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Documents 841031 Telcon Re Exercise Scenario.Comments on Onsite Radiation Levels,Offsite Radiological data,post- Accident Sampling Data,Area Radiation Monitor Readings & Victim Contamination Levels Enumerated.Related Info Encl
	ML20125B696
Person / Time
Site:	Perry
Issue date:	11/14/1984
From:	Stoetzel G; Battelle Memorial Institute, PACIFIC NORTHWEST NATION
To:	Snell W; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20125B635	List: IA-84-896, Partial Response to FOIA Request for Records Re NRC or FEMA Evaluation of 841128 Emergency Planning Drill for Facility. Forwards App a Documents.Documents Also Available in PDR; ML20125B633; ML20125B656; ML20125B675; ML20125B696;
References
	FOIA-84-896 NUDOCS 8506110504
	Download: ML20125B696 (705)
	v • d • e

{{#Wiki_filter:, _____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ __ __ ____ _ _ _ _ s ' Attachment 24 OBaHelle Pacific Northwest Laboratories P.O. Box 999 Richland, Washington U.S.A. 99352 November 14, 1984 relephone (509) , Telex 15-2874 Mr. William Snell U.S. Nuclear Regulatory Comission Region III Office of Inspection and Enforcement 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Bill:

PERRY EXERCISE SCENARIO REVIEW The following is a list of PNL coments on the Perry Exercise Scenario which were given to you by Gary Bethke (COMEX) and myself over the phone on October 31: 4

1. Message #14 - There is no contingency message for calling offsite fire support.

q. ~

2. Message #18 - Point 3; under the controllers notes (discusses erratic operation of winch) should be included in the message given to the Fuel Handling Bridge Operator. The fact that the fuel bundle was jostled could 4

be important in suspecting potential airborne problems. 2

3. Section8.2-Whyareg'tvictimcontaminationlevelsgivenincpm/100cm instead of dpm/100 cm . Instruments will read in cpm.

4. Messages (In General) - From the plant status information it not clear if the players in the Control Room will know which ARMS are alarming.

]
 .                          5. Section 8.2(B) - The post-accident sampling data does not contain data on j                                 general radiation levels in the PASS area (e.g., exposure rates from the
.;                               samples drawn and from the system panel).

6. Section 8.2(C) - It appears that ARM readings will be relied on as the general radiation levels to be given inplant teams during work in the

 ;                               plant. However, has any thought been given to the following:

radiation levels in areas without ARMS e airborne contamination levels y
surface contamination levels.

 ;                           7. Section 8.2(D) - Comments on onsite radiation levels:
            -

More detailed maps should be provided controllers. Present maps would be difficult to pinpoint exact locations.

hDR y 4 850124 l' HIATTB4-89s pM NOV 191984 J/f.,

Mr. William Snell November 12, 1984 ' Page'2

                                                         .                     There should be some method of determining off-centerline radiation levels.                                                                                                  ,
                                                         .                     The introduction to Section 8.2(D) indicates a maximum onsite dose to the whole body of 24 rem /hr, however, the maximum value on 4                                                                               Table 8.1 is 2440 mrem /hr (2.4 rem /hr).

i 8. Section 8.3 - Comments on offsite radiological data: d

j . Again more det' ailed maps should be provided to the controllers.

" . The scenario indicates that off-centerline values should be obtained q by linearly interpolating between centerline values and background 1 at the plume boundary. The controller won't have time to do this in the field, more simplified guidance should be provided such as expo-

;j                                                                             sure rate isopleths.

] . With the high thyroid doses offsite for realism sake there should be ground contamination values. l, d 9. At 0900 the ARM alarm in the refueling building is cleared on the alarm i sumn'ary data sheets but radiation levels remain at 2 R/hr. 4, 10. There is not guidance provided for controllers or players concerning

   '                                              actions to lower the fuel assembly which was hoisted above the upper cut-I                '

out on the refueling crane. This sub-scenario which was used to escalate emergency classification is left hanging! j 11. The parted flange in the line to the fuel pool cleanup backwash receiver

   ;                                              tank does not result in any increased ARM or airborne readings. The resin being backwashed is generally very " hot." This sub-scenario, like the raised fuel assembly, is not addressed in later controller or participant messages. Messages should indicate if the backwash operation is allowed to be completed, if it is secured or if the pipe break is repaired. A5

to 10 gpm leak into the radwaste tank area from this source would create

   !                                              a considerable problem if allowed to continue (as implied by the existing scenario).

12. The data graphs for reactor power level, pressure, etc. do not reflect the pertabations which would be immediately obvious following a safety relief valve (SRV) failure shortly after 1000, f

4 13. At about 1005, with an SRV failed open, recirc pumps tripped and all rods

   ,                                              stuck out. Power is decreased to 57%. The reason for tripping recirc pumps in this situation is to reduce power. All studies this reviewer has seen show that power would be reduced.to about 35% at this time.

Recommend checking this power level against plant specific ATWS studies.

14. By 1010 the offgas pretreatment and main steam line radiation monitor

should have decreased irr proportion to the power level decrease. They I i

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Mr. William Snell November 12, 1984 Page 3

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are still shown at 100% power levels. The MSL rad monitor reacts within seconds since it is primarily monitoring the N-16 gamma in the supersonic , steam flow from the reactor. The offgas detector will be' delayed depend-ing on detector location and holdup times.

15. It is doubtful that operators would wait 15 minutes to initiate standby .

liquid control (SBLC) following a failure to scram (all rods stuck out at position 48). They may initiate SBLC as early as 1003 vs.1015. j 16. Throughout the entire scenario there is no reason provided for the failure to scram. The only possible reason for such a failure is a full scram ? discharge volume (SDV). No SDV instrument volume level readings or SDV d special instrumentation readings are provided in scenario data. The con- " troller information provides no reasons for the failure of alternate scram methods or any guidance as to when the operators may assumed that they 1 are trying the various prescribed alternate rod insertion methods (e.g., , j single rod scram, increasing CRD pump discharge pressure, draining the

'                           SDV,etc.). This aspect of the scenario is terribly unrealistic.

17. The feedwater flow data from 1030 to 1050 is in error in that turbine driven feed pump flow is listed as 8.8 gpm (should at least be 8800 gpm) j ar:' that total feed flow indication varies from 3.5 to 1.2 MLBM/hr,.

( .18. From 1000 to 1200, drywell radiation stays at 1.0 R/hr with an SRV con-tinuously discharging. At 1200 it suddenly jumps to 300 R/hr. This is j (" - not realistic. The levels should increase gradually over the period from j 1.0 to %20 to 50 R/hr. The 300 R/hr at 1200 is indication of significant i cladding failure; at this point the core is not uncovered, and as all

;                           G.E. Owners should know, the fuel is relatively unaffected until <2/3 i                           core covered.

l l 19. Throughout the period that the SRV is failed open the data sheets indi-1 cate that all 19 SRV's are shut. We know that at least one is open and j it would be fairly obvious which one. This information is not provided for the operators (e.g., SRV open, tailpipe temperature, differential l heating of the suppression pool, etc.).

20. It is not clear at 1045 '1050 that the 16% value for turbine bypass valve position would be adequate to receive the power that the plant is continu-ing to produce. If the 16% is 16% power then it makes sense, if it is l 16% of the " normal" BWR bypass capacity of $25% power then additional y, SRV's should probably be opened.

'                      21. At 1155 the failed open SRV shuts. Power remains at 8% with all rods out, no increase in turbine bypass valve position and no successful SBLC.

The SRV closure would cause a void collapse, a power increase and ... (recommend that authors obtain a copy of their plant specific ATWAS response study or copies of Oak Ridge studies on the subject).

22. At 1200 feed pump flow is shown as 0 but total feedflow at 1.2 MLBM/hr.

3 Mr. William Sn211 November 12, 1984 Page 4

23. At 1201 the MSIV's go shut. Prior to this time the failed open SRV had apparently been causing the mismatch in individual steam line flow indi-cation (line "D" indicating higher than A, B, C). This is an indication that the main steam line flow monitors are located upstream of the SRV connection point on the steam lines. Additional SRV's should open at H this point. When the operators later manually open the ADS SRV's no steam flow is shown. Recommend that authors check position of flow moni-y tors with respect to SRV's and MSIV's, s

i 24. The narrative says that RCIC is initiated at 1201 but as late as 1205 no flow is shown in the system. It is also unclear why the narrative ini-tial conditions caution operators not to use RCIC except as a backup to i high pressure core spray (HPCS) and yet in the body of the scenario, RCIC i is brought on line well before HPCS. Unless there is a procedural prob-1 lem, it is not clear why the operators would not initiate HPCS at s1203 4 to save their core. At s1203 any additional sources of water would be

sufficient to save the core. There is no indication that HPCS is j unavailable.

j 25. It is not clear how drywell radiation levels can decrease from 6700 R/hr to 4400 R/hr between 1210 and 1340. There had been cladding and fuel 4 damage and as many as 8 ADS valves open during this period.

  ..                 26. Why was the Unit 2 vent stack used as the release pathway when the acci-11,                         dent was on Unit I? A general arrangement drawing and marked up P&ID l                        should be provided to NRC team evaluators describing the flow path from 4                        the Unit I containment to the Unit 2 stack. Data provided in the scenario did not make this path for release obvious. It is expected that revealing i

of this path will create the need for much additional in plant radiologi-i cal data.

27. Data is not provided to allow participants to calculate a release rate up the Unit 2 stack. The stack flow data is only in the material which is

1) for controllers only. It is assumed that an EPIP exists for converting j stack monitor cpm to pCi/sec. This conversion factor was not described

  !                         in the controller materials.

I 28. Is the top of the Unit 2 stack really a ground level release as indicated in the MIDAS computer program input? 3 j 29. Data provided for reactor coolant and containment atmosphere isotopic sample results contains no reference to time sampled or time available to participants. These data sheets must be labeled with a range of times when sample could have been obtained and a time delay stating when the results would be available to participants (providing the samples were requested in the first place).

30. The controller information contains an analysis of % cladding reacted based upon hydrogen levels in containment. Hydrogen levels do not appear to have been provided in participant data. It is difficult to imagine i,

b .. e - . -

Mr. William Snell November 12, 1984 Page 5

how 7% of the cladding could have undergone a zirc-water reaction in this scenario. The lowest water levels were %35% core uncovered and tempera-tures (and corresponding pressures) never went above normhl operating

- '.                       values. HPCS was running before level could have dropped below 2/3 core covered.
   ;                 31. Using simple assumptions about the size of the RCS and the containment;

if all of the reactor coolant were vaporized instantaneously into the

containment with none of the iodine plated out or retained in suppression pool water, the levels of airborne iodine concentration would still be an order of magnitude too high with respect to the concentrations of iodine

    !                       in the reactor coolant.

]j ' If I can provide any further information please call me at 509-375-2781.

Sincerely, A" G. A. S oetzel Senior Research Scientist Emergency Preparedness Group Health Physics Technology Section

, RADIOLOGICAL SCIENCES DEPARTMENT t x'

    !                GAS:mae cc:    DB Matthews

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g6 cV. . . -ef s OtRRY E-%Este.1 SB c.-. [dov 2 h L>> I.984 ' y , - s ('~ 2.0 EXERCISE INFORMATION 2.1 Exercise Participants ' The participants in the Exercise will include the following: ' i' 2.1.1 The Cleveland Electric Illuminatina Company [;

1. Facilities Manaaement and Support Personnel I i n

a. Control Room' Simulator .

b. Technical Support Center (TSC)

c. Operations Support Center (OSC) j:

d. !!

Emergency Operations Facility (EOF) [' C.

e. , Joint Public Information Center (JPIC) l'

2. Emer)aency Response Teams

[

a. Radiation Monitoring Teams (RMTs) '

 .           f                                                                                                     b.           Fire Brigade

c. First Aid Team

d. Emergency Maintenance Team

e. Security Force I'

f. Post Accident Sampling System (PASS) Team U' i

3 Health Physics Support :: e. 2.1.2 Off-Site Amencies/Ormanizations 7

                                                                .                                        1.      Federal

a. U Nuclear Regulatory Commission (NRC) .

b. b Federal Emergency Management Agency (FEMA) i'

c. United States Coast Guard (USCG) s;

                                                                                                      $ 2.

o State of Ohio . l \ a ** a. Adjutant General's Department 3 A - Disaster Services Agency (ODSA)

s Ohio National Guard c.

l ( b. Department of Health

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h. Public Utilities Commission I

1. Public Welfare Department

3. Local [

a. i-Lake County Disaster Services Agency and appro- J: priate supporting agencies. P 1

b. Geauga County Disaster Services Agency and !

appropriate supporting agencies. !

c. Ashtabula County Disaster Services Agency and appropriate supporting agencies. L i

d. Perry Township Fire Department

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e. Lake County Memorial Hospital, East f r

f. Ashtabula County Medical Center l'

4. Private (Participation Optional) ,

a. Duquesne Light Company '

b. Toledo E'dison Company

c. NUTECH Engineers, Inc. I

d. ECI Corp. t

e. Institute of Nuclear Power Operations 2.2 Exercise Ormanization '

The organization for this Exercise will consist of the Exercise Coordinator, the Controllars, the Evaluators, the Players, and the Observers, as follows: 2.2.1 The Exercise Coordinator will coordinate Exercise prepara-tions including the development of the scenario and

 .(                                                                                            controller input messages. He will control all aspects of A-the conduct of the Exercise; prepare a consolidated evaluation and critique report at the conclusion of the p                         - -    i 2'2 ((,,;* ,y                      - f-                          . ~.
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Evaluators will be identified by wearing red arm bands with white lettering stating " Evaluator."

2.2.4 Players include Perry Plant and other Illuminating Company personnel assigned'to perform emergency functions, as described in the Emergency Plan and Implementing Instruc-tions. Players from off-site organizations and agencies t (county, State, and private industry) are participants in the Exercise as described in their respective Emergency - Plans and Standard Operating Procedures, s Players will be identified by wearing blue arm bands with ! white lettering. ; 2.2.5 Observers from The Cleveland Electric Illuminating Company and other organizations may be authorized, on a limited I r basis, to participate in the Exercise solely for the [ purpose of observing Exercise activity for personal [ education. Observers will report initially to the PNPP } Emergency Planning Coordinator for credential review and authorized admittance. They will be provided with orien- [ tation information and appropriate exercise publication. : Observers will be identified b weari l-with white letteri !

                                                                                   -w-      i Requests to participate as an Observer will be made in writing and contain the Observer's full name, home address and phone number, and organizational affiliation.      Re-     -

quests to participate as Observers will be submitted to the Emergency Planning Coordinator no later than one week before the Exercise. ' j 2.3 Emergency Response Facilities During the Exercise, special facilities must be activated for the j simulated emergency' situation to manage, assess, and support emer-gency response. - 2.3.1 On-Site Facilities The Cleveland Electric Illuminating Company Emergency Response Facilities are: ' l

1. Control Room Simulator i The PNPP Control Room will not be used due to poten-tial interference with Unit 1 construction activities. For the Exercise, the PNPP Simulator, located on the first floor of the PNPP Training and

( Education Center (TEC), will be utilized (see Figure 2.1). Control Room emergency response measures will be exercised from the Simulator under 2-4 l t_

j_ + w.n ' m .~ a- -- -- '- -- L 4 the direction of the Shift Supervisor, acting as the Emergency Coordinator, until relieved by the - s Operations Manager. +

                                                                                                                                                           ,l j-                                                      2.      Technical Support Center (TSC)                                                      ,

U When emergency conditions escalate to an Alert status or higher, ' coordination for emergency response will M shift from the Control Room Simulator to the TSC, f! located in the 603' 6" level of the Service Building E (see Figure 2.2). The Operations Manager relieves U the Shift Supervisor as Emergency Coordinator and 3.; j- directs activities from the TSC until relieved by the ' p [ Emergency Coordinator in the EOF.. The TSC is the location from which technical management personnel J utilize information on plant status provided in the [.( j TSC to support actions being performed in the Control ' The TSC serves as the primary communications ' 1 Room. j source to the NRC, OSC, EOF, and off-site agencies, (; and will perform the functions of the EOF until the ,i l EOF is activated. ;1 j 3. Operations Support Center (OSC) l[ t1

      -C                                                y      The OSC, located on the 574' and 599' elevations of                                        2 l        V                                                      the Control Complex (see Figure 2.3), provides a                                             .'

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,                                             ,- f i, j .       location where emergency response teams can be j                                           4- i         V      assembled and coordinated during an emergency. The                                              '

'j OSC will be activated for emergency conditions i; classified as an Alert or higher, and may be acti- !;

vated for an Unusual Event at the discretion of the

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, Emergency Coordinator. h i l (,!

4. Emeraency Operations Facility CEOF) p.

' The EOF, located in tho' Training and Education Center (see Figure 2.4), will be activated for emergency j conditions classified as a Site Area Emergency or : i General Emergency (optional for the Alert status). , l The Emergency Coordinator (Vice President, Nuclear l Group) relieves the Operations Manager as Emergency ? L Coordinator and directs activities from the EOF. The !j !. EOF is the command post for coordination of response n i measures with off site organizations, assessment of ~ re.diological and environmental conditions and de-

                        .                                      termination of recommended protective actions for the                                       "

i public. The EOF also provides ,g d management of recovery operations under the direction of the f. l Recovery Director. i

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5. Joint Public Information Center (JPIC) s The JPIC, located at the Lakeland Community College in Kirtland, Ohio, (see Figure 2.5), provides the point of contact for the coordinated release of news and information to the news media and the general ,,

public. The JPIC is staffed by Illuminating Company, '? county, State, and Federal officials and will be f activated for amargency conditions classified as a P' Site Area Emergency g{, General Emergency (optional for the Alert status). 2.3.2 Off-Site Facilities

1. Lake County Facilities h L'

Emerzency Operations Center (EOC) - The temporary Lake County Emergency Operations Center will be {e p located in the basement of the Willoughby Police 0 Department. The Willoughby Police Department h Dispatch Center (located on the first floor) is i( temporarily the 24 hour notification point for Lake L. County. ; i, Hospital - Lake County Memorial Hospital East is F (~ located at Washington and Liberty Streets in - Painesville, Ohio. This is a general hospital which offers direct support to the Perry Nuclear Power Plant. Decontamination Facility - The Decontamination Station for emergency workers is located at the !, Auburn Career Center (a public vocational school), .e 8140 Auburn Road, Painesville, Ohio. ' Reception Center - The Reception Center for the ; exercise is located at South High School (Willoughby- ' Eastlake Schcal District) at 5000 Shankland Road, Willoughby, Ohio. This center includes a congregate care center and a decontamination team that can survey evacuees for contamination. ,;

2. Ashtabula County Facilities Emerzency Operations Center (EOC) - A permanent emergency operations center is located in the basement of the Ashtabula County Court House in -

Jefferson, Ohio. This facility houses the administrative offices of the Ashtabula County Disaster Services Agency and the County Sheriff's -

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Contents Of This Section A Section 6.1 Initial Conditions Section 6.2 Narrative Summary - Onsite Sequence of Events 1 Section 6.3 Narrative Summary - Offsite Sequence of Events l Section 6.4 Written Summary of Exercise Scenario 'l e N 44 u-D i s . J l Y I e l I i lI i' r e i I 4

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I h. 6.1 Initial Conditions [ f-g- f.

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2b-PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE s INITIAL CONDITIONS

1. Unit i reactor is operating at 100 percent power. The unit has been

                                -operating continuously and has had a capacity factor of over 90 percent                      c.:

since the last refueling outage 17 months ago. J

2. Emergency Service Water Pump P45-C001A failed to meet its discharge n pressure inservice inspection (ISI) at 2200 on November'25. The pump is

                     ,\,7 '        disassembled and is expected to be placed back in service in about eight
     .h'h4 hours. The following Division 1 Lineup has been established in the                          -

daily instructions for the duration of P45-C001A unavailability: RHR r

   -(                 N 3
                              ,   Pump A and LPCS Pump Breakers are racked in but are not to be used except                    ';

y

               '4         y if Divisions 2 and 3 are inoperable. RCIC use is allowed but should be
      ~

n'y ' limited to a backup to High Pressure Core Spray. Division 1 Diesel h, b h,\.M }c[f*

           , \,-

Generator to be used. is Emergency Closed Cooling out Pump of service P42-C001A with Breaker is also racked out; ECC Pump A is not to be used until the return of ESW Pump its out t [ y P45-C001A. p k,,4

3. A spent fuel element is being readied for shipment to Idaho National !,

Engineering Laboratories for examination and testing of the new barrier [! fuel cladding. [

4.

Annulus Exhaust Gas Treatment System, Train A, is in day three of a seven day Limiting Condition for Operation due to a motor failure on Fan si i M15-C001A. The fan is disassembled awaiting a new motor. Train B is in f

service.

L $

l S. Backwashing of Fuel Pool Cooling and Cleanup Dominera11sers is set to l j begin at 0900. 1 i ,,

6. All other systems are operable. '

V , 7. Unit 2 remains under construction; no significant activities are I scheduled for today.

8. General Electric Company personne'. will be onsite to talk with Main- n tenance and Technical Section staff concerning: ,

s. Intergranular stress corrosion cracking. (IGSCC)

b. New control rod drive seal performance. '

c. Support for the Spent Fuel Element Shipment.

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      "               9.      Current weather conditions are as follows:

Wind speed: 20 miles per hour

                           -Wind direction:       200*

Temperature: - 32*F - E 9111; et---: 0

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I-r: Li i-6.2 Narrative Summary - Onsite Sequence of Events

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I, PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE

                                      '                                                                                              e NARRATIVE

SUMMARY

- ONSITE SEQUENCE OF EVElfrS f

Approximate Time Key Event [~ E Y 0700 Initial conditions are established. Commence exer-cise.

'[

y 0708 A fire breaks out in the PPD machine shop. .; 0710 The Control Room is notified of the fire; the fire [.; brigade is dispatched. r-0715 The Fire Brigade arrives at the scene. The fire is f spreading. The Fire Brigade Leader requests offsite i fire fighting assistance. j,; 0717 The Shift Supervisor calls for offsite fire fighting ll

                                  ,                  assistance,                                                                     j,
               -             ~.

The Shift Supervisor declares an UNUSUAL EVE!fr. [' [ 0720

    /C      l                                         (EPI-A1, Section F.I.1, " Fire within the Protected I
                                                    -Area lasting greater than 10 minutes").                       ,
              ' 0725 [ ),,lf c                       Offsite fire fighting assistance arrives at the                                  )
                "          'V . /

Primary Access Control Point Gate, and is escorted to

the scene of the fire. r (0745 .. . , .

The fire is. extinguished, i 0755 A spent fuel element is being raised in the Spent Fuel Pool for loading into the Spent Fuel Transporta-I* tion Cask. ; 080'0 Offsite fire fighting assistance leaves the site. 0800 The refueling bridge winch position interlock fails 7, i as the bundle is raised to the overhoist position. e t Fuel Handling Building area radiation monitors alarm '> - locally and in the Control Room. The bundle cannot ./s.v., "

be lowered using the winch due to the failure of a Ap//c/ i f fuse in the brake release power. i k, { ! Page 1 of 7 i r .

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A PERRY NUCLEAR POWER PLANT / . ;. 1984 EMERGENCY PREPAREDNESS EXERCISE 4 NARRATIVE

SUMMARY

- ONSITE SEQUENCE OF EVENTS

[~ [ v.

                                            -Approximate                                                                                                                                                          - ,i 4

Time Key Event ;, t, 1 - Il 0805 [ The Shift Supervisor declares an ALERT-(EPI-A1, t; },

'                                                                                                       Section J.II.1, " Fuel handling accident with release- g/n.f if h of radioactivity to Containment or Fuel Handling                                         UjWj'             i.i Tuilding"). The TSC and OSC are activated. Onsite                                                            j

monitoring teams are dispatched. % g . g ( ',i i: ;,

5 ,,,,!. s *4; : . 0900, .'.< The TSC and OSC are fully activated.

                                                                                                                                                                                                               .  .e
                                                                                                                                                                                                                  *p
                                                                                                                                                                                                                      ;)

0915 An operator on rounds in the intermediate building G

notices water coming from inside the Fuel Pool O Cooling and Cleanup Backwash Receiving Tank Room. [.

He slips and falls on a puddle of water, gashes his , i head and breaks his upper left arm. He radios for i

help. (The leak is from a flanged connection on a

                                   ,'~                                     .         .,J',             valve upstream of the pump.)
                ;-                                                                                r     :

.L , 0920 ,.,.". 'j .

                                                                                                 ' iSecurity dispatches a First Aid Team to treat the

[

I

                                                                                               ./ ,' injured victim.

0930 : e' An offsite ambulance should be requested for the

                                                                  ;/' , . 4
                                                                                          . kf ', injured individual.

0940 ' , s.V,g}J T* The offsite ambulance arrives at the Primary Access i g I Control Point Gate. e - I, ; i 0955 The victim is loaded into the ambulance. I-

1000 The ambulance leaves the site. Intermediate Building o

}- decontamination and re-entry operations continue. ; ' ,] 1000 Safety-Relief Valve (SRV) B21-F051D inadvertently ;. . opens. The operators make preparations for a fast p reactor shutdown. , j'

                                                                                                                                                                                                        .           t *,

2002 A scram is attempted by placing the mode switch in ?1 "SHUIDOWN": however, there is no inward motion of

the control rods. In accordance with PEI-1, the ,.

! operators attempt to shutdown the reactor using .

alternate rod insertion. All alternate shutdown '

methods fail. A manual scram is attempted, but < fails. '

                ,a i

Page 2 of 7 l

 .             _ . . ~ . _ _                             :                _                                                _

PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE

SUMMARY

- ONSITE SEQUENCE OF EVENTS Approximate                                                                                                            ,

Time Key Event { 1915 f pl k' The Suppression Pool temperature reaches 110*F. j*J h ". Standby Liquid Control is activated, but the common (v 'g a " (' check valve C41-F007 does not open, and SLC does"not ! ( gN, '? inject. The operators implement PEI-1, Attachment 5, M id ' to lower reactor level. Level will reach approxi- J 'Y ^ ' N mately -145 inches in 30 minutes and power will be / Approximately 8%. Control Complex venumwu andts , to recirculation mode h t 1930 (EPI-A1, Section 7, / A SITE AREA EMERGENCY is declared.D.III.2, " Complete loss of[ ' plant hot shutdown"), al/ . 1050 Reactor water level is being maintained at

                                           -145 inches; reactor power remains at 8%.     [ a., ,wp is,b ,- -,1, j     i
'                                                                                ~"

, 1100 The EOF and JPIC are being activated.

                                                                                        #;'I* ', ;,, w s/'s .J.i:
                                                                                                                     /. I

1115 j TSuppressionPooltemperaturereachesapeakof143*F Il M 'and remains steady. " 1120 All upper pool dump valves fail to open au}oma- 6 tically. Both trains fail due to a hydrauaic lock that exists between the dump valves due yo a failure

                            -             of check valves G43-F508A and G43-F508B. Any effort to open these valves fails.

1130 Reactor power remains steady at 8% power. All I efforts to insert the control rods continue to fail. 1150 SRV B21-F051D closes Suppression Pool Temperature begins to g . .c , 1200 The Turbine Driven Reactor Feed Pump and Feedwator t Booster Pump trip due to Surge Tank Low Level Switch ' N21-N335 malfunction; the entire feedwater system is endered unavailable. Reactorwaterleveldecreasesh], elow -148 inches, initiating MSIV_ isolation g(,g ,.,, k.h, 1201 RCIC is placed in service, but reactor water level continaes to decrease to seven inches above the top of active fuel. 'i} /r , . / f. s /., e . o.. ,

                                                                                                                     . .f. , .q, Page 3 of 7

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  .        .          . . - . ~ . -                         ..- ...      . - . . . . . - -       .   .

PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE

SUMMARY

- ONSITE SEQUENCE OF EVENTS Approximate                                                                               tj Time.                                               Key Event f

1202 The reactor is being'depressurized to the suppression pool.by the operators via the pafety relief valves ; (SRVs) in acecrdance with PEI-1, Attachment 5. E Containment Building Area Radiation Monitors alarm. i

                                           / The Reactor Core is uncovered.                              .

1204 Reactor water decreases to 43 inches below the top of the active fuel. f. [ 1206 In accordance with PEI-1, Attachment 5, Step 7, the ! operators direct jumpers to be installed in , Panel H13-P618 in order to use RHR B to regain reactor water level. The I&C Technician inadver- s tently shorts out the Division 2 RHR LOCA logic which realigns RHR B and C in the LPCI mode. When the sparks arc, he slips and damages the LPCI B Injection j' (

   ,,_                                        Valve Manual Override Relay E12-K248 in the de-energized mode. The Reactor Vessel begins to flood       i rapidly. RHR (LPCI) Pumps B and C are injecting cold water into the vessel at the combined flow rate of 14,000 gym. Reactor Vessel level peaks at +5 inches Wide Range. Reactor power peaks at 55% and decreases     >

to 40%. <

                                                                                             .         r 1208                             The operators close LPCI-C injection valve, but efforts to close the LPCI-B injection valve fail.
                                        ;     Further, when the LPCI B pump control switch is          ,
                                  ,,ph*placedinthe"Stop" s          Control Power Fuseposition,theBreakerTrip blows, thus allowing the pump to g      run. The pump cannot be tripped from the Control Room. Reactor power ilecreases to 20%.

1210 SupgressionPooltemperatureincreasesapproaching - 212 F. Containment radiation levels ', increase. . F Page 4 of 7

              - ,              ..s. .u~, .    .:            .         -        - -,   -          -      --            -

i ll' PERRY NUCLEAR POWER PLAlff - 1984 EMERGENCY PREPAREDNESS EXERCISE 'p

'                                                                                                                                 )

s NARRATIVE

SUMMARY

- ONSITE SEQUENCE OF EVENTS                                          t I-                                                                      ,

Approximate ..!

Time Key Event l{,

                     - 1215                             An operator successfully opens RNR Pump B breaker                    -;
                                            ,            locally (Elevation 620 Control Complex). As he                     'i completes the task, he becomes aware of the scent of               H charred paint and metal. Upon investigation, he                           .

! discovers the Motor Control Cabinet for Bypass '

j. Valve E12-F0483 is charred and inoperable. Bypass . ;

l Valve E12-F0483 is stuck open. y.j L e i: j /.AGENERALEMERGENCYisdeclared(EPI-A1,Sec-tion D.IV.1,1; i 4 with a potential loss of a third" or Attachment 3 W, . Condition 2, "Transientalg failure otrequialta l; core shutdown systems. Could leadl o core melt in 7' *f ..d '7

                                                                                                                    "   ^ <'

J. j seiera11murs71th'coitainment failure likely. More severe consequences if reactor Recirculation Pump E

          ,,                                            Trip does not function").                                          *'

i-4 *(" t? 1230 Suppression Pool temperature reaches 224*F; contain-

,                                                       ment pressure is 5 pois and increasinge RNR B is

being used for containment spray, but RHR Heat ! Exchanger Bypass Valve E12-F0485 is open, rendering '! t 'the spray ineffective due to lack of cooling. HPCS , is maintaining water level. Annulus Exhaust Gas t Treatapat System (AEGTS) and the Unit 2 yent monitor detect increasing levels of radiation. [;

                    ' 1245                              Containment pressure and temperature continue to increase. Suppression Pool temperature is 238'F;                   *

containment pressure is 10 psig and increasing.

l 4 g. i - i o 4 I i l + . , j Page 5 of 7 I

                                                   . i .4 ..u .                                                     -                                                                     '                                           **

1 ( PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE NARRATIVE

SUMMARY

- ONSITE SEQUENCE OF EVENTS                                                                                                                        ,

Approximate Time Key Event 95 1315 Containment pressure reaches 27 pais. AEGTS and the

                 ,                                                                     Unit 2 vent monitor indicate substantially increased                                                                                                                       '

levels to radiation. Offsite radiological monitoring

                                                                                   / teams detect increases in radiation readings.                                                                                                                                L NOTE:                     A release path from the containment to the                                                                                                       [

annulus is available through a crack in the J containment dome-to-wall circumferential j" weld. From the annulus, the radioactive gas is released through the AEGTS. The ; j operators should not turn off the AEGTS '

                                                                                                   ',/ fan; if they do, the extreme annulus-to-
                                                                                                    /                                                                                                                                                              ,

atmosphere pre.ssure could leak out unmoni- ,t

                                                                                                              ~ tored and unfiltered. Also, the fire N ,                                                                      ,J
                                                                                                                                                                                                                                                     //4'}
          --                                                                                              ( dampers do not shut due to a batch of                                                           13 '           5 8"'                        '          l M*f*",*k',fusiblelinks.

_ p .e f3 p**' 1315 Standby Liquid Control System injects into the vessel h0* when Common Check Valve C41-F007 opens. [' 1325 Containment pressure peaks at 28 pois. . 1330 RHR Bypass Valve E12-F0485 is closed; containment ,

                                                                             \ v Spray Loop B is in full operation.

1335 ' Maintenance reports that ESW Pump P45-C001A will be able to be racked in at 13408 final coupling align- l. monts are in progress. ; 1340 ESW Pump P45-C001A.is started; Containment Spray Loop A is placed in operation. ; ! 1400 Some control ro'ds begin to insert due to spurious rod s drifts. . . 1410 The Reactor is shut down due to completion of SLC injection. . 1430 Containment pressure decreases. The release decreases. i . ( Page 6 of 7

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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE s l NARRATIVE

SUMMARY

- ONSITE SEQUENCE OF EVENTS Approximate                                                                                                                                                                                                                                                                      k Time                                                                                                                        Key Event 1445                                  ,

The Shift Supervisor reports that all control rods -

have inserted. 3 1500 Containment pressure returns to atmospheric pressure. c'

                                                                           $p,,g(                     9 :je',s The release stops.

y y.9 1545 9 Offsite radiation readings begin to decrease as wind ;; speed and direction changes disperse the plume. ;,. , I 1615 Offsite radiation readings return to background. The GENERAL EMERGENCY is downgraded. Commence re-entry j and recovery operations. 1645 e The exercise is terminated. '

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                                                   ~ , .                       .             -.        r . - > . ,                                 -                  -                  -- - -_ _- , , . . , ,                                                                                   --     , ,-       . . - ,

b i' 4 C' i., 6.4 Written Summary of The Exercise Scenario 4

                                                                        .P e

6 4 1 l-t 9 0 0l et e

   .                                      . ....a   . ..    .                          .

6.4 Written Summary of The Exercise Scenario NOTE: The following is a synopsis ~of the detailed narrative summary listed in Section 6.2 of this package. The Perry Nuclear Power Plant has*been operating continuously for the last 17 months with a capacity factor of over 90 percent. The Plant is currently operating at 100 percent power and is at the end of core life. , Some equipment problems are ongoing but all have been addressed through surveillance activities. Plans are currently underway to ship one fuel element to Idaho National Engineering Laboratories for examination and testing on the new barrier fuel cladding. Weather conditions remaisi o nt with the indicating a high ' temperature of 60'F for thfiay41th winds out7f the Northwest at . ; 3 miles per hour. . At 7:08 a.m. a fire breaks out in the PPD machine shop on Level 599'. The Control Room is notified to activite the Station Fire Brigade. Upon f arrival at the scene, fire fighting operations are commenced and a j-request is made for offsite fire fighting assistance due to the severe ; nature of the fire. ' Based on this situation, the Shift Supervisor declares an Unusual Event in accordance with EPI-A1, Section F. I. 1 (" Fire within the Protected , Area lasting greater than 10 minutes"). Notifications are begun to ;

   ,(:           offsite authorities and the Nuclear Regulatory Commission.                     ;

A short while later offsite fire support arrives at the Plant and the ~ fire is extinguished at approximately 7:45 a.m. Initial indications are that the fire has not affected any Plant safety systems and a decision is - made to leave the Plant at full power. Plant personnel begin damage assessment activities and preliminary reports indicate that no one was injured as a result of the fire. At 8:00 a.m. a spent fuel bundle is raised beyond the normal up limit due 5 to a winch interlock failure on the Spend Fuel Handling Bridge in the ( Fuel Handling Buidling. This action results in the initiation of 8 radiation alarms locally and in the Control Room. ' The Fuel Handling. Building is evacuated, and the Control Room is notified ,

              /of the situation. Based on EPI-A1, Section J. II. 1 (" Fuel handling              '

I accident with release of radioactivity to containment or Fuel Handling Building") the Shift Supervisor escalates the emergency classification to ' an Alert, and notifications are made to required personnel and offsite ; agencies. The. Technical Support Center and Operations Support Center /s - being activatliutand other emergency response personnel go on standby. . Local Emergency Operations Centers begin notifications and remain in a standby mode.

   '( .

S 0 t I

           .                                              .~                                    .

