ML20065F877
| ML20065F877 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/19/1990 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20065F875 | List: |
| References | |
| NUDOCS 9010120051 | |
| Download: ML20065F877 (341) | |
Text
{{#Wiki_filter:1
;.e ; ' , :n .O 1
THE TOLED0' EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE MANUAL-September 19, 1990 O O 9010120051 9010o1 ADOCK 05000346 {DR PDC
9 4 s!
+
q The Toledo Edison Company . (/N/ ' i 7 Davis-Besse Nuclear Power Station i 1990 Emergency Preparedness Exercise n
-Porvard-j
~
i The Davis-Besse Nuclear.Pover. Station.(DBNPS) Emergency Plan describes the l nuclear emergency response capabilities-at DBNPS, including supportThe provided Plan by. : federal,-state and local-governments,>and private' organizations. -) describes a program-of continuous emergency preparedness, Lone' element of which ;
- is an annual evaluated' exercise.
-i The conduct of this. exercise provides the opportunity to implement the emergency- N plan and its associated procedures, and to activate and enable the evaluation of. !
major portions of the emergency response -organizations,' as required in 10 CFR 50.47.(b)(14) and Appendix E.> This: exercise therefore provides an opportunity.- to.further enhance emergency response;capabillties. , f j The 1990 exercise program provides for activation of.the DBNPS emergency response organization. ; This' Exercise Manual prov' ides.the basis for,the conduct of the exerciset; a.
. simulated radiological ~ incident at the Davis-Besse Nuclear Power Station, .:
located near Oak Harbor, Ohio. It is to be used as the control' mechanism for the-conduct and evaluation of the exercise, and consists'of two parts. .Part"1 l defines the scope and objectives of.the exercise,-and provides an. overview of V the activities. Part.2 includes the specific' sequence:of events-(l'.e. the' scenario) and pertinent data. ,It.'is therefore' subject to a limited, controlled distribution. . Only Exercise Controllers, Evaluators and. authorized observers-
~
vill receive advance-distribution of the information in'Part12. l In the development of an accident which is severe enough.cto adequately-tess.the ' emergency response capabilities of participating organizations, Lit.is necessary to postulate extremely unrealistic situations and multiple' failures of redundant reactor protection functions and systems. The objective of this exercise is to demonstrate the' ability of the partici-pating organizations to protect the public,'and appropriately respond to this- l highly improbable sequence of events. v I 5 l v h ' 1 . l 1 ['- ( l
\
j i i , i !U i
~_
1990-
' Davis-Besse Nuclear-Power Station e Emergency Preparedness: Exercise-1 SCENARIO DEVELOPMENT-COMMITTEE.
Chairman -D. J. Gordon'. Emergency-_ Preparedness
.A. Plant Operations .j;
- 1. 'V. G._Klippstien. Quality Assurance (SRO)
- 2. V. S. Schum- Emergency Preparedness'
- 3. T. L. Lehman 0perations-(SRO)- r Radiological Control j>
- l. C.-E. Upchurch Emergency _ Prepare'dness t
- 2. D. S. Jazviecki Radiological Control- rf
- 3. J. H. Priest Radiological Control. f Maintenance. .t
- 1. A. P. Vise Electrical
- 2. J. G. Hadison Hechanical _(
- 3. K. H. Rhubright I&C Dose Assessment
- 1. I. H. Borland Emergency Preparedness ,
Chemistry / PASS [
- 1. H. H. Alexich -Chemistry q Computer Support (DADS /SPDS/ MET) .
I l
- j
- 1. R. A. Bast Computer Group
. ..t
- h JPIC/ Corporate it
- 1. J. D. Basa Emergency Preparedness >[
- 2. K. L. Moore Emergency Preparedness- _
.t Security ,
i
- 1. C. L. Detray Security c
- 2. F. F. Pitzen Security ;
- 3. D. H. Ruff Emergency-Preparedness -i State and County Agencies {
- 1. C. R. DeVitz Emergency Preparedness
+ . - - -
_ t i
, , i
. J b
'("'g; TABLE OF CONTENTS FOR 1990' DRILL MANUALS' l v[\
" ~ '
);- ;
A- . ONSITE MANUAL PART I GENERAL INFORMATION' 1.0 SCOPE AND OBJECTIVES 1.1 Scope _ .- 1.2 . 0bjectives ' -! o 1.2.11 Toledo Edison c ; 2.0 EXERCISE INFORMATION ; t 2.1 Exercise Participants 2.2 Exer'cise Organizations .l 2.3 . Emergency Response Facilities l 2.4 Exercise Conducts 2.5 Precautions and Limitations- l 2.6- Evaluation and Critique l ; l
3.0 REFERENCES
/ ABBREVIATIONS / DEFINITIONS .;
3.1 References 3.2 Abbreviations } 3.3 Definitions , () 4.0 CONTROLLER / EVALUATOR INFORMATION 5.0 SCHEDULE OF EVENTS ., t PART II CONTROLLED INFORMATION : 6.0 EXERCISE SCENARIO l 6.1 Narrative. Summary- , 6.2 Initial Conditions : 6.2.1 Close of Business 9/18/90-6.2.2 Start of Exercise-9/19/90 , 6.3 Onsite Sequence of Events 7.0 STATION CUE CARDS AND PLANT DATA SHEETS i 8.0 STATION RADIOLOGICAL DATA'AND-RADI0 CHEMISTRY DATA h l 8.1 In-plant Radiation Data'. , 8.2 Onsite (out of plant). Radiation Levels Table 8.1 Onsite Radiological _ Data 8.2 Inside Protected Area Downwind Readings t t g es y 9.0 0FFSITE RADIOLOGICAL DATA i
' 5,
" /
"Nothing needed for this exercise. All data vill be real time and as found."
s >
,7
Xj. , j; I:5 ) lI
, l si 1990 Davis-Besse Nuclear Power Stations ,
i Drill / Exercise Authorization
- t Coversheet .
' Drill / Exercise
Title:
1990 Evaluated Exercise; Date of Conduct: September 19,-1990. Time of Conduct: 0830 1 J' Drill / Exercise Lead Controllers- D. Gordon i Approved: 'b(h Osa e $ 40 = 9/ 06 : Supervis'or J On te'EmerFency Preparedness ' Dhte/ Time ;
' Approved: -
N 5-/o-fo /eco
.Date/ Time ';
I l Manager - Kaergency g edness Approved: ' 0 //2/ / /N
-P4n Manager Date/ Time Approved:
Vice President, Nuclea F
-) *'
sDate/ Time 4 L . L. i 1 s
-v s
O' 1 4
/
'f 1
14- . , , - - . , ,. - . _ . . . .- , _ _ . - _ . , _ , , , . . . . . . - - . '.
e-. i t DRILL / EXERCISE SCENARIO OBJECTIVE CHECK SHEET
. l. Drill'/ Exercise Titles 1990 Evaluated Exercise 2.- Time Frames
- a. ' Season (Circle one)
Vinter Spring -Summer b.- Period of the week (Circle one).
@ Veekend Boliday
- c. On what shift shall the drill begin-(Circle one)
(8 am -5B 6 pm - midnight midnight -.6 am
- d. . Projected Drill / Exercise date' 09 / 19 / 90 e.- The drill vill be-(Circle one)
Unannounced
'f. Date of last similar Drill / Exercise ' 08 / / :- 90
- g. Real time span of Drill- "5 hours,. days
- h. . Drill / Exercise time frame 5 hours,. days
- 3. Maximum Level of Classification Emergency:
- a. Classifications-achieved during the Drill / Exercise (Check one)
Unusual Event Alert-
/ Site Area Emergency General Emergency Not a Classifiable Event
- 4. Organization / Facility Involvement: 1
- a. Onsite
-Control Room Staff h/No TSC QNo
-___..--m
lh ap' ' Rj - -a ; i l a DRILL / EXERCISE SCENARIO 0BJECTIVE CHECK SHEET ( nt.)-
)
Onsite: _ (Cont.) g
]
ECC' &/No: }i - Site Security @ No { Fire Bri ade-F OSC hNo RTL-
@No -'
Public'Information h No '. CRER Organization' @No
- b. 0ffsite: !
Ottava County EOC. Yesh. 1 LLucas County E00 Yesh
-Evacuation host. county EOCs- Yesh j Ottava County Sherifi's Department Yesh .
.Lucas County Sheriff's-Department- Yes Carrol1~ Township Fire Department Yesh 8 State EOC Vorthington,Johio .Ye l Regional NRC Office QNo .. j State of Michigan
'Yesh-EmerJency Medical (St. Charles, Fremont, Magruder hospitals) Yesh Ambulance Yes@
- 5. Communications
- a. Do you desire to exercise the emergency communications ,
systems? hNo
- b. Do you desire to use the emergency paging. system? j hNo 80ttava and Lucas Counties will have limited play at their EOC's and may play '
their PIO's. The State of Ohio vill play their-Dose Assessment Function at'- l their EOC, send a representative ~to the DBNPS ECC and have aid staff at'the JPIC. . 9 y7 , .
- e. e. p- 9 ,y- .---9-9
. +=e-- e--1 y
' c q
Jk s 1 ( DRILL / EXERCISE.SCENARIOOBJECTIVEjCHECKSHEET(Cont.)I k
- b Communication ' '(Cont.) ]
c.- Should a news bulletin be prepared?- hNo ' , 1
- d. 'Do you desireito activate the Joint Public Information Center?-
- hNoi ,
.l Do you. desire to exercise,the Computerized Automated:
e. Notification System (CANS)? h/No L
- f. Is a medical probles'to be involved?- Yesh,. ;
If yes, 1) Onsite response? 'Yes/No.
- 2) Offsite response? Yes/No-
- 3) Victim (s) injury (ies) i l .
O , l. V 4) Is the victim contaminated? Yes/No l
- g. If yes is answered for f.2)'above, describe' involvement.of offsite organization. 3 i
- h. Will the exercise-involve a' fire?- Yesh- ,
Onsite response? Yes/No. j
- 1) j
'2) Offsite response? .Yes/No-
.3) Describe involvement of responder.
..i f
O u i I 1 1
s t, t l. i di *
' DRILL / EXERCISE ;SCENARI0'.0BJECTIVE ' SHEET! (Cont . )- l 5.i.p
),
~ Communications !(cont.).
- 1. VillLthe Security, Force response'b'e-tested?. No !
1)' Sabotage / Bomb?- No.
- 2) Intruder? . Yes/N[
'3) Evacuation? hNo
- 4) Other ,
- 6. Radiolo'gical Releases
- a. Heteorological Capabilities:
- 1) Vill real-time meteorology be used? hNo.
2)- Vill simulated meteorology be used? -Yes/Ah ;
- 3) Will weather forecasting capability be r'equired?- h o- '
L
- b. Dose Assessment:
- 1) Vill dose projection be backed up by . field monitoring? hNo
- 2) Vill long-term dose projections:be calculated? Ye 1
- 3) Source of radioactive release 1
1
- c. Post-accident Sampling:
- 1) Vill post-accident sampling capabilities,be exercised? _ Yeh 2). If yes, to what extent? ,
'I
?
- 7. Approved: / f'/P97 Date Manager-[mergencyPreparedness
.o.. :1
-i !
, , i k i !
l'
'1990 Evaluated Exercise--
=
') ,
.i i
1 i i I 1 I i
^
I i 1 i ( I (- SECTION 1.0 :1 i i i I - SCOPE AND OBJECTIVES ^< l- l l 'O )
)
k i i l , i ( '. T j M I, b 1 fr j
; 2.* ;
'[!; M ( cp. i, i
,w ,
.)
~ , - - . - . - -l
1990 Evalu2tGd'Exorcis3~ 1-1, k 1.0 SCOPE AND OBJECTIVES' l.1 Scope-The.1990 Davis-Besse Emergency Preparedness " Evaluated Exercise", to-
=be conducted on September 19, 1990-vill test and provide the opportunity to evaluate the Onsite Davis-Besse Emergency Plan'and Emergency Plan-procedures. -Itcvill-also test-the emergency response.
organization's ability.to assess and-respond to emergency. conditions and take adequate actions to protect the health and' safety of:the public and station; personnel. The exercise vill demonstrate the q utilization of the Station's Emergency Responseforganization-" Team B" 4 personnel'. The exercise-vill involve activation and operation of ' q select l local emergency response organizations.. Whenever practical,. i the exercise incorporates provisions for "Pree Play";on.the part of
'the participants. ' Additionally selected-"real time" activities vill be conducted to allow-the repair teams the opportunity-:to provide service and repairs to: station equipment during the course of the exercise.- These " repairs" will allow the response organization to have an increased impact upon the-direction-~that the exercise' proceeds-as well as impacting the' completion ~of the' exercise activities. An NRC Region III-Site Team vill respond'and participate, with support from an NRC Region III' Base Team.-
Participation-in,this years Exercise vill also include.the use:of'the Alternate Joint Public Information: Center (JPIC),recently. relocated to O the Edison Club. The~JPIC will be activated and operated to verify. that this new location:is staffed and equipped to properly inform the media and the public'of the situation at Davis-Besse..
-i j
In the development ~of an accident sequence whichfis, severe enoughto adequately test the-emergency response capabilities'of--participating: j organizations,'it is necessary to_ postulate ~ extremely unrealistic' l situations-and multiple failures of: redundant. reactor protection ; functions and/ systems. ~l t i i
._ _ J
a 1990 Evaluated Ex3rcis3. ; 1-2
< t
-Section 1.2(Objectives; L 1.2.1' TOLEDO EDISON OBJECTIVES .l h
SEO. REF.
# -#- 0BJECTIVE i
01 A.1 CONDUCT AN EXERCISE OF THE DAVIS-BESSE NUCLEAR POVER STATION (DBNPS) EMERGENCY PLAN. 02 A.2- PROVIDE OPPORTUNITY FOR THE STATE, OTTAVA,.LUCAS COUNTIES, TO 1 PARTICIPATE IN~AN EXERCISE ANNUALLY.. l 03 A.3 PREPARE AN EXERCISE PACKAGE TO MEET MINIMUM STANDARDS OF THE i REFERENCE. j 04 A.4 CONDUCT A CRITIQUE OF THE EXERCISE. .l
?
05 A.5 ESTABLISH MEANS TO ENSURE COMPLETION OF CORRECTIVE ACTIONS. 06 A.9 CONDUCT THE EXERCISE IN VARIOUS VEATHER' CONDITIONS (DURING DIFFERENT SEASONS). I 07 B.1 DEMONSTRATE THE DIRECTION OF THE' EMERGENCY ORGANIZATION AND IMPLEMENTATION OF THE EMERGENCY PLAN AND EMERGENCY PLAN IMPLE- t HENTATION PROCEDURES.. [ 08 B.2 DEMONSTRATE THE TRANSFER OF THE EMERGENCY COORDINATOR DUTIES. 09 B.3 DEMONSTRATE THE ABILITY FOR TIMELY ACTIVATION AND STAFFING OF THE' ' EMERGENCY' FACILITIES. 10 B.4 DEMONSTRATE THE ABILITY TO CONTROL ACCESS TO' EMERGENCY , FACILITIES. 1 11 B.5 DEMONSTRATE THE ABILITY OF. CORPORATE PERSONNEL T0' AUGMENT AND : SUPPORT THE PLANT' STAFF. r 12 B.8 DEMONSTRATE THE ABILITY TO REQUEST SUPPORT, AND UTILIZE FEDERAL ASSISTANCE. , 13 B.13 DEMONSTRATE THE CAPABILITY FOR STAFF AUGMENTATION IN A TIMELY ! MANNER. STAFF AUGMENTATION DRILL' REQUIREMENT. 14 C.1 DEMONSTRATE THE ABILITY TO ASSESS THE INCIDENT CONDITIONS. 15 C.2 - DEMONSTRATE THE ABILITY'TO RECOGNIZE EMERGENCY ACTION LEVELS (EAL'S) AND PROPERLY CLASSIFY THE INCIDENT. I' 16 D.1 DEMONSTRATE THE ABILITY TO NOTIFY KEY OFFICIALS IN THE EMERGENCY ORGANIZATIONS. (STATION, CORPORATE, STATE OF OHIO, OTTAVA COUNTY AND LUCAS COUNTY) VIA NOTIFICATION SYSTEM VITHIN 15 MINUTES OF , CLASSIFICATION. +
J, I 1990 Evaluatcd Ex rcis3= I-3 , l
-J Toledo Edison Objectives Continued SEO. : REF. - !
# # OBJECTIVE 17 D.2 DEMONSTRATE THE' ABILITY TO NOTIFY THE NRC OF ANY EMERGENCY CLASSIFICATION VITHIN ONE HOUR OF THE.0CCURRENCE.. l D.3 DEMONSTRATE THE CAPABILITY TO NOTIFY AND/OR ACTIVATE EMERGENCY 18 l
PERSONNEL IN EACH RESPONSE ORGANIZATION. i 19 D.4 DEMONSTRATE THE ABILITY T0 DEVELOP AND SEND- AN-INITIAL EMERGENCY ' MESSAGE FOR OFFSITE NOTIFICATION.
}
i 20 D.5 ' DEMONSTRATE THE ABILITY TO DEVELOP AND' SEND FOLLOV-UPIMESSAGES s FOR INFORMATION FOR.0FFSITE AUTHORITIES. DEMONSTRATE THE COMMUNICATIONS CAPABILITY'AMONG THE CONTROL ROOM, .I 21 D.6 ' TSC, AND.ECC,'AND AMONG DBNPS, STATE OF OHIO, OTTAVA AND LUCAS; . COUNTY EMERGENCY. OPERATIONS CENTERS-AND THE' FIELD' ASSESSMENT: f TEAMS, TO~ INCLUDE EVALUATION, OF THE: ABILITY TO' UNDERSTAND MESSAGE CONTENT (COMMUNICATION DRILL REQUIREMENT). ; 22 D.8 DEMONSTRATE THE ABILITY TO DEVELOP.A LEGITIMATE,' INFORMATIVE, AND CLEARLY UNDERSTOOD-MESSAGE T0 BE SENT-TO STATE,-AND COUNTY- ; i . OFFICIALS WHO MAKE DECISIONS TO ACTIVATE THE ALERT AND L NOTIFICATION SYSTEMS. :l l 23 D.11 DEMONSTRATE THE COMMUNICATIONS CAPABILITY FROM THE CONTROL ROOM, l: I TSC, ECC, VITH THE NRC HEADOUARTERS. 24 E.1 DEMONSTRATE THE METHODS AND TECHNIQUES FOR DETERMINING THE SOURCE TERM OF RELEASES OR POTENTIAL RELEASES;0F: RADIOACTIVE: MATERIAL WITHIN PLANT SYSTEMS.- 25 E.2 DEMONSTRATE THE METHODS AND TECHNIQUES FOR. DETERMINING THE MAGNI-TUDE OF THE RELEASES OF RADI0 ACTIVE MATERIALS' BASED ON PLANT l SYSTEM PARAMETERS <AND EFFLUENT MONITORS.i ,
.i' 26 E.3 DEMONSTRATE THE ABILITY TO ESTIMATE INTEGRATED DOSE'FROM' PRO-JECTED AND ACTUAL DOSE ~ RATES'AND TO COMPARE THESE ESTIMATES VITH THE PAG'S..
27 E.4 DEMONSTRATE THE ABILITY TO IMPLEMENT EXPOSURE GUIDELINES. 28 E.5 DEMONSTRATE THE ABILITY TO' CONTINU0USLY 'HONITOR AND CONTROL EMERGENCY VORKER EXPOSURE.
~
O
_1990 Ev01usted Ex3rcisa-
'1 Toledo Edison Objectives Continued- ;
' SEQ. REF.-
4 -# OBJECTIVE-29 E.7 DEMONSTRATE THE RESOURCES AND CAPABILITY FOR FIELD MONITORING VITHIN THE. PLUME' EXPOSURE EPZ.. 30 F.1 DEMONSTRATE THE ABILITY TO RECOMMEND PROTECTIVE ACTIONS TO~
- APPROPRIATE OFFSITE AUTHORITIESF BASES OF RECOMMENDATIONS TO INCLUDE CONSIDERATION 0F PROTECTION AFFORDED BY SHELTERING, AS
. VELL ' AS EVACUATION TIME' ESTIMATES. -
31 F.2- -DEMONSTRATE THE OPERATION OF THE JOINT PUBLIC INFORMATION CENTER' AND THE AVAILABILITY OF SPACE FOR THE MEDIA. - 32 F.3 DEMONSTRATE THE ABILITY:TO BRIEF THE. MEDIA IN A CLEAR, ACCURATE. AND TIMELY MANNER. 33 F.8 DEMONSTRATE THE ABILITY TO ACCOUNT FOR ALL INDIVIDUALS IN THE PROTECTIVE AREA VITHIN'30 MINUTES. 34 G.1 DEMONSTRATE PRELIMINARY DISCUSSIONS OF REENTRY AND RECOVERY CAPABILITIES AND AVAILABILITY 0F PROCEDURES. e
1990 Evolu; tad Exarcis3' 1-5 1.2.2 Region III' Exercise Objectives.
- a. . Demonstrate the' capability to promptly and adequately staff andi activate the Incident Response Center-(IRC)_vithout pres' elected players.
- b. Demonstrate the capability of the Site Team-to function.with'ai limited number of personne1~.
- c. Demonstrate the capability of: the. Site Team tof deploy to the licensee's facilities and become knowledgeable of the events in progress.:
-d. Demonstrate the. capability of the Base andJSite Teams-staffito adequately interface vith each other and-their counterparts.-
- e. Demonstrate the capability of the Base Team.to adequately direct, coordinate and communicate the NRC's response actions.
- f. Demonstrate the capability of=the Base Team management'to-effectively transfer command'and control to'the Site-Team.
- g. Demonstrate the capability of the Site Team-management to .
effectively prepare to receive, and receive' command and' control from the Base Team.
- h. Demonstrate the-capability of the Si.te Team'to adequately' direct, coordinate and communicate the NRC's response actions.
- i. Demonstrate the capability of the reactor safety, staff.to monitor and evaluate plant status-and to assess.the licensee's-evaluation.
- j. Demonstrate-the capability of protective measures-staff'to evaluate the needs for onsite and offsite protective actions and assess the licensee's onsite and offsite recommendations.
- k. Demonstrate-the capability of protective measures' staff to .
monitor the status of protective actions implemented by offsite' officials.
- 1. Demonstrate the capability of Site Team personnel to utilize dosimetry and to monitor their simulated exposures.
- m. Demonstrate the capability of the Safeguards Manager-to provide the licensee with adequate information regarding the composition and arrival time of the Site Team.
- n. Demonstrate the capability of the Base and Site Teams to issue~
accurate and timely Status Summary reports.
- o. Demonstrate the capability of Region III exercise participants to critique their performances.
I
'I
-1990 Evaluated. Exercise 1
i I l I
-4 lI
,s SECTION 2.0'. -
EXERCISE INFORMATION. , j. l
.l ,
?
s i 1
' i, s
+
s
)
?
a 5 y F f a b
-t**e -
v- eer +-,-e e- == -- ***->- n---- e , ,--, a - e ,.e-wt--- +- +- - - - --t= - -
---*---en=--- r--vt- 4-- -' e-e* -w-- =***v.=-w s-
& y .>
el)
~ 1990 Evaluated ExircisM 1
i. D 2.0. EXERCISE INFORMATION-dM . 2.l' Exercise Participants The participants in.the Exercise-vill include the following groupsi. ; 2.1.1 The Toledo Edison Company , l '. Control Room Staff (CR) ; I
- 2. Technical Support Center (TSC)
- 3. Operations Support Center-(OSC).
t
- 4. -Emergency. Control. Center;(ECC) :;
.l 5.- Dose Assessment Center (DAC)-
'+
- 6. Radiological Testing Lab (RTL) .
.?
- 7. Radiation Monitoring Teams:(RMTs)
- 8. Joint Public Information Center.(JPIC)' l 2.2 Exercise Organization ,
9 O
\
The organization for this Exercise vill cons'ist'of the' Exercise Coor-- dinators, the Controllers, the Evaluators, the Players, and the observers, as,follows: l . L 2.2.1 The Exercise Coordinator is= responsible'for a' successful exercise,,and will-coordinate-all Exercise preparations. '. Subsequent to the conduct-of-the' exercise, he. vill coordi- > nate the preparation of a consolidated evaluation package, a and prepare and follow up on the corrective.' actions recommended as a result of the evaluation andJeritique. 2.2.2 The Lead Exercise Controller is responsible 1 for the safe , conduct of the exercise. The Lead Controller vill coordi- ! nate the resolution of any. scenario-related~ inter-facility questions, and ensure that the. conduct of'the exercise does ; not adversely impact the operation of the Station. , 2.2.3 controllers are personnel selected to perform functions as follows:- ,
~
- 1. A Lead Facility Controller is assigned to each emer-gency response facility. The Lead Facility Controller '
is responsible for all Controller, Evaluator, and Observer activities in that facility and, as, appropriate, its associated teams. Controllers.for teams or subgroups of a' facility report to the Lead , Facility Controller.
r
'1990 Evaluatcd Ex rcis3L 2 2. The Controllers vill deliver " Cue Cards" to designated.
players at specified-times and' places during the . exercise,' including. contingency messages.as required to= keep the exercise moving according_to the scenario. Controllers vill also observe the participants'at their assigned locations,'and prepare an evaluation.- Con-
-trollers vill' submit vritten evaluations to the Lead Facility Controllers, who' vill summarize all~ comments-for submittal to the Lead' Exercise Controller.- Con-trollers are-provided with instructions and evaluation' forms in Section 4.0 ofLthis manual.
3, All Controllers vill act as Evaluators, as described! below,'and vill be identified ~as Controllers by wearing-- red arm bands.. 2.2.4 Evaluators are personnel who are assigned to judge -the effectiveness of participating organizations, personnel,land-activities. Evaluators vill record their-observations using-Lthe evaluation forms provided and make recommendations-toi the' Lead-Facility Controller. They vill evaluate performance on the basis of standards or requirements contained in;the; Emergency Plan,-Implementing Procedures,. exercise messages,1and appropriate evaluation criteria.- Toledo Edison Evaluators vill be identified by vearing red arm bands. NRC Evaluators will;beiissued yellow arm bands. 2.2.5 Players include all personnel-assigned-to perform emergency'. functions as' described in the Emergency Plan 1and procedures. Players will beLidentified by wearing blue arm bands. 2.2.6 Observers from Toledo Edison Company.and other. organizations. may be authorized, on a limited basis,1to-participate-in=the a exercise for the purpose of observing exercise activity:forr personal education. Onsite Observers vill report initially to the DBNPS Emergency Preparedness Manager.for credential review and authorized admittance. They. vill be provided with orientation information and appropriate exercise publi-cations. Onsite Observers vill-be identified by'vearing, green arm bands. 0ffsite observers will report to the' Lead Facility Controller for'the respective facility and vill be- < identified by wearing green arm bands. Hequests to participate as an Observer should be made in triting and contain the'0bserver's full name, home address aad phone number, and. organizational affiliation.. Requests to 9articipate as Onsite Observers must be submitted to the DBNF3 Emergency Preparedness Manager no later than one week before the exerd me.- O
a i :I t
.;, >m; y '
5' t
, 1990~ Evaluated Ex3rcisa l i
' 2-3 i
.Y ^
{
. 2.3 Emergency Response Facilitles {
..- l During the Exercise, the following facilities vill be, activated to, 'J manage," assess, and support emergency response activities.' ,i 2.3.1 Onsite Facilities '
N
~
The Toledo Edison Company emergency response facilities are:
- 1. Control Room (CTRM)_ ,
- The DBNPS Control Room, located on the 623' elevation '
of the Auxiliary Building,~is the facility from which' the routine operation.of the planttis conducted.- 1 During abnormal.or: emergency conditions, whenithe- l Emergency Plan is implemented, the Shift-Supervisor is ' given additional responsibilities as the' Emergency . Director; In this capacity. he is responsible for the- ; coordination of the' Toledo Edison /DBNPS response:to the
-emergency _until relieved. The. initial response to this scenario, and any-emergency. condition,=is' managed by' the Operating Shitt.Crev in-the Control Room.. Once.the Shift Supervisor is relieved of the responsibilities'of' -
Emergency Director,,the Operating Shift Crev retains responsibility:for operation of plant systems and equipment.' , I 2. Technical Support' Center,(TSC)'
- t When emergency' conditions escalate .to an Alert: status :
or higher, coordination.of=the operations aspects of the emergency response vill-shift'from the Control Room to-the=TSC, located in=the Davis-Besse Administration Building.- The primary function of the TSC is to support an organization that-provides technical: ; assistance'to Station' personnel during emergency condi-tions. .The TSC.provides-direct voice.and data communications contact-vith the Corporate Emergency-
~
Response (CER) arganization. . Control Room instrumen- 4 tation.can be observed using closed-circuit television: (CCTV):from the TSC. The TSC also contains the DADS (Data Acquisition and Display System)(and the SPDS (Safety Parameter Display System) to enable.the TSC staff to acquire plant data in support-of technical evaluations needed-to mitigate emergency' conditions and-
-recovery operations.
l The TSC contains work space for up to 25 people. . 9 A " Satellite TSC" immediately adjacent to the Control ! Room, provides work space for the Emergency Assistant Plant-Hanager. (This> location allows better coordina-tion of the emergency' response functions by being U)[ ,- closer to problems needing attention. R 3 ! P m E
E < [ y ;e
-1990 Evaluated Exorcisr 4 ! 2 3, I0perations Supporticenter (OSC); -
'The OSC, is located in the:second floor lunchroom of; the Personnel Shop Facility._(PSF). !It provides a location for assembly and coordination of emergency-response teams'during an emergency. The.OSC'is activated at Alert or higher emergency, conditions,'and may be activated for^an_ Unusual EventiatLthe discretion.
of the Shift Supervisor / Emergency Director. The purpose of the Operations' Support' Center'is to pro-vide a pool of skilled manpowerifrom which emergency-- response' teams are assembled-(e.gC First Aid,* Opera-tions,' Fire Brigade, Emergency Maintenance and Reentry teams). Also,-it provides an assembly area-for desig-nated plant personnel _who are not on shift.
- 4. Emergency Control Center.(ECC)
The~ECC,Elocated in the Davis-Besse Administration Building, is activated at Alert or higher emergency conditions. The ECC's primary function:is toLprovide a centralized. location for management'of protective action planning, and-continuous coordination and control of onsite and offsite emergency. activities'.
~
The ECC staff evaluates the impact =of' actual or poten- . tial radioactive releases, and provides management-assistance in the decision-making process to-protect-the public health and. safety. Recommendations to-State and County authorities are based on Station conditions-as well as. radiological and meteorological data. The-ECC-contains advanced' systems to establish _and maintain-communications with state,=-federal,land local offi-cials, and to enable coordination <and control of'Radia-tion Monitoring Teams (RMTs).- The ECC provides space for occupancy of at least-16 people.
- 5. Dose Assessment Center (DAC)
A section of the ECC-that controls _the. operation of the Field Radiation Monitoring to' gather.iradiation-data for evaluation of.the-impact of actual or potential radio-active releases'. Provides technical assistance-in the decision to protect the public health and safety. The Dose Assessment Center contains communication and com-puter equipment to contact RMT's and project radiation doses offsite. O 4
,e
,{
- 1990 Ev31uttsd Ex3rcisi 2-5; ;
; - 6. Radiological Testing Laboratory (RTL)' ,
b The RTL's primary function is to provide a location L ;;i near the ECC'and TSC for radiological analysis of lov level environmental samples. The RTL contains work > areas for 4 people and additional _ space allotted for.' a temporary occupancy by_ field personnel.1 Major- . equipment: components in'the RTL are designed to be> f easily. removable for' potential use'in the-field. !
- 7. Radiation Honitoring Team (RMTs)
-(
. Radiation Monitoring Teams.are' emergency responders ,
trained to monitor radiological _ conditions outside the Protected Area, and report these conditions to:the Dose: -l
-Assessment Center,for-evaluation.-
- 8. ~ Joint Public~.Information Center (JPIC)-
The Joint Public'Information Center (JPIC):istthe. . I emergency facility for coordinating news' releases and' I providing: joint briefings ~ media during an~ event at-
-Davis-Besse.< A' primary and.an alternate. location are
'available to support.this-function. -Toledo Edison-Company, state, local and' federal agencies represented i at the JPIC jointly prepare news information for -
- t -,
release to the public'via:the; news media.- Equipment- 1 i and work spaces-for.Public Information~0fficers_and- , their staf fs are provided to. support timely,communi- . cations on-plant status and emergency response actions.- JPIC facilities include newst briefing areas for;- ; l approxima.tely 200 electronic and: print media.represen-t tatives. TFacility? operations and administrative >
-support are coordinated'by Toledo Edison., JPIC: support is available for any plant emergency. However,- .
facility activation is mandatory at (and above)Lthe
' Alert-emergency classification level.; ,
1
-a. - Primary JPIC.
' The primary JPIC is located in the Energy Education Center..(EEC) at the Davis-Besse Administration Building.'
- b. Alternate:JPICl The alternate JPIC'is located in the Edison Club -
Auditorium,' 1036 River Road, Maumee, Ohio. L l O . q ~ ~ - - n , ,,sr ,---,ma a. ,- -, - . , , , ,
[ i y
+ .
u 1990 Evclu;t d Ex3rciod. t l I . !~
- 2 i i L !
i 2.4 Exercise Conduct, k 2.4.1 Overviev' g
- a. .
The: Exercise vill-simulate an abnormal incident at Davis -- LBesse which vill escalate.- The simulated' emergency will: # ; E then terminate and'then the Recovery Phase vill be- '
.i
'l initiated.
!i'b The conduct of the exercise vill demonstrate the. effective-nessLof participating organizations, personnel, and activi-, '
n ties in support cf the Emergency Plan and-associated pro ,
'cedures..
.c ,
i 2.4.2 " Actions / Emergency response actions during the simulated emergency. ! E vill include: -recognition and classification'of emergency- 1 L conditions; assessment of onsite/offsite radiological con- + sequences; alert / notification and mobil 2zation-of thef.emer-J , L gency-response organization; implementation of in-plantu , corrective actions; activation / operation lof emergency? response facilities and equipment;-preparation'of reports,3 l messages, and'recordkeeping; and recommendation of' b protective actions. . . o e ; 2.4.3 Communications -
~
The Exercise vill also demonstrate the effective:use of: communications systems.- . 3
-t 2.4.4 Players l
l The success of the exercise is largely dependent'uponjplayer -! reaction,. knowledge'of~the Emergency Plan and. objectives of. ; l the exercise. Initial conditions which vill'affectiplayer. action-or reaction vill be provided to'the' players at'the ; time the exercise begins. Most elements of:the. exercise : I vill be introduced through the use of " Cue Cards". ' Players ! are responsible for initiating actions-in accordance{vith ; l exercise instructions, responsibilities, and'pr.ocedures for , their particular duties. Each' Player vill advise his/her , Controller prior to performing emergency response = actions,. to ensure that-the Player is credited'for those actions. a { i
- . 4 O
1 -. . _. - -
n=
, LL' ,
C ,
, ,' y P
~a1 L 1990 Evalunted Ox2rciss!
l , 2 R 4 ! U, 7 : ,- l; > '1. ;The Control Room vill be the central' point forfdistri-bution of exercise cue; cards..andsis the key to- ) L
- ensuring that the' exercise is~on schedule. < Simulated' lJ plant parameters vill'be provided_to the_ Control Room '
,Joperators using plant' data'and status sheets.. The.
Control Room Operators are responsible for: relaying _ pertinent plant drill data to other emergency
. facilities. The Safety Parameter Display System (SPDS) j and=the TSC Plant. Status display will exhibit-specific parameters. SPDS' trends vill display _gradualLtrend; changes in plant parameters. The TSC will have? point'
-value-and group _ displays available to monitor the i
current plant status. A' redundant SPDS system vill 5 ' continue.to provide actual SPDS parameters and alarms. In the event of an actual' emergency ^resulting'inlthei l termination of:the: exercise,treal-time SPDS vill be-. L s restored to:the TSC vithin. minutes. The plant. computer
; vill not_be used for the exercise'.:
2.; In order to develop >a sequence that: exercises thet ; entire emergency response = organization, it is?necessary: to suppose incredible situations._ The Players must accept the-exercise messages as written.: Time shall-not be spent discussing why a situation could not< occur. Players shall-react as though it did. If- s [ corrective actions are: proposed.that would terminate the emergency, theyLshould be identified-to the Lead q Facility Controller, so:that he can acknowledge the- ; corrective actions,1 but; continueathe ^ scenario progress . j as designed. Players are expected to " free play".the ! scenario to the extent' practical. . Notifications of, and. contact vith supervisors,; plant management, and- ., offsite agencies will:be made~inLaccordance vith plant ' l procedures. 3 Players are reminded:not to be excessively concerned with the mechanics or cause of:the simulated malfunc-tions. This exercise is designed to, evaluate.the Emer-gency Plan, Implementing Procedures,L and Emergency Pre- - -; paredness Training. Programs not the~ probability, feasi- : bility, or detailed mechanics of the. simulated acci-. i dent.- Players should note any needed improvements to' Emergency Response Facilities _and. equipment--Emergency, , Procedures,~or Emergency Preparedness Training that t come to their attention during the exercise. . Players. ' shall. submit recommendations to the appropriate Con-troller at the; conclusion of the exercise, l L (T ;
-O 1
l l ! 1
- . - ~ , , - , , , _ . _ , - - - _ . , . . . . _ _ . _ _ - . . - _ :
+
1990 Esluntcd Ex:;rcisaf __2-8 2.5 Precautions and' Limitations-This section provides guidance on the conduct of this exercise. Prior-to initiation, a briefing l vill be held-to review;the exercise process-
-vith all controllers and Evaluators.
- 2. 5.1 - _Shouldi'at any time during'the, conduct of this exercise, an-actual emergency' situation arise,-all activities related to.-
-the exercise may be suspended by the Lead Exercise Control-ler. It,is the, responsibility of any Controller who becomes aware of an actual emergency;to suspend exercise activities in his/her immediate area,and to' inform the Lead Exercise:
Controller ~of the situation.t 'Upon notification of an actual emergency, the Lead Exercise, Controller shall' notify all? Lead Facility Controllers. rThe. Lead Exercise Controller ishall make a determination at that point whether to con-tinue, place a; temporary hold on, or_ terminate the. exercise. 2.5.2 Should, at any time during;the conduct of this exercise, a1 controller vitness any< participant undertake any action'.
-which would,-in the opinion of the. controller, place ~either:
an individual or a component in an unsafe condition, the controller:is responsible for intervening-and. terminating the_ unsafe, activity immediately.- Upon> termination of the activity, the controller is responsible'for contacting the-
-Lead Exercise Controller and informing:him ofithe situation.' .
The Lead-Exercise Controller shall make a determination at . that-point whether to-continue, place aitemporary hold on, or terminate-the exercise. 2.5.3 . Manipulation ofcany plant _ operating systems,' valves', breakers, or controls, in response to this. exercise,lis to be approved by the-Operating Shift _ Supervisor and Qualified-personnel only. 2.5.4 All telephone communications, radio: transmissions, and-public address announcements related>to'the exercise shall begin and end with'the statement', "This is a drill".. Controllers are reminded not to " coach" Players, but shall ensure that exercise communications are clearly identified as,such, to. avoid confusion with other activities. Repeated failure to' identify'that communications are.part of_an exer-cise shall require intervention by a controller. 2.5.5 Care shall be taken to prevent any non-participating indivi-duals who may observe exercise activities from believing that an actual' emergency exists. Any controller who is-aware of an individual or-group of individuals'in the immediate vicinity who may have become alarmed or confused about the situation, should approach that individual.or-group and explain the nature of the exercise and its intent. O
a< , I 1990 Evolu3tcd Ex3rcis3 , l 2-9
, s f
G 'F '2.5.6' Any motor vehicle response.to.'this exercise, whether it bei f( ambulance, fire fighting equipment, police / security vehicles j or field monitoring teams, shall observe all normal motor- i vehicle operating:lavs including posted speed-limits, stop, ~ D lights / signs, one way streets, etcE-2.5.7 Should any onsite~ security actions be required in response, f i to this exercise, exercise participants are to cooperate as ! directed-by the Security Force. Security representatives- j
,are to be prudent.and tolerant-in;their actions.. 1 L.
2.5.8- While exeresse participants areito injectLas much realism-l i into the exe'.cise as-possible, the safety oftthe plant;and:
~
personnel shall r.ot be -jeopardized., 7 2.6 Evaluation and Critique The exercise vill be evaluated.by-individuals who have>expertiselin the activity-in their assignedilocation.- These Evaluators and Con-~ ' trollers vill' evaluate exercise performance ~on the basis of require- t
-ments. contained-in the Emergency Plan Implementing, Procedures, and: .
" Cue Cards". Evaluators and' Controllers shall: prepare evaluationt ' 1, forms and' provide recommendationsito the Lead Exercise Controller.-
After the Exercise is-completed, the; Lead Exercise: Controller shall . conduct a post-exercise critique.. Deficiencies? in ' the. Emergency Plan,: , lV .A Implementing Procedures, the emergency.: preparedness ~ training program, facilities, equipment, and/or otheriareas shallsbe-identified through the critique process. .The~ deficiencies'shall be documented by-the,
' Lead Exercise' Controller and corrected by he t individuals i 1vho:have j
responsibility in the area of the. identified deficiency.,
~
The schedule for the critiques is included-in'Section 5.0. . , -d
- i
, e ) 3 r O
5
~ 1990 Evaluated Exercise.
l
\ l l
l a l- -t
- l l 1 i
1
'l
.I
. I I
f SECTION'3.0 l 1 REFERENCES, ABBREVIATIONS AND DEFINITIONS. j i i i i i i i
'?
' i 1
I I I l l 1 1 O
~-- _ _ . . . _ - _ _ . _ _ _ . _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _.
> "^ '
vi. , ,L*
. s L. - -q 1990 Ev0luatcd Exsrcisa" .
13-1 ~ .
')
-[L '3.1 References i 3.1.1- DBNPS Emergency Plan - Toledo Edison Company,s(Rev. . 13,-12/89); '
~3.1.2 DBNPS Emergency Plan Implementing. Procedures i
l- , 3.1.3 DBNPS Emergency-Plan Station Support Procedures. . 3.1.4 10 CFR 50.47; 50.54 and Appendix E ',l' L l
'3.1.5 DBNPS Radiation Protection Manual' :j 3.1.6 DBNPS, Unit 1,' Technical Specifications- [
i
~
3.1. 7 - DBNPS Piping and Instrumentation Drawingst 3.1.8 Toledo Edison ~ Corporate Emergency Response.(CER) Plan 3.1.9 Toledo Edison Corporate Emergency Response' Plan-(CER) Implementing Procedures ..; 3.2 List of Abbreviations' ; AFP Auxiliary Feed!(Water): Pumpi .; ALARA- As Lov As. Reasonably Achievable ARM Area Radiation Monitor) 2: ARTS Anticipatory Reactor Trip System (O\,._ l ATHOS Atmosphere ATVS Anticipated Transient Vithout Scram AUX ' Auxiliary AVG Average BAAT Boric Acid Addition Tank ' BKWSH Back Vash BRKR Electrical Circuit Breaker , BVST Borated Vater Storage Tank' CAM Continuous Air Monitor _ CANS Computerized Automated Notification-System- ) CAS . Central Alarm Station: CCTV Closed Circuit Television 1 CCV Component Cooling' Water System' i CER- Toledo Edison Corporate Emergency Response Organization. CFT Reactor Core Flood Tank i CFR- Code of Federal Regulations
- CNDS Condensate System COND Condenser CPM Counts Per Minute ;
CS- Containment. Spray System 1 CST- Condensate Storage Tank l CT Circulating Vater System l CTHT Reactor Containment Building j CTRM Control Room i
~ DADS Data Acquisition and Display System l DBAB Davis-Besse Administrative Building 1 A DBNPS Davis-Besse Nuclear Power Station i DEI Dose Equivalent Iodine i
l
-b 1990 Evaluated Ex;rcice I 3-2 j i
DEMIN, Dominera11rer . i DH Decay Heat Removal System i DISCH. Discharge DP Differential Pressure -l DVS Demineralize Vater System EAL Emergency Action Level. ECC Emergency Control Center , EDG Emergency Diesel Generator - EEC Energy Education Center EFP~ Emergency Feed Vater Pump i EMA Emergency Management Agency )
- EOC Emergency Operations Center ;
EOF Emergency Operations Facility
.EPZ Emergency Planning Zone j EVAL Evaluated ,
FAT First Aid Team , FEMA Federal Emergency Management Agency , FT Feet ; FV Feed Vater GPM Gallons Per Minute HDR Header : HLCVT High Level Cooling Vater Tank HPI High Pressure Injection System ! HVAC Heating Ventilation and Air Conditioning System !
- HX Heat Exchanger l l
I&C Instrument and Control Department , IN Inch -
?
