ML20052F110

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Slide Presentation Entitled Containment Sys
ML20052F110
Person / Time
Site: Clinch River
Issue date: 04/01/1982
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20052F101 List:
References
NUDOCS 8205120126
Download: ML20052F110 (20)
v • d • e


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O CRBRP WORKING MEETING FOR NUCLEAR REGULATORY COMMISSION CRBRP PROGRAM 0FFICE

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CONTAINMENT SYSTEMS

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PRESENTED BY S.J.. WORCESTER MANAGER, NUCLEAR / MECHANICAL ENGINEERING BURNS AND ROE', INC'.

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.I CbNTAINMENTSYSTEMS 4.

- e CONTAINMENDCONFINEMENT FUNCTIONAL DESIGN

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e ACCIDENT LEAKAGE e

e CONTAINMENT VESSEL VACUUM' RELIEF SYSTEM ~

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CONTAINMENT / CONFINEMENT FUNCTIONAL DESIGN e

CONTAINMENT VESSEL

~e CONFINEMENT STRUCTURE e

ANNULUS FILTRATION / PRESSURE MAINTENANCE SYSTEM

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e REACTOR SERVICE BUILDING-(RSB) FILTRATION SYSTEM -

e DESIGN BASIS ACCIDENTS 4

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o CONTAINMENT / CONFINEMENT FUNCTIONAL DESIGN CONTAINMENT VESSEL STEEL VESSEL AB0VE MAT - STEEL LINED CONCRETE MAT e

e DESIGN. TEMPERATURE:

250 F e

DESIGNPRESSURE:

10 PSIG INTERNAL 0.5 PSIG EXTERNAL 6

e FREE VOLUME:

3.6 X 10 CU FT. (ABOVE OPERATING FLOOR, EL. 816')

6 1.4 X 10 CD. FT. (BELOW OPERATING FLOOR) e REINFORCED CONCRETE INTERIOR STRUCTURAL WALLS AND EXTERIOR BUCKLING WALL BELOW OPERATING FLOOR 9

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.'V CONTAINMENT / CONFINEMENT FUNCTIONAL DESIGN CONFINEMENT STRUCTURE e

REINFORCED CONCRETE TOTALLY ENCLOSES CONTAINMENT VESSEL AB0VE FOUNDATION MAT FORMS CONTINUOUS ANNULAR SPACE SURROUNDING CONTAINMENT e

VESSEL e

ANNULUS FILTRATION SYSTEM MAINTAINS.1/14 INCH W.G.

NEGATIVE PRESSURE AND FILTERS EFFLUENT DURING NORMAL AND ACCIDENT CONDITIONS O

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CONTAINMENT / CONFINEMENT FUNCTIONAL DESIGN

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REACT 0ilSERVICEBUILDING(RSB)FILTRATIONSYSTEM.

MAINTAINS 1/ll INCH W.G', NEGATIVE PRESSURE AND FILTERS e

EFFLUENT IN CONFINEMENT PORTION OF BUILDING DUR'ING NORilA AND ACCIDEitT CONDITIONS 1

CONFINEMENT PORTION OF BUILDING ENCOMPASSES ABOVE e

OPERATING FLOOR REGION AND SELECTED FUEL HANDLING SYSTEM AREAS O

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CONTAINMENT / CONFINEMENT FUNCTIONAL DESIGN DESIGN BASIS ACCIDENTS l

STRUCTURAL PRIMARY S0DIUM STORAGE TANK FAILURE WITH

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CELL OPEN (NON-INERTED)

APPROX. 180,000 LBS, 0F S0DIUM BURNED MAXIMUM PRESSURE:' O.8 PSIG:(20. HOURS) t RADIOLOGICAL SITE SUITABILITY SOURCE TERM 100% N0BLE GASES d

50%

HAl.0 GENS (25% AIRBORNE) 1%

FISSION PRODUCT (SOLID) 1%

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ACCIDENT LEAKAGE LEAKAGE PATHS CONTAINMENT VESSEL - C.0NFINEMENT ANNULUS CONTAINMENTVESSEL-S.TEAMGENERATORBUILDING CONTAINMENT VESSEL - REACTOR SERVICE BUILDING CONFINEMENT AREAS CONTAINMENT VESSEL - REACTOR SERVICE BUILDING NON-CONFINEMENT AREAS I

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o ACCIDENT LEAKAGE LEAKAGE BARRIERS PATH FILTERED UNFILTERED BARRIER

. ANNULUS' RSB~

RSB

'SGB VESSEL SHEL'L & REFUELING HATCH X

EQUIP./PERS. AIRLOCK X

EMERG AIRLOCK X

PENETRATION CLOSURE ASSEMBLIES X-1 PENETRATION VALVES X

X VACUUM RELIEF VALVES X

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I ACCIDENT LEAKAGE e

" BYPASS LEAKAGE" (BTP CSB 6-3)

