCY BUS (SUPPLY) H:@ DIESEL, DEAD, BACKFEED J @ DIESEL, DEAD. BACKFEED EMERGENCY O!ESEL GENERATOR (E00) H:OP M OC J: OP 00C RESERVE STATION SERVICE A M OEAD C. M DEAD
@ DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS O
LEGENO: HHS! - HIGH HEAD S.I. OSRS - CUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Available, R = Running, 00C = Out of Commission)
PLANT STATUS NORTH ANNA POWER STATION NAEE Ssction 10 U f 8 3 of19% NIT 1 IMARY' SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH S10 F HOTTEST TC S54 F LOOP'1 AT 3y F LOOP "2 AT 3y F LOOP "3 AT 3V F - PRESSURE 2.2 3 5 PSIG PRESSURIZER LEVEL S2 % REACTOR COOLANT PUMP A: A. (fG? 00C B: A, @ 00C C: A. @ 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 5f5 F MARGIN TO SATURATION Ch A - S7 F Ch B - S7 F SOURCE RANGE COUNTS N 31 '- O N 32 - ()' INTERMEDIATE RANGE ' AMPS N 35 - (, 25.4 /o- I N 36 - [ 2S .x Y Y CONTAINMENT TEMP. 98 F PRESS. /O, 7 PSIA SUMP LEVEL [O SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A f/3 % B V5 2 C VS 2 AUX. FEEDWATER . AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL 88 % 7,, 3A: @ R, 00C 3B: ('1D R. 00C FW-P-2 M ( INEERED SAFEGUARDS - RWST 78 6 .SIFLOW O (GPM) HHSI A A, $ COC B: hR. 00C C:/T)R. 00C OSRS As /C R, 00C B : d r> R 0 0 C LHSI A:Q ,00C Ba@ R. 00C ISRS As f@ R. 00C B: 40 R. 00C OS AVQ R, 00C B: A, R/'6bf) 6 4. ssi.f M , 4 7) _ yog g ELECTRICAL DISTRIBUTION >
^A jfg gg ,
EMERGENCY BUS (SUPPLY)
@ DIESEL, DEAD. BACKFEED h DIESEL, DEAD, BACnFEED EMERGENCY DIESEL GENERATOR (EDG)
H: OP8,00C , J:O h 00C
. RESER TATION SERVICE A._H CEAD B @ /CEAD C: h EAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS ,,
(y LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Available R = Running, 00C = Out of Commission)
PLANT STATUS NORTH ANNA POWER STATION [jE,3S o 9 10-10-84 NIT IMARY' SYSTEM REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH 574 F HOTTEST TC SSI F LOOP"1 AT Jo F LOOP "2 AT 3o F LOOP "3 AT 3O F PRESSURE 2235 PSIG PRESSURIZER LEVEL 98 % REACTOR COOLANT PUMP A: A. $_ 00C B: A.
/_1D 00C C: A.
00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 89/ F MARGIN TO SATURATION Ch A - 6/ F Ch 8 - 6/ F
, SOURCE RANGE COUNTS N 31 *- C N 32 - C INTERME0! ATE RANGE AMPS N 35 - [ 0 A /D ~Y N .36 - g d .x /0 ~k CONTAINMENT TEMP. pg F PRESS. /C. 7 PSIA SUMP LEVEL 8I N SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
A V$ % B V$ % C V$ % AUX. FEEDWATER AUX. FEED FLOW C (GPM) 1-CN-TK-2 LEVEL 27 %
,q , 3A: b R, 00C 38: M R. 00C FW-P-2 /
h jlNEERED SAFEGUARDS - RWST @E SIFLOW O (GPM) HHSI A: A. @ 00C B (A)R. 00C C: @R, 00C' OSRS As /O R, 00C B:($7 R, 00C LHSI A:/OR. 00C B: /T)R. 00C ISRS A: @ R, 00C BrtQ R. 00C OS A8 R 00C B: A. R, @ _ Csyfgg g.,gf,pg 7j., g 7 ELECTRICAL DISTRIBUTION W "g W 4 g_
- EMERGENCY BUS (SUPPLY)
H@ DIESEL, DEAO, BACKFEED M O!ESEL, DEAO, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OP,@, 00C J:OP M 00C l
.. RESERVE STATION SERVICE A:S /CEAD Bg/ DEAD C:M OEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT .
