ML20070A894

Exercise Manual Fort St Vrain Nuclear Generating Station NRC Graded Exercise

ML20070A894
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/07/1990
From:	PUBLIC SERVICE CO. OF COLORADO
To:
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ML20070A890	List: ML20070A888 ML20070A894
References
NUDOCS 9101290158
Download: ML20070A894 (312)

Text

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EXERCISE MANUAL FORT ST. VRAIN NUCLEAR GENERATING STATION

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NRC GRADED EXERCISE NOVEMBER 7, 1990 PUBLIC SERVICE COMPANY OF COLORADO l

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FOSAVEX-89 GRADED EXERCISE MANUAL i

i TABLE OF CONTENTS i SECTION PAGE 1.0 Schedule of Events 1.0-1 2.0 Scope and Objectives 2.0-1 2.1 Scope 2.1-1 2.2 Objectives 2.2-1 3.0 Guidelines and Instructions -3.0-1 3.1 Guidelines 3.1-1 3.2 Player Instructions 3.2-1 4.0 Controller / Observer Information 4.0-1 4.1 Precautions and Limitations 4.1-1 4.2 Assignments 4.2-1 4.3 Instructions 4.3-1 4.4 Emergency Response Facilities 4.4-1 4.5 Evaluation Sheets 4.5-1 5.0 Scenario 5.0-1 5.1 Narrative Summary 5.1-1 5.2 Initial Conditions 5.2-1 5.3 Detailed Scenario 5.3-1 5.4 Scenario Time Line 5.4-1 l

6.0 Scenario Data Package 6.0-1 o Plant Messages o Offsite Messages

-o Plant Parameters i

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TABLE OF CONTENTS (Cont.)

SECTION PAGE 7.0 Onsite Radiological Data 7,0-1 7.1 Plant Monitoring Data 7.1-1 7.2 Radiation / Chemistry Data 7,2-1 7.3 Plant Area Radiation Levels 7.3-1 8.0 Offsite Radiological Data 8.0-1 8.1 Meteorological Data 8.1-1 8.2 Relesse Rate / Dose Assessment 8.2-1 8.3 Field Monitoring Data 8.3-1 8.4 Maps . 8.4-1 9.0 References 9.0-1 9.1 Procedure Index 9.1-1 9.2 Key Documents 9.2-1 ii

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y- .t 1.0-1; I SECTION:1.0' i SCHEDULE OF EVENTS Figure 1-1 provides- the schedule for thel1990' Fort.Stc Vrain NRC-Graded Exercise (F0$AVEX-90) which will be conducted on' November 7, -

1990,

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i At 'the Controller / Observer briefing: scheduled for October 29,1990,: .

the specific-details of the scenario will be-presented. 'It will also-provide a forum for discussing any: problems encounteredtduring:thei -5 1990 Dress Rehearsal. Additionally, key; milestones : will:* bei identified and corresponding Controller /0bserver factions wil _l- be .- ,

discussed, . Final Observer assig'nments_will.be made and,any>q'uestions relating to- the . scenario, or . the^iresponsibilities 'of .the; '[

Controllers / Observers.:wil'1 be answered.

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The Controller / Observer debriefing'will occur.'immediatelyfafter-thel

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exercise is terminated by PSC/NRC. Each Controll'er/0bserver'will' be- -

l expected to provide a. brief --synopsis ofd .his/her findings (both -

positive and negative). The Lead Controller / Observer will'. summarize-- .

these findings and will serve as-the) primary exercise spokesperson ati '

the PSC/NRC critique. A preliminary exercise' report will .be provided i

to-the NRC at the conclusion of.the critique; I

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1- FtGURE 1-1 SClllDUtE Of EVENTS l j

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.I .EVENI I DATE 'l TIME I toCAIION I COMMENTS I

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1. Controt ter/ Observer Briefing i Oct 29 1 1300-1530 1 Visi tor Center i Attendance Mandatory for At t 'i

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-l l l Aud i to rium i ControI ters/ Observers. I j l .

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I 1. I i M l ~ l Pre-Exerci se . Pa rticipant Briefing i Nov 6 l 18:00-1530 1 visitor Center l Attendance Recommended ' for Ali key .I -f 2

1 l l I Aud i to ri um - l FOSAVEX-90 Pa rt i c ipants. l ~z6

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, l NRC inspection /QA Audit Entrances l IRA l IBA 1 Visitor Center ,1 PSC Key Management, Lead Controllers, l ,

1 I l l, Auditorium <l QA Auditors. l -[

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' i NRC.C.E.T. Training'and Badging 1 TBA. l IBA . I Conference Room,l NRC Inspectior Team and PSC Training / Security :l

'l l l i Training Bldg. l .I-

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1 'l. t l NRC - Inspect ion Team . Scena rlo - ' l' TBA l TBA l Conference Room,1 NRC f nspection Mam and Key Controllers. 7i! {

l. Briefing :. '1.

.I 1.Iraining Bldg. 'l

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'I l"f0SAVEX-90 Exercise'

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l'Nov 7' l!O700-1530 i Ati ERf's l:

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1 l- f ollowing l ' Visitor Center I All PSC' C$ntrollerf')bservers and QA Auditors. .

, ~ 1 Control ter/ Observer Debriefing. l'Nov 7

. l :l t exercise l Ated i to ri sse i t i 1

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l PSC Exercise critique 1 Nov 8- 1. ! BA l' Visitor Cr 'e r 'l Controllers, Observers; Auditors, Key TOSAU  ! '

l-l 1: - ' Audi toriti i l'a rticipants/ Management' and State /f ederal I

l- !l' .l .- I Personnel.c 1-

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, l'KRC inspection Exit'- ,1?TBA 1 IBA . l Visitor Center ' . I Same as above. I, i'

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~!. ' .I' l QA Audit Exit.. 'I Nov;8f il IBA- I Visitor Center . l .' Same' a s above. ;l i

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< 18 Observer / Participant.l Critique i t : Nov 9.. I? 1300-1530 ^l Visitor Center i I L All" interested Participants and Controller / 1 l and-NRC/NfSC/QA Exit ReviewsL -82 1: ' i l ~ Aud i to rium -. 1 Observers. Will discuss initial critique 1: :j

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3 l I ;' 71- I: rindings, and exit findings. Will also obtaint l

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l- l 'I l- I ; comments = and correct iens trna pa rticipants.

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t 2.0-1 SECTION 2.0 SCOPE AND-0BJECTIVES SECTION PAGE 2.1 Scope 2,1-1

.1 2.2 Objectives 2.2~1 s

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SECTION 2.1

- SCOPE- 0F FOSAVEX 0 The 1990 Fort St. Vrain NRC Graded Exercise, known as FOSAVEX-L 90, will be held on November 7, 1990.- FOSAVEX-90 is-intended to-provide a mechanism by which Public Service Company of Colorado -  ;

(PSC) can test its Radiological-Emergency Response Plans (RERP).

Depending upon personnel availability, The State of Colorado'and-Weld County may participate in FOSAVEX-90. -Since 'the precise leul of participation is not known..no specific objectives for the coordiation of utility / state / local r_esources -have been-established. However, the scenario has'been structured to allow. "

for this type of interaction is state / local -representation should occur. F:MVEX-90 will also provide the means by which 4 PSC can test _its ability to " protect" the. health and safety of the general public.

The exercise scenario will depict a series of' simulated events which will necessitate a number of specific response. actions to, be.taken by PSC. These response _ actions are defined in the Fort St. Vrain Radiological' Ernergency Response Plan -and Implementing:

Procedures, and are intended to safeguard the health and safety of the general' public,- plant personnel,-- as well: as. the environment. The scenario is. being planned such_that major elements of the FSV RERP Plan and-Piocedures are tested.

Since, by necessity, certain elements < off.FOSAVEX-90 'are

. simulated, whenever practicable, the exercise - wil'1 incorporate provisions for " free play" on the part of'the participants. The, only restrictions on this concept will be' if Player-l actions ,

would prematurely terminate the Exerciser or-'would restrict the 4 scenh io in such a manner that it iwould noti provide- an opportunity for PSC to meet its objectives (see Section12.2).

As previou>ly stated, certain . elements- of LFOSAVEX-90 are- '

simulated. Attached -is the proposed table .depicti_ng-'which-activities are- to be simulated and which ones are[to actually-r . occur. i Activities - associated with FOSAVEX-900 will .be' observed; by' r

4 qualified centrollers, observers and' auditors from PSC, Section  ;

4.0- provides.- information on. how -and to whatt criteria the exercise--is to be graded.- A critique. will. be conducted following the exercise.' Any-l deficiencies will be noted, and:

will form the basis for establishing: corrective ~ actions.

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_ TABLE 2.1

$ COPE OF FOSAVEX-90 ACTUAL VS. SIMULATED EVENTS EVENT - ACTUAL. SIMULATED-

1. ACCIDENT ASSESSMENT Ability to properly recognize and X characterize' Simulated events. '

Perform-dose calculations using X simulated meteorological and release rate data. .

' Perform field monitoring - X establish' radiation levels -

onsite and offsite.

Perfore, equipment repair X

2. ACTIVATION OF EMERGENCY FACILITIES -

Activate and staff all primary X Emergency Response. Facilities (ERFs).

Establish functional adequacy X of ERFs.

Use appropriate equipment and X supplies to respond to emergency.

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EVENT ACTUAL SIMULATED 3, NOTIFICATION AND COMMUNICATION Notify Plant, Corporate, Federal, .X State and Local emergency response personnel.

Conduct follow-up notifications - X verify communications.

Communicate with onsitt and . X offsite response teams.

Support " rumor control" activities. X (Limited, due to non participation of state / local personnel)

Conduct press conferances. X Direct notification of persons X living on PSC property.

4. ORGANIZATION CONTROL Activate the PSC emergency X response organization Coordinate with State / Local X response organizations.

l Coordinate with Federal X'-

i response organizations.

Provide management' control of_ X' the emergency.

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' TABLE 2.1(Cont.)

EVENT ACTUAL SIMULATED-

5. HEALTH PHYSICS / SECURITY Receive and analyze field X monitoring data, Provide adequate radiation X protection services (dosimetry, monitoring, habitability,etc.),

Conduct a search and rescue ,, X operation.

Site evacuation of X non essential personnel.

Use of protective clothing, X Simulate use outside owner control-led area.

Provide first aid for an X Transportation injured and contaminated, to hospital will individual, be simulated, l '

Decontaminate personnel X l and/or equipment.

Conduct initial accountability. X Maintain onsitt accountability, X Maintain plant Security under X emergency conditions.

Comply with the Security Plan X under DNSITE Radiological Conditions, 6, PROTECTIVE ACTIONS-Assess and recommend protective X actions.

Warn / advise onsite personnel X about emergency situation. ,

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SECTION 2.2 .

i OBJECTIVES OF FOSAVEX-90 l

The objectives of -the, Fort .St.- Vrain (FSV) 1990 Emergency; Preparedness Exercise Program are based: on- Nuclear Regulatory I Commission (NRC) requirements set forth in 10CFR50.47, Appendix '

E. Data provided in NUREG's 0654 (Rev. 1), 0696,.- and -0737- t (Supplement 1)1as well as previous FSV exercise resultsiwere. >

used in developing the objectives.  ;

- The exercise will include the activation _of the 1 PSC Emergency.

Response Facilities; It may:also include partiel participation l

by State = and Local support groups. '.-The FSV- Early Warning Alert I (EWA) System within tr4e five mile planning- zone will -not be activated in association with FOSAVEX-90; The overall objective of ;FOSAVEX-90 is to evaluate the effectiveness and capabilities of the FSV Emergency Preparedness:

Program. The scenario is: _ structured. to. provide a mechanism which will accurately test the adenuacyfof both the' onsite and-offsite elements of the Emergency Preparedness: Program.

• Another. objective of TOSAVEX-90 is to demonstrate the abil.ity-of '

the Observers / Controllers and Auditors to--conduct- an , exercise, and evaluate- the . response of_ the" FSV, Emergency; Response Organization. At the conclusion of the 'epercise,- a ' critique- .

be ' held to evaluate the various activ.ities of FOSAVEX-90, will i accordingly, another objective of this process is to demonstrate:

the ability. to conduct- an effectiveLLself_ evaluation of the;  ;

exercise.

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2.2-2 Public-Service' Company of Colorado"has established the following objectives for.FOSAVEX-00:

ACCIDENT ASSESSMENT

1. Demonstrate proficiency in recognizing 'and classifying emergency conditions according to _ pre-established =

Emergency Action Levels (EALs).

2. Demonstrate the- ability to' perform dose calculations using radiolo'gical and meteorological information to establish the impact'to the environment.

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3. Demonstrate the- effective ~ ness of the:_ radiological monitoring teams: (onsite and offsite); to:_~ establish-radiation levels a'nd__to effectively track the plume. J ACTIVATION OF EMERGENCY FACILITIES <

1. Demonstrate the ' ability of_ station .and: corporate personnel to activate and staff the primarytemergency:

response facilities within 90 minutes of a declaration:of-an ALERT or higher: emergency ~ classification-during normal working hours (0700 hour0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> _s tol1530 ho,urs).-

2. Demonstrate the transition of responsibilities between:

E m gency facilities as a result of escalating accident.  !

classifications.

3. Demonstrate the functional capabilities of equipment (including status boards,. radiation monitoring. equipment,-

etc.) in-the Personnel Control Center.1 Technical. Support Center, Forward Command Post, State Emergency ' Operations Center, and the Executive Command Post.

4. Demonstrate the_ ability _of the Emergency Coordinator to.

properly : select-the correct: location for the--Personnel -

Control Center, r

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NOTIFICATION AND COMMUNICATION

1. Demonstrate the effective notification of Plant, Corporate, Federal, State and Local emergency _ response personnel.  !

l Demonstrate that initial notifications (and follow-up) l 2.

are verified and logged, I

3. Demonstrate the effectiveness and reliability of the emergency communications equipment,

4. Demonstrate the ability 'o t communicate .with inplant.

monitoring teams, search _and rescue teams, and other station personnel as needed.

5. Demonstrate the ability to communicate with the offsite radiological monitoring. teams.

6. Demonstrate the capability- to obtain, coordinate and ,

assemble emergency information for timely dissemination to the public via the media (actual press releases will l be simulated).

l l 7. Demonstrate the ability of PSC,to-respond directly to i simulated input from the public concerning "real" vs.

l " rumored" events.

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ORGANIZATIONAL CONTROL .

1. Demonstrate the capability to technically evaluate accident conditions and implement appropriate response-procedures.-

2. Denionstrate the ability of the Control Room Director, TSC Director, PCC Director, and the ' Corporate Emergency Director to manage and/or support -the emergency organization in accordance with the FSV-~ Emergency Plan and Implementing Procedures.-

3. Demonstrate the' ability of FSV emergency organization personnel to properly brief Search and Rescue, Fire-Brigade, Corrective Action Teams and other response

, personnel of the emergency situation.

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4. Demonstrate the ability to coordinate activities with FSV outside support groups'in responding to the emergency, as necessary.

5. Demonstrate the ability of the PSC response organization to follow established procedures.

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HEALTH PHYSICS / SECURITY

1. Demonstrate the ability to perform and maintain site accountability and simulate site evacuation,. as appropriate.

2. Demonstrate the ability to provide adequate radiation protection services such as dosimetry, personnel monitoring, and habitability determinations onsite and offsite.

3. Demonstrate the ability to perform area surveys under emergency conditions. .

4 Demonstrate the ability to monitor and control emergency

worker exposure (i.e. Various teams) within the plant.

5. Demonstrate the ability to decontaminate personnel as needed.

6. Demonstrate the ability to provide onsite first aid for

an injured individual who has been contaminated.  ? -

l (Transportation -to the offsite medical facility will be simulated) - ?.

7. Demonstrate the capability of offsite radiological i monitoring teams to perform radiation monitoring and to collect samples.

8. Demonstrate the ability to maintain plant security under emergency conditions.

9. Demonstrate the ability tc conduct timely dose projections in accordance with established. RERP Procedures.

10. Demonstrate the ability of the Security force to comply with the Security Plan under -onsite radiological condit. ions.

PROTECTIVE ACTIONS 1, Demonstrate knowledge of the Protective Action Guides (PAGs).

2. Demonstrate the abil'ity to make protective action l recommendations to offsite authorities.

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3,0-1 SECTION 3.0 EXERCISE GUIDEi.INES ~-

AND INSTRUCTIONS I

i SECTION PAGE-i 3.1 -Guidelines- 3,3 3-5 3.2 Player Instructions 3.2-1 l

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u SECTION 3.1

• GUIDELINES FOR CONDUCTING FOSAVEX )

This section of the . manual is inte'nded to pr6 vide guidance for conducting FOSAVEX-90. All Key _ Players will have had-an -opportunity to review this material prior-to.the exercise. -

P Simulatino Activities t Since drill exercises are intended to. demonstrate actual: emergency ,

response capabilities, the participants of.FOSAVEX-90 should .act' as4 .

they: would during a real emergency- situation.; However,'-sincec  ;

exercise Players are " graded," it-is_important.that a;'certain level of " acting" be done._ This is: especial.ly important in_ areas that.

would normally be accomplished quickly-wiethout: _much notice 4because the events are : simulated ( e . g ,- checking monitoring = equipment,=

i conducting habitability surveys, etc.). In these'typesLof= situations >

the . participant should : inform' La Controller / Observer ~that .a:  :

" habitability survey" has just been completed and1that',- for; example; I the TSC Director was informed of the " findings." '

Since this is an opportunity to . test the response organization,  ;

wherever possible, actions t should .be carried e out : to' the fulle'st extent practicable. Only1 when it i s_ not feasible-to perform an-action, should it be simulated. Any--orders given, that ifor :any reason cannot or should not actually be-performed; should be.. prefaced with the word " Simulate". . For example, you would simulate, ' carrying =

a contaminated, iniured individual' up =a _ fl<ight off stairs .toLthe '

ambulance. Where such actions are-being simulated,:it.is= Muggested 9 that participants inform any Controller (s)/ Observer (s) in the area  ;

what. specific actions would have been taken had~ the 1 emergency: been real. .In the example cited above, specific radiological / medical precautions that would be taken should' be ~ discussed Ewith -the .

Controller (s)/ Observer (s).  :

-Radiation Work Permits (RWP's) will not be; issued for FOSAVEX-90.' If  :

scenario events idirect ' Players to areas (that .are actually .RWP [

controlled. Players will simulate activities that.would i have' occurred  :

inside the area. Under no circumstances should-anyone enter an:.RWP

• controlled area even if they are authorized to dolso.-  ?

Public protection l

Intentionally violating the law is unacceptable;during anyLexercise. .

Participants should not ignore posted traffic laws:-(e.g., speed.

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limits, stop signs, etc.). - Additionally, of fsite field monitoring.

teams should pay particular attention to public/ private' lands- (e.g.,

g farming operations,. livestock, etc.). .

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Since the actions of Federal, State, Local and Utility organizations i receive -continuous public scrutiny, it is possible that the

- activities associated with FOSAVEX-90 could be misrepresented.

Therefore, it is imperative that all communications that can. be monitored by members of the general public (radios, loudspeakers, etc.) be prefaced and concluded with the words, "This is a . drill; This is a drill."

Maintaining Emergency Readiness During F0$AVEX-90 the ability to recognize a real emergency, terminate the exercise, and respond to the .new situation must- be maintained. Therefore, the exercise scenario and actions of participants will not include any actions which seriously degrade the condition of systems, equipment or supplies, or affect the detection,-

assessment, or response capability to radiological or- other emergencies.

Actions taken by the participants will also avoid actually reducing plant or public safety. The potential for creating real radiological or other emergencies will be specifically avoided.

If a real emergency occurs during the: exercise, requiring the actions '

of plant and corporate personnel, the exercise will be terminated. '

All messages about real events will be clearly identified as such.

For example, precede a real message with: "This is'NOT,' repeat, NOT an exercise message."

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3.2-1 SECTION 3.2 PLAYER INSTRUCTIONS Since the primary purpose for conducting an annual graded emergency exercise is to enhance the effectiveness of the FSV Emergency Preparedness Program, it is important that the program receives feedback from both Players and Observers. As previously stated, it is important that the scenario events be treated as "real" situations requiring immediate actions and responses. As part of this response, certain procedures, equip. ment, and facilities may prove to be inefficient or totally inadequate. To improve the program, Players-are requested to review the attached questionnaire. At the conclusion of the exercise, you should complete the form and forward it to a PSC Controller / Observer or,Renee Millison at FSV. Every PSC-Controller /0bserver will have additional forms if.needed, i

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'3.2-2 PARTICIPANT QUESTIONNAIRE In order to identify areas requiring' improvement within the FSV Radiological Emergency Response Plan, you are requested to answer the following Questions. Please be. candid, constructive criticism is appreciated. Please make-comments, identifying any deficiencies you feel exist.

Upon completion, please return to a PSC Controller / Observer or return via Company mail to Renee Millison, Emergency Preparedness, at Fort St. Vrain, Thank you for you- assistance.

1. Name(optional)

Emergency Response Center

2. Approximate time you received initial notification:

3. Approximate time of your arrival at your emergency response-center:

i 4, Please briefly describe your functions / responsibilities:

5. D'. you feel as though .you. have been adequately trained-to fulfill _your duties?

6. What RERP. Implementing Procedures, if any, did you utilize or reference?

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7. Were the procedures easy to locate?

8. Did the procedures adequately describe your functions and/or responsibilities?

9. Did you utilize checklists provided in the procedures?

If so, were the checklists: .

. a. Compatible with the procedure?

b. Able to be used without referring back to the procedure?

c. Complete, (i.e., did they contain all appropriata steps)? _ _

If not, would a checklist have been helpful to you in complete your assigned dutics?

10. Was the equipment and/or material available at your response center adequate? If not, please list any items that l would have been helpful to you:

11. Were the communications systems used (i.e., radio, telephone, etc.) at your facility adequate?

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12. Were internal communications (i.e., messages, status boards, t

etc.) handled effectively?

13. Were you aware of events as they occurred?

14. Comments: Please' use this space to comment on any aspect of the exercise. Again, constructive criticism.is appreciated.

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I4.0-1 SECTION 4.0

_ CONTROLLER /0BSERVER INFORMATION l

SECTION PAGE ,

t 4.1 Precautions and Limitations 4.1-1

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4.2 Observer Assignments 4.2-1 t

4.3 Instructions 4.3-1 4.4 Emergency Response Facilities 4.4-1 4.5 Evaluation Sheets 4.5-1 Control Room Technical Support Center Personnel Control Center Forward Command-Post Executive Command Post l

State Emergency Operations Center Security Force Onsite Radiological Monitoring Offsite Monitoring Teams Corrective Action (Repair) Teams First Aid / Search and Rescue - FSV e

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k 4,2-1 SECTIOR 4.1 - _

PRECAUTIONS AND LIMITATIONST

.- Introduction .

.I Public Service Company of Colorado representatives will serve as ,

-Controllers / Observers for F0$AVEX-90.- Each Controller / Observer has, as a minimum, an Exercise Manual containing' Sections 1,0 thru 9.0 and should be familiar with the following:'

1. The basic Objectives-of the exercise (Section 2.2). y

2. The Guidelines and Instructions provided to' the Players-(Section3.0), ,

3. The exercise 1 scenario,- including" othe initiating events (Section 5,l'and 5,2).

4. The various onsite and.offsite locations that wil1 be utilized by_ the Players when responding to the' scenario events  !

(Sections 4.4, 7.3,.and 8.4)'. t

5. The exercise evaluation form ~(Section 4.5). , j Precautions and Limitations In -addition- to reviehing _the -five 'arecs- described above, .all:

Controllers / Observers must be aware of the following:

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1. Shoulo, at- any time during the: course of-the conduct'of this exercise, an actual emergency situation 11arise, all Jactivities-li and communications related to the exercise will be suspended.--

' It will. be the responsibility of- any. : exercise

- Controller / Observer'thatibecomes aware of an actual emergency to suspend exercise responseL in his/her Limmediate' area and~ to r

4 inform a Lead Exercise ' Controller.tof the: 1 situation. . Upon t notification.of any actual emergency, a Lead Exercise: Controller-may notify all other1 Controllers /00 servers _to 1 suspend .all-exercise activities. fA Lead' Exercise Controller: together with- s

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the TSC Director-and/or theJCorporate Emergency. Director will make a_ determination'at that point whetherito continue, suspend, .

or terminate the exercise,

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2. Should, at any time during the course of the conduct of this exercise, an exercise Controller /0bserver witness- an exercise participant undertake any ection which would, in the opinion of the Controller / Observer, place either an individual or plant component in an unsafe condition, the Controller / Observer must -

attempt to terminate the unsafe activity immediately.

Upon termination. o' the activity, the Controller /0bserver is responsible for esntacting a Lead Exercise Controller and informing him of the situation. A Lead Exercise Controller, together with the TSC Director and/or the Corporate Emergency Director, will make a determination at that point whether to continue, place on hold, or terminate the exercise.

3. Manipulation of any plant operating systems, valves, breakers, or controls in response to this exercise. are only to be simulated. No alteration of any plant operacing equipment, systems, or circuits in response to this exercise should occur,

4. All repair activities associated with the exercise will be simulated. Extreme caution should be used when working near

( operating equipment.

S. All telephone communications, radio transmissions, and public address announcements related to the exercise must begin and end-with the statement, "This is a drill." Should a Controller /0bserver witness an exercise participant not '

observing this practice, it is the Controller / Observer's

! responsibility to remind the individual to follow this practice.

6. Any motor vehicle responding in this exercise, whether for medical, rescue, fire fighting, field monitroring, etc., should observe all normal traffic laws including posted speed limits, stop lights / signs, one way streets, etc. -Controllers / Observers should ensure that exercise participants follow these requirements.

7. Care must be taken to prevent any individual not involved'with the exercise from believing that an actual emergency- exists.

l Any Controller / Observer who believes that this situation exists, should approach that-individual and explain the nature of the exercise and its intent.

8. If- a Controller / Observer is aware of- any- of the above situations, he or she should immediately identify the situation to a Lead Exercise Controller.

= .- . . . - , . . . . . . . - . . . - . ... .. ,. .-. - . , .. . _

4.2-1; SECTION 4. , , CONTROLLER /0BSERVERtASSIGNMENTS' Provided below: are the ~

Controller /0bserverz Assignments' for F05AVEX-90. The! Lead Exercise Controller (s) are responsible for 'a l l -

l activities associated withi - the - exercise. . Senior Controllers / Observers are responsible ,forc activities Lwithin; a specific' Emergency Response' Facility or for a specific response:

activity (e.g. , field monitoring, plant' surveys, etc.),-

=I Facility / Activity iControllers/ Observers:

1. Lead Exercise Controller Renee Mil 1ison L

2. Control Room ' L: Joe Hun'ter -- I

' Wayne.Magninie: Ji

3. Technical Support Center . Dale McCue- l 1Jeff Johns .,

4. Personne1' Control Center: To Be Announced

-- 1 Field Teams iDuano $ herman To Be Announced:

Corrective Action --Repair- Steve Werness ,

Teams and-_Inplant Survey To'Be, Announced:

. Teams ,

MedicallResponse- ;Marty Przybyski j

-Laurie Exby-Stolley ,

5. Site Security Force-  : Charles Holland '!

l

6. -Forward Command Post Brian.Dyck LJim August!

y 7.- Executive. Command Post- -To Be Announced-

8. State EOC ' Robert.Husted-1 i

i NOTE: Additional : Controller / Observer = locations 'to be identified:

later, along' ~with "Se n i o r LERF -

Controller / Observer ci assignmentse

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1 l

! 4.3 t t

a SECTION 4.3 l

CONTROLLER /0BSERVER INSTRUCTIONS l

NOTE: Controller / Observer communication paths will be established, and all Controller / Observers will be informed, prior to.the exercise.

.e ,

Public Sert' ice Company of Colorado representatives ars" assigned as '

Controllers / Observers at all key onsite and offsite exercise areas to; '

, monitor and control F05AVEX 90.

l The activities of the onsite Controllers / Observers will be

, coordinated by a Lead Exercise Controller.- 'If -unable' to reach,- '

contact the Senior Controller / Observer- in :the Technica' Support-Center (TSC).

The activities of the offsite Controllers /0F.ervers will be- .

Any -logistic

coordinated from the Forward Command Post - (FCS).

J problems / questions should be- directed - to the Senior 3 Controller / Observer at the rCP.

Message forms and simulated Control . Room iata- will be used to initiate, modify, and complete- the events' comprising the overall scenario. Selected Controllers / Observers will use the message forms-to place the scenario' events in effect tnd to trigger responses -from-the emergency response organizations. Each Controller / Observer will-4 have copies of the messages controlling the portion of the exercise i

scenario for which he/she 18 responsible.

Two kinds of messages will be used: i '

Control _ ling Messages used as a primary means of implementingLscenario events:

by announcing or placing an event in effect by . hypothesizing conditions resulting from previous actions.

Contingency i

_ Ma n9m used at the -discretion of the Contrc11ers/ Observers with the appraval of.a Lead Exercise Controller. ins order to

- maintain the scenario _ plan continuity or schedule. Contin messages are noted with.t number followed by1a capital:"C."gency

' Controlling; messages will be presented to-the designated exercise participant at the- time specified:Lin the event schedule.; =The Controller / Observer 'should follow ; up. ;withi an -; explanation: of the  :

-message and answer any questions tooensure. that.--the participant understands the message, j

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

4.3-8 Controllers / Observers will n_o t provide information to the participants regarding scenario cevelopment or resolution of problem areas. The participants are expected to obtain infortnation through their own organization and exercise their own judgement in determining response actions and problem resolution, In the event of incomplete responses, or if the participant indicates lach of knowledge of how to proceed, the Controller /0bsever will prompt the participant with necessary instructions or contingency message cards and will so note these actions on his/her critique sheets.

It is important to note that the scenario events are hyt., atical.

Any portions of the scenario depicting plant system operational transients are simulated events. No Control Room actions, or reactions involving operation of pTant . systems or. affecting generation capability, will be initiated. All exercise scenario messages are prefixed and suffixed with the words "this is a drill."

Controllers / Observers stationed at areas vital to maintaining generating capability should be especially aware and take extra precautions in issuing m sages or giving instructions regarding the scenario events.

Some exercise particip

• may insist. that certain parts of the scenario are unrealistic. The Controllers / Observers have the authority to clarify any questions regarding scenario content.

However, in some cases, it may be necessary to exercise " Controller's-prerogative" and say, "This is due to exercise requirements to prdierve the continuity and objectives of the exercise".

Prior to commencement, all telecommunications to be used by the Observers / Controllers should be tested to ensure satisfactory commun: cations are available to coordinate exercise activities.

Additionally, all Controllers / Observers will< synchronize their watches to ensure that messages are delivered at the proper time.  !

Controllers should report to their assigned location approximately 20 minutes prior to any player action.

Since some exercise activities will be conducted offsite, it is important to remember that members of the general public may observe some mon 1toring activities. Accordingly, to help alleviate any potential concerns, protective clothing will not be used outside the owner controlled area, ,

Table 4-1 provides additional 00's and DON'T's for all Controllers / Observers.

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i TABLE 4 '  !

i CONTROLLER $'/0BSERVER$' RULES j 00's t

1. Know the overell Controller / Observer Organization (section  ;

4.2). >

2. Remember that there may be two time ' designations: a scenario time and a clock time. _,

l

3. Identify _the players by name and function.- 'j

4. Identify yourself at all times to.all players. Wear' ball-  ;

caps and/or Controller / Observer tags as provided;by P50.

5. Identify the phone.(or radio for field teams) you will use to maintain communications- with the- Lead Controllers / Observers. ,

?

6. Position yourself to' maximize your effectiveness in issu.ing #

messages and observing the players.  ;

7. Be sure you understand the player's scenario script and the '

3 master scenario. l

8. Keep the play on schedule by checking your script..

, 9, . Issue the- message on time.

understand it.

Make 'sure the players- j -

V

10. Remember to call a Senior Controller / Observer or Lead-Exercise Controller. to report the status _of players'- l actions if off schedule or if in-doubt about what to do.

Call for advice if players significantly: depart from the?

j scenario script. These deviations could cause major _ delays- i or could terminate the exerciseLprematurely. If;necessary, ,

intervene with player action and put -players back on  ;

scenario track.

11. Allow the players reasonable fle'xibility to: perform their_ i functions and demonstrate their skill, knowledge, and- .

initiative.

-[,

12. Identify the federal- evaluator (s),- Make sure'they are. .!

reasonably aware of your actions.and those'of The ; players. s

13. .Make-l notes on. good an'd-bad points-of p1_ayers'f actions, the= i strengths'and weaknesses, and areas for* improvements, Use j

-the Evaluation. Sheets.

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14. ~ Attend the post-exercise critique session _to provide-your l comments-and recommendations.--

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._ ._.-_ _ _ _ _ _ _ _ . _ _ _._ _,- -. _ , ,, _;_ , ,i

4.3-4 15, Identify the players' leaders. Work with them as appropriate.

16. If a real emergency occurs and this affects the players, call off your portion of the exercise, and . notify a- Lead Exercise Controller immediately.

17. Be at your post at least 20 minutes prior to the beginning of any player actions. Set yourself up.

i

18. The federal . evaluators will not issue " surprise" messages or direct " surprise" actions at the players.. They must work through the Controller. 'This is essential for the success of the exercist.

l

• 19.. Controllers / Observers and federal evaluators, do not have ~

i to follow simulated rad'iation exposure control practices.

20. Controllers / Observers will bg -exempt from accountability i and have access to all necessary access areas. (except l security areas).

DON'T's 4

1. Don't leave your post at key times.

2. Don't prompt the players to-take action.

3. Don't coach-the players.

4. Don't criticize the players' actions'during the play.

5.- Don't forget to ' call the appropriate Senior or Lead i Controllers / Observers to seek' advice or help as necessary. ]

I

6. Don't allow external influences to distract the players.  !

No interviews with players are allowed. .

7. Don't allow simulation with respect to radiation-. protection 3 practices or when equipment-ano . facilities =are-;available. i However, don't allow any player to operate any' equipment which would impact plant operations.

i Note:

All participants will _' comply with~the radiation exposure control practices existing at the' station'at. the time of ,

the exercise . '

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4.4-1 ,

l SECTION 4.4 EMERGENCY RESPONSE FACILITY DESCRIPTIONS l

l The FSV Emergency Organization will function from a number of pre-established locations. This section of the Exercise Manual identifies the six facilities which will be activated to assess and manage the accident conditions described by the scenario. All Controllers /Coservers should become familiar with their location and response function (s).

1. Control Room (CR)

Emergency assessment and control is initially dire:ted from the CH by the Shift Supervisor prior to activation of the Technical Support Center (TSC).

The CR, located adjacent to the Reactor Building, is designed to be haoitable during Design Basis Accioents. The CR contains full plant instrumentation, technical crawings, protective breathing apparatus, radio, telephone, and intercom systems, Emergency radiological monitoring equipment and protective clothing are located nearby,

2. Technical Support Center (T'SC) '

Site emergency command activities will be centered in the Technical Support Center (TSC) located immediately adjacent to the Reactor Building and within short walking distance to the Control Room. The TSC is equipped with irrte rcoms , telephones, NRC Emergency Notification System (ENS) telephone, Health Physics Network (HPN) telephone, telecopier, and radios for

communications with the CR, Personnel Control Center (PCC), and Forward Command Post (FCP).

The TSC is equipped with a CDC-1700 terminal for visualization l of plant parameters and offsite dose calculations, essential drawings, specifications, and procedures. Radiation monitoring

( equipment, protective clothing, communications equipment, portable lighting, protective breathing apparatus, and first-aid equipment are located in Emergency Kits. -The TSC meets-habitability requirements similar to those imposed upon the CR, l

4.4-2

3. Personnel Control Center (PCC)

The primary and secondary locations for the Personnel Control Center (PCC) are the Security Administration Building and the Licensing Trailer, respectively. Emergency radiological monitoring equipment, first-aid and decontamination equipment, protective clothing, communications equipment, portable lighting and protective breathing apparatus are st.ored in emergency kits at both on. site locations. There are two designated offsite areas which may be utilized as the PCC if it becomes necessary to evacuate the onsite location (s). The preferred alternate off site location is the Johnstown County Shops. The other alternate of f site PCC location is the Platteville Volunteer Fire Department. Routes to these locations are shown in RERP Implementing Procedure RERP-PCC, Personnel Control Center Procedure.

4. Forward Command Post (FCP)

The Forward Command Post is the focal point for the coordination of onsite and of fsite emergency response activities. Management and technical personnel assigned to the FCP are responsible for protective action recommendations and liaison with offsite authorities and response facilities. The FCP serves as the point from which the Corporate Emergency Director (CED) exercises overall control of the FSV Emergency Response Organization.

The FCP has work space allocated for PSC er.ergency personnel, state and local personnel, and the NRC. The FCP is adequately equipped with an NRC ENS telephone, HPN telephone, commercial phone lines, radio, and telecopy facilities to provide efficient communications with the TSC, ECP, SEOC, NRC, and the Weld County Communications Center. Onsite-offsite communications are channelled through the TSC and FCP.

The FCP is located at the PSC Customer Service Center in Ft.

Lupton, well out of the plume exposure EPZ. The FCP will be activated and manned for an ALERT or more severe incident classification. The FCP is equipped with a CDC-1700 terminal to provide rapid access to plant parameters and to provide for off site dose calculations.

S. Executive Command Post (ECP)

The Executive Command Post (ECP) is located at the corporate headquarters building in downtown Denver. Manned by senior corporate personnel with access to other corporate. resources, the ECP provides direct augmentation to the staffing. of onsite emergency functions by non-station personnel. The staff of the ECP is responsible for obtaining additional manpower for repair / damage control teams, survey teams, access control, and logistical assistance. The ECP will normally maintain- direct communications with the FCP and sne SE00.

4.4-3

6. State Emergency Operations Center (SEOC)

The $[0C is the focal point for the state of Colorado's l emergency response effort. Essentially all coordination of state resources occurs at the SEOC. The facility is located in the basement of the Colorado National Guard Armory and Law Enforcement Training Academy, Build!ng 120, Camp George West, i Golden, Colorado. l I

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4,5 SECTION 4.5 EVALUATION SHEETS This section of the Exercise Manal provides the Observer Evaluation Sheets. Controllers /0D$ervers should remove the appropriate evaluation sheets and be sure to complete the forms as the events occur. At the conclusion of the exercise, review the evaluation sheets. These documents will be used at the exercise debriefing and the formal critique. All of the documents should be given to the lead Exercise Controller at-the conclusion of the critique.

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

Page a FOSAVEX-90 OBSERVER CHECKLIST Location: CONTROL DOOM Name:

Time Frame: to Date:

CRITERIA EVALUATION

1. ACCIDENT ASSESSMENT Control Room personnel .

rapidly and correctly I interpreted scenario related problem (s). '

Control Room personnel' knew when to refer to FSV Operating Procedures, Emergency Procedures, the RERP Plan and Implementing Procedures, and other applicable guidance. <

Plant process information

• was available when required.

Control Room Operators responded to simulated operational events and properly classified the accident condition for:

(1) NOVE (2) ALERT (3) SITE AREA EMERGENCY. -

(4)GENERALEMERGENCY-Control Room personnel assisted in determining extent of plant damage.

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Page 2 CONTROLROOMCHECKLIST(Cont.)

~ CRITERIA EVALUATION

2. ACTIVATION OF FACILITIES Control Room personnel responded to the escalating severity of ever.t s and began call-outs for activation of the Emergency Response Organization.-

The Technical Advisor was

• notified, teported to the Control Room, and provided assistance as required.

Control Room personnel aided in establishing the -

proper location of the PCC. 3 Transition of responsibilities, as plant conditions e degraded, was effectively executed.

3. NOTIFICATION / COMMUNICATION Notifications to State / Federal authorities were timely; and properly completed per RERP-NOTIFICATION for:

(1) NOVE (2) ALERT (3) SITE AREA EMERGENCY (4) GENERAL EMERGENCY All notifications were verified and logged per proper procedures.

Communication networks-were operational and ef ficiently utilized.

Page 3 CONTROLROOMCHECKLIST(Cont.)

CRITThlA EVALUATION Communication flow was aceavate to ensure that information was timely and accurate.

Phone lists were available and complete.

General status announcements were made and updated periodically u by the $hift

$vpervisor/ Control Room

. Director.

, Logs were maintained.

Data flow between the Control Room and TSC was raintained.

Ambient noise level in the Control Room was not a problem. <

There was no interaction / confusion l

between CR operating personnel. "CR Players" CR Controllers / Observers.

Transfer of information within the Control Room was clearly and completely understood.

4 ORGANIZATION CONTROL The Shift Supervisor-in conjunction with other l Control Room persennel i evaluated the plant L conditions and implemented appropriate response actions.

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Page 4 CONTROL ROOM CHECKLIST (Cont.)

CRITERIA EVALUATION The Shift Supervisor took over management control per the RERP Plan and procedures.

Transfer of control between the Shift Supervisor (acting as the Emergency Coordinator) and the Control Room Director was effective ,

and in accordance with procedures.

The proper management chain of command was followed throughout the exercise.

Emergency control and authority were effectively transferred from the Control Room to the TSC. .

Transfer and control of '

authority were announced and logged.

5. HEALTH PHYSICS / SECURITY The Shift Supervisor performed and maintained Control Room accountability per Procedure G-5.

Control Room! habitability was monitored. '

Access to the Control Room was controlled per appropriate procedures.

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Page 5 CONTROLROOMCHECKLIST(Cont.)

CRITERIA EVALVATION

6. PROTECTIVE AftIONS/ MEDICAL Control Room personnel supported the FSV emergency organization in developing and recommending protective actions.

Supplies such as

• respirators, protective clothing, etc. were available to Control Room personnel. .

HP personnel were available to Control Room

• personnel as needed.

Shift Supervisor requested medical transportation services.

Shift Supervisor notified hospital of victim's pending arrival and provided details of injury / contamination.

Shift Supervisor notified appropriate PSC management personnel per the FSV Medical Emergency Plan / procedure.

Shift Supervisor was periodically notified of victim's status -

information relayed to TSC Director.

Shift Supervisor notified the Lead Security Officer (L50) of medical transportation arrangements.

Page 1 F0$AVEX-90 OBSERVER CHECKLIST Location: TECHNICAL SUPPORT CENTER Name:

Time Frame: to Date:

CRITERIA EVALUATION

1. ACCIDENT ASSESSMENT Plant process information was available when required.

TSC personnel responded

+e simulated events and properly classified the accident conoition tor:

SITE AREA EMERGENCY GENERAL EMERGENCY TSC personnel assisted in ,

determining the extent of plant damage.

2, ACTIVATION OF FACILITIES

The first person arriving at the TSC verified habitability and began TSC activation.

The first management individual verified that habitability was checked-and that all communication systems were operable.

The TSC was activated in accordance with RERP-TSC.

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Page 2 TSC CHECKLIST (Cont.)

4 CRITERIA EVALVATION All copies of the Emergency Plan, Procedures, Updated Safety Analysis Report, Tech. Specs., drawings, etc. were available for TSC personnel, r

3. NOTIFICATION / COMMUNICATION Communications with ,,

Control Room was established. Primary and secondary communication links were available.

Communications with the Personnel Control Center (PCC) and the Forward Command Post (FCP) were established.

Plant status and/or-radiation parameters ,

needed to determine existing conditions were available via Status Boards. Status Boards I were updated as required.

Information regarding mejor changes in plant status was disseminatad i to key personnel effectively.

Information relative to Protective ' Action Recommendations was disseminated to key personnel effectively.

Communication with onsite monitoring teams were effective. ,

Logs were maintained.

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

Page 3 -

TSC CHECKLIST (Cont.)

CRITERIA EVALUATION Ambient noise level in TSC was not a problem.

Transfer of scenario information within the -

ISC was clearly and completely understood.

4. ORGANIZATIONAL CONTROL Transfer of command from .

the Control Room was effective.

Transfer of command from the TSC to the Forward Command Post was effective.

The proper management chain of command was followed throughout the exercise.

Transfer and control of authority was announced

! dnd logged.

l l

Per RERP-TSC, the TSC i Director assumed overall responsibility for the coordination and direction of the opsite

)

emergency- response '

centers.

The TSC Director I

i recommended de-escalation-or initiation of post-

, emergency recovery I efforts in a timely manner; per the RERP (Sections 4 or 9).

