Text

Forwards Revised Scenario for 840404 Exercise.Detail Provided for Areas Where Participants Expected to Make Decision in Terms of Classifying Event.Timeline Revised Slightly to Allow for Increased Participation by Personnel
	ML20088A483
Person / Time
Site:	Susquehanna
Issue date:	03/28/1984
From:	Wike C; PENNSYLVANIA POWER & LIGHT CO.
To:	Jamison J; Battelle Memorial Institute, PACIFIC NORTHWEST NATION
References
	NUDOCS 8404120094
	Download: ML20088A483 (116)
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PENNSYLVANIA POWER & LIGHT COMPANY EMERGENCY OPERATIONS FACIUTY R.D.1, BOX 244, BERWICK, PENNSYLVANIA 18603 Telephone: 717-542-2181 March 28, 1984 Mr. James Jamison Battelle Pacific Northwest Labs P.O. Box 999 Richland, WA 99352

Dear Jim:

Enclosed is a revised scenario for the April 4,1984 Susquehanna SES exercise.

Detail is provided for those areas where based upon technical plant data, participants will be expected to make a decision in terms of classifying the event. This data, as found in the scenario, is provided on 15 minute intervals via the Unit Monitoring Console (UMC) as the participants would view the data in real life. Unit Monitoring Consoles are available to the Control Room operator, Technical Support Center staff, and E0F staff. For purposes of expediting your receipt of this scenario,15 minute data for the entire duration of the exercise is not included herein, only that portion along with a description of expected actions pertinent to the participant assessment portion of the scenario. For an approximately 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months exercise, I am sure you are aware, much of this 15 minute data does not change or does not impact the decision making process.

You will note that we revised the timeline slightly to allow for increased time participation by our EOF and M0C personnel. The purpose is to provide the opportunity for participants to bring the emergency condition to a reasonable conclusion.

If you have an call at (717) y 542-3233 questionsoror(717) problems, please do not hesitate to give me a 759-3955.

Sincerely, f h b Y f-Charles R. Wike, Jr.

Supervisor-Nuclear Emergency Planning CRW:mm cc: Ed Woltner U. S. NRC Region I 631 Park Avenue King of Prussia, Pa 19406 8404120094 g493pg hDRADOCK 050003e7 PDR pI 8ll

CONTENTS

1. Scope & Objectives

2. -Timeline

3.. Initial Conditions

4. ALERT - Liquid Release - Scenario and Data

5. Accountability Scenari

6. SITE EMERGENCY - Detaileo ATWS Scenario and Graphs

7. Site Evacuation Scenario

8. Reactor Sump' Leak - Technical and Radiological Scenario

9. Contaminated Injured Scenario

10. Security Problem

11. GENERAL EMERGENCY --Leak Outside' Containment and Associated Radiological Data

'12. Rx Coolant and Suppression Pool Data ~

0 13. Containment Geses

14. In-Plant Radiological Data

15. SPING Data

16. Offsite Release Data to 1510 Hrs.

17.'0ffsite Release ~ Data from 1510 Hrs. ,

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SUSQUEHANNA STEAM ELECTRIC STATION 0BJECTIVES FOR 1984 NRC OBSERVED EXERCISE

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1. -To provide the basis.for an approximately 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months utility-state radiological emergency exercise. This exercise will include participation by Susquehanna SES, Pennsylvania Power & Light Allentown, and the Commonwealth of PA Department of Environmental Resources / Bureau of Radiation' Protection.

2. _To exercise the overall SSES Emergency Plan, and on a modified scale the Radiological Emergency Response Plan of the Commonwealth of Pennsylvania (DER /BRP). ,

3. To determine the cause of the emergency condition, terminate the condi-tion with consideration for appropriate engineering safeguards and radio-logical controls, and place the plant in a safe condition.

4. Tc test and exercise SSES site communications associated with a plant radiological emergency. To test, via simulated communications networks,

.the capability to coordinate SSES, Commonwealth, NRC and federal agency emergency response personnel.

5. To perform a limited site personnel accountability.

6. To perform timely and accurate-calculations for gaseous and liquid releases'.

7. To evaluate the ability to deploy'and control emergency response teams

{- both in-plant and offsite.

8.- To' test communications, activation, functional operation and coordination of the Operations Support Center, Technical Support Center, Emergency Operations Facility, Media Operations Center _ and General Office Support Facilities.

9 .- To' test'the abilit'y of SSES personnel to adequately respond to a contami-nated injury incident.

10. To test the ability of SSES personnel to demonstrate Personnel and Equip-ment contamination control, including appropriate decontamination proce-dures.

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11. .To test the ability of PP&L's Emergency Organization to provide timely and accurate protective action recommendations, including coordination of these reconnendations with appropriate offsite authorities.

12. To test the ability of the plant to effectively use the post accident sampling station'.

13. To ~ demonstrate an effective exercise critique program.

14. :To test.the' ability of the Berwick and Geisinger Hospitals to adequately

(_ respond to the emergency.

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15. To test the ability of local ambulance companies to adequately respond to the emergency.

O 16. To demonstrete e ,imited site e.,cu,1so,.

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1 Rev. 1

' () C0NFID.ENTIAL v

APRIL 4 EMERGENCY PLAN EXERCISE PROPOSED TIMELINE TIME EVENT 0800 START EXERCISE

-ALERT - Based on liquid release greater than 10 x tech specs.