INST Instrument ; j JPIC Joint Public Information Center - KI Potassium Iodide LP Low Pressure ! LVL Level ; MISC Miscellaneous-MSIV Main Steam Isolation Valve 6 MTR Motor :, MU Makeup System i l NI Nuclear Instrumentation i NRC Nuclear Regulatory Commission -! OTSG Once Through Steam Generator 00S Out of Service OSC Operations Support Center PA Public Address System ; PASS Post Accident Sampling System t l l PC Protective Clothing PI Pressure Indication PHP Pump ' PORV Pressurizer Power Operated Relief Valve PPF Personnel Processing Facility . PR Public Relations ! PSF Personnel Shop Facility ? PSIA Pounds Per Square Inch Absolute 3 PSIG Pounds Per Square Inch Gauge . PT Periodic Test PTS Pressurized Thermal Shock ! PVR Pressurized Vater Reactor l f
.i , , , ~ . ~ . _ . - -- -.- -
. . . . . +
3 1990 Evaluated Ex rcise 3-3 j l I PVST Primary Vater Storage Tank , i 1 PER Pressuriser RCA Radiologically controlled Area RC Radiological Controls ! RCP Reactor Coolant Pump RCS Reactor Coolant System RE Fixed Radiation Instrument RLF Relief Valve ' RH Radiation Monitor RNT Radiation Monitoring Team RTL Radiological Testing Laboratory ' Rx Reactor ! SAS Secondary Alarm System r SFP Spent Fuel Pool ! SFAS Safety Features Actuation System
- SFRCS Steam and Feed Vater Rupture Control System
$JAE- Steam Jet Air Ejector SPDS Safety Parameter Display System '.
SPF Spent Fuel SRST Spent Resin Storage Tank , ST Surveillance Test [ SV Service Water System SYS System. i Tc Reactor Coolant System Cold Leg Temperature ' 1 TC Thermal Couple TDG Total Dissolved Geses Th Reactor Coolant System Hot Leg Temperature O-TPCV Turbine Plant Cooling Vater ' TRBL Trouble TSC Technical Support Center V0H Volt Ohm Meter VGST Vaste Gas Storage Tank VK Veek VR Vide Range Instrument VTR Vater XPER Transfer XMIT Transmit i b i i I 1 i 6
- . . . . . . - . _ o . _ , _ ,_. y. ..y.,_ _ _ .. , _ . - , ,_
i 1990 Evaluated'Exircise j lX' 3-4 ! l 3.3 Definitions . ,, 3.3.1 ALERT: The level of emergency classification which indicates ! ' that events are in progress or have occurred which involve an. j actual or potential substantial degradation of the level of : safety of the plant.- l 3.3.2 ANTICIPATED TRANSIENT VITHOUT SCRAM (ATVS): Failure of the- ;
~
F reactor control rods to insert into the core upon a scram signal from the Reactor Protection System or the failure of said system ' to initiate a SCRAM when Reactor Protection System trip limits have been exceeded. 3.3.3 ASSESSMENT ACTIONS: Those actions taken during or after an ; accident to obtain and process information that is necessary to ! ' make decisions to implement specific emergency measures. l 9 L 3.3.4 CONTROL ROOM (CTRM): The principle onsite location from which ; e the reactor is controlled and from which emergency control-is- l
- initially exercised. The CTRM is located on the 623' elevation' L
of the Auxiliary Building. l
3.3.5 CONTROLLER
A member of the Exercise control group, assigned to t one or more activities or functions for the purpose of keeping the action going according to a scenario, resolving scenario dis- , crepancies, and supervising the actions of the players. l 3.3.6 CORRECTIVE ACTIONS: Those emergency measures taken to improve or . terminate an emergency situation. !
3.3.7 DECONTAMINATION
The process by which the body or an object is relieved of radioactive substances (contamination).' ; 3.3.8 DOSE ASSESSMENT: The process of estimating the amount of radia- { l tion a person vill potentially receive as a result of exposure to l a radiological release. : l
3.3.9 DRILL
A supervised event aimed at evaluating, developing, and j I maintaining skills in a particular operation. 3.3.10 EMERGENCY ACTION LEVELS (EALs) - Radiological dose rates; speci-fic contamination levels or airborne, waterborne, or surface-deposited concentrations of radioactivity or specific plant con- ! ditions that may be used as thresholds for initiating specific l emergency measures. l l 3.3.11 EMERGENCY CONTROL CENTER (ECC): The Toledo Edison emergency t response facility from which overall direction and control are i exercised for emergencies at DBNPS. The facility also provides a ; i central point of contact for communications and external (non- l Toledo Edison) organizations, and is fully activated for emer- .! gencies classified as an Alert or higher. ; Oi 1
'1 1990 Evaluated Ex rcis] ;
3-5 ; 3.3.12 EMERGENCY OPERATIONS CENTER (EOC): An emergency response faci- ! lity from which government officials exercise direction and con-trol. The EOCs are located as follovst ! Ottava County: Basement of the Ottava County Courthouse ; Madison Ave. ; Port Clinton, Ohio , Lucas County Subbasement of the Lucas County Correction
- Facility ,
1622 Spielbush Ave. Toledo, Ohio State of Ohio Basement of the Robert B. Beightlet Armory 2825 Vest Granville Rd. > Vorthington, Ohio l
. l State of Michigan: Emergency Management Division ,
Suite 300 j 3005 Vashington Square Lansing, Michigan 48913 l 3.3.13 EMERGENCY PLANNING ZONES (EPZs): The land areas encompassed within approximately 10 and 50 mile radii of the DBNPS, in which j protective actions may be necessary to protect the public in the event of a nuclear plant accident. The 10 mile zone is referred j O to as the Plume Exposure EPZ: the 50 mile zone is termed the , l b Ingestion Exposure EPZ (IPZ). ! 3.3.14 EMERGENCY RESPONSE FACILITY: Any of several onsite and offsite l' l centers which are activated to coordinate emergency actions. ' l Included in this category are the control Room, Technical Support ' Center, Operations Support Center, Emergency Control Center, Joint Public Information Center, and State and local Emergency Operations Centers. '
.i 3.3.15 EVALUATOR: A member of the exercise evaluation group, assigned to one or more activities or functions for the purpose of evalu-ating and making recommendations for. improvement. An evaluator !
may serve in a dual capacity as both a Controller and Evaluator. , 3.3.16 EXCLUSION AREA: The area surrounding the DBNPS in which the - Toledo Edison Company has the authority to determine all activi-ties including exclusion or removal of persons and property from 'I the area during accident conditions.. l 3.3.17 EXERCISE: An event which tests the overall functions and capa- ;i bilities of organizations involved in responding to an emergency. ; situation. An exercise vill usually simulate an emergency that -! results in offsite radiological releases which require response ' by offsite authorities. -l l v . t I
- _ . . - - , , . . . . , . - .--.. . _ . _ , _ _ . ._ . _ . . . , . , __ - . . _ ~ _s
1 I ,
-1990 Evaluated Ex rcis3 3-6~
i P 3.3.18 GENERAL EMERGENCY: The most severe level of emergency classifi- l cation which indicates that events are in progress or have ! f occurred which involve actual or imminent. substantial core degradation or melting with potential for' loss of containment integrity. Release of radioactive material can be reasonably i expected to exceed PAG exposure levels offsite. j 3.3.19 INGESTION PATHVAY: The exposure mode for which the zone of con-cern encompasses an area of approximately 50 mile radius around t
-DBNPS. The principle exposure in this area vould be from inges- ;
tion of contaminated water or foods; such as milk or fresh vege- ; tables. The period of potential exposure could range in length from hours to months. l 3.3.20 JOINT PUBLIC INFORMATION CENTER (JPIC):- An emergency response ! l facility, located in the Davis-Besse Administration Building, ; which is staffed by Toledo Edison Company, local, State, NRC and t FEMA officials. The JPIC provides a forum and point of contact > for a coordinated release of news and information to he news i media, general public, Toledo Edison Company employees and the l special interest groups. 3.3.21 OBSERVER: Any individual'who is authorized to observe the Exer-cise, but is not authorized to interact with the players.- ; 3.3.22 0FFSITE: All land and water areas outside the Owner-Controlled ! Area fence surrounding the DBNPS. : i i 3.3.23 ONSITE: All Ir.nd and water areas within the Ovner-Controlled Area surrounding the DBNPS. ( 3.3.24 OPERATIONS SUPPORT CENTER (OSC): An onsite emergency response , facility which provides a location where emergency response teams can be assembled and coordinated during-an emergency. . 3.3.25 OVNER-CONTROLLED AREA: The area around the DBNPS that is owned / j and to which the access controlled, by the Toledo Edison Company. 3.3.26 PARTICIPANT: An individual who has some part in the Exercise, ; whether as an Evaluator, Controller, Player or Observer. ! 3.3.27 PLAYERS: All individuals (DBNPS, Toledo Edison Company person- f nel, and individuals from offsite organizations and agencies) who - are assigned to perform functions of the emergency response organization, as described in the appropriate Emergency Plan and ! Emergency Plan Implementing Procedutes. 3.3.28 PLUME EXPOSURE PATHVAY: The exposure mode for which the zone of ; l concern encompasses an area of approximately a 10 mile radius - around DBNPS. The principle exposure sources in this area are !
- 1) whole body external exposure to gamma radiation from the plume and deposited material, and 2) inhalation exposure from the passing radioactive plume. The period of potential exposure l could range from hours to days. ,
i i F
1990 Evaluated Ex;rcis] .I 3-7 w I
/
3.3.29 POPULATION AT RISK Those persons for whom protective actions ! vould be taken. 3.3.30 PROTECTED AREA: The area within the Site Boundary encompassed by physical barriers and to which access is controlled for security j purpcses. l 3.3.31 PROTECTIVE ACTION: Those' emergency measures taken after an acci-dent or an uncontrolled release of radioactive materials has occurred, for the purpose of preventing or minimizing radiologi-cal exposures to personnel that vould otherwise occur. ; i 3.3.32 PROTECTIVE ACTION GUIDES (PAGs): Projected radiological doses to ' Individuals in the general population which warrant protective , action following a release of radioactive material. 3.3.33 RADI0 LOGICALLY CONTROLLED AREA (RCA): Any area in which the general area radiation level is equal to'or exceeds 0.25 mrom/hr or radioactive loose surface contamination is equal to or exceeds 1000 dpm/100 cm8 beta-gamma, or 20 dps/100 cm' alpha activity. A - general REP is required for entry to this type area.
; 3.3.34 RADIOLOGICAL MONITORING TEAMS (RMTs): Two-person teams respon- ,
sible for monitoring radiation levels in the environment and ~ collecting soil, air, vegetation, snow, and water samples for
- laboratory analysis.
d 3.3.35 SITE AREA EMERGENCY: The level of emergency classification which indicates that events are in progress or have occurred which
- involve actual or likely major failures of plant functions needed i for protection of the public. any releases of radioactive material are not expected to exceed Protection Action Guide (PAG) }
exposure levels, except within the Site Boundary. - 3.3.36 TECHNICAL SUPPORT CENTER (TSC): An onsite emergency response ' facility for use by technical and management personnel in support , of the command and control functions executed in the control Room. 3.3.37 UNUSUAL EVENT: The lowest level of emergency classification, ' which indicates that events are in progress or have occurred which indicate a potential degradation of the level of safety of ; the plant. ' O
i J t i l 1990 Evaluated Exercise ! i i . i. i ; i t I J i SECTION 4.0 : I CONTROLLER / EVALUATOR INFORMATION j P 6
.i f
9 s a D I i
]
- l. J l i
, i i-
)
1 l l l
1990 Evaluated Ex;rcis] 4-1 4.0 CONTROLLER AND EVALUATOR INSTRUCTIONS Each Controller and Evaluator should be familiar with'the following ;
- 1. The objectives of the exercise.
- 2. The assumptions and precautions.being taken.
- 3. The exercise scenario, including the initiating events and the expected course of action to be taken.
- 4. The various locations that vill be involved and the specific items to' ,
be observed at those locations.
- 5. The evaluation checklists provided herein. .;
4.1 Controller Instructions 4.1.1 Controllers shall position themselves at their assigned : locations a minimum of 30 minutes prior to the activation of i the facility for which they have responsibility. 4.1.2 controller communications shall be tested prior to exercise commencement. All watches and clocks shall be synchronized > vith the Lead Exercise Controller's as part of the communi . ; cations testing. O V 4.1.3 All controllers shall comply with instructions from the Lead
, i Exercise Controller. 'i 4.1.4 No cue cards shall be delivered out of sequence or other !
than as written unless specifically authorized by the Lead Exercise Controller. . 4.1.5 Cue cards controlling the progress of the scenario are noted i vith a number. Contingency cue cards are noted with a num- : ber followed by the letter "X" (e.g., 10X). Contingency cue
- cards are only delivered if certain conditions indicated on the card are met.
4.1.6 Data sheets shall be distributed only in the Control Room.- !,
- i. 4.1.7 C a rollers vill no_t,t provide information to the players ;
i regarding sce.srio progression or resolution of problems encountered in the course of the simulated emergency. i l Participants are expected to obtain information through ! their own organizations and exercise their own judgement in ! determining response actions and resolving problems. , 4.1.8 Some Players may insist that parts of the scenario are unrealistic. The Lead Controllers have the sole authority i to clarify any questions regarding scenario content. ! l i i
- . - _ - ,. _ ,. _ . . _ _ _ _....a. -_ . _ . . . _ . _ - _1 , . _ . . .
1990 Evaluated Ex;rcis] 4-2 4.2 Evaluator Instructions Each evaluator shall take detailed notes regarding the progress of the : exercise and the response of the Exercise participants at their ! assigned locations. Each evaluator should carefully note the arrival . and departure times of participants, the times when major activities t or milestones occur, and problem areas encountered. The standards below should be used by the controller / evaluator to i evaluate assigned areas pertaining to the. emergency response. A dual i purpose vill be served by this rating system. First, the capability ; of each facility or response area vill be evaluated, and second, the ! system vill provide a vehicle for' directing improvement. The rating l scale is as follows: ! f Satisfactory . Personnel and equipment generally performed as expec- I ted. Any errors noted vere not severe and could be corrected without l undue labor or expense. l Unsatisfactory - Personnel and equipment generally performed below i expectations,-and there was several significant deficiencies noted. , The area's ability to carry out its functions was diminished. j N/A - Not Applicable to the situation. f N/0 - Not Observed. . As appropriate, evaluator comments should consider the demonstration - ,, of the following facility and team evaluation elements: ' 4.2.1 Facility l
- 1. Accurate and timely determination of emergency action ,
levels, j
- 2. Timely activation and staffing for each emergency ;
action level, i
- 3. Familiarity of personnel with appropriate emergency l l procedures, duties and responsibilities. !
- 4. Timely notification of Toledo Edison, local, state and federal personnel / agencies (information updates performed). ,
i
- 5. Adequacy of internal information systems (e.g., message ,
handling, displays, status boards and maps). l
- 6. Properly controlled documentation and accurate, timely j record keeping. ;
- 7. Use of correct communications' procedures and I techniques.
1 l 4
.1 i
. _ . _ - . - - . ~ . _ _ - _ - _ _ - .
i 1990 Ev:1uated Ex;rcisa ) f 43 i O b/
- 8. Capability of facility managers to interface with per-sonnel and coordinate facility activities.
j
- 9. Consideration for personnel safety (e.g., exposure '
control).
- 10. Adequacy of interface between emergency response !
facilities.- ,
- 11. Adequacy of equipment and supplies. f
- 12. Timely initiation of onsite protective / corrective j actions.
s
- 13. Development of offsite protective action recommenda , i tions.
- 14. Radiological surveys and assessment of plant damage and l hazardous conditions performed. !
- 15. Timely requests for emergency support services.
- 16. Coordinated, accurate and timely dissemination of information to the news media.
4.2.2 Emergency Teams
- 1. Timely notification and activation.
- 2. Adequacy of staffing.
- 3. Familiarity with appropriate emergency procedures, i duties and responsibilities. !
- 4. Availability and utilization of proper equipment. >
- 5. Performance of contamination control / decontamination.
- 6. Proper interface with emergency support-personnel.
- 7. Use of correct communications instructions and techniques.
- 8. Adequacy of briefing sessions per the dispatch.
- 9. Direction and control by team leaders. *
- 10. Timely requests for additional assistance. '
l l 11. Coordination and interface between emergency response team members.
- 12. Proper interface with plant supervisory personnel.
1 1
..s .,,a--, e -g -
a __ , , , _ . , . _ , . , o.- , _ ,. , , - , ..c.. - n.,.w , c- , , ~-,--n.e y 7.-
1-i 1990 Evaluated Ex;rcico 4-4 i
- 13. Availability of reference documents.
- 14. Utilization of proper radiological control practices (e.g., access control, protective clothing, shielding, stay time). !
4 !
- 15. Assessment of radiological conditions. 1
- 16. . Timely and proper damage assessment.
- 17. Properly maintained records.
Evaluators will record their comments and prepare a written ; evaluation of the exercise. Evaluation forms vill be pro- ; vided to each evaluator for more specific evaluation i criteria. ! 4.2.3 Personnel Assignments i Figure 4.1 lists the personnel assignments for the onsite l controller organization. l 4.2.4 Evaluation Packages l The following evaluation packages vill be provided to the ; appropriate controller evaluators at the pre-exercise briefing j Control Room l
- l. Operations Support Center l
Repair Teams Technical Support Center l Emergency Control Center f Joint Public Information Center Dose Assessment Center ; I l Fire Brigade i ! First Aid Team i l . l -- Radiation Monitoring Teams ! 1 l Security ' l ' Radiological Testing Laboratory' e. x . . ..-., . - - - - . _. -.m._, ,_ ..m . . , ,_,_ y . .#.c.--y y
1990 Evaluated Ex;rciso l 4-5 .i I (3 i 4.2.5 Evaluation Process All evaluators shall maintain an exercise chronology, sini- .l lar in format to Attachment 4A. - This chronology shall be of- ; sufficient detail to enable subsequent completion.of the ! appropriate evaluation form. It should contain a synopsis. l of significant exercise events, actions taken (or not taken) . by players, questions noted, and positive as well as ness- 1 . tive assessments made by the evaluator. This chronological i record may be used to corroborate critique items that are ; questioned by participants. : i Each evaluator shall also complete an evaluation form for l the facility or function to.which they are assigned, i Each Lead Facility Controller shall de-brief the evaluators j in their facility and compile an Exercise Evaluation Report : Sheet (Attachment 48) for that facility. This report sheet l shall reflect an overall assessment of the-performance of l that facility, and of the five (5) specific categories. Significant weaknesses or deficiencies shall be itemised to ;
- ensure adequate follow-up attention is devoted to resolution. :
of tho' problem. Significant positive items shall be ' , included here as well. ! i The formal post-exercise critique shall be conducted by the i Lead Exercise Controller, with.each Lead Facility Controller : providing an evaluation of their facility. ! I
-i i
i I l i I l l l O !
., - - , + , , . _ , . , - - - , , . . . , , , , - , . .
1990 Evaluated'Ex rcisa 4-6 FIGURE 4.1 i EXERCISE CONTROLLER ASSIGNMENTS l CONTROL ROOM i
- J. J. Johnson Control Room Management i V. G. Klippstein Control Room Operator '
J. D. Rollins Control Room Data i OSC i i
- J. J. O'Neil OSC Management i L. R. Harder (RC) OSC RC Coordinator ,
C. E. Upchurch OSC Response Team ! D. S. Jasviecki (RC) OSC Response Team j A. P. Vise.(Elect) OSC Response Team
- K. H. Rhubright (I6C) OSC Response Team '
J. G. Madison (Mech) OSC Response Team , M. M. Alexich (Chem) OSC Response Team j J. M. Priest (RC) . OSC Response Team ,
'B. R. Zibung (RC) OSC Response Team j 1
ASSEMBLY AREA 5 - t r J. C. Troknya Assembly Area Coordinator : D. M. Behrens Assembly Area Coordinator '{ TSC
- V. M. Vatson TSC Management l J. R. Polyak Emergency RC Manager !
T. L. Lehman TSC Operations Engineer : i ECC ,j B. P. DeMaison Emergency Director , j P. J. Smith ~ CANS / Emergency Facility Services Manager- l
- I. M. Borland. ECC !
S. E. Gerhardstein ECC i M. J. Shell Dose Assessment i D. P. Ricci NRC Response RTL f i D. F. Isherwood (RMT) RMT j D. A.-Isley (RMT) RMT l J. M. Less (RMT) RMT l P. J. McCloskey (RMT) RMT I
- G. R. Ravn (RTL) RTL Coordinator l T. L. Steifel (RMT) RMT l
- Indicates Lead Facility Controller G.
1990 Evaluated Ex:rcisa. 4 . FIGURE 4.1 (continued) ' O~ EXERCISE CONTROLLER ASSIGNMENTS i SECLRITY ; R. L. Buehler DBAB Security !
- C. L. DeTray Security Lead l F. J. Pitzen PPF :
D. M. Ruff Rover . G. A. Skeel Emergency Security Manager i C. E. Voods Access Control i R. E. Meier CAS/PA i CONTROL CELL l J. M. Vetter Emergency Planning Advisor ! G. V. Anderson Emergency Preparedness Staff ; J. A. Harmon Emergency Preparedness Staff l P. V. Smith Nuclear Licensing l t JFIC * ; i P. F. Timmerman Technical Assistant '
- J. D. Basa
() K. L. Moore L. M. Kocik JPIC Nanager Corporate EP Advisor Media Relations Supervisor' j T. J. Myers JPIC Rover D. Treverso Company Spokesperson P. Harrison Public Concerns. . - D. M. Robedeau Audio / Visual Coordinator l i. OTERR8 D. J. Gordon PA Rover V. S. Schum DBAB Rover
?
I i
- Indicates Lead Facility Controller i i
1 i t I
-?
r . - ~ .
,r , ,. , - . - ~ - , . . . m.,,+1 .._,,. .. . . _ . .. . . _ . , _ _ . ,. . _ . . . . _ - . . , . _ . . . - - _,....m... .
- . . . . - - - - - - - . - - - - - - - ~ . - - - - - . ~ . . - . . - - . , - - - - - . - - - . - - . - - - - - . ~ ~ ~ . . . . ~ ~ . , , - s - . ~ . - -- r.-...+-~ .-- . ..a.,- .- . .n.-.-.. ~ - u.
t I I r 1 F k j. 5 8 t i f I I i SECTION 5.0 .
' i SCHEDULE OF EVENTS i i
t I i f i - l
)
k i 5 t t I i
-f a
F i i h i l l l l r h l l' i ,- .) h e I I t
) , . , , . . .. ---., . . , , - - . . . . . . . . . . - - . - . . , . - . . , , , ..______.,n., ...n,-,,, ., . , . .. - . . , . . . . . ,. , - . - - . , - , ...,..,,-..-.w..n,., .- , , , - - , , - -, . +
l 5-1 i
<~ -I Davis-Besse Nuclear Power Station
( 1990 Annual Emergency Preparedness Exercise . 1 Schedule of Heetings l l What ! Date/ Time Vhere I September 12, 1990 Energy Education Center Utility Controllers DBNPS Administration Building ~ Meeting 12:30 - 16:00-1 September 18, 1990 Energy Education Center Utility Controllers ' DBNPS Administration Buf1 ding Meeting 13:00 - 14:00 a September 18, 1990 Room 209 - 210 .NRC Briefing DBNPS Administration Building j 14:00 - 16:00 1 1 September 18, 1990 Energy Education Center . Utility Players Briefing ; 15:00 - 16:00 DBNPS Administration Building I September 19, 1990 All Facilities Exercise () All Day September 20, 1990 Energy Education Center Utility Controllers 08:00 - 12:00 DBNPS Administration Building Debriefing. t September 20, 1990 Energy Education Center Utility Player Critique 14:00 - 15:00 DBNPS Administration Building & L September 20, 1990 Energy Education Center NRC Critique l 15:00 - 16:00 DBNPS Administration Building .t l l i (_) e -
--e-e- . -~
e b 1990 Evaluated Ex3rcisa j 6-1. j 6.1 Narrative Summary I i The 1990 Emergency Preparedness Exercise is to be a 5-hour exercise with l limited offsite participation. The Nuclear Regulatory Commission vill be l participating with a partial site team from Region III. Ottava and Lucas l Counties and the State of 0hio vill have a limited' level of play. ! The scenario involves a steam generator-tube leak that requires a plant. i shutdown at a controlled rate. The leak will be within the High Pressure' j Injection System capability. The leak vill grow to a rupture 2 hours after - the start of the exercise. . At the onset of the rupture, one of the BCCS- l trains vill develop a short in its electrical switchgear causing a loss of ; i the entire train. This vill necessitate the Site Area Emergency classifi- l cation to be declared. There is to be no large scale offsite release ! during this exercise and the emergency level is not to be raised ~above a. Site Area Emergency. !
.i
, A complicating feature of the exercise vill be a distraught individual f causing some damage to plant equipment that results in the loss of station vent radiation monitoring. The individual vill then attempt to leave the ! Protected Area. Security's handling of this problem vill also be a part of this exercise. The damaged equipment vill require the use of alternate l l dose assessment capability. , 1 At the declaration of the Site Area Emergency a person who is working.in l the upender pit vill fall into the spent fuel pool. This problem' vill ' provide the opportunity to demonstrate the proper methods of dealing with O t both an externally and internally contaminated individual. l The plant vill be allowed to cool down~at its maximum rate with little interjection of additional exercise information. The players vill be expected to perform as many activities as possible in order to recover the' ; plant. : j Plant cooldown vill continue and the exercise vill be terminated after the ) objectives are met. Each facility vill conduct a. critique and restore the i facilities to their pre-exercise condition. Reentry and Recovery discus- l sions vill take place after the conclusion of the main portion of the j exercise with'the appropriate personnel in Rooms 209-210 of the Davis-Besse l Administrative Building. l l 1 I
-1 I
1 a
1990 Evaluated Ex:rciso i' 6-2 6.2' Initial Conditions i 1.. Plant:is in Mode 1 at 100% power by heat balance. -All systeas in I automatic.
- 2. Station Vent Monitor 4598 BA is Out of Service for Calibration by I60. j
- 3. 530 PPM Boron, 188 EPPD-1
~4. Plant Chemistry is as noted on Chemistry Sheet. I i
1 5. Work continues in the Uponder Pit of-'the Spent Puel-Pool. The j i hydraulic hoses to the upenders are being replaced. I i O! , I f d i 1
. O l
i 1990 Ev luated Ex3rcise 6-3 i 6.3 sequence of Events l T: Time Time l T -0030 0830 Control Roon staff and the Continuous Services ! Personnel receive pre-drill briefing and discuss ! initial plant conditions. Initial conditions are ; established. ., T -0015 0845 Exercise Commenced - Drill Announcement made. The first information of the leak is provided to the j Control Room staff. This is to ensure declaration'of :' the Alert in a timely manner. The Control Roon vill be prevented from declaring the Alert prior to 0900. T -0015 0845 Drill Code sent out on the pager system. T:-0010 0850 Security problem commences. A disgruntled worker smashes both station vent monitors, and then. leaves the ; area. The person working with him reports the damage to security and to the Control Room. l
\
T:0000 0900 Primary System Leak of approximately 60 spa occurs. Alert Declared - EAL 2. A.2 RCS Leak Rate >50 spa but GPI capacity. T:0000 0900 Protected Area Assembly commences and vill be conducted. l l T:0000 0900 VPF restricts site access to ERP personnel and ' l emergency equipment only. Gate closed for 5 minutes
- only. .
i T:0000 0900 il Steam Line Radiation Monitor Alare. f T:0005 0905 Plant shutdown commenced at a rate of approximately 2% per minute. .Several items causing a delay in shutdown vill be introduced. The time of shutdown is to be 1 approximately T:0200. Cue card issued to prevent a . more rapid cooldovn. ! T:0007 0907 Steam Jet- Air Ejector (SJAE) Radiation Monitor- Alarm. T:0015 0915 Assembled personnel vill be returned to work. On-shift l personnel begin to set up the OSC per HS-EP-02410, OSC l Activation and Response Procedure. T:0015 0915 Security should apprehend the individual who damaged [I the equipment before he gets outside of the Protected Area, and contact the Ottava County Sheriff to arrest i the individual. ' T:0015 0915 Offsite Notifications should be completed. J l
?
<f
,j y
P < 1990 Evaluated Ex;rcis3 l
.6-4 T Time Time -
T:0029 0929 Stop S/D at 450 MVe to take off $1 Main Feed Pump. Ol! l T0030 0930 NRC Site Team begins arriving. l l T 0030 0930 Ottava County Sheriff arrives on site (simulated) to- ; arrest the suspected saboteur. i T 0033 0933 Resumed S/D at 18 NVe/ Min (2%/ Min). ] ! T 0048 0948 on Lov Level Limits 926% (199 NVe) stopped' auto shutdown. i T 0050 0950 Emergency Response Facilities should be activated. : T:0106 2006 Trip Turbine, 15% power. i T 0112 1012 Pressuriser Low Level Alarm - lowering pressuriser- ! level in accordance with procedure. . l T:0115 1015 ottava County E00 should'be partially activated. Lucas !
. County will simulate and be available-for 4-vay phone !
messages only. , i T 0115 1015 Sheriff takes custody.of the disgruntled employee.- - T 0115 1015 Subareas 10 and 12 are closed by the counties (SIMULATED). Ol, ; T 0123 1023 SUR Inhibit Enable (Alarm) ! T:0130 1030 1% Reactor Power,' start Motor Driven Feed Pump. l Shutdown #2 Main Feed Pump. (Difference in feedvater i flow between #2'OTSG and'#1 OTSG indicating the leak in
#1). j.
T:0130 1030 Dispatch Radiation' Monitoring Teams to survey for a l radioactive plume. ' l T 0135 1035 Commence continuous rod insertion to bring the reactor j to hot shutdown. ; i T:0200 1100 A worker in the Spent Fuel Pool area falls into the I pool at-this time. The ingestion ~ problem vill be l conducted from this incident. The HP personnel vill j have an additional decontamination problem as the HP , tester assigned to the job is also contaminated. j T:0202 1102 Plant in hot shutdown vith a primary to secondary leak ) of approximately 60 'gpm. T:0205 1105 Primary leak rate increases to'385 gpa. Pressuriser level falls. When the level ~goes out the bottom of the Pressuriser the leak rate vill increase to 1400 spa. Start second Makeup Pump, shift suction to BVST. I 1 l
' 1990 Evaluated Ex:rcias I 6-5 !
T Time Time l T 0210 1110 Lose one train of ECCS due to an electrical problem ! which trips'the vital bus when the HPI pump is started. , Leak nov >HPI capacity. j i T:0210 1110 Site Area Emergency declared. EAL - 2.A.4 loss of j coolant accident greater than HPI. ; T:0210 1110 Protected Area Evacuation commences and vill be conducted. At the completion of Accountability all I personnel are to return to work in the Protected Area. ' owner Controlled Area Assembly vill be simulated. !
~!
T 0213 1113 Depressurize RCS to 2120 psi by shutting off I pressuriser heaters and opening the pressuriser spray ! valve. i T:0215 1115 Reactor trip (the control rods were previously ! inserted). 1 T10217 1117 #1 OTSG tube leak 01400 GPM,' shut Spray Valve. l T 0218 1118 Pressuriser level at- 0 inches,1650 psi, HPI flov - approximately 400 spa. ; T:0219 1119 SPAS level 2. O' T 0220 1120 141 Degrees /hr cooldown rate. "B" OTSG 1evel 200 ! , inches. - T:0222 1122 SFRCS high level #1 OTSG. l T10224 1124 91 OTSG'at 250" on SPRCS indication. T:0225 1125 Counties / State notified of SAE. No Protective Action i recommended. T:0228 1128 Steaming #2 OTSG to cooldown. Spraying Pressuriser to ' reduce RCS Pressure.. T 0230 1130 Stop 1-1 RCP. T:0230 1130 Simulate relocating Carroll Elementary School to i Vanguard. i T:0232 1132 Block 5FRCS, stop Spraying Pressurizer. T 0235 1135 Spraying to maintain RCS pressure less than 1000 psi. s T0239 1139 Throttled HPI flow for PTS considerations (250 gpm/- 1 nozzle). ! O j i _ . . . _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ . _ _ _. - J.
?
1990 Rvaluated Ex:rcise 6-6 l T: Time Time T:0241 1141 Steaming 42 OTSG to continue cooldown at 100 degrees / l hour. The plant operation is now totally procedure driven, , .there is_little reason for intercession by the Controller. Whatever action the operators and the ERO
. determine to be correct is acceptable.- If the ERO-decides to reclassify'from a Site Area Emergency to !
Alert during the exercise, it is acceptable. The ERO vill remain staffed until all objectives have been completed. -It is expected the total drill time vill be approximately 5-to 6 hours. _The Reentry / Recovery ; discussions that-are needed vill be allowed to occur in real time. The NRC response team should be heavily , involved in this activity. 1 T:0250 1150 Ottava County Prompt Notification Systen vill be [ SIllt! LATED activated. i I T10307 1207 Throttle HP1 to 150 gpa/nossle. T:0319 1219 Stopped RCP 2-1 and 1-2. RCP 2-2 running. l . T 0321 1221 Restore Letdown. ! T:0500 1400 Stop the Emergency Phase of the Exercise. T 0515 1415 Commence a 30-Minute critique and. restore facilities, f T:0545 1445 Commence Recovery / Reentry discussions. I 4 i i I l f r i Oi: I
7 7-1 (< DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. 1 SCENARIO NO. 1990 Evaluated Exercise TIME 08:30 l TO: Control Room Staff . T: -00/30 ; l ) i
~ '
****************************************************************************** 1 THIS IS A DRILL
, , I DO NOT initiate actions affecting normal plant operations. l t j ****************************************************************************** , INPORMATION: INITIAL CONDITIONS: 100% Power 958 MVe, by Heat Balance Makeup' Tank level 70 Normal Operating Pressure and Temperature 188 EFFD, 530. PPM Boron. ' Station Vent , s Monitor Monitor 4598 BA is Out of Service for Calibration bysI&C. .Vork is in ; r progress in the Upender Pit in the Spent Fuel Area. The hydraulic hoses are ' being replaced. The pit is drained. r l f 1 i I 6 t THIS IS A DRILL ! l( ****************************************************************************** t
i 4 7-2 I ; i DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 1 i I . TIME: 08:30- ! l TO: Control Room Controller l l T: -00/30 l ! ' ANTICIPATED RESPONSE: i None I I l l I INSTRUCTIONS: Provide this card to give the staff the initial conditions and answer any questions that are asked about the plant status. l i ' e;4 l h l i I d l I I I THIS IS A DRILL
****************************************************************************** g
i 7-3 CilEMICAL ANALYSES STATUS iew llave the Shif t Supervisor rev trol Room.
/ Analyst:rior to delivering to the Con ----- -~~~--
Duty Chemistry Supervisorand ~~- sign - - this status sheet s/ p TIME DATE l PRIMARY CllEMISTRY
/W) l TIME ,_8]tD
- --_ DATE _7/8 /D
- - LYS I S _ ppb
- BORON ANA foo ppm ... e, Boo _
2 _ l 0, < 6' RCS _ f1/ ppm 7 4 W _ ppm PZR C1~ _ 1100 ppm _ __ 4 o.ob _ ppm BWST PWST _43 _ ppm \_ _ F~ L i' _ I . (~ _ ppm
\ l 7./ _
BAAT 1-1 //,, S 00_ ppm _ / 1 l pil _ cc/Kg BAAT 1-2
//,,J yg ppm 37 H, _
fof ppm _ k _ _ _I to" _cc/Kg CWRT l-1 \ _ l N, _
/f/D _ ppm _ __
'/ / _cc/Kg CWRT 1-2 _ l TDG __
^
17 7//D.. ppm f CPT l-1 _ DEI _ t.f I-2 _ Ci/ml 2/fL_. ppm _ \ __ l Specific CPT 1-2 #. '/d 7 C1/ml Activity _/ffd_ ppm _ \1 STP Time 0800 Date
////94 COVER GAS ANALYSES NOTE:
H, 0, Ensure all stated limits on WGST D3 6 . S~ control Room Status board
/. / ~ ~
MO ~ revisions of DB-CH-06900 and CWRT l-1 ~ DB-CH-06901.
/.I p9 ~
CWRT 1-2 0.4 Date _ , , Time 7 - ST Y SECOhDRYCE Daily rw ' l /0 _ ppb re(ss) _ _p. 7 _ ppb 0, pH 9.7 __ _ ppb O.24 _ umhos/cm N , II . lf measured it' 0 _ ppb Slo, _4 / Quarterly rw y/J ppb Date _ 9// /f/ _ Na* Pb d I.O _ ppb C1' ( /. O ppb Monthly FW / Date. / / fb Condensate ppb Cu ,_< t.D / 9dv ppb /o /o 3.1 o, wedbyd Cmervisor_ Time /Date ~- . _ . 3
7-3 ,
.CilEMICAb ANALYSES STATUS Duty Chemistry Supervisor / Analyst: llave the Shif t Supervisor' review ft and sign this status sheet prior to delivering to the Control Room.
----------------------------------------------------ISTRY BORON ANALYSIS TIME DATE PRIMARY CilEM RCS
~
5'oo ppm 6800_ 9///,/@ TIME 6860 DATE ,hg//0 f2/ ppm 7 / l 0, 4 ( ppb PZR BWST '2. 1 0 0 p p m l C1" 4 OM ppm .f '
)
1 l t 4 o.ob ppm PWST 43 ppm \ , l r' Li' I. .(~ ppm BAAT 1-1 //jgdp.. ppm BAAT 1-2 //. J yf_ ppm l pil 7./ C4RT 1-1 fof ppm ( 11 , 37 cc/Kg
\
CWRT l-2 /f/D ppm l i N, 13~ cc/Kg CrT 1-1 . '2 / / 0 ppm ! TDG. '/ 7 cc/Kg ( \ CrT 1-2 ~2 //t_ ppm , DEI /. f # -2 Cl/ml 17 STP /f'/d ppm Specific
\f. Activity 4. Vd 7 Ci/ml i
[ COVER GAS ANALYSES Time 0808 Date 9////f4 l
//
II, O, NOTEt WGST _p.3 6 . S~ Ensure all stated limits on l Control Room Status board are CHRT 1-1 /./ MO in agreement. with the current ! j revisions of DB-CH-06900 and ) CWRT 1-2 ,0. 4 /. / DB-CH-06901. l SECONDARY CllEMISTRY Time 073D Date '((/{/pb f Daily FW ! O, 07 ppb re(ss) / /0 ppb , N,11, 25~ ppb pil 97 q S i O, 4 /0 ppb measured 11' O 24 umhos/cm ; Na' O. '/.5~ ppb Quarterly FW ! C1' ,/ /. o ppb Pb < /. O ppb Date 9// /f/ () Monthly rW V C,o_ndensate
- O, 3. L. ppb Cu < /. D ppb Date / /fo Reviewedby,/) kfby Time /Date / o >/c / 7//r/fd !
StGft Supervisor l
7-4 .] DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. 2 SCENARIO NO. 1990 Evaluated Exercise l TO: Continuous Services Foreman ~ TIME: 08:30 L l T: -00/30
..l l
****************************************************************************** ,j l'
THIS IS A DRILL l
.D.O_ NOT initiate' actions affecting normal plant operations.
f
****************************************************************************** )
i INFORMATION: l INITIAL CONDITIONS: 100% power 958 MWe, by Heat Balance Makeup Tank level 70 ; Normal. Operating Pressure and Temperature 188 EPPD, 530 PPM Boron. Station Vent. .l Monitor Monitor 4598 BA is Out of Service for Calibration by 16C.. Vork is in l progress in the Uponder Pit in the Spent. Fuel Area. The hydraulic hopes are l being replaced. The pit is drained. i i e i 4 i f I L L THIS IS A DRILL J i Os ****************************************************************************** ! i i i [
. - . - . ._.----.- - - - . . - . . - . . . - _ . . . _ . . - . . - . . . . . _ . . - . . .. .i
--- . . . . - -. - - _ -. . = . - - .
7-5 l I DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) ! CUE CARD NO. 2 f TO: Continuous Services Controller TIME: 08:30 T: -00/30 :
. ANTICIPATED RESPONSE:
None. ! 1
't t
. INSTRUCTIONS: l Provide this information to the continuous Services staff and answer any questions about the initial conditions. :
i O!. , i 1 s l l I i i t i
****************************************************************************** 7 THIS IS A DRILL 1
****************************************************************************** i 6
i
- %R=
4 mg w
#4 7-61
.t, .a
= .,
DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE. CARD j S . .- J I l . ... CUE CARD NO.- -3J a i SCENARIO NO. 1990 Evaluated Exercise; 1 f J s TO:- 160 Technician's A, B, . C'. TIMES. ' 08:30-l ' T: - 00/30 - J l-
. THIS IS A DRILL i g NOT initiate actions'affecting' normal plant operations.
~;
INPORMATION:
, j Three I&C Technicians are performing: channel calibration of RE 4598 BA'.- .
Ons technician is in the Control, Room,;one'is'at the Station Vent Monitors on j the Turbine Deck, and the third technician has been sent to get some additional
~
l. test equipment. NOTE: RE 4598 AA is Operational. l a i V: t
- 6. \
b I i l l l. l I p 1 1
- i. l
****************************************************************************** 5 1
' THIS IS A DRILL -1 l
(0 J i
- ]
4 b f
.e.,esb ,p,,., _.%g,, %,. , p _
** " ' * ' C
- l 1
7-7 DBNPSEMERGENCYPRNPAREDNESS'CUECARD(Cont'_d)- CUE CARD NO. 3 TO s ~ OSC I&C Controller TIME- 0830 T:- -00/30 ANTICIPATED RESPONSE: 1 INSTRUCTIONS: Provide this'information to the I&C Technicians-working on Station Vent. Monitor 4598 BA. THIS IS A DRILL 1 f
Q/ O.u ; _y_gi
~ ,. J
$ DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD-1A-D SCENARIO NO. 1990 Evaluated Exercise , CUE CARD NO. , 4-T0 n - Control Room Staff TIME: '08:45 ) i T: -00/45 n
****************************************************************************** I THIS IS A DRILL !
D0_ NOT initiate-actions affecting normal plant operations..
****************************************************************************** s INFORMATION: i Make the following GaiTronics announcements! '
a
" ATTENTION ALL PERSONNEL,. ATTENTION ALL PERSONNEL. THE 1990 EVALUATED EMERGENCY PREPAREDNESS EXERCISE IS COMMENCING.- ALLtANNOUNCEMENTS PRECEDED BY 'THIS IS A
DRILL' - ARE FOR PARTICIPANTS ONLY. ' IF AN ~ ACTUAL EMERGENCY OCCURS,: AN:
- ANNOUNCEMENT VILL BE MADE THAT.THE DRILL HAS BEEN SUSPENDED UNTIL~FURTHER o NOTICE. ALL PERSONNEL ARE' REQUESTED-T0 MINIMIZE THE USE OF-THE GAI-TRONICS 't UNTIL THE DRILL HAS.BEEN TERMINATED."
e , Repeat this announcement once.: ! 4 i e
~
l
- i 1
T THIS IS A DRILL 1 O - h 1
7-9 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd). CUE CARD NO.. 4 h TO: Control Room Controller TIME: 08:45-T: -00/45 ANTICIPATED RESPONSE: Make the announcement. INSTRUCTIONS:. Ensure the Lead Controller is' informed and has the drill code sent on ERO.pages. O i i
****************************************************************************** 4 THIS IS A DRILL ****************************************************************************** h
-7i10 .-
DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD i ^\,
\
SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO.. 5-TO: I&C Technician C TIME: - 08:50 T: -00/10- !
~!
******************************************************************************/ I THIS-IS A DRILL- ;
D0_NOT initiate actions affecting normal plant operations. ;
.t
~ ****************************************************************************** q P
INFORMATION: While returning with additional test equipment you observe Technician B hitting _ something on RE 4598AA and then throwing something at .RE 4598 BA.- .l You. observe Technician'B leave the area. 9 I
' i r
a s s l i 9 THIS IS A DRILL a
. /~'N- !
- (_,/ ****************************************************************************** ,
1
.. , . + . - . - . . . . ,. , - - - . . - .. . . . . . . . .-. - .'
9,,9 a
.{p-m, 7-11 F
DBNPS EMERGENCY PREPAREDNESS = CUE CARD (Cont'd)- ..
, CUE CARD No. ; 5' TO: I&C Controller TIME - 08:50 T: -00/10 ANTICIPATED RESPONSE:
INSTRUCTIONS: Hang signs on equipment describing damageLto equipment. Technician C's lo' cation for observing _this incident vill be midway,across Turbine Deck heading in the direction of the RE's. THIS IS A DRILL
,hi 7-12 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD
. SCENARIO No.-1990. Evaluated Exercise' CUE CARD NO. 6' TO ' Control Room Staff TIME:- 08:50 ;
Tri -00/10 ,f - 1' l ' THIS IS A DRILL' 3 NOT initiate' actions affecting normal plant' operations.
****************************************************************************** ' ]
INFORMATION: The attached Makeup Tank Level Recorder indicates a decrease greater than/2'- inches per minute. E : a
?
.)