PROCESS VENT MAIN STEAM A B C REMARKS O LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY 05 - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Averlobler R = Runn:n;;b 00C = Out of Commission)
NAEE Saction 10 Pags 39 of 190 10-10-84 O SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: OPS-13 EMERGENCY EXERCISE NOVEMBER 15, 1984 TO: SHIFT SUPERVISOR TIME: 1600 For the purposes of this exercise, you have observed or been informed of the following. MESSAGE: THIS IS A DRILL - RM-CH-228 indicates greater than 2.0x10 . O' COOLANT SAMPLE INDICATES GREATER THAN 65.0 uCi D.E. 1-131. gram i I
. THIS IS A DRILL f
ADDITIONAL INFORMATION: 1 D I LU l - 4
PLANT STATUS NORTH ANNA POWER STATION MESmain1 Pags 40 of 190 UNIT 2-10-10-84 IMARY' SYSTEM , REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST THSTS F HOTTEST TCSSS F LOOP"! AT 3d F LOOP "2 AT 30 F toop =3 AT So "F PRESSURE _ 2215" PSIG PRESSURIZER LEVEL f# 7 % REACTOR COOLANT PUMP A: A. 6 00C 8: A. S 00C C: A. h 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 6 98 F MARGIN TO SATURATION Ch A - /f2 F Ch 8 - (.2 F SOURCE RANGE COUNTS N 31 '- O N 32 - 6 INTERMEDIATE RANGE AMPS N 35 - S. 7S .4 /O~ I N 36 - S'78x /d 'I CONTAINMENT TEMP. g F PRESS. /0,'/ PSIA SUMP LEVEL 65 % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A V$ % B VW % C Y % AUX. FEEDWATER AUX. FEED FLOW 6 (GPM) 1-CN-TK-2 LEVEL 23 % o ' 3A: h R, 00C 38 ,_@ R. 00C FW-P-2 A
- Y.,GINEERED SAFEGUARDS - RWST N$ SIFLOW d (GPM)
HHS! A's A.S 00C B: $ R. 00C C: /VR, 00C OSRS A: (C R 00C 8:(5)R. 00C LHSI A:/S] R. 00C 8: /9 R. 00C ISRS A:G R. 00C- B(TO R. 00C 05 A/D R, 00C B: A,Rf5Cr} C,$3,,y q wi,yp 7; . pg g ELECTRICAL O!STRIBUTION EMERGENCY BUS (SUPPLY)
"A g 7 g ,4,jfg ,
Hh DIESEL, DEAD, BACKFEED Jah DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OPM 00C J:0 @ 00C 4 RESERVE STATION SERVICE A:6idDDEAD BM/ DEAD C /0EAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT , PROCESS VENT MAIN STEAM A B C . REMARKS ,
,/ )
LEGEND: HHS! - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRhY LHS! '. ' i HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Anellable, R = Runwg, 00C = O_ut er Cemmam; en)
PLANT STATUS NORTH ANNA POWER STATION fg !$ $9 > 10-10-84 UNIT o IMARY' SYSTEM EACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH5Fo F HOTTEST TC5f/ F LOOP =1 AT 2g F LOOP *2 AT 2.6 F LOOP "3 AT M F PRESSURE 22.JS PSIG PRESSURIZER LEVEL 98 % REACTOR COOLANT PUMP A A, @ 00C B: A. $ 00C C: A,
@ 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE EF8 F MARGIN TO SATURATION Ch A - g7 F Ch 8 - [7 F SOURCE RANGE COUNTS N 31 '- O N 32 - ()
INTERMEDIATE RANGE AMPS N 35 - S, S x /o~ V N 36 - S S x /0 4 CONTAINMENT TEMP. [/ F PRESS. /0, 7 PSIA SUMP LEVEL 88 SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 95 % B M % C 95 % AUX. FEEDWATER AUX. FEED FLOW 6 (GPM) 1-CN-TK-2 LEVEL 25 % c 3A: M R. 00C 38: /7) R. 00C FW-P-2 A
. INEERED SAFEGUARDS - RWST N6 SI FLOW O (GPM)
HHSI A: A N 00C B: @ R. 00C C:(B R 00C OSRS A: 40) R, 00C B:(O R, 00C LHSI A:M9 R, 00C 8: (@ R. 00C ISRS A: 4 R, 00C 8:T67 R. 00C OS Ad R, 00C 8: A, R,760C) gg Oggg9 g - 97 { ELECTRICAL DISTRIBUTION e EMERGENCY BUS "A gfg , gjt , (SUPPLY) H@ DIESEL, DEAD, BACKFEED Jh DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EOG) H: OPM,00C J:OP @ 00C
. RESERVE STATION SERVICE AFTIO3/CEAD / DEAD 8: $ DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PF.QCESS VENT MAIN STEAM A B . C REMARKS LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Avetleble, R = Runntna 00C = Out of Commission)
PLANT STATUS NORTH ANNA POWER STATION p "$ $7N $9 , , 10-10-84 [ MARY' SYSTEM C]REACTORCOOLANTSYSTEM (T = Temperature) - HOTTEST TH 576 F HOTTEST TC 653 F LOOP =1 AT .73 F LOOP "2 AT 23 F LOOP "3 AT U F PRESSURE 22JS PSIG PRESSURIZER LEVEL 93 % REACTOR COOLANT PUMP A: A. $ 00C B: A. @ 00C C: A. h 00C_ CORE PARAMETERS CORE EXIT THERMOCOUPLE 68/ F MARGIN TO SATURATION Ch A - 7/ F Ch 8 - '7/ F SOURCE RANGE COUNTS N 31 '- O N 32 - O INTERMEDIATE RANGE AMPS N 35 - 6.25.X /O'Y N 36 - S 2 Sac /0~V CONTAINMENT TEMP. f7 F PRESS. /O. 7 PSIA SUMP LEVEL bO N SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A YT % B Y$ % C U % AUX. FEEDWATER AUX. FEED FLOW d (GPM) 1-CN-TK-2 LEVEL 28 % 3A: N R, 00C 38: /7Q 'R, 00C FW-P-2 M GINEERED SAFEGUARDS - RWST 99 f SIFLOW d (GPM) HHSI A: A. @ 00C B: @ . 00C C: /19 R. 00C OSRS As MC7R. 00C 8:f32 R, 00C LHSI A:/fI) R 00C B:<PQ R. OOC ISRS A:f3? R, 00C Bf3? R. 00C OS A@ R, 00C 8: A. R,@ CM/wp @m c 7j _ eff { ELECTRICAL DISTRIBUTION "
"4 g _ gg, g ,
EMERGENCY BUS (SUPPLY) H:ODIESEL, DEAD, BACKFEED J@ DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OPM,00C J:OPh 00C 4 RESERVE TATION SERVICE A: DEAD B M DEAD C h/ DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT , PROCESS VENT MAIN STEAM A - B C REMARKS (3/ LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - CUENCH SPRAY RSS - RESERVE STATION SERVICE . . _ (A = Avoiloble. R = Runntsa 00C = Oun mr Cmmmission)
- OO NORTH ANNA POWER STATION NAEE Section 10 Page 43 of 199) NIT 7 -
10-10-84 PRIMARY ~ SYSTEM REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH f79 F HOTTEST TC 563 F *
\
LOOP"1 AT 2/ F LOOP *2 AT :2/ F LOOP '3 AT 2/ F PRESSURE 1 2. 1.9 PSIG PRESSURIZER LEVEL 39 % REACTOR COOLANT PUMP A: A. (%7 00C B: A, N 00C C: A. M 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 677 F MARGIN TO SATURATION Ch A - '7J F Ch B - 7J F SOURCE RANGE COUNTS N 31 *- O N 32 - 6 INTERMEDIATE RANGE AMPS N 35 - S dx /o -I N 36 - S.d x /0 " Y CONTAINMENT TEMP. / F PRESS. /6 7 PSIA SUMP LEVEL b i SECONDARY SYSTEM' STEAM GENERATOR (LEVEL) W L .A V.S X B VS % C X O AUX. FEEDWATER AUX. FEED FLOW (GPM) 1-CN-TK-2 LEVEL 27 % 3A: N R, 00C 38: 7Q R. 00C FW-P-2 A INEERED SAFEGUARDS - RWST NN SIFLOW O (GPM) HHSI A: A. $ 00C B: @ R. 00C C:/Q R 00C OSRS A: /C R.00C BidP R, 00C LHSI A:/D R. 00C B:-/fQR. 00C ISRS A: 41D R. 00C Ba dD R. 00C OS AsfD R. 00C B: A. R & D S/A f & s /,9f )% - 99 $ ELECTRICAL DISTRIBUTION *
" f,,f, g gg- ggfg ,
, EMERGENCY BUS (SUPPLY) l H g DIESEL, DEAD, BACKFEED J@ DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OP, h,00C J:OP @ ,00C l- RESERVE TATION SERVICE
- A EAD B h 0EAD C [/ DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM ,A B C REMARKS O OSRS - OUTSIDE RECIRC. SPRAY LEGEND: HHSI - HIGH HEAD S.I.
I LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Available, R = Running. 00C = Out of Commission) e ~
NAEE Section 10 Page 43 A of 190 11-12-84 l l TIME: 1700 CONTAINMENT GAS HI AIARM: 5.0 x 10 cpm a 1 l i I i i l f l i 4" i t I
NAEE Section 10 Page 43 B of 190 l 11-12-84 l l TIME: 1701 , t l I ! 3 i CONTAINMENT GAS HI HI ALARM: 1.6 x 10 cpm ' I 1 i i
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NAEE Section 10 Page 43 C of 190 11-12-84 TIME: 1705 4 ANNUNCIATOR ALARM: CH-PP to Regen IEf HI/LO Flow l I L i l l l i 1e t I ( i i l l [ l l l l 4' I l i t l t
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NAEE Section 10 Page 43 D of 190 11-12-84 TIME: 1708 i i ANNUNCIATOR: RX CONTAINMENT SUMP HI LEVEL i I l l l l [
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NAEE Section 10 Page 43 E of 190 11-12-84 TIME: 1711 ANNUNCIATOR ALARM INCORE SUMP HI LEVEL l 4 i i l 1 4 1 l 4 l l l 4
t'L AN I blAIUb NORTH ANNA POWER STATION NAEE Section 10 Page 44 of 190 UNIT ? 10-10-84 PRIMARY' SYSTEM G REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST THS'/O F HOTTEST TC SS2 F U LOOP"1 AT /8 F LOOP "2 AT /8 F LOOP "3 AT /8 F PRESSURE J235 PSIG PRESSURIZER LEVEL M % REACTOR COOLANT PUMP A: A, (79 00C B: A. @ 00C C: A, 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 67S F MARG!N TO SATURATION Ch A - 77 F Ch 8 - 77 F SOURCE RANGE COUNTS N 31 '- o N 32 - C INTERMEDIATE RANGE AMPS N 3S - 4/, 7 5 x /o '/' N 38 - 9' 7 5 .x / 0 '/' CONTAINMENT TEMP. h F PRESS. /O, f' PSIA SUMP LEVEL /88 SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A V$ % B W X C V5 2 AUX. FEEDWATER AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL 3C % 3A: N R, 00C 38: h R. 00C FW-P-2 N GINEERED SAFEGUARDS - RWST 7795 SIFLOW O (GPM) HHSI A A.(9 00C 8: $ R, 00C C: /E)R. 00C OSRS As dk R. 00C B:G R,00C LHSI A )iC)R, 00C B: /19 R, 00C ISRS A dD R 00C 8:d5? R. 00C OS AM R, 00C 8: A R,/tfD d A S m p & g f ,p p g g,
# E ELECTRICAL DISTRIBUTION 'g ,,, g ff_ ggjjg, EMERGENCY BUS (SUPPLY)
H M DIESEL, DEAD, BACKFEED Jg DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OPM,00C J: OP ,00C RESERVE STATION SERVICE A: G DEAD B @ / DEAD DEAD
- HIGH RANGE EFFLUENT RAD MONITORS VENT VENT ,
PROCESS VENT
, MAIN STEAM A B C REMARKS I
LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Avetlable, R = Running, 00C Out of Commission)
. . - ~
l l I NAEE Section 10 i Page 44 A of 190 i 11-12-84 i l TIME: 1720 r l ANNUNCIATOR ALARM: PZR LO LEVEL 1 l I i I ( l l l l l l t I l I l I
NAEE Section 10 i Page 44 B of 190 11-12-84 l l [ TIME: 1723 CONTAINMENT PARTICULATE HI ALARM: 1.6 x 10 cpm l l t f i l l l r i i 1 4 I I ( . r Y t I a O 8 1 1 I
4 NAEE Section 10 Page 44 C of 190. 11-12-84 r TLME : 1729 PZR LO Pressure, B/U HTRS _ON L i I i i e 4 I c l 1 i 4 l l
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t'LANI blAIUb NORTH ANNA POWER STATION NAEE Section 10 gg_4(of190 UNIT 2-PRIMARY' SYSTEM . ( )CEACTORCOOLANTSYSTEM (T = Temperature)- HOTTEST TH 5Y7 F HOTTEST TC 5SooF LOOP =1 AT /7 F LOOP "2 AT /7 F LOOP "3 AT /7 F PRESSURE 22.35 PSIG PRESSURIZER LEVEL 20 % REACTOR COOLANT PUMP A: A. /fG 00C B: A. $ 00C C: A. M-00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 5 72. F MARGIN TO SATURATION Ch A - 8d F Ch 8 - 84 F SOURCE RANGE COUNTS N 31 '- O N 32 - C INTERMEDIATE RANGE AMPS N 35 - M O.x/0'Y N 38 - (/,O y /d""Y CONTAINMENT TEMP. //5 F PRESS. /R PSIA SUMP LEVEL N0 N SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A V.S~ % B V5 % C W X AUX. FEEDWATER AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL 3'3 % 3A 4~) R, 00C 38: (T) R. 00C FW-P-2 A CINEERED EAFEGUARDS - RWST 9P 6 SI FLOW O (GPM) HHS! A: A, $ 00C B: $R. 00C _ C: & R. 00C OSRS A (O R, 00C BidD R, 00C LHSI A:/7D R. 00C 8: 79 R. 00C ISRS A $ R. 00C 8:d? R. 00C OS A:/t) R,00C B: A,R,fC W O S /,9 j csw,g q 7j _ fg g ELECTRICAL O!STRIBUTION EMERGENCY BUS (SUPPLY) a N4g j g _ g pg ff, , H@ DIESEL, DEAD, BACKFEED 8 O!ESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OP,@, 00C J: OP@,00C RESERVE STATION SERVICE A M / DEAD BM/0EAD CM/ DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT FROCESS VENT HA!N STEAM A B C REMARKS O LEGEN0: HHS! - HlCH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave:lable, R = Running, 00C s Out of Commission)
