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Rev 0 to Critical Design Characteristics Radiological Events for Millstone 2
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PARSONS POWER Critical Design Characteristics Radiological Events Millstone 2 W

Date:

OT 92 Prepared By:

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Tier 2 Revnion 0 9710010193 970929 29 september 1997 PDR ADOCK 05000336 P

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TABLE OF CONTENTS 1.0 RADIOLOGICAL CONSEQUENCES ASSOCIATED WITH FUEL liANDLING ACCIDENTS &

LOSS OF COOLANT ACCIDENTS AND ANALYSIS OF HYDROGEN ACCUMULATION IN CO NT A I N M E NT

.............. 2 2.0 CRITICAL DESIGN CIIARACFERISTICS...

... 6 2.1 WASTE GAS SYSTEM FAILURE...

.6 2.2 FUEL llANDLING ACCIDENT IN THE SPENT FUEL POOL..

..7 2.3 FUEL HANDLING ACCIDENT IN CONTAINMENT......

.... 10 2.4 SPENT FUEL CASK DROP ACCIDENTS............

. 12 2.5 HYDROGEN ACCUMULATION IN CONTAINMENT..

. 13 2.6 RADIOLOGICAL CONSEQUENCES OF THE DESIGN BASIS ACCIDENT...

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ATTACilMENT 1 RADIOLOGICAL EVENTS 1.0 RADIOLOGICAL CONSEQUENCES ASSOCIATED WITil FUEL HANDLING ACCIDENTS

& LOSS OF COOLANT ACCIDENTS AND ANALYSIS OF llYDROGEN ACCUMULATION IN CONTAINMENT 1.1 FSAR Section 14.7 discusses four design basis events (DBEv's) invohing a radiological release. Three are associated with Fuel Handling and one with Waste Gas System Failure. FSAR Section 14.8 discusses two analyses associated with a Loss of Coolant Accident. One is the Containment Hydrogen Accumulathn analysis and the other is the LOCA radiological consequences. The applicability of each accident for each plant operating mode, and whether an analysis was performed by NNECo, is presented in Figure 1. Development of Critical Design Characteristics (CDCs) is based on information prosided in FSAR Chapter 14.- Rese CDCs will be augmented with information derived from FSAR Chapters 6,7, 8 and 9, and the supporting analyses and calculations.

l Figure 1: Radiological Events 14.7.1 14.7.4.2.1 14.7.4.2.2 14.7.5 14.8.3 14.8.4 Waste Gas Fuel Handling Fuel Handling Spent Fuel Hydrogen Radiological Plant System Accident -

Accident -

Cask Drop Accum. in Consequences Oper.

Failure Spent Fuel Containment Containment of DBA Mode Pool 1

N/A N/A Analyze Analyze 2

N/A N/A Mode 1 Mode 1 3

N/A N/A Mode 1 Mode 1 4

l N/A N/A Moda 1 Mode 1 5

N/A N/A Made 1 Mode 1 6

Analyze Analyze Mode 1 Mode 1 Analyze - The DBEv was analyzed, by NNECo, for the listed operating mode and the results summarized in FSAR sections 14.7 and 14.8.

Mode "n" - He DBEv is bounded by the mode "n" case ("n" = 1 - 6).

Not tied to a plant operating mode 1.2 The AMSR Program will" review" the DBEv's listed as " Analyze"in Figure 1. These are:

'DBEv 14.7.1 - Waste Gas System Failere following RCS degasification for refueling. Note that this event has been delete ( - tm the Standard Resiew Plan.

DBEv 14.7.4.2.1 Mode 6 - Spent fn,

embly drop during refueling.

DBEv 14.7.4.2.2 Mode 6 - Spent fuewsembly drop during refueling.

DBEv 14.7.5 - Spent fuel cask drop.

DBEv 14.8.3 Mode 1 - Containment hydrogen analysis (LBLOCA at full rated power)

DBEv 14.8.4 Mode 1 - Design Basis Accident (LBLOCA at full rated power).

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1.3 Figure 2 shows the systems involved in the mitigation of the analyzed Radiological Events.

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Figt.re 2: Tier-2 AMSR - Systems involved in Radiological Events l

i 14.7.1 14.7.4.2.1 14.7.4.2.2 14.7.fi 14.8.3 14.8.4 i

Waste Gas Fuel Fuel Spent Fuel Hydrogen Radiological System Handling Handling Cask Drop Accum. in Conseq.

Failure Accident -

Accident -

Contain.

of DBA SYS*1 EM SF Pool Contain.

RCS X

X WASTE GAS X

RAD MONITOR X

X X

X ESFAS X

X X

RB SPRAY X

l CONT AIR X

X RECIRC/ COOL CONT PURGE X

IND CONTR X

3 EB VENT X

X X

l EB FILTRATION MAIN EXHAUST X

X X

AUX EX11AUST X

X FUEL llANDL X

X X

SPENT FUEL X

X COOLING CTRL RM VENT X

AIR INTAKE X

i ELECT DIST X

X X

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l.4 Figure 3 shows the Cntical Safety Functions that have corresponding Critical Design Characteristics for cach of the analyzed accidents.

l Figure 3: Tier-2 AMSR - Critical Safety Functions with CDCs in Radiological Events l

14.7,1 14.7.4.2.1 14.7.4.2.2 14.7.5 14.8.3 14.8.4 Waste Gas Fuel Fuel Spent Fuel Hydrogen Radiological System Handling Handiing Cask Drop Accum. in Conseq.

Critical Safety Failure Accident -

Accident -

Contain.

of DBA Function SF Pool Contain.

Reactivity X

Fuel Integrity RCS 11ea? Rem.

RCS Pressure &

Inventory Contain Integrity X

X X

& Radiation Cont ol Electrical Power X

X X

Essential Suppon q

Systems

.1 Emironmental Control 1.5 The calculated Ayroid and Whole Body dose for the Low Population Zone (LPZ) associated with each event are presented in Figure 4.

Figure 4: Tier-2 AMSR - Radiological Events 1 SAR SECTION 14.7 and 14.8 ANALYZED DESIGN Thyroid Dose Whole Body BASIS EVENT LP7.

Dose - LPZ (REM)

(REM)

DBEv 14.7.1 - Waste Gas System Failure 6.6E-2 DBEv 14.7.4.2.1 Mode 6 - Fuel Handl Accid in SF Poal 1.2 2.87E-2 DBEv 14.7.4.2.2 Mode 6 - Fuel Handl Accid in Containment 2.03 7.66E-3 DBEv 14.7.5 - Spent Fuel Cask Drop DBEv 14.8.3 Mode 1 - Containment livdrogen Analysis 8.6 1.4 E-2 DBEv 14.8.4 Mode 1 - Design Basis Accident 6.17 1.4

Not prosidcM in FSAR Section 14.7.5.

" Thyroid dose insignificant after 120 days.

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l.6 Critical Design Characteristics Development Method The following method was used to develop CDCs for the Radiological Events. Six design basis events (DBEv's) invohing a radiological release are described in sections 14.7 and 14.8 of the FSAR. Each event was reviewed and design inputs extracted. Each design input was assigned to one or more Cri ical t

Safety Functions (CSFs). He CSF diagrams were then used to develop functional / system level CDCs for caeh event.

l.7 Systen. Boundary Diagrams System Boundary Diagrams (SBDs) are deve*oped for each accident mitigation system. Using the SBDs, the AMSR Program Team will identify the system configuration and ~*iponent actions required to meet the system / functional CDCs. This information will be loaded into t.c N 2 Data Base and will constitute the Chapter 14 requirement at the component level.