_a# ( Plant assessment activities continue onsite with reports coming in from the work crews who are re-entering the Fuel Handling Building. At 9:15 a.m. an operator on rounds in the Intermediate Building notices water coming from the Fuel Pool Cooling and Cleanup Backwash Receiving Tank Room. While attempting to le' ave the area, he slips, falls and is ' seriously injured. Later indications will show that he is also contaminated by the leaking water. The Plant First Aid Team responds while notifications are made offsite for ambulance support. , Lake County Memorial East Hospital is notified to prepare for receipt of a contaminated, injured man. v Plant conditions remain stable and final reports indicate no serious damage resulted from the fire. Repair activities are begun in the Spent Fuel Pool Area to return the bundle to safe storage. At 10:00 a.m. Safety Relief Valve (SRV) B21-F051D inadvertently opens and ( operators prepare to commence a reactor shutdowg. During the scram li initiation no control rod motion is observed, this is caused by [

~~

mechanical binding of the control rod seals. All alternate attempts to shutdown fail causing an ATWS (Anticipated Transient Without Scram). g ae Operations Manager in the Technical Support Center declares a Site

                     / Area Emeraency based on EPI-A1, Section D.III. 2 (" Transient requiring operation of shutdown system with failure to scram, Anticipatory
     *(,"
       '                Transient Without Scram"). Offsite notifications are made. The             .

Emergency Operations Facility and Joint Public Information Center are activated. State and Local Emergency Operation Centers are also r activated. Operators' attempts to manually scram the reactor continue to fail; and the Standby Liquid Control System fails to initiate upon demand. Duetothesefailures,theControlRoomOperatorsimplementIttachment5 of PEI 1 to lower reactor water level and reduce reactor power through void formation to approximately 8%. Efforts to insert the control rods or initiate boron poisoning continue to fail. , At 12:00 p.m. the reactor's water level is being maintained by only one L feed pump. A short time later the running feedwater booster pumps and the running feed pump trip due to a low hot surge tank level switch

                       -malfunction. Reactor water level control is lost and the water level decreases below the HSIV isolation setpoint resulting in uncovering of
                     ,,,t h e core and fuel clad degradation.

Based on EPI-A1, Attachment 3, 1 (" Loss of 2. fission product barriers with a potential loss of third barrier") the Emergency coordinator

                 //' declares a General Emergency.

e

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t

-_ . - .. w .. .n . ...- -. . . . - . . . - . I Offsite authorities are notified and public protective actions are

(? ^

recommended. The Emergency Broadcast system is utilized to notify the public and use of the early warning siren system is simulated. At 1:15 p.m. increased containment pressure causes the failure of the . third fission product barrier (containment) allowing a major release of radioactivity through the Annulus Exhaust Gas Treatment System to the ' environment. Radiation monitoring teams follow the path of the plume, and onsite ' efforts continue to gain control and stabilize the plant. , r At 2:00 p.m. some of the reactor control rods begin inserting and the ' Standby Liquid Control System completes injection. Forty-five minutes . later the Control Room reports that the reactor is shutdown and all rods ; are inserted. Efforts continue to stabilize and improve plant ' s conditions. With the decrease in containment pressure, the release r decreases until the containment pressure returns to atmospheric pressure I v'and the release is terminated. . t Radiation monitoring teams follow the path of the plume and onsite efforts continue to stabilize and improve plant conditions. Due to the long duration of the emergency, turnovers between key onsite

                           , response personnel will be occuring to provide a rest period for those                                   ;

initial responders who directed the early phases of the emergency j[j' , response effort. , F With all required activities successfully demonstrated onsite and

                 /          offsite, the emergency is de-escalated so that recovery operations can
               /            begin.                                                                                                     ;

l After all required re-entry activities (plant only) are underway, the ( ; event response is terminated at 4:45 p.m. , ,- w ..; ,

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I i l i Time: 0700

   ,)                                                                                                                                                                                                          Message No.:               f i

PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MES' SAGE FORM . Messene Tor: Control Room -> Simulated Plant Conditions: See Initial Conditions Sheet and Data Sheets I Messame: ***THIS IS A' DRILL *** { Commence the 1984 Emergency Preparadness Exercise. Initial I.i Conditions are as specified on the attached sheets. *

                                                                                                                                                                                                                                                             >7 i6 Make the following announcement: " Attention, attention all                                                                                                                  fl, personnel; we are commencing the 1984 Evaluated Emergency                                                                                                                     ..

Preparedness Exercise. Only designated participants should k.

respond to drill announcements." !

I-

.b

b; FOR C0tfrROLLD USE ONLY

                                                                                                                                                                                                                                                             .i
                                                                                                                                                                                                                                                              'L Controller Notes:                                           1. Ensure that the FA announcement is made.

2. Only the Control Roon receives annunciator alare data sheets. ,

NOTE: The following standard will be utilised for ai annuncistors '

a. An annunciator alarm which is new is ,

enclosed by a solid line box. 't

b. An annunciator which has been acknowledged b and is cleared is enclosed by a dotted line box. f

c. An annunciator which remains lit has no i'I box of any type enclosing it. i Actions Exoected: Participants should review initial conditions and plant data ,

sheets. . e l * -

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 ,. PEMY IIMCLEAR PetKR PLAdsT                          1994 E8EERCElICY PSEPAftESIESS EXFRCISE-                            .            TipIE: 0700 PGA1                                          P684 Cost ~#IWi3T PahlfETutS                             SYSTDs leFOIWenTlen                                            PtQf]OR PAPAfETER3 Temperature        Pressure                                                    Pressure     Flow          Pressure           1918    Psig

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supr P8 as 18.2 C SS S ST F8w (Total) 15.4 pelb/hr CDP A OP 275 Line A 3.8 g SYSTEIES teFe m TION ' S OP 200 Line* S 3.8 Pressere Flow _ States iesteI femel C SR 150 Line C 3.0 , ItssR A SR RFDP A OP 130 Line D 3.8 B SR S OF 330 ' C SR C OP 330 LPCS SR D Sat 160 RCIC SR RTP A OP JE 15.1 IsrCS SR S OP 1963 14.9 . ECC A 005 teFP SR O O M11g(-C(leFRATOR S Sat itCI2C A FAST 392S4 PAltAfq[iiRS [Sht A 005 B FAST 192S4 Stuett 1235 I B Set DIVAft 350 l ptfuca VALVE PARAIEETERS l C SR C8IOR Vec 28 In. leg . Status Closed eeen , l CRD A SS Thrt Pr 950 psig 8tSIV tsome O 8 r B OP 1900 44 SYP VLV SRV WOWI 19 0 Posit O E SLC A SR

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                      .                                      BrywoiI Coolles Fem 1A          er er          Operating                                                                             C       SS                e an        er SS          Smeested Statens                                                                      3       SS                e 34        er Atr     -

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 ,. PElev InsCLEAR POWER PLANT                                 19045 EMERCENCY PetEPastEBWESS EMAClK                                                  T iteE: 9700 PHE L P604                                                            PenEtS P669. P670. P671. P672 Process medletten                                                                   femia Steam Line mac                 L 9ht aft /hr Alere                                                                                                      i
                                                                   .                      Catet vont Emse RAD              41.0E-1 aft /hr Offges Pre-treetsomt              2.M+2 R/hr effges Post-treeteent A           2.M*2cpe                                                               PAEIEL P982                                         s B        2.M+2 cpe                                       r - Airterne                              ces (csel                  Alers Eag Service tanter       A         3.9E+1 cpn                                            mWB Vent Esta                      2.0E*1 3         3.0E+1 cpe                                            FMS Vent Em9e                      2.2E*1 OG Corten God woult      A        6.0E+1 aft /hr                                         CR vent Emst                       2.0E+1 5       5.M*1 aft /hr PANEL P906 PANEL 803                                                cm Process and Aree                          Ese                     Alers Turt SIdg East       2.M*e mR/hr                                                     UD-Get-73 East LIg                 ]JQ1                                   ,

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                                                                                                                       -o.ss *r oc vent Pipe                 ;W23                                            sesta 1 W1 Plant went                !  rJ31 ut Paant vont - sem          !  tJag i            is/us vent                   eJ11 TB/IIs went - Im                    M 51 Packing Dde                      fj U2 Plant went                   J 11 ist Plant went - sen         0.0E+e l

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t b AR,EA RADIATION MONITORS Time 0700 , l

                                                                                           $                                                                             t i                                               TAG #                                                          LOCATION                      READING (MR/hr)            .

1D21NO30 Personnel Air Lock. Cntet (600'6") 5.0E+0 1D21N040 CRD HCU West. Cntet (620'6") 5.0E+0 . l ID21N050 RBRT Area. Cntet (642') 1.0E+2 Tio Drive Area. Cntet 1D21N060 (600'6") 3.0E+1 ID21N070 RWCU F/D Area. Cntet (664'7") 7.0E+0 i 1021N080 Upper Pool Area. Cntet (689'6"). 2.0E+0 l 1D21N110 Aux Blda East (574'10") 7.0E+0 '* 1D21N120 Aux Blda West (574'10") 7.0E+0 _1D;1N130 Turb Rm East (647'6") 2.5E+0 l 1D21N140 CRD HCU East. Cntet (620'6") 5.0E+0 . ! 1D21N160 Turb Rm West (647'6") 2.5E+0 '. ID21N170 Turb Blda (605'6") 2.5:P, + 0 1D21N180 Hotwell Puso Area. TB (577'6") 1. 0. ;+1 ', 1D21N190 T3 Sumo Area. TBC (548'6") !2.0:',+ 1 1D21N200 003 (584')

                                                                                                                                                ' t .1l ;+1

_1D21N210 Cnds F1tr Pop Area. TBC (568'6") 9.0E+0 ' 1D21N220 00 After F1tr Area. 003 (602'6") 2.0E+1 ID21N230 HP Tdw Htr Area. HB (600'6") 1.0E+1 _1D21N240 Tdw Puso Area. HB (647'6") 6. 6' ;+0 i, i (S 11)21N400 CR. CC (654'6") 1.6 ;-1 ~l l 1 )21N410 00 Hold Up Area. T3 ($77'6") 1.0 ;+1 e l l)21N250 RWB West (574'10") 2.5 ;+1 ! _D21N260 RWB East (574'10") 1.5 ;+1 i ! D21N270 RWD (602') 5.0 ;+0 i D21N280 Process Sample Rs. RW3 (623'6") 4.0 ;+0 ! l _D21N290 RW Evan. RWB (623'6") 4. 0;;+0 ( ! __D21N310 FPCU F/D Area. IB (599') 6.0: ;+0 , l D21N320 Fuel Preparation Pool. It (620'6") 4.0E+0 ; _D21N330 Spent Fuel Stornae Pool. 18 (620'6") 4. 0lE+0 ! l _D21N420 FPCU Circ Peo Area. 18 (574'10") 9. Olt+0 ! 1D21N340 Unit 1 DW. Portable. Cntet (655') - '! ! _D21N380 Weste Compactor Area. RWB (623'6") 6. 0l;+1 . I _D21N370 SRW Drummina Area. RWD (623'6") 6 . 01;+0 l 1D21N090 Refuelina Bridae. Cntet (689'6") 3.0:;+0 l ,

                         .D21N390                                                            Fuel Serv Hdla Plotform. 18          (620'6")        3.0;;+0 kl                     ,.

f r l . 1. __.i_.___

l l . s Time 9]qq Message No.: 1 j PERRY NUCLEAR POWER PLANT g 1944 EMERGENCY PREPAREDNESS EXERCISE MESSAGE 19Bll l l Messaae Fort Welders in PPD Mac. hine Shop ;; Simulated Plant Conditions: - 51113338 ***THIS IS A DRILL ***

9 There is a fire in the welding area (southwest corner) of the Machine J Shop. The oxySen and acetylene hoses on the welding rig have been cut. Q and the fire is spreading rapidly. 'the hoses are whipping around as ,

! pressure is released, and there is heavy smoke in the area. , , i i t (

       .                                                                                                                              t
   .(A                                                                                                                                ;

I D 1 , FOR CONTROLLER USE ONLY i Gentieller Notes: This message will be phoned in by a Controller, using the ' GAI-11t0NICS System. 7 I

                            .                                                                                                          4 Actions Ennected:

I f . . l DW176/C/2/ba 1 6 4 a_ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _

                                                                                            ~
           ..; ,;..                                     ,     .       ..;.. -      ... . ~ -                                           --    -

Time: 0712 Message No.: 7

    '-                                                          PERRY NUCLEAR POWER PLANT s              1981 EMERGENCY PREPAREDNESS EXERCISE                                                    ,

MESSAGE FORM - 1 Message For: .SAS ' Simulated Plant Conditions: I

               .           Message:    ***THIS IS A DRILL ***                                                                                  f:

s You have a fire alarm in the southwest corner of the Machine Shop in the area of the welding booth, y h I 4 p e

     ,qu                                                                                                                                       .
          -                                                                                                                                    t 9

w i FOR CONTROLLER USE ONLY , Controller Notes: A Walder has severed the acetylene and oxygen hoses on the ,' l welding rig. The fire initially spreads to Class "A" material (plywood, rags, etc.) and Class "B" material (oil and 1 lubricants) in the area. P l Actions Expected: The SAS would inform CAS and a Security Guard should be l dispatched to investigate, but once he receives a call >, . i corroborating the ala h should dispatch the fire brigade, * ! and evacuate the secon r of the Service Building. l ' ' Q

                                                                                                   ,,,xf*.)f','.n    /. . j ;"1 y u,%                        c                                         .

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PERRY NUCLEAR POWER PtANT 1984 EMERGENCY PREPAREDNESS EXERCISE .. TIME: 0712. CONTROL ROON ANNUNCIATORS P601/P877 P680 P870 at BACK PANELS Section 7A

                                                                                    .                                                                                           e FIRE AND                                                            ,

SECUR11Y TRBL P802

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1 Time: 0712 Message No.: 4

   's
   't PERRY NUCLEAR POWER PLANT s                    1984 EMERGENCY PREPAREDNESS EXERCISE                                  -

MESSAGE FORM , 1: Message For: Individual in Planning Office l! y L Simulated Plant Conditions: Messaae: ***THIS IS A DRILL *** ei

                                                                                                                            .g Tnsre is a fire and heavy smoke in the welding area of the PPD                        f Maintenance Shope 4.

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n FOR CONTROLLER USE ONLY l' 1 Controller Notes: This message will be called into the SAS by a Controller. M p Actions Expected: {.

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Time: 0715 Message No.: 1-

  'h PERRY NUCLEAR POWER PLANT s                 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
               ' Message For: SAS Simulated Plant Conditions:

Message: ***THIS IS A DRILL *** You have a flow alarm, indicating that the sprinkler system has been activated in the area of the fire. 4

  .().'

FOR CONTROLLER USE ONLY g 07/q hJ" 8 e s Controller Notes: This should start the ten-minute clock for declaration of an. UNUSUAL EVENT. Actions Expected: Inform the Shift Supervisor in the Control Room. f I e DW176/C/5/ba ( .- I - -

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   .-.. :.   ...               .    . . .        . . - - .    .   -:-->-    --- ~  2-- ~a- r :--              -

Time: 0715

         ,,                                                                                                Message No.: 1
 '       (                                                  PERRY NUCLEAR POWER PLANT s                 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM 9

Message For: Control F,oom Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** 4 t'

       .G                                                                                                                           m FOR CONTROLLER USE ONLY t

Controller Notes: Actions Expected: J t 4

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      , PERRY NUCLEAR POWER PLANT _                   1984 EMERGENCY PREPAREDNESS EXERCISE                              TIME: 0715            - f, nu                                    ren CONTAINMENT PARAMETERS                      SYSTEM INFORMATION                                 REACTOR PARAMETERS           !

Tempe ra tu re Pressu re Pressu re Flow P res su re 1018 psig (*F1 fusial Status fosial (Goal Cntet 81 0 RWCU PMP A OP 1350 Neut ron Drywell 120 0.1 8 OP 1350 Mon 100 Range afBM HWL PHP A OP 230 Mode SW RUN . Tempe ra ture Level-(*Fl fft.) 8 OP 230 FDW Flw 15.4 Mlb/hr Supr PI 88 18.2 C SS O ST Flw (Total) 15.4 Mlb/hr CBP A OP 275 Line A 3.8 SYSTEMS INFORMATION B OP 280 Line B 3.8 Pressu re Flow Status fosial faomi C SR 150 Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 I B SR B OP 330 C SR C OP 330 *

LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 HPCS SR . B OP 1963 14.9 .

ECC A 00S MFP SR 0 0 - 8 SR IUBBINEC[NERATOB

  ,                                                      RCIRC     A      FAST                 39254                  PARAMETERS ESW A        00S                                           B      FAST                 39254      Mwatt           1235                   '

B SR MVAR 350

MAJOR VALVE PARAMETERS k C SR CNDR Vac 28 in. Hg Status Closed Open CRD A . SR Thrt Pr 950 psig -

b OP 1900 44 BYP VLV ' SRV NORM 19 0 Posit 0 % B SR SLC STC TK LVL 4600 gal.

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   .. PERRY NUCLEAR POWER PLANT               1984 EMERGENCY PREPAREDNESS EXERCISE                  e          TIME: 0715                    ?

fjlg ELECTRICAL DISTRIBUTION fgQlj CST Level 410.000 cal. Status Load fMW1 _ Status ! Status fosial Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP l TBCC PMP A OP 75 Con Breakers 2 CL 8 SR I

B OP 75 Div 1 DG OOS- Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DG SR 8 SR SA Comp OP 128 Div 3 DG SR Cont Rm Eng RCIRC Fan A SR IA Comp SR 120 8 SR ZAQQ CIRW PMP A OP 46 Status , EE10 i 8 OP 45 Cntet Vsl Cig Fan A OP Pressure Status _ f o s i a l ._ C OP 46 8 OP NCC Pump A, OP 112' 8 OP 112 I B SS D OP C SS 35 i E OP I ADolTIONAL INFORMATION SW Pump A OP 56 I r SS i Status Abbreviations: . B OP 56 * '

                                           .DryweIi Cooling Fan IA          OP 2A        OP                                                                :

SS Secured Status D SS 0 F-3A OP i-- AV Available MTR Fire Pump SR P 18 SS i SR Standby Readiness DO Fire Pump SR - 28 SS ' SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vsl Purge , Supp Fan A SS F-SP Fast Speed B SS i ISOL Isolated Cntet Vs1 & DW

F Purge EMh Fan ~A SS '

NORM Norea i i-8 SS ' OOS Out of Service Drywell Purge l Suppl Fan A SS CL Closed B SS OVRD Override . AEGTS Fan A 00S B OP

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                ,               PERRY NUCLEAR POWER PLANT                                            1984 EMERGENCY PREPAREDNESS EXERCISE                                 TIME: 0715           (>

l-PANEL P604 PANELS P669. P670. P671. P672 l, r-Process Radiation Main Steam Line RAD 6.8E+2 mR/hr f. Ala rm t j Cntet Vent Exh RAD <.1.0E-1 mR/hr Orrgas Pre-treatment 2.5E+2 R/hr Offgas Post-treatment A 2.0E+2 cpm PANEL P902 , B 2.OE+2 cpm Common Airborne Cas (cgatl AIare Eng Service Water k 3.0E+1 cpm RWB Vent Exh 2.0E+1 B 3.0E+1 cpm FHB Vent Exh 2.2E+1 dG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2. 0E'+ 1 B 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Aree gag Alarm , Turb Bldg East L.31?.g mR/hr UD-MH-73. East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 , PANEL P804 Radweste to ESW 3.0E+1

Airborne Radiation Cas (coal Alarm Radwaste to Sewage 3.6E+1 Annulus Exh A Gas DE_!f! .

B L.D 1. Cntot Ato 2Q 1. METEOROLOGlCAL CONDITIONS Drywell - HR (R/hr) IJ1. : AB Vent 2J 1. Wind Speed 20.0 .. sph ; OCB Vent Exh 2JES Wind Di rection ,.200

OCB Vent - HR L.D WI Tempe ra tu re 32 'F OG Vent Pipe y M Delta T -0.95 *r U1 Plant Vent DJ M U1 Plant Vent - HR QJ W! $

I TB/HB Vent 6JE +.]. TB/HB Vent - HR pQW! p ST Packing Exh HJ 1. U2 Plant Vent 6J 1.

 ,                                   U2 Plant Vent - HR                              DAf1!                        _

Y DW170C/A/4/ba 't e i t I k 4

  -~a...                . . _ . . _ .              ..                          _ _                    _           ,                             _

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l' AREA RADIATION MONITORS Time: 0715 s TAG # LOCATION READING (MR/hr) j ID21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 i 1D21N040 CRD HCU West, Cntet (620'6") 5.0E+0 i 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntat (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0

1D21N120 Aux Bldg West (574'10") 7.0E+0 I 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Blda (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 >

! 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area OGB (602'6") 2.0E+1

1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 I,: 1D21N400 CR, CC O' (654'6") 1.6E-1 ' i 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 i D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Re, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") 4.0E+0 D21N330 Spent Fuel Storage Pool, IB (620'6") 4.0E+0 , D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 i 1D21N340 Unit 1 DW, Portable, Cntet (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntet (689'6") 3.0E+0

D21N390 Fuel Serv Ndig Platform, IB (620'6") 3.0E+0

( i t i

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     ,          . . . . . . - - - - ,       . . - -- --. l : .: . ~ . . . .     .-        - .=t '. ~ x .  - - -   " - - --      >

Time: 0720 J Message No.: 9

.r.

f\'.- PERRY NUCLEAR POWER PLANT s s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM

                                                                                                                                    !,1 Message For: SAS                                                                                                .'.

Simulated Plant Conditions: I Messame: ***THIS IS A DRILL *** The Maintenance Supervisor reports that all maintenance personnel are accounted for. -- s L. t E

r. ;

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i l' 4 FOR CONTROLLER USE ONLY Controller Notes: , t i. [ Actions Expected: This information should be relayed to the Brigade Leader. , t- .

                                                                                                                           *        ?

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DW176/C/7/ba i ,. (: s. ..

l

                                                                .. . . -           m . __                                    _,

        . . - . . . . _            .:.. .~..:.~.             . . . . . .    --       -  - : ~.- - - - . . ~. . .     - -   ..   .-

Time: 0725 Message No.: T - L._, - PERRY NUCLEAR POWER PLANT C

                                 '                 1984 EMERGENCY PREPAREDNESS EXERCISE MES' SAGE FORM t-i-;
                                                                                                                                   ?, ';

Message For: Combat Attack Team (CAT),at Scene q N Simulated Plant Conditions: '" Messaze: ***THIS IS A' DRILL *** y You have moderate heat and moderate-to-heavy dark smoke as you enter !" the door to the Machina Shop.

h.

(- L b: s; . t

                                                                                                                                   +
 . w..

a V FOR CONTROLLER USE ONLY

                                                                                                              ,                     E Controller Notes:       It has now been 10 minutes since the sprinkler system was l                                              activated. The SS should declare an UNUSUAL EVENT.                                   i.

i-Actions Expected: The CAT leader should request that the south door be opened i to provide additional ventilation. 7 IF L: E: 9 _ DW176/C/8/ba

't

{t ' a .~o .s a .

               ..     . . _              . _ . . . . < , . ....- .. ..---- -            =.-:- -       -    --        - -

i' Time: 0729

Message No.: 9 PERRY NUCLEAR POWER PLANT .. s 1984 EMERGENCY PREPAREDNESS EXERCISE r, i<

~'

MESSAGE FORM Message For: CAT Leader N. Simulated Plant Conditions:

Message: ***THIS IS A DRILL *** '

L f. . t You are encountering heavy smoke, but not a lot of flames. The cutting f rig hoses are still whipping around. ci i; p

                                                                                                                             ,t a k

c i.

      <s                                                                                                                      [
     .fg.                                                                                                                    O i-C FOR CONTROLLER USE ONLY'                                                                                   b" i

i ;. i l Controller Notes: This message is delivered when the CAT approaches the area of it ! the fire. t J-l l' i-Actions Expected: D0' NOT allow the fire to spread outside the maintenance area toward the Control Complex.

?.

6 1 i~ i ;; I 5 i -

1 . i ,: i .- l DW176/C/9/ba l l i

2

 ..             .. . ~ . . . ..     .        .__      .___.   ..m_.~         ..    . . _ - . .      . _ . . . . . .  -                         .   .

Time: 0730 Message No : /0% PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE ' L r MES' SAGE FORM' ' ~ ~ ~ * w , i' Message For: Control Room / - T P Simulated Plant Conditions: [ ,f.f/.$7)G9 e'

                                                                                                                         #7e g'                       ;_.

(c Message: ***THIS IS A DRILL *** N- ._ , _ . _M' Declare an UNUSUAL EVENT (EPI-A1, Section F.I.1: Fire within the [1 Protected Area lasting greater than 10 minutes). (. - 4d l'

                                                                                                                              ',1       d.6V     -
                                                                                                                            <f                        I 0
                                                                                                                           /f4                        L' i

F e FOR CONTROLLER USE ONLY 9 6' t I ' Controller Notes: Deliver this message only if an UNUSUAL EVENT hasn't already Ih ! been declared. y i I Actions Expected: E l l {. ! r V 0 e' 1. b DW176/C/10/ba

t. , - . . . , - . -- . . . :. ... . - . . . a .i. u :, - :- .- : - .. :-.

Time: 0730 : t-

       ,c Message No.:     I/

PERRY NUCLEAR POWER PLANT , s 1984 EMERGENCY PREPAREDNESS EXERCISE $

                                                                                                                               .x MESSAGE FORM                         ,#                     '
                                                                                                                             're .

Messane For: Control Room

D G

Simulated Plant Conditions: See attached sheets P Messame: ***THIS IS A DRILL *** ' . p.5 e r

                                                                                                                               .r F.

e" Ii I' i.

FOR COh* TROLLER USE ONLY t. Controller Notes: '

~.

A t' Actions Expected: t t ,.-- 6

e,

                                                                                                                                'n
                             .                                                                                                  1 DW176/C/11/ba 4

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                  .                                                                                4?
  . PERRY NUCLEAR POWER PLANT                                 1984 EMERCENCY PREPAREDNESS EXERCISE                                                          TIME: 0730 P601                                                  P600 CONTAINMENT PARAMETERS                                   SYSTEM INFORMATION                                                          REACTOS PARAMETERS Tempe ra tu re       Pressure                                                         Pressure        Flow                    Pressure        1018    psig f*Fl              fosial                                          _ Status        _fosial         faom)

Level 31 in, c NR_ Cntet 81 0

RWCU PMP A OP 1350 Neut ron Crywell 120 0.1 ,

B OP 1350 Hon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra tu re Level (*F1 fft.) B OP 230 FDW Flw 15.4 Mlb/hr Supr PI 88 18.2 C SS 0 ST Flw (Total) 15.4 Mib/hr . s CBP A OP 275 Line A 3.8 SYSTEMS INFORMATION B OP 280 Line B 3.8 Pres su re Flow Status fosial facel C SR 150 Line C 3.8 ' RHR A SR i RFBP A 330 OP Line D 3.8 B SR B OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 t! H PCS SR S OP 1063 14.9 II { ECC A OOS MFP SR 0 0 ) B SR RCIRC A IMRSINCnC[M[RATOR l' FAST 39254_ PARAMETERS h ESW A OOS B' FAST 39254 Mwatt 1235 I B SR MVAR 350 MAJOR VALVE PARAMETER $ C SR CNDR Vac 28 In. Hg Status Closed Open CRD A SR Thrt Pr 950 psig - MSIV - NORM O 8 B OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR

!           8          SR SLC STG TK LYL         4600     gal.
                               <*     ,_ - 3 a+-p gf y,   *y,+.g m ary.- c- ?- r i y - ve; _- -=v yyj_-+-     w-   ' .

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PERRY NUCLEAR POWEO PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 0730. P870 ELECTRICAL DISTRIBUTION P904 CST Level- 410.000 cal. Status. Load fMW1 _ Status Status fesial 0FFsite Pwr Sources 2 AV' Cont Rm HVAC Supp Fan A. OP TBCC PHP A OP 75 Con Breakers. 2 CL 8 SR 8 ' OP 75 Div 1 DC OOS Cont Ra'HVAC Rtn Fan A. OP C SS 18 Div 2 DG SR B SR SA Comp OP 128 Div 3 DC SR Cont Re Eng RCIRC Fan A SR 1A Comp SR 120 B SR P800 CIRW PMP A OP 46 Status P970 B OP 45 Cntet Vsl Cig Fan A OP Pressure

Statut _fosial C OP 46 B OP NCC Pump A OP 112 SJAE A OP C SS '

8 OP 112 B SS D OP ' C SS 35 E OP - ADDITIONAL INFORMATION SW Pump A OP 56 i. F SS - Status Abbreviations: B OP 56 Drywe1l Coo 1Ing Fan 1A' OP ' OP Opera t ing C SS O 2A OP P SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR l IB SS 5 SR Standby Readiness DD Fire Pump SR i 28 SS SHTDM Shutdown j' 3B SS I S-SP Slow Speed Cntet Val Purge Supp Fan 1-A SS F-SP Fast Speed j B SS ISOL isolated Cntet Val at LV I Purge Exh Fan A SS NORM No ras 1 - B' SS DOS Out of Service - Drywell Purge m Suppl Fan A SS CL Closed B SS OV90 Override . AECTS Fan 00$' A B OP t I

                                  >;,; 7 ,;.      s., , . . ;<-- w.; . , -:S.         ,-~n        cv        -

r'-' ' *** V,' ': '

  - . . . .                                                        ..a           ..;.-..r.     .,,~,....a.....-.                                   .

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          's      =J o             e      a     e   e                                 e       e        e t         3            O      n     O   n  O                             O        O       O            O E             @      R     n   e                                O        n       O           n N        ,=      e-E g                            .

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PERRY 100 CLEAR POWER PLANT 1984 EMERGENCY PREPAREDNES3 EXERCISE TIME: 0730

                                                                                                                                                        -{j PAIIEL P604                                                    PANELS P669. P670. P671. P672 Process Radiation                                                               Main Steam Line RAD           6.8E+2 mR/hr Alare Offgas Pre-treatment               2.5E+2 R/hr Offgas Post-treatment A           EJE+2 cpm                                                       PANEL P902                          ,

8 2.0E+2 cpm Common Airborne cas (coal Alarm - Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.OE+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OC Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gne Alarm . Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1

NCC Heat HM 3.5E+1 I PANEL P80:s Radweste to ESW 3.0E+1 *

Airborne Radiation Gas (coal Alarm Radweste to Sewage 3.6E+1

.y.

Annulus Exh A Gas DJM 8 g i lJ 1. ; . Cntet Ata j@ l. METEOROLOGICAL CON 0lTIONS ; } Drywei1 - HR (R/hr) J1 - . A8 Vent .M1. . Wind Speed J M_ ph j OG8 Vent Exh MM Wind Direction _.E O ' OG8 Vent - HR DJIM Tempe ra tu re : 2 'F. g , OC Vent Pipe E+g Delta T -0.82 'F ' ~ 1 UI Plant Vent M ,'; UI Plant Vent - HR DJIM ' 18/H8 Vent (t&M r 18/198 Vent - HR Lt0 ST Packing Exh JW . U2 Plant Vent M ' U2 Plant Vent - HR MM . t i, e' ( r s 8 DW170C/A/5/ba l'o i-t 9

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                                                                            ~
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    .__   .m      _                                             _ _ __ . . .      . t     .       ..

g 7 %t AREA RADIATION MONITORS Time: 0730 s TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 t, ID21N040 CRD liCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 . 1D21N070 RWCU F/D Area, Cntat (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 - ID21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 y 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 .. ID21N160 Turb Rm West (647'6") 2.5E+0 ' 1D21N170 Turb Bldg (605'6") 2.5E+0 - ID21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 ID21N190 TB Sump Area, TBC I (548'6") 2.0E+1

1D21N200 OGB (584') 1.1E+1 ' 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 - ID21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 ID21N240 Fdw Pump Area HB (647'6") 6.6E+0 !.

    ,h.,l           ID21N400     CR, CC                                     (654'6")                 1.6E-1                i 1D21N410     OG Hold Up Area, TB                       (577'6")                  1.0E+1                '

D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 , D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 , D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0 > D21N320 Fuel Preparation Pool, IB (620'6") 4.0E+0 '. D21N330 Spent Fuel Storage Pool, IB (620'6") 4.0E+0 : D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 ID21N340 Unit 1 DW, Portable, Cntet (655') -- D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 ! D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 l 1D21N090 Refueling Bridge, Cntmt (689 ' 6").. 3.0E+0 { D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.0E+0 ' I i e l l l 1 l

f-

     - ._-.._         , ,    -               .         2..          . :-.C -     ~.._s.-m... . ~ : / --. .       . .
                                                                                                                       ?

Time: 0733

         --                                                                                  Message No.:    12
      ;('s PERRY NUCLEAR POWER PLANT                                 -

1984 EMERGENCY PREPAREDNESS EXERCISE ME$ SAGE FORM Messaae Fort CAT Leader f 4 Simulated Plant Conditions: Messame: ***THIS IS A DRILL *** . The ma'in fire has been confined but the hoses are still whipping : around. i P

                                           -                                                                           1 E.

f' 9 Ad FOR CONTROLLER USE ONLY ; i ., Controller Notes: C Actions Expected: The CAT should make efforts to isolate the oxygen-acetylene bottles. I ( ,

I, [ D i 4 m

             ,.           DW176/C/12/ba
,    . l.I I

e I L 4 . ,

  . ... . . _ _                                                                    ..s m . .._1.        .             _ _  - .

1 Time: 0739 Message No.: 13

    '                                                     PERRY NUCLEAR POWER PLANT                                                                       -

s 1984 EMERGENCY PREPAREDNESS EXERCISE - MESSAGE FORM Messane For: g7 g Simulated Plant Conditions: il 4 f Messame: ***THIS IS A DRILL *** ;~ The bottles are turned off and the hoses are secured. The fire is now f' under control. (- 1

y t: p. h t f: FOR CONTROLLER USE ONLY , p Controller Notes: Once the bottles are isolated, the main (oxygen-acetylene) fire will be extinguished and the brigade can turn their , attention to the peripheral fires. - i a. Actions Expected: T DW176/C/13/ba 4

                                     ,         ,                       -       . ,      _         -- _-        m_              ,        . - , . -

                          .,                      .               .     .     .. .   ... ~.......           ...      ..---:.          ~ --           -.

Time: 0743

         ,q                                                                                                   Message No.:       18-l                      -

PERRY NUCLEAR POWER PLANT

                                 '                                                                                                                           ~

1984 EMERGENCY PREPAREDNESS EXERCISE MES' SAGE FORM Messaae For: CAT Leader h r. Simulated Plant Conditions: l Messame: ***THIS IS A DRILL *** 'p The fire is out.

                                                                                                                                                          ;i l'
                                                                                                                                                        .ht. I b

(.

                                                                                                                                                        -p i   i e

i FOR CONTROLLER USE ONLY D Controller Notes: , i c: l Actions Expected: The CAT should commence cleanup and overhaul of the affected ,. area, and inspection of the second floor for fire and smoke ' damage. q. t.

cd( c.e. - "

  .                                                                                                                                                        P s.

l l- - i DW176/C/14/ba e .- 9 e

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   . . . . . - . .         ....         . .            .           .       .      . ~ . .          . .   .--:~.--    -             . - - . - -,

Time: -0745 Message No.: g PERRY NUCLEAR POWER PLANT - s- 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM b. Message For: Control Room L Simulated Plant Conditions: See attached sheets '.

j. ,

Messame: ***THIS IS A DRILL *** i, O-F: t c k; 4

     ~                                                                                                                                           ,-
                                            .                                                                                                    I-FOR C0!C' ROLLER USE ONLY                                                                                        ;.

Controller Notes: E-Actions Expected: !-

,V.

i i. i b i I,

                                                                                                                                                 ', E t.

DW176/C/15/ba (/, i

I

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( 'A PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0745

   .                          169.1                                    ffAQ CONTAlllMENT PARAMETERS                        SYSTEM INFORMATION                                               REACTOR PARAMETERS                        ,.

Tempe ra ture Pressure Pre s su re F l .,4 Pressure 1018 psig (*FI f oslo) _.. Sta tu s fDslGI_ (403) . Level 31 Ine NR Cntet 81 0 RWCU PMP A OP 1350 Neutron Drywei1 120 0.1 B OP __e350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempera ture Level f*F1 ( Ft.1 8 OP 230 FDW Flw 15.4 Mib/hr Supr PI 88 18.2 C SS 0 ST Flw (Total) 15.4 Mib/hr CFP A OP 275 Line A 3.8 SYSTEMS INFORMAT10N B OP 280 Line B 3.8 Pressure Flow Status fosle) fGDel C SR 150 Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 8 SR B OP 330 C SR C OP 330 < LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 HPCS SR B OP 1063 14.9 ECC A 00S MFP SR 0 0 s TURBllg[-CLNLRATOR

B SR RCIRC A FAST 39254 PARAMEIERS ESW A OOS B FAST 39254 Mwatt 1235 B SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNOR Vac 28 in. Hg Status Closed Open CRD A SR Thrt Pr 950 psig
B OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 %

SLC A SR 8 M SLC STC TK LVL 4600 gal. e

                                 ,    , ,         , -.        -          ,s.<
                                                                                       ~ .