. - - - . - . _ ~ _. . .. _- - - -_. --- _ .- _ -. _. _. _ . .. . ._ - -
NAEE Saction 10 Ptgs 46 of 190 10-10-84 SCENARIO MESSAGE i NORTH ANNA POWER STATION NO.: OPS-14 EMERGENCY EXERCISE NOVEMBER 15, 1984 i TO: SHIFT SUPERVISOR TIME: 1730 i For the purposes of this exercise, you have observed or been informed of the following. j i MESSAGE: THIS IS A DRILL i
~
AUTOMATIC S.I. AND REACTOR TRIP OCCURS FROM LOW PRESSURIZER PRESSURE. i i THIS IS A DRILL f i ADDITIONAL INFORMATION: 6 I
-_-_.m _m._.. _ _ _ . _ _ _.m. _____________m ______._m--m __-_-____-. _ _ _ . . _ _ _ _ _ _ _ - . _ - - _ . _ _ _ -- - ---k-~raN-+e-- -- M N8V
- _ - . - . . . . . . ~ . - - . _ _ . _ _ . . . ._. . . . . . _ _ .- - . . - . . _ . - - . - . . . - - . _ ,
1 4 i NAEE Section 10 Page 46 A of 190 l 11-12-84 i TIME: 1735 i l ! PZR LO PRESSURE RX TRIP I I I l l l l i l i l l l. I l 1 l
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l l NAEE Section 10 Page 46 B of 190 11-12-84 i TIME: 1737 i PZR LO Pressure SI l I l l l 6 F F n
't 4l 4'
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--w.-ve+e.-- .-re-.ww -. e- __ .-
NAEE Section 10 Page 46 C 11-12-84 TIME: 1737 l
-2 l
' RM-263, RX CONTAINMENT AREA MONITOR HI ALARM: 2.0 x 10 R/hr i i I l i i l t i, e i l ' I i f 6 i t i
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i l NAEE Section 10 ; Page 46 D of 109 11-12-84 TIME: 1744
-2 i RM-263, RX Containment Area Monitor HI HI Alarm: 5.0 x 10 R/hr i 4
i i t i l l 4 I t r i I i I 4
PLANT STATUS NORTH ANNA POWER STATION NE Saction 1/7 V8
$8'$f190 g UNIT L PRIMARY SYSTEM fV') REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH 6'/d F HOTTEST TC f30 F LOOPal AT /0 F LOOP "2 AT /0 F LOOP "3 AT /0 F PRESSURE /SSd PSIG PRESSURIZER LEVEL C %
REACTOR COOLANT PUMP A: A. $ 00C B: A. @ 00C C: A, h 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 67_f F MARGIN TO SATURATION Ch A - J'f F Ch 8 - 39 F SOURCE RANGE COUNTS N 31 '- C N 32 - O INTERMEDIATE RANGE AMPS N 35 - /. 8 A /0 - E N 36 - /, d .k /0~ # CONTAINMENT TEMP. 2/g F PRESS. /4 PSIA SUMP LEVEL /80 N SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 70 % B Yd % C 3d % AUX. FEEDWATER AUX. FEED FLOW P 9'O (GPM) l-CN-TK-2 LEVEL JS % 3A A. $ 00C 3B: A, /II) 00C FW-P-2 A f INEERED SAFEGUARDS - RWST 77 [ StFLOW 4/YS (GPM) HHS! A S R. 00C B: A. 6 00C C: A/lD00C OSRS A A, R. 00C ' g: A R 00C LHSI A:_A AD 00C B:_A dl 00C ISRS A A. R. 00C B: A. R. 00C OS A: A. R. (000 B: A R,(TIDf) C/pg p" eg g,3,g 7f - ELECTRICAL DISTRIBUTION j>g ,,j, , g fa ff. ,1, A 006 EMERGENCY BUS (SUPPLY) H @ O!ESEL, DEAD, BACKFEED @ DIESEL, DEAD, BACKFEED EMERGENCY O!ESEL OENERATOR (EOG) l H: OP, @, 00C J: OP@,00C j* RESERVt! STATION SERVICE j A M DEAD B @ / DEAD C M / DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT , PROCESS VENT MAIN STEAM A B C REMARKS ,' I b LEGEN0: HHS! - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE REClRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A s Ave:lable, R s Running, 00C s Out of Commission)
h- NAEE Section 10 Page 48 of 190 10-10-84 O SCENARIO MESSAGE NORTH ANNA POWER STATION NO. OPS-15 INERGENCY EXERCISE NOVEMBER 15, 1984 TO SHIFT SUPERVISOR TIMg 1745 For the purposes of this exercise, you have observed or been informed of the following. MESSAGE: THIS IS A DRILL CONTAIN:4ENT PRESSURE POSITIVE. THIS IS A DRILL ADDITIONAL INFORMATION REFERENCE PLANT STATUS SHEETS e 3 (O
I NAEE Section 10 l Page 48 A of 190 11-12-84 TIME: 1745 RM-262, MANIPULATOR CRANE HI ALAEM: 1.0 x 10" R/hr i t f 4 e i M i _ - , - _ - - - , - - , ~ , - - - - - , , , ~ , - . . - -
- .__ . . - . . _ _ _ _ _ - . -~ - .. .... __ --- _ - . . . -_ - .. .__ . .. - - ..-
NAEE Section 10 Page 48 B of 190 11-12-84 TIME: 1747 , RM-261, CONTAINMENT HI RANGE HI ALARM: 1.0 x 10 R/hr s ) 4 4 i f f
.- .._n- .-..,- -- ..-_ _ ,..- - -_ ,---,-__-._n, . - , , . . _ _ . _ _ . - .m.,,,,.,n.--~-. . - , . . - ~ , -
I NAEE Section 10 Page 48 C of 190 11-12-84 i 1 TIME: 1748 : I 1
~ ; RM-262, MANIPULATOR CRANE HI HI ALARM: 4.0 x 10 R/hr s
I i t f 4 1 ! l ,} i i t i, e i I I { i
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, - ,---c-.---,----- . - - - , - , - , , _-----,--- . - - - - - .
