Text

Emergency Exercise of 930922,Scenario Guide
	ML20059K247
Person / Time
Site:	Millstone
Issue date:	09/22/1993
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
References
	NUDOCS 9311150248
	Download: ML20059K247 (115)
	v • d • e

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MILLSTONE 1993 EMERGENCY EXERCISE

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~f MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 TABLE OF CONTENTS 1.

Introduction 1-1 A.

Scope.

1-2 B.

Schedule......

I 11.

Objectives 2-1 A.

Onsite..

B.

Offsite..

2-7 I

111.

Scenario 3-1 A.

Narrative Summary.

3-4 B.

Integrated Controller Guide I

C.

Timeline....

3-10 i

3 11 D.

Sta: ion Controller Specific Messages...................

i IV.

Subscenarios A.

Fault on Vital Bus 24D.

41 B.

Spurious Sump Recirc Actuation Signal.

4-2 r

C.

Containment Sump Suction Valve Failure.........

4-4 l

D.

A* HPSI Pump Siezed 4-5 E.

Hydrolic Lock of 2-S1-440 4-6 I

4-7 F.

Swing HPSI Breaker Racking Mechanism I

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. r MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 TABLE OF CONTENTS V.

Data A.

Key Operational Plant Parameter Data 5-1 B.

' Radiological Release Data and Dose Rate Summary....

5-6 C.

Inplant Radiological Data 5-10 I:

D.

On-site Radiological Data........

5-30 5-39 E.

Off-Site Radiological Data.......

5-67 F.

Meteorological Data....

5-75 G.

Chemistry Data.

VI.

Off-Site A.

Controllers Guide 6-1 6-33 B.

Messages C.

Extent of Play.

6-58 D.

Rumor Control..

6-93 E.

RERP-15 Exercise Evaluation Manual - Handout Vll.

Medical Exercise A.

Controllers Guide and Data.............

7-1 B.

Extent of Play........

7-6

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3-MILLSTONE 1993 FULL PARTICIPATION EXERCISE E

SEPTEMBER 22,1993 EXERCISE SCOPE Organizations which will participate in the Exercise include the following:

l Utility Town of Montvitie, Millstone Nuclear Power Plant,

- Town of New London, I

Waterford, Connecticut Town of Old Lyme, Northeast Utilities Service Company (NUSCO),

l Corporate Headquarters, Tyn of Old Saybrook, i

Berlin, Connecticut

_g Plum Island, NY, and t

3 CT State Aaencies*

Town of Waterford Governor's Office I

Host Communities

Connecticut Office of Emergency Management.

East Hartford I

Connecticut Department of Environmental Protection, Private Aaencies*

l Connecticut Department of Health.

American Red Cross Connecticut State Police, Salvation Army Connecticut Department of Agriculture.

Connecticut Department of Consumer Protection, Connecticut Department of Transportation, and Connecticut National Guard Municipalities

Town of East Lyme, Fisher's Island, NY City of Groton,

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Town of Groton, Town of Ledyard.

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I MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 SCHEDULE OF EXERCISE ACTIVITIES Event Date/ Time / Location ^

Attendees 1.

On-Site Controllers Walk-Through of August 9,1993 All Station and Corpo-Rehearsal Packages 9:00 a.m.

rate Controllers Millstone EOF 2.

Pre-Exercise Rehearsa/ Drill August 12,1993 Control Room and Site EOF Players -

l Pager Activated I

7:00 a.m. - 12:00 p.m.

All Station and Berlin Millstone EOF & Berlin EOC Players and Contro!!ers.

The State EOC will be Lunch and Critique 1:00 to 3:00 p.m.

All Station & Corporate Players & Controllers (optional)

B 3.

FEMA Briefing to Review Off-site Sce-September 19,1993 State of Connecticut, nario 2:00 p.m.

FEMA and NU Emer-I Raddisson Hotel gency Preparedness New London Staff I

4 On-Site Controllers Walk-Through of September 20,1993 All Station and Corpo-Exercise Packages 9:00 a.m.

rate Controllers r

Millstone EOF Off-Site Controllers Walk-Through of September 20,1993 NU Emergency Prepared-Exercise Packages 4:30 p.m.

ness Staff and I

Berlin Cafeteria State / Local Controllers S.

School Bus Exercise (out of sequence September 21,1993 with the scenario) 10:00 a.m.

Old Lyme 6.

NRC Briefing to Review Changes from September 21,1993 NRC and Nt) Emergency -

60-Day Submittal. Plant Tour for 2:00 p.m.

Preparedness Staff I

NRC, if Requested Millstone EOF I

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7 MILLSTONE SCHEDULE OF EXERCISE ACTIVITIES Event.

Date/ Time / Location Attendees 7.

Host Community Exercise September 21,1993 2:00 p.m. East Hartford I.

t 8.

Medical Exercise September 21,1993 5:30 p.m.

I L&M Hospital New London E

9.

School Bus Exercise September 22,1993 East Lyme, Ledyard, Free Play Montville, New London, Groton, Waterf ord

10. Millstone Exercise September 22,1993 All Players and I

Mi!! stone, Corporate, and Controllers State / Town Emergency Response Facilities i

NU Post-Exercise Review immediately following the Berlin and Station Exercise - Millstone EOF Controllers and Lead g

5 Players. Other Players optional attendance B

11. NU Post-Exercise Review Meeting September 23,1993 Lead Controllers and 8:00 a.m.

Emergency Preparedness Millstone EOF Staff only

12. NU Critique Dry Run September 23,1993 Lead Controllers and 2:00 p.m.

Emergency Preparedness Millstone EOF Staff only I

13. NU/ State / Town Dinner Critique September 23,1993 State and Town Chief 6:00 p.m.

Executive Officers, Civil Reddisson Hotel, New Preparedness Directors, I

London Controllers, and NU Management

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14.' NU Exercise Formal Critique S:pt:mber 24,1993 NU M:nsgement, Lord to NRC 9:00 a.m.

Controllers, Lead Millstone EOF Players, and NRC Team and NRC Exercise Critique to Follow 10:00 a.m.

Millstone EOF I

15. FEMA and State Meeting September 25,1993 FEMA Officials, State 10:00 a.m.

and Utility Staff

_I Raddisson Hotel, New London

16. FEMA Public Meeting September 25,1993 Public Meeting 2:00 p.m.

Waterford Public Library I

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I MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 Section i STATION AND CORPORATE OBJECTIVES

'I CORE ELEMENTS AND OBJECTIVES APPLICABLE FACILITIES l

1.

ACCIDENT DETECTION / ASSESSMENT AND CLASSIFICATION CR EOF Demonstrate the capabihty to classify an incident based on plant

g conditions and confirm (when possible) the eme.rgency classification by g

dose calculations or monitoring.

2.

NOTIFICATION OF ON-SITE AND OFF-SITE RESPONDERS CR EOF Demonstrate the capabihty to promptly notify on-site responders of l

emergency condstions, emergency classifications, activation of emergency organizations and facilities, protective actions, radioactivity release status, and any changes to these conditions.

!l Demonstrate the capability to promptly notify off-site officials, including l E' the NRC, of emergency conditions, emergency classifications, activation of emergency organizations and facihties, recommended protective

!g actions, radioactivity release status, potentially affected populations, l3 projected population doses, and any changes to these conditions.

I-3.

COMMUNICATIONS CR EOF TSC OSC RMT ERT SEC CEOC l

Demonstrate the capabihty for all communications systems within each

!E center to function properly in establishing and maintaining lg communications with each other and especially with the control room.

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RADIOLOGICAL EXPOSURE CONTROL CR EOF TSC OSC l

RMT ERT SEC l

Demonstrate the capability to confirm and continually assess the habitabihty of the emergency response centers.

Demonstrate the capabiltty to properly implement appropriate iodine-protective measures (use appropriate respiratory protection or take KI).

Demonstrate the capabihty to provide at risk on-site personnel with adequate protective equipment such as self contained breathing apparatuses (SCBA) and monitoring equipment with sufficient ranges.

3 osmone As of September 13,1993

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MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 l

Section i STATION AND CORPORATE OBJECTIVES I

CORE ELEMENTS AND OBJECTIVES APPLICABLE FACILITIES 5.

PROTECTIVE ACTION DECISION / RECOMMENDATION MAKING CR EOF CEOC Demonstrate the capability to decide on protective actions for on-site l

and off-site personnel without waiting for a dose assessment..

I Appropriate decision makers should promptly recommend protective

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actions on-site and off-site consistent with criteria established in the emergency plans.

6.

STAFFING AND AUGMENTATION EOF CEOC CR TSC OSC Demonstrate the capability to augment control room staff and staff emergency centers in accordance with staffing requirements identified within the emergency plans and implementing procedures.

I Demonstrate the capability to adequately brief relief personnel when utilized.

I 7.

ANALYSIS OF PLANT CONDITIONS AND CORRECTIVE ACTIONS CR TSC CEOC I

Demonstrate the capability to maintain an overview of the reactor and plant conditions using the expertise of technical staff and the information provided by them from other sources.

Demonstrate the capability to recognize that events are progressing abnormally and develop appropriate strategies to bring the plant to a safe shutdown condition.

8.

FACILITY MANAGEMENT AND CONTROL CR EOF TSCOSC CEOC I

Demonstrate the capability for the facility manager to coordinate and oversee the overall response and redirecting the response when t

necessary.

Demonstrate the capability for emergency response personnel to perform actions in accordance with appropriate emergency response procedures and instructions.

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r MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 Section i STATION AND CORPCRATE OBJECTIVES CORE ELEMENTS AND OBJECTIVES APPLICABLE FACILITIES

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IMPLEMENTATION OF ON-SITE PROTECTIVE ACTIONS CR EOF TSCOSCRMT ERT SEC

,3 Demonstrate the capabihty, if warranted by conditions, for the control room to initiate on-site protective actions until the EOF is activated.

7 Demonstrate the caphikty, while in a Site Area Emergency, to evacuate all on-stte nonessential personnel to off-site locations identified in the emergency plan Demonstrate the capabikty, while in a General Emergency with imminent releases projected, to evacuate all on-site nonessential I

personnel without radiological monitoring or decontamination, to off-site locations identified in the emergency plan.

Demonstrate the capabihty, while in a General Emergency without imminent releases projected, to evacuate all on-site nonessential personnel following radiological monitoring or decontamination, to off-site locations identified in the emergency plan.

10. DOSE ASSESSMENT EOF CEOC I

Demonstrate the capability and knowledge to use approved procedures for dose assessment. If a release is anticipated or in progress I

personnel should correctly and rapidly assess and integrate information from the reactor's systems status and trends, source-term assumptions, post-accident sampling system samples, and meteorological information to define the magnitude and location of the on-site and off-site impact.

Demonstrate the capabikty, if a release is underway, to promptly initiate on-site samphng and monitoring to confirm the composition of releases to better define the source term and confirm projected doses.

11. DISPATCH AND COORDINATION OF RADIOLOGICAL MONITORING CR EOF OSCCEOC TEAMS RMT Demonstrate the capabihty, if a release is anticipated or is underway, to promptly deploy teams to perform environmental samphng at appropriate locations to characterize the size, location and intensity of f

the plume.

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I MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 Section i STATION AND CORPORATE OBJECTIVES I

CORE ELEMENTS AND OBJECTIVES APPLICABLE FACILITIES CR EOF TSCOSCRMT I

12. CONDUCT FACILITY CRITIQUE ERT SEC CEOC Demonstrate the capability for each facility to hold a preliminary critique at the end of the exercise while details are fresh. The preliminary cntiques should be followed by a formal critique that evaluates the overs!! performance and the interaction of facihty representatives and I

players with one another. Evaluators should provide an unbiased and candid evaluation of the exercise identifying areas of strength as well as areas of weakness and areas needing improvement.

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MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 Section i STATION AND CORPORATE OBJECTIVES FIVE YEAR PLAN ELEMENTSIOBJECTIVES APPLICABLE FACILITIES

13. ACTIVATION OF EMERGENCY NEWS CENTER (JOINT CEOC I

INFORMATION CENTER)

(at State Media Center)

Demonstrate the capability to disseminate accurate and timely information to the media / press and to coordinate these releases with off-site officials and the NRC. Information provided to the public should be prepared to the technical level that the pubhc can understand.

Demonstrate the capability to promptly provide corrected or supplemental information in the event of an error or misinformation in I

news stories (e g., Rumor Contro!)

14. USE OF LICENSEE'S HEADQUARTERS SUPPORT PERSONNEL CEOC Demonstrate the capability for the Corporate Command Center to activate and perform it's function in a timely manner with congestion 8

and noise levels kept to a minimum.

Demonstrate the Corporate Command Center's capability to provide timely support in areas such as govemment liaison, logistics and support.

15. DISPATCH AND COORDINATION OF CORRECTIVE ACTION CR TSC EOFOSC ERT TEAMS I

Demonstrate the capability to initiate and perform actions promptly following the decision to conduct an operation in coordination with the control room and to be briefed on potential hazards.

Demonstrate the capabihty to provide teams with adequate radiological exposure control measures and communications.

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MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 Section i STATION AND CORPORATE OBJECTIVES I

ADDITIONAL ELEMENTSIOBJECTIVES APPLICABLE FAC!LITIES i

16. ADHERENCE TO PROCEDURAL GUIDANCE IN IMPLEMENTING

.CR CORRECTIVE ACTIONS OUTSIDE OF NORMAL PLANT l

PROCEDURES 5

Demonstrate the capability to follow established guidance in implementing an action which either deviates or is not contained in I

existing emergency procedures in efforts to bring the reactor to a safe shutdown cond! tion or to mitigate the impact of radiological consequences.

17. CLASSIFICATION OF AN INCIDENT IN ACCORDANCE WITH EOF EMERGENCY PLAN CLASSIFICATION DEFINITIONS Demonstrate the capability to make a classification consistent with; (1) it's associated radiological definrtion within the emergency plan, (2) plant radiological conditions, and (3) the potential magnitude of a I

radiological release.

I Applicable Facilities Key Emergency Operations Facility CR Control Room (Affected Unit)

EOF Operational Support Center TSC -

Technical Support Center OSC Emergency Reentry / Rescue Teams RMT -

Radiological Monitoring Teams ERT SEC -

CAS, SAS, Security Force CEOC -

Corporate Emergency Operations l

Center

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I MILLSTONE 1993 FULL PARTICIPATION EXERCISE i

SEPTEMBER 22,1993 NARRATIVE

SUMMARY

The Millstone Unit 21993 full participation exercise will be run from the Un.t 2 simulator. The exercise is based on a sequence of events involving a small break loss of coolanct accident (LOCA) that degrades to a large break LOCA with a failure of safety injection (SI). The LOCA without Si results in severe core -

damage which produces a large inventory of radionuclides and hydrogs in containment. A pressure spike from a hydrogen bum ruptures the Facility I containment sump suction pipirig, causing a radiological release to atmosphere via the Enclosure Building, the Enclosure Building Filtration System (EBFS), anc the Unit 1 stack.

At the beginning of the exercise Units 1 and 3 are "as is"; Unit 2 is operating at 100% power. The only Unit 2 equipment out of service is the Facility i Hydrogen Analyzer. The "B" (swing) charging pump is aligned to Facility 1. Unkown to the operators, one of the air operated valves for the Facility 11 Hydrogen Analyzer vill not open if the operators attempt to place the analyzer in service.

Shortly after the exercise begins, the operators recognize symptoms of an RCS leak and enter AOP 2568,

" REACTOR COOLANT SYSTEM LEAK". As the leak degrades, the operators trip the reactor per AOP 2568 and enter EOP 2525, " STANDARD POST TRIP ACTIONS", then transition to EOP 2532, " LOSS OF PRIMARY COOLANT" and initiate a plant cooldown.

The Onsite Director of Station Emergency Operations (ODSEO) and the Shift Supervisor (SS) should I

classify the event as an ALERT due to failure of the RCS barrier. Once the event is classified, the on-call organization, the State, and local towns will be notified via the emergency notification and recall systern (ENRS). The Nuclear Regulatory Commision (NRC) will be notified via hotline. The Millstone emergency response facilities should be operational within approximately one hour.

While the oncall organization is activating the onsite facilities, the Facility 114160 volt vital bus (24D) is lost due to a fault, leaving only the Facility I engineered safeguards features equipment with power.