1
'l 1
i l i
.j i
THIS.IS A DRILL { ****************************************************************************** .j 1 I
]
...:, . . - , . , -, , . . - ,, s :- , . . . . . , . . . . . . . . .
7-13 0 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)' . CUE CARD NO2 6-TO - Control Room Controller TIME: 08:50 .: p . . T:' - 00/10 i i l ANTICIPATED RESPONSE: , i Declare an ALERT in accordance with EAL 2-A-2 RCS leak rate >:50 GPM but within- i HPI capacity. ] I I i i INSTRUCTIONS: -! l r 0; 6 l t
- l. !
, 4 I
I - l l i t i i
- l. l l ;
1 L
. THIS IS A DRILL {
t
. . - , - ., , . . . , , . _ . , . - , , , . _ , ,,,,,,.y - . ,- , . ,
l' i
'7-14
- l. ,
L DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD: .{ \b t 7 j L
^
SCENARIO No. 1990 Evaluated ExerEise . CUE-CARD NO.
'l TO n I&C Technician B TIME: 08:50' E!
,5 - T: -00/10: i o .; l
******************************************************************************i '!
THIS IS A DRILL: I
-DO NOTfinitiate actions affecting normal plant operations. :
******************************************************************************: -{
t INFORMATION - Technician B; Damage pump and'aotor on RE4598AA an by. throwing:vrench'breakt ! 3-vay switch on RE4598BA. > l i l ;
.i i
I J I i l
****************************************************************************** -]
THIS IS A DRILL. f ( l a., . . _ - . _ . _ . . . . .__ - . _ _ _ __ . _. _. . _
7-15~ 1 b .. . l- DBNPS' EMERGENCY PREPAREDNESS CUE: CARD (Cont'd)._
. CUE CARD NO. -7 )
TO' ' I&C Technician B TIME: 08:50 T: --00/10
. ANTICIPATED RESPONSE:
INSTRUCTIONS::
-Hang signs indicating damage to equipment.-
O THIS IS A DRILL
t e ilf
' 7-16: 1 i
DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO.~ 8
. SCENARIO NO. 1990 Evaluated Exercise TO: I&C Technician B' ' TIME ' 08:53 T: -00/07 THIS IS~A DRILL: q h . M NOT initiate actions-affecting normal plant: operations. ll INFORMATION:
Leavetheareaandattemptto.exitProtectedAresjby.'wayof-.theI&c.Shopin~
~
1. the PSF.--
- 2. While in the-I&C Shop kiek chairs, throw things around (simulate)'and-be..
generally abusive,'the leave.
- 3. If~ exit of Protected' Area is successful, then go-to your personal vehicle and avait the arrival of Security, b
v
?
r
)
l. !.. THIS.IS A DRILL L ****************************************************************************** l
~
i i
- l
, . 4 ,- b * , m,- ,,m+ . 4 , . - - - ,.w . , . . . . _ , . _ , . ,
-.,.--.,......_,;... l. e . . _ _ ~ ~~, ... _ J . )
A'
.7_37 o
.j DBNPS EMERGENCY PREPAREDNESS CUE CARD-(Cont'd)L ,,
CUE CARD NO., 8-6
=TO: I&C Controller TIME: 08:53- y T:< -00/07 :
l ANTICIPATED RESPONSE: i
-i e
I , -t e INSTRUCTIONS: :
)
Instruct technician to ava_it Security in his vehicle, unless apprehended prior- l to exiting the-PPF. 'He.should be discovered drinking simulated beer in his- , vehicle. , i l 4 91 : i l [ i i THIS IS A DRILL -
/
'f I-
, , . . . . . . - - -,.. . .. m.. -- , ,, . ,...-,.-c-- . ,- - . . . _ , . .- . _ _ . .. . . . .
I i
' l l 7-18: l l- .
l DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD -i q
- t" l SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 9 ,
J 08:53 ~ I
- TO L I&C Technician C. TIME:'
9 T -00/06 j l
-THIS-IS A DRILL
.i DO[NOT: initiate' actions.affectingnormalplantoperations.-
INFORMATION: -; i J
- 1. - Observe ~ damage to RE4598AAi snd RE4598BA.-
i
- 2. Contact Security (CAS). .
i
- 3. Contact Technician A and. advise him as to what has happened.- )
't 6
vf~'T : L
-i u ,
i l r i i i b i L' 4 e THIS ISLA DRILL , 4
.g 3, ,
P
, , . - - ,vv -e--- -, , , - . . -
.a .,,- ,, ., . . - , - -
+-,.+,.,.--4,.. ~..n,.-Jr 9
ll , , 1 1
" ;-7-20
( .- + DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD-: CUE' CARD NO..- 10' SCENARIO No.:1990' Evaluated Exer $1sei
~
TIME:'. 08:54' i TO '--I&C Technician in Control Room .. ( T:- - 00/06
?THIS'IS.-A DRILL: y.
{NOTLinitiate~ actions ~affectingnormalplantoperations.. p.
.******************************************************************************J t
f.. INFORMATION:- , L
.The White Light came on'the RIC panel-for' equipment failure.
r
. Station. Vent Monitor'4598-AA alarms #3 and #6 are alarming.
Station Vent Monitor 4598 BA alarms:#3 and #6 are: alarming. t O
.V <
.c .:
i I:
\
i 1 3
- i i
uf
'THIS IS A DRILL' U.
4 y - e.%<y g = ~v--c--- -+ g -- ,- , -&w.,,,,,y, +v, ~- -, ww,,v
J l' 7-21 l 1 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd). CUE CARD NO.'. 10 l 0 - TO: -I&C Technician Controller TIME:: 08:54 ! T: -00/06
-i j
ANTICIPATED RESPONSE: i Lookup alarm codes and' report to the Control' Room Operators what has been found.- i I Also report the problem to the!I&C Supervisor. 1 3
-1
)
i
]
i INSTRUCTIONS: , This alarm is caused by the damage to the operable Station. Vent Monitor, ; 4598 AA, by the I&C Technician. The #3 Alarm Light indicates actor failure. l The'#6 Alarm Light indicates' low flow. 4 l i I ! S 1 i
-is
-t t
*****************************************************************************F L THIS IS A DRILL
*****************************************************************************e l1 I
+ - - - - - ~ _
. - . , ,n, - ,_ ,-- ,
7-18 DBNPS EMERGFliCY' PREPAREDNESS EXERCISE CUE' CARD SCENARIO NO.'1990 Evaluated Exercise' CUE CARD NO. 9-T0:1 I&C Technician C- TIME: 08:53' T- -00/06 THIS IS A DRILL DO NOT. initiate actions affecting normal ~ plant operations..
****************************************************************************** ~
INFORMATION. - _1. - Observe damage to RE4598AA?and RE4598BA. '2. Contact Security.(CAS). 3.- Contact Technician'A and advise him as to what has-happened. THIS IS A DRILL l
7-19
-DBNPS EMERGENCY PREPAREDNESS CUE.. CARD '(Cont'd)! ] s
- CUE CARD NO. ;
I&C Controller- . TIME: 08:53 TO: l -T: - 00/06 . i ANTICIPATED RESPONSE: 4 7 1 a ; f INSTRUCTIONS: x; i I l S 5 1, . I s
******************************************************************************- 1
..i THIS IS A' DRILL .
****************************************************************************** hj ,
e
~ - - - . - ~ ,a.-r. -r., , .,, w - - - . . , - , ,,n, , . , e -, --o--a v -+,en-~e-
i 7-20: l~ ul
- DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD ~
CUE CARD NO.- 10 j SCENARIO No. 1990 Evaluated Exercise _' r TIME: ~ 08:54-
- TO : -' II.C Technician'in Control Room !
'T: -00/06-i ,
' ~
;t THIS IS A DRILli. v
- @ NOT initiate actions'affecting normal plant. operations. '
I
' INFORMATION:
- The White _ Light: came on the RIC panelifor ' equipment . failure. -
l Station Vent Monitor'4598 AA'alarmsif3 and #6~are alarming.
~
Station Vent Monitor 4598:.BA' alarms #3-and #6 are alarming.
-i l -
5
'i i
a 4
+
1 4
.i 4
4' i .i . v . THIS IS A DRILL -!
-i
{ ****************************************************************************** L r 1 i h w -- e .+n.- - , v. w--.* , - . w ..~ . ,--...,-..-es,--#. .Ae. % . . + . - 4 .. - - -
l
=7-21 l , DBNPS EMERGENCY PREPAREDNESS CUE CARD-(Cont'd)
CUE CARD NO. 10 -
- TO: I&C Technician Controller' TIME: 08:54
.T: -00/06 ANTICIPATED RESPONSE:
( Lookup alarm codes.and; report to the Control Room Operators what-has:been found. Also'= report the problem to the.I&C Supervisor. INSTRUCTIONS: This alarm is caused by.the damage toothe operable St'ation Vent Monitor,. 4598 AA, by the-I&C Technician. The #3 Alarm Light indicates actor failure. The #6' Alarm Light indicates low flow. Oi THIS IS A DRILL
I 7-22 ., l.
.DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARDc 'l0 11X -V SCENARIO NO. 1990 Evaluated Exercise > . CUE CARD NO.
TO: I&C Supervisor ' TIME: 08:56 T: -00/05 ,
.THIS IS A DRILL
?
DO NOT. initiate actions affecting normal plant operations. INFORMATION:- 3 l Report the actions of the disgruntled employee to Security.-(SAS). 3
.i
\ d O : 1 . l C 1 l f i V r THIS IS A DRILL ; i o P
LL nl, ,
- t.+
-; i- :
7 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. _ 11X TO: IEC Controller TIME: OU:55 T -00/05 ANTICIPATED RESPONSE: Report actions of disgruntled employee'to CAS. INSTRUCTIONS: Provide this card to the I&C Supervisor is' he does not' contact sec:trity himself. - i e; THIS IS A DRILL 1 I
\
.'7-24 4
DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE ~ CARD' CUE CARD NO.. 12'
) SCENARIO NO. 1990 Evaluated Exercise- t 4
TO:: Lucas County Sheriff Dispatchl TIME 09:00 T: 00/00 2 rI + THIS IS A DRILL DO NOT. initiate actions affecting normal plant' operations.: j
****************************************************************************** {
i r INFORMATIONs. Do not call" personnel using' Notification Call List (simulate only).: q r L
. v.
?
f
\
l i h-I d i i I d l:
.t THIS IS A DRILL
),
s i f i
25: Y j DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)~. CUE CARD NO.~ 12 TO: Lucas County Sheriff Controller TIME: / 09:00- _ ,
-T: 00/00 _
ANTICIPATED RESPONSE: l Notification forms should be filled out correctly.~...The Dispatcher should turn 1 to the correct section of.the Notification Call List. :The Dispatcher should : perform a smooth turnover of responsibilities to the EOC. . -
' INSTRUCTIONS: f Ensure the Dispatcher' turns to the correct section of..the Notification Call List !
Do-not allow Prompt Notification System' but do not allow telephone calls. activation. Do not'allov EBS message to be sent. i e' i w Y a 4 i
******************************************************************************. ?
l THIS IS A DRILL ,
?
'f
o i -
]
7-26v DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE,. CARD.-
'A
( SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 13' l TIME: 09:05
.TOj Control Room Staff T: 00/05-1
~
)
THIS -IS A' DRILL ~ . i l g NOT initiate actions'affecting normal plant operations.- l
****************************************************************************** j i
INFORMATION: ! i
'When shutting down.the plant use a shutdown rate of 2% per minute.- l t
l 1 0 . s ci
- 's(
h l, 1
?
~
i
+
****************************************************************************** f r
THIS IS A^ DRILL , b. U- ****************************************************************************** i i e 1
7-27 L DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 13 - TO: Control' Room Controller TIME:- 09:05 T: 00/05 ANTICIPATED RESPONSE: Shutdown the Plant at a rate not to exceed 2%'per minute. INSTRUCTIONS: Provide this card only when a shutdown.has been commenced. O THIS IS A DRILL
L f \} %:
' ^ ~ '^~ - -
~'; -
n j
'L' j
J7-28: 03 > m y'>
- DBNPS EMERGENCY PREPAREDNESS'. EXERCISE CUE CARD 7' O '
3'4X ' 3
'h: SCENARIO NO. 1990 Evaluated Exercise: CUE CARD NO.-
g 1
.TO : Equipment, Operator TIME: 09:05 on I T: 00/05 on
~
a
******************************************************************************! l
)
THIS IS A DRILL d _D0 NOT initiate actions affecting normal plant; operations.
******************************************************************************, ;l s
INFORMATION:- When needed the Steam Jet Air Ejector flow is 20 CFM.
,i
-i i ,
'I .
'. A .t i-
~l L
i B .,
'}
;i o
" ~THIS IS A' DRILL t
7-29 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO.- 14X TO: OSC Controller TIME: 09:05 on T: 00/05 on ANTICIPATED RESPONSES
-This information may be needed by Chemistry or other personnel.
INSTRUCTIONS: When this information is looked for provide this card. THIS IS A DRILL
Ll 7-30 , DBNPS EMERGENCY' PREPAREDNESS EXERCISE CUE CARD , CUE CARD NO.. 15X
. SCENARIO NO. 1990 Evaluated Exercise' TO: Equipment. Operator - TIME: 09:05 on! h T:: 00/15 on l
I THIS-IS A' DRILL <
]
l ' _D0 NOT. initiate actions affecting normal plant operations.~ -.. i ****************************************************************************** <
.INFORMATION:
'I'f asked the Station. Ventilation flow. rate is-120,000 CFM. ,
I
- i. --
4 cl J i s j. l: .l i ) .1, 4 e i r t
. i F
THIS IS.A DRILL
******************************************************************************. i a
. , -%, . -e. , i+--. . _ . - - - ,_ - . , -
,&%- ~y... . .. .. - , , ,
. 7-31 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 15X T0: OSC Controller TIME: 20:15 on I T: 00/15 on I ANTICIPATED RESPONSE: This information may be needed by Chemistry or other personnel. l INSTRUCTIONS: When this information is looked for provide this card. i l . I r h t I f r
?
THIS IS A DRILL 1 ( i
.i . - , - . - - - - - , . . - - . - ~ , . , - - - . . . - -.,~.I
7-32' l
)
D8NPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD m SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 16 l T0: I&C Technicians A & C/I&C Supervisor TINE: 09:05 ! T: 00/05 i t l THIS IS A DRILL i g NOT initiate actions affecting noracil plant operations. [t
****************************************************************************** j INFORMATION:
Assess'the' damage and arrange for parts and repair of equipment. . i j i i t i h f t i i f I t f l I THIS IS A DRILL c h
, . , . ,.s,-,..wn,.- . . . - , - - , - - , - - - - - - - , - , , . . . - . < . . - , . - - - - . - - - - - - ov. , - - - - --
i 7-33 ; i
)
DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) ! CUE CARD NO. 16 TO: I&C Controller TIME: 09:05 j l T: 00/05 ! t 4
- AlfrICIPATED RESPONSE:
l Obtain the necessary paperwork to obtain the needed parts. j f INSTRUCTIONS: ; Parts Required Pump and motor unit SC#96-6768 . Three way switch ; 1
- l ,
I r 9: i t t i 4 i l i
****************************************************************************** l 9
THIS IS A DRILL
***************************************************************e************** ,
..- . . ~ . . . . - - . . . - .-- - . - - - - . _ - - . . .
t 7-34 t DSNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD
. CUE CARD NO. 17-SCENARIO NO. 1990 Evaluated Exercise Approx. 09:10 TO: Security at DBNPS Gate TINE:
T Approx. 00/10 , l THIS IS A DRILL {NOT.initiateactionsaffectingnormalplantoperations. l
.INPORMATION: ,
Five minutes after restricting OCA access, open the barrier and. allow normal- ; vehicular access. a I l i b. k
.6 i
?
l l L f i THIS IS A DRILL ! e
****************************************************************************** -j I
i
. ._.-,._ -- __ . _ . . . _ . . _ . . _ _ . . . - _ . . _ . _ . . _ _ . . . _ . . _ _ . _ . _ . _ _ . _ . . _ _ ~ . _ - - . -
r l 7-35 l 1
. r l
DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) ; CUE CARD NO. 17 , TO ' Gate Security Controller TIME: Approx. 09:10 l T: Approx. 00/10 ANTICIPATED RESPONSE The security guard vill open the Cooling Tower gate five minutes after restricting access. l
\
}
INSTRUCTIONS: Issue this card 5 minutes after the gate was closed. [ f Ol ! r 4 i
+ !
i r
?
I l t l THIS IS A DRILL f P
i 7-36 ;
, 1 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD l SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 18X TO ' Apprehending Security Officer TIME: Approx. 09:10 j i
T: Approx. 00/10 -l t
?
l THIS IS A DRILL' DO NOT initiate actions affecting normal plant operations.
****************************************************************************** j INPORMATION: !
t Call the Ottava County Sheriff.to arrest the suspected saboteur.
.?
1 t l 4 I i i r i
.i.
i f I i THIS IS A DRILL i
7-37 ; DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) 18X CUE CARD NO. TO: Security Controller TIME: Approx. 09:10 I T: Approx. 00/10 , i ANTICIPATED RESPON,$Es-1 Call the Ottava County Sheriff to take the saboteur into custody. > l l i i INSTRUCTIONS: , ' Provide this card only if it appears the security force is not going to seek: l assistance from the local law enforcement agency. Allow any discussions with r the corporats legal department to occur as well as any interrogation of the 16C' .; Technician. l Gl r
)
I f P l i I i l i I ' l THIS IS A DRILL l
****************************************************************************** lllli
?
i
7-38
'DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 19 TO: EO Firing Auxiliary Boiler TIME: 09:15 T: 00/15 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.-
.j
***************************************************************** i INPORMATION: ]
Auxiliary Boiler fires-for a few seconds, then goes out. All indications OK, except fuel _ pressure which is lov (<20 psi). Alarms.on the Auxiliary Boiler Control Panel
- 1) Flame failure
- 2) Low 011 Pressure Alarms in control Room
- 1) Auxiliary Boiler trip (9-1-D) i
********************************************** **************,s*****************
THIS IS A DRILL
'7-39 !
DBNPS EMERGENCY PREPAREDNCSS CUE CARD (Cont'd) CUE CARD NO. 19 TO: Controller for E0 at Auxiliary Boiler TIME: 09:15 T: 00/15 ; ANTICIPATED RESPONSE: . Check all indications determine strainer is plugged. Switch strainer to f opposite side. Opposite side strainer vill also plug up in a minute or so. Perform other actions to restore fuel. l l ' s INSTRUCTIONS: i Auxiliary Boiler shutdown due to plugged strainer S0301. Normal operating pressures are (for one train): l } PI PISG 4878 6.5 M' W, 2784 23 ! 1104 17.3 1248 16.5 1120 150 135 1522 t 1482 53 i If the temporary supply downstrema of FO-5 is used for fuel F0-5 is corroded shut and cannot be opened. [ t e t i i. l THIS IS A DRILL
t 7-40 i D8NPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD l CUE CARD NO. 20X SCENARIO NO. 1990 Evaluated Exercise' ' TO: Shift Supervisor TIME:- 09:20- t I T:' 00/20 j
****************************************************************************** i THIS IS A DRILL
{NOTinitiateactionsaffecting'normalplantoperations. l t
****************************************************************************** j i
INFORMATION . l 4 i Declare an Alert in accordance with RAL 2.A.2, RCS Leak Rate >50 GPM but less ! than HPI capacity.
)
l t l \ I j l i 1 THIS IS A DRILL
****************************************************************************** i I
,_._,,,_,_.__._._,.1
7-41 '. ) DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) ! CUE CARD NO. 20X l T0: Control Room Controller TIME: 09:20 l T: 00/20 j ANT 1CIPATED RESPONSE: . l Declare an Alert in accordance with the EAL. Have the initiate Escrgency ; Procedures Alarm sounded. l
-i l '
I INSTRUCTIONS: ! Provide this card only in the event that no action is being taken toward j declaring an Alert by 09:20. Do not allow them to make the declaration or the j announcement before 09001 Ensure that the initiate emergency procedures alarm l is sounded. l l e; ; i I i i
'f r
THIS IS A DRILL h
,w. - -, -. , ,. .. .. . , , _ , . . . . , , _ , _ - _ . _ _ ,,m,,, . . , , , . . . , , ,
7-42 ) l DSNPS EMERGENCY PREPAREDNESS EKERCISE CUE CARD , SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 21 l J TO: I&C Technician A & C/I&C Supervisoc TIME: 09:20' ; T: 00/20-l
****************************************************************************** l THIS IS-A DRILL l i
DO NOT initiate actions affecting normal plant operations. ]
****************************************************************************** j INFORMATION:
Repair of RE'4598AA vill require 8 or more hours to repair and test. :J Repair of RE 4598BA vill require 1 hour to repair and test.
)
t 3 t
?
i l- , t , l THIS IS A DRILL O **** ***** **** **** ***** ****-
7-43 j DBNPS ENERGENCY PREPAREDNESS CUE CARD (Cont'd) I CUE CARD NO. 21 TO: I&C Controller TIME: 09:20i { T: 00/20 ; i ANTICIPATED RESPONSE: l I 3
)
t i i INSTRUCTIONS: 3 Repair to 4598 AA will require complete pump and motor assembly and associated ; tubing. ' 4598 BA repair vill require gluing the switch back together to make the switch -i vork, i i t i i J l j ! 1 I
****************************************f*************************************
THIS IS A DRILL i
.- _ . . ~ _ , . - - - . _. _ _ _ _ . _ _ _ _ , __,. __ _. , ._ ,
7-44 l l m i D8NPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD i s CUE CARD NO. 22 i SCENARIO NO. 1990 Evaluated Exercise '> 09:20 TO - OSC I&C Technician TIME: .l l i T: 00/20 'j i THIS IS A DRILL
-i 4
{NOTinitiateactionsaffectingnormalplantoperations. ' l
****************************************************************************** i r
INFORMATION: i Pump and motor unit is stocked (SC.#96-6768).- Three way switch is not stocked. l
- l l
O .i i l I ; l i i
.i i
.I THIS IS A DRILL j i
f
7-45 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) s CUE CARD No. 22 , k Ilic Controller TIME: 09:20 i TO: i T: 00/20 1
-ANTICIPATED RESPONSE:
Obtain the necessary paperwork and provide to get the part from the varehouse. l
.i i
i i 6 INSTRUCTIONS: The warehouse should locate the necessary parts and then deliver simulated parts to the OSC on vork area as directed. ,
)
i G!? i l l i
+
i { r l l THIS IS A DRILL : j [ i i
,. - - , - . . _ . ~ , . , . .
46 , DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD l . SCENARIO No. 1990 Evaluated Exercise CUE CARD No. 23X T0: Control Room Operator TIME: 09:29 q T: 00/29 I
****************************************************************************** .f THIS IS A DRILL :
DO NOT initiate actions'affecting normal plant operations. 'l
***********************************************************************,****** -{
l
> INFORMATION: 6 Take off 41 Main Feed Pump at 450 NVe (shutdown stopped-briefly during this action).' '
O : I
.1 l
l 1 s Il
-1
*****************************************************************,*****,***,*,- q l
1 THIS IS A DRILL l 1
7-47 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) , CUE CARD NO. 23X TO: Control Room Controller TINE: 09:29 .l T: 00/29 AltfICIPATED RESPONSE: -
.r Shutdown the pump.
r l i i INSTRUCTIONS: Provide this cue card shen they decide to take off a Feed Pump, or at 09:29, .
.i whichever comes first. :
-l t
el B L k h h l i
't i
****************************************************************************** I THIS IS A DRILL i
I I l
?
7-48 t i DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD l SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 24 ! l 70: Emergency Director ' TIME: Approx. 09:30 l l l T: Approx. 00/30 i l THIS IS A DRILL DO NOT initiate actions affecting normal: plant'operationst } U INFORMATION: ; 1 For purposes of the Exercise, controllers are directing nonessential. personnel- -l assembled in the-Protected Area to return to work.' Do Not take.any actions to! i expedite this process; Assembly inLthe Protected Area vill be simulated'at'this point.. Ensure the Emergency Plant Manger and the Emergency Facili. ties Services Manager : are aware of these actions. l 4 1 i i l i i f
.I t
l > i 1 1 l r
****************************************************************************** f I
THIS IS A DRILL ;
****************************************************************************** l f
-6
., , . _ _ , _ ~ . . . . . _ _ _ - . . , _ , . - _ . . . _ . _ , - . _ _
7-49 ; I DBNFS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) l I CUE CARD NO. 24 - l TO: ECC Controller TIME: Approx. 09:30 f i T Approx. 00/30 ! AlfrICIPATED RESPONSE 1 Ensure Emergency Facilities Services Manager and Emergency Plant Manager are l informed. i i i h
?
INSTRUCTIONS: ;, Provide this card to the Emergency Director when notified by the Assembly Area. I Coordinator. 1 i i G< e f 1 l i ! 5 l l e l- , i
?
f I THIS IS A DRILL b
- . - - . _ . . . . - . . . . . , _ . . . ~ . . ., .. _ ,
7-50' DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD () SCENARIO No.-1990 Evaluated Exercise TO: Control Room Operator CUE CARD NO. TIME: 25X 09:30 T: 00/30-THIS IS A DRILL DO NOT initiate actions af fecting normal plant operations.
**************************************s+**************************************
INPORMATION: You have lost all Station Vent monitoring capability. Report this information to the Technical Support Center. O THIS IS A DRILL
.. j
***********************************************************4;*****************
i 1
7-51 j l DBNPS ENERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 25X TO: Control Roon Controller TINE: 09:30 )
?
T: 00/30 l ANTICIPATED RESPONSE: . i None j i t INSTRUCTIONS: Issue this card only if this information has not been passed to the TSC.
-l r
i G! i t h l 1 l l i
)
i ( a r l ****************************************************************************** s 1
.THIS IS A DRILL
.f I
I 7-52' l 1 .
)
i DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD . SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 26 ( 09:45 l TO: OSC Manager' TIME: T: 00/45 . t [ I THIS IS A DRILL ~ DO NOT initiate actions affecting normal plant operations.. ! I i INFORMATION - 'I t Send a response team to the Fuel Handling Area Uponder Pit to complete the replacement of the hydraulic hose.- The team previously working on this job : reported the replacement vill require approximately one hour of work to j complete. j r i t { a i i t
-[
5 i
)
THIS IS A DRILL
************************************h*****************************************
}
t s I
7-53 DBNPS ENERGENCY PREPAREDNESS' CUE CARD (Cont'd)' CUE CARD NO. 26 TO: OSC Controller TIME: 09:45- l l T: 00/45 l ANTICIPATED RESPONSE: Send out a team. > 1 I
'i INSTRUCTIONS: I Give this card to the OSC Manager and insure the-team-is dispatched to be at the.
Uponder Pit by 1100. This team v111'be used for the contaminated person event at 1100. k {'
- j. .
l e r v
.i
?
l THIS IS A DRILL !
****************************************************************************** a f
'P
7-54 j! DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1990 Evaluated' Exercise CUE CARD NO. 27 TO: Upander Response Briefer. TINE: '09:50 ; l T: 00/50 J l THIS IS A DRILL 3 NOT initiate actions affecting normal plant operations. 4 INFORMATION: l The Uponder pit is drained, and ladders / scaffolding'are in place to allov ; replacement of the hydraulic hoses. Some water is leaking past the gate from 4 the spent fuel pool, but a temporary sump pump is. pumping.it back through.a hose- l to the spent fuel pool. All the hydraulic hoses.except one have been replaced, i and all necessary parts and tools are at the job.- It should take about one hour : of work to replace this last hose, j t i t a a
'I
-t I
')
****************************************************************************** 1 THIS IS A DRILL I i
l ,
I 7-55 I l
. DBNPS ENERGENCY PREPAREDNESS CUE CARD (Cont'd)
CUE CARD NO. 27 T0t OSC Controller TIME: 09:50 J T: 00/50 ANTICIPATED RESPONSE: ) i I
- Brief the crew. ,
l ! l 1 INSTRUCTIONS: i l Give this cue card to the Team Briefer when the team is assigned to theiupender I job. ~ Team must be in the spent fuel pool area at 1100. j t
\
l O! ! L l
- l. .
^l f
i
?
I 3 I i I THIS IS A DRILL i h
- . . . - . ,.w-, , . - - - - . ,..y-3,. .,p. -, . , . . . . _ . . , . - - . - , , -
,.-.,-,,_..c .m-,,
1 7-56 l I DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD { SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 28 l b . TO: OSC Rad-Con Briefer TIME: 09:50 l i T: 00/50 l 4
-t THIS IS A DRILL ,
DO NOT initiate actions affecting normal plant' operations. INFORMATION: > Survey results for the Uponder job are on RWP #9999#. 6 I s ) I THIS IS A DRILL !
****************************************************************************** i '( ,
i
- - . - , - . ,- , ,L.- , , . _ - - - - - _ . . -- . . ~ . - -
4 f 7
- i D8NPS EMERGENCY PREPAREDNESS CUB CARD (Cont'd) i
< CUE CARD NO. 28 l TO: OSC Controller TIMit ' 09:50- ,
T: 00/50 ! ANTICIPATED RESPONSE: : None ! i l 1 l INSTRUCTIONS: t Provide this cue card to the RC'. Briefer when the response team for the upender f job is assigned. l r
'l l
O! i
?
v l. j i
.1 i
*****************************************************************************+ ;
)
THIS IS A DRILL : j i ******************************************************************************. -{ , l -- ! 'l r t
-i
,_ ._. -- - - - -- .~ - .-. .-
)
7-58 l 1
. DAVIS BESSE NUCLEAR POWER STATION RADIATION WORK PERMIT (RWP) \'\% Eve Lc25 c.
- PAGE
' ED *
/7 _
, 1 Or 9.,, j g OR#GWATED Dv terent essi esame ersg
- TOR Ai Pnout ExTgggion !
A8kV..E HW. W o M b mmV RDJG l
**"**'*#Pmf /:vsc koL Wua fwsh e 7"z7- 1 0
FI'b1Dk 0d9' SCRi>TaOn ct WORK 1O sE OoNE t) l R i i i
? Mobrnl f~Un HwMIM&- A/? APP lM Aub Acc l A %5 oc1'A Trh s u P P o ff r ~ M 7 7 v 3 7.2 G 5
; p. ,. - , . . ~ ,.
R ,
- p. :'t g. . . n . .
' ~
O SEE SUPPLEMEntTAL NPORMATION SHEET OReonATOR SEi; DON i WWO NUMMR($) FOR THrs WORK W9pn OROUPtsl 0A CRAFfit) WHQ,WILL 00 WORK Lsf auATED MANNOUR$ 2-8'3-oon7- M JOS CON: ACT NAME (Pring M*. cMem Jnn mn RWP REOUESTED C WOR t tv&- HE LED TO DEGIN WOREC
& LET sY
&Nbl Y* D h EW tan's/blbr $ D 5 \estelh/Yl/h b 0 '
smats ll13/R .' WORK CODE / I / ' 4 O OP PLANT OPERATON/$URVEILLANCE D as m.spMCE INSPECTION . O WP WASTE PROCES$iNG O RM ROUTNE MAWTENANCE % $PECIAL MANTENANCE D RF REACTOR REFUELNG - w GENERAL AREA DOSE MATE MAxWUM OC6E RATE - LOCATION 0F MAXNUM DOSE RATE A mRih . mR/h l '[kOM hkMbb -
$ NEUTRON DOSE RATE hoi SPOT DO$E RATE f LOCATION Or HOT & POT af- ,
i O. /,, ,,,,em ,,, Asore / mR,,, IGRAPPLER FZ/J4MS r W GENERAL CONTAMINATION MAXMUM CONTAM8 NATION g,,,, LOCATION OF MAXIMUM CONT %CN Q R i M noo ,m Anrr / ,mm. l6bopwe FME[S . A A PARTCULATII ACTMTY MPC FRACTION NOGLE gas ACTMTV MPC FRACTON RESPeRATORY PROTECTON . b i $ h //d M M nCucel Md72"." d eCuee l OtEOulREO tRPP ATTACHED) > l 0 R ODiNE ACTMTY MPC FRACTION TOTAL MPC f RACDON O NONE REOUIRED o E AA14* h,Cuce l PAnnCuLATE a scomt ONLY g/gr/- $ ! O soof D N,A HEAD O N/A MAfsOS O N/A FEET O NIA F ACE / EYE.s O N/A - I c NLOTH COVERALLS O t ett ' JD URGEowsCAP ICOTTON GLOVE LNER$ NLOTH SHOE COVERS %ETY GLASSES f L b EPAPE kPLAS ERAL1A N SUIT,@ rg f A6 CLOTH N000 O PAPER H000 WMUSSER GLOVES
)C2PR O CLOTH DUCK FEET KPtA$ tlc SHOE COVERS (T. TOPS) O OTHER OFACESHiELO
- i w 0 PLASTIC TOP $D'LASTIC HOOo O CLOTH WORK GLOVES KRUeMR SHOE Covens ;
C 0 ' 0 CLOTH LAB COAT O LE.ATHER WORE ( Gloves O RusaER soots h KT APE CUFFS Jb APE CUFF $ T CENER AL wHOLE 800v A00m0*i AL WHOLE DOOY fA EXTREMITY O NiA lOARY EXPOSURE EXPECTED ! R TLD/0 700 mR $RO O SEE MULDPLE WHOLE Y N HAND D R f 00T INVOL sc UNDE R THt$ i 500 mA SAD EXPO $URE MONITORING FORM % HAND D L Fooi RWP_ _ mp g APgo At 58,ACEN0sitt0GtMtNt _ _ [
' ,/ /,. ; O8't s.s e NOWLE DGE.vtNi s5 . .aste.
APP @f dt ---. ')[jf'S 9,4,
#,81C tfr.4/c)? I ',JA.WALAghe,b'8aOVAttir.re.
im
- n)coa /d'/! < %,A,% ._'. .It s.. . /Y l
. . . t ~ i m t e.,
fgj i ri nwait o e, aC , Oac ui,m. ras.,, atab.,rOaito,e.AIc.4 .
. pOin os.osum i O WOa. COvett :Ea O PaoctovatinuP viopON i l r.. . . .e e a in a n.n. an.e . e a ,ei.. .n. e m m4** . ...-
_ , - _ _ _ . _ _ _ _ _ . . _ _ . m.- - ~ 4 . . . , . ,. _ . . _ , . . , w , . , ,
.l 7-59 CAVI}SEO.'E NUCLEAR POWER STATION 'l CADIATION WORK PE MIT (RWP SUP LEMENTALINF RMATION HEET - \%b G ye's e,- .
g Aooet.o=*t otscan pON Or wOm Loc 4Tm wom To avcArO wco .
\
O I; a ki 1 I J o D i ;
' 1 N ,. c ? - 3 j A ? -
o O R . t?, s j t h ' I y?.$t; $;;., y6** QV )- ;
,'. l- )
ADoITIONAL MDCLOGICAL CONTROL INSTRUC110NS - A/oYr /. l'WTAd7' /RhrA777W AWb &)MAe27WA7~Zou few/C j oAJ 6/APMcA ' TD BE' bE 7%fmsNFb 4/b/A) IV47Fortn1 R !
$ ANb (2ASWlT':rM779 cub Os) ARAfM6-# Abrusxt[), ;
b #677 D. ' ' h ATRBMur Acr2v.rgr./ Apwk 70Ar ha7ts's:zTrc-h/7- $' a l X1mS~ of Asoed l' Do77 3. /Ub' ole Boo [/ khne7At/ 70 BC foSJ"nowch 2'A/ Add??- 6 f /k'd//f5 hAo} .& v' bw A4W \ 0 #677 4 T FI M CA ATWCs A hh - O-Dd0. /)-5R srb 5 $l7)VlR61) p:/y, <
~~
fxM h250kW6t. 6 Darn 9 a s a//- GE/1PRsX ;
/ MMS ~ $AS1.TC5 /EduzftD Rgyazrync ovrM_, t oppyg ,,,,,,,;((S ,
h%/ M* SuATr7DTEi) Xf WAMR 2S Alo?" ff' ESwT
.omo~*L AumconcenNsmsvauct,0~s V15 DEEN NIN CEE ~ AN6 VJDCK PLATFORM - PEJM. Tb jlE. ,
hRDL WOQ.K PLATTUU% ll> -6ET A'TTGirT Tb TIALSC GRAPPLG. h@ ~ SU2.VD). 00MTAM 'I'MLUGTEJAL SWCU TD SUUG _ loa FLT 11P a'5AfITV l%DE q
} MNL WDEL PLRTFof,n) TD RfEh 0F IDlLDT WE-DYT OK LUDT -TF RYSIBLE n
A MbG (URi\PPGD SinOhlDb Ot!&. 140T CPt>T5 tin 1P 3lIGbw6 etDA CCDLllc D'TL , DR- EMiCR EIUX~ TD REhtCC OR.611\lUATE. Tuw RwP waa sctuc A5 Tyc Av a.p ca,ocw gr pu:, yf wint 7ur- ' l UAkOJ1~ hila ILAPJLC '?lhtU%-
~ WHIT E . File copy Y E L LOW . Woe s.ng Copy PINK . AC F o<emadCopy COLO(NROD . Pou Coor
. _ _. ..._s . . .-
. - . - . .. . . . - . . . - . ~ . - - . - -. ..
.- 7-60 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 29; r'
=!
TO: -Auxiliary Boiler Response Team - TINE: 10:00~ l
' T: 01/00=
THIS-IS A DRILL- l DO NOT-initiate actions affecting normal plant operations. , t INFORMATION: Information available-from the Auxiliary Boiler Operator-when asked. j 1 t V 9
+
THIS IS A DRILL g ******************************************************************************-
-4 a
.e.-- . , . - - - , . , , , , . .4,., ...., , , < , , . _ - . , , -,-vvy ,
7-61 i DBNPS ENERGENCY PREPAREDNESS CUE CARD (Cont'd)
. CUE CARD NO. 29 i
TO: OSC Auxiliary Boiler Controller. TIME: 10:00-T: 01/00 ANTICIPATED RESPONSE:~ Contact the Auxiliary Boiler Operator. f b INSTRUCTIONS: Information from the-Auxiliary Boiler Operator: Alarms on the Auxiliary Boiler Control Panel, 1) Flame Failure - 2) Lov'Oll. Pressure ' Alarms:in Control Room > 10 Auxiliary Boiler' Trip (9-1-D). l L i i >
*******************************************w**********************************
THIS IS A DRILL
***************************************************************g**************
E I
'7-62 D8NPS EMERGENCY PREPAREDNESS. EXERCISE CUE CARD, l 't' CUE CARD NO. 30=
SCENARIO N0. 1990 Evaluated Exercise-TO: Control Room Operator TIME: 10:06 T: '01/06 1' THIS.IS A DRILL , DO NOT initiate actions affecting normal plant operations. ,
****************************************************************************** lf INFORMATION:-
Manually; trip the Turbine in accordance.vith the shutdown procedure. t l I
~
i c
?
?
b I t l THIS IS A DRILL
****************************************************************************** +
b f
A, 7-63 a l DBNPS-EMERGENCY PREPAREDNESS CUE CARD (Cont'd). CUE CARD NO".' ~30 . TO:: Control ~ Room Operator TIME . 10:06-T: 01/06 j ANTICIPAT3D RESPONSE -{t 1 None ]
-I .
t i i I INSTRUCTIONS: Shutdown is proceeding normally. -Turbine is tripped manually'at 15% Reactor-Power.' 4 t v i el: 4
+
i I r i L
=;
i
****************************************************************************** +
THIS'IS A DRILL [
****************************************************************************** g ;
l ', l-
L 64C ; i
-DBNPS(EMERGENCY PREPAREDNESS EXERCISE CUE CARD i CUE CARD No.. 31 .
SCENARIO NO.-1990 Evaluated Exercise- !( i r 10:12< cTO: Control Room Operator TIME:- j 1T:: 01:12' 4 t
*********************************************A********************************. 'i THIS IS'A'DRILLL
=.
DO NOT initinte actions affeeting normal plant operations.'
+
INFORMATION: : Lovering. Pressurizer level in accordance with the shutdown procedure. - r i
?
4 4 + s
.4
,1 i g it D
*************************************************************gg***,g****g**g*** ,
k THIS IS A DRILL g 0
, - - + . - - r -- -- e . , , . , , s v v ew,- - -- - - , . + , . - - we'
1 7-65. 1 5 DBNPS ENERGENCY PREPAREDNESS' CUE CARD.(Cont'd)i
' CUE CARD NO.. '31- -
- TO - Control Room Controller TIMES, 110:12'
.! T: 01:12' ANTICIPATED RESPONSE:
~ None-INSTRUCTIONS:
None , O THIS IS A DRILL J
******************************************************************************z l
.l
-\ 7-66 DBNPS. EMERGENCY PREPAREDNESS EXERCISE CUE CARD
, SCENARIO NO..1990 Evaluated Exercise'. CUE CARD NO.- 32' TO: Auxiliary Boiler Response Team-3
. TIME: 10:15 T: 02/15
~
~ THIS IS A' DRILL.
@ NOT initiatefactions affecting normal plant-operations.L 1
INFORMATION:
'StrainerisLfullof-l junk'(rust, paint,'etc.)andwh't'appearsty-bewater. a THIS IS A DRILL
....m. .
]
'1
.7-67 j i
l:, DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)~ CUE CARD NO.- 32< TOs._0SC Auxiliary Boiler Controller TIME:- 10:15 T: 02/15' ) 1 ANTICIPATED RESPONSE: l Attempt to clean / flush fuel. oil pump suction strainers. l I J li INSTRUCTIONS: ; Attempts to clean / flush strainers vill be' successful -.' allow the boilersto be' ' returned to service at 1020. .
. I r
i 0; 1 h i 1 THIS IS A DRILL B _U--- r.+r - w w , - . .-. , - , . _ _ - ,,g
- - s m
. E7-68_-
' ' DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD:
SCENARIO NO.-1990 Evaluated. Exercise CUE CARD No.- 33- Ej l {
- i. V 1
, .TO:- Uponder Repair Tema- TIME:._ 10:15- !
T:: 01/15' .
' ****************************************************************************** l THIS IS A-DRILL- .l
- @ NOT initiate actions affecting normal plant operations.
=
n
******************************************************************************/
, il'
.INFORMATION:- ,
i All tools'and parts are available for the'upender hydraulic hose replacement. i There is only one' hose remaining to be replaced and the-work should;take about 1 one hour. ,.i l c- .
.a
.( ,
a i t
.i P
A t l. 1
~!
L THIS~IS'A DRILL i
***k**************************************************************************
4 1
- , , ~ , , ,
4
, , -l r ,
'7-69 ,
j l
-)
. DBNPSiEMERGENCY PREPAREDNESS CUE CARD (Cont'd), )
, CUE CARD No. 33-TO: 'Uponder. Repair Controller _ . TIME:- 10:15 l T: ' 01/15 '- ;
1 i ANTICIPATED RESPONSE - j None- ; h 4 INSTRUCTIONS: ; This repair team vill'be utilized for the.1100 radioactive uptake event.-
-?
-t
- )
~ w
?
k F
\
s 1 ! i THIS IS A DRILL i l' l 3 l
. . . _ . , , _ _ . . . . _ . . . , , - _ . ~ .! ,L . , _
l
- 7-70.1 i ,
, )
- 1.'DBNPS EMERGENCY PREPAREDNESS EXERCISE. CUE.' CARD 4 4
a b- _(f
- SCENARIO NO.'1990 Evaluated Exercise CUE CARD NO.~. 34 '
l 1 i TO - Securlty Officer TIME: ~10:15
-T. 01/15 -l
-THIS IS A DRILL':
I
-DO NOT initiateLactions affecting normal plant operations. ;
-1 INFORMATION: ,
The Sheriff has taken,the suspected saboteur into custody and removed.him from:
~
-i the site. j o
1 i 1 1 4
-i i
5 THIS IS A DRILL i
****************************************************************************** i J
f w --- w , . ,, .- v'.r- , - - - - .- '-4-< #
+
'7-71: f
.DBNPS' EMERGENCY PREPAREDNESS CUE CARD (Cont d)-
i ,
,' j
, CUE CARD No.. 34- J TO ': Security-Controller' . TIME: !10:15~ -
l T:? 01/15' j ANTICIPATED RESPONSE: l i 2i INSTRUCTIONS:-- , This card terminates the Security event.; .l
.i
.:l.
.-i
-l r
.)
5 i l I
.I
')
l
~1 l
-1 i
-****************************************************************************** _ i THIS IS A DRILL I-
******************************************************************************- 4 i
_ _ . _ . . . . . . _ _ . - - . . a
~ ^ '
.y r , ,
~
7 ^ 4 , l DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE, CARD . f SCENARIO NO. 1990~ Evaluated Exercise CUE' CARD No. 35 ; TO - Control Room Operator -TIMES- 1 10:30- [ r T: 01/30- -!
;5
.************************************************************************e*****'. ,,
THIS IS A DRILL ~ , DO NOT initiatefactions affecting normal plant operations. r t INFORMATJON Start the Motor Driven Feed Pump, and shutdown #2 Main Feed' Pump in accordance. ' with the shutdown procedure.- (( l N
, .i 1
i i
+
?
