ML18029A240

Radiological Emergency Preparedness Exercise.

ML18029A240
Person / Time
Site:	Browns Ferry
Issue date:	10/24/1984
From:	ALABAMA, STATE OF, TENNESSEE VALLEY AUTHORITY
To:
References
NUDOCS 8411080307
Download: ML18029A240 (270)

Text

BROMNS FERRY NUCLEAR PLANT RADIOLOGICAL EMERGENCY PREPAREDNESS EXERCISE OCTOBER 24, 1984 Principally Prepared By:

(

Browns Ferry Plant Staff, TVA Office of Nuclear Power, TVA Radiological Health Staff, TVA Office of Engineering, TVA Alabama Emergency Management Agency (AEMA)

Alabama Department of Public Health 84ii080307 84f024 PDR ADOCK 05000259 F PDR

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BRONNS FERRY NUCLEAR PLANT (BFN) SCENARIO BFN EXERCISE SCENARIO FORMAT I. Objectives II. Dates, Time Period, Place, and Participating Organizations III. Simulated Events Initiating the Postulated Emergency Conditions IV. Time Schedule of Simulated Initiating Event V. Narrative Summary VI. Plant Parameter Sheets and Control Room Messages ATTACHMENTS

1. Exercise direction and observation

2. Radiological releases for observers

3. Observer/controller critique worksheets

4. Meteorological data summary

K I. OBJECTIVES The exercise is planned to demonstrate the capabilities of TVA to fulfillits responsibilities specified in the BFN Radiological Emergency Plan (REP). The following objectives indicate the types of activities planned by TVA.

A. Test the REP notification procedure throughout the notification chain, beginning at the BFN control room and extending to State authorities and to local authorities.

B. Demonstrate BFN's ability to respond to hazardous radiological conditions onsite, i.e., postaccident sampling, HP response, assembly and accountability of nonessential plant personnel, etc.

C. Demonstrate the staffing and efficient operation .of TVA emergency centers.

D. Test the communications networks among TVA, State, and local governments and with other support groups.

E. Activate the Near Site Media Center and demonstrate the capability for periodic public information releases by TVA.

F. Demonstrate the capability of TVA to assemble and transmit in a timely manner the appropriate information needed by offsite authorities to evaluate the necessity for protective actions.

G. Demonstrate the capability to perform accident assessments and the protective action decisionmaking process based upon meteoro-logical conditions, plant radiological release information, and/or plant conditions.

H. Demonstrate the capability to verify offsite predicted doses by radiological field monitoring.

I. Demonstrate the plant's ability to identify and classify emergency classes based on EALs and initiating conditions.

II. Dates, Time Period, Places, and Participating Organizations The exercise will be initiated from the BFN main control room at 0730 (CDT) on October 24, 1984. The exercise will extend over approximately 6 hours. The exercise will initiate at BFN and ini-tially involve the onsite,and offsite TVA emergency organizations.

This is a small scale exercise so the State of Alabama and risk counties will be limited in their level of participation. The TVA onsite and offsite emergency organizations will complete their participation when their objectives are satisfied.

Those par ticipating in the exercise may include, but are not limited to, the following:

A. Browns Ferry Nuclear Plant, Decatur, Alabama B. Tennessee Valley Authority, Muscle Shoals, Alabama, Chattanooga, and Knoxville, Tennessee

0 C. Alabama Emergency Management Agency (TEMA), Montgomery, Alabama, and other State agencies D. Alabama Department of Public Health, Montgomery, Alabama E. Lawrence County Government, Moulton, Alabama F. Limestone County Government, Athens, Alabama G. Morgan County Government;, Decatur, Alabama H. Lauderdale County Gove. nment, Florence, Alabama I.. Tri-County District Health Services J. National Weather Service K. Federal Emergency Management Agency (FEMA)

'L. Nuclear Regulatory Commission (NRC) and other Federal Agencies III. Simulated Events Initiating the Postulated Emergency Conditions The scenario postulates these situations.

A. Fire alarms are received from the area of the unit 1 RBCCW heat

/

exchangers (a vital area). An ALERT is declared. The fire brigade is dispatched to extinguish the fire and brings it under control'within hour. Heavy smoke remains and hampers 1 cleanup operations.

B. A second event postulates a reflash of the fire in a floor penetration between elevations 593 and 621.5. Extremely dense smoke fills elevation 593 and 621.5. The fire reaches cable trays near the peneti ation and causes power loss to RPS MG Set A; half-scram, half-isolation of the MSIUs, isolation of the secondary containment, and startup of SBGTS ensue.

C. A third event postulates the loss of RPS MG Set B causing the reactor to scram and isolation of containment isolation groups 1, 2, 3, 6, and 8. The resultant pressure transient causes damage to the fuel rods and also causes the pa'cking of RNCU outboard valve 1-FCV-69-2 to blow out. A SITE AREA EMERGENCY is declared.

D. The -last event postulates a stack release because of radioactive steam from the damaged RHCU valve flowing through faulty SBGT systems to the stack. The release continues for about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

E. The exercise ends when maintenance crews provide power to the faulty valve and terminate the leak by closing the valve.

IV. Time Schedule of Simulated Initiating Events NOTE: The plant operators will be given the messages and plant parameter sheets at the times indicated on them. (Note: The exact times may vary slightly depending on actual response times. The controller will determine where these variances are appropriate.) The plant parameters were obtained at the BFN simulator at TVA's Power Operations Training Center. -The emergency staff actions indicated below are those expected and are provided for critiquers and controller s. Exercise con-trollers in the control room will record operator actions taken that were not expected and provide necessary input to assure the exercise takes the planned course.

(ALL TIMES CST) 0715 T = -15 minutes Initial Conditio s for BFN Units 1 2 and 3 BFN-1 -. Full power operations toward end of fuel cycle.

BFN-2 - Refueling outage. Maintenance items being performed involve pulling a cable from 4-kv shutdown board 1A through the floor penetration between elevations 593 and 621.5. Fire watch posted during the breach of the fire stop.

BFN-3 - Fifty-eight percent power, increasing from a short outage.

0730 T = 0 minutes Drill begins with fire being reported from the vicinity of the unit 1 RBCCW heat exchangers on elevation 593.

Fire brigade is dispatched to the fire area.

0 0735 T = 5 minutes Dense smoke in the Reactor Building. The source of the smoke is a fire in the unit 1 RBCCM heat exchanger area, elevation 593. Fire brigade begins operations to extinguish fire.

0740 T = 10 minutes Fire brigade reports that th'e source of the fire appears to be a large trash pile in the RBCCN heat exchanger area, elevation 593. Fire is fully developed and is threatening overhead cable trays.

ALERT hould be declared based on a fire threatening a vital area.

0750 T = 20 minutes Trash fire has been knocked down and is being brought under control.

0800 T = 30 minutes Heavy smoke reported throughout elevation 593 and some smoke present at other elevations.

0830 T = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Fire reported out. Heavy smoke hampering efforts to cleanup fire area on elevation 593.

All unit 1 equipment operable.

0900 T = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Heavy smoke still present on elevations 593 and 30 minutes 621.5. Smoke also reported on other elevations to L

a lesser extent.

0930 T = 2 hours Smoke clearing on all elevations. Cleanup

operations star ting.

Operators requested to verify all equipment operable because of concern of potential damage to cables.

1000 T = 2 hours Fire reflashes in cable tray penetrations between 30 minutes elevations 593 and 621.5.

Smoke reported to be getting denser.

1015 T = 2 hours RPS bus 1A lost. Half-scram, half-isolation occur.

45 minutes Secondary containment isolates. Standby gas treatment system starts.

RPS buses - RP 1390 and RP 1365 cables are affected.

ASE sent to transfer RPS bus 1A to backup power supply.

1020 T = 2 hours RPS bus 1B lost. Power to 1-FCV-69-1 lost and 50 minutes valve remaining in open position. Reactor scrams 1

and MSIVs isolate. Groups>2, 3; 6, and 8 isolate.

It is postulated at this time that the pressure transient causes extensive fuel damage and also the packing on 1-FCV-69-2 to blow out. MSRVs cycle.

Torus radiation monitors alarm.

1027 T = 2 hours SITE AREA EMERGENCY should be declared based on a 1

57 minutes ma)or fire affecting vital systems and LOCA.

0 0

Heavy smoke still present on elevations 593 and 621.5.

Radiation monitors on elevation 593 alarm.

HPCI and RCIC start on level 2. CRD still providing flow.

1030 T = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Radiation monitoring. teams sent- into the reactor building to determine source of radiation.

Fire brigade may have to be temporarily evacuated because of potential radiation in area.

ASE reports from RPS MG Set 1A that he is having difficulty transferring set to backup power supply.

Switches 42TA and 42TB fail when transfer is attempted.

1040 T = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> RHR is initiated to decrease torus 10 minutes temperature.

Unit 1 reactor vessel water level stabilized; HPCI and RCIC secured. Level being maintained by CRD.

1045 T = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> MSIVs cannot be reopened, scram cannot be reset 15 minutes because of failed RPS bus power.

Stack radiation high; field team dispatched to

0 monitor releases.

ASE reports that he is not able to transfer power

. to RPS MG Set 1A. He is directed to attempt the transfer on Set 1B.

It is postulated that SBGTS filters degraded because of smoke and steam from the valve leak are not filtering the release.

1100 T = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, Source of high radiation verified to be in general 30 minutes 'icinity of 1-FCV-69-2.

Fire brigade successfully extinguished fire in cable penetration from above.

Plans are formulated to get power back to 1-FCV-69-1 by pulling,cable and splicing it into the burned cable.

RHR is secured, torus temperature normal.

1115 T = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Smoke in reactor building gradually clearing.

45 minutes Steam observed on elevation 593 near RMCU heat exchanger room door.

ASE may be dispatched to auxiliary instrument room to bypass isolation signal to 1-FCV-69-2 in an attempt to backseat the valve.

Stack radiation monitor s still high.

Unit 1 reactor water level stable on CBD flow.

1130 T = 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> AUO reports from BPS MG Set 1B that power has been transferred to backup source.

Scram is reset and groups 1, 2, 3, 6, and 8 isolation r eset.

Operator opens 1-FCV-69-2 in order to backseat valve, leakage is reduced somewhat, but leak is continuing.

Condenser vacuum pumps started.

Stack radiation still high.

1200 T = 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Condenser vacuum reestablished. MSL drain valves 30 minutes opened to equalize pressure across MSIUs. MSIUs immediately isolate on group 1 MSL high radiation signal.

Stack radiation decreasing.

1230 T = 5 hours Stack radiation stable, still higher than normal.

Cable has been laid out to attempt to reenergize 1-FCV-69-1.

Reactor building essentially clear of smoke.

1315 T = 5 hours Cable spliced into position; 1-FCV-69-1 reenergized, 45 minutes and immediately closes because of isolation relay still deenergized.

1320 T = 5 hours Leak is isolated.

50 minutes 1325 T = 5 hours Reactor proceeding to cold shutdown for repairs of 55 minutes fire damage and 1-FCV-69-2 packing.

1330 T = 6 hours Drill terminated.

V. Narrative Summary The initial conditions at the plant assume that unit 1 is at full power operation toward the end of core life, unit 2 is shutdown for a refueling/maintenance outage, and unit 3 is on a power ramp at 58 percent. Part of the ongoing maintenance activities on unit 2 involves pulling cable from 4-kv shutdown board A through a floor penetration at elevation 621.5.

I

Fi.e alarms are received from the area of the unit 1 RBCCW heat exchangers. Smoke in that area is reported by maintenance crews.

P The plant fire brigade is dispatched. An ALERT is declar ed because of a fire threatening a vital area.

The fire brigade locates the fire and begins operations to extinguish it within 30 minutes. Heavy smoke is reported on elevation 593 around the RBCCW heat exchangers, and, to a lesser extent, on other elevations. Within 1 hour, the fire is reported out. Heavy smoke is still present, especially on elevation 593, and is hampering the cleanup operations. Approximately 1 hour 'later (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the fire started), the reactor building is relatively clear of smoke.

The fire is believed to have started in a trash pile.

A short time later,- the fire reflashes in the floor penetration between elevations 593 and 621.5 (the fi,re block had been removed in order to pull cable for unit 2 modifications). Extremely dense, black smoke fills elevations 593 and 621.5.

The fire, bur'ning in the cable trays in and around the open floor penetration, causes power to be lost to RPS MG Set 1A, resulting in a half-scram, a half-isolation of the MSIVs, isolation of the secondary containment (the unit 1 reactor zone and the common refueling zone), and startup of the SBGT system. To counteract the loss of power 'to the RPS Bus 1A, an auxiliary unit operator is dis-patched,to transfer RPS MG Set 1A to its alternate power supply.

Power to the RWCU inboard isolation valve 1-FCV-69-1 is also lost because of the fire.

Before the power to RPS Bus lA can be restor ed, the fire burns through the power cable to RPS MG Set 1B, causirg the reactor to scram, and causing the isolation of containment isolation groups 1, 2, 6, and 8. It is postulated that the pressure transient associated-with the MSIVs closing (group 1) results in fuel damage, and also causes the packing. of RhCU outboard isolation valve 1-FCV-69-2 to blow out resulting in primary system leakage. The unit 1 reactor safety systems respond as expected to the primary coolant leakage. The MSRVs cycle to relieve pressure, and HPCI and RCIC start on low reactor vessel water level (level 2) to restore normal water level in the vessel. A SITE AREA EMERGENCY is declared because of the fire's effect on vital equipment.

Radiation alarms sound in the vicinity of the RMCU outboard isolation valve because of the primary leakage from the valve. The radioactive steam is p'ked up by the SBQ. system. However, the SBGT filters are not working properly because of the degrading effect the steam has had on them; and all of the radioactive material is released out of the plant stack. Offsite monitoring teams are dispatched to track the release.

The AUO is unable to transfer RPS MG Set 1A to the alternate supply, but is successful in transferring RPS MG Set 1B to the alternate approximately 1 hour after the scram. This allows the scram and some of the isolation signals to be reset.. The MSIVs are momentarily opened in order to establish a path to the condenser; however, the highly contaminated reactor water .causes the MSIVs to reisolate on high steam line radiation. The unit operator opens 1-FCV-69-2 in

in an attempt to backseat the valve and thus reduce the leakage. The leakage does indeed decrease, but does not stop completely.

Maintenance crews successfuly pull cable around the damaged power cable of 1-FCV-69-1 and reestablish motive power to that valve. The valve closes immediately (its isolation relay is powered from RPS Bus 1A, which is still deenergized). This terminates the leak of reactor water outside containment. The reactor is then taken to cold shutdown without further incident.

VI. Plant Parameter Sheets/Control Room Messages These will be provided in the controller/observer package.

HBM:JLR 10/04/84 A1248A.JR

0 ATTACHMENT 1 EXERCISE DIRECTION AND OBSERVATION A. Exercise Direction and Guidance by Controllers:

1. Exercise Directcr Assignments/Locations

2. Directors Duties/Guidance

3. Controllers Assignments/Locations Controllers Duties/Guidance

5. Messages/Input - Directors/Controllers B. Exercise Observation and Criti.que/Observers:

1. Observers Assignments/Locations

2. Observers Duties/Guidance

3. Critique Reports/Exercise Areas of Concern

ATTACfPBNT 1 (cont'd)

A. Exercise Direction ard Guidance by Controllers

1. Exercise Directors Assignments/Location An exercise director, who principally ersures that the TVA emergency organization responds appropriately to the scenario events will be located at the CECC. He will prompt controllers as appropriate and resolve unforeseen situations, including coordination with designated state officials as appropriate if events occur that could potentia'ly alter the "course" of the exercise.

2. Directors Duties/Guidance Generally, the director will principally ensure that the exercise is kept moving and that any unexpected or unforeseen circumstances do not significantly change the "course" of the exercise. At principal locations, k controllers are to input data, answer inquiries, or direct/prompt participants that certain actions may be appropriate under their procedures. These prompts should be coordinated with the director as appropriate.

ATTACEHNT 1" (cont'd)

3. Controllers Ass'gnments/Locations Controllers are to input prescribed data into the exercise, answer appropriate inqu'ries as to the exercise scope, and to indicate if information is available for situations not addressed or in response to questions.

Certain controllers ar designated as controller/observers and are requested to note the participant's response of their use of data provided primarily after radiation monitoring and/or other tests are conducted.

Scenario input Data - Directors/Controllers Prescribed input is provided primarily for controllers to give to in-plant/offsite participants.

Director's input will be principally on policy matters on an ad hoc basis. The director may choose to clarify, limit, or restrict-certain controller data input as appropriate.

B. "=xercis Observation ard Critique/Observers

1. Observer Assignments/Locations (to be provided later)

2. Observer s Duties/Guidance An observer's duty is to observe participants and controllers as they function during this exercise. These observations and Judgments are recorded and reported as to strengths and weaknesses, together with recommendations for improvement.

Observers will be supplied with worksheets tha detail the areas on wnich they will provide comments as well as specific comments they may have.

3. Critique Reports/Exercise Areas of Concern Obser vers are expected to provide their worksheets to the WCO Rad'ological Emergency Preparedness Section as soon as possible after the post exer cise critiques.

Critique reports are expected within two weeks after the exercise completion. Specific deadlines and timeframes will be provided during the briefing sessions or by memo.

HBW:JLR 09/04/84 Ai248A.JR

ATTACHMENT 2 RADIOLOGICAL REL"ASES FOR OBSERVERS The time schedule of events indicates a continuous stack release with a duration of approximat ly 3 hours. The release begins approximately 3 hours after the exercise is initiated and results from radioactive steam passed .rom a faulty RMCU valve flowing through SBGT system (rendered ineffective). The release terminates when the faulty valve is corrected and primary containment integrity is reestablished. The release. rate for noble gases is 5 E+7 microcur ies per second.and for Icdine is 2 E+5 microcuries per second.

Heal time meteorological data will be used for this exercise. The dose rate values in the tables below are based on probable eteorological conditiohs as determined from a historical study of meteorological conditions for this time of year. The values 'can be scaled by the players or controllers to correct for varying wind speeds.