THAT LEAKAGE FROM PRIMARY. CONTAINMENT WHICH CAN CIRCUMVENT THE SECONDARY CONTAINMENT BOUNDARY AND. ESCAPE DIRECTLY TO THE ENVIRONMENT,-I.E;.' BYPASSES THE LEAKAGE COLLECTION AND FILTRATION SYSTEM 0F THE SECONDARY CONTAINMENT e

FOR CRBRP, BYPASS. LEAKAGE IS THAT LEAKAGE ESCAPING FROM CONTAINMENT TO STEAM GENERATOR BUILDING OR THE NON-CONFINEMENT AREAS OF THE REACTOR SERVICE BUILDING t

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ACCIDENT LEAKAGE e

DESIGN LEAKAGE FROM CONTAINMENT VESSEL O.1 VOL. %/ DAY (3600 CU. FT./ DAY) 1 e

DESIGN LEAKAGE FROM CONTAINMENT VESSEL TO CONFINEMENT ANNULUS OR RSB FILTRATION SYSTEM 0.099 VOL, %/ DAY (ANNULUS) + 0.0004 VOL. %/ DAY (RSB FILTERED)

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(3,564 CU. FT./ DAY)

(14.4.CU. FT./ DAY) e DESIGN BYPASS LEAKAGE:

FROM CONTAINMENT VESSEL Tb SGB OR RSB (UNFILTERED)

.0006 VOL, %/ DAY (21.6 CU. FT./ DAY)

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ACCIDENT LEAKAGE AT DESIGN PRESSURE (10 PSIG)

MAXIMUM KAXIMUM.

EXPECTED ALLOWABLE LEAKAGE PENETRATION LEAKAGE LEAKAGE **

LEgKAGE**

3 FT / DAY E / DAY PATH TYPE BARRIER _

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BYPASSi.EAKAGE Decontamination Valves'

.025

.100 RSB(unfiltered)

Waste Water' Return

.025

.100 RSB (unfiltered) -

Caps Inlet Header Valves

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Post Accident Valves

.017

.068 SGB(unfiltdred)

Monitoring Sample Line Post Accident Valves

.01 7

.068 SGB(unfiltered)

Menitoring Sample Line Post Accident Valves

.017

.068 SGB (unfiltered)

Monitoring Sample Line, Post Accident Valves

.017

.068 SGB (unfiltered)~

Monitoring Sample Line Post Accident.

Valves

.01 7

.068 SGB (unfiltered)

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Monitoring Sample Line Post Accident Valves

.017

.068 SGB (unfiltered)

Monitoring Sample Line Sampling Line Valves

.0085

.034 SGB (unfiltered)

H2 Suction & Return H2 Sampling Line Valves

.0085

.034 SGB (unfiltered)

Sucticn & Return Pressure Instrument Valves

.0085

.034 SGB (unfiltered).

Lini Pressure Instrument Valves

.0085

.034 SGB (unfiltered)

Lina Containment Air' Valves

.203 -

.815 RSB (unf.iltered)

Exhaust No Trans. Line Valves

.0.34

.136

- SGB(unfiltered)

No Tra.ns. Line Valves

.025

.100 RSB(unfiltered)

NcK DHRS (from,)

Valves

.051

.203 RSb(unfiltered)*

NcK DHRS (to)

Valves

.051

.203 RSB(unfiltered) i 1

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ACCIDENT LEAKAGE ATDESIGNPRESSURE(10PSIG)

MAXIMUM MAXIMUM EXPECTED ALLOWABLE KAGE LEAKAGE leg / DAY **

PENETRATION LEAYAGE LEAKAGE 3

TYPE BARRIER -

.FT / DAY.**

FT PATH Val'ves',

.20.3

.812 SGB (unfiltered).

Containment ir s

Supply RSB (unfiltered),

Containment Purge Valves

.203

.812 Line Containment Purge Valves

.203

.812 RSB (unfiltered).

Line Containment Vent Valves

.203

.81 2 SGB(unfiltered)

Line Containment Vent Valves.

.203

.812 SGB (unfiltered)

Lina Instrument Air Valve s

.025

.100 SGB(,unfilterbd)

Service Air

. Valve s

.025'

.100 SGB(unfiltered)

Emergency Chilled Valye s

.'025

.100 SGB (unfiltered)~

. ater (Supply)

W Emergency Chikled Valve s

.025

.100 SGB (unfiltered)'

Watcr(Return)

Decontamination Valve s

..025

.100

'RSB' (unfiltered)

Water Supply Argon Supply Line Valves

.017

.068 RSB (unfiltered)

Sample Gas Return Valves

.'01 7

.068 RSB (unfil.tered)

Sample Gas Supply; Valves

.017

.068

'RSB (unfiltered)

M2 Supply Lin'e Valves

.017

.068 RSB (unfiltered)

Emerg:ncy Chill 6d Valves

.025

.100 SGB' (unfiltered)

Wat;r (Supply) 4 Emerg:ncy Chilled. '

Valves-

.025

.100 SGB- (unfil tered).