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l Page 4 TSC CHECKLIST (Cont.)

~~~

I CRITERIA EVALVATION If required, the TSC Director requested additional support from the Corporate Emergency Director.

Radiological, Engineering, and Administrative personnel coordinated their activities effectively. *

5. HEALTH PHYSICS / SECURITY i HP coverage in TSC (air sampling instrumentation and dosimetry) was adequate.

Initial accountability and continued accountability was performed satisf actorily.

l In plant Radiation Monitoring was coerdinated with TSC.

Offsite dose assessment evaluations were conducted per procedures (RERP-DOSE).

Initial and subsequent dose calculations were performed in a timely manner.

Computing aids were properly utilized.

Exposure plume was well defined and tracked.

Communications with monitoring teams were maintained.

Page 5 TSC CHECKLIST (Cont.)

~~

CRITERIA CVALVATION Dose Assessment Team Leader ensured comparisons between projected and actual field measurements were made.

Field survey teams were provided sufficient information to perform duties. .

Coordination of HP criteria for exposure control with TSC Director was effective.

TSC HP personnel considered implementing RERP-THYR 010.

TSC HP personnel obtained airborne contamination and radiation survey: in ,

the Control Room and informed TSC Director or results.

TSC HP personnel coordinated activities with the Protective Measures Manager at the FCP, 6, PROTECTIVE ACTION TSC HP personnel coordinated activities with- the "$C Director and l Dose Assessment personnel.

Protective eouipment and associated supplies were available to TSC personne!,

4

i Page 1 FOSAVEX-90 OBSERVER CHECKLIST Name:

Location: PERSONNEL CONTROL CENTER Time Frame: to Date:

EkJTERIA EVALUATION

1. ACCIDENT ASSESSMENT e

Emergency Inplant Repair Teams were dispatched effectively.

Repair tsams evaluated the extent of plant damage and reported information to PCC and TSC personnel.

2. ACTIVATION OF FACILITIES The proposed location of ,

the PCC was known by all personnel.

Access to the PCC was well established arid did not hinder activation.

The PCC was activated in a timely and orderly taa nne r .

PCC staffing was adequate, and met the needs of the emergency organization.

The PCC was activated per RERP-PCC.

3, NOTI FICATION/ COMMUNIC ATION .

L Communication with the TSC or Control Room was l adequate.

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Page 2 PCC CHECKLIST (Cont.)

CRIT [RIA EVALVATION Primary and secondary communication links with the TSC were available - I constant communication with TSC existed.

Communication links with onsite and offsite -teams was adequate.

Team briefings (priorto

• dispatch) were adequate.

Prior to dispatching teams -

the TSC HP Coordinator and the TSC Director were consulted.

Individuals living on plant troperty were notified.

TSC was notified of need to transport < -

injured / contaminated personnel offsite.

St. Luke's Hospital was properly notified of the medical situation.

Detailed logs were maintained.

Plant. status and emergtncy assessment information was readily l available to PCC -

personnel.

4 ORGANIZATIONAL CONTROL l The PCC Director adequately supervised the activities of the PCC.

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Page 3 PCC CHECKLIST (Cont.)

~ CRITERIA EVALUATION The PCC Director coordinated activities with the TSC Director.

The PCC Director utilized the checklist in RERP-PCC.

An effective chain of command was established.

Team formation and briefings were completed Quickly and accurately (see RERP-PCC).

5. , HEALTH PHYSICS / SECURITY HP coverage in PCC was adequate.

The Lead Security Officer (LS0) dispected a security guard to the ,

PCC; access was controlled.

PCC Director coordinated access to/from the protected area with the LSO.

Accountability was initially established and maintained throughout the emergency. ,

Habitability was initially established and ,

verified as appropriate 1 throughout the emergency.

Appropriate briefing sheets were used to inform teams of potential radiological areas.

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9 Page 4 PCCCHECKLIST(Cont.)

CRITERIA EVALVATION Maximum stay times were established .and relayed to survey / repair teams, An HP was assigned to each team.

6. PROTECTIVE ACTION Protective equipment, clothing, decon- .

facilities, and associated supplies wer)

. available to PCC personnel. Specialized tools and equipment were ,

available,

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FOSAVEX-90 i OBSERVER CHECKLIST i

t e t

Location: FORWARD COMMAND POSTJ Name:  ;

e

Time-Frame

to- -, Date: ,

p t

CRITERIA EVALVATION i-1, ACCIDENT ASSESSMENT

. FCP personnel coordinated i

Accident Assessment activities with TSC personnel.

2. ACTIVATION OF FACILITIES L FCP was activated and '

i manned within a >

i reasonable time after declaration of an ALERT' .-

Corporate- Emergency .,

Director received briefing from TSC i Director- prior to i assuming command and control. .

FCP personnel informed of

-assumption =aof specific responsibilities.

.Facsimili machines-functioned -properly,:

status boards. were available.-

Emergency _ Plan and ..

Implement _ Procedures, '

Tech. ' Specs.. etc. were available in current and  ;

controlled copies, l y

Activation: per RERP-FCP '

was .

accomplishedt effectively.  ;

. = _ _ - - - - - .

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Page 2 FCPCHECKLIST(Cont.)

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CRIThilA EVALVATION 3, NOTIFICATION / COMMUNICATION Communications were i established with the TSC; both primary (telephone) and secondary (radio) commuaication lines were established- and maintained.

Communications with the e Executive Command Post (ECP) and the State Emergency Operations Center (SEOC) were established and maintained.

TSC notified FCP of

• location and status of PCC.

Notification / Communication ,

between PSC, local, and <

State agencies was effective.

Needed data was available from TSC and CR.

FCP received prompt information on radiological status, both l- on and off site.

Pertinent information was quickly (15 minutes) transmitted to offsite-l groups.

Up-to-date meteorological data was available.

Plant status information was promptly available; status boards used and=

kept current.

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Page 3 FCP CHECKLIST (Cont.)

CRITERIA EVALVATION Communication with offsite monitoring teams was adequate.

General status announcements and updates were made to FCP personnel throughout the exercise.

FCP coordinated the ,

supply of information to ECP Media Relations personnel, the FCP Public Information Team had sufficient information (and facilities) to prepare and release news and related media releases.

Development and .

presentation of initisi media briefing was effective.

Development and release of initial press release were effective.

Development and release of follow-up briefings and releases was effective.

Necessary documents (logs, etc.) were maintained.

! FCP/ECP- interface effective.

Effective rumor control methods were employed.

Page 4 FCPCHECKLIST(Cont.)

CRITERIA EVALVATION Spokespersons were knowledgeable about ,

technical aspects of plant problems.

4. ORGANIZATIONAL CONTROL The organizational structure and chain of command in FCP was clear.

Appropriate people made prompt decisions and recommendations.

Status boards were kept current.

Plume pathway was tracked i and visil'.y displayed.

Emergency classifications and action level notifications transmitted ,

to proper authorities as required.

The Corporate Emergency Director (CED) utilized the appropriate RERP procedures efficiently.

The CED ensured-continuity of. emergency resources throughout the-exercise.

The CED ensured adequate administrative, technical and logistical support was available.

l Plant status updates to

! the ECP and SEOC were l effective. .

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Page 5 FCP CHECKLIST (Cont.)

CRITERIA EVALVATION The CED provsded direction to, and coordination for, the TSC Director.

The CED coordinated activities with state / local response personnel.

The CED, in conjunction ,

with other emergency response personnel, ,

de-escalated the Emergency Category according to plant conditions.

S. HEALTH PHYSIC'o/ SECURITY -

Only assigned FCP people were present.

Security Control was ,

l established and l maintained.

Computer aids were properly utilized.

Plume was defined and l tracked.

Coordination with TSC -

Dose Assessment team was effective.

Vse of Radiological Status Boards was efiective.

6. PROTECTIVE ACTIONS Protective Measures Manager /CED interface on Protective Action Recommendations was timely and effective.

.t Page 6 FCP CHECKLIST (Cont.)

CRITERIA EVALUATION Protective action recommendations to the State were made clearly and in timely fashion.

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- Page-15

. FOSAVEX - 0BSERVER CHECKLIST 4

1 Location: EXECUTIVE COMMAND POST.  ; Name:!

Time Frame: to Date: -i CRITERJ. A. - EVALUATION  :[

t l.

-ACCIDENT ASSESSMENT-

.ECPpersonnelcoordinatedL  !

accident assessment-activities with FCP-

. personnel, i 2,  : ACTIVATION OF FACILITIES The ECP-was activated-in

-a timely manner. -

The ECP was staffed in a-timely fashion. .

a :

j

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Information was received

-quickly from =the- FCP ancror.TSC,. 1 The- ECP Director

• performed , ' personnel:

accountability to-assure.

-that. sufficient manpower was available to' staff the ECP.

Activation per):RERP-ECP; wasl .

~ accomplished: -

effectively.

13, NOTIFICATIO$/COMMUNICATIONi Established and maintained:. communication- .

with:the FCP.. .!

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u Page12 ECP CHECKLIST (Cont.)4

'. p CRITERIA EVALUATION ~

r

.The Manager , of -: Media ; ,

-Relations assisted. the ECP Director. and: PSC-Media Relations personnel.

in preparing _ press.

releases, announcements,; ,

vi E and interviews,-

Rumor control. methods were used effectively.

1.- i Use of. status boards was' .]

effective,. =-

~

4.- ORGANIZATIONAL CONTROL

.1 The ECP Director assumed q

control of the ECP, ,

Major decisions were made- 'l by the ECp Director,o his ,t staff and the Corporate Emergency Director-(CED), _-

4

- o Tne CED was provided with required support.

The . onsite - emergency organization- was.

supported as required.

Security operations were coordinatedL.with public. '

law enforcement agencies. 4 Additional- .-security.

provided asiroquired, 5, HEALTH PHYSICS / SECURITY Only -persons- with-

. assigned emergency: a responsibilitied were permitted in the CCD.

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i Page 3 ECP CHECKLIST (Cont.)

CRITERIA -EVALUATION ECP personnel were aware of monitoring team activities being coordinated from FCP/TSC/PCC.

ECP personnel were appraised on the. medical emergency and the status of the victim.

C PROTECTIVE ACTIONS

. ECP personnel-were aware of recommendations being made at FCP.

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Page 1 FOSAVEX-90 0BSERVER CHECKLIST Location: STATE EMERGENCY OPERATIONS CENTER Name:

Time Frame: to Date: i CRITERIA EVALUATION

1. ACCIDENT ASSESSMENT SEOC personnel coordinated accident assessment with FCP personnel.

2. ACTIVATION OF FACILITIES PSC representatives performed accountability to ensure adequate staffing.

Established .,

communications with FCP informing them SEOC was ,

manned.

Activation per RERP-SEOC was effectively accomplished.

Information flow between FCP/SEOC was effective.

3.

NOTIFICATION / COMMUNICATION Establ!shed and maintained communications with FCP.

Maintained communications with SEOC representatives.

Rumor control methods were employed.

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_.4

SEOCCHECKLIST/(Cont l) I CRITERIA- EVALUATION :

t Use of status: boards,i meetings, and briefings-was effective.

Proper media coordination-was established, Logs were maintained. i' Up-to-date site N ~

information was..provided- La to Public Information Coordination Team.

'4. ORGANIZATIONAL CONTROL; t

PSC representatives. '

coordinated PSC emergency '

response activities with ,

those of State / local officials, PSC technical' assistance '

e was available asirequired e

-to - support State / local  !

representatives, a" PSC coordinated.

activities associated with news. ' releases, background ' ma t e r.i a l ,

rumorcontroJ,etc. $

- 5, HEALTH PHYSICS / SECURITY- 4 i

1 SEOC personnelcwere awareL of_monitoringLfactivities! .

occurringLonsite/offsite.; '

i

-6.- PROTECTIVE ACTIONS-

• a SEOCLpersonnel'were aware l m 4 of-PARS being made atLthe -

^1 FCP, SEOC personnel'were aware of-PAR status.

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, .Page01

-FOSAVEX-90. ..

f 0BSERVER CHECKLIST-  :

~!

I Location: FORT, ST, VRAIN SECURITY AREAS i Name:

t Time Frame:- to Date: '

CRITERIA EVALUATION j

-i

. i.

I. ACCIDENT ASSESSMENT i

'Se.arityL. . -Officers..

recognized, the severity of .the event - and took-

appropriate; actions _ per, the FSV security Plan, '

2. ACTIVATION OF FACILITIES All security facilities-were properly manned, ,

All- security personnel' .

were aware .of appropriate- +

radiological conditions,

. including'N0 SM0 KING,- NO

.{

1 EATING, NO DRINKING during: radiological- ,

conditions, ,

i

'i

3. NOTIFICATION / COMMUNICATION l Communications were __

established -and! '

maintained throughout the. I security force, 4, 90RGANIZATIONAL CONTROL; The . Lead Security' Officer i effectively' coordinated the Security Force-during l emergency" conditions.

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Page 2-

-SECURITY FORCE CHECKLIST (Cont.)-

CRITERIA -EVALUATION

5. ACCOUNTABILITY CAS/SAS personnel effectively conducted and reported accountability events to the Emergency Coordinator.

SG-05 was completed accurately, ff f

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Page t  !

-FOSAVEX-90-1 1 OBSERVER CHECKLIST -!

i Location:--ONSITELRADIOLOGICAL Name: 1 MONITORING _

i Time Frame: to - Date: ,

CRITERIA > EVALVATION-Onsite monitoring- ,>-

equipment was easily-accessible::and properly i

. distributed. ,

1 Equipment was checked for proper operability prior to its use, Actions by the- Onsite' Monitoring Teams to make:

initial surveys -outside the plant buildings land ,

perimeter- fence ' were r

- correct, cAs appropriate, the TSC HP Coordinator was notified.

Standard HP practices were employed--'for . entry

.into actual oripotential radiation areas.

Proper survey records,. I dosimetry, stay time,-

etc. were maintained during; entry.

Survey- results -

were reported. .to the-appropriate. personnel._in the TSC/PCC, Follow-up. actions were takenton survey- results.

, 4 1

-t lPage 2~

ONSITE- TEAM CHECKLIST '(Conti):

A 3 -

CRITERIA-

-EVALUATION--

- , c Pocket- dosimeters Were .

-frequentli chec ked -. andl

-properly logged. 1 Team members _had adequate understanding- of.- proper .j' utilization of' equipment:

(survey instruments, - ,

radios,;SCBA's,etc.). '

survey .results

~

>Inplant 3. a were- _. systematically ~ .

collected; appropriate- ,

1 datasheets of J,ERP-SURVEY

-were used.

The correct procedure was-

- used -to establish  ;

emergency dose limits if j needed.

Authorization -to exceed ~ t 10CFR20 ' Exposure Limits was documented. . .<-

1-1 Use- of- ysurvey. and decontamination techniques: at designated

contrcl point :priorg to

. entry'into the PCC,

-Debriefing . conducted, _

-i

-records . and -

logs- ,

j collected-- -

LAppropriate radiological! ,

data- were' available to

~

H the teams as neededc l >

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- FOSAVEX 1 OBSERVER CHECKLIST Location: '0FFSITE MONITORING! TEAMS -Name .

Time Frame: Date:

to f

CRITERIA - EVALUATION-i Initial team briefings-  :

were held.- (See .,

RERP-PCC).

. Teams . assembled. with . ,

field kits, vehicles,' and ,

communications equipment in a timely manner.

Contents of . the Field - s Trucks were -checked before leaving site.'(See

• RERP-FIELD) m , ,

Instruments checked for T '

,- / .

L proper operability and c-i current calibration. (See ~

RERP-FIELD)'-

J Teams received explicit: '

instructions-as to where to go and what-to sample, Teams found' sampling locations easily. , ,

Procedures for conducting = *

-'offsite ' monitoring 'were -  ;

- consulted and followed-- .

' Vehicles - were readily--

~

available.

-i for

. Vehicles- checked , ,

contamination- after =  ;

survey was completed.

Sampling- locations' were ~

, i readily located;

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Page 2 OFFSII'E TFAM CHECKLIST-(Cont.)

~l CRITERIA EVALVATION Samples were properly packaged, identified, and labeled.

Appropriate documentation I was maintained, Pocket dosimeters were  ;

periodically checked. '

Use of respirator .

equipment and personnel monitoring was appropriate.  ;

Pocket dosimeter readings were logged in upon '

return to PCC.

Communications were maintained with the TSC and/or PCC throughout sampl.ng activity.

Coordination with state field teams was  :

1 effective, i l

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Page 1 FOSAVEX-90 OBSERVER CHECKLIST Location

CORRECTIVE ACTION (REPAIR) Name:

TEAMS <

Time Frame: to Date:

CRITERIA EVALUATION Need for Repair Team a established; activities-coordinated.

Team . members briefed in accordance with RERP-PCC and RERP-TEAMS.

Safety and first aid equipment available as needed.

Team accountability was maintained. ,

Radio checks performed.

Communications maintained during repair activities.

Log of activities kept.

Debriefing conducted, records and log collected.

As applicable, RERP-EXP was followed by repsir team.

Personal dosimetry used, if needed, l

l l TSC informed of results, l

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Page:11 _

FOSAVEX-90: ..  !

OBSERVER.CHECKLISTz ~

n

.)

Location: FIRST AID / SEARCH AND-RESCUE- Name:

AT-FSV- #

Time. Frame: to- Da't e :-

.i CRITERIA. EVALUATION t t

j An EMT was--asked: to. ~ i..

assist; and the: Firet j Brigade or First Aid Team-L assembly was timely '

I following notification. ' '

q-Fire Brigade /First Aid '

' Team assembled with the '

proper first aid '

O equipment. .

Accident / injury ..

assessment' made by t he.-

Fire- Brigade /First Aid . < . i Team,

- t+

. h.

Level and -- extent- of contamination- was properlyidetermined. -l

, Decontamination measures 1 were_ . Ltaken, -i f i L

, appropriate.

. Maintained communications l with1 Controll Room--(via v

radio: or 'Gaitronics'). ' j c

E ..

1The HP- escort-' reacted- .

T properly to the simulated- - -

n event. ,

n The. ' request for-transportation by :the Shift ' Supervisor was~-in

~

i accordance 'with '

procedures. '

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Page 2 FIRST AID / SEARCH AND RESCUE AT FSV (Cont.)

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i CRITERIA EVALVATION  !

1 i

Patient was made ready ,

i l for transport by the Fire Brigade /First Aid Team.

1

! Appropriate methods were used to identify victim, t

the extent of injuries, contamination levels and locations, first aid administered, etc.

~  !

Periodic status reports were proviued to the '

. Shift Supervisor regarding the injured individual's status, l

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1 1

5.0 .

i SECTION 5.0 EXERCISE SCENARIO _

Section .

5.1 Narrative Summary.

5,2 Initial Conditions 5.3 Detailed Scenario a

5.4 Scenario Time Line I

f e

9 5.1-1 s

L FOSAVEX-90 NARRATIVE

SUMMARY

I FOSAVEX-90 has been designed to test the emergency organization

) in a number of different ways. It will begin during normal working hours with limited State and local participation expected, Fuel Deck personnel are-in the process of lowering a spent fuel l shipping cask loaded with six region 34 spent fuel elements to I

the truck bay trailer located on level 5 of the Reactor Building.

! While the cask is still on level 11 Refueling Floor, hanging over the truck bay, the Turbine Building Train Bay Doors are opened.

The sudden large temperature reduction, due to the extremely cold-outdoor temperature, causes the deluge system for the Unit Auxiliary Transformer (UAT), Reserve Auxi,liary Transformer (RAT),

and the Main Transformer to operate. This in turn causes flooding of a junction box on the north side of the RAT-resulting in damage to control wiring and terminal boards. Tripping of the RAT produces a-loss of offsite electrical power (L0EP) (TI). - A few minutes after the LOEP, Control Room personnel receive a report from the fuel deck that the spent fuel shipping cask is suspended over the truck bay with no power to the Reactor Building crane. The crane is powered from non-essential 480 VAC Bus No. 4. A Notification of Unusual Event should be declared due to a loss of offiste power or onsite AC power capability (C11.8).

Upon automatic initiation, "B'i Diesel Generptor starts and immediately trips on overspeed (electrical control power to the governor malfunction). "A" Diesel Generator automatically starts, its output breaker is automatically closed, energizing l 480 VAC Essential Bus No. 1 and the Bus 1 - Bus 2 tiebreaker-automatically closes. However, service water pump 1A malfunctions and is not automatically started by the load sequencer. Therefore, "A" Diesel Generator is operating with no cooling to- its heat exchangers.

In this condition, firewater should be automatically introduced to "A" Diesel Generator heat exchangers, but the operator on the pressure reduction firewater valve (PCV-4266) has separated from the valve stem and does not open, causing "A"-Diesel Generator to trip on high temperature 5 i

minutes after initiation (T1+:05). "A" Diesel Generator can not be restored until it has sufficiently cooled down so that the high temperature trip resets. PCV-4266 must first be repaired in order to assure proper cooling. The repair action on PCV-4266 and cooling of "A" Diesel Generator will require approximately 45 l minutes. The Control Room should declare an ALERT due to loss of

)

offsite electrical power and vital AC power for up to 30 minutes-i (C11.3).

5.1-2L

" t" Diesel Generator: will be' restarted within approximately;45 m'nutes (T1+i45) and the junction box- on the RAT will be repaired, allowing offsite power res_toration , _w ithin an-hour (TI+1:00). This in turn will allow recovery of 46 system cooling' a.td restart of a helium circulator-approximately-15 minutes after offsite power recovery. Fuel Deck operations will resume shortly; ,

after, depending- upon performance of site accountability during the L0EP.

Once Fuel' Deck - operations are- resumed, the - Fuel- Deck Cranc Operator commences lowering of the loaded spent _ fuel, Lshipping cask. The scissors _on the crane had not engaged properly and <

when movement is initiated, the. loaded cask free falls -from' the Refueling Floor to- the-Reactor Building Sump Key Way, smashing-the truck bay trailer and level. 5 concrete floor plug on its' way-down (T2). The sump key way contains approximately 1 foot of water. Control Room personnel hear a . loud noise and movement zis felt, resulting in:the operation of the s,eismic recorder.

~0pon landing, the cask ruptures dispersing =all 6 fuel elements into the pit. The fuel elements are damaged but remain somewhat i

intact. No: criticality occurs as-the elements are-spread out.

However, hydrolysis of the.. failed _ fuel particles does occur over a two hour time. period. _All noble gas'is released all.1-131 has previously decayed away, and the solid fission products remain in' the fuel particies with -the exceptioniof a-small' amount which

• escape and contaminate the water in the pit -

Area radiation monitors in- the Control-Room alarm. Within 5' minutes, the Control Room receives- a report. from Fuel Deck ,

personnel that the shipping cask _has fallen through level 5 and that there may be some' injured victims in: the truck _ bay.=

Accountability should be performed at this time, if..notLalready done so, and a SITE AREA EMERGENCY declared due-t'o1 major damage ,

to spent fuel due to severe cask damage-resulting in release-of?

radioactivity to plant environs (C6.3).

Two persons weres located in the level 5 truck bay area'when the-cask disengaged and fell, injuring both parties. . Search -and rescue operations will have to be. performed as well as.first' aid measures for contaminated individuals.

The exercise will continue to the pointLthat emergency response-personnel are discussing long term recovery actions,'.i.e.,

re noval of the fuel blocks from. the Key Way,_. removal of_the contaminated Key Way water, plant' clean up, etc.

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

-1 ~

5 . 2- 1 --

lI

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FOSAVEX-90!-

y

)

-1 INITIAL-CONDITIONS:

y Outside. temperature: -20 *F 1

-Defueling and sh'ipping acti_vities'in progress,.

.t Loop 2_46 system in' operation :

Loop 1 46 system 00S for' surveillance testing.1 _ 'i Loop 2 46 system pump,'.P-46025,-cleared.out - -

ACM torn! apart for maintenance.: .,.>

l Main transformer 005 for maintenance fhouse power offithe(RAT 4

~

The. reactor -has :been shutdown for .400- days. : 1 l

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

I L

-DESCRIPTION OF.

NEDICAL EMERGENCIES PERSONNEL CONTROL CENTER VICTIM:- - I r

Insulin Shock:

Signs and Symptoms.of Insulin Shock -

l 1. Normal Breathing Respirations of 12. _

2. Full, Rapid Pulse Pulse of 94  !

l 3. Moist, Pale' Skin. B/P 140/85- 3

4. Headache, Dizziness 5.-Severe Hunger Pangs

6. Shaking, Trembling

7. Disorientation, Fainting. Seizures -

8. Coma The victim is in the PCC when he/she begins experiencing-the above1 signs and:

symptoms. . Insulin 1 shock patients-are often mistaken _for someone suffering from:

alcohol intoxication. Insulin shock is a life-and-death emergency, i

TRUCK BAY-VICTIMS:

First-Victim -

~

Victim is face down and unconscious onLthe bed'of.the' tractor. The victim-is having difficulty breathing :There is a.small amount ofl blood coming L

from the victim's left ear.and'a small indentation:on-the left side of-the victim's head. TheLvictim is LOC x 00 ;His pupils: are dilated:and -

non-responsive. There is no responsetto pain'..

.Second Victim -

~

'The victim-is face'down.and. semi-conscious-beside the trai1er. His:right-arm appears:to be broken,at the elbow. cThere'is a largetgash:above?the: ,

Victim's!right: eye. Thel victim is :very- shocky and ~has lost 'a large amount

-of. blood. 'The victim is LOC'x.1. The respirations'are rapid'and= shallow, '

pulsefis 125, blood ~ pressure is__150/90. '

[

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.L 5.3 A11

~~--.l. ,

FOSAVEX -

I DETAILED SCENARIO-

. Rea'l Emergency

-Event Time = -Class-~ xi Controller briefing ,-0730; ,

Controllers at' assigned stations- '0800 j Train Bay Doors are opened causing 1 0830 NOVE deluge system to fire and~ damage-RAT resulting--in a Loss of Offsite Electrical Power.-(TI)- 3 "B" Diesel Generator starts and T1 *

.immediately. trips on overspeed..

A report is received from the. T1+:02 Fuel Deck that a loaded spent <

fuel shipping cask:1's-suspended ,

'over the truck bay with nc power ,

to the crane.

"A" Diesel Generator trips on- ;T1+:05-

'high temperature; O;

. I 't .

Operator on PCV-4266 is separated _ -T1+:05 .i from valve stem and must be-repaired'in order to ensure sufficient-cooling to "A" DG, LOEP has been sustainedLfor_up to: _

.T1+:30: ALERTi 30 minutes.

PCV-4266,has been repaired. "A" DG: :T1+:45 can be restarted.'

The' junction box- on the RAT has

~

J--

T1+1iOO-been repaired and--offsite power.

can be restored.

System __46 PCRV'l_iner cooling and?

T1+1:15:

a helium circulator have been recovered.

-Fuel Deck operations are resumed. T1+1:30

15.3 i Event Real

- Time'

. Emergency Class j J Loaded cask ~freeifalls from the, - T2 SAE I Refueling floor to the Reactor '

Building Sump. Key Way. .

1

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Control Room personnel l hear:a loud T2-noise and movement ofrthe building 3 is felt. Seismic recorder operates.

Area Raciation Monitors' alarm. Site-accountability: should be: performed.

~

Control Room receives a-report.from-. 72+ 01t ,

the Fuel-Deck that the cask.has fallen' and there may.be: injured parties o,n=

level 5<in.the. truck bay.

Search and rescue as' well' ast first T2+:3'; 0 ,

aid treatment for. contaminated / injured-victims must be performed.

Hydrolysis of the' fuel is complete. T2+2iOO Release of radioactivity will end. 3 Technt:al-evaluation will continue.

No new events will: occur'.. However, -

data will continue to be provided.

~

Emergency response-personne1:are , T2++- . Site objectives' to the point.of discussing llong -met.

- recovery actions. FOSAVEX-90-will-be' concluded.,

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. SCENARIO TIME. LINE:

FOSAVEX -

g

, s

.0830- T1; NOUE -? Train Bay Doors are opened.>.- Deluge: system; J.! i re . RAT damagediresultingfin a LOEPA "B" D/G statts:and1immediatelyJ trips on.

0830- T1 Ji overspeed..

0832 Tl+ 02; - Fuel D0ckcreports loss offpowerito.therReactorJ _

Bldg crane with a~suspendedctuelcs hipping;caski-0835 Tl+:05 "A"?D/G trips ^on high? temperature.x PCV-4266

-operator separated-from valve stem.; Valve must; be repaired.: -

'i 0900 T1+:30 ALERT- - LOEP sustained for thirty minutes. 4 4

~0915 T1-:45 - PCV-4266' repaired. "A"_D/GLrestarted..

0930 T1-1:00 - Offsite electrical. power restored.

^

. T1-1:n Fuel Deck. operations? resumed.

- Loaded cask disengages-from crane and-falls too

~

T2 SAE

. Level?1 Sump KeytWay. ,

~T2 -ControlRoom'personnellheara^.ioudnoise~and:

l feel movement'of the buildingJArea radiations' monitors alarm.: Perform site! accountability.;

T2+:01 ' Control Room?rebelves report'that4 shipping' cask

has~ fallen.--

t T2+:  : Search and Rescue Team must' be ' dispatched toLaid: I

' injured victims.1 > - -

1T2+2:00 -iHydrolysis:of:the'fuelMis complete.rNo.-newJevents willLoccur. Technical: evaluation vill 4 continue.-

or T2++- - Leergency:: Response personnel _are totthe pointfof 1 -

discussing long' term recovery actions. FOSAVEX-90

-concluded. .

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FOSAVEX-90

. PAGE:5--

- SCENARIO TIME: va e e%45

CLOCK TIME:'-

1RpARYAUXILIARIES'

..........................**** BOARD I-13 ********************************

PENETRATION INTERSPACE-aP  : 0'PSIO. ,

REACTOR BUILDING SUMP DISCHARGE FLOW- 0/GrM' -,

- HELIUM CIRCULATORS System 21 l NORMAL-

- ...................********** BOARD.!-15 *****************************"**

j

. REACTOR BUILDING STACK. FLOW , -29.9-KCFM-REACTOR BUILDING AMBIENT AP- -0,25 Inches H2O-CONTROL ROOM TEMPERATURE 75- F- t y

..............................B0ARDI-7507X""*"""*"*""*"*"""

1

~

480V ROOM TEMPERATURE-~

' = 75:'F '

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6.0-1 x

SECTION 6.0 SCENARIO DATA PACKAGE

• t o Plant Messages o Offsite Messages o Plant Parameters ,,

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EOSAVEX-90; t

FOR: Contral Room Operators' MESSAGE NO.

LOCATION: control Room SCENARIO TIME:. T1 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS-IS A DRILL  !

00 NOT: INITIATE ACTIONS AFFECTING. NORMAL PLANT OPERATIONSi I

XXXXXXXXXXXXXXXXXXXXXXXXXXXXxXXXXXxXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX.X.XXXXXXXX MESSAGEi The following alarms-sound: ,

AuN. Trans. Fire-I'-06 H-2-5

.I-06 E 4-4 Trs f er - Rel at- Trip'-

I-06 E 3 -4KV Bus Undervoltage I-06 E 4-6 Aux Trefmr .Undrvltg.

I-06 E 5-6 Trafr~Lossiof? Power-I-06 E 3-7 '480 V Bus Undrvlt:

I-06 E 3-4 AuxiTrsfmr TroubleL I F 1-2 'Stdby-Diesel' Trouble I-06 F 2-3 Stdby Diesel Fail to. Start '

I-06 .F. l3-2 ' . Gen--1B Eng IC_Gng. 1D Troub1_e

'.i 4

xxxxxXxxXxxXXxxxxxxxxxxXxXxXXXXXXXxxxxxxxxxXxxxxxxxxxxxxxXxxxxxxxxxxxXxxXxt i

THIS(ISA.0RILLE XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXxXXXXXXXXXXXxXXXXXXXXXXXXXXXXX 4

.1

-j r

F05AVEX-901 a

p CONTROLLER:INFORMATION ONLY.

. {

LOCATION: FOR TE COURORER AM SCENARIO TIMEi XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX-

. ~i THIS IS A ORILL, _;

DO NOT-INITIATE ACTIONS AFFECTING NORMAL-PLANT OPERATIONS- ,

-XXXXXXXXXXXXXXXXXXXXXYLXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX-

' MESSAGE: ,

1 The foll?> wing alarms sound: . 1 I-06 Mc2-5' Aux.=Trans. Fire l I-00 E 4-4 Trsfmr. Relay Trip--

I.06 E 3-6 4KV Bus Undervoltage' j I-06 .E-4-6 Aux Trstmr Undrvltg- >

I-06~ E 5-6 Traft: Loss of Power I-06 E 3-7: 480 V?Bu's Undrylt I E 3"4 ' Aux Trstmr Trouble I-06 .F 1-2' Stdby' Diesel 1 Trouble i I-06 F ' 2 - 3' Stdby-Diecel.Fai-1 to' Start; j

' Gen 1B Eng 1CiEng 1D~ Trouble I-06 - F.3-2 t

. EXPECTED ACTIONS:

a

-Operators should survey electricallpanelcindicationo'to dstqrmi, i the status-of 4160KV and 480V buses. 1 Dispatch-Equipment.np-:a i n investigate B= diesel generatorVand-. Aux. Tender;tu-investigate / isolate deluge' fir.ing system.:

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i XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A ORILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX R r

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FOSAVEX-90

.-i FOR:

C ntrol-Room-operators IMESSAGE NO.  !

LOCATION: Control iRoom -' SCENARIO-TIME: Tl?

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX .!

