ML20088A611

Forwards Exercise Scenario for 840404 full-scale Emergency Exercise.Offsite County,State & Municipal Participation Not Expected,However,County Will Observe Exercise

ML20088A611
Person / Time
Site:	Susquehanna
Issue date:	02/14/1984
From:	Wike C PENNSYLVANIA POWER & LIGHT CO.
To:	Crocker B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8404120294
Download: ML20088A611 (67)

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PP&L .

PENNSYLVANIA POWER & LIGHT COMPANY EMERGENCY OPERATIONS FACILITY R.D.1, BOX 244, BERWICK, PENNSYLVANIA 18603 Telephone: 717-542-2181 February 14, 1984 Mr. Bud Crocker U.S. NRC Region I 631 Park Avenue King of Prussia, PA 19406

Dear Bud:

Enclosed is a complete copy of the exercise scenario for the April 4,1984 Susquehanna SES Full Scale Exerci,se. You will note that the Technical Data for this exercise package is presented in graph form as compared to 15 minute data sheets as it will ultimately be made available to participants. The graph format will make it much easier for you to review and evaluate the adequacy of the scenario. The final 15 minute data sheets, consisting of duplicates of the plants Unit Monitoring Console as the CR operator, TSC or E0F would obtain the data, will be developed a couple of weeks prior to the actual exercise - these data sheets not being necessary at this time for overall exercise scenario review and evaluation.

As no offsite County, State or Municipal participation is expected, we are planning to have County personnel observe our exercise play in order for them to become familiar with our operations during an emergency condition.

Any questions concerning the scenario can be referred to myself or to Laurie Whittenberger at (717) 542-2181 Exts. 3233 or 3752 respectively.

Sincerely, Charles R. Wike, Jr.

Supervisor-Nuclear Emergency Planning CRW:mm 8404120294 840214 PDR ADOCK 05000 F

3 CONTENTS

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1. Scope & Ubjectives

2. Timeline

3. Initial Conditions

4. ALERT - Liquid Release - Scenario and Data

5. Accountability Scenario and Names

6. SITE EMERGENCY - Detailed 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. Suppression Pool Data

( ') 13. Containment Gases

14. In-Plant Radiological Data

15. SPING Data

16. 0ffsite Release Data to 1510 Hrs.

17. Offsite Release Data from 1510 Hrs.

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SUSQUEHANNA STEAM ELECTRIC STATION OBJECTIVES FOR 1984 NRC OBSERVED EXERCISE O

1. To provide.the basis for an approximately 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> utility-state-county-local municipality 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. To test and exercise SSES site communications associated with a plant radiological emergency. To test, via communications networks, the capa-bility 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.

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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 ability 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. ,

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

('l 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.

16. To demonstrate a limited site evacuation.

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C0NFIDENTIAL g)

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

. 0845 SITE EMERGENCY - Based on failure to SCRAM resulting in fuel damage and de-graded containment conditions. Water level remains below TAF for five minutes Activate E0F Perform limited evacuation

() 0900 Reactor sump leak 0915 TSC operational 0945 Contaminated Injured 1045 EOF operational 1115 Security problem 1300 Leak outside containment starts 1530 GENERAL EMERGENCY - Based on projected integrated dose Recommend Evacuation 1630 TERMINATE DRILL

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Emergency Plan Exercise April 4, 1984

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INITIAL CONDITIONS

!1. Unit 1'is at 100% power.

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

3. Primary Coolant Activity levels are 0.15 pCi/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, IC618, 1C609, IC611, IC620,1C622 and 1C623 during a recent 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 _011 shipment is scheduled for this shift.

8. Auxiliary Boiler A is out of service due to failure of its feed pump.

9. The Unit 1 Offgas Recombiner temperatures have been erratic, though the system continues to function.

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10. Radwaste collection tank level ' gauge has been giving intermittent, faulty readings. Maintenance is currently being performed on the level gauge.

11. At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on April 3, 1984 a decision was made to not pump the Rx building sump to Radwaste until level gauge problem is resolved.

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C0NFIDENTIAL

^ h- April 4,1984 Emergency Plan Exercise 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 just above 10 times MPC.

ACTION: At 0800 on 4/4/84 liquid radwaste tanks C_& D will be released to the River. The release will be discontinued at 0840 when operations realizes the wrong tanks were released. Chemistry will collect a water sample at blowdown lines.

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- Page 13 of 21

- LIQUIDDISCNARGE '

DATA SHEET ,

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Section 1: Release Data

" Time of initial release into river (A) d8dC Release termination time (B) d B40 .

Total release time (C) //O min.

Sample location S ction 2: Determination of Activity in' River at Danville Part A - Complete if sample _was taken from blowdown line en - sa rn-sn inAl- Gu Activity of blowdown sample (L) 3E-3 /. 5r- 1

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3E-3 uCi/ml .

' :Riverwater' depth (from gauge at R. I Biological Lab) ft.

Dispersion factor to Danville -

(from Table 1) (M)

J/oD Activity in river, at Danville (N) = L = / /fE-E 59E-4 /, /5E-fuC f /ml .

1%%$mMm VobunL NftML (twa x acogallpnyt Gb R 000 Part B - Complete if sample was taken from w1ste stre)am entering directly into the blowdown (include 3 sample taken from spray pond).

Activity of sample (H) uCi/ml.

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

Rate of blowdown discha'rge (J) = ~

gal / min.

Blowdown Dilution Factor (K) = J = .

. I Activity of blowdown (L) = H = *

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K uCf/ml.

River water depth (from gauge '

at Biological Lab) ft.

- FORM EP-IP-053-1, Rev. O, Page 1 of 3 -

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Revision 0 Page 14 of 21 Dispersion factor to Danville (from Table 1) (M) 1 Activity in river at Danville (N) = L = uCi/ml.

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Part C - Complete if sample was taken from waste stream entering the spray pond before being released to blowdown line -

Volume of release into spray pond (D) cal.

Volume of spray pond (E) 2500bd0 gal.

Spray Pond Dilution Factor (F) = E D

~ Activity of Sample (G) uC1/ml.

Activity of volume in Spray Pond (H) = G uCi/ml.

O 7 Rate of release into blowdown (I) cal / min.

Rate of blowdown discharge (J) gal / min.

Blowdcwn Dilution Factor (K) = J =

I Activity of blowdown (L).= H = uCi/ml.