Watre(Return)

Floor Drain Sump.

Valves

.051

' RSB (unfiltered)'

.204 Discharge

.272 SGB (unfil'tered)

Normal Chilled Valves

.068 Watcr Supply s

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ACCIDENT LEAKAGE-AT DESIGN PRESSURE (10 PSIG)

MXIMUM MAXIMUM

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EXPECTED-ALLOWABLE ~

LEAKAGE LEgrAGE

'PENETR TION LEAKAGE LEAKAGE **

'FT / DAY **

PATH 3

FT / DAY TYPE BARRIER l

' Nonnal Chilled Water Valves.-

.068.

.272

. SGB'. (unfil tered),

Re' turn

. Nonnal Chilled Water. Valves

'.051

.204 SGB(dnfiltered)

Return Nonnal Chilled Water Valves

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.204

.SGB(unf.iltered)

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Supply Nonnal Chilled Water Valves

.05) 204 SGB (unfiltered)

Return

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.'204 SGB (unfiltered)

Nonnal Chilled' Water Valves

.051 Supply

.204 SGB(unfiltered)

Nonnal Chilled Water Valves

.051 Supply

.204 SGB(unfil.ered) t Nonnal Ch'illed Water Valves

.051.

RettiHi

~ SGB (unfiftered)

Emergency Chilled' Valves

.017

.068 Wat:r Supply Emergency Chilled Valves

.017

.068 SGB (unfiltered)

Water Return Emergency Chilled Valves 017

.068 SGB (unfiltered)

Water Return Emergency Chilled Valves

.017

.068 SGB (unfiltered)

Water Supply Emergency Chided

-Valves

.017

.068 SGB (unfiltered)

Wat:r Supply,

Emergency Chilled Valves

.017

.068 SGB (unfiltered)

Wat r Return Fire Protection

. Valves-

.034

.136 SGB (unfiltered).

Standpipe Valves

.0085

.034 RSB (unfiltered)

Liquid N2 Emergency / Personnel Compression Gaskets 8.126 RSB (unfiltered)

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TOTAL BYPASS LEAKAGE 10.57 21.6 I

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MAXIMUM MAXIMUM

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EXPECTED ALLOWABLE leg /DAYKAGE g,

- LEAKAGE DENETRATION LEAKAGE LEgKAGE,

FT PATH TYPE BARRIER,

- FT / DAY 2.

LEAKAGE TO ESF FILTRATION SYSTEMS _

El.cc. Penetrations Compression Fitting 2.72 10.88 Annulus (filtered)

Cerami,c Seal

.408-Annulus (filtered)

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Containment Vacuum Valves

.1.02 Breaker Valve Containment' Vacuum

Valves,

.102

.408 Anndlus (filtered).

Breaker Valve 25.124 Equipment / Personnel Compression Gaskets 16.252

,RSS(filtered)

Airlock Annulus (filtehed)

Shell/ Refueling Welds and Hatch Compression Gaskets

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Penetration Welds Annulus (filtered)

Closure Assemblies TOTAL LEAKAGE TO 3,578.4 ESF PILTRATION SYSTEMS:

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ACTUAL CUBIC FEET / DAY.(i.e.10 psig, 250 F) m 9

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REACTOR CONTAINMENT SYSTEM VACUUM RELIEF SUBSYSTEM A NEGATIVE PRESSURE IN CONTAINMENT CAN RESULT FROM' e

COOL-DOWN AND OXYGEN COMBUSTION AFTER A DESIGN BASIS -

ACCIDENT A CONTAINMENT VACUUM-RELIEF SYSTEM IS PROVIDED TO e

LIMIT THE DESIGN NEGATIVE PRESSURE IN CONTAINMENT ~

TO A VALUE BELOW 0.5 PSIG TWO SETS OF SERIES CONNECTED VACUUM BREAKER SELF-e ACTUATED VALVES (ONE VALVE LOCATED ON EITHER SIDE OF RCB SHELL) ARE PROVIDED 6

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REACTOR CONTAINMENT SYSTEM VACUUM BREAKER VALVES DESIGN BASIS e

SAFETY CLASS 2/ SEISMIC CATEGORY I l

VALVE CODE CLASS - ASME SECTION III, CLASS.2 e

CLASS 1E VALVE POSITION STATUS INDICATION IS PROVIDED

.e IN THE CONTROL ROOM ON THE. CONTAINMENT ISOLATION P NEL e

SETPOINTS:.

dPEN 0.12 PSIG CLOSED - 0.06 PSIG EACH VALVE !3 PROVIDED WITH FOUR LIMIT SWITCHES.

THREE e

LIMIT SWITCHES FOR VALVE CLOSED INDICATION AND ONE 1

LIMIT SWITCH FOR VALVE FULL OPEN INDICATION CONTROL ROOM ALARMS WHEN ANY ONE OF THE 3 LIMIT SWITCHES s

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