THIS-.IS A ORILL 00 NOT INITIATE ACTIONS.AFFECTING NORMAL PLANT.0PERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX: ,

MESSAGE: ,

The following indications are noted on I-06:'

4160 KV buses indicate'O.

480 V. buses 3, 4,-5, 6 -7 &-8? indicate.0.- -

480 V buses.1 & 2 indicate 480 Volts B Diesel Generator indicates-no-' lights. .

High side -&- Low sidelRATr Bl;r.. indicates green and white light s  ;

with'a red target.

A Diesel Generator running and atarting-to pick up-1 pad;un ,

sequencer.

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'THIS IS A DRILL-

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<FOSAVEX-90 i q

FOR:: cnvTontirp 3 ernnutTne nyt v MESSAGE,NO. ,

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LOCATION: rno ur c.nvrt.n.a rn nety SCENARI0' TIME: 1 yc  ;

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXxXXXXXXXXXXXXXXXXxXXXXXXXXXX 9 THIStIS A DRILL f

00 NOT INITIATE ACTIONS AFFECTING NORMAL; PLANT OPERATIONS 3

• XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXxXXXXXXXXXXXXXXXXXXXXXX-l MESSAGE:,

8 9

The following indicationsJtr- noted on11 06:-

4160 KV buses indicate 0.  !

480 V buses 3, 4, 5,.6,17 &=8 indicate-0.-..

480 V buses 1 &.2 indicate 480 Volts _

B Diesel-Generator indicates no-lights. "j High side-& Low side P.ATLDkr.Lindicates green andEwhite light >

with a red, target. ..

(

A Diesel-Generator' running.andLstarting.lto:pickLupfload:en-l sequencer.

l- EXPECTED-ACTIONS:

1

[ Operators should attempt va rious - means - to - r ecove r .ou t si d- ;p. >..g 1

l using approved' procedures-(EOP-6,-AOP-F)', Cons ide ra t i on -_: shou l l -

be given to LOFC in progress.=

3'

\

s xxxxxxxxxxxxxxxxXxxxxxxxxxxxxxxxxxxxxxxxxxxxxxx'xxxxxxxxxxxxxxxxxxxx.xxxx THIS ISJA' DRILL- u XXXXXXXXXXXXXXXXXXXXXXXXXxXXXXXXXXXXXXXXXXXXXXXxXXXXXXXXXXXXXXXXXXXXXXXXXX I,

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F,05AVEX-90 l

FOR: control Room operator MESSAGE NO.

- LOCATION: ruel D e c P, to control Room SCENARIO TIMEt,11 :02_ t i XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX' t

li i THIS 15 A ORILL ,

00NOTINITIATEACTIONSAFFECTINGNORMALPLANTOPERATIOM  !

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX I r

MESSAGE: ,  !

1 .

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) . A loaded spent fuel shipping each is suspended ovel the truck bar un level 11 with no power to the crane.- ..

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'I XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX' ,,

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THl$-IS A DRILL-- .

- XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX ,

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F05AVEX-90 l

FOR: Control Room Operators MES$ AGE NO._ _

LOCATION: r'ontrol Room SCENARIO TIME: T1-:05 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THl$ IS A 0 RILL 00 NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS

. XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX  !

MESSAGE:

'! h o f e..llowing alarms and iridica tioils are received:

I 06 f 2 Gon ,.A Eng 1A Eng 1B Ttouble Lighting switchn 10 DF, 480 V bu8es 1 & 2 1.alcatv 0. i Battery buses and instrument. buses are normal.

A Diesel Generator indicat es rio light n.

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m XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS'I5 A DRILL-XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXYYXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX

.- -, . .. c_ . . . _ _ . . . . . _ . _ .,. - a_ ., ,_ , , _ . _ - . . _ . . . - . . _ - . . .. _ . . , _ . _ . _ . . _ . , . , _ .

)

4 F05AVEX ,

1-i  :

a FOR

CONTROLLER INFORMATIN ONLY MESSAGE NO.

l LOCATION: FOR Tilt rONTROLLER ONLY SCENARIO TIME: T1-:05 l xxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxXxxxxxxxXxxxxxxxxxx THIS IS A DRILL- 1 DO NOT INITIATE A0710NS AFFECTING NORMAL-PLANT;0PERATIONSl XXXXXXxXXXXXXxXXXXxxxXXXxXXxXXXXxXXXXXXXxXXXXxxxXXXxXxXXXxXxxXXXXxXXXXxXXx 1 ,  ;

~

MESSAGE: ,

i The f ol;owing. alar ms arid indicativns= are received:  ?

I-06 r 2 -2 Gen 1A Eng 1A Eng 1B=Troub1'e.

Lighting switcher to DC..

480 V buses.1 & 2 indicate 0, '

[

, Battery buses and-instrument buses are normal. l A Diesel Generator indicates-no light 8. '

EXPECTED ACTIO.NS: I i

Dispatch or call'EO to investigatA trip on 1A Diesel Gen t .it . . }

o  !

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i THIS IS A DRILL i

l XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXxXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXxXX j E

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(.__.-.-... . - - ..- -- .._,

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FOSAVEX-90 l . [

i FOR: Equipment Operator ME$$ AGE NO.

LOCATION Diesel Generators ~

$CENAR10 TIME: T1~

, XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX 1 THl$ IS A DRILL r

DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS r

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX HES$ AGE: ,

The opera tor vri PC\'-4206 has nepara t ed f r om . t he,Td ve s t em.

l I

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX

-THIS IS A' DRILL: ,

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX l-

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.* , .- 3 -w.0.%-- cv- e v s= + + d-+= 6-w- + * ~

F05AVEX_90 FOR: Control Room operator ME$$ AGE NO.

LOCATION: control Ronm '

$CENAR10 TIME: I1**10 -

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THl$ 15 A ORitt.

00 NOT INITIATE ACTION $ AFFECTING NORMAL PLANT OPERATION $'

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE:-

The following alarm 10 r e,'e i v ed t -

I-06 11 4 - 6 Air Preos Lu.

PI-8212 indicates'75 ris10 PI-8254 indicates 75 psig.

FCV-8218 indicates open. 1 TCV-8255 indicates open, j

i X

XX XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A-DRILt.

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX'XXXXXXXXXXXXXXXXXXXXXXXXXXXXX

i l

i F05AVEX-90 l

l FOR: control ennm n:wratnr MESSAGE NO.

LOCATION: contrni Rnnm SCENARIO TIME: T1-:45

XXXXXXXXXYYXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS'!S A DRILL

! DO NOT INITIATE ACTIONS AFFECT 1hG NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE:

dC Dieul oener. tor inch t emperatur e aiarm has reset .

0 1

a XXXXXXXXXXXXXXXXXXXXXXXXXXXX'XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A.0 RILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXu xXX-

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FOSAVEX-90 FOR: Control Room Operator MESSAGE-NO. <

LOCATION: control Roce .SCENARI O TIME: m..s .

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX t

THIS IS A ORILL 00 NOT INIT! ATE' ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE:

The Junction boS Ni the nort h side of the R A T ! b a s b e *2 n 1 .ti m i r ..<1 dhd the P.AT shog}d b9 Jpefdtichdl in about j $ miHULOU. :

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'XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A 0 RILL i XXXXXXXXXXXXXXXXXXXXxXXxXxXxXxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxx 4

FOSAVEX-90 FOR: Control Room operator MESSAGE NO. _

LOCATION: Control Room SCENARIO TIME: T2 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A ORILL DO NOT INITIATE ACTIONS AFFECT!NG NORMAL-PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX f

MESSAGE:

The following alatmo and indleatjons are received:

The building shakes and a loud noise is heard.

.I-06 E 5-5 Seismic Recorder Operat'e ,

1-03 A 4-6 Gas Waste Act Hi #2 {

I-01 C 4-1 Monitor Rad Hi 1 1-01 C 5-1 Acknu I-13 Alarm 4 I-03 A 2-6 Liq Want Act 1 Hi I-06 G 5-7 Trnsfr Pumps Trip I-13 C 1-5 Gas Wae', Act Hi #1 1-01 C 2-2 Pipe Act High >

Area Monitor 93250-5 is alarming at 1 mr/hr.

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS'IS A ORILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXx.

F0$AVEX-90 FOR: cnvTpot!rn ixrnps1ATinN'nN1Y MESSAGE NO.

LOCATION: rno cnnent i rp n*:t y SCENARIO TIME: T2 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THl$ IS A ORILL 00 NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE:

Tlie following alarms and indications ate ryceived:

The building shakes and a loud noise it heard.

.I-06 E 5- 5 Geismic Recorder Operate I-03 A 4-6 Gas Waste Act 111 #2 1 01 C 4-1 Monitor Rad 111 1-01 C 5-1 Ackno I-13 Alarm I-03 A 2-6 Litt Kast Act 1 lij I-06 G 5-7 Trusfr Pumps Trip I-13 C 1-5 Gas Wast Act Hi #1 1-01 C 2-2 Pipe Act High i Area Stonitor 93250-5 is alarming at 1 mr/hr.

EXPECTED ACTIONS:

Operators should-respond to AOP-K, AOP-H, and.EOP-5 ta

• determine what actions to take. One operator should check out the radiation levels on 1-14.-

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX  ;

l- THIS IS A ORILL '

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX i

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1 1

i q FOSAVEX-90  ;

i FOR: control Room nn araer.re MESSAGE NO.

i >

LOCATION: rual Dack to the t'ein t en1 p n c,n, SCENARIO TIME: - e nt -

l XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THis IS A DRILL.

DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS a XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX:XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE:

The sh2 pping through the plugc.is); ondisengagad level 5. fruin the trane and has fallen We cin hear yelling and screaming coming from level 5 and believe that the guys dr+n there may be hurt.

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XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX-.

.THIS IS A DRILL.

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX' 9

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F0$AVEX 90 l

FOR: Pcc Peronnel MESSAGE NO.

LOCAT10N: parnnnnel c t,n t r M rone.o- =,_ . SCENARIO TIME:

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX TH!$ !$ A ORILL t DO NOT ! NIT! ATE ACT!OL$ AFFECTING NORMAL DLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXhXXXXXXXXXXXXXXXXXXXXXXXxXXXXXXXXXXXXXXXXXXXXXX MES$ AGE:

. Respi t a t ions c.f 10 Pulse of 94

3. B/P 140/85

. 4. Moiut, Pale skj n ,

5. Disurlentation l

XXXXXXXXXxXXXXXxXXXXXXX),XXxXXXXXXXXXXXXXXXXXXXXXXXXxXxXXXXXXXXXXXXxXXXXXXX THIS IS A DRILL xXXXXXXXxXXXxXXxXxXxXXxxxxxxXXxxxxxxxxxxxxxxXxxxxxxxxxxxxxxxxxxxxxxxxxxxxx L

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F05AVEX 90 FOR: Search and Rescue Team MESSAGE NO.

LOCATION: Reactor Building Trueli Bay SCENARIO TIME: _T2-XXXXXXXXXXXXXXXXXxxXXXXXXXXXXXXXXXXXXXXXXXXXXXxxxXXxXxxXxXXxxxxXXXXXXXXXXx THIS IS A OR!LL 00 NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXxxXXXXXXXXXXXXXXXXXXXXXXXXxxXXXXXXXXXXXXXXxxxxxXXXXXXXXxxXXXxxxxxxx MESSAGE: FIRST VICTIM Umall aniount.of tilood coming frem the left en .

l cina l l indentation on the luft side of head.

Di!fIcultdes breathitig.

Pupils are dilat.ed and non-responsive.

Sa response to pain.

5 LOC x 0 e

i xxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxx-THIS'IS A ORILL xxxxxxxxxxxXXxxxxxxxxxxxxxxxxxxxxxxxxxxxxXxxxxxxxxxxxxxxxxxixxxxxxxxxxxxxx j

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i F0$AVEX-90 FOR: Search and pncut. T a a r" MESSAGE NO.

LOCATION: o.n,-tor r Buildino Truck Bar $CENAR10 TIME: _ T2-XXXXXXVXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX.XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX- .

THl$ 15 A ORILL t

00 NOT INITIATE ACTION $ AFFECTING NORMAL-PLANT OPERATIONS i XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE:

e

trros:p vir'T P1:

Exh21;its siglas of shuck.

Lost a large amount of bleiod.

Respirations sre rapid and shallow. t Pulse is 125, 7 Blood pressure is 150/90. ,

LOC N 1.

E-4 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS'15 A ORILL.

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX i

,- . - - . .. . . _s - _

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FOSAVEX-90 <

FOR: Control Room Operator MESSAGE NO. c LOCATION: ONLY -IT PERSOXNEL . DISPATCHED -TO B68NAR10 TIME: = T1 :02 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THis 15 A ORILL 00 NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERAfl0NS I XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX -I MESSAGE: I The deluge sistem has fired. The deluge. valve-is dl..ised.

There appears to be damage tu the junctivn bux'on the north side of the RAT.

i

, l 4

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS 15.A DRILL- .

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX.

._ .. ---a' - - - _ _ _ _ _ - . - - - - - - - - . - - - _ _ _ - . - - - . -

r FOSAVEX-90 control Room Operator- c*

. FOR: MESSAGE NO, ONLY IF PERSONNEL DISPATCHED TO i-LOCATION: nirnr' n rvre gney SCENARIO TIME: T 1 *.-

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL-i 00 h'TJ INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX

, MESSAGE: ,

B Diesel Generator, engines 1 & 2, t ripped on OVer speed.

In A Diesel Generator room, engine cool' ant la all user the i floor and is still coming out of'the eNpansion tanha. Alarms indicate.that A Diesel Genetator engines tripped on high temperature.

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XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX-

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-THIS IS A 0 RILL I XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX

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ff F05AVEX-90 j FOR:

contrel Room operator MESSAGE NO. c LOCATION: Control Room - (ONLY IT ASKED FOR) SCENARIO TIME: T1-

) XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX::XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX i

--TH15 15 A DRILL 00 NOT INITIATE ACTIONS AFFECTING NORMAL PLANT-OPERATIONS-XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX-

MESSAGE

- , j Service water precsure is 0, i

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i XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXxxxxxxxxxxxxxxxXxXxx'xxxxxxxxxxxxxxx_ ,

THIS-15 A DRILL-

-XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX l l

i i

l F0$AVEX-90 i -n FOR: control Room operator MESSAGE NO. c-1 LOCATION:- contrni Room SCENARIO TIME: 71- 1:9o XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS.IS'A DRILL 00 NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERAT10NS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE: ,

The loaded opent fuel chipping cash is a*.ill hanging Irom ,

Iwel 11. We need to get it duwn as quickly as pourtble.

i

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f XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS 15 A'ORILL" XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX  !

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t F05AVEX-90 FOR: contr01 Rcom noeratorc MESSAGE NO. c LOCATION: cc,n t roi noom SCENARIO TIME: -t1  !

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL  !

00 NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATION 5 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE:

e IT OPERATORS ATTEMPT TO RESTORE POWER TO THE CRANE PFIOR Ir-I<ECTOFATION OF OFFDITE POWER--

The 1.owside breaker on 180\' bus S has failed.

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XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX -

l THIS-IS A DRILL .

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX i-

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FOSAVEX-90 FOR: Eningeering Tech. Analysis Team MESSAGE NO. -

LOCATION: Technical Support Center SCENARIO TIME: .g XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL 00 NOT INITIATE ACTIONS AFrECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE:

T F MT E D The spent. fuel shipping eduk was loaded W4th 6' spent tuel elemerits f rom segment 4, region 34.

i i

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS-IS A. DRILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX:

FOS _AVEX FOR: Inspection Team MESSAGE NO. c LOCATION: Reactor Building SCENARIO TIME: te XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THis IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX-MESSAGE:

1 IF AND WHEN A VISU At T NDPETinN of T HE RE APTnP DUTLDING-MEY Wu 18 01ADF -

1

[

The six spent tuel elements are dispetsed=in-the Reactor Building Key Way, i The elements appear to be spread out and anmewhat intant.

The Key Way appears to contain approximately 1 f oo t _. o f t wat:t, The fuel elements are not submerged.

XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A:0 RILL

.XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX'XXXXXX~

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

(.

F0$AVEX-90  :

4 SCENARIO TIME: ~77-/ #

CLOCK TIME: _,_  !

RADIAi!ON M 11 TORS:

I NUMBER VALUE ALARMING $ENSITIVITY I

RT-6212 7.0 X 108 CPM N 2.2E-8 .

i i RT-6213 8.0 X 101 CPM N. 2.2E-B RT-7312 005- CPM N/A +

RT-7324-1 2.0 X 101 CPM N 1.57E-8 RT-7324-2 2.0 X 108 CPM N 4.36E-7 RT-7525-1 1.0 X 108 CPM N- 1.49E-5' [

RT-7325-2 1.0 X 105 mr/br N N/A  ;

RT-73437-1 1.5 X 10' CPM 'N 2 51E-10 RT-73437-2 4.0 X 10$ CPM N 2.73E-10 RT-9301 005 CPM N/A -

RT-93252-12 1.0 X 108 m'r/hr N, N/A AREA MONITORS  !

t i

RT-93250-1 1.0 X 102 mr/hr N RT-93250-2 1.0 X 10 mr/hr N r RT-93250-3 1.0 X 101 mr/hr N .

RT-93250-4 1.0 X 108 mr/hr N RT-93250-5 1.0 X 108 mr/hr N RT-93250-8 1.0 X 105 mr/hr N RT-93250-13 2.0 X 108 mr/hr N k

RT-93250-14 4.0 X 108 mr/hr N RT-93251-1 2.0 X 10' mr/hr N i

RT-93251-3 -2.0 X 101 mr/hr N , ,

i RT-93251-4 1.0 X 105 mr/hr N l

RT-93251-5 1.0 X 101 mr/hr N  !

RT-93251-6 1.0 X 108 mr/hr N l RT-93251 3.0 X 108 mr/hr N ,

RT-93251-8 1.0 X-101 mr/hr N ,

RT-93251-9 2.5 X 105 mr/hr N'  :

RT-93252-1 2.'5 X 108 mr/hr N  !

RT-93252-2 1.0 X 10' mr/hr N i RT-93252-4 1.0 X 10mr/hr N i RT-93252-6 1.5'X 108 mr/hr N i RT-93252-7 1.0 X 108 mr/hr. N-  :!

r EQUIPMENT-MONITORS t RTs6314-2 1.0 X 108 CPM -N RT-46211 ' 5.0 X:101 CPM. N RT-46212 7.0 X 105 CPM N i METEOROLOGICAL DATA

. Wind: Speed . . 3.0 MPH - i Wind 10irection From 315 Degrees  :

Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature 2 . 2

• F, i

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

.. j ,

s F0$AVEX-90 I

'PAGE 1-  !

SCENARIO TIME: N/r

! CLOCK TIME:

f 1 OVERALL PARAMETERS -

Reactor Shutdown YES i Decay Heat Power 0,05 MW I

PRIMARY COOLANT -:;

Pressure 10 PSIA ,

Temperature Circulator Inlet 95 'F "

Core Inlet '105F t Core Outlet 125 'F Calculated Bulk Core -(CBCT)= N/A  !

Haximum Region Differential-(AT) 28 'F

^

Helium Flow Circulator C- 10 X 108 Circulator 0 0 X'102 r TOTAL 10:X 108 r

, Cire.ulator Speed '

Circulator C 2900 RPM 4

Circulator 0 0 RPM Moisture (Dew Point)

ME-9306 41t*F '

ME-9307 ~ 3 9 -.' F-SECONDARY COOLANT.

Emergency Condensate Header j Flow Loop 1 . .. '0ilb/hr-Loop 2 1.0 X: 10'ilb/hr EES Inlet Temperature- 85- 'F-EES Outlet Temperature 1003'F Pressure- -350 PSIA 1

H PCRV LINER COOLANT, (In Service)-

Loop 1 NO: -

Loop 2' YES-l . {

-l

, .. , _ . _ _ . _ _ . _ . . . - , , , . - , - , . , _ , _ _ . . -,-...._...a , ,; _ . ~ . 2 ._ . _ -. _ . .aa_ _ , , _ , _ - . . .

F05AVEX-90 PAGE'2

$CENAR10 TIME: 7- 0C/S

-CLOCK-TIME:-

PRIMARY AUXILIARIES

. . . . . . . . . . . . . . . . . . . . * * * * * * * *

• B O A R D I - 01 " " " * " " " " " " * " " " " " " ,

GA$ WA$TE System 63 Inlet Pressure 10 PSIA Vacuum Tank-Pressure 8 PSIA-Surge Tank "A" Pressure 200 P5JG Surge Tank "B"' Pressure O PSIG -

L10010 WASTE System 62 - NORMAL:

REACTORPLANTCOOLINGWATERl $ystem 46:  ;

Loop 1 P-4601 CLEARED OUT P,46015- CLEARED OUT Header Inlet Temperature CLEARED.0UT Barrel and Top Head Outlet _ Temperature CLEARED OUT Top Penetration inlet Temperature. . CLEARED OUT Loop 2 i P-4602- - ON 1 P-4602$ CLEARED OUT- '

Header-Inlet Temperature- -115 'F ,

Barrel and Top Head Outlet Temperaturei 115F' '

Top Penetration Inlet Temperature '

115t*F.

Surge Tank Level "A" 0 INCHES  ;

Surge Tank' Level "B" . 45 INCHES 1 i

1 i

1 l-l:

i

_ _;_1

. 'l FOSAVEX 4 PABE 3 l i  !

$CENAR10 TIME: -r/ - ce T l

CLOCK TIME:

I

! PRIMARY AUXILIARIF_$

3 ...................***"a**** BOARD l-02 """""" * """""""""

• i HELIUM STORAGE System 24 ,

Low Pressure Bottles 270 PSIG High Pressure Bottles 575 PSIG

{

HELIUM CIRCULATOR ~ AUXILI ARIES - System 21 Circulator C-2103 (C)

Bearing Water Flow 170 GPM Bearing Water Inlet Temperature 78 'F Main Drain AP 2.5 PSID Buffer /Mid-Buffer AP B PS10 t Buffer Helium Flow 7.40 ACFM Buffer Helium Return Flow 3.79 ACFM~

Circulator C-2104 (0)

Bearing Water Flow 0 GPM Bearing Water Inlet Temperature 78 'F Main Orain AP. 4 PSIO.

Buffer /Mid-Buffer AP 0 PSID s' Buffer Helium Flow 'O ACFM-Buffer Helium Return Flow 'O ACFM

..............u............. BOARD l -0 3 """"""""""" " " " " "

REACTOR CORE - System 12 All Systems NORMAL

..................n.......**

BOA R D - I -0 5 " "" " " " " " " " " " " "" * "

s HELIUM CIRCULATORS System 21 Circulator C-2103 (C) ..

Rotor Speed .2900 RPM Helium Flow (Low Range)- -0,019 PSID-Helium Flow-(High Range) 0 ?e t Circulator C-2104 (0) l Rotor Speed' O RPM-l Helium Flow (Low Range) -0.003 PSIO l

Heli _um Flow (High . Range): 0 14 --

MAIN TURBINE System 51 . NORMAL s.-  ;

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

F05AVEX-90 PAGE 4 SCENARIO T!ME: -r/ - oM CLOCK TIME:

PRIMARY AUXILIARIES

......n..........*********" BOARD l -0 6 " * " * " * "" """" " "" " * "

MISCELLANEOUS Bypass Flash Tank Pressure O PSIG PLANT ELECTRICAL System 92 Essential Bus 1 Bus 2 Bus 3 N/I Bus 3 480 VAC 485- =485 485 120 VAC -118 118 116 118:

120 VOC 130. 130

' "A" "B" Standby _ Diesel Generator NORMAL NORMAL-ACM Diesel Generator CLEARED OUT Non-Essential Switchyard NORMAL Bus:1 Bus 2 Bus-3 4160 VAC 4160 4160 4160 480 VAC NORMAL MAIN TOWER System 41 DRAINED SERVICE WATER TOWER System 42 NORMAL-FIRE WATER- System 45' NORMAL INSTkUMENT AIR System 82 "A" HOR "B" HOR 93 ;93 SERVICE AIR System 82 -95'PSIG-

...........................** BOARD I-10 ********************************'

PLANT-PROTECTIVE SYSTEM REACTOR BUILDING TEMPERATURE - HIGH Bay 100 80 'F Bay 200- 80 'F-Bay 300 80 'F

- REHEAT' ACTIVITY MONITORS -005' BUFFER.5EAL MALFUNCTION NORMAL r - e v ~

J FOSAVEX-90 1

PAGE S

SCENARIO: TIME . 7/- ce/5

! I CLOCK TIME:

, PRIMARY AUXtLIARIES

..........n...............** BOARD I-13 * "" * """ * """""" * """

3 a

PENETRAT!0N INTER $ PACE AP 0 P$10' ^

REACTOR BUILDING $ UMP 0!$ CHARS.* FLOW 0 GPM-HELIUM CIRCULATORS System 21 NORMAL

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B O A R D .1 - 15 * " " " " " " " " " " " k " " " "

R REACTOR BUILDING STACK FLOW- 29.9 KCFM ,

4 1

REACTOR BUILDING AMBIENT AP -0.25 Inches H2O- -

CONTROL'R00M 1EMPERATURE 75 'F

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B O AR D I - 7 5 0 7 X " " " " " " " " " " " " * " " l

- 480V ROOM TEMPERATURE 75 *F s-1 3

Y b

o

.i s

y v

P we * = -ww e - w [ r * *- + "'

c '-s v- v -- 4 , r w -www t'-r e * * - * - - - - -4'- -*--v------+= e-- 4 h m,eIw- w n- M * *w w --' ~+~-m r

• ww.---w**

+

! FOSAVEX-90 i

1 SCENARIO TIME: f/

CLOCK TIME

I 4

RADIATION MONITORS: ,

NUMBER VALUE. ALARMING SENSITIVITY ,

o RT-6212 7.0 X 101 CPM N 2.2E-8

RT-6213 8.0 X 108' CPM N 2.2E-8

! RT-7312 005 CPM N/A RT-7324-1 2.0 X 105 CPM N 1.57E-8 r

RT-7324-2 2.0 X 10' CPM N 4.36E RT-7325-1 1.0 X 108 CPM N 1.49E-5 RT-7125-2 1.0 X 102 mr/hr N N/A q 2.51E-10

, RT-73437-1 1.5 X 10' CPM N 'i RT-73437-2 4.0 X 10 CPM N 2.73E-10 RT-9301 005 CPM N/A -

RT-93252-12 1.0 X lot mr/hr_ N, N/A AREA MONITORS l

RT-93250-1 1.0 X 108 mr/br N RT-93250-2 1.0 X 105 mr/hr N

! RT-93250-3 1.0 X 108 mr/hr N I RT-93250-4 1.0 X 10 mr/hr N .

RT-93250-5 ' 1.0 X 101-mr/hr N -

RT-93250-8 1.0 X 102 mr/hr. N

, RT-93250-13 2.0 X 105 .m r/hr N l RT-93250 4.0 X 108mr/hr N RT-93251-1 2.0 X 108 mr/h'r N=

RT-93251-3 2.0 X 108 mr/hr N ,

RT-93251-4 1.0 X 108 mr/hr N RT-93251-5 1.0 X 10 mr/hr N RT-93251-6 1 0 X 105 mr/hr 4 N RT-93251-7 3.0 X 108 mr/hr' N RT-93251-8 1.0 X 101-mr/hr N i RT-93251-9 2.5 X 10$ mr/hr N RT-93252-1 2.5 X 105 mr/hr N RT-93252-2 - 1.0 X 10' mr/hr N RT-93252-4 - 1.0 X 10 mr/hr N RT-93252-6 1.5 X-108 mr/hr N '

I RT-93252 ' 1.0 X 108 mr/hr N- -

i l- EQUIPMENT MONITORS  !

RT-631'4-2 1.0 X 108 CPM' N-RT-46211 5,0 X 101 CPM :N RT-46212 7.0 X 108 CPM N- ,

METEOROLOGICAL DATAL Wind Speed 3.0 MPH Wind Direction. _

From- 315 Degrees- =

Plume Deviat_ ton / Sigma Theta 4.0 Degree s'.-

Differential. Temperature 12 'F . _.

--.,,4.--,.,vd- r- ew E e m m+ ,#sy- ,s u d.> . 'w,-wm_.#- .. h>_, , hw- , , - , .- , f .., , p .w wwpn o ,.,.,,,,,,.p,., y,y,,w,3--,,. w. pm e-w -m , - + go %, - , . g e ., wer-,.

t i

F0$AVEX-90 j PAGE 1 1

' SCENARIO TIME: -r/

, CLOCK TIME:

OVERALL PARAMETERS.

Peactor Shutdown YES Decay Heat Power 0.05 MW  !

)

PRIMARY COOLANT Pressure 10 PSIA' 1

Temperature -

Circulator Inlet 95 'F 2 Core Inlet N/A 4 Core Outlet 125 'F Calculated Bulk Core (CBCT) :110.'F :

Maximum Region Otfferential (AT) P/A -

r Helium Flow Circulator C 0 X 10' Circulator 0 0 X 103

, TOTAL -OiX 108: ,

Circulator Speed ~c l Circulator C -0 RPM Circulator D 0 RPM:

Moisture (Oew Point)

ME-9306 41 'F ME-9307 '39 'F L SECONDARY COOLANT Emergency Condensate Header ,

Flow Loop.1 Olib/hr- -

Loop 2 0 lb/hr .

EES Inlet Temperature 85 *F-L EES Outlet Temperature 100L*F:

Pressure 350 PSIA'

& u .

PCRV_' LINER COOLANT (InSerfice)  ;

Loop 1.. ,NO: .

Loop 2- =NO s

__,._......r., ...,;._, - . . , _.-.._.,,_..__.-m,__. _ . . . . , . . ~ . . . . .. . . . , , . . . _ , _ _ _ . - ._

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

7-..__..--

~

FOSAVEX-90i

< , AGE ~2;  !!

4

. SCENARIO TIME: 7'/

. CLOCK TIME:-

• PRIMARY AUXILIARIES-i

- . . . . . . . . . n . . . . . . . . . . . * * * * * " , BO A R D I - 01. " " * " " " * " " " " * " " * " " " '

GAS WASTE . system 63' 'i Inlet Pressure = .

' 12.3 PSIA 1

Vacuum Tank Pressure- 12.3 PSIA) '

Surge Tank "A". Pressure '

200 PSIG Surge ' Tank "B" Pressure - 0 PSIG--

LIQUID WASTE System 62 .

- N0'RMAL; REACTOR PLANT. COOLING-WATER Systen.46'  !

Loop 1 - -

P-4601- iCLEARED 0UT P-46015t CLEARED 0UT-Header Inlet Temperature .

, CLEARED.0VT Barrel and Top Head Outiet Temperature' CLEARED OUT' '

Top Penetration Inlet' Temperature CLEARED OUT-Loop 2 P-4602 0FF, . -

P-4602$ CLEARED OUTr i Header Inlet Temperature; .

J115 i

• F _~

Barrel and~ Top; Head Outlet Temperaturei 115' - ' F -

Top PenetrationiInlet Temperature? '- 115 'F -  !

Surge Tank Laval "A" 0 INCHES- i Surge Tunk "B" 45i!NCHES 4

a i

L a

l 1

i i-

.}

i

p +

f r , - - - .m . . , - , ... . ~ , - - , - .r.,m.. *w. + - - , - , , - - - - ~ ~ , - - . . - . . . -+

_- - - _ . -. . .- .- _- . _ .- . _ . . = . .

FOSAVEX-901 ~, '

PAGE:3

~'

. SCENARIO TIME: 7/-

CLOCK TIME:-

i PRIMARY AUXILIARIES-

............*****************BOARDI-02'"""**""""""*""*""* i HELIUM STORAGE- System 24 Low Pressure Bottles 270 PSIG High Pressure-Bottles S75 PSIG-HELIUM CIRCULATOR AUXILIARIES System 21 Circulator C-2103 (C)-

~

Beering Water Flow 0 GPM 78 'F ]j Bearing _ Water Inlet Temperature Main Drain 6P 4 PSIO.

• O PSID Buffer /Mid-Buffer-aP

' Buffer Helium Flow 0.ACFM Buffer Helium Return Flow 0 ACFM Circulator C-2104 (0)-

Bearing Water Flow 0-GPM Bearing: Water Inlet Temperat'ure -78 'F Main Orain 6P 4 PSID Buffer /Mid-Buffer 6P 0 PSID 1 Buffer Helium Flow- 0 ACFM'  ;

Buffer Helium Return Flow s0 ACFM l

..*********"****"*****"*****BOARDI-03"""""""""""**""""

REACTOR CORE- System 12 All Systems

'AL

.............n.............* BOARO LI-L S """ * * """ " ' """"""""

HELIUM CIRCULATORS- System 21' Circulator C-2103 (C)

Rotor-Speed- .

0 RPM Helium Flow -(Low Range). . -0.PSIO Helium-Flow-(High Range) .0%

. Circulator C-2104 (0)' .

. Rotor Speed- .0-RPM .

Helium Flow (Low Range)' -0.003'PSID Helium Flow (High Range). O%-

p MAIN TURBINE  ; System 51 . NORMAL 1.

i-l' ,, - _ - - . ,. , . -- 1 -

FOSAVEXa90

PAGE'5

, SCENARIO TIME:- 7/

CLOCK TIME:

PRIMARY AUXI'LIARIES'

.............................BOAROI-13*"""*"""""***"""""*'

PENETRATION INTERSPACE AP 0- PSID ;- -j REACTOR BUILDING SUMP DISCHARGE FLOW 0 GPM--

HELIUM CIRCULATORS System 21 NORMAL

. . . . . . . . . . . . . . . . . . . . . . . . . . .

• B OA R D I - 1 5 " " " " " " * " " * " " " " " " "

REACTOR-BUILDING STACK FLOW 6 KCFM s REACTOR BUILDING AMBIENT.AP- 0~ Inches H20' CONTROL-ROOM TEMPERATURE 75 'F- l

...o......................** BOARD I -7 50 7 X '""" * "" """" " * """"

8"" ROOM TEMPERATURE - 75 *F

=i i

4 i

i

's

.-j 97 - YP vv*" iwT- Wi-- w w a= %T s 4 6e- 6- - 7  % s- e

LCD 4.1.9 COMPLIANCE SYSTEM 12 DVERVIEV HENU ALARM INHIBITS

[ START'

-f' _IS DATA DK FOR FLDV CALC [ > FLOV > 0 7 .;;ND "

"" YES ND ND y YES DENSITY 4_ DENSITY - >= 27 DRIF. p - -

<=107.5% ==

..ND <= 60% IN EQ FLOV ?.=

' IS REMAINING

..YES

=

. ~'.i.,'+

DATA DK 7 q, E ND I yYES yYES y ND REACTOR DOES REACTOR DDES REACTOR 4 PVR EXCEED POVER EXCEED P'3VER EXCEED -

RX PRESSURE > 50 PSIA LCD4.1.9-1 LCD 4.1.9-3 LCD 4.1.9-5 YES El ND CURVE 7 ".. CURVE 7 ..

CURVE 7 ..

V ARE ALL 37 DRIFICES ND YES V ND YES V ND YES V IN EQUAL FLOV 7 ..

N/A N/A N/A i =

V V V VYES ND V IS FLOV - >= l IS FLOV ->= ARE AT'S <= ARE ALL. l f ARE ALL

. LCD4.1.9-1 LCD 4.1.9-3 LCD 4.1.9-5 REGION AT'S REGION AT'S CURVE 7 ., CURVE 7 ., CURVE 7 ., <= 600 DEG F. <= 350 DEG F yYES ND yYES ND yYES' ND yYES ND yYES ND IC IC IC IC IC V T V Y_ V 4 M i IS REACTOR SHUTDD'<N 7

_ . . _ _ . _ gg 4-V W 37 DRIF CAN REQ FLOV ENDUGH FLOV NIC. , FLOV > 0 7 . EQ FLOV7. . BE DETERMINED g FOR CMG-25 7 .

MrND y ND y ND ND YES

O F n

U IP'E g4- IS- INITIAL DECAY HEAT AVAILABLE 7 , ,4 .y ND Y

V U E'S < 760'DEG F ?.d EXECUTED: -

11/ 07/ 90 CMG4 TIME' TD 760 I "

N/A FOR PES ND y 8: 34i 14 p 4-- DEG F EXPIRED 7 335.6 HRS =. , N/A NIC. ,

4. .

YES

,NU

- ==

.. y

-d

FOSAVEX SCENARIO TIME: 7N-: /6 ~

CLOCK TIME::

RA0!ATION MONITORS:

NUMBER VALUE ALARMING SENSITIVITY RT-6212 7.0 X:105 CPM N -' .2.2E {

8.0 X-108 CPM RT-6213 N 2.2E RT-7312 005' CPM N/A. '

RT-7324-1 2.0 X 108 CPM N 1.57E-8 RT-7324-2 -2.0 X-105 CPM N - 4.36E RT-7325-1 1.0 X 10* CPM N. 1.49E-5 1' RT-7325-2 . 1.0 X 105-mr/hr N N/A1 RT-73437-1 :1.5 X-102 CPM N '2.51E-10' i RT-73437 4.0 X:108 CPM N. 2.73E~10 RT-9301 005 CPM N/A" RT-93252 12 1.0 X 101 _mr/hr.- N ,

4 N/A AREA MONITORS ,

i RT-93250-1 1.0 X 105 mr/hr .N' i RT-93250-2 1.0 X 101mr/hr- N RT-93250-3 1.0 X 108 mr/hr N RT-93250-4 -1.0 X 108 mr/hr N i R1-93250-5' 1.0.X 105. mr/hr N RT-93250 1.0.X 108 mr/hr N RT-93250-13 2.0-X 10* mr/hrL N RT-93250 14 4.0 X 108 -mr/hr .N RT-93251 2.0 X-108 mr/hr N ,

RT-93251 2.0 X 101'mr/hr N , i RT-93251-4 1.0 X 102-mr/hr N y

RT-93251-5 1.0 X 102'mr/hr .N RT-93251-6 1.0-X 101 mr/hr N RT-93251-7 3.0 X 101 mr/hr N- ,

RT-932;1-8 1.0-X 102 mr/hr- N <

RT-93251-9 '2.5 X-?105 mr/hr N-RT-93252-1 2.5'X 101 mr/ hr. - N

-RT-93252-2 1.0 X:10' mr/hr N' RT-93252-4 1.0:X 101 mr/hr N' "1 RT-93252 1.5 X 108 mr/hr -N RT-93252-7 '1.0 X 101 mr/hr

-N-

~

EQUIPMENT MONITORS-RT-6314-2 1.0 X 108 CPM N

^

RT-462111 5.0 X 102 CFM N-

-RT-46212: ;7.0 X 101 CPM N

-METEOROLOGICAL DATA-Wind Speed :3.0: MPH Wind Direction . - From ,315 Degrees :

Plume'0eviation/ Sigma Theta 4.0.0egrees Differential Temperature 2.2-*F~

J l

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

a; FOSAVEXe90!

PAGE 1 ,.

SCENARIO TIMEi T/+ cos- li CLOCKiTIME: .

'OVERALL' PARAMETER [  ;

t l Reactor Shutdown. YES-Decay Heat. Power 0.05 MW.

PRIMARY COOLANT

Pressure- ,

~10 PSIA Temperature: -' '

Circulator Inlet '

95 'F =

Core Inlet N/A; Core Outlet. 1251*F  :

Calculated Bulk Core (CBCT)_ . 111 'F=

Maximum Region Differentialg(AT); -. N/A ;  ;

Helium Flow: ,

Circulator C '

- 0 X:l10 8  ;

Circulator 0 0 X1108-TOTAL JOLX :103; i

-

Circulator Speed 1

-Circulator C # '0! RPM-

l. Circulator D- , -0 RPM:

Moisture (Oew Point)  ;

M ME-9306- 41 -.

• FJ ME-9307 39 *Fi

-1.

SECONDARY COOLANT-

Emergen'cy Condensate. Header._

Flow ~

Loop 1 <

0.- 1 b/hr.

Loop:2 '

0.lb/hr'

-EES Inlet Temperature- 85 *F-EES Outlet _ Temperature

-100 'F L Pressure

350 PSIA--

-PCRV LINER COOLANT- (In Servise)

Loop =l-NO Loop-2 NO- -

w

=-

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

'FOSAVEX-90 PAGE 2

]

- SCENARIO TIME: -r/ s cc/f l 4

CLOCK TIME:

• PRIMARY AUXILIARIES

'l

. . . . . . . . . u . . . . . . . * * * * * * * * * *

• B O A R D 1 - 01 * " * " * " * * * " " " " " " " " " "

-I GAS WASTE-  : System 63' Inlet Pressure 12.3 PSIA' vi Vacuum Tank Pressure- 12.3 PSIA _ 1 Surge Tank "A" Pressure -200 PSIG i Surge Tank "B" Pressure 0 PSIG LIQUID WASTE  : System 62 NORMAL =

REACTOR PLANT COOLING WATER System 46 :l

, c Loop 1

-P-4601- - CLEARED:OUT P-460lS . CLEARED OUT-Header Inlet Temperature

~

CLEARED 0VT >

Barrel and-' Top Head Outlet Temperature

' C LEARED' 0VT- ,

Top Penetration Inlet Temperature! CLEARED OUT. >

Loop 2 P-4602 0FF P-46025 L CLEARED -0UT; Header Inlet-Temperature . 115 'F Barrel and Top: Head Outlet Temperature- ~115F - '

Top Penetration- Inlet Temperature '-

- '115 *F Surge Tank Level "A" OLINCHES Surge Tank Level "B" ,- 45 INCHES- _

L  :

i b ,

6 --

'FOSAVEX-90'

~~  :

PAGE 3:

SCENARIO: TIME: - r / s o e x';-

CLOCK TIME: ,

PRIMARY AUXILIARIES

...........****************** BOARD I-02 ********************************

HELIUM STORAGE . System 24 Low Pressure Bottles 270 PSIG-High-Pressure Bottles 575 PSIG HELIUM CIRCULATOR AUXILIARIES System 21 Circelete- C-2103-(C)

Bearing Water' Flow 0 GPM-Bearing Water Inlet. Temperature '

78 'F Main Orain AP 4 PSID Buffer /Mid-Buffer AP

• O PSIO Buffer Helium Flow 0 ACFM Buffer Helium Return Flow 0-ACFM Circulator _ C-2104'(0)_

Bearing Water Flow 0 GPM Bearing Water Inlet Temperature 78 'F-Main Drain AP 4 PSID-Buffer /Mid-Buffer AP' O PSID: ,

Buffer Helium Flow 0 ACFM Buffer Helium Return: Flow 0 ACFM Ns ..

4