NAEE S3ction 10 Pcg3 49 of 190 10-10-84 v SCENARIO MESSAGE , NORTE ANNA POWER STATION NO.: OPS-16
- EMERGENCY EEIRCISE l NOVEMBER 15. 1984 i
7 Tot SHIFT SUPERVISOR TIME: 1755 For the purposes of this exercise, you have observed or been informed of the fallowins. MESSAGE: THIS IS A DRILL AN EXPLOSION IS REPORTED IN THE VICINITY OF CONTAINMENT PURGE VALVES. O R00 DRIVE ROCH.
-~ ~~' STEAM 15 REPORTED ESCAPING FROM THE THIS IS A DRILL ADDITIONAL INFORMATION:
O
< s
PLANI SIAIUS NORTH ANNA POWER STATION m s:ction 1/N
$0 4 ~ M A R Y' S Y S T E M REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH S/5 F HOTTEST TC S/S F LOOP 81 AT d F LOOP "2 AT O F LOOP "3 AT d F PRESSURE //O d PSIO PRESSURIZER LEVEL O %
REACTOR COOLANT UMP A: A. R 00C B: A. @ 00C C: A, @ 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 62O F MARGIN TO SATURATION Ch A - 90 F Ch 8 - 9'd F SOURCE RANGE COUNTS N 31 '- 72O N 32 - 72.O INTERMEDIATE RANGE AMPS N 35 - < /. 0 .x /0 "// N 3G - < /, o x /0 * # CONTAINMENT TEMP. yg F PRESS. /df. PSIA SUMP LEVEL /dd N SECONDARY SYSTEM STEAM OENERATOR sLEVEL) A 9'S X B V'5 % C V5 % AUX. FEE 0 WATER AUX. FEED FLOW Jgd (GPM) 1-CN-TK-2 LEVEL 37 % e) 3A A, b 00C 38: A. h 00C FW-P-2 [ 'dINEEREDSAFEGUARDS-RWST 98 6 StFLOW h 78 (GPM) HHS! A:OR, 00C_ B: A $ 00C C: A. @ 00C OSRS As @ R, 00C g, _ A, R, 00C LHS! A: A 8 00C _B: h (9 00C _ ISRS A: A R, 00C B: A. R. 00C OS A: A,R/6dD_8: A,R/D09 (4,rfg f,, @ c,w p 7- - ELECTRICAL O!STRIBUTION s,
'3 , g g _ [ g og EMERGENCY BUS (SUPPLY)
F@ DIESEL, DEAD, BACKFEED J h DIESEL, OEAO, BACKFEED EMERGEN Y O!ESEL GENERATOR (EDG) H: OP, ,00C J:O g ,00C RESERV STATION SERVICE As _HO DEAD B @ / DEAD C @ DEAD HIGH RANGE EFFLUENT RA0 MONITORS VENT VENT PRQCESS VENT MAIN STEAM A B C REMARKS m_. LEGENO: HHS! - HIGH HEAD S.I. OSRS - OUTS!DE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Availabin, R Running. 00C s Cua of Commission)
PLANT STATUS
.- NORTH ANNA POWER STATION NAEE Saction 10 /MI Pcg2 51 of 190VNIT L 10-10-84 PRIMARY
- SYSTEM (D REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST THS#tf F HOTTEST TC 500 F LOOP"1 AT O F LOOP "2 AT o F LOOP "3 AT a F PRESSURE /O S*O PSIG PRESSURIZER LEVEL O %
REACTOR COOLANT PUMP A: A. 4 00C 8: A. F'O 00C C: A. (19 OOC CORE PARAMETERS CORE EXIT THERM 0 COUPLE 805 F MARGIN TO SATURATION Ch A - </ 7 F Ch 8 - F7 F SOURCE RANGE COUNTS N 31 '- 7/O N 32 - '7/ 8 INTERMEDIATE RANGE AMPS N 35 - < /,0 x /0"# N 36 - < /, O x /p * # CONTAINMENT TEHP. ] g.7 F, PRESS. /84 PSIA SUMP LEVEL /00 N SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 6? % B .G % C N % AUX. FEE 0 WATER AUX. FEED FLOW 9/)8 (GPM) 1-CN-TK-2 LEVEL J3 % O 3As A. $ 00C 38: A, /O 00C FW-P-2 8 C 3!NEERED SAFEGUARDS - RWST Nk S! FLOW 4 9 2m (GPM) HHS! A:6 R. 00C B: A8 00C C: A/9 00C OSRS A: A. R. 00C 8: A, R. 00C LHS! As. A.dD 00C B: 4 A 00C ISRS A: A. R. 00C 0 A. R. 00C 05 A A. R.dD B: A, RM Gvc/a 4 yi - ELECTRICAL O!STRIBUTION C d s.s q ' f$ g jfg 4 g , pgy r. EM R NCY BUS (SUPPLY) H: O!ESEL, DEAD, BACKFEED M OIESEL, OEAD, BACKFEED EMERGENCY O!ESEL OENERATOR (EDG) H: OP @,00C J:OP h ,00C
- RESERVE STATION SERVICE A @ DEAD B6IUDDEAD CdD/ DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT '
PRQCESS VENT , HAIN STEAM A B C REMARKS d V - LEGENO: HMS! - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A s Available, R s Running, 00C = Out of Commission)