Total Body Dose Rates (rem/h3 Mind Speed 3 m/s 5 m/s 6 m/s Stability D Distance 1 mile 5.7 x 1O-5 1.4 x10 4 5.5 x 10"5 2 miles 1.3 x 10"3 3.3 x 1O-4 8.3 x 1O-4 5 miles 1.8 x 10"3 93x104 1.0 x 10-3 10 miles 1.3 x 10"3 9.0 x 10" 6.6 x 10-4

ATTACE<r.!'T 2 (cont'd)

Thyroid Dose Rates (rem/h)

Wind Speed 3 m/s 5 m/s 6 m/s Stability D D Distance 1 mile 1.9x 10 2 4.7x 10 2 1.8x102 2 miles 2 x 10-1 1.1 x10 1 2.7 x 10" 5 miles 0 x 10-1 3.1 x 10 3.3 x 10"1 10 miles 4.2x10 1 2.9 x 10-1 2.2 x 10-1 HBW JLR 09/04/84 A1248A. JR

ATTACHMENT 3 OBSERVER/CON'ROLLER CRITIQUE MORKSHEETS Observe s will be supplied with worksheets which will detail the areas on which observers are expected to supply comments. These worksheets will also have space for other comments which the observers may have. These worksheets will be i,ncluded in the final observer/controller package.

Controllers will be supplied with'he following worksheet which will enable them to document the control process that took place in the exercise.

HBW:JLR 09/04/84 A124 8A. JR

I 0

CONTROLLER i>ORKSHEET

]. Did you have to prompt any player(s) to take appropriate actions?

2. Did any players make suggestions which would have significantly itigated the emergency but which you had to disallow to keep the scenario on track?

3. Did any changes have to be made to the scenario during the exercise?

4. Comments:

HBM:JLR O9to4r84 A1248A .JR

ATTACHiKNT 4 METEOROLOGICAL DATA SU%SARY The meteorological data used during this exercise will be real time data.

An historical study of meteorological cata indicates that the most probable meteorological conditions for the exercise will be as follows.

A. Hns probable conditions for stack release (between 0700 and 1200):

Wind Speed 5 m/s Mind Direction SE, SSE, S (These sections account for about 30 percent of the winds.)

Stability class D (80-90 percent of time)

D. Mind speed frequencies:

~

MS < 2.5 m/s occurs 20 percent of time 2.5 < MS < 5.5 m/s occurs 45 percent of time MS > 5.5 m/s occurs 35 percent of time A meteorologist will provide real time meteorological data to the dose a sessment team and to the environmental coordinator. The environmental will direct u

coordinator envit onmental monitoring teams based on the real t me m teorological data. The monitoring teams will be provided data packages which were developed based on historical data. The environmental coordin'ator will decide if these data packages ar'e to be used. If the data packages are not used, the simulated dose values will be entered into the system by the environmental coordinator.

'M:

JLR 09/10/84 A1248A. JR

BROKERS FERRY NUCLEAR PLANT 1984 REP EXERCISE

/message For SHIFT ENGINEER Date: October"24, 1984 fimc T -15 minutes '715 Hessage: THIS IS A DRILL, INITIAL CONDITIONS:

U-1 Full power operations toward end of core life U-2 Refueling outage -'ire watch is posted in Reactor Building, Elevation 593 621.5 because of a fire stop being open to pull 4 KV electric cable from shutdown 1-A board through the floor penetration.

U-3 Fifty-eight percent power, increasing from a short outage

'l actual emergency.,occux'turing this drill, the Shift Engineer

~

NOTE: Should an may cancel the unit.

if drill he feels the drill will endanger the safety of the

~ ~

BRO'4'NS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: MAIN CONTROL ROOM CONTROLLER Date: October 24, 1984 Time: T=O 0730 Message: T}IIS IS A DRILL.

An ALERT should be declared due to fire threatening a vital area.

Controller should intervene only to keep the scenario on track. Some reasonable amount of time should be allowed for the Shift Engineer to recognize the emergency condition.

BR014NS FERRY NUCLEAR PLANT

}984 REP EXERCISE Message For: MAIN CONTROL ROOM CONTROLLER Date October 24, 1984 Time: T = 10 minutes 0740 Message: THIS IS A DRILL.

\

An ALERT should be declared due to fire threatening a vital area.

Some reasonable amount'of time should be allowed for the Shift Engineer to recognize the emergency condition.

• Controller should intervene only to keep the scenario on track.

~V 1

BROGANS FERRY NUCLEAR PLANT 1984 REP EXERCISE i'fessage For: SHIFT ENGINEER Date: October 24, 1984 Time: T=2 hours 45 minutes  : ~

1015 Nessage: TflIS IS A DRILL.

RPS Bus 1-A is lost (RPS Bus A under voltage)- half isolation occurs.

Secondary. containment isolates Standby Gas Treatment System initiates

1 BRO'RlS FERRY NUCLEAR PLANT 198li REP EXERCISE Message For: MAIN CONTROL ROOM CONTROLLER Date: October 24, 1984 VI Time: T= 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 45 minutes 1015 Message: THIS IS A DRILL. /

If Shift Engineer doesn't indicate that an AUO would be dispatched to transfer power from Bus 1-A to the backup power supply (480V shutdown board 1-B), the Shift Engineer should be told to do so at this time.

4 ~

BROGANS FERRY NUCLEAR PLANT l984 REP EXERCISE Message For: SHIFT ENGINEER Date: October 24, 1984 Time: T 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 50 minutes 1020 THIS IS h DRILL. 'essage:

RPS Bus l-B is lost Reactor scrams MSIV's isolate following annunciation- Main Steam "Hi radiation" Groups 1, 2, 3, 6, and 8 isolate I-FCV-69-1 fails to close MSRV's are cycling TORUS radiation alarms

0

BROWNS FERRY NUCLEAR PLANT 1984 REP EXERCISE Nessage For: SHIFT ENGINEER Date: October 24, 1984 Time: T= 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 57 minutes Hessage: "THIS,IS A DRILL.

Radiation monitors on elevation 593 are alarming HPCI and RCIC initiate,'RD is still providing flow High temperature in RWCU room

BROWilS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: MAIN CONTROL ROOM CONTROLLER/ TSC CONTROLLER Date: October 24, 1984 Time: T= 2 hours 57 minutes 1027 Message: THIS IS A DRILL.

Site Emergency Director should declare a Site Area Emergency based on a major fire affecting vital systems (both buses of RPS lost and LOCA)

+Controller will intervene only to keep the scenario on track. Some reasonable amount of time should be allowed for the Site Emergency Director to recognize the condition.

BROWNS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For'HIFT ENGINEER Date: October 24, 1984 T= 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 1030 Message: THIS IS A DRILL.

AUO is having problems transfering emergency RPS backup power to Bus 1-A .

Switches 42TA (Bus A) and 42TB (Bus B) in battery board 1, panel 9 failed.

RWCU room floor drain annunciation- "Hi Temperature" RWCU room temperature annunciation- "Hi Temperature" Air particulate radiation monitor 90-55 (elevation 593) alarms "Hi"

H BROMNS FERRY NUCLEAR PLAiNT 1984 REP EXERCISE Message For: SHIFT ENGINEER Date: October 24, 1984 Time: T=3 hours 1030 Message: THIS IS A DRILL.

As MSRV's are cycled, ARM's on elevation 519 alarm ARM numbers; '1 RE- 90-29 1 RE- 90-24 1 RE- 90-25 1 RE- 90-26 1 RE- 90-,27

BROGANS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: SHIFT ENGINEER 1

Date: October 24, 1984 Time: T= 3 hours 5 minutes 1035 Message: THIS IS A DRILL..

ARM 1 RE-90-14 on 593 elevation alarms along with CAM 1 RE-90-55 on the 593 elevation.

l3RO'MNS FERRY NUCLEAR PLANT 1984 REP EXERCISE Hessage For: SHIFT ENGINEER Date: October 24, 1984 Time: T= 3 hours 10 minutes 1040 i'lessage: THIS IS A DRILL.

HPCI and RCIC are secured Reactor water level is being maintained by CRD flow MSIV's cannot be reopenned and scram cannot be reset due to the failed RPS buses h

BROGANS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: MAIN CONTROL ROOM CONTROLLER Date: October 24, 1984 r

T= 3 hours 10 minutes 1040 Message: THIS IS A DRILL.

RHR should be initiated to decrease rising TORUS temperature (100 degrees).

• If the Shift Engineer does not elect to do this, he should be prompted in order to support the scenario.

r>> L u

BROI4NS I'El<RY NIICI FAR PLANT 1984.REP EXERCISE Ilessage For: SHIFT ENGINEER 1)ate: October 24, 1984 I II

'I'me: T 3 hours 15 minutes 1045 Hessage: TIIIS IS A I)RII.L.

AUO reports that he cannot get power to RPS bus 1-A but will attempt to energize bus 1-8 by energizing the transfer switch.

Stack radiation release monitors alarm. an 3 E+6 Cps

c BROlJNS FERRY NUCLEAR PLANT 1984 REP EXERCISE Hessage For: TSC CONTROLLER Date: October 24, 1984

'I'ime: T= 3 hours 15 minutes 1045 Hessage: TllIS IS A DRILL.

Stack radiation is high. It is postulated that SBGTS filters have been de-graded due to the smoke, steam, and moisture affect on charcoal beds. SBGTS is not.filtering the releases.

• This information can be interjected if necessary.

II C ~ 4 BROWNS FERRX NUCLEAR PLANT 1984 REP EXERCISE message For: H P CONTROLLER/TSC CONTROLLER/MCR CONTROLLER Date: October 24, 1984 Time: T= 3 hours 30 minutes " 1100 lfessage: THIS,IS A DRILL..

If personnel enter the RWCU room to identify the source of the leak, they will determine that the steam and high radiation is in the general vicinity of the 1-FCV-69-2 valve.

.*If no one enters the RWCU room, the information should be provided to the Shift Engineer.

'I ~

~

~

HROWNS FERRY NUCLEAR PLANT 1984 REP EXERCISE Hessage For: TSC CONTROLLER Date: October 24, 1984 f Jme ' 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 30 m'inutes 1 100 Hessage:

is TIGRIS IS A DRILL.

~

Plans should be formulated to get power back to the 1-FCV-69-1 valve by pulling cable and splicing into the burned ones.

choosing some other option 15r-

BRO'tPilS FERRY NUCLEAR PLANT" 1984 REP EXERCISE Message or: SHIFT ENGINEER Date: ctober 24, 1984 Time: T= 3 hours minutes 1115 Message: THIS IS A D Radiation monitors for stack rema high Reactor water level is stable still b ng maintained by CRD

BROMNS FERRY NUCLEAR PLANT 198I'l REP EXERCISE Message For: SHIPT ENGINEER Date: October 24, 1984

'I'1mc: T = 4 hours 1130 Message: TllIS IS A DRILL..

AUO reports that RPS bus 1B is energized Scram reset Groups 1, 2, 3, 6, and 8 isolations are reset 1-PCV-69-2 is opened and backseated in an attempt to reduce leakage from the valve Condenser vacuum pumps started

Page 1 of 3 BFN - IPD BFN, XP-20 nt tach'nt A APl< L ( )99il Urait No. (/DO

~ara eter rstru en +a~e gLeei~dn Level (Accident) LI 3-62 (inches) 9-3 " 'eactor (Zero at top of fuel)

D. ywell Low Pressure PX 64-'9A or (Low range) XR-64<<159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)

Drywell Hide Range . ': PZ-64-160A or Pres ure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen) a 9"3 ~

)30 Torus Mater Temperature TZ 64-55h ( F) (Units 2 3) 9"3 TR 64-161/162,(blue pen)

(Unit 1)

Torus Mater Level LI-64-1 59 A ( 0-20 ' 9-3 XR-64-159 pen 3 (0-240")

(Unit' only)

HPCZ Flow FXC 73-33 (&pm)

'IG RCXG Flow 71-36A (gpm) 9-3'-3 NRC/C RHR,Loop X Pressure PI 74<<51 (psig)

Rpt 81-19 RHR }.oop I Flow FX 74-50 (gpm)

- RHR Loop XZ Pressure . PX 74-65 (psig) 9-3 RHR Loop ZZ Flow .FZ 74-64 (gpm) 9-3 Core Spray Loop I Press. "

PX a

75-20 (psig) 9-.3 8<

I Flow I

Co. e Spray Loop FX 75-21 (gpm) 9-3 Core Spr ay Loop II Press PI 75-48 (psig) 9-3 Core Spray Loop XI Flow FX 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

III' Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics REP Communicator DNPEC (Telecopy)

'(Revision

t I'

Page 2 of' BFW - XP EFN, XP-20 Attachment Unit No.

(g Reactor Coolant Temp.

(Valid orDy if recirc.

TR 68-2 Loop A ( F) red

~30 pumps running) Loop B ( F) black Reactor Level (Accident) LX 3-46A (inches) 9-5 (Zero at inst. zero)

Reactor Pressure PX 3-54 (ps')

Reacto. Level (Normal) LX 3-53 (inches) 9-5 (Zero at inst. zer o)

(1)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 Torus H conc.

H2R 76-39 or 37 ($ ) . 9"54'5 (1) Torus 02 conc. ~

0 0 76-03 o a< (g) 9-54'5 3. P>o (1) Drywell H conc. or 37 ($ )

H2R 76-39 9-54> 55 (1) Dr ywell or 41 (g) 02 conc. 02R 76-43 9-5<, 55 .

(1) HS 76-49 and HS 76-59 must be checked to determine what recorder pens are active.

NPC/C Othe s ec f Rpt 81-19 E ui ment cerab t - Check the listed equipment for oper ability. Xf less than fully operable, explain in REMARKS.

g~uiment er b e Init +Lu,~ment ~e~ab~e Standby Liquid Control ADS/Relief Ulvs CRD Pumps SBGT Core Spray Control Room Emer. Press.

RHR (LPCX) CAD RHR (CTMT Cooling) Diesels (U1 U2)

HPCX Diesels (U3)

RCXC EECM 500 KV Po~er RHRSM 161 KV Power Feedwater System 0 KV System Condensate System 480 V System Primary Containment, DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer "Revi ion

~%

Page 3 of 3

~

BFti IPD BFN, IP-20 Attachment A APR 1 7 i"-8<

Unit Nn: Ti SBGTS Total Flow = FI 65 50 + FI - 65 - 71 (SCFM x1000) 9-25 I3 Drywell Radiation Unit 1 HR-90-272A (R/hr ) l,o Unit 1 HR-90-273A (R/hr ) 9-55 Urd.t 2 RR-90-272A (R/hr) 9-54 Unit 2 RR-90-273A (R/hr) 9-55 Unit 3 RR-90>>272A (R/hr) 9-54 O. p Unit 3 ,. RR-90-273A (R/hr), 9-55 Torus Radiation Unit 1 RR-90-2727 8 (R/hr) 9-54 5pQ Unit 1 HR-90-27370 (R/hr) 9-55 Unit 2 HR-90-272B (H/hr) 9~54 O Unit 2 RR-90-273B (R/hr) 9-55 c3 Urd.t 3 HR-90-272B (R/hr) 9-54 Urd.t 3 RR-90-273B (R/hr ) 9-55 Stack Radiation HR-90-147A (Cps) U-Z

>RC/C Stack Flow (Common - on Urd.t 1)

HR-90-147B (Cps)

FI-1-90-271 (cfm) 9 2 9 53 ~,. OG 1>>19 Remarks:

Ãi/0 x'/0

~ (@OS /~7~ 1//r2 After completion, hand carry. to secretary in hallway outside TSC for distribution.

'tribut Technical Assessment Manager Maintenance Manager Operations Manager REP Communicator NRC Commurd.cator .

Radiochemical Engineer Health Physics DHPEC (Telecopy)

'Revision

0 is Page 1'- of 3 BFV/ - XPD BFH, IP-20 A~tao nt; A APB r,7 '!}U'l Unit No. Tim oyer

~ada@'er ~nt r uttra one Reactor Level (Accident) LI 3-62 (inches) 93 ~ OO (Zero at top o fuel)

Drywell Low Pressure PI 64-39A or (Low range) /R-64-159 pen 2 (-5 to +5 psig} 9-3 (Unit 1 only)

Drywell Mido Range PX-64-160A or 9-3 Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only) 64-52 ( 0 F} (black pen}

Drywell Air Temperature Tor us Hater Temperature 'ITR 64-55A ( 0 F) (Units 2 3) 9-3 TR 64-161/162 (blue pcn) 9-3 (Unit 1)

Torus Mater Level LI-64-159A (0-20' < 9-3 XR-64-159 pen 3 (0-240")

(Unit 1 only)

HPCX Flow FIC 73-33 (gpm)

I RCIC Flow FXC 71-36A (gpm) 9-3 NRC/C RHR Loop I Pressure PI 74-51 (p rig)

Rpt 81-19 RHR Loop I Flow FX 74-50 (gpm) 9-3 RHR Loop II Prcssure PX 74-65 (psig) 9-3 RHR Loop II Flow FX 74-64 (gpm)

Core Spray Loop I Press. PX 75-20 (psig)

Cor'e Spray Loop I Flow FI 75-21 (gpm) 9-3 Core Spray Loop IX Press PX 75-48 (psig) 9-3 Core Spray Loop XX Flow =

FI 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.'is tribu takin Technical Assessment Manager 'iRC Communicator,'adiochemical Maintenance Manager Engineer Operatiorrs Manager . 'ealth Physics REP Communicator DHPEC (Telccopy)

'r Revisi on

ct ~

,~ ~ t of a

Page 2 3 BFle - XP BFN, IP-20 Attachment A

~APR 1 tggd Unit No.

Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9-4

(.Valid only if recirc.

F) black '-4 pumps running) Loop B (

Reactor Level (Accident) LI 3-46A (inches) 9-5 + 9o (Zero at inst. ero)

Reactor Pressure PX 3-54 (psia) 9-5 Reactor Level (Nor mal) LX 3-53 (inches) 9-5" (Zero at inst. zero) fr Condenser vacuum P/TR 2-2 (in Hg) black 9-6 @S (1 Torus H R 76-39 or 9-54f 55 ep H2 conc, 2 37 ($ )

(1) Torus  : 024 76-43 or 9-54f 55 02 conc. 41 ($ )

(1) Drywell H conc. H R 76-39 or 9-54 t 55 2

37 ($ )

(1) Drywell 0 conc.