.........................**** BOARD I-03 ********************************

t REACTOR CORE System 12- '

All Systems NORMAL

...........................** BOARD-I-05 *********************************

HELIUM CIRCULATORS System 21 ,

Circulator C-2103 (C)-

-Rotor _ Speed, O RPM Helium Flow (Low Range)- 0 PSID-Helium Flow (High Range) 0%

Circulator-C-2104 (D)

Rotor Speed 0 RPM Helium Flow (Low Range) -0.003-PSID- :i' Helium ~ Flow (High Range)_ 0%

w .

MAIN TURBINE System 51 NORMAL 1

- - , , , , . - - . . - . n , , ,

T "-

FOSAVEX-902 t PAGE 4 i

SCENARI0 TIME: 7 / oc/r -

]

CLOCK TIME:

-1 PRIMARY AUXILIARIES

.............****************BOARDI-06""**""""""""*"*""**

MISCELLANEOUS-Bypass Flash Tank Pressure- 0 PSIG-PLANT ELECTRICAL System 92 Essential . Bu~s 1 Bus 2 Bus 31 N/I_ Bus 3 480 VAC -0 0 :0 120 VAC -115 115 .0- 1151

120 VDC 119 -117 "A" . B'!  ;

Standby Diesel Generator- FAILED FAILED ACM Diesel Generator'- CLEARED OUTc ,

Non-Essential ,

Switchyard: NORMAL  !

Bus,1 Bus 2 Bus 3 a 4160 VAC 0 10 O.

480 VAC. ~0 1

i MAIN TOWER System 41: DRAINED 4 SERVICE WATER TOWER- System!42 . NORMA'L '

FIRE-WATER- System 45. NORMAL INSTRUMENT AIR System 82 "A" POR . "B" :HDR- '

75 '75 -

L L SERVICE AIR System 82: 95 PSIG.

L

. . . . . . . . . . . . . . . . . . . . . . . . . . . *

• B O A R D 1210 " " " " * " " * " " " " " " " " " "  :

~ PLANT' PROTECTIVE SYSTEM REACTOR BulLDING TEMPERATURE HIGH- _

' Bay 100s _.r80FJ <

. Bay 200' -80 *F? -i

Bay:300 80 'F-REHEAT ACTIVITY MONITORS 1005:  ;

.T

' BUFFER SEAL MALFUNCTION NORMALD L

i 4t

.: ;, = . .

, _ .f.. . . , . . .. , - . -

. . ._ . . . y; FOSAVEX-90. ..

j

.PAGE 5:

. SCENARIO TIME:'T-/ #co6

, CLOCK TIME:

.. , j PRIMARY AUXILIARIES-

. . . . . . . . . . . . . . . . . . . . . . . . . . * *

• B C A R D ' I e 13 ~ " * " * * " * " " * " " * " * " " * " "-

PENETRATION INTERSPACE AP :0 PSID i

REACTOR BUILDI'NG SUMP DISCHARGE FLOW 0 GPM- I HELIUM CIRCULATORS Sy5 tem 21: NORMAL-  !

............................. ,0ARD 1 15 ................................

l REACTOR BUILDING STACK FLOW 0-KCFM

-REACTOR-BUILDING AMBIENT.4P. ~0 Inches H20-CONTROL ROOM TEMPERATURE -75F

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . - BOA R D l - 7 5 0 7 X " " " " " * " " " " " " * " " "

480V-ROOM TEMPERATURE 75 'F s

. . _ . . _ . _ . . . . ___.__2-_-.am.a

. .. - . . . - _ = . . . . . - . . . ..

F FOSAVEX-90!

I SCENARIO TIME: ru.30 i CLOCK TIME: 1 :1 i

RADIATION MONITORS:

NUMBER VALUE- ALARMING SENSITIVkTY-: .

L RT-6212 7.0 X 101 CPM N 2.2E-8:

RT-6213 8.0 X 102 CPM' N' 2.2E-8  !

RT-7312 005 CPM N/A- '

RT-7324-1 2.0 X 108 CPM.- N 11.57E RT-7324-2 2.0:X=102 CPM N 4.36E-7o RT-7325-1 1.0'X 10' CPM- N 1.49E-5^

RT-7325-2 1.0 X-104 mr/hr.. N N/A-RT-73437 1.5-X'102 CPM- .N. -- 2 . 51 E .10 -

RT-73437-2 4.0 X 108 CPM 2.73E -

N RT-9301' 005 . CPM - - N/A -

RT-93252-12 1.0 X 10mr/hr. N.,. .N/A AREA MONITORS-RT-93250-1. 1.0 X:10Vmr/hr: N RT-93250-2 1. 0.-X '.10 8 mr/hr=

N RT-93250-3' 1.0 X 108'mr/hr N

RT-93250-4 1.0 X.10$ mr/hr N

-RT-93250-5 1.0 X 10mr/hr- N RT-93250-8 1.0 X 105 -mr/hr: N.

-RT-93250-13 2 0 X IF mr/hr

. N i RT-93250-14 4.0 X 105 mr/hr. N RT-93251-1 2.0 X 10' mr/hr' N RT-93251-3: 2.0'X.102 mr/hr-N y RT-93251 1.0 X l'31 mr/hr -N RT-93251 1.0-X 105 mr/hr '. N ,

RT-93251-6 1.0 X 105 mr/hrL N: '

, RT-93251-7 3.0-X 10' mr/hr N "

1. RT-93251-8 1.0:=X 102 mr/hr.: N i L

L

/RT-93251-9 2.5 X .'.0Fmr/hr -N' RT-93252-1 2.5'X 10~'.mr/hr--

N RT-93252-2 1.0 1 -10'imr/hr' N RT-93252-4 1;. 0 : X ; 10 2 mr/hr N

RT-93252-6. 1.5'XL108 mr/hr N RT-93252-7 1.0 Xl105 mr/hrJ 'N' L

EQUIPMENTsMONITORSl 4 7

RT-6314-2= 1.0'X 108 CPM. N --

RT-46211: 5.0 X -- 10 8 -CPM.-

. N RT-46212; (7.0 X 108 CPM N=

METEOROLOGICAL: DATA.

Wind Speed' 3.0 MPH =

l Wind Direction- From 315 Degrees Plume Deviation / Sigma.,Thetai - 4.0 Degrees i

Differential. Temperature 2.2:'F 1

-LFOSAVEX 1

'PAGE 1 ,

. SCENARIO TIME: /~/ > cosci CLOCK TIME:-

0VERALL PARAMETER $'

Reactor Shutdown YES Decay Heat Power 0.05 MW PRIMARY COOLANT-l i

Pressure 10 PSIAj Temperature *

Circulator. Inlet! 95 'F:

Core-Inlet N/A Core Outlet- . .

125 'F.

1 Calculated Bulk Core (CBCT) _ 112:'F Maximum Region Differential (AT) N/A l

Helium Flow Circulator C 0 X 108 Circulator 0= 01X-102' -

TOTAL 0 X 108 Circul'ator Speed i-Circulator C '- ,0~ RPM!

Circulator 0- 0. RPM; Moisture (Oew Point) __

ME-9306' 41 'F

ME-9307

:39 'F SECONDARY COOLANT Emergency Condensate Header:

Flow '

-Loop 1 10-lb/hr;

-Loop 2 -OElb/hr.

EES Inlet Temperature 1

851'F

~

EES Outlet Temperature 1100 *F Pressure 350;iPSIA I

PCRV LINER COOLANT (In Servic'e) ,

Loop.1 N0'

. Loop 2 NO

_t -

gl FOSAVEX-90'  !

PAGE-2= i SCENARIO TIMEi r / 4 ccao  !

CLOCK TIME:~  !

PRIMARY AUXILIARIES -j BOARD.1-01""""*"*"*"""""**"***-  !

GAS-WASTE System-63 Inlet.Sressure 12.3 PSIA.-

Vacuum Tank. Pressure 12.3: PSIA Surge Tank "A" Pressure 200 PSIG

. Surge Tank "B" Pressure :0 PSIG' l:

LIQUID WASTE System 62 NORMAL REACTOR PLANT COOLING ~ WATER System 46 l Loop 1 P-4601 CLEARED OUT P-46015-- .

-CLEARED.OUT Header Inlet Temperature ' CLEARED OUT Barrel and Top Head Outlet.Temptrature CLEARED OUT-Top Penetration Inlet Temperature CLEARED OUT Loop 2 P-4602 0FF' P-46025 CLEARED OUT Header Inlet Temperature - 115 'F Barrel and Top. Head Outlet Temperature 115F Top-Penetratio'n Inlet Temperature -' 1115 'F--

Surge Tank level "A" 0-! INCHES i Surge Tank Level "B"- 45' INCHES i

r i

I

____---__,---_-.-----_1. - _ . - - - - - -

k FOSAVEX-90:

PAGE:31 SCENARIO TIME: 7'/sceM CLOCK TIME: .

l PRIMARY AUXILIARIES'

]

. . . . . . . . . . . . . * * * * * * * * * * * * * * *

• B OA R D I - 0 2 " " " * " " " " " " " " " " * " " : 1 HELIUM STORAGE System 24 Low Pressure Bottles 270 PSIG l High Pressure Botties 575 PSIG- j<

HELIUM CIRCULATOR AUXILIARIES System 21  ;

1 Circulator C-2103 (C) .-.

Bearing Water Flow -0 GPM Bearing Water.-inlet: Temperature 78 *F Main Drain AP 4 PSIO Buffer /Mid-Buffer AP

• 0-PSID Buffer Helium Flow-' 0 ACFM-Buffer Helium Return Flow; 0.ACFM Circulator. C-2104 (D)

Bearing Water Flow -O-GPM:

Bearing Water Inlet Temperature 78 'F Main Drain AP -4 PSID-Buffer /Mid-Buffer AP 0-PSID Buffer Helium-Flow. O ACFM Buffer Helium Return. Flow -:0 ACFM

.................n....******

BOAR D I - 0 3 " * " * " " a * " * " " * " " * " " "

• REACTOR CORE System 12 <

a All Systems NORMAL

............................" BOARD I-051*********************************

HELIUM CIRCULATORS System 21 Circulator C-2103 (C)'

Rotor Speed ODRPM Helium Flow (Low Range) 0;PSID Helium-Flow (High Range) 0%

Circulator C-2104 (0)

Rotor Speed . 0; RPM.

Heitum Flow (Low Range) -0.003'PSIO Helium Flow-(High Range) -0 %

MAIN TURBINE System 51 T

. NORMAL

'1

FOSAVEX-90 PAGE: 4~

SCENARIO TIME:- > / 4 C c3 o i

CLOCK TIME:

PRIMARY AUXILIARIES

..................*********** BOARD-I-06 ************************a*******

MISCELLANEOUS _

Bypass Flash Tank Pressure- .0 PSIG PLANT ELECTRICAL System 92 Essential Bus 1 Bus 2 Bus 3 N/I Bus 3-480 VAC 0 0 0 120 VAC 115 115 0 115-120 VDC 119 117

• "A" "B" ,

Standby Diesel Generator FAILED FAILE0 ACM Diesel Generator CLEARED OUT I

Non-Essential Switchyard . -NORMAL' Bus 1 Bus 2 Bus 3 a' 4160 VAC 0 0: 0-480 VAC 0 MAIN TOWER System 41 DRAINED-SERVICE WATER TOWER System 42. -

NORMAL  !;

i l

FIRE WATER- System 45- NORMAL INSTRUMENT AIR System 82 "A":HDR ="B" HDR 75- .75' SERVICE AIR System 82 95 PSIG'

- ............................* BOARD I-10 ********************************

PLANT PROTECTIVE SYSTEM l

REACTOR BUILDING TEMPERATURE --HIGH Bay 100 80 'F-Bay-200 80 *F Bay 300 80 *F:

I REHEAT-ACTIVITY MONITORS- 005 BUFFER SEAL MALFUNCTION NORMAL

+ --,. , -em.-+ - , ,

FOSAVEX '

PAGE 5 SCENARIO- TIME: T/ *CO30 CLOCK TIME:- ,

PRIMARY AUXILI ARIES:

....................********* BOARD l-13 ********************************

.t PENETRATION. INTERSPACE AP- 0 PSID-s REACTOR BUILDING' SUMP DISCHARGE FLOW 0 GPM ,

HELIUM CIRCULATORS ' System 21 NORMAL- l

. . . . . . . . . . . . . . . . . . . . . . . . . . * *

• B OA R D .1 - 15 . " " i" " " * " * " " * " " * " " * "

REACTOR. BUILDING STACK FLOW. .

0-KCFM

. REACTOR BUILDING. AMBIENT-AP 0-IncFes H20 ,

CONTROL ROOM TEMPERATURE -75L*F t

. . . . . . . . . . . . . . . . . . . . . . . . . . . *

• BOA R D 1 -7 5 0 7 X " " " " " * " " " " " " " " "

-480V ROOM TEMPERATURE 75 'F -

o r  !

l.

.r a

i 3

l. i z_

~f-j' i t

l- , '

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

a ..

LCD 4.1.9 COMPLIANCE SYSTEM 12 DVERVIEV HENU ALARM INHIBITS

~

l START b IS DATA DK FOR FLOV CALC ,, 7 FLOV > 0 7 i_ ND j .. yes ND }f yYES NO DENSITY + DENSITY = >= 27 DRIF. p IS REMAINING

<=107.5% ..--NO <= 60% ..YES IN EQ FLOV 7,

. 'i .iEk. + DATA DK ? ..

g ND y YES yYES y ND REACTOR DDES REACTOR DDES REACTOR V*

PVR EXCEED POVER EXCEED POVER EXCEED RX PRESSURE > 50 PSIA "

LCD 4.1.9-5 YES

' LCD4.1.9-1 LCD 4.1.9-3 CURVE 7 .. CURVE 7 .. CURVE 7 .. V ND ND YES V ND YES V ND YES if IN EQUAL FLOV 7 ..

LN/A N/A N/A --

V V V VYES ND V IS FLDV >= IS FLOV >= ARE e T'S <= ARF, ALL ARE ALL LCD4.1.9-1 LCD 4.1.9-3 LCD 4.1.9-5 REGION AT'S REGION AT'S CURVE 7 CURVE 7 ,, <= 600 DEG F," <= 350 DEG F,

_' CURVE-? ,,

~

ND ND ND ND ND yYES 3 RYES 3 RYES 3 fYES fYES V V V _j f _ . V 4

-> IS REACTOR SHUTDOVN 7 4-

! E y ND -hym 37 URIF CAN REQ FLOV ENDUGH FLOV NIC, , FLDV > 0 7 BE DETERMINED,.YES FOR CMG-25 7 .

g ,g. N.YES EQ FLOV7..YES ND l r.lF.CK H!Pu r IS. INITIAL. DECAY HEAT AVAILABLE 7 ,

,4 y gg "V

YES < 760 DEG F 7,d EXECUTED:

11/ 07/ 90 CMG4 TIME TD 760 i N/A FOR p ND y 8: 34: 14 tgp 4--- DEG F EXPIRED 7

,, NU 335.1 HRS ,,lN/A NIC, ,

YES

. . . _ ._ . _ _ . . _ _ _ - __ . _ . _ _ m. . .

. 4 FOSAVEX-90 SCENARIOiTIME: ~

Thih- ' "

CLOCK TIME:-

t RADIATION MONITORS: ,

.J.

'VALUE' ALARMING' -SENSITIVITY: -.

NUMBER.

7,0 X 108 CPM N- 2,2E-8 RT-6212 E2,2E-B-8.0 X 108 CPM' N RT-6213 i AT-7312 005 CPM N/A.

2,0 X 105 CPM N 1.57E-8 RT-7324-l' -4.36E-7 RT-7324-2 2,0 X 105 CPM: N'

'1,49E RT-7325-1 1.0 X 108 CPM N 1,0 X 101~mr/hrL -N EN/A-

.T-7325-2 2.51E RT-73437-1 1.5 X 102 CPM, N 4.0 X 1;2 0 CPM N- 2,73E ,

RT-73437 005 CPM N/A -

RT-9301 LN/A 1.0 X 105 mr/hr - N-.

RT-93252-12 AREA MONITORS RT-93250-1 l',0 X 108 mr/hr 'N l

RT-93250-2 1,0 X 101 mr/hrf 'N-RT-93250-3 1.0 X-10' mr/hr N" RT-93250-4 1.0 X 108 mr/hr N- i RT-93250-5 1,0'X-101:mr/hr; N!

RT-93250-8 1.0 X 101 /mr/hr Ji RT-93250-13 2.0 X 105 -mr/hr iN RT-93250-14 4,0 X 105 mr/hr - N --

a.

RT-93251-1 ~2,0 X'108 mr/hr N.

RT-93251-3 2;0 X-10*!mr/hr- N #

RT-93251-4 1.0;X~102 mr/hr- N RT-93251-5 1.0 X 105 mr/hr' 14 '

RT-93251-6 l'.0*X 105 mr/hr N RT-93251-7 -3.0 X.102 mr/hr .N1 RT-93251 1,01( 105 mr/br :N-RT-93251-9 2,5 X 102 mr/hr :N-RT-93252-1 2.5X 105 mr/hr: 11-

't RT-93252-2 1,0;X 10' mr/hr - 11 RT-93252-4: 1.0 X 10l mr/hr. N RT-93252-6 1.5 X 105 .mr/br: 44

" 1.0LX-10 mr/hri N; RT-93252-7

= EQUIPMENT MONITORS ,

RT-6314-2' 1.0-X 108 CPM;

- N

-5.0 X 105 CPM- N RT-46211

.7.0 X 10 : CPM N RT-46212

]

METEOROLOGICAL-DATA ,

Wind Speed .3.0 MPH Wind Direction From; '315.0egrees Plume Deviation / Sigma Theta 4.0 Oegrees Differential Tempe ature r ~2.2 *F,' ,

a r ., .- , , , , , . , , . . . , - . .. . , .,., n -. ,,- . ,.

l q

=FOSAVEX-9b= .

i PAGE l'

-l SCENARIO TIME: T/-oovy l

-l CLOCK TIME: q 9

OVERALL PARAMETERS-- ,j Reactor Shutdown - YES Decay Heat Power- 0.05 MW q

PRIMARY COOLANT t

Pressure 10,5< PSIA-Temperature Circulator Inlet 95.*F Core Inlet N/A Core Outlet 125.*F.

Calculated Bulk Core (CBCT) 113 *F' Maximum Region Di_fferential (AT)- N/A-Helium Flow . .  ;

Circulator C 0 X-103 Circulator-D 'OLX 103 TOTAL 0,X1108 Circulator Speed ,

Circulator C

~

l0 RPM.

Circulator D 0 RPM-- c- j

-i Moisture-(Oew Point) i HE-9306 41 *F

-ME-9307 39;* Fi  !

SECONDARY COOLANT Emergency Condensate = Header Flow-Loopc1 0-lb/hr Loop 2 0-lb/hr-EESl Inlet Temperature ~ '85-*F-EES Outlet Temperature 4100:*F

' Pressure- -350. PSIA-PCRV_ LINER COOLANT -(In Service)

Loop 1 ~NO Loop 2 NO

' [' 'S _'_

____i_______i________._1_'___ ._

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

~. . . . ..

--FOSAVEx-903 PAGE'2-

-SCENARIO TIME: r/+o64-' Ci

. CLOCK TIME:.  !

y PRIMARY AUXILIARIES l

. . u . . . . . . . . . . . . . . . . . . . . . . . * * - B O A R D - I - 01 ' * " " " * " " " " " " " " * " " "

r

System 63 GASJWASTE  :

Inlet: Pressure 12.3 PSIA:  :*

Vacuum Tank. Pressure ~12.3 PSIAi Surge' Tank A" Pressure 200:PSIO

. Surge Tank "B" Pressure.-

04PSIG: W A

. LIQUID WASTE _ System 62: ' NORMAL :-

REACTOR PLANT. COOLING WATER > JSystem 46 -

1 Loop 1 i

' P-4601:

CLEARED OUT :

P-46015- CLEAREDLOUT j Header Inlet. Temperature.  : CLEARED OUT Barrel and Top' Head Outlet: Temperature = 1 CLEARED OUT Top Penetration-Inlet Temperature CLEARE0;0UT.

s

'l

-Loop 2 P-4602 10FF P-46025 . CLEARED OUTi Header. Inlet Temperature 115 'F- '

' Barrel and-' Top Head Outiot Temperature :115.'F Top: PenetrationfInlet(Temperature '- .115i'Fu i Surge Tank Level "A" 0 INCHES; SurgenTank Level "B" 45 INCHES:

)

I 3

9 l

-e

)

, ,, w y - ,- , , - , - . .# J- _ , ,,.m.4,. . -.4- . , , , , ,r . . . . . . - , .1,,.. a -,

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

FOSAVEX-90)

PAGE SCENARIO TIMEi rf, c<Nh

, CLOCK TIME:

PRIMARY AUXILIARIES

......................*****"BOARO.I-02"*"""*"""**"""""""

HELIUM STORAGE -

System 24 Low Pressure Bottles. 270'PSIG High Pressure Bottles 575 PSIG HELIUM CIRCULATOR AUXILIARIES. - System 21  !

Circulater C-2103 (C) -

Bearing Water Flow 0.GPM Bearing Water Inlet Temperature 78 *F Main Drain AP 4.PSID.

Buffer /Mid-Buffer AP 0 PSID Buffer-Helium Flow , O ACFM Buffer Helium Re+ urn Flow 0 ACFM' Circulator C-2104 (D)

Bearing Water Flow . _

-0 GPM i Bearing Water Inlet Temperature 78F Main Drain AP 4 PSID Buffer /Mid-Buffer-AP O PSID--

Buffer Helium Flow 10 ACFM Buffer. Helium Return Flow- 0-ACFM

. . . . . . . . . . . . . . . . . . . . . . . . . . . .

• B 0 A R D ' I - 0 3' * " " " " " " " " " " * " " * " * "

REACTOR CORE System 12- < l All Systems NCRMAL

...................********** BOARD I-05 *********************************

HELIUM CIRCULATORS System 21 CirculatorC-2103(C)

Rotor Speed -

0 RPM-Helium Flow (Low Range) _

0 PS!D' i Helium _ Flow (High Range) 0 *.'

Circulator _C-2104-(0) '

Rotor Speed .. '0-RPML Helium Flow (Low Range) -0.003 PSID

' Helium Flow (High Range)- OS MAIN' TURBINE ' System 51 -NORMAL

~

w -

rk i *r- ei - -- 4 - e 'w - * - * - ie = t

FOS AVEX-90 '-

PAGE 4, -,

. SCENARIO-TIME: 7~/

• Sob CLOCK TIME:

PRIMARY AUXILIARIES

. . . . . . . . . . . . . . . . . . . . . . . . . . *

• BO A R D ' I - 0 6 " " " " " " " " " " " a a " " * " * -

MISCELLANEOUS -- '

Bypass Flash Tank Pressure O PSIG , i PLAkT ELECTRICAL.- System 92 _l 1

N/I Bus 3-Essential _.

' Bus 1- ' Bus 2- Bus 3-

• 480 VAC 485 :485: . ..

120 VAC. -- 118 : 115- 118- -118-  !

120L:VOC- 125' 117--

. . "A" "B"J =

Standby Diesel Generator NORMALx -FAILED ACM Diesel Generator '

CLEARED OUT Non-Essential Switchyard . NORMAL LBus-1 iBus 2-- Bus 3 4160 VAC 0- 0 0 1 480 VAC- 0 l MAIN TOWER -System 41-

~0

.- RAINED- ,

1 SERVICE WATER TOWER System 42- _<_ NORMAL  !

i' FIRE WATER System.45 NORMAL:

INSTRUMENT AIR System 82 "A"iHDR "

B"-HDR.

193' '75 1 SERVICE AIR System-82' 95 PSIG.

..............................B0ARD:1-10 ******************************** '

PLANT PROTECTIVE SYSTEM REACTOR BUILDING TEMPERATURE - HIGHT ~

Bay 100 '80 *F:

l Bay 200: 80 *F Bay 300. 80 'F

~ REHEAT ACTIVITY MONITORS 005 BUFFER SEAL MALFUNCTION NORMAL =

i

o FOSAVEX-90 'ic _

- PAGE 5~

-SCENARIO TIMER y /,a c d r CLOCK TIME:

I

'a. MARY AUXILIARIES

........n.................** BOARD 'I - 13 ' " " "" " " "" * * "" * "" " " * -

- PENETRATION INTERSPACE 6P -

O PSIO ,

REACTOR BUILDING SUMP OISCHARGE . FLOW 0 GPM HELIUM CIRCULATORS System 21 NORMAL-

.........................**** BOARD I-15.********************************  ?

REACTOR BUILDING STACK FLOW -15.0 KCFM-REACTOR BUILDING-AMBIENT AP' J-Oi25InchesH2O~ -r n

i CONTROL ROOM TEMPERATURE 75 'F l

. . . . . . . . . . . . . . . . . . . . . * * * * * * *

• BOAR D ' I - 7 5 0 7 X " " " " " " " " " " " " * " " ~

- 75 'F 2 480V ROOM TEMPERATURE- [

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

~. - .- . . - .

L

+

.FOSAVEX-90: i

~

SCENARIO TIMEi - -rMAoo:

-CLOCK TIME:-

RADIAT!0N MONITORS:

NUMBER' VALUE -ALARMING SENSITIVITY- 'l RT-6212- 7.0 X-108-CPM: IN ~ 2.2E-8 :

RT-6213 - 3,0 X 108 CPM Ni '2.2E-8 RT-7312 005 CPM' N/A. 4 RT-7324-1 -

. 2.0 X 108. CPM N. J.1. 57 E-81 RT-7324-2 ' 2.0 X 101 CPM- N -4.36E-7 J RT-7325-1 1.0 X 108 CPM , -N , .1,49E-5 4 RT-7325 1.0 X-108 a r/hr N- N/A RT-73437-1 1.5 X 108 JCPM- -N '2.51E-10 RT-73437-2 4.0 X.101 CPM N 2.73E-10 .

RT-9301 005- CPM N/A~ .i RT-93252 1.0 X'105 mr/hr N D, - N/A ] .

AREA MONITORS y RT-93250-1 1,0 X 105 mr/hr N-RT-93250-2 1.0 X 108 mr/hr- N RT-93250-3 1.0 X 105 mr/hr- 11 '

RT-93250 1.0 X-103 mr/hr- N' RT-93250-5 1.0 X 108 mr/hr' N.

RT-93250-8 - 1.0 X 108 mr/hr: N; RT-93250 2.0 X 105 -mr/hr ,N RT-93250-14. 4.0 X 105 mr/hr- =N:

RT-93251-1 2.0 X 102 mr/hr !N RT-93251-3 2.0 X 108 mr/hrL ~N ,

RT-93251-4 1.0LX-102 mr/hr! Ns RT-93251-5 1.0.X 102 mr/hr N' i-RT-93251-6 - 1 .0 'X liO5 mr/hr= .N

-RT-93251-7: 3.0 X 105 mr/hr 14 RT-93251-8 1.0 X 101~mr/hr' N RT-93251-9 2.5 X 105 mr/hr N RT-93252-1 2.5 X-105 mr/hr ins >

RT-93252-2 - l'0-X:10' mr/hr- 11J J RT-93252-41 1.0 X 102 mr/hr 14 RT-93252-6  : 1.5 X:10' mr/hr Ni  ;

RT-93252-7 1.0 X 1051mr/hr N EQUIPMENT MONITORS 3

RT-6314-2 1.0-X.108. CPM: 14 RT-46211 5.0 X-101 CPM- N -

RT-46212- 7.0 X 10! CPM N METEOROLOGICAL DATA' Wind Speed ,

3.0 MPH From:;315 Degrees '

Wind DirectionL Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature. >

2i2 ?F:

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i FOSAVEX-90 '

PAGE:1:

, SCENARIO TIME: 7-/,, o <oo ; ,

CLOCK T_IMEi

L OVERiLL PARAMETERS: -;

Reacter Shutdown YES Decay Heat Power _ 0.05 MW~

PRIMARY-COOLANT' ll: PSIA-  !

Pressure Temperature- _ _

Circulator Inlet 95;*F:

Core-Inlet-iN/A' Core Outlet 1 .

125 'F ,

Calculated Bulk:-Core' (CBCT) .'114 'F' ,

Maximum Region' Di f ferenti_al_--( AT). N/A  ;

Helium Flow '

Circulator-C- (01X 108_-

Circulator D '0iX 10' .

TOTAL 1 0"X1108 ,

Circulator Speed

., 7 Circulator C. ;0: RPM Circulator D 0. RPM' .

Moisture (Oew Point)- '

ME-9306 i 41.

• F - l ME-9307 l 39f

• F L: 1 SECONDARY'C00LANT' Emergency Condensate H uder-

, Flow .

Loop 1; OLib/hr

- Loop.2- '0 lb/br--

EES In,.let' Temperature --85 'F-EES Outlet Temperature: 100 *F

-Pressure --350 PSIA: 'j e

)

PCRV LINER COOLANT _(In_ Service)

Loop 1- NO Loop 2'- '

YES a

,?*

'J:'

t

-.s. * -

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s FOSAVEX-90L s lPAGE 2 H J

~ SCENARIO TIMEi v f o/cc ; -i

, , CLOCK TIME:

' PRIMARY AUXILIARIES- ,

' ~

.....u........******"****** BOA RD I -01. " * " " " " * "" " " " " * " ""

• i GAS WASTE System 63 q Inlet Pressure 10 PSIA _ m 'a l Vacuum Tank: Pressure- 8 PSIA j Surge-Tank."A". Pressure 205 PSIG' a Surge Tank .B" Pressure.

. :0 PSIG= q i

LIQUID WASTE System 62 JNORMAL' u REACTOR. PLANT- COOLING WATER System .46' .

Loop 1 P-4601 CLEARED OUT P-4601S - CLEARED 0UT Header Inlet Temperature- _.

' CLEARED OUT.

Barrel and Top Head Outlet TemperatJre  : CLEARED OUT- ,

Top Penetration Inlet Temperature'

~

CLEARED-00T. .

]

Loop 2 P-4602 'ON _

P-46025: CLEARED OUT J Header l Inlet Temperature .

115 *F- 0 Barrel and Top Head' Outlet _ Temperature-

--115 'F- ,

' Top Penetration: Inlet Temperature '

115 *F  :

Surge Tank. Level'"A" '0-LINCHES -

Surge Tank Level '.'B" 45 INCHES'. s q

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T I .

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.s.. . _ , - ,. 4.-. ,-- - ,-

-Fv5AVEX-90'

. PAGE-3

' SCENARIO TIME: c / + c oc-CLOCK TIME:-

PRIMARY AUXILIARIES j

.......................****** BOARD I-02 ********************************

HELIUM STORAGE' System 24-Low Pressure Bottles 270 PSIG High Pressure Bottles-

.575 PSIG l

HELIUM CIRCULATOR AUXILIARIES System 21  !

1 1

Circulator C-2103-(C)_ .

Bearing Water Flow- 0 GPM Bearing Water-Inlet Temperature ~ 78 'F:

Main Drain AP '

4 PSID Buffer /Mid-Buffer AP .0 PSIO-Buffer Helium-F'ow. 0-ACFM-

.Buf fer Helium Return Flow 0 ACFM-

. Circulator C-2104-(D)

Bearing Water Flow 0 GPM-Bearing Water Inlet Temperature =78 'F Main Orain AP 4 PSID Buffer /Mid-Buffer AP 0 PSID Buffer Helium Flow ACFM Buf fer Helium: Return Flow 10 ACFM ,

..............n......n..... BO ARD I-0 3 ' " " * "" * * """ " "" " * * " " "

4 REACTORcCORE System-12' .

All Systems NORMALi ,

............ ..n.........."*

BOARD!:205"""*"""""""""""""

WELIUM CIRCULATORS Sys?.es ?.(

V \

Circulator C-2103=(C) .

Rotor Spe2d 0 RPM:

Helium- Flow f(' Low- Range) +- 0-PSIOL n Helium Flow (Hign; Range)l 0 4% -  !

Circula:or C-2104 (0)

Rocor Speed ' 0: RPM-Helium Flow (Low: Range)- -0.003 PS10- '

Helium Flow-(High' Range) -0%

MAIN TURBINE -System 51) NORMAL

.t 1

l

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

5

.FOSAVEX-90--

, 'PAGE 4'

--l SCENARIO TIME: 7 / + o/co CLOCK TIME:

PRIMARY AUXILIARIES ,

l

................************* BOARD 1-06"""""*""""***"***"*"

MISCELLANEOUS- -

Bypass Flash Tank Pressure- 0.PSIG PLANT ELECTRICAL- . -System 92

' Essential' Bus l~ Bus: 2.; Bus.3: 2 N/I Bus 3 480: VAC- 435= 485: 485-- .

Y 9 120 VAC 118 118' '118 118-120 VDC- -125 125- i v "

A""

" B'?

Standby Diesel Generator NORMAL FAILED-ACM Diesel Generator- CLEARED 0UT Non-Essential 1

Switchyard NORMAL Bus 1- Bus.-2 Bus 3  !

4160 VAC 4160- 4160 41601 480 VAC NORMAL MAIN TOWER System 41 OAINED)

~

SERVICE WATER TOWER System.42 '-

NORCAL FIRE WATER System 45- NORMAL INSTRUMENT AIR System 82 n"A"'HDR i"B"3HDRE

93 - 93.

SERV'CE AIR System 82 95.PSIG '

............................. B0ARD-I-10 ********************************

PLANT.-PROTECTIVE. SYSTEM REACTOR BUILDING TEMPERATURE - HIGH Bay-100- 80 'FJ 1 Bay.200 80 'F.

l- Bay-300 80 *F REHEAT ACTIVITY. MONITORS 005: ,

BUFFER SEAL' MALFUNCTION NORMAL l 1

.i l .

3 5

, ,, . , . ~ . , +. _, - ~,-x - g -,,,n

FO$AVEX-90 PAGE 5 SCENARIO TIME: -"/

• c e c CLOCK TIME:

PRIMARY AUXILIARIES

.......... ...............*** BOARD I-13 ********************************

PENETRATION INTERSPACE AP 0 PSID ,

REACTOR BUILDING SUMP DISCHARGE FLOW 0 GPM HELIUM CIRCULATORS System 21 NORMAL

............................. BOARD I-15 ********************************

REACTOR BUILDING $ TACK FLOW , 29.9 KCFM REACTOR BUILDING AMBIENT AP -0.25 Inches H2O CONTROL ROOM TEMPERATURE 75 'F

............................. BOARD I-7507X *****************************

480V ROOM TEMPERATURE 75 'F

/

LCD 4.1.9 COMPLIANCE SYSTEM 12 DVERVIEV MENU ALARM INHIBITS

[ START.

- - b IS DATA DK FDR FLDV CALC d_ yes> FLOV > 0 7_m i W V VE E DENSITY + DENSITY - >= 27 URIF. p

<=107.5% ., Na

<= : 60% H YES IN EQ FLDV 7 ..,

[' 4- IS REMAINING g ND DATA UK ? g VM V " VW REACTDR DDES REACTOR DDES REACTOR Y PVR EXCEED POVER EXCEED POVER EXCEED RX PRESSURE > 50 PSIA LCD 4.1.9-5 YES LCD4.1.9-1 LCD 4.L9-3 CURVE 7 .. CURVE 7 ,, CURVE 7 V W ARE ALL 37 DRIFICES m mV ta m V ND m V IN EQUAL FLOV 7 .,

N/A N/A N/A 1 j

V V V VYES 70 Y IS FLOV >= IS FLOV >= ARE AT'S <= ARE; ALL ARE ALL

- LCD4.1.9-1 LCD 4.1.9-3 LCD 4.1.9-5 REGION AT'S REGION AT'S CURVE 7 ,, CURVE 7 ,, CURVE 7 ,, <= 600 DEG F." , <= 350 DEG F." , l yYES 70 yYES ND yYES ND

~yYES ND yYES NO

~

IC [ICl IC IC IC y y _ . . _ _ _ _ __ _

______._.____4 p, #

IS REACTOR SHUTDOVN 7 4G-

- >1 --

E

'V T 37 DRIF CAN REQ FLOV ENDUGH FLOV NIC, , FLOV > 0 7 .N EQ FLUV7 -. " N g- CMG-2

+y m- " y Na BE +DETERMINED.,N"No

,,FOR d4 IS INITIAL DECAY MEAT AVAILABLE 7 y l CliEi?K IMPUI a& No YES

< 760 DEG F 71

1. V -

EXECUTED:

CMG4 TIME TU 760 i N/A FOR 1P WV 1_ ___ ___-

11/ 07/ 90 "

8: 34: 14 4- DEG F EXPIRED 7 334.6 HRS , , N/A NIC1

.N.p

"" IU " -

YES

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

\

F05AVEX-90 <

i i

! SCENARIO TIME: 77 t/zzr l CLOCK TIME: i i

RA0!ATION MONITOR $:  !

NUMBER VA!.UE ALARMING . SENSITIVITY--  !

2.2E-8  !

! RT-6212 7.0 X 105 CPM N RT-6213 8.0 X 108 CPM N 2.2E-8 ,

RT 7312 00$ CPM N/A #

RT-7324-1 2.0 X 105 CPM N -. 1.57E-8 1 RT 7324-2 2.0 X 108 CPM N 4.36E .i RT-7325-1 1.0 X 108 CPM N- 1.49E-5 1.0 X 108 mr/hr N/A RT-7325-2 N '

RT-73437-1 1.5 X 108 CPM N 2.51E  :

i RT 73437-2 4.0 X 105 CPM N -2.73E-10 ~

RT-3301 005- CPM .

N/A +.

RT-93252-12 1.0 X 108 mr/hr N, N/Al AREA MONITORS i 1.0 X 10 mr/hr RT-93250-1 N RT-93250-2 -1.0 X 108 mr/hr: N RT-93250-3 1.0 X-108 mr/hr N k RT 93250-4 1.0 X 105 mr/hr N RT-93250-5 1.0 X 108 w/hr N -

l RT-93250-8 1.0 X 101 inr/hr N RT-93250-13 2.0 X 108 mr/hr N RT-93250-14 4.0 X lui mr/hr N i RT-93251-1 -2.0 X 105 mr/hr N RT-93251-3 2 u X 102 mr/hr .N ,.

RT-93251-4 1.0 X 108 mr/hr N .

-RT-93251-5 1.0 X 105 mr/hr- N l RT-93251-6 1.0 X 108 mr/hr N--

RT-93251-7 3.0 X 102 mr/hr N RT-93251-8 1.0 X'101 mr/hr N

, - RT-93251-9 2.5 X 102 mr/hr' .N RT-93252-1 2.5 X 103 mr/hr. N -

RT-93252 1.0 X"10' mr/hr N RT-93252-4 1.0 X 103 mr/hr N RT-93252-6 1.5 X~108 mr/hr N RT-93252-7 1.0 X 105 mr/hr N

EQUIPMENTliON! TORS RT-6314 1.0 X'108 CPM N .

RT-46211 '5,0 X-10n CPM- N RT-46212 :7.0.X: 103. CPM. N' L t

METEOROLOGICAL DATA t i

Wind Speed 3.0 MPH Wind. Direction -

From 315 Degrees i Plume-Deviation / Sigma _ Theta; ~4.0 Degrees-  !

Differential Temperature ..- , _2.2.'F:

~

~

s t

1

. - - - _ _ . ~. -

FOSAVEX ~'

c?

PAGE 1 SCENARIO TIME: 7i+c^'

CLOCK TIME:

OVERALL PARAMETERS Reactor Shutdown YES Decay Heat Power 0,05 MW PRIMARY COOLANT Pressure 11 PSIA Temperature "

Circulator Inlet 98 'F Core Inlet 105 'F Core Outlet 128 'F Calculated Bulk Core (CBCT) N/A Maximum Region Differential (AT) 2B 'F Helium Flow Circulator C 10 X 108 Circulator D 0 X 108 TOTAL 10 X 108 Circulator Speed circulator C '

2900 RPM Circulator 0 0 RDM.

Moisture (Oew Point)

ME-9306 41 "F ME-9307 39 'F SECONDARY COOLANT Emergency Condensate Header Flow Loop 1 0 lb/hr Loop 2 2.0 X 10' lb/hr EES Inlet Temperature S5 'F EES Owtlet Temperature 100 'F Pressure 350 PSIA PCRV LINER COOLANT (In Service)

Loop 1 NO Loop 2 YES v

F05AVEX-90 PAGE 2 SCENARIO TIME: T/ + c w r

-x CLOCK TIME:

PRIMARY AUXILIARIES i

............................. BOARD I-01 ********************************

GAS WASTE System 63 1

Inlet Pressure 10 PSIA Vacuum Tank Pressure 8 PSIA Surge Tank "A" Pressure 205 PSIG Surge Tank "B" Pressure O PSIG LIQUID WASTE System 62 NORMAL REACTOR PLANT COOLING WATER System ,46 Loop 1 i P-4601 CLEARED OUT .

F-46015 CLEARED OUT Header Inlet Temperature CLEARED Ol'T Barrel and Top Head Outlet Temperature CLEARED OUT Top Penetration Inlet Temperature CLEA9ED OUT Loop 2 P-4602 ON P-46025 CLEARED OUT Header Inlet Temperature 115 'F ,

Barrel and Top Head Outlet Temperature 115 'F '

~

Top Penetration Inlet Temperature '

115 'F i

Surge Tank Level "A" 0 INCHES Surge Tank Level "B" 45 INCHES i

l

f05AVEX-90

-PAGE 3' ,

SCENARIO TIME:

T"/- o- {

CLOCK TIME: _

PRIMARY AUXILIARIES

............................. BOARD'l-02 ********************************

HELIUM STORAGE System 24 Low Pressure' bottles-High Pressure Bottles 270 PSIG 575-PSIG HELIUM CIRCULATOR AUXILIARIES- System 21 '

Circulator C-2103 (C)

Bearing Water Flow-Bearing Water Inlet Temperature 170 GPM Main Drain AP 78 'F Buffer /Mid-Buffer AP

• 2.5 PSIO Buffer Helium Flow 8 PSID Buffer Helium Return Flow 7.40 AC/M.

3.79 ACFM

+ Circulator C-2104 (0)

Bearing Water Flow Bearing Water Inlet Temperature 0 GPM Main Drain AP 78 'F-Buffer /Mid-Buffer AP- 4 PSIO.

Buffer Helium Flow 0 PS10 0 ACFM Buffer Helium Return Flow .

0 ACFM I

-............................. BOARD 1-03""*""*"""*""""*"""-

REACTOR CORE System-12 '

All Systems NORMAL

............................. BOARD-I-05 *****************************"'**

HELIUM CIRCULATORS System 21  !

i Circulator C-2103 (C) i Rotor Speed ,

Helium-Flow (Low Range)- 2900 RPM- '

Helium Flow (High Range) 0.020 PSID 0W '

CirculatorC-2104(0)

Rotor Speed -

Helium Flow Low Range). 'O RPM ,

Helium Flow.((High Range)- -0.003 PSID-i 0i i MAIN TURBINE System 51 '

NORMAL. .

____ 1q .

FOSAVEX-90 PAGE 4 SCENARIO TIME: -r/- C' f CLOCK TIME:

PRIMARY AUXILIARIES

....u.....u...............* BOARD I t06 " * " """ *""""""""""

MISCELLANEOUS Bypass Flash Tank Pressure ' O PSIG i

PLANT ELECTRICAL System 92 i Essential Bus 1 Bus 2 Bus 3- N/I Bus 3 480 VAC 485 485 485 120 VAC 118 118 118 118-120 VDC 125 125 "A" "B" Standby Diesel Generator NORAAL FAILE0-ACM Oiesel Generator CLEAREO OUT-

? a

Non-Essential Switchyard .

. NORMAL .

Bus 1 Bus 2 Bus 3 4160 VAC 4160 4160- 4160 480 VAC NORMAL-MAIN TOWER System 41 ORAINEO SERVICE WATER TOWER System 42 NORMAL FIRE WATER System 45 NORMAL-INSTRUMENT AIR System B2 "A" HOR "B" HOR 93 93; a

l SERVICE AIR System 82 1 :95 PSIG

............................*-BOARO I-10=********************************/

' PLANT PROTECTIVE-SYSTEM ~

REACTOR BUILDING-TEMPERATURE - HIGH!

Bay 100 + -80 *F m

Bay 200 80 'F B3y 300- 80 *F-j REHEAT ACTIVITY FONITORS 005 l

p BUFFER SEAL-MAGUNCTION NORMAL l

~~

A

FOSAVEX-90 PAGE 5 SCENARIO TIME: -/ -re6 CLOCK TIME:

PRIMARY AUXILIARIES

............................* BOARD I-13 ********************************

PENETRATION INTERSPACE AP O P510 REACTOR BUILDING SUMP DISCHARGE FLOW 0 GPM HELIUM CIRCULATORS System 21 NORMAL

............................* BOARD I-15 ********************************

REACTOR BUILDING STACK FLOW 29.9 KCFM REACTOR BUILDING AMBIENT AP -0.25 Inches H2O CONTROL ROOM TEMPERATURE 75 'F

............................' BOARD I-7507X *****************************

480V ROOM TEMPERATURE 75 'F l

I l

l I

=

LCD 4.1.9 COMPLIANCE SYSTEM 12 DVERVIEV MENU ALARM INHIBITS

[ START

+ IS DATA UK FOR FLOV CALC i ,gg

- FLOV > 0 7 .,..NU E DENSITY DENSITY >= 27 DRIF. p NU y ,y y YES

+ m 4_ IS REMAINING

<=107.5% ., ND <= 60% . ,'YES IN EQ FLOV 7 .. ,

= .. 2 '

E ND DATA UK ? .,

yYES yYES y ND t REACTOR DDES REACTOR DOES REACTOR V V PVR EXCEED POVER EXCEED POVER EXCEED RX PRESSURE > 50 PSIA "

LCD4.1.9-1 LCD 4.19-3 LCD 4.1.9-5 YES CURVE 7 ., CURVE 7 ., CURVE 7 g VN ARE ALL 37 DRIFICES ND YES V ND YES V ND YES V IN EQUAL FLOV 7 .,

N/Al V lN/Al N/A V V VYES ND V Y-IS FLOV >= IS FLOV >= ARE AT'S <= ARE ALL ARE ALL LCD4.1.9-1 LCD 4.1.9-3 LCD 4.1.9-5 REGIDN AT'S REGIDN AT'S CURVE 7 ., CURVE 7 ., CURVE 7 ., <= 600 DEG F." , <= 350 DEG F, ,

y RYES ND 3 yYES' ND 3 yYES ND 3 yYES ND YES NU lIC lf IC l IC l IC l IC lf lf lf lf I

->1 IS REACTOR SHUTDOVN 7 l4-g UND yYES 37 DRIF CAN REQ FLOV ENDUGH FLOV NIC. , FLOV > 0 7 . EQ FLOV7 - BE DETERMINED FDR CMG-25 7 ,

VND y ND y NU YES g

CHECK II

PUT ,4 - IS INITIAL DECAY HEAT AVAILABLE 7 ,f y ND YES < 760 DEG F 7 EXECUTED V --

-11/ 07/ 90 CMG4 TIME TD 760 m N/A FOR PES ND y 4

9: 32: 37 t@ 4- DEG F EXPIRED 7 #### HRS .. . , N/Al l NIC...,

yES ,,

.. ND

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

-1 FOSAVEX-90

! - SCENARIO TIME:-- r/4 / 30 I

CLOCK TIME:-

RADIATION MONITOR $:

. NUMBER VALUE ALARMING $ENSITIVITY RT-6212 - 7.0 X 108 CPM N. 2.2E l

! RT-6213 8.0 X 108 CPM N 2.2E-8 RT-7312 00$ CPM 'N/A- )

RT-7324-1 2.0 X 108-CPM N 1.57E RT-7324 2- 2.0 X 108 CPM N ~4.36E RT-7325-1 1.0 X 108 CPM N 1.49E-5 RT-7325-2 .1.0 X-108 mr/hr. . N- N/A RT-73437-1 1.5 X.108 CPM N 2.51E-10 RT-73437-2 4.0 X 108 CPM N 2.73E-10 1

RT-9301 00$ CPM, N/A -

RT-93252-12 1.0 X 108 mr/hr- N . N/A-1 AREA MON! TORS-

]

RT-93250 1.0 X 108 mr/hr N RT-93250-2 1.0 X 108 mr/hr .N

- RT-93250-3 1.0 X 108 mr/hr N RT-93250-4 ~ 1.0 X 108 mr/hr . N: -

RT-93250-5 1.0 X 108 .mr/hr - N. o-

! RT-93250-8 1.0 X 108'mr/hr -N RT-93250-13 2.0 X 105 mr/hr N RT-93250-14. 4.0 X 108 mr/hr N RT-93251-1 2.0 X 108 -mr/hr- N.

RT-93251-3 2.0 X 10l N: ,

l RT-93251-4 1.0 X 108- mr/hr mr/hr N RT-93251-5 1.0 X 108 mr/hr N- '

i RT-93251-6 1.0 X 108'mr/br N l RT-93251-7 3.0 X 108 mr/hr N RT-93251-8 1 0 X 108 mr/hr N RT-93251-9 2,5 X 108 mr/hr -N RT-93252-1 2.5 X 108 mr/hr N RT-93252-2 1.0'X 10' mr/hr N RT-93252-4 1.0 X 108 mr/hr  : N

- RT-93252-6 . 1.5 X 108 mr/hr- N-RT-93252-7  :

1.0 X 108 mr/hr. N EQUIPMENT. MONITORS RT-6314-2 1,0 X 108 CPM N RT-46211 - 5.0 X 10.8 - CPM N-RT-46212- - 7.0 X 108~ CPM - N-METEOROLOGICAL DATA  :

Wind. Speed _ .- 3.0 MPHL

' Wind'Oirection- From--315 Degrees Plume Deviation / Sigma Theta- 4-0; Degrees;

-Differential Temperature: - 2.2 'F m+ 4ses-e--=&--- e m. -,...v+ .me - -e e es.v e d- -, e,- w ww. ar w w w ee.- ww -ww r -o

• V r ee e++=' * * = * - y s**J9-- v6 ww'*ee~ 9 . t1 + N W P-~ tv+r----k

FOSAVEX-90 PAGE 1 SCENARIO TIME: 7 / s c> to CLOCK TIME:

OVERALL PARAMETERS Reactor Sh';tdown YES Decay Heat Power 0.05 MW PRIMARY COOLANT Pressare 11 PSIA Tempe ra ture Circulator Inlet 98 'F Core irlet 105 'F Core outlet 128 'F Calculated Bulk Core (CBCT) N/A Maximum Region Differential (AT) 28 'F Helium Flow Circulator C 10 X 108 Circulator 0 0 X 108 TOTAL 10 X 108 Circulator Speed ,

Circulator C 2900 RPM Circulator 0 0 RPM Molsture (Dew Point)

ME-9306 41 'F ME-9307 39 'F SECONDARY COOLANT Energency Condensate Header Flow Loop 1 0 lb/br Loop 2 2.0 X 10' lb/hr EES Inlet Temperature 85 'F EES Outlet Temperature 100 #F Pressure 350 PSIA PCRV LINER COOLANT (In Service)

Loop 1 NO Loop 2 YES i

F05AVEX-90  !

PAGE 2

) l l SCENARIO TIME: r /

• cw i 1

. CLOCK TIMEi i PRIMARY AUXILIARIES

+

i

. . . . . . . . . . . . . . . . . . . . * * * * * * * *

• B O A R D I - 01 " " " " " " " " * " * " * * " " " "

• f GAS WASTE System 63 ,

Inlet Pressure 10 PSIA l Vacuum Tank Pressure 8 PSIA o Surge Tank "A" Pressure 205 PSIG- 4 Surge Tank "B" Pressure 0 P$10 ,

t LIQUl0 WASTE System 62 NORMAL l e REACTOR PLANT COOLING WATER ' Sy s tem.,46 -

Loop 1 . .

!~

P-4601 CLEARED OUT-P-46015 - CLEARED OUT.

1 Header Inlet Temperature CLEARED:0UT' ,