Activate TSC Perform limited accountability 0830 TSC operational

' 0900' SITE EMERGENCY - Based on f.ailure to SCRAM resulting in fuel damage and de- graded containment conditions. Water level remains below TAF for five minutes

' Activate EOF n,

k/ Perform limited evacuation 0915 : Reactor sump leak 1000 Contaminated Injured 1130 EOF operational Security problem

. 1300 Leak outside containment starts 1530 GENERAL ~ EMERGENCY - Based on projected integrated dose Recommend Evacuation 1800 . TERMINATE DRILL gp '#*k yy-y , e- w w .-3---m.-e e m -n--*- -. ,,a- - -, 9, -

Emergency Plan Exercise April 4, 1984

) INITIAL CONDITIONS

1. Unit 1 is at 100% power and has been operating at this level continuously for the past month.

2. Unit 2 is in startup testing phase. Currently shutdown for drywell cooling modifications.

3. Primary Coolant Activity levels are 0.15 Ci/ml.

4. Unit 1 is in the 17th month of its first full 18 month fuel cycle.

5. Preventive Maintenance was performed on relays in panels 1C617, 1C618, IC609,1C611,1C620, IC622 and 1C623 during the last forced outage. The relays were cleaned, relubricated and functionally tested.

6. ESW flow balancing and water hammer testing were completed during the last shift.

7. Diesel Fuel' Oil shipment is scheduled for this shift.

8. Auxiliary Boiler A is out of service due to failure of its feed pump, o - 9. The Unit 1 Offgas Recombiner temperatures have been erratic, though the V system continues to function.

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10. RPCU Phase Separator Tanks A&B are out of service and both RWCU Backwash receiving tanks are full. RWCU is in service but goes out intermittently on filter high delta P. Vessel conductivity has started to rise slowly. Work is planned for this morning to repair the inlet It appears the eductors are fouled on phase

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. valve to phase separator.A.

separator B.

, 11. All liquid Radwaste Collection Tanks and the Surge Tank are filled to capacity. After the release in progress liquid radwaste processing should be able to start again. At 2000 on April 3, 1984 a decision was made to not pump the Rx Building sump to Radwaste until room is available in liquid radwaste.

12. The inventory of the Unit 1 Spent Fuel Pool is as indicated in Attachment 1.

13. Liquid Radwaste release in progress (started at 0720) (see attached data).

14. CRD pump A is out of service for pump seal replacement (work is in progress).

15. Liquid Radwaste Effluent radiation monitor (RE06433) is out of service h, for pump motor replacement (work in progress).

C0NFIDENTIAL g- April 4,1984 Emergency Plan Exercise 1_-

Re: Liquid Release Scenario SYSTEM: Liquid Radwaste ACTIVITY: There is to be a planned release of liquid radwaste from Tanks (A & B) and (C & D) respectively. All four tanks are full to capacity (11,000 gal each). ,

PROCEDURE: Plant Chemistry will collect routine samples from each of the four tanks to ensure that radioactivity levels are below the maximum permissible concentration as specified in 10cFR20 Appendix B, Table II, Column 2 before being released to the Susquehanna River.

PLAN: results will show that tanks A & B may be released Chemistry 4/4/84. (Tanks are arranged to release effluents in tandem.)

However, tanks C & D will require additional decay time or dilution as activity levels are above 10 times MPC.

ACTION: At 0720 on 4/4/84 liquid radwaste tanks C & D will be released to the River. The release will be discontinued at 0800 when chemistry realizes the wrong tanks were released. Chemistry will calculate actual concentration of release to river and report findings that ne90 x Tech Spec concentrations were released.

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Attachment G EP-IP-053 Revision 0 Cb3 - Page 13 of 21 LIQUID DISCHARGE DATA SHEET .

Srction 1: Release Data

' Time of initial release into river (A) 07/O Release termination time (B) OSCC Total release time (C)

//C min.

Sample location

_ /8mby; 3/t/

Section 2:

Determination of Activity in River at Danville PartA-Completeifsamplewastakenfromblowdowglig, Activity of blowdown sample (L) J E-3 ~

/.5r-3 Riverwater depth (from gauge at 3r-(uti/ml.

Biological Lab) 8. / ft.

Dispersion factor to Danville -

(from Table 1) (M) _

J/oD Activity in river, at Danville (N) = L = USE-E 5,FE-4, /, /SE- fuCi/ml .

%mun vdamt nhaad (tim !9xyl/a

_Part 8 - Complete if sample was taken from wlste stre)am entering dir into the blowdown (includes sample taken from spray pond).

Activity of sample (H) uti/ml.

Rate of waste stream released into blowdown (I) = qal/ min.

Rate of blowdown discha'rge (J) = -

_ cal /mi6.

Blowdown Dilution Factor (K) = J = '

I Activity of blowdown _ (L) = H =

uCi/ml.

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K River water depth (from gauge -

at Biological Lab) ft.

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Iw)AEP-IP-053-1,Rev.O,Page1of3 -

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a Attachment G l'- EP-IP-053 0 Revision 0 Page 14 of 21 9

Dispersion factor to Danville (from Table 1) (M)

Activity in river at Danville (N) = L =

M uCi/ml.

Part C - pond Complete if sample was taken from waste stream entering the spray before being released to blowdown line Volume.of release into spray pond (D) cal.