2R 76-43 or 41 (5) 9-54r 55 3.7 /o (1) HS 76-49 and HS 76-59 must be checked to determine what recorder pens are active.

NRC/C +tl~ter s ea~f

" 81-19 gguug>mant~~arab It Check tha ltsted eqnlt>ment for operebtlttY. If less than fully operable, explain i'n REHARKS.

e ggnp~ran>t crab e Xn t ~Eu mant ~ca~be Standby Liquid Control ADS/Relief Vlvs CRD Pumps SBGT Core Spr ay Control Room Emer . Press.

RHR (J.PCX) CAD RHR (CTHT Cooling) Diesels (U1 U2)

HPCX Diesels (U3)

RCXC EECW 500 KV Power RHRSW 16'1 KV Power Feedwater System 4 KV System Condensate System 480 V System Primary Containment DC Power After completion, hand carry to.secretary,in hallway,outside TSC for I.~ .

distribution.

Technical Assessment Hanager Haintenance Hanger Operations Hanager REP NRC Communicator Communicator R=diochemical Engineer Health Physics DNPEC (Telecopy)

"Revision

< ~

Page 3 of 3 BFN IPD BFN) IP-20 Attachment A APA 17 1'-'84 Uni No. T',m: ~><~

l3 P

SHUTS Total Flow FI 65 - 50 + FI 65 - 71 (SCFM x1000) '9-25 Drywell Radiation Unit 1 RR-90-272A (R/hv) '9-5'i Unit 1 RR"90-273A (R/hv) .9-55 Unit 2 RR-90-272A (R/hr ) '-54 Unit 2 RR-90-273A (R/hr) 9-55 Unit 3 RR-90-272A (R/hr) 9-54 Unit 3 RR-90-273A (R/hr) 9-55 Torus Radiation Unit 1 8

RH-90-272'R/hv) 9 54 Unit RR-90-273'8 (R/hr) 9 55 Unit 2 RR-90-2728 (R/hr) 9-54 Unit 2 ,'R-90-2738 (R/hr) 9-55 Unit 3 RH-90-2728 (R/hr) 9-54 Unit 3 RH-90-2738 (R/hv) 9-55 Stack Radiation HR-90-147A (Cps) 9<<2 RH 90 147B (Cps) 9-2 Stack Flow FI-1-90-271 (cfm) 9-53 C/C (Common - on Unit 1) 81-19 Remarks:

After completion, hand carry to secretary in hallway outside TSC for distribution.

~~ t"i b~u Technical Assessment Manager Maintenance Manager Operations Manager REP Communicator NHC Communicator Radiochemical Engineer Hcaltn Physics DNPEC (Telecopy)

~Hcv'ision

y

~.

II

DROll1NS FERRY NUCLEAR PLANT 198ll. REP EXERCISE Message For SHIFT ENGINEER Date: October 24, l984

~

l"m . T= 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 30 mi'nutes 1200..

Message: TllIS IS A DRILL.

Main Steam Line (MSL) drain valves opened to equalize pressure across MSIV's MSIV's are opened and immediately =isolate on group J. MSL high radiation.

Stack radiation beginning to decrease.

0 0

4

BROWS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: SHIFT ENGINEER Date: October 24, 1984 T= 5 hours 1230 Message: THIS IS A DRILL.

Stack radiation 1

is stable but still higher than normal

BROt&iS FERRY NUCLEAR PLANT 1984 REP EXERCISE

>message For: MAIN CONTROL ROOM CONTROLLER Date: October 24, 1984 T= 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 55 minutes l325.

Hessage: THIS IS A DRILL.

plans should be made to bring the Reactor to cold shutdown for repairs of)fire damage and l-PCV-69-2 packing

BROVHS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: SITE EIKRGENCY DXRECTOR Date: October 24, 1984 Time: T= 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 1330 Hessage: THIS IS A DRILL.,

DRILL TERHZNATED

BROGANS FERRY NUCLEAR PLANT 1984 REP .EXERCISE FIRE MATCH, EMPLOYEE, OR CONTROLLER Date: October 24, 1984 Time: T O 0730 Message: THIS IS A DRILL.

There is dense smoke apparently coming from the vicinity of the Unit 1 RBCCN heat exhanger area, elevation 593 of the Reactor Bldg. Exact source is unknown,

BROMNS FERRY NUCLEAR PLANT 1984 REP EXERCISE

~~message For: FIRE BRIGADE LEADER Date: October 24, 1984 Time: T= 5 minutes 0735 Hessage: TIIIS IS A DRILL.

Dense smoke in the Reactor Bldg. The source of the smoke is a fire in the U-l RBCCW heat exchanger area, elevation 593.

BROWNS FERRY NUCLEAR PLANT 1984 REP EXERCISE lfessage For: H P TECHS WITH THE FIRE BRIGADE Date: October=.24, 1984 Time: T= 5 minutes 0735 l/essage: THIS IS A DRILL,...

General area radiation levels are not elevated above what is normal for this area;

e BROGANS FERRY NUCLEAR PLANT 1984 REP EXERCISE Hessage For: FIRE BRIGADE LEADER Date: October 24, 1984 Time: T = 10 minutes 0740 message: THIS IS A DRILL.

Source of the fire appears to be a large trash pile in the RBCCW heat exchanger area, elevation 593. Fire is fully developed and is threaten-ing overhead cable trays.

>,, 'jj ~,"

4 ~

I

,l ~

BROWNS FERRY NUCLEAR PLANT 1984 REP EXERCISE

'I Hessage For: H P LAB SHIFT SUPERVISOR 6 COORDINATOR Date: October"24, 1984 ,I J ~

I Time+ T= 15 minutes '745 =-,"'when air sample is returned and counted from the fire area Hessage: THIS IS A DRILL...

Air activity from the fire area shows no increase from normal levels Dose rates in the area are those actually observed

~ i N

0 BROGANS FERRY NUCLEAR PLANT 198lt REP EXERCISE Hessage For: PIRE BRIGADE LEADER Date: October 24, 19S4 Time: T = 20 minutes 0750 Nessage: THIS IS A DRILL.

Trash fire has been knocked down and is being brought under control

BROILS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message Fo r: FIRE BRIGADE LEADER 1

Date: October 24, 1984 Time: T=30 minutes'800 Message: THIS IS A DRILL..

Smoke is present at all elevations of the U-l Reactor Building

BROliNS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: FIRE BRIGADE LEADER Date: October 24, 1984 Time: T= 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0830 Message: THIS IS A DRILL..

The fire has been extinquished, but heavy smoke is hampering cleanup of elevation 593. Some smoke still present at other elevations.

BROGANS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: FIRE BRIGADE LEADER Date: October 24, 1984 Time: T= 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 30 minutes 0900 Message: THIS IS A DRILL.,

Heavy smoke remains on elevation 593 and 621.5.

Some smoke , but to a lesser degree, on other elevations.

'0 DROWNS I'EI<RY NUCLEAR PLANT l 984. REP EXERCISE Message For: FIRE BRIGADE CONTROLLER Date: October 24, 1984

'I'imc: T= 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 0930 Message: TIIIS IS A DRILL.

~

Smoke is clearing on all elevations - according to the surveillance conducted.

BROMNS FERRY NUCLEAR PLANT 1984 REP EXERCISE l'<essage For'IRE MATCH, EHPLOYEE OR CONTROLLER Date: October 24, 1984

'I'irnc: T = 2 hours 30 minutes 1000 Hessage: THIS IS A DRILL.

Fire has reflashed in cable tray EG-ES 1 penetration between elevations 593 and 621.5. Smoke is getting denser.

BROGANS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: FIRE BRIGADE LEADER Dace: October 24, 1984 Time: T= 2 hours 57 minutes 1027.

Message: THIS IS A DRILL.

Heavy smoke is still present on elevations 593 and 621.5 Cables are still smoldering

BROWNS FERRY NUCLEAR PLANT 198li. REP EXERCISE Message For: H P TECHS CHECKING .ARM AND CAN ALARMS ON 593 ELEVATION Date: October 24, 1984

. rq Time: T= 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (approximate)  :..'030 Message: THIS IS A DRILL.

CAM is alarming, meter and chart are both off-scale High Extremely loud noise is coming from the RWCU h'eat exhanger room and steam is observed issuing from the door vents to the room.

BROMNS YERlA NUCLEAR PLANT

(

1984 Rl:"P EXERCISE i<essage 1'or:

e H P TECHS CHECKING ARM's ON 519 ELEVATION f)a te: October 24, 198li J II T = 3 hours (approximat5) :10'30 Message: 'HIS IS A l)RILL.

Increasing dose rates as the TORUS is approached. TORUS ARM's are alarming and ARM's in each quadrant are alarming.

Contact . dose rate at TORUS ARM k are 525 mR/hr Contact dose rates in each quadrant are 200-300 mR/hr

BROOMS FERRY NUCLEAR PLANT 1984 REP EXERCISE iNessage For: FIRE BRIGADE LEADER.

Date: October 24, 1984

'I'1mc: T = 3 hours, 10 minutes 1040 .

Hessage:, THIS IS A DRILL.

Fire is continuing and there is damage in electrical cable conduits affecting RPS bus cables RP 1390 and RP 1365 Cables are smoldering

BROtPifS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For:

Date: October =24, 1984 ~ =

Time:T= 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 20 minutes (app'r'oximate) ~

1050 Message: THIS IS A DRILL.,

Air sample cartridge is returned from U-1 593 elevation at the RHCU heat exchanger 'room door. The cartridge is too hot to count.

H. V. AIR SAMPLE particulate filter: 23 R/hr at contact.

145 mR/hr at one foot L. V. AIR SAMPLE particulate filter: 9 R/hr at compact I

60 mR/hr at one foot

~0 charcoal filter: f5 R/hr at contact I

mR/hr 'at one foot

~

BROMNS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: H P LAB CONTROLLER / H P FIELD CONTROLLER Date: October -24, 1984 T= 3 hours 30 minutes 1100 Message: THIS IS A DRILL.

1. If High Volume Air Sample is collected at 593 elevation CAM Particulate filter dose rate: 23 R/hr at contact 145 mR/hi't one foot

'2. If Low Volume Air Sample is collected at 593 elevation CAM Particulate filter dose rate:

r 9 R/hr at contact 60 mR/hr at one foot If by T-4 hours the H P does n'ot have aotkvity at ARM provide the following formula:

I= 6CE where: I= dose rate R/hr at one'foot C= activity in Curies E~ ve energy in Nev (g>'I ~e g

r Estimated:air activity at ARM.on 593 elevation should be close to:

charcoal,: 4.9 E-2 uCi/cc particulate : 8,204 E-3 uCi'/c'c Estimated air activity in RMCU heat 'exchanger room should be close to:

charcoal: 5.663 uCi/cc particulate  : 8.204 E-1 uCi/cc

DROWNS PERRY NUCLEAR PLANT 1984. REP EXERCISE Message P r. H P CONTROLLER/TSC CONTROLLER/MCR o 0 flate: October 24, 1984 V

T= 3 hours 30 minutes I'l60 Message: TliIS IS A DRILL.

If the MJCU heat exchanger room were entered, a great deal of condensed water would he present and the source of the intense noise is observed to be coming from 'the corner of the 'room diagonally across from the door

BRONNS FERRY NUCLEAR PLANT 1984 REP EXERCISE ge o 'IRE BRIGADE LEADER Date: October 24, 1984 T= 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 30 minutes "'100 Hessage: THIS IS A DRILL..

Fire has been extinquished

BROWNS FERRY NUCLEAR PLANT 198~i. R EP EXERC IS E HEALTH PHYSICS TE~ LEADER/ELECTRICAL MAINTENANCE LEADER/FIRE BRIGADE LEADER Date: October 24, 1984 Time:, T = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 45 minutes 1115 Nessage: THIS IS A DRILL'.

Smoke in the Reactor Building is gradually clearing. Extremely loud noise continues from the RWCU heat exchanger room and steam continues to come out of the= room's door vents..-

BROWS FERRY NUCLEAR PLANT 1984. REP EXERCISE Nessage For. H P CONTROLLER Date: October 24, 1984 Time: T= 4 hours 1130 i'message: THIS IS A DRILL.

The noise level from the RUCU heat exchanger room has decreased and the amount of steam leakage through the room's door has decreased, but is continuing to a lesser degree.

~

~

ii P TEAN LFhDER

<),)(( ()~" e))$ b ~ ) g

)()V1'(

= 4 hours (approximate) When'hem lab is requested to collect reactor

~

coolant sample

!S h i)',;...

P

( ~ 1~1) ) ~ ~ ~

Dose rate from a one liter bottle will be:

5 R/l)r at contact i00 mR/hr at I foot Estimated from activity of 0,3 Ci in one liter Sampl in'tation General area - 2.5 R/i)r Extremity - 20 R/hr

f I

BRO't&S FERRY NUCLE PLANT 1984 REP EX CISE Message r: H P TEAM LEADER Date: October'24, 198 Time e T = 4 ho s (approx'mate) 'hen chem lab is requested to collect reactor coolant sample Message: THIS I IL D ILL, Dose rate from a one iter bo le will be:

500 R/hr at ontact 2 R/hr at one foot Estimated from ctivity of 0.3 Ci in one l& er

~ ~

4 1

I 1

DROWNS FERRY NUCLEAR PLANT 1984. REP EXERCISE Message For: ELECTRICAL MAINTENANCE LEADER Date: October 24, 1984 I

T= 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1230 Message: '1'jiIS IS A DRILL.

Cable has been laid out to reenergize 1-FCV-69-1 Noise and steam continue to come out of the RWCU heat exchanger room q1 ~

BROWS FERRY NUCLEAR PLANT 1984 REP EXERCISE Hessage For: FIRE BRIGADE LEADER Date: October 24, 1984 Time e T= 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1230 Hessage: THIS IS A DRILL..

Reactor Building is essentially"clear of all smoke.

BROGANS FERRY NUCLEAR PLANT 1984 REP EXERCISE Message For: ELECTRICAL MAINTENANCE LEADER Date October 24, 1984 T~ 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 45 minutes .,-1315 Hcssagc: T}1IS IS A DRILL.

Power cable has been spliced for 1-PCV-69-1. It is reenergized and closed.

DROWNS FEI<l<Y NUCLEAR PLANT l 98'< REP EXERCISE Hessage For.: H P CONTROLLER I)a te: October 2', 198li T= 5 hours 50 minutes 1320 iessagc 'I'IIIS IS A I)I<1I.L.

The noise from the RWCU heat exchanger room has ceased Steam leakage has subsided

i I1

Page 1 of 3 BFN - XPD BFN, XP-20 Attachment A APB.1( l'~b'I Unit No. Time D '7/

ara e er ns ue g~ne )~cad ~n Reactor Level (Accident) LI 3-62 (inches) 93 'QOO (Zero at top of fuel)

Drywell Low Pressure PI 64-'9A or

'(Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 1 only) 'Unit Drywell Wide Range . .PI-64-160A or 9-3 Pressure XR-64<<159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen) 9-3 Tor us Water Temperature TI 64-55A ( F) (Units 2 3) 9-3 TR 64-161/162 (blue pen) 9-3 /

(Uni,t 1)

Torus Water Level LI-64-159A (0<<20' 9-3 XR-64-159 pen 3 (0-240")

(Unit 1 only) v HPCX Flow FXC 73-33 (gpm) 9-3.

RCIC Flow FXC 71-36A (gpm) 9"3 NRC/C RHR,Loop I Pressure PI 74-51 (psig) 9-3 Rpt 81-19 t O

RHR Loop I Flow FX 74-50 (gpm) 9"3 RHR Loop XX Pressure PX 74-65 (psig) 9-3 RHR Loop XX Flow FI 74-64 (gpm) 9-3 v

Core Spray Loop Z Press. PI 75-20 (psig) 9-.3 Core Spray Loop t

I Flow FX 75-21 (gpm) 9-3 Core Spray Loop IX Press PX 75-48 (psig) 9-3 Core Spray Loop XI Flow FI 75-49 (gpm) 9-3 After completion,, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics

'EP Communicator DNPEC (Telecopy)

<<Revision

Page 2 of 3 BFN - IP BFN, IF-20 Attachment A

'PR17 Iggq "Unit No, Time ~~I Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9-4 (Valid only if recirc. Loop F) black pumps running) B ( 9 4 Reactor Level (Accident) LX 3-46A (inches) 9-5 (Zoro at inst. zero)

Reactor Pressure PX 3-54 (psia) 9-5 0 (0 Reactor Level (Normal) LX 3-53 (inches)

(Zero -at inst. rero)

(l)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 Torus H2 conc. H2R 76-39 or 37 9-54) 55 C) Wa (1) Torus 02 conc.

(l) Drywell H2 conc.

(l)Drywell 02 cone.

'2R ~

024 76-43 76-39 02R 76-43 or 41 .(5) or 37 (C) or 41 (5) 9"54i 55 9-54l 55 9-54'5 Q 7a 3 7 VQ

~

(l)HS 76-49 and HS 76-59 must be checked to determine what recorder pens are active.

NRC/C Other s ec f P ~

Rpt Gl-19 u ent crab t Check tho listed equipment for operability. If less than fully operable, explain in REMARKS.

g~um~en Standby Liquid Control 4~

ADS/Relief Vlvs

'CRD Pumps SBGT

.Cot'e Spr ay, Control Room

'mer.

4 Press.

RHR (LPCI) CAD RHR (CTMT Cooling) Diesels (Ul U2)

HPCX Diesels (U3)

RCXC; EECW 500 KV Power RHRSM 161 KV Power Feedwater System 4 KY System Condensato System 480 V System Primary Containment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision 4

4

Page 3 of 3 BFN - IPD BFN) IP-20 Attachment A APB 17 1""84 Unit No. I Ti~:- O7/~

SBGTS Total Flow = FI 65 - 50 + FI - 65 - 71 (SCFM x1000) 9-25 G Drywell Radiation Unit 1 RH-90<<272A (R/hr) 9-54 0.8 Unit 1 RR-90-273A (R/hr) 9-55 ~O.