K River water depth (from gauge at '

ft.

i Biological Lab)'

Dispersion factor t'.o Danville '

(from Table 1) (M) -

. Activity _ in river at Danville (N) = L = uC1/ml.

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

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

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\_/ Revision 0 Page 15 of 21

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Section 3: Time of Arrival at Danville -

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

Time of Arrival at Danville (P+A) / 70 0 ej/p/gy .

Section 4: Recommendations I. Aldbij ban / h]2ffJ) /)ti$tJU A/ . 41tllAt/fadt 3 A/sf b Ps DER / APP s/ Al Mdf of  ! /

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imulated Accountability: Security personnel will be dispatched to Accountability Roster pick-up locations to obtain Prepositioned Accountability Rosters. One Plant caployee will be reported missing which will necessitate the Security Controller to

- check the Security Data Management System and determine the individuals last known

' location. The~ Security Data Management System will reflect that the individual d:: parted the plant just prior to the announcement directing all personnel to raport to their Accountability Assembly Areas.

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C0NFIDENTIAL g

() April.4, 1984 Emergency Plan Exercise Re: Detailed Technical Scenario Time Event 0840 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".

0845 MSIVs Close on High Steamline Radiation The feedwater transient caused an increase in Condensate Demin flow and foreign matter was shaken loose. The material passes through % Reactor Vessel and is activated. High radiation is sensed in the Main Steam lines and the Main Steam Isolation Valves close.

0845:01 ATWS Q, The Reactor fails to SCRAM on the closure of the MSIVs. The full core display, four rod display, 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.

0845:05 Fuel Damage Reactor Pressure increases rapidly and most safety relief valves open. Reactor power increases very sharply. (Peaks at M500%. ) Serious fuel damage occurs.

The Reactor fails to SCRAM on high pressure but the Recirculation Pump Trip (RPT) breakers open on high reactor pressure. Recirc Pumps stop and Reactor Power decreases to

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

HPCI and RCIC initiate at level "2", " low, low level" and inject the Reactor Vessel but their flow is insufficient to stop the

.n . level decrease. Level drops below the level 1 Low, Low, Low tj 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 record timer has started. Water

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

-.dg voiding in the core. Water is expelled from the core and subsequent rewetting causes additional fuel 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.

0849:00 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.

The ADS timer does not time out. (The fuel was uncovered for 5 g minutes.) HPCI restores vessel level. Conditions stabilize, level round, pressure high, high radiation in the Suppression Pool and High drywell pressure. The operator has ground the RPS power supplies 1Y201 A,B.

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REACTOR POWER

-0800-0840 ss 0 100%

0840 Slight power increase during Feedwat'er transient 0845-0900 (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 level reaches TAF to ~8%.

RCIC & HPCI recover water level to TAF, power increases to equilibrium level at ~10%.

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0900 Reactor SCRAMS - power drops immediately to zero and remains

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there for remainder of Exercise MSIV Closure

\/ 125 FW Transient .

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• ss , Water Level below TAF Water Level at TAF 0840 0845 0850 0855 0900

/s k TIME

REACTOR WATER LEVEL O 0800-0840 ss 0 +35" 0840 FW level control failure, level increases to +47 and returns to ss 0 +37" 0845-0900 (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 & HPCI can't keep up, water level continues to drop to TAF and then below. RCIC & HPCI start to recover and level steadies out at just above TAF.

Steam flow = Combined HPCI and RCIC flow 0900 After SCRAM operator returns level to normal range with RCIC and level remains at +35 for remainder of Exercise

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0845 0850 0855 0900 0840 TIME

REACTOR PRESSURE

'0800-0840~ ss'0 1000 psig_ ,

.0840 FW Transient slight pressure increase during power increase 0845-0900 -(MSIV Isolation) Pressure spikes to 1110, All~ relief valves except K&M open.

1 After ATWS recirc runback, all but six relief valves close.

'ABCDE & H cycle open, average pressure-at 1090.

When water' leval -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

0900 Aftier . SCRAM codiddwn is at -100 /hr.', pressure' decreases at corresponding rate for remainder of exercise O

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1. - J 1000 0840 0845 0850 0855 0900 TIME

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DRYWELL PRESSURE I 0800-0845 ss.9 15 psia . m

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After reliefatvalves 18.5 psia 0915. start Pressureto open, pressure.

slowly. decaysincreases to SCRAMsteadily setpoint and levelp(eaks 1.5 at a ... _ psig/16.2 psia).. . _ . ,

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0845 0900 0915 1600 TIME

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SUPPREUIONP00[ TEMPERATURE (g) -

After relief valves start to open, temperature increas6s'. steadily and peak's at 150'F 0 30 minutes (0915). Operator starts suppression pool cooling at 0900.

.. Temperature slowly decreases to 90 F by 1600.

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110 s

-90 ~.

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70 0845 0900 0915 C' 1600 s TIME ,

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

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C0NFI'DENTIAL

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' April '4,1984 Exercise Scenario Reactor Sump Leak 3,

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 tank. 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. $

TheReactorbuildingsumponelevation'645isfilledtocapacity(2f08 gal.)'

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

elevation '645. Water comng from'the CRD SCRAM discharge drain has been emptying from the valve pits at.a rate _of one gallon per minute.

At 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, valves XV 1F011B.and1F011A fa.1 to seat properly allowing

.. leakage of-Reactor' water to the Reactor buiding sump. The activity of the Reactor water is'just over 2000p Ci/cc and is backing up through the floor drain valve pits resulting in elevated airborne activity leve'is. + The activity is recirced through the Reactor building via the ventillation system resutling

?in average building dose rates;of about 5 mR/nc.

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Contaminated / Injured Patient Drill Berwick Hospital /Geisinger Medical Center Time: Approximately 0945 (one victim will call into Control Room)

General Location: Radwaste Building Elevation '646 WASTE MIXING TANK ROOM Prestaging: Health Physics Tech and Operator for Search and Rescue Team will be sent from Technical Support Center.

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Team will notify Shift Supervisor who in turn will have a prompt response to accident. Ambulance from Hunlock Creek SHictsHWuy and Erwat::i&% Lake will transport injured individuals.

Both individuals will go to Berwick Hospital. Victim with serious injury will then be Life Flighted to Geisinger.

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

Background:

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.

Medical: Victim 1 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.