Barrel and Top Head Outlet Temperature _'

i

. CLEARED 00Ti -

Top Penetration' Inlet Temperature, CLEARED.0UT '

Loop 2 i P-4602 ON- .

P-46025 CLEARED OUT i Header Inlet Temperature 115.*F-115 'F' Barrel and Top-Head Outlet Temperagure Top Penetration Inlet Temperature 115 'F.

Surge Tank Level "A" .'0LINCHES Surge Tank Level "B" 45 INCHES. <

s ir.

i k

k i

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

FOSAVEX -

PAGE 3 i

. 1 i SCENARIO TIME: nr/+cvMy 4

j CLOCK TIME: __ _

l PRIMARY AVXILIARIES

..........................*** BOARD ~I-02 ********************************

HEL!UM STORAGE System 24 ,

Low Pressure Bottles 270 PSIG High Pressure Bottles 575 PSIG HELIUM CIRCULATOR AUX!LIARIES System 21 Circulator C-2103 (C) i Bearing Water Flow 170 GPM Bearing water Inlet Temperature 78 'F -

2.0 PSID

~

Main Drain AP '

Buffer /Mid-Buffer AP 8 PSID-Buffer Helium Flow 7.40 ACFM Buffer Helium Return Flow 3.79 ACFM

. Circulator C-2104 (0).

Bearinn-Water Flow 0 GPM-

< Bearing Water-Inlet Temperature 78 'F-Main Drain-AP 4 PSID~

Buffer /Mid-Buffer AP 0 PSIO Buffer' Helium Flow 0 ACFM Buffer Helium Return Flow 0 ACFM i

............................. BOARD I-03 ******************************** m REACTOR CORE System 12 All Systems NORMAL

............................. BOARD I-05 *********************************

HELIUM CIRCULATORS- System 21  ;!

~

Circulator C-2103-(C)

Rotor Speed '2900 RPM 0,020 PSID

~

1+elium Flow (Low Range) -

Helium Flow (High Range) 0%

Circulator C-2104 (0)-

Rotor Speed' .

O RPM Helium Flow.(Low Range) -0.003 PSIO:

-Helium Flow (High Range) .0 %

i MAIN-TURBINE- System 51 NORMAL

-t s .

4  %

. - , . , - - - ., _. . . . . .; - -,,.-.,,;._._._._.m.. - .,- -,---.._..._ . ,.~.m .- ..'

, __ _ ___._ ._... _ -... _ _ . _ - _ _ _._.- _ _ _ _._. . _ _ . - . . . . . _ _ _ . ~ . _ _

FOSAVEX-90  ;

{

- PAGE 4 I SCENARIO TIME: r-/ r o/fo ' .

J CLOCK TIME: _

PRIMARY AUXILIARIES

, ...........................**BOARDI-06""""""""*"*"""""" ,

- i MISCELLANEOUS .- -

[ -Bypass Flash Tank Pressure O PSIG.. ) i PLANT ELECTRICAL System 92 j

[

- Essential Bus 1 -Bus 2 Bus 3' N/I Bus 3 l'

) 480. VAC 485 485- 485 120 VAC -118 -118 118 '118:

120 VDC 125 125-l "A" "B" Standby 01esel Generator NORMAL FAILE0 i

i ACM Diesel. Generator CLEARED OUT-j Non-Essential Switchyard NORMAL Bus 1 Bus 2 Bust 3 4160 VAC' 4160 4160 4160 480 VAC NORMAL

MAIN TOWER System 41 .0 RAINED SERVICE WATER TOWER System 42 *

. NORMAL ,

FIRE WATER System 45 = NORMAL INSTRUMENT AIR System 82 "A" HOR "B" HOR 93 93 SERVICE AIR System 82 6 PSIG

............................* BOARD-I-10 ********************************

PLANT = PROTECT!VE-SYSTEM REACTOR BUILDING. TEMPERATURE - HIGH '

Bay 100 80 'F. i Bay 200 801'FE Bay 300 80 'F i

. -REHEAT-ACTIVITY MONITORS -005 BUFFER SEAL MALFUNCTION- NORMAL-

-]

!- j o- .l L  ;

u

FOSAVEX-90 PAGE 5

$CENAR10 TIME: r/ + o e CLOCK TIME:

PRIMARY AUXILIARIES

....................********* BOARD I-13 ********************************

PENETRATION INTERSPACE AP 0 PSID REACTOR BUILDING SUMP DISCHARGE-FLOW-- 0 GPM HELIUM CIRCULATORS System 21 NORMAL

............................. BOARD l-15 ********************************

REACTOR BUILOING STACK FLOW ,

29.9 KCFM REACTOR BUILDING AMBIENT AP -0.25 Inches H2O CONTROL ROOM TEMPERATURE 75 'F

............................. BOARD 1-7507X *****************************  ;

480V ROOM TEMPERATURE 75 'F '

i l

h

- i- -

F0$AVEX-90 SCENARIO TIME: v/v v &

CLOCK TIME:

RADIATION MONITOR $: 1 NUMBER VALUE ALARMING SENSITIVITY l RT 6212 7,0 X 105 CPM N 2.2E-8 ,

RT-6213 8.0 X 108 CPM N 2.2E-B .

RT-7312 005 CPM - N/A RT-7324-1 2.0 X 101 CPM N 1.57E-8 RT-7324-2-- 2.0 X 108 CPM N 4.36E-7 RT-7325 1.0 X 108 CPM N 1.49E-5 RT-7325-2 1.0 X 108 mr/hr N N/A-RT-73437-1 1.5 X-108 CPM- N 2.51E-10 RT-73437 4.0 X 108 CPM N- 2.73E-10 RT-9301 00$ CPM N/A' RT-93252-12 1.0 X 105 mr/hr N ,- N/A AREA MONITORS RT-93250-1 1.0 X 108 mr/hr. N RT-93250-2 1.0 X 105 mr/hr N RT-93250-3 1.0 X 10 8.mr/hr N RT-93250-4 1.0 X 108'mr/hr N <

RT-93250-5 1.0 X 105 mr/hr N RT-93250-8 1.0 X 101 mr/hr' N RT-93250-13 2,0 X 105 mr/hr N RT-93250-14 4.0-X-10$ mr/hr N RT-93251-1 2.0 X 105 mr/hr N .

RT-93251-3 2.0 X-105 mr/hr N , I RT-93251-4 1.0 X 108 mr/hr N .

RT-93251-5 1.0.X 108 mr/hr N  !

1.0 X 108 mr/hr- 1 RT-93251-6 N RT-93251-7 3.0 X 105 mr/hr N' l RT-93251-8 1.0 X 101 mr/hr N RT-93251-9 2.5 X 101 mr/hr- N RT-93252-l' 2.5 X.102 mr/hr N RT-93252-2 1.0 X 10' mr/hr N '! '

RT-93252-4 1.0 X 105 mr/hr- N~

RT-93252-6 -1.5 X 108 mr/hp N RT-93252 1.0 X 105 mr/hr N EQUIPMENT MONITORS .

RT-6314-2 1.0 X 108 CPM N.

RT-46211 5.0 X: 105 CPM N RT-46212 7.0 X 105 CPM N-1 METEOROLOGICAL DATA 1 Wind' Speed 3.0 MPH Wind Direction .

From 315 Degrees.

Plume Deviation / Sigma-Theta 4.0 Degrees

Differential-Temperature 2 . 2 ..

• F . 3 i

I-F0$AVEX-90 PAGE 1

$CENARIO TIME: T c s-CLOCK TIME:

OVERALL PARAMETER $

Reactor $hutdown YES Decay Heat Power 0.0$ Md PRIMARY COOLANT Pressure 11 PSIA Temperature Circulator Inlet 95 'F Core Inlet 105 'F Core Outlet 125 'F Calculated Bulk Core (CBCT) N/A Maximum Region Differential (AT) 28 'F Helium Flow ,

Circulator C 10 X 10' Circulator 0 0 X 108 TOTAL 10 X 108 Circulator Speed '

Circulator C 2900 RPM Circulator 0 0 RPM Moisture (Dew Point)

ME-9306 41 'F ME-9307 39 'F

$ECONDARY COOLANT l Emergency Condensate Header Flow l Loop 1 0 lb/hr l Loop 2 2.0 X 10' lb/hr ,

< EES Inlet Temperature 85 'F I EES Outlet Temperature 100 'F Pressure 350 PSIA PCRV LINER COOLANT (In Sarvice)

Loop 1 NO l- 'oop 2 YES

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

i 2

FOSAVEX-90' i PAGE 2 SCENARIO TIME: r/ . c < l CLOCK TIMEi .

PRIMARY AUXILIARIES

...........................** BOARD I-01'********************************

l GAS WASTE System 63 Inlet Pressure 10 PSIA' Vacuum Tank Pressure ,8 PSIA  ;

-Surge Tank "A" Pressure 205 PSIG Surge Tank "B" Pressure O PSIG q l

L10VID WASTE- System 62 NORMAL.  ;

! REACTOR PLANT COOLING WATER System'.46 Loop 1  ;

3 P-4601 - CLEARED:0UT

.- P-46015' CLEARED OUT-Header Inlet Temperature . .

' CLEARED 0UT Barrel and_ Top Head. Outlet _ Temperature  : CLEARED OUT:  ;

Top Penetration ~ Inlet Temperature l CLEARED OUT ';

Loop 2 P-4602 OH-P-4602S CLEARED OUTJ Header Inlet Temperature .

115 'F:

Barrel and Top Head-Outlet Temperature :115 'F.

, Top Penetration Inlet Temperature ' 115F Surge Tank Level "A" :0 INCHES

-Surge Tank Level "B" L45:!NCHES  !

?

t a

1 d

.p F

1 s ' i, r

(

4 11

~

l}  ; ., '?

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

F0sAVEX-90

PAGE 3 SCENARIO TIME

c '+ce 4 )

CLOCK TIME:

PRIMARY AUXit!hRIES

........................***** BOARD I*02 ********************************

r i

HELIUM STORAGE System 24 Low Pressure Bottles 270 PSIG-High Pressure Bottles 575 PSIG HELIUM CIRCULATOR AUXILIARIES System 21

. Circulater C-2103 (C) '

)

Bearing Water Flow 170 GPM Bearing Water Inlet Temperature 78 'F Main Drain AP , 2.5 P$ID Buffer /Mid-Buffer AP 8 PSID-Buffer Helium Flow 7,40 ACFM'  !

Buffer Helium Return Flow 3.79 ACFM Circulator C-2104 (0)

Bearing Water Flow 0 GPM Bearing Water Inlet Temperature 78 'F.

Main Drain AP ~ 4 PS10-Buffer /Mid-Buffer AP 0 PSID -

Buffer Helium Flow . O ACFM L Buf fer Helium Return Flow _0 ACFM  !

. . . . . . . . . . . . . . . . . . . . . . . . . . . .

• B OA R D I - 0 3 " " " " " " " " " " " " " " " ," i l '

REACTOR CORE System 12  ;

All Systems NORMAL-

............................. BOARD I-05.***********************==****a **

HELIUM CIRCULATOR $ System 21L Circulator C-2103 (C). ..

Rotor Speed- .

. 2900 RPM Helium Flow (Low Range)- 0,020'PSID-Helium Flow (High-Range) 0%

Circulator C-2104 (D)

Rotor Speed- 0 RPM-Helium Flow (Low Range) L -0.003 PSIO Helium' Flow (HighRange) 0%

MAIN TURBINE System 51 NORMAL

?

~ +a d..r., Q ,na. , ,  !.A . . O , +: .,n ,.,,,:,,p.- - , , . , .,.,,.,n,i,,.,,., L,.4 -. ,..,,-A,.~

F0$AVEx-90 PAGE 4 SCENARIO TIME: -r' - ods-CLOCK TIME:

PRIMARY AUXILIARIES

............................. BOARD l-06 ********************************

MISCELLANEOUS Bypass Flash Tank Fressure O PSIG PLANT ELECTRICAL System 92 Essential Bus 1 Bus 2 Bus 3 N/I Bus 3 480 VAC 485 485 485 120 VAC 110 118 118 118 120 VDC 125 125 "A" "B" Standby Diesel Generator NORMAt FAILED 4 .

ACM Diesel Generator CLEARED OUT-_

Non-Essential Switchyard NORMAL Bus 1 Bus 2 Bus 4160 VAC 4160 4160 . 4160.

480 VAC NORMAL MAIN TOWER _ System 41 ORAINED' SERVICE WATER TOWER System 42 ' NORMAL

\

FIRE WATER - System 45 NORMAL  !

INSTRUMENT AIR System 82 "A" HDR '"B" HDR 93 93' j SERVICE AIR System.82 95-PSIG

............................. sorgo i.10 ................................

PLANT PROTECTIVE SYSTEM REACTOR BUILDING TEMPERATURE -'HIGH -

. Bay 100 80 'FE Bay:200 80 'F Bay 300 '

80 'F l

REHEAT ACTIVITY MONITORS 005 BUFFER 5EAL MALFUNCTION' NORMAL-1

\.

t

_m ____.m__.-.__.

F0$AVEX-90 PAGE 5 SCENARIO TIME: T/ - C'+ r" CLOCK TIME:

PRIMARY AUXILIAR!E$

4

...............************** BOARD I-13 ********************************

I PENETRATION INTER $ PACE AP 0 PSID REACTOR BUILDING $ UMP 0!$ CHARGE FLOW 0u I

HELIUM CIRCULATOR $ System 21

............................. BOARD I-15 **********'-

REACTOR BUILDING STACK FLOW ,

29.9 N FM REACTOR BUILDING AMBIENT \P -0 4 H2O CONTROL ROOH TEMPERATURE 75 'F

............................* BOARD I-7507X *****************************

1 I

480V ROOM TEMPERATURE ,

75 'F

F0$AVEX-90 SCENARIO TIME: r/g r oo CLOCK TIME: . __

RA0;ATION MONITOR $:

NUMBER VALUE ALARL.NG $ENSITIVITY RT-6212 7.0 X 108 CPM N 2.2E-8 RT-6213 8.0 X 108 CPM N 2.2E-8 RT-7312 005 CPM N/A RT-7324-1 2.0 X 108 CPM N 1.57E-8 RT-7324-2 2.0 X 108 CPM N 4.36E-7 RT-7325-1 1.0 X 108 CPM N 1,49E 5 RT-7325-2 1.0 X 108 mr/hr N N/A RT- 7.5 4 37 - 1 1.5 X 108 CPM N 2.51E-10 RT-73437-2 4.0 X 101 CPM N 2.73E-10 RT-9301 005 CPM N/A RT*93252-12 1.0 X 108 mr/hr N ,, N/A AREA MONITORS RT-93250-1 1.0 X 108 mr/hr N RT-93250-2 1.0 X 108 mr/hr N RT-93250-3 1.0 X 108 mr/hr N RT-93250-4 1.0 X 108 mr/hr N RT-93250-5 1.0 X 108 mr/hr N RT-93250-8 1.0 X 108 mr/hr N RT-93250-13 2.0 X 103 mr/hr N RT-93250-14 4.0 X 108 mr/hr N RT-93251-1 2.0 X 108 mr/hr N RT-93251-3 2.0 X 108 mr/hr N ,

RT-93251-4 1.0 X 108 mr/hr N RT-93251-5 1.0 X 108 mr/hr N RT-93251-6 1.0 X 108 mr/hr N RT-93251-7 3.0 X 108 mr/hr N RT-93251-8 1.0 X 108 mr/hr N RT-93251-9 2.5 x 108 mr/hr N RT-93252-1 2.5 X 108 mr/hr N RT-93252-2 1.0 X 108 mr/hr N RT-93252-4 1.0 X 108 mr/hr N RT-93252-6 1.5 X 105 mr/hr N RT-93252 7 1.0 X 105 mr/hr N EQUIPMENT MONITORS RT-6314-2 1.0 X 108 CPM N RT-46211 5.0 X 105 CPM N RT-46212 7.0 X 101 CPM N METEOROLOGICAL DATA Wind Speed 3.0 MPH Wind Direction Frem 315 Degrees Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature 2.2 'F

FOSAVEX-90 l PAGE 1 SCENARIO TIME ~~~/ - e . c c CLOCK TIME:

OVERALL PARAMETERS Reactor Shutcown YES Decay Heat Power 0.05 MW PRIMARY COOLANT Pressure 11 PSIA Temperature

• Circulator Inlet 95 'F Core Inlet 105 'F Core Outlet 125 'F Calculeted Bulk Core (CBCT)- N/A Maximum Region Differential (f.)

- 28 'F ,

Helium Flow Circulator C 10 X 108 Circulator 0 0 X 108 TOTAL 10 X 108 Circulator Speed Circulator C 2900 RPM Circulator 0 0 RPM Moisture (Dew Point)

ME-9306 41 'F ME-9307 39 'F SECONDARY COOLANT Emergency Condensate Header Flow Loop 1 0 lb/hr Loop 2 2.0 X 10' lb/hr

! EES Inlet Temperature 85 'F l EES Outlet Temperature 100 'F Pressure 350 PSIA' PCRV LINER COOLANT (In Service)

Loop 1 NO Loop 2 YES a

t 1

f FOSAVEX-90:

l PAGE 2 i i

SCENARIO TIME:' h C : T ' [

)

CLOCK TIME:

PRIMARY AUXILIARIES 3

- . . . . . . . . . . . . . . . . . . . n . . * * " *

• B O A R D I - 01 " " " " " * " " " * " " * " " " * " - ,

GAS WASTE $ystem 63-  !

Inlet Pressure '10 PS!A  !

Vacuum Tank Pressure 8 PSIAL Surge Tank "A" Pressure 205 PSIG Surge Tank "B" Pressure-i t 0 PSIG

+

, -LIQUID WASTE System 62 NORMAL-1 REACTOR PLANT COOLING WATER -System 46 ,

Loop 1 P-4601 CLEARED OUT- ,

P-4601$ ' CLEARED OUT-Header Inlet Temperature -CLEARED OUT  ;

Barrel and Top Head Outlet. Temperature

~

-CLEARED OUT Top Penetration Inlet Temperature CLEARED OUT' s

l Loop 2 ,

P 4602 ON .  ;

P-46025 . CLEARED OUT Header Inlet Temperature

115 'F i

Barrel and Top Head Outlet Temperature 115.*F, i~ .

, Top Penetration-Inlet Temperature '

' 115 'F.

L Surge Tank Level "A"- 0 INCHES ~ l Surge Tank Level "B" 45 INCHES' 4

r

. _ _ , - _ _ - m---  ?

o .

l. .

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

1

'F05AVEX-90

'PAGE 3 SCENARIO TIME: ""/ - c a c c.

5

CLOCK TIME

I PRIMARY AUXILIARIES

...............************** BOARD l-02 ********************************

HELIUM STORAGE System 24 ,

Low Pressure Bottles 270 PSIG  :

High Pressure Bottles 575-PSIG l

HELIUM CIRCULATOR AUXILIARIES System 21 <

-t Circulator C-2103 (C)  ;

i Bearing Water Flow 170 GPM Bearing Water Inlet Temperature 7B 'F Main Orain AP 2.5 PSID '

Buffer /Mid-Buffer 4P B PSID Buffer Helium Flow 7.40 ACFM Buffer Helium Return Flow

-3'.79 ACFM Circulator C-2104 (D)

Bearing Water Flow 0 GPM '

Bearing Water Inlet Temperatura 78 'F Main Drain AP -4 PSID- 'r Buffer /Mid-Buffer AP O PSID Buffer Helium Flow 0 ACFM Buffer Helium Return Flow ~ 0 ACFM

............n...............

BOARD 1 -0 3 " " * " " * * " " " " "" " " " "

• k i

REACTOR CORE ' System'12.

All; Systems = NORMAL

.............................BOARDl-05*"""""""""""""""" -

s i

HELIUM CIRCULATORS = System 21_ ,

j tirculatorC-2103(C)

Rotor Speed 2900 RPM Helium Flow (Low Range) 0.020 PSID' Helium Flow (High Range) 0 %-

Circulator C-2104 (D). i Rotor Speed .

O RPM L_ Helium Flow (Low Range) ..

-0.003 PSID Helium Flow (High-Range)' 0%

MAIN TURBINE System 51 NORMAL

. = _

~

r-., - , ., s,~ v._-, , . . , , -- = 4 . _ , , . . . . , _ . . . , , . , - ~  % -.m ,. .4r - v.,. #.. v

'I 4

FOSAVEX-90

PAGE 4 1

- . .1

SCENARIO TIME: 7. ot.cc CLOCK TIME:

l , _

]

! PRIMARY-AUXILIARIES i

...............n...******" BOARD I-06 """ * """" a """"" * """

MISCELLANEOUS- ,

c Bypass Flash Tank Pressure O PSIG' Syst9m 92 PLANT ELECTRICAL Essential Bus 1 Bus 2 Bus.3 N/I Bus t

> 480- VAC 485 485 485 120 VAC 118 118 118 118 120 VDC 125 125 4A" . "B" Standby Otesel Generator NORMAL._ PAILED  !

ACM Diesel Generator CLEARED OUT Non-Essential  !

Switchyard NORMAL Bus.1 Bus 2 Bus:3 ,

4160 VAC 4160 4160 4160~

i 480 VAC NORMAL (

MAIN TOWER System 41 LDRAINED SERVICE WATER TOWER System 42 NORMAL FIRE WATER System 45 NORMAL.  ?

INSTRUMENT AIR System 82 "A" HOR "B"-HOR-93 93-SERVICE AIR System 82 95 P5!G

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . BO A R D . 1 - 10 " " " " "'* " " " " " ' " " " " "

PLANT PROTECTIVE-SYSTEM REACTOR-BUILDING TEMPERATURE - HIGH -

Bay 100 80.*F Bay-200 80' ' F -

Bay 303 '80 'F REHEAT ACT!VITY MONITORS- 005

. BUFFER SEAL MALFUNCTION WORMAL 0

1 ) l

..p

.g

/ 1

- - , -.,.~.--,,,.,,-..,.-:,-~...,-....,w. .-.,-,-.,,,.e,. ,. . , . . . ,

' :>$AVEX

• - W -

PAGE-5 SCENARIO TIME: WsceeC CLOCK TIME:

PRIMARY AUX' LIARIES

.......................******BOARDl-13""*"""""*"""**"**""

PENETRATION INTIR$ PACE AP 0 PSID REACTOR BUILDD!G $ UMP 015 CHARGE FLOW D GPM .

HELIUM CI'4CULATOR$ System 21 UORMAL

........................***** BOARD I-1$ **************************"***** .

REACTOR BUILDING STACK FLOW ,

29.9 KCFM REACTOR BUILDING AVOIENT AP -0,25 inches H2O CONTR01, ROOM TEMPERATURE- 75 'F m.........................." BO ARD l-7 507X * " " * """ * "" " "" * * " *

• i 480V ROOM TEMPERA 7URE ,

75 'F f

l I

1 l

1

• g 1

-. . . - ..o.

FOSAVEX-90 SCENARIO TIME: 7,0 s t #

CLOCK TIME:

RADIATION MONITORS:

NUMBER VALUE nLARMING SENSITIVITY R'-6212 5.0 X 10' CPM Y 2.2E-8  ;

If-6213 5.0 X 10' CPM #

2,2E-8 di-7312 005 CPM N/A iT ,~3t4-1 6.3 X 108 CPM N 1.57E-8 h' 7324-2 2.2 X 105 CPM N 4.36E-7

?1 7325-1 1.0 X 10' CPM N 1.49E-5 RT i.125-2 1 1 X 108 mr/hr N N/A RT <>417-1 1.5 X 10' CDM N 2.51E-10

, k '34S? 2 4.0 X 105 CPM N 2.73E-10 R)' 301 005 CPM N/A At J3252-12 1.5 X 108 mr/hr Y ,

N/A

4 '

AREA MON!iOR$

RT-93250-1 2.0 X 10' mt/hr Y RT-93250-2 3.0 X 108 mr/hr Y  ;

(, 91250-3 5.0 X 10' mr/hr N 4 RT 'C0-4 3.0 X 108 mr/hr Y

<' T-3R +5 1.0 X 10' mr/hr Y if-9321 8 6.0 X 10' mr/hr Y Al-032K 13 1.4 X 108 mr/hr Y I

RT-932!I = 14 2.5 X 10' mr/hr N RT-9325.-1 7.0 X 108 mr/hr N RT 93?61-3 8.0 X 10' mr/hr N '

1 Rb91251-4 2.0 X 108 mr/hr Y I RT-93251-5 1.0 X 108 mr/hr Y

&T-93251-6 1.0 X 10' mr/hr Y RT-93251-7 CFF SCALE Y R'-93251-8 5.0 K 108 mr/hr Y s'-93251-9 CFF "' ALE Y 9 ^3232-1 3.0 l.0 8 mr/hr Y Rf-9f52-2 3.5 X 105 mr/hr Y

! .l RT-932v'-4 5.5 X 10' mr/hr Y i RT-9325F 5 4.0 X 108 mr/hr Y RT-93252 7 3.0 X 108 mr/hr Y 4

EQUIPMENT MONI M S 1 RT-6314-2 1.' X 105 CPM N t

ET-46211 L X 10' CPM Y RT-86212 1 ( X 10' CPM Y METE 0hfA0GICAL DATA Wind Speev 2.5 MPH Wind Direction s om 315 Degrecs Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature 2.4 'F

~ _ _-

1

-FOSAVEX-90 PAGE:li SCENARIO,TIMEi "s s ec c o CLOCK TIME:-

od? ALL PARAMETERS Reactor Shutdown. .YES Decay Heat Power-. 0,05'MW'

}

l PRIMARY-COOLANT >

]

Pressure. + 11/ PSIA E j Temperature ..

Circulator Inlet ' 95 ' FJ Core Inlet 105 *F >

Core Outlet- . . - 125F-Calculated Bulk Core':(CBCT)-

.N/A:

Maximum Region'0ifferential (AT). 28. 'F-

-Helium-Flow Circulator C-- :10: X110

Circulator D-  ? 01X:"10 8 .-:

TOTAL 10iX=10' Circulator Speed -

Circulator C- "

2900LRPM-Circulator.D -

0 RPM j

Moisture-(Oew Point)- . .

l

-ME-9306' .341 *F5 ME-9307 39 'F: 1 SECONDARY COOLANT.-

Emergency Condensate-Header: -

i

' Flow-Loop;l-- '

= 0 : 1b/hr!-

Loop 2_ 2'.-0 X 10':lb/hr EES'InletLTemperature:

'851'F :q EES Outlet Temperature-- -100.*F- 9 Pressure.  ; 350: PSI A 1 PCRVLINERCOOLANTl(Inservice)

LoopEl- N0; Loop'2 YES

_ _ _ _ _ _ _ _ - _ _ _ _ _ _ . . 21

[O g ,

l FOSAVEX-90 PAGE 2'

)

SCENARIO TIME: r# # oor CLOCK TIME:

PRIMARY AUXILIARIES

............................. BOARD I-01 ********************************

GAS WASTE System 63 l Inlet Pressure 10 PSIA Vacuum Tank Pressure 8 PSIA.

Surge Tank "A" Pressure 205 PSIG Surge Tank "B" Pressure O PSIG l

LIQUID WASTE System 62 NORMAL REACTOR PLANT COOLING WATER System 46 Loop 1 P-4601 CLEARED OUT P-4601S CLEARED OUT Header Inlet Temperature CLEARED OUT Barrel and Top Head Outlet Temperature CLEARED OUT Top Penetration Inlet Temperature CLEARED OUT Loop 2 P-4602 ON P-46025 CLEARED OUT Header Inlet Temperature 115 *F Barrel and Top Head Outiet Temperature 115 'F -

Top Penetration Inlet Temperature '

115 F Surge Tank Level "A" 0 INCHES Surge Tank Level "B" 45 INCHES

1 'F05AVEX-90

~PAGE~3-SCENARIO TIME: r -e .eco-CLOLM TIME-i PRIMARY /JXIllARIES:

...........****************** BOARD I-02 ********************************

HELIUM STORAGE' System-24 -

Low Pressure Bottles 270 PSIG

• High Pressure Bottles 575 PSIG HELIUM. CIRCULATOR AUXILIARIES System 21- <

Circulator C-2103 (C)

Bearing' Water-Flow 170 GPM Bearing Water Inlet Tempera *.ure 78 'F Main-Drain AP_ 2,5 PSID-Buffer /Mid-Buffer'AP 8 PSID-Buffer Helium Flow. 7.40 ACFM Buffer Helium-Return Flow 13,79 ACFM CirculatorC-2104(D)

Bearing Water Flow 0 GPM Bearing Water Inlet Temperature 78 *F ,

Main Drain AP 4 PSID Buffer /Mid-Buffer AP' O PSID- ,

Buffer Helium Flow: 0 ACFM-Buffer Helium. Return-Flow - 0.ACFM

............................. BOARD I-03 ********************************

REACTOR CORE System 12-All Systems- NORMAL-l

.......................****** BOARD I-05 *********************************

l HELIUM CIRCULATORS System 21 CirculatorC-2103(C)-

Rotor Speed -2900 RPM Helium Flow (Low Range) 0,020 PSID Helium Flow (High. Range)- 0%

i CirculatorC-2104(D)

Rotor Speed 0 RPM Helium Flow (Low Range)- -0.003 PSIO Helium Flow (High Range). O%

l l_ MAIN TURBINE. System 51 NORMAL

-. - . _ _ _.m _ _ - . . _ - ._ _ ._ ._. _ ._ _._ _

FOSAVEX PAGE- 4'-

-SCENARIO TIME: n + cC45' CLOCK TIME:

l PRIMARY' AUXILIARIES ,

........................*****BOAROI-06""""**""*""**""*"****

i MISCELLANEOUS '

Bypass Flash Tank Pressure -

0 PSIG PLANT ELECTRICAL- System 92; Essential __ Bus--I Bus 2 Bus'3' N/I Bus 3' 480 VAC; 485':

'485 485 120 VAC 118 118 118 118 125-

.120 VDC 125-

"A"- "B" -

Standby Diesel __ Generator- NORMAL- FAILE0 ACM Diesel Generator. TCLEARED OUT Non-Essential Switchyard- .

NORMAL ~

Bus 1 -Bus 2 Bus :3 -;

1

- 4160 VAC 4160- -4160- 4160 480 V/C NORMAL' <

u '

MAIN TOWER _ System 41 -0 RAINED SERVICE WATER TOWER System 42 NORMAL-FIRE WATER. System 45 1 NORMAL' INSTRUMENT AIR' System 82 '"A"'HDR "B"LHDR= .

l 93; 93 1

SERVICE AIR: System 82- 95 PSIG I

......................*****"* BOARC I-101********************************

~

1

' PLANT PROTECTIVELSYSTEM REACTOR BUILDING TEMPERATURE - HIGH Bay 100 80 *F Bay 200- 'F Bay 300 80 'F-3 g REHEAT ACTIVITY MONITORS- 005 3~

i BUFFER SEAL MALFUNCTION NORMAL .l

_,_,y. _ _ ,+ , --v-< ,,y., , ,__,.4 , . . . . . , , , , .

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

~(

FOSAVEX-90.

.PAGE 5=

t

- SCENARIO-TIME: mooy i CLOCK TIME: r

- PRIMARY AUXILIARIES ~ i

. . . . . . . . . . . . . . . . * * * * * * * * * * * *

• B O A R D I .- 1 3 ' * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * '

PENETRATION: INTERSPACE AP- -0 PSID REACTOR BUILDING SUMP DISCHARGE FLOW' -

-0 GPM-HELIUM CIRCULATORS System 21= NORMAL j

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B O A R D 11 - 1 5 * " * " " " " * " * " " " " " " " " a REACTOR-BUILDING STACK FLOW 29.9-KCFM' 4 REACTOR BUILDING AMBIENT AP- -0,25 cinches H2O CONTROL: ROOM TEMPERATURE 75 *F-

............................"BOARDI-7507X""*"""""*"""*"""'

480V ROOM TEMPERATURE 75 'F:- s 9

1 l

t1 4 F

f L

vu 4 -+.-i .-e,.w-r ,,--e- er-+> - . ,e,-- --

-%. +v - - - - , *e .- e,. ,---,-e4,-* ra - <-v- ,,w+ -. -

. 1 d

FOSAVEX-90 SCENARIO TIME: TB9130 CLOCK TIME:

i RADIATION MONITORS:  !

NUMBER VALUE ALARMING SENSITIVITY:

RT-6212 5.0 X 10 CPM '( : ~2.2E-8 .!

RT-6213 5.0 X 10' CPM Y 2.2E-8 i RT-7312 005 - CPM N/A RT-7324-1 5.7 X 108 CPM N 1.57E-8 .

RT-7324-2 1.9 X 108 CPM N 4.36E-7 RT-7325-1 1.0 X 108 CPM- N -1.49E-5 RT-7325 1.0 X 108'mr/hr N N/A- :i RT-73437-1 1.5 X 108 CPM N 2.'51E-10 RT-73437-2 4.0 X=105 CPM' N 2,73E-10 RT-9301 005 CPM N/A RT-93252-12 1.6 X 108 mr/hr Y N/A AREA MONITORS RT-93250-1 2.0 X-108 mr/hr Y RT-93250-2 3.0 X-10mr/hr Y RT-93250-3 5.0 X 10' mr/hr N RT-93250-4 3.0 X 101 mr/hr- Y:

RT-93250-5 1.0 X-108 mr/hr Y-RT-93250-8 6.0'X 108 mr/hr Y RT-93250-13 1.5 X 108 mr/hr- Y RT-93250-14 2.5-X 108 mr/hr N RT-93251-1 7.0 X 105 mr/br -N' RT-93251-3 8.0 X-108 mr/hr- N RT-93251 2.0 X 108- mr/hr Y- '

'RT-93251 1.0.X 10' mr/hr Y RT-93251-6 1.-0 X 108 mr/hr Y RT-93251-7 0FF SCALE =Y-RT-93251-8 5.0 X:108 mr/hr- Y

-RT-93251-9 0FF SCALE Y RT-93252-1 3.0 X 108 mr/hr Y RT-93252-2 3.5 X 108 mr/hr Y-RT-93252-4~ 5.5 X 108 mr/hr- Y RT-93252-6 4.0-X 108 .mr/hr =Y RT-93252-7 3.0 X 108 'mr/hr Y EQUIPMENT MONITORS RT-6314-2 1.5 X 108 CPM N;

RT-46211 - -1,0-X 10' CPM Y RT-46212 1.0 X-10' CPM Y METEOROLOGICAL DATA-Wind Speed 2.7 MPH Wind Direction- . From 315 Degrees Plume Deviation / Sigma Theta 4.0 Degrees-Differential Temperature 2.2 *F

J j

FOSAVEXb90~ > .  !

PAGE 1-SCENARIO TIME: 7 o s c oSo 4

- CLOCK TIME:

.0VERALL PARAMETERS-i Reactor. Shutdown. . YES-.

~

Decay Heat Power 0.05 MW:

PRIMARY COOLANT Pressure 11 PSIA Temperature *:

Circulator Inlet- 195 :

• F1 Core Inlet- 105?*F Core Outlet- .

. 125 *F. .'

-Calculated Bulk Core..(CBCT) . N/A Maximum Region Otfferential-(AT) 28 'F -

Helium Flow Circulator-C 10 X'108 Circulator D OLXL108- 3

-TOTAL 10 X 108 ,

Circulator Speed ,

!- Circulator C- T <: 2900 RPM .

Circulator D 0: RPM.

Moisture-(Dew Point) ,

ME-9306' :41 *F.

ME-9307- -

39 'F-

SECONDARY COOL NT-

' Emergency? Condensate Header 1 1

-Flow.  !

Loop 1 0 lb/hr. ,. ;

2.0 XL10' lb/hr Loop 2. .

EES1InletxTemperature? :85 'F '

.EES Outlet Temperature l

~

100 *F1 -

-Pressure ~ 350 PSIAL IPCRV LINERLC00LANT~ (In Service)i-Loop 1 LNO -

, . Loop 2 YES. ,

e

. :. _ . u .- -. . . - . . .

- . t y. + . .m... . . . ....m. - - . . . - - ~ - . . . x . . -.~. . -

t=-

4 EOSAVEX-90

+

PAGE-2' SCENARIO TIME: -rgs mm CLOCK TIME:' ,

~'

PRIMARY AUXILIARIES-

...........n....************ BOARD I-O lt """ * """""" * """ * " * " -  ;

l GAS WASTE' System 63-  :

1 Inlet Pressure .- 10'. P SI A Vacuum Tank Pressure- -8. PSIA' i Surge Tank "A". Pressure 205 PSIG ' '

-Surge Tank "B"_ Pressure- 0 PSIG.

o LIQUID WASTE - System 62 . NORMAL REACTOR PLANT-COOLING WATER System 46

+

Loop 1 .

P-4601' '

' CLEARED'0VT _

P-46015 CLEARED =0VT Header. Inlet Temperature CLEARED OUT.

Barrel and-Top Head Outlet Temperature CLEARED:0UT-Top Penetration Inlet Temperature CLEARED OUT--

Loop 2 4

P-4602' _ 0N.

P-46025 . CLEARED OUT.

Header. Inlet Temperature 115 'F-l . Barrel and Top. Head Outlet Temperature- 115-*F- - .

Top Penetration: Inlet Temperature - -115 'F-Surge Tank Level'"A" .0JINCHES'

Surge Tank Level'"B" 45 INCHES; }

5 4

1 a

e 1

d I'

3 s >

, , . . . . . , - . . . . - _.. .,-,....1. , - . . . , , . - . . . - - - . . _ _ _

FOSAVEX-90 PAGE:3 i

SCENARIO TIME: -ra omo 1 1

CLOCK TIME: j PRIMARY AUXILIARIES

..........******************* BOARD l-02 ******************************** .

HELIUM STORAGE System 24' Low Pressure Bottles ~ 270 PSIG- '

High Pressure Bottles 575 PSIG HELIUM CIRCULATOR AUXILIARIES System-21 ,

Circulator-C-2103 (C)

Bearing Water Flow- 170 GPM Bearing Water Inlet Temperature 78""F Main Drain AP ~2.5 PSID Buffer /Mid-Buffer AP-

• 8 PSID Buffer Helium Flow .

7.40 ACFM Buffer. Helium Return Flow 3.79 ACFM Circulator C-2104 (0) >

Bearing Water Flow - .

O GPM.

Bearing Water Inlet Temperature 78; F Main Drain'AP' -4 PS10 Buffer /Mid-Buffer AP 0 PS10 Buffer Helium Flow 0 ACFM Buffer Helium Return- Flow 0 ACFM

...........................** BOARD I-03 ********************************

REACTOR CORE System 12

- All Systems: NORMAL

....r......................** BOARD I-05 ********************************* 1 HELIUM CIRCULATORS System 21 CirculatorC-2103(C).

Rotor Speed 2900 RPM Helium Flow (Low Range) 0.020 PSID -

Helium Flow (High Range) 0%

1

-CirculaterC-2104(D)

Rotor Speed 0 RPM' ..

Helium Flow -(Low P.ange) -0.003 PSID-Helium Flow (High Range) 0%

MAIN TURBINES System 51 NORMAL-

]

i

( a, 1

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

FOSAVEX-90~

PAGE 4 SCENARIO TIME:- r# + ec*c--

CLOCK TIME:

PRIMARY AUXILIARIES ,

i

.un....................,...-BOARD-!*06"*"*"""*""**"""**"*" .

MISCELLANEOUS .

t Bypass Flash = Tank Pressure O PSIG-PLANT ELECTRICAL' . System 92-Essential - Bus"1 ' Bus 2-Bus 3 - - N/I-Bus 3 480 VAC 485- 485 485 120 VAC 118' .1181 :118- 118-120- VOC :125--

125L

. n'A" "B" i Standby Diesel Generator NORMAL' - FAILED-ACM Diesel Generator- CLEARED OUT.

t Non-Essential Switchyard NORMAL Bus'1- Bus'2 -

Bus 3 ,

4160 VAC -4160 4160 4160 480 VAC- NORMAL.

MAIN TOWER System 41 ' DRAINED' SERVICE WATER TOWER System 42' NORMAL' FIRE WATER System 45 -NORMAL-INSTRUMENT AIR- . System 82- '"A"2HDR "B" HDR-93 93 i SERVICE AIR System 82 -95 PSIG:

............................. BOARD:1-10 ********************************-

PLANT PROTECTIVE SYSTEM REACTOR BUILDING TEMPERATURE SHIGH

' Bay 100' 80 *F' Bay-200 80:'F-Bay 300 80 'F.~

REHEAT ACTIVITY MONITORS ' 005 BUFFER SEAL MALFUNCTION NORMAL k

- -.d.- & r# 3,-r y v ,4-* y , ,,9<- -

,w+w,,--'e 9 ,-v4m--*-y - +

FOSAVEXi 90 t- -

-PAGE 5~

SCENARIO TIME: r-@ + oeso-CLOCK TIME: .

{

PRIMARY AUXILIARIES 7

..................*********** B O A R D I - 13 * * * * * * * * * * * * * * * * * * * * * * * * * * * "" '

• PENETRATION INTERSPACE AP.

O PSID-0 GPM REACTOR BUILDING SUMP OISCHARGE . FLOW-HELIUM CIRCULATORS System 21 NORMAL

.....................******** BOARD I-15 ********************************

-29,9 KCFM-REACTOR BUILDING STACK FLOW REACTOR BUILDING AMBIENT 6P- _0.25[lachesH20

CONTROL ROOM TEMPERATURE 75 'F

............................. BOARD-I-7507X *****************************

480V ROOM TEMPERATURE- 75;*F .s .

a l

L l

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., .r, , - -

e r + 4- ---,~___r --+--- --s-

FOSAVEX SCENARIO TIME:L -Te P s : M CLOCK TIME:- {

e .

RADIATION MON! TORS: -l NUMBER VALUE ALARMING- SENSITIVITY-RT-6212 5.0 X 10' CPM Y 2.2E-8. ,

RT-6213 5.0 X 10' CPM Y 2.2E-8 ^!

RT-7312 005' CPM N/A RT-7324-1 1,9 X 10' CPM N 1.57E-8 1 RT-7324-2 6.4 X 108 CPM N. 4.36E-7 l RT-7325-1 1.0 X 108 CPM N 1.49E-5 Li RT-7325-2 1.0 X 105 mr/hr N N/A- 'l RT-73437 1.5 X 108 . CPM- N 2.51E-10 i RT-73437 4.0 X-108 CPM N- 2.73E RT-9301 005' ' CPM N/A-RT-93252 1.6 X 108 mr/hr Y, N/A :- d AREA MONITORS i RT-93250-1 2.0-X 108 mr/hr Y RT-93250-2 3.0 X 105 mr/hr Y i RT-93250-3 5.0 X 10'nmr/hr N RT-93250-4 3.0 X 105 mr/hr Y-RT-93250-5 1.0 X 10' mr/hr Y RT-93250-8 6.0 X 102 mr/hr Y RT-93250-13 1.5 X-108-mr/hr Y 1 RT-93250 2.5 X-108 mr/hr N RT-93251-1 7. X 108 mr/hr N- i RT-93251-3 8;0 X 10' mr/hr- N ,

RT-93251-4 2.0 X 108Tmr/hr -- Y .

RT-93251-5 1.0 X 108:mr/hr Y 1 RT-93251-6 1.0 X 108 mr/hr  : Y-RT-93251-7 0FF SCALE Y-a RT-93251-8 5.0 X 102 mr/ht- Y' 4 RT-93251-9 0FF SCALE' Y--

RT-93252-1 3.0 X'102 mr/hr Y RT-93252-2 3.5 X 102 mr/hr- Y RT-93252-4 5.5 X 102 mr/hr- Y RT-93252 4.0 X 102-mr/hr .Y  !

RT-93252-7 3.0 X 102 mr/hr LY EQUIPMENT MONITORS RT-6314-2. 1.5 X 108 CPM ~ ~ N-RT-46211 '1.0 X 10* CPM-Y RT-46212 1.0 X 10' CPM-

-Y j METEOROLOGICAL. DATA Wind Speed 2.7 MPH. ,

Wind Direction ' From 315 Degrees Plume Deviation / Sigma Theta 4.0 Degrees 01fferential Temperature- 3. 6 F-

i F05AVEX-?O PAGE 1 SCENARIO TIME: "a + cces-CLOCK TIME:

OVERALL PARAMETERS Reactor Shutdown YES Decay Heat Power 0.05 MW PRIMARY COOLANT Pressure 11 PSIA Temperature

• Circulator Inlet 95 'F Core Inlet 105 'F Core Outlet 125 'F i Calculated Bulk Core (CBCT) N/A Maximum Region Differential (AT) 28 F Helium Flow Circulator C 10 X 102 Circulator 0 0 X 103 TOTAL 10 X 103 Circulator Speed Circulator C '

2900 RPM Circulator 0 0 RPM Moisture (Dew Point)

ME-9306 41 *F ME-9307 39 'F SECONDARY COOLANT Emergency Condensate Header Flow Loop 1 0 lb/hr.

Loop 2 2.0 X 10' lb/hr:

EES Inlet Temperature 85 *F EES Outlet Temperature 100 F-Pressure 350 PSIA PCRV LINER'C00LANT (In Service)

Loop 1 NO Loop 2 YES

(

____-_-_ _- _ \

FOSAVEX-90 .

PAGE:2-- -3

' 1

-SCENARIO TIME: ra + oot CLOCK TIME:-

PRIMARY-AUXILIARIES-

.......................******BOARDI-01-"*"""""*"""""**""" l GAS WASTE System 63:- 'l i

Inlet Pressure 10 PSIA Vacuum Tank Pressure 8 PSIA: .s l

-Surge Tank "A" Pressure ' 205 PSIG Surge Tank "B"-Pressure 0'PSIG

]

LIQUID WASTE System 62" NORMAL j REACTOR PLANT COOLING WATER' System-46 Loop 1 P-4601 CLEARED OUT' P-46015 .

CLEARED OUT i Header Inlet Temperature CLEARED'0VT.

Parrel and Top. Head Outlet' Temperature CLEARED 00TL ,

,vp Penetration Inlet Temperature CLEARED OUT-Loop 2 P-4602- -ON-P-46025 CLEARED-OUT-Header Inlet. Temperature _.

115 'F:

Barrel and Top Head Outlet Temperature -115:*F-Top Penetration Inlet Temperature '

115:'F~ a Surge Tank-. Level "A" 0-INCHES-Surge Tank Level "B" -45 :- INCHES - R i

_{ .

t

'+..

FOSAVEX-90 PAGE 3 I

SCENARIO TIME: _

3 p + oc.&,

CLOCK TIME:

PRIMARY AUXILIARIES

............................* BOARD I-02 ********************************

HELIUM STORAGE System Low Pressure Bottles 270 PSIG High Pressure Bottles 575 PSIG HELIUM CIRCULATOR AUXILIARIES System 21-Circulator C-2103-(C)

Bearing Water Flow 170 GPM Bearing-Water Inlet Temperature 78 'F Main Drain-4P 2.5 PSID-Buffer /Mid-Buffer AP

• B PSIO Buffer Helium Flow '7-40 ACFM-Buffer Helium Return Flow '3,79.ACFM

. Circulator C-2104 (0)

Bearing Water Flow 0 GPM Bearing Water Inlet Temperature 7B 'F Main Orain AP 4 PSID Buffer /Mid-Buf fer AP - 0-PSID Buffer Helium Flow 0 ACFM Buffer Helium Return Flow -:0 ACFM

............................. BOARD I-OS ********************************

REACTOR CORE System 12

All Systems NORMAL

.............................BOARDI-05*********"**********************

HELIUM CIRCULATORS System 21 CirculatorC-2103(C)

Rotor. Speed -2900 RPM Helium Flow (Low Range)- 0.020 PS10 Helium Flow-(High Range) 0 %.  ;

Circulator C-2104 (0)-

Rotor Speed. O RPM Helium Flow (Low Range) -

-0.003.PSID Helium-Flow (High-Range) 0%

MAIN TURBINE- SystemiS1 -NORMAL

i q

FOSAVEX-90-- 'i t PAGE'4-l- -

i I

SCENARIO-TIME:: Ta + cok -

CLOCK TIME: 1 PRIMARY AUXILIARIES

.......................****** BOARD I-06 ********************************

MISCELLANEOUS -  !

Bypass Flash Tank Pressure O'PSIO

]

-PLANT ELECTRICAL System-92 Essential- Bus'l Bus 2- Bus 3 'N/I Bus!3 480: VAC- 485 485 485 120 VAC 118 118 118 118

'120.-VOC: :125 -125 A"- . - "B" Standby Diesel Generator NORMAL F AILED, ACM Diesel Generator CLEARED OUT Non-Essential Switchyard. NORMAL Bus 1 Bus 2 Bus.3 -

4160 VAC -416d --4 160- 4160' i 480 VAC NORMAL q MAIN TOWER System 41 DRAINED s

SERVICE WATER TOWER LSystem 42 -'

' NORMAL FIRE WATER' System 45 - NORMAL =

1 INSTRUMENT AIR System 82 "A'! HDR:

"B" HDR--

-- 93 SERVICE AIR System 82 95 PSIG

......................n....*

BO ARD = I - 10 ' " '"" " * " "" * " " " " " " * "

PLANT PROTECTIVE SYSTEM REACTOR BUILDING TEMPERATURE - HIGH

~ Bay 100 .~80 'F LBay 200 80 'F

' Bay-300. 080 'F REHEAT ACTIVITY MONITORS 005

BUFFER-SEAL. MALFUNCTION NORMAL

\

__._-._. 'I

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

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

-f FO$AVEX 1 [

PAGE 5-

-SCENARIO TIMEi rA 4 obM CLOCK: TIME:

1 PRIMARY AUXILIARIES'

.........n............****** BOARD I - 13 " * "" * " " " " " " ' " " " " * "

PENETRATION INTERSPACE AP O PSID REACTOR BUILDING. SUMP O!$ CHARGE-FLOW 0'GPM HELIUM CIRCULATORS System 21 NORMAL

..........................*** BOARD'I-15 ********************************

REACTOR: BUILDING.. STACK FLOW' 29.9 KCFM REACTOR BUILDING AMBIENT 6P' -0.25 Inches H2O CONTROL ROOM TEMPERATURE 75 'F