Unit 2 RR<<90-272A (R/hr) 9-54 O. 8 Unit,2 RR-90-273A (H/hr) 9-55 Unit 3 RR-90-272A (R/hr) 9-54 Unit 3 .. RR-90-273A (H/hr) 9-55 .~al Torus Radiation Unit 1 RR>>90-272K 8 (R/hr) 9-54 Unit 1 RR-90-273'8 (R/hr) 9-55 Unit 2 RH-90-272B (R/hr) 9-54 Unit 2 RR-90-273B (R/hr) 9-55 Unit 3 RR-90-272B (R/hr) 9-54 Unit 3 RR-90-273B (R/hr) 9>>55 Stack Radiation RR-90-'147A (Cps) 9-2 RH-90-147B (Cps) 9-2 Stack Flow FI<<1-90-271 (cfm) 9 gp EJ> 6 OoO NHC/C (Common - on Unit 1)

Rpt 81-19 Remarks:

Aftei completion, hand.' carry. to secretary in hallway outside .TSC for distribution. -,,

• I. ,-:,

I

~ ~

I st bu 1

f Technical Assessment Manager, Maintenance Manager Operations Manager'.

PREP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

<<Revision

Page 1 of 3 BFN - IPD BFN, IP-20 A t tachracnt A APl< 1( 190 Uatt No. I Time 730

~aaa ata nst u e +~el ILeed~nig Reactor Level (Accident) LX 3-62 (inches) q ~OO (Zero at top of fuel)

I ~

N Drywell Low Pressure ,

PX 64-'39A or a (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)'

Drywell Wide Range . ':. PX-64-160A or 9-3 Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen) 9-3 0

Torus Water Temperature TI 64-55A ( F) (Units 2 3)

TR 64-161/162 (blue pen) 9-3 (Unit 1)

Torus Mater Level LI-64-159A (0<<20') 9-3 XR-64-159 pen 3 (0-240")

'(Unit 1 only)

HPCX Flow FXC 73-33 (gpm) 9-3 RCXC Flow FIC 71-36A (gpm)

NRC/C RHR.Loop X Prcssure PI 74-51 (psig) 9-3 Rpt 81-19 RHR Loop X Flow ', FI 74-50 (gpm)

RHR Loop XX Pressure PI 74-65 (psig) 9-3 RHR Loop IX ,FI 74-64 (gpm) 9-3 Flow'oro Spray Loop X Pr ess. PI 75-20 (psig) 9-.3 Core Spray Loop I Flow FI 75-21 (gpm) 9-3 Core Spray Loop II Press PX 75-48 (psig) 9-3 8o Core Spray Loop XX Flow FI 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

a' Technical Assessment Communicator Manager NRC Maintenance Manager Radiochemical Engireer Operations Manager Health Physics

'EP Communicator DNPEC (Telecopy)

<<Revision

Page 2 of 3 BFN - IP BFN, IP-20 Attachment A Unit No. Time ~~~

~

APR ) 7 ~gsq Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9 4 3 (Valid only if recirc. fo pumps running} Loop B ( F) black 9-4 Reactor Level (Accident) LI 3-46A (inches) 9-5 (Zero at inst. zero) N

~ ~

Reactor Pressure PX 3-54 (psia) 9-5 Reactor Level (Normal) , LX 3-53 (inches) 9-5 (Zero at inst. zero)

(l)Condenser vacuum . -'/TR 2-2 (in Hg) black 9-6 &8" Torus H2 conc. . - H2R 76-39 or 37 ($ )

(1) Torus .(5) 3 f 0o 024 76-43 or 02 conc. 41 9 54, 55 ~

(l)Drywell H conc. " ' R 76-39 or 37 ,($ ) 954 55

' Qo (l)Drywell 02 conc. ,- '-

02R 76-43 or 41 (5) 9-54, 55 (l)HS 76-49 and HS 76-59 must be checked to determine what recorder pens are active' NRC/C Rpt 81-19 u ment crab t - Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

ggu~m~en e In t ggu5~ment ~era>>~e Standby Liquid Control ADS/Relief Ylvs

~ 'CRD Pumps SBGT

.Core Spray Control Room C

'mer. Press.

RHR (LPCI) ~

CAD (CTMT Cooling) 'HR Diesels (U1 U2)

HPCI Diesels (U3}

RCIC'ECM 500 KV Power RHRSM 161 KV Power Condensate Containment'ra Feedwater System 4 KV System System'ri'mary 480 V System DC Power After completion, hand carry to secretary in hallway outside TSC for distr'ibution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

Page 3 of 3 BFN - lPD BFN, XP-20 Attachment A AI'R l7 1""84 Unit No. Time: 07> <

SBGTS Total Flow = FX 65 - 50 + FX - 65 - 71 (SCFM x1000) 9-25 Drywel1 Radiation 1, .;'R-90-272A Unit ' (R/hr ). 9-54 Unit 1 '

- - RR-90-273A (R/hr) 9-55 Unit 2 , RR-90-272A (R/hr) 9-'54

, Unit,2 ..., RR-90-273A (R/hr) '9-55 Unit 3

'Unit 3 ,", -

HR>>90-272A (R/hr)

RR-90-273A (R/hr) 9-54 9-55 Torus Radiation,,

Unit 1 ,' "

RR-90-272'K (R/hr) 9-54 Unit 1 RR<<90-273'h~ (R/hr) 9-55 Unit 2 . ,':,. RR-90-272B (R/hr) 9 54 Unit 2 , . , RR-90-273B (H/hr) 9-55 Unit 3

- RR-90-272B (R/hr) 9>>54 Unit 3 RR-90-273B (R/hr) 9-55 Stack Radiation RR-90-147A (Cps) 9-2 'FJ D

RR-90-1 47B ( C ps ) 9 2 ~Og Stack Flow FZ-1-90-271 (cfm) 9 55 ~7. Q SOD NRC/C (Common - on Unit 1)

Rpt 81-19 Remarks:

After completion, hand carry to secretary in hallway outside TSC for distribution.

str u Technical Assessment Manager Maintenance Manager Operations Manager

. REP Communicator NHC Communicator Radiochemical Engineer Health Physics ~

DNPEC (Telecopy)

~Revision

I P

Page 1 of 3 BFN - IPD BFN, IP-20 Attachment A APl) l. 7 190~i Time G SO&

~are eter n. tru en anel pe~ad n~

Reactor Level (Accident) LI 3-62 (inches) 9-3 ~ p.eO

. (Zero at top oi fuel)

Drywell Low Pressure PI 64 39A or.

(Low range) XR>>64-159 pen 2 (-5 to +5 psig} 9-3 (Unit 1 only)':.

Drywell Mide Range PX-64-160A or 9-3

'ressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

. Drywell Air Temperature , TR 64-52 ( F) (black pen) 9-3 Torus Mater Temperature TI 64-55A ( F) (Units 2 3} 9-3 TR 64-161/162 (blue pcn)

(Unit 1)

Torus Mater Level LI-64-159A (0-20'}

XR-64-159 pen 3 (0-240")

(Unit 1 only)

HPCI Flow FIC 73-33 (gpm) 9-3 RCIC Flow FXC 71-36A (gpm) 9-3 NRC/C RHR.Loop X Pressure PI 74-51 (psig)

Rpt 81<<19 RHR Loop I Flow FI 74-50 (gpm)

RHR Loop IX Pressur e PI 74-65 (psig) 9-3 RHR Loop II Flow", FX 74<<64 (gpm) 9-3 ee Core Spray Loop I

I Press. PX 75-20 (psig) 9-.3 e

Core Spray Loop I Flow FI 75-21 (gpm) 9-3 Core Spray Loop XI Press PI 75-48 (psig)

Core Spr ay Loop XI Flow FX 75-49 (gpm) 9-3 After completion,. hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics

'REP Communicator DNPEC (Telecopy}

IRevision

0 Page 2 of 3

~

BFH IP BFH, IP-20 Attachment A Unit Un. 17 l984 Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9-4 W33 (Valid only pumps if recirc.

running) Loop R ( F) black 9 4 Reactor Level (Accident) LI 3-46A (inches)

(Zero at inst. zero)

Reactor Pressure PI 3-54 (psia) 9-5 (o(o Reactor Level (Normal) LI 3-53 (inches) 9-5 (Zero at. inst. zero)

(l)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 Tor'Us H2 conc .H2R 76-39 or 37 ($ ) 9-54'5 3'(

~

(1) Torus ~o 02 conc. 024 76-43 or 41 -($ ) 9<<54U 55 (l) Drywell H conc. H R 76-39 or 37 ($ ) 9-54, 55 O 7o 2

(1) Drywell 02 conc. 02R 76-43 or (5) 9-54~ 55 3 / 70

~

(l)HS 76-49 and HS 76-59 must be checked to determine what recorder pens are aotive.

NRC/C Rpt 81-19 u ent crab t - Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

~uvment crab e n t J~u~ment ~eab~e Standby Liquid Control ADS/Relief Vlvs

'CRD Pumps SBGT

.Core Spray Control Room Emer. Press.

RHR (LPCI) CAD RHR (CTMT Cooling) Diesels (Ul U2)

HPCI Diesels (U3)

RCIC EECM 500 KV Power RHRSM 161 KV Power Feedwatcr System 4 KV System Condensate System 480 V System Primary Containment DC Power After completion, hand can y to secretary in hallway outside TSC for distribution.

Technical Assessment Manager Maintenance Manager '

'. REP NRC Communicator Communicator Health Physics DNPEC (Telecopy)

Operations Manager

<<Revision

'adiochemical Engineer I

~ ~ 3 n r "l

0 Page 3 of 3 BFN - IPD BFN, IP-20 Attachment A APR 17 j""84 T~me 'O SBGTS Total Flow -"FX 65 - 50 + FX - 65 - 71 (SCFM x1000} 9-25 G Dr'ywell Radiation Unit 1 RR-90>>272A (R/hr) 9-54 Unit 1 RR-90-273A (R/hr) 9-55 Unit 2 RH-90-272A (R/hr) 9-54 Unit 2 RR-90-273A (R/hr) 9-55 Unit 3 RR-90-272A (H/hr) 9-54 Unit 3 RR-90-273A (H/hr) 9-55 Torus Radiation Unit 1 HR>>90-272A8 (R/hr) 9-54 Unit 1 RR-90-2734 (R/hr) 9-55 Unit 2 RR-90-272B (R/hr) 9-54 Unit 2 RR-90-273B (R/hr) 9-55 Unit 3 RR-90-272B (R/hr) 9-54 Unit 3 RR-90-273B (R/hr ) 9-55 Stack Radiation RR-90-147A (Cps)

HR-90-147B (Cps) gp ~O Stack Flow -

FX-1-90-271 (cfm) 9 g3 6P' 000 NRC/C, (Common - on Unit 1)

Rpt 81-19 Remarks:

c After completion, hand carry to secretary in hallway outside TSC for distribution.

k4 r 'S"'s Technical Assessment Manager Maintenance Manager Operations Manager REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy) t'Revision

Page 1 of 3 BFN IPD BFN, IP-20 Attachment A API< 1.7 iso~

Unit No. Ti.me D 8 3.O

~ara ater nst u en J ~ne ~e~r~din Reactor Level (Accident) LI 3-62 (inches) 9-3 P-oG (Zero at top of fuel)

Drywell Low Pressure PI 64-39A (Low range) pen 2 or'R-64-159

(-5 to +5 psig) 9-3 (Unit 1 only)

Drywell Wide Range PI-64-160A or 9-3 IY Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (b3.ack pen) 9-3 Torus Water Temperature TI 64-'5A (

0 F) (Units 2 3) 9-3 7h TR 64-161/162 (blue pen) 9-3

,, (Unit 1)

Torus Mater Level LI-64-159A (0-20')

XR-64-159 pen 3 (0-240")

(Unit 1 only)

HPCI Flow FIC 73-33 (gpm) 9-3 RCIC Flow FIC 71-36A (gpm)

NRC/C

'I RHR.Loop X Pressure PX 74<<51 (psig) 9-3 eo Rpt 81-19 RHR Loop I Flow 74-50 (gpm) 9"3 RHR RHR Loop Loop II Flow'I II Pressure PI 74-65 (psig)

FI 74-64 (gpm) 9"3 9-3 Core Spray Loop I Press. PX 75-20 (psig) 9".3 -go Core Spray Lo*op I Flow FX 75-21 (gpm) 9-3 Cor e Spray Loop IX Press PX 75-48 (psig) 9-3 Core Spray Loop XX Flow FX 75-49 (gpm)

After completion, hand carry to secretary in hallway outside TSC for distribution.

lt!'

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engi.neer Operations Manager REP Communicator Health Physics DNPEC (Telecopy)

<<Revision

Page 2 of 3 BFN - IP BFN, IP-20 Attachment A APRIL lgg4 Unit No. Time ~~~g Reactor Coolant Temp. TR 68-2 Loop A ( F) red $ 35 (Valid only if rocirc.

pumps running) Loop B ( F) black 9 4 Reactor Level (Accident) LI 3-46A (inches)

(Zero at inst. zero)

Reactor Pressuro PI 3-54 (psia) 9 5 lO(O Reactor Level (Normal) LI 3-53 (inches)

(Zero at inst. zero) 2-2 (in Hg) black (1)Condenser vacuum Tor'us H2 conc ~ -

P/TR H2R 76-39 or 37 ($ )

9-6 9-54) 55 ~Q 3.Q 0o Torus 02 conc. 0 4 2

76-43 or 41 .(5) 9-54, 55 (1) Drywell H 'conc.

H2R 76-39 or'7 ($ ) - 9-54~ 55 Q 7p (1) Drywell Q 1 2e 02 conc 02R 76-43 or 41 9-54) 55 ~

~

(5)'e (1) HS 76-49 and HS 76-59 must checked to determine what recorder pens are active.

NRC/C Other s ec 8 ~

Rpt 81-19 it - Check If less u

Standby ent

'CRD Pumps crab

'E~~Liquid Control ..

-~,Z

'"'ontrol than, f

A the listed equipment fully operable, explain in REMARKS.

'BGT M'~

for oper ability.

ADS/Relief Vlvs

, ~e~e

....Cor e Spray RHR (LPCI)

RHR (CTMT HPCI Cooling),.

(::""

I

'Emer. Press.

CAD.

Room Diesels (U1 U2)

Diesels (U3)

RCIC; EECW 500 KV Power RHRSM 161 KY Power Feedwater System 4 KV System Condensate System 480 V System Primary Containment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintonance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer NRevision

l Page 3 of 3

~

BFN XPD BFN, IP-20 Attachment A AP-R 17 )""84 Unit Nn. Time: 0 GO I

SBGTS Total Flow = FX 65 - 50 + FX 71 (SCFM x1000) 9-25 Drywell Radiation Unit; 1 RR-90-272A (R/hr ) o.8 Unit 1 RR-90-273A (R/hr) 9-55 Unit 2 RR-90-272A (R/hr) 9-54 Unit .2 RH-90-273A (R/hr) 9-55 Unit 3 RH-90-272A (R/hr) 9 54

'Unit 3 RR-90-273A (R/hr) 9-55 Torus Radiation Unit 1 RR-90-272K 8 (R/hr) 9-54 Unit 1 RR-90-273'8 (R/hr) 9-55 Unit 2 RR-90<<272B (R/hr) 9-54 Unit 2 RR-90-273B (R/hr) 9-55 Unit 3 RH-90-272B (R/hr) 9 Unit 3 RH-90-273B (R/hr) 9-55 Stack Radiation RR-90-'147A (Cps) 9-2 'FW RR-90-147B (Cps) U-N ~OD Stack Flow FI-1-90-271 (cfm) UH EST NHC/C (Common << on Unit 1)

Rpt 81-19 Remarks:

After completion, hand carry. to'secretary in hallway outside TSC for distribution. n

~

n n

Technical Ass'essment Manager

'I Maintenance Manager Operations Manager

.REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

IRevision

Page 1 of 3 BFN - XPD BFN, IP-20 Attachment A ppj~ ~ 7 )9O,I Unit No. Time O 9 OO

~ara . e ter ntuen gaane, +egad. n~

Reactor Level (Accident) LI 3-62 (inches) 9-3 (Zero at top of fuel) hh Drywell Low Pressur e PI 64-'9A or (Low range) pen 2 (-5 to +5 psig) 9-3F'R<<64>>159 (Unit 1 only)

Drywell Mide Range , ': PX-64-160A or 9-3

'ressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pcn) 9-3 Torus Mater Temperature TX 64-55A ( F) (Units 2 3) 9-3 TR 64-161/162 (blue pen) 9-3 (Unit 1)

Torus Mater'evel LI-64-159A (0-20') 9"3 XR-64-159 pen 3 (0-240")

(Unit 1 only)*

HPCX Flow FIC 73-33 (gpm) h RCIC Flow FIC 71-36A (gpm) 9-3 NRC/C RHR,Loop X Pressure PX 74-51 (psig)

Rpt 81-19 h

RHR Loop', X Flow FI 74-50 (gpm) 9"3 RHR Loop II Pressure PI'74-65 (psig) 9>>3 RHR Loop II Flow" FX 74-64 (gpm) 9-3 Core Spray Loop h

I Press.

\ a t

PI 75-20 (psig) -fo Core Spray Loop I Flow FX 75-21 (gpm) 0 F

Core Spray Loop IX Press PI 75-48 (psig) 9-3 Core Spray Loop IX Flow FI 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

h"'"'""

'Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics REP Communicator DNPEC (Telecopy)

<<Revision

Page 2 of 3 BFN IP BFN, IP-20 Attachment A

~

APR 1984 "Unit No. Time Reactor Coolant Temp. TR 68-2 Loop A ( F) red 34 pumps onl'y if running) recirc. 'Valid Loop B ( F) black 9-4 Reactor Level (Accident) LX 3-46A (inches)

(Zero at inst. zero)

Reactor Pressure PX 3>>54 (psia) 0lO Reaotor Level (Normal) LX 3-53 (inches) 9<<5 (Zero at inst. zero)

(l)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 PB" Torus H2 conc. H2R 76-39 or 37 ($ ) 9-54~ 55 (1) Torus 02 conc. ,024 76-43 or 41 -($ ) 9-54> 55 (l)Drywell H2 conc. e H2R 76-39 or 37 ($ ) 9-54, 55 (l)Drywell 02 conc. 02R 76-43 or 41 ($ ) 9-54, 55 3e ) QO (l) HS 76-49 and HS 76<<59 must be checked to determine what recorder pens are active.