By approximately 0845 the onsite emergency response facilities are expected to be operational with the Oncall Director of Station Emergency Operations (DSEO) directing activities from the Emergency Operations Center (EOC).

At 0900 a spurious Facility I containment sump recire actuation signal (SRAS) is received due to a circuit failure. All automatic actions associated with a SRAS occur the Facility I low pressure safety injection (LPSI) pump is tripped (if running) and the Facility I containment sump suction valve (2-CS-16.1 A} opens.

At this point, the irijection sources for makeup to the RCS are the "A" and "B" charging pumps and the Facility I high pressure safety injection (HPSI) pump.

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The operators recognize that the SRAS was spurious and attempt to close the Facility I containment sump suction valve from the control room. Due to a failure of the cable from the breaker for 2-CS-16.1 A to the j

motor operator on the valve, the valve cannot be shut re notely. The control room operators are expected i

I to direct a Plant Equipment Operator (PEO) to shut the valve locally, if dispatched, the PEO will be able to operate 2-CS-16.1A locally, but due to the length of time required to shut the valve manually, he 'will not be able to shut the valve fully before leaving the area due to the next event.

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At 0920 the RCS piping rupture will degrade catastrophically to a large break LOCA. The PEO anempting to shut 2-CS-16.1A locally will hear the noise of the LOCA from containment as well as momentary flow noise from the containment sump suction piping and will evacuate the area.

Because the Facility I containment sump suction VElve is open, the high pressure that develops in containment from the LOCA establishes a reverse differential pressure across the RWST Facility I suction l

I check valve, backseating the check valve and isolating the RWST from the Facility i HPSI, LPSI, and containment spray (CS) pumps.

Since there is not enough water in the containment sump to provide adequate suction head, running Facility I pumps will begin to cavitate. Because of the close construction tolerances required for the HPSI pumps to deliver relatively high capacity at high RCS pressures,"A" HPSI pump will fail due to overheating I

from cavitation before the ope stors can stop it. "A" LPSI pump, if running, and "A" CS pump are expected to be stopped by the operators before damage occurs, so these pumps will be available if suction can be restored.

Plant conditions at this time are as follows:

t Facility il HPSI, LPSI, and CS pumps are disabled due to loss of vital 4160 volt bus 24D.

Facility I HPSI pump is out of service due to overheating from cavitation.

i Facility I LPSI and CS pumps are not damaged and have electrical power, but do not have a

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I suction source.

A large break LOCA has occurred, safety injection tanks have reflooded the reactor vessel, and f

core boil down is in progress.

"A" and "B" charging pumps continue to inject water from the RWST, but the combined capacity i

of approximately 90 gallons per minute is not enough to recover reactor vessel level.

By approximately 0940 the DSEO should escalate the event classification to a SITE AREA EMERGENCY due to loss of two fission product barriers, the RCS (LOCA) and the fuel cladding (reactor vessel level =

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0%).

During the period of core boil down and core damage, the operators and the emergency response l

I organization will attempt to regain injection capability by aligning electrical power to the swing HPSI pump i

from Facility I and aligning the suction to Facility 11. When the operators attempt to rack up the "B" HPSI pump breaker to the Facility I bus, the racking mechanism jams.

If the operators attempt to restore suction to Facility 1 LPSI pump by crossconnecting to the intact Facility 11 suction via the shutdown cooling system (SDC), manually operated gate valve 2-SI-440 will be found hydraulically locked in the shut position.

The emergency response organization will continue efforts to restore electrical power to Facility 11 equipment and suction to Facility I LPSI and CS pumps.

At 0955 injection capability will be regained, either by repairing the breaker racking mechanism for "B" HPSI pump or by venting the bonnet of the LPSI to SDC cross connect valve, 2-SI-440.

By approximately 1003, core damage will be terminated. The emergency response organization will assess the degree of core damage that has occurred and will develop dose projections based on the radiological conditions in containment while continuing efforts to shut the Facility I containment sump I

suction valve.

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At 1100, the containment barrier fails when a hydrogen bum causes a pressure spike in containment that ruptures the Facility I sump suction line downstream of the stuck open suction valve, 2-C3-16.1A. A I

radiological release begins from containment, through the ruptured sump suction line, into the Enclosure Building, to the Enclosure Bwiding Filtration System, and out the Unit 1 stack.

f By 1115 a GENERAL EMERGENCY, Posture Code " Alpha", should be declared by the DSEO due to I

projected offsite doses. The field monitoring teams will locate and track the plume while dose projections are modified based on current data. Recommended protective actions will be provided to the State and local towns.

i At 1200 repairs will be completed allowing remote closure of 2-CS-16.1 A, restoring containment integrity.

After approximately thirty minutes, the contribution to the plume of the radioactive water in the Enclosure Building will have decreased until the the release is effectively terminated.

The fac;lity and offsite organizations will continue to track the plume and to perform actions to minimize the exposure of personnel until the exercise is terminated at 1400.

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MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993 INTEGRATED CONTROLLER GUIDE TIME AC11VITY MESSAGE CONTRC' LER INFORMATION 0630 Pre-shift brief and board wa!kdown for the Shift Tumover Sheet and pre-shift MOL; 100% power Operations crew.

brief provided by simulator instructor.

EGR13 The Facility I I hydrogen analyzer is EGR18 out of service for replacement of the power supply.

0700 Start exercise.

Malf RC-04,200 gpm,300 seconds 0725 Operators recognize symptoms of RCS leakage Disable the Facility I Hydrogen and enter AOP 2568, RCS LEAK, then trip the Analyzer by preventing operation of reactor and go to EOP 2525, STANDARD air operated isolation valve 2-AC-12.

POST TRIP ACTIONS.

After carrying out the actions of EOP 2525, the operators will enter EOP 2532, LOSS OF PRIMARY COOLANT, and perform the following:

o initiate a plant cooldown at 50 - 75

F per hour.

o Stop LPSI pumps.

o Align Chg pumps to RWST.

o Shift CR ventilation to recirc mode.

o Direct Chemistry to sample the RCS per EOP 2526 REACTOR TRIP RECOVERY.

o Secure Diesel Generators per EOP 2526.

o Place SDC in service per OP 2310, SHUTDOWN COOLING SYSTEM.

o Attempt to place the Facility I hydrogen analyzer in service.

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-M TIME ACTIVITY MESSAGE CONTROLLER INFORMATION 0745 The ODSEO and SS classify the event as an ALERT. posture code Charlie 1, due to failure of the RCS barrier (leakrate > charging capacity).

0800 issue contingency message.

Declare an ALERT, posture code Charlie 1, due to failure of the RCS barrier".

0820 Fault on Facility 11 vital 4160 VAC bus (bus Subscenario A.

ED05D 24D).

Bus 24D is not to be restored during the exercise.

0845 ERFs are activated; the DSEO has relieved the ODSEO and is in the EOC.

0900 A spurious SRAS occurs due to a circuitry Subscenario B.

1/O override: HS-3039, True malfunction.

1/O override: HS-3008-D, on (red The Facility I containment sump suction valve light)

(2-CS-16.1A) opens and the LPSI pump trips (if HS-3008-B, True (valve closed, running).

necessary for loss of suctiion)

The power cable from the breaker for 2-CS-Subscenario C.

16.1 A to the motor operator on the valve fails, preventing remote closure of the valve.

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0905 The operators recognize that the SRAS was The valve pcsition indicatun shows spurious and attempt to shut 2-CS 16.1A from the valve to be fi

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the control room.

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TIME ACTNITY MESSAGE CONTROLLER INFORMATION 0910 A PEO is dispatched to shut 2-CS-16.1 A The valve operates as expected.

The valve operates normally except locally.

however, it is very stiff.

for being stiff. Due to the many tums and the difficult operation, the valve will not be fully shut by the PEO.

Provide intermediate valve position after PEO begins opening the valve.

0920 Large break LOCA occurs, pressure in To PEO at 2-CS-16.1 A: Audible RC03A,100%

containment exceeds 30 psig.

indication of large break LOCA and audible indication of short duration Containment pressure acts through the partially flow through the containment sump open containment sump suction valve and suction line.

backseats the Facility l RWST suction check valve, causing a toss of suction to the Facility I ESF pumps.

o "A" HPSI pump fails due to overheating from loss of suction pressure.

o "A" LPSI and "A" CS pumps are stopped by the operators due to cavitation.

Free The operators attempt to regain suction to the When the team arrives at 2-St-440, 2-SI-440 is postulated to be play "A" LPSI pump by crossconnecting to the intact direct them to relocate to the mockup.

inoperable due to being hydraulically Facility 11 suction via the shutdown cooling The handwheel for 2-SI-440 cannot be locked. A mockup is set up in the Unit system.

tumed.

2 Maintenance area.

Subscenario E.

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M TIME ACTMTY MESSAGE CONTROLLER INFORMATION Free The emergency organization attempts to regain The "B" HPSI pump breaker will not play injection by racking up the swing ("B-) HPSI rack up due to minor misalignment.

pump breaker and aligning the suction to Facility 11.

Subscenario F.

0940 SITE AREA EMERGENCY, posture code Charlie 2, declared by the DSEO due to loss of the RCS barrier and potentialloss of the fuel barrier (RVLIS indicates 0%)

0953 Injection capability regained through one of the When notified by controller that the f@] wing two success paths:

"B" HPSI breaker has been racked up, enable breaker closure from the o "B" HPSI pump breaker racked up The "B" HPSI pump breaker is racked control board.

up.

o 2-SI-440 opened after venting the bonnet Allow the players to report valve 2-SI-440 open only after the required When notified that 2-SI-440 has been actions have actually been performed opened, enable LPSI injection.

on the mockup.

0955 issue contingency message.

" Declare a SITE AREA EMERGENCY, posture code Charlie 2, due to loss of the RCS barrier and potential loss of the fuel barrier" 0955 Injection flow initiated.

1003 Core damage terminated.

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-M TIME ACTNnY MESSAGE CONTROt1ER INFORMAT10N 1100 A hydrogen bum causes a containment Provide the following:

Use Hazeltine to control containment pressure spike that ruptures the Facility I sump (1) Audible indication of hydrogen burn pressure.

suction line downstream of the open suction to anyone in a position to hear it.

valve (2-CS-16.1 A)

(2) Increase on seismic monitor indication.

(3) Actuation of acoustic monitors.

1115 GENERAL EMERGENCY, posture code Alpha, declared due to nrojected offsite doses.

1130 issue contingency message.

Declare a GENERAL EMERGENCY, posture code Alpha, due to projected offsite doses.

1133 issue command message.

UPI has distributed information stating that the containment breach is due to an earthquake in southeastern Connecticut.

1200 Containment integrity restored by closing 2-CS-Subscenario C.

Remove malfunction when notified by 16.1 A remotely.

controller of simulated repair.

1215 A contaminated person enters the EOF.

1230 The contribution to the release of the radioactive water outside containment decreases until the release is essentially terminated.

s 1400 Ex we terminated.

.t

MILLSTONE 1993 FULL PARTICIPATION EXERCISE SEPTEMBER 22,1993

'i TIMELINE

~

t 0700 Start 0725 Small break LOCA 0745 Declaration of ALERT due to loss of the RCS barrier 0820 Loss of power to Facility 11 ESF equipment (fault on bus 24D) 0845 Emergency response facilities activated 0900 Spurious sump recirculation actuation signal (SRAS) causes the Facility I containemnt sump suction valve to open 0920 Large break LOCA; high containment pressure acts through the sump suction valve to backseat the RWST suction valve causing a loss of injection 0940 SITE AREA EMERGENCY declared due to loss of the RCS barrier and potentialloss of the fuel barrier 0955 injection restored 1003 Core damage terminated 1100 Containment breached downstream of the containment sump suction valve due to a pressure spike from a hydrogen bum 1115 GENERAL EMERGENCY posture code "A" declared due to loss of three barriers; the-RCS, the fuel clad, and the containment 1200 Containment integrity restored by shutting the Facility I containment sump suction valve 1215 Contaminated person enters the EOF 1230 Radiological release terminated 1400 Exercise terminated I

I I

9 1

I I

I THIS SECTION NOT APPLICABLE TO THIS SCENARIO GUIDE I

.I

'I I

LI g

g I

I w-r

4

!I

I i

!I i

lI V. DATA t

lI A. KEY OPERATIONAL DATA h

i i

I 4

t I

j 1

s W

i I,

l i

1 i'I

-)

I I

M' M.

M M

Mi M M

N M

M M

M M.

M M

M 'M M

M HEAD LEVEL INDICATION 1gg 90 80 70 x

60 v

S C

50 LU

__J 4 g-C y-

} @-

~

l

/

20 w. c,,ng,,,

t

(

10 m

~

i l..

..i...-.. L...E JaA

' } --

---s'~~~

9:20 10:20

[

TIME

seu uma sua mas uma muu man.

aus uma sum num uns uma sum mas les sum uni-um 1

i CORE EXIT THERMOCOUPLE TEMPERATURE INDICATION r

l 3,600-2,4ggi..

e i

A N

4

-u_1,800r e,

k u

x e

v a

u s

<r I-

?

4 z 1,200!

F H

c4 s

s

~

q 600 e m,,,_ m,,

m

?^*h":m gy 7..._,

4" h

e'

+.

+

"y,

g

^

wmyew Tw e n*" m w?3 s.

, ~

r:t 4

j;.

y 7 g4

y 1 1: -

--l rz z..

9:20 9:30 10:03 TIME I

m.

m..

m.

mm m

mm.

m,

.u u-m u

__m,.

s_,-,.

y

M M

miill

.5 M

M M

'W. mm p

a m'

L l

CTMT PRESSURE INDICATION I

i b0r 6

i 50-l

- 40 m0 t_D s

y CD L

Y :a.

y_ 3 0 l

v 4

i A,s,,,,):

EL. -

p-u 4

y-D%' ' 'I,W e i b 2 @.-

g y

g pj j }'.';

23 "

w

?h k

' ;k h%

,d i':l2f:

} G.-

ll 4

g a

l'.t

.v

..-,,_,,-mwr -

m

-,e-,m-tre' f ^ -

-5:-

7

.j

[

g '+,:-.. g -

-<g

g

g -

.g 7:25 9:20 10:10 11:00 TIME-

MILLSTONE UNIT II 1993 EXERCISE AGE 1 OF 2 PAGES 06:18 11-SEP-1993 I

MAX CONTAINME MP1 STACK Wind REACTOR REGION T HI RAD HI RANGE Ambient Wind speed VESSEL AVG TEMP MON HON Temperatu Speed 33' 142' LEVEL (F)

(R/HR)

(uCi/cc) e 33' (F)

(MPH)

(MPH) 06:00 AS READ AS READ 1

AS READ 68.5 3.3 13.7 6:15 AS READ AS READ 1

AS-READ 68.5 3.3 13.7-

^

6:30 AS READ AS READ 1

AS READ 68.7 6.6 16.7 6:45 AS READ AS READ 1

AS READ 69.1 9.0 18.0 07:00 AS READ AS READ 1

AS READ 69.6 9.0 20.0 g7:15 AS READ AS READ 1

AS READ 70.0 10.8 21.2 E7:30 AS READ AS READ 1

AS READ 70.0 11.2 20.6 07:45 AS READ AS READ 1

AS READ 69.4 9.4 19.0 8:00 AS READ AS READ 1

AS READ 69.4 8.3 19.5 8:15 AS READ AS READ 1

AS READ 69.4 8.5 19.5 8:30 AS READ AS READ 1

AS READ 69.6 11.0 20.0 8:45 AS READ AS READ 1

AS READ 69.6 9.9 17.5 9:00 AS READ AS READ 1

AS READ 69.4 8.7 16.6 9:15 AS READ AS READ 1

AS READ 69.4 8.3 15.7 09:20 0

260 1

AS READ 69.4 8.3 15.7 0

260 1

AS READ 70.3 12.3 20.3

!g9:30 y9:45 0

1505 334 AS READ

-70.3 13.9 21.5 09:55 0

2300 1000 AS READ 70.3 13.9 21.5 0:00 0

2300 47250 AS READ 70.2 13.7 20.8 0:03 0

2300 75000 AS READ 70.2 13.7 20.8 0:15 0

260 75000 AS READ 70.0 12.1 19.5 10:20 7

260 75000 AS READ 70.0 12.1 19.5

,$0:30 7

260 75000 AS READ 70.0 11.9 19.0 R0:45 12 260 75000 AS READ 69.6 10.3 17.7 11:00 19 260 75000 58.80 70.0 8.7 16.4 l

1:15 19 260 75000 58.80 70.3 9.8 18.1 1:30 19 260 75000 58.80 70.5 10.3 18.1

! 11:45 19 260 75000 58.80 70.5 10.3 17.2 l

2:00 19 260 61000 5.88 71.2 9.9 18.1 l

2:15 19 260 61000 0.59 71.4 11.2 19.3 2:30 19 260 61000 AS READ 71.6 9.4 17.0 12:45 19 260 61000 AS READ 71.8 7.8-14.3

$3:00 19 260 61000 AS READ 71.4 7.2 14.8 R 3:15 19 260 61000 AS READ 71.4 8.1 15.2 13:30 19 260 61000 AS READ 71.6 8.7 15.5 3:45 19 260 61000 AS READ 71.6 9.6 18.1 4:00 19 260 61000 AS READ 72.0 12.3 18.6 l

l

\\

LI

.I I

5-4 I

l HILLSTONE UNIT II 1993 EXERCISE TAGE. 2 OF 2 PAGES 06:18 11-SEP-1993 Wind Wind Wind I

Speed Wind Direction Direction Delta Delta 374' Direction 142' 374' Temp 142' Temp 374' (MPH) 33' (DEG)