A cervical collar (or equivalent) should be applied. The 7~ s patient should be immobilized and transported out of the

' ) area. (Transportation is optional.) Must be transferred from Berwick Hospital-to Geisinger Medical Center.

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_Victim 2 should be 'a' suspected right hip injury. Initial primary survey of this patient shows right foot and leg

.( ]) rotated out. Secondary survey shows tenderness in right hip area.

b Initial' vital signsi Pulse: 160 faint Respirations: 25 ' deep and irregular Blood pressure: 70/40 Skin Temp: cold Skin color: extremely pale Pupils: widely dilated Victim is somewhat unresponsive when first aiders arrive.

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If _ treated properly pulse will return to about 80; respirations will become strong and return to 20; blood pressure will become 128/95. If treatment is not appropriate, victim will continue to deteriorate until death (M 0 minutes).

A traction splint should be applied and victim treated for shock.

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RADIOLOGICAL INFORMATION 7_

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1. General area readings are 1 Rem /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 for 1 hr. 45 min. prior to accident.

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

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

q. 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 1,200 cpm (If properly protected while deconing Body (Chest) face & iieck) 2nd Decon Face 500 cpm Hair (Front) 100 cpm Nasal 2,500 cpm Mouth 2,500 cpm e.. Neck 500 cpm

(.J Body (Chest) 100 cpm

E140-N Beta & Gama 3rd Decon Face. 4100 cpm Hair (Front) 4100 cpm Nasal 1,000 cpm Mouth- 1,000 cpm Neck 4100 cpm

' Body (Chest) 4 100 cpm fth Decon'(if necessary) ,

Nasal 200 cpm Mouth- 200 cpm

" VICTIM 2" INSTRUMENTS e

E140-N R0-2 Beta & Gama Beta & Gama Gama (open window)

Protective' Clothing (Outer)

. Front 150,000 cpm 20 mrad /hr 2 mR/hr

(.J- .Back If outer PC's are removed the inner contamination levels are:

Note:

Front 20,000 cpm 3 mrad /hr 1 mR/hr Back- 5,000 cpm 1 mrad /hr .5 mR/hr Initial prior to decon 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)

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

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E140-N

. Beta & Gamma O'L 2nd Decon'

.  : Face . _

300 cpm l Hair (Front <100 cpm

- Nasal 2,500 cpm Mouth 2,500 cpm.

{i . Neck. 4100 cpm  ;

Chest- <100 cpm

3rd Decon Face . .

. 4100 cpm Hair-(Front- 4 100 cpm Nasal 1,000 cpm  !

Mouth. 1,000 cpm '

r Neck' <100 cpm Chest <t100 cpm 4th Decon (if necessary) i- - Nasal ~ 200 cpm Mouth 200 cpm u

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. CIVIL DISTURBANCE (SECURITY) j l

SCENARIO: iTwo/three individuals demonstrating against nuclear power lay across the entry doors to the North Gatehouse and prevent plant employees (1115 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.

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1300 Leak Outside of Crntainment A SCRAM Discharge Volume drain valve, C12-F011A, fails. (The Bonnet is blown off of the valve body.) Reactor water is lost via the CRD, through the SCRAM outlet valves and then through the. SCRAM discharge volume. Coolant is discharged into the RHR j) piping area, 1202, at elevation '704. This discharge is

's / eventually ventilated by the Reactor Building HVAC system and discharged offsite.

1300 Control of the Leak Outside Containment Appropriate Area Radiation Monitors sound to help direct In-plant teams to the source of the leak. Coolant and steam are being discharged at a200 gallons per minute. RCIC maintains level.

The C12-F011A valve cannot be capped because of the high radiation fields. The only means of terminating the release is to reset the RPS SCRAM thereby closing the 185 SCRAM Outlet valves that are allowing coolant to leak out of C12-F011A. This can only be done after RPS power is restored and the Drywell Pressure SCRAM is cleared or bypassed. It wiTT be difficult to cool the drywell quickly enough to reduce pressure. It may be possible to electrically bypass the SCRAM. One of these methods will be successful sometime after the General Emergency has been declared.

Il v

--7

(

A h 4

');

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

4-REACTOR COOLANT DATA Ld;

1. Incident happens at 8:40'a.m.

2. The Reactor water mixed with the suppression pool at a rate of a complete -

~

turnover of Reactor water every'20 minutes.

. 3. Tne Halogens all remain in the water.

4._ The Nobles all go to gas, b - 5. The: Gas Volume is the wet well and dry well combined - assumed equilibrium E -. is. instantaneous.

- 6. 10% Clad failure.

L i

i L

i

}

O .

k I

I I .

1

,e

(

8 e

1 -

1 O ,

9 s ,

a y <y- ,,,.-y. -r <-v,.. .-ga.- . ...r..m,.comnw,m...,,.,w,_r,-~,,.,we,..w,,,.,....,#ww-m ..,,..e,...,,,,,,,,w-ww,.,,,

/

w REACTOR WATER DATA MbcQ e40 850 900 910 IODINE-131 5.4 E2 3.9 E2 2.9 E2 2.2 E2 IODINE-132 6.2 E2 4.3 E2 3 E2 2.1 E2 IODINE-133 1.2 E3 8.6 E2 6.3 E2 4.7 E2 IODINE-134 7.1 E2 4.6 E2 2.9 E2 1.9 E2 IODINE-135 1 E3 7.2 E2 5.2 E2 3.8 E2 C ES I Ut1-137 1.9 E2 1.4 E2 1 E2 7.6 E1 920 930 940 950 IODINE-131 1.7 E2 1.3 E2 1 E2 8.4 El IODINE-132 1.6 E2 1.2 E2 8.7 El 6.8 El IODINE-133 3.5 E2 2.7 E2 2.2 E2 1.8 E2' IODINE-134 1.3 E2 8.8 El 6.2 El 4.4 E1 IODINE-135 2.9 E2 2.2 E2 1.7 E2 . 1.4 E2 CESIUM-137 5.8 El 4.5 El 3.6 El 3 El 1000 1010 1020 1030 IODINE-131 7.1 El 6.2 El 5.6 El 5.1 El IODINE-132 5.5 El 4.6 El 3.9 El 3.4 El IODINE-133 1.5 E2 1.3 E2 1.2 E2 1.1 E2 IODINE-134 3.3 El 2.5 El 2 El 1.6 El IODINE-125 1.2 E2 9.9 El 8.7 El 7.9 El CESIUM-137 2.5 El 2.2 El 2 El 1.8 El