NRC/C Other s ec f Rpt 8l-19 ui ment orab t - Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

/guff)ment crab e Xn t ~uf meet ~elbe Standby Liquid Control ADS/Relief Vlvs CRD Pumps SBGT

.Coro Spray Control Room t Emer. Press.

RHR (LPCI) CAD RHR (CTMT Cooling). Diesels (U1 U2)

HPCI Diesels (U3)

RCXC; EEL 500 KV Power RHRSM 161 KV Power Feedwater System 4 KV System Condonsato System 480 V System Pr imary Containment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assossmont Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

Page 3 of 3 BFN - ZPD BFN, IP-20 Attachment A AP-R1r )."-8<

Unit No. Time r SBGTS Total Flow = FX 65 - 50 + F1 - 65 71 (SCFM x1000) 9-25 Drywell Radiation Uni.t RR-90-272A (R/hr). o 8 Unit 1, Unit 2 1

RR-90-273A RR-90-272A (R/hr)

(R/hr) 9 54 9-55 9-54

~D.

Unit,2 RR-90-273A (R/hr) 9-55 Unit 3 RR-90-272A (R/hr) 9 54 Unit 3 .. RR-90-273A (R/hr) 9-55 Torus Radiation Unit 1 RR-90-272A 8 (R/hr) 9 54 Unit 1 RR-90-273'8 (R/hr ) 9-55 Unit 2 RR-90-272B (R/hr) 9 54 Uni.t 2 RR-90-273B (R/hr) 9-55 Urd.t 3 RR-90-272B (R/hr) 9 54 Unit 3 RR-90-273B (R/hr) 9-55 I

Stack Radiation RR-90-"147A (Cps) 9-2 RR-90-147B (Cps) 9-2 Stack Flow FI-1-90-271 (cfm) g gp ~7 ~

0 GOO NRC/C (Common - on Unit 1)

Rpt 81-19 Remarks:

After completion, hand carry to secretary in hallway outside TSC for distribution.

C Technical Assessment Manager Maintenance Manager Operations Manager

. REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

~Revision

Page 1 of. 3 BFN - IPD 0'nit BFN, XP-20 Attachment A PPP )7 )gg(I No. unpen Time O 900

~ara ete n +e~d[~n Reactor Level (Accident) LX 3-62 (inches) 9-3 ~00 (Zero at top of fuel) a Drywell Low (Low range)

Pressure e

'I a 64-'9A or XR-64>>159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only) IY I

Drywell Vide Range  :, PI-64-160A or 9-3

"'ressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen) 9-3 Torus Vater Temperature TI 64-55A ( F) (Units 2 3) 9-3 TR 64-161/162 (blue pen) 9-3 (unit 1)

Torus Mater Level LI-64-159A (0-20') 9-3 XR-64-159 pen 3 (0-240")

(Unit 1 only)

HPCX Flow FIC 73-33 (gpm) 9-3 RCIC Flow FXC 71-36A (gpm) 9-3 NRC/C RHR,Loop I Pressur e PX 74-51 (psig) 9-3 So Rpt 81-19 RHR Loop X Flow FI 74-50 (gpm) 9-3 0 RHR Loop XI Pressure Pl 74-65 (psig) 9-3 RHR Loop II Flow FX 74-64 (gpm) 9"3 Core Spr ay Loop a

I Press. ,PX t

75-20 (psig)

Cor e Spray Loop I Flow FX 75-21 (gpm) 9-3 Core Spray Loop XX Press PX 75-48 (psig) 9-3 FI 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

e' Technical Assessment Manager N RC Communica tor Maintenance Manager Radiochemical Engineer Oper ations Manager Health Physics

'REP Communicator DNPEC (Telecopy)

<<Revision

Page 2 of 3 BFN - IP BFN, IP-20 Attachment A APR Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9-4 3S (Valid only pumps running) if recirc.

Loop B { F) black Reactor Level (Accident) LI 3-46A (inches) 9-5 32-

'I (Zero at inst. zero)

Reactor Pressur e l

PI 3-54 (psia) 9-5 '19 /0 Reactor Level (Normal) 3-53 (inches) 9-5 (Zero at inst. zero)

Condenser (1) Torus vacuum P/TR 2-2 (in Hg) black 9-6 HZ conc ~  : ~

HZR 76-39 or 37 ($ ) 9"54) 55 (l) Torus 02 conc. 0 4 76-43 or 4t ($ ) 9-54~ 55 2

(1) Drywell H conc. 9-54'5 (1) Drywell 76-43 or 4l (5) ) 7Q 02 conc. 9-54~ 55 ~

02R (1) HS 76-49 and HS 76-59 must be checked to determine what t ecorder pens are active.

NRC/C E ~

Rpt 81-19 ui e t crab t Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

'~ul~ment Standby Liquid Control i~

ADS/Relief Vlvs g)~a~be "CRD Pumps SBGT

.Core Spray Control Room

'L '"Emer. Press.

RHR (LPCI) CAD RHR (CTMT Cooling) Diesels (Ul U2)

HPCI Diesels (U3)

RCIC; EECM 500 KV Power RHRSM l6 l KV Power Feedwater System 4 KV System Condensate 480 V System Containment System'rimary DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

0 Page 3 of 3 BFN - IPD BFNe IP-20 Attachment A APR 17 1984 Unit No. Time: Q 5 OO SBGTS Total Flow = FZ 65 - 50 + FI >> 65 71 (SCFM x1000) 9-25 Drywell Radiation Unit 1 RR-90-272A (R/hr) 9 OS 8 Unit 1 RR-90-273A (R/hr) 9-55 Unit 2 RR-90-272A (R/hr) O

'nit 2 RR-90-273A (R/hr) 9<<54 9-55

~C)

Unit 3 RR-90-272A (R/hr ) 9-54 Unit 3 ., RR>>90-273A (R/hr) 9-,55 ~O.

Torus Radiation Unit 1 RR-90-2721I, (R/hr) 9 54 Unit 1 RR-90-273'8 (R/hr) 9-55 Unit 2 RR-90-272B (R/hr) 9 54 Unit 2 RR-90-273B (R/hr) 9-55 Unit 3 RR-90-272B (R/hr) 9-54 Unit 3 RR-90-273B (R/hr) 9-55 Stack Radiation RR-90-147A (Cps) 9-2 RR-90-147B (Cps) 9-2 ZOO Stack Flow FZ-1-90-271. (cfm) 9 g3 ~I, 0 000 NRC/C (Common on Unit 1)

Rpt 81-19 Remarks:

After completion, hand carry to secretary in hallway outside TSC for distr ibution.

st bu Technical Assessment Manager Maintenance Manager Operations Manager REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

IRevision

Page 1 of 3 ag HFN - IPD BFN, IP-20 Attachment A Apt<. lr l98~t Unit No. Time Di3O

~ara eter ns u ent Jara e.L g~e>d~n Reactor Level (Accident) LI 3-62 (inches) 93 4 3-OO (Zero at top of fuel)

Drywell Low Pressure PX 64-'9A or (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)

Drywell Mide Range 'PI-64-160A or 9-3

'ressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen) 9-3 Torus Mater Temperature TI 64-55A ( F) (Units 2 3) 9-3 TR 64<<161/162 (blue pen) 9-3

-, (Unit 1)

Torus Mater Level LI-64-159A (0-20') 9"3 XR-64-159 pen 3 (0-240")

(Unit 1 only)'XC HPCI Flow 73<<33 (gpm) 9-3 RCIC Flow FIC 71-36A (gpm) 9-3 NRC/C RHR,Loop X Pressure PZ 74-51 (psig) 9-3 Rpt 81-19 RHR Loop I Flow FX 74-50 (gpm) 9<<3 O RHR Loop IZ Pressure PI 74-65 (psig) 9-3 RHR Loop XX Flow FI 74-64 (gpm) 9-3

'ore Spray Loop X Press. PZ 75-20 (psig) 9-.3 Core Spray Loop Z Flow FZ 75-21 (gpm) 9-3 Core Spray Loop XI Press PZ 75-48 (psig) 9-3 Core Spray Loop II Flow FI 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer

'perations Manager Health Physics REP Communicator DNPEC (Telecopy)

~Revision

Page 2 of 3 BFH - IP BFN, IP-20 Attachment A APR17 1984 Unit No. Time ~p~~

Reactor Coolant Temp. TR 68-2 Loop A ( F) red 3S (Valid only pumps if recirc.

running} Loop R ( F) black 9-4 Reactor'evel (Accident) LI 3<<46A (inches) 9-5 (Zero at inst. aero)

Reactor Pressure PI 3-54 (psia) 9-5 IOto Reactor Level (Normal) LI 3-53 (inches)

(Zero at inst. sero)

(1}Condenser vacuum P/TR 2-2 (in Hg) black 9-6 Q8" Torus H2 conc. .H2R 76-39 or 37 ($ ) 9-54t 55 (1) Torus 3 p'Y ~O 02 conc. 0,4 76-43 or 41 ($ ) 9-54~ 55 (1) Drywell H conc. 954, H2R 76-39 or 37 ($ ) 55 (1) Drywell ) Qo 02 conc. 2R 76>>43 or (N) 9>>54, 55 (1) HS 76-49 and HS 76-59 must be checked to determine what recorder pens are aotive.

NRC/C ther s ec f Rpt 81-19 ui ment crab it - Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

g~u~ment era e In t ~~ui )given ~ea~e Standby Liquid Control ADS/Relief Vlvs CRD Pumps SBGT

..Core Spr ay Control Room Emer. Press.

RHR (LPCI) . CAD RHR (CTMT Cooling) Diesels (U1 U2}

HPCI Diesels (U3)

RCIC; EECW 500 KV Power RHRSM 161 KV Power Feedwater System 4 KV System Condensate System 480 V System Primary Containment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

~Revision

Page 3 of 3 BFN - IPD BFN, IP<<20 Attachment A APR 17 i."-a4 Unit No. Time!" Q /30 1

SBGTS Total Flow = FI 65 - 50 + FI - 65 71 (SCFM xt000) 9-25 Drywell Radiation Unit 1 RR-90-272A (R/hr) 9-54 G' Unit 1, RR-90>>273A (R/hr) 9-55

<< Unit 2 RR-90>>272A (R/hr) 9-54 Unit 2 RH-90-273A (H/hr) 9-55

<< Unit 3 RR-90-272A (R/hr) 9-54

<< Unit 3 . RR-90-273A (R/hr) 9-55 Torus Radiation Unit. 1 RH-90-272K8 (R/hr) 9-54 Unit 1 RR>>90-2738 (R/hr ) 9-55 Unit 2 RH-90-272B (R/hr) 9 54 Unit 2 HR-90-273B (R/hr) 9-55 Unit 3 HR-90-272B (R/hr) 9-54 Unit 3 RR-90-273B (R/hr) 9-55 Stack Hadiation HR-90-147A (Cps) 9-2 HR-90-147B (Cps) 9 2 /OO 6 00o t NRC/C Rpt 81-19 Stack Flow (Common Hemarks:

- on Unit 1)

FI>>1-90-271 (cfm) 9-53

'After completion, hand carry. to secretary in hallway outside TSC for distribution. I s ibu Technical Assessment Manager Maintenanco Manager Operations Manager REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

<<Revision 4

Page 1 of 3

~

) BFN - IPD BFN, IP-20 Attachment A APB. [7 )'.)8'1

~ -.

, Unit No. Time /boo.

~ara eter n uen ~nel ~cad S~n Reactor Level (Accident) LI 3-62 (inches) 93 + >GO (Zero at top of fuel)

Drywell Low Pressure PX 64-39A or

'l

, (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)

Drywell Wide Range '.". PX-64-160A or 9-3 Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen)

Tor us Mater Temperatuve TX 64<<55A ( F) (Units 2 3) 9-3 TR 64-161/162 (blue pen) 9-3 (Unit 1)

Torus Mater Level LI-64-159A (0-20')

XR-64-159 pen 3 (0-240")

'(Unit 1 only)

'I HPCI Flow FXC 73-33 (gpm) 9-3 0 RCXC blow FIC 71-36A (gpm) 9-3 NRC/C RHR.Loop X Pressure PI 74-51 (psig) 9-3 Rpt 81-19 I I Flow e

RHR Loop I FI 74-50 (gpm) 9-3 RHR Loop IX Pressure PI 74-65 (psig) 9-3 RHR Loop XX FlowFI 74-64 (gpm) 9-3 Core Spray Loop 1 Press. PI 75-20 (psig) 9-.3 -sa Core Spray Loop I Flow FX 75-21 (gpm) 9-3 e

Cove Spray Loop II Press PI 75-48 (psig)

Core Spray Loop IX Flow FX 75-49 (gpm)

After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics

'.='REP Communicator DNPEC (Telecopy)

IRevision t

~ ~

~ ~

4

,A

Page 2 of 3 BFN - IP BFN, XP-20 Attachment A Unit tlo.

Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9-4 W3Z (Valid only pumps running) if recirc.

Loop B ( F) black 9-4 Reactor Level (Accident) LI 3-46A (inches)

(Zero at inst. zero) 9-5'I Reactor Pressur e 3-54 (psia) iQiQ

~V

'I Reactor Leve3. (Normal) LI 3-53 (inches)

(Zero at inst. zero)

(l)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 Torus H conc. ~ H R 76<<39 or 37 ($ ) 9 5ll, 55 2

Torus 02 conc. 24 76-43 or 41 -($ ) 9-54> 55 .g 'Jo (l)Drywell H conc. H2R 76-39 or 37 ($ ) 9-54> 55 (l) Drywell 02 conc. 02R 76-43 or 41 ($ ) 9-54) 55 ~ 7 2c7 (l)HS 76-49 and HS 76-59 must; be checked to determine what recorder pens are active ~

NRC/C ther s ec f I J~

Rpt Gl-19 u e t crab t Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

~uf~ment er b e In t ~ui~>ent ~ca~be Standby Liquid Control ADS/Relief Vlvs CRD Pumps SBGT

~

,Core Spray Control Room Emer. Press.

RHR-.(LPCI) CAD RHR (CTMT Cooling) Diesels (U1 U2)

HPCI Diesels (U3)

RCIC '.

EECM 500 KV Power RHRSH 161 KV Power Feedwater System 4 KV System

'ondensate System ll80 V System Primary Containment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

Page 3 of 3 BFN - IPD BFN, IP-20 Attachment A APR 17 I""84 Unit No. vane ~QO V SBGTS Total Flow = FI 65 - 50 + FX - 65 71 (SCFM x1000) 9-25 Drywell Radiation Unit; 1 RR-90-272A (R/hr) 9-54 Unit 1 RR-90-273A (H/hr) 9-55 Unit 2 RR-90-272A (R/hr) 9-5

, Unit 2 RR-90-273A (H/hr) 9-55 Unit 3 RR-90-272A (R/hr) 9-54 Unit 3 .. RR-90-273A (R/hr) 9-55 Torus Radiation

'I Unit 1 RR<<90-272'A (R/hr) 9-54 Unit 1 RR-90-273'R/hr) 9-55 Unit 2 RH-90-272B (R/hr) 9-54 Unit 2 RR-90<<273B (R/hr) 9-55 Unit 3 RH-90-272B (R/hr) 9-54 Unit 3 RR-90-273B (R/hr) 9-55 Stack Radiation RR-90-147A (Cps) 92 VW RR-90-147B (Cps) 9 2 /OO Stack Flow FI-1-90-271 (cfm) 9-H EV r, r .Doc>

NRC/C (Common - on Unit 1)

RPt 81-19 Remarks:

After completion, hand carry. to seer'etary in hallway outside TSC for distribution.

f h

s 3bu

'echnical Assessment Manager Maintenance Manager Operations Manager

~ ~

REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

<<Revision

Page 1 of 3 BPN - XPD BFN s IP-20 Attachment A APl< ( l98~1 O. Unit No. Time D2 0 1

~ara eter ns u en ~atone g~ed i~n Reactor Level (Accident) LX 3-62 (inches) 93 'OO (Zero at top of fuel)

Drywell Low Pressure PX 64-'39A or (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)'rywell Mide Range . ': PI-64-160A or 9-3 Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen) 9-3 Torus Mater Temperature TX 64-55A ( F) (Units 2 3) 9-3 TR 64-161/162 (blue pen) 9-3

.. (Unit 1)

Torus Mater Level LI<<64-159A (0-20') 9-3 XR-64-159 pen 3 (0-240")

(Unit 1 only)

HPCX Flow FXC 73-33 (gpm) 9-3 RCIC Flow FIC 71-36A (gpm) 9"3 NRC/C RHR,Loop I Pressure PI 74-51 (psig) 9-3 Rpt 81-19 RHR Loop' Plow FI 74-50 (gpm) 9-3 I

RHR Loop XI Pressure PI 74-65 (psig) 9-3

. RHR Loop IX Flow" FX 74-64 (gpm) 9"3 Core Spray Loop I Press. PX 75>>20 (psig) 9-.3 -po Core Spray Loop I Flow FI 75-21 (gpm) 9-3 Core Spray Loop II Press PI 75-48 (psig) 9-3 Core Spr ay Loop II Flow FI 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Oporations Manager Health Physics

'REP Communicator DNPEC (Telecopy)

<<Revision

Page 2 of 3 BFW - XP BFN, XP-20 Attachment A Unit No. l ~AH g Lhjgq Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9-4 (Valid only if recirc.

pumps running) Loop B ( F) black 9-4 Reactor Level (Accident) LI 3-46A (inches)

(Zero at inst. rero)

Reactor Pressure PI 3-54 (psia) lo io Reactor Level (Normal) LX 3-53 (inches)

(Zero at inst. zer o) h (1)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 Torus H2 conc. ~

H2R 76-39 or 37 (S) . 9-54) 55 (1) Torus or 41 -($ ) 9-54'5 3 02 conc. 0 4 76-43 2

(1) Drywell H cone. H R 76-39 or 37 ($ ) 9-54~ 55 2

(1) Drywell conc. 0 R 76-43 or ($ ) 9-54~ 55 3. 7 9'0 02 (1) HS 76-49 and HS 76-59 must be 2 checked to determine what recor der pens are active.