+
'h t
/)
~
THIS IS A DRILL ,
*********************ve******************************************************** .\.
I, a t
'n
, .ae-w - - - - - , w,-, + =+ .e e-w e =w,-e ---eue<=-< - +-+w-e
i!
.7-73 1 l
~
l DBNPS EMERGENCY-PREPAREDNESS CUE CARD (Cont'd) .., CUE CARD NO. 35-L :TO: Control Roon. Controller' .: TIME: 10:30' -; t l
. T:' 01/30 1
l ' p' ANTICIPATED RESPONSE: , 1 Shutdown the pump. ;
?
i i
'}
l i
,1
' ~
INSTRUCTIONS: None _i
.?
91 4 i b i
-t J
1 i
'l l
- )
S I i J THIS IS A DRILL 'l -
*******************************.'***************************************w******
.1
. _ . _ . _ _ . _ , . . - - . _ n.__.. _ __
7-74 DBNPS EMERGENCY-PREPAREDNESS EXERCISE-CUE CARD SCENARIO NO.'1990 Evaluated Exercise CUE CARD NOi 36: TO:- I&C Technician A'& C TIME: 10:30' T: '01/30 THIS IS A DRILL DO NOT initiate actions affecting normallplant operations.
^
INFORMATION: Repair and' testing of RE 4598BA.is complete and returned to service.
's THIS IS A DRILL l',;.* , }2 ;. lhn"'. *,'A - ~ ff-Q _ _f_ ;.la.
f.;ff f;hb ?l_ f_'f Y ,2_.l t 0 f k_{ h$), l+# l
_ . ._ . . _ _ . . . _ . . _ ~. _ . _ _ _ _ _ !- i 7-75'- i DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)- , CUE CARD NO.. 36 l
"to: I&C Technician A & C ~ TIME: -10:30
- t- T: 01/30 7
i ANTICIPATED RESPONSE: i
, .t l- 1
. Notify the OSC of the completion of this action. i i
t 1 INSTRUCTIONS: 1! i e: i I a I I
,1 l
l THIS IS A DRILL' !
******************************************************************************. {
\
l l t.
.. J 4 7 g ,
L DBNPS ENERGENCY PREPARF.DNESS' EXERCISE CUE CARD
-h O
. SCENARIO NO.4 1990 Evaluated Exercise CUE CARD NO.= 37 TO: RC Personnel: , TINE: 11:05' h E T- 02/05 q l.
b 1 THIS IS A DRILL '
'\ .
- DO NOT, initiate actions affecting normal' plant operationst- q
.c.T INPORMATION :
- [
3 [TheControllervilliprovidethecontaminationlevelsasthe; personnel.are-aonitored and decontaminated. , , 0
- i 1 .'i{
.i i
s F t J THIS IS A DRILL , i
- e . - - . , , . - ., ,. . -n., , ,y .
. ~N ,- 4 , '.a,,
7-77
.]
DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD No. 37- [l TO: RC Tester Controller TIME: 11:05 T: 02/05 j j ANTICIPATED RESPONSE: The RC personnel should ensure adequate contamination control 1 during the personnel monitoring and subsequent decontamination efforts. A body count 1 should be obtained for:the person who fall in the spent fuel pool.
~
j . i I il . INSTRUCTIONS: , Use 'one of the members of the repair team for the, upender job for - the ' contaminated person. During'the monitoring of the personnel for contamination,'the person who fell in-the spent fuel pool and the'RC Tester that are found to be. contaminated. Provide levels as'necessary from attached forms. Su , 5
.l
'f f
ll i I l ' THIS IS A DRILL
1 L ,
-. ,,("
78. 1 DBNPS EMERGENCY-PREPAREDNESS EXERCISE' CUE CARD SCENARIO NO. 1990 Evaluated: Exercise" CUE CARD NO.. 38~ LTO' SFP. Repair Team TIME:: 11:05-T 02/051
***********************************e*********v********************************u TFIS IS'A DRILL
'.D0 NOT initiate' actions an scties. normal ~ plant. operations..
INFORMATION: None ,8 - THIS'IS A DRILL
****************************t*************************************************
I
'7-79 0
ll
- DBNPS EMERGENCY. PREPAREDNESS CUE CARD-(Cont'd)i.
CUE-CARD.NO.- 38~ l ;1 q SFP RC Controller TIME' 11:05- l TO: i T: 02/05'-
' ANTICIPATED RESPONSE:
L)
'q q
INSTRUCTIONS: j Providethefollowingcontaminationlevelsandbodycountprintouts'as.personne1[ - monitoring and decontamination efforts are conducted.- a i RC Technicians j i 2nd: I INITIAL .Ist :3rd.
-LOCATION OF' LEVEL DECON- DECON DECON- >
l CONTAMINATION cpm eps- cpm com Arms 2000 1000 <100 - Chest 2500- 1000 <100 '
?
Waist 1800 300 <100 a i Method-of Decon Shover Shower Worker who fell into the Spent Fuel Pools' q l INITIAL 1st 2nd 3rd e4th LOCATION OF LEVEL DECON- DECON DECON-- DECON CONTAMINATION cpm cpm cpm cpm com Total Body 20,000 3000 1000- <100 Face 25,000 7000 2500 <100 Hair- 35,000 4000 2500 <100 Nasal Smear 15,000 -9000 7500- 5000 2000 Bar- 7,000 5000- 1000 <100- , l Mouth 12,000 7000 3000 .-500 200- . Method of Decon Shower & Shower;&,- Shower & Mouth Rinse-& Damp Svab Damp Svab Damp Svab Damp Svab
****************************************************************************** 3 THIS IS A DRILL ,
~,
l-1
11-I
-. 7-80 '
4 _3
- o. . .
......o- . .......p..-._ _.4 l CANBEtkA/thC AMC0" Il _l- L invesusstional Count Report . Ifprinted: 1l
- o. ._. _ ... _ , .. - . _ - _ -._..-._..o...._. ,
I noe last: fitst: elddle: _l p _. . . . . . I social security / ID: 299-48-2592
, ' file number:' 3011. input: -1 I l . .
- - - l l counted: 09-apt-90 21:11:57 operator: C300,001) MASON _ 1MVIS BESSE TASISCAN L12.11.44' -1 I .
l l esployer: Blu job code /furetion: frequercy of count: 1 1 I . l height: . ins, weight (Ibs.): 39e: - yrs. fl. l .L- - . . - . l Showered before count: Y ' wore special clothing for count: Y; ;1 I sex: M I -. I 11 date/tiae of exposure: 09 APR-90 16:00 . type /aeount of exposure: FACIAL- protective seasures: PC'S- . l. l .
. , ' li l . coseents: 2ND SHOWER I W/0 UCERWEAR RUP. number: 77 l l= 1 o . ..... . .. . .. .. . . . ........ . ... _ . .. ,
l Preliminary Whole Body Count Results:: (Peak Energy Analysis) _ tl
- o. o . o. . . o . o.... o .. o . . o....... o .. . o . .......... .. ..... ... . t i nuclide i energy I activity i I error l Siin i fit I burdenl peat Icentroidl: wirniro 1: consents , ' l' l 1 (kev) l ( uti ) l(2.0SD)]-(I)'l o.....o.o.........p......,_..o..o......o.......o...........o..............._......._'l l (1) I area 1 (ch) - l AC TT GN BB l- .
ICS-134 1 604.6 i l I. _l l [ 1158.941 IGAactivity-5.5142E-03uti l IRURH-106 1 621.6 l l l -_ -l l l l 163.72 l < ]GA activity: 5.430SE 02 uti ~' l 121-95 1 724.1 l 1 1 1 1_ l .I189.571-- lCAactivity;1.2221E-02uti 1. l!!*95 .] 756.7l l~ l 1- I .l l_197.771 (UAactivitya1.1787E-02uti;l' lH-95 1 765.8 l l l l 1 rl . I200.06l lCA activity 6.8759E-03 uti cl-lTE-59 l1099.2l l l l 1 _;283.23(= .lCA activity 1.1687E-02 uCit 1. IK l1460.7I I I d d .,ihN 1372.50.1 IGA acttvity 3.5112E-02 uCi,'l itA140 l 15L2 l l l l [i 11 b $ :l% '.I 405.86 l lG4 activity 2.1352E-03 uti .} l e l" i4 l l l- 1 1 i 1 I 1 .,t I k l C .I Hlipitit g l .I , k ! 1 I I 'l-1 I I G Gi s slMM1 i 1 1 l 1 -l i 1 1 4.R 11 - 1 l- l' I I 1 l I 1 I I I gI I I
.I I
I I l-I : I 1 l' 1 1
-l I l i t i I I 'l i l I-1 I I I I l- I l- 1 I I i r...._..,_.........._.......,_..._.., .............o..............o .o.................._.........<
l totals ]0.2718 I i 17. I totals are computed from the fiM1 (raclide amlysis) report j
....... ....... . o.o. ... w o ..... ...o.... =o .... o...... ..............o.................. .. o........ .
!counttime: 300 1 input I sus of counts I fraction.1 calibrations used I wnrnirn levels l-p............. ... ............ . _........ p... ...o.................... . .... p.........= __
=....o ............
Iamlysislialts: 1 11 169623.l 0.713 l energy: 11 24JUL-39l tit (ft): 3.00l l low: 11.0(kev)1 0! 68261 1 0.287 iTWH.1: 7 24JUI.-89ig)in(GN): _ 2.000 I lhi9h: 2017.9 (kev) l 0l 01 0.000 l efficiency: 23 26-Jut-89 I activ:ty (AC): 1.001 I 1 0l 0, 1 0.000 Ilibrity: 101. c6-APR-901 I :.urden (m: 1.0 l l l 01 01 0.000 ibict3round: 1258.07-0EC-89l -l
; ! 0! C. 0.000 1 i i o.................... o......o..............o........ g..............................g...................... g.............
I l Feviewed by: Dite: l I facility: DAV13-BESSE SAD Hl.IH nGMT o.... ............ ...................................................................... .... ..............................c
7-81' l: M . ..: __... .. _ ., .. . . . _ . . . . . . . :_ 4,J . _ CA@EttA/RMC ADAC05-il 1- -Investiptioul Count Report . I printed:- I _1:
. . . . _ . . . . . , _ . . .. +_ - - ,' .
I name last:- first:- l
.. . .. ... _ . _siMle: _. ,
i social security / ID: 299-48-2592~ filenumber: 3011. input: 1 l-l' l l counted: 09-Att 90 21:11:57 operator: 1300,0011 MASON : DAVISDESSEEASISCANLI2.11.44_ l 1 -
- . l l esployer: B H jobcode/ function:. frequency of count:- :
l i ~ 1 l-. height:J ins. -wei9t(lbs.):- h a3e: yrs. I l- . . ..
. - l-1; sex: H ;showeredbeforecount:Y vore special clothing for count: Y- . l-1 - . I- .I e te/Line of exposure: 09-Aft-90 16:00 type /anount of exposure: TACIAL protective seasures: PC'S' l 1 - !
I coseents: 2 0 SHOWEt I W/0 UNDERWEAR ' RWP roeber: 77 L1 1 Ll ' -4 n
.. . _ _ ... _ ... [. . .
1 Frellel uty Whole body Count lesults- (Feat Energy Amlysis) 13
. .. 4 .......+ . _ , . . . , ..+ . _ . . . . . . , . . _ . . _.c l nuclide i energy I activity iIerrorl 9 tin l fit i burdent penk \centroidl wirning_] consents- l l l -(kev) I ( uCi 1 l( 2.0 SD)! (I) l l (D -1 area I (ch) lACETGNFBl- ! ... .. . 4. ...... ........... ... . ... _ .. . ...... _ ..... ..... . . ... . ... ...,
1C0-58 1 511.0 l 9.6416E-02 1 13.2 1 0.03 1 0.56 1 3.3 1 24 % .-1 135.50 I ni i lautH-106 I sll.t 1 0.1385 l 13.1 1-0.08 1 0.57 1 23.1 1 263. l'135.62 l AA-1 1 lCS-137 1 661.6 l 5.2013E 03 l 42.7l-2.2010.621-0.0l 393.l170.42l AA :I l ,
]CS-134 ] 795.7 1 0.1230 1 3.7l 1.4610.701 0.6l 8617.I210.51l l l: :
1C0-58 l 810.7 l 8.5592E 02 l 5.5i-0.7010.711
< 2.9l 6022.I209.84I. AA 1: 1 IMN54 -l 334.8 l-1.6907E421 36.1 1 0.01 1 0.67 1 0.5l 1358.l217.40l I i 1C0-60 11112.210.1562 l- 2.9 l -0.24 l 0.851 13.0 I 11147,1300.83 i AAi 1 IFE-59 !1291.512.8431E-021 51.5l-0.10l1.12l 1.4l 857.I330.45l -AA L 'l
- 100-60 l1332.510.1494 1 3.4 l -0.16 l 1.261 12.41 10333. l 340.3G ' AAl. I junknown?l 135.1l9.9401E-031 62.2 1 5.10 1 1.27 l 0.0 l. 694, 1 31.84 l h i . !
lCEPR-144 1 133.5 ! ! 1 1 l. 1 i 37.5?l- ih A activity 9.7075E-02 uti 11131 l 364.4I i c't fl y OI" y [ 97.88 l- lMDAactivity-8.6197E-03uti ! l Ruth-1031 497.01 11431 1 529.5 1 -l I{ n! p,jlj g! pij n -[ 3(#p l
; h,1 gi=
J1
. L'l Q
, t131.95l 1140.25l
'inDAactivity.7.5374E-03uCi :
lhDAactivity~7.2109E-03uti ! lBA-140 l 537.31 km Tb d7 N. , c 71 w
*%*f U 1142.24l -lMDA activtty 3.1247E-02 uti I
$69.2 l i150.36l 'IMDAactivityL3.6956E-02uCi )
1C5-134. ..!.. ....... ...........- l l l l l
'l tottis 10.2718 17. I totils are conuted from the final-(nudide aml s............................................................................................ysis)reporti-l l Icounttime: 300. l innt ! sus of counts i fractin cilib ntions used I warntrig levels 1 I-i.... ... .. ........................ .... .. . ...I........ . . ............... ..... ...............................,
Iamlysislimits: I i 169628.l 0.713 1ene:3j: 11 24 W A 9 I fit (EU : 3.'00l ! llow: 11.0 D eV) l 2- j 68261.l 0.227 l IWM: 7 24-jJ'-89 l pin (GN): 2.0001 ; I high:. 2017.9 D eV) 1 01 0.t 0.000 1 efficiency: 23 26-Jut-29 ' wtivity (AC): 1.00l 1 l l 't O.l 0.000 l library: 101. 06 AFE-90 1 % burda (10 : 1.0l 1 1 1 0 , 0.l 0.000 lbxiground: 1358, 07 4 7.-2) [
- l l 01 0.t 0.000 l l l l
_......... _ ..........................- =....................... .............................................................. _3 1 i k iwec by: hie: i l i nilit i: 0Av!3-6E35E RAD .i:' ?: -M i
.................................. - ................... ........ ........ ...__ ....... ... ............ .................. j 1
i 1
F 7-82^ .t . W d pg
/ e ,
7
% ./ s
. _ . _ ...; 2
! +._- . _ . . . . _ . . . ..__......._.._+___. 1-
'l'CAN9EttA/IMCADAC05 l 1rrvestiptional Count Report' lfprinted: )l- .
cl fitst: eiddle: l: l.namelast: . - .. _ _ -
. _ . . _ .., r file numbef.: _ 3011. Input: 1 l
-1 social security / ID: .
-l l'
l;
. DAVIS BESSE EASISCAN L12.11.44 ;
counted:09-APR-9021:11:57- operator: (300,001) MASON . { l 1
'l job code / function: - frequency of count:L l esployer: B&W _
l , I- - age: yrs; l l= height: ins. weight (lbs.):, l l shouered before count: Y vore special clothing for count: Y -l
-I sex: M' l l' .
protective seas ~u res: PC'S I ;
- l date/tise of exposure: 09-APR-9016:00; type /aecunt of exposure: TACIAL .'
-l l
RWP number: 77- l I consents: 2ND SHOWER 1 W/0 UNDERWEAR .l$~ , l . .... .... _ _ . . ._+..
.... .. . . _ . ... ... .- . . . . . . . . . . . . . . . . . . . . . _ . .._....- _....+-
.Einal Whole Body Count Results (Nuclide Anslysis) \~
i _ .... . . . . . . . . _ _ . _ _ . . .. o j, . ... ~ . . ..... ..,.. _ ... , _ . .+ ... _ +...... .... . ............ l
/,
Inuclidel activity.lIerrorltordenl critical l- 1 consents l l ( uti ) l(2.050)) (1) l orpn l l 'l V; N i l
. .. .... ._. ...._ ... 4 .. . ..... _ . . ... .. . ... _ . . . . . . . .
- 1 -
100-58 l9.6416E-021 - 13.21 3.3iLuuG l l 1C5-137 l5.2013E-03-l '42.7l 0.0lfBODY- -l l l: ll.,
-lhN-54 11.6907E021 36.1l '0.5l LUNG l l 100-60 10.1533 l 2.2l 12.0l LUNG ], _l. l ,
i .1 I l I I I I .3 I I i 1 1 I i ^
.x %M I i l l l ,. . ,: l l l l \ +
I l i i I 1 l ... ,'..i. -
.v i n.oO4.>.. n
~
I l l l l l 1 , . P,N-- I
; 5. 4 ;
i I l l l l l Oy,h.. 7p. h. ;. c. w; i i i i e i t i I : 1 I
$p -
I I v$ g.- s 3 l i i i I I 1 . ! I l I I I I l l l I
. ........... a............ ..... ...... ........................ ...................................._............ ;
Itottls 10.2719 -l l 17.I l- I l
-ltot:11torden lung: 16.6 G.I.: 0.0 total body: 0.0 thyroid: 0.0 -c her: 0.0 l
[ ;. ............,
.............. ..... ......._....- ............ ......-- -2 I mlysis energy range: 11.0 to 2017.9beV. nuclide librity used: 101.1sst updited: 06-Aft-90 .
1; L l calibri'. ion energy: 1124-Jul.-89 EkHit: 7 24-N.-59 efficiency 23 26-30:.-39 bidground hie: 1358. 07-DEC-89 l I l l e. l ' . ienewed by: Dite: I I i t g I it:ility: DAVIS-!< ESSE l
.....................................................'OHl.NC.T .........................................................................
l 1
4 0 4 ,
' i 7-83
< DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD: ,
. CUE CARD'NO. '39
. SCENARIO NO.:1990 Evaluated Exercise.
.TO:' Control Roon Staff
~
TIME:' '11:10-sT --02/10 '?
-3
******************************************************************************=
I THIS IS A' DRILL ~- DO,NOTinitiateactionsaffectingnormallplantoperations... 1 p ' \ INFORMATION: t Make the following announcement over'the Gai-tronics systems "THIS IS A DRILL.' ' ATTENTION ALL PERSONNEL,- ATTENTION' ALL PERSONNEL. .' A SITE) AREA EMERGENCY HAS BEEN DECLARED. JALL MEMBERS'0F THE ONSITE EMERGENCY; RESPONSE ORGANIZATION REPORT TO YOUR DESIGNATED EMERGENCY-RESPONSE FACILITIES. 'ALL'
. NONESSENTIAL PERSONNEL VITHIN THE PROTECTED' AREA EVALUATE TO THE TRAINING CENTER
.i
' ASSEMBLY AREA IMMEDIATELY. . 0WNER CONTROLLED AREA ASSEMBLY IS NOT REQUIRED.".
Repeat this message once. t i ] i f l 1 1
.- i b
THIS IS A DRILL
'. 84' ' DBNPS EMERGENCY, PREPAREDNESS CUE CARD (Cont'd)- i CUE CARD No.; 39' l . 11:10 TO ' . Control Room' Controller: TIMES-I
- T: 02/10 ANTICIPATED RESPONSE:
Have announcement made, Simulate Owner Controlled Area Assembly. 1
- l INSTRUCTIONS:
Provide!this card when a SITE AREA EMERGENCY har been declared, a 1 O> 4 i
'I l
l THIS IS' A DRILL
, -d b .7-85
.m DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD-
;1., SCENARIO.NO. 1990 Evaluated Exercisel CUE CARD NO. 40-
]
TO: -Ottava County Sheriff Dispatch.! , TIME: -11:10 l
'l
-T: 02/10 j
-)
i l l THISlISA~ DRILL i
- DO NOT initiate actions affecting normal. plant. operations. 'l j
s INFORMATION:. Do Not' activate sirens.(Simulate Only)h Do Not activate EBS (Siaulate Only).; .
~i
)
4 l 1 i c.;
*************+****************************************************************
THIS IS:A DRILL !
. i ,-~, - -_ . , - , , , , _ , , _ , _ . , . ~ , , , . . . _ - - . , .
.7-86 DBNPS ENERGENCY PREPAREDNESS CUE CARD (Cont'd)
CUE CARD NO. 40 TO - Ottava County Controller TIME - 11:10 T: 02/10 ANTICIPATED' RESPONSE The dispatcher should correctly describe the steps for activating the Prompt. Notification System and EBS. INSTRUCTIONS:- Provide this card when1the Dispatcher receives.the notice of the SITE' AREA EMERGENCY. e
'\
e THIS IS A DRILL
****************************************************************************** g q
i 7-87 i i
- l
. 5 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD.
SCENARIO No. 1990 Evaluated Exercise CUE CARD NO. 41
)
'TO: Lucas County Sheriff's Dispatcher TIMES. 11:10 l 1 :
T 02/10 :
******************************************************************************' l THIS IS A DRILL ,
DO NOT initiate actions affecting normal plant operations. I
****************************************************************************** i INFORMATION:
-Do Not activate sirens (Simulate Only).
Do Not activate EBS (Simulate Only). 5 i
?
q .
}
h i 4
****************************************************************************** j i
IRIS IS A DRILL ; ({])
?
I h
.> r
7-88 t l DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) l CUE CARD NO. 41 g I TO: Lucas County Controller TIME: 11:10 T: 02/10 1 ANTICIPATED RESPONSE: The Dispatcher should correctly describe the steps for activating the Prompt l Notification System and RBS. l i { l. I i INSTRUCTIONS: i i Provide this card when the Dispatcher receives notice of the SITE AREA i EMERGENCY. l Ol
)
l i b 1 I i i t t t 1 f
****************************************************************************** l THIS IS A DRILL f
******************************************************************************- 'gggg
, .- - w. - - . . .- . . , .- --, ,-.#. . , - - - .r.. .
- , .- - , . - . . , - - . . ~ . _ . . . -
I 7-89 ; 1 l DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. 42 SCENARIO No. 1990 Evaluated Exercise f-(% l TIME: 11:10 f l TO: OSC Repair Team at AD 111 : T: 02/10 ! , i i , i ****************************************************************************** l i THIS IS A DRILL.. t DO NOT initiate actions affecting normal plant operations. i
***********I******************************************************************
i INPORMATION:
?
l . The following targets are present on D-1 Bus: AD 111 50/51A INST. 50 GS-AD 110 51-5A 51-58 ; i There j There are indications of excessive heat on the back of the AD111 cubicle. . is a bus lock out present. ! 1 i i I i I i [ I i THIS IS A DRILL f
****************************************************************************** f a
f
. . - - . . . . . , . . . . . , , . _ , _ _ , . , _ , . . . . . ~ , _ . . , - . _ . . . . _
7-90 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) l CUE CARD NO. 42 i TO: OSC Team at Breaker AD 111 TIME: 11:10 l l T: 02/10 ; l ANTICIPATED RESPONSE: l Inform the OSC of the damage. Obtain permission from the Electrical Supervisor
-and the Shift Supervisor to clear the Lock Out. Inspect for further damage and t repair. j r
l t INSTRUCTIONS: As asked relevant questions by players, provide the following information: After routine maintenance on AD 111 (HPI pump #2) a can of cleaner was left in l the cubicle. When the breaker was operated, the can punctured and sprayed its l contents in the cubicle causing the fault and bus lockout. There is l considerable damage to the breaker, and its cubicle. The bus vill not be , returned to service, but provide indications which will keep the repair team ; working to fix the fault. i l i s i I i I
-THIS IS A DRILL , =******************************************************************************
1 7-91 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUB CARD CUE CARD NO. 43 SCENARIO NO.1990 Evaluated Exercise i TIME: 11:10 l TO: Control Room
- T: 02/10 l i
l THIS IS A DRILL' l l DO NOT initiate actions affecting normal plant operations. i INFORMATION: None ; i -! r i f I i I l THIS IS A DRILL h,
- %/
t t f u , .r ~ , - - , , - ,
, -n,.. -.,m, 4., , - - , e ,+ , . . ee,,, ,-m.,..,e v ,. ~,,,e-n,-- s
7-92 t DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 43 TOs. Control Room Controller' . TIME: 11:10 .j i T: 02/10 ) I AlfrICIPATED RESPONSE: < e None ! i i t i INSTRUCTIONS:' ,
.When HPI Pump 42 is started the D-1 Bus will trip off with the attached alarms. i t
l-l l
'l i
l i l i L : l > i L-t i r 1
****************************************************************************** l THIS IS A DRILL i 1 , .,..-_.,,_...m.. . .,_,..y-.., _m. . . , _ _ . _ . . , y ., , _ _ . , ., _,.-...,_,...,._.m,_., , _ . . . . , . , . , , . , . _
l 7-93 ; iiio l 1-ELECTRICAL DISTRIBUTION . EDG 2 , ( ~- . EDG 1 l 480V 4160Vl . .
, 13.8KV. .
l4160Vl4.80V:
)
(DC1 (DC 1 C *1 MrWR AC
'l 0 gg
*l. gf 9 188k FAULI rayLt IAULI rautt FAul.T F.AUL1 1
- f.AAT , ,
c- . . CDC 2
. .WWR ' CDC 2 CDC 1 WWR IU #"" "U" #"R IU' #"" WH M Dr s. 2 , CURRCNI AIR RCVR CDC I WWR AC tl D2' CCl 2 01 PRC$$ 40 AsR RCvn CURRENT DNCR , Opek . CR/IRSL FA%I H8 Hi fAUL1 DNCR/IRDL DNOR ,
PRC$$ LO em,,. y' W. .o n. Aux <= su -un. CoC 2 ,,,, coC i '~ *
- g. ,,,, ***
r( R to *E'el'
,y,c, F ^^ t d ,
E , N. ' 7"I - YRet rt w to [* tat"C' ["Iout"C' ,
*. . iACC*' :
~$' i ." o'f,* i,
.J,R,2". -i,ifC,L asC ~5 A 4 #,,,',a, s,i!!L, m
#,,,",.",, miAu' rAxi
< =T .
m
. GUS D ,' .N5 01 - DV$ F1 EDC 2 OCI DuS (I DOS Cl 905 A DC PANCL tr oAv =
j
-s ws atAOC =s pu,R 2 5 oar in Lg te
==
NINW , NINW , to , 'ws N1Ned.. . , NINW , 'lvm.t Lg HI l ,
. .. . - - . - g. .
"V mv DC tus i SATI RW DC WS DVS 19R ~ " * "
Bus VAR
",',,#^ vettact i WN .2*
*: VOL1ACC, tRBL ROL
',*, [V3 Lo
,1 R. t , .I SYS .
,R. .to . .
A C D E F G. H I J K B . 2
' ~
[ LETDOWN #AKEUP _BA .
,,... . .. 0# '
LE TOOWN PWP 1 PWP 2 . 1 ^00 I. RAD HI LUBE OIL LUBE OIL . PRESS LO PRESS LO A
- e. . o . . r MU MU OA I LCTDOWN
- 2 PRCSS Hi TK LW HI TK LVL LO ADD TK 2 TEMP i i.
.~';'"' '
OA * - WU uu LETDOWN HEATED- C
} " H' TK PRESS Hs TK PRESS LO ROO"' '
T[uP LO *
'LE TDOwI
- og ug MU WU BA .
4 pgt y FLOW Hi TRN 1 FLOW Hi TRN 2 ADD TK 1 LvL' i 3p g, w . BATCH I BA 5 MV FLOW HI ADD IK 2 LW I 6 A B C __ D y ww. -a-y ,.,,sc.,.--,,--w -aw-.,- .-9+%-.w,-, ,e. ,,,_w y,,..mg.ge.w
- 7-94 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 44 TO: OSC Team at D-1 TIME: 11:20 T: 02/20 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
INFORMATION: When AD111 is racked out the remains of the spray can is found. There is damage to the breaker contacts and considerable damage to the bus work. O , THIS IS A DRILL () ****************************************************************************** ~ ~ - j
_ _ _ _ _ _ . _ ~ . _ . . ___ . _ _ ~ _ _ . . 7-95 4 DBNPS ENERGENCY PREPAREDNESS CUE CARD (Cont'd) i CUE CARD NO.- 44 i OSC Controller At D-1 TINE: 11:20 TO: T: 02/20 j; r ANTICIPATED RESPONSE: , Notify OSC. INSTRUCTIONS: ; i Vhen the breaker cubicle is opened, simulate racking out the breaker and discover the damage. i I ej i ( I i l E
****************************************************************************** t THIS IS A DRILL >
l
****************************************************************************** 'fi i
4 i
~- .. - .- - , . - - . - - - - - _. . - . . _ _ . . -- . . . ...
I 7 96 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD' SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO.- 45 TO: Control cell TIME: 11:30 T: 02/30 j
\
****************************************************************************** i l
l THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. q INFORMATION: f t Call the Emergency Facilities Services Manager as'the various' Assembly Area i
. Coordinators and provide the:following.Information: The following number of l personnel are assembled as listed Warehouse AAC 36 ,
~ Service Building #3 41 l Training Building ist Floor 28 i DBAB (at desks) 18 l
, DBAB Annex (at desks) 51 1 l DBAB 2nd Floor 63 ! l DBAB Mezzanine 7 j Personnel Processing Facility 9 !
?
I I i
-t
?
****************************************************************************** i i
THIS IS A DRILL .! O ************************************** *************************************** i i I i
7-97 1 l DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) 1 CUE CARD No. 45 TO: Control Cell' TIME: 11:30' i T: 02/30 ANTICIPATED RESPONSE: ; t
. None 1 i
r I i i INSTRUCTIONS: i t None , f
}
G! ! l i 1 e I f i l i i i s t . I l ! I e THIS IS A DRILL I h
i' 7-98
'i DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD i SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. 46X l l( ) j 70: Emergency Director TIME: 11:30 T: 02/30' i l
l
?
f THIS IS A DRILL i DO NOT initiate actions affecting normal plant operations. ; ( ' L
****************************************************************************** l INFORMATION: .
Declare a-Site Area Emergency in accordance with EAL 2.A.4, RCS Leak Rate > 50 [ spa and > HPI capacity. i l l h t i f I r i f 1 l 5 ( I 1 i } L i' 1
****************************************************************************** t t
THIS IS A DRILL i
****************************************************************************** f i
t f
i 7-99 , i DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) i CUE CARD NO. 46X TO: ECC Controller TIME: 11:30 l T: 02/30 ! ANTICIPATED RESPONSE: Declare the Site Area Emergency in accordance with EAL 2.A.4. , t f INSTRUCTIONS: 1 L Provide this card only if the Emergency Director does not declare a Site Area l Emergency in accordance with the EAL. , i i i G!, i t I l f i l I s
]
q l 1 THIS IS A DRILL l
7-100-DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD-
. CUE CARD NO. 47 SCENARIO No. 1990 Evaluated Exercise i
TO: Emergency Director TIME: Approx. 11:40 j T: Approx. 02/40 . i i ******************************************************************************- THIS IS A DRILL !
. i NOT initiate actions affecting normal plant operations. ,
****************************************************************************** t f
INFORMATION: For purposes of the Exercise, controllers are instructing personnel assembled outside the Protected Area to return to work. Do Not take any actions to- l,
-expedite this process. ,
Simulate that they are assembled in the Owner Controlled Area for any future ,
?
activities that they would-be involved with. . Ensure the Emergency Facilities i Services Manager, the Emergency Plant Manager, and the Emergency Security Manager are aware of these actions. O l t i
}
i I i THIS IS A DRILL ; l
.,_s .,,; , , , , , . . . , , . . . , . ,,,m,.e
i l 7-101 ! l l DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 47 TO: ECC Controller TIME: Approx. 11410 , i T Approx. 02/10 ; ANTICIPATED RESPONSE: ad he Ene gen Secu i >' Manage i INSTRUCTIONS: p Provide this card after the controller in the Protected Area has contseted you. l I 6 9! 1 i h 5 i e I t l h
,I THIS IS A DRILL
.........*......................*..........................*.................. qq;p 1
7-102: l l L DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CAPS i
)
SCENARIO NO.' 1990 Evaluated Exercise CUE CARD NO. 48 j TO: Emergency Director TIME: , 14:00 t
.i T: 05/00- )
t b 1 THIS IS A DRILL ,; J. l DO NOT initiate actions affecting normal plant operations. ; INFORMATION: i Have the following announcement made on the ERF PA system and the GaiTronics: 1 i
" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL. THE EMERGENCY PREPAREDNESS' EXERCISE HAS BEEN COMPLETED. THERE WILL BE NO FURTHER DRILL ANNOUNCEMENTS." j Repeat this announcement'once.
O 1 i l. f i l l
.I
)
I THIS IS A DRILL
i
-l
. 7-103 I
DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. 48 TO: ECC Controller TIME: 14:00 T: 05/00 5
' ANTICIPATED '
RESPONSE
Make the announcement. -l i 1
)
I t INSTRUCTIONS: ; i Vhen directed by the Exercise Coordinator provide this card to the Emergency.' Director.. l Note to all Controllers i After a break conduct a facility critique and direct the' facility' manager to j attend the Reentry / Recovery discussion in 209/210. ) el, 6 1 h i a T
****************6*************************************************************
THIS IS A DRILL ~ f
.t
+
t 9 7# t t =--'w=yr ' e - ' - 'W'T D 7 p ---we- r-
- 7-104 )
i I DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD j
/)
_ ( ,j 4 SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. PR-1X I j TO: JPIC Manager TIME: 09:45 1 T: 00/45 I
*****************************************************************.?************
J THIS IS A DRILL -l 1 l DO NOT Initiate' actions affecting normal plant operations. l INFORMATION: .! Call the Emergency Control Center. Request information on the followings j
- Plant Status
~
i
- Cause of the emergency declaration ,
- Potential for conditions to vorsen- I I
~!
l r i l j f I f I
?
****************************************************************************** t I
THIS IS A DRILL l , k
- h
- k kkk k k 1
l l l
. .. _ _ - . . . ..~.m.,. . ...s., . , - . . , . , . _ _ . _ . _ _ _ . . . , . - . I
i 7-105 l t 1 DBNPS ENERGENCY PREPAREDNESS CUE CARD (Cont'd) j CUE CARD NO. PR-1X TO: JPIC Controller TIME: 09:45 l
)
T: 00/45 ; ANTICIPATED RESPONSE: ] i EON or other official in the ECC should provide emergency information to the ! JPIC Manager as requested. i i l I i i INSTRUCTIONS: l ' Observe interaction of JPIC Manager, JPIC Vriter and Company Spokesperson $ ' following receipt of plant information. Discussion to call the JPIC staff l should-take place due to the significance of the emergency. l t l Ol, I l l l
)
l l i l THIS IS A DRILL
. . . - . - _ . - - . . , - - _ . -- , - , . . . . - . . . , . . - . . . - _ . . . - - . . . . - . . . ~ . . - .,
7-106 DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR2 SCENARIO NO. 1990 Evaluated Exercise TO: Control Cell TIME: :09:55 - 11:00 ; I T: 00/55 - 02/00 -l
)
THIS IS A DRILL , l t DO NOT initiate' actions affecting normal plant operations. l
+
INPORMATION: i Use the following questions only during the ALERT classification. Place calls at the indicated time. Call the Edison Operator at 5000. State "This is a [ drill" for all calls. Log responses,to questions. Record the call if* tape j recorder is available.
- l. Name San / Shelly Majors ;
- 2. Town: Toledo.
I'm at radio station VXYZ, 950 AM. We've just been informed by Ottava County l O officials to announce closing of Crane Creek State Park and to tell boaters near Davis-Besse to leave the area. Supposedly this is due to a disaster at.the -! il plant. Our next news goes on in five minutes and I need ansvers to some questions, so here's the first one. l Is this an evacuation? What's the problem and is the plant still running?. =6 i How long vill it last? < What should the people do? vhy didn't the sirens go off? Is anyone at the plant injured? l Thanks, if anything changes let me know right away. Call me at (provide f your extension). t i
'I >
l
)
i THIS IS A DRILL l
6 7-107 y i DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR2 TO: Control Cell TIME: 09:55 - 11:00 ; T: 00/55 - 02/00 l l ANTICIPATED RESPONSE: j JPIC Manager .JPIC Vriter or Company Spokesperson should respond to questions. e
~i
- - Call back number should be requested. !
i i INSTRUCTIONS: j Provide extension you are using. f i t i 1 O! : I [ t h 1 1 i THIS IS A DRILL I
.1
- j. ****************************************************************************** .
l l
=t 7-108 l 1
i l DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD ^ SCENARIO NO. 1990 Esaluated Exercise CUE CARD NO. PR-2(Cont.) f TO: Control Cell TINE: 09:55 - 11:00- ! l' T: 00/55 - 02/00 7 i THIS IS A DRILL ; DO NOT initiate actions affecting normal plant' operations. i'
****************************************************************************** -i INPORMATION: t
- 2. Name: Lou LaRue Town Port Clinton !
I I'm from the Port Clinton News Herald and got a tip that Davis-Besse has had a' big emergency. ; What happened? --- How many people were injured? Is the public in danger? . --- When vill it be fixed? Hov large is the hole in the reactor?
' OK, thanks. This is a drill.
- 3. Name: Dean /Deena Douglas l Town: Toledo y I'm at VHIZ, TV9. Our news desk was asked to report on your emergency. ,
Vhat is all this talk about an emergency at Davis-Besse? , Hov long has this problem been going on? Is there any radiation problem? - Why is the park and lake being evacuated? Are you sure there isn't any radiation getting.out into the air? This is a drill. THIS IS A DRILL () ****************************************************************************** !
..,.,r. , , - < - - - , . , - , , _ _. . -
p.- ,,y,-.,,- . , . . -
. _ _ _ _ - - _ _ _t-7-109 i
)
DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD N0; PR-2(Cont.) SCENARIO NO. 1990 Evaluated Exercise TO: Control Cell TINE: 09:55 - 11:00 , T: 00/55 - 02/00
****************************************************************************** j i
THIS IS A DRILL i f _D0 NOT initiate actions affecting normal plant operations. l
- ****************************************************************************** .i INFORMATION:
s
- 4. - Names Benny Dover Town: Toledo
- Hi, this is Benny Dover from the Blade. I heard on my car radio that i
~
Davis-Besse is in trouble again. vhat's the problem? --- Is anybody, contaminated? l' What actions have taken place? --- - Is public safety a concern? How much contaminateo water is leaking and where is it going? -: Are the plant workers evacuating? --- This is a drill. !
- 5. Name: Stacy Palmer Town: Clyde .
I was going to take my kids to Crane Creek today and then I heard about some . kind of nuclear problem on the radio. The DJ said it was an alert. l What does that mean? If there isn't any affect then why is the park closed? i What should I do if it gets vorse? l 3 i i h
****************************************************************************** l THIS IS A DRILL
.9~
t w . , , .,. .~ --- ,r. e . ..n,, , -.s - . - , , -. - , .,,--.n. _ , . . ~ , , - - - , ,
.. - . - ~ -- -~ . - - _ - . . . - - - --
110 - 1 L ! D8NPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD l SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. PR-2(Cont.) !. TO: Control Cell TIME: 09:55 - 11:00 [ l T: 00/55 - 02/00- j i l
******************************************************************************! -f l
THIS IS A DRILL ll I DO NOT initiate actions affecting normal plant operations.
******************************************************************************- f INFORMATION: .
f
- 6. Names Steve Pike i Town: Columbus l; I' calling from Columbus, TV2-VILT. We got a call from the' Governor's Press l Secretary saying he had to cancel an interview because of an emergency at !
Davis-Besse station.- According;to him the Governor must respond to the i accident. ;
+
What does Alert mean? ! 5 Vill you FAX any information you have to me?' (Provide control cell FAX number { if agreed.) . What other governmental officials are involved? ; If-the radiation gets out can it get to Columbus? ' I'm going to send a crew out. Where should they go when they get to the plant? Ve'll need someone to help show them around, vill you be available. j 1 l l j ') L 1 l l 1 1
)
i THIS IS A DRILL I a
i 7-111 : i l DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD CUE CARD NO. PR-3X SCENARIO NO. 1990 Evaluated Exercise TO: JPIC Manager . TIME: 1'0:00 ; r T: 01/00 ,
****************************************************************************** i THIS IS A DRILL- $
l {NOTinitiateactionsaffectingnormalplantoperations.
****************************************************************************** r 9
Y INPORMATION: t Commence notification of JPIC staff using call tree activation. Notify and call- l' in all JPIC staff positions required for full staffing. . : i l b I i t
)
l ' 1 i l l l l 1 THIS IS A DRILL 1 o
7-112 l b t DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-3X TO: JPIC Controller TIME: 10:00 l l T: 01/00 t I, ANTICIPATED RESPONSE: l l . JPIC Manager commences JPIC staff notifications. l l
?
i 1 INSTRUCTIONS: ! Log length of time required to notify JPIC staff. ; i
'l I
I l l ' i P l $ 1 I i i t THIS IS A DRILL i. F 9 L
-, . , , . ., , - . , - ., - .+ ,
. - - .. ~ _ . -. .. _.
7-113 DBNPS EMERGENCY PREPAREDNESS ~ EXERCISE CUE CARD SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. PR-4 g TO: Hock Media Leader TIME: 11:10 j T: 02/10 I 1 i l ******************************************************************************' j THIS IS A DRILL , 1 DO NOT initiate actions affecting normal plant operations.
****************************************************************************** l l
INFORMATION - t l Enter the alternate JPIC via the media entrance. Upon entrance and completion i of registration, ask for plant conditions, information on persons who are ! affected, public safety recommendations, and who vill be presenting information. . I () l [ i
'l
?
\
t i 1 i i i THIS IS A DRILL l ([]) . t I
~?
- . . . . - . . ~ . . , _ _ _ . . - . . .
7-114 i ! DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) CUE CARD NO. PR-4 l TO: JPIC Controller TIME: 11:10 < T: 02/10 ; 4 ANTICIPATED RESPONSE: ; Observe the media Relations Assistants registration process for arriving Media : representatives. : { f INSTRUCTIONS: 1 None r i s h i , ) \ l (. i 1 l THIS IS A DRILL
. . __ o
m J 7-115
-D DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE' CARD SCENARIO NO. 1990 Evaluated Exercise- CUE CARD NO. PR-5:
-x To: Control Cell .Public TIME: ' '11:15 - 12:001 T- 02/15 - 03/00
****************************************************************************** +
1 THIS IS A DRILL-f
- DO NOT initiate actions affecting normal plant operations. b Ik INFORMATION:
Place calls'during the indicated. time.. Use these questions only during.the Site Area Emergency classificatien.- Place calls as frequently as pessible.: Each - Public_ Concern Operator should respond-to-one call every five minutes., Repeat-
' questions if'necessary. : Record call-if-tape-recorder-i< .vailable. . State "This is a-Drill" for all calls.
Calls should be placed'on extensions l6047 or 6048. O h THIS IS A DRILL y - e, i-
4 'L e
.ff ) j 7-116
-i DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
CUE. CARD NO.- PR-5' - T9: ' Control' Cell TIME: -11:15 .12:00 > i T: 02/15 - 03/00 . ANTICIPATED RESPONSES. Public Concern Operators should respond.to questions. . Call back number should~ I be requested. . l i INSTRUCTIONS: .; Provide extension you are using. . i i i l Ol . i t i t
' s f
****************************************************************************** s THIS IS A DRILL i
_ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ - _. ,, -- + - ---v-- e t
. 7-117 L
DBNPS EMERGENCY PREPAREDNESS EXERCISE' CUE CARD '- . . . -4 l SCENARIO NO. 1990 Evaluated Exercise ; CUE CARD NO. PR-5(Cont.)- : y..
, TIME:' '11il5 - 12:00 70s Control Cell-Public - -
1 T: 02/15 - 03/00 I THIS IS A DRILL D0 NOT initiate' actions affecting normal plant l operations. ,
****************************************************************************** g i
I INFORMATION1 J
- 1. This is? Jill / John Richards.-' Hello,,I say-this number on' my'televisio'nand: 1
; thought:I should call.' I' live in Toledo. What is the latest on'the
~
L . l emergency-at Davin-Besse?- Do you think we are safe hereiin, Toledo?; What-- ! is the difference.between an Alert and a Site Area' Emergency? This is a j (Provide the operator-our telephone number if requested. ' Note thei drill. time your call was' returned)., j l
- 2. This is. Karen / Devon Dell. I' live in Genoa.- My' kids are at atday care. l l
center in-Oak Harbor and I work in Port Clinton.l I'm a single parent and 'I
, can't get over-to pick up my kids because of the traffic jam. If you move j
my kids, where vill'I 'be able to find them?- I'm really worried, what -; should'I do? (Your kids-are at. Tiny-Tots Play School. LYou'have.two sons, a ages 2 and 3.) , s
- 3. Hello, This is Paul Fenton.: I' live about 12 miles south-of'0ak Harbor.