1040 1050 1100 1110 IODINE-131 4.S El 4. 6 E1. 4.4 El 4.3 E1

! J

[' DINE-132 ~3 El 2.7 El 2.5 El 2.3 El L) 10 DINE-133 .9.9 E1. 9.4 E1 9 E1 8.7 El IODINE-134 1.3 El 1.1 E1 9.2 EO 7.9 EO

- IODINE-1S5- 7.3 El 6.8 El 6.4 El 6.2 El CESIUM-137 1.7 El 1.6 El 1.6 El 1.5 E1 1120 1130 1140 1150 10 DINE-131 'd.2 El 4.1 El 4.1 E1 4.1 El I ODI NE-1'32 2.2 El 2 El 1.? El 1.9 El

,. " IODINE-133- 8.5 El S.3 El E.2 E1 9.1 E1 IODINE-134 6.8 EO 5.8 EO 5.1 EO 4.4 EO DINE-135 5.9 El 5.8 El 5.6 E1' 5.5 El CE51UM-137- 1.5 El 1.5 El 1.4 El 1.4 E1 1200 1210 1220 ,1230; IODINE-131 4 El 4 El 4 El- *

, 4 E1 -

IODINE-132 1.7 El 1.6 El 1.5 El 1.5 El 10 DINE-133 8 El 7.9 El 7.9 E1 7.8 E1

~~

. IODINE-134 3.6 EO 3.4 EO- 2.9 E0 2.6 E0 10 DINE-135 5.4 El 5.2 El 5.1 El 5 El CE91UM-137 1.4~El 1.4 El 1.4 El 1.4 E1

'N x i

%.)

1240 1250 1300 1310' ,

SIODINE-131- 4'El 4 E1. 4 E1' / 4 Ell..::g (![ i"f

_JO I NF-1 M . ji c.1_____ ___ Lm .t,7 =t ilF3

N N- 6 M8 7.6 E1 IODINE-134 2.2 E0 2 E0 1.7 E0 1.5 E0 10 DINE-135 4.9 'El 4.9 El 4.8 El 4.7 El CESIUM-137 1.4 El 1.4 El 1.4 El 1.4 El 1920 1330 1940 1350 IODINE-131 4 El 4 El 4 El 4 El 10 DINE-132 1.1 El 1.1 El 1 E1 9.6 E0 10 DINE-133 7.6 El 7.5 El 7.5 El 7.5 El 10 DINE-134 1.3 E0 1.2 E0 1 EO 8.9 E-1 10 DINE-135 4.6 El 4.5 El 4.4 El 4.4 El CESIUM-137 1.4 El 1.4 El 1.4 El 1.4 El 1400 1410 1420 1430 10 DINE-131 4 El 4 E1 . 4 El 4 El c 10 DINE-132 F.2 EO 8.7 EO 8.3 EO 7.9 E0 10 DINE-133 7.4 El 7.4 E1 -

7.3 El 7.3 El ICDINE-134 7.8 E-1 6.8 E-1 6 E-1 5.2 E-1 ICDINE-135 4.3 El 4.2 El 4.1 El 4.1 El C'ESIUM-137 1.4 El 1.4 El 1.4 El 1.4 E1 1440 1450 1500 1510 10 DINE-131 4 El 3.9 El 3.? El 3.0 El IODINE-132 7.5 EO 7.1 EO 6.9 EO 6.4 E0 iDINE-153 7.5 El 7.2 El 7.2 El 7.1 El 10 DINE-134 4.6 E-1 4 E-1 3.5 E-1 3.1 E-1 ICDINE-135 4 El 3.9 El 3.7 El 3.3 El C E S I U'1- 137 1.4 El 1.4 El 1.4 El 1.4 El

1520 1530 1540 1550 ODINE-131 3.9 El 3.9 El 3.9 El 3.9 El IODINE-132 6.1 EO 5.8 EO 5.5 EO 5.2 E0 IODINE-133 7.1 El 7.1 El 7 El 7 El IODINE ,134 2.7 E-1 2.4 E-1 2.1 E-1 1.9 E-1 IODINE-135 3.7 El 3.7 El 3.6 El 3.5 El CESIUM-137 1.4 El 1.4 El 1.4 El 1.4 E1 1600 1610 1620 1630

CDINE-131  ?.S El 3.? El I.0 El  ?.* El

?'DIt;E-132 5 EO 4.7 E0 d.5 :D 4.3 EO IODINE-133 6.9 El d . ' E1 .d . ? E1 6.8 El IODINE-134 1.6 E-1 1.4 E-1 1.2 E-1 1.1 E-1 IODINE-135 3.5 El 3.4 El 3.4 El 3.3 El CESIUM-137 '1.4 El 1.4 El 1.4 El 1 . '; E1 4

9

SUPPRESSION POOL DATA (C O

340 850 900 910 10 DINE-131 0 E0 1.2 El 2 El 2.6 El IODINE-132 0 E0 1.3 El 2.1 El 2.6 El

, !ODINE-133 0 EC 2.6 El 4.4 El 5.6 El IODINE-134 0 E0 1.4 El 2 El 2.3 El IODINE-135 0 E0 2.2 El 3.6 El 4.6 El CESIUM-137 0 EO 4.1 EO 7.1 EO 9.1 EO 920 930 940 F50 InnIN. _1e1 _ v e _ 1 e_ . e _ 1 e_ . =. c1

- e.<

. e1 IODINE-132 2.8 El 3 El 3 El 3 El IODINE-133 6.5 El 7.1 El 7.5 El 7.3 E1 IODINE-134 2.4 El 2.3 El 2.1 El 1.9 El IODINE-135 5.2 El 5.7 El 5.9 El 6.1 El CESIUM-137 1.1 El 1.2 El 1.2 El 1.3 E1 x . 1000 1010 1020 1030 IQDINE-131 9.9 El 3.? El 3.? El 3.9 E1 A .r .. .e.r.r._ i c _e e. . ;. - 1 e. . ::. ci. e

u. < r1

- 9. . d C1 IO~INE-133 7.0 El B El 5.1 E! E .1. E l i I O D I N E - 13.1 1.7 El 1.6 El 1.2 El 1 . 2 E ',

IC?INE-135 6.1 El 6.1 El e.1 El 5.1 E1 C E S I Ut t- 137 1.3 El 1.4 El 1.4 El 1.4 El