NRC/C Rpt 81-19 ui ent er ab t Check the listed equipment for operability. If less h

than fully operable, explain in REMARKS.

'gu ~ment II Q)~estabe Standby Liquid Control ADS/Relief Viva CRD Pumps SBGT

..Coro Spr ay ,Control Room h

h

'mer. Press.

RHR (LPCX) . CAD RHR (CTMT Cooling) Diesels (U1 U2)

HPCX Diesels (U3)

RCXC; EECW 500 KV Power RHRSM 161 KV Power Feedwater System 4 KV System Condensate System 480 Y System Primary Containment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

0 Page 3 of 3 BFN - XPD BFN, XP-20 Attachment A APR 17 )."-S4 Unit No. t Toms: ~O~ 0 SBGTS Total Flow "- FX 65 50 + FX - 65 - 71 (SCFM x1000) 9-25 Drywell Radiation Unit 1 RH-90-272A (R/hr) 9-54 Unit 1 RR-90-273A (R/hr) 9-55 Unit 2 RR-90>>272A (R/hr) 9 54 Unit .2 RR-90-273A (R/hr) 9-55 Unit 3 RR-90-272A (R/hr) 9-54 0 Unit 3 .. RR-90-273A (R/hr) 9-55 sP Torus Radiation Unit RR-90-2728(R/hr) 9-54 1'nit 1 RR-90-273'8 (R/hr) 9-55 Unit 2 RR-90-272B (R/hr) 9~54 Unit 2 RR-90-273B (R/hr) 9-55 Unit 3 RR-90-272B (R/hr) 9-54 Unit 3 RR-90-273B (R/hr) 9"55 Stack Radiation RR-90-147A (Cps) 9-2 RR-90-147B (Cps) 9-2 ~oo .

NHC/C Rpt 81-19 Stack Flow (Common - on Unit 1)

FX-1-90-271, (cfm) 9-5<gg. ~<<

Remarks:

completion, hand carry to secretary in hallway outside TSC for I'fter distribution.

s bu

\0 Technical Assessment Manager Maintenance Manager

~

Operations Manager REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

~Revision

Pago 1 of 3 BFN - IPD BFN, IP-20 Attachraent A APf<. 1,7 l98<t Unit No. Time 0 +7-.

~ara eaer ns u nt j earn~

Reactor Level (Accident) LZ 3-62 (inches) 9-3 (Zero at top of fuel) a Drywell Low Pressure PI 64-39A or I (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3, (Unit 1 only)

Drywell Mide Range  : PI-64-160A or 9-3 r

](f Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64<<52 ( F) (black pen) 9-3 Torus Mater Temperature TI 64-55A ( F) (Units 2 3) 9-3 9'o TR 64-161/162 (blue pen)

(Unit 1)

Torus Mater Level LI-64-159A (0-20') 9-3 XR-64-159 pen 3 (0-240")

'(Unit 1 only)

HPCX Flow FIC 73-33 (gpm) 9-3 oooo RCIC 5'low FIC 71-36A (gpm) (cQ NRC/C RHR.Loop X Pressure PI 74-51 (psig) 9-3 Rpt 81-19 RHR Loop I Flow FI 74-50 (gpm) 9"3 RHR Loop XX Pressure PI 74-65 (psig) 9"3

RHR Loop XX Flow FI 74-64 (Gp61) 9-3 Core Spray Loop X Press. PI 75-20 (psig) 9-.3

, ~

r Core Spray Loop I Flow FX 75-21 (gpm) 9-3 Core Spray Loop II Press PX 75-48 (psig) 9-3 Core Spr ay Loop II .Flow FI 75-49 (gpm) 9-3 After completion, hand carry to secretar y in hallway outside TSC for distribution.

a'echnical Assessment Manager NRC Communicator Maintenanco Manager Radiochemical Engineer Operations Manager Health Physics

"-'REP Communicator DNPEC (Telecopy)

<<Revision'

Page 2 of 3 BFW - IP BFN, XP-20 Attachment A No.

"Reactor Coolant Temp. TR 68-2 Loop A ( F) r ed 9 4

~~

~

APR17 198'ime if recirc.

3Z'nit (Valid only pumps running) Loop B ( F) black 9 4 Reactor Level (Accident) LI 3-46A (inches)

(Zero at inst. zero)

Reactor Pressuro PI 3-54 (psia) 9-5 Reactor Level (Normal) LI 3-53 (inches)

(Zero 'at inst. zero)

(l)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 Torus H2 conc. H R 2

76-39 or 37 ($ ) 9-54) 55 (1) Tor'us 02 conc. 0 4 76-43 or 41 -($ ) 9-54) 55 3.H ')~

2 (l)Drywell H conc. H2R 76-39 or 37 ($ ) 9-54 55 (1) Drywell or 41 (C) 02 conc. 0 R 76-43 2

9-54) 55 (l)HS 76<<49 and HS 76-59 must be checked to determine what recorder pens are active.

NRC/C ther s ec f 1~

Rpt 81-19 ui ent crab t Check tho risted equipment for operability. If less than fully oper able, explain in REMARKS.

ggu~ment crab e In t ~uvment g)~eab e Standby Liquid Control ADS/Relief Vlvs ~

CRD Pumps SBGT

, Core Spray Control Room.

/ 'mer. Pr ess.

RHR (LPCI) . CAD RHR (CTMT Cooling) Diesels (U1 U2)

HPCI Diesels (U3)

RCIC'ECN 500 KV Power RHRSM 161 KV Power Feedwater System 4 KV System

. Condensate System 480 V System Primary Containment DC Power carry to secretary in hallway outside After completion, hand TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

0 Page 3 of 3

~

BFN IPD BFN, IP-20 Attachment A 0- Unit Nn. Time:"

AP-R

.(QW7

>7 t."-84 SBGTS Total Flow = FX 65 - 50 + FX - 65 - 71 (SCFM x1000) 9-25 Drywell Radiation Urd.t 1 RR-90>>272A (R/hr) 9-54 o.8 0.9 Unit 1, RR-90-273A (H/hr) 9-55 Urd.t 2 RR-90-272A (R/hr) 9-54 Unit 2 RR-90-273A (R/hr) 9-55

, Unit 3 HR-90-272A (R/hr) 9-54 0 ~ 3 Unit 3 .. RR-90-273A (R/hr) 9-55 C7 )Y Torus Radiation Unit 1 RR-90-272A (R/hr) 9-54 Unit 1 RR-90-273'8 (R/hr) 9-55 Unit 2 RR-90-272B (R/hr) 9-54 Urd.t 2 RH"90-2738 (R/hr ) 9-55 Unit 3 RR"90-272B (R/hr) 9-54 Urd.t 3 RR-90-273B (R/hr) 9-55 Stack Radiation RR-90-147A (Cps) 9-2 RR-90-147B (Cps) 9-2 Stack Flow FI-1-90-271 (cfm). 9-53 C ooO NRC/C (Common - on Unit 1)

Rpt 81-19 I Remarks:

After completion, hand carry. to secretary in hallway outside TSC for distribution.

st bu Technical Assessment Manager Maintenance Manager Operations Manager REP Communicator NHC Communicator Radiochemical Engineer Health Physics .

DNPEC (Telecopy)

~Revision

Page 1 of 3 BFN >> XPD BFN, XP-20 Attachment A APB 17 l98~l Unit No. Time oQO

~ara eter stru n ga~e ~ead~n Reactor Level (Accident) LI 3-62 (inches) 93 '2OO (Zero at top of fuel)

Drywell Low Pressure PI 64-39A or (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)

Drywell M,de Range PI-64-160A or 9-3

'ressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen) 9-3 Torus Mater Temperature TI 64-55A ( F) (Units 2 3) 9-3 lGO TR 64-161t162 (blue pen) 9-3 /

(Unit 1)

Torus Mater Level LX-64-159A (0-20') 9-3 XR-64-159 pen 3 (0-240~)

(Unit 1 only)

HPCX Flow FIC 73-33 (gpm) 9-3 RCIC Flow FIC 71-36A (gpm) 9"3 NRC/C RHR,Loop X Pressure PI 74-51 (psig) 9-3 Rpt 81-19 RHR Loop I Flow FX 74-50 (gpm) 9-3 "l1 ooO RHR Loop, XX Pressuz e . PI 74-65 (psig) 9-3 RHR Loop XX Flow Core Spray Loop

" Core Spray Loop I Press.

I Flow

'I,

'FI 74-64 FX (gpm) 75-20 (psig) 75-21 (gpm) 9"3 9-.3 9"3 Core Spray Loop IX Press PI 75-48 (psig) 9-3 Coz'e Spray Loop XX Flow FI 75-49 (gpm) 9 3 lt~

After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics

'REP Communicator DNPEC (Telecopy)

<<Revision

E y

Page 2 of 3 BFN - XP BFN, IP-20 Attachment A Unit No.

~

APB 17 198rJ Reactor Coolant Temp. TR 68-2 Loop A ( F) red ~zo (Valid only pumps if running) recirc.

Loop B ( F) black Reactor Level (Accident) LI 3-46A (inches)

(Zero at inst. zero)

Reactor Pressure PI 3-54 (psia) 9-5 Reactor Level (Normal) LI 3-53 (inches) 9-5 (Zero at inst. zero)

(1)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 Torus H2 conc. H R 2

76-39 or 37 ($ ) 9-54r 55 o ra (1) Tor'us 0 4 76-43 or g,y 'Pea 02 conc ~

~

2 41 ($ ) 9<<54, 55 (1) Drywell conc. H R 76-39 or 37 ($ ) 9>>54) 55 0

H2 2 (1) Drywell 0 conc. 0 R 76-43 or 41 ($ ) 9-54> 55 3 790 (1) HS 76-49 and HS 76-59 must be 2 checked to determine what r ecorder pens ar e active.

NRC/C ther s ec ~~

Rpt 81-19 u ent er b t - Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

EW '

2R~J"rJJ e Standby Liquid Control . i ADS/Relief Vlvs

-'CRD Pumps SBGT

.Core Spray "

Control Room Emer. Pr ess.

RHR (LPCI) CAD RHR (CTHT Cooling) Diesels (Ul U2)

HPCI Diesels (U3)

RCIC, EECM 500 KV Power RHRSM 161 KV Power Feedwater System 4 KV System Condensate System 480 V System Pr'imary Containment DC Power After completion, hand carr y to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

~Revision

Page 3 of 3 BFN - XPD BFN, IP-20 Attachment A l

APR 7 l984 Unit No. Talma:r ~OM SBGTS Total Flow = FX'65 - 50 + FX- 65 71 (SCFM x1000) 9-25 Drywell Radiation Unit 1 RR-90-272A (R/hr) 9 54 Unit 1 RR-90-2? 3A -

(R/hr) 9-55 Unit 2 RH-90-272A (R/hr) 9 54 Unit;,2 RR-90-273A (R/hr) '9-55 Unit 3 RR-90<<272A (R/hr) 9-54

'Unit 3 .. RH-90-273A (R/hr) 9-55 Torus Radiation Unit 1 RR-90-272K 8 (R/hr) 9-54 Unit 1 RR-90-273'tP (R/hr) 9-55 Unit 2 RR-90-272B (R/hr) 9 54 Unit 2 RR-90-273B (R/hr) 9-55 Unit 3 RR-90-272B (H/hr) 9-54 Unit 3 RR-90-273B (R/hr) 9-55 Stack Hadiati.on RR-90-147A (Cps) 9-2 RH-90-147B (Cps) 9-2 Stack Flow FI-1-90-2?1 (cfm)

NRC/C (Common - on Unit 1)

Rpt 81-19 Remarks:

After completion, hand carry, to sect etary in hallway outside TSC for distri.bution.

'l ~

Techni,cal Assessment Manager Mai.ntenance Manager Operations Manager REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

<<Revision

Page 1 of 3 BFN - XPD BFN, XP-20 Attachment A

~- Unit No. Time l APB.

O Q t7 SO~I

~aea ete s uen ~Pa. el g~ead~n~

~

Reactor Level (Accident) Ll 3-62 (inches 9-3 + XOG (Zero at top of fuel)

Drywell Low Pressure PI 64-'39A or (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)

Drywell Mide Range . ':, PI-64-160A or 9-3 Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only}

Drywell Air Temperature TR 64-52 ( F) (black pen} l3O Torus Mater Temper attire TX 64-55A ( F) (Units 2 3) 9" 3 1

TR 64-16 1/162 (blue pen) 9-3

., (Unit 1)

Torus Mater Level '. LI<<64-'l59A (0-20')

XR-64-159 pen 3 (0-240")

(Unit 1 only)'IC HPCX Flow 73-33 (gpm) 9-3 RCXC Flow FXC 71-36A (gpm) 9-3 NRC/C RHR.Loop X Pressure PX 74-51 (psig) 9-3 Rpt 81-19 RHR Loop',

j1 I Flow FX 74<<50 (gpm) 9-3 RHR Loop XX Pressure PX 74-65 (psig) e RHR Loop II Flow FI 74-64 (gpm}

Core Spray Loop I Press. PI 75-20 (psig) 9-.3 Core Spray Loop I Flow FX 75-21 (gpm) 9-3 Core Spray Loop XX Press PI 75-48 (psig) 9-3 Core Spray Loop XI Flow FX 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

g~st~rb~uti q Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics

REP Communicator DNPEC (Telecopy)

<<Revision l

e Page 2 of 3 BFtt - IP BFN, IP-20 Attachment A 7 l984 Unit Ho, Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9 4 (Valid only if,.recirc.

pumps running) Loop B ( F) black 9~4 Reactor Level (Accident) LI 3-46A (inches)

(Zero at inst. zero)

Reactor Pressure PI 3-54 (psia) 9-5 Reaotor Level (Normal) LI 3-53 (inches) 9-5 S (Zero at inst. zero)

)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 AS" Torus H2 conc. AH R 76-39 or 37 2 (S) 9-54'5 (1) Torus . 0 4 76-43 or 41 .($ ) 9-54) 55 02 conc'1) 2 Drywell H conc. H R 76-39 or 37 ($ ) 9-54) 55 2

(1) Drywell 02 conc. 0 R 76-43 or (5) 9-54~ 55 3 770 2

(1) HS 76-49 and HS 76-59 must be checked to determine what recorder pens are aotive.

NRC/C Other spec f Rpt 81-19 E ui ment crab t - Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

JdLuupment e n t ~u~men t ~ereb e Standby Liquid Control ADS/Relief Ylvs

'CRD Pumps SBGT

.Core Spray Contr'ol Room

'mer. Press.

RHR (LPCI) . CAD (CTMT Cooling).

'HR Diesels (U1 U2)

HPCI Diesels (U3)

RCIC EECM 500 KY Power RHRSl 161 KV Power Feedwater System 4 KV System Condensate System 480 Y System Primary Containment DC Power I

After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator Dt/PEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

Page 3 of 3

~

BFN IPD BFN, IP-20 Attachment A APR 17 i".-84 Unit No. (fOO-SBGTS Total Flow -" FI 65 - 50 + FI - 65 - 71 (SCFM x1000) 9-25 Dr ywell Radiation Unit 1 RR-90-272A (R/hr) 9-54 Unit 1 RR-90-273A (R/hr) 9-55 Unit 2 RR-90-272A (R/hr ) 9~54 Urd.t 2 RR-90-273A (R/hr) 9-55 Unit 3 RR-90-272A (R/hr) 9-54 Unit 3 .. RH-90-273A (R/hr) 9-55 Tor us Radiation Unit 1 RR-90-272K8 (R/hr) 9-54 Unit; 1 RR-90-2738 (R/hr ) 9-55 Unit 2 RH-90-272B (R/hr) 9-54 Urd.t 2 RR-90-273B (R/hr) 9-55 Urd.t 3 RR-90-272B (R/hr) 9 54 O Unit 3 RR-90-273B (R/hr) 9-55 O Stack Radiation RR<<90-147A (Cps) 9>>2 ++4 RR-90<<147B (Cps) 9-2 <+I'o Stack Flow FI-1<<90-271 (cfm) gG

!o UIO0 NHC/C (Common -'n Unit 1) U U3 Rpt 81-19 Remarks:

After completion, hand carry, to secretary in hallway outside TSC for distribution.

n ~

II, ~

st ~

t Technical Assessment Manager Maintenance Manager Operations Manager

. REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

<<Revision

0 Page 1 of 3 BEN - XPD BFN, XP-20 Attachment A APl< 17 i90~I Unit No. Time C l30--

~araaeter n tru en ~rlee ~edging Reactor Level (Accident) LZ 3-62 (inches) 9-3

,.(Zero at top oi fuel) I Drywell Low Pressure PX 64-'39A or

,(Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)

Drywell Hide Range PX-64-160A or 9-3 Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pcn) . l~ 0 Torus Mater Temperature TZ 64-55A ( F) (Units 2 3)

TR 64-161/162 (blue pen) 9-3 (Unit 1)

Torus Mater Level LX-64-159A (0-20') 9-3 XR-64-159 pen 3 (0-240")

(Unit 1 only)

HPCI Flow FIC 73-33 (gpm) 9-3 RCXC 5'low FIC 71-36A (gpm) 9-3 NRC/C RHR.Loop I Pressure. PX 74<<51 (psig) 9-3 Rpt 81-19 e I Flow e

RHR Loop FI 74-50 (gpm) 9"3 II RHR Loop XI Pressure PZ 74-65 (psig) 9-3

,RHR Loop IZ Flow'* FI 74-64 (gpm) 9-3

-8 C

Core Spr ay Loop I

I Press.

e h, PI 75-20 (psig) 9".3 Core Spray Loop I Flow

'I FX 75-21 (gpm) 9-3 Core Spray Loop IX Press PI 75-48 (psig) 9-3 Core Spray Loop IX Flow FI 75-49 (gpm)

After completion, hand carr y to secretary in hallway outside TSC for distribution.

II Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics

'REP Communicator DNPEC (Telecopy)

<<Revision

Ti Page 2 of 3 BFN - XP BFN, IP-20 Attachment A Unit No. , ~pggv m8<

Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9-4 (Valid only if recirc.

pumps running) Loop B ( F) black +3Q Reactor Level (Accident) LI 3-46A (inches)

(Zero at inst. zero)

Reactor Pressure PX 3-54 (psia) 9-5 %GO Reactor Level (Normal) LX 3-53 (inches) 9-5 (Zero at inst. zero)

(l)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 &8" Torus H2 conc. . H2R 76-39 or 37 ($ ) 9-54'5 (1) Torus .($ ) 3. V>a 02 conc. ~

0 4 76-43 or 41 2

9-54~ 55 (l) Drywell H conc, H2R 76-39 or 37 (5) 9-54~ 55 (l)Drywell 02 conc. 02R 76-43 or 41 ($ ) 9-54 ) 55 3 790 (l)HS 76<<49 and HS 76-59 must be checked to determine what recorder pens are active.

NRC/C Ot e s ec f Rpt 81-19 ui ent crab '

Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

IADS/Relief II ggu~) ment "W'" ~e~a~e Standby Liquid Control Vlvs CRD Pumps SBGT

.Core Spray Control Room Emer. Press.

RHR (LPCI) CAD RHR (CTMT Cooling) Diesels (UI U2) '00 HPCX Diesels (U3)

RCXC '

EEL KV Power RHRSW 161 KV Power Feedwater System 4 KV System

Condensate System 480 V System Primary Containment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

Page 1 of 3 BFN - IPD BFN, IP-20 Attachment A APB l.7 190)

Unit No. Time (a on

~ara etee nst u en ~eden Reactor Level (Accident) LI 3-62 (inches) 9-3 QO0 (Zero at top of fuel)

Drywell Lcw Pressure PI 64-39A or (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)

Drywell Wide Range PI-64-160A or 9-3 Pressure XR<<64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperatur e TR 64-52 ( F) (black pen) 9-3 Torus Water Temperature TX 64-55A ( F) (Units 2 3) 9-3 TR 64-161/162 (blue pen) 9"3 (Unit 1)

Torus Water Level LI-64-159A (0-20' 9"3 XR-64-159 pen 3 (0-240")

(Unit 1 only)

HPCI Flow FIC 73-33 (gpm) 9-3 RCIC Flow FIC 71-36A (gpm), 9"3 NRC/C RHR Loop I Pressure PI 74-51 (psig) 9-3 Rpt 81>>19 RHR Loop I Flow FI 74-50 (gpm) 9-3 Loop XI Pressure PI 74-65 (psig) 9-3 RHR RHR Loop II Flow'I 74-64 (gpm) 9-3 e&0 Core Spray Loop I Press. PI'75-20 (psig) 9-3 Core Spray Loop I Flow FI 75-21 (gpm) 9-3 Core Spray Loop XI Press PI 75-48 (psig)

Core Spray Loop II Flow FI 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

~ate t etX~

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics REP Communicator DNPEC (Telecopy)

IRevision

0 I

Page 3 of 3

~

BFN XPD BFN, XP-20 Attachment A APR 17 ~SBC Unit No. Ti~:-'(3~

Total Flow 65 - 50 + FX - 65 - xt000) 9-25 I '0 SBGTS = FX 71 (SCFM Dr ywell Radiation Unit 1 RR-90-272A (R/hr) 9-54 Unit 1 RR-90-273A (R/hr) 9-55 Unit 2 RR-90-272A (R/hr) 9-54

<< . Unit 2 RR-90-273A (H/hr) '9-55

<< Unit 3 RR-90-272A (R/hr) 9-54 O,p

<< Unit 3 ~

.. RR-90-273A (R/hr) 9-55 Torus Radiation Unit 1 RR-90-272K 8 (R/hr) 9-54 Unit 1 RR-90<<273'8 (R/hr ) 9-55 Unit 2 RR-90-272B (H/hr) 9-54 O Unit 2 HR-90-273B (R/hr) 9-55 -c9 Unit 3 RR-90-272B (R/hr) 9-54 CO Unit 3 HR-90-273B (R/hr) 9-55 Stack Radiation RR-90-147A (Cps) 9-2 RR>>90-147B (Cps) 9-2 t NRC/C Rpt 81-19 Stack Flow (Common << on Remar ks:

Unit 1)

FX-1-90-271 (cfm) 9-53 After completion, hand carry. to secretary in hallway outside TSC for distribution.

st bu Technical Assessment Manager Maintenance Manager Operations Manager REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

<<Revision

E Page 2 of 3 BFN - IP BFN, IP-20 Attachment A Unit No. I ~pl'B r ~o8<

Reactor Coolant Temp. TR 68-2 Loop A ( F) red 94 52O (Valid only pumps running) if recirc. Loop B ( F) black Reactor Level (Accident) LI 3-46A (inches) 9-5 (Zero at inst. zero)

Reactor Pressure PI 3-54 .(psia) 9-5 Reactor Level (Normal) LI 3-53 (inches)

(Zero at inst. zero)

(l)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 Torus H2 conc. H2R 76-39 or 37 ($ ) 9-54'5 Torus 02 conc. ~ 0 4,76-43 2

or 41 (5) 9-54 55 (l)Drywell H2 coro. H2R 76-39 or 37 ($ ) 9-54~ 55 (l)Drywell 02 conc. 02R 76-43 or 41 (g) 9-54) 55 3-Q w (l)HS 76-49 and HS 76-59 must; be checked to determine what recorder pens are active.

HRC/C her s ec f Rpt 81-19 ui ment crab t - Check the listed equipment for operability. If less than fully operable, explain in REMARKS.

gguuvent ggui~ment ~estabe Standby Liquid Control ADS/Relief Vlvs CRD Pumps SBGT Core Spray Control Room Emer. Press.

RHR (LPCI) CAD RHR (CTMT Cooling) Diesels (U1 U2)

HPCI Diesels (U3)

RCIC EEC'II 500 KV Power RHRSM 161 KV Power Feedwater System 4 KV System Condensate System 480 Y System Primary Containment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC DNPEC (Telecopy)

Operations Manager Communicator'adiochemical Engineer

<<Revision

n

+I Page 3 of 3

~

BFN IPD BFN, IP-20 Attachment A APR 17 l984 Unit Uo. Time ~~@

i SBGTS Total Flow = FI 65 - 50 + FI >> 65 - 71 (SCFM x1000) 9-25 ~(

Drywell Radiation Unit 1 RR"90-272A (R/hr) 9-54 ~Q Unit 1 HR"90-273A (R/hr) 9"55 ~O Unit 2 RR-90-272A (R/hr) 9-54 Unit 2 RR-90-273A (R/hr) 9-55 O Unit 3 RR-90-272A (R/hr) 9-54 0.3 Unit 3 RH-90-273A (R/hr) 9-55 n

Torus Radiation Unit 1 RR-90-272A (R/hr) 9 54 Unit 1 RR-90-273A (R/hr) 9-55 Unit 2 RR-90-2728 (R/hr) 9-54 Unit 2 HR-90-2738 (R/hr) 9"55 a Unit 3 RR-90-2728'(R/hr) 9~54 Unit 3 RR-90-2738 (R/hr) 9-55 Q Stack Radiation RR-90-147A (Cps) 9-2 RR-90-1478 (Cps) 9-2 ~aZ <+(

Stack Flow FI-1-90-271 (ofm) 9 53 4~~~ l=t'0 o 0 (Common - on Unit 1)

Remarks:

After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager Maintenance Manager Operations Manager REP Communicator NRC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy)

"Revision

Page 1 of 3 BFN - XPD BFN, IP-20 Attachment A APB l7 )90~)

Unit No. Time (~>G

~aa ster u en ~ate 1 Reactor Level (Accident) LI 3-62 (inches) 9-3 (Zero at top of fuel)

I Drywell Low Pressure PI 64-'39A or I XR-64-159 pen 2 (-5 to +5 psig) 9-3 only)'-3

.(Low range)

(Unit 1 Drywell Wide Range ,. .PI-64-'l60A or 9-3 ~/

Pressure XR-64<<159 pen (Unit 1 only) 1 (0 to 300 psig)

~l Drywe11 Air Temperature TR 64<<52 ( F) (black pen)

Torus Mater Temperature TX 64-55A ( F) (Units 2 3) 9-3 I

TR 64-161/162 (blue pen)

(Unit 1) '.

Torus Hater Level LX-64<<159A (0-20') 9-3 XR-64-159 pen 3 (0-240")

(Unit 1 only)

HPCI Flow FXC 73-33 (gpm)

RCXC Flow FXC 71-36A (gpm)

NRC/C RHR.,Loop I Pressuve- PI 74 51 (psig) 9-3 Rpt 81-19 RHR Loop I Flow FX 74-50 (gpm) 9-3 RHR Loop II Pressure PI 74-65 (psig) 9-3 RHR Loop XX Flow" FX 74-64 (gpm) 9-3 Core Spray Loop I Press. . PX 75-20 (psig) 9-.3 e

Core Spray Loop I Flow FX 75-21 (gpm) 9-3 I

Core Spray Loop XI Press PI 75>>48 (psig) 9-3 86 Core Spray Loop II Flow FI 75-49 (gpm)

Aftev completion, hand carry to secretary in hallway outside TSC for'istribution.

~stribu~ti Technical Assessment Manager NRC Communicator Haintenance Manager Radiochemical Engineer Operations Hanager Health Physics

" 'REP Communicator, DNPEC (Telecopy)

>>Revision a ~

Page 2 of 3

~

BFN - IP BFN, IP-20 Attachment A Unit No. ~AP r7 Ig84 Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9>>4 (Valid only running) if reciro.

pumps Loop B ( F) black Reactor Level (Accident) LX 3-46A (inches)

(Zero at inst. zero) ~ ~

Reactor Pressuro PI 3-54 (psia) 9-5 Reactor Level (Normal ) LX 3-53 (inches) 9-5 (Zero at inst. zero) 1 Condo naor vacuum P/TR 2-2 (in Hg) black 9-6

( ] ) Torus H R 76-39 or 37 H2 conc. 2 ($ > 9-54> 55 (1) Tor'us 0 4 76-43 or 41 .($ ) 9-54'5 '3. /0o 02 conc ~

~

2 (1) Drywell H conc. H R 76-39 or 37 9-54, 55 2 ($ )

(1) Dr ywell 02 conc. 02R 76-43 or 41 (~) 9-54~ 55 (1) HS 76-49 and HS 76-59 must bo checked to determine what recorder pens are active.

f t Other NRC/C s ec Rpt 81-19 ui me t crab t Cheek tho listed equipment for operability. If'ess than fully operable, explain in REMARKS.

, y~ui~men erbe Int ~u)~men: ~e~alQe Standby Liquid Control ADS/Relief Viva

'CRD Pumps SBGT

.Coro Spray Control Room Emer. Press.

RHR (LPCI) CAD RHR (CTMT Cooling) Diesels (Ul U2)

HPCI Diesels (U3)

RCIC'ECM 500 KY Po~er RHRSH 161 KV Power Feedwater System 4 KV System Condensato 480 V System Containment System'ri'mary DC Power After completion, hand carry to secretary in hallway outside TSC for distr ibution.,

Technical Assessmont Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telocopy)

Operations Manager Radiochemical Engineer

<<Revision

Page 1 of 3 BFN IPD BFN, XP-20 At tachment A APf< l.7 lq8~1 Unit No. Tine l +O Zaara eter stru en ~arLee /earn Reactor Level (Accident) LX 3-62 (inches) ~OO (Zero at top of fuel)

Drywell Low Pressure PI 64-'39A or (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9-3 (Unit 1 only)'

Drywell Mide Range  :, PX-64-160A or 9-3 Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen) 9-3 Torus Mater Temperature TX 64-55A ( F) (Units 2 3) 9-3 QO TR 64-161/162 (blue pen) 9-3 /

(Unit 1)

Torus Mater Level LI-64<<159A (0-20')

XR-64-159 pen 3 (0-240")

(Unit 1 only)

HPCI Flow FXC 73-33 (gpm) 9 3 RCXC 5'low FIC 71-36A (gpm) 9-3 NRC/C RHR,Loop X Pressure- PI 74-51 (psig)

Rpt 81-'l9 4 RHR Loop' Flow FX 74-50 (gpm)

RHR Loop XX Pressure PX 74-65 (psig) 9-3

'4 a

RHR Loop XX Flow"', ,FX 74-64 (gpm) 9-3 4'

I Core Spray Loop I Press. PI 75-20 (psig) 9-.3 -QO e

Core Spray Loop I Flow FI 75-21 (gpm) 9-3 Core Spray Loop IX Press PX 75-48 (psig)

Core Spray Loop II Flow FX 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics REP Communicator DNPEC (Telecopy)

~Revision

C Page 3 of 3

~

BFN XPD BFN, IP-20 Attachment A APR 1? ~."-BC Unit No. Time:

l SBGTS, Total Flow = FX 65 - 50 + FX - 65 71 (SCFM x1000) 9-25 Drywel 1 Radiation Unit 1 RH-90-272A (R/hr) 9-54 Unit 1 RR-90-273A (R/hr) 9-55 Unit 2 RR-90-272A (R/hr) 9-54 Unit 2 RR-90-273A (R/hr ) 9-55 Unit RH-90-272A (R/hr) 9<<54

'nit 33 =.. RR-90-273A (R/hr ) 9-55 Torus Radiation Unit 1 HR-90-272'8(H/hr) 9-54 Unit; 1 RR-90-273'8 (R/hr) 9-55 Unit 2 RR-90-272B (R/hr) 9 54 Unit 2 RR-90-273B (R/hr) 9-55 Urd.t 3 RH-90-272B (R/hr) 9-54 Unit 3 RR-90-273B (R/hr) 9-55 I

Stack Radiation

'I RR-90-147A (Cps) 9-2 +k.

RR-90-147B (Cps) 9-2 Stack Flow FX-1-90-271 (c fm) 9 53 Q~ 4a 000 NRC/C (Common - on Unit 'l)

Rpt 81-19 Remarks:

I After completion, hand carry to'seer etary in hallway outside TSC for distribution. = '.

'j *,';,'-

\

Technical Assessment Manager.,

Maintenance Manager Operations Manager

.REP Communicator NHC Communicator Radiochemical Engineer Health Physics DNPEC (Telecopy) e IRevision

Pace 2 of 3

~

BFN IP BFN, IP-20 Attachment A APR > 7 jgsq Unit Nn.

Reactor Coolant Temp.

(Valid only if recirc.

TR 68-2 Loop A ( F) red 9-4 j ~o pumps running) Loop B ( F) black Reactor Level (Accident) LI 3-46A (inches)

(Zero at inst. zero)

Reactor Pressure PI 3-54 (psia) 9-5 Reactor Level (Normal) LI 3-53 (inches) 9-5 (Zero at inst. zero) l Condenser

( ) Torus vacuum P/TR 2-2 (in Hg) black 9-6 H2 conc. H R 2

76-39 or 37 ($ ) 9-54N 55 (1) Torus - O 4 76-43 or 41 (5) '3. (5o 02 conc. 2 9<<54N 55 (l)Drywell H2 conc. H R 76-39 or 37 ($ ) 9-54N 55 2

(l)Drywell 02 conc. O R 76-43 or 41 (C) 9-54N 55

'3 1 ~p (l)HS 76-49 and HS 76-59 must be checked to determine what recorder pens are active.

NRC/C Othe s ec f Rpt 81-19 u me er t - Check the listed equipment for operability. If less than fully oper able, explain in REMARKS.

ggui~e~n e e ~u)~n Standby Liquid Control ADS/Relief Vlvs CRD Pumps SBGT

.Core Spray Control Room v, Emer. Press.

RHR (LPCI) , CAD RHR (CTMT Cooling) Diesels (U1 U2)

, 'PCI Diesels (U3)

RCIC; RECT 5pp KV Power RHRSW 161 KV Power Feedwater System 4 KV System Condensate System 480 V System Primary Containment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicator DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

Page 1 of 3 BFN IPD BFN, IP-20 Attachment A APl< 1.7 ji)U'1 Unit No. 1 Time 30 ara eter ntuen Jarae], Qe~dn~

Reactor Level (Accident) LI 3-62 (inches) 9-3 (Zero at top of fuel)

Drywell Low Pressure PX 64-39A or (Low range) XR-64-159 pen 2 (-5 to +5 psig) 9>>3 (Unit 1 only)

Drywcll Wide Range PX-64-160A or 9-3 Pressure XR-64-159 pen 1 (0 to 300 psig)

(Unit 1 only)

Drywell Air Temperature TR 64-52 ( F) (black pen) 9-3 0 cyQ Torus Water Temperature TX 64-55A ( F) (Units 2 3) 9-3 TR 64-161/162 (blue pen) 9-3 (Unit 1)

Torus Water Level LI-64-159A (0-20') 9-3 XR-64-159 pen 3 (0-240")

(Unit 1 only)

~ '>

HPCI Flow RCIC Flow FXC FXC 73-33 (gpm)71-36A (gpm) 9"3 9-3 NRC/C RHR.Loop I Pressure PI 74-51 (psig) 9-3 So Rpt 81-19 RHR Loop I Flow FX 74-50 (gpm) 9-3 RHR Loop II Pressure PI 74-65 (psig) 9-3 RHR Loop II Flow . FX 74-64 (gpm) 9-3 Core Spray Loop I Press. PX 75-20 (psig) 9~3 Core Spray Loop I Flow FX 75-21 (gpm) 9-3 Core Spray Loop XI Press PX 75-48 (psig) 9-3 Core Spr ay Loop II Flow FI 75-49 (gpm) 9-3 After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager NRC Communicator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics REP Communicator DNPEC (Telecopy)

~Revision

Page 2 of 3 BFN - IP BFN, IP-20 Attachment A 984 Unit No. I Reactor Coolant Temp. TR 68-2 Loop A ( F) red 9-4 (Valid only if recirc.

running} black pumps Loop B ( F) 9 4 Reactor Level (Accident) LI 3-46A (inches) 9-5 (Zero at inst. zero)

Reactor Pressure PI 3-54 (psia) 9-5 Reactor Lovel (Normal) LI 3-53 (inches) 9-5 (Zero at inst. zero)

(l)Condenser vacuum P/TR 2-2 (in Hg) black 9-6 +$ lt Torus H2 conc. AH R 76-39 or 37 2 ($ ) 9"54> 55 .0 70 (1) Torus 02 conc. ~

0 4 76-43 or ($ ) 9-54> 55 3.'f )a 2

(l)Drywell H conc, H R 76-39 or 37 (5) 9-54> 55 2

(l)Drywell 02 conc, 02R 76-43 or (5) 9-54~ 55 3 7 00 (l) HS 76-49 and HS 76-59 must be checked to determine what r ecorder pens are active. ~ ~

NRCIC Other s ec f Rpt 81-19 than fully operable, explain in REMARKS.