1.8 CDC Validation he CDCs will be validated "as present" in the installed plant configuration. The validation method will be determined following review of the detailed analyses supporting the FSAR Chapter 14 events.

Millstone-2 system and component test data will be used to the extent practical to perform this validation.

When CDCs cannot be validated by test, then analysis or alternate means will be used to perform the validation.

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2.0 CRITICAL DESIGN CllARACTERISTICS l

A discussion of the Radiological Release DBEv's from FSAR sections 14.7 and 14.8 are presented in sections 2.1 through 2.6 of this attachment. The functional / system CDC listing is included. These CDCs will be augmented with information derived from FSAR Chapter 6, 7, 8 and 9, and the detailed analyses and calculations that support FSAR Chapter 14.

1 2.1 WASTE GAS SYSTEM FAILURE 2.1.1 EVENT DESCRIPTION i

The limiting accident considered is the postulated and uncontrolled release to the auxiliary building of the radioactive xenon and krypton gases stored in one waste gas decay tank. Note: %is accident is no longer part of the SRP, however, the MNPS 2 FSAR contains an analysis of this postulated event in section j

14.7.1.

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2.1.2 DESIGN BASIS i

j The MNPS 2 Waste Gas System Failure DBEv is based on the following primary assumptions:

Activity based on degassing one RCS volume for refueling.

Reference:

FSAR Section 14.7.1.2.

a.

b. Event follows extended operation at full power with one percent defective fuel.

Reference:

FSAR i

Section 14.7,1.2.

c.

Instantaneous ground level release.

2.1.3 SYSTEM INTERFACE The following systems interface during the Waste Gas System Failure DBEv:

1' a.

Waste Gas System 2.1.4 EVENT DISPOSITION Rupture of one Waste Gas Decay Tank is postulated.

2.1.5 FUNCTIONAUSYSTEM CDCs - EVENT 14.7.1:

There are no apparent system / component design inputs for this postulated accident. The source term calculation and associated assumptions will generate such inputs, if any. The final resolution of this review will be developed upon review of the corresponding calculation packages. Thus no System / Functional CDCs are identified at this time.

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2.2 FUEL IIANDLING ACCIDENT IN Tile SPENT FUEL POOL 2.2.1 EVENT DESCRIPTION This event is initiated by the drop of a fuel assembly or consolidated fuel storage box during handling.

Fourteen (14) fuel rods are expected to fail in this postulated accident. Per Reg. Guide 1.25, this accident has been analyzed assuming the failure of one assembly. Prior to handling ofirradiated fuel, the fuel pool ventilation exhaust air is diverted manually to the auxiliary exhaust systen., through the enclosure building filtration system's (EBFS) charcoal filters, and released via the Unit I stack. 'Ihe MNPS-2 Fuel 11andling Accident in the Spent Fuel Pool analysis is described in FSAR Section 14.7.4.2.

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2.2.2 DESIGN BASIS

'Ihe MNPS-2 Fuel Handling Accident in the Spent Fuel Pool analysis is based on the following primary assun.ptions:

a.

Fuel movements limited by administrative controls and physical limitations imposed on fuel handling operations.

Reference:

FSAR Section 14.7,4.1.

b. Reactor core power level = 2700 MWt.

Reference:

FSAR Table 14.7.4-1.

c.

Failure of I assembly.

Reference:

FSAR Section 14.7.4.2.1, Table 14.7.4-1(Sa),

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d. Source term per RG 1.25.

Reference:

FSAR Table 14.7.4-1.

i 2.2.3 SYSTEMINTERFACE

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The following systems interface during the Fuel Handling Accident in the Spent Fuel Pool event:

a.

Spent Fuel Cooling & Purification System

b. Fuel Handling System c.

Radiation Monitoring

d. Enclosure Building Filtration System (EBFS) c.

Auxiliary Exhaust System (AES) f.

Electrical Distribution System 2.2.4 EVENT DISPOSITION The worst fuel handling incident that could occur in the spent fuel pool is the dropping of a fuel assembly to the fuel pool floor. The consequences of the dropping of a consolidated fuel storage box is boun6d by

. the fuel assembly drop to the fuel pool floor.

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2.2.5 FUNCTIONA1/ SYSTEM CDCs EVENT 14.7.4.2.1:

"Ihe Critical Design Characteristics for the Fuel llandling Accident in the Spent Fuel Pool are presented below.

2.2.5.1 REACTIVITY CONTROL Functional / System CDCs - Spent Fuel Pool boron concentration > 800 ppm.

Reference:

FSAR Section 14.7.4.1.

2.2.$.2 CONTAINMENT INTEGRITY & RADIATION CONTROL CSF EMP.S.tignaldnita C.QQ Core ofiload delav vi for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after shutdown. This is basis for nuclide decay times used in dose calculation.

Reference:

FSAR Table 14.7.4-1.

Functional / System CDCs - Spent fuel decay heat removed provided by forced circulation in the spent fuel cooling system.

Reference:

FSAR Section 14.7.4,1.

Functional / System CDCs - Auxiliary Exhaust System maintains negative pressure in the fuel pool building to provide for filtered release path.

Reference:

FSAR Table 14.7.4-1.

Functional / System CDCs - EBFS Filter Efficiencies are Organic 1 - 70%, Elemental 1 - 90%

Reference:

FSAR Table 14.7.41.

Functional / System CDCs - Activity release path via MP-1 Stack (Basis for Atmospheric Dispersion Factor value usul in dose calculation.

Reference:

FSAR Table 14.7.4-1 Functional / System CDCs - Fuel llamiling System mechanical design limits elevation to which the assembly can be raised to ensure minimum required water level for shielding.

Reference:

FSAR Section 14,7.4.1 Functional / System CDCs - Radiation monitoring system alarms loss of shielding due to low water level in the fuel pool.

Reference:

FSAR Section 14.7.4,1.

Functional / System CDCs - Radiation monitoring system alarm setpoints include Fuel Handling Accident as a basis.

Reference:

FSAR Section 14.7,4.1.

Functional / System CDCs - System design precludes handling of heavy objects such as shipping casks over the fuel storage pool.

Reference:

FSAR Section 14,7.4.1.

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l Functional / System CDQ - Mechanical interlocks prevent inadvertent disengagement of a fuel assembly or consolidated fuel storage box from the fuel handling machine.

Reference:

FSAR Section 14.7.4.1.

i Functional / System CDCs - Radiation monitoring system monitors ventilation exhaust air from containment and auxiliary buildings and alarms upon indication of fuel landling incident.

Reference:

FSAR Section 14.7.4.1.

Functional / System CDCs - Spent fuel pool area air is aligned to exhaust through the enclosure building filtration system prior to release through the Unit I stack.

Reference:

FSAR Section 14.7.4.1.

Functional / System CDCs - Fuel pool designed without protruding structures that could damage fuel if dropped.

Reference:

FSAR Section 14.7.4.2.