1040 1050 1100 1110 10 DINE-131 3.9 El 4 El 4 El 4 El ODINE-132 2.5 El 2.4 El 2.3 El 2.2 El IODINE-133 8.1 El 8.1 E1 9.1 El 3.1 El IODINE-134 1.1 E1 9.5 EO 8.3 EO 7.3 E0 l

l 10 DINE-135 6 El 5.9 El 5.9 El 5.7 El CESIUM-137 1.4 El 1.4 El 1.4 El 1.4 El i

1120 1130 1140 1150 l

l 10 DINE-131 4 El 4 El 4 El 4 El t _. n_.i _v .=. _ . c_ _

. .o .1 e ., _, e_1 ,. . o. =_1

. . e_ :1 I OD I t !E-121 9.1 E1 9 E1  ? El 9 El 10 DINE-134 6.4 EO 5.6 E0 d.? EO 4.3 E0 10 DINE-135 5 . -' E l 5.6 El 5.5 El 5.4 El CEE!UM-137 1.4 El 1.4 El 1.4 El 1.4 E1 1200 1210 1220 1230

• 0 DINE-131 4 El 4 El 4 E1 -

4 El 10D!NE-132 1.7 El 1.6 El 1.5 El 1.4 El

. Je n. ir .. =4__ l . . .-oo < .-7 ,

. < . :. =1

_ < . _:. .,_. . . e: _ ., _

IODINE-134 3.8 E0 d.2 E0 2.9 E0 2.6 EO IODINE-135 5.3 El 5.2 El 5.1 El 5 El CEEIUM-137 1.4 El 1.4 El 1.4 E-. 1.4 E1 9 ., . q. r.

i_ca-- . s. e. e.i

.. 'C'- . f.e

' LODINE-131 4 El 4 El a El 4 El tenter-toe t -- -- _

, c

.__1

r. ,- . .__o___=,,

_ e_ , _ _ _ - - -. _, _o _e ,__

, g ,

i ~ .

IODINE-134 2.2 E0 2 E0 1.7 E0 1.5 EO IODINE-135 4 .'? El 4.8 El 4.9 El 4.7 El

~

q OESIUM-137 1.4 El 1.4 El 1.4 El 1.4 El V

1920 1330 1340 1350 IODINE-131 4 El 4 El 4 El 4 El IODINE-132 1.1 El 1.1 El 1 E1 9.6 EO IODINE-153 7.6 El 7.5 El 7.5 El 7.5 El IODINE-134 1.3 E0 1.2 E0 1 EO S.9 E-1 IODINE-135 4.6 El 4.5 El 4.4 El 4.4 El CE51U't-137 1.4 El 1.4 El 1.4 El 1.4 E!

1400 1410 1420 1430 I ODINE-i ll 4 El 4 E1 . 4 El 4 El

, ,v.

. ., .r >: 4 ,:_ _ .< s .. . n_. =. n.

d, . ,< _ co  :. . : _ = . < . 9 = r>

IODINE-133 7.4 El 7.4 E1 -

7.3 El 7.3 El IODINE-134 7.8 E-1 6.3 E-1 6 E-1 5.2 E-1 IODINE-135 4.3 El 4.2 El 4.1 El 4.1 E1 CESIUM-137 1.4 El 1.4 El 1.4 El 1.4 E1 1440

• 1450 1500 1510 I,,n.. ..t s. _ l e:

. -+-  :<

_ . . e_. . . . :1

_., r_ 4 ., . e.

e1 IODINE-1?2 7.5 EO 7.1 E0 d.E EO 6.4 E0 i...-, , n t. v : _._. ,:e < . .q. _ ;1 < . .,

e, p1 e._1 r . .:. -. ,<.1 _

l IODINE-134 4.6 E-1 4 E-1 1.5 E-1 3.1 E-1 l ICD 1NE-135 4 El 3.9 El 3.9 El 3.3 El l

CE51UM-157' 1.4 El 1.4 El 1.4 El 1.4 El I

1520 1530 1540 1550 b'ODI NE-131 3.9 El 3.9 El 3.9 El 3.9 El IODINE-132 6.1 EO 5.8 EO 5.5 EO 5.2 EO IODINE-133 7.1 El 7.1 El 7 El 7 E1 IODINE-124 2.7 E-1 2.4 E-1 2.1 E-1 1.8 E-1 I ,_in

m. t;.,ie_ i_m. e s. 3.< El 5

w.<- P1

• . . ._e, C_ .' *5

... C1 CESIUti-127 1.4 El 1.4 El 1.4 El 1.4 E1 i

1600 1610 1620 1:.30

^

, t. O D . I ".-C .' 'ad. 2. '1' C1

- A. 9 C_1 2 . c.

c'

-. 5. . :. C1 i

IODINE-132 5 EO 4.7 EO 4.5 EO 4.3 EO k ~ODINE-133 6.? El 6.? El 6.9 El 6.3 El

..c,e..

i .r.,,- .. , , ,

..-4 :

, _v . c. - ..e  :

t - .1 t-1 i

IODINE-135 3.5 El 2.4 El 3.4 El 3.3 El CESIUti-137 1.4 El 1.4 El 1.4 El 1.4 Ei 9

E 1

1 3

1 i

9 I

e D ,, ,, , ,,,, _ _ .

J GAS SAMPLE DAT4 840 850 900 910 KRYPTON-83M 2.4 EO 2.3 E0 2.1 E0 2 E0 KRYPTON-85M 9.2 EO 9 EO 8.8 EO 8.6 EO KRYPTON-85 3.3 E-1 3.2 E-1 3.2 E-1 3.2 E-1 KRYFTON-87 1.2 El 1.1 E1 9.8 EO 5.9 EO KRYPTON-88 2.1 El 2 El 1.9 El 1.9 El KRYPTON-89 1.3 E0 1.4 E-1 1.6 E-2 1.9 E-3 XENON-131M 2.3 E-1 2.3 E-1 2.3 E-1 2.3 E-1 XENON-133M 1.1 E0 1.1 E0 1.1 E0 1.1 EO XENON-133 4.6 El 4.6 El 4.6 El 4.6 E1 XENON-135M 2.1 E0 1.4 E0 S . 6- E-1 5.4 E-1 XENON-135 4.1 El 4.1 El 4 El 4 El XENON-137 2 EO 3.2 E-1 5.2 E-2 9.5 E-3 XENON-138 8.3 EO 5.1 EO 3.1 E0 1.9 EO 920 930 940 150 KRYPTON-83M 1.9 E0 1.5 E0 1.? E0 1.6 EO KPYFTON-85M 8.3 EO 8.1 EO 7.9 EO 7.7 EO KRYPTON-35 3.2 E-1 3.2 E-1 3.2 E-1 3.2 E-1 KRYFTON-87 9.2 EO ,