(DEG)

(F)

(F) 06:00 20.4 124.1 139.7 145.0 1.30 1.60 6:15 20.6 124.6 139.1 147.7 1.10 1.80 6:30 24.1 135.6 146.7 151.7 1.30 1.80 6:45 24.6 142.7 150.2 157.9 1.30 1.80 07:00 25.1 150.8 159.8 163.0 1.30 1.40 g7:15 25.5 159.2 164.1 165.3 1.10 1.10 37:30 23.5 161.3 166.6 171.0 1.30 1.30 07:45 21.7 159.7 167.8 171.6 1.60 1.60 8:00 22.6 156.7 164.8 167.4 1.40 1.40 8:15 21.5 158.2 164.8 168.5 1.30 1.30 8:30 21.3 162.3 169.7 175.0 1.40 1.30 8:45 20.6 163.4 174.5 176.9 1.80 1.40 9:00 20.4 167.6 175.9 178.7 1.60 1.60 9:15 19.9 188.9 188.2 183.7 1.40 1.60 09:20 19.9 188.9 188.2 183.7 1.23 1.60 23.5 186.3 189.4 184.9 0.90 0.50 5)19:30 5 9:45 23.0 184.7 187.7 184.7 1.10 0.50 09:55 23.0 184.7 187.7 184.7 1.23 0.50 0:00 21.2 182.6 186.8 184.1 1.30 0.70 0:03 21.2 182.6 186.8 184.1 1.32 0.70 0:15 19.5 179.4 185.0 184.9 1.40 0.90 10:20 19.5 179.4 185.0 184.9 1.40 0.90 0:30 18.8 178.6 183.7 183.8 1.40 0.90 0:45 19.0 181.4 181.0 181.4 1.40 1.30 11:00 18.8 171.8 178.2 180.9 1.40 1.10 1:15 18.1 165.9 175.6 178.2 1.30 0.70

.1:30 19.0 171.7 181.1 180.8 0.90 0.50 1:45 20.4 181.3 186.9 187.1 1.10 0.50 2:00 19.9 187.9 193.0 187.0 0.70 0.50-2:15 21.5 183.6 189.6 186.4 0.50 0.50 2:30 21.3 167.0 178.6 182.5 0.00 0.50 12:45 18.4 162.9 170.5 178.8

-0.20 0.20 3:00 16.4 163.5 171.7 174.9 0.50 0.50 3:15 18.4 163.7 173.2 176.4 0.90 0.70 13:30 17.7 163.6 171.8 174.8 0.70 0.70 3:45 20.4 164.7 171.8 174.6 0.00 0.70

.4:00 22.8 179.0 184.8 181.5 0.20 0.20 I

I I

I 5-5 I

g I

I I

I V. DATA I

B. RADIOLOGICAL RELEASE l

DATA AND DOSE RATE

SUMMARY

.E I

I 3

I i

I I

I l

I-5 I-

I

'.j Millstono Unit il 1993 Exerciss Clock Noble Gas : Step NG i lodine ! Step 1 Time

' Rel. Rate Released i Ref. Rate Released j

3 (Ci/Sec)

(Curies)

! (Ci/Sec)

(Curies) i 7iOO~

^

~

O'E60E4 00 0 0.00E + 00 e

l 8:00 0 0.00E + 00 0: 0.00E + 00 1

9:00 0 0.00E+ 00

0. 0.00E + 00.

f 10:00.

0 0.00E + 00 0 0.00E + 00 5000 4.50E + 06 O.015 1.35E + 01.

l 11:00 O.015 1.35E + 01 11:15 5000 4.50E + 06 i

13 0 5000 4.50E + OS t

0.015 1.35E + 01 i

11:45 5000 4.50E + 06 0.015 1.35E + 01 l

12:00 500 4.50E+ 05 0.0015 1.35E + 00

)

i 12:15 50,4.50E + 04_

0.000,15 1.35E41 0 0.00E+ 00 12:30 0 0.00E+ 00 12:45 O. 0.00E + 00 -

0 O.00E + 00 13:00 0 0.00E + 00 0 0.00E + 00 13:15 0 0.00E + 00 0 0.OOE + 00 l

13:30 0 0.00E + 00 0 0.00E + 00 l

j Total 1.85E + 07 Total 5.55E + 01 s

lI Noble Gas Release Rate 5000 g

E 4000 o

3000 I

E

$ 2000 1000 i

O

_M e

i aaaaseawae8

ans

~

n n

n s

e e

o I

lodine Release Rate I

0.016 o

4 0.014 3 0.012

. 0.01 I

O.008 ge 0.006 ---- - ------

l 0.004 g

m2 g

aaaaae8 a;8 ae8 e

2 e

e

=

Clock Time I

5-6 I

1

1 4

Millstona Unit 111993 Exercisa a

1 Stack to Stack Hi Stack Noble !

Noble CTMT i

Flow i

Gas Gas l

High J

! Range Range

3 Clock Monitor Monitor Rate Available ! In CTMT 1

! Range (CFM) j (Curies)

(Curies) l (R/hr) j i

_ Time j (CPS). (uCi/cc) !

4 i

j i

i i

h i

1 j

7:00 j 6.00E + 00 1.30E43 170000 9.13E4 08 0

IO.00E + 00 8:00 t 6.00E + 00 1.30E43.

170000 4.73E + 08; O

!O.00E + 00 3

ll 9:00

6.00E + 00 1.30E-03 170000 4.4E + 08 O'

10.00E + 00 l5 9:55

_6.00E + 00' 1.30E43! 170000:4.05E + 08 ' 2.71 E + 06 :

11.00E + 03 i

10:03

! 6.OOE + 00_ 1.30E-03 J 170000 4.05E+ 08 2.03E + 08.

! 7.50E + 04_

{g 11:00

'OFF HI

! 5.88E + Ol i 170000 4.05E + 08 ' 2.03E+ 08 i 7.50E + 04

~

11:15

.OFF HI

!5.88E + 01 170000 3.83E + 08.1.92E + 08

6.13E + 04 l

lg l

11:30

.0FF HI

' 5.88E + 01 170000. 3.83E + 08 1.92E + 08 6.13E + 04 i

11:45 OFF HI

! 5.88E + 01 = 170000l 3.83E + 0W~92E + 08

- 6.13 E + 04' 12:00 OFF HI

5.88E + 00 170000 ' 3.83E + 08 1.92E + 08

. 6.13E + 04 T

isu 12:15 OFF HI i 5.88E-01 ! 170000l 3.83E + 08 i-~92E + 08

> 6.13E + 04 12:30

' 6.00E + 00_ 1.30E-03 ) 170000 3.83E + 08 ' 1.92E + 08,

' 6.13E 4 04 i

12:45

6. ODE + 00 1.30E-03 170000 ' 3.83E + 08 1.92E + 08 -

6.13E + 04 l

13:00 6.00E + 00. 1.30E-03 170000 3.83E + 08 1.92E + 08

' 6.13E + 04 13:15 6.00E + 00 1.30E43 170000 3.03E + 08 - 1.92E + 08

' 6.13E + 04 i

i i

l Unit 1 Hi Range Stack Monitor i

j 6.OOE + 01 l

5.OOE + 01 lg g

4.00E + 01

g 3 3.00E + 01 l

8 l

2.00E + 01 e

1.00E + 01 l

0.00E + 00 M

h h

8 U

h$

h h$

8 e:

e e

e

~

=

Clock Time i

t

!I CTMT Hi Rad Monitor i

8.00E + 04 7.00E + 04 6.00E + 04 5.00E + 04 ig E 4.00E + 04 l

ig 3.OC E + 04 ------

2.00E + 04 i

1.00E + 04 '

0.00E + 00 i

h hh h

h hk k$

hk h$

3 e:

e

=

Clock Time i

I 5-7 i

!I f

Millstone 1993 Exercise R'd D"'l Summary RCS Leak Phase (07:25)

Comments 400/m ramp cpm 1 uCi/ml CTMT Gas

=

I 5.2e4/m ramp cpm 6.15e-3 uCi/ml CTMT Particulate

=

.1/m ramp mR/hr CTMT ARMS

=

As Read mR/hr CTMT Contact

=

As Read mR/hr 2" of steel piping CTMT Penetrations LOCA Phase (09:20)

Comments isolate as is epm Full Blow <'own CTMT Gas

=

I lsolate as is epm CTMT Particulate

=

step to 100 mR/hr CTMT ARMS

=

step to 10 mR/hr 2" of steel piping CTMT Penetrations

=

As Read mR/hr CTMT Contact

=

Core Damaoe Phase (10.03)

Comments r I Off Scale Hi epm inside Encl Bldg CTMT Gas

=

Off Scale Hi cpm insid, enel Bldg CTMT Particulate

=

I

=

7.5e4 R/hr 40 - 50 % Core Damage CTMT ARMS CTMT Penetrations

=

1e4 R/hr.

2" of steel piping

=

390 R/hr CTMT conc,1' Rad,2" steel -

Sump Suct. Contact I-CTMT Contact

=

180 mR/hr 50 mR/hr inside Enci Bldg

=

11 mR/hr 15' air +.25" steel Enct Bldg Contact

=

As Read mR/hr 15' air +1* conc +.25" steel Enct Bldg Contact CTMT Leak Phase (11:00)

Comments CTMT Gas

=

Off Scale Hi cpm 3000 cfm Leak rate Off Scale Hi epm CTMT Particulate

=

7.5e4 R/hr CTMT ARMS I

=

CTMT Contact

=

No Access mR/hr

=

No Access R/hr 2" of steel piping CTMT Penetrations

=

67 R/hr inside Enct Bldg I

=

53 R/hr 15' air +.25" steel Enct Bldg Contact 1.2 R/hr 15' air +1' conc +.25" steel Enct Bldg Contact

=

No Access R/hr CTMT conc,1' Rad,2" steel Sump Suct Contact I

=

42 - 26 mR/hr 0 - 20' from Enci Bldg inside Aux Bldg 100 R/hr CTMT Conc,1" steel

~ i EBFAS Duct

=

Ramp to 5000 R/hr 1% of CTMT lodines EBFAS Fitters

=-

Unit i Stack

=

58.8 uCi/cc 5000 Ci/sec NG I.

7 mR/hr Plume, 2' Conc +Re-Bar i

Inside other Buildings

=

5 R/hr Under Plume Centerline Peak On-site Outside

=

September 11,1993 5-8

e Millstone 1993 Exercise Rad Da', Summary g

=

3 R/hr Under Plume Centerline Peak Site Bound

=

1.3 R/hr Under Plume Centerline Peak 2-mile

=

370 mR/hr Under Plume Centerline Peak 5-mile I

170 mR/hr Under Plume Centerline Peak 10-mile

=

CTMT Restored Phase (12:00)

Comments CTMT Gas

=

Off Scale d epm Release Diminishes CTMT Particulate

=

Off Scale Hi cpm Until 12:30 CTMT ARMS

=

6.1e4 R/hr

,I' CTMT Contact

=

No Access mR/hr CTMT Penetrations

=

No Access R/hr 2" of steel piping

=

6.7 R/hr inside Enct Bldg I

=

6 R/hr 15' air +.25" steel Enci Bldg Contact

=

130 mR/hr 15' air +1' conc +.25" steel Encl Bldg Contact

=

No Access R/hr CTMT conc.1' Rad.2" steel Sump Suct Contact I

4.2 - 2.6 mR/hr 0 - 20' from Enci Bldg Aux Bldg

=

10.0 R/hr CTMT Conc,1" steel EBFAS Duct

=

5000 R/hr 1% of CTMT lodines EBFAS Fitters 5.8 uCi/cc 5000 Ci/see NG Unit i Stack

~I

=

As Read mR/hr 2' Conc +Re-Bar Inside Buildings

=

500 mR/hr Under Plume Centerline Peak On-site Outside I

=

300 mR/hr Under Plume Centerline Peak Site Bound Peak 2-mile

=

130 mR/hr Under Plume Centerline Peak 5-mile

=

37 mR/hr Under Plume Centerline

=

17 mR/hr Under Plume Centerline Peak 10-mile Release Ended Phase (12:30)

Comments

=

Off Scale H.

cpm Release Ended CTMT Gas

=

Off Scale Hi cpm CTMT Particulate

=

6.1e4 R/hr CTMT ARMS No Access mR/hr CTMT Contact

=

No Awess R/hr 2" of steel piping CTMT Penetrations

=

.67 R/hr Residual Activity Inside Enci Bldg 100 mR/hr 15' air +.25" steel I

Enct Bldg Contact

=

As Read R/hr 15' air +1' conc +.25" steel Enci Bldg Contact

=

No Access R/hr CTMT conc.1' Rad,2" steel Sump Suct Contact

=

As Read mR/hr 0 - 20' from Enct Bldg Aux Bldg

=

I, 100 mR/hr CTMT Conc,1" steel EBFAS Duct

=

5000 R/hr 1% of CTMT lodines EBFAS Fitters

=

As Read uCi/cc 5000 Ci/see NG Unit i Stack

=

As Read mR/hr 2' Conc +Re-Bar Inside Buildings

=

As Read mR/hr Under Plume Centerline Peak On-site Outside j

Peak Site Bound

=

As Read mR/hr Under Plume Centerline As Read mR/hr Under Plume Centerline 3-Peak 2-mile

=

3 mR/hr Under Plume Centerline Peak S-mile 1.5 mR/hr Under Plume Centerline Peak 10-mile

=

September 12,1993 5-9 I

.I

.I I

V. DATA

I C. IN PLANT RADIOLOGICAL lI DATA I

!I i

i, i

i 5

i.

I

-I 1

-I i

I I

I B:

i

M M-M W-W M

M M

M m

m mm me Millstons Unit 111993 Ex:rcisa Indoor Rad D:ta

_ p g

Time

. Time Time Time Time

'n

Osti & ti contioi Room io m a mr_

As READ AS RtAD

[_

AS DEAD

~

~As htAD '

~

.1 unit i s'ii 6Sc ~~~;

A.ndD_

_ 5o mamr' As ntAo 7 ~ 1 ~ ~~1ZlaiEdo i-

~

AsntAo

~

- - ~ ~ 5htAs _ ~.

^ imnmr j_ _

~

~s~nEAD~

' AS' READ [,1, _. [~ 1T[A5i

~

~ Unii ni contioi. Room A

- ~ swurz: Z

_ ' Unii ni Osc;7

_ _. _ Asado;;1. _

is mnm, e ne w

_ _. 1 As atAo

~

A

~ ~ ao - '.