Volume of spray pond'(E) assume 25,000,000 cal.

Spray Pond Dilution Factor (F) = E D

Activity of Sample (G) uti/ml. " ~

Activity of volume in Spray Pond (H) =,G O '

uti/ml.

Rate of release into blowdown (I) cal / min.

Rate of blowdown discharge (J) gal / min.

Blowdown Dilution Factor (K) = J =

I Activity of blowdown (L) = H =

uti/ml.

K River water depth (from gauge at Biological Lab) '

ft.

Dispersion factor to Danville '

(from Table 1) (M) -

sActivity in river at Danville (N) = L =

, M .

uti/ml.

NOTE:

If a sample is taken from the river below the discharge, assume thetheactivity of sample. in the river at Danville is the same as the activity

)x FORM EP-IP-053-1, Rev. O, Page 2 of 3 4

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Attachment G i

g EP-IP-053 rN Revision 0 -

V - Page 15 of 21

_Section 3: Time of Arrival at Danville -

Transit time to Danville (from Table 1) (P) 9 hrs.

Time of Arrival at Danville (P+A) //W /-766 4/f/89 Section 4: Recommendations l A/St 0 l1YAf/11lk6U m' Y a A / d1 E / Ps DER /RPP is/ At 42 '

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Simulated Accountability: Security personnel will be dispatched to Accountability Roster pick-up locations to obtain Prepositioned Accountability

-Rosters. One Plant employee will be reported missing which will necessitate the Security Controller to check the Security Data Management System and determine-the individual's last known location. A check with the individual's supervisor will indicate the missing person's last known location is the Circ Water Pump House. Security will be dispatched to find the missing individual.

Exercise participant will be in Circ Water Pump House and will be easily i'dentifiable as a player. After being found the missing employee will report to accountability station and accountability demonstration will be complete.

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C0NFIDENTIAL p

v April 4,1984 Emergency Plan Exercise Re; Detailed Technical Scenario ,

Time Event 0855 Spurious'Feedwater Transient The. feedwater level control. system malfunctions momentarily causing a feedwater flow increase and subsequent Reactor Vessel level increase to 47 inches. The high, level alarm is received in the control room but no operator action is needed as level returns to normal at 37".

0900 MSIVs Close'on High Steamline Radiation The feedwater transient caused an increase in Condensate Demin flow and foreign matter was sh'aken loose. The material > passes through the Reactor Vessel and is activated. High radiation is sensed in the Main Stiam' lines and the Main Steam Isolation Valves close, 0900:01 ATWS The Reactor fails to SCRA.M n the closure of the MSIVs. The full core display, fourirocsdispTcy, RSCS'" Full in"~and OD7 all indicate that no rods have scrammed. (The-SCRAM relays, C72-K14A-H, have de-energized but are stuck in the energized position. The new lubrication has liquified due to the heat generated by the constantly energized relay coils. The lubricant has fouled the relay contacts.)

The backup SCRAM valves C12-F110A&B do not open because their power supply fuses have been blown for some time.

0900:05 Fuel Damage c ,

Reactor Pressore' increases rapidly and most safety rel'ief valves open. ' Reactor power increases very sha[ ply. (Peaks at '

~1500%. ) Serious fuel damage occurs.

The Raactor fails to SCRAM (n high pressure but th'e

- Recirculation Pump Trip (RPT); breakers open on high reactor pressure. Recirc Pumps stop and Reactor Power decreases to -

~ 30%. The'elergy is being discharged to the Suppression Pool.

A HPCI and RCIC initiate at J1evel "2", " low, low level" and inject the Reactor lessel but their flow;is. insufficient initially'to q stop the le, vel decrease. level drops below the level 1 Low, b- Low, Low setpoint and the~RHR and Core Spray pumps start.

Reactor pressure is still high so the RHR and CS pumps cannot inject into.the RPV. <The ADS 105 second timer has started.

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,--.----,---c- , g- - _ . - -,, --

Water level drops below the top of the active fuel (TAF). Cold water: injected by HPCI and RCIC causes sudden pressure drops and

-J voiding in the, core. Water is expelled from the core and Is -). subsequent rewetting causes additional fu'el damage. Level oscillations are reversed. Water level remains below TAF for five_ minutes causing additional fuel damage. HPCI and RCIC recover level to above TAF. Operators reset the ADS timer so no ADS cccurs.

0915:00 Reactor SCRAM Fifteen minutes after the MSIV closure the Reactor SCRAMS. The operators should attempt to open the RPS power supplies, 1Y201A,B, per E0-00-014, Step 4.1.2. If operator action does not occur before fifteen minutes, the Reactor will SCRAM. The K14 relays will fall open sequentially as they cool and each of the 4 rod groups will SCRAM.