7.4 EU 6.8 EO 6.2 EO r'R JF 7 0N-E i 1.8 El 1.7 El 1.6 El 1.6 El kC.YPTCN-39 2.1 E-4 2.4 E-5 2.9 E-6 1.2 E-7 ENON-131!1 2.3 E-1 2.3 E-1 2.3 E-: 2.3 E-1 AENCN-153M i.1 E0 1.1 E0 1.1 EG 1.1 EO XENON-133 4.6 El 4.6 El 4.6 El 4.6 El

XENON-135 3.9 El 3.9 El 3.8 El 3.8 E1 XENON-137 1.4 E-3 2.2 E-4 3.6 E-5 5.9 E-6 XENON-138 1.2 EO 7.1 E-1 4.3 E-1 2.7 E-1 1000 1010 1020 1030 KR'(FTON-83M 1.5 E0 1.4 E0 1.3 E0 1.2 EC KRYPTON-95M 7.5 EO 7.3 EO 7.1 EO 7 EO KPYPTON-85 3.2 E-1 3.2 E-1 3.2 E-1 3.2 E-1 KRYFTON-97 5.7 EO 5.2 EO 4.7 EO 4.3 E0 t

KRYPTON-88 1.5 El 1.5 El 1.4 El 1.3 El KRY: TON-90 3.6 E-5 4.1 E-9 4.7 E-10 5.4 E-11 p_<

~ =v.

- . .. a. _ ., .:: t h, .e . :. .e_,. . . c. e_ _ ., ..  : -=_.

. e. . :.

< EN CN- 13 91 1.1 E0 1.1 E0 1.1 E0 1.1 EO XENON-133 4.6 El 4.6 El 4.6 El 4.6 El v q. C v. 1 .e c. y. 1..ca c- _s n. 1.a v.= e. . x. =__ n. .. o. - c_ u XENON-135 3.7 El 3.7 E! 3.6 El 3.6 El XENON-137 9.5 E-7 1.5 E-7 2.5 E-E 4 E-9 XENON-138 1.6 E-1 10 E-2 6.1 E-2 3.7 E-2.

1040 1050 1100 1110 KR'r PTON .?3M i.1 E0 1.1 E0 10 E-1 9.4 E-1 KRYPTON-95M 6.8 EO 6.6 EO 6.4 EO 6.3 EO KRinTON-95 3.2 E-1 3.2 E-1 3.2 E-1 3.2 E-1 KRYPTON-37 3 . .: EO 3.6 EO 3.3 EO I EO KRYPTON-98 1.3 El 1.2 El 1.2 El 1.1 El h K RPT ON - 9 9 6.2 E-12 7 E-13 E E-14 9.2 E-15 w

XENON-131M 2.3 E-1 2.3 E-1 2.3 E-1 2.3 E-1 XENON'133M 1.1 E0 1.1 E0 1.1 E0 1.1 EO XENCN-133 4.6 El 4.6 El 4.6 El 4.6 E1

XENON-135 3.5 El 3.5 El , 3.5 El 3.4 E1 X-ENON-137 6.5 E-10 1.1 E-10 1.7 E-11 2.8 E-12 XENON-138 2.3 E-2 1.4 E-2 8.5 E-3 5.2 E-3 4

1120 1130 1140 1150 KRYPTON-SSM' 8.8 E-1 8.3 E-1 7.8 E-1 7.3 E-1 KRYPTON-85M 6.1 EO 6 EO 5.8 EO 5.7 EO KRYPTON-65 3.2 E-1 3.2 E-1 3.2 E-1 3.2 E-1 KRYPTON-67 2.7 E0 2.5 E0 2.3 EO 2.1 EO KRYPTON-88 1.1 El 1.1 El 1 E1 9. 7 EO .

KRYPTON-29 1 E-15 1.2 E-16 1.4 E-17 .6 E-18 XENON-131M 2.3 E-1 2.3 E-1 2.3 E-1 2.3 E-1 XENCN-153M 1.1 E0 1.1 E0 1.1 E0 1.1 EO XENON-133 4.6 El 4.6 El 4.6 El 4.6 E1 XENON-135M 1.4 E-3 9.2 E-4 5.5 E-4 3.7 E-4 XENON-135 3.4 El 3.3 E1 . 3.3 El 3.2 E1 XENON-137 4.5 E-13 7.3 E-14 1.2 E-14 1.9 E-15 XENON-138 3.2 E-3 2 E-3 -

1.2 E-3 7.3 E-4 1200 1210 1220 1230 KRYFTGN-33M 6.3 E-1 6.4 E-1 6 E-1 5.7 E-1 KRYPTON-85M -

5.5 EO 5.4 EO 5.2 EO 5.1 E0 KRYPTON-55 3.2 E-1 -

3.2 E-1 3.2 E-1 3.2 E-1

] KRYFTON-S7 1.9 EO 1.7 E0 1.d E0 1.4 E0 m

KRYPTON-98 9.3 EO 8.9 EO 8.6 EO S.2 EO q KRYPTON-89 1.8 E-19 2 E-20 2.3 E-21 2.6 E-22 XENON-131M 2.3 E-1 2.3 E-1 2.3 E-1 2.3 E-1

. XENON-133M 1.1 E0 1.1 E0 1.1 E0 1.1 EO XENON-133 4.6 El 4.6 El 4.6 El 4.5 El

X ENON-137 3.1 E-16 5 E-17 S.1 E-18 1.3 E-18 XENON-138 4.5 E-4 2.7 E-4 1.7 E-4 1 E-4 1240 1250 1300 1310 KRYPTdN-83M 5.3 E-1 5 E-1 4.7 E-1 4.4 E-1 KRYPTON-95M 5 EO 4.5 EO 4.7 EO 1.6 EO KRYPTON-85 3.2 E-1 3.2 E-1 3.2 E-1 3.2 E-1 KRYPTON-87 1.3 E0 1.2 E0 1.1 E0 1 EO KRYPTON-85 7.9 EO 7.6 EO 7.3 EO 7 EO KRY: TON-89 3 E-23 3.4 E-24 3.? E-25 4.5 E-26 v, n, J n_ s. J _., o. <i t.t . . e. =_.4

- o.o E_1

- . . _ . _ . o.-

- _ c_ _ .i XENON-133M 1.1 E0 1.1 EG 1.1 EC 1.1 EO XENON-133 4.5 El 4.5 El 4.5 El 4.5 El h XENON-135M 2.8 E-5 2.4 E-5 1.5 E-5 9.6 E-6 XENON-135 3 El 3 El 3 El 2.9 El v es4 n_

n -2 i 1_ ,.-e <- e_ . 4 __ 1 e. e e . m. _ _

m e n. c..( __e. .