2.2.5.3 ELECTRICAL POWER CSF F_unctional/ System CDCs - Provide electrical power for accident mitigation loads.

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2.3 FUEL llANDLING ACCIDENT IN CONTAINMENT 2.3.1 EVENT DESCRIPTION This event is initiated by a drop of a fuel assembly during fuel handling inside containment. Fourteen (14) fuel rods are expected to fail in this postulated accident. Per Reg. Guide 1.25, this accident has been analyzed assuming the failure ofone assembly. Release of activity from containment occurs sia the containment purge system. The release is terminated by closure of the containment purge system isolation dampers. He MNPS 2 Fuel Handling Accident in Containment analysis is described in FSAR Section 14.7.4.2.

2.3.2 DESIGN BASIS The MNPS 2 Fuel Handling Accident in Containment analysis is based on the following primary assumptions:

Fuel movements limited by administrative controls and physical limitations imposed on fuel handling a.

operations.

Reference:

FSAR Section 14.7.4.1.

b. Reactor core power level = 2700 MWt.

Reference:

FSAR Table 14.7.4-2.

c Failure of I assembly.

Reference:

FSAR Section 14.7.4.2.1, Table 14.7.4-2(la),

d. Source term per RG 1.25.

Reference:

FSAR Table 14.7.4-2.

2.3.3 SYSTEM INTERFACE De following systems interface during the Fuel Handling Accident in the Spent Fuel Pool event:

a.

Fuel Handling System

b. Containment and Enclosure Building Purge System c.

Main Exhaust System

d. Radiation Monitoring System e.

Electrical Distribution System 2.3.4 EVENT DISPOSITION This eent is initiated by a drop of a fuel assembly during fuel handling inside contamment.

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a 2.3.5. FUNCTIONAllSYSTEM CDCs - EVENT 14.7.4.2.2:

he Critical Design Characteristics for Fuel Handling Accident in Containment are presented below.

2.3.5.1 REACTI'/ITY CONTROL Functional / System CDCs - Refueling cavity boron concentration > 1720 ppm.

Reference:

FSAR Section 14.7.4.1.

j 2.3.5.2 CONTAINMENT INTEGRITY & RADIATION CONTROL CSF i

FunctionaVSystem CDCs - Contamment circulation fans operate to provide uniform mixing in containment at time of release.

Reference:

FSAR Table 14.7.4 2.

Functional / System CDCs - Purge Flow Rate 32000 cfm

Reference:

FSAR Table 14.7.4-2.

Functional / System CDCs - Isolate Containment Purge System at 10 minutes to terminate release.

Reference:

FSAR Section 14.7.4.1, Table 14.7.4-2.

Functional / System CDCs - Containment personnel and equipment hatches are closed during fuel handling i

operations.

Reference:

FSAR Section 14.7.4.1.

Functional / System CDCs - Fuel Handling System mechanical design limits elevation to which the assembly can be raised to ensure minimum required water level for shielding.

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Reference:

FS AR Section 14.7.4.1 functional / System CDCs - Radiation monitoring system alarms loss of shielding due to low water level in the refueling cavity.

Reference:

FSAR Section 14.7.4.1.

Functional / System CDCs - Radiation monitoring system alarm setpoints include Fuci Handling Accident 4

as a basis.

Reference:

FSAR Section 14.7.4.1.

2.3.5.3 ELECTRICAL POWER CSF Functional / System CDCs - Provide electrical power for accident mitigation loads.

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2,4 SPENT FUEL CASK DROP ACCIDENTS 2.4.1 EVENT DESCRIPTION This event is initiated by the drop of a spent fuel cask into the spent fuel pool resulting in the rupture of 587 intact fuel assemblies. The analysis assumes that the fuel has decayed for a minimum of 120 days.

The MNPS 2 Spent Fuel Cask Drop Accident analysis is described in FSAR Section 14.7.5.

2.4.2 DESIGN BASIS The MNPS-2, 'Ihe MNPS-2 Fuel 1-landling Accident in the Spent Fuel Cask Drop Accident analysis is based on fw following primary assumptions:

a. - Reactor core power level = 2700 MWt.

Reference:

FSAR Section 14.7.5.

b. 587 fuel assemblics damaged.

Reference:

FSAR Section 14.7.5.

C. 217 assemblics in core.

Reference:

FSAR Section 14.7.5.

Dose calculation performed with a 120 day decay time.

Reference:

FSAR Section 14.7.5.

c.

d.

Dose calculated per NUREG-0612 generic assumptions using MP-2 specific values.

2.4.3 SYSTEM INTERFACE The following systems interface during the Spent Fuel Cask Drop Accident:

Spent Fuel Cooling & Purification System a.

b. Fuelliandling System c.

Radiation Monitoring

{

d. Enclosure Building Filtration System (EBFS) e.

Auxiliary Exhaust System (AES) f.

Electrical Distribution System 2.4.4 EVENT DISPOSITION

'Ihis event is initiated by the drop of a spent fuel cask into the spent fuel pool resulting in the rupture of 587 ints.ct fuel assemblics.

2.4.5 FUNCTIONAIJSYSTEM CDCs - EVEi4T 14.7.5:

.Ihe Critical Design Characteristics for the Spent Fuel Cask Drop Accident are presented below, 2.4.5.1 CONTAINMENT INTEGRITY & RADIATION CONTROL CSE Functional / System CDCs - Fuel fission product decay time at least 120 days.

Reference:

FSAR Section 14.7.5 12 Revision 0 29 September 1997

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2.5 HYDROGEN ACCUMULATION IN CONTAINMENT I

2.5.1 EVENT DESCRIPT;0N His condition is a consequence of the LOCA event. The safety analysis includes both the post-accident flammability and containment purge radiological concerns. Regulatory requirements require that containment hydrogen concentration be kept under 4% by volume and that the radiological consequences of the purge do not result in doses exceeding the guidelines of 10CFR100. The MNPS 2 Hydrogen Accumulation in Containment analysis is described in FSAR Section 14.8.3.

2.5.2 DESIGN BASIS 1

The MNPS 2 Hydrogen Accumulation in Containment analysis is based on the following prir..ary assumptions:

a.

RG 1.7 assumptions for H2 considerations.

Reference:

FSAR Section 14.8.3.2.

b. NUREG 75/087 Section 15.6.5 App. C assumptions for purge considerations. Reference FSAR Section 14.8.3.5.

c.

2700 MWt power level.

Reference:

FSAR Section 14.8.3.5.

2.5.3 SYSTEM INTERFACE De following systems interface during the flydrogen Accumulation in Contaimnent event:

f a.

Reactor Coolant System

b. Containment Air Recirculation and Cooling System c.

Containment Spray System

d. Contamment Post-Accident Hydrogen Control System e.

Enclosure Building Ventilation System f.

Main Exhaust System g.

Engineered Safety Features Actuation System h.

Electrical Distribution System 2.5.4 EVENT DISPOSITION LOCA post-accident flammability and containment purge radiological concerns are evaluated.

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2.5.5 FUNCTIONA1> SYSTEM CDCs EVENT 14.8.3:

The Critical Design Characteristics for the Hydrogen Accumulation in Containment event are presented below.

2.5.5.1 CONTAINMENT INTEGRITY & RADIATION CONTROL CSFfHydronen Generation)

Functional /Swtem CDCs - Zircaloy clad inventory $3700 lbs.

Reference:

FSAR Section 14.8.3.2.2.

2 Funnional/ System CDCs - Aluminum surface area 2300 ft

Reference:

FSAR Section 14.8.3.2.3.

Functional / System CDCs - Galvanized steel surface area 125000 ft2

Reference:

FSAR Section 14.8.3.2.3.