HPCI restores vessel level. Conditions stabilize, level normal, pressure high, high radiation in the Suppression Pool and High drywell pressure. The operator has deenergized the RPS power supplies 1Y201 A,B.

rm t

Detailed Control Room ATWS Scenario

- s Initial Conditions at t'= 0900 Reactor. Level = 37" (following FW controller malfunction)

Rx Power- = 100%

Reactor Pressure = 1020 psia /1005 psig

-Reactor Temp = 545 F

.- Supp. Pool Temp, = 75 F All Relief valves closed All MSIV's open Both Recire pumps = 100% speed At 0900 Get Hi Main Fteam Line Rad Trip signal All MSIV's c.ose All Turbine stop & control valves close Get auto SCRAM indication Recirc pumps. trip on E0C RPT Get the following annunciat' ors e RPT SYS A (B) TRIP ~

e MAIN STEAM LINE HI RAD TRIP A (B) ,

o MAIN STEAM LINE NOT FULLY OPEN TRIP A (B) 3r e. TURBINE STOP VALVE CLOSURE TRIP A (B) 1(s.) - - e TURBINE CONTROL VALVE FAST CLOSURE TRIP A (B) <

Don't get: REACTOR AUTO SCRAM A (B)

Full core display same as before isolation OD7 same as before isolation ,

At 0900+ - seconds afte'r'MSIV's close !

Rx Power = offscale Rx Pressure = 1110 psig All Relief valves except K8M open ,

Water drops, then swells Get the following additional annunciators:

e RECIRC PUMP HI PRESS /LO LEVEL TRIP

, o RX VESSEL HIGH PRESS TRIP A'(B) j e RX VESSEL LOW LEVEL TRIP A (B) e NEUTRON MONITORING SYSTEM TRIP A (B)

MAIN STEAM LINE HI RAD TRIP clears Immediate operator action's should be from E0-00-01 o' Place mode switch to shutdown - no chance in rod status Get RX MANUAL SCRAM SYS~(A) (B) annunciatorv 4

t

. I N

The e RPT following(annuniciators SYST A B) TRIP clear e MAIN STEAM LINE NOT FULLY OPEN TRIP p)

( e TURBINE STOP VALVE CLOSURE TRIP e TURBINE, CONTROL VALVE PAST CLOSURE TRIP e Arm and depress manual SCRAM switches - l no change in rod status Get MANUAL SCRAM SWITCH ARMED A (B) e E0-00-01 directs operator to E0-00-014 I

Between 0900 & 0905 i Rx Power drops linearly to 8% at 0905 (average 30%)

Avg-steam flow = 2.83 mlb/hr HPCI and RCIC start at -38 use 200,000 lb/hr steam input 2 mlb/hr water (5600 gpm)

Relief valves ABCDE&H cycle Water drops continuous after swell reaching TAF at 0905 Supp pool temp rises to 116 F by 0905 Get DRYWELL PRESS HI TRIP A (B)

Operator actions based on E0-00-014 e Can't start second CRD pump (its 005)

One. of+bese. fe Sends NPO to open RPS breakers S M be.

> k4c, by M(5'(o Sends NP0 to isolate & bled SCRAM air header '

These annunciators clear: .

e RECIRC PUMP HI PRESS L0 LEVEL TRIP (then trips again at -129) l e NEUTRON MONITORING SYSTEM TRIP A (at 15% power) i Between 0905 & 0910

( Rx Power steady at 8%

Steam flow = 750,000 lb/hr HPCI & RCIC in service fuse 200,000 lb/hr steam 2 mlb/hr water (6000 gpm)

Reliefvalves-B&Ecycle(input Water level drops below TAF and oscillates I while chugging of HPCI water in the overheated core takes place it stops chugging and returns to TAF at 0910 Suppression pool temp rises linearly to 129 F by 0910 Between 0910 & 0915 0 0910 operator throttles HPCI to maintain level just above TAF Rx Power = 10%

Steam flow = 943,000 lb/hr .

p- -HPCI/RCIC in service use 72,000 lb/hr

()- input' 943,0001b/hr(2000gpm)-

'- - - ,i .

Relief valves open - E (operator open manually at 0910)

Water level steady just above TAF p Supp pool temp rises to 145 F by 0915 x -

Before 0915 operator

- puts A Loop of RHR in Supp pool cooling (per E0-00-023)

- initiates drywell cooling Operator should not have to initiate SBLC (per E0-00-014)

At 0915 Rx SCRAM - Full core display & OD-7 confirm all rods in Power = 0 Steam flow = 300,000 lb/hr E Relief valve manually open HPCI/RCIC in service Water level rises rapidly Supp pool temp = 145 F Drywell pressure = 18.5 psia

= 250 F Drywell tempCont. - Rad Monitor = 10}R A Loop of RHR in Supp Pool Cooling at 10,000 gpm

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By 0930 Rx water level is +35" steady HPCI has been secured p) t RCIC is maintaining level pumping 600 gpm RX WATER LEVEL HI TRIP 2 reset RX PRESS HI TRIP j Drywell coolers are in service HI DRYWELL PRESS TRIP IS ONLY TRIP SIGNAL PRESENT Operators will continue to cool down through the open relief valve at 100 F/hr At 0930 B Loop of RHR put in Supp Pool Cooling A Pump of core spray i.n service discharging to Supppression Pool for Suppression Pool mixing At-1230 B Loop of RHR is put in shutdown cooling E Relief valve is closed

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REACTOR WATER LEVEL

'l '0800-0855 ss @ +35" 0855- FW 1evel control failure, level increases to +47 and returns to ss at +37" 0900-0915 (MSIV closure) voids collapse with pressure spike get level spike down, level returns but drops quickly as relief valves open, RCIC and HPCI start at -38 RCIC and HPCI can't keep up,, water level continues to drop to TAF and then below. RCIC and HPCI start to recover and level steadies out at just above TAF Steam flow = combined HPCI and RCIC flow 0915 After SCRAM operator' returns level to normal range with RCIC and level remains at +35 for the remainder of the exercise

~+ 40 --

n s

_g -100

.> <r-

,, ULTAF --- -- - -- -- - - - - -

d D'-200

=

~ -300

(\s} BAF ----- _ __ _ __ ___ _ __ _ _ __ _ _._ _ _ __ __

0855 0900 0905 0910 0915 TIME

REACTOR POWER

/-s t 0800-0855' ss @ 100%

v %.)