. . , . = _ ___. ,

XENON-ISS 6.3 E-5 3.? E-5 2.4 E-5 1.4 E-5 1520 1330 1340 1350 KRYPTON-33M 4.1 E-1 3.9 E-1 3.6 E-1 3.4 E-1 KRYPTON-95M 4.5 EO 4.4 EO 4.3 EO 4.2 EO KRYPTON-55 3.2 E-1 3.2 E-1 3.2 E-1 3.2 E-1 KRY; TON-87 9.1 E-1 9.3 E-1 7.6 E-1 7 E-1 KRYPTON-93 6.7 E0 e.5 E0 e.2 EO 6 E0 m KRYPTON-99 5.1 E-27 5.9 E-29 f.~ E-2y <.$ E-30 I

XENON-131M 2.3 E-1 2.3 E-1 2. :3 E-1 2.3 E-1 a

XENON'133M 1 E0 1 EO  ! E0 1 EO m

XENON-133 4.5 El 4.5 El 4.5 El 4.5 E1

M9;N -IV$ z.y a z.y a z.e el .c.e es XENON-137 1.5 E ~2 2 2.4 E-23 3.9 E-24 6.3 E-25

~

XENCN-138 8.5 E-6 5.4 E-6 3.3 E-6 2 E-6 r

s 1400 1410 1420 1430 KRYFTON-83M 3.2 E-1 3 E-1 2.5 E-1 2.7 E-1 KRYPTON-65M 4 EO 3.9 EG 3.9 EO 3.7 EO KRYPTON-85 3.2 E-1 3.2 E-1 3.2 E-1 3.2 E-1 KRYPTON-87 6.3 E-1 5.8 E-1 5.3 E-1 4.3 E-1 KRYPTON-88 5.7 EO 5.5 EO 5.3 EO 5.1 EO KRYPTON-89 2.7 E-31 10 E-32 1.1 E-32 1.3 E-33 XENON-131M .l . 3 E-1 2.3 E-1 2.3 E-1 2.3 E-1 XENON-133M 1 E0 1 E0 1 E0 1 EO XENON-133 4.5 El 4.5 El 4.5 El 4.5 E1

. XENON-135M 0.6 E-7 6.2 E-7 3.0.E-7 2.5 E-7 o.<

v e_.v.

v.1 .. _1 e

- o. 7 g,

t1 e . .- t1

. e_ . _ e_1

~

XENON-137 1 E-25 1.6 E-26 2.7 E-27 a.3 E-28 XENON-138 1.2 E-6 7.e E-7 4.6 E-7 2.8 E-7 1440 1450 1500 1510 v.o.y : r o.N. :_ c '< o.es c?. - e.- t-1 o

- . :- c_

1 e.+

- . E <.

KRYFTON-85M 3.6 EO 3.6 EO 3.5 EO 2.4 EO K RY P"i CB.' 0"

- o_. .. ' c_ '.  ? . .' :-1

_ 0. . _0 C-1

_ * ' C-1 v.. -

c Nc/oTON-97 4.4 E-1 .

4 E-1 3.7 E-1 3.4 E-1 RP1FTON-3E- 4.9 EO 4.7 EO 4.5 EO 4.3 E0 ggy: p;_::o -

1. 5 : 'd 1 . ', e_ c_ e_ 1. C_ U_ -' . ._-

"' C

• 7

_M

= .. _..

_m. . 2.r. . . ,., c__1

..v t-1 , _ =_.

, .v,E1 B

- XENON-133M 1 E0 1 E0 1 E0 1 EO

" XENON-133 4.5 El 4.5 El 4.5 El 4.5 El M - _ _ _ _ _ _ _ _ _ _ . __

XENON-135 2.6 El 2.6 El 2.5 El 2.5 E1 XENON-137 7 E-29 1.1 E-29 1.8 E-30 3 E-31 XENON-139 1.7 E-7 1.1 E-7 6.5 E-8 4 E-8 1520 1530 1540 1550 KRY: TON-33M 1.9 E-1 1.0 E-1 1.7 E-1 1.f E-1 KRYPTCN-85M 3.3 EO 3.2 EO 3.1 EO 3 EO p4

.n, . :.v . .- c_.o,

_ e_.. e  : . .. = -_ 1  :. . e. - o. . e. c._ _ .. .._ c__1 KRYPTON-87 3.1 E-1 2.8 E-1 2.5 E-1 2.5 E-1 KRYPTON-88 4.2 EO 4 EO 3.o EO 3.7 E0 v..- Ri. v e n. n o

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• e,i 1 e_n XENON-133 4.5 El 4.5 El 4.5 El 4.5 El Q ENCN-135M 2.6 E-8 1.6 E-8 1 E-S 6.5 E-9 V

XENON-135 2.5 El 2.5 El 2.4 El 2.4 E1

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1600 1610 1620 1630 KRYPTON-92M 1." E-1 1.4 E-1 i.3 E-1 1.2 E-1 ki -nv. F. T i ,, _. c._, e. .s1 ,

=_0

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p. .vi. : T un._ o =a .