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                                                                                                        -                                                         ) . [,

d Q. PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE

      *,                                                                                                                                            . TIME: 0745 P870                                    '

[LECTRICAL DISTRIBUTION' P904 CST Level 410.000 cal. _Stattes Load fMW1 _StatuL , Status _ _ fosial .0FFsite Pwr Sources -2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 +Cen Breakers 2 CL B SR

                 ,        8       OP               75               Div 1 DC                           00S                   Cont Rm liVAC Rtn Fan A          OP '

C SS 18 Div 2 DC SR 8 SR . i , SA Ccap OP 128 Div 3 DC SR Cont Re Eng RCIRC Fan A SR IA. Comp SR '120 B SR P600 CIRW PMP A OP 46 . Status P970 " B OP 45 Cutet Vsl Clg Fan , A OP Pressure __ Status fosial C OP 46 8 OP NCC Pump A OP 112 SJAE A OP C SS N . 8 *OP 112 B SS D OP C SS 35 \ E OP ADDITIONAL INFORMATION l SW Pump A OP 56 f;

                                                                 '                              F' SS i

Status Abbreviations: B OP S6 + r Drywe i I Cool ing Fan I A OP OP Ope ra t ing -. ' C SS O 2A OP SS Secured Status D SS 0 3A OP AV Available MTR Fire Pump SR IB SS

         -         SR         Standby Readiness                                                                              DD Fire Pump        SR 28            SS SHTDN    -Shutdown i

3B SS S-SP Slow Speed Cntet Vsl Pu rge ' Supp Fan A SS _ F-SP Fast Speed B SS I ISOL Isolated Cntet Val as DW

           ,                                                          Purge Exh Fan             A             SS NORM      Normal                                             -

B SS OOS Out or Service . Drywe l l Purge Suppl Fan A SS CL Closed B SS OVRD Override S, AECTS Fan .A 00S B OP l g p

9*_ .#4 'J g"' ,

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                                                                                                                                                                                                                                  ' ,Q  I

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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 0745 PANEL P604 PANELS P669. P670. P671. P672. Process Radiation Main Steam Line RAD 6.8E+2 mR/hr

                                                                                                                                      . Alarm Cntet Vent Exh RAD            41.0E-1 mR/hr' Offgas Pre-treatment                                  2.5E+2 R/hr Offgas Post-treatment A                               2.0E+2 cpm                                                                                             PANEL P902                               f B                    2.0E+2 cpm                                                                      Common Airborne                        cas (comi        Alarm Eng Service Water                A                    3.0E+1 cpm                                                                .

RWB Vent Exh 2.0E+1 B 3.0E+1 cpm FHB Vent Exh 2.2E+1 , O'G Ca rbon Bed Vaul t A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area ,cp_a.! Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq MQ1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX M L+1 PANEL P804 Radwaste to ESW 3.0E+1 Airborne Radiation Gas (comi Alarm Redwaste to Sewage 3.6E+1

Annulus Exh A Gas D E iQ B LDQ Cn'.mt Ata ' jJEt.. , NETEOROLOGICAL CONDITIONS Drywell - HR (R/hr) _JQ. AB Vent LpQ Wind Speed 20.0 mph OCB Vent Exh LpES, Wind Direction __g_ 0

OCB Vent - HR OC Vent Pipe DJEE Tempe ra tu re :i2 'F a g tg Delta T -0. 82.,, ' F +

UI Plant Vent 6M.1], U1 Plant Vent - HR DMif! TB/HB Vent (t, ret,], TB/HB Vent - HR EJ ! ST Packing Exh 1. U2 Plant Vent 9 1. U2, Plant Vent - HR D.d M - er DW170C/A/6/ba E e g * -"e ae '**( *

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                                                                                                                                     'y   'T   & T *1       l'              %c              3 $fe e    #       **           '

      . _ , _ .        . . . . -           -- . . - - - . ~ - - - ~ ~ - ~ ~ ~                    '
                                                                                                   - - - - -       -~   -                 "*  ^ " ~~

f i [ AREA RADIATION MONITORS Time: 0745 s I . TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 1 1D21N040 CRD HCU West, Cntet (620'6") 5.0E+0 1D21N050 RBRT Area Cntat (642') . 1.0E+2 ID21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 ID21N080 Upper Pool Area, Cntat (689'6") 2.0E+0 ID21N110 Aux Blda East (574'10") 7.0E+0 1D21N120 Aux Blda West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 -CRD HCU East, Cntmt (620'6") 5.0E+0 1' 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Blds (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 l ID21N200 OGB (584') 1.1E+1 1D21N210 Cnds Fitr Pmp Area. TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 ID21N240 Fdw Pump Area, HB (647'6") 6.6E+0

     '(                          ID21N400                 CR, CC                                             (654'6")           1.6E-1
            -"                   1D21N410
           '                                              OG Hold Up Area, TB                                (577'6")           1.0E+1 D21N250                RWB West                                           (574'10")          2.5E+1 D21N260                RWB East                                           (574'10")          1.5E+1 D21N270                RWB                                                (602')             5.0E+0 D21N280                Process Sample Rm, RWB                             (623'6")           4.0E+0 D21N290                RW Evap, RWB                                       (623'6")           4.0E+0 D21N310                FPCU F/D Area, IB                                  (599')             6.0E+0 D21N320-               Fuel Preparation Pool IB                           (620'6")           4.0E+0 D21N330                Spent Fuel Storage Pool IB                         (620'6")           4.0E+0 D21N420                FPCU Cire Pmp Area. IB                             (574'10")          9.0E+0 1D21N340                 Unit 1 DW, Portable, Cntat                          (655')               -

D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntat (689'6") 3.0E+0 / D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.0E+0 J-i 't r

~.

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                                                                                                                                                  -l Time: 0800
     -                                                                            Message No.: _19 PERRY NUCLEAR POWER PLANT C
                           '                1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
                               -QF$                                                                                                            ,

Messane For: Sh6 i Simulated Plant Conditions: - Messame: ***THIS IS A DRILL *** ,- No apparent damage on second floor, but there is moderate smoke. r. g 6 - L

    ,.                                                                                                                                         l-(                                                                                                                                           !
   .s .

J r FOR CONTROLLER USE ONLY i Controller Notes: Actions Expected: The brigade should ventilate the building to remove smoke, i i. d DW176/C/17/ba

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A 6 5

           +-- s             -   -
                                                          -a    . - ,                    v - - . . - -- - - - . - - - - - - - - - - - - - -

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Time: 0800

          .,                                                                                  Message No.:        (9 PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Fuel Handling Bridge Operator Simulated Plant Conditions:

Messame: ***THIS IS A DRILL *** The fuel handling bridge winch position interlock has failed,.and the e fuel bundle has been raised above the NORMAL-UP limit and.the winch has shut down. The fuel handling bridge ARM is alarming and reading ';. 2 Rem /hr. 2 ,

   ,                                                                                                                   c i

FOR CONTROLLER USE ONLY Controller Notes: 1. Attempts to lower the bundle fail. ,

2. The failure mechanism is as follows: '

3. Operation of the winch was erratic when raising the N bundle near the up limit, and the bundle was jostled. .

Actions Expected: 1. Evacuate the area.

2. Notify the Control Room. *

3. Control Room should implement ONI-D17.

     , , , . DW176/C/18/ba x.
                                     -             -.        . ~-        ,

    ...n:    u. c ..::a . . .-                                                -  La w L --   '

Time: 0800 Message No.: lQ G- PERRY NUCLEAR POWER PLAlfr

s # 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messaae For: Control Room ; Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** ; i m '

     .h                                                                                                                                                     ;

FOR CONTROLLER USE ONLY Controller Notes: ' l Actions Expected: - t-l t-l - ! DW176/C/19/ba !- r. E, l a ? - t . L - t i

                                       - - - - - - - - - . --          .                        - . . . . _ . . - - . . ~ - - _ .      . . .    . . - - - .

g ~ '- ?-) 3I, -

    ,  PERRY NUCLEAR POWER PLANT                   1984 EMERGENCY PREPAREDNESS EXERCISE                                          . TIME: 0800               I-4 A

CONTROL ROOM ANNUNCIATORS P601/P877 'P680 P870 ar BACK PANELS Section 8A .- COM AREA / , PRCS RAD MON PANEL ALARM P906 l s

                                                                                                                                                           -t t.f h'

l. I. 6 DW1708/A/17/ba 1 i i

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p , . 3 ,. , + r

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e f? (w' ' .0 l i PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 0800 [. tint 1 thnQ - f CONTAIMMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressu re 1018 psig f*FI fosial _ Status- fosial foom) Level 31 i nc ~ NR Cntet 81 0 RWCU PMP A OP 1350

Neut ron D rywel l 120 0.1 8 OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempera ture Level f*Fl (Ft.1 B OP 230 FDW Flw 15.4 Mib/hr Supr Pi 88 18.2 C SS 0 ST Flw (Total) 15.4 Mlb/hr C8P A OP 275 i Line A 3.8 SYSTEMS INFORMATION 8 OP 280 Line B 3.8 Pressure Flow

_ Status losial faomi C SR 150 Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 8 SR B OP 330 C SR C OP 330 LPCS SR D SR 160 ,' t RCIC SR RFP A OP 1065 15.1 je HPCS SR B OP 1063 14.9

                                   '                                                                                                                                f ECC A          00S                                          MFP                    SR        0              0                                             f B          SR luB61NE-GENERATOR RCIRC      A      FAST                    39254                 PARAMEIERS                    +

ESW A 005 8 FAST 39254 Mwatt 1235 , 8 SR NVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg _ Status Closed Open CRD A SR Thrt Pr 950 psig B OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR S SR SLC STC TK LVL 4600 gal.

o j g 6q' $ *MW q *$ r 'F f$ d d' b

(' Q ' ID- . t. PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE-

   , .,                                                                                                                                                   TIME: 0800 P870                              , ELECTRICAL DISTRIBUTION                                                    P904 CST Level                  410.000 aal.                                     Status              Load fMW)                                                                '

Sta tus Status loslal 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP ' TBCC PMP A OP 75 con Breakers 2 CL B SR 8 OP 75 ,Div 1 DG OOS Cont Rm HVAC Rtn Fan A OP ' , C SS 18 Olv 2 DG SR B SR SA Comp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A SR IA Comp SR 120 B SR P800 CIRW PMP A OP 46 Status B OP 45 P970 Cntet Ysi Cig Fan A OP Pressure C OP 46 _ Status .(pslal 8 OP SJAE A OP NCC Pump A OP 112 C SS B SS 8 ' OP 112 O OP ' C SS 35 E OP

                /.00lT10NAL INFORMATION                                                                                    SW Pump'      A           OP           56 Status Abbreviations:

r SS +- 8 OP 56 - Drywell Cooling Fan IA OP OP Ope ra t ing i C SS O

2A OP SS Secured Status D SS 0 3A OP' AV Avellable MTR Fire Pump SR E.

18 SS i SR Standby Readiness DO Fire Pump SR 28 SS SHTDN Shutdown . I S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS 1 F-SP Fast Speed 8 SS ISOL isolated Cntet Vsl at DW Purge Exh Fan A SS NORM Normal - , 8 SS 00S Out or Service Drywe l l Purge Suppi Fan A SS CL Closed 8 SS I OVRD Override . l AEGTS Fan A 00S , a 8 OP F

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u 4 h PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE #

 .                                                                                                                       TIME: 0800 PANEL P604                                            PANELS P669. P670. P671. P672 Process Radiation                                                   Main Steam Line RAD            6.8E+2 mR/hr t-Alarm Cntet Vent Exn RAD 41.0E-1 mR/hr                        !

Offgas Pre-treatment 2.5E+2 R/hr Offgas Post-treatment A 2.0E+2 cpm PANEL P902 , 8 2.0E+2 cpm Common Airborne cas (comi Alarm Eng Service Water A 3.CE+1 cpm RWB Vent Exh Mf,.+1 i 8 3.0E+1 cpm FH8 Vent Exh 2.2E+1

       'OC Carboes Bed Vault   A     6.0E+1 mR/hr                              CR Vent Exh                    2.0E+1 8     5.5E+1 mR/hr PANEL P906 i                               PANEL 803                                Common Process and Area                 gag          Alarm

! Turb 81dg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 i Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5Et1 PANEL P804 Radweste to ESW 3.0E+1

Airborne Radiation Ces (com) Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Gas D g 10 8 MQ i Cntet Ate ME. LIETEOROLOCICAL CONDITIONS Drywell - HR (R/hr)

AB Vent L.9R. ; 2d)E .. Wind Speed ?1.5 mph OCB Vent Exh 2,9E+2 Wind Direction 2 0 *

OCB Vent - HR DE.iQ Tempe ra tu re . 2 'F ',

OG Vent Pipe Ed)E_12 Delta T -1.20 ' f' Ut Plant Vent ; 6.J11 ; Ui Plant Vent - HR QAW) TB/HB Vent (tJ;1.1 TB/HB Vent - HR Q,9 10 ST Packing Exh LQ 1.

U2 Plant Vent 6JQ.

U2 Plant Vent - HR QiDJ;11!

                                                        -                                                       ,                            i l

DW170C/A/7/ba ' 3

1

   !                                                     AREA RADIATION MONITORS                        Time:      0800                               -

i s TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntet (620'6") 5.0E+0 l' 1D21N050 RBRT Area, Cntet (642') 1.0E+2 l 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntat (664'7") 7.0E+0 I ID21N080 Upper Pool Area, Catet (689'6") 2.0E+0 . _1D21N110 Aux Blda East (574'10") 7.0E+0 l 1D21N120 Aux Blda West (574'10") 7.0E+0 I ID21N130 Turb Rm East (647'6") 2.5E+0- !I [ 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 1 ID21N160 Turb Rm West (647'6") 2.5E+0

1D21N170 Turb Blda (605'6") 2.5E+0 l 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1

1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 l[

i 1D21N200 OGB (584') 1.1E+1 .

1D21N210 Cnds F1tr Pop Area. TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Her Area. HB (600'6") 1.0E+1 i ID21N240 Fdw Pump Area. HB (647'6") 6.6E+0 i 1D21N400 CR, CC (654'6") 1.6E-1 I

) .. 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 f; J D21N250 RWB West (574'10") 2.5E+1 D21N260 h ] RWB East (574'10") 1.5E+1 3 D21N270 RWB (602') 5.OE+0 i; j D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 ' 1 D21N290 RW Evap, RWB (623'6") 4.0E+0 ' D21N310 FPCU F/D Aree IB (599') 6.0E+0 1 D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3

i. D21N330 Spent Fuel Storane Pool IB (620'6") 5.8E+2 l D21N420' FPCU Cire Pep Area IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable Cntet (655') -

D21N380 Waste Compactor Area RWB (623'6") 6.0E+1-D21N370 SRW Drummina Area, RWB (623'6") 6.0E+0 / l 1D21N090 Refuelina Bridae, Cntet (689'6") -3.0E+0 / l D21N390 Fuel Serv Hdla Platform. IB (620'6") 2.0E+3 If 4 I I I l ! 'f i j .. 1 i t

Time: 0805 Message No.: 2

 .(                                         PERRY NUCLEAR POWER PLANT s              1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Controllers Simulated Plant Conditions:

Message: ***THIS IS A DRILL *** i

-)

I i (~;

  . ( .,

t FOR CONTROLLER USE ONLY - Controller Notes: 1. % Ehift Supervisor sb Juld declare an ALERT (EPI-A1, .

hection J.II. " Fuel riandling accider.t6i t

to Containment or Fuel Handling in ). f-f

2. He should implement EPI-A3 " ALERT":

R _. -

a. Activate the TSC and OSC. 7

b. Make notifications. V l, (

! c. Assess the situation. i Actions Expected: DW176/C/20/ba

'b.

l e

       .... t_u.   , . . . .    . . _   . :._  ' . . . . . .                           . . . _, c. _ .: . _.   ._-   .

Time: 0815 Messa'ge No.: Aj_ C. ,. f PERRY NUCLEAR POWER PLANT s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Roos' - Simulated Plant Conditions: See attached sheets

                   -Messame:   ***THIS IS A DRILL ***

h-

V

  .. h                                                                                                                .!-

I w FOR CONTROLLER USE ONLY s Controller Notes: . r,

                  . Actions Expected:

i .

           .      -DW176/C/21/ba
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9

   . PERRY NUCLEAR POWER PLANT                                1984 EMERGENCY PREPAREDNESS EXERCISE                  -

TIME: 0815-P601 P680 CONTAINMENT PARAMETERS -SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressuto Pressu re Flow Pressure 1018 psig t'F1 fDsIG) Status IDsIGI IQDm) Level 31 10 NR Cntet 81 0 ' RWCU PMP A OP 1350 Neut ron Drywel l 120 0.1 B OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW = RUN Tempe ra ture Level f*FI fft.) B OP 230 FDW Flw 15.4 Mlb/hr Supr PI 88 18.2 C SS 0 ST Flw (Total) 15.4 Mib/hr

                                                                .CBP        A          OP              275                           Line A              3.8 SYSTEMS INFORMATIO1                                                                                                                                  1 B          OP              280                           Line B              3.8             ,

Pressure Flow Status IDslal __fepal C SR 150 Line C 3.8 RHR A SR _ RFBP A OP 330 Line D 3.8 B SR . 8 OP 330 - C SR __ C OP 330 i LPCS SR D SR 160 , RCIC SR _ RFP A OP 1065 15.1

H PCS SR , 8 OP 1063 14.9 i

ECC A 00S MFP SR 0 0 TURBIN[-CENERATOR B SR RCIRC A FAST 39254 PARAMETERS ESW A DOS B FAST 39254 Mwatt 1235 1 8 SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 In Hg Status Closed ODen CRD A SR Thrt Pr 950 psig MSIV NORM 0 8 8 OP 1900 , 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR 8 SR SLC STC TK LVL 4600 gal. 37, * - . - -,

w -,g, ;g e *
i:.

[' - 2 ,f

                                                                                                                                                   .M PERRY IIUCLEAR POWED PLAIIT                         1984 EMERGESICY PREPAREDNESS EXERCISE

TIME: 08 5 P870 ELECTRICAL DISTRl8UT1000 M CST Level- 410.000 M L. , Status Load iMWI Status Status _ D11L OfFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP E5 Con Breakers 2 CL 8 SR -

8 OP 7L .Div 1 DG OOS Cont Rm HVAC Rtn Fan A OP C SS 'tL Div 2 DC SR 8 SR SA Camp OP 123 Div 3 DG SR Cont Rm Eng RCIRC Fan A SR IA Comp SR JO ~g SR CllIW PMP A OP 2;5 Status B OP 45 Cntet Val Cig Fan A OP Pressure , C OP 86 Status iosla) - 5 B OP .

                                  ,                                                                        NCC Pump A       'OP          112 8        SS                                                                                    B       OP         112       'f D            OP C       SS          35 E            OP                                                    3 eppiT10NAL INF01WIAT1000                                                                  SW Pump i

A OP 56 F SS Status Abbreviations: B OP 56 t. OP Opera ting C SS 0 i 2A OP SS Secured Statum D SS 0 3A OP t AV Available i-MTR Fire Pump SR t 18 SS SR Standby Readi..ess DD Fire Pump SR [- 28 p SS SHTDN Shutdown , 38 SS S-SP Slow Speed Cntet Vsl Purge I' Supp Fan A SS F-SP Faat Speed B SS ISOL 1solated Cntet Vsl at DW

,[
'                                                          Purget Exh Fan       A            SS NORM       NorasI                                  -

00S Out or Servics Drywell Purge Suppl. Fan A SS CL Closed 8 SS OVRO Override AECTS Fan A 00S 8 OP ,

7 '. . ,

PERRY lluCLEAR POWER PLANT 1984 EMERCENCY PREPAREDMESS EXERCISE TIME: 0815 f RX WATER LEVEL RX PRESS RX POWER }UPR PL TEMP 31 jf 1018 ff.LG 100 1 88 'E 60- 1100- 120- 110 45- 950- 90- 90-30- 800- 40- 70-15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 0 20 -10 0 -30 -20 -10 0 Time (min) Time (min) Time (min) - Time (min) DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL 120 'E 81 'E O 211Q 18.2 LI 200- 110- 20- 19- ' 4 150- 90- 15- - [. 100- 79- 10- 18-50 50- 5- - {'

                    -30   -20   -10    0       -30   -20     -10   0       0-                         17 l                                                                           .

Time (min) Time (min) -5 -30 -20 -10 0

                                                                              -30   -20   -10     0            Time (min)

Time (min) 9 E

m. - _ . . -

                                  ,     _                       .      . ~ _ . . . _     _.     -       .       ~               ._        _

~

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                                                                                                                                                                                     . ;~

PElutY IIUCLEAR POWED PLAIIT 1988: EfeERCEIICY PREPAREDesESS EXERCISE TlHE: 0815 E

                            *                                                                                                                                                        -i PAIIEL P60dt                                                 . PANELS P669. P670. P671. P672 Process Radiation                                                            feeln Steam Line RAD           6.,8E+2 mR/hr Alare                                                                                                                 I Cntet Vent Exh RAD-            1.0E-1 mR/hr Ofrgas Pre-treatment'             2.5E+2 R/hr Offgas Post-treatment A           2.0E+2 cpm                                                     PANEL P902                                   -,

8 2.0E+2 cpe Common Airborne cas fcoal Alers Eag Service Water - A 3.0E+1 cpe RW8 Vent Exh 2.0E+1 8 3.0E+1 cpe FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 aft /hr PAllEL P906 PANEL 803 Common Process and Area gag Alam Turb Bldg East 2.5E+0 mR/hr UD-HH-73 East Lig 3.0E+1 , Turb Bldg West 2.5E+0 mR/hr UD-HH-70 West Liq 3.2E+1 5^ i IOCC Heat HX 3.5E+1 PAllEL P804 Radwaste to ESW 3.0E+1

Airborne RedIatIon Caa Icom1 AIare Radwasto to Sewage 3.GE+1

, Annulus Exh A Gas f!A y ' 8 lJ!'t.. { Cntet Ate l JQ. < - ptETEOROLOGICAL C0ll0ITIONS I Drywel1 - MR (R/hr) ; .OE+ A8 Vent lJL+. .. Wind Speed J 21.5 mph OCS Vent Exh iM Lt2 Wind Direction l o * (

  .'                  OG8 Vent - HR            0.0 '+0                                   Tempera ture                a2            *F OG Vent Pipe                    ft                                 Delta T                      -1.20         *F I

U1 Plant Vent Jt 11 U1 Plant Vent - HR 920 fg

18/HS Vent 6d! 11 18/H8 Vent - HR fg l ST Pecking Exh [

                                                     .t1                                                                                                                                 c U2 Plant vent                   11 U2 Plant Vent - HR        0. 0 .+0 I           DW170C/A/8/ba i

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.                                                                        AREA RADIATION MONITORS                                                Time:       0815 s

TAG # LOCATION READING (MR/hr) l ID21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 } 1D21N040 CRD HCU West. Cntet (620'6") 5.0E+0 ' 1D21N050 RBRT Area. Cntet (642') 1.0E+2 ? 1D21N060 Tip Drive Area. Cntet (600'6") 3.0E+1 l 1D21N070 RWCU F/D Area Cntet (664'7") 7.0E+0 ID21N080 Upper Pool Area Cntet (689'6") 2.0E+0

;                       1D21N110              Aux Blda East                                       (574*10")                                     7.0E+0                                           -

1D21N120 Aux Blda West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East. Cntet (620'6") -5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 - l 1D21N170 Turb Blda (605'6") 2.5E+0 : 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 l 4

  ,                     1D21N190              TB Sump Area. TBC                                   (548'6")                                     2.0E+1                                            1 1D21N200              OGB                                                 (584')                                        1.1E+1 l-                       1D21N210              Cnds F1tr Pan Area. TBC                             (568'6")                                     9.CE+0 j                        1D21N220              OG After F1tr Area. OGB                             (602'6")                                     2.0E+1                                            r

1D21N230 HP Fdw Htr Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0 1

     '('                1D21N400 1D21N410 CR. CC OG Hold Up Area. TB (654'6")

(577'6") 1.6E-1 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 4 D21N260 RWB East (574'10") 1.5E+1 l D21N270 RWB (602') 5.0E+0 l D21N280 Process Sample Rs. RWB (623'6") 4.0E+0 j D21N290 RW Evan RWB (623'6") 4.0E+0 D21N310 FPCU F/D Arsa. IB (599') 6.0E+0 l D21N320 Fuel Preparation Pool. IB (620'6")- 2.0E+3

D21N330 Spent Fuel Storano Pool. IB (620'6") 5.8E+2 i D21N420 FPCU Cire Pop Area. IB (574'10") 9.0E+0 i 1D21N340 Unit 1 DW, Portable. Catet (655') -

1 D21N380 Waste Compactor Area. RWB (623'6") 6.0E+1 , {- D21N370 SRW Drummina Area. RWB (623'6") 6.0E+0 l 1D21N090 Refuelina Bridae. Catet (689'6") 3.0E+0 D21N390 Fuel Serv Hdla Platform. IB (620'6") 2.0E+f h i {s < l r n .

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_ _ . _ , . . . . .cs . a . . . .. - - - - ' - - - - - " * " '- - "" ' "~ ~ Time: 0815 Message No.: / PERRY NUCLEAR POWER PLANT s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM - ' " ~~~~ ~ ' ~ s -. ,

                                                                                                                                                           /
                                                                                                                                                                             ,                                 u Messane For: Control Room                                                                                                                                      ,"e g< , , , g i g. .,' ,; g ,
                                                                                                                                                                                                    -p>

Simulated Plant Conditions: - ' Messame: ***THIS IS A DRILL *** .m _ ,, '__. . Declare an ALERT (EPI-A-1, Section J.II.1, " Fuel handling accident with release of radioactivity to Containment or Fuel Handling Building"), i--

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i t' FOR CONTROLLER USE ONLY , Controller Notes: Deliver this message only if an ALERT has not been declared by this time. Actions Expected: See " Actions Expected" Message No.10. e e

       -( _                                 DW176/C/22/ba                                                                                                                                      *
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__ c . .._._ m u .. _ _ . . a_.._ . - . . - . . - _ . . ..... _ . . _ Time: 0830 (,., Message No.: R PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM i Messaae For: Control Room /TSC Simulated Plant Conditions: See attached sheets Messame: ***THISISiDRILL*** t i

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I i i FOR CONTROLLER USE ONLY .. . 4 Controller Notes: TSC and OSC activation should be underway. Actions Expected:- , t DW176/C/23/ba 1 .i W i i

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   . PERMY NUCLEAR POWER PLANT                                1984 EMERGENCY PREPAREDNESS EXERCISE                                    i-          TIME: 0830 2691                                             P680 CONTAIIIMENT PARAMETERS                                 SYSTEM INFORMATION                                                  REACTOR PARAMETERS                 y Tempe ra ture          Pressure                                                     Pressure        Flow             Pressure       1018     psig f*F1                fosial                                         Status        fosion         feoel Level             31    in  f. NR Cntet              81                  0                     RWCU PMP A                OP         1350 Neutron Drywell           120                  0.1           .                  8              OP         1350                            Mon             100    Range APRM HWL PMP    A              OP            230                         Mode SW         RUN                       '

Tempe ra ture Level

            .           f*F1                fft.)                               8              OP            230                         FDW Flw         15.4 Mlb/hr Supr PI            88                 18.2_                             C              SS              O                    ST Flw -(Total)      15.4 Mib/hr i

C8P A OP 275 Line A 3.8 '- SYSTEMS 9NF0flMAT10s i 8 OP 280 Line B 3.8

Status losial femel C SR 150 Line C 3.8 , n RHR A SR -] RF8P A OP 330 - Line D 3.8 8 SR 8 OP 330 i i C SR C OP 330

LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 HPCS SR 8 OP 1063 14.9 ,

o ECC A 00S MFP SR 0 0 JyRS!IfE-G[NERATOR 5 8 SR RCIRC A FAST 39254 PARAMETERS ESW A OOS 8 FAST 39254 Mwatt 1235 ? 8 SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg ! _. Status Closed Open CRD A SR Thrt Pr 950 psig MSiv - 800RM 0 8 8 OP 1900 44 8YP YLV ' SRV y 19 0 Potit 0 %

SLC A SR '

-V 8 SR SLC STG TK LVL- 4600 gal. e e

9- 6 +'"**88%f*9,* '***4

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Y) PERRY IIUCLEAR POWER PLANT 1984 EMERCE81CY PREPAREDISESS EXERCISE TIME: 0830 P870 ELECTRICAL DISTRIBUTION P9080 CST Level 410.000 eat. Status Load IMWI Status Status fosial OFFsite Pwr Sources 2 AV Cont Re HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL 8 SR

                                                                                                                                               /                '

8 OP 75 Div 1 DC OOS Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DC SR 8 SR SA Coop OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A SR IA Comp SR 120 B SR P800 CIRW PMF A OP 46 Status

                                                                                                                          -P970                                 ,

B OP 45 Cntet Val Cig Fan A OP Pressure _ Status fosial C OP 46 8 OP i. SJAE A OP C SS 8 OP 112 ' B SS D OP ^ C SS 35 ' E OP . ADDIT 10NAL INFORMATION SW Pump A OP 56- ~ F SS j Status Abbreviations: 8 OP 56 i Drywe1I CooIing Fan IA OP t OP Operating

C SS O !

2A OP SS Secured Status D SS O g 3A OP f AV Available MTR Fire Pump SR 1 ' IB SS SR Standby Readiness DO Fire Pump SR ' 28 SS - SHTDN Shutdown S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed - 8 SS ISOL Isolated Cntet Vsl at DW Purge Exh Fan A SS fe0RM 800roeI B SS OOS Out of" Service Drywell Purge , Suppl Fan A SS B SS OVRO Override AECTS Fan A 00S 8 OP s n .g : -r . .~.-....,;- --:-a m -- ~ ~ ~- . , ,

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   .-    PERRY IIUCLEAR POWER PLAflT                           1984 EMERCEIICY PetEPAREDIIESS EXERCISE                                                       TIME: 0830 PAllEL P604                                                                        PAftELS P669. P670. P671. P672 Process Radiation                                                                                 Hein Steam Line RAD              6.8E+2 mR/hr
      .                                                             Alarm Cntet Vent Exh RAD            c1.0E-1 mR/hr Orrgas Pre-treatment              2.5E+2 R/hr

Orrgas Post-treatment A 2.0E+2 cpe PA80EL P902 /

8 2.0E+2 cpm Common Airborne ces fcomi AIare Eng Service Water A 3.0E+1 cpm RWS Vent Exh 2.0E+1 ; 8 3.0E+1 cpe FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PA8 EEL P906

PA8KL 803 Common Process and Area cgs _ Alare Turb Bldg East 2.5E+0 mR/hr UD-HH-73 East Liq 3.0E+1 i Turb Bldg West 2.5E+0 mR/hr UD-HH-70 West Liq 3.2E+1 ;. - IICC Heat HX 3.5E+1 f'

PAIIEL P804 Radweste to ESW 3.0E+1 i

~,

Airborne Radiation Ces (csel algf3 Redweste to Sewage 3.6E+1 AnnuIus Exh A ces Q,9Q9 ; 8 L_0!1. F Cntet Ata 2JQ. peETEOROLOCICAL C08101110ess ; Drywell - HR (R/hr) JJQ , A8 Vent Lpd. Wind Speed ... 2L.g_._ aph ! OC8 Vent Exh LgEfjl

Wind Direction Jo OC8 Vent - HR g,9Efg Tempe ra ture 35 *F i OG Vent Pipe LDL12 Delta T -1.20 *F e ut Plant vent 6.0Lfl US Plant Vent - MR Q,Did!

TB/HS Vent !L9il). 18/H8 Vent - der !18;fj! Si Packing Exh < 1 1. U2 Plant Vent i;f. U2 Plant Vent - MR 0.0E+0

DW170C/A/9/ba ;

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a b x . r J AREA RADIATION MONITORS Time: 0830 - s TAG # LOCATION READING (MR/hr) F. 1D21NO30 Personnel Air Lock, Cntat (600'6") 5.0E+0 E ID21N040 CRD HCU West, Cntet (620'6") 5.0E+0 1D21N050 RBRT Area, Cntet (642') 1.0E+2 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 ID21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 1D21N080 Uoper Pool Area, Cntet (689'6") 2.0E+0 1D21N110 Aux Blda East - (574'10") 7.0E+0 1D21N120 Aux Blda West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 k 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 !-

!.   #         ID21N160           Turb Rm West                          <

(647'6") 2.5E+0 f 1D21N170 Turb Blda (605'6") 2.5E+0 ,. 1D21N180- Hotwell Pump Area. TB (577'6") 1.0E+1 I' 1D21N190 , TB Sump Area TBC (548'6") 2.0E+1 1D21N200 ~ OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pep Area, TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area, OGB (602 ' 6) 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 ,

'      n       1D21N240           Fdw Pump Area, HB                             (647'6")                                 6.6E+0 k,/     1D21N400            CR, CC                                        (654'6")                                 1.6E-1 h;

1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 D21N250 RWB West (574'10"). 2.5E+1 h^ D21N260 RWB East (574'10") 1.5E+1 :. . D21N270 RWB (602') 5.0E+0 " 2 _D21N280 Process Sample Re, RWB (623'6") 4.0E+0 F 4 D21N290 RW Evap, RWB (623'6") D21N310 4.0E+0 i. FPCU F/D 1rea. IB (599')- 6.0E+0 ' D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3 i, , D21N330 Spent Fuel Storane Pool IB (620'6") 5.8E+2 -p D21N420 FPCU Cire Pop Area. IB (574'10") 9.0E+0 i.: 1D21N340 Unit 1 DW, Portable, Cntet (655') - h D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 F D21N370 SRW Drummina Area RWB (623'6") 6.0E+0 5: ID21N090 Refuelina Bridae, Cntat (689'6") 3.0E+0 g D21N390 Tuel Serv Hdla Platform. IB (620'6") 2.0E+3 j i.t i Q

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e Time: 0845 Message No.: M - PERRY NUCLEAR POWER PLANT - s 1984 EMERGENCY PREPAREDNESS EXERCISE ' MESSAGE FORM .

s Messane For: Control Room /TSC .

Simulated Plant Conditions: See attached sheets [. Messame: ***THIS IS A DRILL *** ,.. a L.

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                           '                                                                                                   ~

f. ll f by. FOR C0h"R07~2R USE ONLY ri

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Controller Notes: f,. b, Actions Expected: r f.$ ! ?> [ L

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            , PERRY NUCLEAR POWER PLANT                                             '1984 EMERGENCY PREPAREDNESS EXERCISE                                               TIME: 0845 P601                                                           P660 CONTAINMENT PARAMETERS                                              SYSTEM INFORMATION                                                REACTOR PARAMETERS Tempe ra tu re       Pressu re                                                              Pressure       Flow                 Pressure-       1018         psig f*F)              fosial                                                     Status      fosial        faomt

Level 31 in. f _ NR Cntet 81 0 RWCU PMP A OP 1350 Neutron Drywe1i 120 0.1 B OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra ture Level

(*F1 (Ft.) B OP 230 FDW F1w 15.4 Mib/hr Supr P1 88 18.2 C SS O ST Flw (Total) 15.4 Mlb/hr CBP A OP 275 Line A 3.8 SYSTEMS INFORMATION B OP 280 Line B 3.8 Pressure Flov __ Status ioslo) fcoal C SR 150 Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 B SR B OP 330 . 1 C SR C OP 330

-{

LPCS SR D SR 160 l' RCIC SR RFP A OP 1065 15.1 i HPCS SR 8 OP 1063 14.9 [ i ECC A 00S MFP SR 0 0 8 J,URg1M-CRIERATOR ) B SR RCIRC A FAST 39254 PARAMETERS f ESW A OOS B FAST 39254 Mwatt 1235 f B SR I MVAR 350 e-MAJOR VALVE PARAMETERS !- C SR CNDR Vac 28 In. Hg ' Status Closed Open CRD A SR Thrt Pr 950 psig ;' MSIV- NORM 0 8 ! B OP 1900 44 BYP VLV j SRV NORM .19 0 Posit 0 % - SLC A SR 1' B SR I SLC STG TK LVL 4600 gal. [ i s

9;w. 7.. . p p ,- *yu - y ; r. . -- , - e e c : ey,- wp, __,y_, p- u - = ;g. 75 . ,,7_r; , s '. 3. ,- e . 2.. 7, .

r _, Q ,O ' PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDelESS EXERCISE TIME: 0845 1119 ELECTRICAL DISTRIBUTION P904 CST Level 410.000 esl. Status Load fMW) Status Status foslel OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP

      . TBCC PHP A                   OP                                  75                Con Breakers                    2 CL                                                        B. SR B            OP                                  75                Div 1 DC                        OOS                          Cont Rm HVAC Rtn Fan A                OP             i SS                                 IB                                                                                                                                  '

C , Div 2 DC. SR B SR SA Comp OP 128 , Div 3 DC ,_ }R Cont Re Eng RCIRC Fan A SR i-IA Comp SR 120 B SR P600 CIRW PHP A OP 46 _ Status P970 ' B OP 45 Cntet Val Cig Fan A OP Pressure .