2 Functional / System CDCs - Zinc based painted area 206000 ft

Reference:

FSAR Section 14.8.3.2.3.

Functional / System CDCs - Containment spray pH ~ 5.5

Reference:

FSAR Section 14.8.3.2.3.

Functional / System CDCs - Containment spray temperature 0-1 hr,240 F; l-10 hr,180 F;

>10 hr,150*F.

Reference:

FSAR Section 14.8.3.2.3.

2.5.5.2 CONTAINMENT INTEGRITY & RADIATION CONTROL CSF 3 fydrouen Rqnqral)

Functional / System CDCs - Administrative limit for recombiner start is 7 days. Maximuni delay is 13 days.

Reference:

FSAR Section 14.8.3.2.4, Section 14 8.3.3.2.

Functional / System CDCs - Minimum H2 recombination rate = 0.27 Lb-Moles /Hr (equal to the H2 generation rate at 4% concentration in containment at_13 days.)

Reference:

FSAR Section 14.8.3.3.2, Figure 14.8.3-2, Figure 14.8.3-3.

Functional / System CDCs - Containment circulation fans operate to provide uniform mixing in containment at time of recombiner start / purge system operation.

Reference:

FSAR Section 14.8.3.

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1 2.5.5.3 CONTAINMENT INTEGRITY & RADIATION CONTROL CSF (Radiolonical)

Functional / System CDCs - Containment Free Volume 1.899E6 fl' Reference FSAR Section 14.8.3.5.

Functional / System CDCs - Purge Start Time 5 days after LOCA (radiological assumption), but no later I

than 7 days (flammability assumption).

?

Reference:

FSAR Section 14.8.3.5 and 14.3.3.4.1.

}

Functional / System CDCs - Nominal Purge Flow Rate 50 cfm

Reference:

FSAR Section 14.8.3.4.1.

Functional / System CDCs Filter Efficiency: 90% Elemental lodine; 70% Organic lodine; 90%

Particulate

Reference:

FSAR Section 14.8.3.5.

2.5.5.4 ELECTRICAL POWER CSF Functional / System CDCs - Provide electrical power for hydrogen recombination / purge and reactor 3

building circulation fans.

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2.6 RADIOLOGICAL CONSEQUENCES OF Tile DESIGN BASIS ACCIDENT 2.6.1 EVENT DESCRIPTION i

9 he Design Basis Accident (DBA) involves a gross release of activity from the fuel to the containment building. no MMPS 2 Radiclogical Consequences of the Design Basis Accident analysa' is described in FSAR Section 14.8.4.

1 2.6.2 DESIGN BASIS l

The MNPS 2 Design Basis Accident analysis is based on the following primary assumptions:

r..

asumptions per Reg. Guide 1.109 and RG 1.4. Reference FSAR Seion 14.8.4.2.

b. Core Power Level 2700 MWt and Core Operating Time 3 years.

Reference:

Table 14.8.4-1 MNPS Unit 2 LOCA radiological release with both low and high wind conditions. Re."crenc~

c.

FSAR Section 14.8.4.2.

C

d. Control Room habitability analysis assuming cases for: Unit i LOCA, Unit 2 LOCA, Unit 3 LOCA and Unit 1 MSLB.

Reference:

FSAR Section 14.8.4.3.2.

2.6.3 SYSTEM INTERFACE ne following systems interface during the postulated LOCA-Containment analysis:

a.

Reactor Coolant System I

b. Containmut Air Recirculation and Cwling System c.

Enclosure Building Ventilation System

d. En:losure Building Filtration System e.

EBFS Actuation System f.

Main Exhaust System g.

Control Room Ventilation System

h. Control Room Emergency Ventilation System

i. Control Roo'n Filtration System

j. Air Intake System

k. Radiation Monitoring System 1.

Engineered Safety Featutes Actuation System

m. Electcial Distribution System 2.6.4 EVENT DISPOSITION ne Design Basis Accident (DBA) involves a gross release of activity from the fuel to the containment building and release to the environment. Low and high wind speed cases are analyzed for the Unit-2 LOCA releases. Control Room habitability analysis is performed for the following events: Unit 1 LOCA, Unit 2 LOCA, Unit 3 LOCA and Unit 1 MSLB. Reference FSAR Section 14.8.4.3.2.

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2.6.5 FUNCTIONAIJSYSTEM CDCs EVENT 14.8.4:

The Critical Design Characteristics for 16 Radiological Consequences of the DBA are presented below.

2.6.5.1 CONTAIN_httiNT INTFGRITY & RADIATION CONTROL CSF (Offsite Dose Ur.it 2 LOCA) r Functional / System CDCs - Containment circulation fans operate to provide uniform mixing in containment at time of niase.

Reference:

FSAR Table 14.8.4-5 Functional / System CDCs - RB leak rate 0.599a: / s 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,0.259Vday > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Reference:

FSAR Table 14.8.41, Table 14.8.4 5.

Functional / System CDCs - EBFS bypass flow s 1.69% of containment leakage (Iow wind case).

Reference:

FSAR Section 14.8.4.2, Table 14.3.4 1.

Funct8onal/ System CDCs - EBFS negative pressure established within 110 seconds.

Reference:

FSAR Section 14.8.4.2, Table 14.8.4-1.

Functional / System CDCs - EBFS charcoal filter etliciencies 90% elemental 1,70% organic 1,90%

pr.niculate 1.

Reference:

FSAR Table 14.8.4-1 and 14.8.4-5.

Functional / System CDCs - Exfiltration volume for high wind (30 MFH) case is s 10% of EBFS flow rate with I fan operating.

Reference:

FSAR Section 14.8.4.2.

2.6.5.2 CONTAINMENT INTEGRITY &EADIATION CONTROL CSF (CR Habitability Unit-2 LOCA)

Functional / System CDCs - Isolate Control Room (CR) within 5 seconds upon EBFS Actuation Signal (FBFAS) 5 seconds.

Reference:

FSAR 14.8.4.3.2, FSAR Table 14.8.4-3.

Functional / System CDCs - Initiate Control Room Emergency Ventilation System operation at 2500 cfm within 42 seconds of receipt of EBFS Actuation Signal.

Reference:

FSAR Section 14.8.4.3.2, Table 14.8.4-3,14.8.4-7.

Functiona / System CDCs - Control Room (CR) normal make-up air flow rate is 2000 cfm and ramped t

down linearly to zero during the CR isolation period for LOCA events.

Reference:

FSAR Section 14.8.4.3.2, Table 14.8.4-3.

Functiona!/ System CDCs - Control Room Emergency Ventilation System charcoal filter efficiency =90%

for Iodine.

Reference; FS AR Table 14.8.4-3 Fenetional/ System CDCs - Control Room unfiltered leakage in rcirculation mode s 100 cfm.

Reference:

FSAR Table 14.8.4-3.

17 Revision 0 29 September 1997

- 2.6.5.3 C.ONTAINMENT INTEGRITY & RADIATION CONTROL CSF (CR liabitability Unit 1 LOCA and Unit 3 LOCA)

Functional / System CDC;- Isolate Control Room on Air intake high radiation signal within 23.1 seconds.

4

Reference:

FSAR Section 14.8.4.3.2, Table 14.8.4 3.

Egnftianal/ System CDCs - Enclosure Building ventilation rate for external source dose rate n

calculations is 6000 cfm.

Reference:

FSAR Table 14.8.4 5.

Functional / System CDCs - MP 1 containment leakage rate is s 1.2"/dday.