_Z1so~mnm, ~

. _. 1 -near' - ~~

~-- AsacA6-

_~

. z. -As ntAo"

' nae -

As nt

~ AP

~~

~

,As ad(( _

~ ~ '5m's

_ _, _ 50 mRMi' _ _ _

~~ ' 5mRMr_1[

, _[RtAD[~"~

~~

S

~ 1 2 504;Z T

' ~sirid:E ~

._ _E sa s:

7 simn+i~

_ _ i a mril -~

_1Aiirsb 1_

.. S nS 1 _.. E -

iisns6 71_ ~

3mnmE

~ - ~

s mamin

_ AsntA671.

_ 7 ens 5:17 7

g, g

3,

~-

~ ~~-

. ~ T :: :..

7 r : ^'. :TTT.' T r~:...

T'...

t'.

NOTE - ALL DOSE RATES PRESENTED HERE ARE DUE TO PLUME StHNE ONLY. ALL AIR SAMPLES TAKEN ONSITE WILL RESULT IN NO NET POSITIVE RADIOACTIVITY.

m M

M M

M-MILLSTONE UNIT 111993 EXERCISE RMS DATA PAGE 81 Nntmal Ahrm Mrpest M

RAWor Readeg SWorse New 0

Loede leRarve Ht Reeve U*ste Shpere; 100% PWR (U%l 10r>% PWR (0%)

ON OFFS ARM CTMi HI REGE RM 8240 CTMi DLDG 14V 1

1 ODE +08 Rihr NONE OF F LOW 5Rh e.RM CTMT HI RANGE AM 8241 CTMT BLOG 146*

1 100E +08 Rh NONE OFF LOW 5R4 VPt MAN ST ACM GAS HI RNG rut BASE OF StACM 01 100E +06 uC*e Sheldad to 3 uCec 1E-f uCvec VP2 ST ACM GAS Hi RNG 8 tGOA B 21 SWGR RM 311r 100E 03 100E +05 uC*c 7 LEAD OFF LOW 2uC*e WG E10W DOWN RM 4252 AUX BLUG 1er 10 100E *06 com 5" LEAD 1000 eum 4 500 epm UE MON AM $099 TURO BLDG 3t'6" to 100E+06 epm NONE 100 com 200 com "ASL MONS 42004 EAST PEN ROOM 0 01 100E *04 R4 NONE OFFL.OW 03 Rh

93. MON 3 42000 EAST FTN ROOM 0 01 100E *04 Rh NONE OFF LOW 03 f0ft MSL MONS 42u0C WEST fTN ROOM 0 01 100E *04 R.h NONE OFF LOW 03 R4r cQ1 LED FUEL LE TDOWN RMr2A AUM BLOG 14r 10 100E +06 com TLEAD 2 000 cem 10dicom VP2 ST ACM GAS NORM RNG RV8132R 38'6" E PEN RM 10 100E *06 rpm SNeldad 40 eom 500 epm U1

[

Temo Time Temo Time Tm Trne Teme im Tm Pnor 70 7 25 7 25 8 20 9 20 10 03 11 00 1200 12 30 AF TER 12 30 Wnder Morder E ver4 Ever4 E vert E vert E vant Everd Eve 4 E verd Everd Name ID 100 % Povme 200 gum Inak 4 Inp Ltme t4 gewer LBLOCA Core Damage CTMt Fadure CTMT FHrod R*ea=e Stopped Freiof Dnti ON OFIS MIM. CTM T HI RANGE RM 8240 OFF LOW romped to 76000 7.60E+04 8.10E +04

^NM CTMT HIRANGE RM 8241 OFF LOW remewf to 75000 760E+04 0.10E+04 MPt MAIN STACM GAS HI RNG rut 100E43 888E+01 884E*00 1.30E43 1.30E43 MP2 STACM GAS HI RNG 8 tA8A B OFF LOW St., fu.OW DOWN RM 4262 1000 SJAE MON RM $099 100 NOPOWER VR MONS 4299A OFF LOW 8 ODE 42

8. TOE *01 8 70E+00 8 TOE 41 8 TOE 41 MSL MONS 4290s OFF LOW 8 00E42 870E*01 8 F0E*00 8 70E41

8. TOE 41 VR MONS 4290C OFF LOW 8 00E 42 8 70E*01 870E+00 9.70E41 0.70E41 rallED FUEL LETDOWN RV202A 2000 NO POWER VP2 STACM GAS NOfM RNG RMR1378 40 180E*05 OFF H6 00 NOT PROVOE VALUES UNTIL THE EVENT HAS OCCURED F THE DRt L IS RUNNWG LATE CONtWUE WfTH LAST READNG F DRILL IS AHE AD OF SCHEDULE JUMP TO THE EVENT THAT HAS OCCURED AND PROYtDE THE CORRESPONDWG VALUES

m.m W

Mm m

m m

M M

m MILLSTONE UNIT 111993 EXERCISE RMS DATA 0 "83 PAGE F2 Normal Ainrm MoMrw Myser Monnor Raarjiry Se* poet Name O

toesdort le Ranoo HiAnnas Units Sheerg 100% PWR (0%)

1001 PWR (0%)

NOT ON Orts MP2 ST ACM PARTICUt ATE RM 8132A 3Er6*E FTN RM to 400E+06 erm She W 30 epm 3 000 com CC$A. CONTROL. ROOM

'U#4011 490 V SWGR RM 10 100E *06 cpm NONE 20 epm 100 r pm CAM. FUEL MANDt.NG RMS 148iA E PEN RM 366" 10 100E *M cpm NONE 200 com 400 eTvn

";AM. F UEL HANDI NG RMG1450 E PEN RM 386" 100E *01 100E *06 cpm NONE 60 epm 800 com CAM RADWSASTE VENTS RM 8434 A AUK BLOG 14 6*

10 100E*06 cpm NONE 200 epm 2 500 cem CAM - RADWSASTE VENTS RM 84348 AUX MDG 1415" t0 100E *06 epm NONE 20 epm 100 erm CAM RADWSASTE VENTS RM 890T W PEN RM -28r8"

0 100E *M epm NONE fiO0 com 1200 epm CAM RADWSASTE VENTS RM 4908 AUX BtDG 14'6" 10 100E *06 epm NONE 300 erm 12 000 rpm CAM - RADWSAS TE VE NTS RM 8999 RAD F AN ROOM 10 100E +06 com NONE 200 com 8 000 com CONTANMENT AA PART RM 8123A ENCLOS OLOG to 100E +06 epm NONE 5 0tm erm T0 000 cem CONT AINMENT AH GAS RM 81239 ENCLOS BLOG 10 100E *06 com NONE 1000 com TO.000 cpm CCNTAfNMENT AA PART RM 8262A ENCLOS HLDG 10 100E *06 epm NONE 6 000 epm 70 000 etm CONTANMENT AR GAS p*.182628 ENCLOS BLDG 10 100E *06 epm NONE 30ncepm T0 0ic eem

?

o M

Trne Time Time Time Tsme Time Time Time Tirre Pnor TO T 25 T 25 8 20 9 20 10 03 11 00 12 00 12 30 AFTER 12 30 Moretor Rdor E vert E vert E mnt E vert E wart E vent Evert Event E vert Name D

100 % Power 200 gem ipsk 8 tnp tem cd omver LBLOCA Core Demnon CTMT Fn' hse CTMT Fmed Rele==a Storrad ErvJ et Ddil NOT ON Orts MP2 STACM PARTICULATE AM- *lA 30 160E+09 OFF H1 CAM. CONTROL ROOM RM-1 20 2.10E +04 2.10E+03 20 CAM FUEL.HANDlNG R8 4

200 NO POWER CAM FUEt HANDLNG A

A 800E*01 NO POWER CAM RADWSASTE VENTS RM 84344 200 7.90E+04 2 00E *02 CAM. RADWSASTE VE NTS RM 44340 20 NO POWER CC$A. RADWSASTE VENTS RM 899T 900 160E+05 OFF HI a

CAM.RADWSASTE VENTS RM.8906 300 NO POWER CC# - RADWSASTE VENTS RM 8999 200 2.10E +04 2 00E+02 CC:4TANUENT AIR PART RM 8123A 6000 8 2o4/m ramp OFF N1 OFF HI CONTAINMENT AIR GAS RM 61230 1000 400rm ramp 4 00E*04 OFF HI CONTANMENT AIR PART RM 8262A 8000

$2e4/mramp OFF H1 OFF Hi CONTA4NMENT A!R GAS RM 8262R 3000 400/m esmo 4 60E+04 OFF Hf DO NOT SHOVOE VALUES UNTil THE EVENT HAS OCCURED fF THE DR!LL IS RUNNNG LATE CONTNUE WITH LAST READING F DRILL IS AHEAD GF SCHEDULE JUMP TO THE EVENT THAT "AS OCCURED AN OJRRESPONDING VALUES

m m

M M-M M

M M

M m

M -m m

M M -

.M-MILLSTONE UNIT !! 1993 EXERCISE RMS DATA

"O PAGE23 NormW Alym W'*w Mo'*ir MorWor Ren$ng Se port a

W ID LormW to Rence M Renos UrWs Shed$ng 100% F"#R 10%)

100% PWR (0%)

NOT ON OFIS O R VENT NTAKE RM 9790A 0 AUX BtDG 386*

01 100E*04 mRN NONE Ce F LOW i f'Atw WQSTE GAS MON RM 9n95 AUX BLOG -2F to i txt +0s com 3"tEAD 300 cpm e00 epm rQILE D FUEL LETDOWN RM 202 AUX OLOG 146" 10 10'E +06 com 3 LEAD soOnoepm 10 6 com CLEQNLc WASTE EFF RM 9049 AUX OtDG -2F6" 100E +01 100E*0 F erm SHIELDED 7 000 rpm 14 000 cem AERQTED LO WASTE EFF 9 9 9116 AUX BtDG -256" f) 100E *07 com SHIELDED 10 0nc epm 20 000 cem WG OLOWDOWN TRF ATMFNt RM 4245 AUX OLOG 14 6" 10 100E *07 cpm

$* LEAD OOS

$xNORN RECCW RM 6038 AUX OLOG -25'6" 10 100E +06 com 5" LEAD 600erm 1200 ecm COND RECOVERv RM 9327 AUX Br_DG -2F8" 10 1 OnE +06 epm e r LE AD 600 epm 4Onoerm ARM - CTMNT HATCH RM F800 CTMT OLOG 3K6*

O1 10nE +04 mRev NONE 30mReiv 12) 60 mRav (5)

ARM. CT MNT RE FUEL MACH RM Fe91 CTVT BLOG 38'6" 01 10nE *04 mRW NONE 112 mR+v (20) 225 mRh (en)

MEd. R.XR ACCFSS RM F892 AUX BtDG 141" 01 1Olt+04 mRN NONE 4 mR+v 150 mRN AR A CHG PMP HALL RM 7804 AUM BtDG 25G" 01 1 Ort +04 mRW NONE 1 mR+v 150 mRihr Y.-

Time Time Time irma Tn,o Time Time Time Time Pncr TO T 25 7 25 8 20 9 20 10 03 1100 12 00 17 30 AFTER 12 30 Morvtcr Wnetor Evad E verd E ved E ved e vert Evert E ver*

E va t Evant Name ID itD % Power 200 apm inek & inn toss of power LBLOCA Ctwo Damegn CTVT Felure CTVT Finant Raleen Stopped Eruf of Dnn NOT ON Orts 0H VENT INTAME RM 9799A B OFF LOW 7 00E +00 OFF LO

-e WQSTE GAS MON RM 9005 300 rQR.ED FUEL LETDOWN RM 202 80000 NO POWER CLEANLO WASTE EFF RM 9049 TOOE+03 210E *04 7 00E *03 AERATED LO WASTE EFF RM 91t6 10000 21000 10000 VG OLOWDOWN TRE ATMENT RM 4245 OUT OF SERV RBCC#

RM 6038 800 NO POWER COND RECOVERY RM 9327 800 com NO POWER ARM-CTMNT HATCH RM Te90 30 NO POWER ARM - CTMNT REFUEL MACH RM F891 112 20 e.1/m temp step to 100 OFF Hi ARM. RXR ACCESS RM F802 0.4 f

04 ARM - CHG PMP HALL RM Feg4 1

NO POWER DO NOT PROVIDE VALUES UNTL THE EVENT HAS OCCURED F THE DRILL IS RUNNNG LATE CONTINUE WITH LAST RE ADING F DRILL IS AHEAD OF SCHEDULE JUMP TO THE EVENT THAT 4AS OCCURED AND PRov!DE THE CORRESPONONG VALUES

m M

M M

m W

W W

W

.m M

M M

M M ~m m

MILLSTONE UNIT 111993 EXERCISE RMS DATA

"s3 pac 4 u termal Ainrm McMor Morttrw McMor Roehg Se*pont Nave 10 Loceben le Ranoo Hi Rnry UMs Shmid+rg 100% PWR (0%)

ttc% PWR (0%)

NOT ON OFlS mW NONE 2WW 25mRh UtM PRIM SAMPLE ROOM RM T895 AUX OLOG 14 6" 01 100E +04 r

ARM. RADWASTE PROCE SS RM F996 AUX OLOG -25T 01 100E+04 mRh NONE 1mRW 25 mRh ARM-AUX BLOG AERATED RM 7897 AUX BLDG" 45'6' 01 100E *04 rnRN NONE SmRW 50 mR/hr ARM. CONTROL ROOM RM T890 C R BLOG 38'6*

100E41 100E +04 RAW NONE 1mRh 2mRh ARM e AUX BLDG DRUMNG RM 9813 AUX BLOG -45W 10 100E*06 mRN

'NONE 50mRW 200 mRh ARM - SF POOL SW RM 8139 FUEL OLDG 38'6" 01 100E +04 mRN NONE 5 reAltw 50mRh ARM - SF POOL NW RM 8142 FUEL OLOG 387 01 1 OrX +04 mRh NONE 1mRh 50 mRh ARM SF POOL SE RM eisT FUEL OLOG 3Lr8" 01 100E *04 mRh NONE 5 mRW 50 rnRh ARM - SF POOL NE RM 0156 FUEL BLOG 38'6" 01 100E *04 mRN NONE 1mRh 50 mRW Y

Tm inne Trme im Twne Tane Time few Trne Pnor TO T 25 7 25 8 20 9 20 10 03 11 00 12 00 12 30 AFTER 12 30 McMor Mormor Evert Evert Evwt Eved E vert E vert Evert E vert E vert Name C

100 % Powee 200 pm leak 8 Inp less of power LBLOCA Core Damage CTUT f eture CTMT Fmed Relem== Shtred End of Dr4 NOT ON OFIS ARM. PRiu SAMPLE ROOM RM F995 2

7.00E+00 2 00E+00 ARM. RADWASTE PROCESS RM T896 1

NOPOWER ARM - AUX BLDG AERATED RM 7897 6

2 00E*01 5 0cE+00 ARM. CONTROL ROOM RM T899 1.00E+00 NO POWER ARM AUX BLDG DRUMNG RM 9813 50 80 60 ARM.SF POOL SW RM 8139 05 7

05 ARM. SF POOL NW RM B142 1

7 1

ARM. SF POOL SE RM 8157 05 7.00E +00 S COE41 ARM SF POOL NE RM 8156 01 7 00E+00 100E41 DO NOT PROVIDE VALUES UNTil THE EVENT HAS OCCURED F THE DRILL r3 RUNN NG L ATF CONTINUE WITH LAST RE ADING F DRILL IS AHE AD OF SCHEDULE JUMP TO THE EVENT THAT HAS OCCURED AND PROVIDE THE CORRESPONDINGVALUES '

. l MILLSTONE NUCLEAR POWER STATION UNIT 2 OUTSIDE AREAS

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COMMENTS 19mu

< c.s ME/FJt OUMIrr arAS

'7:00 Aa Tls.d Fi ve. A b ov<.

it:00 S e e.