                                                                                                                                                                     . Status            fosial C            OP                                  46                                            B           OP NCC Pump A              OP           112 SJAE            A            OP                                                                               C            SS B            OP           112
                     - 8             SS                                                                               D            OP C            SS            35 E          OP                                                                         i ADDITIONAL INFoltMATION                                                                                                                SW Pump    A                          56 OP F          SS Status Abbreviations:                                                                                                                                       B           OP             56 Drywell Cooling Fan IA                  OP OP          Ope ra ting                                                                                                                           C            SS             O 2A           OP                                                                          .

SS Secured Status D SS 0 l' 3A OP i AV Available MTR Fire Pump SR 4 18 SS i' SR Standby Readiress DO Fire Pump SR 28 SS >. SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Vsl Purge. [- Supp Fan A SS F-SP Fast Speed ! B SS

ISOL 1solated Cntet Vsl 4: DW Purge Exh Fan 'A SS B SS 00S Out of Service Drywell Purge Suppl Fan A SS ,

CL Closed B SS OVRD Override i AECTS Fan A DOS ! I B OP f' I . I i 77$<-e* " ' '

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                                                                                                                                                                           'i PERRY NUCLEAR POWER PLANT                          1984 EMERGENCY PREPAREDNESS EXERCISE                                                     TIME: 0845 PANEL P604                                                         PANELS P669. P670. P671. P672 Process Radiation                                                                 Main Steam Line RAD                   6.8E+2 mR/hr Alarm Cntet Vent Exh RAD                 s.t.0E-1 mR/hr Orrges Pre-treatment              2.5E+2 R/hr Offgas Post-treatment A          2.0E+2 cpm                                                                PANEL P902                                 ,

8 2.0E+2 cpm Common Airborne Gas fcomi AIa rm . Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FH8 Vent Exh 2.2E+1

dG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 '

B 5.5E+1 mR/hr PANEL P906 $ PANEL 803 Common Process and Area GRE Alarm <. Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Llg 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW LDL11

5 Airborne Radiation Gas fcpal Alarm Redweste to Sewage 3.6E+1 Annulus Exh A Cas DJL+0 ;

8 hpE+ Cntet Ate Drywe1I - HR (R/hr) 9JE Lg_Et. METEOROLOGICAL CONDITIONS AB Vent ;- LDL11 Wind Speed 24.0 enh l OGB Vent Exh LDLig Wind Direction Jo

t.

i OGB Vent - HR

Q OE_tg Tempera ture 35 'F l OG Vent Pipe RJ y - Delta T -1.15 *F ,

e l-U1 Plant Vent itJ di i U1 Plant Vent - HR gJ dQ TB/HB Vent nJEt1 TB/HB Vent - HR QJEiQ i ST Packing Exh hDL11 U2 Plant Vent i (tJLil i U2 Plant Vent - HR 0.UE+0 - 8 DW170C/A/10/ba l t i I .

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___ _ . - - . -~ ~ - - 4 3~ AREA RADIATION MONITORS Time: 0845 s 5 TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntmt [ (600'6") 5.0E+0 L' 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 ' 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0

   ,          ID21N080         Upper Pool Area, Cntet           (689'6")           2.0E+0 1D21N110         Aux Bldg East                    (574'10")          7.0E+0 1D21N120          Aux Bldg West                    (574'10")          7.0E+0 ID21N130          Turb Rm East                     (647'6")           2. 5E+0 '                     -

1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 , 1D21N160 1D21N170 Turb Rm West Turb Bldg (647'6") 2.5E+0 '[r (605'6") 2.5E+0 E ID21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 E ID21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 ID21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 h" ID21N400 1C21N410 CR, CC OG Hold Up Area TB (654'6") (577'6") 1.6E-1 1.0E+1 r

?.

D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 ,

              -D21N270         RWB                             (602')              5.0E+0 D21N280         Process Sample Rm, RWB          (623'6")            4.0E+0 D21N290         RW Evap, RWB                    (623'6")            4.0E+0 D21N310         FPCU F/D Area IB                (599')              6.0E.+0                        i.

D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3 ,'_ D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2 ' D21N420 FPCU Cire Pmp Area IB (574'10") 9.0E+0 ! 1D21N340 Unit 1 DW, Portable, Cntmt (655') - p D21N380 Waste Compsetor Area, RWB (623'6") 6.0E+1 , D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 , D21N390 Fuel Serv Mdig Platform, IB (620'6") 2.0E+3 r, I, b f: 4 A L e

     . . .                  ,. .   . .. . . . - .               -  .~         --        - -     -.~         - - -   ~ . -

Time: 0900 Me'ssage No.: M

         ..                                             PERRY NUCLEAR POWER PLANT                                                         '.

s 1984 EMERGENCY PREPAREDNESS EXERCISE

MESSAGE FORM

[t Message For: Control Room /TSC f r,. Simulated Plant Conditions: See attached sheets ~ b. Message: ***THIS IS A DRILL *** . [. - 7' c W

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                                                                                                                                            ~

FOR CONTROLLER USE ONLY

A'.. Contro11er' Notes: .The TSC and OSC should be activated by this time. /4 /I - Actions Expected: 4 t DW176/C/25/ba

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      , PERRY NUCLEAR POWER PLANT                           1984 EMERGENCY PREPAREDNESS EXERCISE --                                            TIME: 0900 P601                                            P680                                                                                      .

CONTAINMENT PARAMETERS SYSTFM INFORMATION REACTOR PARAMETERS - Tempe ra tu re Pressu re Pressu re Flow Pressure , 1018 psig f*F1 fosial _ Status loslo) feon) Level 31 In< NR Cntet 81 0 RWCU PMP A 'OP 1350 Neu t ron Drywell 120 0.1 B OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra tu re - Level (*F) trt.) B OP 230 FDW Flw 15.4 Mlb/hr Supe PI 88 18.2 C SS O ST Flw (Total) 15.4 Mlb/hr CBP A OP 275 Line A 3.8 SYSTEMS INFORMATION B OP 280 Line B ~ 3.8 Prsssure Flow - Status fosial foomi C SR 150 Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 B SR 8 OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 H PCS SR B OP 1063 14.9 'i ECC A OOS __ MFP SR 0 0 B SR IEB61MEr c[NERATOR i RCIRC A FAST 39254 PARAMETERS ESW 'A 00S B' FASF 39254 Mwatt 1235 8 SR HVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 In. Hg Status closed Open CRD A SR _ Thrt Pr 950 psig B OP 1900 44 BYP VLV SRV- NORH 19 0 Posit O % , SLC A SR 8 SR SLC STG TK LVL 4600 gal.

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  , . PERRY NUCLEAR POWER PLANT                            1984 EMERCENCY PREPAREDNESS EXERCISE                                                     TIME: 0900 P870                                   ELECTRICAL DISTRibui_10M                                                 P904 o                                                                                                                                                                                        [.

CST Level 410.000 cal. - Status Load IMW) Status Status fosial Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP -I TBCC PMP A OP 75 Ce'n Breakers 2 CL B SR B OP 75 Div 1 DC OOS Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DG SR B SR SA Comp OP 128 Div 3 DG SR Cont Pm Eng RCIRC Fan A SR 1A Comp SR 120 B. SR P800 ClRW PMP A OP 46 Status P970 8 OP 45 Cntet Vsl Cig Fan A OP Pressu re Status fosial C OP 46 8 OP NCC Pump A OP 112 SJAE A OP C SS B OP 112 8 SS D OP C SS 3 5 _ __ E OP I-ADDITIONAL INFORMATION SW Pump A OP -- 56 F SS Status Abbreviations: B OP 56 Drywe1I Coo 1Ing Fan IA OP OP Ope ra t Ing C SS O ___ 2A OP SS Secured Status D SS 0 3A OP AV Available MTR Fire Pump SR : , 18 SS , SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Vsl Purge

                                                      -Supp Fan                 A             SS F-SP      Fast Speed B             SS ISOL       isolated                        Cntet Vsl se DW Purge Exh Fan           A_            SS NORM      Normal B             SS                                                                                         '

00S Out of Service Drywell Pu rge Suppl Fan A SS 4 CL Closed B SS OVRD Override AEGTS ran A 00s B OP l F

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PERRY MUCLEAR POWER PLANT -1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0900 .

s , RX WATER LEVEL RX PRK32 RX POWER SUPR PL TEMP 11 .l.ll 1018 PSIG 100 % as *E 60- 1100- 120 ' 110 45-950- 90- 90-30- , 800- 40- 70-15- 650- 0 50 O 500 -30 -20 -10 0 -30 -20 -10 0

                   -30  -20    -10        0                  -30            -20    -10            0                         Time (min)                                          Time (min)

Time (min) Time (min) DW TEMP CONTMT TEMP CONTMT PRkSS SUPR PL LEVEL

i-120 *E s1 *E O PSIG 18.2 f.I 200- 110- 20- 19-1 150- 90- 15- -

100- 70- 10- 18-50 50- 5- -

                   -30  -20    -10       0                  -30             -20    -10            0            0-                                                 17 Time (min)                                          Time (min)                       -5                                                        -30      -20     -10        0
                                                                                                                       -30  -20       -10             0                         Time (min)                        ,

l ' Time (min) i

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            ,         PERRY NUCLEAR POWER PLANT'                                                                            1984 EMERGENCY PREPAREDNESS EXERCISE                                                                  . TIME: 0900 PANEL P604                                                                         PANELS P669. P670. P671. P672 Process Radiation                                                                                                                        Main Steam Line RAD                  6.8E+2 mR/hr
,                                                                                                 ".                           Alarm Cntat' Vent Exh RAD                41.0E-1 mR/hr Orrgas Pre-treatment                                                 2.5E+2 R/hr Offgas Post-treatment A                                              2.0E+2 cpm                                                                                  PANEL P902                                           e B    2.0E+2 cpm                                                      Common Airborne                             Gas (comi                     Alarm J                          Eng Service Water                                               A    3.0E+1 cpm                                                            RWB Vent Exh                          2.0E+1 8    3.0E+1 cpm                                                            FHB Vent Exh                          2.2E+1                                        .

i OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr ! PANEL P906 PANEL 803 Common Process and Ares ggtg Alarm g Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 fAKEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (coal Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Gas (IAM B M 1. Cntet Atm Sg ;t, METEOROLOGICAL CONDITIONS . Drywell - HR (R/hr) JEf.

                                                                                              .M!1.

AB Vent Wind Speed {. OG8 Vent Exh gJ M J5. 0 mph Wind Direction JS [- OG8 Vent - HR QJdQ Tempe ra tu re 36 "F OG Vent Pipe E_tg Delta T -1.03 'r UI Plant Vent ;.t.1 U1 Plant Vent - HR ;tQ I 18/HB Vent ;1] TB/H8 Vent - HR ;1f! ST Packing Exh ;t U2 Plant Vent 6J.;1., ' U2 ilant Vent - HR Gd M, _ DW170C/A/11/ba

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4 (, ' AREA RADIATION MONITORS Time: 0900

                                 \
                                                                    =

TAG # LOCATION READING (MR/hr) . 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 ID21N040 CRD HCU West, Cntet (620'6") 5.0E+0 !. 1D21N050 RBRT Area, Cntat (642') 1.0E+2 ID21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 . 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 ,, ID21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 + 1D21N110 Aux Bldg East (574'10") 7.0E+0 ' 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 Y 1D21N140 CRD HCU East, Cntat (620'6") 5.0E+0 - ID21N160 Turb Rm West (647'6") 2.5E+0 [ ID21N170 Turb Blda (605'6") 2.5E+0 i 1D21N180 Hotwell Pump Area, TB (5 7 7 ' 6") 1.0E+1 [3 g 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 6

ID21N200 OGB (584') 1.1E+1 -

1D21N210 Cnds Fitr Pmp Area TBC (568'6") 9.0E+0 [ 1 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 , 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 ' 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 h-O 1D21N400 CR, CC (654'6") 1.6E-1 p b 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 i D21N250 RWB West (574'10") 2.5E+1 {[ RWB East <r D21N260 (574'10")~ 1.5E+1 f D21N270 RWB (602') 5.0E+0 [,

D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 E D21N310 FPCU F/D Area, IB (599') 6.0E+0 h D21N320 Fuel Preparation Pool, IB (620'6") 2.0E+3 '

D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2 i;. D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 i 1D21N340 Unit 1 DW, Portable, Cntat (655') - f, D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 if D21N370 SRW Drummina Area RWB (623'6") 6.0E+0 - 1D21N090 Refuelina Bridge, Cntet (689'6") 3.0E+0 V D21N390 Fuel Serv Hdla Platform, IB (620'6") 2.0E+3 t-i. F

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                                                                                                                 .   . = .
 . . . . .      ... .. . . . -                   ,      -,       .-- -- ~ ~ - - -    --     -                      -       -

Time: 0915 Message No.: h PERRY NUCLEAR POWER PLANT s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Control Room ' - Simulated Plant Conditions: .

            -            Message:    ***THIS IS A DRILL ***

From' Perry Plant Operator on routine rounds'in the Intermediate Building, Elevation 574': -

                                      " Simulator. I am at the Fuel Pool Cooling and Cleanup Backwash                               .

Receiving Tank, Elevation 574'. I have fallen in a pool of water T out here. I gashed my head and hurt my left arm. Land some p assistance!" I1 4 n F {. y t' i 1 ', FOR CONTROLLER USE ONLY . C Controller Notes: There has been some leakage from the downstream flange , connection on G50-F303 resulting in approximately ten : gallons of fluid on the floor. The flange is still dripping slowly and will continue until it is tightened. 1 Actions Exper.ted: A First Aid Team should be dispatched. 4 DW176/C/26/ba

( s D

                               -                                                  --          ,    w   -   - , -

Time: 0915 Message No.: M PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM -

                                                                                                                                  . (_ .

4 Message For: Control Room /TSC p. .

                           . Simulated Plant Conditions: See attached sheets                                                         .

Message: ***THIS IS'A DRILL *** E.

                                                                                                                                     ?:
                                                                                                                                      't    ,

FJ E 1,: E i t t a V-() h h r~ r1 L

                                                                                                                                     ,, c FOR CONTROLLER USE ONLY                                                                                   f u

L Controller Notes: b ' si n f-i Actions Expected: ' Q Y. is 4 l

DW176/C/27/ba-( s

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 ,         PERRY NUCLEAR POWER PLANT                                                                         1984 EMERGENCY PREPAREDNESS EXERCISE                                       TIME: 0915 EftDI                                                                fit 00                                                                                i CONTAINMENT PARAMETERS                                                                       SYSTEM INFORMATION                                          REACTOR PARAMETERS Tempe ra tu re                       Pressure                                                                        Pressu re    Flow          P res su ro        1018        psig

(*F) fosial Status fosial foom) Level 31 In, NR Cntet 81 0 RWCU PHP A OP 1350 Neut ron Drywell 120 0.1 8 OP 1350 Mon 100 Range APRM HWL PMP A OP -230 Mode SW RUN Tempe ra tu re Level 7-f*F) fFt.) B OP 230 FDW Flw 15.4 Mlb/hr Supr P1 88 18.2 C SS O ST Flw -(Total) 15.4 Mib/hr CBP A OP 275 Line A 3.8 SYSTEMS INFORMATION B OP 280 Line B 3.8 Pressure Flow Status _1pslal faomi C SR ___150 Line C 3.8 RHR A SR RFBP A OP 330 . Line D 3.8

8 SR 8 OP 330 '

I C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 HPCS SR 8 OP 1063 14.9 , ECC A 00S MFP SR 0 0 1MR@lN[-C[NERATOR

B SR RCIRC A FAST 39254. PARAMETERS ESW A 00S B FAST 39254 Mwatt 1235 8 SR .

MVAR 350 MAJOR VALVE PARAMETERS ; C SR CNDR Vac 28 in. Hg Status Closed Open CRD A SR Thrt Pr 950 psig MSIV NORM 0 8 8 OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR B SR SLC STG TK LVL 4600 gal.

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    . PERRY NUCLEAR POWER PLANT.                                1984 EMERGENCY PREPAREDNESS EXERCISE                                                                      TIME: 0915                                        -

P670 ELECTRICAL DISTRIBUTION P904 ! 1 CST Level 410.000 cal. Status Load IMWI Status Status fosial 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL B SR s B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan- A OP

1 C SS 18 Div 2 DC SR B SR SA Comp OP 128 Div 3 DG 'SR Cont Re Eng RCIRC ran A SR 1A Comp SR 120 B' SR P800 s CIRW PMP A OP 46 Status ! P970 8 OP 45 Cntet Vsl Cig Fan A OP Pressure Status Iostal C OP 46 B OP NCC Pump A OP 112 SJAE A OP C SS 8 OP 112 B SS D OP- ' C SS 35 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywell Cooling Fan 1A OP OP Ope ra t ing C SS O 2A OP D SS Secured Status D SS 0 I 3A OP AV Available MTR Fire Pump SR , 1B SS SR Standby Readiness DD Fire Pump SR 28 SS

Shutdown

SHTDN - S-SP Slow Speed Cntet Vsl Pu rge Supp Fan A SS F-SP Fast Speed B SS ISOL 1solated Cntet Val as DW,

              .                                              Purge Exh ran                   'A              SS NORM       Norua 1 8              SS 00S        Out of Service                       Drywell Purge Suppi Fan                        A              SS CL         Closed                                                                                                                                                                                             ,

B SS OVRD Ove rride AEGTS Fan A 00S

B OP r.

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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 0915 PANEL P604 PANELS P669. P670. P671. P672 1 Process Radiation Hain Steam Line RAD 6.8E+2 mR/hr , Cntet Vent Exh RAD 41.0E-1 mR/hr Orrgas Pre-treatment 2.5E+2 R/hr Offges Post-treatment A 2.OE+2 cpm PANEL P902 , 8 2.DE+2 cpm Common A1rberne ces fcom1 AIare Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHB Vent Exh 2.2E+1 OC' Carbon Bed Vault A 6.0E+1 mR/hr _ _ , , CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area sp.g A f a re Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Lig 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 ' PANEL P804 Radweste to ESW 3.0E+1 Ai rborne Radiation Gas (coal Alarm Radweste to Sewage 3.6E+1 Annulus Exh A Gas 6.QQQ 8 jd ;+_t Cntet Ata L.Q 1. METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) LQQ AB Vent 2J 1. . Wind Speed 20.0 mph OGB Vent Exh EJ R Wind Di rection 220

OGB Vent - HR QJE+Q Tempe ra tu re 3L_ 'F OG Vent Pipe 2JE +2 Delta T -0.82 *r

, US Plant Vent L.QQ1 U1 Plant Vent - HR TB/ IIB Vent QJMQ stJEE TB/HB Vent - HR MQ ST Packing Exh E_1 . U2 Plant Vent JQ. U2 Plant Vent - HR 0.0E+4 - DWl70C/A/12/ba

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i e AREA RADIATION MONITORS TAG # LOCATION ID21NO30 Personnel Air Lock, Cntet RBRT Area, Cntmt (642') 1D21N060 Tip Drive Area, Cntmt 1D21N080 Upper Pool Area, Cntat 1D21N120 Aux Blda West 1D21N130 Turb Rm East ,, 1D21N140 1D21N160 Turb Rm West ID21N220 1D21N230 OG After F1tr (600'6") 2.0E+1 1.0E+1 [ 0 f- . ID21N240 Fdw Pump Area, HB C 1D21N400 CR, CC D21N270 RWB . D21N310 t' D21N320 Fuel Preparation Pool, IB D21N330 Spent Fuel Storage Pool, IB D21N420 FPCU Circ Pmp Area, IB 1D21N340 Unit 1 DW, Portable, Cntat U D21N380 Waste Compactor Area, RWB 1D21N090 Refueling Bridge, Cntet [ D21N390 Fuel Serv Hd1g Platform. IB Time: 0915 s READING (MR/hr) } (600'6") 5.0E+0 b 1D21N040 CRD HCU West, Cntat (620'6") 5.0E+0 1D21N050 [ 1.0E+2 ' (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 . (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 [. (574'10") 7.0E+0 4. - (647'6") 2.5E+0' .'. CRD HCU East, Cntet (620'6") 5.0E+0 (647'6") 2.5E+0 f ID21N170 Turb Blda (605'6") 2.5E+0 i-1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 I ID21N190 TB Sump Area, TBC (548'6") 2.0E+1 T 1D21N200 OGB (584') 1.1E+1 T 1D21N210 Cnds Fitr Pmp Area TBC (568'6") 9.0E+0 . Area, OGB HP Fdw Htr Area, HB (602'6") (647"6") 6.6E+0 h. (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 < (602') 5.0E+0 i D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 I, i D21N290 RW Evap, RWB (623'6") 4.0E+0 FPCU F/D Area, IB (599') 6.0E+0 [.. (620'6") 2.0E+3 I* (620'6") 5.8E+2 , (574'10") 9.0E+0 . (655') - (623'6") 6.0E+1 D21N370 SRW Drumming Area RWB (623'6") 6.0E+0 . (689'6") 3.0E+0 (620'6") 2.0E+3 ,i;

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Time: 0920 i l Message No.: H I PERRY NUCLEAR POWER PLANT s 1984 EMERGENCY PREPAREDNESS EXERCISE

, MESSAGE FORM f

  .,                                                                                                                                               t-Message For: Controller with injured victim Simulated Plant Conditions:

Messame: ***THIS IS A DRILL *** a FOR CONTROLLER USE ONLY IL. Controller Notes: 1. Section 8.2, Part A, shows the location of the Backwash j. Receiving Tank and contamination levels in the area. 9

2. The initial survey of the victim producas'the first body map shown in Section 8.2, Part A. The information will be provided only when appropriate surveys are taken. .

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3. The victim has a gash on his head and has broken his ;.l upper left arm. The victim also complains of dizziness '

and head pain with pupils slightly dilated.

4. Following removal of the victim's outer clothing

i '. N simulated by paper clothing), the second body map I shows residual levels of contamination on the victim.

Actions Expected: 1. The victim and area should be surveyed quickly to obtain-an estimate of contamination and radiation levels. - Appropriate ALARA precautions should be observed.

2. The victim's simulated clothing (paper) should be removed.

Request an offsite ambulance.' [ l/ f

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3. -

4. SAS calls Lake County Memorial East Hospital with the following information: <

                                                                                                                                               # 1;

a. We are sending an injured contaminated individual. - yt/

b. Extent of injury. [ y/ 'g' / .s u ,

gg'/ i c. Number of victims.

d. Estimated time of arrival at hospital./ . . f ,, ,

1, , f 7 , '. .:

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Time: 0930 B" Message No.: M PERRY NUCLEAR POWER PLANT s' 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Room /TSC [3 . Simulated Plant Conditionn: See attached sheets Messaae: ***THIS IS A DRILL ***

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(. !i i; FOR' CONTROLLER USE ONLY , Controller Notes: An offsite ambulance should be requested by now. o

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                                                                                                                #                        s Actions Expected:     Call for an offsite ambulance;.poordina g this request with

Security and/or Health Physics; esigsfate coordinate a pickup i

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     ,. PERRY NUCLEAR POWER PLANT                                   1984 EMERCENCY PREPAREDNESS EXERCISE                                 .-            TIME: 0930 ffdt1                                                 P680 CONTAINMENT PARM4ETERS                                  SYSTEM INFORMATION                                              REACTOR PARAMETERS i-Temperature -        Pressure                                                   Pressure        Flow              Pressure         1018     psig

(*Fl fosial Status foslo) faom) Level 31 in, NR Cntet 81 0 RWCU PHP A OP 1350 Neutron Drywell 120 0.1 B OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra tu re Level . I'F1 fft.) B OP 230 FDW Flw - 15.4 Mlb/hr Supr Pt 88 18.2 C SS 0 ST Flw (Total) 15.4 Mlb/hr CBP A OP 275 Line A 3.8 - B OP 280 Line B 3.8 . Pressure Flow Status fosial teos) C SR 150 Line C 3.8 [I

          - RHR A              SR                                          RFBP.         A            OP         330                              Line e         R                   ?
 ,                 8           SR                                                        8            OP         330 C           SR                                                        C            OP         330                                                                   ,

LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 , HPCS SR B OP 1063 14.9 ECC A 00S MFP. SR 0 0 TURBIME-CENERATOR B SR RCIRC A FAST 39254 PARAMETERS ESW A 00S B FAST 39254 Mwatt 1235 I B SR MVAR 350 MAJOR VALVE PARAMETERS Status Closed Open CRD A SR Thrt Pr 950 psig B OP 1900 44 BYP VLV !, SRV NORM 19 0 Posit 0 % SLC A SR 8 SR SLC STG TK LVL 4600 gal. S V

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 ,. PERR'Y NUCLEAR POWER PLANT                         1984 EMERGENCY PREPAREDNESS EXERCISE                                           TIME: 0930 P870                               ELECTRICAL DISTRIBUTION                                         P904 CST Level                410.000 cal.                                 _Jtatus         Load fMW)                                          Status' Status      fosial           OFFsite Pwr Sources       2 AV                           Cont Rm HVAC Supp Fan A            OP TBCC PHP A           OP          75             Cen Breakers              2 CL                                                       B      SR            .

i B OP 75 Div 1 DG OOS Cont Rm HVAC'Rtn Fan A OP C SS 18 Div 2 DG SR B SR SA Comp OP 128 Div 3 DG SR Cont Rm Eng RCIRC Fan A SR IA Comp SR 120 B SR P800 CIRW PMP A OP _ 46 Status P970 8 OP 45 Cntet Vs1 Cig Fan A OP Pres su re Status fosial C OP 46 8 OP 1 NCC Pump A OP 112 SJAE A OP C SS B OP 112 t B SS D OP l~ C SS 35 [

 .                                                                        E            OP ADO 1TIONAL 1NFORMATION                                                                             SW Pump      A        OP          .56       [

F SS , Status A::breviations: 8 OP 56 Drywell Cooling Fan 1A OP ' OP Ope ra t ing C SS O i; 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed Cntat Vsl Purge Supp Fan

SS
F-SP Fast Speed i B SS '

ISOL isolated Cntet Val er DW Purge E$ Fan 'A SS NORM Normal B SS OOS Out oF Service Drywell Pu rge Suppl Fan A SS CL Closed - B SS OVRD Override AECTS Fan A OOS B OP

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t-a PERRY NUCLEAR POWER PLANT , 1984 EMERCENCY PREPAREDNESS EXERCISE TIME:0930

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as *[ i 60- 1100- 120-110 I

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45- - 950- 90- , 90-i - % 30- 800- 40 - i 70-15 l '650- 'o s50 0 500 -30 -20 -10 0 -30 -20 -10 0

                             -30  -20    -10    0                         -30        -20     -10,   O                    Time (min)                                      Time (min)                 ,

Time (min) Time (min) f-f, t DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL s 120 'I 81 'E O ffj.G 18.2 11 y

                                                                                                                                                                                                    #9 .

200- 110- 20- 19- !' 150- , 90- 15- - 100- 70- 10- 18- ,. 50 50- 5- -

                             -30  -20    -10    0                         -30        -20     -10    0       0-                                            - 17 Time (min)                                         Time (min)            -5                                                      -30  -20    -10     0
                                                                                                                   -30   -20      -10           0                       Time (min)

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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 0930-- PANEL P604 PANELS P669.' P670. P671. P672 . Process Radiation . Main Steam Line RAD 6.8E+2 mR/hr. Alarm Cntet Vent Exh RAD 41.OE-1 mR/hr Offges Pre-treatment 2.5E+2 R/hr Orrges Post-treatment A 2.0E+2 cpm PANEL P902 , B 2.0E+2 cpm Common Airborne Gas (coal Alarm Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 B 3.CE+1 cpm FHB Vent Exh 2.2E+1 bG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0Et1 B 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gas! Alarm , Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Llg 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1, NCC Heat.HX 3.5E+1 i

  ,                                 PANEL P804                                                     Radvaste to ESW            3.0E+1 l;

Alrborne Radiation Gas (C2stl Ala rm Radweste to Sewage 3.6E+1 Annulus Exh A Gas Q,0110 I-

  ,                          B             JiQE1.                                                                                                             .,

Cntat Atm 929 ;.1.. METEOROLOG1 CAL CONDITIONS !

 "            Drywe l l - HR (R/hr)        149 1 AB Vent                      210 1.       .

Wind Speed 17.0 mph } OCB Vent Exh ZipES Wind Direction 225 * !- OCB Vent - HR Q20';+Q Tempe ra ture 38 'F OG Vent Pipe 2J ;.12 Delta T -0.80 'F U1 Plant Vent niD ;11 ' , U1 Plant Vent - HR QipEfD_ l TB/HB Vent 6 OLij.

TB/HB Vent - HR Q J Lift l '. ST Packing Exh 811gE1.

l U2 Plant Vent 6.4901 U2 Plant Vent - HR

0. 0 E+(! -

( l l DW170C/A/13/ba i i e [ t < s

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, ._ .. . , . . ..w. , - ~ . . L. AREA RADIATION MONITORS Time: 0930 s TAG # LOCATION READING (MR/hr) - 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0

,              1D21N040     CRD HCU West, Cntet              (620'6")                 5.0E+0 ID21N050      RBRT Area, Cntet                 (642')                   1.0E+2 1D21N060    Tip Drive Area, Cntet             (600'6")                 3.0E+1                                     .

1D21N070 'RWCU F/D Area, Cntat (664'7") 7.0E+0 ' 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 l 1D21N110 Aux Blda East (574'10") 7.0E+0 , ID21N120 Aux Blda West (574'10") 7.0E+0 '

ID21N130 Turb Rm East (647'6") 2.5E+0 #

ID21N140 CRD HCU East, Cntet (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Blda (605'6") 2.5E+0 l 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 I ID21N190 TB Sump Area TBC (548'6") 2.0E+1 ! 1D21N200 OGB (584') 1.1E+1 ID21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 - 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 ;..

      /?      ID21N400     CR, CC                            (654'6")                 1.6E-1 b~. 1D21N410     OG Hold Up Area, TB               (577'6")                 1.0E+1                                     ;

, D21N250 RWB West (574'10") 2.5E+1 l-i D21N260 RWB East (574'10")~ 1.5E+1 D21N270 RWB (602') 5.0E+0 l D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 l D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 F?CU F/D Area. IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") 2.0E+3 D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2 D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntet (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 ID21N090 Refueling Bridge, Cntat (689'6") 3.0E+0 , D21N390 Fuel Serv Hdig Platform, IB (620'6") 2.0E+3 i s 4 4

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Time: 0930 - m Message No.: M r-Q' PERRY NUCLEAR POWER PLANT -' . < 1984 EMERGENCY PREPAREDNESS EXERCISE -' ', s MESSAGE FORM / f ; s'c. l ; Messane For: Control Room m I

                                                                                                                                                 ,p Simulated Plant Conditions:                            )                                         x*~           .._'
                                                                                                                                         '3-                                                             r:

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Message: ***THIS IS A DRILL ***/ -

                                                                         /
                                                                        /                                                                                                                                ,

Call Lake County Memorial East Hospital and inform them of the impending g transport of an injured contaminated victim to them. 7-

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t5., e /. . i> a P L 4-e 5-FOR CONTROLLER USE ONLY ' .- . ,q [. 6 Controller Notes: . I !! j r l Actions Expected: -- t.

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          ,          DW176/C/30/ba                                                                                                                                                                        .

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Time: 0940 Message No.: A

    -. .                                                               PERRY NUCLEAR POWER PLANT I

s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Controllers [. Simulated Plant Conditions: Messame: ***THIS IS A DRILL *** . k i i i e G. . :; t. FOR CONTROLLER USE ONLY e I Controller Notes: The ambulance arrives at the Primary Access Control (PAC) point gate approximately at this time. . Actions Expected: 1. Security at the PAC gate should notify SAS. 2.- PAC Security should distribute dosimetry and escort the ambulance to the designated area to pick up the i' victim. 9 4 DW176/C/31/ba e E b

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Time: 0945 Message No.: M a (. PERRY NUCLEAR POWER PLANT s 1984 EMERGENCY PREPAREDNESS EXERCISE 1 MESSAGE FORM Message For: Control Room /TSC [. f' Simulated Plant Conditions: See attached sheets Message: ***THIS IS A DRILL *** L: I T: I s

I' t-i. FOR CONTROLLER USE ONLY i i . Controller-Notes: l Actions Expected: ( I e b

               . DW176/C/32/ba                                         ,

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      , PERRY NUCLEAR POWER PLANT                                1984 E:1ERCENCY PREPAREDNESS EXERCISE                              .-

TIME: 0945 P601 P680 CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressu re Flow Pressu re 1018 psig (*Fl fosial Status. loslal faom) Level 31 Ins NR Catet 81 0 RWCU PMP A OP 1350 Neutron Drywell 120 0.1 B OP 1350 Mon 100 Range APRM HWL PMP A OP 230 Mode SW RUN Tempe ra tu re Level f*F1 frt.) B OP 230 FDW Flw 15.4 Mlb/hr Supr PI 88 18.2_ C SS 0 ST Flw (Total) 15.4 Mlb/hr CBP A OP 275 Line A 3.8 , SYSTEMS INFORMATION

  .                                                                              B          OP        280                                Line B           3.8                P Pressure             Flow                                                                                                                    -

Status fosial local C SR 150 Line C 3.8 RHR A SR RFBP A OP 330 Line D 3.8 [ 8 SR B OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 HPCS SR B OP 1063 14.9 ECC A OOS MFP SR 0 L ' TURBINE-CEMRATOR S SR RCIRC A FAST 39254 PARAMETERS ESW A 00S B FAST 39254 Hwatt 1235 B SR MVAR 350 MAJOR VALVE PARAMETERS C SR CNDR Vac 28 in. Hg Status closed Open s CRD A SR Thrt Pr 950 psig MSIV NORM 0 8 . 8 OP 1900 44 BYP VLV SLC A SR SRV NORM 19 0 Posit 0 % B SR ' SLC STC TK LVt. 4600 gal. [

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t'^ O 1hc I PERRY NUCLEAR POWER PLANT 1984 EMERCEllCY PREPAREDNESS EXERCISE ' TIME:~ 0945 P870 ELECTRICAL DISTRIBUTION P904 i CST Level 410.000 eat. Status Load iMW1 _ Status-Status loslel 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP i TBCC PMP A OP 75 Con Breakers 2 CL 8 SR

    .                                    8             OP                   75                               Div 1 DC                               00S                              Cont Rm HVAC Rtn Fan A                  OP '

C SS 18 Div 2 DC SR 8 SR SA Comp OP 128 Div 3 DC SR Cont Re Eng RCIRC Fan A SR

  .                         IA. Comp                   SR           120                                                                                                                                            8         SR P800 CIRW PMP A                 OP                  46                                                                               Status P970                                          ,

8 OP 45 Cntet Vsl Cig Fan A OP Pressu re - Status (osial C OP 46 8 OP , NCC Pump A OP 112 b SJAE A OP C SS i-8 OP 112 t-8 SS D OP - 5 ' C SS 35 1 E OP .