Reference:

FSAR Table 14.8.4-5.

Functional / System CDCs - MP-1 Reactor Building ventilation rate for external source dose rate cdculations is 100*/dday

Reference:

FS AR Table 14.8.4-5, Functionet/ System CDCs - Unit i Standby Gas Treatment System (SGTS) filter efficiency = 90% for all fonns oflodine.

Reference:

FSAR Table 14 9,4-5, i

2.6.5.4 CONTAINMENT INTEGRITY & RADIATION CONTROLSSF (CR liabitabjlity Unit -1 MSLB1 Functional / System CDCs - Unit i MSLB release duration s 5/.) reconds.

Reference:

FSAR Table 14.8.4 7.

Functional / System CDCs - La 1 h1SLB Case. Unit 2 operators assumed to start using Scott Air Packs within 20 minutes.

Reference:

FSAR Table 14.8.4-7.

Functional / System CDCs - Unit 1 MSLB Case. Scott Air Packs effectiveness 10,000.-

Reference:

FSAR Table 14.8.4-7, Functional / System CDCa - Unit 1 MSLB Case. Unit 2 Operators initiate CR purge within 30 minutes.

Reference:

FSAR Table 14.8.4-7.

, Functional / System CDCs - Unit i MSLB Case. Unit 2 CR purge duration 30 minutes to 4 Hours.

Reference:

FSAR Table 14.8.4-7.

Functional / System CDCs - Unit 1 MSLB Case. Unit 2 CR Purge Flow Rate 16500 cfm.

Referencc: FSAR Table 14.8.4-7.

I8 Revision 0 29 September 1997

Functional / System CDCs - Control Room (CR) Normal Make-up Air Flow Rate 2000 cfm ami

.ssumed 2000 cfm all the time for MSLB since isolation occurs at 23.1 seconds, i.e., after completion ofrelease.

1

Reference:

FSAR Table 14.8.4 7, 2.6.5.5 ELECTRICAL POWER CSF Functional / System CDCs 7 ovide elect ical power for accident mitigation loads.

i l

l J-19 Revision 0 29 September 1997

AARSONS POWER System Boundary Diagrams Radiological Events Millstone 2 l

Revision 0

- PARSONS POWER -

Tier 2 Revision 0 29 September 1997

__d

e i

4 i

RARSONS POWER I

System Boundary Diagrams i

?

System Boundary Diagram Symbols M2-T2SBD-SYMB Rev. O j

Reactor Protection & ESAS M2-T2SBD-RPS/ESI Rev.O Reactor Protection & ESAS M2-T2SBD-RPS/ES2 Rev.O Process and Area Rad. Monitoring M2-T2SBD-RADMON Rev. 0 Containment & Enclosure Building Ventilation M2-T2SBD-CEBV1 Rev. 0 Containment Post Incident H Ccatrol M2-T2SBD-H2CTRI Rev.O 2

Main Exhaust M2-T2SBD-ME1 Rev.0 Fuel Handling Ventilation M2-T2SBD-FHV1 Rev. O Control Room HVAC M2-T2SBD-CRV1 Rev. O Spent Fuel Pool Cooling and Purification M2-T2SBD-SFPCI Rev.0 4

Revision 0 1

i i

- PARSONS POWER -

Tier 2 Revision 0 29 September 1997 I

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? k. khe$kf' h' 7 l a-y _ snwnL nnstanmos m Y ACAS CLOSE/STOP a V ACAS OPEN/ START [ k AUX REED INITIATE OPEN/ START [ 9 CIAS CLOSE/STOP O CI AS OPEN/ START [4] CS AS CLOSE/STOP j 8 CSAS OPEN/ START l O DIESEL CLOSE/STOP [ O DIESEL OPEN/ START l - EnrAS CLOSE/STOP [ O - EnrAS OPEN/ START we. y,

L DEEGutJDB 111Gll RAD CLOSE/STOP MSICLOSE/STOP MSI OPEN/STAllT It PS SI AS CLOSE/STOP ANSTEC APERTURE l-SI AS OPEN/STAltT CARD SMOKE STOPS PAN Also Availablo on Apot1uro Card - SMOKE PUltGE SIGN AL SilAS CLOSE/STOP - SRAS START /0 PEN - TUllDINE TRIP 97/00/0/ 9 -O u IPlPARSONS 536852-00085 TIER 2 0 T,,5

U."LJ.4%Hra-

"WbRE 6fiDER Nh.'FIGURE 'M212SBD SYMB ' EEi.~ f? ~~ U systEs counonni oinGnns svMaas !g s, n i diA d/A WIA. bettergt ta tt patt erer t te tt p,Tlaru g ta tt wan

-v I RPS / FSAS SENSOR BOUNDARIES I SLNSOR SERVICE TRIP RPS SETPOINT ACTUATION CH ANNEl s PT +102 A.D.C,0 Wessurlier hessure Low 1850 PSIA DEC, (1)(5) RX TRIP Low Low m.. 1600 ~~ifIgEI~~ 2400 PSIA 1 d~.~iIii5i'(12) RX TRIP ~'~" ~~~~ PI 8113,4,b,6 Contalnment hessure High 4,75 PSIG INC, (3) RX TRIP 4.75 High-High 9.4 PT 1013A B.C,D Steam Generator Pressure Low 680 PSIA DEC. (1)(7)(12) RX TRIP PT 1023.A,D,C,D LowLow 500 LT 3001,2,3,4 RWST Level Low Low 4'( LT 1113A,0.C.D Steam Generarator Water Level Low 30% DEC. (1)(12) RX TRIP 1 LT 1123A,B,C,D High TBD RX TRIP (via Turbine Trip) PDT 111 A,B,C,0 Reactor Coolant Flow Low 4 PUMP. 91,7 % DEC (1)(12) RX TRIP POT 121 A,B C,0 l ST 134,13b,136,137 Henctor Coolant Pump Speed Low 830 RPM DEC.(1) RX TRIP M i T1 112H A,B,C,0 Thermal Margin (TM/LP TRIP) Low Calculated SP RX TRIP TT 122H A,B,C,0 TT 112C A,B,C,0 > - 1850 PSIA DEC (1)(5) TT 122C A B.C,0 Ex Core Nuclear Mon. channels 5,6,7,8 Local Power Density Trip Low 21 Kw/Ft INC. (1)(4) RX TRIP Varlable Overpower Trip < = 9.6% above measured RX TRIP ~ ... W 107 % maximum (1)(12) r

( l EsAs fiEffRENCES ACTUATION @lNT CHANNrts (1) FSAR Table 7.21 (2) FSAR Sedion 7.3.2.2.a (3) FSAR Section 7.3.2.2 b EIA DEC. (2H11) SlAS (4) FSAR Section 7.2.3.3.10 CIAS (5) FSAR Section 7.2.3.3.7 EBFAS (6) FSAR Sedion 7.2.3.3.6 DG START (7) FSAR Sedion 7.2.3.3.5 (8) FSAR Seetion 7.3.2.2 f (9) FSAR Section 7.3.2.2 h (10) FSAR Section 6.2.3.1 LIG INC. (3)(11) SlAS (11) FSAR Sedion 6.3.2.1 CIAS (12) FSAR Table 14.0.71 EBFAS MSIAS (13) FSAR Section 7.3.2.2 d DG START ANSTEC PSIG INC. (3) CSAS hg CARD sTA 65C i~3) MSi~S 4 80 ~ ~ ~~~ 3 DEC. (0)(10) SRAS % DEC. (9) AFAIS r IPlPARSONS 53S852-00085 TIER 2 0 imt.49,'4, tag,5- ~ ~ 6niini(R n5,~ FIGURE 'H2 T2SBD-RPS/ES) ~ Et'. j? ~ ~ w N neacion rnotteti m Esas 1j ni s au JM k 4h?( M A7D Ma&fC L, % 5? f . ~ 4D... .t.. D .,E <..L. ,,t gg dh J/A J/A. twit w aC E Daft >T s as aC E Daf t >f teract Daf t