3 12 00 Va\\ue.: in Fiforu Akeve. X.1 I

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i

8s v.w te m 3 -.. A x.or IJ 33o As T(c.,d I

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MILLSTONE NUCLEAR POWER STATION UNIT 2 14'6 ENCLOSURE BU!LD!NG

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GENERAL AREA DOSE RATES (mr/hr)

COMMalTS

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_7; Ob At hee d

,4 4 heegs. 10: 0 3 I?O r:1R/L ne,r dT MC 'I I/ :00 67 R lle. n :oo 67 RIL _13:30 , G7 R I -k

l' t

II:oo HICH AIR 60 Rive ACTIVITY I IL

. I. _ MILLSTONE NUCLEAR POWER STATION UNIT 2 38'6 AUX BLDG SFP -;l .>===8 I. O E L r I m am.use .u4m / ) I 3 UFPER row. razzum. pg,,g j:, swet 3 5 4' f f I e' *R ] [ j! I I)i Po%'i"Le*"." L I i n F, g .3 i M4*!57--____-M'*, 1+3 m .b2"9 4.., a e 1 4 h.. ~-- 3 r-- W , I$~*D ,' ' 4& J L = ~ ...T _ I'l l T-Y. 'O e wtsT e o j ~ EA8* ~ N$1 ( 'h I j ToH { ( M)"' ,O i' 'n r + I-i ' I) } l nu4m us r l I. sm> t TIME GENERAL AREA" DOSE' RATES (mr/hr) COMMENTS .ee- - u c.ux w.we orwar,s I 7:oo As Re.d tw Au au I 120valb to 6 d + M i-f b ~it.. m s so: 03 w cm7~. All else As hd ___ll:oo 67 R ik /o suf <+ m.rf 4 7eo o. 42 m7/A in Avie 'M A. cTwr d,... m 3 -h.36 47/k me' oww. All elseis 7e R/k nLw At Reul. w e a, Ja' o o 6,7 R l a i,, B u t v v a r b. Vee

3. All elst is-As Deacl.

~ 12: 2o ,0 / w /A in P,4 y ts f m,. h m All che Ar R,.d o .I-o i II : 00 HIG H AlR sorus ACTIVITY Irv ?GW R00mS Q EfUt"L 6LD6 5-17 No Mn sontoE ACTIv1TY ELSE toHERE I4LL. DA Y. I

yy y I MILLSTONE NUCLEAR POWER STATION UNIT 2 RR ACCESS 1 14'6 EAST 4 g 3 j g ~L ~l L a-00 0 OO C f l ii !! O uiO i I g 8 D'O A D'G,, f { i j ER ACCE33 k O k Oi I C, ,s. s. s. s s. v L- - 9 s. s o s. s o u 5 000 s .g s. s

s.

v !? P? @ E 3BJ@ j E q l l = au-mq s I i = nw s g m i 1 I ii MH l E i EtWrMI / lssewai4El 5 I @ CC" I i;..:x=:.g = = = = E um; i un Ii = =- c=a i b ~ = ' EI'l O j j i l; ( ) E g> eux. l TIME GENERAL AREA DOSE HATES (mr/hr) COMMENTS mcw < or s== orsun ow.

3. u w = cwem nu m aw mocw 1:00 4s % el k edt a m s II:oo noo RIL es cod.ck w;4L eSFAS dved wk. 5000 em co,4chuith Fd%.

'l 12 :00 so alk n eaA.4 wo+\\ CBFAS due+ wo<k. s,oco en ceAw.+ wdL Filters 12 0 0 noo mil l% e codae+ w,4L ESTM dec{- week. s, coo en cad wdl RNert. I No 41RBORNE ACTWITY ALL DAV I 4 4

MILLSTONE NUCLEAR POWER STATION UNIT 2 14'8 AUX BUILD!NG WEST 1 = l _r s c~ 14'6 AUX BUILDING WEST j, ac 4 x w as m r. I 3 j g a w

mm, _% O l

I, iwh C .o i mi _ _ _, j s e m ?" m . q- -2 g j ,te - -a e .a = [ = au-ms N e t N N l **ll *^l $..$,s$$$.$: . i. m = .s o i 1 2 O l l l i. 4 - E.. ~ l as a TIME I-GENERAL AREA DOSE RATES (mr/hr) COMMENTS i < o s - e uam rux ws wssr corar:. Ansis orrn l ':00 A s. %d k M\\ an.1 II:00 42 m RIL zn Ave sids vee < C,d Wds. ' props +o a6 mtlk 30' qwey. g' A1) eb. u ~/ m P IL ab A r Re ed.- a:oo A.s m,cl im All geet No AIRBoRME Ac71urry A L L 'D A tr. - I S-19 I-h

I MILLSTONE NUCLEAR POWER STATION UNIT 2 l 14'6 AUX BUILDING EAST ^ -5' EAST PEN 'I \\ O% 4 e exsT PCN B &E ll R C' j o w C.. I-2 e I _N _ g -N 4 I m vs EAST b j m l 9$ 'e hl L h h 7 s ~E a 5\\ p .E.- we usr ecN E f fR -uu o O O L-0 g H i N EEF U Uy i s i lg B ( l F M . H 'x l'% WDb ..o _ m' N 8E N E i ___ s c i b i T V.E GENERAL AREA DOSE RATES (mr/hr) COMMENTS lrm s 0.6 -5 MRM m Bur.Dr4 W8 EAST. W6 EAST PEN, APC-8 O EAST PEN GUGW, ARMB 7:oo As Re.d A gil arcas to: o*5 Sto m Rik & Cor4 4 UM+ 9em %~5 skav cTwsT. All elSc is As Revd g si:oo 67 R /A t-C=34

Mrf % L.-1,

@ m ? / L tr A u g N c.< i crivrr deonen, t, at AIL,so%,a. All else fs 2 m RIJu &c-as pad. b.'7 91L" ~,i, _ as-f a. taa,+ % %-s, C)ll else ss As %d g u:oo 5 p:so ,67 R IL is F.W-Y tou4 L h,er. All else is As b d. l sa : oo, H)GH 4lnsonrJe AcTIvsTY In PEtJ Woorv)s.+ ENch. SLD&. 'i ND AIR SORNE ACTWITV fd!'EWH E R E A M. D A Y. I 1

l 'FlLLSTONE NUCLEAR POWER STATION UNIT 2 I -5 AUX BUILDING EAST e --ee.e-g y 3 R r w oo r= r e O D uw /5 00 5 5

ST l

l es encm.w= = ( ) .I C_________. _ _ _ _.:5

34 ______

.-________..E ~ -g 10 v i-0 !1 R I

ii I

E EB n'ai W- + ,I ' g c~ eiie l E I Y j l Y HEY l o 4 I C s I

l c:==c 1.

i C3rDA i n -E

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.3 % i l l t l 8 l s i o g TIME GENERAL AREA DOSE RAMS (mr/hr) COMMENTS PNe t < f.10 s/Ausa CTr# mat ARFag: aio. 500 AtAma OMERAL AAEA N Arw NNTRATOR RM Am ReAST #M 7:oo As Oe,d c., Att one n :o= <<a mall a Avv. 2\\ds. ve., crm7 dro. ore 6 Ao m?/L Jobuav. l-All ciu is 7 m R/L a6ve GeRd. e c:oo A3 A.cl i, /411 aer. I t tJo A1R sowE AcTIVsTY All "DA Y I I E b-d l l

MILLSTONE NUCLEAR POWER STATION UNIT 2 I: -5 AUX BUILDING WEST l I taw MON & MC YAfx Rhr s H VdST PEN

7,9 m

) bf I P 5"*J l "L' O E .a"t VCT /' = D, -p = D. E I,j $ o .w 4 h l y q cy tnoo 2 '110P lwh aus h -O h 0 g g () cji e,'

l s

m I STAR '

2 S

I: [ l M 4l t

=:-_

Et f. e ~ g,y 8 = C I l o =;=J 'JJJJ $ CC$ I 'JJJJ c c i S p'JJJyg j m >JJJJ I ~, f = 'JJJ E 'JJJ tJJJ = s e r3 rL._. '{o e 1 TME GENERAL AREA DOSE RATES (mr/hr) COMMENTS eC/J. <f 5 - 15 MRW GES. TRAL AAEAS; 15 - SC MR/HR OFNEMAL AREA N WEST PfN 7'00 Mg Qg d (% Q){ pfggy, so: 01 sto a Rik plans crMT well. All else As Reed l n:oo 67 n/L c. to,+ Pe n. R.. . %7 m R/L cn Aux BIA. n en )- c rtw1 dmoen, h a s en R l.t-A o'asu a s. All eist is 7 >?lL a% As t?e<d - 12:co 63 n 15 T, u kA Gon. AlIelse ir As 9e,cl. I I:.:3 o A7_ 9 i L,;, ulo~b L L% . all e lse a As (L,el -l n :oo 14IGH Ata BoRtvE ACTIVITY tw PEN R00ntS 4 TNCL. BL DG: l 10 0 Alf? Bon u E-ACTIvn[r' EME WHERE I

l MILLSTONE NUCLEAR POWER STATION UNIT 2 -25 AUX BUILDING EAST wi++g 6g W-n. I dz rn ,3 n b - - ----- e O Ed s c -b El } kw h e g l 5 r ~ O E [ f 7 4 r1 rig-Es - - x _ _- l /, gn:L_S=-= i 00 b EED F-* '- "* "+' L = ===., I ~~- tra ~ ~. ~g -1 C:s - ---------- 3 [. wa ntcar m gI

t k,mm l

(_,;

n

~- I 85 / f I l TIVE GENERAL AREA DOSE RATES (mr/hr) COMMErfrS I D"thi <0.5 - 1D MF./}0t GSTAAL AIKAS. l 7:00 As Re,cl to All anos. II:00 42 m g 1.L c, %.Wa,uw crorr dren>;m -fs 3L m? lam 90'mway. s~ Pll else 18 7.mnIL nbon As Rd.' " I ' lL: o O 4s Gead th All prens. No AtR BORNE ()cTIVITY ALL 'DA Y I I 5 23

l

MILLSTONE NUCLEAR POWER STATION UNIT 2 i

f -25 AUX BUILDING WEST _l gp 5 JJ w $961$,J1E JI i EMEl O. l r = D l@ Cr = 1

g oi=n is Oto FUMFS i

I am.mw I. 0 0 morg O 4 m t-se E j. ) i m vr ecx g = _i=_..w_=> l 0 Jj 8

E

== s i s.,. sessD

==} i i 3.s 3,3. .s mu l \\ e) $$33: td s., s. ew m.m., i ) i "J T I m e E t i I' i TME GENERAL AREA DOSE RATES (mr/hr) COMMENTS ns w. e.s - ie mm armru Aro.s: in-se mm cetra are w ewous es ora

/ ;oo As Reed tw Q\\\\ avens.

10:03 180 m Rlk in Earf 4 Wst+ 9evs. Rocons ne<< GTMT. All esIe is As Re<cl l 'l. ll:oo C T R I k in e<s + + wa + Pe-ko ms. 42 m R IL, ,u a n sid3 cee< cTmr ar prin3 in as ir,Ql.fr ao ' awe v'. All else Is 7m Rlk sha As Re.e d.

g ta.:oo b.7 RIL, a 2.,-l e+ Lie >+ (7e.,. 0 on. All else. ts As Ge,d.

E n:3 o ,67 Rico c, e<,f 4 user / P c.,. R.. -,. All eist is -As Ae J. .t n :00 HIGH A 6 It BoR10 5 ACTWITY IN PE W ROorvu' 4 E N o. DL W sa tuo AtR BoRAIS ACTIvtTV ELSWER & ALL DA Y. I'

MILLSTONE NUCLEAR POWER STATION UNIT 2 --45 AUX BUILDING I Il = _, h I ,_ u t.aos ..a s a= I e, = = u s = u g = D(" y = T =M(" .CL_. v. ,7 5 [ N Mb $ 1 h h. sM w" 9 % 5 ..'L .=====.r.:= s = u. _ _ c. _ _ :S> s

=

,.: 8 00 l l W" r.: 0 u y' I l m-nu .y.Q._ "J Z t me h5 "1 M_ i 5 / 3 <l g g3gy 4 'R = U; *;,"h".'.".**.?

dEUd:L.7,5 Uj

~ ~ E~~~~ ~ r; g "J e msm (ove rhead) Q, ,e p I h r# s" ,( -p 4H 3 E ~; .L.........1...y.. 2. l 5:" p B B

1 50 L'

= i mL brser ["""" I /=_ o t g g g( ~ n p m _. ] m g. ( 4- -5 mg 3 i s \\/ ..^ R ?=n a ~* I Tit /E GENERAL AREA DOSE RATES (mr/hn COMMENTS _mn .n m.ncrm e are I 7:oo As b d in m\\ arms. ll: o o 4a m ? IL in n u1. %. seer crm'r droppins +c ab n,P/k po'qwav. I All esle is '7 m R16 'above As Retl.~ ~ I;:oo 4s R e e el + All awAs. MD AIR BontvE Acrivtry ALL DAlf. I I i U-L U I

MILLSTONE NUCLEAR POWER STATION UNIT 2. CONTROL ROOM AREA I I u; .',2j,, I p t'X

n.

- -r; F b. / ~ ,.. '..~.. :.x (J,;c' _;>~---g....'...1,... p4 m . y-:

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' %%ljQQQ? yyyf&flly-ll Q E) llh(" Q ifj~ Q ^L4Q: q,. - 3 / f,;$;7 fC."' I"'M N f "l N / I C EOC4 amme CCMrt.TER I OOM K U.; OPS $WCCM CEG w ~':sc%p- .i gr.;,, WTROL ROOM Br1AZ f ...c..r:, u.-': ;,Y t RM-soit

wl;jes

;

-n 5'""5-r.;$;L ~f p T 8" b U.1 cowTsot Roou I f I I TIME GENERAL AREA DOSE RATES (mr/hr) COMMENTS tr:rM ee5 MP/H3 A L strvict FturtNG ALEAS 7:00 As Read in All acces. 7 m RI k ctl,on As (Jag d. 11 : 00 Ja.:oo Ar had N All avtasn il tJo Ale noRivE ACTIVITY ALL 'b A V k R ') A - l l 1 i

!I . MILLSTONE NUCLEAR POWER STATION UNIT 2 TURBINE BUILDING TB 1es TB 31'6 TB 54's ~ nn I Davu n U D**PO, Ilft 3 2 0 <l g v)v v O ) 4*'""^$

== 0 7 BBU

..u il O

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~ ~ 8 M-M' M M M M. M' M N M M M M M mN M M l Mill:tsno Unit 11 Em:rg:ncy Pl:n Ex;rci:o - 9/22/93 l l Site Area Dose Rate Map instructions l Instructions: Values listed for Iso-dose rate lines are approximate for the time period between 11:00 and 12:00. When located at an RMP use values from table only. For all other areas use linear interpolation between Iso-dose rate lines. For time period between 12:00 and 12:15 multiply Map Values X (0.1). For time period between 12:15 and 12:30 multiply Map values X (.01). For time period between 12:15 and end of exercise use AS READ readings.