0855 Slight power increase during Feedwater transient 0900-0915 (MSIV isolation without SCRAM) Power initially spikes off scale with void collapse and pressure spike After ATWS recirc runback- power reduces to 30%

Power drops slowly at first as level drops, then drops suddenly when water reaches TAF to 8%

RCIC 6 HPCI recover water level to TAF, power increases to equilibrium level at 10%

0915 Reactor SCRAMS- power drops immediately to zero and remains there for remainder of exercise MSIV

. closure 10

-(_/-

123 FW Transient 100 -

A 3

E n

Water level below TAF Water level at TAF 4

0855 0900 0905 0910 0915

} (~j _ TIME s .- .

REACTOR PRESSURE

(-%, 0800-0855 ss-@ 1000.psig

%)

0855 Feedwater transient slight pressure increase during power increase 0900-0915 (MSIV isolation) Fressure spikes to 1110, all relief valves except K&M open After ATWS recire runback, all but six relief valves close.

ABCDE & H cycle open, average pressure at 1090 When water level drops below TAF, only B&E relief valves cycle, pressure rapidly cycles between 1050 and 1080, operator opens B & E to stop cycling, pressure steady at 1060 0915 After SCRAM cooldown is at 100*/hr., pressure decreases at corresponding rate for the remainder of the exercise, operator leaves E valve man-ually open.

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q; 1100 t /

3 0

E

, 1050 -

S

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1000 # d 7x 0855 0900 0905 0910 0915

.L]

TIME

DRWELL PRESSURE 0800-0855 ss at 15 psia Af ter relief valves start to open, pressure increases steadily and peaks at

.V(]- 18.5 psia at 0930. Pressure remains at 18.5 psia until primary containment leak starts at 1300. Pressure slowly decays to SCRAM setpoint level (1.5 psig/

16.2 psia).

19 18 ,

17 5 16 ---- - - - - - - - - - -- - SCRAM m

C 15 ,

14 0900 0915 0930 1300 1800 TIME SUPPRESSION POOL TEMPERATURE

) After relief valves start to open temperature increases steadily and reaches 145' by 0915. Operator starts suppression pool cooling at 0900. Temperature continues to rise as reactor cools down. Temperature peaks at 187' at 1230. After relief valve closes temperature slowly decreases to 165* by 1800.

-190' 170 150 130 C

v 110 ,

N s N -90 ,

i 70 3 i

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0900 0915 0930 1230 1800 TIME

q Simulated Evacuation: Two Security evaluators will role play groups evacuating the plant area through the designated exit portal. They will evaluate Security actions during the preparation phase to expedite personnel departures; update Security control on evacuation progress and insure that entry credentials are collected.

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C0NFIDENTIAL g- ~3 April 4, 1984 Exercise Scenario

\_,/ Reactor Sump Leak Recent evidence indicates that radwaste collection tank instrumentation has been giving faulty level indication. The level gauge currently reads 90%

capacity on the last available collection tanks. It is believed that the' tank may be only 50% full. Maintenance is currently being performed on the level gauge instrumentation in the radwaste mixing tank room.

The Reactor building sump on elevation '645 is filled to capacity (2708 gal.)

and has been allowed to back up through the floor drain valve pits on elevation '645.

At 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months , valves XV 1F011B and IF011A fail to seat properly allowing leakage of Reactor water.to the Reactor building sump. Water from the CRD SCRAM discharge line is flowing into the sump at the rate of one gallon per minute. The activity of the Reactor water is just over 2000pti/cc and is backing up through the floor drain valve pits resulting in elevated airborne activity levels. The activity is recirced through the Reactor building Z.ne I via the ventilation system resulting in average building dose rates of about 5 mR/hr.

Two hours later (1115) the damage control team should be successful in manually closing one of the drain valves.

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Contaminated / Injured Patient Drill Berwick Hospital /Geisinger Medical Cente'r O

%J Time: Approximately 1000 (one victim will call into Control Room)

General Location: Radwaste Building Elevation '646 RADWASTE COLLECTION TANK ROCM A&B

Background:

Maintenance is being performed on the level element in a radwaste collection tank room. 2 Maintenance personnel working on scaffolding 5.5 meters above floor. One of the pins falls out of scaffold. Both workers fall. One victim ends up under material with lacerations on forehead and a compressed cervical vertebrae on the spinal cord. Second victim will end up on top of scaffold material with lacerations- to forehead and a broken right hip. 2nd victim can call the Control Room via radio. Both victims will remain conscious.

Expected Response: Health Physics Tech and Operator for Search and Rescue Team will be sent from Technical Support Center.

Team will notify Shift Supervisor who in turn will have a prompt response to accident. Ambulance from Hunlock Creek and Shickshinny will transport injured individuals. Both individuals will go to Berwick Hospital. Victim with

,3 serious injury will then be Life Flighted to Geisinger.