.............................BOARDI-7507X""*""*"*"*"""*"*"*'

i 4BOV ROOM TEMPERATURE 75.

• F' 1

I

- 4e-- m y w+ d ..w-- , , ,-m'y 3, y e-9,3,y-- -+ -'mi+ --,-- 4- y v ra r*y w, --+ t

FOSAVEX-90$ I.

r

-SCENARIO TIME: -roanos *

CLOCK TIME: i RADIATION-MONITORS:

NUMBER VALUE~ ALARMING SENSITIVITY RT-6212 5.0~X 10* CPM Y 2.2E-8 RT-6213 5.0 X.10' CPM Y 2-2E-B RT-7312 005 CPM. H/A j RT-7324-1 3,8 X 106 CPM Y 1.57E-8 RT-7324-2 1.3 X 10'? CPM Y 4.36E-7 RT-7325-1 1.0 X1108 CPM N 1.49E-5 RT-7325 1.0'X-10 mr/hr N N/AL 4 RT-73437-1 1.5 X 102 CPM N 2.51E-10 i RT-73437-2 4.0 X 108' CPM N 2.73E-10 RT-9301 005 CPM' N/A-* i RT-93252-12 1.6 X 108 mr/hr Y, N/A Jj AREA MONITORS RT-93250-1 2.0 X 108 mr/hr Y RT-93250-2 3.0 X 105 mr/hr -Y RT-93250-3 5.0 X 10' mr/hr N RT-93250-4 3.0 X 10 mr/hr Y RT-93250-5 1.0 X 10' mr/hr Y

RT-93250 6.0 X 108 mr/hr Y-RT-93250-13 1.5 X 108 mr/hr Y ,

RT-93250-14 2.5 X 108 mr/hr~ N RT-93251-1 7.0 X 105 mr/hr- N 1 RT-93251-3 -8.0 X-10' mr/hr' -N.

. RT-93251-4 2.0 X'108 mr/hr Y i RT-93251-5 1.0 X 10' mr/hr Y l RT-93251-6 1.0 X 10' mr/hr Y' RT-93251-7 0FF! SCALE Y RT-93251-8 5.0 X 102 mr/hr LY RT-93251-9 0FF SCALE l' '

RT-93252-1 3.0 X 108 mr/hr- Y '

-RT-93252-2 3 5 X 108 mr/hr

. Y' RT-93252-4 5.5 X 108 mr/hr Y RT-93252-6 -4,0 X 108 mr/hr -Y-RT-93252-7 3.0 X 108 mr/hr Y-

-EQUIPMENT MONITORS RT-6314-2 1.5 X 10' CPM N RT-46211 1.0 X 10' CPM' Y RT-46212 1.0 X 10' CPM Y METEOROLOGICAL DATA 1

Wind Speed 2.5 MPH l Wind Direction- From 315 Degrees Plume Deviation / Sigma Theta 4.0 Degrees:

Differential Temperature 3.6 F I i l

L L-r: - - -

1 F SAVEX-90'

~] PAGE II

, SCENARID T!_ME: ryised

CLOCK. TIME:-

OVERALL PARAMETERS-Reactor Shutdown YES Decay Heat Power 0.05 MW r

,i M

' PRIMARY COOLANT ..j Pressure 11 PSIA ~* -

.- i

Tempera ture  :)

Circulator Inlet 95 - 'F- .

-Core Inlet- ' 105 *F- I Core Outlet- , 1125FL q Calculated Bulk Core (CBCT) N/A j Maximum Regi.on Differential (AT) -28 *F  !

i Helium Flow L. .

- Ci rcul a tor _ ' C.. -10: X 10' -i

~ Circulator 0 -OLX.108 l

~ TOTAL 10 X.-100

.q Circulator' Speed- -

i Circulator C -2900 RPM i Circulator 0 0. RPM Moisturei(Dew Point) ..

i ME-9306 . 41t* F:

.ME-9307_ ~39 'F -

SECONDARY COOLANT: 4 Emergency Condensate Header Flow' ,

! Loop 1 .- 0 -. i b/ h r -.

Loop.2' 2,0 X 10'ilb/hr.

EES: Inlet Temperature: 85 *F

, -EES Outlet Temperature 100 'F Pre s sure-:  :

350-PSIA 1

1

.PCRVLINERCOOLANT-(-liService) <

Loop'l'-

N0 '-

Loop 2 YES-l

'  ?

l! >

9

FOSAVEX-90i PAGE 2 SCENARIO TIME: Y#ro/cc i

. CLOCK TIME:

PRIMARY AUXILIARIES 1 ti BOARD-1-01L********************************' H GAS WASTE System 63 i

Inlet 1Pressure 10 PSIA:

Vacuum Tank-Pressure-- 8 PSIA Surge Tank "A" Pressure 205 PSIG

- Surge Tank:"B" Pressure -

0 PSIG LIQUID WASTE System'62: NORMAL-REACTOR PLANT ; COOLING WATER -

System 46-

-Loop 1 l P-4601 CLEARED OUT i

, P-46015 CLEARED'0VT i Header Inlet Temperature' = CLEARED OUT!

Barrel- arid Top Head OutletLTemperature CLEARED OUT-Top Penetration Inlet Temperature CLEAREDLOUT- 1 Loop 2

-P-4602 ON P-46025- CLEARED OUT 3 Header Inlet Temperature .

=115 'F

' Barrel and Top Head Outlet Temperature 115,*F' -

Top _ Penetration: Inlet, Temperature: 115 'F- -j o.

-Surge Tank Level "A"; . 011NCHES 1 Surge' Tank Level "B" 45' INCHES

{

i

FOSAVEX-90 .

_ PAGE 3-SCENARIO TIME: n

• o <co CLOCK-TIME:

PRIMARY AUXILIARIES

.........................**** BOARD I-02-********************************-

HEllUM STORAGEL 1 System 24-Low Pressure Bottles 270 PSIO:

High Pressure _ Bottles 575 PSIG HELIUM CIRCULATOR AUXIL'IARIES- System 21  :

Circulator C-2103 (C)

Bearing Water Flow 170 GPM Bearing Water; Inlet Temperature '78 'F-Main Drain AP- 2;5 PSID Buffer /Mid-Buffer AP + :B'PSID Buffer Helium Flow 7.40 ACFM-Buffer Helium Return Flow . 3.79 ACFM Circulator C-2104 (0)

Bearing Water Flow- 0 GPM Bearing Water.. Inlet Temperature 7B 'Fi Main Drain AP 4 PSID Buffer /Mid-Buffer AP -0 PSID Buffer Helium Flow 0 ACFM_

Buffer He'lium Return Flow 'O ACFM

.............................BOARDI-03*********"*"******************

l System 12; d l

REACTOR CORE L All Systems NORMAL

~

.............................* - BOARD I-05.*******'*************************

HELIUM _ CIRCULATORS System 21 Circulator C-2103 (C)

. Rotor Speed 2900 RPM

-Helium Flow (Low Range)- 0.020'PSID Helium Flow"(High; Range)~ 0%

Circulator C-2104-(0)_ i Rotor Speed.- 0 RPM-Helium Flow -(Low Range)- -0,003 PSIO Helium Flow-(High= Range) 0%

MAINsTURBINE System 51 NORMAL ~

.--,.--& ,y . , - . - ,,...-,,.4., ,

.s. _

FOSAVEk-90'. -

PAGE 4 SCENARIO TIME: 74 4040 CLOCK TIME:

PRIMARY ' A'UXILI ARI ES-u...u....n....***"**""" - BOARD : 1 - 0_6 . " * " " " * " " " " * " " " " * " "

4 '

MISCELLANEOUS '

Bypass Flash Tank Pressure O PSIG.

PLANT ELECTRICAL'- System 92 Essential _.

Bus =1 Bus 2 - Bus 3 -N/I Bus =3-480 VAC 485; 485 485-120 VAC 118 118- -118: 118'

, -120. VOC 125-- '125 "A" "B" ,

-Standby Diesel Generator NORMAL FAILE0 ACM Diesel Generator CLEARED OUT-Non-Essential

> Switchyard NORMAL Bus 1 . Bus 2- Bus 2 3-' ,

4160 VAC 4160 4160 4160-4801%C NORMAL ,

MAIN TOWER -System 41 0 RAINED-SERVICE WATER TOWER System 42 NORMAL.

FIRE WATER System 45 ' NORMAL  ;

INSTRUMENT AIR' System 82- "A"' HOR "B" HOR 93 -93 .

3 SERVICE AIR < System 82 95 PSIG- =l

.- . .n.n.....n......n..****

- BOARD 1 - 10 " " " * " * " "" * " " "" " " " "

PLANT PROTECTIVE SYSTEM- ,

.i'

' REACTOR BUILDING TEMPERATURE - HIGH- . -_

Bay 100 80L*F ,

~

Bay'200 80 'F i Bay ~300.- 80 'F~

REHEAT ACTIVITY MONITORS' 005

l. - BUFFER SEAL _ MALFUNCTION  ! NORMAL i ,

J

i FOSAVEX . -

PAGE 5

-SCENARIO TIME: r#*o co

"~

i

-CLOCK TIME: ,

PRIMARY AUXILIARIES

. . . . . . . . . . . . . . . . . . . . . * " " * " B O A R D I - 13 " " " " * " * " " " " " * " " " "

• PENETRATION-INTERSP' ACE-AP 0 PSID

~

REACTOR BUILOING' SUMP DISCHARGE FLOW-- 0 GPM- I HELIUM CIRCULATORS- System 21.. NORMAL

. . . . . . . . . . . . . . . . . * * " * * * * * * *

• B O A R D - I - 1 5 '" * " * " " " * " " " " " " " * " " ,

t REACTOR _ BUILDING STACK ~ FLOW. 29,9 KCFM- ,

REACTOR. BUILDING-AMBIENT AP -0,25 Inches H20.

CONTROL ROOM TEMPERATURE 75 'F ,

. . . . . . ~. . . . . . . . . . . . . * * * * * * *

• B O A R D I - 7 5 0 7 X " " a

• 4 * " * * " * " " * " " " "

• 480V ROOM' TEMPERATURE 75 'F

.6 1

a i:

i i

e. + - -~ ...,n , e , v- .w,'.

l 4

FOSAVEX-90--

SCENARIO TIMEi V a i /v r -

CLOCK TIME: _

RADIATION MONITORS:

. NUMBER VALVE- ' ALAR 41NG .SENSITIVITYx RT-6212 5,0 X 10 CPM Y 2.2E-8 .i

-RT-6213 5.0 X=10' CPM Y 2.2E-8 RT-7312- -005 CPM- N/A RT-7324-1 4.5 X 10' CPM. -

Y .-- 1.57E  ;'

RT-7324-2= 1,4 X-106-CPM Y- 4.36E-7' RT-7325 1.0 X~108 CPM- N- l'.49E-5 RT-7325-2 1.0 X'101-mr/hr- N N/A-

-RT-73437-1 1.5.X 108 CPM N 2.51E RT-73437-2 -4.0 X 101 CPM N 2.73E i RT-9301 005- CPM N/A-RT-93252-12 -1.6 X 108~mr/hr-- -Y- N/A' 4

AREA MONITORS RT-93250-1 -2.0 X 108 mr/hr 'Y 1 RT-93250-2 3.0 X 105 mr/hr Y >

RT-93250-3 5.0 X 108 mr/hr:- N RT-93250-4 3.0-X 101 mr/hr Y RT-93250-5 1.0 X 108 mr/hr

- Y- .

RT-93250-8 -6.0 X-108 mr/hr :- -Y-RT-93250-13 1.5 X:108 mr/hr- Y-RT-93250 =2.5 X--108:mr/hr. -

N-RT-93251-1 -7.0 X 101 mr/hr. -N

-RT-93251-3 '8.0 X~10' mr/hr: N '

RT-93251-4. 2.0 X 108 mr/hr -Y RT-93251-5 1.0 X 108 mr/hr ,Y-RT-93251-6  :- 1. 0 - X - 10 8 mr/hr Y >

RT-93251-7 0FF SCALE Y

-RT-93251-8 5 . 0 X --- 10 8 mr/hr Y RT-93251-9 0FF SCALE- .

Y -

RT-93252-1 -3.0 X:102 mr/hr Y RT-93252-2 3.5 X 108 mr/hr: Y j RT-93252-4 5.5 X.108-mr/hr Y RT-93252-6 4.0 X 108 mr/hr.- Y-RT-93252-7 3.0 X 108 mr/hr Y EQUIPMENT MONITORS RT-6314  : -1.5 X 108 CPM .N RT-46211 1.0 X 10* CPM' -

Y RT-46212 1.0 X 10' CPM Y METEOROLOGICAL DATA Wind Speed: . 2.2 MPH

' Wind Direction From 315 Degrees Plume Deviation / Sigma Theta 4.'O Degrees Differential Temperature 1.9-*F 1

._7_.__.

}

e FOSAVEX-90 PAGE-1 SCENARIO TIME:- T # s o w 5'1  :

CLOLX TIMEi OVERALL PARAMETERS _

Reactor Shutdown YES-Decay Heat Power 0.05 MW.

l PRIMARY COOLANT  ;

.- PSIAL-Pressure '11 Temperature- _

Circulator--Inlet 95 *F .

Core Inlet 105 _* F:

Core Outlet .

125 *F-Calculated Bulk Core .(CBCT) N /A- -

Maximum Region Differential-(AT) 28.*F Helium Flow-Circulator C X 10' Circulator 0 0 X 10' TOTAL 10 X 10' Circulator Speed-_ .

~ Circulator C '

2900 RPM Circulator D -0 RPM Moisture (Dew Poi.nt) ..

ME-9306 411*F-ME-9307 -139

• F _-

- SECONDARY COOLANT l

L Emergency Condensate Header Flow Loop l'  :; O ~ lb/hr j Loop 2 '2.0<X~10lb/hr-2 EES Inlet Temperature.- 85 *F

.EES Outlet Temperature:-'

-100 *F-

-Pressure- -350 PSIA-PCRVILINER COOLANT (In Service)-

L

. Loop 1 NO l Loop 2 YES l

l. ,

_ , + , _ - , , _ , , , . . . , , . -

1 ?

F05AVEXe901 ..

PAGE 2' SCENARIO-TIME: 72;r mtty

-CLOCK T.lME:

PRIMARY AUXILIARIESr

• * * * * * * " * * * * * * * * * * * * * * * * * * *

• B O A R G I - 01 " " " " " * * " " * " " " " " * * " a GAS WASTE System 6'

'l Inlet Pressure: 10 PSIA 'f Vacuum Tank Pressure- - B PSIAL  ;

Surge Tank."A" Pressure 205 PSIG. i Surge Tank '_'B" Pressure - 0 PSIG ' o LIQUID WASTE: System,62- 3 NORKAL~ <

REACTOR PLANT COOLING. WATER System L46 --

4 Loop-1 _

P-4601 CLEARED OUT-P-4601S CLEARED OUT

' Header Inlet. Temperature' CLEARED OUT Barrel and Top Head Outlet Temperature CLEARED 0UT' Top Penetration Inlet Temperature CLEARED OUT-Loop -

P-4602- ON P-46025;. . - CLEARED OUT-Header Inlet Temperature . 115 *F' - . !.

Barrel and Top Head Outlet Temperatures :115 'F Top Penetration Inlet Temperature i 1).5 -L

• F L Surge Tank-level "A" 011NCHES

~

Surge-Tank Level "B" 45l INCHES i

' \

( l

s>

__._.____.__E_E _ _ _ _ - - _ _ - - _ - -

FOSAVEX-90:

- SCENARIO TIME:to w ogr i-

-CLOCK:TIMEi ,

t

' PRIMARY AUXILIARIES

. . . . . ,, . . . w . . . . . . . . . . . . . n o . . . . B 0 A R D I - 0 2 " " " " * " * " " ' " " *

• L " " * " " -

HELIUM STORAGE- ' System 24 - . ..

-Low Pressure Bottles l <

. 270 P313-- 3 i

, tiigh Prusure Bottiss 3 575 PSIG HELIUMsCIRCULATOR AUXILIARIES Systein 21 ,

i I

Circulator C-2103 (C)- -

Bearing Mater Flow- i lUO GPM-Bearing Vater Inlet Temperature ~ -18 aF- )

Main Orain: AP . .

-2.5 PSID= '

• 8;PSID

-Buffer /Mid-Buffer AP Buffer kelium Flew -'7.40'ACFN Buf fer Helium -Return' Flow 3.79 ACFM Ci reula terz C-2104 ,(D): '  !

8 earing Water Flow 0 GPM' Bearing Water Inlet Temperature- 78 'F Main-Orein AP- 4 PSID Buffer /Mid. Buffer AP -0 PSID' Buffer Helium Flow. 10-ACFM Buf fe- Helium Return Flow- 0 ACFM 1

...............************* BOARD-I-03"*""*"*""""""""""*

REACTOR CORE ' System-12 '

i -

All Systems NORMKJ

...n......u ...n n.........

BOAft D - I - 0 5 ' "" " " " " ' " " " " " " " " " "

HELIUM CIRCULATORS- System 21 .q  :<

J Circulator C-2103-(C).

Rotor Speed 2900 RPM-Helium Flow (Low.i'ange) 0,'020 PSI)

Helium- Flow (High'hange) D fi; y- 4 Circulator;C-2104 (D) '

Rotor Speed- ~ . ,

. . ._ 0 RPMa Helium Flow (Low Range) .- =-0.003 PSID -

Helium Flow -(High4Ra'nge) .

O T.

• MAIN-TURBINE System 51 ' NORMAL q 4

k

! \

-j

~

.. - - . - . ._. --. __- ~ _ , , _ . . m ... .m , , ._

F05AVEX-90 PAGE 4 SCENARIO TIME: r,c r oa5-CLOCK TIME:

PRIMARY A'lXILIARIES

. . . . . . . . . . . . . . . . . . . * * * * * * * * *

• B O AR U I - 0 6 " * * " " * * " " " " " ' " * * " " "

MISCELLANEDUS 1 Bypass Flash Tank Prnssure O PSIG PLANT ELECTRICAL System 92 Essential Bus 1 Bus 2 Bus ? K,I Bus 3 480 VAC 485 4RE 485 120 VAC A18 ((0 118 118 12U VDC 125 125 nn a ngn Standoy Diesel Generator h0RMA'l F ^ 1 L'.5 ACM Diesel Generator CLEARED OU1 .\

Non-Essential Switchyard NORMAL Bas 1 Bus 2 Bus 3 4160 VAC 4160 4160 4160 480 VAC NORMAL MAIN TOWER System 41 DRAINED SERVICE WATER TOWER System 42 NORMAL FIRE WATER System 4'5 NORMAL

'Itl3iRUNENT AIR System 82 "A" HOR "B" HDR 93 93 SERVICL AIR System 82 95 PSIG

,, . . , . . . . . . . . . . . . . . . . . . . . ., . . . .

• B O A R D I - 1 0 " " " " " " * * " " " " " " " " "

PLANT PROTECTIVE SYSTEM REACTOR 'dVIt0ING TEMPERATURE - HIGH Bay 100 80 F Bay 2JO 80 F l Bay 305 80 'F '

l REMEAT ACTIVITY MONITORS 005 BUFFER SEAL MALFUNCTION NORMAL 6

-" eNr 'MN.

i .MN -_ _ _ _ . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ -

4 FOSAVEX-90 PAGE 5 SCENAt:0 TIME: -n.s

• car

CLOCK 11ME:-

PRIMARY AUXILIARIES

............................' BOARD l-13 ********************************

PENETRATION INTERSPACE-AP 0 PS10 '

REACTOR BUILO!NG $ UMP 0!$ CHARGE FLOW 0 GPM HEL10M CIRCULA!0R$ Sys' tem - 21 NORMAL .

............................* BOARD I-15-********************************

REAC10R BUILDING $ TACK FLOW -29,9 KCFM REACTOR BUILDING AMBIENT AP -0.7, Inches H2O 4

CONTROL ROOM TEMPERATURE 75 'F

............................. BOARD.1-7507X *****************************

i 480V ROOM TEMPERATURE 75 'F ,

I i

j 2

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

.1 j FOSAVEX 90 ,

!' SCENARIO TIME: tr?? - /.6C)

CLOCK TIME:

RADIATION MONITOR $;

NUMBER VALUE ALARMING SENSITIVITY j RT-6212 5.0 X 10' CPM Y 2.2E-8 RT-6213 5.0 x 106 CPM Y 2.2E-8 q RT-7312 _ U05 CPM - N/A .  !

RT-7324-1 6.3 X 10' CPM Y 1.57E-8 RT-7324-2 2.1 X 108 CPM Y 4.36E-7

. RT-7325-1 1.0 X 108 CPM N 1.49E-5 ,

l RT-7325-2 1.0 X 108 mr/hr N N/A RT-73437-1 1,5 X.108 CPM N 2.516-10 RT-73437-2 4.0 X 108 CPM N 2.73E-10' RT-9301 00$ CPM N/A RT-93252 1.6 X 108 mr/hr. Y, N/A AREA MONITORS b RT-93250-1 2.0 X 108 mr/hr- Y RT-93250-2 3.0 X-108 mr/hr Y RT-93250-5 5.0 X 108 mr/hr N.

RT-93250-4 3.0 X 108 mr/hr Y RT-93250-5 1.0 X 108 mr/hr Y RT-93250-8 6.0 X 108 mr/hr Y .,

RT-93250-13 1.5 x 108 mr/hr Y

RT-93250-14 2.5 X 108 mr/hr N RT-93251-1 7.0 X 105 mr/hr N RT-93251-3 8.0 X-108 mr/hr .N '

RT-93251-4 2.0 X 108 mr/hr Y RT-93251-5 - 1.0 X 108 mr/hr Y.

RT-93251-6 1.0-X 108 mr/hr Y-RT-93251-7 0FF SCALE .Y RT-93251-8 5.0 X 108 mr/hr- -Y RT-93251-9 0FF SCALE Y

- RT-93252-1 3.0 X 108 mr/hr Y r RT-93252 3.5 X=108 mr/hr: -Y i RT-93252-4 5.5 X 108 mr/hr Y RT-93252-6 4.0 X 108 mr/hr Y .

RT-93252-7 - 3.0 X 108 mr/hr .Y EOUIPMENT MONITORS-RT-6314-2 1.5 X 108. CPM N RT-46211 1.0'X 106 CPM =Y l- - RT-46212- 1.0 X 10' CPd Y-METEOROLOGICAL DATA f

Wino $ peed 2.0 MPH-Wind Direction . From 315 Degrees-Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature -1.9 'F P

-, , .. y-s., . . , , , . . _ ._m., ..,y , , ,.,.,,.,,-.v..,- ,v,,m..,.y,-.e..-- , , , . ,,_-,.,,,..,.4..._ -

, , , , - , - . . , ~ r._,%,_n .

F0$AVEX-90 q PAGE 1 l SCENARIO TIME: Tw + oeo CLOCK TIME:

OVERALL PARAMETERS r

Reactor $hutdown YES Oecay Heat Power 0,05 MW PRIMARY COOLANT Pressure 11 PSIA Temperature

• Cire.ulator 1.ilet 95 'F' l Core Inlet 105 'F_  !

Core Outlet 125 'F ,

Calculated Bulk Core (CBCT) N/A Maximum Region Differential (AT) , 28 'F Helium Flow

• Circulator.C 10 X 108 Circulator 0 0 X 10' TOTAL 10 X;108 t Circulator $ peed . j Circulator C '

2900 RPM Circulator 0 0 RPM i Moisture (Dew Point) ._ _

ME-9306 41 'F L ME-9307 39- 'F - ,

SECONDARY COOLANT-Emergency Condensate Header Flow Loop 1 0 lb/hr Loop 2 2.0 X.10' lb/hr i EES Inlet Temperature -85 *F2 1 EES Outlet Temperature- 100 'F Pressures 350 PSIA PCRV LINER: COOLANT (In Service)

-Loop'1 1NO -I Loop 2: 1 ;YES:

_4: -

m_ m_. ___. -

FOSAVEX-90

~~

PAGE 2 SCENARIO TIME: T *edo CLOCK TIME:

PRIMARY AUXILIARIES

............................* BOARD I-01 ********************************

GAS WASTE System 63 Inlet Pressure 10 PSIA Vacuum Tank Pressure 8 PSIA Surge Tank "A" Pressure 205 PSIG Surge Tank "B" Pressure O PSIG LIQUID WASTE System 62 NORMAL REACTOR PLANT COOLING WATER System 46 Loop 1 P-4601 CLEARED OUT P-46015 CLEARED OUT Header Inlet Temperature CLEARED OUT Barrel and Top Head Outlet Temperature CLEARED OUT Top Penetration Inlet Temperature CLEARED OUT Loop 2 P-4602 ON P-4602S CLEARED 0)T Header Inlet Temperature 115 'F Barrel and Top Head Outlet Temperature 115 'F-Top Penetration Inlet Temperature '

115 *i-Surge Tank Level "A" 0 .*4cdES Surge Tank Level "B" 4: . ,,JH E S 4

I FOSAVEX-90 PAGE 3 SCENARIO TIME:_ v

• odo -

CLOCK TIME:

PRIMARY AUXILIARIES

............................' BOARD I-02 ********************************

HELIUM STORAGE System 24 Low Pressure Bottles 270 PSIG High Pressure Bottles 575 PS!G HELIUM CIRCULATOR AUXILIARIES System 21 Circulator C-2103 (C)

Bearing Water Flow 170 GPM Bearing Water Inlet Temperature 78 'F Main Drain AP- 2.5 PSID Buffer /Mid-Buffer AP

• 8 PSID Buffer Helium Flow 7,40 ACFM Buf fer Helium Return Flow -3.79 ACFM Circulato- C-2104 (D)

Bearing Water Flow 0 GPM Bearing Water. Inlet Temperature

~

78 'F Main Drain AP 4 PSID Buffer /Mid-Buffer AP 0 PSID Buffer Helium rlow 0 ACFM Buffer Helium. Return Flow- -0 ACFM

............................. BOARD-I-03 ***********************'********  !

REACTOR CORE System 12 '

j All Systems NORMAL-

............................. BOARD I-05 *********************************

HELIUM CIRCULATORS System 21 Circulator C-2103 (C)

Rotor Speed. 2900 RPM Helium- Flow (Low Range) 0.020 PS!D Helium Flow (High Range) 0%

Circulator C-2104'(0)  !

Rotor Speed 0 RPM. 1 Helium Flow (Low Range)- -0.003 PSID Helium Flow (High Range) 0% l l

MAIN TURBINE System 51 NORMAL' l

l.

_ . x. _  : _ _

d

FOSAVEX-90 PAGE 4 SCENARIO TIME: m

• c Jo CLOCK TIME: _

PRIMARY A'JXILI ARIES

..........................*** BOARD I-06 ********************************

MISCELLANEOUS Bypass Flash Tank Pressure O PSIG PLANT ELECTRICAL System 92 Essential '

Bus 1 Bus 2 Bus 3- N/I Bus 3 480 VAC 455 485 485 120 VAC 118 118 118 118 120 VOC 125 125-

"A"' "B" Standby Diesel Generator ' NORMAL FAILEO.

ACM Diesel Generator CLEARED.0VT

-. {

Non-Essential Swi ;hyard NORMAL Bus 1 ' Bus 2 Bus 3 4160 VAC 4160 4160 4160 480 VAC NORMAL MAIN TOWER System.41 ORAINED- j SERVICE WATER TOWER System 42 -NORMAL FIRE WATER System 45 NORMAL 1 INSTRUMENT AIR System 82 "A" HDR "B" HOR 93 -93 SERVICE AIR System 82 95 PSIG

.........................**** BOARD I-10 ********************************

PLANT PROTECTIVE SYSTEM REACTOR BUILDING TEMPERATURE - HIGH' Bay 100 l 80 '.' F .

Bay 200 - 80 'F'-

Bay 300 .80.'F REHEAT ACTIVITY MONITORS 005

-BUFFER SEAL MALFUNCTION NORMAL-1

__._m__ _-. _ _ . _ _ _._._._. _ _ _ _ _ __... - ._ .. _ _ _ _._ _ _. _ _ _.__ . _ _ _ . ~ _ .

)  !

F05AVEx-90 -

-PAGE 5  :

1 i

SCENARIO TIME: f/ *cc*o <

- CLOCK TIME:

PRIMARY AUXILIARIES

/

i u.............**********"" BOARD - I - 13 " " " " * " " " * " "" " " " " " j 0 PS10 PENETRATION !NTERSPACE 6P-0 GPM l REACTOR BUILDING SUMP DISCHARGE FLOW HELIUM CIRCULATORS: System 21 -NORMAL

. . . . . . . . . . . . . . . . . . . . . . . . . . . *

• B O A R D I - 15 " " " " " " " " * * " " " * * " " "

REACTOR BUILDING STACK FLOW 29.9 KCFM

-0,,2'3 Inches H2O REACTOR BUILDING AMBIENT 69

CONTROL ROOM TEMPERATURE 75 'F i

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . BO ARD I - 7 5 0 7 X " " " " " " " " " " * " * * " "

4 75,'F 480V ROOM TEMPERATURE ,

o

)

i l

l l

i.

4 e+ , '#: '

F0$AVEX-90 SCENARIO TIME: # +e-CLOCK TIME: ,

RADIATION MONITORS:

VALUE ALARMING SENSITfyITY NUMBER RT-6212 5.0 X 10' CPM Y 2.2E-8 RT-6213 5.0 X 10' CPM Y 2.2E-8 RT-7312 OOS CPM N/A RT-7324-1 3.2 X 10' CPM N 1.57E-8 RT-7324-2 1.0 X 10' CPM N 4.36E-7 RT-7325-1 1.0 X 108 CPM N 1.49E-5 RT-7325-2 1.0 X 10$ mr/hr N N/A RT-73437-1 1.5 x 108 CPM N 2.51E-10 RT-73437-2 4.0 X 10 CPM N 2.73E-10 RT-9301 00$ CPM N/A RT-93252-12 1.6 X 108 mr/hr Y, N/A AREA MONITORS RT-93250-1 2.0 X 108 mr/hr Y RT-93250-2 3.0 X 108 mr/hr Y RT-93250-3 5.0 X 10' mr/hr N RT-93250-4 3.0 X 101 mr/hr Y RT-93250-5 1.0 X 108 mr/hr Y .

RT-93250-8 6.0 X 108 mr/hr Y RT-93250-13 1.5 X 108 mr/hr Y RT-93250-14 2.5 x 108 mr/hr N RT-93251 1 7.0 X 105 mr/hr N RT-93251-3 8.0 X 10' mr/hr N '

RT-93251-4 2.0 X 108 mr/hr Y RT-93251-5 1.0 X 108 mr/hr Y RT-93251-6 1.0 X 108 mr/hr Y RT-93251-7 0FF SCALE Y RT-93251-8 5.0 A 1C8 mr/hr Y RT-93251-9 0FF SCALE Y RT-93252-1 3.0 X 108 mr/hr Y RT-93252-2 3.5 x 108 mr/hr Y RT-93252-4 5.5 X 108 mr/hr Y RT-93252-6 4.0 X 108 mr/hr Y RT-93252-7 -3.0 X 108 mr/hr Y EQUIPMENT MONITORS RT-6314-2 1.5 X 10' CPM N RT-46211 1.0 X 10' CPM Y RT-46212' 1.0 X 10' CPM Y METEOROLOGICAL DATA Wind Speed 1.9 MPH Wind Direction From 315 Degrees-Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature 3.9 *F l

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

i

) - FOSAVEX-90 PAGE 1 i

SCENARIO TIME: 74

• o/W  !

i

' l CLOCK TIME:

l I' OVERALL PARAMETERS Reactor Shutdown YES j 4

'; =

09eay Heat Power 0. S MW t

i PRIMARY COOLANT -

Pressure 11 PSIA-r Temperature Circulator Inlet 95 'F  ;

Core' Inlet 105 *F-

- Core Outlet 125 'F Calculated Bulk Core _ (CBCT) _

N/A-Maximum Region Differential (AT) 28 ?F ,

Helium Flow  !'

Circulator C 10 X_108 Circulator 0 0 X 10' ,

~

TOTAL 10 X1108 Circulator Speed 1 Circulator C '

2900 RPM /

Circulator 0 0 RPM' Moisture-(Oew Point)

ME-9306 _ 41F ,

ME-9307- 139 'F- +

SECONDARY. COOLANT.

-Emergency condensate Header-Flow. .

' Loop 1 0-lb/hr t' Loop 2 2.0 X 10'1lb/hr1 EES Inlet Temperature. 85 F-EES' Outlet Temperature -100 'F: ,

Pressure 350 PSIA-

?

PCRV'LINERCOOLANT (In Service)_ .

Loop;1. NO Loop:2.. -YES-  ;

w j ..-

%?

^

+.. . ' , , - . . . I..,_._ -;,,,,.,_,.m y. ; . . . _ . _ , . _ , .,_,,;,.~,...,,,m,._,

. .__,L,,____<...is,_..., ,,-.. ,, -,

,J... 4 ,0-~,.,~

F05AVEX-90 PAGE 3-SCENARIO TIME: Ts e o/&

l CLOCK TIME:

PRIMARY AUXILIARIES

......,...................... BOARD l-01 ********************************

GA$ WASTE System 63 Inlet Pressure 10 PS!A Vacuum Tank Pressure 8 PSIA Surge Tank "A" Pressure 205 PSIG Surge Tant "B" Pressure O PSIG-LIQUID WASTE System 62 NORMAL-REACTOR PLANT COOLING WATER System 46

' Loop 1 P-4601 CLEARED OUT l P-46015 CLEARED OUT Hender Inlet Temperature CLEARED OUT Barrel and Top Head Outlet.Temperatare CLEARED OUT Top Penetration Inlet Temperature CLEARED OUT I

Loop 2 P-4602 ON-P-46025 CLEt, RED OUT Header Inlet Temperature 115 'F Barrel and Top Head Outlet Temperature 115 'F ,

Top Penetration Inlet Temperature ' 115 'F:

Surge Tank Level "A" 0 INCHES Surge Tank Level "B" 45 INCHES 1

l

FOSAVEX-90 PAGE 3 SCENARIO TIME: 7 - c/VS" CLOCK TIME: .

1 PRIMARY AUXILIARIES

............................. BOARD I-02 ********************************

HELIUM STORAGE System 24 .

Low Pressure Bottles 270 PSIG i High Pressure Bottles $75 PSIG:

HELIUM CIRCULATOR AUXILIARIES System 21

' Circulator C-2103 (C)

Bearing Water Flow 170-GPM Bearing Water Inlet Temperature 78 'F -

Main Drain AP 2,5 PSID Buffer /Mid-Buffer AP 8 PSID Buffer Helium Flow 7.40 ACFM Buffer Helium Return Flow 3.79-ACFM- j CirculatorC-2104(0)

Bearing Water Flow 0 GPM Bearing Water Inlet' Temperature 78 'F -

Main Orain AP 4 PSID Buffer /Mid-Buffer AP O P$10 Buffer Helium Flow 0 ACFM-Buffer Heis;m Return Flow 0 ACFM

...........................** BOARD 1-03 ********************************

REACTOR CORE System 12 All Systems- NORMAL

............................. gagno 3.o3 ................................. j HELIUM CIRCULATORS System 21 Circulator-C-2103(C) .-

Rotor Speed 2900 RPM Helium Flow (Low Range) 0,020 PSID Helium Flow (High Range) - 0 %'

Circulator C-2104 (D)' i' Rotor. Speed ~ O RPM-Helium Flow (Low Range)'.

-0.003'PSID l Helium Flow (High Range). ' O.%

MAIN TURBINE- System 51 NORMAL-

=__-__ _ _ _ _ _ . . _ _ ___.: _ _ _

J

! i F0$AVEX-90 PAGE 4 SCENARIO TIME: re

• o/W s CLOCK TIME:

PRIMARY AUXILIARIES

............................. BOARD 1 03 - - - -.-.- - - -.- -.- - -

i MISCELLANEOUS -

Bypass Flash Tank Pressure O PSIG t PLANT ELECTRICAL System 92

-Essential Bus 1- Bus 2 - Bus 3 N/l Bus 3 480 VAC 485 485- 485-120 VAC 118 118 118 118<

120 VOC 125 125-

"A" "B" Standby Oiesel Generator - NORMAL FAILED ACM Diesel Generator CLEARED 0UT Non-Essential Switchyard NORMAL Bus 1 Bus 2 Bus 3 4160 VAC 4160 4160 4160 480 VAC NORMAL-MAIN TOWER System 41 ORAINED-SERVICE WATER TOWER- System 42: '

NORMAL FIRE WATER System 45 NORMAL INSTRUMENT AIR System 82 "A". HOR B" HOR 93 93-SERVICE AIR System 82= :95 PSIG

............................. BOARD l-10 ******************************** '

PLANT PROTECTIVE SYSTEM .

REACTOR BUILDING TEMPERATURE - HIGH L Bay'100 80 *F-Bay 200 .80 'F  :

Bay 300 80 'F ,

REHEAT ACTIVITY MONITORS 005 BUFFER SEAL MALFUNCTION. NORMAL' L

4 i

h i

L

l FOSAVEX-90 PAGE 5 S

SCENARIO TIME: * *c M.T" CLOCK TIME:-

1 PRIMARY AUXILIARIES

. . . . . . . . . . . . . . . . . . . . . . . . . * * " B O AR D I - 13 ' " " " " * " " " " " " " * " " "

• PENETRATION INTERSPACE AP 0 PSIO  ;

REACTOR BUILDING SUMP DISCHARGE FLOW 0 GPM ]

HELIUM CIRCULATMS System 21 NORMAL

. . . . . . . . . . . . . . . . . . . . . . . . . . . *

• B O A R D I - 15 " " " " " " " ' * " " " " " " " "

- REACTOR BUILDING $ TACK FLOW 29;9 KCFM i

REACTOR BUILDING AMBIENT AP- - -0225 Inches H2O

CONTROL' ROOM TEMPERATURE 75 'F i

. . . . . . . . . . . . . . . . . . . . . . . . . * * *

• BO AR D l - 7 5 0 7 X " " " " " " " " " " " " " * "

i 480V ROOM TEMPERATURE 75 'F I

I l.

l r

~L s

5

~

t l.

i..

?

li

'; . g. .F

_.4-u--.., 4 . , . - - , ,.,,.-,,s..+, ,..w,'+ n._,.m#,.,,m.:,,, -.1,.,.y.w..m. . ,:,yy, ,y,,, , ..<,-,>.-,.,,,,r,

,,,.-..,-..,r.,,,,a.<

l F0$AVEX-90 l

SCENARIO TIME: 7 - e.et?

CLOCK TIME:

RA0!ATION MONITOR $:  !

i NUMBER VALUE ALARMING SENSITIVITY '

RT-6212 5.0 X 10' CPM V 2.2E-8 RT-6213 5.0 x 10' CPM Y 2.2E-8 RT-7312 005 CPM N/A RT-7324-1 3.2 X 10' CPM N 1.57E-B RT-7324-2 9.6 X 108 CPM N 4.36E-7 RT-7325-1 1.0 X 108 CPM N 1.49E-5 RT-7325-2 1.0 X 108 mr/hr N N/A RT-73437-1 1.5 X 108 CPM N 2.51E-10 RT-73437-2 4.0 X 108 CPM N 2.73E-10 RT-9301 005 CPM N/A RT-93252-12 1.6 X 108 mr/hr Y, N/A AREA MONITORS RT-93250-1 2.0 X 108 mr/hr Y AT-93250-2 3.0 X 108 mr/hr Y RT-93250-3 5.0 X 10' mr/hr N RT-93250-4 3.0 X 108 mr/hr Y RT-93250-5 1.0 X 10' mr/hr Y RT-93250-8 6.0 X 108 mr/hr Y RT-93250 13 1.5 X 108 mr/hr Y RT-93250-14 2.5 X 108 mr/hr N RT-93251-1 7.0 X 102 mr/hr N RT-93251-3 8.0 X 108 mr/hr N 2.0 X 108 mr/hr RT-93251-4 Y RT-93251-5 1.0 X 108 mr/hr Y RT-93251-6 1.0 X 108 mr/hr Y RT-93251-7 0FF SCALE Y RT-93251-8 5.0 X 108 mr/hr Y RT-93251-9 0FF SCALE Y RT-93252-1 3.0 X 108 mr/hr Y RT-93252-2 3.5 X 108 mr/hr Y RT-93252-4 5.5 X 108 mr/hr Y RT-93252-6 4.0 X 108 mr/hr Y RT-93252-7 3.0 X 108-mr/hr Y EQUIPMENT MONITORS RT-6314-2 1.5 X 108 CPM N RT-46211 1.0 X 10' CPM Y RT-46212 1.0 X 10' CPM Y METEOROLOGICAL DATA Wind Speed 2.3 MPH Wind Direction From 315 Degrees Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature 4.0 'F I

i

F05AVEX-90 PAGE 1 SCENARIO TIME: %'soago CLOCK TIME:

OVERALL PARAMETERS Reactor Shutdown YES Decay Heat Power 0.05 MW PRIMARY COOLANT Pressure 11 PS!A Temperature

• Circulator Inlet 95 'F Core Inlet 105 'F Core Outlet 125 'F Calculated Bulk Core (CBCT) N/A Maximum Region Differential (AT) 28 'F Helium Flow Circulator C 10 X 10' Circulator 0 0 X 10' TOTAL 10 X 10' Circulator' Speed-Circulator C '

2900 RPM Circulator 0 0 RPM Moisture (Dew Point) l ME-9306 41 'F ME-9307 39 'F SECONDARY COOLANT Emergency Condensate Header Flow Loop 1 0 lb/hr Loop 2 2.0 X 10' lb/hr EES Inlet Temperature 85 'F EES Outlet Temperature 100 *F Pressure 350-PSIA PCRV LINER COOLANT (In Service)

Loop 1 NO Loop 2' YES

FO$AVEX-90 PAGE 2 SCENARIO TIME: 79 - cace CLOCK TIME:

PRIMARY AUXILIARIE$

..........................*** BOARD I-01 ********************************

GAS WA$TE System 63 Inlet Pressure 10 PSIA Vacuum Tank Pressure B PSIA Surge Tank "A" Pressure -

205 PSIG Surge Tank "B" Pressure 0 PS!G LIQUID WA$TE System 62 NORMAL REACTOR PLANT COOLING WATER System 46 p

Loop 1  !

P 4601 CLEARED OUT P-46015 CLEARED OUT Header Inlet lemperature- CLEARED OUT Barrel and Top Head Outlet Temperature CLEARED OUT Top Penetration Inlet Temperature CLEARED OUT Loop 2 P-4602 ON P-46025 CLEARED OUT Header Inlet Temperature 115 'F Barrel and Top Head Outlet Temperature 115 'F Top Penetration Inlet Temperature 115 'F Surge Tank Level "A" 0 INCHES Surge Tank Level "B" 45 INCHES 6

F0$AVEX PAGE 3 SCENARIO TIME:  :.t* caco

, CLOCK TIME:

PRIMARY AUXILIARIES

............................* BOARD Ir02 '****************************

HEllUM STORAGE System 24 Low Pressure Bottles 270 P$1G High Presture Bottles 575 PS!G HELIUM CIRCULATOR AUXILIARIES $> stem 21 Circulator C-2103 (C)

Bearing Water Flow- 170 GPM Bearing Water Inlet Temperature 78 'F Main Drain AP 2.5 PS10--

Buffer /Mid Buffer AP

• 8 PSID Buffer Helium Flow 7.40 ACFM Buffer Helium Return Flow

-3.79 ACFM CirculatorC-2104(D)

Bearing Water Flow 0 GPM Bearing Water Inlet Temperature 78 'F Main Drain AP - 4 PS10-Buffer /Mid-Buffer AP 0 PSID Buffer Helium Flow O'ACFM Buffer Helium' Return Flow 0 ACFM

............................. BOARD I-03 ********************************

REACTOR CORE System 12 '

All Systems NORMAL l

............................'BOARDI-05**********************"*******"  !

i HELIUM CIRCULATORS System 21:

CirculatorC-2103(C)

Rotor Speed 2900 RPM =

Helium Flow (Low Range) 0.020 P510 Helium F_ low (High Range) OA Circulator C-2104 (D)

Rotor Speed . .

0 RPM' Helium Fiow (Low Range) -0.003 PSID-Helium Flow (Hign Range) 0%

MAIN TURBINE  : System 51 NORMAL:

'q

F05AVEX PASE 4 SCENARIO TIME:TJ *occo CLOCK TIME: _

PRIMARY AUXILIARIES

.........................**** BOARD I-06 ********************************

1 MISCELLANEOUS- . -

Bypass-Flash Tank Pressure O PSIG PLANT ELECTRICAL System 92 Essentt:1 - Bus 1 - Bus 2 i Bus- 3 N/l Bus 3 480 -VAC 485 485 485

-120 VAC 118- 118i ^118- 118:

120 VOC 125 125

-+ ogn iign Standby Diesel Generator NORMAL- FAILED-ACM Diesel Generator

-- CLEARED- OUT -

q Non-Essential '

Switchyard NORMAL ..

1 1

Bus 1- Bus 2. Bus 3 .-

4160 VAC 4160 '4160 4160 480 VAC _ NORMAL.

MAIN TOWER System 41= ORAINE04 W SERVICE WATER TOWER -System 42 NORMAL FIRE WATER -System 45 NORMAL.

INSTRUMENT AIR System 82- "A" HOR "B" HOR 93- <93 .

SERVICE' AIR System 82 95' PSIG

. . . . . . . . . . . . . . . . . . . . . . . . . . . .

• B O A R D .1 - 10 : " " " " " " " " " " " " " " " "

PLANT; PROTECTIVE SYSTEM REACTOR BUILDING ~ TEMPERATURE - HIGH'

-Bay'100 80 'F .

Bay 200 80 'F-Bay 300 80 'F.

REHEAT-ACTIVITY MONITORS '005

_ BUFFER SEAL MALFUNCTION' _

NORMAL

. . - - u -_r _

.4

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

i 1 F0$AVEX-90 PABE 5 i

SCENARIO TIME

7 e

• caco CLOCK TIME:

PRIMARY AUXILIARIES

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B O A R D 1 - 13 " " " " " " * " " " " " " " " * "

PENETRATION INTER $ PACE AP 0 P$10 REACTOR BUILDING SUMP DISCHARGE FLOW' O GPM HELIVM CIRCULATORS System 21 NORMAL

. . . . . . . . . . . . . . . . . . . . . . . . . . . .

• B O A R D 1 - 15 * " " " " " " * " " " " " " " " "

REACTOR BUILDING STACK FLOW 29,9 KCFM REACTOR BUILDING AMBIENT AP -0.25 Inches H2O CONTROL ROOM TEMPERATURE 75 'F. ,

..........................*** BOARD l-7507X *****************************

480V ROOM TEMPERATURE 75 'F l

l v

l l

l 4

5

-=.

I"

F05AVEX-90 SCENARIO TIME: -7v - Je t~

CLOCK TIME:

RADIATION MONITORS:

NUMBER VALUE ALARMING SENSITIy!TY RT-6212 5.0 X 10' CPM Y 2.2E-8 RT-6213 5.0 X 10' CPM Y 2.2E-8 RT-7312 005 CPM N/A RT-7324-1 2.0 X 108 CPM N 1.57E-8 RT-7324-2 2.0 X 108 CPM N 4.36E-7 RT-7325-1 1.0 X 108 CPM N 1.49E-5 RT-7325-2 1.0 X 10 mr/hr N N/A RT-73437-1 1.5 X 108 CPM N 2.51E-10 RT-73437-2 4.0 X 10 CPM N 2.73E-10 RT-9301 005 CPM N/A RT-93252-12 1.5 X 108 mr/hr Y, N/A AREA MONITORS RT-93250-1 2,0 X 108 mr/hr Y RT-93250-2 3.0 X 108 mr/hr Y RT-93250-3 5.0 X 10' mr/hr N RT-93250-4 3.0 X 108 mr/hr Y RT-93250-5 1.0 X 10' mr/hr Y RT-93250-8 6.0 X 108 mr/hr Y RT-93250-13 1.4 X 108 mr/hr Y RT-93250 14 2.5 X 108 mr/hr N RT-93251-1 7.0 X 108 mr/hr N RT-93251-3 8.0 X 10' mr/hr N RT-93251-4 2.0 X 108 mr/hr Y RT-93251-5 1.0 X 108 mr/hr Y RT-93251-6 1,0 X 10$ mr/hr Y RT-93251-7 0FF SCALE Y RT-93251-8 5.0 X 108 mr/hr Y RT-93251-9 0FF SCALE Y RT-93252-1 3.0 X 108 mr/hr Y RT-93252-2 3.5 X 108 mr/hr Y RT-93252-4 5.5 X 108 mr/hr Y RT-93252-6 4.0 X 108 mr/hr Y RT-93252-7 3.0 X 108 mr/hr Y EQU1PMENT MONITORS RT-6314-2 1,5 X 108 CPM N RT-46211 1,0 X 10' CPM Y RT-46212 1.0 X 10' CPM Y METEOROLOGICAL DATA Wind Speed 2.1 MPH Wind Direction

• From 315 Degrees Plume Deviation /S19ma Theta 4.0 Degrees Differential Temperature 2.2 'F

r FOSAVEX-90 PAGE 1 SCENARIO TIME: Ya + oc/C CLOCK TIME:

OVERALL PARAMETERS Reactor Shutdown YES Decay Heat Power 0.05 MW PRIMARY COOLANT Pressure 11 PSIA Temperature Circulator Inlet 95 *F Core Inlet 105 'F Core Outlet 125 'F Calculated Bulk Core (CBCT)- N/A Maximum Region Differential (AT) 28.*F Helium Flow Circulator C 10 X 108 Circulator 0 '

0 X 10' TOTAL 10 X 10' Circulator Speed '

Circulator C 2900 RPM Circulator D 0 RPM Moisture (Oew Point)

ME-9306 41 'F ME-9307 39 'F SECONDARY COOLANT Emergency Condensate Header Flow Loop 1 0 lb/hr Loop 1 2.0 X 10' lb/hr EES Inlet Temperature 85 'F EES Outlet Temperature 100 'F Pressure 350 PSIA PCRV LINER COOLANT (In Service)

Loop 1 NO Loop 2 YES

.3: - _ . .

m _

FOSAVEX-90 PAGE 2 SCENARIO TIME: rO f R c-CLOCK TIME:

PRIMARY AUXILIARIES

..........................*** BOARD l-01 ********************************

GAS WASTE System 63 Inlet Pressure. 10 PSIA Vacuum Tank Pressure 8 PSIA Surge Tank "A" Pressure 205 PSIG l Surge Tank "B" Pressure O PSIG LIQUID WASTE System 62 NORHAL REACTOR PLANT COOLING WATER System ,46 Loop 1 P-4601 CLEARED OUT P-46015 CLEARED OUT Header Inlet Temperature CLEARED OUT Barrel and Top Head Outlet Temperature CLEARED OUT Top Penetration Inlet Temperature CLEARED OUT Loop 2 P-4602 ON P-46025 CLEARED OUT Header Inlet Temperature 115 'F Barrel and Top Head Outlet Temperature 115 'F Top Penetration Inlet Temperature ' 115 'F Surge Tank Level "A" 0 INCHES Surge Tank Level "B" 45 INCHES

F0$AVEX-90  !

PAGE 3-  !'

1 c ; A f

., SCENARIO TIME:_-- w i ,

t CLOCK TIME:

PRIMARY AUXILIARIES i

. . . . . r . . . . . . . . . . . . . . . . . . . . . .

• B OA R D I - 0 2 ' " " " " " * " * " " * " * * * " " "

• System 24

~

i HELIUM STORAGE -