.~ -- RPS / ESAS SENSOR BOUNDARIES SENSOft SLRVICE 1 RIP RPS SUPOINT ACTUATION CHANNFlS Manual SIAS Manual CS AS Manual CIAS Manual EBF AS Manual MSIAS ^ Manual SRAS = Manual AEAS Manual RX Trip RX 1 RIP Emergency Bus Undervoltage 84 V ( = 294 RM 8139, RM 8142 Fuel Handling Area Hadiation High RM 8156, RM-8157 2 Time RM B123A,B Containment Radiation High RM 8262A,B RM 8240, RM 8241 Containment Radiation High PS4597 A B.C.D Turtune EHC 600 PSIG DEC, (6) RX TRIP (3) Low Hydraulic Fluid, Pressure AUTOA% TIC WITHDPAWAL PROHIBIT INTERFACE BOUNDARIES COMPONENI ID SERVICE SETPOINT TT 112H A,B,C,0 Thermal Margin (TM/LP) Pre Trip 75PSIG ABOVE TRIP SP (4)(5)(6) TT 122H A,B,C,0 TT 112C A D C,0 TT 122C A,B,C,D Ex Core Nuclear Mon. channels 5,6,7,8 Variable Overpower Pre Trip (5) TBD i p+ ve

ESAS REFERENCES ACTUATION T CHANNrt s (1) F3AR Fi ure 7.3. 3 0 =- SIAS (2) FSAR Figure 7.3.1 sh.1 CIAS (3) FSAR Section 7.4.6.3.3 EBFAS (4) FSAR Section 7.2.3.3.7 (5) FSAR Section 7.4.2.4 CSAS (6) FSAR Table 7.21 r CIAS EDFAS NOTES: MSIAS

1. The trip ts set on the 120v side of a 4200/120v PT and corresponds to the 4KV level shown.

SHAS AEAS w/o EBFAS ANSTEC APERTURE LTS DEC, (1) DG START Pv See note 11 Background (2) AEAS w/o EDFAS Also Avallable on Apettuto Card 180 CPVIS 1BD Containment H2 Purge Valves Close 00 0 {PlPARSONS 536852-00085 TIER 2 0 c.t ' g gR'd ~ FIGURE 'H212SBO-RPS/ES2 ~ REY. h

o... ~ i c-

~ y iI REACTOR PROTECil0N & ESAS h ~s e g %t fMr1fn(A /keflytWInW~.rJWias. ... c... q~ N/A d/A N/A ......o (.wree 3 i

RADIATION MONITORING SEb COMPONENTID SERVICE COMPONENT ID i RM-8139 Spent Fuel Pool Area

RM-8240 Conta RM 8142 Spent Fuel Pool Area
RM-8241 Conta RM-8156 Spent Fuel Pool Area
RM 5099 SJA RM 8157 Spent Fuel Pool Area
RM-8132A Stack RM 8123A Containment Area
RM-8132B Stack RM-81238 Containment Area
RM 8168 Stack RM 8262A Containment Area
RM-7891 Serv RM 82628 Containment Area
RM 7892 Drum Dect The Radiation Monitors listed above are used for accident monitoring and, in some cast with an asterisk (*). For specific ESAS applicability see RPS/ESAS Boundary Diagram I

i N MY& E 9

C bR BOUNDARIES i RVICE COMPONENT ID SERVICE nent Area

RM 7894 Charging Pump Area nent Area
RM 7895 Gampling Room Sischarge RM 7896 Waste Processing Area

' fluent Gas RM 7899 Control Room Muent Gas RM-4299A SG #1 Main Sham Line ANSTEC tuent Gas RM-42998 SG #1 Main Steam Atm. DLmp APERTURE i Platform RM-4299C SG #2 Main Steam Line , amination Area CARD l are used for ESAS functions. Those used in the ESAS are marked a a e on pc l t 0 0 / 57 b PARSONS 536852 00085 T!ER 2 0 N g W 9".' '9 %',t " %.t P ~ "WERE i)R'0E"R N0. FIGURE 'M2 T2SBO-RAOMON ~ Qi,' p ~ ~ ra0 cess mo anta ne.eironx g A_ <r/ i 09 S $ S.,,1ls/11 $ U $ flSk f dS&2[f7 $$ i o ,,t., ott Alls d/A

g/A p~

.a. ,,e m'twact .rt witwact .rt inttwact .rt - n.

P' 7.._.._.._....-.._..-.._._.._._._._......._ l j 7., N. 4%- o. / \\ l / \\ FROM He. l / runt.E l SYSTEH - I \\ W I E37 l w ~.eauuNU.m I I l AC-$ + AC.4 i I e l l -O AC-1 l l 1 [ k I l e e)F-23 l 2 T W l u 3 l

(X350MJ I

WT PURGE SUPPLY t#417 v CONT AINMEN T I -* (X-35C h J l

{ X 35D }*- RBCCW a{__x35A h-RBCCW l

t l l l [e [e a { ( l M 4C (. l N a F-140 0 1 b T4 r -140 r.14 A (M EB 73 l l } l l---- F-~ F--- l l 1 l l i t F~ -FUS!BLE LINK i y l j e PL ATES tivP.) l o ettuun Q { g = l l CONTAINMENT AIR PECIRCULAi!ON l i l y, a AND COOLING UNITS (di W,C EB-72 { l l i ( l l 3 l I l gxQky _ 'I T LP I } I { [y t ' 3e CONTAINMENT 5 t S TEM g 'ac.'y l Ck L._._._._._._._._._._._._._._._.J l l L.._.._.._.._.._.._.._.._.._.._.._.. _.. _.. _.. _.. _.. _.. _,._

= l -rRCH Etr R00,4 'l )E BulLOluG IIL1RA110tJ StSTEH <[Drs ELEDcs ^

HIGH RAD ELOSE/STOP l

f EBr5 PLEM M 6 - SIAS OPEtJ/ST Af ti (Low Sr((D' U - EBf AS OPEtJiST Ant I ( l $ - E t,r AS ELOSE /S T OP F h l O. CIAS OPEN/ST Ant Q 401E 3 0 - CIAS CLOSE/$10P $'c,.EB-40 l V - AE AS OPEN/SI ART Y AE AS ELOSE / ST OP 4,;N'. h e f ;. [O D~,J EB 50 i _. 3pagg.g.OR COMM0t4 FLOW FATH IJ0TE 3 @u l -e-Et4C LOSURE ) AC-3 i I l 40TES:

l. ALL COMP 0tJEH1 1.0.'S ARE FRECEEDED BY '2 ' UNLESS OTHERWISE #40f ED.