Q (Life Flight can not land at Susquehanna; closest location for landing is Berwick.)

Medical: Victim i should be a suspected neck injury. Initial Primary survey of the patient shows:

Arms: No feeling or reaction to pain or movement Trunk: No feeling or reaction to pain or movement Legs: No feeling or reaction to pain or movement Paralysis in legs and arms.

Initial vital signs:

Pulse: 68 Respirations: 14 shallow and irregular

Blood pressure: 90/70 Skin Temp: cool Skin color: pale Pupils: ' slow but equal to react If treated properly pulse will rise to 72; respirations will become regular and about 19; blood pressure will increase to 120/80. If treatment is not appropriate vital signs will remain about the same as initial.

O A cervicel coiler (or equ4veient) snould be eppi4ed. Tne patient should be innobilized and transported out of the area. (Transportation is optional.) Must be transferred from Berwick Hospital to Geisinger Medical Center.

Victim 2 should be a suspected right hip injury. Initial primary survey of this patient shows right foot and leg s rotated out. Secondary survey shows tenderness in right

(~J i- hip area.

Initial vital signs:

Pulse: 130 faint Respirations: 25 deep Blood pressure: 90/60 Skin Temp: cool Skin color: pale Pupils: normal re'sponse Victim is somewhat unresponsive when first aiders arrive.

If treated properly pulse will return to about 80;

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respirations will become strong and return to 20; blood pressure will become 128/95. If treatment is not appropriate, victim will continue to deteriorate A traction splint should be applied and victim treated for shock.

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RADIOLOGICAL INFORMATION

1. General area readings are 1 Red /hr at scene of accident, 300 mR/hr at egress point.

2. -Contamination levels are 150K cpm to 200 mrad smearable throughout area.

3. Both victims have been working in this area intermittently for 1 hr. 45 min. prior to accident.

" VICTIM #1" INSTRUMENTS E140-N R0-2 Beta & Gamma Beta & Gamma Ganna (open window)

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Protective Clothing (Outer)

Front 150,000 cpm 20 mrad /hr 10 mR/hr Back (Saturated) 150 mrad /hr 75 mR/hr

" NOTE: If outer PC's are_ removed the inner contamination levels are:

Front 20,000 cpm 3 mrad /hr 1 mR/hr Back 5,000 cpm 1 mrad /hr .5 mR/hr

-p. Initial prior.to decon v

Face .. 50,000 cpm 7 mrad /hr 3 mR/hr Hair (Front) 10,000 cpm '2 mrad /hr 1 mR/hr :

Nasal-Smear 10,000 cpm 2 mrad /hr 1 mR/hr !

Mouth Smear. -10,000 cpm 2 mrad /hr 1 mR/hr Neck Area 10,000 cpm- 2 mrad /hr 1 mR/hr Body (Chest) 2,000 cpm 1 mrad /hr 1 mR/hr 1st Decon Face- 5,000 cpm Hair (Front)' 1,000 cpm Nasal Smear 5,000 cpm (If irrigated or nose can be blown)

Mouth Smear 5,000 cpm (If rinsed)

Neck Area 5,000 cpm -

Body (Chest) 1,200 cpm (If properly protected while deconnirg face & neck)

.2nd Decon Face '500 cpm Hair (Front) 100 cpm Nasal -2,500 cpm-Mouth 2,500 cpm 500 cpm-

- Neck ,

- m Body.(Cnest) 100 cpm !

c

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

E140-N Beta & Gamma

. r 3rd Decon Face 4.100 cpm Hair (Front) 4100 cpm Nasal 1,000 cpm Mouth 1,000 cpm Neck 4.100 cpm Bocy (Chest) 4100 cpm 4th Decon (if necessary)

Nasal 200 cpm Mouth 200 cpm

" VICTIM 2" INSTRUMENTS E140-N R0-2 Beta & Garrrna Beta & Gamma Gamma (open window)

Protective Clothine (Outer)

Front 150,000 cpm 20 mRac/hr 2 mR/hr

3 Back

D Note: If outer PC's are removed the inner contamination levels are:

F ront '20,000 cpm 3 mrad /hr 1 mR/hr Back. 5,000 cpm 1 mrad /hr .5 mR/hr

Initial prior to oecon Face 30,000 cpm 4 mrad /hr 2 mR/hr Hair (Front) 5,000 cpm 1 mrad /hr .5 mR/hr Nasal Smear 10,000 cpm 2 mrad /hr 1 mR/hr Mouth Smear 10,000 cpm 2 mrad /hr 1 mR/hr Neck Area 10,000 cpm 2 mrad /hr 1 mR/hr Chest 2,000 cpm 41 mrad /hr 41 mR/hr 1st Decon Face 3,000 cpm Hair (Front) 500 cpm Nasal Smear 5,000 cpm (If irrigated or nose can be blown)

Mouth Smear 5,000 cpm (If rinsed) t

. . . Neck Area 500 cpm Chest 200 cpm (If properly protected while doconing face & neck) e v

i t.