PLANI SIAlUS NORTH ANNA POWER STATION NAEE S:ction 10 Pega 52 of 190 UNIT E 10-10-84 A IMARY' SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH Ff/F HOTTEST TC W7 F LOOP =1 AT .3 F LOOP "2 AT 3 F LOOP "3 AT 3 F PRESSURE /O.2 S PSIG PRESSURIZER LEVEL d % REACTOR COOLANT PUMP A: A. /D 00C B: A. $ 00C C: A. N 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE Y88 F MARGIN TO SATURATION Ch A - (f,3 F Ch 8 - 63 F SOURCE RANGE COUNTS N 31 '- 74O N 32 - 70C INTERMEDIATE RANGE AMPS N 35 - 4 /. 0 A /0 ~ ## N 36 - 4 /, o x /0 ~// CONTAINMENT TEMP. .Q Og F PRESS. /f,f PSIA SUMP LEVEL /dd N SECONDARY SYSTEM STEAM GENERATOR (LEVEL) . a C3 x B C,3 x C O x AUX. FEEDWATER AUX. FEED FLOW C (GPM) 1-CN-TK-2 LEVEL J2_% 7f 3A A. @ 00C 38: A,
@ 00C FW-P-2 [ ' d INEERED SAFEGUARDS - RW T 73 % SIFLOW @88 (GPM)
HHS! Ar/9 R. 00C B: A. .00C C: A/9 00C OSRS A: A, R, 00C B: A, R, 00C
~
LHS! A:A @ 00C B:_A. 6 00C ISRS A: A. R. 00C B: A. R. 00C OS A: A, R,6C') . B: 'A. R,t1%Q CAS/Sfr- Cosud(r _
^'
ELECTRICAL DISTRIBUTION / sci ~ps A r'd _A , A', 00 C' EMERGENCY BUS (SUPPLY) H:8 DIESEL, DEAD, BACKFEED J M DIESEL', DEAD, BACKr*EED EMERGENCY DIESEL GENERATOR (EDG) H: OP, M 00C J:O M ,00C
, RESERV2 TATION SERVICE As EA0 BM/0EAD C(1Dy0EAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS LEGEND: HHS! - HIGH HEAD S.I. DSRS - CUTSIDE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A : Available, R Running, 00C = Out of Commission)
rt.nni oinivo NORTH ANNA POWER STATION NAEE Ssetion 10 $ Paga 53 of 19(1) NIT b 10-10-84 PRIMARY' SYSTEM
/m. (T = Temperature)- HOTTEST TH fggF HOTTEST TC WI F U,REACTORCOOLANTSYSTEM LOOPal AT / F LOOP "2 AT / F LOOP =3 AT '/ F PRESSURE /025 PSIG PRESSURIZER LEVEL d %
REACTOR COOLANT PUMP A: A. (#li) 00C 8: A. @ 00C C: A. h 00C_, CORE PARAMETERS l CORE EXIT THERMOCOUPLE 78 F l
' MARGIN TO SATURATION Ch A - 75 F Ch B - 78 F SOURCE RANGE COUNTS N 31 '- 786 N 32 - 705 INTERMEDIATE RANGE AMPS N 35 -< /, o y /a ~ ' ' N 36 - < /, /> .y /0 ~" l CONTAINMENT TEMP. ]gg F PRESS. /7 PSIA SUMP LEVEL /88 N SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
A $S X B $3 % C $5 % AUX. FEEDWATER AUX. FEED FLOW C (GPM) 1-CN-TK-2 LEVEL _ 3 3 % 3A A. N 00C 3B: A, /fC 00C FW-P-2 A OINEEREDSAFEGUARDS-RWST 7/ SIFLOW h97 (GPM) HHS! And? R. 00C B: A. 6 00C C: A/T) 00C OSRS As A. R, 00C g: A. R. 00C LHS! A:,~A. AD 00C 8 , A dD 00C ISRS A: A. R. 00C B: A. R. 00C OS A A,R,66D 8: A, R,@C) CM/w fe Gouc q. g - _
^
ELECTRICAL DISTRIBUTION "/Jegs Wg- pf; SO6 EMERGENCY BUS (SUPPLY) H @ OlESEL, DEAD, BACXFEED Jg DIESEL, DEAD, BACkFEED l EMERGEN DIESEL GENERATOR (EDG) f H: OP, ,00C J: OP ,00C l RESERVE STATION SERVICE
- Ai O / DEAD B h / DEAD CN/ DEAD HIGH RANGE EFFLUENT RAD MONITORS l VENT VENT '
l PROCESS VENT MAIN STEAM A B C REMARKS ' i
~
.O i LEGENO: HHS! - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A s Avatleble, R Running, 00C Out of Commission)
PLANT STATUS NORTH ANNA POWER STATION ke !$ o $9k C 10-10-84 UNIT 91 MARY' SYSTEM 4 hREACTORCOOLANTSYSTEM (T = Temperature)- HOTTEST TH N0*F HOTTEST TC f(D F _ LOOP =1 AT C F LOOP "2 AT C F LOOP "3 AT C F PRESSURE 9BO PSIG PRESSURIZER LEVEL /5' % REACTOR COOLANT PUMP A: A. (D 00C B: A. @ 00C C: A, 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE WS F I MARGIN TO SATURATION Ch A - 67 F Ch B - 87 F_ SOURCE RANGE COUNTS N 31 '- 69b N 32 - 87O INTERMEDIATE RANGE AMPS N 35 < /,0 x /o N 36 - < /, O x /o -" CONTAINMENT TEMP. / F PRESS.