I'm outside your emergency zone, I knov,;because I just saw the map on TV. I'm still vorried because no line on-a map'is going to keep 1 me-safe from radiation. Should I be doing anything special like going to-the basement or filling containers with water, or just what am I supposed l to do? ' i
- 4. This is Sue /Stan Keller. .I heard the sirens again and this time I'm going to Fremont. That is were I'm supposed to evacuate to, right? .(Caller lives in Graytown.)
]
a
, 1 THIS IS A DRILL I
l
7-118'
,I o ,
l 1 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD a
~
CUE CARD'NO. PR-5(Cont.) SCENARIO NO. 1990 Evaluated Exercise { TO: Control-Cell-Public TIME .- 11:15 - 12:00 i
]
T: ~02/15 - 03/00 a i
.I THIS IS A DRILL: 3 D0NOTinitiateactions;affectingborealplantoperations. {
. ******************************************************************************- ]
INPORMATION: l
?
~ '
'5. Names Ann / Allen Jones.- What's going-onLout'there? I own a bait shop in- i Bono. Some of my customers are getting angry / because the rangers 'are ~.
(sending them out of the area. People vant refunds and my charter business3 for-the day is lost. Who's gonna. pay for this?: i
,a
- 6. Names Barb / Bob Reeler. I' live on Duff-Vasha Road near Highway.19. People = 1 are leaving the plant in a hurry, the sirens have gone;off; where should I. ;
go? The radio said no-action is required but people are leaving, what's ' really going on? = t L 7. Hi, this is Paul Evens from the Blade. What is the latest about the i emergency out there? How are your_ injured-employees doing?c Who is in
. . 1 charge at Davis-Besse during an emergency? JHas Toledo Edison estimated how ;
much this vill cost the rate-payers? This is a drill. . (Provide the. " 1 operator your telephone number if requested. NoteLt he time yourJeall-was: returned.)- < 1 l L. i h
****************************************************************************** j THIS IS~A DRILL
****************************************************************************** i h
-e.- -- ,- - -,, - ,--,,,.,,.n. ,-n ,-.-..----n.- --.,-n - .. - - - . . . . <,-
._ ~ _ _ . _ _ ._ _. .
i 7-119 2 I
.DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD .;
I SCENARIO NO. 1990 Evaluated Exercise ~ CUE CARD NO. PR-5(Cont.) : TO " Control Cell-Public1 TIME:- 11:15'- 12:00' .l T: '02/15'- 03/00- ; i THIS IS A DRILL- h I {NOTinitiateactions'affectingnormallplantJoperations'.. ] INFORMATION: 8.- 'Ask to speak to someone who handles claims. :Name . Jane /Jin Potter.- I~own. ! a hotel in Port Clinton._- People are checking out, I'm-losing reservations 1 q and most. folks-are just_ plain scared. 'Who's gonna' pay for my lostl
- business.- I want an answer,'todayL
- 9. You heard the sirens, what do they mean? What;should you do if-they-go off again?.
- 10. Ask for direction'to the closest evacuation center.
~
- 11. Why no protective actions if the sirens have sounded? !
- 12. What are the State and County doing to help the public? - l 1,
- 13. - Why did the accident happen?
- 14. Are the same people who caused the problem still vorking there?'
- 15. You missed the EBS message, can someone tell.you what it is?. I
- 16. - What should I do with my livestock?
i
- 17. Place this call as a Toledo Edison employee. Hello,:this is Ken /Carla ,
Austin over at the Acme Coal Station. . How's'it' going out'at Davis-Besse?
.I heard that they are at the worst kind of emergency. When did that< t happen? ] <
l
******************************************************************************. l
)
THIS IS A DRILL -l O . . ...... . ..... .. 1 1 l l l J
4 1: 7-1204 :
- DBNPS EMERGENCY PREPAREDNESS. EXERCISE CUE CARD'
< SCENARIO NO. 1990 Evaluated-Exercise' CUE. CARD NO.-PR-5(Cont.) -
- TO: ControlCelNPublic-- TIME: 11:15 - 12:00 -;
t r, T: -02/15 - 03/00- / t
.****************************************************************************** -t i
THIS IS A DRILLE .' l {NOTinitiateactionsaffectingnormal-plantoperations.
.******************************************************************************~
.i INFORMATION: j
- 18. This is Donna /Doug Hillman. .I-heard two radio shows tell about the nuclear-j problems and that they are getting:vorse.. Where'should I take_sy kids -
- l. because we're leaving town.; I live'in Lacarne and want to know the closest: 1 l place to me that's set up for evacuation. ]
)
19.- This is Ronda/ Rick Stover. I need a copy of_the' emergency'information., I live in: Oak Harbor and4 can't find the~ copy. mailed to me last year.- Where ! can I get one if we're told to evacuate? Where should I go if they tell us. J to leave? _'
- 20. Inform operator you are trying to get-help-for your family. You are, S. Jones, a medical technicir n at Fremont Hospital. You have been-called 1 in because of an accident at Davis-Besse. YouLhave only one car for1the :
whole family and your vife is expectingLto have a baby at anytime. 2
~
If my family needs to get away from here, villtsomeone come_to help?_ j
)
Where vill they be taken to? 1 l '\ How much vill.the help cost? (You live at 123 Maple,St., Rocky Ridge.)_ (Family Info. 3 sons, 2 daughters, ages 2.through 10 and expecting a baby.)
)
i L i
****************************************************************************** I THIS IS A DRILL O ,
l
1, ~ J -:1 , s 7-121-u o G: / ,
=DBNPS ENERGENCY PREPAREDNESS EXERCISE-CUE CARD'
-PR-6'
~
SCENARIO NO.~ 1990 Evaluated Exercise CUE CARD NO. g a
.TO ' Mock Media TIMEt, '11:20
- 6 T: 02/20- -i
-i 4 '
*****************************************************4************************
1 ' THIS~IS A DRILL, DO NOT initiate actions affecting normal plant operations. -
. .o - 1
****************************************************************************** ; q INFORMATION: .
Enter the JPIC via,the media entrance. . When~registrationis' completed [laskfor~ j information on areas that are affected by the emergency,: numbers:.of people by
~
l subarea that could:be affected, status on the plant. systems and potential'for.
~
l
-safety problems. _
i k l L( ,
-1
-t r
f i y V L < 1 i i i THIS IS A DRILL j J l3
****************************************************************************** 3
. s l A i
i
,, - . - - - - - -+ . ~ , .. -, - ~ . . _ . . . - . _ . . - , ,-,m . . , , . . . , .~ . --, -
L' i' s 7-122: DBNPS EMERGENCY-PREPAREDNESS CUE' CARD (Cont'd) CUE-CARD NO. PR-6 < - TO:' Media Controller.
- TIME:- 11:20-T: 02/20 ANTICIPATED RESPONSE -
Consistent with questioning. Response may.be provided.-by JPIC Manager _or-Company Spokesperson. INSTRUCTIONS: Observe-the Media Relations Assistants registration process for arriving media - representatives. 9 THIS IS A DRILL
********************************************************************A*********
1 1
--7-123' ,
1 DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD.- , , CUE CARD NO.1 -PR-7? SCENARIO NO. 1990 Evaluated Exercise :!
;j 1 70s; Media Actors
. TIMES. 11:20:- 14:00=
n
.T: 02/20 - 05/00
.?,
, a THIS IS A DRILL ;
NOT initinte actions affeeting normal plant operations.-- .
)
. INFORMATION:
y Interject ' free play consistent with simulated Emergency Conditions.at DBNPS. . , d j
~
' Questions may:be directed'to'any JPIC Staff member..
.l
~Ask questions,concerning the'following: .
Actions Taken:to protect public' health and safety.
..i l
' Plant Conditions-(Technical).. >
-Q- '
V Effect on Toledo Edison and Centerior. Player could refer your question to the Company lSpokesperson or other -l Information sources.' j j i
.l I
i I THIS'IS A DRILL lqf ****************************.***.********************************************* o (
)
5
- 'I" y - -
re -- c- - - - + , , , __.,.w.-...---,...e.. . , , .,_...e, . - . e n - - .
7-124 ] - i s DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd). j l CUE' CARD NO.1- PR-7 - TIME: 11:20' .14:00' 'J TO: -Media' Actor Controller-T: 02/20 - 05/00 1 ANTICIPATED RESPONSE - .) i Response'should be consistent with. questions. ! I J J INSTRUCTIONSs. i Be-aggressive in questioning. 8 :
.) ,
4 f 1
'i
- i t
i i THIS IS A DRILL ;
****************************************************************************** l I
t 4
'f
4 125 ' DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARDe SCENARIO NO..:1990' Evaluated Exercise CUE CARD NO. PR-7a , TO:- MediaLActors IIME: 11:20 --'12:00
' T: ~ 02/20 - 03/00- 'I
)
l 1
-- THIS IS A DRILL' I
_DO NOT initiate actions affecting normal plant operations. l, INFORMATION: As simulated news media, your responsibility:islto'ask: questions'of the , spokespersons. - The purpose is to assure that each'spokesperson demonstrates'the- 5 ability: to._brief the news media in- a_your timely _ manner. _ Below' statements.'.If: are just: sampleheal questions, but you'should. develop own based _on'their - news media.are present and'are asking sufficient questions, make your. role less f active. State of Ohio Spokespersons _O ; V 1. 2. Has 'the State activated it!s emergency center?-
. Has the Governor made a statement?
l
- 3. Has Toledo _ Edison kept the State briefed? ;
=i Ottava County Spokespersons-
- 1. Has Toledo Edison requested assistance from Ottava. County? .
1 Lucas County Spokesperson: .
- 1. Have you evacuated any of Lucas County? .. ;
- 2. What kind of training have the Lucas County- employees -received: to prepare ' l" for this emergency?
- 3. What action has the'Lucas County Sheriff taken?' j
' Toledo Edison Spokesperson:
- 1. Did the reactor shutdown by itself?
- 2. Has Toledo Edison evacuated the site? :
- 3. Are there_enough people left on. site to' prevent further problems? l l
THIS IS A DRILL 1
~
-i i
i
,a , e-, a ,,- , , , - - . - --.,,,e ,s . .-e-,-,, , - . , , a n - , , ,,,--n.s...es..-o,- ,,n-e , - - - -a
7-136 DBNPS'EMERGENCYPREPAREDNESSCUECARD)(Cont'd), .I
.1 CUE CARD NO.. PR-7a ,
TO : - Media A6 tor Controller. TIME: 11:20 - 12:00 T: 02/20 - 03/00 t l I ANTICIPATED RESPONSE: e Each spokesperson should address only those questions that apply-to his agency J or company. The spokespersons should not speculate. 1 I v i INSTRUCTIONS: Be aggressive. e I l l l l l
****************************************************************************** .i THIS IS A DRILL I
af
^ t 7-127L .
l DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD . SCENARIO N0'.;1990' Evaluated Exercisei CUE CARD NO2 PR-8
, l
.TO - Media Actors. TIME: 12:00 - 13:00
.i 03/00 - 04/00 T.
t L . .. . - .
****************************************************************************** a ETHIS IS A DRILL g} NOT initiate' actions,affecting normal plant operations.- ,
INFORMATION: As simulated news media, your: responsibility is to_ask~ questions-of the spokes-- j persons.--The purpose is to assure that each spokesperson present demonstrates i the ability to brief the newsfmedia in.a. timely.manneri Below are just sample i questions,.but you'should develop your own-based on their statements. If real news' media are present and are asking' sufficient questions, make~your role less active. L . State of Ohio Spokesperson: f
- 1. When did the' Governor declare the Site' Area Emergency?._ _ _
- 2. Have.other. states vith. nuclear. plants offered Ohio assistance?- -
- 3. Vill the State reimburse farmers for their losses? l t
Ottava County-Spokespersons q 4
- 1. How many people live in the evacuation. zones? _l
- 2. How many people must be evacuated? ;
l l 3. What are the protective actions necessary for Toledo? e 4 Toledo Edison Spokespersons
- 1. What more can you tell about the plant?
- 2. Is-there any indication of intentional damage? .
i
- 3. Is a meltdown possible at-this point? ?
- 4. What is Centerior Energy in Independence doing. ,
L i THIS IS A DRILL - ()
************************w*****************************************************
l ,
-r w .-e - - . - - . - .- . , , - .-._,,...,.~e...%-- ..-.,., --
i (- i
'7-128 L DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd) :
CUE-CARD NO. PR-8___ TO: Media Actor Controll'er TIME s - 12:00 - 13:00-j- i T: 03/00 - 04/00' l ANTICIPATED RESPONSE:
.Each'spokesperson should address only,those questions that apply to his agency '
or company. The spokesperson should not speculate. INSTRUCTIONS: Be aggressive. O ; y f t f l
******************,s***********************************************************
THIS IS A DRILL
*****************************************,************************************ (
.(-'
- 7-129 -
~DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD' CUE CARD NO. PR-8a-it( ) SCENARIO NO.J1990 Evaluated Exercise l
TO: MediaLActors. . TIME: 12:00c--13:00: r A T: . 03/00 - 04/00 l, l THIS IS A DRILL , DO NOT initiate actions affecting normal-plant operations. INFORMATION: i Toledo Edison Spokesperson:
- 1. How does Toledo Edison decide when to escalate the levellof-the: emergency?;
i
- 2. LVhoisinchargeofthe plant? ,
- 3. What is the Nuclear. Regulatory Commission's> role?- Whay aren't they in j charge? .
k 4. Have other utilities with similar-plants been contracted to assist Toledo Edison? j 1 1 I
?
I v i ll' ****************************************************************************** THIS IS~A DRILL
,---..-....r - , -- .. . . , . , . , ~,- > - - - , -
7-130 l; . .
-DBNPS EMERGENCY PREPAREDNESS CUE CARD-(Cont'd) k CUE CARD NO. PR-8a !
. TO : - Media ~ Actor Controller TIMES. 12:00 - 13:00'- l 1
L T:. 03/00 - 04/00 1 I . ANTICIPATED RESPONSE:~ 4 Each spokesperson should address only those questions that apply to his agency
' or company. The spokesperson should not speculate.. ;
h INSTRUCTIONS:
-i Be aggressive. i' Ob :
-)
i i THIS IS A DRILL
t 7-131 j l DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD: ,
' CUE CARD NO. .PR-9
-SCENARIO NO. 1990 Evaluated Exercise!
TO: Control Cell .Public' . TIME - :12:00 - 13:00 1 T: 03/00 - 04/00< i i THIS'IS A DRILL DO NOT initiate actions affecting normal plant operations'.- l
******************************************************************************c .{
l INFORMATION: >
- Place calls during the indicated. time. Use these questions only during'the. Site. :
Area Emergency classification.- Callias frequently as:possiblev Each Public- ' Concern Operator:should respond to one callievery five minutes.: ' Repeat , questions if necessary. Record csllsLif tape recorder is available. State- .:
"This is a Drill" for all calls. :
- 1. Name: Dale Caldwell .
Town: Bono - Jerusalem Township ! l
.(\
l : \d l I need help! I heard on.TV that I'm supposedLto ready myfEmergency brochure. I can'.t find mine. What should I do? i
- 2. Name: Karen / Dan Zeller Town: Perrysburg .
i l What is the expected increase in cancer casesLbecause of the accident? l What are my electric rates going to be'now?- 1 l THIS IS'A DRILL () ****************************************************************************** b A
, _ . , _ _ , . . cr..yg, - n- - ,--
l 7-132-4 DBNPS EMERGENCY PREPAREDNESS CUE CARD (Cont'd)' CUE CARD NO. . PR . TO - Control Cell i TIME: 12:00 - 13:00 j T: 03/00 - 04/00- ! 2 ANTICIPATED RESPONSE: ; Public Concern Operators should respond to questions. Call back number should be requested.
- l:
I INSTRUCTIONS: s t Provide extension you-are using. :
-i t t OJ a
I
.i i
-)
i n
****************************************************************************** t r
THIS IS A DRILL
g ;
^
i7-133" ,[ DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD . t G- j SCENARIO No.'1990 Evaluated Exercise CUE CARD NO.~:PR-9(Cont.')- TO: Control Cell - Public TIME: : 12:00 - 13:00" l Tax -03/00 - 04/00 <
')
-i '
THIS IS A DRILL' r DO NOT initiate actions affacting; normal
- plant. operations.-
1
.******************************************************************************- {
i INFORMATION:"
- 3. Name: = Dawn / Don' Edwards-Town: Marblehead>
What caused this: disaster?' How many people are going to get~ sick because of.this problem? 4.- Name - Sam / Sally Blake i i Town: Lacarne L Does this emergency. af fect: my- electricity?- Where-is my'pover coming.from?_ If power goes away I won'.t be able'.to, listen to the1 news, I don't'have.a-
' battery powered radio. What should I.do?- -n 1
- l. 5. Name Gale Fletcher. i L Town: Allen Township I just moved int'o this house-last week...Ve: don't understand what isl going on or what to do. My family is frightened >and vant to leave. Vill.you-Eexplain what this is about?
- 6. Name: Jim / Jane Little-Town: Elliston l Do you have the reactor turned off yet? Is.it going..to blovup? What.does d Site Area Emergency really mean?'
)
****************************************************************************** 4 THIS IS A DRILL-1
u
. 7-134 L1 l
.DBNPS EMERGENCY PREPAREDNESS: EXERCISE CUE CARD I SCENARIO NO.'1990' Evaluated: Exercise . CUE'CARDNO.'.PR-9(Cont.1 .
12:00 - 13:00 TO ' Control Cell ; Public' TIMEst
.i T: ' 03/00 - 04/00' l q
~THIS IS A DRILL
);
.D0 NOT. initiate actions affecting normal plant' operations.: :{
.i
, )
~-INFORMATION:
- 7. Names' Mark / Martha Felner !
Town: Toledo ., This accident is almost like Chernobyl all over again, so why haven't-we . been told to evacuate?- j Dr. Pool, MD
- 8. Name:
Towns. San Diego, California , I'm a specialist in nuclear medicine.- I'm getting ready.to: leave. California for your plant. Please give 'me t the: account number I should-
.l j
charge my expenses against. .My staff. vill also tue arrivingctomorrow. '.
- 9. Name Craig/Clare Booth-Town: Rocky Ridge Who determined the meanings of Emergency Classifications?' Isn't an-emergency an emergency? Why are we told'to do things-differently for each classification?
l
- 10. Names Bart/ Ben Tork I Town: Fremont i I'm a retired engineer and vant to help you. Where should I go to lend a '[
hand? What exactly is the problem? 9
- 11. Names Mark / Maggie Blass :
Town: Bowling Green ! 1 What broke to-cause all of this confusion? How many of those broken parts '} do you have? How often do they break? Has this happened'anywhere else in , America? Where?
******************************************************************************- -l THIS IS A DRILL l l_
*********A********************************************************************
?
q -m ; y
> :7-135: ?
?
m _. DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD.- ; SCENARI0'NO. 1990 Evaluated Exercise-. CUE' CARD NO. PR-9(Cont.): sTOL Control' Cell - Public TIME 12:00 - 13:00- j
=T: 03/00 - 04/00 :!
J
+ THIS IS A DRILL [f J
-l p NOT-initiate actions affecting normal plant operations. '
e INFORMATION:
.;j
- 12. Names Greg/Gail Brady:
Town: Toledo ~ j
,)
I'm a student at UT working on my doctorate.in; industrial psychology.' How- 3 are people-reacting at?the plant?. How.about'public response-- has anyone , called and what questions are they asking?. How many people live near.the plant?' . t l Where is your company president, and villihe be going:to the= plant?! q t
- 13. Name: Dee/Deek-Martin O\ Town: Detroit ]
I'm a staff reporter from'the Detroit Free Press. Has Fermi been asked to .j help? ; How many people are affected? , , What broke and why? Is the leaking. fluid getting into Lake Erie? -! What' keeps it from getting out? ;j
- 14. Name: Jamie Singleton ;
Town:- Washington D.C. .t This is Jamie Singleton:from USCEA. Please provide me your FAX number, a' -s list of your current public;information assistance'needs', Land biographical sketches of your Corporate Emergency-Staff.. (Provide Control Cell FAX; Number.) j 15. Names Penny / Paul Steel - Town: Cleveland
- Ji What does this accident mean in terms of employment in Toledo? Vill.the .
emergency affect property values near Port Clinton? What does the NRC do ; during emergencies? Os THIS IS A DRILL
i_ o 1 e
#' 7-136.
Je DBNPS EMERGENCY PREPAREDNESS 1 EXERCISE CUE CARD iy SCENARI0'NO.o1990 Evaluated Exercise CUE CARDINO. PR-9(Cont'.) TO: Control Cell - Public TIME: 12:00 - 13:00
' T: 03/00'- 04/00 THIS IS A DRILL'-
@ NOT initiate actions affecting normal! plant operations.-
INFORMATION:.
- 16. Name: Agnes/ Adam Avery Town:.' Oak Harbor I own a-condo.at-Green Cove; vhatlshould I'do-toiprotect my property from'-
the leaking-radiation.
- 17. Name: Joan/ Rich Hillman Town: Genoa I've heard about the disaster on my radio. If I need-_to evacuate how will you tell me? By the way, hov are you sure everybody knows what.to do? LVho .
makes the decision to evacuate; the County Commissioners,' Governor or Toledo Edison?-
- 18. Name: Bingo Varren Town: Sandusky Good afternoon, this is Bingo Varren - Radio. Station VJDBIL"All_New 92".
We're on the air live, and want a'fev:ansvers:to some questions concerning the Davis-Besse Emergency. What. kind of danger is there to the public due to this accident? How did this tragedy happen?. Tell our' listeners what-safety actions they need to take. What's' going on at the plant right now? One last question;=how expensive-vill this be to fix,'and who' picks up the cost?
- 19. Name: Kelly Villiams Town: Port Clinton By listening to the radio I understand that I'm.0K. If the radioactivity gets out vill it get into the lake? I'm really enjoy fishing and I have almost $5,000 in equipment. If the accident affects the lake and I can't use my gear, vill Toledo Edison pay me for my lost hobby?
THIS IS A DRILL
g 2 m n.*I 7-137
=DBNPS~ EMERGENCY PREPAREDNESS EXERCISE CUE ~ CARD. !
-SCENARIO NO. 1990 Evaluated Exercise 1 CUE CARD NO.:PRi9(Cont'.). ,
. TO: Control Cell - Public- . TIME: 12:00 13:00 T: 03/00 - 04/00 ;
-1
,f
- i, THIS.IS A' DRILL .j a
DO NOT. initiate, actions:affecting normal plant operations. 1 l l
******************************************************************************-- .-}
1 4 1 INFORMATION:
- 20. Name Davey Lear j 1 Town: Dayton- ,
I heard ab'out your emergency, could'.it affeet my. health?, j 4 What level of contamination.causes cancer?' 1
]
What are the exposures- near Toledo? - ; When was the last. time-the plant was refueled? j - v . Why vasn't the broken part found during refueling?- '
'l s ,
s
.k
')
i i , t 1
.f
~
1 1
?
l
****************************************************************************** i THIS'IS A DRILL' 'l D ******************************************************************************
)
l
a- , . J 7-138? ' <
'l
-- 1 s .
i DBNPS EMERGENCY-PREPAREDNESS EXERCISE CUE CARD-9,~s CUE' CARD NO.~ 'PR-10' phs,) SCENARIO NO. 1990 Evaluated' Exercise. =a D ~ TO: Media Actors-TIME: r13:00 - 14:00J :1
?
T: 04/00 - 05/00'- ' 1 l
~******************************************************************************
o THIS IS.A DRILL ~ . DO NOT initiate' actions affecting-normal plantioperations.- ] t s 1 INFORMATION:. t As simulated news media, your' responsibility istto'askiquestions of the spokes-- , J persons. The purpose,is_to assure that each'spokesperson present demonstratesJ the ability to brief the news media in a timely manner._ Below are just sample. !! questions, but-you should develop your own based-on their statements. If.real: i nevs' media are present and are'asking sufficient questions,;make-your role lessL
-active. t State of Ohio Spokespersons J
l' 1.. Do you have a copy of the latest EBS Message?:
- 2. How much radiation has the state detected? I 3.- Has:the state requested assistance from the Federal Government?-
Ottava County Spokesperson:
- 1. How many people _have been evacuated? .
l
- 2. Has anyone refused to leave their home or, business? !
- 3. How many people have registered at evacuation centers?
Lucas County Spokesperson lj How much vill this cost Lucas county? I 1.
- 2. Vere people cooperative when told to evacuate?-
j . Toledo Edison Spokesperson 4
- 1. Why was Davis-Besse operating'vith so many pieces of equipment broken?-
- 2. Have you personally been to the Control Room to discuss the emergency.vith the operators? ,
- 3. Vould improved operator-training have prevented this emergency?
i. THIS IS A DRILL t l O ****************************************************************************** t I
g _. . _ . _ . . _ _ _ _ _ _ __ _ _ _ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (: < 1 I ' R L' . 7 139 i DBNPS EMERGENCY PREPAREDNESS CUE CARD.(Cont'd)- .
' ' CUE CARD NO. 'P'-10 R
' TO - Media ~ Actor Controller TIME: 13:00 - 14:00 1
T: 04/00'-' 05/00 a
' ANTICIPATED RESPONSE:
Each spokesperson should' address only those questions that' apply to his' agency! ? or' company. The spokespersons should not speculate. ! t li , i INSTRUCTIONS: , Be aggressive. i
?
f f I i t THIS IS A DRILL
p,
+ ' '
7-140; J L ,# DBNPS ENERGENCY PREPAREDNESS EXERCISE CUE CARD (- +
- CUE CARD NO.' PR-11t i '" ( ) _ SCENARIO NO.a1990-Evaluated Exercise JTOs. Control Cell; LTIME: 13:00 - 14:00; !
L ' . T: 04/00 - 05/00-. -i d L, b THIS<IS A: DRILL i DO NOT. initiate; actions affecting-normal' plant operations.
- \
******************************************************************************: 3
;INFORMATION: *
. . . ?
Place' calls ~during-the indicated' time.::Use these questions.only during the Site Area Emergency classification. Call as frequently as possibleD Each Public , a Concern Operator should respond _to;one' call.everyafive_ minutes. Repeat' a questions if necessary.. When callszareTplaced use'the name-and town as listed. ; State "This is.a Drill" for~all calls., i i
- 1. Name: Craig/ Karen Gardner !
Town: . Bono' 1; I'm calling to see how much' longer'the beach at Crane Creek vill,be closed. Is the beach contaminated with radiation and'how vill you clean.it up? , What is going to happen to the fishing business .in Port Clinton?J ;
- 2. Name: Adam / Alice Johnson i Town: Fremont (Boating Supply Store Ovner): 1 1
I called the Ottava County' Emergency Management Agency to make a' claim for l lost business at-my store. They said=to call Toledo Edison becauseLyou're - supposed to know what to do. I'm going to lose-about $25,000. l' L l 3.- Name: Paula/Pete Ross- l L Towns Perrysburg ; What are the emergency levels and-why are they different? Isn't an : L emergency; dangerous anytime? How-do you tell the difference-between emergencies?.
-j i
THIS.IS A DRILL () ****************************************************************************** l t , ry- -
-ww - . . . .c . . . , . - -.,,c., . , - y ,- .,a w w '=en,- e-esv
i
'1 7-141 DBNPS' EMERGENCY PREPAREDNESS CUE CARD (Cont'd)
CUE CARD NO. PR-11 L 13:00 - 14:00 TO: Control-Cell Controller . TIME: i l T:- 04/00 - 05/00'
- ANTICIPATED RESPONSES _ -
Public Concern Operators should respond to questions. Call back number should be requested. ; i 4 i INSTRUCTIONS: l l Provide extension you are using. I el 9
+
t l THIS IS A DRILL
****************************************************************************** 3
y , n , t 7-142- a
~ DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD- 1
( SCENARI0'NOW 1990 Evaluated Exercise . CUE CARD.'N0'. . PR_-11(Cont . ) j
-TIME: '13:00 - 14:00 'j TO: Control Cell-T: 04/00 - 05/00-i q
, THIS IS' A' DRILL D0 NOT initiate actions-affecting normal plant operationse;
******************************************************************************f 'l 1
INFORMATION: ! != '4. Name: Jane / Jack Bottoastone Town: Curtice--(Farmer'on Wildacre Road): , How'far from the plant do the safety monitoring teams go.to detect . radiation? I think'ay field'should - be checked: and I'm not paying to have it done.' - When vill you. get here? l
- 5. .Name:- Dale Jefferies Towns. Genoa i
'What does the NRC have to say about this emergency?- Who says'that we're safe - Toledo Edison, the State,- or the NRC7 What do they: base the '
decision on?
- 6. Names Tina /Ted Roberts q Town: Maumee i
How long vill the cleanup take at'the plant? -Will truckloads of. l radioactive vaste be removed from the, site? Where vould:it-be sent to, and . ;: how does it get there?. l. 1
~$
i e
)
5
- t '
THIS IS A DRILL i i
. . ~ - - - - . . .-- , .m_.- . . , - - . . . . - , . . _ . - .
7-143 j DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD i SCENARIO NO. 1990 Evaluatus Exercise- CUE CARD NO. PR-11(Cont.) To: Control Cell TIME: 13:00 - 14:00 l T: 04/00 - 05/00' l i f ****************************************************************************** ! l Y l THIS IS A DRILL , ' l l DO NOT initiate actions affecting normal plant operations. I
****************************************************************************** [
6 i INFORMATION: i [ 7. Names Gloria / George Byrd i Town: Lucky l I called my broker about activity of Centerior Stock today. She said , trading was stopped. Will I be able to claim any losses through your insurance people? j
- 8. Name Sally /Seth McCoy i Town: Greytown l l
My home uses well water. Is it safe to drink the water or should I wait ; until you have tested it? j i
- 9. Name: Phil Duffy ;
Town: Riga, Mich. i My family was f5shing in Lake Erie this morning and caught a few Valleye. Are they safe to eat? } Do they need to be boiled first? l i i I I I
****************************************************************************** f i
THIS IS A DRILL f 1 i
l 7-144-DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD l N CUE CARD NO. PR-11(Cont .) l l SCENARIO NO. 1990 Evaluated Exercise ' l TO: Control Cell TINE: 13:00 - 14:00 .l l T: 04/00 - 05/00 l I j l THIS IS A DRILL-DO NOT initiate actions affecting normal plant operations. l i INPORMATION: j
- 10. Names Barb /Bart Glee \
Town: Limestone j Where can I get some of those radiation protection pills (KI)? How do f those work and what do they look like? j i
- 11. Names Betty / Bob Becker ;
Town: Oak Harbor ! How do you know that the containment building vill holdt. What if it explodes? How far could the fallout spread? l
- 12. Name: Alma / Jack Feaster Town: Lindsey j How many people from the NRC are at Davis-Besse? Are they in' charge and :
who are they? What are their names? ! Jenny /Stan Davies j
- 13. Name Town Port Clinton l
\
Is this the same as Chernobyl? How does radiation cause cancer? Don't j doctors use radiation to stop cancer? I'm really confused about all of -; this. I i THIS IS A DRILL j O ****************************************************************************** l
} - - . -. -- - - . =.. - - . _
i 7-145 ;
)
1 DBNPS ENERGENCY PREPAREDNESS EKERCISE CUE CARD- ; SCENARIO NO. 1990 Evaluated Exercise CUE CARD NO. PR-11(Cont.) TO: Control Cell TIME: 13:00 - 14:00 l
-t T: 04/00 - 05/00
?
****************************************************************************** l l
THIS IS A DRILL
- DO NOT initiate actions affecting normal plant operations.
i i INFORMATION:
- 14. Names Emma/Ernie Tipps j Town: Oak Harbor ,
Where vill we get electricity now that Davis-Besse is brokedown again? I I'll bet this mistake is going to cost me a fortune. Hev long vill it take i to fix the problem and how much will it cost? ; i
- 15. Names Doctor J. . Vood, MD. !
Town: Sacramento, California j r This is Doctor Wood calling. I received this number from Ottava. County. ; My services have been requested for post trauma disorders. My. staff and I 1 vill be arriving at 9 p.m. in Toledo.. You are to provide me an account ; number for billing. Could you please give me the invoice number? (If 4 asked, your staff consists of 5 assistants. Your cost is $7,200 for a '42 i hour day plus expenses.) j
- 16. Name: Sandy Tolbert .
Town: Clay Center ,
. t How long vill the reactor be broken? What is the damage to the reactor ,
core? ! Is this going to cause Davis-Besse to close down for good? . i i THIS IS A DRILL i i i t
. _ _ _ - _ . - . . . . . . - , . . . _ , . _ __ _ __ _ _ _ - . - , _ _. 4 -!
.__ . _ _ . . _ _ . . _ _ . _ _ _ . _ _ . _ . _ _ _ . _ _ _ . - . ~ .______ _
l 7 146
.DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD l
() SCENARIO NO. 1990 Evaluated Exercise TO: Control Cell CUE CARD NO.'PR-11(Cont.) TIME: 13:00 - 14:00 i T: 04/00 - 05/00 i
)
4 *************************************************************f 3************* ! THIS IS A DRILL -l l DO NOT initiate actions affecting normal plant operations. : I INFORMATION: ! I
- 17. Name: Qunit Adams ;
Town: Chicago (Reporter for the Chicago Times) l I understand that your nuclear plant is near meltdown. Is that true? According to a spokesman from Commonwealth Edison this is the most serious l accident in the United States since Three Mile Island. Vould you comment j on that statement? : O How many people have been evacuated so far? i i What is the status of the employees who were injured when the emergency started? ;
- 18. Name: J. Smith l Town: Toledo Request an interview with someone from the Public Affairs Department, i Inform the operator that you are J. Smith from the radio station VPAK-FM ,
109. You have a scheduled news broadcast on the hour and intend to discuss the Davis-Besse accident. You vere informed by UPI network. When l connected, ask the following: .
- a. Who are you and what is your title?
- b. What is the condition of the reactor? !
- c. Is anyone hurt? j
- d. Who should listeners call for more information? ;
- e. Vill this get vorse? :
- f. Are local citizens safe? i What is the impact on power availability?
g.
- h. What is you corporate headquarters doing? Who is in charge and when 4 vill they be able to speak with me? i L
O THIS IS A DRILL 4
************************************************************************>***** t 1
e t i.,--. s_ , _ . . . . . , _ , , , ,,,.._.?
.I i
7-147 l
)
)
DBNPS EMERGENCY PREPAREDNESS EXERCISE CUE CARD i 1 SCENARIO NO.1990 Evaluated Exercise CUE CARD NO. ' PR-11(Cont . ) TO: Control Cell TIME: 13:00 - 14:00 i T: 04/00 - 05/00 I
****************************************************************************** l t
THIS IS A DRILL t DO NOT initiate actions affecting normal plant operations. t INFORMATION: l
- 19. Names Vilma/ Fred Boulder )
Town: Detroit I How many times has this happened before at Davis-Bessef How about other ; power plants. What is the cause of the accident? What is the cost of ; replacing the broken sections? ! i
- 20. Names Judy /Elroy Jensen <
Towns Port Clinton .
- - What was the latest EBS message? How do I make a claim if I need to? .
r When vill this probles be fixed? l I i THIS IS A DRILL i h 4 b
, _ , , , _ , ..__,...,r, , , _ . , , . . . . . . ,
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME: -00/30
- CUE CARD NO. T
- 08:30 .
REACTOR COOLANT CONTAINMENT
' RCS Pressure 2162 psig Ctat. Pressure 15 psia T Avg. 582 *F Ctat. Temperature 105 *F Th/Tc 607/558 *F Radiation (See Radiation Monitor Data Sheet)
Boron Concentration 530 ppm Sump Level (Normal /WR) 538/538 ft RCS Subcool. Marg. 39 *F Przr. Temp. 646 *F STEAM GENERATORS , Przr. Level 256 in S/G 1 Level / Press. 190 in / 901 psig RCS Flow (Loop 1/2) 76/76 Mpph S/G 2 Level / Press. 188 in / 900 psig PORV AUTO Block Valve OPEN S/G Shell Temp. (1/2) 534 F / 534 *F Spray Valve AUTO Block Valve OPEN Turbine Hdr. Pressure 870 psig . Letdown Flow 68 gpm MSIV Position. OPEN
- RCP Seal Flows 36 gpm (TOTAL) .
1-1 9 gpm 2-1 9 gpm FEED fn CONDENSATE 1-2 9 gpm 2-2 9 gpm Main FW Flow (loop 1/2) 5834/5863 Mpph Quench Tank Level / Pressure 9 ft/ 25 psig Hotwell Level / Pressure 4 ft/ 3 in Hg , CST Level (1/2) 40 / 40 ft REACTOR CORE Aux.' Feed Flow 0/0 gpm Source Range Level (NI-1/NI-2) O/0 cps Motor. Driven Feed Pump Press. O psig Intermediate Range (NI-3/NI-4) -3/-3 amps , Power range (NI-5/NI-6) 102/102 % ELECTRICAL (NI-7/NI-8) 102/102 % BUS A/B NORM / NORM Core Thermocouple (AVG) 607 *F BUS C1/C2 NORM / NORM
. BUS D1/D2- NORM / NORM MAKE-UP AND ECCS EDG 1/2 NORM / NORM
' Makeup Flow 27 gpa 480 VAC Distribution NORM Makeup Tank Level / Pressure 72 in / 30 psig 250 VAC/125'VAC Dist. NORM Core Flood Tank #1 Level / Press' 13 ft / 599 psig Inst. AC NORM-Generator Wattneter (Gross)
Core Flood Tank #2 Level / Press 13 ft / 599 psig. 940 Mw HP Injection Line Flow (1-1) 0 /(1-2) O (2-1) 0 /(2-2) O OTHER LP Injection Line Flow (1/2) 0 / 0 gpm- < DHR Hx Inlet Temp. (#1/#2) 100/100 *F Instrument 3r Service Air 110/ NORM Ctat.. Spray Flow (#1/#2) 0/0 gpm Spent Fuel Pool Level / Temp -24 ft/102 *F-CCw Surge Tank Level. (1/2) 51/52 in BWST Level 42 ft CCW Hx Outlet Temp (1/2) 95/95 *F-i
._______.._____.____________________-.__m_ _ _ . _ . _ . _ _ _ _ . _ _ _ . _ _ . _ . _ _ _ _ _ _ _ _ _ . . . . _ _ _ _ . _ . _ _ _ . _ ~ - . _ _ _ _ _ . _ . - _ . _ - - _
i EMERGENCY PLAN DRILL I AND EXERCISE PROGRAM j SCENARIO NO. 90 EVAL TIME: 08:30 ! T: -00 30 DAVIS-BESSE NUCLEAR POWER STATION 1 EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT STATUS l i COMPONENT: STATUS: , Reactor Coolant Pumps #1-1............................ RUN -
#1-2............................ RUN 'i
#1-3..................'.......... RUN .
#1-4............................ RUN l 1
M a ke up Pumps # 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . RUN i
#2....................................... -STBY- !
t HPI Pumps #1.......................................... OFF !
#2.......................................... OFF j Decay Heat Pumps #1................................... OFF
#2................................... OFF i Decay Heat Removal Coolers #1......................... RUN- ;
#2......................... AVAIL '
)
Containment Spray Pumps #1............................
~
OFF
#2............................ OFF !
Containment H2 Dilution Blowers #1.................... OFF !
#2.................... OFF J
Containment Recirculation Fans #1..................... RUN t
$2..................... RUN .;
Containment Air Cooler Units #1....................... RUN-S LOW
#2.......................- RUN-SLOW
#3....................... OFF i component Cooling Water Pumps #1......................
RUN
#2...................... RUN l
#3...................... STBY l Service Water Pumps #1................................ RUN ,
#2................................ RUN i
.STBY-
#3................................
Backup................................ OFF , Auxiliary Feedwater Pumps # 1. . . . . . . . . . . . . . . . . . . . . . . . . . OFF
#2.......................... ,OFF l' Motor Driven Feedpump ................................ OFF i 1
I i
)
i i y, +-+--.y- - -w, , - - *-,-
~
O O O DAVIS-BESSE NUCLEAR POWER STATION 4 PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME:___00/00 CUE CARD NO. T: 09:00 i REACTOR COOLANT CONTAINMENT RCS Pressure 2162 psig Ctat. Pressure 15 psia T Avg. 582 *F Ctat. Temperature- 105 *F Th/Tc 607/558 *F Radiation (See Radiation Monitor Data Sheet) 538/538 ft Boron Concentration 530 ppe Sump Ievel (Normal /WR) RCS Subcool. Marg. 39 *F l Przr. Temp. 646 *F STEAM GENERATORS Przr. Level 256 in S/G 1 Imvel/ Press.- 190 in / 901 psig RCS Flow (Loop 1/2) 76/76 Mpph S/G 2 Level / Press. 188 in / 900 psig PORV AUTO Block Valve CLOSED S/G Shell Temp. (1/2) 534 F / 534 *F i
-Spray Valve AUTO Block Valve CIDSED Turbine Hdr. Pressure 870 psig Letdown Flow 68 gpm- MSIV Position. OPEN RCP Seal Flows 36 gym (TOTAL)
I 1-1 9 gpa 2-1 9 gpm FEED _E_ CONDENSATE l 1-2 9 gpa 2-2 9 gpa Main FN Flow (loop 1/2) 5818/5864 Mpph Quench Tank 14 vel / Pressure 9 ft/ 25 psig Hotwell Level / Pressure 4 ft/ 3 in Hg CST Ievel (1/2) 40 / 40 ft REACTOR CORE Aux. Feed Flow 0/0 gpm Source Range Level (NI-1/NI-2) 0/0 cps Motor Driven Feed Pump Press. O psig
. Intermediate Range (NI-3/NI-4) -3/-3 amps Power l range. (NI-5/NI-6) 102/102 % ELECTRICAL l (NI-7/NI-8) 102/102 % BUS A/B NORM / NORM Core Thermocouple (AVG)- 607 *F BUS C1/C2' NORM / NORM BUS D1/D2 NORM / NORM MAKE-UP AND ECCS EDG 1/2 NORM / NORM l Makeup' Flow 27 gpa 480 VAC Distribution NORM l
Makeup Tank Level / Pressure 72 in / 30 psig 250 VAC/125 VAC Dist. NORM , Core Flood Tank #1 Level / Press 13 ft / 599 psig Inst. AC NORM Core Flood Tank #2 Level / Press 13 ft / 599 psig Generator Wattneter (Gross) 940 Mw
, HP Injection Line Flow (1-1) O /(1-2) 0 I
(2-1) 0 /(2-2) O OTHER LP Injection Line Flow (1/2)-O / 0 gpm . DHR'Hx Inlet Temp. (#1/#2) 100/100:*F Instrument & Service' Air 110/ NORM Ctat. Spray Flow ($1/#2) O/0 gpm Spent Fuel Pool Level / Temp. 24 ft/102 *F CCW Surge Tank Level (1/2) 51/52 in BWST Level 42 ft CCW Hx Outlet Temp (1/2).95/95 *F 4 k-
;...-.i..-.....-__.-..-~ .-. . - - ~ . . - . . - . - , . . . - . - . ~ . . . . . . . . . . . - . - . . - . . . . . . . - . - - . - _ - - _ . . . _ - . - _ __. - _- - --
t EMERGENCY PIAN DRILL AND EXERCISE PROGRAN SCENARIO NO.- 90 EVAL TIME: 900 T: 00:00 l l DAVIS-BESSE NUCLEAR' POWER STATION l EHERGENCY PREPAREDNESS. EXERCISE EQUIPMENT' STATUS ! 1 COMPONENT: . . STATUS: j Reactor Coolant ' Pumps # 1-1. . . . . . . . . . . . . . . . . . . . . . . . . . . . RUN i
#1-2..........'.................. ,RUN l
#1-3............................. RUN- j
#1-4............................ RUN-i Makeup Pumps #1....................................... RUN l
#2........................................ STBY- ]
1 l HPI Pumps #1.......................................... . OFF j
#2.......................................... 0FF' J
Decay Heat Pumps #1................................... OFF
#2................................... OFF :
Decay Heat' Removal Coolers #1......................... RUN .;'
#2.........................- AVAIL Containment Spray Pumps $1'............................ OFF !