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XENCN-133 4.5 E! 4.5 El 4.5 El 4.4 E1 l

XENON-135M 4.1 E-9 2.6 E-9 , 1.7 E-9 1.1 E-9 XENON-135 2.4 El 2.3 El 2.3 El 2.3 E1

>$AON-137 3.3 E-35 5.4 E-36 8.7 E-37 1.4 E-37 XENCN-138 3.4 E-9 2.1 E-9 1.3 E-9 7.9 E-10 3

6 e

4

PLANT DATA

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

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

5

. O 4

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l i O i-

TYPE OF ACCIDENT RELEASE WITH FUEL DAMAGE 840 0"iEREACTORSHUTDOWNAT TIME RELEASE STARTS 900 DURATION OF RELEASE 120 MINUTES VOLUME OF COMPARTMENT A 3.5 E8 CC UENTILATION RATE OF COMP. A 5.7 E7 CC/ MINUTE VOLJME OF CCeSARTMENT S 10 E!O CC

, VENTILATION RATE OF COMP. 8 1.8 E3 CC/ MINUTE IODINE-131 SOURCE RELEASE 8 E2 UCI/ MINUTE NOBLE GAE 50URCE FELEASE 1.6 E3 UCI/ MINUTE

/ .A h O '

h3 u: i r .-

u l-+ cm ,1 <- L AL ,

40 u (1, ct I 'i 31 H4 k/ u. f ' UAr% ,

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'T TYPE OF ACCIDENT RELEASE WITH FUEL DAt%GE THE REACTOR SHUTDOWN AT 840 -

.N

- . : m_,_,.,.:

_,t,_ _ _ . . _ _ .

4mn!: , ,: n. 0 DURAT!ON OF RELEASE 210 MINUTES UOLUME OF CO'doART!4ENT A 2,6 EC CC VENTILATION RATE OF COMP. A 5.7 E6 CC/ MINUTE

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IODINE-ISI SOUPCE c.ELEASE 1. 3 E9 UC I /M i t ".iT E ELE GAS SOURCE RELEASE 5.2 E7 UCI/ MINUTE

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CONCENTRATION IN BUILDING L

78ME IODINE-131 NOBLES WHOLE BODY UCI/CC UC1/CC MREM /HR .j 900 0 EO O EO O EO f 910 4 E-8 8 E-s 3.7 E-1 i i o20 1.1 E-7 2.'2 E-7 9.6 E-1 ,'

930 .1 8 E-7 3.7 E-7 1.5 EO 940 2.6 E-7 5.1 E 2.1 EO 950 3.3 E-7 6.5 E-7 2.5 E0 1000 4 : <- _ .i . o. ;_t . .. o. c0 -

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1050 7.2 E-7 1.4 E-6 4.5 EO l 1100 7.7.E-7  :.5 E26 -

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TIME IODINE-131 NOBLES WHOLE BODY UCI/CC UCI/CC MREM /HR l t

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3 7 E-1 '

910 4 E-8 8 E-8 o, -o 0 1.1 E_< o.o e<

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OFFSITE DATA

-O Weather A. 0840 to 1515 D stability 3 mph wind from the Northeast B. 1515 (Enter stable high front)

G stability 1 mph wind from the North O

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

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(MHE AFFECTED SECTOR SW WIND FROM SECTOR NE WIND FROM DIRECTION 45 DEGREES WIND 5?EED S MPH STAEILIT CLASS D

EC':-: TAT:O ATE C INCHES /H:-

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TIME (MILES) 900 910 920 930

.33 0 0 0 0 0 0 0 0

.429 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1.5 0- 0 0 0 0 0  : 0 2 0 0 0 0 0 0 0 0 2.. u 0 0 0 0 0  : 0

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DISTANCE TIME (M!LES) 940 950 1000 1010 gj.

.33 0 0 0 0 0 0 0 0 i

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^

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D! STANCE

• TIME (MILE 5) 1020 1030 1040 1050

.53 0 0 0 0 0 0 0 0 429 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0

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, DISTANCE TIME

. (MILES) 1100 1110 1120 1130 i .33 0 0 0 0 0 0 0 0 L .42? O O O O O O O O V

. 0 0 0 0 0 0 0 0 b

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.:  : O O  :'

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II 2

DISTANCE Tl'ME n

..- (MILES) 1140 1150 200 1210 l

. e ,:: 0 0 0 0 M 0 0 0 0 l

l .429 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

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$ DISTANCE TIME b_

~

s (MILES) 1220 1230 1240 1250 br 4 y W.33 0 0 0 0 E O O O O s-s .42? O O O O e

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I DISTANCE TIME (MILES) 1300 1310 1320 133'

.33 0 0 go ,

0 0 D !50.3 b .429 0 0 0 .3

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.319TANCE TIME a

9 ~J

!a, (MILES) 1320 1330 1840 1350 P

.32 .? 2.2 3.6 4.8 1185.3 3048 4967.1 677?.3 o .429 . 6 1.6 2.6 3.5

$ 864 2221 7 3620.6 4937.2 r

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be (MILES) 1400 1410 1420 1430 t

, . .e.: o, o . .,

t . a,

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? .429 4.4 5.3 6 6.9 6171.5 7405.8 9051.6 9874.4

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u.. .  :: e . . -_ __ .

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r i DISTANCE TIME (MILES) 1440 1450 1500 1510

.33 10.3 11.1 11.9 12.6 1 15240 1d.933.3 18626.7 20320 429 7.5 S.1 3.6 0.2 h 11109.7 12343 12577.3 14811.6 f ,

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i h TYPE OF ACCIDENT .

RELEASE WITH FUEL DAMAGE

{

THE REACTOR SH'UTDC/J s /,7 g 40 W

$ THE A::ECTED SECTOP s N

d WIND FROM SECTOR N I WIND FROM DI RECTI O!1 0 DEGREES WIND SPEED  : MPH

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u 2 9.3 E-2 3.5 E-7 1.5 E-26 0 EP.

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DISTANCE TIME 4

4 (MILES) 1520 1530 1540 1550 tm.f L. . . ',: 0 0 112.1 117.5

.25 l 0 0 1877FE.6 19675?.5 s

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• b9-(% DISTANCE TIME m

$.v g (MILES). 1600 1610 1620 1630 MW fil .25 122.? 128 133.1 229022.6 138 238183.6 h 210700.8 219861.7 N

iwi .341 108.5 113.5 118.3 123 3,.1 193980 196315.? 205373.5 '12930.3 19?:

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DISTANCE TIME (MILES) 1640 1650 1700 1710 e i.ce.q

. a - . . 2. i . 4 .c=.

. . ,. ., 4 4, 247344.5 256505.4 261065.9 256505.4

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DISTANCE TIME (MILES) 1720 1730 1740 1750

. 1e.,

i ~.c s.6 icv.o .1

,25 1.ov . z . o. a 3 256505.4 251924.9 247244.5 247344.5

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