4

E140-N Beta & Gamma 2nd Decon Face 300 cpm Hair (Front <100 cpm Nasal 2,500 cpm Mouth 2,500 cpm Neck 4100 epm Chest <100 cpm 3rd Decon Face -

4100' cpm Hair (Front 4 100 cpm Nasal 1,000 cpm Mouth 1,000 cpm Neck <100 cpm Chest <.100 cpm 4th Decon (if necessary)

Nasal 200 cpm Mouth 200 cpm O .

m Oe O

April 4,1984 SSES Energency Drill I ,) BACKGROUND INF0 INJURY SCENARIO Terry Soya -- Maintenance Dept. (PP&L)

Age 29 e Employed (PP&L) April 1979 e Prior to PP&L employment -

U.S. Navy - Machinist - 6 yrs.

Personal Status e Ma rried e 2 children Boy - 6 yrs, old Girl - 3 yrs. old residence - Hazleton, Pa.

John Meyer -- Health Physics Dept. (PP&L)

Age 28 o Employed (PP&L) July 1982 e Prior to PP&L employment

,- Peach Bottom Atomic Power Plant (4 yrs)

(3 ) (Health Physics Technician)

Personal Status e single e residence - Berwick, Pa D

/ \

April 4,1984 SSES Emergency Drill O stSSAct rRos InauacD He To ConTaol aoon l

Control Room, Control Room, "THIS IS A DRILL" "THIS IS A DRILL" There has l been an accident in the Phase Separator Tank Room. Send a first aid team.

< I think I broke my hip and Terry can't move. "THIS IS A DRILL" "THIS IS A DRILL"

'l

,---.,-n, , - - - - ,,-.e-,,-,.r-,- ,---.-n,--,n, - ,, ---.v., -,7------m-.m.,--,_ , , - - - . .m,,,--,,,-~ - . , - - , - m , , - - - - , - , , ---

t April 4, 1984 SSES Emergency Drill

o Injury Scenario INITIAL CONDITIONS Valve on influent valve HV06620A to Phase Separator Tank A is stuck closed. RWCV filter demins keep going out on hi DP. Valve must be rapaired to allow resin processing. If the valve is not repaired the plant may have to shut down due to high conductivity in Rx coolant.

One maintenance person and one HP Tech are dispatched at 0800 to investigate and repair the valve.

l-4 An extension ladder is necessary to reach the valve. All equipment is

, obtained and the HP and Maintenance worker enter the A phase separator tank room at 0830, equipped with a UHF radio.

At 1000 the Maintenance. worker while standing on the ladder attempts tr reposition himself and slips and falls causing his tools and himself to land on top of the HP Tech.

f 4

0

'k I

l 1

O v

CIVIL DISTURBANCE (SECURITY)

SCENARIO: Two/three individuals demonstrating against nuclear power lay across the entry doors to the North Gatehouse and prevent plant employees (1130 Hrs) from entering and proceeding to their work location. The demonstra-tors refuse to move or cooperate with the responding Security Force necessitating State Police assistance.

t")

\- /

e x__/

1300 Leak Outside of Primary Containment A 1" suppression pool instrument line breaks off between s containment and the excess flow check valve. The break is at valve XV15775B (wide range suppression pool level B, reference leg). This break will result in a slow venting of the suppression pool air space and drywell into the Reactor Building The airborne levels in the Rx Building will prevent any attempt to'stop the leak. Only depressurizing primary containment will stop the leak.

The location of the break can be diagnosed from instrument-readings following the break. The B wide range suppression pool level indication will be approximately 10 feet higher than the indication on the A wide range instrument and the 2r.d rea range instruments.

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PLANT DATA First leak starts at 0900 in Sump Room and lasts 120 minutes.

Second leak starts at 1300 in CRD Room and lasts 210 minutes.

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Assume the HVL for these energies is one inch of concrete. '

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C) Therefore, if a wall is greater than 9" thick, assume no

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Assume all doors into secondary containment reduce the dose to 59% of the interior dose rate. This is the contact dose on the door.

Stairwells; assume doses are 0.1% of airborne dose in zones I and III.

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DOSE RATES DROM VARIOUS PIPES O

Pipe Diameter Contact Dose Rate 1 ft 3 ft 6 ft (inches) (R/hr) (R/hr) (R/hr) (R/hr) 1 33 0.45 0.13 0.05 2 59 1.7 0.51 0.2 4 100 6.4 2.0 0.79 6 140 13.0 4.4 1.8 8 170 22.0 7.5 3.0 10 200 32 11 4.7 12 220 88 16 6.5 24 350 190 52 23 36 450 280 130 47 l

O Assume all pipes aer 500 cm long G

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TYPE OF ACCIDENT RELEASE WITH FUEL DAMAGE THE REACTOR SHUTDOWN AT 840

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')ENTI LATI ON MTE Or COMP. B 2. 8 E S CC/MINU r E I

~ODINE- S1 SOURCE cELEASE 1.S ES UCI/ MINUTE iE:LE GAS-SOURCE RELEASE 5.2 E7 UC1/ MINUTE

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(N APRIL WEATHER FORECAST

%)

FAIN CONDITIONS WITH WINDS FROM THE NORTHEAST AT ABOUT 3 MPH.

A HIGH PRESSURE FRONT IS MOVING IN FROM THE NORTH PASSING THROUGH WILKES BARRE AROUND NOON. THIS FRONT IS BRINGING VERY STABLE CONDITIONS WITH MODERATING TEMPERATURES AND CLEAR SKIES PROBABILITY OF PRECIPITATION = NEAR ZERO PERCENT p.,

V i

e k d

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3 \'.