#2............................ OFF -
Containment H2 Dilution Blowers #1.................... OFF' ;
#2.................... OFF Containment Recirculation Fans'#1..................... 'RUN
#2....................- RUN Containment Air Coolor Units #1....................... RUN-S LOW
#2....................... RUN-SLOW
#3....................... OFF.-
Component Cooling Water Pumps #1...................... RUN- '
#2...................... RUN
#3...............'....... STBY Service Water Pumps #1................................ RUN
#2................................ RUN
#3...........'..................... STBY Backup................................ OFF Auxiliary Feedwater Pumps #1.......................... OFF- ;
OFF
#2..........................
i Motor Driven Feedpump ................................- OFF ; O i
.- ..2 _ - - _ . . _ . . _ _ . . ,
~
~
l O O O 4 DAVIS-BESSE NUCLEAR POWER STATION i PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME: 00/15 CUE CARD NO. T: 09:15 J l REACTOR COOIANT CONTAINMENT I RCS Pressure 2160 psig Ctat. Pressure . 15 psia T Avg. 583 *F Ctat. Temperature 105 *F Th/Tc 603/563 *F Radiation (See Radiation Monitor Data Sheet) Boron Concentration 530 ppa Sump Level (Normal /WR) 538/538 ft RCS Subcool. Marg. 43 *F ., Przr. Temp. 646 *F STEAM GENERATORS -l Przr. Level 256 in - S/G 1 Level / Press. - 141 in / 907 psig - RCS Flow (Loop 1/:c) 76/76 Mpph S/G 2 Imvel/ Press. 141 in / 907 psig. PORV AUTO Block Valve CIDSED S/G'Shell Temp.- (1/2) 535 F / 535 *F .i l Spray Valve AUTO Block Valve CLOSED Turbine Hdr. Pressure 885 psig i Letdown Flow 68 gpm MSIV Position OPEN RCP Seal Flows- 36 gpa - (TOTAL) 1-1 9 gpa 2 9 gpm FEED & CONDENSATE 1-2 9 gpa .2-2 .9 gpm Main FM Flow (loop 1/2) 4474/4506 Mpph Quench Tank Level / Pressure 9 ft/ 25 psig Hotwell Level / Pressure 4 ft/ 3 in Hg CST Level (1/2) 40 / 40 ft REACTOR CORE Aux. Feed Flow 0/0 gpm i Source Range Level (NI-1/NI-2) 0/0 cps Motor Driven Feed Pump Press. O psig Intermediate Range (NI-3/NI-4) -3/-3 amps Power range (NI-5/NI-6) 85/86 % ELECTRICAL ~ (N1-7/NI-8) 86/86* % BUS A/B NORM / NORM Core Thermocouple (AVG) 603 F. BUS C1/C2 NORM / NORM
- j. BUS D1/D2 NORM / NORM MAKE-UP.AND ECCS EDG 1/2 NORM / NORM Makeup Flow. 101 gpm 480 VAC Distribution. . NORM i Makeup Tank Level / Pressure 57 in /.30 psig - 250 VAC/125 VAC Dist. NORM 13 ft / 599 psig Inst. AC NORM i Core Flood Tank #1 Level / Press 787 Mw Core Flood Tank f2 Level / Press 13 ft / 599 psig Generator Wattneter_(Gross)
HP' Injection Line Flow. (1-1) 0 / (1-2) 0 (2-1) O /(2-2) 0 . OTHER LP Injection Line Flow (1/2) 0 /'O gpm ' DHR Hx Inlet Temp. (#1/#2) 100/100 *F Instrument &' Service Air. 110/ NORM Ctat. Spray Flow (#1/#2) 0/0 gpm Spent Fuel Pool Level / Temp 24 ft/102 *F CCW. Surge Tank Level '(1/2) 51/52 in BWST Level 42 ft CCW Hx Outlet Temp (1/2) 95/95 *F
-w.-++-, -
g ,----i.,,-.e%mw -we.,we-w-- =--*=w--m-w--wws* ewe =.--**m-n= = * - - - - v v a- , -we<- .--www w= ev-+-==. w w+-m "%~mn' wow-+<+s -m-ve-=-e-e-e k ==w- -. .-=~=w=e------ - - - - = = - - - - - - - - - _ - - - -
EMERGENCY PIAN DRILL AND EXERCISE PROGRAN i SCENARIO NO. 90 EVAL . TIME: 915 j T: 00:15 DAVIS-BESSE NUCLEAR POWER STATION i EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT STATUS , COMPONENT: STATUS: - Reactor Coolant Pumps #1-1............................' RUN
#1-2............................ RUN ;
#1-3............................ RUN .
#1-4............................ ~RUN i
Makeup Pumps #1................,...................... RUN
#2....................................... STBY j
'HPI Pumps $1...................................... ... . 0FF-
#2.......................'................... OFF. ,
Decay' Heat Pumps-#1...................................: OFF !
#2................................... OFF j I
Decay Heat Removal-Coolers #1......................... RUN ' AVAIL i
#2.........................
i Containment Spray Pumps # 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . OFF- l
#2............................ OFF l Containment H2 Dilution Blowers #1.................... OFF
#2.................... OFF }
Containment Recirculation Fans
~
#1..................... 'RUN !
#2..................... RUN l Containment Air Cooler Units 41....................... RUN-S LOW ;
#2....................... 'RUN-SLOW- ,
#3....................:... OFF j
- component Cooling Water Pumps #1...................... RUN- !
#2...................... RUN.
#3..............'........ STBY i
Service Water Pumps #1................................ RUN
#2................................ RUN i
#3................................ STBY j Backup................................ OFF Auxiliary Feedwater Pumps #1.......................... OFF [
#2..................-........ OFF
-l Motor Driven Feedpump ................................ OFF- 3 i
t t I: _ _ , , - . _ , . _ .. f
~ ! O O O i
DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET 4 SCENARIO NO. 1990 EVAL TIME: 00/30 CUE CARD NO. T: 09:30 REACTOR COOLANT CONTAINMENT RCS. Pressure 2169 psig Ctat. Pressure 15 psia
- - T Avg. 582 *F Ctat. Temperature- 105 *F Th/Tc 594/571 *F Radiation (See Radiation Monitor Data Sheet)
Boron Concentration 530 ppa Sump Level (Normal /WR) 538/538 ft RCS Subcool. Marg. 53 *F ,- Przr. Temp. 645 *F STEAM GENERATORS l Przr. Level 257 in S/G 1 IA!! vel / Press.. -72 in / 883 psig RCS Flow .(Loop 1/2) 76/76 Mpph S/G 2 Level / Press. 72 in / 883 psig .; PORV AUTO Block Valve CIDSED S/G Shell Temp.: (1/2) 532 F / 532 *F Spray Valve AUTO Block Valve CIDSED Turbine Hdr. Pressure 873 psig Letdown Flow 68 gpm MSIV Position OPEN-RCP Seal Flows 36 gpm (TOTAL)
- 1-1 9 gpa 2-1 9 gpa FEED & CONDENSATE i 1-2 9 gpa 2-2 9.gpm Main FW Flowi(loop 1/2) 2450/24731Mpph 7 Quench Tank Level / Pressure 9 ft/ 25'psig Hotwell Level / Pressure 4 ft/ 3 in Hg
! CST Level '(1/2) 40 / 40 ft REACTOR _ CORE . Aux. Feed Flow. . O/0 gym Source Range Level (NI-1/NI-2) 0/0 cps Motor Driven Feed Pump Press. O psig Intermediate Range (NI-3/NI-4) -3/-3 amps Power-range (NI-5/NI-6) 53/53 %. ELECTRICAL (NI-7/NI-8) 53/53 % BUS A/B NORM / NORM-l Core Thermocouple- (AVG). 594 *F BUS C1/C2 NORM /MORK' BUS D1/D2 NORM / NORM MAKE-UP AND ECCS EDG 1/2 NORM / NORM-Makeup Flow 80 gpm 480 VAC Distribution NORM Makeup Tank Level / Pressure. 73 in / 30 psig 250 VAC/125 VAC Dist. : NORM Core Flood Tank #1 Level / Press 13 ft'/.599 psig Inst. AC - NORM l i Core Flood' Tank #2 Level / Press .13 ft / 599 psig Generator Wattneter (Gross). 456 Mw HP Injection Line Flow (1-1) O /(1-2) O .l
-(2-1) 1 /(2-2) O OTHER i LP Injection Line Flow (1/2) / O gpm DHR Hx Inlet Temp. (#1/#2) 100/100 *F Instrument & Service Air- 110/ NORM Ctint. Spray Flow (#1/#2).O/0 gpm' Spent Fuel Pool Level / Temp 24 ft/102 *F' CCW Surge Tank Level (1/2) 51/52 in BWST Level 42 ft CCW Hx Outlet. Temp (1/2) 95/95F E.-~.....-,-_,...__._.._. -
. . . - . _ . - . . ~ . . , - , ._____.____.m _-..-____._____-..,__.._...____,____...i?..~--
e i AND EXERCISE PROGRAM
]
SCENARIO NO.- 90 EVAL TIME: 930 i T: 00:30 i i DAVIS-BESSE NUCLEAR POWER STATION. EMERGENCY PREPAREDNESS EXERCISE Ll}UIPMENT STATUS i COMPONENT: STATUS: ? Reactor Coolant. Pumps #1-1............................ RUN ;
#1-2...........'................. RUN !
#1-3............................ RUN
#1-4............................ ~RUN j t
Makeup Pumps #1....................................... RUN i
#2....................................... STBY. ;
i 5 HPI Pumps #2.......................................... OFF
#2.......................................... :OFF l Decay' Heat Pumps-#1................................... OFF i
#2................................... OFF -
i Decay Heat Removal Coolers #1......................... RUN -!
#2......................... AVAIL Containment Spray Pumps #1............................ OFF !
#2............................ OFF. j Containment H2 Dilution Blowers #1..........,......... OFF -
#2.................... OFF !
1
-5 Containment Recirculation Fans #1..................... RUN :
#2..................... RUN l
^
Containment Air Cooler Units #1....................... RUN-SLOW
#2....................... RUN-SLOW i
#3.......................- OFF .
Component Cooling Water Pumps #1....................... RUN i l
#2...................... RUN !
#3....................... STBY l j
Service Water Pumps #1................................ RUN j RUN j
#2...............................~.
#3................................ STBY ,
Backup...............................'.. OFF j Auxiliary Feedwater Pumps #1.......................... OFF i
#2.......................... OFF 1 1
Motor Driven Feedpump ................................ OFF j O 1 , , i L i
~
i O O O DAVIS-BESSE NUCLEAR POWER' STATION PLANT PARAMETER SHEET _
'I t
SCENARIO NO. 1990 EVAL TIME: 09/45 _, R l CUE CARD NO. T: 09:45 .l
.. i
! REACTOR COOLANT CONTAINMENT RCS Pressure 2151 psig Ctat. Pressure- 15 psia T Avg. 582 *F Ctut. Temperature- 105 *F Th/Tc 589/576 *F Radiation (See Radiation Monitor Data Sheet) , Boron Concentration 530 ppa Sump Level (Normal /WR) 538/538 ft-l RCS Subcool. Marg. 56 *F Przr. Temp. 645 *F STEAM GENERATORS l Przr. Level _254 in S/G 1 Level / Press. 40 in -/ 874 psig l RCS Flow (Loop 1/2) 76/76 Mpph S/G 2 Level / Press. 40 in / 874 psig. PORV AUTO Block Valve CLOSED S/G Shell Temp. (1/2) 532 F / 532 *F Spray Valve AUTO Block Valve CLOSED Turbine Hdr. Pressure 872 psig : l- OPEN Letdown Flow 68 gpa MSIV Position j RCP Seal Flows 36 gpm (TOTAL) 1-1 9:gpm 2-1 9 gpm FEED & CONDENSATE ; l i 1-2 9 gpa. 2-2 9 gpa Main FW Flow (loop 1/2)- 1341/1358 Npph ' Quench Tank Level / Pressure 9 ft/ 25 psig Hotwell Level / Pressure 4 ft/ 3 in Hg' CST I4 vel: -(1/2) .40 / 40 ft REACTOR CORE . Aux. Feed Flow 0/0 gym Source Range Level (NI-1/NI-2) 0/0 cps Motor Driven Feed Pump Press. O psig j Intermediate Range (NI-3/NI-4) -3/-3 amps Power range (NI-5/NI-6) 31/31 %. ELECTRICAL :i (NI-7/NI-8) 31/31 % BUS A/B NORM / NORM Core Thermocouple (AVG) 589 *F- BUS C1/C2 NORM / NORM 1 4 BUS D1/D2- NORM / NORM-MAKE-UP AND ECCS EDG 1/2 NORM / NORM 480 VAC Distribution Makeup Flow. 130 gpm NORM Makeup Tank-Level / Pressure 71 in / 30 psig 250 VAC/125 VAC Dist. NORM 13 ft / 599 psig Inst. AC NORM Core' Flood Tank #1 Level / Press Generator Wattneter (Gross) ! Core Flood Tank f 3 Level / Press 13 ft / 599 psig 243 Mw l HP Injection Line Flow (1-1) 0 /(1-2)~0 (2-1) 0 /(2-2) 0 .- OTHER LP Injection Line Flow (1/2) 0 / 0 gpm. Instrument'&. Service Air DHR Hx Inlet Temp. (#1/f2) 100/100 *F 110/ NORM Ctat. Spray Flow (#1/#2) 0/0 gpm Spent Fuel Pool Level / Temp 24 ft/102 *F i CCW Surge-Tank Level (1/2) 51/52 in BWST Level 42 ft 'CCW Hx Outlet Temp (1/2) 95/95 *F.
. . , - - - . - . - . - - . - . - . . _ . . . . . - _ = - . - . . - . - - - - . - . . - - - - .. . . . .~
=>
EMERGENCY PIAN DRII1
. AND EXERCISE PR.OGRAM SCENAR10'NO. 90 EVAL TIME: 945 T: 00:45 :
DAVIS-BESSE NUCLEAR POWER. STATION f EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT STATUS l~ L COMPONENT: STATUS: ! Reactor Coolant Pumps #1-1............................ RUN !
#1-2............................ RUN :
#1-3............................ RUN
#1-4............................ RUN ,
Makeup Pumps #1....................................... RUN .
#2..............................~......... STBY' b
HPI Pumps #1...... 4.................................. OFF'
#2.......................................... OFF .;
Decay Heat Pumps #1................................... OFF
#2................................... OFF ;
.?
Decay Heat Removal coolers #1......................... 'RUN !
#2......................... AVAIL 1 Containment Spray Pumps #1............................ OFF j
#2............................ OFF ;
Containment H2 Dilution Blowers #1.................... 'OFF '!
#2....................- OFF' l.
I Containment. Recirculation Fans #1..................... RUN' t
#2..................... RUN ,
Containment Air Cooler Units #1................'....... RUN-S LOW . 1
#2....................... RUN-S LOW I
#3....................... OFF l
Component Cooling Water Pumps #1......................- RUN- '
#2...................... . RUN !
#3...................... STBY l l
Service Water Pumps #1................................- RUN
#2................................- RUN .
#3................................ STBY Backup................................ OFF ;
Auxiliary Feedwater Pumps #1........................... OFF
#2.......................... OFF i i
Motor Driven Feedpump ................................ OFF 1 ! L l l- ,e + ,
- o o o R
! DAVIS-BESSE NUCLEAR POWER STATION -
i PLANT PAPJWEETER SHEET j SCENARIO NO. 1990 EVAL TIME: 01/00 CUE CARD NO. T: 10:00 i REACTOR COOLANT CONTAINMENT 'l Ctat. Pressure- 15 psia .;j RCS Pressure 2152 psig
, T Avg. 577 *F Ctat. Temperature 105 *F 582/572 *F Radiation (See Radiation Monitor Data Sheet) 'l Th/Tc Boron Concentration 530 ppm Sump Level (Normal /WR) 538/538 ft i RCS Subcool. Marg. 64 *F Przr. Temp. 645 *F STEAM GENERATORS Przr. Level 254 in S/G 1 Level / Press. 40 in / 869 psig RCS Flow (Loop 1/2) 76/76 Mpph S/G 2' Level / Press. 40 in / 869 psig.
CIOSED S/G Shell Temp. ~(1/2) 530 F / 530 *F PORV AUTO Block Valve i Spray Valve AUTO Block Valve- CIDSED Turbine Hdr. Pressure 869 psig. Letdown Flow 52 gpu MSIV Position- OPEN - RCP Seal Flows 36 gpm (TOTAL) 1-1 9 gpa 2-1 9 gpa FEED & CONDENSATE 1-2 9 gpm 2-2 9 gpm Main FW Flow-(loop 1/2) 917/943 Mpph Quench Tank Level / Pressure ~ 9 ft/ 25 psig Hotwell Imvel/ Pressure . 4 ft/ 3'in Hg' CST Level (1/2) 40 / 40 ft REACTOR CORE . Aux. Feed Flow 0/0 gpa Source Range Level (NI-1/NI-2) 0/0 cps Motor Driven-Feed Pump Press. .O psig j Intermediate Range (NI-3/MI-4) -3/-3 amps ELECTRICAL Power. range (NI-5/NI-6) 19/19 % (NI-7/NI-8) ~19/19 % BUS A/B NORM / NORM Core Thermocouple (AVG) 581 *F BUS C1/C2 NORM / NORM BUS D1/D2 NORM / NORM MAKE-UP AND ECCS EDG 1/2 NORM / NORM Makeup Flow 160 gpm 480 VAC Distribution NORM
-Makeup Tank Level / Pressure 77 in / 30 psig 250 VAC/125 VAC Dist. NORM Inst. AC. NORM ~
Core Flood Tank #1 Level / Press 13 ft / 599 psig Core Flood Tank #2 Level / Press '13 ft / 599 psig Generator Wattneter (Gross) 174 Mw -] HP Injection Line Flow (1-1)'O /(1-2) 0 (2-1) 0 /(2-2) 0 OTHER
-LP Injection Line Flow (1/2) 0 / O - gpm '.
Instrument-E. Service Air DHR Hx Inlet. Temp. (#1/#2) 100/100 *F 110/ NORM Ctat. Spray Flow (#1/f2) 0/0 gpm Spent Fuel Pool Level / Temp. 24 ft/102 *F-CCW Surge Tank Level -(1/2) 51/52 in BWST Level 42 ft CCW Hx Outlet Temp (1/2) 95/95 *F
.____;...__-.___.____.._____..__._--_....___._...-__-..__._-.________________-l --
. _ - - __ ._ _ _ _ _ . _ _ _ _ . _ .. ._. . _ _. . . -~
EMERGENCY PLAN DRILL AND EXERCISE FROGRAM , t
- SCENARIO NO. 90 EVAL TIME: 1000
. T: 01:00 , i DAVIS-BESSE NUCLEAR-POWER STATION- : EMERGENbYPREPAREDNESSEXERCISE'EQUIPMENTSTATUS : s , .- , ; COMPONENT! STATUS: l Reactor Coolant Pumps #1-1............................ RUN -i
#1-2............................ . RUN. :
#1-3............................ RUN i
#1-4............................ RUN J Makeup Pumps #1.................................'...... .RUN j
#2....................................... STBY t i
'HPI Pumps #1.......................................... OFF, ;
#2.......................................... OFF- l
'I Decay' Heat Pumps #1................................... OFF.
#2................................... OFF :
.i Decay Heat Removal Coolers #1......................... RUN !
#2.........................- AVAIL i Containment Spray Pumps #1............................ OFFL !
#2............................ OFF [
! Containment H2 Dilution Blowers #1.................... OFF l #2.................... OFF Containment Recirculation Fans #1..................... RUN. ;
#2..................... 'RUN- 4
?
Containment Air Cooler Units #1....................... ! RUN-S LOW
#2.......................- 1RUN-SLOW f
#3....................... ' OFF-
- j. Component Cooling Water Pumps #1...................... RUN
#2...................... RUN-
#3...................... STBY i
S e rvice Wa te r Pumps # 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . RUN .
#2.....................'............ RUN !
#3................................ STBY l Backup................................ OFF
{ Auxiliary Feedwater Pumps #1.......................... OFF j
#2.......................... OFF !
I i Mot o r D riven Fe edpump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . OFF. ] . 1 I r
?
I
. . ~ . _ ._ _ _ . . _ _ _ _ _ .- .
~
O O O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME: 01/15 CUE CARD NO. T: 10:15 REACTOR COOLANT CONTAINMENT RCS Pressure 2113 psig Ctat. Pressure 15 psia T Avg. 560 *F Ctat. Temperature 105 *F Th/Tc 564/558 *F Radiation (See Radiation Monitor Data Sheet) Boron Concentration 530 ppm Somp Level-(Normal /WR) 538/538 ft RCS Subcool. Marg. 80 *F Przr. Temp. 643 *F STEAM GENERATORS Przr. Level 221 in S/G 1 Level / Press.-- 40 in / 871 psig RCS Flow (Loop 1/2) 76/76 Mpph S/G 2 Ievel/ Press. 40 in / 872 psig PORV AUTO Block Valve CIDSED -S/G Shell Temp. (1/2) 530 F / 530 *F Spray Valve AUTO Block Valve CIDSED Turbine Hdr. Pressure 877 psig Letdown Flow 52 gpa MSIV Position .OPEN RCP Seal-Flows 36 gpa (TOTAL) 1-1 9 gpm 2-1 9 gpm FEED & CONDENSATE 1-2 9 gpm 2-2 9 gpm Main FN Flow (loop 1/2) 573/594 Mpph Quench Tank Level / Pressure 9 ft/ 25 psig Hotwell Level / Pressure 4 ft/ 3 in Hg CST Level (1/2) 40 / 40 ft REACTOR CORE Aux. Feed Flow 0/0 gpa Source Range Level (NI-1/NI-2) 0/0 cps Motor Driven Feed Pump Press. O psig Intermediate Range (NI-3/NI-4) -3/-3 amps Power range (NI-5/NI-6) 10/10 % ELECTRICAL (NI-7/NI-8) 10/10 % BUS A/B NORM / NORM Core Thermocouple (AVG) 564'*F BUS C1/C2 NORM / NORM BUS D1/D2 - NORM / NORM-MAKE-UP AND ECCS EDG.1/2 NORM / NORM Makeup Flow 62 gpm 480 VAC Distribution NORM Makeup Tank Level / Pressure 72 in'/ 30 psig '250 VAC/125 VAC Dist.- NORM' Core Flood Tank #1 Level / Press 13 ft /.599 psig Inst. AC NORM Core Flood Tank #2 Level / Press 13 ft / 599 psig Generator Wattneter (Gross) O Mw HP Injection Line Flow (1-1) ~ O / (1-2) 0 (2-1) 0 /(2-2) O OTHER LP Injection Line Flow (1/2)'O / O gpm DHR Hx Inlet Temp. (#1/#2) 100/100 *F Instrument & Service' Air 110/ NORM Ctat. Spray Flow (#1/#2) 0/0 gpm ' Spent Fuel Pool Level / Temp 24 ft/102 *F i CCW Surge Tank Level (1/2) 51/52 in~ BWST Level 42 ft CCW Hx Outlet Temp (1/2) 95/95 *F-
'I
_ ~_ . . . -. . _ _ . _ _ _ . _ . M .2ENCY PLAN DRILL
- &EP EXERCISE PROGRAM !
I
-l SCENARIO NO. 90 EVAL TIME: '1015 )
T: 01:15 .l DAVIS-BESSE NUCLEAR' POWER STATION ! EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT STATUS ! COMPONENT: STATUS: l Reactor Coolant Pumps #1-1............................ RUN .j
#1-2............................ RUN ,
#1-3......'...................... RUN l
#1-4............................ RUN Makeup Pumps #1....................................... RUN !
#2....................................... -STBY- j .
HPI Pumps #1.......................................... OFF' :
#2.......................................... OFF i
- De c a y He at ' Pumps . # 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . OFF
#2................................... OFF Decay' Heat Removal-Coolers #1......................... RUN= U
#2.......................~..- AVAIL ;
Containment Spray Pumps #1............................ OFF- . I
#2............................ OFF i
Containment H2 Dilution Blowers #1.................... OFF- ;i
#2.............~........ OFF Containment Recirculation Fans #1..................... .-RUN- i
#2..................... RUN
{ Containment Air Cooler Units #1....................... RUN-S LOW !
#2....................... RUN-S LOW ;
#3.......................- OFF ,;
Component Cooling Water Pumps #1...................... RUN :
#2...................... RUN
#3....................... STBY l I
Service Water Pumps #1................................ RUN i
#2...................'.............- RUN
#3................................ STBY q Backup................................ OFF j j
Auxiliary Feedwater Pumps #1........................... OFF :
#2.......................... OFF Motor Driven Feedpump ................................ OFF.
O i
H DAVIS-BES PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME: 01/30 CUE CARD NO. , T: 10:30 REACTOR COOLANT CONTAINMENT RCS Pressure 2162 psig Ctat. Pressure 15 psia T Avg. 542 *F Ctat. Temperature 105-*F 4 Th/Tc 544/541 *F Radiation (See Radiation Monitor Data Sheet) Boron Concentration- 530 ppa Sump Level (Normal /WR) -538/538.ft. RCS Subcool. Marg. 102 *F Przr. Temp. 644 *F STEAM GENERATORS Przr. Level 160.in S/G 1 Level / Press.- 40 in / 872 psig.
- RCS Flow (Loop 1/2) 76/76 Mpph S/G 2 Imvel/ Press. L 40.
- in f/ 872 psig PORV AUTO Block Valve CIDSED S/G Shell Temp. (1/2)l530 F / 530 *F.
Srcay Valve AUTO Block Valve CIDSED Turbine Hdr. Pressure 877 psig Letdown Flow 52 gpm- MSIV Position OPEN RCP Seal Flows 36 gpm (TOTAL) 1-1 9 gpm 2-1 9 gpm FEED fr CONDENSATE 1-2 9 gpm 2-2 9 gpm Main FW Flow (loop-1/2) ~ 226/243 Mpph Quench Tank Level / Pressure 9 ft/ 25 psig Hotwell. Level / Pressure 4 ft/ 3 in Hg'
-(1/2)
~
CST Level- 40 / 40 ft REACTOR CORE Aux. Feed Flow' 0/0 gpm Source Range Level (NI-1/NI-2) 0/0 cps Motor Driven Feed Pump Press. O psig Intermediate Range (NI-3/NI-4) -3/-3 amps Power range (NI-5/NI-6) 3/3 % ELECTRICAL (NI-7/NI-8) 3/3'% BUS A/B. NORM / NORM Core Thermocouple (AVG) 544 *F BUS-C1/C2. NORM / NORM BUS D1/D2 NORM / NORM MAKE-UP AND ECCS EDG 1/2 NORM / NORM l Makeup Flow 160 gpe. 480 VAC Distribution NORM Makeup Tank Level / Pressure 57 in /.30 psig 250 VAC/125 VAC-Dist. :-NORM Core Flood Tank #1 Level / Press 13 ft / 599 psig Inst. AC ' NORM Core Flood Tank #2 Level / Press .13 ft / 599 psig Generator Wattneter (Gross)... O Mw [ HP Injection Line Flow (1-1) 0 /(1-2) 0- - (2-1) 0 /(2-2) 0 OTHER 1 LP Injection Line Flow (1/2) 0 / 0 gpm . DHR Hx Inlet. Temp. ( #1/ #2) ; .100/100 *F Instrument & Service Air _110/ NORM Ctat. Spray Flow "(#1/#2) 0/0 gpm Spent Fuel Pool Level / Temp 24 ft/102 *F
- CCW Surge Tank Level (1/2) 51/52 in
- BWST Level 42 ft CCW Hx Outlet Temp (1/2);95/95 *F
_ _ . _ . , _ . . . ~ _ . _ _ , _ _ . _ _ . . . - . _ . . . . . - . - . - , ~ - _ _ , _ _ - _ _ . _ _ _ _ - - _ _ _ _ _ . . _ _ _ _ __ _ _ __i
EMERGENCY PLAN DRILL l AND EXERCISE PROGRAM l l 1 SCENARIO NO.. 90 EVAL TIME:' 1030-T: 01:30 l. DAVIS-BESSE_ NUCLEAR POWER STATION 'l EMERGENCY PREPAREDNESS EXERCISE' EQUIPMENT STATUS t COMPONENT ' _ STATUS: l Reactor Coolant Pumps #1-1............................ RUN ;
#1-2............................ RUN .l
#1-3..............'.............. RUN- ;
#1-4.'........................... RUN.
Makeup. Pumps #1.......................................- RUN l
#2...................'.................... STBY j
- HPI Pumps #1.................................'......... OFF
#2.......................................... OFF {
l ' t . . , l< Decay Heat Pumps #1................................... OFF ; , #2................................... OFF , I i Decay _ Heat' Removal Coolers #1......................... RUN t
#2.........................- AVAIL Containment Spray Pumps #1............................ OFF
#2............................ OFF ,
Containment H2 Dilution Blowers-#1.................... OFF -
#2........~............ OFF s
l- Containment Recirculation Fans #1..................;.. RUN
#2..................... RUN ,
Containment Air Cooler Units #1....................... RUN-SLOW i L
#2....................... RUN-SLOW
#3....................... OFF Component Cooling Water Pumps #1...................... RUN- t
#2....................... RUN i
#3....................... STBY Service Water Pumps #1................................ RUN
#2................................ RUN
#3................................. STBY .i Backup................................ OFF i Auxiliary _Feedwater Pumps #1.......................... OFF ,
#2.......................... OFF Motor Driven Feedpump ................................. OFF G!
-?
i i
~, - _ m. _ _,- ,. , . - . . . , - . . . - . ,
- O
~
e O O . -1 DAVIS-BESSE NUCLEAR POWER STATION i PIANT PARAMETER SHEET , i ! SCENARIO NO. 1990 EVAL TIME: 01/45
- CUE CARD NO. T: '10:45 .
REACTOR COOIANT CONTAINMENT RCS' Pressure 2175 psig Ctat._ Pressure 15 psia T Avg. 534 *F Ctat. Temperature 105 *F Th/Tc 535/534 *F Radiation (See-Radiation Monitor Data Sheet) Boron Concentration 529 ppm Sump Imvel (Normal /WR) 538/538'ft RCS Subcool. Marg. 112 *F
- Przr. Temp. 644 *F STEAM GENERATORS Przr. Level 110 in S/G 1. Level / Press. 40 in / 872 psig RCS Flow (Loop 1/2) 76/76 Mpph S/G _2 Imvel/ Press. . 40 in / 872 psig. 1 PORV AUTO Block Valve CIDSED S/G Shell Temp.- (1/2) 530 F / 530 *F I Spray Valve AUTO Block' Valve CIDSED Turbine Hdr. Pressure 877 psig-Letdown Flow 52 gpa MSIV Position. OPEN RCP Seal Flows 36 gpm (TOTAL) ,
FEED & CONDENSATE 4 1-1 9 gpm 2-1 9 gpa 1-2 9 gpa 2-2 9 gpm Main FW Flow (loop 1/2). 66/82 Mpph Quench Tank Level / Pressure 9 ft/ 25 psig Hotwell Level / Pressure 4 ft/ 3 in Hg CST Level (1/2) 40 / 40 ft--
. REACTOR CORE Aux. Feed' Flow .
0/0 gym 4 Source Range Level (NI-1/NI-2) 6/6 cps. Motor' Driven Feed Pump Press. O psig Intermediate Range (NI-3/NI-4) -4/-4 amps Power range (NI-5/NI-6) 0/0 % ELECTRICAL ! (NI-7/NI-8) 0/0 % BUS A/B NORM / NORM i Core Thermocouple (AVG) 535 *F BUS C1/C2- NORM / NORM BUS-D1/D2 NORM / NORM t
~!
. MAKE-UP AND ECCS~ EDG 1/2 NORM / NORM Makeup Flow 79 gpm 480.VAC Distribution- NORM-Makeup Tank Level / Pressure 72 in'/-30-psig 250 VAC/125 VAC Dist. NORM-
- Core Flood Tank #1 Level / Press'.13.ft./-599 psig Inst. AC- NORM .t 2
Core Flood Tank #2 I4 vel / Press 13 ft / 599 psig Generator Wattneter (Gross) O Mw HP Injection Line Flow (1-1) 0 /(1-2) O ; (2-1) 0 /(2-2) 0 OTHER
? "' Injection Line Flow (1/2) 0 / 0 gpm
{ D;.R Hx Inlet Temp. Instrument & Service Air- ~ 110/ NORM Ctat. Spray Flow (#1/#2) (#1/#2)~ 0/0 gpm _ 100/100 *F Spent Fuel Pool ~ Level / Temp 24-ft/102 *F f CCW Surge Tank Level (1/2) 51/52 in i BWST Level 42 ft CCW Hx Outlet Temp (1/2) 95/95 *F-i i _._._..._ __ _____.._._. ~ _ ~_...._. - .~..,._ ....__ _._.. ._.: ._..- .___ ....: ,_.___.-
EMERGENCY PLAN DRTLL ! AND EXERCISE PROGRAM < i t SCENARIO NO. 90 EVAL TIME: 1045 ! T: 01:45 DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT STATUS t
?
COMPONENT: STATUS. - Reactor Coolant Pumps #1-1................ ........... RUN ;
#1-2............................ RUN 4
#1-3............................ RUN l
#1-4............................ RUN Makeup Pumps #1....................................... RUN ;
#2.......'................................ STBY :
HPI. Pumps #1.......................................... OFF. '
#2.............................'.............. OFF. ;
Decay Heat Pumps #1................................... 0FF !
#2................................... OFF. 1 Decay Heat Removal Coolers #1......................... RUN
#2......................... AVAIL i i
Containment Spray Pumps #1............................ OFF j
#2'............................. OFF 4 Containment H2 Dilution Blowers #1.................... OFF !
#2.................;.. -OFF j
Containment Recirculation Fans #1..................... RUN
#2..................... RUN l i
t Containment Air Cooler Units #1....................... RUN-SLOW !
#2.......................' RUN-S LOW I
#3.................'...... OFF ;
)
Component Cooling Water Pumps #1...................... RUN l
#2...................... RUN l
#3....................... STBY !
Service Water Pumps #1................................. RUN 1
#2................................ RUN ,
#3................................ STBY !
Backup................................ OFF l t
'l Auxiliary Feedwater Pumps #1.......................... OFF ;
#2.......................... OFF q Motor Driven Feedpump ................................ .
OFF t 1 1 z, e i s
~
L O O O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET i' TIME: 02/00 SCENARIO NO. 1990 EVAL CUE CARD NO. T: 11:00 REACTOR COOLANT CONTAINMENT RCS Pressure 2145 psig Ctat. Pressure 15 psia T Avg. 534 *F Ctat. Temperature 105 *F Th/Tc 535/534 *F Radiation (See Radiation Monitor Data Sheet) Boron Concentration 528 ppm Sump Level (Normal /WR) .538/538-ft RCS Subcool. Marg. 110 *F Przr. Temp. 645 *F STEAM GENERATORS Przr. Level 111 in S/G 1 Invel/ Press. 40 in / 872 psig RCS Flow (Loop 1/2) 76/76 Mpph S/G 2 Level / Press. 40 in / 872 psig PORV AUTO Block Valve CIDSED S/G Shell Temp. .(1/2) 530. F /.530 *F Spray Valve AUTO Block Valve CIDSED Turbine Hdr. Pressure- 877 psig Letdown Flow 52 gpm .MSIV Position OPEN RCP Seal Flows 36 gpm (TOTAL) 1-1 9 gpa 2-1 9 gpm FEED & CONDENSATE 1-2 9 gpm 2-2 9 gpm Main FW Flow (loop 1/2) 59/74 Mpph Quench Tank Level / Pressure 9 ft/ 25 psig Hotwell Level / Pressure 4~ft/ 3 in Hg ~ l. CST Level (1/2) 40 / 40 ft j
- REACTOR CORE . tux. Feed. Flow . 0/0 gym i
Source Range Level.(NI-1/NI-2) 5/5 cps Aotor Driven Feed Pump Press. _0 psig .i i, Intermediate Range (NI-3/NI-4) -12/-12 amps- ' Power range (NI-5/NI-6) 0/0 % ELECTRICAL . i (NI-7/NI-8) 0/0 % ~ BUS A/B NORM / NORM Core Thermocouple (AVG) 535 *F BUS C1/C2~ . NORM / NORM
~ BUS D1/D2 : NORM / NORM MAKE-UP AND ECCS ._
EDG 1/2 NORM / NORM ? Makeup Flow 61 gpm 480'VAC Distribution NORM' Makeup Tank Level / Pressure 62'in / 30-psig
~ 250 VAC/125 VAC Dist. NORM Core Flood' Tank #1 Level / Press 13 ft./ 599 psig- Inst. AC . NORM Core Flood Tank #2 Level / Press- 13 ft / 599 psig Generator Wattneter (Gross) 0 Nw-
- HP. Injection Line Flow
- (1-1) O /(1-2) 0
! (2-1) . 0 / (2-2) 0 OTHER , LP' Injection Line Flow (1/2) 0 / 0 gpm i DHR Hx Inlet' Temp. (#1/f2) 100/100 *F Instrument Kr-Service Air 110/ NORM Ctat. Spray Flow (#1/42).0/0 gpm Spent Fuel Pool-Level / Temp 24 ft/102 *F CCW Surge Tank Level (1/2)1 51/52 in BWST Level 42 ft 'CCW Hx Outlet Temp (1/2) 95/95 *F i
.j
. __.._ _.._ _ . ~ _ _._ _ _ _ _ __ _ __ _.___ _ . _ __ ___ . .. ._. _ _ .__ _ _ _ _.
I b EMERGENCY PLAN DRILL AND EXERCISE PROGRAM SCENARIO NO. 90 EVAL' - TIME: 1100~ T: 02:00 DAVIS-BESSE' NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT STATUS ; I e COMPONENT: STATUS: > t Reactor Coolant Pumps #1-1............................ RUN
#1-2............................' RUN -;
#1-3............................ RUN, 6
#1-4............................ RUN :i Makeup Pumps #1....................................... :RUN j
#2.......................................- STBY :
i, HPI Pumps #1.......................................... OFF l
'#2...........................................'OFF i Decay Heat, Pumps-#1................'................... OFF
#2................................... OFF. ;
Decay Heat Removal Coolers #1.............~............ . RUN l
#2......................... AVAIL- ;
Containment Spray Pumps #1............................ OFF
#2............................ OFF 1
Containment H2 Dilution Blowers #1....................- OFF
#2.................... Orr ,
-t Containment Recirculation Fans #1..................... ~RUN- -i
#2..................... RUN.
l Containment Air Cooler Units #1................'........ RUN-SLOW 3
#2....................... RUN-SLOW l
-#3....................... OFF !
Component Cooling Water Pumps #1.................. . ... RUN
#2......................- RUN i
~
#3...................... STBY l i
Service Water Pumps #1................................- RUN ,
#2........'..................:...... RUN
#3................................ STBY !
Backup................................ OFF t Auxiliary Feedwater Pumps #1.......................... OFF
#2.......................... OFF .;
, i l-Motor Driven Feedpump ................................ OFF j l' l i i la , L = - ------- ,, ,,,e ,- w .e , . - - - - , , - m -. -a y
O: O O ^
' DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME: 02/15
, CUE CARD NO. T: 11:15 REACTOR COOIANT CONTAINMENT RCS Pressure 2143 psig Ctat.. Pressure 15 psia T Avg. 532 *F- Ctat. Temperature 105.*F i .Th/Tc 533/532 *F Radiation-(See Radiation Monitor-Data Sheet) .j l Boron Concentration '615 ppa Sump Level (Normal /WR) 538/538 ft RCS Subcool. Marg. 112 *F Przr. Temp. 645 *F STEAM GENERATORS . Przr. Level 41 in S/G 1 Level / Press. 70 in / 869 psig S/G 2 Imvel/ Press. 40 in- / 872 psig. ! RCS Flow (Loop 1/2) 76/76 Mpph , ! PORV AUTO Block Valve CIDSED _S/G Shell Temp.- (1/2) 530 F / 530 *F
~
i- Spray Valve AUTO Block Valve CLOSED Turbine Hdr.iPressure' 874 psig Letdown Flow 0 gpa MSIV Position OPEN i RCP Seal Flows 36 gpm (TOTAL) { 1-1 9 gpm 1 9 gpu FEED 6 CONDENSATE . ; 1-2 9 gpa 2-2 9 gpa Main FW Flow.(loop 1/2) 0/41 Mpph Hotwell Level / Pressure- 4 ft/ 3 in Hg i Quench Tank Level / Pressure 9 ft/ 25 psig -l CST Level (1/2) 40 / 40.ft-l REACTOR CORE .
. Aux. Feed Flow 0/0 gym i Source Range Level (NI-1/NI-2) 5/5 cps Motor Driven Feed Pump Press. 'O psig Intermediate Range (NI-3/NI-4)--12/-12 amps j
-Power range (NI-5/NI-6) 0/0 % EIZCTRICAL (NI-7/NI-8) 0/0 ' % ' BUS A/B .
NORM / NORM. l Core Thermocouple .(AVG) 533 *F . BUS C1/C2-~ NORM / NORM l -BUS D1/D2 .OFF/ NORM ! MAKE-UP AND ECCS- ~ EDG~1/2 NORM / NORM i Makeup Flow- x. 160 gpm' 480 VAC Distribution NORM Makeup Tank Level / Pressure 100 in / 30 psig 250 VAC/125 VAC Dist. NORM- ! NORM
~
Core Flood Tank fl..-Level / Press 13-ft / 599 psig- ~ Inst. AC Core Flood Tank #2 Level / Press' 13 ft / 599 psig Generator Wattneter (Gross) O Mw HP Injection Line Flow (1-1) 0 /(1-2)L0 (2-1} 0 /(2-2) 0 OTHER i
'LP Injection Line Flow- -(1/2) 0 / O gpm DHR Hx Inlet Temp. ( #1/#2).' 70/70 '
- F Instrument &' Service-Air- 110/ NORM Ctat. Spray F1ow (#1/#2) 0/0 gpm Spent Fuel Pool Level / Temp- 24 ft/102 *F CCW' Surge Tank Level (1/2) 51/52 in .j BWST Level 42:ft CCW Hx Outlet Temp (1/2) 95/95 *F 4
EMERGENCY PLAN DRILL AND EXERCISE PROGRAM SCENARIO NO. 90 EVAL TIME: 1115 T: 02 15 DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT STATUS COMPONENT: STATUS: Reactor Coolant Pumps #1-1............................ RUN
#1-2............................ RUN
#1-3............................ RUN
#1-4............................ 'RUN j Makeup Pumps #1....................................... RUN I
#2..................................'..... OOS HPI Pumps #1.......................................... RUN
#2;......................................... OOS Decay Heat Pumps #1................................... RUN
#2................................... OOS Decay Heat Removal Coolers #1......................... -RUN
#2......................... AVAIL Containment Spray Pumps #1............................ OFF
#2............................ OFF Containment H2 Dilution Blowers.#1.................... OFF
#2................ ... OFF Containment Recirculation Fans #1..................... RUN
#2..................... RUN.
Containment Air Cooler Units $1....................... RUN-SLOW
#2....................... RUN-SLOW
#3....................... OFF Component Cooling Water Pumps'#1...................... RUN
#2...................... OOS
#3...................... STBY-Service Water Pumps #1................................ RUN
#2........................-........ OOS
#3................................ STBY Backup................................ OFF Auxiliary Feedwater Pumps #1........................... OFF
#2.......................... OFF Motor Driven Feedpump................................. OFF
o o o DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME: 02/30' CUE CARD NO. T: 11:30 REACTOR COOLANT CONTAIMMENT RCS Pressure 1970 psig Ctat. . Pressure - 15 psia T Avg. 520 *F Ctat. Temperature 105 *F-Th/Tc 508/507 *F Radiation (See Radiation Monitor Data Sheet) Boron Concentration 917 ppa Sump Imvel (Normal /WR): 538/538 ft i. RCS Subcool. Marg. 50 *F Przr. Temp. 558 *F STEAN GENERATORS Przr. Level 0 in S/G.1 Level / Press. 270 in / 707 psig RCS Flow (Loop I,f.) 76/76 Mpph S/G~2 Level / Press. 124 in: / 713 psig . S/G Shell Temp. (1/2) 529 F / 528 *F PORV AUTO Block Valve CLOSED j- Spray Valve AUTO Block Valve CLOSED - Turbine Hdr. Pressure 600 psig Letdown Flow 0 gpm MSIV Position CIDSED i RCP Seal Flows 36 gpm (TOTAL) l 1-1 9 gpm 2-1 9 gpa FEED & CONDENSATE l 1-2 9 gpm 2-2 9 gpm Main FW Flow (loop.1/2) 0/0 Mpph
- Quench Tank Level / Pressure 9 ft/ 25 psig Hotwell IAvel/ Pressure - 4 ft/ 30 in Hg l
CST Level . (1/2) 40'/ 40 ft REACTOR CORE . Aux. Feed Flow 0/37 gpu ; Source-Range Level (NI-1/NI-2) 5/5 cps Motor Driven Feed Pump Press. O psig-Intermediate-Range (NI-3/NI-4) -12/-12 amps Power range (NI-5/NI-6) 0/0 % ELECTRICAL (NI-7/NI-8) O/0 %* BUS A/B ' NORM / NORM Core Thermocouple (AVG) 508 F BUS C1/C2 NORM / NORM BUS D1/D2 OFF/ NORM i MAKE-UP AND ECCS EDG 1/2 RUN/RUN Makeup Flow' 160 gpm 480 VAC Distribution NORM- .i Makeup Tank Level / Pressure 100 in /'30.psig 250 VAC/125 VAC Dist. NORM Core Flood Tank #1 Level / Press 13 ft /.;599 psig. Inst. AC NORM 4 Core Flood Tank #2. Level / Press 13 ft / 599 psig Generator Wattneter-(Gross) O Mw HP Injection Line Flow (1-1) 336 /(1-2) 336 (2-1) 0 / (2-2) O OTHER - LP Injection Line Flow -(1/2) 0 /.O'gpm ! DHR Hx Inlet Temp. (#1/#2) 70/70 *F -Instrument &. Service Air 110/ NORM
,. Ctat. Spray Flow (#1/#2) 0/0 gpm Spent Fuel Pool. Level / Temp 24 ft/102 *F-
! - CCW Surge Tank Level (1/2) 51/52 in l BWST Level 42 ft' CCW: Hx' Outlet Temp (1/2)'95/95 *F ,
.y-e ng c y a
e 4t,-,.e-,,-'.,m-,.,-.w-*,.cg. ,,,gg,.-,w A 'sWvg ww-:'-w+ws mir p- "ee-gi+--- s g*.e--+-g-we-d~e - y--w-*w+,eas 'rerea w-v' -W***ev'*N'eW'"v" --1e T 9' e e 6 - em -We--**-*um' "l-n*- '+'e u 4 -**WA eet'-C-.' enes a 16---h--h -- - - - - --s--
- g. . -- . -
'to , i r i-(
l: s ,' '
]= ' ,
i j l: ~ ( l
- i. -n .
l i.7 , EMERGENCY PLAN DRILL , j h ' AND EXERCISE PROGRAM ! SCENARIO NOL 90 EVAL' TIME:; 1130 T: 02:30 , .- ,,} ll ' , o . DAVIS-BESSE NUCLEAR > POWER STATION ^i EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT! STATUS' ! COMPONENT: STATUSi ! Reactor 1 Cool ant Pumps # 1-1. . . . . .. . . . , . . . .. . -. . . . . . . . . . . . . - OFF
, .i' i # 1 - 2 . . . . . . . . . . . . . . . . . . . . : .' . . . . . . . ' . .