Low Pressure Bottles . '270 PSIG >

High Pressure Bottles 575 PS!G HELIUM CIRCULATOR AUXILIARIES System 21-Circulator C 216 20)

, Bearing Watn fiow 170 GPM  ;

Bearing Wawr Inlet Temperature- '78 'F  ;

Main Drain AP. 2.5 PSIO '

Buffer /Mid-Buffer AP

• 8 PSIO. 4 Buffer Helium Flow 7.40 ACFM Buffer Helium Return Flow 3,79 ACFM +

Circulator C-2104 (0)

Bearing Water Flow 0'GPM Bearing _ Water Inlet Temperature 78 'F.

Main Orain AP- 4 PSID >

Buffer /Mid-Buffer AP O PSID Buffer Helium Flow 0 ACFM Buffer Helium Return Flow 0 ACFM

...........................** BOARD I-03 ******************************** s REACTOR CORE System 12 '

All Systems  ! NORMAL  !

l . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 0 4, o I . 0 3 - - - - - - - - - - - - - - - . _

l HELIUM CIRCULATORS System 21 CirculatorC-2103(C)

Rotor-Speed. 2900 RPM'  ;

Helium Flow (Low Range) . -:0,020 PSID Helium Flow (High Range) ~

0 *4 Circulator C-2104 (0)'

Rotor Speed . _

0 RPM Helium Flow (Low Range)' .. -0,003:PSID--

Helium Flow'(High Range) 0%

MAIN 3 TURBINE. System 51 NORMALL l

i l

1 -- . :

I v

i -FOSAVEX-90 PAGE 4 l

3 SCENARIO TIME: -7 6 c o S~

CLOCK TIME:

i PRIMARY AUXILIARIES

............................. BOAR 0 1 0, ................................

MISCELLANEOUS Bypass Flash Tank Pressure . 0 PSIG._

PLANT ELECTRICAL System 92 Essential Bus 1 Bus 2. ' Bus 3 _N/!_ Bus:3_

! 480 -VAC 485 485 -485-120 VAC 118 118. -

118 118.  :

120 VOC- 125 125-

"A"- "B" - ,

Standby Olesel Generator.- NORMAL- FAILE0 -

ACM Diesel Generator CLEAREO.0UT -

Non-Essential ,

Switchyard' .

_ NORMAL Bus'll -Bus.2 Bus 3 4 -

4160 VAC 4160 4160-. 4160 480.VAC NORMAL-MAIN TOWER System 41 DRAINEO

~'

SERVICE WATER TOWER System 42 NORMAL-System 45 FIRE WATER ' NORMAL INSTRUMENT AIR -System 82_ "A" HOR "B" HOR 11 93 93 -

l l

. SERVICE AIR System 82 95 PSIG; 4

............................. B m 0 1 10 ................................

PLANT PROTECTIVE SYSTEM. -

RFACTOR BUILDING TEMPERATURE - HIGH' Bay 100 80 'F Bay 200 80 'F-Bay 300- 80 'F REHEAT-ACT!VITY MONITORS !00$-

• BUFFER SEAL MALFUNCTION NORMAL T

4 g

., s

- ,.E,, -, ,.# .- ,' , _ . . _ . , _ . . _ . . _ . . _ r

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

i F0$AVEX 4 SCENARIO TIME: r#

• M / r I

CLOCK TIME:

PRIMARY AUXILIARIES  ;

. . . . . . . . . . . . . . . . . . . . . . . . . . * *

• B O A R D I - 13 " " " " " " " " " * " * " " " " " .

I d

• PENETRATION !NTERSPACE AP . . .0. PSID -

t REACTOR BUILDING $ UMP 0!$ CHARGE FLOW 0 GPM System 21 NORMAL t

, HELIUM CIRCULATORS

. . . . . . . . . . . . . . . . . . . . . . . . . . * *

• B O A R D l - 15 ' " " " " " * " " " " " " " " " "

• REACTOR BUILDING STACK FLOW 29.9 KCFM i

REACTOR BUILOING AMBIENT $P ' -0.25 In'ches H20- '

4 CONTROL ROOM TEMPERATURE- 75 'F ,

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B O A R O . I '- 7 5 0 7 X * " " " " " " " " " " " " " " f 480V ROOM TEMPERATURE ,

75 'F-

?

?

F l

u 0 1 .u

,c.. .. .,,4 .-- , ,-,4_+, ~ -,..- ,. , , _ , , - _ , _ . . , , . , , . . . , - . - , , .

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

r F05AVEX-90 I f

SCENARIO TIME; 'vJ sefo i CLOCK TIME.' , , , _ _ _  ;

I RADIAT10N MON! TORS:

NUMBER VALUE ALARMING $ENSITIVITY RT-6212. 5.0 X 10' CPM Y- 2.2E-8  :

RT-6213 5.0- X: 106 CPM Y 2.2E-8 )

RT-7312 005 CPM ,N/A l RT-7324-1 2.0 X 108 . CPM' N 1.57E-8 .

RT-7324-2 2.0 X 108 CPM N 4.36E-7 ,

RT-7325-1 1.0 X 108 CPM N 1.492-5 ->

RT-7325-2 1.0 X 108 mr/hr N N/A'  :

RT-73437-1~ 1.5 X 108 CPM N '2.51E i RT-73437-2 4.0 X 105 CPM N 2.73E-10 RT-9301 005 CPM N/A ,

RT-93252-12 1.5 X.108 mr/hr Y, N/A AREA MONIT0F.5:

RT-93250-1 2.0 X 108 mr/hr Y-RT-93250-2 3.0 X 108 mr/hr Y RT-93250-3 5.0 X 109 mr/hr N RT-93250-4 3.0 X 105 mr/hr Y RT-93250-5 1.0 X 10' ar/hr .Y' RT-93250-8 6.0 X 108. mr/hr' Y

RT-93250-13 1.4 X=108'mr/hr Y T

RT-93250-14 2.5 X 108'mr/hr 'N ,

RT-93251-1 7.0 X 102 mr/hr- N RT-93251-3 -8.0 X 108 mr/hr N ,

RT-93251-4 2.0 X 108 mr/hr Y RT-93251-5 1.0 X 108 mr/hr Y RT-93251-6 1.0 X 108 mr/hr -Y ~

RT-93251-7 0FF SCALE Y t RT-93251-8 5.0 X 108 mr/hr. Y

, RT-93251-9 0FF SCALE .

Y L RT-93252-1 3.0 X 108 inr/hr Y ,

RT-93252-2 3.5 X 108 mr/hr- Y

-RT-93252 5.5 X:-108 my/hr- Y-RT-93252 4.0 X-108 mr/hr Y RT-93252-7 3,0 X 10' ar/hr 'Y EQUIPMENT MONITORS i

RT-6314-2 .1.5 X 108 CPM N-RT-46211. '1.0 X 106 CPM 'Y RT-46212 1.0-'X 1D* CPM Y '. .

METEOROLOGICAL DATA:

i .. Wind Speed- c2.1 MPH l

Wind Direction- ' Frcm 315' Degrees _

~

Plume Deviation / Sigma _ Theta _ 4.0 Degrees Otfferential Temperature 2-.2 ' F_ ,

.w . . _ . ~ - , --,<.m. _ , _ . . . . , . , . . .- . . . , . . . , . , - - _ . _ , , . . . . -

r

'0$AVEX-90 PAGE 1 f 1

SCENARIO TIME:2 c:33 H CLOCK. TIME:

OyERALLPARAMETER$

Reactor Shutdown fES.

Oecay Heat Power- 0.05 MW PRIMARY COOLANT Pressure 11 PSIA Temperature

• Circulaisr Inlet 95t*F Core Inlet 105 'F

, Core Outlet 125 'F ';

Calculated Bulk Core (CBCT) N/A  !

Maximum Region Differential (AT)- -28 'F Helium Flow Circulator C 10 X.102 Circulator D 0 X 30' TOTAL 10LX 10' Circulator. Speed- s Circulator C '

2900 RPM- .

Circulator 0 10; RPM Noisture'(Dewpoint)

ME-9306 411af-ME-9307 39 *F SECONDARY COOLANT-Emergency. Condensate Header  ;

Flow.

Loop 1 - 0 lb/hr

" Loop;2, '

2.0 X:10'.lb/hr- --

EES-Inlet Temperature 85 'FE  !

EES Outlet Temperature =

Pressure

'100z *FL l 350 PSIA. 1 1

PCRV LINER'C00LANT< (In Service)- ,

Loop:1 NO-Loop ~2 YES

~

a rf _

1 . -

.1

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

FOSAVEnt2fl PAGE 2 i

SCENARIO TIAEs p e c. 30 CLOCK TIME:

PRIMARY AUXILIARIES

................************* BOARD I-01 ****'*******"*******************

GAS WASTE !ystem 63 i

, Inlet Pressure IC PS!A ,

VaiJum Tank Pressure 8 ^SI A -

Surge Tank "A" Pressure 205 PSIG Surge Tank "B" Pressure O PSIG LIQUID WASTE System 62 NORMAL REACTOR PLANT COOLING WATER System 46 Loop 1 -

P-4601 CLEARED OUT P-46015 CLEARED OUT Header Inlet Temperature CLEARED-0UT -

Barrel and Top Head Outlet Temperature- CLEARED OUT Top Penetration Inlet Temperature CLEARED 007 Loop 2 P-4602 ON .

P-46025 . CLEARED OUT Header *.nlet Temperature 115 F Barrel and Top Head Outlet Temperature 115 SF Top Penetration Inlet Temperature <

115 SF Surge Tark Level "A" O INCHES Surge Tans Level "B" 45 INCHES-L l

l' I

l

.)

4 1

F05AVEX-90 s

PAGE 3 ,

SCENARIO TIME:~ v.p

• M 501 i CLOCK TIMEi PRIMARY AUXILIARIES

...........................** BOARD I-02 *******"************************-

HELIUM STORAGE .

System 24 u Low Pressure Bottles 270 PSIG' High Prassure Bustles .575 PSIG HELIUM CIRCULATOR AUXILIARIES System 21_  !

CirculatorC-2103(C) '

Bearing Water Flow 170 GPM

' Bearing Water. Inlet Temperature: 78 'F-Main Drain AP '

2.5 PSID-Buffer /Mid-Buffer AP- 8'PSID

~ Buffer-Helium. Flow 7;40.ACFM-Buffer Helium Return Flow 3'79 ACFM-Circulator C-2104 (D)

Bearing-Water Flov . 0 GPM Bearing Water Inlet Temperature 78 'F Main Orain AP 4 PSID B'.er/Mid-Buffer AP 0 PS10 ,

-Bo Mer Helium Flow- 0 ACFM Buffer-Helium Return Flow 10 ACFM 6

........................***** BOARD I-03 **************"**************"**

REACTOR CORE System 12 All Systems NORMALT

............................" BOARD  !-05-*********************************

HELIUM CIRCULATORS . System 21 Circulator C-2103 (C)

Rotor Speed .2900 RPM' Helium-Flow (Low Range)- 0.020.PSID-Helium Flow (High Range) - 0%

Circulator C-2104-(D)

Rotor Speed . _

0-RPP Helium Flow (Low Range) -0.003'PSit Helium Flow (High Range) 0 %.

MAIN TURBINE System 51 NORMAL i .

I  %

a -# d FOSAVE6901 _ _

~ PAGE-4 3

-SCENARIO TIME: 7:0 + C M b CLOCK TIME: ,

.\

-PRIMARY AUXILIARIES 1

.....u..u..........******** - BOARD I -06 """"" "" * """ * " """ " ;

MISCELLANEOUS 1 Bypass Flash Tank Press.re . 0 PSIGi FLANT ELECTRICAL System:92f Essential Bus 1- - Bus 2 Bus 3- N/IiBus-3L 480 VAC- >485 1485- -485 120 -VAC a 118- -118- -.118 118-- l 120 'VDC--

125 .125~ '

V

" A'? - - "B" Standby Diesel. Generator- ,.

=

NORMAL -FAILED-CLEARED OUT-ACMDieselGenerato{

Non-Essential ,

Swttchyard -NORMAb Bus 1- Bus-2' Bus 3  !

-4160 VAC- :4160- -4160 4160-

-480 VAC NORMAL MAIN TOWER System 41- LORAINED:-

-SERVICE WATER TOWER ~ System 42-l LNORM Li i FIRE WATER System.45 NORMAL- .

INSTRUMENT ~ AIR' -System 82-_ <

"A";HDRl ="B" HDR:-

93: 93; SERVICE AIR- System 82N <

95 PSIG?

............................. BOARD I-10'********************************

-PLANTLPROTECTIVE SYSTEM f

REACTOR BUILDING' TEMPERATURE - HIGH Bays 100 -80 *F:

-Bay'200 ' 80 : .* F -; '

Bay,300 80 -

• F.

' REHEAT ACTIVITY MONITORS' '005

-BUFFER SEAL MALFUNCTION ,

NORMAL I

+u' L__-__--__----2-------:-L-

i.

FO$AVEX-90 PAGE-5'

)

-l SCENARIO TIME: 7.P + caSo' CLOCK TIME: -=

PRIMARY AUXILIARIES- *

. . . . . . . . . . . . . . . . . . . . . . . . . . . " B O A R D l - 13 ~ " * " * " " " " " " " " " " " " "

PENETRATION-INTERSPACE AP- :D P51D-REACTOR BUILDING-SUMP DISCHARGE FLOW: 0-GPM

HELIUM CIRCULATORS System 21 NORMAL

. . . . . . . . . . . . . . . . . . . * * * * * * * * *

• B O A R D I - 15 * " " " " * " " " " " * " " " " " " -

1

-REACTOR' BUILDING STACK FLOW- 29.9 KCFM REACTOR BUILDING AMBIENT-AP -0.25 Inches H2O:

CONTROL ROOM TEMPERATURE 75 'F a 1-7507x " " " " " " " " " " " " " "'

.............................-BOARD ,

480V ROOM TEMPERATURE

-75 'F- --

t A'.

'I

( f, i s

(. ' .- .

l i

FOSAVEX-90 SCENARIO TIME:

CLOCK TIME:

O Meh RADIATION MONITORS:

NUMBER VALUE ALARMING SENSITIVITY RT-6212 5.0 v 10' CPM Y 2.2E-8 RT-6213 5.0 x 10' CPM Y 2.2E-8 RT-7312 005 CPM N/A RT-7324-1 2.0 s 102 CPM N 1.57E-8 RT-7324-2 2.0 X 108 CPM N 4.36E-7 RT-7325-1 1.0 X 103 CPM N 1.49E-5 RT-7325-2 1.0 X 102 mr/hr N N/A RT-73437-1 1.5 X 108 CPM N 2.51E-10 RT-73437-2 4.0 X 101 CPM N 2.73E-10 RT-9301 005 CPM N/A <

RT-93252-12 1.5 X 108 mr/hr Y , N/A AREA MONITORS Ri-93250-1 2.0 X 108 mr/hr Y RT-93250-2 3.0 X 102 mr/hr Y RT-93250-3 5.0 X 10' mr/hr N RT-93250-4 3.0 X 10' mr/hr Y RT-93250-5 1.0 X 10' mr/hr Y .

RT-93250-8 6.0 X 108 mr/hr Y RT-93250-13 1.4 X 108 mr/hr Y RT-93250-14 2.5 X 108 mr/hr N RT-93251-1 7.0 X 102 mr/hr N RT-93251-3 8.0 X 10' mr/hr N ,

RT-93251-4 2.0 X 102 mr/hr Y RT-93251-5 1.0 X 108 mr/hr Y RT-93251-6 1.0 X 108 mr/hr Y RT-93251-7 0FF SCALE Y RT-93251-8 5.0 X 108 mr/hr Y RT-93251-9 0FF SCALE Y RT-93252-1 3.0 X 108 mr/hr Y RT-93252-2 3.5 X 108 mr/hr Y RT-93252-4 5.5 X 108 mr/hr Y RT-93252-6 4.0 X 108 mr/hr _Y RT-93252-7 3.0 X 108 mr/hr Y EQUIPMENT MONITORS RT-6314-2 1.5 X 10' CPM N RT-46211 1.0 X 10' CPM Y RT-46212 1.0 X 10' CPM Y METEOROLOGICAL DATA Wind Speed 1.9 Wind Direction From 315 Oegrees Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature 2.3 *F I

3 FOSAVEX-90 PAGE 1 SCENARIO TIME: ra + o;.9 CLOCK TIME:

OVERALL PARAMETERS Reactor Shutdown YES Decay Heat Power 0.05 MW PRIMARY COOLANT Pressure 11 PSIA Temperature Circulator Inlet 95 *F Core Inlet 105 *F Core Outlet 125 *F Calculated Bulk Core (CBCT) N/A Paximum Region Differential (AT) 28 *F Helium Flow Circulator C 10 X 10' Circulator D 0 X 102 TOTAL 10 X 102 Circulator Speed Circulator C 2900 RPM Circulator 0 0 RPM Moisture (Dew Point)

ME-9306 41 F ME-9307 39 F SECONDARY COOLANT Emergency Condensata Header Flow Loop 1 0 lb/hr Loop 2 12.0 X-10' lb/hr EES Inlet Temperature. 85 *F EES Outlet Temperature 100 *F Pressure 350 PSIA PCRV LINER COOLANT (In Service)

Loop 1 NO Loop 2 YES

, s -

FOSAVEX-90 PAGE 2 SCENARIO TIME: ra edt CLOCK TIME:

PRIMARY AUXILIARIES.

...............************** BOARD l-01 ********************************

GAS WASTE System 63 Inlet Pressure 10 PSIA Vacuum Tank Pressure 8 PSIA Surge Tank "A" Pressure 205 PSIG Surge Tank "E" Pressure O PSIG LIQUID WASTE System'62 NORMAL REACTOR PLANT COOLING WATER System 46 Loop 1 P-4601 CLEARED OUT P-46015 CLEARED OUT Header Inlet Temperature CLEARED OUT Barrel and Top Head Outlet Temperature CLEARED OUT Top Penetration Inlet Temperature CLEARED OUT Loop 2 P-4602 ON P-4602S '

CLEARED OUT Header Inlet Temperature 115 'F Barrel and Top Head Outlet Temperature- 115 F Top Penetration Inlet Temperature 115 'F Surge Tank Level "A" 0 INCHES Surge Tank Level "B" 45 INCHES r .

4

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

1 FOSAVEX-90 PAGE 3 SCENARIO TIME: n +o w  :

CLOCK; TIME

c PRIMARY AUXILIARIES- i

...... ....................** BOARD I-02 ********************************

HELIUM STORAGE System 24-Low Pressure Bottles 270 PSIG High Pressure Bottles 575 PSIG HELIUM CIRCULATOR AUXILIARIES System 21 -

Circulator C-2103 (C) i Bearing Water: Flow . _ 170 GPM i Bearing Water Inlet Temperature 78 'F Main Drain AP

• 2.5 PSID.

Buffer /Mid-Buffer AP '8 PSID Buffer Helium Flow = 7,40-ACFM Buf fer Helium Return- Flow .3.79 ACFM Circulator C-2104 -(D)

Bearing Water Flow 0 GPM Bearing Water Inlet Temperature 78 'F .

Main Drain AP.

4 PSID Buffer /Mid-Buffer AP -0 PSID Buffer Helium Flow = 0 ACFM Buffer Helium Return Flow 0 ACFM

...........................** BOARD-I-03 *****************************?**

4 REACTOR CORE System 12-All Systems NORMAL

.........................****BOARDI-05*********"**********************

HELIUM CIRCULATORS System 21-CirculatorC-2103(C)

-Rotor. Speed -2900 RPM.

Helium Flow (Low Range) . 0.020 PSID Helium Flow (High Range) 0%

Circulator C-2104 (D)

Rotor Speed 0 RPM Helium Flow (Low Range)

-0.003 PSID' Helium Flow (High Range)- 0%

e MAIN TURBINE System'51 NORMAL v

a

-, , 4. - -e,,, - , -

~

' *E , ,

-:t y

FOSAVEX d SCENARIC TIME: w - s k j CLOCK ~ TIME:

PRIMARY AUXILIARIES

..........................*** BOARD I-06 ********************************

\

MISCELLANEOUS Bypass Flash Tank Pressure .O PSIGi PLANT ELECTRICAL System 92 Essential Bus l' Bus-2 N/I Bust 3i 4

Bus 13-

480 VAC 485 485-- 485 120 VAC 118 118' 118. 118--

120 VOC '125- 3125

.- 4 upu -- u g n j

Standby Diesel Generator = NNMAL FAILED ACM: Diesel Generator 'LEARED OUT Non-Essential j

Switchyard. NORMAL Bus li Bus <2 = Bus!3 4160 VAC 4160- -- 4160' ?4160e 480 VAC NORMAL j 1

MAIN TOWER System 41 0 0RAINE0~

SERVICE WATER TOWER , System 42- ' NORMAL FIRE WATER System 45: . l NORMAL-INSTRUMENT AIR System 82 "A" HOR "B". HOR l' 93: 93: i 1

SERVICE AIR System 82 , 95.PSIG, I

............................* BOARD 1-10 ********************************-

PLANT PROTECTIVE SYSTEM REACTOR BUILDING TEMPERATURE'- HIGH: .

Bay 100- -80 'F.

Bay:200 80 'F-Bay 300- --80 'F' REHEAT ACTIVITY 1 MONITORS 2005 BUFFER SEAL MALFUNCTION NORMAL

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

, ' I ,

F05AVEX-90J PAGE 5 SCENARI0 TIME: 79 + o .ds" CLOCK TIME:  !

t PRIMARY AUXILIARIES  ;

. . . . . . . . . . . . . . . . . . . . . . . . . . . *

• B O A R D ; ' I - 13 i " " " " " " " " " " * " " * " " ".. a PENETRATION INTERSPACE AP O PSID.

REACTOR-BUI'LDING SUMP-DISCHARGE FLOW. t0-GPMI a

HELIUM CIRCULATORS System 21- NORMAL

. . . . . . . . . . . . . . . . . . . . . * * * * * * *

• B O A R D I : 15 ; " " " " " " " " " " " " " * * " " ;

t

~

REACTOR BUILDING STACK FLOW: i29.9 KCFM ,

REACTOR. BUILDING AMBIENT AP -0,25 Inches H2O i t

- CONTROL ROOM TEMPERATURE-- 75 *F: -

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . BO A R D - I - 7 5 0 7 X " " * " " * " " " " " " * " " "

. t 480V ROOM TEMPERATURE. 75 *F-I

)

r

'i ll 4 , # -. _ - . . _. -, . . . . . _ , , , , - . . . . . , . - . , _ . . . . , - . . - _, . , . . . . ~ . _

i FOSAVEX-90~

SCENARIO TIME: 1 rap 43:CC; LCLOCK TIME:-

RADIATION MONITORS:

NUMBER 1 :VALUE. JALARMING. SENSITIVITY: 4 RT-6212 5,0 X 10' CPM;1 , Y. ;2.2E-8;

-RT-6213 5.0: X 10' CPM- Y 2.2E -RT-7312' 005- CPM:: .

N/A

-RT-7324-1 2.0 X 103 CPML N' :1.57E-BL RT-7324-2l 2.0 X 101 CPM- N t4;36E-7 RT-7325-1 1.0 X 108 CPMf_ N- :1.49E RT-7325-2 ;N/A

'1.0 X 101 mr/hr_ - N RT-73437-1 1.5 X 108-CPM N. _2,51E-10:

RT-73437-2'- 4.0 X 105 CPM _ _N 2.73E-104 RT-9301 ~

'005- CPM N/A RT-93252-12 1.5 X 102 .mr/hr Y; _ N/AL ,

-AREA MONITORS 1 4

RT-93250-1 2-0 X 108 mr'/hr

. Y RT-93250-2 3.0 X 105 mr/hr- Y.

RT-93250 5.0 X:10'smr/hr: N RT-93250-4 3.0 X 105 mr/hr Y RT-93250-5 1.0 X 10' mr/hr Y .

RT-93250 6.0 X-108 mr/hr

Y RT-93250-13 ~1.4 X 108:mr/hr LY

-RT-93250-14 '2.5 XE108'mr/hr N RT-93251 7.0-X 101 mr/hr- N RT-93251 8.0 XJ10' mr/hr ~N

-RT-93251-4 -2.0 X 108 mr/hr LY; RT-93251-5 1.0 X-108 mr/hr

. - Y=

RT-93251-6 1.0 X 108 -mr/hr- EYJ  :

a' RT-93251-7 OFF SCALE- Y1 RT-93251-8 2.0 X-108 -mr/hr -Y; RT-93251-9 0FF SCALE __ Y =

RT-93252-1 3.0 XL108 .mr/hr' Y "

'RT-93252-2 ?3.5;X 108 mr/hr Y RT-93252-4 5.5 X'108'mr/hr= Y RT-93252-6 4 '.0 :X = 108 : mr/hr Y RT-93252-7 3.-0 X 108-mr/hr Y

~

EQUIPMENTEMONITORS

-RT-6314-2' L1.5 X 102-CPM N '

RT-46211 1.0 X 10' CPM l'-

RT-46212 1.0EX 10' CPM ~Y METEOR 0 LOC'.AL" DATA Wind Speed - -I '. 9 .

ldind-Direction- -_From L315' Degrees Plume-Deviation / Sigma Theta ~4.0 Degrees Differential Temperature '2.3=*F:

5 . -

i--

~

. 1 FOSAVEX-90 PAGE 1 SCENARIO TIME: -c + caoo CLOCK TIME:

OVERALL PARAMETERS Reactor Shutdow., YES Decay Heat Power 0.05 MW 4

PRIMARY COOLANT Pressure 11 PSIA -

Temperature

Circulator Inlet 95 'F Core Inlet 105 *F Core Outlet 125 *F Calculated Bulk Core (CBCT) N/A Maximum Region Differential (AT) 28 'F Helium Flow Circulator C 10 X 102 Circulator 0 0 X 10' TOTAL 10 X 108 Circulator Speed Circulator C '

-2900-RPM Circulator 0 0 RPM Moisture (Dew Point)

ME-9306 41 F ME-9307 39 'F SECONDARY COOLANT Emergency Condensate Header Flow Loop 1 0 lb/hr Loop 2 2.0 X 10' lb/hr EES Inlet Temperature 85 "F  :

EES' Outlet Temperature 100 'F Pressure 350 PSIA PCRV LINER COOLANT (In Service)

Loop 1 NO Loop 2 YES I

- '4M .. _ _ - - _ - _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ . - . _ _ . _ _ _ _ -

- F05AVEX-90;- - -.

PAGE 2-SCENARIO lTIMElTa+oace:

,  : CLOCK; TIME:

PRIMARY AUXILIARIES

. . . . . . . . . . . . . . . . . . . . . . . . . . . *

• BO A R D I - 0 1 " " " " " " " " " " " " " " * " "

l GAS WASTE- _ System 63 .

Inlet Pressure '10' PSIA:-

Vacuum Tank Pressure . 8 PSIA:'_

Surge Tank "A" Pressure. .

.205 PSIG4 l Surge Tank "8 Pressure-0 PSIG=_

LIQUID WASTE - System _62_ i NORMAL =

REACTOR-PLANT-COOLING. WATER System 46-v-

~ Loop 1 lj P-4601 - CLEARED 0UT ~.

P-46015 _

CLEARED OUT-Header Inlet Temperature " CLEARED OUT Barrel and-Top Head Outlet Temperature CLEARED.0UT .o Top Penetration Inlet Temperature CLEARED OUT.--

-Loop 2 P-4602 ON: .

P-46025 CLEARED OUT-

Header Inlet Temperature  : 115 'F?

Barrel and. Top Head Outlet Temperature -,115 *F

-_ Top-- Penetration Inlet Temperature '

~115 'F.-

p ' Surge Tank-Level "A" 0 INCHES-Surge Tank Level "B" 45l INCHES-o i

1 i

9 4

0 1

~

F05AVEX PAGE 3 4

SCENARIOLTIME: -w -esoo CLOCK TIME:  !

PRIMARY AUXILIARIES

.............................BOARDI-02'"""""""""***""*"*"

HELIUM STORAGE- System 24' Low Pressure Bottles

~

~ 270'PSIG High Pressure Bottles. 575 PSIG  !

HELIUM CIRCULATOR AUXILIARIES System 21 Circulator C-2103-(C)'-

Bearing Water-Flow .

170 GPM Bearing Water; Inlet Temperature 78 'F'-

Main Drain AP- 2=.5 PSID Buffer /Mid-Buffer AP . 8 PSID Buffer Helium Flow = 27.-40 ACFM Buffer Helium Return Flow '3.79 ACFM Circulator C-2104 (D)-

Bearing Water Flow = 0 GPM Bearing Water Inlet Temperature- 78 'F Main Orain AP 4 PSID Buff;r/Mid-Buffer AP. O PSID Buffer Ne M um Flow? 0 ACFM

' Buffer Hel M Return Flow ;0 AC;M

............c.....ovo...... BOARD I-03 L "" * "" "" * """"" "" * ""

REACTOR CORE System 12-l All Systems ' NORMAL

..........s....n..n o......

BOAR D I .- 0 5 * " " " " " " " " " " " " " " " "

. HELIUM CIRCU'LATORS System 21-Circulator C-2103 (C) ..

Rotor Speed- - 2900 RPM Helium Flow (Low . Range)

. 0.020 PSID Helium Flowi(HighLRange)= ,

OT Circulator C-2104 (D)

Rotor _ Speed- 0. RPM Helium Flow (Low Range)

-0.003 PSID Helium Flow (High Range)

_ 01 :.

MAIN TURBINE System 51- = NORMAL-4 2

' ' ~

___..._j:_.--.._l.- -_

FOSAVEX-90

-PAGE 4-'

SCENARIO TIME: re + cace CLOCK TIME:

PRIMARY AUXIllARIES-

..................... ******* BOARD I-06.********************************

MISCELLANEOUS Bypass Flash Tank Pressure O PSIG PLANT ELECTRICAL System 92 Essential Bus 1 Bus 2 Bus 3 .N/I Bus 3 480 VAC 485 485- 485 .

120 VAC- 118 118 118' 118 120- VDC 125; 125'-

A"- . "B" Standby Diesel Generator -NORMAL FAILED ACM Diesel Generator CLEARED OUT -

Non-Essential Switchyard . NORMAL-Bus 1 Bus,2 Bus 3-4160 VAC 4160-- 4160 4160 480 VAC NORMAL' MAIN TOWER- System 41 DRAINED

. SERVICE WATER TOWER System 42 -NORMAL )

FIRE WATER . System 451 , NORMAL'-

INSTRUMENT AIR System 82 "A" HDR "B"'HDR -

93 93 SERVICE-AIR System 82- 95-'PSIG

. . . . . . . . . . . . . . . . . . . . . . . . . . . . " B O A R D 1 1 - 10 ~ - " " * " " " " * " " " " " " " " "

PLANT PROTECTIVE SYSTEM REACTOR BUILDING TEMPERATURE - HIGH -

Bay ~100 - 80 'F .

Bay 200- 80 *F Bay 300 80:'F REHEAT ACTIVITY. MONITORS 005

' BUFFER: SEAL. MALFUNCTION NORMAL'

4 FOSAVEX-900

.PAGE15  :

SCENARIO TIMEi -ra -cres .

CLOCK TIME: ,

PRIMARY AUXILIARIES i

.............................-BOARD I-13 **********"*********************

a PENETRATION INTERSPACE AP' O PSID) .i REACTOR BUILDING' SUMP OISCHARGE FLOW 0 GPM 'I

~

HELIUM CIRCULATORS . System.21 NORMAL-q

.........................**** BOARD-I-15""*"""*""""""""""  !

i REACTOR BUILDING STACK FLOW :29.9 KCFM .i l

REACTOR BUILDING AMBIENT AP- -0.'25 Inches H20- ^!

I CONTROL RVOM-TEMPERATURE 75

'F I

. . . . . . . . . . . . . . . . . . . . . . . . . . . .

• l B O AR D I - 7 5 0 7 X " " " " " " " " " " * " " " " '

480V ROOM TEMPERATURE- 75 'F ,

-t i

6

-I

-l

'FOSAVEX-90=

SCENARIO TIME: -ra -+.si/5 -

' CLOCK' TIME:=

RADIATION. MONITORS:

NUMBER VALUE. ALARMING SENSITIVITY RT-6212 '5.0 X 10' CPM -Y- 2.2E  !

RT-6213- 5.0 X 10' CPM Y 2.2E-8 RT-7312 005 CPM N/A.

-RT-7324-1 2.0 X'10'EcPM; N: >

1.57E-8 -

RT-7324-2. 2.0 X110 CPM .N 4.36E-7f RT-7325-F 1.0 X.108 CPM N. ,1.49E-5 RT-7325 1.0 X:108 mr/hr N ~ N/A- .

RT-73437-1 1.5 X: 108 CPM: 'N- 2.51E l RT-73437 4.0 X 108-CPM N -2.73E-10 b RT-9301- 005 CPM N/A RT-93252-12 1.5 X 108 mr/hr fY 1 N/A-AREA MONITORS RT-93250-1 2.0 X 108 mr/hr Y RT-93250-2 3.0-X'105 mr/hr' Y RT-93250-3 5.0 X 10' mr/hr N I RT-93250-4 3.0 X.105'mr/hr Y RT-93250-5 1.0 X 10' mr/hr: Y RT-93250-8 6.0-X-108 -mr/hr- :Y RT-93250-13 1.4 X 108 mr/hr -Y.  !

RT-93250-14 2.5 X 108:mr/hr +1 4

-RT-93251 7.0 X 108 mr/hr N:

RT-93251-3 8.0,X 108 mr/hr- 11 -

RT-93251-4 2.0 X 108 mr/hr- Y RT-93251-5 1.0:X(108 mr/hr Y:

RT-93251-6 1.0 X 108 mr/hr- Y RT-93251-7 0FF SCALE 'Y RT-93251-8 5.0-X 108 mr/hr YJ RT-93251-9 0FF SCALE -

Y RT-93252-1 3.0 X 108 .mr/hr Y

.RT-93252-2 3.5 X 108 mr/hrf 10 RT-93252-4 5'.5'X 108 mr/hr Y RT-93252-6 -4.0 X'108 mr/hr- YL RT-93252 3.0 X 108 mr/hr Y EQUIPMENT MONITORS j

.RT-6314-2' .1.5 X 10' CPM N RT-46211 1.0-X:10' CPM Y RT-46212- ~1.0 X 10' CPM Y METEOROLOGICAL DATA Wind Speed 2.'1 MPH Wind Direction From 315 Degrees Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature- 2.2 *F i

.. - _________O

FOSAVEX-90 PAGE 1-SCENARIO TIME:rge + c 345- -

CLOCK TIME:

OVERALL PARAMETERS Reactor Shutdown YES Decay Heat Power 0.05 MW PRIMARY COOLANT Pressure 11 PSIA Temperature

• Circulator Inlet 95 'F Core Inlet 105 'F ,

Core Outlet 125 'F Calculated Bulk Core (CBCT) N/A Maximum Region Differential (aT) 28 F Helium Flow Circulator C 10 X 10' Circulator 0 0 X 10' TOTAL 10 X 105 Circulator Speed Circulator C '

2900 RPM Circulator 0 0 RPM Moisture (Oew Point)

ME-9306 41 F ME-9307 39 'F SECONDARY COOLANT Emergency Condensate Header Flow Loop 1 0 lb/hr Loop 2 2.0 X 10' lb/hr EES Inlet Temperature 85 *F EES Outlet Temperature 100 *F Pressure 350 PSIA PCRV LINER COOLANT (In Service)

Loop 1 NO Loop 2 YES

m FOSAVEX-90

.PAGE 2 SCENARIO TIME: r + o b r CLOCK TIME:

PRIMARY AUXILIARIES

..........................*** BOARD I-01 "*******************************

GAS WASTE System 63 Inlet Pressure 10 PSIA Vacuum Tank Pressure 8 PSIA Surge Tank "A" Pressure 205 PSIG Surge Tank "B" Pressure O PSIG LIQUID WASTE System 62 NORMAL i REACTOR PLANT COOLING WATER System 46 Loop 1 P-4601 CLEARED OUT P-46015 CLEARED OUT Header Inlet Temperature CLEARED OUT Barrel and Top Head Outlet Temperature- CLEARED OUT Top Penetration Inlet Temperature CLEARED OUT Loop 2 '

P-4602 ON P-46025- CLEARED OUT Header Inlet Temperature 115 "F Barrel and Top Head' Outlet Temperature 115 'F Top Penetration Inlet Temperature c 115 'F Surge Tank Level "A" O INCHES Surge Tank Level "B" 45 INCHES

, _ _ _ _ _ , , , , , , ._a,- - - - - - - - - - - - - - - - - - - - - - - - - - ' '

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

~

FOSAVEX-90 PAGE 3 u

SCENARIO TIME: Ta-oarr CLOCK TIME:

PRIMARY AUXILTARIES

.......................****** BOARD:!-02 ******************************** ,

-HELIUM STORAGE System'24' -.

Low Pressure Bottles- 270'PSIG-High Pressure Bottles 57E PSIG= 4)

HELIUM CIRCULATOR. AUXILI ARIES System 21- ,

Circulator C-2103 (C)-

Bearing Water Flow 1 170 GPM

. Bearing Water Inlet Temperature 78,*F:

Main Orainz aP -2.5 PSID Buffer /Mid-Buffer AP -s- 8 PSIDS Buf fer Helium Flow 7.40 ACFM-Buffer Helium Return Flow .

3.79:ACFM Circulator C-2104 (D)

Bearing Water Flow 0 GPM' Bearing Water Inlet Temperature 78 *F:

Main Drain AP . 4 PSID Buffer /Mid-Buffer AP. 0:PSID .

Buffer Helium Flow 0 ACFM

-Buffer Helium Return Flow 0'ACFM

-1

....************************* BOARD I-03~******************************** .i n

REACTOR-CORE System 12 <-

All Systems NORMAL

............................. BOARD I-05 *********************************

' HELIUM CIRCULATORS ' System 21 Circulator C-2103 (C)

Rotor Speed . 2900 RPM i Helium Flow (Low Range) 02020:PSID ,

Helium Flow (High' Range) .0 %.  ;

Circulator,C-2104 (D)

Rotor Speed RPM-

Helium Flow-(Low Range)' -0.003 PSID Helium Flow-(High Range) 0%

MAIN 1 TURBINE System 51 -NORMAL 4

F05AVEX-90 PAGE 4'

.i

- SCENARIO TIME: re 6evs - i CLOCK TIME:

PRIMARY AUXILIARIES

. . . . . . . . . . . . . . . . . . . . . . . . * * * *

• B O A R O I ,- 0 6 t " * " " " " " " " " " " " " * " "

MISCELLANEOUS-Bypass Flash _ Tank Pressure 0 PSIG PLANT ELECTRICAL System 92 Essential Bus 1- ' Bus 2 ~ Bus 3- N/I' Bus 3- .-

480 VAC -485 -485: :485 H 120 :VAC 118 118- 118 118 -I

.120 VOC 125- 125~

"A" "B" Standby Diese) Generator NORMAL- FAILED ,

ACM Diesel Generator CLEARED OUT.

' Non-Essential Switchyard . - NORMAL-Bus 1 Bus:2- Bus.3 4160 VAC :4160- 4160 4160 480 VAC NORMAL:

1 MAIN TOWER System 41 DRAINED' --n SERVICE WATER TOWER System 42 <

NORMAL

-4 FIRE WATER System 45- NJRMAL :j

- INSTRUMENT AIR- System 82 " A" HDR =-- "B" HDR

93- .93 SERVICE AIR- System 82 -95 PSIG'-

............................* BOARD l-10 ********************************

PLANT PROTECTIVE SYSTEM REACTOR BUILDING TEMPERATURE - HIGH -l

. Bay 100- 80 'F Bay 200 80 *F-Bay-.300 80 'F i REHEAT ACTIVITY MONITORS 005 '

BUFFER SEAL MALFUNCTION NORMAL

F05AVEX -

PAGE 51 SCENARIO TIME: ve . n t e LCLOCK TIME: _

PRIMA'RY- AUXILI ARIES f

...................********** BOARD I-13 ********************************

PENETRATION INTERSPACE-AP 0 PSID:

REACTOR BUILDING $ UMP DISCHARGE FLOW- 30 GPM HELIUM CIRCULATORS System 21  ! NORMAL

............................. BOARD I-15 ********************************

REACTOR-BUILDING;STACKrFLOW- 129.9.KCFM-REACTOR BUILDING AMBIENT AP- --Oi25-Inches H20-CONTROL ROOM TEMPERATURE ~7 5' ' F -

............................. BOARD-I-7507X *****************************

480V ROOM TEMPERATURE 75 *F -

A f

FOSAVEX-90 SCENARIO TIME: W M GO CLOCK TIME:

RA01ATION MONITORS:

NUMBER VALUE ALARMING SENSITIVITY RT-6212 5.0 X 10' CPM Y 2.2E-8 RT-6213 5.0 X 10' CPM Y 2.2E-8 RT-7312 005 CPM N/A RT-7324-1 2.0 X 102 CPM N 1.57E-8 RT-7324-2 2.0 X 108 CPM N 4.36E-7 RT-7325-1 1.0 X 108 CPM N 1.49E-5 RT-7325-2 1.0 X 108 mr/hr N N/A RT-73437-1 1.5 X 102 CPM N 2.51E-10 RT-73437-2 4.0 X 105 CPM N 2.73E-10 RT-9301 005 CPM N/A -

RT-93252-12 1.5 X 108 mr/hr Y N/A s

AREA MONITORS RT-93250-1 2.0 X 102 mr/hr Y RT-93250-2 3.0 X 10' mr/hr Y RT-93250-3 5.0 X 10' mr/hr N RT-93250-4 3.0 X 108 mr/hr Y RT-93250-5 1.0 X 10' mr/hr Y RT-93250-8 6.0 X 102 mr/hr Y RT-93250-13 1.4 X 108 mr/hr Y RT-93250-14 2.5 X 102 mr/hr N RT-93251-1 7.0 X 105 mr/hr N RT-93251-3 8.0 X 10' mr/hr- N RT-93251-4 2.0 X 102 mr/hr Y '

RT-93251-5 1.0 X 102 mr/hr Y RT-93251-6 1.0 X 103 mr/hr Y RT-93251-7 0FF SCALE Y RT-93251-8 5.0 X 102 mr/hr Y RT-93251-9 0FF SCALE Y RT-93252-1 3.0 X 102 mr/hr Y RT-93252-2 3.5 X 108 mr/hr Y RT-93252-4 5.5 X 102 mr/hr Y RT-93252-6 4.0 X 102 mr/hr Y RT-93252-7 3.0 X 102 mr/hr Y EQUIPMENT MONITORS RT-6314-2 1.5 X 102 CPM N RT-46211 1.0 X 10' CPM Y RT-46212 1.0 X 10' CPM Y METEOROLOGICAL DATA Wind Speed 1.9 Wind Direction From 315 Degrees Plume Deviation / Sigma Theta 4.0 Degrees Differential Temperature 2.3 F

FOSAVEX-90 PAGE 1 SCENARIO TIME: 74 + c 3 ?.o j CLOCK TIME:

OVERALL PARAMETERS Reactor Shutdown YES Decay Heat Power 0.05 MW PRIMARY COOLANT Pressure 11 PSIA Temperature

• Circulator Inlet 95 'F Core Inlet' 105 *F Core Outlet 125 *F Calculated Bulk Core (CBCT) N/A Maximum Region Differential (AT) 28 *F Helium Flow Circulator C 10 X 108 Circulator D 0 X 10' TOTAL '10 X 108 Circulator Speed Circulator C '

2900 RPM Circulator D 0 RPM Moisture (Dew Point)

ME-9306 41 F 3

39 'F-ME-9307

. SECONDARY COOLANT Emergency Condensate Header Flow Loop 1 'O lb/hr Loop 2 2.0 X 10' lb/hr EES Inlet Temperature 85 *F EES Outlet Temperature -100 'F-Pressure 350 PSIA PCRV LINER COOLANT (In Service)

Loop 1 NO Loop 2 YES i

FOSAVEX-905 ..

.PAGE!2 :

SCENARIO TIME: rip r e8W y

CLOCK ~ TIME:-

~

PRIMARY AUXILI ARIES-

. . . . . . . . . . . . . . . . . . * * * * * * * " " BO A R D :- I - 012 * " * " " " " * " * " * " " " " " " * :

i H GAS-WASTE System 63- I a

Inlet Pressure l'0 PSIA 1 ,

Vacuum Tank Pressure- :8 PSIAl a Surge Tank "A" Pressure '205-PSIG' ?f Surge Tank "B" Pressurc 0_ P SIG -- 1 LIQUID WASTE System 62 -NORMAli +

p REACTOR ~ PLANT COOLING: WATER System 46 <

Loop 1- -

P-4601 CLEAREO OUT 1

-P-46015  : CLEARED OUT- l Header Inlet' Temperature .

-CLEARED OUT g Barrel and Top Head Outlet-Temperature ' CLEARED OUT l Top Penetration Inlet Ter.rature CLEARED.0VTL j

-Loop 2 P-4602 . ON . .

P-46025- CLEARED.00T-Header.Inle . Temperature 115 *FJ  ;

Barrel and Top .-Head Outlet Temperature - 115 'F- - 1 Top Penetration Inlet Temperature 115 .

• F- i Surge = Tank Level-"A" 0-INCHES:

Surge Tank Level "B"' 45 INCHES

• i 4

l 4

1 1

L_

F05AVEX-90' _ _

iPAGE 3 ,

- SCENARIO--TIME: rc eosw -

CLOCK TIME:

PRIMARY AUXILIARIES.

............................* BOARO I-02:'*******************************'

HELIUM STORAGE System 24' .

~

Los Pressure-Bottles 270 PSIG:

High Pressure Bottles- l575 PSIG1 HELIUM CIRCULATOR AUXILIARIES ' System 21:

' Circulator C-2103 (C)_

Bearing Water Flow- -170 GPM Bearing Water-Inlet Temperature' 78 'F >

Main'0 rain AP 2.5 PSID Buffer /Mid-Buffer AP

• 8 PSIO Buffer Helium Flow 7.40 ACFM Buffer Helium Return Flow 3.79 ACFM Circulator C-2104 (0)

Bearing Water Flow' O.GPM Bearing Water Inlet Temperature- 78 *F .

Main.Orain AP 4 PSIO-Buffer /Mid-Buffer 6P 0 PSID Buffer Helium Flow 0 ACFM Buffer Helium Return Flow .0 ACFM:

.............................BOARDI-03****"****************""*"***

REACTOR CORE System 12 '

-All Systems: NORMAL

............................. BOARD I-05 *********************************

1 <

l HELIUM CIRCULATORS' System 21 Circulator C-2103-(C) '

Rotor Speed 2900 RPM.

LHelium Flow (Low Range) . 0.020 PSID' Helium Flow (High Range) 0 .%

Circulator.C-2104 (0) .-

3 Rotor Speed- :0 RPM -

Helium: Flow'(Low Range) _ -0.003 PSIO Helium' Flow (High Range: 0 %-

l MAIN TURBINE System 51- ~NORMAL U

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

f g JFOSAVEXi90:

~

=-

L PAGE 4 y 1  ;

SCENARIO-TIMEf - A s e v e d

~

C'.0CK TI IMEi _____ ,

1 PRIMARY / AUXILIARIES- .

zi

. . . . . . . . . . . . . . . . . * * * * * * * * * * * * - B OA R D I - 0 6 " " * " " * " "

• L * " * " * " " * " " 4 y

~

MISCELLANEOUS Bypass Flash Tank Pressure 0 PSIO:

PLANT' ELECTRICAL - System 921 '

, ,7 Essential. Bus 1 . Bus 2 ;BusL3' -N/I; Bus'3-480 VAC ,48SJ 485-. 485  ? ~

120 VAC. :118c 118D '118' 118 .

120 VOC l125= 1251 ^ q "A". "B"-

Standby Diesel Generator ;RCRMALE_ FAILED

'ACM Diesel Generator JCLEARED 0UT y Non-Essential ,

i Switchyard NORMAL Bus .1? -Bus-2^ Bus'3~  ;

4160-VAC 4160 4160' -4160t

'480 VAC NORMAL:

MAIN TOWER -System 41 -DRAINEO>  !

SERVICE-WATER TOWER- System 42 (10RMAL - ' y FIRE WATER- System 45; 3 NORMAL--

INSTRUMENT AIR System 82 A'.' H D R -:

"B".HDR' 193 93. 3

. SERVICE = AIR System _82l JPS PSIG~

y BOARD'I-10"""*""*""*"""""*""

PLANT-. PROTECTIVE SYSTEM .

REACTOR BUILDING TEMPERATURE - HIGHD Bay 100- 80 '* Fg

-Bay'200 80'*F7 Bay 300 80 *F-4~

REHEATLACTIVITY-MONITORS C05

-BUFFER' SEAL MALFUNCTION NORMAL 1

. _ _ _ _ _ _ _ _ _ _ _ _ . ___..m._ _ _

i w 1 m 8 ~

r FOSAVEX-90 ,

PAGE 5.

$CENARIO TIMEfThes}D

-s . .

o Ct.0CK TIME:--  :

j PRIMARY AUXILIARIES

............................. s o A Ro . l .13 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . j 7

FENETRATION IN7EAS.' ACE AP . 0.PSID

.. i REACTOR BUILDING TU.MP DISCHARGo FLOW 0 GPHL HEL;UM CIRCUI.AT0kS System-211 "

3

- NORMAL'

- . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - B O A R 0 _ I - 1 5 : * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * --

REACTOR BUILDING-STACK FLOW -29.-9 KCFM:

REACTOR BUILDING ~ AMBIENT AP - -0.25 Inches 5H20:

CONTROL ROOM TEMPERATURE 175 aF-

........................***** BOARD I-7507X_*****************************-

i.

\ .

4 480V ROOM TEMPERATURE. 75MF <

J Y

.1 l

l FOSAVEX-90< i SCENARIO TINE: he a s h CLOCK TIME: 7-RADIATION MONITORS:L NUMBER VALVE ALARMINGL -SENSITIVITY' RT-6212 5.0'X 10' CPM- ;Y L 2.25-8 RT-6213- 5.0 X:10' CPM' Y- 2. 2 E- 3 --

RT-7312 ~005- CPM . N/A RT-7324-1 2.0 X 108 CPM N- 1.57E-8; l QT-7324 2: 2.0 X.108 CPM N 4;36E-7.:

RT-7325-1 1.0 X-108 CPM- N- -1.49E-5' RT-7325 1.0 X 108 mr/hr. ;N ~N/A RT-73437-1 1. 5 .. X - 10 8 CPM N; 2.51E-10 4, '

RT-73437-2 4.0 X 108: CPM) -N 2.73E-10: '

RT-9301 005- CPM . iN/A" i

, RT-93232-12 1.5 X1108 mr/hr Y, - N/A ;-

i AREA MONITORS

-RT-93250,-1 2.0 X.108 mr/hr Y RT-93250-2 3.0 X 108 mr/hr- Y RT-93250-3 5.0 X 10' mr/hr -N ,

RT-93250-4 3.0 X 10' mr/hr- Y

-RT-93250-5 1.0 X'10' mr/hr- Y; RT-93250-8 6.0 v.108 mr/hr- Y RT-93250-13 1.4 X 108 mr/hr Y RT-93250-14 2.5 X 102 mr/h r - .N d

RT-93251-1 7.0 X-108 mr/hr N- '

RT-93251-3 8.0 X 10' mr/hr= =N. . - -

RT-93251-4 2.0 X.108 mr/hr=. Y!

RT-93251-5.- 1.0 X 108 - mr/h_r . Y ll RT-93251-6 1.0 X 108 mr/hr' YJ o RT-93251-7 0FF SCALE. Y'

• RT-93251-8 5.0 X 108 mr/hr "Y RT-93251-9 0FF SCALE :Y RT-93252 -3.0 X--108 mr/hr-

-Y-RT-93252-2 =3.5 X;108 mr/hr- Y- o RT-93252-4 5.5 X 108=mr/hr. Y RT-93252-6i 4.0 X 108 mr/hr Y-RT-93252-7 3.0 X-102 mr/hr- .Y EQUIPMENT MONITORS RT-6314-2 1.5 K-108 . CPM- N-y RT-46211 1.0 X 10' CPM' Y RT-46212 1.0 X 10' CPM Y

, METEOROLOGICAL DATA Wind-Speect 1.9 Wind Direction From315 Degrees Plume : Deviation / Sigma Theta 4.0 Degrees Differential' Temperature 2.3 'F-

_-__-_______-_______x-- - --- ._ _ Y

. I a

F05AVEX-90. l 4

PAGE 1 1 SCENARIO TIME: --s + otV5  ;

i t

CLOCK TIME:

1 i

OVERALL PARAHETERS i

Reactor $hutdown YES l

Decay Heat Power 0.05 MW- .)

]

PRIMARY COOLANT Pretsure 11 PSIA Temperature, Circulator Inlet 95 'F -

Core Inlet- 105 'F 4 tore Outlet .

125 eF .

Calculated Bull Core (CBCT) N/A Maximum Regi.4, " fferential (AT) . 28 *F Helium Flow ,

Circulator C -10 X 108 i

Circulator 0 -0 X 108 '

TOTAL 10 X 108 Circulator Speed.

Circulator C '

2900 RPM Circulator D 0 RPM Moisture (Dew Point) '

ME-9306 .41 *F ME 9307 . 39 'F -

a i 4 SECONDARY COOLANT t Emergency Condensate Header- .

Flow-Loop l' 0 lb/hr .

Loop 2- 2',0 X 10' lb/hr EES Inlet Temperature' 85 'F EES Outlet Temperature 100 'F -

Pressure 350 PSIA i .i

. .. +

I PCRV LINER COOLANT' (In~ Service).

loop 11 LN0' .

Loop /2 YES

-[ >

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

. ~ . _ .  ;..... ,_,4,. . ,.,-~.,,,,% . ,....., .. ..,~., . .

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

l l

! FOSAVFb90-PAGE-2 SCENARIO TIME: To + ovic CLOCK TIME:

PRIMARY AUXILIARIES  ;

..........................."BOARDI-01""""*""*"*"*"*""**""

GA; WASTE System 63 i

I Inlet Pressure 10 PSIA Vacuum Tank Pressure 8 PS1AJ Surge Tank "A" Pressure 205 PSIG' Surge Tank "B" Pressure O PSIG LIQUID WASTE Sy5 tem.62' NORMAL REACTOR PLANT COOLING WATER System 46

+

Loop 1 P-4601 CLEARED OUT  ;

P-46015 CLEARED OUT Header Inlet Temperature CLEARED OUT Barrel and Top Head. Outlet Temperature CLEARED OUT - .

Top Penetration Inlet Temperature-- CLEARED OUT q Loop 2 _

P-4602: v- ON P-46025 CLEARED OUT Header Inlet Temperature _

115 'F Barrel and Top; Head Outlet Temperature 115 'F Top Penetration Inlet Temperature '

115F- ,

Surge Tank Level "A" 0 INCHES .

Surge Tank Level "B" 45 INCHES 3 .

i

't l

l \

l.

I i

l

, _ . ~. - , ,..c .i..- - - _ - ..., , , - + , . . . . , . , , , . . , - , , _ - , . , , , , , , , ,, . _ . . , , . . - , , , , , , -, .J. , ,, .

__..._m._.._._._.-._.._ _ . _ . _ - . . _. _ _ _ _ - _ _ _ _ . . _ . _ _ . _ _ _ . . .

i

. FOSAVEX I I

PAGE 3 l SCENARIO TIMEt c.s + c14r CLOCK TIME: i

PRIMARY AUXILIARIES l

.......................******BOARDle02""""*""""*""""""" )

L HELIUM STORAGE System 24 i Low Pressure Bottles 270 PSIG 1 High Pressure Bottles 575 PSIG j'

HELIUM CIRCULATOR AUXILIARIES System 21

~ Circulator C-2103 (C)' I Bearing Water Flow 170 GPM Bearing Water Inlet Temperature 78 'F .

Main Orain AP 2.5 PSID

-Buffer /Mid-Buffer AP 8 Pbt0 l Buffer Helium Flow 7.40 ACFM Suffer Helium Return Flow 3.79 ACFM Circulator C-2104-(D)

Bearing Water Flow - 0 GPM .

, Bearing-Water-Inlet Temperature 78.'F

" [

Main Drain AP -

' 4-PSID $

Buffer /Mid-Buffer AP ,

1 0 PSID' ,

Buffer H611um Flow - 0 ACFM

. Buffer Helium Return Flow - 0 ACFM <

l

............................' BOARD l-03 ********************************

i REACTOR CORE - System 12 ,

d .

All Systems NORMAL-

.............................BOARDl-05*********"**********************

HELIUM CIRCULATORS System 21 Circulator C-2103-(C) y Rotor Speed -

-2900 RPM- I Helium Flow (Low Range) 10.020 PSID Helium Flow (High Range) 0%

c Circulator C-2104 (D)-  !

Rotor Speed 0 RPM Helium Flow (Low Range). ' -0 003.PSID; Helium Flow (High Range) 0%

MAIN. TURBINE System 51 NORMAL i l

, 0

b t

. ~ ._ . , , , . . ,_..# . . _ . __ c .,,,.m_, -, __.,-,,m,__,-,. ...,r,__ , . . ,..,,,v......-~,... .

. ~ . . , ~

I

) F0$AVEX-90 -

i PABE 4

$CENAR10 TIME

-r a + csW CLOCK TIME:  :

r PRIMARY AUX!L! ARIES

....................n....." BO ARD l -06 * """ * * " * " * * * " * " """ " "

3 >

l MTSCELLANEOUS  :

i Bypass Flash Tank Pressure - 0 P$1G- l PLANT ELECTRICAL System 92 -

l Essential. Bus 1 Bus 2 Bus.3- N/I BusL3

! 4.80 .VAC 485 4B5 485 '

4 120 VAC 118- 118 118 118 -

, 120 VOC- 125 125 r "A" "B" >

i

! $tandby Diesel Generator NORMAL FA! LED ACM Diesel Generator CLEARED OUT ,

Non-Essential l

Switchyard e NORMAL bus 1 Bus 2 Bus 3

• 4160 VAC 4160 4160 4160

, 480 VAC NORMAL-MAIN TOWER $ystem 41 DRAINED 4

SERVICE WATER TOWER System 42 NORMAL FIRE WATER System 45 NORMAL T

IN$TRUMENT AIR System 82 "A" HDR. "B" HDR u' 93 93 System 82 95 PSIG -!

SERVICE AIR

...............n.........." BO ARD l- 10 " "" """ "" "" " " " " " " -

PLANT PROTECTIVE SYSTEM-i REACTOR BUILDING TEMPERATURE - HIGH: .

Bay 100 180 'F Bay 200 80 'F-1 - Bay 300' 80 *F REHEAT' ACTIVITY MONITOR $ 005.

i BUFFER SEAL MALFUNCTION-- NORMAL' I

l is l

'l L

+ -- - -. ,.,,m , - , , . , . . , . ., , _, . . , , . , , , , , , _ , , , _ _ . . _ , . , , , . 'l

F05AVEX-90 PAGE-5 .

SCENARIO TIME: vs + e%W CLOCK TIME:

PRIMARY AUXILIARIES

............................* BOAP.0 1-13 ********************************

PENETRATION INTERSPACE AP O PS10 REACTOR BUILDING SUMP 0!$ CHARGE FLOW 0 GPM HELIUM CIRCULATORS- System 21 NORMAL-

......................******* BOARD I-15 ********************************

REACTOR BUILDING STACK FLOW ,

29.9 KCFM REACTOR BUILDING AMBIENT AP -0.25 Inches H2O

- CONTROL' ROOM TEMPERATURE 75 'F ,

............................* BOAR 0'l-7507X *****************************

F u 480V ROOM TEMPERATURE 75 'F 1

. l b

t

- - _ . = - - . . . -

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

b 7.0-1 J

t SECTION 7,0 ONSITE RADIOLOGICAL DATA.

e Section 7.1 Plant Monitoring Data Page 7.1-1 7.2 Radiation / Chemistry Data Page 7.2-1 ,

7.3 Plant Area Radiation Levels Page 7.3-1 l

l

' 4 i

i

v v o SECTION 7.1 00SAVEX-90 Plant Monitoring Data '

0800 T2+15 T2-30 T2 T2-100 T2 T2-29 T2-44 T2-59 T2-114 Stack - PING:

RT-4801 1.0 E 1 1.0 E -1 1.0 E -1 1.0 E -1 1.3 E -1 i

RT-4802 1.0 E 1 1.0 E -1 1.0 E -1 1.0 E -1 1.0 E  !

RT-4803 1.0 E -1 8.2 E -4 7.5 E -5 2.$ E -6 5.0 E 6 Liquid: RT-6212 , 7.0 E -1 5.0.E -4 +5.0 0 -4 5.0 E -4 5.0 E l RT-6213 8.0 E -1 5.0 E - 1 5.0 E -4 5.0 t -4 5.0 E -4 Stack Noble Gas:

RT-7324-1 2.0 E -1 6.3 E -2 5.7 E 3 1.9 E -4 3.8.E -4 RT-7324-2 2.0 E -1 2.2 E -1 1.9 E +2 6.4 E -2 1,1 E -3 Stack Iodine:

RT-73437-1 -1. 5 E - 2 1.5 E -2 1.5 E ,-2 1.5 E -2 1.5 E 2-PCRV Relief Valve:

1.0 E -1 1.5 E -2 RT-93252-12 1. 6 E + 2 1.6 E -2 1.6 E -2 mr/hr - mr/hr mr/hr. mr/hr nir/hr L f

ALL READING IN CPM UNLESS SPECIFIED OTHERVICE I

?

s r

7 .1 - L

SECTION 7.1 EOSAVEX-90 Plant Monitoring-Data T2-115 T2 130 T2-145 T2-200 12+215 i T2+129 T2+144 T2 159 T2-214 END 1 l

Stack - PINO:

RT-4801 1.0 E -1 1.0 E 1 1.0 E 1 1.0 E 1 1.0 E 1 l RT-4802 1.0 E -1 1.0 E -1 1.0 E *1 1.0 E *1 1.0 E -1 ),

RT 4803 5.8 E -7 8.3 E -6 4.2 E -6 4.2 E +6 1.0 E -1 1.i q u i d : PT-6212 5.0 E -4 5.0 E -4

• 5.0 E -4 h . (' E -4 5.0 E -4 RT-6213 5.0 E -4 5.0 E 4 5.0 E -4 5.0 E -4 5.0 E -4 Stack Noble Gas.

RT-7324-1 4.5 E -5 6.3 E -4 3.2 E -4 3.2 E 4 2.0 E -1 RT-7324-2 1. 4 E + 4 2.1 E +1 1.0 E 3 9.6 E -2 2.0 E +1 Stack Iodine:

RT-73437-1 1.5 E -2 1. 5 E -2 1.5 E ,-2 1.5 E +2 1.5 E -2" PCRV Relief Valve:

RT-93252-12 1. 6 E -2 1. 6 E + 2 1.6 E -2 1.6 E -2 1.5 E -2 mr/hr mr/hr mr/hr mr/hr- mr/hr ALL READING IN CPM UNLESS SPECIEIED OTHERWISE f

7.1-2

\

i SECTION ?.2 FOSAVEX-90 ,

Radiochemistry Data j PRIMARY COOLANT RADIOACTIVITY LEVELS L

t If a primary coolarit grab sample 1:5 reqtiented, let necessary ,

personnel perform an actual graib sample test and use actual-resultn olta?.n-d.

e e.

7,2-1 l-s.

l L__.__.___.___.-_________________._.. -

I SECTION 7.3 TOSAVEX-90 AREA RADIATION MONITOR 0 Channel 'ocation R1-93250-1 Ref ueling Machine Control Rooni - Rx (el. 4881')

RT-93252-1 Refueling rioor Northeast -

Rs (el. 1881')

RT-93251-l* keactor Plant Exhaust filter Rooni -

Tb (cl. 4864')

RT-93250-2 East Walkway Outside HST ,Rx (el. 4849')

R"-93252 2 Ocuth Stairvell -

kN (el. 4864')

R1-93250 .1 Hut Oervice facility Platform -

kN (el. 1849')

kT-93251-3 Hot Cervice racility Blower Suction -

Rx (el. 4849')

RT-93250 4 Last Walkway HST Entrance -

Rx (el. 4339')

KT-93251-4 General O!!1ce Area -

Tb (el. 4811')

RT-93252-4 Analytic Instrument kooni -

Rx (el. 4829')

i RT-93250-5 Main Cont rol Rooni - Tb (el, 4829')

, RT-93251-5 cas Kaste filters -

Rx (el. 4781')

RT-93251-6 Reactor Building Truck Bay -

Rx (el. 4791')

RT-93252-6 Couth Stairvell - RN (el. 4791')

RT-93251-7 Core Support floor Filter -

RN (el. 4781')

RT-93252-7 East Walkway -

Rx (el. 4781')

RT 93250-8 Northeast Walkvay - Rx (el. 4771')

RT-93251-B Health Physics Room Laundry -

Rx (el. 4771')

RT-93251-9 Buffer Helium Dryer Loop 1 -

Rx (el. 4740')

RT-93250-13 Condensate Deraineralizers -

Tb lel. 4791')

RT-93250-14' East Wall Refueling Floot -

RN (el. 4881')

Rx = Reactor Building I Tb - Turbine Building t High range nionitot 7.3 1

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1 EgCTION 7.3 FOSAVEX-90 *

, Plant Area Radiation Levelo INPLANT CONTAMINATION LEVELS Prior to T2: 51DA for all non-HPCA aredo.

After T2: (llorfzontal Surfaces) f or non HPCA arects.

Level 1: 3000 dpm/100 cm' f MDA A Level 2: 2000 dpm/100 cin

$T

< MDA d Leve1 3: 1000 dpm/100 cm# p

< MDA d Level 4*: 300 dpm/100 cn/ $9

< MDA A Level 5: 200 dpm/100 cm# Si

< MDA d Level 6-1]: < MDA $Y

< MDA J

i 8.0-1 SECTION 8.0 0FFSITE RADIOLOGICAL DATA P Section ,

8.1 Meteorological. Data Page 8.1-1 8.2 Release Rate / Dose Assessment Page 8'.2-1 4

8.3 Field Monitoring Data .Page 8.3-1 8.4 Maps ";ge 8.4-1

• /

N E

= . .. - . - .-

+

, ' cv t

[

i

,SECTION 8.1' ,

FOSAVEX l

-Meterological Data 'I

.}

0800 T2+15-. T2+30 -T2445~ -T2+100' T2+115 T2+130 T2+145 .T3-200

.T2 T2+29 T2+44 T2+59 >T2+114~ T2+129 LT2+144L- -T2+159 T2+214-WZND SPEED 3.0- 2. 5 - ~2 7 -

. 2.7 2.5 !2. 2.- 2.0 li9'-  ; 2 .~ 3 L Ji (mph) ,

WIND DIRECTION 315 315. 315 =315- L315- 315 315 315- ':315i (degrees) .,,_

=

PLU.NE uGIATION/

4.0 4.0 7' SIGMA THETA 4.0 4 . 4.0. 4.0 4. 0.. 4.01 ,4.0L (degrees)

DIFFERENTIAL  ;

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/

u 4

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i SECTION 8.2 '

FOSAVEX-90 l Release' Rate / Dose-Assessment  ;

Plume Segment:- A- From T2+:15- To T2+:29 Release Rate:

Noble Gas: 1.4 E -4 C1/sec Iodine (Total).: O C1/sec PROJECTE DL,'S: ,

D%ST- DILUTION WHOLf;30DYLCHLD THY-ANCE FACTOR 308E' RATE DOSE l RATE

. (41 LEE) (SEC/MS) (REM /HRF (REM /HR)-

-EAB 3.254E- 4 '3.660E--5 -0.000E+ 0 1.0 8.947E 1-062E- 5 0.000E+ 0 i 2.0 4.162E -5 4.938E- 6 0.000E+ 0. '

-/

3.0 2.696E- 5 '3.199E- 6 0.000E+ 0-4.0 1.983E 2.352E-16 0.000E+ 0 5.0 1.559E- 5 1.850E- 6 LO.000E+ 0 6.0 1-.083E- 5' 1.522E _6- 0.0_00E+ 0 7.0 1.090E 1.293E- 6- 0.000E+ 0: -

8.0 9.478E-'6 1.1'25E 6 'O .' 0 0 0 E + 0-9.0 8.385E- 6 9.949E- 7 0.000E+~0 '

10.0 '7.518E- 6: 8.920E- 7 0.000E+EO 20.0 3.620E- o 4.296E- 7: 0.000E+ 0 -

30.0 2.375E- 6 2.818E- 7 0.000E+ 0 2

40.0 1.755E- 6 2.083E- 7f .0.000E+ 0 50.0 1.386E o 1.e45E 7 0.000E+ 0 8.2-3

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

t

=-;

SECTION - 8. 2 --  ;

FOSAVEX-90 Release Rate / Dose AsseLsment Plume Segment: B From.T2+:30- To T2+:44 Release Rate: -

Noble Gas: 1.3 E Ci/sec -

j Iodine'(Total):- 0 Ci/sec PROJECTED DOSES: s lyrsr.-

3rLOTION ?WHOLE BODYLCHLDLTHY I AWCE FACTORz ~ DOS E ' RATE - DOSE LRA TE (MIL E G) (SEC /M3) '(REM /HR) g(REM /HR)

EAB 3.013E :4 3.234E- 4 -O'.000E+ 0' 1.0 8.285E- 5 8.894E 0.000E+ 0- j 2.0 3.854E- 5 4.137E--5

/

J0.000E+-0 5.0 2.496E- S' 2.680E 5- O . 0 0 0 E + -~ 4.0 1.836E- 5 1.971E- 5 -0.000E+s0-5.0 1.444E- 5 1.550E-15 :0.000E+ 0-.

6.'O 1.18SE- 5 '1.275E .5- 0.000E+ O 7.0 1.009E- 5 1.083E- 5' O.000E+'0- -

8.0 8'.776E '6 9.422E- 6: 10.000E+ 0-9.0 =7.764E :6 -i 8.335E- 6 0.000E+ 0' a

10.0 ~6.'961E- 6

-7.473E <

0.000E+ 0-20.0 3'.352E-.6 3.599E- 6' O.000E+ 0;-

30.0 2.199E- 6 2.361E-'6: _O.-000E+ 0' 40.0 1.625E- 6. 1.745E-;6 .0.000E+ 0 50.0 1.283E --6 1.378E 6' O.000E+ 0 i

8.2-4 1

- . . ~ . .

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

4 I

'?

'SECTION 8.2_ _;

' FOSAVEX-90 Release-Rate / Dose Assessm'nt- e j

Plume Segment: C From T2+:45 To T2+1':00- -- -

-t Release Rate:

Noble Gas: '4.2 E Ci/sec  ;

Iodine . (Total)-: O C1/se'c 5.

PROJECTED DOSES:

DIST- ~ DILUTION WHOLE-BODY CHLDEThY

~

ANCE FACT 6R DOSE RATE = DOSE RATE (MILES) (SEC/M3) . (REM / HR) -(REM /HR) .

EAB 4.872E--4 1.744E _0.000E+ 0

1. 0- 1.359E-J4. -4.861E 0.000E+LO-

-2. 0 6.401E .5 2.2,90E 4 .0.000E+-~0 3.0 -4.130E -1.478E- 4' O.000E+ 0 4.0 3.019E--5 1.-080E---4 01000E+L0 5.0 2;372E- 5 8 . 4 8 7 E - : -0.000E+10-6.0 1.953E- 5' 6.989E .5 0.000E+ 0-  ;

7.0 ti.661E- 5 5.945E-.5 f0,000E+-O l 8.0 1.447E- 5 '5.176E--5 0 000E+[0' 9.0 1.283E .5 '4.592E--5 0.000E+<0 10 . 0 -- 1.155E 4.131E 5 -0.-000E+DO 20.0 5.919E .6 '2.118E 0.000E+-0 0.000E+ O'

~

30.0- 4.107E- 6 -1.470E -5 -

l I

40.0 :3 ~.'15 9 2 -' 6 1.130E 0.000E+ 0 ]

50.0 '2.574E- 6 9.".09E--'6 0.000E+ 0-

^

8.2-5

_ _ _._ - - . . _ _ - . _ . . .m - _. - - , , , .. __.I

i a i I-1 FECTION 8.2 FOSAVEX-90 Release Rate / Dose Assessment Plume segment: D From T2+1:00 To T2+1:14 Release Rate:

Noble Gas: 8.4 E -3 C1/sec Iodine (Total): O C1/sec PROJECTED DOSES:

DIET- D1LUT10N WHGLE E:0 D Y CHLD THY ANCE FACTOR DOSE RATE DOSE RATE (MILES) (SECIM ? > - MEM/ hR) (REM /HR)

EAE; 5.162E- 4 3.766E- 3 0.000E+ 0 1.0 1.467E- 4 1.050E- 3 0.0i E+ 0 2.0 6.913E- S 4.94,7E- 4- 0.000E+ 0 3.0 4.460E- 5 3.192E- 4 0.000E+ 0 4.0 3.2e.1E- 5 2.334E- 4 0.000E+ 0 5.0 2.561E- 5 1.833E- 4 0.000E+ 0 6.0 2.100E- 5 1.510E- 4 0.000E+ 0 7.0 1.794E- 5 1.284E- 4 0.000E+ 0 8.0 1.562E- 5 1.118E- 4 0.000E+ 0 9.0 1.386E- 5 9.919E- S 0.000E+ 0 10.0 1.247E- 5 8.924E- 5 0.000E+ 0 20.0 6.391E o 4.574E-'S 0.000E+ t 30.0 4.436E- 6 3.175E- 5 0.000E+.O-40.0 3.412E- 6 2.442E- 5 0.000E+ 0 50.0 2.779E- 6 1.989E- 5 0.000E+ 0 i

8.2-6

. .t. <

\

SECTION 8.2 FOSAVEX-90  :

Releare Rate / Dose Assessment

{

Plume Segment:. E 1From T2+1:15 To-T2+1:29- ,

Release Rate: s t

Noble Gas: 9.9'_E -2 Ci/sec_ .,

lodine.(Total): O C1/sec-PROJECTED DOSES:

D!ST- DIL UT 10_N  : WHOLE-BODY CHLD THY ANCE. FACTOR DOSE RATE: DOSE ~-_R A TE _

(ii! L Ei n (SEC/m3h ( RE M / hR)- (REM /HR)

EAB 3.e.97E-_4_ ?3.'133E--2. :0.000E+ A- -

t

~

1.0 1.017E- 4 -8.617E.3 -

'O.000E+ 0 2.0 '4.729E --5--4.008E /_

' 3: ' 0 . 0 0 0 E + : 0 .-

3.0 3.064E-- 5  :-2. 597 E 3 0.000E+io 4.0 2.253E--5 1.909E 3' O .'00 0E+ : 0' S.O 1.772E- 5 1.502E---3'-0.000E+'O >

6. 0 - _1.454E'=5 1.235E- 3' O.000E+ 0 7.0' 1.23GE- 5 1.050E--3 0.000E+:0 5.0 -.1 '. 0 7 7 E - 5 9.129E -4 0.000E+-0-'

9.0 9,5I9E 3.076E 0.000E+ 0 10.0' 4l.543E- 6 7.240E- 4- -0.000E+ 0 1 20.0 4.114E -6 3. 417 E- 4 10.000E+ 0i f

30.0 2 . :. ; ; E - - : -

2.227E- 4 0.000E+='O 40.0 1. M SE ~ 6 1.690E- 4 0.-000E+ 0

?

$0.0 1.57!I- 4 1.335E- 4 0.000E+ 0

( 8.2-71  :

l

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

l l

i SECTION 8.2 FOSAVEX-90 Release Rate / Dose Assessment-Plume Segment: F From T2+1:30 To T2+1:44 Release Rate:

Noble Gas: 1.4 E Ci/sec l

Iodine (Total): O C1/sec PROJECTED DOSES:

. DIST- DILUTION WHOLE BODY CHLD THY A N C. E FACTOR DOSE RATE DOSE RATE (MILES) (SEC/M3) (REM /HR) (REM /HR)

(

-EAB 4.067E- 4 4.826E- 3 0.000E+ 0 1.0 1.118E- 4 1.327E- 3 0.000E+ 0 2.0 5.202E- 5 6.17CE- 4 0.000F+ 0-3.0 3.370E 3.999E- 4. 0.000E+ 0 4.0-2.478E- 5 -2.941E -4 0.000E+'O 5.0 1.949E- 5 2.313E- 4 0.000E+'O' ,

6.0 1.603E- 5 1.902E- 4- O '. 00 0E + 10 7.0 1.362E-15 1.616E- 4 0.000E+ 0 8.0 1.185E- 5 1.406E- 4- 0.000E+ 0 9.0 1.048E- 5 1.244E- 4 0.000Et 0 10.0 9.397E- 6 1.115E- 4 0.000E+ 0 20.0 4.526E- 6 5.370E- 5 0.000E+ 0 30.0 2.969E- 6 3.522E- 5 0.000E4 0 40.0 2.194E- 6 2.603E- 5 0.000E+ 0 50,o .7aat- 6 24*~o e .

2. 51. ;1 1 400E+ 0 8.2-8

9

.)

}

SECTION 8.2 FOSAVEX-90 Release Rate / Dose Assessment Plume Segment: G From.T2+1:45- 'To T2+1:59

~

-J Release Rate:

Noble Gas: 7.1 E Ci/sec-Iodine (Total): O Ci/sec PROJECTED DOSES: y DIST-DILUTION- WHOLE BODY CHLD THY

. ANCE FACTOR

' DOSE RATE- DOSE RATE (MILES) (SEC/M3) (REM /HR) (REM /HR)

EAB 6.924E- 4 4.173E- 3 0.000E+ 0 1.0 1.931E- 4 1.164E- 3 -0.000E+ 0 2.0- 9.096E- 5 5.482E- 4 0.000E+ 0

/

3.0 5.86BE- 5 3.537E- 4 0.000E+ 0-4.0 4.291E- 5 2.586E- 4 0.000E+ 0 5.0 3.370E- 5 2.031E- 4. 0.000E+ 0-6.0 2.775E- 5 1.673E--4 0.000E+ 0 7.0 2.361E- 5 1.423E- 4 0.000E+ 0 8.0 2.056E 1.239E- 4 '

0.000E+ 0 9.0 1.824E- 5 1.099E- 4 0.000E+ 0 10.0 1.641E- 5 9.888E- 5 0.000E+ 0 .

20.0 8.410E- 6 5.068E- 5 0.000E+ 0 30.0 5.836E- 6 3.517E- 5* 0.000E+ 0 40.0 4.499E- 6 2.706E 0.000E+ 0 30.0 3.66?E- 6 1.104E- 5 0.000E+-0 8.2-9

e, SECTION 8.2 FOSAVEX-90 Release Rare / Dose Assessment Plume Segment: H From T2+2:00 To T2+2:14 Release Rate:

Noble Gas: 7.1 E -3 Ci/sec Iodine (Total): O C1/sec PROJECTED DOSES: ,

DIST- DILUTION WHOLE BODY CHLD THY-ANCE. FACTOR DOSE-RATE-' DOSE RATE (MILES) (SEC/M3) (REM /HR) (REM /HR)

EAB 5.720E- 4 3.447E- 3 0.000E+'O -

1.0 1.595E .4 9.612E- 4 0.000E+.0 2.0 7.514E- 5 4.528E -4 - 0.000E+ 0 3.0 4.8'48E- 5' 2.922E- 4 0.000E+ 0 4.0 3.545E- 5 2.136E- 4 0.000E+-0 5.0 2.784E- 5 1.678E 4 0.000E+ 0 6.0 2.293E- 5 1.382E 0.000E+ 0 7.0 1.950E 1.175E- 4 -0.000E+ 0 8.0 1.698E- 5 1.023E- 4 0.000E+ 0 9.0' 1.506E- 5 9.079E- 5 ' 0'.000E+-0

-10. 0 - 1.355E- 5 8.168E 5- 0.000E+ 0 20.0 6.947E- 6 4.187E- 5 0.000E+ 0-30.0 4.821E- 6 '2.906E 0.000E+ 0 40.0 3.709E- 6 2.135E- 5= 0.000E+ 0 50.0- 31 21E- 6 1.821E 0.-000E+ 0 8.2-10

.a . - , --,<w.,- -,r -

L SECTION 8.3 FOSAVEX-90 Field Monitoring Data-  ;

Time:- - From 0000- To T2+:29' IN FIELD SAMPLING RESULTS -j Ambient-Radiation Levels Particul' ate I-131' (mr/hr) Activity- Activity-Concentra-- Net .Concentra- Net' Dista--* Window Window Count Rate' - tion- Count Rate I (milea. fClosed Open h- tion( Ci/cc) (cpm) -

'( Ci/cc) (cpm)-

EAB Bkgd*- Bkgd* MDA 0 MDA 0 0.5 - Bkgd* Bkgd* MDA 0 MDA 0 1.0 Bkgd* Bkgd* MDA 0: MDA. 0 1.5 Bkgd* Bkgd* MDA 0 MDA 0- 4 2.0 Bkgd*~ --

Bkgd* ~MDA 0 MDA 0 i m 2.5 Bkgd* - Bkgd* MDA 0 MDA 0 ti 3.0 Bkgd* - Bko4* 'MDA 0- -MDA' 0 4.0 Bkgd*' Bkgd*- 'MDA' 0 .MDA~ .0 5.0 _Bkgd* Bkgd* MDA 0 MDA- 0-6.0 Bkgd* Bkgd* -MDA -0 MDA. 0 7.0 Bkgd*~ Bkgd* -MDA ~0 =MDA: 0-8.0 Bkgd* - Skgt

• MDA 0 MDA 0

- 9.0 Bkgd*- Bkgd*- MDA 0 MDA' O 10.0 _Bkgd* _Bkgd* MDA 0- MDA. .0 -

l

• Actual' Met'er Reading

- Note: True reading = 5(hY-k )

8.3-1

- .~- m . n -- . ,--# ,,, , , , -.....,n+w--,--r--n - wr w , -

ars + .v r , e

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

~

~- .

. ELCTION 8.3 FOSAVEX-90 .

field Monitoring Data- l Time: From T2+:30- To T2+144' s

IN FIELD' S AMPLING - RESULTS Ambient-Radiation '!

Levels Particulate .I-131 i (mr/hr) . Activity- Activity -L

-Concentra NetL -

Concentra - Net tion tion- _

~

Distance Window Window .

Count Rate- Count Rate:  ;

(miles) 3 Closed- _Open@d-- ( Ci/cc) (cpm) ( Ci/cc)-

(cpm)7 EAB 0.2 4.2 MDA 0' MDA 0 0,5 Bkgd* 2.9_ MDA 0 MDA 0 -3 i

1.0 :Bkgd* 1.6 MDA -0 MDA' .0-1.5 Bkgd* Bkgd* 'MDA 0 - MDA 0_ gI 7

2 . 0 -- Bkgd* Bkgda- MDA 0- - MDA _- --

05 i 2.5 .Bkgd* Bkgd* MDA 0- MDA .0 3 3.0 Bk;d* Bkgd* .MDA> 0 - MDA- -0 4.0 Bkgd*' Bkgd* _MDA 0 - MDA 0 l

5.0 Bkada Bkgd* MDA 0- MDA -- 0 --

6.0 .Bkgd* Bkgd* MDA 0 MDA' O 7.0 Bkgd* Bkgd* MDA- -0 MDA. 0 8.0- Bkgd*' Bkgd* MDA 0' - MDA -0 9.0 Bkgd* Bkgd* .. MD A 0 - MDA- -- O j 10 ~. 0 - Bkgd* Bkgd* MDA 0 MDA ~'O i

l

• Actual Meter Reading

' Note: True reading = 5pd-k) 8.3 ,

, - , - - , . ,.grrr,e

, y-,-.. -.--y r -

-$ n ~ ~ , -,e-- ~m,m.,e -

. _ _ . - _ - . . _ . ..-._._.__m..

4 r

i SECTION 8.3- 1 FOSAVEX-90 ~

Field Monitor 1ng Data Time: From T2+:45 70-T2+:59

.i

-IN~ FIELD SAMPLING RESdLTS Ambient -!

Radiation -

l Levels Particulate: I-151 '

.(mr/hr) . Activity.) Activity Concentra- *.Not .Concentra Net Distance- Window Window tion. Count ~ Rate Lion' Count 1 Rate (miles) TClosed Openg$ ( Ci/cc) (cpm)  :( Ci/cc) (cpm)

EAB 1.6 33.0 'MDA 0 -MDA- 0 0.5 1.0 20.7 MDA- 0: MDA- " 0 -- -

1,0 0.4' -8.3 MDA Os -MDA> 0~

1.5 0.3 6.2 MDA 'O MDA 'O=

2.0 -0.2- 4.0 MDA 0 MDA 0 2.5 Bkgd*- 1.9 MDA- .0 MDA=  : 0~

3.0 Bkgd* Bkgd* MDA 0 MDAi 0 -

4.0 Bkgd* Bkgd* MDA MDA 'O-

-5.0 Bkgd* .Bkgda~ -

MDA. -.0 - MDA 0 6.0 Bkgd* Bkgd* MDA '0- MDA .- 0 :-

7.0- Bkgd* .Bkgd* MDA' O MDA 0 .

8 .~ 0 LBkgd* Bkgd* MDA 'O- -MDA~ .0-9 . 0 - .. Bkgd* Bkgd* MDA 0' MDA 0-10.0 .Bkgd* Bkgd* .MDA - 0- ,MDA- -0 Actual: Meter Reading

' Note: True greading .= 5(hk-i) -

8.3-3

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

ffCTION 8.3' FOSAVEX-90 i Field-Monitoring Data' l Time: From.T2+1:00 To T2+1:14 1

.1

~IN FIELD SAMPLING RESULTS l Ambient Radiation Levels Particulate' I-131 (mr/hr) Activity Activity, Concentra- Net Concentra T Net.

Distance Window Windov tion Count Rate tion: Count-Rate (mile s) TClosed Open%9 -

( Ci/cc) (cpm) i( Ci/ce) -(cpm)-

EAB 3.5 73.0 MDA 0' MDA- 0: -

0.5 2.3 46.5 MDA. O ;MDA- 0 1.0 1.0 20.0 MDA 0: MDA~ 0-1.5 0.7 13.5 'MDA

~0' 'MDA- 0,

't 2.0 0.4 7.0 MDA- 0' .MDA

0.

2.5 0.4 6.5 MDA 0 lMDA 0 3,0 0.3 6.0 MDA -0. i.MDA 0 4.0 0.2 4. 0 =. MD A '. '0- 'MDA 0 t

5.0 Bkgd* Bkgd* -MDA: 0 -MDA 0' 6.0 Bkgd*- Bkgda MDA - --MDA - O '-

7.0 Ekgda Bkgd* MDA- 0 MDA. 0 8.0 Bkgd* Bkgd* MDA. 'O MDA 0-r 9.0 Bkgd* Bkgd* MDA' -0 MDA 0 10.0 Bkgd* Bkgd* MDA -b MDA 0 h *

' Note:ActualMeterReadingh-S-):

Truepreading=5(

t r

6.3-4

' ;I t

. . . . . , . . . . , . , - + ,L. - - - - - . , .

r l

j SECTION 8.3:

'FOSAVEX-90 Field Monitoring Data'  ;

i

-j Time: From T2+1:15 -To T2+1:29!

l IN FIELD SAMPLING RESULTS l Ambient  ?

Radiation 5 Levels Particulate- I-131-(mr/hr) -Activity ~

., Activity-Concentra ' Net: Concentra = Net =

Distance Window Window tion Count Rate- tion! -

_ Count Rate

, -(miles) IClosed- Open$N ( Ci/ce)

(cpm) .( .Ci/ce) (cpm)

'i EAB 30.0. 625 -MDA~ 0 MDA- -O 0.5 19.1 .395 MDA O_'- :MDAi

. 0 .-

1.0 8.2 165 MDA ~- 0 : :MDA. 0 1,5 6.0 122 MDA- _ 0.- MDA 0,

/

2.0 3.8 79.0' - MDA- 0- lMDA= 0 Li 2.5 3.0 60.5 MDA _0. MDA 0 3.0 2.1 42.0 MDA~ 0- MDA. '0- <

4.0 1.5 31.0 -MDA- 0 MDA 00l 5.0 1.3 27.0 ~MDA 0- MDA: 6.0 1.0 21.0 MDA 0 MDA 0 1 7.0 0.9 18.5 MDA:- =0L MDA: 0- i 8.0 0.8' 16.5 MDA- 0- MDA :0- -)

9.0 0.7 14.b MDA'  :. 0 - MDA- Oi -- -;

10.0 - 0.6, 12.5 MDA' . 0- MDA- 1 0_ -

• Actual Meter Reading. '

Note: True reading = 5( ~f) e o p 8.3-5  ;

i ,

,-r --

--,-.-,J.L >--,n .- - .. -

' 'i 4.. ..

q SECTION 8.3: lj FOSAVEX '

Tield Monitoring Data. .i Time: From T2+1:30- To=T2+1:44- .

\

IN' FIELD SAMPLING:RESULTS i Ambient l'

i Radiation Levels Particulate I-131'- (j (mr/hr) . Activity' -Activity-Concentra- Ne t-- -~Concentra--- Net Distance Window Window tion Count Rate- tioni Count Ratei (miles) jClosed - Open$i .( Ci/ce) (cpm)- ( C1/ce) (cpm); '

,i i

EAD 4.5 95.0 Il MDA 0 MDA-- ~0- -1 0.5 2.9 58.0- -- MD A 0- -MDA-0- . N 1.0 1.2 21.0 -- M D A > 10 MD A -~ 0=

1.5 0 =. 9 16.5 MDA 0' MDA- 0- >

2.0 0.6 12.0 MDA 0 MDA 0: bg 2.5 0.5 9.0 MDA- 0 MDA: 0 j 3.0 0.3 6.0 MDA- 0 .

_MDA- 0 --

4.0 0.2 4.0 MDA 0: MDA- 0-5.0 Bkgd* Bkgd* MDA 0. MD A -= 0-6.0 Bkgd* Bkgd* LMDA 0 MDA; O I 7.0 Bkgd* Bkgd* MDA' (0- MDA 0-8.0 Bkgd* Bkgda MDA- 0 MDA 'O' 9.0 'Bkgd* Bkgd* MDA 0, MDA- -0 ~ ,-

10.0 Bkgd* BLgd* <MDA. '

MD A .' =0" Actual Meter Reading Note: True g reading = 5(h- )

8.3-6 - 1

. 1 0

> \'

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

- s i

SECTION-8.3 f FOSAVEX-90 i

. Field Monitoring Data i 1

Time: From T2+1:45 To T2+1:59 IN FIELD SAMPLING RESULTS i  !

Ambient '

Radiation'. ..

Levels Particulate _I-131' (mr/hr) Activity - Activity--

Concentra- ' Net Concentra-~ Net' -

l Distance Window Window t tion- Count-Rate j i (miles) jClosed .Open h (ion.. Ci/cc) , (cpm)

Count: Rate' 4( Ci/cc) (cpm)' A EAB 4.0 84.0 MDA .0- MDA- 0 1 1

0.5 2.5 52.5 MDA 0: MDA; O "

}

1.0 1.0 21.0 'MDA 0 MDA- 'O' l 1.5 0.8- 15.5 MDA 0. MDA' .0  :

/ f 2.0 0.5 10.0 -MDA- 0'- MDA _ 0 .-

- o l 2.5 0.4 8.0 MDA 'O -MDA- 0- -i 3.0 0.3 6.0 'MDA- 0 ;MDA- 0.

l 4.0 0.2- '4.0 MDA 0 -- MD A ~0-l 5.0 Bkgd* Bkgd* MDA [0 MDA 0

[

6.0 .Bkgd* Bkgd* MDA- 0 MDAL 0-7.0- Bkgd* Bkgd* MDA 0 '.MDA 0 8.0 'Bkgd* Bkgda MDA 0 MDA~ 0: r

, 9.0 .Bkgd* -Bkgd* MDA 0 -MDA: 0 10.0 Bkgd* Bkgd* MDA 0 MDA 0 a Actual Meter Reading )

Note: True g reading = 5(pi T) i 8.3-7  ;

_ m. _. . . _._ _. _ _ _ .

cj s

.SECTION 8.3' FOSAVEX.90' TieldLMonitoring Data-r Time: From-T2+2:00 .To T2+2:15 IN FIELD SAMPLING RESULTS' Ambient i Radiation Levels Particulate I-131

-(mr/hr) -Activity Activity.

Concentra- Net- Concentra-- Net- -

Distance Window Windo Count = Rate tion - Count-Rate- it (miles) IClosed Openhw.(-C1/cc) tion (cpm) -( Ci/cc). (cpm): i EAB 3.0 63.0 MDA 0 -MDA 0 0.5 1.9 39.5- MDA 0 MDA 0 1.0 0.8 16,0 MDA- 0 MDA- 10" 1.5 -0.6 12.3 .MDA- 'O . MDA. 0- .

/ .

2.0 0.4 8.5 MDA 0 MDA- O.

2.5 0.3 6.3 MDA- 0, MDA. Oc 3.0 0.2- -4.0 MDA: 0- MDA~ 0 4.0 Bkgda- Bkgd* _MDA 0 MDA -0 5.0 Bkgd*. Bkgd* -MDA 0 MDAL 0 6.0 Bkgd* Bkgd* MDA 0- MDAL 0-I 7.0' Bkgd* Ekgd* MDA MDA 0-8.0 Bkgd* Bkgd* MDA 0- MDA :0 -

9.0 Bkgd* Bkgda MDA 0- MDA 0 10.0 Bkgd* Bkgd* MDA 0 MDA 0

-* Actual Meter Reading Note: True reading = 5(fY- )

-8.3-8 J

i SECTION 8.3 i

, FOSAVEX-90 1 Field Monitoring Data i

Time:L From T2+2:15l To End IN FIELD SAMPLING RESULTS -i Ambient >

Radiation Levels Particelate I-131 (mr/hr) Activit,yy Activity j Concentra- . Net- Con' centra Net.

Distance Window Window t Count Rate tion' Count Rate (miles) jClosed Open k (ion' Ci/cc) (cpm) ( Ci/cc) (cpm) 9 EAB Bkgd* Bkgd* MDA 0 MDA ^0 0.5 Bkgd* Bkgd*- MDA 0 MDA 0 5 1.0 Bkgd* Bkgd* MDA 0 MDA- 0 1.5 Bkgd* Bkgd* MDA 0/ MDA: ,

O.

i, 2.0 Bkgda Bkgd* MDA 0 'MDA- 0 2.5 Bkgd* Bkgd* 'MDA 0 MDA- 0 3.0 Bkgd* Bkgd* MDA 0 MDA> 0 -' -l 4.0 Bkgd* Bkgda MDA 0 MDA. 0-4 5.0 Bkgd* Bkgd * -- MDA- 0- MDA' O' ,)

6.0 -Bkgd* Bkgd* MDA 0 MDA- 'O 7.0 Bkgd*- Bkgd* MDA '0

-MDA- 0 8.0- Bkgd* Bkgd* MDA 0 MDA 0; 9.0 Bkgd* Bkgd* MDA .0 MDA 0 10.0 Bkgda- Bkgd* MDA 0 MDA 0 Note:Actual' Meter Reading True$Qreading=.5( k- ) -i 8.3-9

. i.

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SECURITY anunNE MM . q CITY -

+N y 170'

9 . 0 -

SECTION

9.0 REFERENCES

1 Section i

, 9.1 Procedure Index Page 9.1-1 9.2 Key Documents Page 9'.2-1 4

4 4

J n

4

, ~ wy e

_ ._~ . _ _ _ __ . ._ _ .. .

9.2-1 SECTION 9.1 l

PROCEDURE INDEX l

Tables 9-1 and 9-2 identify the FSV RERP Implementing Procedur9s and Suoporting Procedures respectively. Controllers / Observers should' become familiar with those ' procedures which directly affect the portion of the emergency organization they are _ responsible-. for evaluating, s

e 4

/

O

=*

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

i 9.1-2

~

4

~

TABLE'9-1 RADIOLOGICAL EMERGENCY RESPONSE PLAN.

IMPLEMENTING PROCEDURES:

j N0, SUBJECT- .

i l

Emernency Procedures EP-CLASS Classification Guidance ,

Book No. 1 of-RERP ImplementingiProcedures- 1 RERP-Alert -Action: 5,umma ry . .for=  ; Alert iClassification  ;

RERP-Site Area Action : Summary .for l Site : Area-Eaergency Classification <

RERP-GE ActionlSummary for General Emergency:

Classification

~'

t RERP-NOTIFICATION Prctedure for making-notifications' outside;of the-Control Room' l

RERP-CED Procedure . for- :the . Corpo' rate j Emergency Director,- ;l RERP-CR Control Room procedure -!

REkP-ECP- Executive-CommandPost; procedure' i RERP-FCP Activation of the Forward Command l ~ Post RERP-PCC Activation: of the Personnel Control?

Center-RERP-SEOC State Emergency, Operations -Center.  !

procedure RERP-TSC Activation -of the-Technical Support

-Center f;

-RERP_-RECOVERY 1 Recovery Operations procedure 1 q

-i

+

'I

_* y,..

. ._ ._.m.._- _

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

q

' ~

953_

1

. . TABLE'9-1 ' l RADIOLOGICAL: EMERGENCY RESPONSE PLAN: -

IMPLEMENTING PROCEDURES a

!NO. SUBJECT .

.. t 1

Book No.-2 of RERP Implementino Procedures J*

- RERP-CORE

- ~ Core Damage Evaluation-RERP-DECON Emergency Decontamination Practi.ces-;

RERP-DOSE- Off-31te Do s e -- Calcul.ation .;

Methulology,- .,

- 1

- RERP-ENVIRON. Long Term Environmental Monitoring ,

l

~RERP-EVAC Evacuation of Site procedure -3 i

. RERP-EXP EmergencyExposureLGuidelines s  ;

r RERP-FIELD -Field Monitoring procedure- -

RERP-MET' Meteorologicali Data iAcquisition-procedure

.RERP-PAR Protective Action Recommendations"

- procedure -' 9 L

RERP-SURVEY ~ Inplant/Onsite- -

. Radiological

-Monitoringfprocedure;

~

LFormation' 'and-RERP-TEAMS- Emergency . Team' 4 .

Direction p)ocedure-Thyroid'_ _ Blocking- Agent-! j RERP-THYROIDT Administration'_ procedure- , j q

f

.li i

L r

if

t. ."

\c .i I -. m . . . . . .- . - . . - . - - . . ,4., _ . . , ,-..,.,,-/,, - . . , . . , . . , _ .

9,1-4 1 I

l l

l TABLE 9-2 i FSV SUPPORTING PROCEDURES i Procedure Designation l and litle FSV Administrative Procedures G-2 FSV Procedure Systems G-3 Action Request - Preparation and Processing G-4 Physical Security and Access Control Personnel Emergency Response G-S G-7 Personnel Training and Qualification Programs G-9 Controlled Work Prr 'edures G-10 Data Management P-1 Piant Operations P-7 Station Service Request Processing P-8 Fire righting and Prevention <

P-10 Industrial Safety Q-1 FSV Organization and Responsibilities 0-2 Quality Assurance Program Q-3 Design Control System Q-16 Corrective Action System Q-18 QA Audit and Monitoring Program 4

9.1-5 Procedure Designation and Title 4

Health Physics Procedures ,

HPP-30 Shipment of Radioactive Materials HPP-105 Operation of Portable Survey Instrumentation ,

HPP-110 Routine Survey Intervals and' Survey Documentation HPP-115 Radiation Surveys HPP-120 Surface Radioactive Coptamination Surveys HPP-125 Establishing and-Posting Controlled Areas HPP-130 Portable Air Sample Collection and Analysis HPP-135 Calibration and Operation Procedure for the Eberline SAM-2 Stabilized Assay Metar HPP-140 Continuous Air Monitors F HPP-145 Continuous Air Monitors Filter.and Cartridge Change Out HPP-155 Operating the Harshaw TASC-12rA6 Automatic Alpha / Beta Count;ng System HPP-170 Air Activity Analysis Using the RM 14/15 with HP-210 Probe HPP-185 Personnel Decontamination i

i h

9.1-6 Orocedure Designation and Title q

t HPP-19') Area and Equipment Decor.tamination i

HPP-195 Radioactive Material Spill HPP-205 Calibration of Radiation Detectior. Instruments HPP-305 Bioassay Program HPP-310 Personnel Dosimetry .

HPP-410 Quantitative Respirator Fit Testing l1 HPP-425 SelectionandUseofkespiratoryProtectionEquipment HPP-430 Routine Maintenance, Inspection, and Cleaning of Respiratnry Equipment HPP-435 Breathirig Air System Sampling Procedure HPP-525 Fast Gas and Iodine Sampling HPP-605 Radioactive Liquia (Sys"62) Effluent Sampling and Release Determination HPP-615 Radioactive Gas Waste Release' Rate Calculations HPP-620 Reactor Building Exhaust Stack Discharge Activity Calculation HPP-625 RT 7325 and RT 7343hEmergency Filter and Cartridge Removal HPP-630 Radioactive Material Control and Handling HPP-915 RERP Inventory List t

I e

9

i, l 9.2-7 2

i i - .

j Procedure Designation ,

and Title i

4 -!

l j Radinchemistry Procedures -

! RCP-9 Sample Preparation For Gamme: Spectral Analysis z; 1

l RCP-24 Analysis for Vent Particulate and Iodine Monitor '

j; F iter for Surveillance. Requirement E3R 8.1.lef-W:

RCP-36 Radioactivity Calculations-a

RCP-38 Operation and Calibration of Computer Based-Beta L Gamma Analysis System.

i RCP-40 Operation and Calibration of;the Whole Body Counting; System-l Procedure Manuals and Plant 4

Training Procedure - Radiological Emergency '

Response Plan  !

Fire Suppression and Prevention Manual. l Sections 1, 2, 8-

-i

, Abnorma' Operating Procedures - ( AOP) 4 All Sections a '

Emergency Operating Procedures ManualL(EOPs)

All-Sections-3 Station RERP Implementing Procedures -

All Procedures .

Medical Emergency Plan-FSV

~ Security Administrative Procedures ,

i j' Station Manager's Administrative Procedures- c

?

t 1

p <

v b

P-A 4 t 4

I

. 4 L ,

t

. - - + . . . . - ...-...m,,e= - e - - m , ,,s,__ _.,s . - . - . - . . . , + - ..,e. - - . , - ~ ~ . - . ---,.-+,,.-,~.m. -, .---

9.1-8 Procedure Designation eid Title Technical / Administrative Services Manager's Administrative Procedures Public Service Company RERP Public Information Manual State of Colorado Fert St. Vrain Radiological Emergency Response Plan (State RERP) .

Weld County Radiological Emergency Response Plan

• SG-05

' (Personnel Accountability .*or Station Emergencies)

Operations Order Book i

a

9.2-1 SECTION 9.2 KEY OOCUMENTS Provided below is a list of those documents which govern the FSV Emergency Preparedness Program,

1. Fort St. Vrain Radiological Emergency Response Plan. .

2. Fort St, Vrain System Operating Procedures.

3. Fort St. Vrair Emergency Procedures.

l 4 Fort St. Vrain Technical Specifications. l 1

5. Fort St. Vrain Updated Final Lafety Analysis Report.

6. Title 10, Code of Federal Regulations Part. 50.47 and Appendix E. I

7. NUREG - 0654/FEHA - REP - 1 Revision 1.

8. NUREG - 0696.

l I

I

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