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Mill:tona Unit 11 Em:rg:ncy PI:n Excrciso - 9/22/93 Radiological Data ON-SITE DOSE GUIDE Scenario Time: 11:00 - 11:15 .I SURVEY METER READINGS IODINE SAMPLE READINGS WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC I OPEN CLOSED CONC FILTER SAMPLE ( + 7) (y only) POINT mR/hr mR/hr epm cepm Ci/m**3 ccpm I 0. 0.00E+00 0. A 0.1 7.20E+02 7.20E+02 0. 0.00E+00 0. B 0.1 7.55E+02 7.55E+02 0. 0.00E+00 0. C 0.1 4.21E+01 4.21E+01 C 0.2 4.81E+00 4.81E+00 14526. O. 0.00E+00 0. I_ G 0.1 1.28E+01 1.28E+01 38556. O. 0.00E+00 0. H 0.1 1.05E+01 1.05E+01 31713. O. 0.00E+00 0. J 0.1 1.31E+01 1.31E+01 39525. O. 0.00E+00 D. I K 0.1 2.71E+01 2.71E+01 81529. O. 0.00E+00 0. P O.1 3 19E+01 3.19E+01 95772. O. 0.00E+00 0. Q 0.1 2.53E+01 2.53E+01 75991. D. 0.00E+00 0. R 0.1 5.22E+02 5.22E+02 0. 0.00E+00 0. I I I I I I I Notes: LLD for an RO-2A is 2.0 mR/hr ( <2. 0mR/hr= background) LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) I LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) I I s.23 I

Ll Millstone Unit 11 Emergency Plan Exercl:3 - 9/22/93 Radiological Data ON-SITE DOSE GUIDE Scenario Time: 11:15 - 11:30 SURVEY METER READTNGS IODINE SAMPLE READINGS WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC OPEN CLOSED CONC FILTER m SAMPLE (f + y) (y only) POINT mR/hr mR/hr cpm cepm Ci/m**3 'cepm 0. 0.00E+00 0. A 0.1 9.26E+02 9.26E+02 0. 0.00E+00 0. B 0.1 6.00E+02 6.00E+02 0. 0.00E+00 0. C 0.1 3.49E+01 3.49E+01 C 0.2 3.41E+00 3.41E+00 10337. O. 0.00E+00 0. i I G 0.1 1.21E+01 1.21E+01 36501. O. 0.00E+00 0. l r H 0.1 1.01E+01 1.01E+01 30351. O. 0.00E+00 D. J 0.1 1.27E+01 1.27E+01 3B218. O. 0.00E+00 0. I-- K 0.1 2.66E+01 2.66E+01 79780. O. 0.00E+00 0. a 0. 0.00E+00 0. P 0.1 3.34E+01 3.34E+01 Q 0.1 3.13E401 3.13E+01 93897. O. 0,00E+00 0. 0. 0.00E+00 0. R 0.1 6.97E+02 6.97E+02 I i I I I I I I Notes: LLD for an RO-2A is 2.0 mR/hr (<2.0mR/hr= background) LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) I LLD for an ASP-1 is 0.002 mR/hr ( < 0. 002mR/hr= background) I 1 5-34 I

Mill tona Unit 11 Emcrg:ncy PI:n Exarcira - 9/22/93 Radiological Data ON-SITE DOSE GUIDE Scenario Time: 11: 30 - 11:45 I SLTRVEY METER PEADINGS IODINE SAMPLE READINGS WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC I CONC FILTER OPEN CLOSED SAMPLE ( + y) (y only) POINT mR/hr mR/hr epm ecpm Ci/m**3 cepm I 0. 0.00E+00 0. A 0.1 6.88E+02 6.08E+02 0. 0.00E+00 0. B 0.1 7.05E+02 7.05E+02 0. 0.00E+00 0. C 0.1 3.85E+01 3.85E+01 C 0.2 4.34E+00 4.34E+00 13110. O. 0.00E+00 0. I G 0.1 1.18E+01 1.18E+01 35389. O. 0.00E+00 0. H 0.1 9.68E+00 9.6BE+00 29151. D. 0.00E+00 0. J 0.1 1.21E+01 1.21E+01 36451. O. 0.00E+00 0. I K 0.1 2.52E+01 2.52E+01 75672. O. 0.00E+00 C. P 0.1 2.96E+01 2.96E+01 BBB37. D. 0.00E+00 0. Q 0.1 2.34E+01 2.34E+01 70271. O. 0.00E+00 0. 0. 0.00E+00 0. R 0.1 4.96E+02 4.96E+02 I I I I I I I Notes: LLD for an RO-2A is

2. 0 mR/hr

(<2.0mR/hr= background) LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) 5 LLD for an ASP-1 is 0.002 mR/hr ( < 0. 0 02mR/hr= background) 8 'I s.2e I

Millstone Unit 11 Emergency Plan Exerciso - 9/22/93 Radiological Data ON-SITE DOSE GUIDE Scenario Time: 11:45 - 12:00 SURVEY METER READINGS IODINE SAMPLE READINGS I WINDOW WINDOW BACKGROUND SAMPLE 1-131 PARTIC OPEN CLOSED CONC-FILTER SAMPLE ( + y) (y only) POINT mR/hr mR/hr cpm cepm Ci/m**3 cepm 0. 0.00E+00 0. A 0.1 2.65E+02 2.65E+02 0. 0.00E+00 0. B 0.1 1.09E+03 1.09E+03 0, 0.00E+00 0. C 0.1 5.21E+01 5.21E+01 I C 0.2 8.80E+00 B.80E+00 26488. O. 0.00E+00 0. G 0.1 1.07E+01 1.07E+01 32122. O. 0.00E+00 0. H 0.1 8.53E+00 8.53E+00 25684. O. 0.00E+00 D. I J 0.1 1.05E+01 1.05E+01 31544. O. 0.00E+00 0. K 0.1 2.16E+01 2.16E+01 64955. O. 0.00E+00 0. P 0.1 2.12E+01 2.12E+01 63831. O. 0.00E+00 0. Q 0.1 1.09E+01 1.09E+01 32757. O. 0.00E+00 0. R 0.1 1.99E+02 1.99E+02 0. 0.00E+00 0. I I I I I-I g Notes: LLD for an RO-2A is 2.0 mR/hr ( <2. 0mR/hr= background) LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) 8 LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) I I 5-36 I

Millstone Unit 11 Emergency Plan Ex:rcizo - 9/22/93-Radiological Data ON-SITE DOSE GUIDE Scenario Time: 12:00 - 12:15 SURVEY METER READINGS IODINE SAMPLE READINGS { WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC I OPEN CLOSED CONC FILTER SAMPLE ( + y) (y only) POINT mR/hr mR/hr cpm cepm Ci/m**3 cepm A 0.1 2.5BE+01 2.5BE+01 77380. O. 0.00E+00 0. B 0.1 1.06E+02 1.06E+02 0. 0.00E+00 0. C 0.1 5.02E+00 5.02E+00 15160. O. 0.00E+00 0. C 0.2 8.37E-01 8.37E-01 2612. O. 0.00E+0D 0. .I G 0.1 1.02E+00 1.02E+00 3172. O. 0.00E+00 0. H 0.1 8.18E-01 8.18E-01 2554. O. 0.00E400 0. J 0.1 1.01E+00 1.01E+00 3121. O. 0.00E+00 0. I-K 0.1 2.09E+00 2.09E+00 6360. O. 0.00E+00 0. P 0.1 2.04E+00 2.04E+00 6221. O. 0.00E+00 0. Q 0.1 1.04E+00 1.04E+00 3213. O. 0.00E+00 0. R 0.1 1.94E+01 1.94E+01 58218. O. 0.00E+00 0. I I I I I I I Notes: LLD for an RO-2A is 2.0 mR/hr ( <2. 0mR/hr= background) l LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) I LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) .i I 5-37 I

E8 Millatena Unit 11 Emergancy Plan Exorciao - 9/22/93 Radiological Data g ON-SITE DOSE GUIDE Scenario Time: 12:15 - 12:30 .I SURVEY METER READINGS IODINE SAMPLE READINGS WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC I OPEN CLOSED CONC FILTER SAMPLE ( + y) (y only) POINT mR/hr mR/hr epm cepm Ci/m**3 cepm I. A 0.1 2.62E+00 2.62E+00 7963. O. 0.00E+00 D. B 0.1 9.51E+00 9.51E400 28642. O. 0.00E+00 0. C 0.1 4.48E-01 4.48E-01 1443. O. 0.00E+00 0. C 0.2 7.17E-02 7.17E-02 315. O. 0.00E+00 0. G 0.1 9.46E-02 9.46E-02 384. D. 0.00E+00 0. H 0.1 7.58E-02 7.58E-02 327 O. 0.00E+00 0. i J 0.1 9.35E-02 9.35E-02 380. O. 0.00E400 0. I K 0.1 1.94E-01 1.94E-01 682. O, 0.00E+00 0. P 0.1 1.93E-01 1.93E-01 679. O. 0.00E+00 0. Q 0.1 1.02E-01 1.02E-01 406. O. 0.00E+00 0. R 0.1 1.94E400 1.94E+00 5919. O. 0.00E+00 0. I ~ i I I I I Notes: LLD for an RO-2A is 2.0 mR/hr (<2.0mR/hr= background) l LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) 5 LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) I I me I

I I I V. DATA I E. OFF-SITE l RADIOLOGICAL DATA B !I r !ll l lE !I l ll II lI I I I I

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Mill;tona Unit 11 Em:rg:ncy PI:n Excrci23 - 9/22/93 Radiological Data I OFF-SITE DOSE GUIDE Scenario Time: 11:00 - 11:15 I SURVEY METER READINGS IODINE SAMPLE READINGS WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC I OPEN CLOSED CONC FILTER SAMPLE ( + y) (y only) POINT mR/hr mR/hr epm cepm Ci/m**3 cepm I 0. 1.10F-14 0. A 1.1 5.05E+02 2.52E+02 A 2.1 1.34E+02 6.72E+01 0. 8.82E-15 O. 0. 3.93E-12 2. A 2.2 2.87E+02 1.43E+02 A 3.1 1.90E+03 9.48E+02 12. 4.52E-10 182. A 3.2 1.24E+03 6.22E+02 42. 1.56E-09 630. A 4.1 9.77E+02 4.BBE+02 41. 1.53E-09 609. A 4.2 3.92E+02 1.96E+02 40. 1.50E-09 606. I A 6.1 7.12E-01 3.56E-01 1168. O. 6.05E-12 2. B 2.1 4.25E+01 4.25E+01 0. 0.00E+00 0. B 2.2 3.48E+00 3.48E+00 10542. O. 0.00E+00 0. I B 3.1 3.46E+00 3.46E+00 104B4. O. 0.00E+00 0. B 3.2 1.25h-02 1.25E-02 137. O. 0.00E+00 0. B 5.1 1.55E-01 1.55E-01 565. O. 0.00E+00 0. C 1.1 2.05E+01 2.05E+01 61651. O. 0.00E+00 0. C 1.2 5.51E+00 5.51E+00 16618. O. 0.00E+00 0. C 2.1 6.56E-02 6.56E-02 297. O. 0.00E+00 0. D 1.1 5.01E-02 5.01E-02 250. O. 0.00E+00 0. I E 1.1 4.64E-02 4.64E-02 239. O. 0.00E+00 0. O 2.1 7.37E-03 7.37E-03 122. O. 0.00E+00 0. R 2.1 1.04E+01 1.04E+01 31398. O. 0.00E+00 0. I R 2.2 4.66E-02 4.66E-02 240. O. 0.00E+00 0. R 3.1 4.18E-02 4.18E-02 225. O. 0.00E+00 0. R 4.1 1.82E-02 1.82E-02 155. O. 0.00E+00 0. I I I I Notes: LLD for an RO-2A is 2.0 mR/hr ( <2. 0mR/hr= background) LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) I g s.40 I

l Mill:tona Unit 11 Em rg:ncy Picn Excrciso - 9/22/93 l Radiological Dose Rate Map e I t jf F1-WB RATE '.MONTUI LLE \\ A F3-THY DOSE l LEDYAR5\\ l l i. F5-SECTORS g I 0W .c CROTON F6-MA JOR ROA DS .l EAST LY l.1E [. F l'. F8-POINTS [ \\ .g h l]I F9-TOWNS l \\ ~ ~ k' I F10-CET DOSE F11 - PR I NT ) ,Q ON O4 E F12-r ETURN { OLD LYME ) i },f, PR I t-JT I NG FISH S WB D RATE ~ I S Lp T: 1100-1115 M [ L ~ G > 50 uRem/hr se hc. > 1 mrem /hr PL y g 7 mammmen > 100 mrem /h > 1 Re m/hr K H summmma > 1O Rem /hr /, THIS IS A DRILL g I I e. I

I Millstone Unit 11 Em rg:ncy PI:n Ex:rci23 - 9/22/93 .l Total integrated Radiological Dose Map (For Use in Providing Player Plc Readings) / F1-WB RATE 4f F2-WB DOSE \\

MONrutLtE:

N ^ F3-THV DOSE \\ ,p ~ i [ LEDYARb\\ F5-SECTORS { s ( EAST LvME \\ " RD,C - F"7-MI NOR ROGDS g ((F F8-POI NTS h ITI F9-TOWNS p ~ \\ ~ .g l i \\ .- :-)- \\- F10-CET D05E -R N ( ON E / OLD LVME [f. PRI NTI NG INT WB DdSE FISH RS ISLA D T: 1100-1115 M C L _ y 2 mpen mec._ > 20 Mrem p I S LA ND sammum > 100 mrem > 1 Rem K H ammans > 5 Ren I l THIS IS A DRILL I I. sm lI

I Mill:tana Unit 11 Em rg:ncy PI:n Exercina - 9/22/93 Radiological Data OFF-SITE DOSE GUIDE Scenario Time: 11:15 - 11: 30 SURVEY METER READINGS IODINE SAMPLE READINGS WINDOW WIND')W BACKGROUND SAMPLE 1-131 PARTIC I OPEN CLOSED CONC FILTER y) (y only) EAMPLE ( + POINT mR/hr mR/hr cpm cepm Ci/m**3 cepm 0. 1.39E-13 0. A 1.1 8.40E+02 4.20E+02 0. 2.75E-13 0. A 2.1 2.06E+02 1.DiR+02 1. 3.08E-11 12. A 2.2 6.24E+02 3.12E+02 7. 2.53E-10 102. A 3.1 6.88E+02 3.44E+02 I 33. 1.27E-09 514. A 3.2 6.63E+02 3.32E+02 32. 1.22E-09 493. A 4.1 4.67E+02 2.33E+02 A 4.2 7.99E+02 3.99E+02 49. 1.89E-09 763. I A 6.1 3.92E+00 1.96E+00 5980. 2. 9.52E-11 38. A 6.2 5.1EE+02 2.59E+02 60. 2.33E-09 919. A 8.1 3.17E+02 1.58E+02 51. 1.98E-09 A 9.1 0.00E+00 0.00E+00 100. O. 5.65E-15 O. A10.2 2.77E-03 1.38E-03 104. O. 2.92E-14 367 B 2.1 2.29E+01 2.29E+01 68767. O. 0.00E+00 0. B 2.2 1.73E+00 1.73E+00 5290 0. 0.00E+00 0. I B 3.1 1.51E+00 1.51E+00 46.6. O. 0.00E+00 0. B 5.1 3.54E-02 3.54E-02 206. O. 0.00E+00 0. C 1.1 1.63E+01 1.63E+01 49121. O. 0.00E+00 0. I C 1.2 4.24E+00 4.24E+00 12811. O. 0.00E+00 C. C 2.1 4.57E-02 4.57E-02 237 O. 0.00E+00 0. D 1.1 4.20E-02 4.20E-02 226. O. 0.00E+00 0. I E 1.1 4.11E-02 4.11E-02 223. O. 0.00E+00 D. Q 2.1 9.69E-03 9.69E-03 129. O. 0.00E+00 0. R 2.1 1.57E+01 1.57E+01 47272. O. 0.00E+00 0. R 2.2 7.92E-02 7.92E-02 338. O. 0.00E+00 0. I R 3.1 1.02E-01 1.02E-01 407. O. 0.00E+00 0. R 4.1 5.75E-02 5.75E-02 273. O. 0.00E+00 0. I I I Notes: LLD for an RO-2A is 2.0 mR/hr ( < 2. 0mR/hr= background) LLD for an RO-2 is 0 2 mR/hr (<0.2mR/hr= background) i I LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) ,W 5-43 I

Millstono Unit !! Em rg:ncy PI:n Excrciso - 9/22/93 .g Radiological Dose Rate Map I O# - A j / / FJ - WB R A TE q9 _._ - g F2-WB DOSE \\ \\ i \\ F3-THY DOSE OOM LEDYARD\\ F5-SECTORS { -M OA DS EAST Lvi1E RD f. F7-M1NOR ROADS f LY ME $ ^ 6 F8-POI NTS [ f F9-TOWNS }I '( /. ) 'N F10-CET DOSE g i IT Fil-PRI NT "Np) .O ] ON ON g F12-RETURN i, )f j ' ' l OLD LY ME g PRINTINs i h FISH RS WB D RATE i I SLA D T: 1115-1130 ( u I O > 50 vRem/hs i emmenc > 1 mrem /hr f ~ Pf.U M ISLA / asumme > 100 mrem /h > 1 Rem /hr K H ammans > 10 Rem /br g 8 L THIS IS A DRILL