RUN,
#1-3..:........................-......
. RUN
#1 4.'...c......../.2............. 'RUN: .
f'*, i M a k e u p P u m p s i # 1 . . . .'. . .'.:.:. . . . . . . .=. . . . . . . . . . . . . . . . . . . . . . - RUN.
#2.....'...............'............'.....:..: '005 M:
.I H PI Pump s # 1.. . . . . . . . . . . . . . . . . '. . . . . . . -. . . - . . . . . . . . . . .. . . . . .' . . - . RUN. 4
-#2.......................................-........: OOS. s j
9 Decay' Heat Pumps [#12....................~..........-.....:' HUN. j y i#2...........?.....'...................'.1 ,OOS M, J DecayJ Heat Removal ~- Coolers - # 1. .x.'. . . . . . .. . . . . . . .. ' . . . . . . . RUN= t
#2.......................... AVAIL' , .
; containment Spray Pumps' "t # 1. . . . . . . . . . .. = . ;. .;. . :. . . '. . . . . . . .- :OFFi
#2.....'........'.'......".'.'.1.;.'.. -: OFF -
Containment:H2.DilutionLBlowers1#1.................... OFF ~i
#2.-...............'....-
OFF' ,; : 1 Containment 1 Recirculation
- Fans #1. . . . . ... . . . '. . . . . .'. . . . .- 'RUN: ,
1
#2..'.................... RUN4 3
x' L' Containment - Air! Cooler Units #1. . . .:. . . . . -. . . . . . . . . . . .L. . -RUN-SLOW
~
Li
'#2..........c..'..........- )RUN-SLOW-
. l'
, #3.......................' OFF: ..e 1 Component Cooling Water Pumps:#1...............'...-.... RUN-
#2....'..........'...'.....: 005
#3......................- 'STBY .
Service Water Pumps #1.................... ............ RUN
#2.....:.......................-. . .... OOS. '
# 3 . . . . . . . . . . '. . . . . . . . . . . . . . . . . . . . . . .' . L S T B Y Backup................................. OFF.
Auxiliary Feedwater Pumps #1........................... OFF, 3
#2.............'............. 'OFF Motor Driven Feedpump ................................- - OFF- ,
9i ikk _ :_ _ _ _ , _ . , a. . . .:___ , ,,..1 . . _ . . . _ . _ . . , . _
4: y e - m n_ _ _ ,
~
(.:. , DAVIS-BESSE-NUCLEAk-POWER STATION-
~
- I
-[ ~ PLANT PARAMETER SHEET - SCENARIO NO.- :1990 EVAL - 1 TIME: '02/45 - CUE-CARD NO. .T: 11:45-
! REACTOR 1 COOLANT CONTAINMENT '
I ' RCS Pressure 847 psig. Ctat. . Pressure '15 psia; ~ T Avg. 520 *F Ctat.-Temperature .
. 105 *F~
Th/Tc 483/481
- F Radiation;(See Radiation Monitor Data Sheet): ;
Boron Concentration 1229 ppm Sump _ Level (Normal /WR)-t538/538'ft '
- RCS Subcool. Marg. 48'*F STEAM GENERATORS
~
! Przr. Temp. 531 *F - Przr. Level 108 in - S/G ~ 1; Le. vel / Press.:. _ 270 fin c/l_554 psig
- - - RCS Flow (Loop 1/2) 34/34 Mpph .
S/G~2 Level / Press.~. . 124 in '/.670 psig. PORV AUTO Block Valve CIDSED - -S/G ShelltTemp.: (1/2)"525.:F / 519 ' F " . Spray Valve AUTO- Block Valve CLOSED, Turbine Hdr. Pressure '600;psig Letdown Flow JO gpm- MSIV Position' H ! CIDSED _. ! RCP Seal Flows 36 gpm (TOTAL)'. 1-1 9_;gpm 2 --1 ~ 9Lgpm . FEED E CONDENSATE 1-2 9l.gpm 2-2 -9 gpm Main FW Flow (loop 1/2) 0/0 Mpph c Quench Tank" Level / Pressure 9 ft/ 25 psig: Hotwell-- Level / Pressure '4 ft/l30 in.Hg " CST Levelf . _ c(1/2): 39.5 / 39.5:ft' - REACTOR' CORE nAux.: Feed Flow . . . . 0/41 gpa Source Range Level-(NI-1/NI-2) 5/5-cps MotorsDriven Feed.. Pump Press. 0 psig - ~ Intermediate Range ~(NI-3/NI-4) -12/-12 amps-U Powerrrange .(NI-5/NI-6) ' 0/0 % JLECTRICAL i .
' (NI-7/NI-8) . : 0/0 %; BUS A/B' NORM / NORM e
, ' Core Thermocouple (AVG). ' 483^*F. BUS C1/C2. NORM / NORM . BUS D1/D2. ~ OFF/ NORM MAKE-UP'AND ECCS-
- - .EDG 1/2~. .
RUN/RUN , - MakeupfFlow '160 gpm~ .
- 480. VAC Distributilon - NORM
! Makeup ^ Tank Level / Pressure- 100;in5/ 30 psig 250 VAC/125 VAC Dist. . NORM: Core: Flood Tank #1' Level / Press'}:131ft /i599 psig Inst.1AC, . NORM ~ E Core' Flood Tank #2 Level / Press J13ift~ / 599 psig. Generator:WattneterL(Gross); ; O Mw-
~ ~
I HP Injection Line Flow. . (1-1)1240-/(1-2)1240 .. .. 1
-i -
-(2-1) 10 '/ (2-2) LO . LOTHER z 4 LP. Injection _.Line Flow.~ .(1/2) 0 /.0:gpmi- ..
6 'DHREHx Inlet. Temp. (#1/#2) 70/70:*F Instrument &TService Air. 110/ NORM- -- 4 Ctmt.' Spray. Flow (#1/#2) 0/0 gpm .. Soent Fuell Pool f Level / Temp' . . 241ft/102:*F: - (1/2) 51/52'in TCW Surge: Tank Level i BWST Level 42 ft .CCW Hx Outlet l Temp ^
~
(1/2) 95/95'*F: o .
-W ' o-i-w-Y w * = , , a r.- d. = - m ---*,-m-_m-t-__
_. .--a _. m--m__e ---.e_.1-'- .s . w' sa4^*...__".<-e.#_---a __[_-ei,-.-r*"*-__.--om.m . .$<--__..-m__a-._.m._ - __m -c,m.w-__ .n[.____.-.~_.--,--
, . . . . . _~. . -- _- .. -- ,
L :! 8 9 w . 1 $ EMERGENCY PLAN DRILL ~l AND EXERCISE PROGRAM 6
' ~ SCENARIO NO.4 90-EVAL' TIME:' 1145- mi T: 02:45- , ;
, : DAVIS-BESSE' NUCLEAR POWER STATION l
~ EMERGENCY PREPAREDNESS EXERCISE, EQUIPMENT STATUS: !
I COMPONENT: STATUS:~ j Re a ctor. Coo l ant Pump s # 1'- 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . OFF !
#1-2'............................'.'.- RUN ',
.#1-3..................-..-......... RUN. '
4
; , #1-4......'.......'..'.............~.,
RUN . ,, Ma . 'e up . Pump s # 1. . . . . . . . . . . . '. . . . . . . . . .' . . . . . . . . . . . . : . - . ' . . . . RdN.., .j j
. #2............:...............~............- ..
OOS , H PI Pump s # 11 . . . . . . . . . . . . . . . . . . . . : . . . . . . ' . . . . . . .' . . . . . . . . RONI ; 4
#2...'..........'..............................-.- OOS i ', ,
De c ay He a t Pumps # 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . - . . . . . . .. RUN, s s R
#2.................'.'................. .OOS, ,
1i
- i Decay Heat Ramo'v'al . Coolers # 1 L. . . . . ... . .. . . . . . . . . . .-. . . . . RUN~ . o O j!
'#2.................:.......... AVAIL",
j t-
.Conta inment Spray Pumps . # 1. . . . . . . . . . . . . . . . . . . . . . . . . . . .: OFF i
'#2............................. OFF Containment H2 Dilution Blowers #1. . . . . . . . . . . . . . . . . . . . i - OFF
#2.................... .0FF ' , q Containment Recirculation Fans #1. . . . . . . . . . . . . .'.'. . . . . . -RUN' , '!
'#2.......-.............. RUN' i
Containment Air Cooler Units #1. . . . . . . . . . ... . . . . . . . . . . . RUN-SLOW
#2.................-....... RUN-SLOW =j
#3.......................'. "OFF' :
l ; Component Cooling Water Pumps # 1. . . . . . . . . . . . . . . . . . .. . . . . ' RUN -
#2....c.................- OOS . j
#3....................... 'STBY ;
i S e rv i c e Wa t e r Pump s # 1. . . . . . . . . . . . . . . . . . . . . . - . . . . . . . . . ~.- RUN
# 2 . . . . . . . . . . . . . . . . . . . . . . . .-... . . . . . . - O O S >
#3..............................~... STBY Backup................................ OFF ai i
Auxiliary Feedwater Pumps # 1s . . . . . . .' . . . . . . . . -. . . '. . . . . ... RUN
#2.......................... .RUN' ,
Motor Driven . Feedpump . . . . . . . . . . . . . . . .. . -. . . . . . . . . . .. . . . . OFF-. f l l; > l i l J kI. ve.
. . - . . . , , - - . - . _ . . . . < . * . . ., . . ~ . _ . , , - . . . , .,,.m , . . . . . . , .
r,,
^
O O O ; DAVIS-BESSE NUCLEAR POWER' STATIM - cj PLANT PARAMETER SHEEI l SCENARIO NO. 1990 EVAL TIME: 03/00~ N f
' CUE CARD NO.
~
T: - 12:00' i CONTAINMENT
~
I
-REACTOR COOLANT .
l RCS Pressure 903 psig Ctat. Pressure 15 psia L T' Avg. 520 *F Ctat. Temperature' 105 *F-Th/Tc 468/465 *F Radiation-(See Radiation ~ Monitor Data Sheet) i Boron Concentration 1392 ppa Sump Level (Normal /WR)~ -538/538 ft~ ' < RCS Subcool. Marg. 71
- F -l
- Przr. Temp. 538 *F STEAM GENERATORS _
t Przr.-Level 105-in S/G.~1 Level / Press. .270'.in -
/L459-psig'
! - 'RCS Flow (Loop 1/2) 34/34 Mpph 3/G : 2 nLevel/ Press.. 124 in /.819 psig.. PORV AUTO Block Valve CIOSED S/G'Shell Temp. (1/2)'505; F f 507.*F !~ Spray' Valve AUTO Block Valve CLOSED Turbine 1Hdr.1 Pressure 600 psig , Letdown Flow O gpm -MSIV Position: CLOSED RCP Seal' Flows 36 gpm (TOTAL) 1-1 9 gpm :2-1 9 gpm FEED & CONDENSATE -- 1-2-- 9 gpm 2-2~ .9 gpm Main:FW Flowf(loop!1/2)- .0/0 Mpph .. Quench Tank Level / Pressure' 9 ft/-25 psig HotwellLLevel/ Pressure-~ '4 ft/.30 in Hg. CST Level: (1/2) 39 /'39 ft REACTOR CORE-- Aux.DFeedIFlow-~ . 0/43 gpm Source' Range Level.(NI-1/NI-2) 5/5 cps. Motor Driven: Feed Pump Press..;0 psig-' ' ' Intermediate Range (NI-3/NI-4) -12/-12 amps ELECTRICAL .;
- Power range. ~ (NI-5/NI-6) , 0/0 % -' _
BUS A/B-
.l (NI-7/NI-8) 0/0 %. _. ' NORM / NORM _
- . Core Thermocouple (AVG) 468 *F BUS C1/C2 NORM / NORM ~
} jBUS[D1/D2, . OFF/ NORM ?
~~
MAKE-UP'AND ECCS - EDG ~ 1/ 2 ' . .
?RUN/RUN
- Makeup. Flow 160 gpm .
480._VAC Distribution . NORM. Makeup Tank-Level / Pressure. 100 -in / : 30 - psig . 250 VAC/125:VAC Dist. NORM 13-ft /L599 psig. . Inst. ? AC ._ NORM-
' Core Flood Tank _#1 Level / Press
' Core Flood Tank #2. Level / Press 13 ft / 599 psig . Generator Wattneter.(Gross); j0 Mw HP Injection 1Line Flow (1-1) 234./(1-2);234' - -
- (2-1) 0 /(2-2) 0 _ OTHER-
-(1/2) 0 /.0 gpm LP Injection Line Flow DH.R Hx Inlet Temp. (#1/#2)'70/70fTF. . Instrument & Service Air- 1110/ NORM Ctat. Spray Flow -(#1/#2) 0/0 gpm. Spent: Fuel Pool! Level / Tempi ;247ft/102 *F-
- CCW Surge. Tank 1 Level ~' (1/2)f51/52 Din m
- BWST Level' 42 ft CCW
- Hx Outlet Temp' ~(1/2) 95/95 *F
s ,
's ,
EMERGENCY PLAN DRILL w l i. i-AND EXERCISE PROGRAM ; SCENARIO:NO.. 90 EVAL : TIME: -1200 . T: 03:00 -( ;
. 'l
- l. .
l- : b DAVIS-BESSE NUCLEAR POWER STATION- i 1 + q 1 1 EMERGENCY. PREPAREDNESS EXERCISE EQUIPMENT. STATUS. 1 , 1,
- COMPONENT: : , . STATUS:
i J Reactor Coolant' Pumps #1-l..........-...................--OFF
#1-2............................; 'RUN ,
#1-3........... .........'......... RUNL - ,
1
~ # 1 - 4 . . . . . . . . . . . ' . . . . . . . . . . . . . ' . n. . . - RU N '
I) RUNJ Ma ke up Pump s _ # 1. . . .~ . : . . . . . . . . . = . :. . . . . . . . . . . - . . . . . . . . . . . . . . . . .
-. O O S :
#2.......:.................................. :
I 6 HPI Pumps #1...................................-'..;... . .RUN-- j
'#2...;..;...'...'............~.....:............. :OOS- i Decay Heat' Pumps #1.-_...............'.................... 1 'RUN.
#2....;.........'......-..'.............. LOOS! [
q f
^
Decay . Heat Removal / Coolers # U . . . '. . . . . '. . . . . . . . . '. . . . . . 7 .RUNJ ll
#2.......'............. -
. . . AVAIL ^ 3j Containment Spray _ Pumps - # 1. . . . . . .. . . .' . . . . . . .'. . . . . . . . .'. . OFF i
~ '
#2......'....................... 0FFJ Containment H2 Dilution Blowers:#1................'.... 'OFF j;
#2...-..'..............
;OFF: .
Containment Recirculation Fans.fl...,...=..-.....-........ RUN .
# 2 . . . . . . . . . . . . . . . . . . . . . :. 1RUN?
,i Containment Air' Cooler Units #1.......:.......'......... -RUN-SLOW ;
l- #2.'....................... 'RUN-SLOW; l
. # 3 s . . . . = . . ' . . 1. . . . . . . . . . . ....c OFF j
i
^
i RUN ' Component Cooling Water-Pumps #1....-.................. .
#2....................... OOS
#3......................... STBY ,
p Service Water Pumps #1..................................~RUN . ! #2.................................. OOS -)
#3................................. LSTBY- j Backup...............-................. 'OFF ;
Auxiliary Feedwater Pumps #1...........................- RUN
~
#2............................. RUN .
Motor Driven Feedpump ................................ OFF , a 1 p -- 4 s =- ,"m, s- ~ w w;w's
~
O O O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME: 03/15 CUE CARD NO. T: 12:15
' FEACTOR COOLANT CONTAINMENT
. RCS Pressure 779 psig Ctat. Pressure - 15 psia-T Avg. ~520 *F Ctat. Temperature 105J*FJ
- i. Th/Tc 454/449 *F- Radiation ~(See Radiation'-Monitor ~ Data Sheet)'~
Boron Concentration- 1489. ppm- Sump! Level ^(Normal /WR) .. 538/538-ft RCS Subcool. Marg. 68 F Przr. Temp. 521 *F STEAM GENERATORS Przr.-Level 123 in S/Gi1L Level / Press. . . 270 in. ./ 398.psig' RCS Flow (Loop 1/2) . 34/34:Mpph' . S/G 2 Level / Press. - 124 ini /J812 psig . (1/2) . 482; 'F / 502 PORV AUTO -Block Valve CIDSED iS/G Shell; Temp.J F.- Spray Valve AUTO. Block Valve ~ CLOSED Turbine Hdr. Pressure ~: 600 psig;
- Letdown Flow- .O gpm MSIV
- Position .; ~ CLOSED RCP Seal Flows- 36:gpm (TOTAL) 1-1 9 gpm 2-1 9 gpm FEED & CONDENSATE a1 1-2 .9 gpm .2-2 9 gpm Main.FW: Flows (loop;1/2)- O/0;MpphT Quench Tank Level / Pressure 9 ft/ 25 psig. - Hotwell. Level / Pressure' .~ 4 .f t/ 3 0 ?in " Hg
f(1/2):
~
3 CST'Levelf i '
' ~ '
38.5 fi38.5 ft ~ , REACTOR CORE . Aux..FeedJFlow' . 0/581jgpa Source Range Level'(NI-1/NI-2) 5/5. cps , MotorcDriven Feed Pump Press..'Ofpsig Intermediate' Range (NI-3/NI-4) -12/-12 amps Power range (NI-5/NI-6)- 0/Of% ' , ELECTRICAL . (NI-7/NI-8) - 0/ O . .% . ; BUS A/B NORM / NORM Core Thermocouple -(AVG) 454 *F- . BUS.C1/C2- .. _; NORM / NORM ~ BUS . D1/D2 OFF/ NORM MAKE-UP AND ECCS- . . EDG'1/2- . RUN/RUN Makeup Flow <160 gpm: . .
; 480 VAC Distribution' : NORM Makeup Tank Level / Pressure 1100 fin-/J30 psig - 250'VAC/125 VAC Dist. NORMI Core? Flood Tank #1-Level / Press -13.'fti/J5991psig7 Inst. ACJ . . ,
NORM' Core' Flood Tank-#2 Level / Press 13 ft f i S99'psig. ' Generator Wattneterz (Gross) O Mw:- HP Injection Line Flow .(1-1)' 84 ' / (1-2)1106 (2-1) 0 /(2-2).-0 . OTHER LPtInjection Line~ Flow (1/2)f0 / 0..gpm. DHR.Hx Inlet' Temp. (#1/#2) 7 0/70.r
- F. - Instrumentf&: Service' Air 1110/ NORM:
- Ctat.. Spray Flow l( #1/ #2) 0/0 gpm - Spent Fuel PoolT-Level / Temp. 241ft/102 F CCW Surge; Tank Level ' '(1/2) 51/52'~in ;
~
( 1/2)L95/95
~
. -BWST Level '42;ft. CCW Hx Outlet Temp' FL -!
- re d"
.w ,,w7 spe._.g," g,_,-w-+w ,.1.wigy" 9'e, /+ 9 ,m - -w.ww.vbg p-p g'# '5 g . g e- ,-1%'*T ' . yg 9 9f'*-9#."@iWq W" g g ' * ' * -- g** 'fJ*# w- e ?_ ra Y ' ~ ' ' * ' _-_hm__.._#".__m_.m.-.3-m ------ _ --- s w sl2'E.d
. _ ~ - _ _ _ _ _ _ _ - - - _ - - _ - . . _ - _ - _ _ _ -
t 1- .: EMERGENCY PLAN DRILL -1 i AND EXERCISE PROGRAM i i SCENARIO . NO. -- ~90-EVAL TIME: ~ 1215 . . T: 03:15' L , a m . DAVIS-BESSE NUCLEAR' POWER STATION .! 4 EMERGENCY PREPAREDNESS ~ EXERCISE EQUIPMENT STATUS j i COMPONENT: STATUS: Reactor Coolant i Pumps ? # 1-1. . . =. . . . . . . . . . . . . . .' . . . .. . . .. . . . OFF;
# 1 - 2 . '. . . . . ~. . . . . . . - .1. . . . . . . . . . . . . . " RU N : i
#1-3.,.............'................. RUN! l
# 1 - 4 ~. . . . . . . . . . . . . . . . . . . . . . . . ' .- '. . . L' 1 RUN L ] :
Make up i Pump s ; # 1. . . :. . . . . . . . . . .. . . . . . . '. . . !. . . . . . . . . . . . :. .. ~. . . - RUN- q f $ 2 . . . . . . .'. . . . . . . . . .,-. . . . . . . . . . . .:. . . . . . . . .> OOS.
- HPI Pumps #1'............................................-RUNL ,
# 2 . . . . '. . . . . . . . .. . . . . . . . . : . . . . . ; . '. . . . . . . . . . . - . . . . . : O O S ;
y RUN',
- De c ay - He a t Pump s ; f l . . . . . .. . . . . . . . . ' . , . . . . . . : . . . . . .. . . . . . ..' . . . ,
3
#2..............................:......- LOOSL .,
j
- r i' Decay Heat. Removal Coolers #1.'...........'...'......'....: RUNi. '
# 2 . = . . . . . . . . . . . .: . . . :. . . . . . . - . . . ; , AVAI L '
N j 1 , .
. Conta inment ~ Spray ' Pumps " # 1. . . . . . . . -. . . . . . . . .^. . . . . . . . . . . . , OFF
# 2 . - . . . . . . . . . . . . . '. . . . . . . . . . . . . ' . y . O F F
, q
- Containment H2 Dilution' Blowers #1.................'4 . . IOFF o#2.................'... . J OFF6 1i
? Containment Recirculation Fans #1.....................'- 'RUNL. ei f
#2.................J...y LRUN)' i Containment Air Cooler Units #1........'........-...v....;. RUN-SLOW.
#2.........'....,,,......... . RUN-SLOWE
#3...........'........... :OFF~ .
t Component Cooling. Water Pumps #1.-.....................-.- . RUN
~#2..........'.-......'~...... OOS
#3......-................ 'STBY -}
Service Water Pumps #1........................'.'.~....... RUN- ,
#2.................................= OOS lL #3................................~.. STBY, ,
l Backup................'.'................ OFF 1 ? L . . C ( Auxiliary Feedwater Pumps #1........................... RUN k
#2.....-..................... RUN n L
Motor Driven-Feedpump ........... . . . . . . . . . . . . . . . . . . OFF t
$ i L*
$ I l .E e ,,a < w- --
e v. rs s g r. , wes e.e-- - ~ - - e e
..7..--
w _. , ..
; O~
~
O O . DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET- , 1990 EVAL -TIME: 03/30 SCENARIO NO. T: '12:30-CUE CARD NO. CONTAINMENT
. REACTOR COOLANT ~15' psia RCS Pressure 736 psig- Ctat.. Pressure' 520 *F- Ctat. Temperature- >105 *F T Avg.
Th/Tc 459/456 *F Radiation (See Radiation Monitor Data. Sheet) Boron Concentration 1539 ppm Sump Levelo--(Normal /WR).- 538/538-ft RCS Subcool. Marg. 57 *F Przr. Temp. 515 *F STEAM GENERATORS 97 in S/G 1 Ievel/ Press. . -270 in / 432'psig, Przr. Level .124-inD/'783 psig-RCS Flow (Loop 1/2) 37/37 Mpph S/G 2' Level / Press..(1/2) 475 -F /..495 *F-
~
PORV AUTO Block-Valve CIDSED S/G Shell Temp.- Turbine:Hdr. Pressure ;600.psig Spray Valve AUTO . Block Valve CIDSED Letdown Flow 29.gpm ~ MSIV Position CLOSED' RCP Seal Flows 36 gpm (TOTAL) ' ~ 1-1 9 gpm 2-1 9 gpm FEED &-CONDENSATE- , 1-2 9 gpm- 2-2 9 gpm -Main FW Flow-(loop 1/2) .0/0 Mpph 9 ft/ 25 psig LHotwell Level / Pressure. 4 ft/ 30'in Hg Quench Tank Level / Pressure CST Level' (1/2)l -38 /.38 ft'
=
Aux. Feed Flow 0/200 gpa REACTOR CORE . Source Range Level (NI-1/NI-2) 5/5 cps Motor ~DriveniFeed Pump Press. :O psig-
~
Intermediate Rangen(NI-3/NI-4) -12/-12 amps-Power range (NI-5/NI-6) ~ 0/0 L % . FLECTPICAL (NI-7/NI-8) O/0 %J BUS A/B. NORM / NORM Core Thermocouple (AVG)- 459 *F BUS C1/C2 - . NORM / NORM. - BUS D1/D2 __OFF/ NORM-MAKE-UP AND ECCS EDG 1/2 RUN/RUN. Makeup Flow 160 gpm . 480'VAC Distribution' NORM--
'100 inif 30 psig 250 VAC/125 VAC.Dist. NORM-Makeup Tank Level / Pressure l NORM Core Flood Tank #1-Level / Press 13.ft / 599.psig Inst. AC: -
Core Flood Tank #2 Level / Press 13 ft -/ 599 psig ~ Generator Wattneter.(Gross).._ 0 Mw
.HP. Injection Line Flow- (1-1) 0 /(1-2.);109-~
. (2-1) . 0 / (2-2) . O. OTHER -
LP Injection Line Flow (1/2) 0 / 0 gpm . DHRJHxSInlet-~ Temp. Instrument &;ServicefAir- L110/ NORM:
- ( # 1/ # 2 ) -. 70/70 J
- F.
.Ctat.-Spray Flow . (#1/#2) O/O'gpm- SpentLIbeliPool~ Level / Temp- 24'.ft/102 *F CCW Surge Tank- Leveli : (1/2 ) -. 51/52 / in L BWST Level 42 ft CCW Ex Outlet 1, Temp (1/2)_95/95 *F
.m.
4
MP.NCY ' PIAN ' DRIII -
. , RND kIRRCISE' PROGRAM
-G SCENARIO NO. 90 EVAL' sTIME:- 1230
- T: 03:30 DAVIS-BESSE NUCLEAR > POWER = STATION.- -
EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT. STATUS COMPONENT! .
' STATUS:
Reactor Coolant - Pumps # 1-1. . '.:. . . . . . . '. . . . . . . . . . . . . . . .. .'. OFF.
-#1-2;............-...............'.-..-. OFF.
-#1-3......'.................'...... OFF
, #1-4'............'................
RUN.
* - Ma ke u p ~ Pump s 7 # 1. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .',. . . . . ; RUN'
'#2....^..............'.............=.-........i OOS' H P I Pump s # 1'. . . . . . . . . . . . . - . . . .' . . . . . . . . . . .' . . . 1. .' . ' . '. . . . . . . - RUN
#2......................... . . . . ...-......... 1 OOS .
De c a y . He at ' Pump s # 1. . . . . . . . . . . =. ~. -. . . . . . - . . . . . .' . . . . . . . . . . . - RUNJ
,#2...........................-........ OOS? .
=3:
-Decay Heat Removal-. Coolers #1...........~........'...'.. RUN:
; # 2 . . . ' . . . . - . . . . .' . . . . - . . . . . . . . . . , - AVA I L a
. p.
Containment Spray Pumps:#1....-........................ .0FFl 1
#2..............'....-...'.......- OFF -
Containment H2 Dilution Blowers #1'................
. . ... OFF -
, #2..............'.==.'...:. OFF -
Containment Recirculation Fans - # 1'. . . -. . . . . . . . :. . . .L. . . .' . . RUN
, -#2................,..... RUNL w '
Containment Air Cooler Units' #1. . . . . . . . . . . . . .. . . . . . .:. .-..- RUN-SLOW >
#2........................'.. RUN-SLOW-
.i:
# 3 . . . . . . . . . . . . ' . . . . . i . . - . .. . . L O FF Component Cooling Water Pumps!#1........'............... RUN
#2.................'..... OOS <
#3.......'.....'......i... STBY Service Water Pumps #1..................'.............. RUN
#2.................................. OOS
-#3................................ STBY:
. Backup........ 1.......................:.. OFFL Auxiliary Feedwater Pumps #1'.........................
. RUN,
#2............................ RUN q
' Motor Driven-Feedpump ................................ OFF l
i 4
&9
.h
.i 5
4 r i
< J 1h
o O o..-
~
DAVIS-BESSE NUCLEAR POWER STATION 4 "' PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME: 03/45 . CUE CARD HO. . T: 12:45 - o 1 y REACTOR COOLANT CONTAINMENT - 688 psig RCS Pressure Ctat.-Pressure. 15: psia. T Avg. -520 *F Ctat. _Temperaturr.- 105 *F- ~ Th/Tc 437/435 *F Radiation (See Radiation Monitor. Data Sheet)" d
~ Boron Concentration 1637 ppa . Sump: Level-(Normal /WR) '538/538-fti 71 *F-
~
RCS Subcool. Marg. . Przr. Temp. 508 *F' STEAM GENERATORS ~ Przr. Level 106 in S/G 1. Level / Press. '270 in'~/:346'psig. RCS Flow (Loop 1/2) ~37/37 Mpph S/G 2. Level / Press. .1124'in ./ 737 psig-PORV' AUTO : Block Valve CIDSED S/G Shell' Temp. .(1/2)~461 F / - 487.
- F-Spray Valve AUTO Block Valve- CLOSED Turbine Hdr. Pressure. 600.psig -l Letdown Flow 28.gpm MSIV Position :CIDSED RCP Seal Flows 36 gpn (TOTAL) .
. 1-1: 9 gpm 2-1 9 gpm' . FEED & CONDENSATE ~
- 'l-2 - 9 : gpm 2-2 9 gpm Main FWl Flow ~(loop 1/2)-- 0/0'Mpph Quench Tank Level / Pressure 9 ft/J25 psig. Hotwell Level / Pressure. 4 ft/.30)in'Hg CST LevelT .(1/2) :37.6-/.~37.6 ft' .:
REACTOR CORE ' Aux. FeedfFlow - 0/165 gpm. Source Range-Level (NI-1/NI-2) 5/5 cps. Motor:DrivenTFeed Pump Press.,'O psig. Intermediate hange :(NI-3/NI-4) -12/-12. asps :1
"- Power range a (NI-5/NI--6) 0/0 % ELECTRICAL 'i
, (NI-7/NI-8) O/0 % BUS:A/B NORM / NORM i Core Thermocouple (AVG). .437...*F. . BUS C1/C2i . NORM / NORM BUS 1D1/D2 OFF/ NORM g MAKE-UP AND ECCS .EDG'1/2- . . .RUN/RUN M d Makeup Flow 160 gpm 480 VAC Distributioni NORM Makeup Tank Level / Pressure. '100 in /.30.psig. - 250i VAC/125-.VAC lDist. - NORM Core Flood Tank #1 Level / Press ~ 131 ft / 599 psig- - : Inst. AC~ NORM' Core Flood Tank #2 Level / Press' 13-_ft /.-599 psig Generator.:.Wattneterj (Gross)I :0 Mw.
~
HP Injection Line Flow - (1-1)-0 /(1-2) 112 (2-1) 0:/(2-2): 0: OTHER" .- LP Injection Line Flow (1/2) 0--/-0 gpm' _
.: Instrument &' Service'-Air ~
~
DHR Hx Inlet' Temp. (#1/$2) 70/70_'*F- 110/ NORM
;Ctut. Spray' Flow 1(#1/#2) 0/0 gpm Spent: Fuel Pool: Level / Temp- L24 ft/102 *F; '~
CCWLSurge Tank Level: ~ -(1/2) 51/52 in BWST.Lovel 42 ft CCW Hx Outlet Temp 4
'(1/2) 95/95 *F.
{ :\ _ _ . _ _ _ _ _.. . .. ~ .m m -
- m. m._ , __ __. _ _ . _ _ _ . .
1 EMERGENCY PLAN DRILL AND EXERCISE PROGRAM 'i i
- SCENARIO NO.- 90? EVAL 1 - TIME: 1245- -
..I =
T: .03:45' , DAVIS-BESSE NUCLEAR 1 POWER' STATION i!
. EMERGENCY: PREPAREDNESS EXERCISE: EQUIPMENT" STATUS- d T
COMPONENT:. 4
~ STATUS: .{
Reactor-Coolant' Pumps #1-1.........................-... OFF. i
.#1-2...........................'. , OFF, -- l
#1-3........'............-.......... OFF [i
#1-4...'..-......................... 1RUN: l Makeup Pumps;#1........................................ RUN:
- 2.........................:.....'........... .
OOSL .4 H P I Pump s ; # 1. . - . . . . . . . . . ' . . . . . . . . '. '. . . . . . . . . . . . . . . . . . . . . . . . . RUN- :!
#2'.......................................... OOS-
- 4 Decay' Heat' Pumps #1...........,........................ .
RUN1 , i f#2................... _...'........-..;....' OOS: 3 Decay' Heat Removal Coolers #1...'.....'.3....1.....:..c... RUN -. !
- 2........'...-.......;....... ' AVAIL 1 Containment Spray Pumps #1............:.....'......... .. OFF 1
-#2............................. .
OFF, _ Containment H2 Dilution. Blowers #1. ................... .OFF . I
~#2..............i..... OFF q Containment" Recirculation Fans
#1....................!. RUN.
# 2 . _ , . . .L . . _ . . . . . . . . . 1. . . . ' . . 'RUN , ,
Containment. Air Cooler Units #1 ........'............... RUN-SLOW' :
# 2 . . . . . . , . . . . . . . . . . . . . . . . . . : RUN -S LOW (
h
#3..................'......- OFF. .;
l' l
. Component Cooling Water Pumps #1............i.......,..: PUN 1 l OOS;
#2..............-........ '
#3................-.....-. STBY i
Service Water Pumps #1.................-................ .
-RUN :
12.................................. OOS j u
#3................-................. STBY .
B a c ku p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ' . . . . - . OFF Auxiliary Feedwater Pumps #1.......................... RUN
#2'.......................... . RUN
' Motor Driven Feedpump ................................ OFF .
?
h u; I t y w t , e . e r,.+, e, ,N., v , e - - - - --e - e
DAVIS-BESSE NUCLEAR' POWER STATION . PLANT PARAMETER SHEET y
~
, ' SCENARIO NO. 1990 EVI,L TIME: 04/00 ; CUE CARD NO. _.T: 13:00 l
~ REACTOR COOLMIT CONTAINMENT RCS Pressure ' 671 psig Ctat. Pressure 15 psia-T Avg. 520 *F Ctat. Temperature 105 *F:
Th/Tc 432/429 *F Radiation.(See' Radiation Monitor Data Sheet) Boron-Concentration' 1658 ppm ' Sump Level ~ (Normal /WR) ' 538/538 Lft-~ ~ 74 *F
~
RCS Subcool. Marg. Prtr. Temp. 50G *F SIE&M_CtEHEBAT9BE . 1 Przr. Level 105 in . S/G 1; Level / Press. T270:in .
. /.325'psig-
--g RCS Flow (Loop 1/2) . 37/37 Mpph S/GE2~ Level / Press. ' 124 'in ~ / . 721 psig :
PORV AUTO Block Valve CLOSED S/G Shell Temp. -(1/2)L457 'F / 485 *F . a Spray Valve AUTO- Block Valve CLOSED Turbine Hdr.' Pressure 600 psig-Letdovm Flow 28 gpm MSIV Position L. CLOSED - RCP Soe.1 Flows 36 gpm (TOTAL) F 1-1 9 gpm 2-1 9 gpm- . FEED & CONDENSATE i
' Main f FN Flow : (loop 1/2)) <0/0 Mpph
~
1-2 9 gpm 2-2 . 9 gpm Quench Tank Level / Pressure 9 ft/ 25 psig Hotwell - Level / Pressure ..- 4.ft/ 30 in Hg CST. Level- . (1/2) 37.2 '/; 37.2 '. ft '
' REACTOR-CORE Aux.-Feed: Flow [..~ 0/180'gpm-Source Range Level (NI-1/NI-2) ~5 /5 cps' MotoriDriven Feed-Pump Press. -O psig Intermediate Range'(NI-3/NI-4) -12/-12. amps (NI-5/NI-6)-
Power range 0/0 %. ELECTRICAL (NI-7/NI-8)- -0/0 % BUS;A/B . NORM / NORM Core Thermocouple (AVG) 432~*F - BUS C1/C2, iNORM/ NORM-BUS D1/D21 fOFF/ NORM-MAKE-UP AND ECCS EDG71/2.. . RUN/RUN: Makeup" Flow . 160.gpm .. :480'VAC~ Distribution. -NORM Makeup Tank; Level / Pressure- 1 100."in / 30 psig! 250 VAC/1251VAC Dist.. .NORMc Core Flood Tank'#1cLevel/ Press::l:13 ft'/-599 psig - Insti AC- -NORM-Core Flood' Tank-'#2 Level / Press '13 f t ' / 599 . psig [ Generator _Wattneter?(Gross)- l0.Mw HP Injection ~Line' Flow (1-1) -. Of / (l-2)-- 112
- (2-1) (O', / (2-2) ~.0
~
i . OTHER' w LP_ Injection 1Line Flow (1/2 ) 57, / ' O.-gpmi- -
. ._f
- DHR Hx' Inlet-Temp. '(#1/#2)f70/70s*F Instrument'&' Service Air
- 110/ NORM ~
4 Ctat. Spray Flow (#1/#2)'0/0;gpm - Spent'FueliPool~ Level / Temp' .24'ft/102.*F: CCW:SurgefTanklLevel- ~ (1/2).51/52 in - - BWST Level 42 ft CCW.HX.' Outlet Temp L(1/2) 95/9.5 :
- F - 'i
( 2 .v. .
#g .g .m.h.r . . -g7 -
+-,c yr + ,
, , ., h.,'d. . . ~ . , - , h h--. , , ,-,.- w - ,,d. - ..-,%~ _ _ . . . . . . . .
EMERGENCY PLAN DRILL AND EXERCISE PROGRAM i1 4 SCENARIO.NO. 90 EVAL ~ = TIME: ~ 1300 .= T: 04:00 i DAVIS-BESSE NUCLEAR 1 POWER' STATION.~. . e EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT.-STATUS ~, j I l' , .
^*
l! COMPONENT: . . STATUS: L Reacto r . Coolant' Pumps # 1-1. . .' . . . . . . . . . . . .. . . . ' . . .. . . . . . . . -. ' - OFF l
~#1-2....~.......'.'............-....: EOFFi .
q
#1-3'.:...'.'..........'.....'......... - OFF .l
.C .#1-4...........i.......J..1....-......- RUN-. ,
1 ! <.I
~'
fMakeup J Pumps #1 ...........i.............,.............. ' RUNj ' ^
;#2;:..-.~...;.'...'...........,...'.'.......'..~...:iOOSL 6 3A, ,
W; H P I Pump s ! # 1 . . . . . . . _ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . ) . ' . . . . . - RUN
/#2.:......................................'...'.. . .- OOS' m:
(;>
- o. , .
De ca y _ H e a t ; Pump s # 1. . . . . .' . . . . . . :. : . ' . . ; . . . . .' . . . , . . . . :. . . . . . ; .RUN . i#2....-.'......~:.........'........;'.......: , OOS. < i
' Decay, Heat: Removal Coolers-#1.........................'.( -RUN~~ .f n #2...........-...~...i..........1 AVAIL?
9 6 , Containment' Spray Pumps # 1. C. . . . . . . . . . . . . . . :.- . ... . . .". .:. . l OFF ,
#2...........................'.... OFF .
~
Containment H2 Dilution l Blowers #1.................... -OFF '
#2.,......-....:..'.'..=.'.'- OFF,-
N. . 1 Containment -. Recirculation Fans ' #1. . . . . ... . . . .:. . . . . . . . .'. < RUN g
#2....-.................. . RUN- d
' ~
n Containment Air Cooler Units #1..............".......... RUN-SLOW' f;
#2....:.....;.............. RUN-SLOW {
#3...................-..... OFF: ':
cJ Component Cooling Water Pumps #1...........-............- RUN j
#2....................:....- OOSo j
# 3 . . . . . . . :. . . . . . . . . . . .: . . . . - STB Y 1 i
Service Water Pumps #1........................:........ RUN j
.#2.....................;............ OOS, d
#3.............-..................-.. STBY ]
Ba c ku p l. . . . . . . . . . . . . . . -. . . . . . . . . . . . . . . . . . . OFF ; Auxiliary:Feedwater Pumps #1..........................- RUN -l
#2.....-..............-......... .
'RUN .I
~ Motor Driven Feedpump ................................. OFF 1 OJ l
1
, i 1T % " > ~ v w -~~e w w w w w y - ,
4 DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL TIME: 04/15-CUE CARD NO. T: -13:15 REACTOR COOLANT CONTAINMENT l RCS Pressure 671 psig Ctat. Pressure. 15 psia 3 T Avg. 520 *F Ctat. Temperature '105 *F- - Th/Tc 432/429 *F Radiat' ion (See Radiation Monitor Data Sheet)' Boron Concentration 1658 ppm Sump Level 1(Normal /WR) -538/538 ft - RCS Subcool. Marg. 74
- F Przr... Temp. 506 *F STEAM GENERATORS _ .
Przr. Level 105 in S/G:1 Level / Press.- 270 in'. f:325 psig RCS Flow (Loop 1/2) 37/37 Mpph S/G 2 Level / Press.- 1124.in / 721 psig. PORV - AUTO Block Valve' 'CIDSED; S/G :Shell Temp.' (1/2) 457 ~F /-485 *F Spray Valve AUTO Block Valve CLOSED Turbine'Hdr.: Pressure; 600 psig
-Letdown Flow 28 gpm MSIV Position CIDGED RCP Seal Flows 36 gpm (TOTAL) .
1-1 9 gpm 2-1 9 gpm. FEED &-CONDENSATE 1-2' 9.gpm 2-2 9.:gpm ? Main FWfFlow (loop 1/2) . 0/0-MpphL Quench Tank Level / Pressure 9-ft/ 25 psig~ Hotwell Level / Pressure 4 ft/ 30iin Hg c CSTiLevel. - (1/2)~ 36.9-/ 36.9_ft' REACTOR CORE . .
~
1 Aux.-Feed Flow- 0/180Egpm Source Range Level.(NI-1/NI-2) 5/5 cps Motor Driven Feed Pump-Press... 0 psig .. Intermediate Range-(NI-3/NI-4).-12/-12 asps ~ ~~ Power range (NI-5/NI-6) 0/0 %. ELECTRICAL (NI-7/NI-8)- 0/0 % . BUS A/B ~ NORM / NORM-Core Thermocouple ~ (AVG) 432 ?F:- fBUSiC1/C2. ~ NORM / NORM:
~ BUS.D1/D2 OFF/ NORM-4 MAKE-UP AND ECCS :EDG 1/2f ..
RUN/RUN' I Makeup Flow 160 gpm ^ J480.VACLDistribution' NORM 1100-in fr30;psig~_ l Makeup Tank Level / Pressure' ,250 VAC/125-VAC'Dist. . 1 NORM L Core Flood Tank-#1 Level / Press 13 ft /:599~psig: Inst. AC' ..