  .                               ADD 1T10NAL INFORMATION                                                                                                                            SW Pump       A       OP                56                    '[

F SS t Status Abbreviations: 8 OP 56 i' ' Drywell Cooling Fan IA OP OP Opera ting C SS O 2A OP SS Secured Status D SS 0 , 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDil Shutdown 38 SS , S-SP Slow Speed Cntet Vsl Purge - Supp Fan A SS F-SP Fast Speed 8 SS 3 ISOL Isolated Cntet vsl er DW , Purge Exh Fan A SS NORM No rea 1 - 8 SS ,i OOS Out or Service Drywell Purge l Suppl Fan A SS CL Closed 8 SS l OVRD Override l AECTS Fan A 00s , 1.. : 8 OP P i

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Q.. C) !', PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDMESS EXERCISE TIME: 0945 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 6.8E+2 mR/hr

     -                                                        Alarm Cntet Vent Exh RAD                  41.0E-1 mR/hr Orrgas Pre-treatment           2.5E+2 R/hr*

Orrgas Post-treatment A 2.0E+2 cpm E6HEL P902 , B 2.0E+2 cpm Common Airborne Gas icpal Ala rm Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 B 3.0E+1 cpm FHB Vent Exh 2.2E+1 OG Ca rbon Bed Vaul t A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 . B 5.5E+1 mR/hr f6HEL P906 PANEL 803 Common Process and Area gne Ala re i Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East. Liq 3.0E+1 Turb Bldg W est 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 F

                                                                                         .NCC Heat HX                            3.5E+1

[ PANEL P804 Radweste to ESW 3.0E+1 - I V Airborne Radiation Cas (coal Alarm Radweste to Sewage 3.6E+1 ', i Annulus Exh A Gas DtDLif? i B 1sDLt ? Cntet Ata 2tD Lt.. MLIEQEDLOGICAL CONDITIONS t Drywell - HR (R/hr) lid!E1.. AB Vent 2,9 _;1;.. Wind Speed ___20.0 . sph OGB Vent Exh

2,0 2SL Wind Direction- 225 OGB Vent - HR QtQ ;10 Tempe ra tu re 38 *F OG Vent Pipe EtD 2t2 Delta T -0.75 *F U1 Plant Vent 6tD it1 U1 Plant Vent - HR QtD 2tQ TB/HB Vent 6tD JU, TB/HB Vent - HR Ot0Lif!

ST Packing Exh haQLt ' U2 Plant Vent 6tDL1;. . U2 Plant Vent - HR 0.0E+0 DW170C/A/14/ba I

                            . -. ,- sn .                         .-           . ;, .        .                                                  ,
                                          .---.r,.......,.,-                                                   . .,-.;,; 7 .,, . , , - .--,,,

    . . . . .                 . . . , _                               . . . .                z..                           . . -           a -                                                               -- - - +

t 1 l

f'V AREA RADIATION MONITORS Time: 0945 1 i

s , 7: TAG #A LOCATION READING (MR/hr) l i 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 1 . ID21N040 1D21N050 CRD HCU West, Cntet RBRT Area, Cntet (620'6") (642') 5.0E+0 1.0E+2 f t i 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 *

ID21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 ,

                    ,                 1D21N080                                Upper Pool Area, Cntat                                       (689'6")                                          2.0E+0                     '"

1D21N110 Aux Bldg East (574'10") 7.0E+0 (~ I 1D21N120 Aux Blda West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 *: i 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 I 1D21N160 Turb Rm West (647'6") 2.5E+0 .. 1D21N170 Turb Blda (605'6") 2.5E+0 [- 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 L 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 j, 1D21N200 OGB (584') 1.1E+1

.                                     1D21N210                                Cnds F1tr Pmp Area TBC                                       (568'6")                                          9.0E+0                   !

! 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area HB (600'6") 1.0E+1 ! ! 1D21N240 Fdw Pump Area, KB (647'6") 6.6E+0 f

1D21N400 CR, CC (654'6") 1.6E-1 I C/ 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 l D21N260 RWB East (574'10")' -1.5E+1

} D21N270 RWB (602') 5.0E+0 ' D21N280 D21N290 Process Sample Re, RWB RW Evap, RWB (623'6") 4.0E+0 i (623'6") 4.0E+0 ' D21N310 FPCU F/D Area IB (599') 6.0E+0 i D21N320 Fuel Preparation Pool, IB (620'6") 2.0E+3 '/ 1 D21N330 Spent Fuel Storage Pool. IB (620'6") 5.8E+2 [: D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 - 1D21N340 Unit 1 DW, Portable, Cntet (655') [ 4 D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB jk (623'6") 6.0E+0 - 1D21N090 Refueling Bridge, Cntet (689'6") 3.0E+0 D21N390 Fuel Serv Mdla Platfo* IB (620'6") 2.0E43 ([

;~

4 p-l 4 i l-

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                                                            ,:    -......A.*       i ?.        - .                                   -                                                            - ~ ~ ~ .

Time: 1000 y

      ,                                                                                                        Message No.: M i

PERRY NUCLEAR POWER PLANT s 1984 EMERGENCY PREPAREDNESS EXERCISE '. (* MESSAGE FORM E l-

                                                                                                                                                                                                              "n i-              Message For: Controllers                                                                                                                                                                         u r.
              . Simulated Plant Conditions:

Messame: ***THIS IS A DRILL ***' - t., p 7 f..

;l:

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                                                                              /         3 *: / '                                                                                                                [

t. FOR CONTROLLER USE ONLY h

k. -

                                                                    /                                                                                                                                           t; Controller Notes:       1. The ambulance'should be leaving the site by now.                                                                                                                     !J l?

2. Controllers and Evaluators at Lake County Memoriti ; ,

East should be in place at this time. l l Actions Expected: The PAC Security should notify SAS. E: e.

                                                                                                                                                                                                                  #     L.

O O DW176/C/33/ba b

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Time: 1000 Message No.: 384 C-t.' PERRY NUCLEAR POWER PLANT s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Control Room /TSC Simulated Plant Conditions: See attached sheets Message: ***THIS IS A DRILL *** . G - FOR CONTROLLER USE ONLY , Controller Notes: 1 l l Actions Expected: The operators should prepara to commence a fast reactor l shutdown. '

                                                                        /       '7 1

! (: 3 ; a) /j; ;dcCWNi{ ' l l i l DW176/C/34/ba e6

l. O. h ,. r f 'T ' l;' r . _ PERRY IIUCLEAR POWER PLA81T 1984 EMERCE90CY PREPAREDetESS EXERCISE TIME: 1000 .f-- CONTROL ROOM AIIftUf0CIATORS l' P601/P877 P680 P870 ar BACK PANELS r SectIon 7A , SAFETY / RELIEF f VALVE LEAKAGE &. ALARM P614 '

*[-

i

3. t 2-2 f

9

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                                                                                                                                                 *~'
   . PERRY IIUCLEAR POWER PLANT                      1984 EMERGENCY PREPAREDIIESS EXERCISE                               TIME: 1000 1.

P601 M i CONTAIIstENT PARAMETERS SYSTEM INFORMAT1001 REACTOR PARAMETERS Temperature - Pressure . Pressure Flow Pressu ro 1018 psig f*F1 loslal Status fosial (GDBl Level 31 ins NR Cntat 81 O RWCU PMP A OP 1350 Neutron , Drywell 120 0.1 B 0F 1350 Mon 100 Range 6f399 !' HWL PMP A OP 230 Mode SW' RUN Tempe ra ture Level f*F1 (Ft.1 B OP 230 FDW F1w 15.4 Mib/hr Supe P1 88 18.2 C SS O ST Flw (Total) 15.4 Mib/hr CDP A OP 275 Line A 3.5 SYSTEMS INFORMATl001 8 OP 280 Line B 3.5 Pressure Flow l Status fosial local C SR 150 Line C 3.5 RHR A SR RFBP A OP 330 .Line D 4.5 B SR B OP 330 C SR C OP 330 LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 [, HPCS SR S OP 1063 14.9 ECC A 00S MFP SR 0 0 IURpl ML-GENERATOR B SR RCIRC A FAST 39254 PARAMETERS l ESW A 005 B FAST 39254 Mwatt 1162

B SR MVAR 403 MAJOR VALVE PARAMETERS ,

C SR CNDR Vac 28 in. Hg ' Status Closed open CRD A SR Thrt Pr 948 psig B OP 1900 44 BYP VLV SRV al0RM 19 0 Posit 0 % SLC A SR B SR . SLC STG TK LVL 4600 gal. 4 5

                                                                                                                                                                  .k y

6 9 ; PERRY lluCLEAR POWEO PLAllT 1984 EMERCEllCY PREPAREDNESS EXERCISE TIME: 1000 '{ - i ~. i MIQ ELECTRICAL DISTRIBUTION m CST Level 410.000 est. Status Load IMWI 0.' Statu1. ;

Status fasiel 0Frsite Pwr Sources 2 AV Cent Rm HVAC Supp Fan A OP + TBCC PMP A OP 75 con Breakers 2 CL 8 SR B OP 75 Div 1 DC 00S Cont Rm HVAC Rtn Fan A ~OP C SS 18 Div 2 DC SR 8 SR SA Comp OP 128 Div 3 DC SR Cont Re Eng RCIRC Fan A e SR , iA. Comp SR 120 B SR , 2000 CillW PMP A OP 46 Status 8 OP 45 E919 Cntet Vsl Cig Fan A 0F * ' Pressure Status fosial C OP 46 8 OP llCC Pump A- OP 112 SJAE A OP C SS' 8 SS B OP 112 i D OP t C SS 35 E OP ADDITIONAL INFORMATI0ll ~ SW Pump A OP 56 F SS - b Status Abbreviations: B OP 56 Drywe1I Cooling fan 1A OP OP Operating C SS

 ,'                                                                                                                                                O 2A        OP SS        Secured Status                                                                            D       SS            O 3A        OP AV        Available                                                                      MTR Fire Pump      SR IB       SS SR        Standby Readiness                                                              DD Fire Pump       SR                        ?

28 S$ _ L-38 SS S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed , 1, 8 SS ISOL 1solated Cntet Val & DW Purge Exh Fan -A SS IBORM NorasI - .' B SS 00S Drywell Purge . Out of Service - Suppl Fan A SS 3 CL Closed 8 SS OVRD Override AECTS Fan A 00S 8 OP 9

                                                                                             .-                ow

               .                                                                                                                                    i (f+                                                        'f I.

PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1000 i.:

                                                                                                                                                    ? ..

I RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP I' 31 IN 1018 PSIO .100 . 1 88 *E [ 60- 1100- 120- 110 45- 950- 90- 90-30- 800- 40- 70-15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 0 f

                -30   -20    -10     0              -30         -20   -10     0                 Time (min)                     Time (min)

Time (min) Time (min) DW TEMP CONTMT TEMP CONTMT PR5SS SUPR PL LEVEL i . 120 *E 81 *E - O fi1G 18.2 EI 200- 110- 20- 19-150- 90- 15- - i l 100- 70- 10- 18- - 50 50- 5- -

               -30   -20    -10      0              -30         -20          0         0-                           17

_-10 Time (min) Time (min) -5 -30 -20 -10 0

                                                                                          -30   -20   -10     0 '             Time (min)               d' e

Time (min)

y p -% 'C] .

 ,. PERRY NUCLEAR POWER PLANT                                      1984 EMERCEIICY PREPAREDNESS EXERCISE                             TIME: 1000 PANEL P604                                                              PANELS P669. P670. P671. P672                  I I~

Process Radiation Main Steam Line RAD 6.8E+2 mR/hr i Alarm ! Cntet Vent Exh RAD s1.OE-1 mR/hr ; Orrgas Pre-treatment 2.5E+2 R/hr > Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 / j 8 2.OE+2 cpm Common Airborne Gas icoal Alarm Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1 , 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Aree ggLa Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Sidg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Ridweste to ESW 3.0E+1 j Airborne Radiation Cas fcomi Atern Radweste to Sewage 3.6E+1

Annulus Exh A Ces D D![fg + 8 JR 11 Cntet Ata Lg y METEOROLOCICAL CONDITIONS Drywell - HR (R/hr) L911. A8 Vent L9E1. Wind Speed . IA d _ aph + Oc8 Vent Exh LQQi; Wind Direction 225

Oc8 Vent - HR gipQg Tempe ra ture -

38 'F OG Vent Pipe L gtig Delta T -0.80 'F, , U1 Plant vent 6JEE 7 U1 Plant Vent - HR (J D L+9 T8/H8 Vent gall T8/HB Vent - HR 19 ~ ST Packing Exh 9 11 ' U2 Plant Vent 11 , U2 Plant Vent - HR 0.0E+0 ' DW170C/A/15/ba <

                                                                                                                                                        ?
                                                                                                                                                         \'

b

                           ~         .-_.- - .           ..                   .       - _

. . . . - . .i - L. , ~ . . - - - - - - =:-- - -- e -- < - ~~ 1 i i b AREA RADIATION MONITORS Time: 1000 I l 4 TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntet (620'6") 5.0E+0 1D21N050 RBRT Area, Cntet (642') 1.0E+2

1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 i 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 l 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 t 1D21N110 Aux Blda East (574'10") 7.0E+0
1D21N120 Aux Blda West (574'10") 7.0E+0 l 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0: l. 1D21N170 Turb Blda (605'6") 2.5E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1

! 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 ' . 1D21N200 OGB (584') 1.1E+1 l 1D21N210 Cnds F1tr Pop Area TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (64'7'6") 6.6E+0 . ? - 1D21N400 CR, CC (654'6") 1.6E-1

          .                  1D21N410                          OG Hold Up Area. TB                                                         (577'6")                                  1.0E+1
;                              D21N250                          RWB West                                                                   (574'10")                                2.5E+1                                            5

!' . D21N260 RWB East (574'10")- 1.5E+1

D21N270 RWB (602') 5.0E+0 i D21N280 Process Sample Ra, RWB (623'6") 4.0E+0 I D21N290 RW Evap, RWB (623'6") 4.0E+0 '

D21N310 F?CU F/D Area. IB (599') 6.0E+0 l D21N320 Fuel Preparation Pool, IB (620'6") 2.0E+3

D21N330 Spent Fuel Storane Pool, IB (620'6") 5.8E+2 l D21N420 FPCU Cire Pop Area. IB (574'10") 9.0E+0

! 1D21N340 Unit 1 DW, Portable Cntet (655') - 5 D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 , D21N370 SRW Drummina Area RWB (623'6") 6.0E+0 f ID21N090 Refuelina Bridae, Cntet (689'6") 3.0E+0 l D21N390 Fuel Serv Hdla Platform, IB (620'6") 2.0E+3 1 6 e I i

               ------w,~-          --mr*       -

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                                                                      -en, - - ---,e-     ,e.w,----,    , , , , , , . , ,       's,--e.--~~--we m   -   y ,.m,,,----,,wp       g e -wem.+,r-w,,-e--wen,~,                -,y-c.-r-

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1 I Time: 1001 Message No.: M e,

   ,k,~                                                PERRY NUCLEAR POWER PLANT                                                   a.

r s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM ;-

                                                                                                                                . ll Messaae For: Control Room /TSC                                                                                        r' r
                                                                                                                                - "h ,

Simulated Plant Conditions: See attached sheets ~ Messame: ***THIS IS A DRILL *** f' f t p t'

                                                                                                                                   ,P   ..

l' i. 4 I

       ".                                                                                                                           I'

(%. k,' 7 5 FOR CONTROLLER USE ONLY Controller Notes: l i ;. Actions Expected: 3 l t 5 ! I i.

. I t c p i l

t. 5 6 6 DW176/C/35/ba 5 i

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      ,. PERRY NUCLEAR POWER PUulT                                 1984 EMERCENCY PREPAREDetESS EXERCISE :                           TIME:'1001 CONTROL ROOM A80000NCI AT0fts                                                            f P601/P877                                                                   P680'              P870 at BACK PANELS           *
                                                                                                                                                                     ?

Section 20A Section 7A ; SUPP POOL SAFETY / RELIEF e LEVEL A HIGH VALVE LEAKAGE i ALARM P614 ;. Section 17A t-SUPP POOL LEVEL B HIGH j~ 4 a Y e i 4 3 k

                                                                                         .                                                                           j.

r I

1 DW1708/A/44/ba' P

                                                                                                                                                                   '4 9

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[ PERRY NUCLEAR POWE2 PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1001 6-

    ,.                                                                                                                                                                  t-P601                                              P680 i ~

CONTAINMENT FARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS , 3. Tempe ra ture Pressure Pressure Flow Pressure 1018 psig , f*F1 3 3iel Status fosion local i Level 31 In, NR ! Cntet 81 0 RWCU PMP A OP 1350 j Neutron 5 Drywell 120 0.1 8 OP 1350 Mon 100 Range APRM j HWL PHP A OP 230 Mode SW RUN $ Tempe ra ture Level ' f*F1 ; f ft. ) B OP 230 FDW Flw 15.4 Mlb/hr 1'

       .         Supr PB            91                   18.3                             C          SS          0           ST Flw (Total)         15.4 Mlb/hr!         !

C8P A OP 275 Line A 3.5 ' '

  ,                               SYSTEMS INFORMATION

B OP 280 Line B 3.5 Pressure Flow

                           . Status           fosle)           foom)                      C          SR      150                     Line C          3.5

1 RHR A SR RFBP A OP 330 Line D 4.5 !-

B SR 8 OP 330 C SR 'C OP 330

f-LPCS SR D SR 160 I RCIC SR RFP A OP 1065 15.1 p HPCS SR 8 OP 1063 14.9 '

I ECC A 00S MFP SR 0 0 < B TURB1ME-GEM [RATOR p SR RCIRC A FAST 39254 PARAMETERS ' ESW A 00S B FAST 39254 Mwatt 1162 i' 8 SR MVAR 403 ? MAJOR VALVE PARAMETERS C SR . CNDR Vac 28 in. Hg CRD A SR Thrt Pr 948 psig MSly NORM 0 8 8 OP 1900 44 BYP VLV SRV NORM 19 0 Posit O % t SLC A SR ' i B SR + SLC STC TK LVL 4600 gal. ' e E ( p d e,f _ -0 * *R"' 1 N*% ,N W # '"* ,Y A M' ' 4 9 9

ih--

0; .

).

PERRY NUCLEAR POWER PLAllT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1001

     ,.                                                                                                                                                                                      l.

P870 ELECTRICAL DISTRIBUTION P904 : CST Level 410.000 est. Status Load IMWI Status Status fosial Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 con Breakers 2 CL B SR 8 OP 75 Div 1 DC ___00S Cont Rm HVAC Rtn Fan A OP C SS 18 Div 2 DC . SR B SR , SA Comp OP 128 Div 3 DC SR Cont Re Eng RCIRC Fan A SR 1A Comp SR 120 B SR P600 .

, CIRW PMP A OP 46 Status *

'. P970 ' B OP 45 Cntet Vsl C1g Fan A OP Pressure ,

                                                    ._                                                                                                       Status _   fosial             .

C OP 46 5 OP c NCC Pump A OP 112 SJAE A OP C SS 8 OP 112 :- 8 SS D OP C SS 35 h' E OP e

     .               ADDITIONAL INFORMATION                                                                                                 SW Pump    A       OP          56 F          SS Status Abbreviations:                                                                                                                    8       OP ~        56 Drywe l l Cool ing Fan 1 A         OP                                                          +

OP Ope ra t ing C SS O 2A OP i SS Secured Status D SS O { 3A OP ; AV Available MTR Fire Pump SR : 18 SS t SR Standby Readiness DD Fire Pump SR 28 SS .,, SHTDN Shutdown i 38 SS I S-SP Slow Speed Cntet Vsl Pu rge ; Supp Fan A SS F-SP Fast Speed , 8 SS i ISOL isolated Cntet Vs1 at DW Purge Exh ran A SS NORM Noraa1 8 SS f, OOS Out of" Service Drywe l i Purge Suppl Fan A SS

Ct. Closed ;

8 SS OVRD Ove rride i AECTS Fan A OOS B OP I <

l. .

I. r l' , l . t s.. 5- -,,., 7 7 .-,- ,e.--- - q 7--n 7 .---- seq- n.,yqr4 :1 v - , , - +mif.y

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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1001 RX WATER LEVEL RX PRESS RX' POWER SUPR PL TEMP h i 31 1! 1018 23_LC 100 f 91 *f i 60- 1100- 120- 110

l; 950- 90-45- 90- ; i

30- . 800- 40- 70- f.

.                                               15-                                                                   650-                                          0                                       50 1

0 500 -30 -20 -10 0 -30 -20 -10 0 f.' r

                                                      -30          -20             -10         -0                             -30     -20     -10        0                   Time (min)

Time (min) i-t= ti Time (min) Time (min) B-

                                                 .                                                                                                                             .                                                                         C.

g: DW TEMP C0!!TMT TEMP CONiMT PRESS SUPR PL LEVEL }. ( i' 120 'f 81 'f, O PSIG l8.3 fl [ 200- 110- 20- 19- I i 90-is0- is- - [ 100- 70- 10- 18- ' l 50 50- 5- - t; t

                                                      -30          -20             -10              0                         -30     -20    -10         0          0-                                     17                                          'I i

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PERRY leUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDOIESS EXERCISE , TIME: 1001 *- PAleEL P604 EAleELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 6.8E+2 inR/hr Alarm Cntet Vent Exh RAD ' 41.0E-1 mR/hr . Orrgas Pre-treatment 2.5E+2 R/hr Offgas Post-treatment A 2.0E+2 cpm EglEL P902 , B 2.0E+2 cpm common Airborne Gas (coal Ala re Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 ! B 3.0E+1 cpm FH8 Vent Exh 2.2E+1 L OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0C+1 8 5.5E+1 mR/hr i .' fe81EL P906 g PANEL 803 Common Process and Area ges! Ala rm II i Turb Bldg East 2.5E+0 mR/hr UO-MH-73 East Liq 3.0E+1 1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 I t NCC Heat HX 3.5E+1 I. PA81EL P804 I Radwaste to ESW 3.0E+1 ' S Alrborne Radiation O Gas (coal Alarm Radweste to Sewage 3.6E+1 !: Annulus Exh A Gas (!J W! B ;Jilj. i-Cntat Ata ;JM METEOROLOGICAL CONDITIONS [' Drywell - HR (R/hr) ;J!1, y A8 Vent M 1. Wind Speed 18.0 mph 3 ( OCS Vent Exh EJW Wind Direction 225 * ' OC8 Vent - HR QJ[tQ Tempe ra tu re __ 18 'F OG Vent Pipe RJMZ Delta T -0.80 'F [ t U1 Plant Vent (tdy i U1 Plant Vent - HR QJ 1(! T8/H6 Vent (tA1]. TB/H6 vent - HR QJ!M! i ST Packing Exh MJ:+ ' U2 Plant Vent (tJ 1, t U2 Plant Vent - HR QJ 3! _

+-

DW170C/A/16/ba 9 4

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,.:.. . .. . ..- ..s . :- . s.:. .. . ,: nn,'- . - i AREA RADIATION MONITORS Time: 1001 s TAG # LOCATION READING (MR/hr)

ID21NO30 Personnel Air Lock Cntet (600'6") 5.0E+0 7 1D21N040 CRD HCU West. Catet (620'6") 5.0E+0 ;

1D21N050 RBRT Area Cntet (642') 1.0E+2 , ID21N060 Tip Drive Area. Cntet (600'6") 3.0E+1 1D21N070 RWCU F/D Area. Cntet (664'7") '7.0E+0 1D21N080 Upper Pool Area. Cntet (689'6") 2.0E+0 1D21N110 Aux Blds East (574'10") 7.0E+0 . 1D21N120 Aux Bldz West (574'10") 7.0E+0 g ID21N130 Turb Rm East (647'6") 2.5E+0 F 1D21N140 CRD HCU East. Cntet (620'6") 5.0E+0 ;. ID21N160 Turb Rm West (647'6") 2.5E+0 i 1D21N170 Turb Blda (605'6") 2.5E+0 i 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 II 1D21N190 TB Sump Area. TBC (548'6") 2.0E+1 ? 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds Fitr Pop Area. TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area. OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0 (# ; ID21N400 .CR. CC (654'6") 1.6E-1 ,, 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 .. D21N250 RWB West (574'10") 2.5E+1 !' D21N260 RWB East (574'10") '1.5E+1 y D21N270 RWB (602') 5.0E+0 i

             ._ D21N280          Process Sample Rs. RWB            (623'6")              4.0E+0                     [

D21N290 RW Evap. RWB (623'6") 4.0E+0 i D21N310 FPCU F/D Area. IB (599') 6.0E+0 '. D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3 ' D21N330 Spent Fuel Storane Pool. IB (620'6") 5.8E+2 D21N420 FPCU Cire Pep Area. IB (574'10") 9.0E+0 , 1D21N340 Unit 1 DW. Portable. Cntet (655') - r D21N380 Waste Compactor Area. RWB (623'6") 6.0E+1 [ D21N370 SRW Drummina Area. RWB (623'6") 6.0E+0 , r 1D21N090 Refuelina Bridae. Cntet (689'6") 3.0E+0 . . f D21N390 Fuel Serv Ndla Platform. IB (620'6") 2.0E+3 f i s l 4

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                                                                                                                                                                                         ---                                       +-                                  -

Time: 1002 . Message No.: M i

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PERRY NUCLEAR POWEF. PLAfft s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE Ft '.@l - Messane For: Control Room /TSC ( Simulated Plant Conditions: See attached sheets i s Messame: ***THIS IS A DRILL *** - - " v t-6 i k I O ~I W~ el I! i fi 0, FOR CONTROLLER USE ONLY t , Controller Notes: A scram should be initiated by placing the mode switch in D; F

                                                                                    " SHUTDOWN." However, there will be no inward motion of the control rods. In accordance with PEI-1, the operators should                                                                                                                           (

attempt to shut down the reactor using alternate rod insertion. f*-

All alternata shutdown methods fail. A manual scram is ini- ' tiated, but fails, b.i e y

                                               'h .                                                                                                                                                                                                                         V Act' ions Expected:                    As stated above.                                                                                                                                                                        ,..

l l e DW176/C/36/ba ! ' ( ,*- . 4

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 .,      PERRY NUCLEAR POWER PLANT                        1984 EMERGENCY PREPAREDNESS EXERCISE                                            TIME: 1002 C081 TROL ROOM AlpIUIICt ATORS P601/P877                                                            P680                              P870 & BACK PANELS       ,      4 i 1

SectI03.23A Section 5A SUPP POOL MANUAL SCRAM e LEVEL A HICH , SWITCH ARMED , Section 17A RPS LOGIC , MANUAL SCRAM SUPP POOL N LEVEL B HIGH Section 7A SAFETY / RELIEF Lj VALVE LEAKAGE 1s ALARM P614 4

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($ , PERRY MUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1002 CONTAIMMENT PARAMETERS SYSTEM INFORMA{1_05 REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 1018 psig f*Fl (DsIG) . Status (DslGI IQDS)

Level 31 i n .e _. NR '

Cntet 81 0 RWCU PMP A OP 1350 Neutron Drywell 120 0.1 8 OP 1350 Mon 100 Range M HWL PMP A OP 230 Mode SW Shutdown Tempe ra ture Level f*FI (Ft.1 8 OP 230 FDW Flw 15.4 Mlb/hr Supr PI 93 18.4 C SS O ST FIw (Total) 15.4 Mlb/hr C8P A OP 275 Line A 3.5 SYSTEMS INFORMATION Pres su re 8 OP 280 Line li 3.5 Flow Status _ fosle) feDel C SR 150 Line C 3.5 MHR A SR RFBP A OP 330 Line D 4.5 , 8 SR 8 OP 330 C SR C OP 330 ' LPCS SR D SR 160 RCIC SR RFP A OP 1065 15.1 'j HPCS SR 8 OP 1063 14.9 f ECC A OOS 'MFP SR 0 0 JyEglNL-CENERATOR 8 SR RCiRC A FAST 39254 PARAMETERS s, ESW A OOS 8 FAST 39254 Mwatt 1162 h 4 8 SR MVAR 403 f MAJOR VALVE PARAMETERS . C SR CNDR Vac 28 in. Hg Status Closed. Open CRD A SR Thrt Pr 948 psig 8 OP 1900 44 BYP VLV SRV NORM 19 0 Posit 0 % SLC A SR t., 8 SR f SLC STC TK LVL 4600 gal. '

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y. f. I;)4 G l g , .. PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1002 [ P870 ELECTRICAL DISTRIBUTION P904 CST Level 410.000 aal. Status Load fMW1 _ status Status fosial 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMr A OP 75 Con Breshers 2 CL B SR + s L B OP 75 Div 1 DC OOS Cont'Rm HVAC Rtn Fan F OP C SS 18 Div 2 DC SR B SR SA Comp OP 128 Div 3 DC SR Cont Re Eng RCIRC Fan A SR lA Comp SR 120 B SR IIQQ CIRW PMP A OP 46 Status P970 B OP 45 Cntet Val Cig Fan A OP Pressu re Status _1pslal NCC Pump A OP 112 SJAE A OP C SS B OP 112 8 SS D OP C SS 35 E OP ADDITIONAL INFORMATION SW Pump A OP .56 ? F SS Status Abbreviations: . B OP 56 OP Ope ra t ing C SS O 2A OP i SS Secured Status D SS 0 3A OP - AV Available MTR Fire Pump SR ! 1B SS ' SR Standby Readiness DD Fire Pump SR i 2B SS ' SHTDN Shutdown 38 SS S-SP Slow Speed Cntet Val Purge ., Supp Fan A SS t F-SP Fast Speed g B SS

ISOL isolated Cntet Vsl ar DW l Purge Esh Fan A SS NORM No rea I '

B SS 00S Out of Service Drywell Purge - Suppi Fan A SS CL Closed B SS ' OVRD Ove rride i AECTS Fan A 00S t B OP l I e

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   ,. PERRY NUCLEAR POWER PLANT                      1984 EMERCENCY PREPAREDNESS EXERCISE                                             TIME: 1002 PANEL P604                                                       fAMELS P669. P670. P671. P672 Process Radiation                                                             Main Steam Line itAD              6.8E+2 mR/hr Alarm Cntet Vent Exh RAD              41.0E-1 mR/hr Offgas Pre-treatment          2.5E+2 R/hr i          Offgas Post-treatment A       2.0E+2 cpm                                                         PANEL P902                            e B      2.OE+2 cpm                                  Common A1rborne                         Cas fcomi      AIare Eng Service Water      A      3.0E+1 cpm                                        RWB Vent Exh                      2.0E+1 a

B 3.0E+1 cpm FHB Vent Exh 2.2E+1 OC Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 B 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area Ega AIarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX 3.5E+1 ' PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Ces (coal Alarm Radweste to Sewage 3.6E+1

Annulus Exh A Ces ND L+g B

lJ M , Cntet Ata J .12 METEOROLOGICAL CONDITIONS DryweII - HR (R/hr) ;J ;+.. AB Vent M _E+_, Wind Speed 18.0. sph OCB Vent Exh L.pl+g Wind Direction J g5

0C8 Vent - HR g g +g Tempe ra ture 38 'F OC Vent Pipe g g +g Delta T -0.80 'r U1 Plant Vent 6&di U1 Plant Vent - HR g,y 2Q TB/HB Vent (t&ll TB/HB Vent - HR - DL+Q ST Packing Exh .1.

U2 Plant Vent al, U2 Plant Vent - HR D g +1! DW170C/A/17/ba . 1 4. i

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1 4 {, AREA RADIATION MONITORS Time: 1002 TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntat (620'6") 5.0E+0

                   , 1D21N050          RBRT Area, Cntet                    (642')                         1.0E+2 1D21N060          Tip Drive Area, Cntet               (600'6")                       3.0E+1 1D21N070          RWCU F/D Area, Cntet                (664'7")                       7.0E+0 1D21N080          Upper Pool Area, Cntet              (689'6")                       2.0E+0 1D21N110          Aux Bldg East                       (574'10")                      7.0E+0 1D21N120         Aux Blds West                        (574'10")                      7.0E+0 ID21N130         Turb Rm East                         (647'6")                      2.5E+0 1D21N140         CRD HCU East, Cntet                  (620'6")                      5.0E+0 1D21N160         Turb Rm West                         (647'6")                      2.5E+0 1D21N170         Turb Bldg                            (605'6")                      2.5E+0 1D21N180         Hotwell Pump Area TB                 (577'6")                       1.0E+1
!                    1D21N190         TB Sump Area, TBC                    (548'6")                      2.0E+1 ID21N200         OGB                                  (584')                         1.1E+1 1D21N210          Cnds F1tr Pmp Area, TBC             (568'6")                       9.0E+0 1

1D21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 (~; ID21N410 OG Hold Up Area. TB (577'6") 1.0E+1 D21N250 RWB West (574'10") 2.5E+1 ' ' i D21N260 RWB East (574'10") 1.5E+1 2 D21N270 RWB (602') 5.0E+0 i D21N280 Process Sample Ra, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area. IB (599') 6.0E+0 D21N320 Fuel Preparation Pool. IB (620'6") 2.0E+3 i D21N330 Spent Fuel Storage Pool IB (620'6") 5.8E+2 D21N420 FPCU'Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable Cntat (655') - i D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntet (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") 2.0E+3 I 9 9 s n.--W---ar,... -

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_ _ . . . _ ,_. . _. . - _ . . _ = . - . _ .. .._-.m . .- _. _ _ . . . Time: 1005 Message No.: M l, PERRY NUCLEAR POWER PLANT s 1984-EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Control Room /TSC Simulated Plant Conditions: See attached sheets Message: ***THIS IS A DRILL *** - kh FOR CONTROLLER USE ONLY Controller Notes: Suppression Pool temperature is increasing. Actions Expected: j DW176/C/37/ba h 4 4

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10 W k O E W e e e e e e e e e e e E W M M M M M M M M M M M " W W E W w E , A , 2 3 e m e e t .e e c e , M M M M M M M M M - ..- e e 60 a0 e e e e e O . . M M M 'M M M M M M e M M M M M M M C h e M M M C C-e N 6 e N 't-N, e U m . c - ~ m . n -w ~ e m g X,m m m N N e O O

1 6 .- .e __ i PERRY NUCLEAR POWER PLANT '1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1005 fitG1 2009 CONTAltl MENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 953 psig t'Fl fosial Status f osIGI _f403) Level 34 Ip. NR Cntet 82 0 RWCU PMP A SS Neutron DryweIi 120 0.1 B SS Mon 57 Range APRM HWL PMP A OP 230 Mode SW Shutdown Tempe ra ture Level t'F1 fft.) B OP 230 FDW Flw 8.8 Mlb/hr Supr PI 97 18.5 C SS 0 ST Flw (Total) 8.8 Mlb/hr. CBP A SS 150 Line A 2 SYSTEMS INFORMATION B SS 150 Line B 2 Pressure Flow Status _ fosial faomi C SS 150 Line C 2 RHR A SR RFBP A OP 330 Line D 2.9 8 SR 8 OP 330 C SR C SS 160 *

LPCS SR D SS 160 RCIC SR RFP A OP 1000 8.8 HPCS SR B SS O O -

ECC A 00S MFP SR 0 0 4 IMBgjM[-CEMERATOR B SR RCIRC A SS O PARAME it'RS ; ESW A OOS B SS 0 Mwatt 713 B SR MVAR 472 MAJOR VALVE PARAMETERS C SR CHOR Vac 28 in. Hg Status Closed Open CRD .A SR Thrt Pr 937 psig MStV NORM 0 8 8 OP 1900 44 BYP VLV SRV _. NORM 19 0 Posit O % , B SR SLC STC TK LVL 4600 gal. l t 4

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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME:~1005 P870 ELECTRICAL DISTRIBUTION P904

CST Level 410.000 aats ' Status Load IMW) Status Status fosial 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL 8 SR 8 OP 75 Div 1 DC OOS Cont Rm HVAC Rtn Fan. A 'OP C SS 18 Div 2 DG SR 8 SR SA Comp OP 128 Div 3 DC SR Cont Rm Eng RCIRC Fan A SR IA Comp SR 120 B SR P800 CIRW PMP A OP 46' Status P970 8 OP 45 Cntet Vsl Cig Fan A OP Pressure Status fosial C OP 46 8 OP NCC Pump A OP 112 SJAE A OP C SS B OP 112 B SS D OP C SS 35 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywe 1 I Coo 1 Ing Fan 1 A OP OP Opera t ing C SS O ,

2A OP SS Secured Status D SS 0 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fi re Pump SR 28 SS - SHTDM Shutdown ; 38 SS S-SP Slow Speed Cntet Val Pu rge l Supp Fan A SS F-SP Fast Speed 8 SS ' ISOL isolated Cntet Vs1 & DW Purge Exh Fan A SS NORM No rea l B SS ' -< 00S Out of' Service Drywell Ptfrge f Suppl Fan A SS CL Closed , 8 SS OVRD Override AECIS Fan A 00S B OP , m . ,- , .

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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1005

PANEL P604 PANELS P669. P670. P671. P672 i Process Radiation Main Steam Line RAD 6.8E+2 mR/hr Alarm . i Cntet Vent Exh RAD ,1.0E-1 mR/hr ' Offgas Pre-treatment 2,1L,+2 R/hr , Offges Po.t-treatment A 2.0E+2 cpm PANEL P902 , 8 2.0E+2 cpm Common Alrborne Gas (coal Ala re Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3s0E+1 cpa FHB Vent Exh 2.2E+1

        '0G Ca rbon Bed Vault      A        6.0E+1 mR/hr                                          CR Vent Exh                  2.0E+1 8        5.5E+1 mR/hr PANEL P906 PANEL 803                                              Common Process and Area                gna!          Alarm              .

Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 NCC Heat HX- 3.5E+1 PANEL P804 Radwaste to ESW 3.0E+1 Airborne Radiation Gas icoal Maraj Radwaste to Sewage 3.6E+1 Annulus Exh A Gas Q,020 B 3.19 11 Cntet Atm 1,5 d2 METEOROLOGICAL CONDITIONS D rywe l l - HR (R/hr) 1,9 1. AB Vent 2J 1, Wind Speed 18.0 _ sph OCB Vent Exh 2 OL+2 Wind Direction ,_225

OGB Vent - HR Q,DLtQ lempe ra ture J8 'F OG Vent Plpe R J Lt2 Delta T -0.80 'F U1 Plant Vent (t,D E_+ 1 i Ut Plant Vent - HR QJfdQ TB/ IIB Vent 6,DLt1 TB/HB Vent - HR Q,QE_t!!

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AREA RADIATION MONITORS Time: 1005 [ s TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air I.ock, Cntet (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntat (642') 1.0E+2 - ID21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 - 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 . j ID21N110 Aux Blda East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 < 1D21N140 CRD HCU East, Cntat (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Blda (605'6") 2.5E+0 [ 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 ; ID21N190 TB Su:np Area, TBC (548'6") 2.0E+1 i. 1D21N200 OGB (584') 1.IE+1 ID21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area. HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 p 1D21N400 CR, CC (654'6") 1.6E-1 W 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 D21N250- RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10"). 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 r D21N310 FPCU F/D Area, IB (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") 1.9E+3 D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2 D21N420 FPCU Circ Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntet (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 .; D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 , i 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform. IB (620'6") , 1.6E+3 ^

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_ .. - . . . .. . - - .a--. .= -. . - .- f r Time: 1010 Message No.: 3 I (! PERRY NUCLEAR POWER PLANT , s 1984 EMERGENCY PREPAREDNESS EXERCISE ' MESSAGE FORM , Message For: Control Room /TSC 'f Simulated Plant Conditions: See attached sheets Messaae: ***THIS IS A DRILL *** - 9 i. 1 r- *

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w i-FOR CONTROLLER USE ONLY e Controller Notes: i Actions Expected: l l ! t DW176/C/38/ba' s

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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1010-CONTROL ROOM ANNUNCIATORS P601/P877 P680 P870 at BACK PANELS Section 20A , Section IA SUPP POOL RWCU PUMP TRIP , LEVEL A HICH SUCTION FLOW LOW SUPP POOL TEMP A HIGH Section SA section 17A MANUAL SCRAM SWITCH ARMED SUPP POOL t LEVEL 8 HICH RPS LOGIC MANUAL SCRAM 4 SUPP POOL TEMP 8 HICH RRCS MAN INITIATION Section 19A

                                                                                                                                     .Section 7A ADS 8 PERMISSIVE                                                                                           SAFETY / RELIEF RHR 8/C RUN                                                                                         VALVE LEAKAGE ALARM P614 L

l DW1708/A/53/ba t i

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 . PERRY NUCLEAR POWER PLANT                              1984 EMERGENCY PREPAREDNESS EXERCISE                                          TIME: 1010                   ,

P601 fnB CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 953 psig , f*FI losial Status._ fosial focal Level 34 int NR Cntet 82 0 RWCU PMP A SS Neutron Drywe I i 120 0.1 B SS Mon 57- Range efBfg ' HWL PMP A OP 230 Mode SW Shutdown Tempe ra ture Level f*F1 fit.) B OP 230 FDW Flw 8.8 Mlb/hr Supr P1 104 18.7 C SS O ST Flw (Total) 8.8 MIb/hr e CBP A SS 150 Line A 2 - SYSTEMS INFORMATION B SS 150 Line B 2 Pressure Flow _ Status fosial feoel C SS 150 Line C 2 RHR A SR RFBP A OP 3] L Line D 2.9 8 SP CLC 250 7000 B OP 330 C SR C SS 160 LPCS SR D SS 160 , RCIC SR RFP A OP 1000 8.8 HPCS SR S SS O O ECC A 00S MFP SR 0 0 luggig-CMERATOR B OP 114 RCIRC A SS O PARAMETERS ESW A 00S S SS 0 Mwatt 713

   .      E        OP             95                                                                                          MVAR             472 MAJOR VALVE PARAMETERS C        SR                                                                                                         CNDR Vac          28      in. Hg
                                                                                  ._. Sta tus     Closed         Open CRD A         SR                                                _                                                        Thrt Pr          937      psig MSIV                   NORM            0               8 8        OP           1900            44                                                                            BYP VLV SLC A         SR SRV                    NORM           19               0        Posit-            0     %

8 SR SLC STG IK LVL 4600 gal.

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                                                                                                                                                         , j-PERRY NUCLEAR POWER PLANT                     1984 FMERGENCY PREPAREDliESS EXERCISE                                              TIME: 1010                ,

P870 ELECTRICAL DISTRIBUTION P904 , CST Level 410.000 est. Status Load fMWI Status Status fostel Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP ' TBCC PMP A OP 75 Con Breakers 2 CL B SR

, B OP 75 Div 1 DC 00S Cont Rm HVAC Rtn Fan A OP . C SS 18 Div 2 DC SR B SR SA Comp OP 128 Div 3 DC SR Cont Re Eng RCIRC Fan A SR

8A Comp SR 120 B SR P800 CIRW PMP A OP 46 Status P970 8 OP 45 Cntet Vsl Cig Fan A- OP Pressure Status Ios101 C OP 46 8 OP NCC Pump A OP 112 SJAE A OP C SS 8 OP 112 8 SS D OP ,

E OP ADDITIONAL INFORMATIOll SW Pump A OP 56 F SS Status Abbreviations: B OP 56 DryweiI Coo 1Ing Fan IA OP OP Ope ra t ing C SS O 2A OP SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS , SR Standby Readiness DO Fire Pump SR 25 SS SHTDN Shutdown ' ! 38 SS ! S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS , F-SP Fast Speed

 .                                                                     8            SS ISOL        isolated                 Cntet Val at DW Purge Egh Fan          'A            SS 00S         Out of" Service          Drywell Purge Suppl Fan               A            SS CL          Closed 8            SS                                                                      i OVRD        Override AEGTS Fan                 A           00S                                                                      !

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                -30  -20    -10    0               -30   -20    -10      0                             Time (min)                               Time (min)

Time (min) Time (min) DW TEMP , CONTMT TEMP CONTMT PRESS SUPR PL LEVEL - 120 82

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Time (min) Time (min) -5 -30 -20 -10 0

                                                                                                -30   -20       -10     0                       Time (min) i Time (min)
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    , PERRY NUCLEAR POWER PLANT-                   1984 EMERGENCY PREPAREDNESS EXERCISE                                  .-             TIME: 1010 PANEL P604                                               PANELS P669. P670. P671. P672                                   '

Process Radiation Main Steam Line RAD 6J Qg mR/hr Cntat Vent Exh RAD al.0E-1 mR/hr Orrgas Pre-treatment 2.5E+2 R/hr Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 - 8 2.0E+2 cpm - Common Airborne cas (coal Ala re Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1 8 3.0E+1 cpm FH8 Vent Exh 2.2E+1 , OG Carbon Sed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 . PANEL 803

Common Process and Area Epe Alarm i Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 ,

NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (coal Alora Radweste to Sewage 3.6E+1 Annulus Exh A Gas flJQ(! 8 ;J 1. Cntet Ata ;Jy METEOROLOGICAL CONDITIONS DryweII - HR (R/hr) ;JE. A8 Vent M29E . Wind Speed 18.0.._ sph OG8 Vent Exh RJU2 Wind Direction J g) OG8 Vent - HR QJ d Tempe ra ture 38 'F i OG Vent Pipe U1 Plant Vent p y g29Q1 Delta T -0.80 'F U1 Plant Vent - HR g,9QQ

18/HB Vent gd 11 TB/H6 Vent - HR $!

ST Packing Exh J :1. . U2 Plant Vent 1 U2 Plant Vent - HR R d .+1! DW170C/A/19/ba - i I

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  .                                        AREA RADIATION MONITORS            Time:    1010 s

TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 1D21N040 ID21N050 CRD HCU West, Cntet RBRT Area, Cntet (620'6") (642') 5.0E+0 1.0E+2 [ ID21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 ! 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 . 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Blda West (574'10") 7.0E+0 ; 1D21N130 Turb Rm East (647'6") 2.5E+0 t ID21N140 CRD HCU East, Cntet (620'6") 5.0E+0 [ 1D21N160 Turb Rm West (647'6") 2.5E+0 i 1D21N170 1D21N180 Turb Blda Hotwell Puer Area. TB (605'6") (577'6") 2.5E+0 1.0E+1 [ [- ID21N190 TB Sump Aree. TBC (548'6") 2.0E+1 L' ID21N200 OGB (584') 1.1E+1 1D21N210 Cnds Fitr Prp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area HB (600'6") 1.0E+1 [ ID21N240 Fdw Pump Area HB (647'6") 6.6E+0 . 1D21N400 CR, CC (654'6") 1.6E-1 hg 1D21N410 OG Hold Up Area, TB (577'6") 1.0E+1 ; D21N250. RWB West (574'10") 2.5E+1 I D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB - (623'6") 4.0E+0 p~ D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area. IB (599') 6.0E+0 i! D21N320 Fuel Preparation Pool. IB (620'6") 1.6E+3 f D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2 4 D21N420 FPCU Cire Pmp Area. IB (574'10") 9.0E+0 , 1D21N340 Unit 1 DW, Portable, Cntmt (655') - . D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 b D21N370 SRW Drummina Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridae, Cntet (689'6") 3.0E+0 D21N390 Fuel Serv Hdla Platform, IB (620'6") 8.0E+2 , 9 p k

- e

Time: 1015 Message No.: M PERRY NUCLEAR POWER PLANT s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Control Room I Simulated Plant Conditions: See attached sheets Message: ***THIS IS A DRILL *** - 4 6 I c '9 FOR CONTROLLER USE ONLY Controller Notes: The Suppression Pool temperature reaches 110*F. Standby Liquid Control is activated. The common check valve cc C41-F007 does not open. SLC does not inject. . Actions Expected: The operators should implement PEI-1, Attachment 5, and lower reactor level. Level will reach approximately

                                -145 ihdhes in 30 minutes N

DW176/C/39/ba ,p s

i' (f 't ? : PERRY NUCLEAR POWEO PLANT 1984 EMERGEllCY_ PREPAREDNESS EXERCISE ' TIME: 1015 CONTROL ROOM AllNullCI ATORS P601/P877. P680 P870 at BACK PANELS Section 20A Section 1A CONT RM HVAC

    '                                                                                                                                      EMERG RCIRC A SUPP POOL                                                          RWCU PUMP TRIP LEVEL A HICH                                                                                                                    INITIATED ,-      P904 SUCTION FLOW LOW                                           CONT RM HVAC SUPP POOL                                                                                                                 EMERG RCIRC 8 TEMP A HIGH                                                             Section 5A                                          INITIATED         P904            t Section 17A                                                           MANUAL-SCRAM SWITCH ARMED SUPP POOL LEVEL 8 HIGH                                                                 RPS LOGIC MANUAL SCRAM SUPP POOL

TEMP 8 HIGH RRCS-MAN INITIATION ,

Section 19A Section 7A ADS 8 PERMISSIVE SAFETY / RELIEF RHR 8/C RUM ' VALVE LEAKAGE . ALARM P614 , Section 22A Section 8A

CRD PUMP AUTO 1 RIP COMMON HVAC PANEL ALARM -

P904 t DW1708/A/56/ba . i

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fs {l% . PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1015 l EnD1 EbGQ Co* ital 81 MENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressure Pressure Flow Pressure 953 psig f*F1 fosial Status _fosial fopel Level 34 in. NR. Cntet 84 0.1 RWCU PHP A SS Neut ron DryweIi 120 1 8 SS Mon 57 Range Mgt4 _ HWL PMP A OP _ZJ Q_ Mode SW Shutdown Tempe ra ture Level I'F1 fft.1 B OP 230 FDW Flw 8.8 Mlb/hr Supr Pt 109 ,_1R R_ C SS 0 ST FIw (Total) 8.8 Mib/hr CCP A SS 150 Line A 2 SYSTEMS INFORMATION B SS 150 Line 8 2 Pressure Flow Status f osial fepel C SS 150 Line C 2 RHR A PMP OVRD RFBP A OP 330 Line D 2.9 . 8 VLV DVRD 275 B OP 330 C VLV OVRO 275 C SS 160 LPCS PMP OVRD D SS 160 RCic SR RFP A OP 1000 8.8 HPCS SR 8 SS 0 0 ECC A DOS MFP SR 0 0 IMBQiNg-cLMERATOR B OP. 114 RCIRC A SS O PARAMETERS ESW A 00S B SS 0 Mwatt 713 8 OP 95 MVAR 472 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Status Closed _ Open CRD A SS Thrt Pr 937 psig B SS BYP VLV SRV NORM 19 0- Posit 0 %

SLC A OP 1600 8 OP 1600 SLC STC TK LVL 4600 gal.

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                                                                                                                                                                              /~-} '    y PERRY HUCLEAR POWEA PLAllT                                      1984 EMERCEllCY PREPAREDNESS EXERCISE
                                                                                                                                                            ' TIME: 1015

( -P870 ELECTRICAL DISTRIBUTION P904 CST Level 410.000 eat. Status Load fMW1 Status i Status fosle) 0FFsite Pwr Sources 2 AV Cont Rm HVAC.Supp Fan A OP , TBCC PMF A OP ~75 Gen Breakers 2 CL 8 OP ! 8 OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS

C SS 18 Div 2 DC OP O 8 SS SA Camp OP 128 Div 3 DG SR Cont Re Eng RCIRC Fan A OP IA Comp SR 120 8 OP P800 l ClitW PMP A OP 46 Status B OP 45 Cntet Vsl Cig Fan A OP Pressure '

Status fosial . C OP 46 8 OP 'I . NCC Pump A SS 112 SJAE A OP C SS S SS 112 8 SS D OP : C SS 35 E OP

ADDIT 1000AL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: 8 OP 56 DryweiI Coo 1Ing Fan 1A OP OP Ope ra ting C. SS O i 2A OP

SS . Secured Status D SS
O !

i 3A 0F ;

!            AV                 Available                                                                                          MTR Fire Pump         SR                             i i

18 SS-CR Standby Readiness DO Fire Pump SR 28 SS Shutdown SHTDel

38 SS I S-SP Slow Speed Cntet Val Purge '

Supp Fan I A SS F-SP Fast Speed l' SS i ISOL isolated Cntet Val at DW Purge Exh Fan 'A SS Norea1 NORM 8 SS , OOS Out oF Service Drywell Purge ' Suppl Fan A SS j CL Closed

 !                                                                                          8                 SS                                                                        '

OVRO Override i AEGTS Fan A _ OOS 8 OP 4 4

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w m C W e *=

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PERRY PUCLEAR POWER PLANT 1988s"EMERCENCY PREPAREDNESS EXERCISE TIME: 1015,

w. -

PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 6.8E+2 mR/hri

                                                                                ,4,.

Alarm Cntet Vent Exh RAD <-1.0E-1 ma/hr Orrgas Pre-treatment 2.5E+1 R/hr~ __ Orrges Post-treatment A 2.0E+2 cpm PANEL P99.2 e t 6 2.0E42 cpm Common Airborne Gas fcoal Alare E:ng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 t a B 3.0E+1 cpm FH8 Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 skNEL803 Common Process and Ares gp_al Ala rm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 1 Turb aldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 + .~,J4 ~ ~ ' 's ; NCC Heat HX _ 3.5E+1

                                                                                                                                                                                                 ~                             '

PANEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Gas (coal Alarm Radwaste to Sewage 3.6E+1 Annulus Exh A Cas i ^ QJU.0 - B LQE+1 ti , Cntet Ata ;J Ef2 METEOROLOGICAL CONDITIONS - % - Drywell - HR (R/hr) ; JEig AB Vent i;JE+1 Winid Speed -' 18.0 . sph I-OCB Vent'Exh EJE12

Wind Di rectlon - J 10 * -

                                                                                                                                                                            *r OCB Vent - HR                            DJEfg                                                              Tee,)e ra ture                        38 OG Vent Pipe                             LpitZ                                                              Delta T                               -0.85     *F U1 Plant Vent                            (tJ E +1
                                                                        -                                                                                                                                            s U1 Plant Vent - HR                       gJ[ig, TB/HB Vent                               (J[t_{ '

TB/HB Vent - HR ;1k ST Packing Exh Jtg ' U2 Plant vent a ll U2 Plant Vent - HR L.9M DW170C/A/20/ba - 9 4

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                                           ~

( AREA RADIATION MONITORS Time: 1015 TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntat (600'6") 5.0E+0 ' 1D21N040 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N050 RBRT Area, Cntet (642') 1.0E+2 ' 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Blda West (574'10") 7.0E+0 , ID21N130 Turb Rm East (647'6") 2.5E+0 . 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 [.

        -1D21N160      Turb Rm West                        (647'6")               2.5E+0          i' ID21N170      Turb Bldg                           (605'6")               2.5E+0         r) 1D21N180      Hotwell Pump Area, TB               (577'6")               1.0E+1         f ID21N190      TB Sump Area, TBC                   (548'6")               2.0E+1         p 1D21N200      OGB                                 (584')                 1.1E+1         !J 1D21N210      Cnds Fitr Pmp Area TBC              (568'6")               9.0E+0          (

ID21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 *

         ..D21N230 HP Fdw Her Area, HB                 (600'6")               1.0E+1 1D21N240      Fdw Pump Area. HB                   (647'6")               6.6E+0         ,I j 1D21N400      CR, CC                              (654'6")                1.6E-1         ll b.2       1D21N410      OG Hold Up Area, TB                 (577'6")                1.0E+1        jl D21N250     RWB West                            (574'10")              2.5E+1          [

D21N260 RWB East (574'10") 1.5E+1 [; D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 [ D21N290 RW Evap, RWB (623'6") 4.0E+0 ;, D21N310 FPCU F/D Area, IB (599') 6.0E+0 : D21N320 Fuel Preparation Pool IB (620'6") .1.4E+3 ; D21N330 Spent Fuel Storage Pool, IB (620'6") 5.8E+2 , D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 ? 1D21N340 Unit 1 DW, Portable, Cntmt (655') -- I' (623'6") 6.0E+1 ' D21N380 Waste Compactor Area, RWB D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 : D21N390 Fuel Serv Hdig Platform. IB (620'6") 4.2E+2 t b N e.

                                                                                         ~
  . . - - -    - ! .   . . . .       -                        - .:.... ,. -. -- ..~ . -.     - . . . .

Time: 1020 Message No.: 40 s. (n.

    .. 1.

PERRY NUCLEAR POWER PLANT

                                 .,                1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messane For: Control Room /TSC                                                                   jf I

Simulated Plant Conditions: See attached sheets . Messame: ***THIS IS A DRILL *** if b

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FOR CONTROLLER USE ONLY. . jn r--' f Controller Notes: : e. l '. l Actions Expected: Emergency classification discussions should be underway. !;i e g' i l' . I r; s E i t t. I i f i I DW176/C/40/ba

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   , PERRY NUCLEAR POWER PLANT                         19% kMERCENCY PREPAREDNESS EXERCISE                               e.           TIME: 1020           f CONTROL ROOM ANNUNCIATORS P601/P877                                                                         P680                 .P870 k BACK PANELS SectIon 20A                                                                    Section 1A
                                                                                       --~~

COMT RM HVAC 3 EMERC RCIRC A SUPP POOL IMITIATED e P904 LEVEL A HICH fUPUMPTRIPl SUCTION FLOW l_ LOW g CONT RM HVAC SUPP POOL EMERC RCIRC B TEMP A HICH Section SA IMITIATED P904 Section 17A MANUAL SCRAM SWITCH ARMED

SUPP POOL LEVEL B HICH RPS LOGIC

! MANUAL SCRAM SUPP POOL ,- 6 TEMP B HICH RRCS MAN INITIATION Section 19A RPS LOW LEVEL ADS B L-3 PERMISSIVE < RHR B/C RUN Section 8A ADS A COMMON HVAC *

PERMISSIVE PANEL ALARM

RPV L-3 P904 ADS B PERMISSIVE l RPV L-3 l Section 22A CRD PUMP l lAUTOTRIPl 1 l :

I l 1 DW1708/A/59/ba

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PERRY 810 CLEAR POWER PLANT 1984 EMERCENCY. PftEPAREDNESS EXERCISE TIME: 1020 2691 ' P680 i CONTAINMENT PARAMETERS SYSTEM INFORMATION BEACTOR PARAMETERS Tempe ra ture Pressure Pressu re Flow Pressure 948 psig (*F) loslo) _ .- Sta tus fosial faomi 87 Lovei 10 l er. NR

Cntet 0.2 RWCU PMP A SS i

Neutron. DryweIi 120 1 8 SS Mon 40 Range APfM - HWL PMP A OP 230 Mode SW Tempera ture Level Shutd2dl

t*FI fFt.1 B OP 230 i

FDW Flw 6.2 Mlb/hr Supr PB 115 19.1 C SS

i. 0 ST Flw (Total) 6.2 Mlb/hr CSP A SS 150 Line A 1.3 '

? SYSTEMS INFORMATION . 8 SS 150 Line B 1.3 Pressure Flow Status fosle) faomi C SS 150 .Line C 1.3 RHR A PMP OVRD RFBP A OP 330 Line D 2.2 B VLV OVRD 275 B OP 330 C- VLV OVRD 275 C SS 160 LPCS ' PMP OVRD SR D SS 160 RCIC SR RFP A OP 1000 8.8 HPCS SR B' SS 0 0 ECC A 00S MFP SR 0 0 TURBig[-C[MERATOR B OP 114 RCIRC A SS 0 PARAMLIERS ESW A 00S S SS 0 Mwatt 500 i B OP 95 MVAR 100 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg

he_g_. Closed Open CRD A SS Thrt Pr 932 psig.

MSly NORM 0 8 i

5 SS SYP VLV SRV 910RM 19 0 Posit 0 %

SLC A OP 1600 3 B OP 1600 SLC STG TK LVL 4600 gal. w

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PERRY. NUCLEAR POWER PLANT ~ 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1020 I fglg ELECTRICAL DISTRIBUTION M CST Level 410.000 cal. Status Load IMW) Status Status fosial 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP

          -TBCC PMP A                              OP              75          Con Breakers                 2 CL                                                          B.       OP B     OP             75           Div 1 DC                     00S                         Cont Rm HVAC Rtn Fan' A                    SS '

C SS 18 Div 2 DG OP 0 8 SS SA Comp OP 128 Div 3 DC SR Cont Re Eng RCIRC Fan A OP I A Comp SR 120 B OP P600 CIRW PMP A OP 46 Status B OP 45 Cntet Vsl Cig Fan A OP Pre ssu re Status fosial p SJAE A OP C SS B SS 35 B SS D OP C OP 112 E OP ADDITIONAL INFORMATION SW Pump A OP 56 i F SS Status Abbreviations: B OP 56 Drywe1 I Cooling Fan I A OP OP Ope ra t ing C SS O SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 2B SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Val Purge Supp Fan A SS F-SP Fast Speed . ISOL isolated Cntet Vsl B DW Purge Exh Fan A SS NORM Normal - B SS 00S Out of Service Drywe l l Pu rge Suppl Fan A SS CL Closed B SS OVRD Override AECTS Fan A 00S B OP

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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE TIME: 1020 RX WATER LEVEL . RX PRESS RX POWER SUPR PL TEMP 10 11] 948 ESJ.9 40 7 115 'f 60- 1100- 120- 110 x 45- 950- ^ 90- 90- . N 30- s 800- 40- h 70-i 15- 650- 0 50

0 500 -30 -20 -10 0 -30 -20 -10 0

                -30  -20    -10     0                 -30   -20    -10       0                         Time (min)                                 Time (min)

Time (min) Time (min) > DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL 120 'f 87 'f 0.2 PSIC 19.1 fl

200- 110- 20- 19- ,.

r 1 150- 90- 15-f - 100- 70- 10- 18- ! i

- 50 50- 5- -

                -30  -20    -10     0                 -30   -20    -10       0               0 --                                     17 1

l Time (min) Time (min) -5 -30 -20 -10 0

                                                                                                -30    -20    -10      0                          Time (min)

Time (min) i 9 4 5 1--. .<. ;.. -~~:->:- g -v : , : ,~-w

                                                                                                        . -, nw. ..m n - - < , . ;s n ~ n ; p 3 ,s,z .
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                                                                                 - &. .r.                                                           0.;

g. PERRY 800 CLEAR POWER PLANT 1984 EMERGENCY PREPAREDetESS EXERCISE . TIME: 1020 ( ,

t. . .

P PAllEL P604 PANELS P669. P670. P671. P672 ; Process Radiation Hein Steam Line RAD 6.8E+1 mR/hr Ale rs . 11.0E-1 mR/hr Cntet Vent Exh RAD offges Pre-treatment 2.5E+1 R/hr ,

                                                                                                                                                                      .j offgas Post-treatment A            2.0E+2 cpm                                                        PANEL P902                             -

S' 2.0E+2 cpm Common Airborne ~ Cas fcoal Alarm-Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PA81EL P906 PAllEL 803 Common Process and Area seg Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 . 10CC Hoat HX 3.5E+1 !' 1-PANEL P604 Radwaste to ESW 3.0E+1 i Airborne Radiation Ces tcoal Alarm Radweste to sewage 3.6E+1 Annulus Exh A Ces Q,9 E_.+.Q 8 LDE+1 Cntet Ata LDQg METEOROLOGICAL Coll 0ITIONS Drywell - HR (R/hr) .L.QQg . A8 Vent LgE.+1 Wind Speed ' SL ph. OC8 Vent Exh Lgeg Wind Direction ._ 1,0 0C8 Vent - HR DipMq Tempe ra ture .l8 'r DC Vent Pipe L9Q2 Delta T -0.85 *F U1 Plant Vent MM U1 Plant Vent - HR IW) TB/HB Vent Id . TB/HB Vent - HR ~ 029QQ __ ST Packing Exh - JJid! U2 Plant Vent -n9 M . U2 Plant Vent - HR QJ. W! _ 5-DW170C/A/21/ba 7 : . , , :. r r . , . :, _ - - y _ , n . , . , :m

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r y ., v - vv . ~ J.

                                                                                                                                       .        .       t

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( AREA RADIATION MONITORS Time: 1020 s TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntat (620'6") 5.0E+0 I 1D21N050 RBRT Area, Cntet (642') 1.0E+2 h 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 )' 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 ,. 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 -[ 1D21N110 Aux Bldg East (574'10") 7.0E+0 ( 1D21N120 Aux Bldg West (574'10") 7.0E+0 - 1D21N130 Turb Rm East (647'6") 2.5E+0 , 1D21N140 CRD HCU East, Cntat (620'6") 5.0E+0 s ID21N160 Turb Rm West (647'6") 2.5E+0 T c 1D21N170 Turb Bldg (605'6") 2.5E+0 ' 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 / ID21N190 TB Sump Area, TBC (548'6") 2.0E+1 F

         '1D21N200      OGB                            (584')         1.1E+1        f 1D21N210     Cnds Fitr Pmp Area, TBC        (568'6")      9.0E+0         5 1D21N220     OG After Fitr Area, OGB        (602'6")      2.0E+1 1D21N230     HP Fdw Htr Area, HB            (600'6")       1.0E+1 1D21N240     Fdw Pump Area, HB              (647'6")      6.6E+0 e      1D21N400     CR, CC                         (654'6")       1.6E-1        '

( 1D21N410 OG Hold Up Area TB (577'6") 1.0E+1 - D21N250 RWB West (574'10") 2.5E+1 {E D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB (623'6") 4.0E+0 (599') 6.0E+0 D21N310 FPCU F/D Area, IB D21N320 Fuel Preparation Pool, IB (620'6") 1.2E+3 D21N330 Spent Fuel Storage Pool IB (620'6") 5.8E+2 D21N420 FPCU Cire Pmp Area IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 l D21N390 Fuel Serv Hdig Platform, IB (620'6") 3.6E+2

   'l N.

L

       ,.   , . _ .,                  .R . 3,J.-a               ,                                                   .                                                                          r-     - - --          -

j Time: 1025 Message No.: -4/ [ PEaRY NUCLEAR POWER PLAlfr 1984 EMERGENCY PREPAREDNESS EXERCISE

                                                  .s
              .                                                                                                                                                                      MESSAGE FORM Messane For: Control Room /TSC p

Simulated Plant Conditions: See attached sheets F 1: Messame: ***THIS IS A DRILL *** *~ y p. P i-E

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                                                                                                                                                                                                                               . D r.

y-y V (~._. (. r t,. 4 FCR CONTROLLER USE ONLY . r_ s

Controller Notes: ;.

                                                                                                                                                                                                                                   .br Actions Expected:

, i .

                                                                                                                                                                                                                                     ,L 9

4 4 I k DW176/C/41/bi I 4 9 9

                                ,          . , ,       y   . . _ . . . _ .                                                                               .                      . . ,             _ ,        ,f? _!

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I $ 6 s 5 a 4 0 0 S m' L E N P 9 9 P A P A 8 C AC,.CAC K 5 C VR VR 2 A HID HID , 0 B CE CE 1

MRT MRT

4 R A R A

GI GI E

0 TRT TRT M 7 NEI NEI I 8 OMN OMN T P CEI CEI r 5 r n s a s o 0 e 8 s 6 a F E S I L . MD C M E R A AE CA N V E S 5 RM IR NO E - X R CR GC AI L , E O n SA OS MT 3 A W-

T o L S A i LH L SI OL S I t AC SA CT L .. E C c 01 PU RI N G I e 0l 8 R8 1 RN S -. e-D U S AW A I P -

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R I S A A P . E M . R O

P O R

Y C L - N O E R G i . R l e E o -- M C E o 8 s 8 9 1 7 e. 7 7 8 P -.

                         /                                                                                                         -                n 1

0 6 T P , N A - L P. R E W O A H H A H H A l l P 0 LG LG 7 LG LG 9 EU E E , 2 OI OI 1 OI OI 1 VR V3 V3 s R OH OH OH OH aI AI - SI - e A n P P n P P n SC SL SL / E e P A P A oi P 8 S o SS/ SS SS 2 L l P i DIB DIV DIV 6 C t PL PP t PL PP t AM AMP AMP / U e c UE UM c UE UM c RR RR RR A I e $V ESE eT SV SE e EH E E / S S E T S PR P P 8 Y L L 0 R 7 R 1 E - W P D iil LllIlI >ll.[l1' i[lICl ll lI

                                                                                       ,-                                                                 -- m PERRY NUCLEAR POWEO PLANT                              1984 EMERCENCY PREPAREDNESS EXERCISC
    .-                                                                                                                                 TIME: 1025 NdL1                                           P680                                                                           '

CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempera ture Pressure Pressure Flow Pressure 932 psig ('F1 Iosial _ Status fosial_ Jgpal Cntet 90 0.1 RWCU PMP A Level -20 in. _ WR SS i. Drywell 120 .1 8 Neutron

SS Mon 30 Range APRM {

HWL PMP A OP 230 Mode SW SHTON Tempera ture LoveI f*FI fft.) 8 OP 230 . FDW Flw 4.6 Mib/hr ,.- Supr PB 120 19.2 C SS 0 ST Flw (Total) 4.6 Mlb/hr ' CSP .A SS 150 Line A 0.9 SYSTEMS INFORMATION 4 8 SS 150 Line 8 0.9 ' Pressure Flow _ Status fosial faomi C SS 150 Line C 0.9 RtIR A PHP OVRD RF8P A OP 330 Line D 1.8 8 VLV OVRD 275 8 OP 33 L

C YLV OVRD 275 C SS 160 LPCS PMP OVRD SR D s SS 160 RCIC SR i RFP A OP 1000 8.8 '

HPCS SR 8 SS O O ECC A 00S MFP SR 0 0 '

3 OP 114 RCIRC A SS J_UBB_JME-C[N[ RAT 06 0 PARAMETERS ESW A 005 8 SS O Watt 375 C OP 95 MAJOR VALVE PARAMEfERS CNDR Vac 28 in. Hg CRD A SS _ Status Closed Open MSIV Thrt Pr 929 psig 8 NORM 0 8 SS SRV BYP VLV SLC A NORM 19 0 PosIL 0 OP 1600 % 8 OP 1600 ' SLC STC TK LVL 4600 gal,

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r' ., PERRY NUCLEAR POWER PLANT 1984 EMERCEIICY PREPAREDNESS EXERCISE TIME: 1025 P870 ELECTRICAL DISTRIBUTION P904 CST Level 410.000 est. Status Load IMbfl Status Status fosiel 0FFsite Pwr Sources 2 AV Cont Rm HV5C Supp Fan A OP TBCC PMP A OP 75 Con Brealsers 2 CL B 0F B OP 75 Div 1 DC 00S Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DC OP O B SS SA Comp OP 128 Div 3 DC OP G Cont Re Eng RCIRC Fan A OP , IA Camp SR 120 B OP k-P800 CIRW PMP A OP 46 _. Status P970 f 8 OP 45 Cntet.Vsl Cig Fan A OP Pressure Status fosiel C OP 46 8 OP IICC Pump A SS 35 SJAE A OP C SS !, 8 SS 35 8 SS D OP C OP 112 t E OP ADolTIONAL INFORMAT1001 SW Pump A OP 56 '

                                                                            -F              SS Status Abbreviations:                                                                                                     8             OP             56 Drywe l l Cool ing Fan 1 A                 OP OP         Ope ra t ing                                                                                            C              SS               O          ,

2A OP SS Secured Status - - D SS O 3A OP AV Available MTR Fire Pump SR ;, 18 SS SR Standby Readiness DO Fi re Pump SR 28 SS SHTDM Shutdown - ' 38 SS , S-SP Slow Speed Cntet Val Purge Supp Fan A SS F-SP Fast Speed . B SS ISOL Isolated Cntet Vsl k DW Purge Exh Fan A SS NORM 800rea I 8 SS OOS Out of Service Drywell Purge Suppl Fan A SS CL Closed ' 8 SS OVRD Ove rride AECTS Fan A 00S B OP f 9 s .+ p y g-== y, y 3 -

4 * =p-** *'y *" 7*',*y'"w."' ' ** * ' '; 4 8 # {d #f - *#

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,. . PElutY IIUCLEAR POWER PLAllT 1984 EMERGENCY PREPAftEDelESS EXERCISE TIME:^1025 !. PAIIEL P604 . PA80ELS P669. P670. P671. P672 ,. Process Radletlen femin Stese Line RAD 7.0E+1 mR/hr

A t a rio Catet Vent Exh RAD 41.0E-1 mR/hr Ofrgas' Pre-treeteent 2.5E+1 R/hr Offgas Post-treetsent A 2.0E+2 cpe PAllEL P902 ..e B 2.0E+2 cpe Common AIritorne Ces fcom1 A1a rio Eag Service 1 deter A 3.0E+1 cpe RW8 Vent Exh 2,0E+1 3 3.0E+1 cpe FHS Vent Exh 2.2E+1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR vent Exh 2.0E+1 3 5.5E+1 mR/hr PAftEL P906 PAIIEL 803 Common Process and Area Ests AIers ,

Turb Bldg East 2.5E+0 mR/hr UD-FEM-73 East Lig 3.0E+1 ks Turb Bldg idest 2.5E+0 mR/hr UD-99H-70 West Lig 3.2E+1 l NCC Heat HM 3.5E+1

PAIIEL P904 Radweste to ESW 3.0E+1 Airborne Radiation Gas (csel Alers Radweste to Sewage 3.6E+1 , Annulus Exh A Ces s (LJEig [ hJtti ; Cntet Ata iJL+2 METE 0st0 LOGICAL C0800lT1000S Drywell - HR (R/hr) ;J Lig 1 A8 VenL jJLil Wind Speed '8.O aph ! OCS Vent Exh jJ[+2 0

Wind Direction _1 ,

OCs Vent - MR lLJLig Tempera ture 18 'r t OG vent Pipe IJ[t2 Delta T -0.85 'F ' U1 Plant Vent ! id ;tl U1 Plant Vent - IIR !M;+g 18/HS Vent llJ .11 . 18/HS Vent - 00R Q,9[tg. , ST Packing Exh Lig ,. U2 Plant Vent til U2 Plant Vent - MR 0.0E+0 , k DW170C/A/22/es . t '

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        .                                                                     AREA RADIATION MONITORS               Time:      1025 TAG #                      LOCATION                         READING (MR/hr)

ID21NO30 Perstgiel Air Lock, Cntat (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntet (620'6") 5.0E+0 1D21N050 RBRT Area, Cntet (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0

                                           '. 1D21N110      Aux Blda East                       (574'10")         7.0E+0 1D21N120      Aux Blda West                       (574'10")         7.0E+0           ?