I

'I 1 l 5-44 I 'I

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I Mill:tona Unit 11 Emcrg:ncy Pinn Ex rci;o - 9/22/93 Radiological Data OFF-SITE DOSE GUIDE Scenario Time: 11:30 - 11:45 SURVEY METER READINGS IODI1?E SAMPLE READINGS WINDOW WINDOW BACKGROUND SAMPi E I-131 PARTIC I OPEN CLOSED CONC FILTER SAMPLE ( + y) (y only) POIITT mR/hr mR/hr cpm ccp n Ci/m**3 Cepm I 0. 1.17E-14 0. A 1.1 4.81E+02 2.40E+02 0. 9.39E-15 0. A 2.1 1.25E+02 6.25E+01 0. 4.12E-12 2. A 2.2 2.60E+02 1.30E+02 A 3.1 1.74E+03 8.69E+02 11. 4.60E-10 180. I A 3.2 1.21E+03 6.05E+02 40. 1.60E-09 625 A41 9.09E+02 4.55E+02 38. 1.54E-09 604. A 4.2 3.72E+02 1.86E+02 38. 1.54E-09 603. I A 6.1 3.11E+01 1.55E+01 46685. 17. 6.99E-10 276. 50. 2.02E-09 796. A 6.2 1.95E+02 9.77E+01 A 8.1 2.47E+02 1.23E+02 40. 1.62E-09 I-A 9.1 1.09E-03 5.45E-04 102. O. 1.71E-14 0. A10.2 5.56E-02 2.78E-02 183. O. 3.73E-13 7223. B 2.1 3.88E+01 3.88E+01 0. 0.00E+00 0.. B 2.2 3.13E+00 3.13E+00 9499. O. 0.00E+00 0. I B 3.1 3.11E+00 3.11E+00 9444. O. 0.00E+00 0. B 3.2 1.12E-02 1.12E-02 134. O. 0.00E+00 0. B 5.1 1.41E-01 1.41E-01 522. O. 0.00E+00 0. I C 1.1 1.86E+01 1.86E+01 56047. O. 0.00E+00 0. C 1.2 4.97E+00 4.97E+00 15007. O. 0.00E+00 0. C 2.1 5.89E-02 5.89E-02 277. O. 0.00E+00 0. I-D 1.1 4.50E-02 4.50E-02 235. O. 0.00E+00 0. E 1.1 4.17E-02 4.17E-02 225. O. 0.00E+00 0. Q 2.1 6.68E-03 6.68E-03 120. O. 0.00E+00 0. R 2.1 9.59E+00 9.59E+00 28862. O. 0.00E+00 0. R 2.2 4.24E-02 4.24E-02 227. O. 0.00E+00 0. R 3.1 3.81E-02 3.815-02 214. O. 0.00E+00 0. R 4.1 1.66E-02 1.66E-02 150. O. 0.00E+00 0. I I Notes: LLD for an RO-2A is 2.0 mR/hr ( <2. 0mR/hr= background) LLD for an RO-2 is 0.2 mR/hr ( < 0. 2mR/hr= background) I. LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) t I I s.. I

I Millstono Unit 11 Emorgancy Plan Exorcito - 9/22/93 l Radiological Dose Rate Map t F1-WB RATE i J F2-WB DOSE \\ p A F3-THY DOSE i 4 l LEDYARhs \\ j F5-SECTORS ",.\\ F6-MA JOR ROADS F7-MINOR R06DS 7 l FS-POI NTS F g ht'I F9-TOWNS \\ F10-CET DOSE \\ ',\\ ( lT Fil-PRI NT i ,Q g g F12-RETURf4 pos E f '{ \\ OLD LY ME )yf j PR I NT i f M ~ WB D RATE F1SH RS T: 1130-1145 ISLAt D M J l ~ i L C > 50 uRem/hr m ) 1 mrem /hr p summme > 100 mrem /h. I S LA > 1 Re m/hr K H summme > 10 Rem /hr I . l THIS IS A DRILL 3 , g I E l

Mill:tona Unit 11 Em rg:ncy PI:n Excrcico - 9/22/93 'l Total Integrated Radiological Dose Map (For Use in Providing Player Plc Readings) I g ..ffd [ F1 - WB RATE '\\ -$hN ~ F2-WB DOSE A F3-THY DOSE fi F4-ZOOM. O -i g (1 5 - F5-SECTORS i f CROTON, g_gg g g O MI \\ l g ^ FRD, ,l EAST lyt J F7-fil NOR ROADS F8-PCI NTS F g*., y ,,f tI F9-TOWNS g .;J \\. l ' F10-CET DOSE .Ih . '{ ~ ^ Fil-PR I NT ~ ON E F12-RETURN ~ OLD LYI1E ),<,7 PR I t JTi t JG f, 73gy.RS INT WB DOSE e T:1130-1145 I S LA tilD M ~ o >1 mrem j L e w.= > 10 Mrem PLUi > 100 mRen i [g l'"'" I THIS IS A DRILL g I 1 ~ I

I Millstona Unit 11 Em:rg:ncy Pl:n Excrcl33 - 9/22/93 Radiological Data OFF-SITE DOSE GUIDE Scenario Time: 11:45 - 12:00 SURVEY METER READINGS IODINE SAMPLE READINGS WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC I OPEN CLOSED CONC FILTER SAMPLE ($ + y) (y only) POIIC' mR/hr mR/hr epm ecpm Ci/m**3 cepm 0. 0.00E+00 0. A 1.1 6.53E+01 6.53E+01 A 2.1 9.86E+00 9.86E+00 29667. O. 0.00E+00 0. A 2.2 2.11E+01 2.11E+01 63309. O. 0.00E+00 0. 1. 2.48E-11 9. A 3.1 1.22E+02 6.08E+01 I A 3.2 1.81E401 9.06E+00 27281. O. 2.07E-11 8. A 4.1 8.42E+00 4.21E+00 12723. O. 1.74E-11 6. A 4.2 2.40E+00 1.20E+00 3699. O. 4.55E-12 2. I A 6.1 4.12E+01 2.06E+01 61871. 21. 8.85E-10 334. A 6.2 3.15E-01 1.58E-01 573. O. 1.02E-11 4. l A 8.1 1.53E+00 7.67E-01 2401. O. 1.07E-11 I A 9.1 1.23E+01 6.15E+00 18549. 2. 8.33E-11 A10.1 1.03E+00 5.16E-01 1649. D. 6.78E-12 B 2.1 2.63E+02 1.31E+02 0. 1.17E-13 0 B 2.2 3.84E+01 1.92E+01 57638. O. 1.86E-15 O. I B 3.1 3.78E+01 L.89E+01 56859. O. 6.72E-13 0. B 3.2 1.24E-01 1.24E-01 472. O. 0.00E+00 0. B 4.1 7.51E-03 7.51E-03 123. O. 0.00E+00 0. I B 5.1 7.03E+00 3.52E+00 10645. 1. 4.90E-11 18. C 1.1 2.77E+01 2.77E+01 83207. O. 0.00E+00 0. C 1.2 7.93E+00 7.93E+00 23891. O. 0.00E+00 0. I C 2.1 1.24E-01 1.24E-01 471. O. 0.00E+00 0. D 1.1 5.51E-02 5.51E-02 265. O. 0.00E+00 0. E 1.1 4.29E-02 4.29E-02 229. O. 0.00E+00 0. R 2.1 2.66E+00 2.66E+00 8076. O. 0.00E+00 0. R 2.2 8.01E-03 8.01E-03 124. O.

0. 0 01 0

0. I I I Notes: LLD for an RO-2A is 2.0 mR/hr ( <2. 0mR/hr= background)' LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) i I LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) I I 5-49 I

I Millstone UnM 11 Emergency Plan Exercise - 9/22/93 l Radiological Dose Rate Map I

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~ . - ~ // F1 - WB R A TE F2-WB DOSE l ~ ~ 4 F3-THY DOSE \\ \\ O F4-ZOOt1 DY F5-SECTORS I \\ \\ EAST LYi1E Df-LY t1C., [ k. ~ J ,f ~~ i-3 'l F8-POI tJTS ~kI F9-TOWt JS \\ \\, + \\ \\ -, F10-GET DOSE g ,,Q ) Fil-PRI NT I F12-RETU Rt J i 'ON g \\ OLD lyt 1C l ')f,j/j , t-q' i ) I PR I t JTi t-JG FISH RS WB D RATE \\,~ ISLAtD T=1145-1200 f g P /C > 50 vRem/hr L ec > 1 mrem /br l p I S LA mu'umm ') 100 mrem /h I M H > 1 R e m/ hr-amamm > 10 Rem /hr i g THIS IS A DRILL j I s.so 1

i B Millstone Unit 11 Emerg:ncy PI:n Excrci23 - 9/22/93 l Total Integrated Radiological Dose Map (For Use in Providing Player Plc Readings) Ig -2 cA F1-WB R A TE =-- was.L - K -[\\ k[j;N 35 F2-WB DO5E \\ ub b-N 4 F3-THY DOSE ~' " A..a $ \\ l 1 l 3 f NIkN[.h ( LEDY AR 'N 215E?? F F5-SECTORS g jf CR'OTON O MI I \\ c F6-MAJOR RCADS l EAST LYME \\ ^T RD F'7-MI NOR ROA DS LY tie. ./ \\ l. F8-POI f 4TS P y 3 (, w I ti F9-TOWNS N F10-GET DOSE \\, .) g, \\ f \\ \\ Ig1 Fil-PR I NT '. ~ ,[ F'12-R ETU RN lf Yo a o a i \\ p ,,s OLD LVME pp p p. 7 g7 7, y, M.- INT WB DOSE FISH S \\ T: 1145-1200 I S LA M ~ I G >1 mrem t= =_. ).10 MREM P{Uji > 100 mrem i > 1 Rem K mammes > 5 Rem-I l; l THIS IS A DRILL ] I 5-51

I Mill;tsna Unit II Em rgency Plzn Ex:rci20 - 9/22/93 Radiological Data I OFF-SITE DCSE GUIDE Scenario Time: 12:00 - 12:15 SURVEY METER READINGS IODINE SAMPLE READINGS WINDOW WINDOW BACKGRCUND SAMPLE I-131 PARTIC I OPEN CLOSED CONC FILTER SAMPLE ( + y) (y only) POINT mR/hr mR/hr epm ccpm Ci/m**3 cepm A 1.1 6.30E+00 6.30E+00 19011. O. 0.00E+00 0. A 2.1 9.39E-01 9.39E-01 2937. O. 0.00E+00 0. A 2.2 2.02E+00 2.02E+00 6149. O. 0.00E+00 0. A 3.1 1.17E+01 5.86E+00 17693. O. 2.39E-12 1. I A 3.2 1.73E+00 8.63E-01 2690. O. 2.05E-12 1. A 4.1 7.99E-01 4.00E-01 1299. O. 1.73E-12 1. A 4.2 2.28E-01 1.14E-01 443. O. 4.56E-13 0. A 6.1 2.93E+01 1.46E+01 44043. 15. 6.40E-10 235. A 6.2 1.61E-01 8.06E-02 342. O. 2.97E-12 1. A 8.1 4.43E-02 2.21E-02 166. O. 3.26E-13 5086. 16. 6.94E-10 A 9.1 9.77E+03 4.88E+01 A10.1 3.92E+01 1.96E+01 58912. 6. 2.67E-10 B 2.1 2.55E+01 1.27E+01 38290. 0 1.06E-14 0. B 2.2 1.83E+00 1.83E+00 5603. O. 0.00E+00 0. I B 3.1 3.62E+00 1.81E+00 5527 D. 6.49E-14 0. B 3.2 1.17E-02 1.17E-02 135. O. 0.00E+00 0. B 5.1 6.72E-01 3.36E-01 1108. O. 4.91E-12 2. I B10.1 0.00E+00 0.00E+00 100. D. 1.42E-15 O. C 1.1 2.66E+00 2.66E+00 8070. O. 0.00E+00 0. C 1.2 7.55E-01 7.55E-01 2364. O. 0.00E+00 0. C 2.1 1.17E-02 1.17E-02 135. O. 0.00E+00 0. D 1.1 5.20E-03 5.20E-03 116. O. 0.00E+00 0. R 2.1 2.52E-01 2.52E-01 856. O. 0.00E+00 0. I E I Notes: LLD for an RO-2A is 2.0 mR/hr (<2.0mR/hr= background) 'g LLD for an RO-2 is 0.2 mR/hr ( < 0. 2mR/hr= background) 3 LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) i I 5-52 I

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' I Millstone Unit 11 Emergency Plan Exercise - 9/22/93 l Total Integrated Radiological Dose Map (For Use in Providing Player Plc Readings) (

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-[g --9 95~ ' " F2-WB DOSE l \\, Ib F3-THY. DOSE { ri$,I[ O i \\ - [. I LEDYAR Mh'_li' S ; F5-SECTORS s ~ f g CROTON O M1 F6-MA JOR ROA DS EAST LVME RD f," F7-MI NOR ROADS LY riE. ) \\l F8-POI NTS (, J, 'I F9-TOWNS [ \\ \\ j \\, F10-GET DOSE ~ g'OTW F11-PR I NT ' g' i F12-REW RN ON E \\). ag -f.. '. OLD LY ME PRIUTING .j h INT WB DOSE FISH RS \\ ISLAt D T=1200-1215 M -l 4 G > 1 mRes ^ w-, s.-_. > 10 MRe M PLUM ummmm. > 100 mrem enemmes > 5 Rem E g THIS IS A DRILL I I s.s. I

11 Millstone Unit 11 Em:rg:ncy Pl:n Ex:rci20 - 9/22/93 Radiological Data I OFF-SITE DOSE GUIDE Scenario Time: 12: 15 - 12:30 SURVEY METER READINGS IODINE SAMPLE READINGS WINDOW WINDOW EACKGROUND SAMPLE I-131 PARTIC I OPEN CLOSED CONC FILTER SAMPLE ( + y) (y only) POINT mR/hr mR/hr epm cepm Ci/m**3 cepm A 1.1 6.69E-01 6.69E-01 2107. O. 0.00E+00 0. A 2.1 1.02E-01 1.02E-01 406. O. 0.00E+00 0. A 2.2 2.26E-01 2.26E-01 778. O. 0.00E+00 0. A 3.1 1.43E+00 7.13E-01 2238. O. 4.20E-13 0. I A 3.2 2.22E-01 1.11E-01 433. O. 4.06E-13 0. A 4.1 1.07E-01 5.34E-02 260. O. 3.47E-13 0. A 4.2 2.95E-02 1.48E-02 144. O. 1.03E-13 0. I A 6.1 9.13E-01 4.56E-01 1469. O. 2.10E-11 8. A 6.2 2.08E-02 1.04E-02 131. O. 7.18E-13 0. A 8.1 9.86E-03 4 93E-03 115. O. 7.52E-14 1197. A 9.1 7.22E+00 3.61E+00 10933. 1. 5.40E-11 A10.1 3.66E+00 1.83E+00 5592. 1. 2.61E-11 B 2.1 1.13E400 1.13E+00 3483. O. 0.00E+00 0. B 2.2 1.40E-01 1.40E-01 521. O. 0.00E+00 0. I B 3.1 2.89E-01 1.45E-01 534. O. 2.69E-15 O. B 5.1 4.25E-02 2.13E-02 164. O. 2.38E-13 0. C 1.1 2.35E-01 2.35E-01 804. O. 0.00E+00 0. i I-C 1.2 6.61E-02 6.61E-02 298. O. 0.00E+00 0. R 2.1 2.58E-02 2.5BE-02 178. O. 0.00E+00 0. II 4 11 E r i E Notes: LLD for an RO-2A is 2.0 mR/hr ( <2. 0mR/hr= background) r LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) { I LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) 4 I p i 5-55

Millstone Unit 11 Em rg::ncy Plan Exarciao - 9/22/93 Radiological Dose Rate Map i Ni F1 - WB R A TE s. Tr f.. - F2-WB DOSE ,/ F3-THY DOSE j \\ LEDYARhN F5-SECTORS \\ 52 ', : GROTON O MI [ RD f g l { EAST LY.t1E I l LY t-iE. k 'I h ,/ [ F8-PCI NTS 'j p ~ ~}' / . -sI \\ / .\\ fI F9-TOWNS i -[ ,1 F10-GET DOSE I F11-PR I NT F12-RETURt J - ' ' ON E ),f,j. OLD lyt 1E PRi t JTi t JG -I x . ~ WB D RATE FISHGRS \\ T:1215-1230 Istog p I C > 50 vRem/hr \\ L em er:r > 1 mrem /hr asumen > 100 mrem /h I S LAND > 1 R e m/ hr H H I ammmmum ) 10 Ren/hr .I l THIS IS A DRILL I I. s.se I