/7 PSIA SUMP LEVEL /dd N SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
A 8 ?---- % B 6 ~2._. -
% C %
O AUX. FEEDWATER AUX. ' FEED FLOW (GPM) 1-CN-TK-2 LEVEL 37% 3A: A, h 00C 38: A,
@ 00C FW-P-2 A ,
htGINEERED SAFEGUARDS - RWST i d (( SI FLOW MOf (GPM) HHSI A@R 00C B: A800C C: A S 00C OSRS As A R, 00C ~ B: A, R, 00C LHSI Ar A dD 00C B: ' A.19 00C ISRS A A. R. 00C B: A. R. 00C OS A: A, R, @ B: A. R, gtD C4S/,9 f- d*0cuwf r/ - ELECTRICAL DISTRIBUTION "
"/ ggg-g g opp ~ '
EME NCY BUS (SUPPLY) H DIESEL, DEAD, BACKFEED Jh DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OP,6. 00C J: OPM,00C
< RESERVE STATION SERVICE AM/ DEAD B @ DEAD C(TIODOEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS
- O LEGEN0: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI~ ' LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION . SERVICE
_ _ _ _ _ . Rt n - F fPa n aaenn)_. _ _ _ . _ . . _ _ _ . _ _
PLANT STATUS NORTH ANNA POWER STATIONNAEE Section 10 O/I Page 55 of 190 UNIT L 10-10-84 ' e'Ti! MARY' SYSTEM
/
C REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH /SfF HOTTEST TC 955 F LOOP"I AT C F LOOP "2 AT o F LOOP "3 AT o F PRESSURE 930 PSIG PRESSURIZER LEVEL S4 % l REACTOR COOLANT PUMP A: A, S 00C 8: A. @ 00C C: A, $ 00C CORE PARAMETERS . CORE EXIT THERMOCOUPLE #gO F l MARGIN TO SATURATION Ch A - 74 F Ch 8 - 7g F SOURCE RANGE COUNTS N 31 '- 8 78 N 32 - 8 7d INTERMEDIATE RANGE AMPS N 35 - < /. O x /0 '# N 36 - < /, o X /o -## CONTAINMENT TEMP. / 3 F PRESS. /7 PSIA SUMP LEVEL /08 SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 40 % B 60 % C 60 % O V1
~
AUX. FEEDWATER AUX. FEED FLOW (GPM) 1-CN-TK-2 LEVEL % 3A: A, 00C 38: A,
@ 00C FV-P-2 9NGINEERED SAFEGUARDS 27 5 - RWST SIFLOW 684- (GPM)
HHSI A/K)R. 00C B: A 8 00C C: A $ 00C OSRS.A A, R, 00C 8: A. R, 00C LHSI A. A AD 00C B: A /@ 00C ISRS A: A. R, 00C B: A. R. 00C OS A: A, R,(603 B: A. R,$UF) CA S M f Coo u y 74 - ELECTRICAL DISTRIBUTION s "A 4 /g- g g dM EMERGENCY BUS (SUPPLY) H:@ DIESEL, DEAD, BACKFEED Jh DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H:OP, h 00C J:O h ,00C RESERVE STATION SERVICE A:<A6I> DEAD B@/ DEAD C h 0EAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT , PROCESS VENT MAIN STEAM A B C REMARKS i m LEGEND: HHSI - HIGH HEAD S.I. OSRS - QUTSIDE RECIRC. SPRAY l LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - CUENCH SPRAY RSS - RESERVE STATION SERVICE l _ _ _ _ _ ~
PLANI STAIUS NORTH ANNA POWER STATION NAEE Section 10 3d Page 56 of 190 UNIT 2' ' 10-10-84 j
/~
lkj!! MARY' REACTORSYSTEM COOLANT SYSTEM (T = Temperature)- HOTTEST TH VS# F HOTTEST TC VM F , LOOP *I oT C F LOOP "2 AT d F LOOP '3 AT o F 1 PRESSURE /00 0 PSIG PRESSURIZER LEVEL KS' % REACTOR COOLANT PUMP ! A: A. $ 00C B: A, $ 00C C: A, @ 00C CORE PARAMETERS l ! CORE EXIT THERMOCOUPLE 9M F l MARGIN TO SATURATION Ch A - 9J F Ch 8 - 9J F l SOURCE RANGE COUNTS N 31 '- 870 N 32 - 870 l INTERMEDIATE RANGE AMPS N 35 - </. O x /O'# N 36 - < /, O x /0 ~# < l CONTAINMENT TEMP. /f[ F PRESS. [5 PSIA SUMP LEVEL /6O , l SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 80 % B TO % C Sd % AUX. FEEDWATER AUX. FEED FLOW O (GPM) 1-CN-TK-2 LEVEL SC % c 3A: A. b 00C 38: A, M 00C FW-P-2 [ GINEERED SAFEGUARDS - RWST ,95'[ SI FLOW 860 (GPM) HHSI A:hR, 00C B: _A 4 00C C: A/II) 00C
~
OSRS A: A R. 00C B: A. R. 00C LHSI A:' A. /0 00C B: A @ 00C ISRS A: A R. 00C B: A. R. 00C OS A: A, @ 00C B: A. R,(COC2 g ,4 g % g,,4,p f4 - ELECTRICAL DISTRIBUTION - "g gg_ 4 4 g4 EMERGENCY BUS (SUPPLY) Hh DIESEL. DEAD, BACKFEED J@ DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OP@,00C J: OP.h. 00C
< RESERVE STATION SERVICE A N DEAD h /0EAD C M OEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS (D %_J LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE em h_h,nmnavs 1
NAEE Section 10 Page 57 of 190 10-10-84 O SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: OPS-17 EMERGENCY EXERCISE NOVEMBER 15. 1984 TO: SHIFT SUPERVISOR TIME: 1930 For the purposes of this exercise, you have observed or been informed of the following. , MESSAGE: THIS IS A DRILL CONTAINMENT DEPRESSURIZATION EQUIPMENT OPERABLE.