ID21N130 Turb Rm East (647'6") 2.5E+0 , ID21N140 CRD HCU East, Cntet (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Blda (605'6") 2.5E+0 . 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 > 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area. TBC (568'6") 9.0E+0 1D21N220 OG After Fitr Area. OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area. HB (647'6") 6.6E+0

             ,                                   1D21N400      CR, CC                              (654'6")          1.6E-1

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   %                                             1D21N410      OG Hold Up Area. TB                 (577'6")          1.0E+1 D21N250     RWB West                            (574'10")         2.5E+1 D21N260     RWB East                            (574'10")         1.5E+1 D21N270     RWB                                 (602')            5.0E+0 D21N280     Process Sample Rm, RWB              (623'6")          4.0E+0 D21N290     RW Evap. RWB                        (623'6")          4.0E+0 D21N310     FPCU F/D Area, IB                   (599')            6.0E+0 D21N320     Fuel Preparation Pool, IB           (620'6")          9.5E+2 D21N330     Seent Fuel Storage Pool IB          (620'6")          5.6E+2 D21N420     F.'CU Cire Pmp Area. IB             (574'10")         9.0E+0           -

1D21N340 U.it 1 DW, Portable. Cntet (655') ---- D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 , ID21N090 Refuelina Bridge, Cntet (689'6") 3.0E+0 I D21N390 Fuel Serv Hdig Platform, IB * (620' 6") # 1.7E+2 N [ o/ [

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s- . :.. : . ,- . ..t:: .a . ~ i ~ . x . ~ .. . -; ., -. . . Time: 1030 Message No.: M (g- ' PERRY NUCLEAR POWER PLANT s , 1984 EMERGENCY PREPAREDNESS EXERCISE s MESSAGE FORM ] Messaae For: Control Room /TSC [ Simulated Plant Conditions: See attached' sheets - Messame: ***THIS IS A DRILL *** .,

                                                                                                                       ,. i 2

I e 1 l

                                                                                                                          ~l t

FOR CONTROLLER USE ONLY I. , Controller Notes: . Actions Expected: The Emersency Coordinator should declare a SITE AREA EMERGENCY (EPI-A1, Section D.III.2, " Complete loss of any functions needed for plant hot shutdown").

1. Implement EPI-A4, SITE AREA EMERGENCY. ,

l 2. Make notifications, c

3. Activate the EOF and JPIC.

t ..

4. Assess the situation.

5. Activate Radiation Monitoring Teams in accordance with EPI-B3. f .

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                          .                 PEltRY IOUCLEAR POWER PLAllT                  1984 EDIEIICEIICY PREPAREDIIESS EXERCISE                                       TIME: 1030 s

COIlTROL It00M AIIIIUIICIATORS .. P601/P877 P680 PS70 at SACK PAIIELS

                                                                                                                                                                                                            ' i. l SectIon 20A                                                            Section 5A                                      COIIT ItM HVAC                       ','

EMERC RCIItc A - SUPP POOL MARIAL SCRAM INITIATED e P901 LEVEL A HIGH StilTCH AftMED COIIT IIM HVAC SUPP POOL - RPS LOGIC EISERG RCIRC 8 TEMP A HICH MAIIGAL SCRAM INITIATED P904 Section 17A RftCS MAII IMITIATION SUPP POOL LEVEL 8 HICH RPS LOW LEVEL 'I L-3 SUPP POOL TEMP S HICH RRCS RX LEVEL .l Section 19A LO L-2 ADS 8 PERMISSIVE RHR B/C RUll . ADS A

PERMISSIVE !

RPV L-3 , ADS 8 PERMISSIVE ' i 'l RPV L-3 . I'

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   ..                                                                                                                                                               TIME: 1030                   -l' 290.1                                                           M00
                                                                                                                                                                                                 .I CONTAllBIElsT PAflAMETERS                                            SYSTEM INFOIWMil0N REACTOR PAIWIETERS Temperature           Pressure                                                                     Pressure     Flow f*F1                fasiel           .

Pressure 930 _ psig i Status :fasiel femel Level -50 in( WR Catet 92 8.3 ftWCU PMP A SS 0 . t 122 Iseutron

      , DryueIi 0.1                                            B'            SS               O                       Mon                   23       Range 6fgl left. PM P        A             0F            230                      IItoele SW       SMTOII
                   *Temporeture              Lovei
           .             t*F1                I f t. I                                          B             OP            230                       FDW Flw'           3.5          Mlb/hr Supr Pt           125                  19.4                                            C             SS              0               ST Flw (Total)             3.5          Mlb/hr CSP               A             SS            150                              Line A     0.7' SYSTDIS IIIFOIWETBON
                                                                                            -B               SS            150 ~ ~                          Line B'    O.7 Pressure _              Flow Status        fasial              femel                                  C             SS            150                              Line C     0.7 RIOR A      PHP OWIIO                                                RFBP             A              OP            330                              Line D      1.6 S        SP CLC          250               -1u00                                 3              0F            330 C      YLY OVRO          275                     0                               C              SS            160 LPCS        PMP OVRO                                                                  D              SS            160 RCic        FLW OVRO          500                     0             RFP            .A               OP            1000          a.8 NPCS       VLV OWRD           900                     0                               5             SS               0             0

ECC A 005 NFP SR 0 0 S OP 114 flClitC A SS 0 TUR8I E- L9tRATOR P TERS E

g ESW A 005 :- 3 SS O hatt 288 ,l ' B OP 95 MWAR 20 MMOR VALVE PARAMETERS C OP 95 CIIOR Vec 28 In. Hg ' Status Closed Omen ,> CRO A SS Thrt Pr 927 psig B SS SYP VLV e SRV NOIDI 19 0 Posit 0 % SLC A OP 1600 t B 0F 1600 ' SLC STG TE LVL 4600 gol. e

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T PEstRY lluCLEAR POWER PLAllT 1984 EMERCENCY PREPAREDetESS EXERCISE TIME: 1030 k. M ELECTRICAL DISTRIBUTIO88 P904 i CST Level 410.000 eat. Status Load fleil Status Status fasial Orrsite Pwr Sources 2 AV Cont its HVAC Supp Fan A OP l

TBCC PMP A OP 75 Con Breakers 2 CL B OP 5 OP 75 Div 1 DC 00S Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DC OP O 3 SS . SA Camp OP 128 Div 3 DC OP O Cont Re Eng RCIRC Fan A OP ' IA Camp SR 120 8 OP Ps00 CIRW PMP A OP 46 Status B OP 45 Cntet Vsl Cig Fan A OP Pressure Status losial C OP 46 8 OP UAE A OP C SS B SS 35 B SS O OF C OP 112 E OP ADDITIoseAL IserosinaTIcel Sw Pump A OP 56' Status Abbreviations: 8 OP 56 Drywell Cooling Fan 1A OP OP Operating 2A 0F C SS O '.' SS Secured Status D SS O ' 3A OP v AV Available MTR Fire Pump SR g , SR Standby Readiness DD Fire Pump SR ' 28 SS

SH1 Del Shutdown 38 SS ;'

S-SP Slow Speed Cntet Vs1 Purge , Supp Fan A SS ' F-SP Fast Speed

B SS ISOL isolated Cntet Vs1 & DW Purge Exh Fan A SS I 800RM Normal -

8 SS 00S Out of Service Drywell Purge k9pI Fan g A SS CL Closed B SS 0%D Override 4 AECTS Fan A OOS , 8 OP 4

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I' C' ' Dy st Q ' PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDIIESS EXERCISE -

                                                                                                                      ,             TIME: 1030 PAIIEL P60dl                                                     PANELS P669. P670. P671. P672                            h
                                                                                                                                                      ~

Process Radiation Main Steam Line RAD 7.0E+1 mR/hr Alaru _ Cntet Vent EFh RAD c1.0E-1 mR/hr offgas Pre-treatment 2.5E+1 R/hr Offgas Post-treatoent A 2.OE+2 cpm PANEL P902 e B 2.0E+2 cpm Common Airborne Ces Icomi A1ere Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 S 3.0E+1 cpm FHS Vent Exh L2Q1 OG Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1

8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gne '

Alarm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 leCC Heat HX 3.5E+1 PAIIEL P804 Radweste to ESW 3.0E+1 Airborne Radiation Ga s (com) Alara Radweste to Sewage 3.6E+1 Annulus Exh A Ces QJE+9 8 }JM1 Cntat Ata PJf+2 METEOROLOGICAL CON 0lTIONS Drywell - HR (R/hr) M E19 AB Vent Lgul Wind Speed 17.5 mph OC8 Vent Exh LDL_2 + Wind Direction _,2JO

OC8 Vent - HR QJMQ Tempe ra tu re 40 'F !

OG Vent Pipe LD;12 Delta T -1.02 *F U1 Plant Vent LQ ;+_1 U1 Plant Vent - NR DJIM 18/HS Vent M ;tl , TB/H8 Vent - HR NDQQ ? ST Packing Exh h3 ;10 t U2 Plant Vent A 9';ti ,, U2 Plant Vent - HR DAtQ t DW170C/A/23/es l

                                                                                               . . . y.. . 7

AREA RADIATION MONITORS Time: 1030 !(' . s.

TAG /1 LOCATION READING (MR/hr) ~ Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21NO30 CRD HCU West, Cntmt (620'6") 5.0E+0 1D21N040 RBRT Area, Cntmt (642') 1.0E+2 1D21N050 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N050 7.0E+0 1D21NC70 RWCU F/D Area, Cntmt (664'7") Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N080 Aux Bldg East (574'10") 7.0E+0 1D21N110 Aux Blda West (574'10") 7.0E+0 1D21N120 Turb Rm East (647'6") 2.5E+0 1D21N130 CRD HCU East, Cntet (620'6") 5.0E+0 1D21N140 Turb Rm West (647'6") 2.5E+0 1D21N160 Turb Blda (605'6") 2.5E+0 1D21N170 Hotwell Pump Area. TB (577'6") 1.0E+1 1D21N180 TB Sump Area TBC (548'6") 2.0E+1 l 1D21N190 OGB (584') 1.1E+1 1D21N200 Cnds F1tr Pmp Area. TBC (568'6") 9.0E+0 1D21N210 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N220 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N230 Fdw Pump Area. HB (647'6") 6.6E+0 . 1D21N260 t CR, CC (654'6") 1.6E-1 1D21N400 I OG Hold Up Area TB (577'6") 1.0E+1 (,t ID21N410 2.5E+1 D21N250 RWB West (574'10") RWB East (574'10") 1.5E+1 D21N260 I (602') 5.0E+0 D21N270 RWB Process Sample Rm, RWB (623'6") 4.0E+0 D21N280 RW Evap, RWB (623'6") 4.0E+0 D21N290 (599') 6.0E+0 D21N310 FPCU F/D Area. IB Fuel Preparation Pool, IB (620'6") 4.8E+2 D21N320 Spent Fuel Storage Pool IB (620'6") 4.8E+2 i D21N330 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 D21N420 - 1D21N340 Unit 1 DW, Portable. Cntmt (655') Waste Compactor Area, RWB (623'6") 6.0E+1 , D21N380 SRW Drumming Area RWB (623'6") 6.0E+0 ; D21N370 Refueling Bridge, Cntmt (689'6") 3.0E+0 ID21N090 Fuel Serv Hdla Platform, IB (620'6") 4.6E+1 D21N390 - / , i a t

Y

   -... . .     . . . . .         .    . :   . . .. . .:.. ; :. : = . . . -       -           ....  . . . .   .-

Time: 1035 Message No.: M

     ' "                                                PERRY NUCLEAR POWER PLANT s-            1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM                                     ;.

Messane For: Control Room /TSC i Simulated Plant Conditions: See attached sheets - Messame: ***THIS IS A DRILL *** 5-4 i O h' t I

TOR CONTROLLER USE ONLY ,. Controller Notes h Actions Expected: . l-t r i h. I o ,DW176/C/43/ba [ 1 L.

[ Q

                                                                                                                                                                                                                                                                     'S    t t,

PUIRY HUCLEAR POWER PLASIT 1984 EMERGEIICY PREPAREDISESS EXERCISE T 100E l'035 COIITIt0L noon AnsivesetATORs P601/P877 P680 P870 ar BACK PAllELS Section 20A Section 5A C001T RM HVAC EMERG RCIRC A , SUPP POOL MAseUAL SCRAM INITIATED e P904 LEVEL A HIGet SWITCH AfWEED i COIIT RM HVAC SUPP POOL RPS LOGIC EteERC RCIRC 8

                              - TDer A MIGet                                                                             9WIUAL SCRAM                                                        INITIATED                                                               P9045 Section 17A                                                                                    RRCS stAsl INITIATION
                                  $UPP POOL LEVEL 8 HlGM                                                                               RPS LOW LEVEL e                                                                                                                                    L-3                                                                                                                                     ~

SUPP POOL -

                        .        TEMP B MIGet                                                                                      RItCS                                                                                                                                   r RX LEVEL

Section 19A LO L-2 I AoS s Pense:SSIVE AnR s/c Rua s

ADS A , p-PERMISSivt RPV L-3 t. ADS 8 1-PEstMISSIVE j' RPV L-3 ;. e 4 e DW1708/A/68/es i. 9 i

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   . PERRY IOUCLEAR POWER PLAlli                               1964 EMERGENCY PREPAREDNESS EXERCISE                                                                TIME: 1035               .

f69.1 P680 COIITAIISEENT PAlW4ETERS SYSTEM INFORMATIOII REACTOR PARAMETERS Tempe ra ture Pressure Pressure Flow Pressure 927 psig f*F1 fasiel Status fosiel femel Level -80 19 WR Cntet 95 0.4 RWCU P9tP A SS O Neutron DrywoII 134 0.4 8 SS O Mon 18 Range APftM HWL PMP A OP 230 Mode SW SHTON , Tempe ra ture Level f*F1 frt.) 8 OP 23 L FDW Flw 2.8 Mlb/hr Supe Pt 130 19.6 C SS O ST Flw (Total) 2.8 Mib/hr C8P A SS 150 Line A 0.5

SYSTDeS IMF0flMAT104 8 SS 150 Line 8 0.5 e

 .                            Pressure            Flow         .

Status fosial f emel ._ C SS 150 Line C 0.5 RNR A PMP OVRD RFBP A OP 330 Line D 1.5 . 8 SP Ctc 250 7000 8 OP 330 C VLV OVft0 275 0 C SS 160 , LPCS PMP OvetD D SS 160 RCIC FLW OVRO 500 0 RFP A OP 1000 8.8 t HPCS VLV OVIt0 900 0 8 SS 0 0 ECC A 005 MFP SR 0 0 IMOINE-ctNERATOR 8 OP 114 RCIRC A SS O PARAMETERS ESW A 005 8 SS O Natt 225 8 OP 95 MVAR 10 MMOR VALVE PARAMETERS C OP 95 CIIOR Vac 28 in. Hg _ Status Closed _ Open CR0 A SS Thrt Pr 925 psig 8 SS BYP VLV SRV IIORM 19 0 . Posit 0 % SLC A OP 1600 8 OP 1600 SLC STC TK LVL 4600 gal. f i , - . , .. .. . . ,,p.. , ~ . . . . . . _ . . . , . .. .-. ,._so . . , . . . .- , , , , _ . . . .

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f) ~ PEllRY IIUCLEAR POWER PLA81T ' 1984 EMERCEIICY PREPAftEDetESS EXEftCISE TIME: 1035 ' r fEIR ELECTRICAL DI$TRIBUT1001 P908I CST Love 1 410.000 emI. .E Status _ Load iMW1 _ Status __ . Status lastel_ Orrsite Pwr Sources 2 AV' Cont Ste HVAC Supp Fan A 0F

     'TBCC PHP A                    OP             75               Con Breakers               2 CL                                                                     '

B OP B OP 75 Div 1 DG 005 Cont Re HVAC Rtn Fan A

                                                          .                                                                                          SS                  .

C SS 18 Div 2 DC t OP O B SS SA Comp OP 128 Div 3 DC OP O cont ite Eng RCIRC Fan A ' OP IA Comp SR 120 P300 8 OP CIInf PHP A OP 46 - __ Status B OP 45 Cntet Val Cig Fan fil0 A _ _ . 0F . Pressu re C OP 46 B Status _fostel OP .. SJAE A 0F IICC Pump A $$ 35 ' C SS B SS S SS 35 D OF C OP 112 E OP ADDITIOIGAL IIeF0A004TICII SW Pump A OP 56 F SS i' Status Abbreviations: ;- B DryweiI CooiIng Fan IA OP 56 i~ OP Ope rating OP

C SS 0 SS Secured Status D SS 0

{ Av 3A OP Available i' - MTR Fir Pump SR # SR IB SS Standby Readiness ;*' DO Fire Pump SR Smit,M 28 SS g Shutdoun , S-SP Slow Speed 33 SS ' Cntet Vsl Purge supp Fan A SS F-F* Fast Speed B SS ' ISOL isolated Catet Val & DW Purge Exh Fan A SS 100ftM Igorma l - B SS OOS Out or Service DryweI I Purge Suppl Fan A SS CL Closed OVRO 8 SS Override AECTS Fan A _. 00S B OP 9

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              ' PERR) UCLEAR POWER PLANT                                                                                                     ,

1984 EMERGENCY PREPAREDNESS EXERCISE ; TlHE: 1035 , PANEL P604. I fA,esELS P669. P670. P671. P672-Process Radiation Alarm ? Main Steam Line RAD 7.0E+1 mR/hr Orrgas Pre-treatment 2.5E+1 R/hr ' 4 Cntet Vent Exh RAD 41.0E-1 mR/hr >

          .       Orrgas Post-treatment A           2.0E+2 cpm fML P902                              i                           '

B 2.0E+2 cpm Common +1rborne Eng Service Water A Gas (catl Ala rm s 3.0E+1 cpm - RWs vent Exh ~ P

                                                                                                                                  ,ggi  , '                 2. , 3   .

B 3.0E+1 cpm

FH8 Vent; Exh 2.2E+1

                 ,0G Carbon Bed Vault        A      6dg.+1 mR/hr                                                                                                                            .

CR Vent 3Exh 2.0E+1 B 5.5E+1 mR/hr g i g fAMEL P906 PANEL Sql [ Common Process and Area cgm Alarm Turb Bldg East 2.5E+0 mR/hr ,, d UD-MM-73 East, Liq '+ 3.0E+1 Turb Bldg West 2.5E+0 mR/hr,

                                                             \                                      UD-MH'-70 West Liq            3.2E+1                                               I NCC Heat HX.                  3.5E+1                                      '

PANEL P804 ;,

                                                                                                  ' Redwoate do ESW              3.0E+1

Airborne Radiation Cas (coal Alarm j p Redweste to Sewage 3.6E+1 Annulus Exh A Cas QJ M '

 -                                 8-             L.D Et.1                                                                                                                             '

Cntet Atm LJ dg Drywell - HR (R/hr) LQC+Q METEOROLOGICAL CONDITIONS " AB Vent L QE_11 ' OGB Vent Exh ZJCig Winst Speed 17.5 mph OGB Vent - FR QJEE Wind Direction 230 * [ OC Vent Pipe gJ E_12 Tempe ra ture 40 'F U1 Plant Vent LQEt1 Delta T -1.02 'r U1 Plant Vent - HR QJ 20 TB/HB Vent DJ [11 : 18/ IIB Vent - HR QJ M , ST Packing Exh h6 ;10 U2 Plant Vent L.Q :11

U2 Plant Vent - HR QJdQ DW170C/A/28s/es 9 e

             .4
                                                                            .,,p     wee-

      .x s'                                        AREA RADIATION MONITORS                 Time:     1035 s

TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntet (620'6") 5.0E+0 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'.6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1

              )      1D21N190   TB Sump Area TBC                 (548'6")               2.0E+1
               }     1D21N200   OGB                              (584')                 1.1E+1 1D21N210   Cnds Fitr Pmp Area, TBC          (568'6")               9.0E+0 1D21N220   OG After F1tr Area. OGB          (602'6")               2.0E+1 1D21N230   HP Fdw Htr Area, HB              (600'6")               1.0E+1 1D21N240   Fdw Pump Area, HB                (647'6")               6.6E+0 1D21N400   CR, CC                           (654'6")               1.6E-1

(~

     +               1D21N410   OG Hold Up Area, TB              (577'6")               1.0E+1 D21N250   RWB West                         (574'10")              2.5E+1 D21N260   RWB East                         (574'10")              1.5E+1

! D21N270 RWB (602') 5.0E+0 l D21N280 Process Sample Rm, RWB (623'6") 4.0E+0

D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area, IB (599') 6.0E+0-D21N320 Fuel Preparation Pool, IB (620'6") .- 4.5E+2 D21N330 Spent Fuel Storage Pool, IB (620'6") 2.5E+2 D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') -

D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 j D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 __ ID21N090 Refueling Bridge, Cntmt (689'6") 3.0E+0 D21N390 Fuel Serv Hdig Platform, IB (620'6") r 4.0E+1N

l l C

. , . . . . . . .               -.   ..     .   . . . .     .w.     ..   ..~....-.:.....a......

Time: 1040

                  ,                                                                               Message No.:   44

([,', PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE s MESSAGE FORM Message For: Control Room /TSC Simulated Plant Conditions: See attached sheets Message: ***THIS IS A DRILL *** i 4 FOR C0!CROLLER USE ONLY I Controller Notes: Actions Expected: DW176/C/44/ba , q.

[ b t,T >

I 4 . PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1040 CONTROL ROOM ANNUNCIATORS ..

f P601/P877 P680 P870 & BACK PANELS SectIon 20A Section 5A CONT RM HVAC EMERC RCIRC A SUPP POOL MANUAL SCRAM INITIATED / P904 LEVEL A HIGH SWITCH ARMED SUPP POOL RPS LOGIC CONT RM HVAC > TEMP A HIGH MANUAL SCRAM LMERG RCIRC B INITIATED P904 + CONTAINMENT RRCS MAN ' PRESS A HIGH ' INITIATION DRYWELL RPS LOW ~ LEVEL PRESS A HIGH L-3 A Section 17A RRCS RX LEVEL ' SUPP POOL LO L-2 . LEVEL 8 HIGH ' SUPP POOL , TEMP B HIGH

CONTAINMENT

3 PRESS B HIGH DRYWELL * '

PRESS B HICH

.            Section 19A                                                                                       (

ADS B 4 PERMISSIVE RHR B/C RUN ; t ADS A t '- PERMISSIVE ; RPV L-3 : ADS B

PERMISSIVE -- RPV L-3 - DW1708/A/71/es

_ _ _ _ _ _ _ _ _ _ _ - - - - . . . - - . - - - - - - - - - - -- - - - - - - - - - ~ - ~ ~~ '~ I

                                                                                                                                                                ~
                                                                                                                                                           ,Q   -

r. s-PERE IUCLEAR POWER PLANT t-1984 EMERGENCY PREPAREDNESS EXERCISE t TIME: 1040 ESnQ1 E.699 f CONTAINMENT PARAMETERS SYSTEM INFORMATION Tempe ra ture Pressure REACTOR PARAMETERS f*F) l _fosial_ Pre ssu re Flow Pressure _ Status _ _fosial_ _,Lqpa l 925 psig Cntet 98 0.5 RWCU PMP A SS 0 Level -100__ In. WR Drywel l 139 _ 0.9 _ B SS Neutron 0_ Mon 14 HWL PMP Range 6ER,flR Tempera ture Level A OP _ 230 f*FI Mode SW _SHTDN f f t ._)._ B OP _ 230 _ Supr Pl 132 FDW Flw: 2.2 Mlb/hr J1 C SS O CBP ST Flw (Total) 2. 2 ___ Mlb/hr SYSTEMS INFORMATION A SS 150 Line A .3 Pressure B SS 150 Flow Line B Status _fosial _ fqomi .3 C SS 150 RHR A PMP OVRD Line C .3 RFBP A OP 330 B _ SP CLO _ Line D 1.2 250 _ _ 7000 _ B OP C VLV OVRD 330__ 275 0 , C SS 160 LPCS PHP OVRD D SS 160 RCIC TLW OVRD 500 # 0 RFP A OP 1000 8.8 HPCS VLV OVRD 900 _ 0 B SS k O O ECC A _ OOS HFP SR L 0 0 B _ OP 'f. 114 RCIRC A SS l!LRQlN[-C[NERATOR ESW A _ OOS O PARAMETERS B SS ; B O Mwatt OP 95 225__ C OP 95 MVAR 10 ' MAJOR VALVE PARAMETERS CRD A SS Status _ Closed __Doen ' B SS MSly NORM Thrt Pr 924 0 __ 8 psig SLC A OP 1600 SRV _.. NORM ' BYP VLV 19 - 0 Posit 0 . B OP 1600 - SLC STG TK LVL 4600 gal. Ge9

                                                               -                                                                                                      0

                                         .                                                                                                                                                 i'
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h[ h_ i PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE h

    ~,                                                                                                                                                               TIME: 1040

2019 ' i ELECTRICAL DISTRIBUTION ffQg I' CST Level 410.000 cal. Status ' Load fMWI Status [

Status .losl i 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP T80C PMP A OP J_ con Breakers 2 CL 8 OP

8 OP 75 Div 1 DC 00S Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O 8 SS SA Comp OP 128 Div 3 DG OP O Cont Re Eng RCIRC Fan A OP IA Comp SR 120 B OP CIRW PMP A OP 46 _ Status ' B OP 45 _ Cntet Val Cig Fan A OP Pressure _1tatus _fosial SJAE A OP C SS i B SS 35 8 SS D OP i C OP 112 > E OP ADDIT 10NAL lNFORMAT10N SW Pump A OP

                                                                                                                                                                         , 56              i F          SS i              Status Abbreviations:                                                                                                                   B          OP          56 Drywe1I CooiIng Fan 1 A           OP                                                           ;

OP Opera t ing C SS 0 2A OP p SS Secured Status e-D SS O O 3A OP ; AV Available MTR Fire Pump SR p 18 SS ' SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown . 38 SS S-SP Slow Speed Cntet Vsl Purge l Supp Fan A SS . F-SP Fast Speed i. 8 b ' SS ISOL 1solated Cntet Val 3: DW , Purge Exh Fan A SS NORM No rue I - B SS OOS Out of Service Drywe l l Purge Suppl Fan A ; SS CL Closed - e 1 B SS OVRD Ove rride AECTS Fan

A 00S B OP i

         .[                                                             ,Q
                                                                                                                                    <S TIME: 108a0 lr PERRY NUCLEAR POWER PLANT                    19884 EMERGENCY PREPAREDNESS EXERCISE                                                p.

RX WATER LEVEL RX PRESS RX POWER SUPR PL TEMP i

                        -100      JJ   WR               925    EH1G ,                  Its        T                  132      ' F, f

60- 1100- 120- 110 84 5 - 950- 90- 90-30- 800- 40- 70-15- 650- 0 50 0 500 -30 -20 -10 0 -30 -20 -10 0 ; ..

                                                                                                                                       }'
                  -30  -20    -10    0          -30  -20    -10     0                Time (min)                   Time (min)

Time (min) Time (min) DW TEMP CONTMT TEMP CONTMT PRESS SUPR PL LEVEL l 139 *f 98 'f 0.5 E31Q 19.8 fl < 200- 110- 20- 19-150- 90- 15- -

                               /                                                                                                        t 100-                              70-                                                        18-10-r ss 50                               50-                              5-                           -
                  -30  -20    -10    0          -30  -20    -10     0        0-                        17                               ,

Time (min) Time (min) -5 -30 -20 -10 0

                                                                                -30  -20   -10      0             Time (min)

Time (min)

                 'M _+                                                               O'?

l PERRY NUCLEAR POWER PLANT 1964 EMERCENCY PREPAREDNESS EXERCISE TIME: 1040 ,- E PANEL P664 PANELS P669. P670. P671. P672 l Process Radiation Main Steam Llpe RAD \ 7.0E+1 mR/hr i Ala rm . Cntet Vent Exh RAD c1.0E-1 mR/hr I. Offgas Pre-treatment

2.5E+1 R/hr ^

Offgas Post-treatment A 2.0E+2 cpm PANEL P902 -

  '                                                                                                                                                   i B    2.0E+2 cpm                                    Common Airborne                  cas ICDel     Ala re          I

< Eng Service Water A 3.0E+1 cpm , RWB Vent Exh 2.0E+1 a B 3.0E+1 cpm FHB Vent Exh 2.2E+1

0G Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 B 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area gag Ala rm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq liq [i1 i Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 i NCC Heat HX 3.5E+1 fANEL P804 Radweste to ESW 3.0E+1 Ai rbo rne Rad ia t ion Gas (coal Ala rm Radweste to Sewage 3.6E+1 f Annulus Exh A Gas {63 :+J! .I B ;29 J :U. I Cntet Atm L) 2Sg METEOROLOGICAL CONDITIONS ! Drywell - HR (R/hr) 1,0 ;19 AB Vent 2m9 dl Wind Speed 17.5 mph 008 Vent Exh g 0012 Wind Direction 230 *

      ,         00B Vent - HR            Q,gE1D                                        Tempe ra ture           40       'F r

DG Vent Pipe gigLig Delta T -1.02 'F ' U1 Plant Vent 6,9011 U1 Plant Vent - HR QiDE1D TB/HB Vent nigE_il n TB/HB Vent - HR Q,gEig ST Packing Exh ligEig U2 Plant Vent 6tDE 1 !,._ U2 Plant Vent - HR 0.0E+0 _ DW170C/A/25/es ,i t. 4 1

       .a---.              .-           / . . a . i. .          .c .- -             '. - - -   --     . - - . .           .- -         s. .   . . ..:. ~

1 4 l

       - {---                                                             AREA RADIATION MONITORS                              Time:        1040
                                                                                      =

TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 . i 1D21N040 CRD HCU West, Cntat (620'6") 5.0E+0 ' { ID21N050 RBRT Area, Cntat (642') 1.0E+2 - ID21N060 Tip Drive Area, Cntat (600'6") 3.0E+1 ID21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 . j ID21N110 Aux Bldg East (574'10") 7.0E+0 i 1D21N120 Aux Bldg West (574'10") 7.0E+0 ! 1D21N130 Turb Rm East (647'6") 2.5E+0 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.5E+0 . 1D21N170 Turb Blda (605'6") 2.5E+0 [ ID21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 L 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 t ID21N200 CGB (584') 1.1E+1 i i 1D21N210 Cnds F1tr Pop Area, TBC (568'6") 9.0E+0 ID21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 ' 1D21N230 HP Fdw Htr Area HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area HB (647'6") 6.6E+0 h' ID21N400 CR, CC (654'6") 1.6E-1 : 1D21N410 OG Hold Up Area. TB (577'6") 1.0E+1 I D21N250 RWB West (574'10") 2.5E+1 ; D21N260 RWB East (574'10") 1.5E+1 i D21N270 RWB (602') 5.0E+0 !. D21N280 Process Sample Ra, RWB (623'6") 4.0E+0 i D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area IB (599') 6.0E+0 ' D21N320 Fuel Preparation Pool, IB (620'6") 2.6E+2 j D21N330 Spent Fuel Storage Pool IB (620'6") 1.6E+2 , D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') -

D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 !' D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 1D21N090 Refueling Bridge, Cntet (689'6") 3.0E+0 , (620'6") D21N390 Fuel Serv Hdig Platform, IB M .5E+1 l. , s ,/ ; 4 x

i 1 i

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                                  .~ .. .......'/..;.   ...--~..-.-.~~.,.-.asa:---......--.        ~ . . .      .     . . . - - ~

Time: 1045 Message No.: I f; PERRY NUCLEAR POWER PLANT 3 1984 EMERGENCY PREPAREDNESS EXERCISE r

MESSAGE FORM

                                                                                                                                . g.

Messate For: Control Room /TSC '( Simulated Plant Conditions: See attached sheets i; - i Message: ***THIS IS A DRILL ***

                                                                                                                                   .1-
                                                                                                                                   */

t' Y s . i: 4 !- FOR CONTROLLER USE ONLY n Controller Notes: Actions Expected: ! L H 7 Lj 44 t' 6 8

                     .DW176/C/45/ba

, (.: . 3 .. 6 i

                                                                                               .                                      L-
                                                                                                              ,   . ~--      _.: 2

               ,rh                                                                                                  iD r

PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1045 !' g CONTROL ROOM ANNUNCIATORS . P601/P877 P680 P870 ar BAC!' PANELS t Section 20A Sect 1on SA CONI RM HVAC

EMERG RCIRC A '

SUPP POOL MANUAL SCRAM INITIATED- f P904 LEVEL A HIGH SWITCH ARMED ; CONT RM HVAC SUPP POOL RPS LOGIC EMERG RCIRC B TEMP A HIGH MANUAL SCRAM INITIATED P904 ' CONTAINMENT -

                                                                     -RRCS MAN PRESS A HIGH                                             INITIATION                                             *      ,

DRYWELL RPS LOW LEVEL 4 PRESS A HICH L-3 [, '

Section 17A RRCS

RX LEVEL SUPP POOL LO L-2 LEVEL B HIGH I' SUPP POOL '

TEMP 8 HIGH I CONTAINMENT PRESS B HIGH ' DRYWELL PRESS 8 HIGH Section 19A 4 l ADS 8 PERMISSIVE t

   ,          RHR B/C RUN                                                                                                      :

ADS A ! PERMISSIVE ! RPV L-3 i nDS B PERMISSIVE RPV L-3 . t.. i DW1708/A/74/es 9

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e

                                                  ,y                                                                     4

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i PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE > TIME: 1045 P601 P680 f' CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS , Tempe ra ture Pressure . Pressu re Flow Pressure 924 psig f*F1 fosial Status _1psig) ' focal Level -130 In. WR Cntet 102 0.6 RWCU PHP A SS 0 ; Neutron ' Dryweli 145 1.5 B SS O ' Mon 11 Range MRH ! i HWL PMP A OP 230 Mode SW _SHTDN Tempe ra ture Level f*F1 (Ft.) B OP 230 FDW Flw 1.7 Mlb/hr

Sup r PI 134' 20 C SS O ST Flw (Total) 1.7 Mib/hr :

CBP A SS 150 Line A .3 SYSTEMS INFORMATION [. 8 SS 150 Line B .3 f. Pressu re Flow h' Status fosial faom) C SS 150 Line C .3 RHR A PMP OVRD RFBP A OP 330 'Line D .8 I b B SP CLC 250 7000 B OP 330 i ( C VLV OVRD 275 0 C SS 160 i LPCS PMP OVRD D SS 160 ; RCIC FLW OVRD 500 O RFP A OP 1000 8.8 HPCS VLV OVRD 900 0 B SS 0 0 ECC A 00S MFP SR 0 0 l![RBlN[-CLNERATOR B OP 114 RCIRG A SS 0 PARAMETERS ESW A 00S B SS O Mwatt 225 b l. B OP 95 MVAR 10 i< MAJOR VALVE PARAMETERS i. C. OP 95 CNDR.Vac 28 in. Hg . [ ' Status Closed Doen - CR0 A SS Thrt Pr 923 psig MSIV NORM O 8 8 SS BYP VLV e S6V NORM 19 0 Posit 0 % SLC A OP 1600 8 OP 1600 , l SLC STC TK LYL 4600 gal. I ! t I t a f

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     ,    PERRY NUCLEAR POWER PLANT                                                        '1984 EMERCENCY PREPAREDNESS EXERCISE                                                 TIME: 1045 ERZA                                       ELECTRICAL DISTRIBUTION.                                           P904 i

CST Level 410.000 aal. Status Load iMW1 _ Status Status fosial OFFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL 8 O P -- r - B OP 75 Div 1 DC OOS Cont Rm HVAC Rtn Fan A SS {, C SS 18 Div 2 DC OP O B' SS SA Comp OP 128 Div 3 DC OP O Cont Re Eng RCIRC Fan A OP i 1A Comp SR 120 B- OP P600 . CIRW PHP A OP 46 Status ' P970 8 OP 45 Cntet Vsl Cig Fan A OP Pressu re i Status fosial . C OP 46 B OP *

                                                                                                                                                                                                                     },
 *                                                                                                   ,                                                     NCC Pump A         SS          35                         ;.