Mill: tono Unit 11 Emcrg ncy PI:n Ex;rciDo - 9/22/93 l Total Integrated Radiological Dose Map-(For Use in Providing Player Plc Readings) / F1 - WB RATE fJi J '. :7 F2-WB DOSE \\ \\ [, F3-THV DOSE l / . 5~..._ 5 F4-ZOOt1 l /3 ~~ LEDYA I W9*,.: ; F5-SECTORS ' if-QOr' I ^ RD /' \\ I EAST LV-fjE NOR R O' DS \\ l Lyric \\ h [I F F8-POI NTS f. \\ '\\., 'i F9-TOWNS k. F10-CET DOSE I. 'h \\ ,OTON O E 1 PE N OLD LYl1E [

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PR I NTI N'~. 1 I INT WB DOSE FISH.RS \\ I S LA 'D T: 1215-1230 t1 E G y 1.ng,m L e: - > 10 mRen p mumamum > 100 mRen I S LA ND > 1 Rem K H I ammmmes > 5 Rem I g THIS IS A DRILL I I s.s, I

f Millatona Unit 11 Emorgoney Plan Exorciao - 9/22/93 Radiological Data g OFF-SITE DOSE GUIDE Scenario Time: 12:30 - 12:45 SURVEY METER READINGS IODINE SAMPLE READINGS WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC 'I OPEN CLOSED CONC FILTER SAMPLE ($ + Y) (y only) POINT mR/hr mR/hr epm cepm C1/m**3 cepm j i I A 4. 2 6.50E-02 3.25E-02 197. O. 1.06E-12 0. j A 6.1 8.92E-03 4.46E-03 113. O. 2.06E-13 0. l l A 6.2 3.14E+00 1.57E+00 4805. O. 2.12E-11 8. l I l A B.1 1.71E+00 8.56E-01 2667 O. 1.36E-11 A 9.1 1.55E-04 7.75E-05 100. O. 1.45E-15 18. l A10.1 4.32E-04 2.16E-04 101. O. 7.53E-15 53. I L I lI tI I l I lI l l E l l 5 i E i I Notes: LLD for an RO-2A is 2.0 mR/hr (<2.0mR/hr= background) LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) I LLD for an ASP-1 is 0.002 mR/hr ( < 0. 002mR/hr= background) j 5-58

I Millstona Unit 11 Emcrg:ncy Plzn Ex rci o - 9/22/93 j Radiological Dose Rate Map 5 ^ A 'M // / N F1 - WB RcTE -$7 F2-WB DO5E .g_ F3-TH4 DOSE ~~~ t /h N g Lggyppks\\ N N1 / ' ~ - F5-S EC TOR S i CROTON O MI F6-t1A JOR ROA DS / l LA ':: 1 LNML \\ [ p 7-MI t40R RO6DS p _d '7[ \\. F8-POI NTS 7" f t: F9-TOWf 15 y/ [ 's ] ' F10- GET DOSE J 9 JD'I \\/ { \\ 3 Fi l - PR I NT fl' k h' 5DJ VYE F12-RETURt1 j ') p,7 .j. /i OLD LUME pp 7 g7 ;, y, \\,' k WB D RATE F1SH f ~ ISLAt D T: 1230-1245 M N / / I C 50 vRem/hr I k PLUM N >1 mrem /hr -= asemans > 100 mrem /h I 6'A > 1 R e m/ hr M [ N samanne > 10 Rem /hr N

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J .c THIS IS A DRILL

I Millstone Unit 11 Emorgoney Plan Exorciso - 9/22/93 h Total Integrated Radiological Dose Map (For Use in Providing Player PIC Readings) l / F1 - WB RATE Ni M .]$((Gi- [e F3-THY DOSE F2-WB DOSE N y LEDY A Rli\\ ~ f / \\ F5-SECTORS I \\ Ih'f92~.? I i / I Mfi - l 7 \\. CROTON O MI s ~ ' l EAST LY ME RD,r-" F'7-MI NOR ROGDS LY HE I IF q ( F8-POI NTS a-p p } 'k I F9-TOWT JS / h \\, ^/ g i F10-GET DOSE i.. ~ i \\ ..O , ON E F12-RETURN i l OLD LVME{ 9-FR I f JTi t J:~. \\ t ,I" h. INT WB DOSE b FISH RS 's ' j l / I S LA ND T: 1230-1245 M I\\ b a- >1 MR@m e > 10 NRem p > 100 mRen \\ mammmin I S LA N >1 Rem \\K H I. _ > 0 Rem I l P

Millstone Unit 11 Emergency Plan Exorciao - 9/22/93 lg-Radiological Data OFF-SITE DOSE GUIDE Scenario Time: 12:45 - 13:00 SURVEY METER READINGS IODINE SAMPLE READINGS WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC l OPEN CLOSED CONC FILTER SAMPLE (p + y) (y only) q POINT mR/hr mR/hr epm cepm C1/m**3 cepm l A10.2 5.34E-02 2.67E-02 180. O. 4.15E-13 0. l l 5 l lI i I lI E I 'I I I Notes: LLD for an RO-2A is 2.0 mR/hr ( <2. 0mR/hr= background) LLD for an RO-2 is 0.2 mR/hr (<0.2mR/hr= background) I LLD for an ASP-1 is 0.002 mR/hr (<0.002mR/hr= background) I I 5-61 5

~ Millstona Unit 11 Em:rg:ncy PI:n Excrcizo - 9/22/93 !l' Radiological Dose Rate Map 1 Y ,,7 [" / F1 - vJs Rc TE F2-us DOSE mj!_- A i F3-THY Dose /aj -? ( LEDY AF \\ l {g F5-SECTORS I jy F6-MAJOR ROADS CROTOt J O MI 7 ?1 ' EAST LY ME N _f F"?- MI NOR ROADS F d. -s F8-POI NTS p \\ ./ 1i F9-TOWNS . f- - \\/. J ' Flo-cET DOSE \\ .k.h$ 1 1,.. g-Fil-PRI NT OTON sj \\ \\ \\ 5 j ' ../ ...f. .; I F12-RETURf 4 ON E h .t ') f p./ ' ' ' I il, OLD LVME ) .i PRIlJTitF. WB D RATE pjgy pg \\ ISLA D e T: 1245-1300 M L C > 50 uRem/hr > 1 mrem /hr P U 19 g L ummuna > 100 MP.em/h > 1 R e m/ hr g H mummme > 10 Rem /hr .h B THIS IS A DRILL g I

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I Millstone Unit 11 Emergency Plan Exercise - 9/22/93 i Radiological Data g f OFF-SITE DOSE GUIDE Scenario Time: 13: 00 - END OF DRILL I SURVEY METER READINGS IODINE SAMPLE READINGS I WINDOW WINDOW BACKGROUND SAMPLE I-131 PARTIC OPEN CLOSED CONC FILTER SAMPLE ($ + y) (y only) POINT mR/hr mR/hr epm cepm Ci/m**3 cepm I [ PLUME HAS CLEARED THE EPZ - ALL READINGS ARE AS READ) I lI i I 1 I f 8 1 E l I I I I Notes: LLD for an RO-2A is 2.0 mR/hr (<2.0mR/hr= background) LLD for an RO-2 is 0.2 mR/hr ( < 0. 2mR/hr= background) LLD for an ASP-1 is 0,002 mR/hr (<0.002mR/hr= background) 5-64 W

E Millstona Unit ll Em;rg:ncy PI:n Excrcl23 - 9122/93 g' Radiological Dose Rate Map I l 4 F1 - WB R A TE 7 F2-WB DO5E .MONTUIL

1___-

N F3-THV DOSE B / \\ ___ l F4-ZOOt 1 f s FS-SECTORS ( l y CROTON O M1 F6-t1AJOR ROADS EAST LOME \\ [ F7-MI NOR ROF DS LY t iC. $ I )\\q D\\ FS-POI NTS \\ ) k .' j r_, pg_ Towns f \\, F10-CET DOSE 'N 1 / f \\! \\ - I 4 F11 - PR I NT l E F12-RETURN .) .,p ' W OLD LVME )< pp y g 7 7 g,, T 130 EhD tp gm N/ B O > 50 vRem/hr I > 1 Mrem /hr n_ PLUM ummassa > 100 MREM /h \\.- f I G LA ND > 1 R e m/ hr usumans > 10 Rem /hr I g THIS IS A DRILL I I s-es I

I Millstone Unit 11 Em:rg:ncy PI n Ex:rcb3 - 9/22/93 h Total Integrated Radiological Dose Map (For Use in Providing Player Plc Readings) } f(d. F1-WB RATE / F2-WB DOSE / \\, f F3-THY DOSE \\ ~ *N~#. f i NY F4-ZOOM \\ gg LEDYAR \\ F5-SECTORS \\ - MAY; @. {' CROTON O M1 TT114"p:: -M OR ROADS { EAST Lv.ME RD 'f F7-MI NOR ROADS / Ii 6 LY t1E. F8-POI NTS I F9-TOWNS '\\ j .k l F10-GET DOSE I Fil-PRI NT ' ') ..O l F12-RETURN [ LO Oh E /' ,+ OLD LY ME j PR I NTI NG g, FISH RS INT WB DOSE \\, I S LA N: T: 1300-END M j G > 1 mrem L ee.2 > 10 mRen PU maamme > 100 mrem j g >1 Rem g H sumune > 5 Rem l l THIS IS A DRILL i I l I 5-66

I I ~ I V. DATA F. METEOROLGICAL DATA l AND FORECASTS I I I .I I lI I I-I I I I I I

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M M O O M' M .M M M M M M M M 'M Ml 8 8[ (Pachage B) MILLSTONE METEOR _QLOGICAL FORECAST FORECAST #1 TIME: 0700 (EDT) AT033 WD033 WS033 WD142 WS142 WD374 WS374 STAB. CLOUD PRECIP _PRECIP FOR PERIODS: 20.9 160 4.0 165 0.0 165 9.5 S None None D11QQ TO RB1QD 21.5 170 5.0 175 8.5 180 9.0 S None None HalqQ TO 1010_Q 22.0 180 d.5 185 7.5 185 8.5 N P. CLDY None 1010_Q TO 13AQQ V'* 22.0 160 4.0 175 6.5 1*i 5 8.0 N P. CLDY None JhQ TO 12J2 TO TO , m vex.esa

MILLSTO]LE METEOROLOGIIAL_EQ]LEQA_ST FORECAST #2 TIME: 0800 (EDT) AT033 WD033 WS033 WD142 WS142 WD374 WS374 STAB. CLOUD PRECIP PRECIP FOR PERIODS: 21.5 175 6.0 185 0.5 185 9.5 N None None Q0109 TO 101Q_Q 21.5 185 4.5 185 8.5 185 8.5 N P. CLDY None 12.LQ.Q TO 131QD 22.0 160 3.0 170 6.5 175 7.5 N P. CLDY None 1310.0 TO A_?2p_Q TO T o TO TO 2 - invex.esA

P IC ER P P I e e e C n n n E o o o R N N N P Y Y D D D e L L U n C C O o L N P C P BA N N N TS 4 0 3 5 7 0 S 9 8 8 W ISACE 4 R 7 5 5 0 O 3 7 0 8 F D 1 1 1 W ) L T A D C 3 E I ( G 2 O T 0 4 0 5 5 L S 0 1 O A 9 S 8 7 6 3 R C 0 W O E E R T O E F E M M 2 I 4 5 5 5 E T 1 7 8 7 N D 1 1 1 O W T SLL M 3 3 0 5 0 0 S 4 4 4 W e 3 3 5 0 5 0 6 8 6 D 1 1 1 W 5 5 0 3 3 0 1 1 2 T 2 2 2 A 9 D 9 0 Q 0 1 L 1 S 2 S 1 D 1 X 1 O I O O O O O O R T T T T T T A E P Q A Q_ e. R Q D x R L L 2 o Q ?3 y O 2 D 3 m F D A 1

M P IC ER P M P I e e C n n E o o R N N M P Y Y D D D U L L M O C C LC P P M BA N N TS M 4 7 0 5 3 S 9 7 MT W H D E 4 MF R 7 5 5 O 3 8 7 D 1 1 W ) L T A D C 4 E MG I ( 2 O T 0 4 5 5 L S 0 1 O A 0 S 8 6 4 R C 1 W E M0 h R A O a F E h M 4' 5 5 2 I E T 1 8 7 D 1 1 MN Q W T__J LL I 3 MM 3 5 5 0 S 5 3 W M 3 3 5 5 0 8 6 D 1 1 W M 3 0 0 3 0 1 2 T M I 2 2 A M R D 0 0 1 1 S 3 7 D 1 1 W O I O O o O o O R T T T T T T A E e P 0 0 c. 0 0 x R 1 1 W ev O Q 3 1 F 1 1 c y n W

P IC ER P P I e e C n n E o o R N N P Y Y D D D U L L O C C L C P P DA N N TS 4 7 5 0 3 S 7 0 W TSACE 4' R 7 5 5 O 3 7 7 F D 1 1 W ) L T A D C 5 E I ( Q 2 Q T 0 4 5 5 L S 0 1 O A 1 S 7 6 5 R C 1 W O E E R T O E F E M M 2 I 4 5 5 E T 1 7 7 N D 1 1 O W TSL 1I_ 3 0 M 3 0 0 S 4 4 W 3 3 0 0 0 7 6 D 1 1 W l 3 0 0 3 0 1 2 T 2 2 A Q. Q 0 Q 1 S 3 7 D 1 1_ O I O O O U O O R T T T I T T E A s P D 0 c. 0 0 R 1 1 se O 1 3 t v F 1 1 U 7 7 3

MILLSTONE METEOROLOGICAL FORECAST FORECAST #6 TIME: 1200 (EDT) AT033 WD033 WS033 WD142 WS142 WD374 WS374 STAB. CLOUD PRECIP PRECIP FOR PERIODS: 21.0 185 4.5 190 8.0 185 8.5 N P. CLDY None 1210R TO 131DA 22.0 160 3.5 170 625 175 7.5 N P. CLDY None 13100 TO 1710.0 TO TO v1 TO TO 37tver.esa

a--, iE.- !E !I V. DATA .I G. CHEMISTRY DATA .l 4

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CEE e ca ww &0-o o-w Pt 0-- O QQQ N o 7 5-75

ll Millstone Unit 111993 Exercise =I Chemistry Data ll~ Containment Air Sample il 07:00 08:00 9:00 lg. Gaseous 9.0e-6 uCi/cc 1e-5 uCi/cc 6.De-4 uCi/cc 4g Particulate 1.0e-8 uCi/cc 1.1e-8 uCi/cc 6.6e-7 uCi/cc lodine 7.4e-10 uCi/cc 8.1e-10 uCi/cc 4.9e-8 uCl/cc 10:30 J Xe 133 7.3e2 uCi/cc 3 Xe 135 8.2e1 uCi/cc Xe 133m 2.5e1 uCi/cc Xe-131m 2.3e0 uCi/cc I Kr-85m 6.8e1 uCi/cc Kr-87 5.2e1 uCi/cc Kr-88 2.3e2 uCi/cc I l-131 1.2e0 uCi/cc l-132 9.8e-1 uCi/cc l-133 2.4e0 uCi/cc l-135 1.9e0 uCi/cc Cs-134 4.8e0 uCi/cc j Cs-137 2.9e0 uCi/cc Hydrogen 35 % by Vol. (for controller info only) Steam 40 % by Vol. Air 60 % by Vol. I Un-dilluted CTMT Air l Sample Dose Rate 145 mR/hr/cc (Contact) < 1 mR/hr/cc (at 1 foot) I I e.>e I

g Millstone Unit 111993 Exercise I-Chemistry Data I

Reactor Coolant Sample l 07:00 I Goss Activity Be-3 uCi/g Dose Equivalent lodine-131 7e-3 uCi/g -I- } 10:30 1-131 8.5e4 uCi/ml l-132 6.6e4 uCi/mi I l-133 1.Be5 uCi/ml 1-135 1.4e5 uCi/mi Cs-134 1.Ge4 uCi/ml Cs-137 9.9e3 uCi/mi j I Un-dilluted RCS or Sump Sample Dose Rate 1,312 R/hr/ml (Contact) 3 R/hr/ml (at 1 foot) .I I I LI I I s.,, I 1}}

ML20059K247

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