g

2. orc"5 o" atas ir "o teras ANSTEC

3. ELOSES 014 AE AS Ir f 40 EBr AS APERTURE CARD 4l50 AvallUbl6 On

10 UNIT l 4 orturo Card 9

P j StAtx OV OV OV 7 l L.v 4 7 ' +.7 m,noH S m,ANS ,mH 2, L2 L.z,. g EB-55 EB-56 EB 51 F 25A L},, V HCC 22-2E NOTE 2, EEEEEEUCE18 EB-[0 25203 26028. SH.l. REv. 30 NOTE 2.__.FROH rbEL HANDLlHG SYSTEH 25203-26028. SH.2. REV. 35 7 l 25203-2E,020. SH.3. REV.10 y 25203-26028. SH.4. REv. 7 eu-EB-61 25203 26028. SH.5 REY.15 Qp 7.. CV Ov ~ p# 3*tt. EB 42 l lL-298} 'L EHUM j l EB-41 r-250 / {a_ HCC 22-2F I t 0 {o b PARSONS 53s852-e0085 TIER 2 FIGURE 'H2-12SBD-CEBvl 'EEi.'p i +0.. - c. VORK ORDER NO. 8[ CONTAINMENT AND ENCt0sVRE Butt 0 LNG js vtNiitAtioN sistm YN / 10 0 0 C Q f,gd. / ['[

j 8 _IY I

Det I 8, v5 w,0 <*,( / APPa05,D e ORicle,,0 Dn,t p/A mn WIA ? u'

e% + ~,. [NCL1 's / 7 AW > l 7' l \\ / IH0H H \\ f. l / PUPC.E SVS1EM-l / l \\ I ~. Q. - \\ pn l -* - l tod j Iod ENUMl AC-5 AC 4 I I i l l I I -r AC l 1 I l e I I e r-23 j h b I l } 3 CONT AINMENT f PURGE Sur' PLY LNil u 3 u l T a T i l E u y l

] x 350 h J l

g q x.y,c hJ g ad x-350 h-ABCCW a d x-35A l-s-RBCCW f l l o j o l i e. a I ea i ,+ i . a . a i g F -14 B F 14C g*, -. '.ta.73 l F -140 %4A l l f~ W V---' > 5-- I h '-FUStBLE LINK j l PL ATES (T YP.1 l Q ^ e o l NENUM W l l v,__ l CONTAINHENT.41R RECIRCUL ATION AND C011NG UNiiS (4> l @H ED-72 I I l r l 1 l L l l l I I .s p T ^ CONTAINMENT l EX U 'M' S15iEM " l AC-6 PURGE EXHAUST l AC-7 l l L._._._._.._._.._._._._._._._..._..J L.._.._.._..._.._.._.._.._....._.._..._..._.._.._.._._.._..d 1 W 0 I _..a

- rROM E tr ROOM > ~ ~ *. - -.. - -. ~.. -.. _. CE Dull 0140 Fit tRA1104 StSTEM iEprSi . _l } l LLELtDJ EBr$ PLtNuH l

f HlGH RAD ELOSE/STOP q

l A SIAS OF'EN/ST ART (LOW SF E ED) { O - EBr AS OPEN/51 AR1 4 EE; RAS CLOSE/SIOP O r."UIL 3 l 0 - ElAS OPEN/st ART h* EB 40 l 0 - CIAS ELOSE/STOP i V - AE AS OPEN /ST ART Q l Y AEAS CLOSE/STOP ug

g. 'g g,,,. g

) - - 1 RAIN 'A' 0" COMMON F LOW FAT H +J --= ENCLOSURE N01E 3 AC-3 g l l l l l Noit s,

l. ALL COMP 0tJENT l.0.'S ARE PRECEEDED g

BY '2

UNLESS OTHERWISE NOTED.

ANSTEC 2.OrENS ON,.EAS ir EerAS

3. CLOSES 04 AE AS IF 40 EDFAS AP.E. RTURE l

CARD i ' SB'N 2 AIM Avalleble on CV A erturo Card P .O V 09 N .T I 3 3 (NUM l .y=====5T~2 l D2 ^ EB-51

F ROM SJ AE F ANS g

EB 55 EB 56 F 25A V HCC 22-2C 001E 2 EB 0 BLEifLtCESi NOTE 2._ FROM FUEL 25203 20028. SH l. REY. 30 HANDLING SYSTEM g 7 25pg3 26028. SH.2. REY. 35 I 25203 26020. SH.3 F<EV. la e o EB-6l l 25203-26028. SH.4. REV. 7 Q7 g 25203 20028. SH.5, REY.15 OV 0v ] l UJUM ' lL -24BI E 2 EB 41 l F-25B HCC 22 2F l / ..-...-...I &q_ LP_) PARSONS 53s852-00085 TIER 2 0 {b ' ~ 5si ~o& Rid.' FIGURE 'M212SBO CEBvl ' EEV. Q

n n..s-m m. e -

~ w p amamni mnctosunE ouiEoinc VENTILATION Sts1EM j$ e ,n o n n 8 _IY / -,, uf,a,, 7 ee 9/A diA N/A ye

e .-+--*.s,%, p l l N y e ). l ft f l S '" E3SFe\\ e,N7 0* Hi t*<0 GEN I / PUR(E k SYSTEM Poj \\ PJ l / E0 100 ' EB 99 ENCLOSURE l 2$@\\ @bTs's"0: DillLDit4 l O* i I l g x r l l EB 91 EB 92 ~ l l l l SSl &S EB 89 AC 47 g l l _.sG! 046 EB 88 AC 12 o I I I f?< /*( / ( 9' Sa 1 l 1 I w i / / i B i i i S-4. 8 e]vge]v - u.. ~pf - [ l r .c l l v A v l u my O 0 l POST INCIDEN) log nECint sysrEM o l l AC 15 esse 4 i AC.2e y l j g_g__g_g nu A a sTanM l I I I a 8.24 i j l I I s l l f ER l era. '45, REC E l l H 290 i I I I L. _. _. _. _ _. _. _.. _. _. _. _. _.._. _.._..J l l L.._..._...._..._.._....._.._.._.._.._.._.._.._.._.._.._..,

)t 05E I LLLLtos l V P'GH RAD Cl.0$E/$10P l 9 'lAS ELOSE/STOP l TRAIN 'A' OR COW 10N FL OW FA1H I I e I l l l talte

1. ALL COMPUNENT !.0.'S ARE PRECEEDED I

Bf '2 ' UNLESS OTHERWISE NOTED. I &Il ANSTEC APERTUR E CARD l l Also Available o i Aperture Card I g REFERENCEL 25203 20028. SH.2. REV. 35 25203 26026. SH.3 REV. le 1 1 I l b PARSONS 536852 00085 TIER 2 0 ' g 3g0ER d ~ FICd)RE 'M2 T2SBD-H2 CTRL ~~ ~ i. ~ h ..u mi .o.