SJAE A OP C SS t B SS 35 : B SS D OP f E OP C OP 112 I' ADDITIONAL INFORMATION SW Pump A OP 56 F SS

Status Abbreviations: B OP 56 f' DryweiI Coo 1ing Fan 1A OP OP Ope ra t ing C SS O 2A OP '

SS Secured Status D SS O ' 3A OP AV Available MTR Fire Pump l SR - IB SS i. SR Standby Readiness DD Fire Pump SR ; 28 SS i SHTDN Shutdown ' 38 SS . S-SP Slow Speed Cntet Vsl Purge Supp Fan A SS F-SP Fast Speed , . 8 SS / ISOL isolated Cntet Vs1 & DW ; Purge Exh Fan A SS NORM No raa 1 8 SS i OOS Out of Service Drywe l l Purge , Suppl Fan A SS , 8 SS OVRD Override AECTS Fan A 00S B OP I h e u-,- -- ~: n y.r -- - m ,,: py--r- - - - - e- , T v -?,rv*T~n~/-- w cry =c c ' ' ~~ "

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' r- E @ g m e O e C e. t N *= w U > E E W A e . I v

FR ,'

   ,. PERRY NUCLEAR POWER PLANT                            1984 EMERCENCY PREPAREDNESS EXERCISE                                               TIME: 1945 t

1 PANEL P604 PANELS P669. P670. P671. P672 i' Process Radiation Main Steam Line RAD 7.0E+1 mR/hr Alarm Cntet Vent Exh RAD 41.0E-1 mR/hr

 ,        Orrgas Pre-treatment              2.5E+1 R/hr Orrgas Post-treatment A           2.0E+2 cpm                                                                 PANEL P902                          /

8 2.0E+2 cpm Common Airborne Cas (coal ' Alarm l . Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 B 3.0E+1 cpm FHB Vent Exh 2.2E+1 > OC Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr , PANEL P906 l PANEL 803 Common Process _and Area gem Ala rm Turb Bldg East 2.5E+0 mR/hr UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-70 West Liq 3.2E+1 I NCC Heat HX 3.5E+1 PANEL P804 Radwaste to ESW 3.0E+1 f

Airborne Radiation Cas (coal Ala rm Radweste to Sewage 3.6E+1 ;

Annulus Exh A Ces QtD ;il! f B 119.;11 t, Cntet Ate 2,1;12 METEOROLOCICAL CONDITIONS !. Drywell - HR (R/hr) 1&;10 [w AR Vent Etq!;11 Wind Speed 17.0 mph DG8 Vent Exh 210Lig Wind Direction __g35

DG8 Vent - HR Q,HEig Tempe ra ture 40 *F 1 OC Vent Pipe R plig Delta T -1.00 *F }'

l U1 Plant Vent 61D[11 - l ut Plant Vent - HR QiDL19

l. TB/HB Vent 6,9 ;11

! TB/HB Vent - HR QiD 20Q l ST Packing Exh 1,6 LtQ U2 Plant Vent 6 ,Q ill U2 Plant Vent - HR Q,D.1Q b DW170C/A/26/es e t. 4 # 91, ._'*W *%,

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                                                         AREA RADIATION MONITORS                  Time:     1045 s

TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntet (600'6") 5.0E+0 - ID21N040 CRD HCU West, Cntet (620'6") 5.0E+0 - 1D21N050 RBRT Area, Cntmt (642') 1.0E+2 1D21N060 Tip Drive Area, Cntat (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntet (689'6") 2.0E+0 ' 1D21N110 Aux Bldg East (574'10") 7.0E+0 : ID21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.3E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0 1D21N160 Turb Rm West (647'6") 2.3E+0 g 1D21N170 Turb Bldg (605'6") 2.5E+0 i' 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 L ID21N190 TB Sump Area, TBC (548'6") 2.0E+1 L ID21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 ; ID21N220 OG After Fitr Area, OGB (602'6") 2.0E+1 g 1D21N230 HP Fdw Her Area, HB (600'6") 1.0E+1 ,. 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0 [ 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area, TB (577'6") 9.5E+0 D21N250 RWB West (574'10") 2.5E+1 1.5E+1 [' D21N260 RWB East (574'10") ; ! D21N270 RWB (602') 5.0E+0 t D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 b; l D21N290 RW Evap, RWB (623'6") 4.0E+0 p i D21N310 FPCU F/D Area. IB (599') 6.0E+0 J;

D21N320 Fuel Preparation Pool, IB (620'6") >1.9E+2 D21N330 Spent Fuel Storage Pool, IB (620'6") 1.2E+2

l " D21N420 FPCU Cire Pmp Area, IB' (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') - s D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 's l D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 " Refueling Bridge, Cntmt (689'6") 3.0E+0 5' l 1D21N090 D21N390 Fuel Serv Hdig Platform, IB (620'6") 1.3E+1 t

5 l I l l ., l i l l -

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Time: 1045 m

                                                                                                                      ,.--                   )

Message' Nof: 4(c)( !

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   -                                          PERRY NUCLEAR POWER PLANT                                                          sI      /
                                                                                                                                     /               ,

[.,, y/' 1984 EMERGENCY PREPAREDNESS EXERCISE >

                                                                                              ,r.                i             ,

MESSAGE FORM '- -

                                                                                                                     /
                                                                                         /'                   -

Message For: Emergency Coordinator I, ' Simulated Plant Conditions: See attached sheets i Messame: ***THIS IS A DRILL *** . Declare a SITE AREA EMERGENCY (EPI-A1, Section D.III.2, " Complete < loss of any functions needed for plant hot shutdown"). 3 p. C i: lC h. i i FOR CONTROLLER USE ONLY , . l-Controller Notes: Deliver this to the Emergency Coordinator only if a SITE [ AREA EMERGENCY has not been declared by now. t- . p i . Actions Expected: See " Actions Expected" Message No. 42. Ii t-

                                                                                                                                                       -t h

DW176/C/46/ba 1 k. m - --.i,_ ' , _ - '$'"- , ,

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                                                                                                       .. . ~ .

Time: 1050 Message No.: 4 '7 h PERRY NUCLEAR POWER PLANT s 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Messare For: Control Room /TSC i./ Simulated Plant Conditions: See attached sheets ' Messaae: ***THIS IS A DRILL *** t

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                                                                                                                ' E .,

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                                                                                                                  ?1 i

IJ i.: (' . {i i r. I FOR CONTROLLER USE ONLY [: i j t C

                     -Controller Notes:     Reactor water level is being maintained at -145 inches; reactor power remains at 8%.
                                                                                                                    .a
                                                                                                                   ?

Actions Expected: 1 o L J 8 9 DW176/C/47/ba

t .

 . PERRY NUCLEAR POWER PLANT                                      1984 EMERCENCY PREPAREDNESS EXERCISE                                          TIME: 1050 f64.1                                            E6AQ CONTAINMENT PARAMETERS                                  SYSTEM INFORMATION                                            REACTOR PARAMETERS Tempe ra tu re      Prassure                                                     Pressu re     Flow         . Pressure               923      psig f*FI           _loslal                                          Status       _fosial       faomi Level                -145        in,   WR Cntet                  106               0.7                      RWCU PMP A               SS-           0 Neut ron Drywe l l              152               1.8                                8              SS            0                     Mon                        8   Range APRM     c HWL PMP - A              OP        230                      Mode SW           SHTDN Tempe ra tu re        Level
      .                 (*F1             fft.1                                 B              OP        230                      FDW Flw              *1.2       Mlb/hr I

Supr Pt 135 20.1 C SS' O ST Flw (Total) ' 1. 2 Mlb/hr CBP A SS 150 Line A .2 SYSTEMS INFORMATION . 8 SS 150 Line B .2 Pressure Flow _. Status fosial focal C SS 150 Line C .2 RHR A PMP OVRD' RFBP A OP 330 Line D .6 B SP CLC 250 7000 8 OP- 330 C VLV OVRO 275 0 C SS 160 LPCS PMP OVRD D SS 160 RCIC FLW DVRD 500 0 RFP A OP 1000 8.8 HPCS VLV OVRD 900 0 B SS 0 0 ECC A 00S MFP SR 0 0 IURBjNE-GE_N[RATOR B OP 114 RCIRC A SS 0 PARAMETERS ESW A 00S B SS O Mwatt 0 B OP 95 MVAR 0 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Status Closed Open CRD A SS Thrt Pr 922 psig MSIV NORM 0 8 8 SS BYP VLV SRV NORM 19 0 Posit 16 % SLC A .0 P 1600 B OP 160d SLC STG TK LVL 4600 gal. e t I w

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    . PERRY NUCLEAR POWER PLANT                1984 EMERCENCY PREPAREDNESS EXERCISE                                                      TIME: ,1050 j

2019 ELLCTRICAL DISTRIBUTION E2Qif CST Level 410.000 cal. Status Load (MW1 Status Status fosial Offsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PMP A OP 75 Con Breakers 2 CL B OP B OP 75 Div 1 DG OOS Cont Rm HVAC Rtn Fan A SS C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DG OP O Cont Re Eng RCIRC Fan A OP IA Comp SR 120 B- OP fB99 CIRW PMP A OP 46 Status 8 OP 45 Cntet Vsl Cig Fan f219 A OP Pressure

                                                                                                                                - Status         fosial C        OP           46                          B                  OP NCC Pump A               SS            35 SJAE       A        OP                                       C                  SS B            SS            35 8        SS                                       D                  OP C            OP           112 E                  OP ADDITIONAL INFORMATION                                                   -

SW Pump A OP .56 F SS Status Abbrevlations: B OP 56 Drywell Cool ing Fan I A OP OP Ope ra t ing C SS O 2A OP " SS Secured Status D SS O 3A OP AV Available MTR Fi re Pump SR 18 SS SR Standby Readiness DD Fire Pump SR 28 SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Val Purge Supp Fan A SS F-SP Fast Speed B SS ISOL isolated Cntat Val er DW ' Purge Exh Fan A SS NORM Noreai B SS OOS Out of Service Drywell Pu rge Suppl Fan A S$ CL Closed B SS , OVRD Override AECTS Fan A OOS B OP t

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.- PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PP.EPAREDNESS EXERCISE TIME: 1050 PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.0E+1 mR/hr

Ala rm Cntet Vent Exh RAD 41.0E-1 mR/hr Offgas Pre-treatment 2.5E+1 R/hr ,

Orrgas Post-treatment A 2.0E+2 cpm PANEL P902 -e B 2.0E+2 cpm Common Airborne cas (CDal Ala rm Eng Service Water A 3.0E+1 cpm RW8 Vent Exh 2.0E+1 B 3.0E+1 cpm FHB Vent Exh 2.2E+1 OC Carbon Bed Vault A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 8 5.5E+1 mR/hr PANEL P906 PANEL 803 Common Process and Area ces Alarm Turb Bldg East 2.5E+0 mR/hr- UD-MH-73 East Liq 3.0E+1 Turb Bldg West 2.5E+0 mR/hr UD-MH-7d West Liq 3.2E+1 NCC Heat HX 3.5E+1 PANEL P804 Redwaste to ESW 3.0E+1 t' Airborne Radiation cas IcDal Ala rm Radwaste to Sewage 3.6E+1 Annulus Exh A Cas QiD[ig ' B ltD[f1

Cntet Atm EinE12 METEOROLOGICAL CONDITIONS Drywell - HR (R/hr) L9Eip AB Vent gig [1] Wind Speed 17.0 mph 00B Vent Exh R,gEfg __gj5
Wind Di rection

. OCB Vent - HR Q1DEig Tempe ra tu re 40 'F OC Vent Pipe EiDL12 Delta T -1.00 *F U1 Plant Vent htDLil US Plant Vent - HR Q1DLig TP/HB Vent 6 QLil TB/HB Vent - HR Q1QLig ST Packing Exh 113EfD , U2 Plant Vent 6.0E+1 U2 Plant Vent - HR 0.0E+0 DW170C/A/27/es f i

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     . _                        _                    . . ~               ._                                                                                    .

I L AREA RADIATION MONITORS Time: 1050 i . TAG # LOCATION READING (MR/hr) , ID21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntat (620'6") 5.0E+0 { ID21N050 RBRT Area, Cntet (642') 1.0E+2 " 1D21N060 Tip Drive Area, Cntet (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntet (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntet 4689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7.0E+0 1D21N120 Aux Bida West (574'10") 7.0E+0 ID21N130 Turb Rm East (647'6") 2.3E+0 1D21N140 CRD HCU East, Cntet (620'6") 5.0E+0 l 1D21N160 Turb Rm West (647'6") 2.3E+0 1D21N170 Turb Blda (605'6") 2.5E+0 1D21N180 Hotwell Pump Area. TB (577'6") 1.0E+1 , 1D21N190 TB Sump Area, TBC (548'6") 2.0E+1 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area. TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1

 ,           1D21N230               HP Fdw Htr Area, HB                .

(600'6") 1.0E+1 JD21N240 Fdw Pump Area, HB (647'6") 6.6E+0 1D21N400 CR, CC (654'6") 1.6E-1 1D21N410 OG Hold Up Area TB (577'6") 9.5E+0 ' D21N250 RWB West (574'10") 2.5E+1 ' D21N260 RWB East (574'10")- 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 , D21N290 RW Evap, RWB (623'6") 4.0E+0 D21N310 FPCU F/D Area IB (599') 6.0E+0

l. D21N320 Fuel Preparation Pool, IB (620'6") 1.5E+2 l D21N330 Spent Fuel Storage Pool, IB (620'6") 1.0E+2 D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0

[ 1D21N340 Unit 1 DW, Portable Cntet (655') ~ D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1

D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0

ID21N090 Refueliam Bridge,.Cntet (689'6") 3.0E+0 ,

D21N390 Fuel Serv Hdlg Platform. IB (620'6") 1.2E+1 4

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                                                                                                                              -Time:        1055 47
                                                                                                                        ~

Message No.: PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM ! Messane For: Control Room /TSC Simulated Plant Conditions: See attached sheets Messaa'e: ***THIS?IS A DRILL *** ..- r 4 I b5 ! i' P FOR CONTROLLE*< USE ONLY , Controller Notes: *' I-Actions Expected: . - i.: DW176/C/48/ba I D s 4. e

           ~ <              -,      -9                      *
                                                                         - , . - - - . , - - . . - . . - - . .        -                 ,+..---.$,-

p.~ .,. . . .

  . PERRY NUCLEAR POWER PLANT                                   1984 EMERGENCY PREPAREDNESS EXERCISE                       TIME:'1055 CONTROL ROOM ANNUNCIATORS P601/P877                                                       P680          P870 & BACK PANELS Section 20A    Section 19A                                        Section 5A                    CONT RM HVAC EMERG RCIRC A SUPP POOL        ADS B                                       ' MANUAL SCRAM                    INITIATED   f   P904 LEVEL A HIGH    PERMISSIVE                                       SWITCH ARMED

RHR B/C RUN CONT RM HVAC SUPP POOL RPS LDGIC EMERG RCIRC B TEMP A HIGH ADS A MANUAL SCRAM INITIATED P904 PERMISSIVE CONTAINMENT RFi L-3 RRCS MAN PRESS A HIGH INITIATION ADS B '

DRYWELL PERMISSIVE RPS LOW LEVEL PRESS A HIGH RPV L-3 L-3 LOGIC FOR LPCS/ ADS A RRCS LPCI A FRM RHR A PERMISSIVE RX LEVEL DW PRESS HIGH DW PRESS HIGH LO L-2 , CONTAINMENT ADS S RPS TEMP A HIGH PERMISSIVE DRYWELL DW PRESS HIGH PRESS HIGH , SUPP POOL Section 7A

MAKEUP TRAIN A TIMER ACTUATED SAFETY / RELIEF VALVE LEAKAGE ALARM P614 Section 17A Section 17A ORVwtLL Section 9A

                                                                                           - ~ ~ ~

TEHP A CONTAINMENT HIGH TEMP B HIGH I GENERATOR l ILOCMOUT RELAY SUPP POOL DRYWELL TRIP l LEVEL B TEMP B l HIGH HIGH l AUTO VOLTAGE l s REGULATOR s SUPP POOL SUPP POOL 'I TRIP a TEMP B HIGH MAKEUP TRAIN 8 l ___ .__ __ _. I TIMER ACTUATED CONTAINMENT PRESS B HIGH

DRYWELL PRESS B HIGH LOGIC FOR LPCI B/C . FM RHR DW PRESS HIGH DW1708/A/80/es

                                                              '                  ~~'                              ~~

____ _ _ _ _ _ _ _ _ _2-' i _'_ ~ l

                                                            -              -I                                    l'              *

[~; & PERRY NUCLEAR POWER PLANT 1964 EMERCENCY PREPARED 00ESS EXERCISE TIME: 1055 260.1' - Inan i CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS , Tempera ture Pressure -Pressure ' Flow Pressure 923 psig f*F1 fosial . Status fosial faomi Cntet 110 __ 0.8 RWCU PMP A SS 0

Neutron e Drywell 160 2.2 8 SS 0 Mon 8 Range APRM -

HWL PMP A OP 230 Mode SW _SHTDN Tempe ra tu re Level f'F1 ift.I B OP 2 30'__ FDW Flw 1.2 Mib/hr Supr Pt 136 __20.2 C SS 0 ST Flw (Total) 1.2 Mib/hr . CBP A SS 150 Line A .2 SYSTEMS INFOR51AT10N ' 8 SS 150 Line B .2 Pressure Flow Status fosial (epal C SS 150 Line C .2 R!lR A PMP OVRD RFBP A OP 330 Line D .6 , 8 SP CLC 250 7000 B OP 330 C VLV OVRD 275 0 C SS 160

LPCS PMP OVRD D SS 160 RCIC FLW OVRD 500 0 RFP A OP 1000 8.8 HPCS VLV OVRD 900 0 8 SS O O ECC A 00S - MFP SR 0 0 l!LRglM -CE_NERATOR B OP 114 RCIRC A SS O PARAMETERS

. ESW A 00S B SS 0 Mwatt 0 B OP 95 MVAR 0 MAJOR VALVE PARAMETERS C OP 95 . CNDR Vac 28 in. Hg Status S W esL. Open CRD A SS Thrt Pr 922 psig MSIV NORM 0 8 i B SS BYP VLV l SRV NORM 19 0 Posit 16 % SLC A OP 1600 B OP 1600 l-. SLC STC TK LYL 4600 gal, I4 e 9 9

                                                                      ,  ,.9          .                      --t~~-                    9        e                      .*               t

C: (3 lT' PERRY NUCLEAR POWER PLANT 1984 EMERGENCY PREPAREDNESS EXERCISE TIME: 1055 l P870 ELECTRICAL DISTRIBUTION f29A CST Level 410.000 esl. Status Load IMW) Status. Status loslal 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP TBCC PHP A OP 15 Gen Breakers 2 CL B. OP . B OP 75 Div 1 DG OOS Cont Rm HVAC'Rtn Fan A SS ' C SS 18 Div 2 DG OP O B SS SA Comp OP 128 Div 3 DC OP 0 Cont Re Eng RCIRC Fan A OP IA Comp SR 120 8 OP , CIRW PHP A OP 46 Status f210 B OP 45 Cntet Val Cig Fan A OP Pressure . Status fosial ' C OP 46 - B OP NCC Pump A SS 35 4 SJAE A OP C SS , 8 SS 35

B SS D OP C OP 112 E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS Status Abbreviations: B OP 56 Drywell Cooling Fan 1 A OP OP Ope ra t ing C SS 0 2A OP I SS Secured Status D SS O 3A OP AV Available MTR Fire Pump SR

' 1B SS i SR Standby Readiness DD Fire Pump SR l 2B SS SHTDN Shutdown 3B SS S-SP Slow Speed Cntet Vsl Pu rge Supp Fan A SS F-SP Fast Speed B SS ISOL 1solated Cntet Vsl ar DW Purge Exh Fan A SS B SS 00S Out of Service Drywell Purge Suppi Fan A SS , CL Closed . B SS OVRD Ove rride , AEGTS Fan A 00S B OP f e h

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c, PERRY NUCLEAR POWER PLANT t > 1984 EMERGENCY PREPAREDNESS EXERCISE , , TIME: ,1055'

 ...,                                                                                                                       .<                                                                         4 3

PANEL P604 PANELS P669. P670. P671. P672 Process Radiation Main Steam Line RAD 7.0E+1 mR/hr .g Alann f- - , Cntet Vent Exh RAD s.t.0E-1 mR/hr- '/ r . 'Orrgas Pre-treatment 2.5E+1 R/hr Orrgas Post-treatment A 2.0E+2 cpm , PANEL P902 ,, m : 8 2.0E+2 cpm Common Airborne Gas'fcom) Al a re , Eng Service Water A 3.0E+1 cpm RWB Vent Exh 2.0E+1 8 3.0E+1 cpm ,1 " FHB Vent Exh 2.2E+1 ._ _ OG Ca rbon Bed . Vaul t .A 6.0E+1 mR/hr CR Vent Exh 2.0E+1 B 5.5E+1 mR/hr u , PANEL'P906 ' s PANEL 803 Common Prccess and rea spo Ma_tg

                                                                                  -                          J Turb Bldg East         2.5E+0 mR/hr                              ,;                        UD-MH-73 [Ee,st Llqj ? '                      3.0E+1 Turb Bldg West         2.5E+0 mit/hr                                - '

UD-MH-70 West 2.84 3.2E*f < . NCC Heat HX 3.5E+1 PANEL P804 Radweste to ESW L_Qfd ' Airborne Radiation Gas (CDel Alarm Radweste to Sewage L1Q+1 Annulus Exh A Gas D10LtQ B M E11 Cntet Atm 2d ;+2 METEOROLOGICAL CONDIT10Mg Drywe l l - HR (R/hr) LD do AB Vent 2 0 ;+1 Wind Speed 17.0 . sph OCB Vent Exh E M ig Wind Direction 235

OCB Vent - HR Q M tD Tempe ra ture 1:0 *F OG Vent Pipe 210Eig

_ Delta T -1.00 'F U1 Plant Vent 6 OLt1 U1 Plant Vent - HR Q.0E+0 TB/HB Vent Qi9Lt1 TB/ IIB Vent - HR Q M fD ST Packing Exh M LtD U2 Plant Vent 6 QE_t1 U2 Plant Vent - HR 0.0E+0 - DW170C/A/28/es r e

                                       - ge       ,      te+                        4 ws ==ee +- r e ,             w e ego      ees          ,a g .g        .-m..-

AREA RADIATION MONITORS Time: 1055 , s TAG # LOCATION READING (MR/hr) 1D21NO30 Personnel Air Lock, Cntmt (600'6") 5.0E+0 1D21N040 CRD HCU West, Cntet (620'6") 5.0E+0

                  '1D21N050            RBRT Area, Cntmt               (642')           1.0E+2             '

1D21N060 Tip Drive Area, Cntmt (600'6") 3.0E+1 1D21N070 RWCU F/D Area, Cntmt (664'7") 7.0E+0 1D21N080 Upper Pool Area, Cntmt (689'6") 2.0E+0 1D21N110 Aux Bldg East (574'10") 7'.0E+0 1D21N120 Aux Bldg West (574'10") 7.0E+0 1D21N130 Turb Rm East (647'6") 2.3E+0 1D21N140 CRD HCU East, Cntmt (620'6") 5.0E+0- i-ID21N160 Turb Rm West (647'6") 2.3E+0 1D21N170 Turb Bldg (605'6") 2.5E+0 1D21N180 Hotwell Pump Area, TB (577'6") 1.0E+1 1D21N190 TB Sump Area TBC (548'6") 2.0E+1 ; 1D21N200 OGB (584') 1.1E+1 1D21N210 Cnds F1tr Pmp Area, TBC (568'6") 9.0E+0 1D21N220 OG After F1tr Area, OGB (602'6") 2.0E+1 1D21N230 HP Fdw Htr Area, HB (600'6") 1.0E+1 1D21N240 Fdw Pump Area, HB (647'6") 6.6E+0

         .          1D21N400           CR, CC                         (654'6")          1.6E-1
           ,        1D21N410           OG Hold Up Area, TB            (577'6")         9.5E+0             ,

D21N250 RWB West (574'10") 2.5E+1 D21N260 RWB East (574'10") 1.5E+1 D21N270 RWB (602') 5.0E+0 D21N280 Process Sample Rm, RWB (623'6") 4.0E+0 D21N290 RW Evap, RWB ,. ( 623 ' 6".) 4.0E+0 D21N310 FPCU F/D Area, li (599') 6.0E+0 D21N320 Fuel Preparation Pool, IB (620'6") .1.1E+2 D21N330 Spent Fuel Storage Pool, IB (620'6") 6.0E+1 D21N420 FPCU Cire Pmp Area, IB (574'10") 9.0E+0 1D21N340 Unit 1 DW, Portable, Cntmt (655') - D21N380 Waste Compactor Area, RWB (623'6") 6.0E+1 l D21N370 SRW Drumming Area, RWB (623'6") 6.0E+0 l ID21N090 Refueling Bridge, Cntet (689'6") 3.0E+0 (620'6") 1.1E+1 D21N390 Fuel Serv Hd1.g Platform, IB L l b _ - 3 --

  .~m.._,       . . _ . , - . . ~ . _ . .. _            ..    .   ..             ..                                             .- - - . . - - . . . . .     .4:

Time: 1100 Message No.: 4/9 p .. 0] PERRY NUCLEAR POWER PLAhT s 1984 EMERGENCY PREPAREDNESS EXERCISE - MESSAGE FORM i .; Message For: Control Room /TSC/ EOF i: t Simulated Plant Conditions: See attached sheets Messame: ***THIS IS A DRILL *** j. r A ' e i; r l' t t. l' f, t: Q l'i ! ,t - . FOR CONTROLLER USE ONLY l . . Controller Notes: EOF and JPIC activation should be underway. r Actions Expected: t: i. {'. I

i i l e DW176/C/49/ba M i l 1 l f a .. _ _ . . _ ..._ -_-, _ _ _ . , _ . , , . . _ .-,

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                ,-                        PERRY NUCLEAR POWER PLANT                                                                                     -1984 EMERGENCY PREPAREDNESS EXERCISE-                                     TIME: 1100 CONTROL ROOM ANNUNCIATORS t

P601/P877 P680 P870 k BACK PANELS Section 20A Section 19A Section 5A CONT RM HVAC EMERG RCIRC A SUPP POOL ADS B MANUAL SCRAM INITIATED e P904 , LEVEL A HICH PERMISSIVE . SWITCH ARMED RHR B/C RUN CONT RM HVAC - SUPP POOL RPS LOGIC EMERG RCIRC B TEMP A HIGH ADS A MANUAL SCRAM INITIATED P904

                      .                                                                PERMISSIVE CONTAINMENT       RPV L-3                                                                                            RRCS MAN PRESS A HIGH                                                                                                         INITIATION ADS B DRYWELL      PERMISSIVE                                                                                        RPS LOW LEVEL PRESS A HIGH        RPV L-3                                                                                                   L-3 LOGIC FOR LPCS/             ADS A                                                                                                  RRCS                                                       ,

LPCI A FRM RHR A PERMISSIVE RX LEVEL ,' DW PRESS HIGH DW PRESS HIGH LO L-2 ' CONTAINMENT ADS B RPS

TEMP A HIGH PERMISSIVE DRYWELL DW PRESS HIGH PRESS HIGH SUPP POOL -

MAKEUP TRAIN A Section 7A , TIMER ACTUATED - SAFETY / RELIEF DRYWELL VALVE LEAKAGE TEMP A ALARM P614 HIGH Section 17A Section 17A SUPP POOL CONTAINMENT LEVEL B TEMP B HIGH HIGH DRYWELL . SUPP POOL TEMP B TEMP B HIGH HIGH CONTAINMENT SUPP POOL PRESS B HIGH MAKEUP TRAIN B TIMER ACTUATED DRYWELL _ PRESS B HIGH LOCIC FOR LPCl B/C FM RHR DW PRESS HIGH DW1708/A/83/kay ; i

s. , . . . . . . . , .

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O O - f PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDNESS EXERCISE - TlHE: 1100 f.69.1 f6AQ CONTAINMENT PARAMETERS SYSTEM INFORMATION REACTOR PARAMETERS Tempe ra tu re Pressu re Pressu re Flow P ressure 923 psig ' (*Fl fosial Status _(pslal topol 110 RWCU PMP A

Cntet 0.8- SS O Neutron Drywell 160 2.2 B SS 0 Mon 8' Range APRM IfWL PMP A OP 230 Mode SW .SHTDN Tempe ra tu re Level f*Fl (Ft.) B OP 230 FDW Flw 1.2 MIb/hr

~

Supr Pt 136 20.2 C SS 0 ST Flw (Total) 1.2 Mib/hr CBP A SS 150 Line A .2 SYSTEMS INFORMATION B SS 150 Line B .2 Pressure Flow . Status foslo) foDel C SS 150 Line C .2 . V RHR A PMP OVRD RFBP A OP 330 Line D .6 B SP CLG 250 7000 B OP 330 i' C VLV OVRD 275 0 C SS 160 - 5 i LPCS PMP OVRD D SS 160 RCIC FLW OVRD 500 0 RFP A OP 1000 8.8 H PCS VLV OVRD 900 0 B SS O O ECC A 00S MFP SR 0 0 TURBINECENERATOR B OP 114 RCIRC A __ SS 0 PARAMETERS ESW A DOS B SS O Mwatt 0 B OP 95 MVAR 0 MAJOR VALVE PARAMETERS C OP 95 CNDR Vac 28 in. Hg Status Closed Open CRD A SS Thrt Pr 922 psig MSIV- NORM 0 8 B SS BYP VLV SRV _ NORM 19 0 Posit 16 % B OP 1600 SLC STC TK LVL 4600 gal. t

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PERRY NUCLEAR POWER PLANT 1984 EMERCENCY PREPAREDMESS EXERCISE TIME: 1100 f. i P870 , El.ECTRICAL DISTRIBUTION P904 CST Level 410.000 cal., Status Load IMW) Status ' Status fosla) 0FFsite Pwr Sources 2 AV Cont Rm HVAC Supp Fan A OP' - TBCC PMP A OP 75 Con Breakers 2 CL B OP B OP 75 Div 1 DC 00S Cont Rm HVAC Rtn Fan A SS ' C S'S 18 - Div 2 DG OP O B SS SA Comp OP 128 Div 3 DC OP O Cont Re Eng RCIRC Fan A OP I A Comp- SR 120 B OP P800 CIRW PMP A OP 46 Status P970 B OP 45 Cntet Vsl Cig Fan A OP Pressu re Status fosial C OP 46 B OP NCC Pump A SS 35 SJAE A OP C SS B SS 35 !. 8 SS D OP C OP 112 . E OP ADDITIONAL INFORMATION SW Pump A OP 56 F SS . Status Abbreviations: B OP 56 . Drywell Cooling Fan 1A OP t OP Ope ra ting C. SS 0 2A OP SS Secured Status D SS 0 i i 3A OP i AV Available MTR Fire Pump SR IB SS SR Standby Readiness DO Fire Pump SR 28 SS SHTDN Shutdown 38 SS S-SP Slow Speed, Cntet Val Purge Supp Fan A SS F-SP Fast Speed 8 SS ISOL isolated Cntet Vs1 as DW Purge Exh Fan .A SS NORM NoreaI . a B SS OOS Out of Service Drywell Purge Suppl Fan A SS CL Closed

                         .                                                                                                         B          SS                     -

OVRD Override AECTS Fan A 00S B OP f e 4

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PERRY NUCLEAR POWER PLANT 1984 EMERGENCY. PREPAREDNESS EXERCISE TIME: 1100 f RX WATER LEVEL RX PRESS RX POWER SUPR PL' TEMP-

                         -145       11      WR                    923       fig                            8            y                              136      'f 60-                                 1100-                                     120-                                     110                                       *
                                                                                                                                                                 /

45- 950- 90- 90-N 30- 800- 40- 70-e w ' 15- 650- 0 50 . . 0 500 -30 -20 -10 0 -30 -20 -10 3 '

                  -30   -20     -10    0                 -30    -20   -10        0                     Time (min)                                   Time (min)

Time (min) Time (min) ; l'

                                                                                                                                                              -                5 DW TEMP                                       CONTMT TEMP                            CONTMT PRESS                            SUPR PL LEVEL 160       'F                            110         'l                         0.8     PSIC                                 20.2      fJ              l 200-                                    110-                                     20-                                      19-150-                                    90-                                      15-                                         -

100- 70- 10- 18-50 50- 5- -

                  -30   -20     -10    0                 -30    -20   -10        0            0-                                     It Time (min)                              Time (min)                  -5                                             -30     -20     -10     0
                                                                                                 -30   -20   -10         0                          Time (min)

Time (min) 4

ne

                                     }-e da*-- P  **a.;M  9  %W        9-4=        s""+]'#,t-                    ' Ih p   9 g9 +- _   ea   e 74 J*e F                *4 9

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__r 1984 EMERGENCY PREPAREDNESS < 7.0E+1 mR/hr 4XER PANELS PERRY NUCLEAR POWE2 PLANT Main-Steam Line RAD c1.0E-1 mR/hr PANEL P604 Alarm Catet Vent Exh RAD Process' Radiation PANEL.P902 Alarm

2.5E+1 R/hr Gas.fcoo l Ofrges Pre-treatment. ,_,_.,,_, _

2.0E+2 cpm Common Airborne 2.0E+1 A Orfees Post-treatment8 2.0E+2 cpm RWB Vent Exh 2.2E+1 s . 3.0E+1 cpm FHB Vent Exh 2.0E+1 ~ A Eng Service Water 3.0E+1 cpm _,,_,,,,_ CR Vent Exh B A 6.0E+1 mR/hr Alarm . gem OC Carbon Bed Vault 5,5E+1 mR/hr ____.,_. B Common Process and Area 3.0E+1 UD-MH-73 East Liq PANEL 803 3.2E+1 _ UD-MH-70 West Liq mR/hr 3.5E+1 2.5E+0 Turb Bldg East _ NCC Heat HX 3.0E+1 2.5E+0 mR/hr _ I, r, Turb Bldg West Radweste to ESW 3.6Et1 / Radweste to Sewage ? PANEL P804 g Alarm . e Ces (cool 5 Airborne Radiation METEOR 0EOCICAL 16.5._ mph CONDITIONS l QJE.19 S Annulus Exh AB Cas t1 Wind Speed ,,,,,13 5 L_Q[E 2,7 +2 ,,__,,.__ 41 _*F L.QEt9 Wind Direction -0.95 'F Cntet Atm gJLil Temperature Drywell - HR (R/hr) Delta T AB Vent RJES +Q Exh OGB Vent OCB Vent - HR Q J [E+W _ OC Vent Pipe 6dEM 1Q U1 Plant Vent Q,,_0[E nJE U1 Plant Vent - HR QJg.tQ TB/ IIB Vent LA[tfl TB/HB Vent - HR 1.1 ST Packing Exh 6J[E+Q U2 Plant Vent 0.0 U2. Plant Vent - HR - G

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                                                                                                                                                                                                        - ,                    ~,,

i ' Time. ' "1100 s AREA

                                            -                 RADIATION MONITORS                                                                            '
                                                                                                                                              ~                   '

MR hr READING 5.0E+0 600 6 5.0E+0 IC LOCATION Cntet (620 6 g TAG # Personnel Air Lock Cntmt 7.0E+0 ' ('

 .D21NO30              CRD HCU West                                                                                  2.0E+0 ED21N040 64 7 8                                      7.0E+0 Cntmt                                                                 7.0E+0 D Area 116                   RWCU r Pool       Area ntet                  574 2.2E+0 1D21N070                               East                                     4                                     5 0E+0                              ,

1D21N080 Aux West 2.2E+0 f: ID21N110 Aux B 620 647 6 2.5E+0 1D21N120 Turb Rm East Cntet 1.0E+1 ,; ID21N130 CRD NCU East 605 6 ' 1D21N140 Turb Rm West 577 6 . Turb Bld TB 1D21N160 Area 9.0E+0 ID2XN170 Hotwell Pum 2.0E+1 ID21N180 568 6 Area TBC 602 6 OGB 2N Cnds F1tr Pm 1.6E-1 ID21N210 OG After Fitr Area 9.3E+0 l-654 6 D21N220 r a ikB 577 6 0 T3 [l ID CR CC Area h 5.0E+0 ID21N400 OG Hold U 4.0E+0 ID21N410 602 623 6 4.0E+0 6.0E+0 N6 RWB RVB 623 6 Process Sam le Rm , 599 9.0E+1 D21N270 4.4E+1 D21N280 .. IB 20 6 . Area IB 9.0E+0 FPCU F D IB -* D21N310 Fuel Prep Maration~Peol IB 574 6.0E+1 .. D21N320 nt Fuc Area 65 Cntet 623 6 6.0E+0 lJ D21N330 FPCU Cire PPortableRWB 23 6 3.0E+0 !- D21N420 Unit 1 DV actor Area 1.1E+1 1D21N340 Waste Com D21N380 SRW Drumming Area, _P.WB . ridge, Cntet . B ~ D21N370 1D21N090 _hServ Fuel latfor D21N390 e ai. t

                             . - +                  t-  . - -    .       3    -.5_    a    -      -     5.,.r,   ,                    _ . - _

       , . - -                   .     . - -   ,           -              .. ...}}

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