~ament crab e n t ggu 1gi~ent /~elle Standby Liquid Cont;rol ADStRelief Vlvs CRD Pumps SBGT

.Core Spray Control Room Emer. Press.

RHR (LPCI) CAD RHR (CTMT Cooling), Diesels (Ul U2)

HPCI Diesels (U3)

RCXC .

EECM 500 KV Power RHRSM 161 KY Power Feedwater System 4 KV System Condensate System 480 Y System Primary Cont;ainment DC Power After completion, hand carry to secretary in hallway outside TSC for distribution.

Technical Assessment Manager REP Communicator Health Physics Maintenance Manager NRC Communicat;or DNPEC (Telecopy)

Operations Manager Radiochemical Engineer

<<Revision

0 Page 3 of 3

~

BFN XPD BFil, XP-20 Attachment A APR 17 1984 Unit Un. Time: ~ c30 SBGTS Total Flow = FX 65 - 50 + FX-- 65 - 71 (SCFM x1000) 9<<25 Drywell Radiation Urd.t 1 RR-90-272A (H/hr) 9-54 k Unit 1 RR-90-273A (R/hr) 9-55 g Unit 2 RR-90-272A (R/hr) 9-54 Unit 2 HH-90-273A (H/hr) 9-55 Unit 3 RR-90-272A (R/hr) 9-54

'Unit 3 RR-90-273A (R/hr) 9-55 .~nn .

Torus Radiation Unit 1 RH<<90-272K 8 (R/hr) 9-54 Urd.t 1 RR-90-273'R/hr) 9-55 Unit 2 RR-90-272B (R/hr) 9-54 Unit 2 RR<<90-273B (R/hr) 9-55 Urd.t 3 RR-90-272B (R/hr ) 9-54 Urd.t 3 RR-90-273B (R/hr') 9-55 Stack Radiation RR-90-147A (Cps) 9-2 RR-90-147B (Cps) 9-2 00'9 t RHC/C Rpt 81-19 Stack Flow (Common Remarks:

- on Unit 1)

FX-1-90-271 (cfm) ,

After completion, hand carry to secretary in hallway outside TSC for distribution.

st ibu Technical Assessment Manager Maintenance Manager Operations Manager REP Communicator HHC Communicator Radiochemical Engineer Health Physics Dtt/PEC (Telecopy)

IHevision

Page 3 of 3 BFN IPD BFN, IP-20 Attachment A APR 17 1-""84 Timer SBGTS Total Flow = FI 65 - 50 + FI 65 - 71 (SCFM x1000) 9-25 Drywell Radiation Unit 1 RR-90-272A (R/hr) 9-54 I O Unit 1 RR-90-273A (R/hr) 9-55 Unit 2 RR-90-272A (R/hr ) 9-54 Unit 2 Unit 3

,Unit 3 RR-90-273A (R/hr)

RR-90-272A (R/hr)

RR-90-273A (R/hr) 9-55 9-54 9<<55

~3 Torus Radiation Unit 1 RR-90-272A (R/hr) 9-54 . $ 2-P Unit 1 RR-90>>273A (R/hr) 9-55 Unit 2 RR-90-272B (R/hr) 9-54 Unit 2 RR-90-273B (R/hr) 9<<55 Unit 3 RR-90-272B (R/hr) 9-54 Unit 3 RR-90-273B (R/hr) 9-'55 Stack Radiation RR-90-147A (Cps) 9-2 ++a RR-90-147B (Cps) 9-2 Stack Flow FI-1-90-271 (cfm) 9-53 k kD NRC/C (Common - on Unit 1)

~ )Ipt 81-19 Remar ks r After completion, hand carry to secretary in hallway outside TSC for distribution.

st bu Technical Assessment Manager ~( \

k ~

Maintenance Manager Operations Manager

.REP Communicator NRC Communicator Radiochemical Engineer

~k k Health Physics 9NPEC (Telecopy)

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occr55 "rynril 1 5. cl rt55) occiss.'/S63./2'<< n J A'reine c)vij: 'rn/ hnnosr/ ~ ~ p@rris(m EI rsrc I j+ 0rywc// 'fIS49 L<< ~ rrd llnrm EI S3988 I S5/nlpr / pres sore C/Ielrlber 6 s~:EI5)r0 ssion General Area Radiation Levels Time ~or<</ cf t// ter c c S t RI R~> R4 .-.e SJ /S2'-3" 2ee0" 26"0" 26:0 2b" 0" 26>0 22 V" 8>0 <<5/ crdne Cob Re Fuelin>2 PC>fo/Or pic>I Fords c/con up S!>tc/d plug /6 pteccs) h'a / /i >mr r<<m7i>, Dd/es r Bepdrdlor Dry> sfordge poo/~ ~Fc!e/ poo/ Gd/es S ~lord ge C!C JtLCS> SJC cttif!> h!III> bd 4 Jrrt/<<>J/ rcc 1<<n~ I ~~4/60r rc/Mn re/ E/ 625.2S I Ef "~S> I c> Ct'csed L R dcfor c/edn rp cco/I'.srer 4 tr s!ter> /fedf't'$0 I[ b~mrr/ B > M Il II Core I gl iF ~ 'JZS> f, , ps/I/Cr<<> I D!ydrdug. >I F/98<N; pc'dc /or can// J/ I!nt'If !essel- IS%>tl'/y>f!rtf Conlrol >I/K IJ I >tie> I O~ Idr -"/ 5 />f. /2 ~ unite I r . I , ',Cfccr Ckc>l I I I rtsS ) ' 'c>CCCII Pry<cress. rtc r'Ice<</ c)uttL tco/ />Jntlfr>/; p!cilrcrm rl cS:c I 96s./2'i 0ry>!Ie// Bc/mp~~ F/94992'tdr/rvm FI539SB. 'J . . ssure stgcrssslon C/Id<<;ber F/SS7. General Area Radiacion Levels Tillle t u J;>$ $ io~ /wuals>>~ Ft.5// ~l sc S El S+~ ,R I gRig'ay/ /52'-3" 2590" 26$ 0 26'-0 26 .0 24 c0 3:0 /25 t orane Cob /tefvel/ng Pt>$ /cr platform c/ron up sh>'rid plug h'o I /$ >/er ~EJ $> $ . (6 p>ected $ a>>r>>$ $ l Gates pose. Rd~e: QC9 n R /hr Dr On s/or age poo/~ r se ara/'Or Fve/ 5/on a qe pool Gates ~ g;r Ac<iu/~V'/>> > ci- /<Oi/ bd rl i':,,ooa~ A 5>> I t sr+At ~ 'I>>/ C/cc>>.w ccc/m/h raC />r/$ d'/ o25. 25 ~ >62> 2$ I' . I ' ~ I'<tel. <I.~C 0/os tet roocrr>>> Reactor clean /p $ .$ / 'r he'at ece$ $ /ngers g.aoe YW4 kc I <>6>5>> jhld>$ hozrr/ B a)rehangers) I I Core II. I 4m gPj r(=h'0  ; ~ /-'.$>///orrr. hgdsmrtw 5 fl58488; peoctor wssc/- 'Vtydravlic l 5c.C (( coo/no/ vr$ Control >tz $ >rr> I Pea,' l >o r 5/5/ vn'ta =/ 5 1/ +2 <~r 65:O, ttorrr> .C~r'/$ ' bccrt1 $ here/s, ~ $ gryrr// f/565 /2' . 'Zi'r:/$ >n>/ e u>$ . $ <C$ / t>cr>>'//>r>/ A ~ ~ p/>$ /ro/$ >$ C/55$ :c/ Dry@a// f/549 97 ( 5vmp~ / pcs >cire scrplE'5'n I .i I C/$+$//$ erI f/$Ã 6 ~/ E/ z/q C-0/ry'ro flOr h e56/IgC OO AIRLOCK pAR L><< s <<4 f 3'0-dr - So ~Rfg 7>ik Li~ ~ g, +d. 3Dowl+/I lgt - SO ~@ OO g3R nv EQUIPMENT AIRLOCK General Area Radiation Levels Ti e 7'.3D p /< <<rd /cd} I.err//I'd f'~d ~ l<uf l5 O~ El Pcs, c!5 13 - ~ > Z'/ RI <<R<<l'D <<5'0" 26'-0 26<<0 /52'-3" 26"0" 26<<0 ' 3$ 0 I+Y'" I 8 tlat /z5/ crane Cdb //e Fue/tng pedetCr p/dr FOrn/ e/edn up 6/I>etd Pt<<<<9 //a / Ir! /er ~EI<<<<i.i I /6 pieces) w rrsn<<li<< G<<$ /e$ ~ Ocs e 3C/" m I<<c'!c: g /]sr /)r)t<<<<r .~eparch/o Ster dge pOO/~ poo/ ~ Fuc/ 9/or r/ ge $ ~6 G<<$ /<<<<9 14GP<<vi fc , uO<<i ed .a r'C .+/COr $ xA~n Sr r / rid/ Sr<Pl r<<c rd /I~ C/<<r~~<<<<c sccsn<<rs/i C/<<dre<<ea I E/ 625. 25 g~ /cl/<<< ~E6PI ii l<< c<< C/@seel eootr /leuc/or c/edn rp Pa r~>C c/~"~~ nr/er hegf twit ewer<<<<3//gers q,/ E-$t'~</cc, l </S<<) barr<</ 6 r sritdn <</ ~l I C Ccsr I, 4/393o r 'Di&AI lc /:.cdt/erm f/ <<84Nl l /ted<<terr x'see/ ~- Ohydrd I//rc 5'ee } <<Confro/<</nits r<<<<j/<<1r<<<< Conk c<</ I I 9/Sv' un/Pe Pefcl't l =/,5//./2 I Cled r Ckdr dccess Pld /form ' 0ryrrl/ 'ccess<< L SKAG@ f/963,/2 e <<'r'n/ ~}<<np Ic nl 4 "~, pc/ac/nr 6/SS <<<<j P'jj pre$ $ <<<<re dc/<<cA'.Owon r 6f/537 Dry<<eel/ 5ump<< / . j/549 9~~ / /'/d I/am<< f/93988 <<,J I rchant A R LOCK I R X-I 565 co aaJ ( (+L goo'X 593'NIT - 1 AR& IRK,9o ~ <9 22$ j Qc~ A.e~ A.'c.hvA~ ql', Ave~ dc, I Z.~g-2 qC. cc. p~~fic~lgfc Q i ~ 3 Q/ gAI t A6-fo-5'5 EQUIPHENT AIRLOCK General Area Radiation Levels Time lg ~ S + p /+ IicntI I rcrr/ rr 71 on /e c /5 g Cjg ~ ~g tl=/'S:59" IS2'-3 26c cg 264 26"c5"'6559" 23.3r IQY"" +c. crane Cab /IeFuelinc2 Ew lcr pta>Form I!tan un "hctld plug Aa/ /I 'ter ~cccc .c /6 P'eecc5) I ig;micI, Gates Pos< Ante: 30 rnid/hr r Or in de stordgc'oo/~ I cti dtor I pool Gd/a 9 ~ Fud/ Star d qe 5 clccc<<ctc Scclccuih Slag cd 4 < a/i I IVI rIC Icrk~ AIir A('l iud""I ~ ~~WICOr .huWn 'r<kr IIOard A E/6ZS.2S '< Cia/ 'hat ~l'lccccs II ( I c I~ ci j~ I'o,+:culate. G/oscd ~i L //cdchor clean ip ruat etc/I tngerd Qi/ i:-3p 4560 v salon hn)rc/ B ir iten neaP bl Y ~l I~ .I II, Core EIS&.O r 5ce I i/D hydra i' contra/italy'ts c PJI/teria E/584883 Peec Iecsct Ior ~ riiiIlicc Dtydrau/2 Contr o/ gaddi I l 9 Jft unilid I = /.5 lt.t2 I 'CJtvr . Cker I ~ plat/'arm cICCC 5 5 I $4/II Drynttl fl56 J,I2'. I pc'rnl<<re/ r)pep Irni ~~')Sit C'I>~~tin I SJ~I/i c Drys&/ 'I549 I 92' rid i/arm f/53966 6 un'~ Pressure J455cression CIIa.<'dec I t EIS3'Z I Dill[ A I R LOCI', .o Q 0 Cl 00 RX-I 565 0 0 0 0 RX - 593'NIT l ARw I R6. 9D ~ iV Res Qe~ A.e~ A<w Ac]hctl4q ggs5 /vga chare.,~l 2.+ 5-2 < C. cc-p4Hi<+1hkg $ ( p 3 Q/ gAA I RE-fn 55 EQUIPHENT AIRLOCK General Area Radiation Levels Time I 9C ( p J f g'~'ocr /MD<<. IS D'~ s~g El rag IS2'-3" ZS'0" 26 00 2650 )~Y'650 26".0 ICS/ crone Cob Pe Fueling Pcd c Icr pie>Form /iron VP <<h)rid P/vs I/a I f/ //K / ~tlcl44 /6 psccr5) w rrlmin, Gdte5 j~/C S~O /5ry n nepdndton stondgo I Poo/~ I pool Gd/09 ~ Fete/ 5/ond ge Dose P.fata; 5 n~ C//As N 5DcrAv/l zS. ~r ri/ rr/ rcC ID 30 n)R /bi- )I/65/ oct,rI '/ (~4/Cor 5~Md ~ Sr<<. Io E'/ 66$ . ZS ~rr Szi II ) C hdr 6O/) I C/os co/ ooa// A Redo/on c*dn /p

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5/ twd ercictngens I ~I 1 ccr 1 CIIII/~6 g ~ C //r.c, c/S9)o 4m 6/dl/Crrn Core I DDrr<<At lr , 'f/56489; pc'dc tor P/~v4 control vnit5 s Jc'I . I( rcv Arcc Con/ro/ 5'e6. I ~/4/ S/St cln//d I =/5 it.ra yon<I'l I 'C/ocr I. PIC/form .CMr'//C/Jc ,occr55 I "/I rc/rrnt r ai~ crnt hrn,'g pry 0r// fl56S.IZ . p/ '/rocn/ cl Sz/5 5'( r Gree// ~ '/549 92' Sc/nip~<< Pres \ I SOCC Sugars. 55/On ~ ~ Chd.c.ken 4 EISJ f. c I T b [IIIII] A R LOCK I JAR L~~< Q o ~ ~4 c'f - f 5 ~ I Zf -2$ 0/g Q Cl QQ R X-I 565 Q Q Q 0 RX - 593'NIT 1 RRW I R6,9o -iV 2.Z Sg go~ A.e~ A<~ Ac/7&0~+ fLtg /vga chare,os.l ~ 2 ~~ p 2 4 Q cc-l~kc q.l P<<hie p 3g/ (AR I R6-1o. 55 EQUIPl'1ENT AIRLOCK II P Tl',AM !.EhDER !).)t i>>: >>b< ~ ~ v' nII ' T = 4 hours (approximate) When'hem lab is requested to collect reactor coolant sample I'jI 4; I c' ')>>; >>>>,, "E ~ ~ Dose ra to from a one liter, bottle will be: 5 R/hr at contact 100 mR/hr a t 1 foo t I stimated from activity of 0.3 Ci in one liter SamplInI, station Gonera.l. area 2.5 R/hr Extremity - 20 R/hr i ~ I ~ ~ ~ lg ~ ~ I/ f, I s') s /i r BKOVHS FERRY NUCLEAR PLANT . 1984 REP EXERCISE H TEA~Lt LEADER ' r 24, 198 'cto Time T = 4 hours (a prox mate) " Mhen chem lab is requested to collect reactor coolant sample tfessage: ,THIS IS A II,I . Dose rate from a one iter b tie will be: 500 R/hr at ontact 2 R/hr at ne foot Estimated from a tivity of 0.3 Ci in one liter g 1 0 Post Accident Sample RCS Inventory 1 Hour After Fuel Damage Reactor Coolant Concentration Nuclide (Micro curie/gm) I 131 2.14 E+2 I 132 2.10 E+2 I 133 4.09 E+2 I 134 1.72 E+2 I 13.5 3.42 E+2 N 16 0.0 Rb 89 9.39 Cs 134 1.65 E+2 Cs 136 1.03 Cs 137 2.2 E+1 Cs 138 4.05 Co 60 3.28 E-1 Sr 89 1.02 E-1 Sr 90 5.16 E-3 Sr 91 'r

2. 61 92 7. 67 Te(M) 131 7.44 E-2 Te 132 7. 54 E-3 Ba(M) 13? 8.85 E-1 Ba 140 3.04 'E-1 La 142 2. 92 Pr 143 3.04 E-2 HBM:JME 10/1/84

ENVIRONMENTAL DATA PACKAGE Environmental Field Data does not reflect the 50% reduction in the radio-logical release rate which occurs at T = 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Mhile inplant radiolog-ical data will take the reduction into account, offsite data will not. A-three hour continuous release was postulated for offsite data to ensure that TVA and State of Alabama field teams have a full three hours of data with measurable dose rates for all meteorological stability classes. Monitoring locations not covered by the map overlay are assumed to be background. Background readings should be in the range of 0.02 0.04 mR/hr for survey instrument readings and 2 E-11 5 E-11 uCi/cc of I-131 for air samples. Instructions: Choose the data package based on wind speed at T = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (-3 m/s or +3 m/s) Use the same package regardless of wind speed changes during the drill. l;0 i5 7 5 ll ) ~en< ~B / in X . ,~,. <.~. (w/~ y=inc,-l5I cancenkra4~ (pQ <3 Plorz: (a-6) = ax lo

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