~
i b i l l THIS IS~A DRILL l. l l
. ADDITIONAL INFORMATION:
i l l 1 i
PLHNI blHlus NORTH ANNA POWER STATION NAEE Section 10 NII Paga 58 of 190 UNIT b 10-10-84 PRIMARY ~ SYSTEM (T = Temperature) - HOTTEST TH380 F HOTTEST. TC J'IS* F OREACTOR LOOP"1 AT COOLANT S SYSTEM F LOOP "2 AT S F LOOP "3 AT S F PRESSURE //OO PSIG PRESSURIZER LEVEL (2 % REACTOR COOLANT PUMP A: A. (T) 00C 8: A. $ 00C C: A. M 00C CORE PARAMETERS CORE. EXIT THERMOCOUPLE J75 F MARGIN TO SATURATION Ch A - / 7/ F Ch 8 - /7/ F SOURCE RANGE COUNTS N 31 '- 47C N 32 - 67d INTERMEDIATE RANGE AMPS N 35 -(/, /> a /o ~# N 3,6 - < /. C .y /O # CONTAINMENT TEMP. //g F PRESS, /9'. 8 PSIA SUMP LEVEL /86 i SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 30 % B 30 % C 3d 2 i AUX. FEEDWATER AUX. FEED FLOW 860 (GPM) 1-CN-TK-2 LEVEL $$ % 3A: A, O 00C 38: A, M 00C FW-P-2 N
.n 79 h SI FLOW 978 (GPM)
VINEERED SAFEGUARDS - RWST HHSI A: 8/ , ROdC 8: A 8 00C ~ C: A S OOC OSRS A: A. R. 00C 8: A. R, 00C LHSI A 4. @ 00C B: A,@ 00C ISRS A A. R. 00C B: A. R. 00C OS A: A./@ 00C B: A. R,/8 C/ffsv g @cfs,g 74. - _ ELECTRICAL DISTRIBUTION "A gy& 4,# OdC/ EMERGENCY BUS (SUPPLY) Hh DIESEL, DEAD, BACKFEED J M DIESEL, DEAD, BACKFEED EMERGENCY DIESEL- GENERATOR (EDG) H:OP h 00C J:OP h 00C i RESERVE STATION SERVICE L A:M EAQ B M EAD ( M DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT YENT , l PRCCESS VENT l MAIN STEAM A B C REMARKS LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY [ OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Avatleble, R = Running. 00C = Out of Commission)
7-NAEE Section 10 Page 59 of 190 10-10-84 O SCENARIO MESSAGE NORTH ANNA POWER STATION NO.: ops-18 EMERGENCY EXERCISE NOVEMBER 15, 1984 TO: snTvm stiprnvison TIME: 2000 For the purposes of this exercise, you have observed or been informed of the
-following.
MESSAGE: THIS IS A DRILL
- CONTAINMENT PRESSURE IS SUB-ATMOSPHERIC.
- RECOVERY PHASE BEGINS.
6 THIS IS A DRILL ADDITIONAL INFORMATION: O .
I r I" L N 11 8 OIMiUO NORTH ANNA POWER STATION NAEE Section .10 , Page 60 of 190 UNIT A ! 10-10-84 i
! MARY' SYSTEM
! [Q REACTORf COOLANT i F LOOP "2 AT SYSTEM (T = Temperot.ure)- HOTTEST TH3ra F HOTTEST TCJ7F F S F LOOP "3 AT S F l' LOOP?! AT l PRESSURE //00 PSIG PRESSURIZER LEVEL g7 % REACTOR COOLANT PUMP A A, fiQ 00C. B: A. g 00C C: A, 8 00C l CORE PARAMETERS CORE EXIT THERMOCOUPLE Jfg F MARGIN TO SATURATION Ch A - / 7/ F Ch 8 - / 7/ F f SOURCE RANGE COUNTS N 31 ' - 870 'N 32 - 8'70 l INTERMEDIATE RANGE AMPS N 35 - < /, o x /o*# N 36 - < /. o x /0 ~ # l CONTAINMENT TEMP. //6 F PRESS.
/</,5 PSIA SUMP LEVEL /00 N SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
A k8 %B k8 % C b % AUX. FEEDWATER AUX. FEED FLOW /SO (GPM) 1-CN-TK-2 LEVEL 67 % 3A: 'A, [ 00C 38: A, j 00C FW-P-2 dGINEERED SAFEGUARDS - RWST 79 % SIFLOW 4'7f (GPM) HHSI- A:/$ R. 00C B: A.(79 00C C: A,71900C OSRS A: A, R, 00C B: A. R. 00C LHSI . A:7tO R. 00C B: 69 R. 00C_ ISRS A: A. R. 00C B: A. R. 00C OS A:M) R. 00C 8: A, R,(TOI/ JG - ELECTRICAL DISTRIBUTION CfSMf Daudfr-A , p g g A A P; O O G e i l ! EMERGENCY BUS (SUPPLY) ) H:@ DIESEL, DEAD, BACKFEED J DIESEL. DEAD, BACKFEED l EMERGENCY DIESEL GENERATOR (EDG) H:OP M ,00C J:OP g 00C RESERVE TATION SERVICE l A: T EAD B: h 0EAD C[/ DEAD j HIGH ' RANGE EFFLUENT RAD MONITORS ) t . VENT VENT PROCESS VENT l l MAIN STEAM A B C l REMARKS l l LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE ML=Amilable.] = Runn:Ra. 00C = OuCM CemmaesnonL._ ___.__
NAEE Section 10 Page 61 of 190 in in_96 , i o o N f o o o N o o
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