- i.

y RE h, CONTAINHENT POSI INCIDENT H2 CONTRk 3p o. /1 4., W rAA m )_W?..&h7Vd...,_A1$'L97 WYlds..k.Q.. 1 ( r. r/4

g dA WA S

,..e 1.

on,., ai. I l l l l l / l / l I I I I I l (3 . _ FROM Coto. l l AIR ACH0 VAL l u F-34A cr

~ F HOH HADW A51E l

\\ FROH FUEL ~~ gy; hat 0 Lit 0 l g (, ' g$ AC'8 7$h V F 340 FROM A.EAATED o i m:$ I_ a c wasic.ss nEAocn o & SOL;i-RADWA510 [3 6 T l 8" 1 o C EE) inLEta: 'T - I Y.,e .,J Ac in L25 Ac 57 Ac.7 ! Ac 6 r.34c b 7 --- 0.A. -f-i L*-- dg AC $9 a L.._.._..._.._ s l a

a 2 LLLt.tG e,s. HIGH RAD CLOSE/Stor EtJCLOSLEE BUILD!'4Gl O - CIAS orttusf Ani S - CIAS ClosE/STOP l -- 1 RAIN 'A' OR COMMON rLOW F ATH \\, \\ I \\ \\ l I I I NOTEsa

l. ALL COMPONENT l.D.'S ARE PRICEEDED I

l BY '2 ' UNLESS OTHERWISE NOTED. i l I I I ANSTEC I F r*ONT AINHEN T C ct t="aust I APERTUR3 i CARD I ( ' -- ~ - ' - ' T o 704Ti6HTNi T ' - ' J l Also Available o i tNCtostmE nuiLoiNo Aperture Card (,,_, vtNilLAllON SYSTEM , _,, _,l BfifBE!KILs 25203-20028 SH.l. REv. 30 25203 26028. SH.2. REV. 3$ IFlPARSONS 536852-00085 ilER 2 0 s

M f M P & Mff 4

' ' WORE i)Ri[R35.' FIGURE *H212SBO-MEl ~ EEi.~ 4 9 ff MAIN EXHAUST 3 E. . x 1 -2. J n [ W_ /,, g / f" l.11 / % $,.N W NA<h4,,?k $$ ee _ b. l{ ' Onl11 N/A A)/A. "~ ik,t W WE Datt tuttsa gt te rg ges tg M M E tatt y-.-.

s 4 p..-..-..-.,..-..m l 1 1 1 l l t t t l Y gill l l SUPPLY FILTER & FAN HE AilNG NEW FUEL O.A + l 1, X. 41,I [) STORAGE y Hy. it.5 l l SPENT FUEL POOL AREA F-20 NOTE 2 l l I I T r i TO ENCLOSURE DUILO!NG _ FILinAil0N SYSTEM

N9

w-.e Lf&UJD1 Y AEAS CLO!E/STOP - 1 RAIN 'A* 00 COHHON FLOW F' A T H

r ** t.FAS g j g,ygg g ANSTEC h-l APERTURE l

3. _l CAno b

I8.$7d"sifa Y Y t10lfSA kENUMj 44 *

1. ALL COMPONENT ID'S T'RECEEDEO ny.g7g g'y.g7g BY '2

UNLESS OTHERWISL NOTED.

2. INTERLOCA W!!H MAIN EXHAUST F ANS.

l l l l 8144 1, A MAIN ~ FIL1ERS 4AUS T *

H, lL 27 l ENUM Hy-3 73 M

llEE.f.fitEESJ 25203-26028, SH. 2. REY. 35 25003 26028. SH 5. REV,15 25203 26029, SH,3. REY. 7 0 / 6 [PlPARSONS 536852-00085 ilER 2 0 ~ ~ 5n Bnis~ts.- FIGURE 'H212SBD FHVI ~ RE'. ' h7

= w c m a -

w N FLEL HANDLING VENI!LAil0N j8 A K/, f $ n msn 8 E, NW AS W,,#/W.l$mn.....,,, /kh f --Y "g e sh.h, an WA. lNf(W AC I DAff lNT(M M E (e f f lNT[W M( [mf[ g_.

4

- O
p-10 Alla. PtillDING F 3] A

( p Hy.phy Hy,497 blNilLAll0N S 51[H Hv tocA 1

- O FLENUM

~~ y.,_. y. ogQ* ru NU- _ t.A. HV 200 HV 496 ) gy. ppg,g F J10 k* k* V*f-v *y- - ~~ PLENUM OUTSIDE ~ HVh02 "IN Hy.495 i 11 O s,6 V I"@y l Hv-210j'-@ Hv 211 O L304 e l Pl4lC l Hv.212A L Hy.213; [f[h C$Ni o PLENUM F IL T RAlloN -> CONT UNIIS O-o L300 7 { l Pl AlCl Hv.21;0 HCCl P l rp I424 I x428 lCCl P l P h -* 10/FC RE FRl CONF ( CONTROL ROOM

l w-* l i LC.L'L!OJ V AEAS Ol'EN/ START y - AE AS CLOSE/STOP [ Q - LBrAS OPEWST ART 4 EBrAS CLOSE/StOP 8." - HIGH RAD CLOSE/St0P O SHc* E PURGE $1GNAL B SMOLE STOP FAN IRAlti 'A' OR COMMON FLOW PATH tQ1LSs

1. ALL COMP 0tJENt 1.0.'S ARE PRECEEDED BY '2 ' Ul4LESS OTHERWISE NOTED.

ANSTEC APgGTung CARD

eRAN,

,e ReaH w Al*o Avallab Ca) 7 CONTROL ROOH 496ttuII Carg8 Ort A;, HAD HON)iOR HU 203A F47 R00 Of y I F2iA ^ g REFERENCEL 25203 20027 SH 3 REV 20 HU-203B F21B PLENLIM TH ERAN7 1L A00H 'O' l k. b PARSONS 8* 536852-00085 TIER 2 0 '5

.rmcm e-

~ dRE UR'DE'Rl5.~ FIGURE 'M2-T2SBD CRyl ' EE Y. 'n CONTROL ROOM HVAC k 9 9 / f.&_,, b.$1N m 5b gy/f] SC h.-..a...wa Nf7 f q" dia 4/a JIA.

% s. - F19w SY Rw 137 { A NOTE O ~ EMERGEtJC v tw E -UP wATE k F ROM Auw. ret D TEMP 0hARi CotJuf C110N { SHUT-DowtJ HEAT E ECtw n D I Stull.J.itL CDQL %) -l L t< gY l a W P21 hV [) o W o L19A Ll90 P L Sk R PUMP l t SPENT FUE L POOL SK!MMER FILife.a PIM Pld RBCCW RBCCW t i P13B !*20A ] ! *2N ! P14! r ) f RBCCW RBCCW SPENT FUEL REFUEllH POOL COOLING SPENT FUEL POOL PURlFIC All' PUMPS ME AT EXCHANGE RS FROM RWST 1 .~ % m

. =.

LLCitG

- - TRAIN 'A* 0R C061MotJ F LOW PATH I H -

TO RWS1 7

SPEtat rVEL POOL k, DEMINERolllER 'M

l. ALL COMPorJENT 1.0.'S ARE PRECEEDED BY '2 ' UMLESS OTHERw!SE NOTED.

l /

2. CLOSES ON HIGH FLCL POOL LEVEL.

A l\\(y AP5pf Q CArig Alao %* $$*hlljn I0^ REFERENCEL 25203 2E.O. 3 SH.2. REv.12 LIBB N' SOENT FUEL POOL FILTERS )MPS )/ V [P] PARSONS 536852-00085 UER 2 0 jS ' ' if2 [)RDER t5. - FIGURE 'M2-T2SBD-SFPCI ^ EE. {y ~~~ '229"2th",,Mf M - ~~ W hof SP[N1 FUEL POOL C00llNG AND PURiflCAll0N gg O k' thth7 [g/wyegdY_m.. -,,' e'. alA d/A d{A. , ~,...,,,, m r,m a _ _. _ -. - -.}}

ML20211F717

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