APRIL 4, 1984 7,*EATHER REPORT :,

O 0600 - 1510 '

I Wind from 45' (NE) ,

1

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ITYPE OF ACCIDENT RELEASE WITH FUEL DAMAGE 1

.;THE-REACTOR SHUTDOWN AT 900 TH: AFFECTED SECTOR -

S WIND FROM SECTOR N WIND FROM DIRECTION O DEGREES WIND SPEED ; MPH fn STABILITY CLAS3 /G/

V

PRECI PITATI ON RATE D INCHES /HR L 10 m W s

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i DISTANCE TIME j (MILE 5) 1340 1350 1400 1410 io euw sr.ae

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DISTANCE TIME gG oic ~,1 g AT l ~-

i (MILES) 1500 1510

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hYPEOFACCIDENT RELE4SE WITH FUEL Da'-GE ITHE REACTOR SHUTDOWN AT 900 i

TH~ FFECTED SECTOR SW NE lWINDFROM SECTOR WIND FROM DIRECTION 45 DEGREEE

.' WIND SPEED 3 MPH 4

s' iSTABILITY CLASS

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e MULTIPLICA~10N VALUES TABLE B i

{ CENTER MILES 0.1 MILES 0.25 MILES 0.5 MILES :.0 MILES O

1.25 0 EO O EO O EO O EO

.341 0 EO O EO O EO O EO

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DATA SET TABLE 2 DISTANCE TIME

< ES) 1510 1520 1530 1540

.25 0 0 : sod.6 426.3

, 0 0 5054.6 6412.6

. 341 -

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j 2. 5 0 0 0 0 O O O O IS 0 0 0 0 0 0 0 0

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t I

l DISTANCE TIME .

1

'O E5') 1550 1600 1610 1620 l .25 448.4 469.9 490.8 511.2

' 6870.7 7328.< <<8e.8 8244.8 i

6 l.341 393.6 414 433.? 453,3 !

5 5??O 6417.9 6845.8 7273.6 i i

1. 0 0 189 203.4 0 0 Slee.- e s d 2 . s- '

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l

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O O O O .

i l i :

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I i i i s t u

a b b

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DISTANCE TIME I I

( ES) 1630 1640 1650 1700

. 20 531.1 550.4 569.3 521.4 8702.9 9160.9 9c19 10077

!.341 472.2 490.6 508.e 52e.1 7701.5 8129.4 8557.2 SPS5.1 e44 .o o.sa.< o e. e_. o a e, i1 . . . .. . .

t 3602.S 3843 . 4083.2 4323.4 I g.ev 1g 0 1 .o ,. . c.. 9 e_ ,. .-

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i- ,

i 4

!,DI STANCE TIME 4

( EE) 1710 1720 1730 1740 v .25 599.4 617 609.E 663 l 10535 10995.1 11451.1 11909.2 l

i,.341 537.3 554.1 570.4 563.8 i 9412.9 9840.8 102e8.7 10696.5 t a

1 Q C .A w .6 F

.Rtc' n.A .

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P. Q Q. . F.

?

i 4563.6 4803.8 5045.9 5284.1 l F

l 1. 5 147.5 154.4 161.1 167.6 t l,

c,c,.,. ,. ,.

- .,c. v %e . o

. u n_. . e_

c,--

j- t I2 87.3 94. ??.2 104.2 [

! 1625.4 1750.4 1875.5 2000.5 :

I j2.5 0 0 0 64.*

! 0 0 0 1278.? -

l: ,

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)

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DISTANCE TIME 1750 1800 1810 1520 (gES) l.25. 655.4 648 d.99 691.3 12367.2 12825.3 13283.3 13741.4 4

.341 613.1 60d. 2 599.4 646.6 '

11124.4 11552.2 11980.1 12408 Il 288.8 297.6 294.5 320.5 L 5524.3 5764.5 . 6004.7 6244.9

1. 5 174.1 180.4 184.5 190.e 3344.2 3511.4 3678.6 3S45.c

..:2 109.2 114 118.7 123.3 2125.5 2250.6 2375.6 2500.6

.o.e u a < C, e.m.o

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1377.2 3475.6 1574 1672.4

3 0 0 50.2 54.2 0 0 1044 1124.3

!3.5 0 0 0 0 0 0 0 0 14 0 0 0 0

' i 0 0 O O 4

i

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0 0 0 0 4

i5 0 0 0 0 0 0 0 0 i

!6 0 0 0 0 0 0 0 0 l7 0 0 0 C O O O O t8 0 0 0 0 0 0 0 0 9 0 0 0 0 0 0 0 0 j 10 0 0 0 0 0 0 0 0 -

l 9

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April 4 Emergency Plan Exercise Expected Participant Actions V,o Time Expected Action Triggering Data 0805 Shift Supervisor will declare an Alert See Attachment A and assume the role of Emergency Director 0980 Emergency Director will declare Site Energency See Attachment B 0930 Reactor Coolant Leak will be detected See Attachment C QiL L 1005 Shift Supervisor ^ sends Search and Rescue Team See Attachment D to Contaminated Injury Recovery MANAGE-E <a>LL NCLh2 E 13 po General EmcrGDJcy + AEammitJD 'AiLTE2 mig See httachment E 1530 Recovery Manager U/LL Recem mcN D See Attachment F l)

v Evi?Ctu? T/CN O

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Contents

Text

Dear Jim:

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