; NORM-
- Core Flood: Tank #2 Level / Press. 13"ft / 599 psig ; Generator. Wattmeter 1(Gross ); .O Mw i - HP Injection Line Flow :
(1-1)- O / (1-2) 112 1 (2-1) 0 / (2-2) ' - OTHER
=
LP Injection Line Flo_w (1/2) 7 / O gpm- . DHR Hx Inlet Temp. . (#1/#2)'70/70'*F. Instrument.&1 Service Air- L 110/ NORM -- - Ctat. - Spray. Flow (#1/#2) 0/0 gpm: z Spent FueluPool-Level / Temp. 24 f t/102
- F.
CCW Surge. Tank' Level. (1/2) 51/52'ini BWST' Level 42 ft CCW HxiOutlet(Temp f (1/2) 7 95/95 -
- F-4 l
eN ,)=.., .,+~..g
. m -
, g..-% -,. ~ .W,- ,n,.. # <g-- ~ - h ., . - , -w- e - .s p gw .. ..w. g.,,- #.#-#.m, ..yw.,_2u -2u,. -a a
1 1 1 EMERGENCY PLAN DRILL AND EXERCISE PROGRAM , .
. SCENARIO NO. 90 EVAL TIME:- 1315 T: 04:15 q
~
LDAVIS-BESSE NUCLEAR POWER-STATION EMERGENCY PREPAREDNESS. EXERCISE' EQUIPMENT STATUS .l 4 COMPONENT:. STATUS: L Reactor Coolant' Pumps #1-1.... . i................-...... OFF
#1-2......................;.....- OFF ;
#1-3............................. OFF~ i
#1-4...-...........i...-............ RUN !
J Makeup Pumps #1.................................-....... :RUN
~
- 2......................................'. ?OOS? -1 HPI Pumps #1....................................-....... :RUN OOS- 1
#2............................~..r.'...........
' ~ J De c a y . He a t Pump s # 1 . . . . . '. . . . . . . . . . . . . . . . . . . .' . . :.1. . . . . . . ; ;RUN. j .
#2....................'......'.......... .
-OOS) f 1 Decay Heat Removal Coolers'fl.....................".;..~. <RUN. , j
-#2...............=-....'.'.r..., .
' AVAIL 1 Containment Spray : Pumps : # 1. . . .' . . . . . .. . . . . . . . . . . . . .. . . .' . .
OFFJ ! OFFj l #2....................'...;...... . _. , Containment H2 Dilution Blowers #1............... ,..:..- _OFF _ ! #2s..................r..; OFF j i w Containment Recirculation Fans #1............... . ...'.. .RUN-
#2...-............:.-.....
RUN-Containment Air Cooler Units #1......'................. -RUN-SLOW .
#2.....................'.. ~RUN-SLOW
#3...............'..........- 'OFF i Component Cooling Water Pumps #1.......-................ RUN ,
#2..............'......... OOSi l l
l- #3................-...... STBY ! l,
- l. Service Water Pumps #1................................. .RUN -!
l #2................................. OOS t L'
#3.....-............................
Backup................................ STBY OFF ; Auxiliary Feedwater Pumps #1.......................... RUN
#2.......................... RUN ;
! Motor Driven-Feedpump .................................. OFF
^
l t
- l. .
f
~
O O O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL iTIME: ~ 04/3'O CUE CARD NO. -T: 13:30-REACTOR COOLANT CONTAINMENT RCS Pressure 671 psig Ctat. Pressure ,
.15 psia-T Avg. 520 *F Ctat.-Temperature-105 *F Th/Tc 432/429 *F Radiation-(See Radiation Monitor Data Sheet)'
Boron Concentration 1658 ppm Sump. Level.(Normal /WR) 538/538 ft' RCS Subcool. Marg. 74 *F Przr. Temp. 506 *F STEAM GENERATORS Przr. Level 105 in S/G 1 Level / Press. '270 in / 325 psig RCS Flow (Loop 1/2) 37/37 Mpph S/G 2 Isvel/ Press.' ~124 fin' /~721 psig PORV AUTO Block Valve CIDSED S/G Shell; Temp.. :(1/2) 457f F / 485 *F-Spray Valve AUTO Block' Valve CIDSED Turbine"Hdr. Pressure' 600'psig-Letdown Flow 28 gpm MSIV-Position-- 'CIDSED RCP Seal Flows 36 gpm .(TOTAL) 1-1 9 gpm 2-1 9~gpm- FEED &. CONDENSATE . 1-2 9 gpa 2-2 9_gpm -Main ~FW Flow (loop :1/2) 0/0 Mpph Quench Tank-Level / Pressure 9 ft/ 25 psig Hotwell:- Level / Pressure T4rft/ 30 in Hg;
.(1/2)
~
CST Level.- '
,36.6:/ 36.6.ft-REACTOR-CORE ' Aux. Feed Flow: L_ 0/180 gpm: '
Source Range Level (NI-1/NI-2) 5/5 cps Motor' Driven Feed' Pump' Press.: 0 psig'
. Intermediate' Range (NI-3/NI-4) -12/-12~ amps Power range (NI-5/NI-6)- 0/0:% ELECTRICAL ~
(NI-7/NI-8) O/0:% BUS A/B- . NORM / NORM Core Thermocouple (AVG)- '432 *F BUS C1/C2~ NORM / NORM-
-BUS D1/D2 ~
.OFF/ NORM. _ _ _
MAKE-UP AND ECCS , .
~EDG"1/2: .' RUN/RUN. -
- Makeup, Flow , ~160 gpm _
480'VAC Distribution NORM
-Makeup Tank Level / Pressure- .100 in_/'30;psig. 250)VAC/1251VAC Dist. NORM-Core Flood Tank #1 Level / Press _E13'ft /-599-psig Inst..AC- ' NORM Core Flood Tank-#2 Level / Press :13. ft / /599 psig Generator Wattmeter.(Gross)7 .OfMw1 (1-1)_0 /(1-2)-112 HP Injection Line Flow '
(2-1) 0 /(2-2)10: 1OTHER. ^ ~ '
- (1/2 ) _-7 . /_ O_: gpm .
-LP Injection'Line--Flow _
7 DHRLHx-Inlet 1 Temp. (#1/#2) 70/70f*FJ Instrument & Service-Air :110/ NORM: Ctat. Spray Flow (#1/#2) 0/0 gpm Mpent; Fuel Pool Level / Temp ^ .f24 ft/102 *F' CCW Surge: Tank' Level ~ .-(1/2): 51/52 in CCW Hx Outlet Tempi
~
- l. BWST Level -42 ft ((1/2) '. 95/95 ~
- F
~
~
.e
[ -- _ ._ _j.~... '
4 i
'1
,. , EMERGENCY PLAN DRILL <
-% AND EXERCISE PROGRAM
!\ '
SCENARIO NO.-
'90' EVAL - TIME: 1330- '
T:' 04:30 - l w _
.;1
- -DAVIS-BESSE' NUCLEAR POWER STATION- ,r
- EMERGENCY PREPAREDNESS' EXERCISE.. EQUIPMENT STATUS t a
- i COMPONENT: . STATUS:
j L Reactor Coolant Pumps #1-1..-..................-.....-... =OFF l 4
#1-2................'.........1.. .
. 0FF 2 s
~#1-3..............,............-.. OFF. l L #1-4..-.........................;... .
RUN' l t g L M'a k e up Pump s " # 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . . ;RUN.. l' ' OOS ~ ' j
#2....................................'....
HPI=Punps #1.'..a..................................i . 1 'RUNu I
#2..........................~.................. .
- - OOS ., j o ,
Decay Heat Pumps,#1......................-........._..... RUNc '
#2.....:.......'..........'...........'....: OOS Decay Heat . Removal ' Coolers # 1. .'. . . . . .. .-. . . . . . . . . . . . '. . . :. .- RUN!
#2..............-...'........;1AVAILD
- Containment Spray ' Pumps 1 # 1. . . . . . . . . . . . - . . . . . . .. . . . . . .. . .l. = OFF
#2.............'.=.............. OFF!
Containment'H2 Dilution Blowers.#1...................:.- OFF, 1
.#2.................'.t.. LOFF s Containment Recirculation Fans #1...................... .
^RUN: :i ll =#2..........:.............
RUN- 1 a Containment Air Cooler Units #1...-.....'.^.........-..... ,RUN-SLOW !'
# 2 . '. . . . . . . ' . . . . 7 . '. . : . . . . . . . RUN-SLOW:
#3........-.........~....-..'.. OFF .;
Component' Cooling Water Pumps-#1................ ....... RUN l
- # 2 . . . . . . . . . . . . = . . . . .J . . ; . . .
OOS j
#3...................... .
'STBY t
Service Water Pumps
#1..........................- LRUN :
#2..........................'....... -OOS- .;
#3................................. STBY j Ba c ku p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '.' . . OFF. i 1
g Auxiliary Feedwater Pumps #1............................ RUN'
#2.......................... 'RUN ,
Motor Driven Feedpump ................................. . OFF
?
-)
it I w [;f b T f y ,
.. y u e 4, -- - _ . . .- ._. _
~
O O O DAVIS-BESSE NUCLEAR POWER STATION PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL ~ TIME: 04/45 CUE CARD NO. T: 13:45' REACTOR COOLANT CONTAINMENT RCS Pressure 671 psig Ctat. Pressure 15 psia-T Avg. 520 *F Ctat. Temperature 105.*F Th/Tc 432/429 *F Radiation?-(See; Radiation Monitor Data Sheet) Boron Concentration 1658' ppa Sump Level ~ (Normal /WR): 538/538 ft i _.RCS Subcool. Marg. 74 *F Przr. Temp.- 506 *F STEAM GENERATORS Przr. Level 105 in S/G l' Level / Press. 270 in /~325 psig RCS Flow (Loop 1/2) 37/37 Mpph S/G 2. Level / Press.. . 124 in / 721 psig
-PORV AUTO Block Valve CLOSED 'S/G Shell Temp. (1/2):457 F'/_485 *F-Spray ~ Valve AUTO Turbine Hdr.-Pressure. 600 psig Block Valve CIDSED-Letdown Flow _ 28 gpm-^ MSIV Position. CLOSED--
RCP Seal Flows. 36 gpm (TOTAL) 1-1 '9 gpm 2-1 9-gpm FEED & COhDENSATE 1-2 9 gpm 2-2 -9 gpm Main FW Flow (loop.1/2) . O/O'Mpph Quench Tank Level / Pressure 9.ft/ 25 psig- .Hotwell' Level / Pressure. 4 ft/ 3G in Hg-4 CST Ievel'. . '(1/2) 36.3 / 36.3.ft REACTOR CORE- Aux. Feed' Flow . _ 0/180 gpm Source Range Level (NI-1/NI-2)~ 5/5_~ cps- Motor' Driven Feed Pump: Press. ' O psig-Intermediate Range (NI-3/NI-4) -12/-12' amps-Power range (NI-5/NI-6). 0/0 % ELECTRICAL (NI-7/NI-8) 0/0 ~.% : BUS A/B NORM / NORM-
~
Core' Thermocouple- (AVG) 432~*F .' BUS C1/C2 NORM / NORM. _ , BUS,D1/D2' OFF/ NORM MAKE-UP AND'ECCS EDG 1/2 .
- RUN/RUN'
. 480tVAC Distribution?
Makeup Flowz 160:gpm: NORM-Makeup: Tank-~ Level / Pressure f 1001in5/f30"psigI 250 VAC/125'VAC Dist. NORM
' Core Flood. Tank #1 Level /Pressi ~13~ ft /_599JpsigJ 4
Inst.:AC'_ - JNORM
-Core ' Flood ~ Tank . #2 Level / Press' ;-13 ft :/ 599 f psig Generator Wattneter;(Gross) O . Mw HP Injection.Line Flow- - (1-1) f 0 / (1-2) .112- --
-(2-1)10.~/(2-2) O OTHER
- LP Injection Line Flow (1/2)E.7./ 0;gpm _ .
DHR,HxfInlet Temp. (#1/#2)170/70 *F. . Instrument &' Service 1 Air- :110/ NORM SCtmt. Spray Flow .. ( # 1/ # 2 )i O/ 0 ~ gpm - SpentiFuel PoollLevel/Te.mp.- ,24 ft/102/*Ff _ . CCW -. Surge ~ Tank (Level? ' ' (1/2 ):. 51/52 L in BWST Level '42 ft CCW Hx; Outlet Temp! :(1/2).95/95 *F- -
. .u. # ~. . ___..~.u. -
_1. , . , a n ._ _ _ _ _ 2.2. _ _ ; ;. ,. . _ _ _ . _ _. _ d
i J i
'.7 ' ~
g EMERGENCY PLAN . qQLL l , M.- AND EXERCISE T,, ,Q :
-j
< SCENARIO NO. ,, 90 EVAL '
~ TIME: -1345 .I 1 T: -04:45- j DAVIS-BESSE NUCLEAR-POWER STATION' i
-EMERGENCY PREPAREDNESS: EXERCISE EQUIPMENT STATUS' .
?)
1
)
COMPONENT:- < STATUS: .l Reactor Coolant Pumps #1-1..l........'.................. OFF :
#1-2...:...:...-.................... OFF d
'#1-3....:.... 1....................- -OFF' '
#1-4.....................-........ RUN' i :1 Makeup Pumps-#1'.........................-..............
RUN' 3
#2.................,........................- . OOS: ;
l H PI Pump s ; # 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - . iRUN' 1
.'#2'.......................~..'...'........~......-OOS De ca y H e a t Pump s # 1. . . . . . . . . . . . . . . . . '. .' .' . . . !. . . . . . . . . . .. . . . . RUN
'~
s #2.............'................:.........- .OOS j i Decay Heat Removal Coolers #1~;.'.....-...,,.;............. RUN .
,#2............'........'......
. AVAIL M ,
l Containment Spray. Pumps.#1.........................'...'. . OFF 1
#2..........................'.. . 'OFF.l ..
Containment ' H2 Dilution i Blowers (#1. . . . '. . . . . . . .'. . . . . . .'. OFF'
#2.............-..'..... OFF- ,
y Containment Recirculation - Fans ^ # f. . . . . . . . . . . . . . . . . . . . - RUN ' , j RUN ; j #2.......................
.e Containment Air Cooler Units.#1........................ .RUN-SLOW- ?a
# 2 . . . . . . . . . . . . : . . :. :. . .' . . . . . . i . RUN - S LOW ' l l '#3..:.~.............>.... . ... OFF- '
Component Cooling WaterrPumps #1........-...'............ RUN
- 2...........-............ OOS
#3..................
7... 'STBY {
+
Service Water Pumps #1.....'........................... RUN' .
#2.....'...................,....... OOS
#3................................. STBY G
. Backup;................................. ,OFFj d
- r. .
- i Auxiliary Feedwater Pumps #1.......................... RUN-
#2......................-....... RUN. p, Motor Driven Feedpump .................................- 'OFF^ l
-f f
f p
,f
, s 1 1
y'). , y - - -e v .-- , , . . , ,
o a;
~ ,4 y 0 y DAVIS-BESSE NUCLEAR POWER STATION--
PLANT PARAMETER SHEET SCENARIO NO. 1990 EVAL . TIME: '05/00- .= CUE CARD NO. . T: - 14:00 REACTOR COOLANT CONTAINMENT RCS Pressure 671 psig Ctat.: Pressure 15' psia T Avg. 520 *F Ctatc Temperature . . . . 105 *F-Th/Tc . 432/429 *F Radiation _~(See Radiation Monitor Data Sheet)- Boron Concentration 1658 ppm Sump Leveli;(Normal /NR).l 538/538 ft~
~RCS Subcool. Marg. 74 *F i Przr. Temp. 506 *F STEAM GENERATORS "
Przr. Level 105 in S/G 1 Level / Press.. 270 in / 325 psig ; RCS Flow (Loop 1/2) 37/37'Mpph S/G 2 Invel/ Press. .. 124~in ./ 721 psig PORV. AUTO Block Valve CIDSED 'S/G Shell Temp. '(1/2) 457 F /,'485.*E q Turbine Hdr.l Pressure !600 psig
' Spray Valve AUTO Block Valve CIDSED Letdown Flow 28 gpm MSIV Position ~CIDSED t 1
RCP Seal Flows 36 gpm (TOTAL) . . l . 1-1 9 gpa 2-1 9 gpm ' FEED &' CONDENSATE ! L 1-2 9'gpm 2-2 9 gpm IMain FWl Flow:.(loop.1/2) ..O/0 Mpph. Quench Tank Level / Pressure 9 ft/ 25 psig ~Hotwell-Level / Pressure. ;4 ft/ 30"in Hg l (1/2):l l361/ 36'ftt , LCST Level.?. 3 (. REACTOR CORE Aux.~ Feed Flow l - 0/180 gpm( ' Source Range Level (NI-1/NI-2)- 5/5 cps ;MotorLDriven Feed Pump Press. 0 psig ! . 2 Intermediate Range (NI-3/NI-4) -12/-12 ampsj (NI-5/NI-6)
~
- ~~1 ~' '
Power range 0/0 %- : ELECTRICAL
- 0/0 %-
~
(NI-7/NI-8) : BUS:A/B7 NORM / NORM _- T Core Thsrmocouple (AVG) 432 *FL BUS;C1/C2 NORM / NORM
' BUS D1/D2 - , OFF/ NORM ~ -
l MAKE--UP L AND ECCS EDG)1/2'~ . _
.RUN/RUN' Makeup Flow ..
160 gpm- a -
-480;VAC Distribution' NORM -
i ~ Makeup Tank Level / Pressure. .100.in!/ 30.psig:- 250IVAC/125 VAC-Dist. NORM g _
- ~
' Core Flood Tank #1' Level / Press- 13 ftiff599';psig' ' Inst.tACi .
- NORM;1 -
Core Flood Tank #2: Level / Press 13 ft /~599(psig . Generator ~Wattneter (Gross)- OLMw i (1-1)70 /(1-2)'112{
~
l HP Injection'Line' Flow ! (2-1)'O /(2-2);0' -
?OTHER I
LP Injection'Line Flow- (1/2)-.7-/ O gpm-(#1/#2) 70/70 *FL
~
DHR Hx Inlet Temp. ' Instrument &' Service Air '110/ NORM .
- .Ctat.' Spray Flow- '(#1/#2) 0/0 gpm ' Spent Fuel PooljLevel/ Tempi '24 ft/102 *F. i -~ ' '
CCW Surge;. Tank Level? '(1/2) 51/52 Tin ^ - w
~BWST Level l42~ft -CCW"Hx. Outlet _ Temp' - (1/2);95/95?*F?-
n u .- =-,,.- . - . x . . , . ..wwa .. = w-
>x -=.
. . - . . . . .. - - . =
p s i
- E EMERGENCY PLAN DRILL
'AND EXERCISE PROGRAM SCENARIO NO.. 90-EVALi TIME: '1400- 2 J T: 05:00-DAVIS-BESSE-NUCLEAR-POWER. STATION
-EMERGENCY PREPAREDNESS: EXERCISE' EQUIPMENT STATUS COMPONENT: .- . ' STATUS:
Reactor Coolant Pumps #1-1..'...-..........-....z. . . - . . . . . . . - OFF
# 1 - 2 . .J. . . . . .'. . . . W . . . . .'. . . . ... . . . 3 OFF'
#1-3.-................^..-.......... OFF~
#1-4'..-...~......:.................. . RUN-
^
M a ke u p . Pump s _ # 1' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . = , . . . . RUN: i#2...............:..................-..'.;..,.. OOS* H PI ; Pump s - # 1 b . . ~ . . . . . . . . . . . . . . . . . . . . . . . . . . ;. - . . . . . . . . . . ' . . . . . , RUN: 42........'....'.............-.=..:................, 'OOS : Decay Heat Pumps:#1....................-...........'.....: :RUN:
'#2...............................-...... :OOS.
Decay Heat RemovalLCoolers #1~.a......................-....."RUN E
#2.-........................... : AVAILt Conta inment : Spray Pumps - # 1'. . . . . . . . . .. . . . . . . . . ,. . . . . . . . . . -.0FF ,
N
#2............................". OFFU Containment H2: Dilution-Blowers #1.....'..........., . ..;'.OFF
-#2..............:...;.... ;OFF.
Containment ~ Recirculation Fans #1.....;...............;-RUN! y
#2.............:.......'.: .
RUN' ' - 4 Containment-Air
- Cooler Units #1...'..........'.........-.. RUN-SLOW "
#2.......................'. RUN-SLOWL
#3.'.'....................:.
OFF Component Cooling Water Pumps #1'..................'...... RUN:
'#2.........-.............-. JOOS
#3..'.................. 1 STBY. . .
Service WateriPumps #1.....................;.........-. . RUN
#2...............................-.. OOS y~
#3................................ STBY- .
' Backup................................ -OFF . s Auxiliary Feedwater Pumps #1.......................... RUN
#2....................-...... RUN Motor Driven Feedpump .................................-OFF a.
O o o 1 DAVIS-BESSE NUCLEAR POWER STATION PLANT' PARAMETER SHEET
' SCENARIO NO. .
1990 EVAL .: TIME: 05/15
- CUE CARD NO. 'T: 14:15 REACTOR COOLANT CONTAINMENT RCS Pressure 671 psig Ctat.. Pressure ~ 15 psia si T Avg. 520 *F Ctat. Temperature- . . ' .10 5 '
- F - '!
Th/Tc 432/429 *F -Radiation =(See. Radiation Monitor Data Sheet) Boron Concentration -1658' ppa. Sump Level:-(Normal /WR): '538/538 ft' RCS Subcool. Marg. 74 *F Przr. Temp. 506 *F STEAM GENERATORS _ . Przr. Level 105-in S/G'1.7 Level / Press. . 270 in- /J325'psig RCS.FlowL(Loop 1/2) _'37/37 Mpph. . S/G'2--Level / Press . . 11241in. / 721'psig. PORV. AUTO Block Valve CIDSED 'S/G Shell Temp.; (1/2)14571'F /'485 *F Spray Valve AUTO . Block Valve CIDSED Turbine Hdr.. Pressure: 600'psig Letdown' Flow 28 gpm MSIV Positioni~ fCLOSED. RCP Seal Flows . _ 36 gpm (TOTAL) . .~ 4
- 1 9 gpm : 2 19 gpa . FEED & CONDENSATE _
1-2~ .9~gpa 2-2 '9 gpm- Main FW Flow E (loop ~.1/2); 0/0LMpph Quench Tank Level / Pressure -9 ft/J25 psig HotwellRLevel/Pressurei 24'ft/ 3O?in Hg-J(1/2)
~'
- CST Level, -
i 35. 8.: / _. 35. 8 = ft1 y
~
. REACTOR CORE- _
Aux.fFeed F1ow._ . . 8/180.gpa: ' . Source ~ Range Level. (NI-1/NI--2): :' ' l f5/5jcps: 1 Motor Driven' Feed. Pump: Press..-0 psig L c Intermediate Range -(NI-3/NI--4)... -12/-12 ' amps - ( . Power? range- (NI-5/NI--6) .0/0 %~ ELECTRICAL ~ - . l . : (NI-7/NI- 8 ) - 0/0 ~ % : 5BUSiA/B- ._. l NORM / NORM; i Core Thermocouple ( AVG) _. ~ 432;*F_ BUS C1/C2f ; NORM / NORM , BUS, D1/D2/
~
j- - _. OFF/ NORM.
- MAKE-UP AND ECCS .m 1 EDGil/2_ _ . . - '
1RUN/RUN! , 3 -- ~ ~
- -Makeup Flow . _
1 '160ogpm. ~ -480VVAC.Distributionc ' N O R M E Makeup Tank: Level / Pressure' .100yinc/ 30~psigc
, 250 VAC/125 VAC,Dist.- NORM' -
Core' Flood Tank #1' Level /Pressi313?ft f 5995psig- ' Inst. AC' NORM-Core Flood Tank-.;#2 Level / Press !13 ft1/L599 psig' -: Generator. Wattneter ;(Gross) : 0 Mw ; HP Injection Line Flow : ~ (1-1)10 - / (1-2) E112 . ' .. _
~
J l _ c(2-1):0 /(2-2)?O: OTHER
- LP Injection 1-Line Flow --(1/2) 7 /?O_gpm,
?
-Instrument L &'. Service: Air a
~
l '_DHRaHx Inlet 1 Temp.' (#1/#2).' 70/70 :
- FT. ~ 110/ NORM.
' Ctat. Spray ' Flow - ( #1/#2)c:: 0/0igpm Spent Fuel Pool Level / Temp ~24lft/102 "F 3
.CCW Surge Tank'Levelf ~~ (1/2)'51/52'in BWST Level 42 ft CCW Hx_..Outletc Tempi z(1/2).95/951*F-V a- -. - = w.- . . . . La . . . =. :a = _ . x x...l.. :--- - .L =.__ - a
t EMERGENCY PLAN DRILL AND EXERCISE PROGRAM ,
-SCENARIO NO. 90 EVAL TIME: 1415
- j T: 05:15-ll ':
,I DAVIS-BESSE NUCLEAR POWER STATION-- l l
EMERGENCY PREPAREDNESS EXERCISE EQUIPMENT. STATUS. + d i j COMPONENT: STATUS: Reactor Coolant Pumps #1-1............................ OFFa , i
#1-2.................'...........-.- OFF, ,
#1-3...-.............................. OFF '!
)
#1-4....................... . ....:- RUN-3<
Makeup Pumps #1.......................-............-...... 'RUN
#2.................................1..-.... :OOS? ,
H PI . Pump s # 1. . . . . ~ . . . . . . . - . . . . . . . . . . . . . . . . . . .~. . . . . . . . . . . . . _RUN ,
;l
'#2....=...................'....................s OOS-a
- De c a y H e at Pump s # 1. . . . . . . . . . . . . . . . . . . . . . . : . . . . . . . . . ',' . . . . L .RUN: '
#2.........................'.............. (OOSA c
V s Decay Heat Removal Coolers #1............................ .RUN , i i
# 2 . . . . . . . . - . . . . . . . . . . . . . . . . . . . , AVA I LS ,
Containment Spray Pumps #1..............'........:......:. LOFFJ
#2....................'.:..c...... 'OFF Containment H2 Dilution Blowersi#1........-..........;.- i OFFJ .1
'#2................'..... .
OFFl i
'O Containment Recirculation Fans
~
#1....'..... 1.. .........- RUN- t
- 2.....................- 'RUN i g -Containment Air Cooler Units #1........ . .........'...... RUN-SLOW' L #2.................'........ -RUN-SLOW .
#3........;.........-..... .
OFFJ Component Cooling Water Pumps #1.... '
- RUN:. .g
'#2.......J..:..........'..... 005 .
#3.................l.....
-STBY- .
Service Water' Pumps #1.................................
--RUN .
l
#2.........................'........ OOS ,
#3...................:............... STBY' L' Backup................................. OFFt
- Auxili'ary Feedwater Pumps #1..............-............ 'RUN -
#2...............:.............. RUN ;
l' Motor Driven Feedpump ..................1. . . . . .-. . . . .-. . OFF ] ) l 1 ft - , 5 l' l' '
., .-,n. 6<,.. ?
1-ELECTRICAL DISTRIBUTION 09o0 1
- EDG 1 480V 4160V 13.8KV. EDG 2 l4160Vl4.80V .
l
. l. .
. C00 t
>R8L CD rACT 1 ll ,c' A,
", IFWR AC rAmt IU xrwR
,A 0t Aux,xtuR
,AUL, SU xFMR.
,As xFWR 80 rAar .,A,-
R m CDC 2 FAm t COG 2 rRx i 1 = (OC 1 CDC 1 VMR $U xFWR aux xruR $U xrWR grum" ggyg gg gg, gg CDC 2 COC 2 4:9 RCWt CURRCN! CCl- 2 01 11 02' HI 0F1-2 CURRENT AIR RCvR PRC$$ LO FAULT ,0NM/TR8L DNm DNCR , . ONCR.. ONCR/ TROL FAUL, He pq[$$ to
. . . . . .. . - I C00 'I" " SV xrwe AUX xrun $U xrwR
)' CDC BUS Cl xrwR C00 2
~
CCW CCl-1 BUS 01 . COG 2 I rRC0vCNCY ggg y 01 11 , 02 ., gggy Orl-l CCW Flow LO TROL TR8L , IR8L IR88, TR8t, FRCOUCNCY
, , Flow LO l _ - . - . .... . . . . . .... . .
CDC 1 CDC 1 #wR 4 OAY TK $1RC TK CCl- 2 BUS C1 VOLTACC
- BUS A FAULT SUS 8 BUS On.
xruR
-2 CDC 2
$mC Tk CDC 2 O AY IK tw to LA LO 1R8L FAULT; VOLTACC
. TR8L - LW LO tw t,0
]
i
. . .... . . - . m. =
i... .. ... I - CDC i BUS Cl 80$ Cl BUS A OC PANCL 80$ 8., 8v$ 01 ' BUS fl j D DAY fx TROL OkR$ SkRS VOLIACC BKR5 ; BKRS , ,RSL SUS F7 EOO 2 DAY 14 Lvt ni , NINW NINW LO 7,gg
, , , , N THW l . , N INM ,_ LW Nt V
.... . .i . . . s- - . .
l
,g,79 3 BUS YAR OC BUS B Aff RW WS m O'
,gy yy, 0' vC(1ACC 1 WNi $YS DC BUS 2* VOLIACC
,yy yyg y,Vyv,
" i
.
- LO TRSL TROL
.1R8L -
LO 4 . "" I
- l
{ IA [8_ IC D E F G fil *
. l J_] @ I 2 -
i
~
s LETDOWN ..
#AKEUP _BA j LETOOWN PMPl PMP 2
} RAD HI LUBE OL ADO TK 1 LUBE OL -
PRESS LO PRESS LO ! x . i LET00WN OA PRESS Hi ADO N 2 o , LVL Hi TEMP - y !
. n. m. m. .
-l LETOOWN
} "I' TK TK HEA ED-ROOM PRESS Hi PRESS LO gp r
. LETOOWE' ""
MU MU BA . 4 OR MU FILT FLOW Hi FLOW Hi A00 TK I i AP Hi TRN 1 TRN 2 LVL ' e - f p38 7 ..N l BATCH BA 5 uu Am m 2 I i FLOW HI LVL , { , 6 ' 1 A B C D ' o
- 8 1- i t
.l [ t j
.1
- STM'G EN: lA zSFRCSS 7" m # 00
.m ~~ f =
WN STM- SC 1 SC.2.
-- 1
)
) LINE 2 LO PRESS LO PRESS .,
;2 l TRIP . -
L: R AO' H1 k ' TRIP 1 . l]
- SC 1 * /SC 2 " CH 1 "" ' . CH 2 "" ,
TO AFPT 2 TO AFPT 1 2 MN STM MN STM HI LW OR HI AP Hi-LW OR HIAP: ' PRESS LO i
' PRESS LU L' TRIP LL TRIP :J
. 6. .. *
, 50.1' , 5C 24 CH l " CH:2-j OPERATE 10PERATE to gg. OR
-NO RCPS LO LW' OR
.NO RCPS 1
- . LW ~ HI - LW HI :!
[ TRIPi ..L* L . TRP .- '! a i SC'l- 50 2 SC'1"" SC 2 " ' 4 . LW LO LW'LO LO PRESS AND Hi LVL LO PRESS AND HI LW ' I 8LK PERM BLK PERM _u .; j SC 1 OR 2 6 SC 1 " i SC 2 " ' L0 PRESS L0 PRESS ') h- . FW WV AND HI LW ANO Hl:LW
.hPlLO TRIP BLK '
. ~ TRIP SLK '
.. .. a ,.
6 SS ST "$ TEMP Hi lSTM OuT: TEMP Hi 'iR. . l ! i
;i A B C
_- D ' q 9] , CNDS-r ** l LP FW:
*=
p HP FW: . , ,
]
y CNOS DEAR 11
..$= g gp py
- s HP FW'~ II DEAR 2' , -
I . STRC TK HI LW HI LW l ,*. HW1-6 11TR 2-6 ' ' h LW TRIP ' TRIP ~ g, LyL g,ggy ;;
' TR@ # TRIP . '
~ .,
CNDS * ' CNDS
- LP FW'I fLPFW" f HP FW 1HP FWI 2 DEMIN PMP - HTR 1-2 ' HTR 2-2' ' H TR.1 - 5 ~ H TR -2'-S
)
SYSTEM ' DISCH HOR HI L W l HI LW t .'.jil LW -i (HI LL AP Hi PRESS TRIP TRIP - 3- ' TRIP t ' TRIP - CNDS
- CNDS * .LP FW"" LP FW'" vj HP FW'"
PMP HP. FW'" :
} DEMIN HTR l-1 : HTR 2-1 HTR 3 -4 ' ,HTR, 2 UNIT SUCT HI LW ' j Hi t W < .(H1 LW ' .Hl LW'l AP Hi
']
PRESS LO. TRIP - TRtp ' 'CTRIP - TRIP' _ i f ,. se r sa r: sa. r _ v.n r ~. . w. -' l HP CNDSR -DEAR n 0 EAR; HP 'FW h '" OUTLEY HOTwtLL STRO TK 1 STRG TK 2 > HTR l-6
- HP FWl HTR '2-6 CNOCT Hi AN '
C CNDSR
.. i . r i./ .
HTR 6 . _ @ FW - 1 1P FW ,;HP3C HP FK ' O WTdi : HOTwtLL HTR 1-2 rHTR 2-2 HTR 1-5 HTR*2-5 i CNOCT Hi NN N * ^@ N . 47 Cs05 - 4P,rW- (, ,g-[g ,g- - 6 """ "'" "'". OUTLET = ORN TK 1 ORN'TK~2 HTR ' i-4
- 4R 2-4
<1
+ CNOCT Hi - LW LR '
~. ' - ~
A B C - D 1 E F i n __.a ' ______z____________________
~ .:
~
INSTR f RADWASTE ? TRIPS l
- ~- COMPUKR . CLN WST .WST CAS WISC WST ,' CRO. ' T-C
) FAILURE SYS OUT ,SYS OUT SYS OUT: , ), TRIP W ASTER !
-) ;
RA0 HI R A0 HI ' RAD HI-- ' *CONnRM- TUR8 TR!P l ! L .1
^'
COMPUTER
' CLN WSi'
^
# - - " / "
L. 2 WONIT TK I
'.WISCWSI MONIT TK RCP 1-1 RCP 1-2 ;
uLPLxR PWR LOSS OR no x OEC^v TxS TROL
. nL1-- '
2 WTa Taal
. TRIP Mia Tael TRIP -
i TRBL TRBL' ( a . = . R ii t .- = .
. .= ,,r COMPUTER WST CAS MISC WST
, .m 7 . }
~CLN WST-3
. RCP 2-1: RCP 2-2 'l Mi,PLXR PWR xFER SYSTEM : SYSTEM SYSTEM . *
- 3 MTR TR8L MTR TRB( l TRBL~ , TR8L . - TRSL:
[ TRIP ; . TRIP { m . . ,,,- . y . COMPUTER CLN WST
]
l i= 4 -MLPLxR 'OECAS-4 MFPT 1 TRIP -
'MrPT 4 TRIP TEMP . HI :TRBL '
l g . 1 .
- m. C ,: ,.
. . . ==l
' n ;
-ANNUN. SA, RC . . ' SWYO -
l 5 SYS TR9L EvAP: -dan TK ? 5 ACs m a Ace mo SWYO-i TRBL LVL ' - TRIP TRIP - ;
+ ^
STA "REMOTI RAD M6I RAD MONT # " ."" l,l g 6 SEISMIC INSTR SHUTOOWN PANEL IN COMPUTER LOCKUP COMPUTER LOCKUP- y
.fSFRCS:
, ACTU ATED OSSi TRIP
.ON- OPERATION CH I CH 2 *
- i gi i l A B C D -
A B 93 A\ " S 7 RV C 7S. i t
~
VENT W.TR HEATING AIRJ FIRE' CREVS DEMIN WTR
. ,, 7 STA AIR lNSTR ' AIR 1 TRAIN l STRC TK 2 AUX BLR ARE-OR.
' TRIP - CMPSR'1: , HOR RADIATION i
RAD Hi TROL TRIP . PRESS LO : TROL J ! CREv5 S TA '"' " ' "' ' ' * AUX RR STA AR: 2 TRAIN 2 DEMIN WTR TREATMENT .SYS CMPSR'2 EMER INSTR AIR CMPSR FIRt WTR ELEC PMP 1 RAD H! *TR8L ] SYS TRE TRIP , TRIP ON . a a " *= I
. 374 r. = -
a" gygg.,gsg l l Aux s'a ST^ Aia riac.wtR ..--- 3 UNIT VENT RAD HI-WTR PRE-TRE ATMEN T ORUM HOR. A. CuPSR OSL PMP i AFTCLR , ;
, . SYS TR8L - Lvl PRESS LO gyp g, ON j i
l HW HTC" ' aux-STd" .STA- AIR"
~
l 4 SUPPLY LINE :- CNOS TKS/ FLASH TK CMPSR t-:
.-AFTCLR ySM AIR ORYER-nRE WM
. OSL PMP 1
l TEMP LO LVL Hi TEMP Hf ~ ** t.et . rm ; a
- s 3M .a y esse e.m
-l LAB HOOD 5 ExH nu p f. OSL Oll' STRc Tx h8p A
~
N2 FIRE. WTR ~j TEMP HI u ,E ,,TCt , +0R ruRe eLOC ' p LYL PRESS p , PRESS *LO SEC HW H'k, NEW .
" # r ""
6 RECIRC HX OUTLET LUBE O STRC TK
' IL FIRE WTR
.STRC TK FIRE WTR
'STRC TK m
TEMP HI LVL TEMP LO LC lA. B R ICI Dl IE 'lF I e ,- + +----v' w = v--- e--+
@h I
INSTR RADWASTE ' I TRIPS:
.... .. . .. . . .m .. _ ..
" C!N WST WST CAS MISC WST CRD ' T- C -
) FA[URE SYa OUT SYS OUT- .SYS OUT. <:.< 'l TRIP M ASTER - (
. R AD Hi RAD Hi , R A0 HI . '
CONFIRM TURS TRIP l
. *- ""
- r
- CLN WSf
- WST CASI '.MISCWSI
# '" C "
C
.MLPLxR OMPUTER MONIT W '." . g- RCP l-1 RCP 4-2 '
2 M ALT DECAY TKS MONIT TK OR FILT .. Z MTR TROL MTR TRBL { PWR LOSS Ok , TRIP TR8L TRBL g , Trip j R.. . .. .- P , ., , ,
)
COMPUTER CLN WST WST CAS MISC WST RCP 2-1
.l , RCA 2-2 3 'MLPLxR PwR xFER SYSTEM SYSTEM SYSTEM , '*
MTR TR8L MTR TRBL )[
,lTRBL ,
TROL TRBL: , l 1,. . TRIP : TRIP COMPUTER CLN WST r .. 1 4 MLPLxR TEMP Hi DECAS
, 4 MFPT 2; TRIP i
5 TR8L '
'y .j
, a., .. .
- r. se .,- .'. '
. .m ANNUN BAl RC SwYD ~ ! SWYD 5 SYS TRBL.
EVAP- MN TK .
't 5 ACs um ACs u m i
TRBL LVL ' < TRIP ' TRIP ' n.< A
}
STA " REMOTE RAD MON RAD M0'NI i # "' '"' 6 SEISulC INSTR SHU TDOWN PANEL IN COMPUTER LOCdVP COMPUTER LOCKUP.
,. SFRCS ACTUATED OSS TRIP '
ON OPERATION CH I CH 2 . , g 3
~
A B C D - A B ! 1 9 3 A\" SHV0fS i VENT l WTR CREVS HEATING l AIRS FIRE l DEMIN WTR
~
STA AIR INSTR Al
) TR AIN 1 STRC TK 2 AUX BLR CMPSR 't. , ' HDR FIRE O RADIATION RAD Hi TR9L. ~ TRIP .
TRIP . P.RESS LO TRSL'
. .. . .= . m. , em .. , ..
n CREVS Z TR AIN 2 DEMfN R AUX BLR STA AIR EM'ER ' INSTR FIRE WTR ,3
~ TREATMENT SYS. CMPSR 2 AIR CMPSR ELEC PMP RAD Hi ;
SYS TRet ' TROL . _ TRIP . ,l TRIP - ON ; a r S T A ""' '" '"" " EMER INSE 3 UNIT WNT R AD HI ' WTR PRE-TREATMENT
* # OL
' ## ' AIR- CMPSR 0%
SYS TROL PR Sh AFTCLft TEMP Hi l
* *"" i HW HTd' * "'
VAC SYS ' AUX ST0"' iSTA.Al[ I NSM AIR 4 DtSCH' SUPPLY UNE CNOS TkS/ FLASH TK CMPSR l~- AFTCLR-FIRE WM 0% N j R AD Hi . 3 TEMP LO LVL HI ' TEMP HI ** '
^
. . m on
. n. m ... -4 LAB H000 OSL OL gyppgy 5 ExH riti TEMP HI t,Nt SmC m CMPSR 2.
ArTCtR Ha N2 MRC WM
= e eLoC 5
pto, LYL II I TEMP . Hl . n
# -i
$CC HW H'TG NEW " -
6 RECIRC HX OUTLET LUBE dlL STRC TK FIRE WTR STRC TK FIRE "WIR
'STRC TK i
3
. . . . TEMP Hi Lvl. TEp LO M. '
A. B ICI IDI- IEl ~lF l. 1GI
<J
' s , ,\
j~ '
, . 03#3 1;
-)
MSR ICS/NSTRUMENTAT10N
* ~
j I ' ICS "
- NN1- N" NNI=Y 24 VDC- 24.VDC /24 VOC '
}
TUR8 iP TV 3 IP ' TR L - TR g P-MSR 1"* MSR 2"* *ICS/hNF . I 0I " Q MOIST SEP moist SEP g, l118 VAC
'- DRN TK DRN TK PWR. FUSE ' -
- LW He LW HI Hi U MIT blown -
L TRBL-e MSR 1"" MSR 2** gg ". ICS Mrf*' '!-
~!
gpy MOIST SEP MotST SEP LOSS OR ,
} DRN TK DRN TK RCP LOSS LO DEAR * . MN STM !
RUNBACK , PRESS, LVL LO LR LO RUNBACK
,l
# # ~ ^
MSR l'"' ^ ' MSR 2"" ICS ** ICS ? ** . ifg - ISI STC ICS 4 DRN TK - IST STC ORN TK R X PWR -
- UMITED
-FW UMITED '
INPUT' INPUT' i
' BY Tw MtSMATCH TRANSTER LVL LW BY RX PWR
-t MSR l'"'-
MSR 2*" ICS 1CS 2ND STC- 2ND STC
} DRN N DM M HiLDAD -LO LOAD gy,7 gygy' LW LW-n' .
_. lCS - _ e.e ICS 6 '5
,N? RACK Sc a Sc 2 BTU,UMai STU Uusi A B C D E F -- '
5 ~UR3 \ E SEAL.S l EHC TURNG LUBE - TUR8 CNDSR .'
,U,, _ _ _ _ . ,,,, ._
$ty Sggt EHC T-C T-C' ; TUR8INE.. '
HP CNDSR
~
1 HDR 2ND PMP -ROTOR DC [ BOP ~ FAULT, PRESS LO STARTED STOPPED ON - TR,lPI +
'T- C TURY
TUR8 EHC T-C . - T-C ' - 2 s SPE - rou D
"^a " ' 'a caosa U AC TCOP .Euu C - -
PRESS Hi PRESS LO ' ON PRESS Hi R VIB ';HI, a= C um . T-C
- T-C LUB"E" h SPE LR HI FLU D DSCH . 0\ IN EXH NOOO LR PRESS L0 TEMP HI -
PRESS LO
,,C m-e ? T.e 4 CABINET LUBE OL TK OutLL SHAFT' TRBL
. LW- FML ' ,
EHC "" T-C * " .' " 5 c'a' PANEL v^aca Exi ALAng
' Ap to i
. 'TRBL .,
a EHC "" T-CLUEiI 6 FLUtD SHUTDOWN OL TK - SHUTDOWN LW HI LVL Hi
- l A B C D E , F .
b
-- *p P sv v w-y--ug *w
'l l-
}hf
- 1 u INSTR -
RADWASTE: c
- TRIPS CLN WST WST CAS WISC WST ',*
]
COMPUTER gg g gyg g .SYS OUT l i I# - RAD Hi RAD Hi RAD Hl:-
] *
\: k i , " -
- CLN WST ' ^- ^
% ^5 ' ^
e) WONIT TK ,< f ' OR FtL T * } , i_ TRBL' L L g n . qiis .
. == *
- r.-. r 3, COMPU TER CLN WST-. -WST CAS '
^1 ;(' RCP 2-l ' RCP 2-2 MLPLxR PWR xrER SYSTEM TR8L SYSTEM.
TRBL' 4 2v ^Q , 3 MTR TROL MTR:TRBL
. TRIP ' TRIP m '~
.e" . =s / .a*
COMPU TER 4 k MLPLxR TEMP HI 4 MFPT 1}}