ML092470413

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Final Safety Analysis Report, Amendment 94. Watts Bar Nuclear Plant Containment Peretrations and Barriers- Table 6.2.4-1
ML092470413
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 08/27/2009
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
References
Download: ML092470413 (69)
v • d • e


Text

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AND BARRIERS-TABLE 6.2.4-1 AMENDMENT^^

PENETRAT l ON D A T A I

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PENETRATION DATA VALVE DATA

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ABBREVIATIONS FOR TABLE V A L V E TYPE ACTUATORS ISOLATION SIGNAL GL = GLOBE GA = G A T E BF = BUTTERFLY CK = CHECK R V = R E L I E F BL = BLIND F L A N G E TC = TEST CONNECT l ON T V = TEST VENT WV = WAFER V A L V E D

= DOOR A 0 = A I R OPERATED MO = MOTOR OPERATED OPERATED l LRT C

= CLOSED 0

= OPEN CV = CONTAINMENT VENT l SOLAT l ON PA = PHASE A P B = PHASE B PC? = PUMP RUY i

CP = CONTAINMENT PRESSURE S I = SAFETY 1 NFECT 1 ON A F l S = A U X I L I A R Y FEEDWATER ISOLATION SIGNAL MS = M A I N STEAM ISOLATION SIGNAL I FW = FEEDWATER I SOLAT I ON S l GNAL I BA = BALL I

AND BARRIERS-TABLE 6.2.4-1, AMENDMENT 85 ABBREVIATIONS FOR TABLE ACTUATION MODE VALVE P O S I T I O N S RM = REMOTE MANUAL 0

= OPEN LM = LOCAL MANUAL C

= CLOSED 4

I SA = SELF ACTUATOR V

  • V A R I E S A T = AUTO TRIP A l = AS IS PROCESS F L U I D STATE POSS l BLE LEAKAGE PATHS C

= COLD H

= HOT SEE FSAR SECTION 6. 2. 4. 3. 1 F L U I D BU l LD l NG STRUCTURES A

= A I R 111

11) A T r n W

= W H I L K S

= STEAM N

= NITROGEN 1

= I C E CB = CONTAINMENT BUI LDING SB = SHIELD BUl LDING AB = A U X I L I A R Y BUl LO ING

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AND BARRIERS-TABLE 6.2.4-,.

AMENDMENT 85 1 /

I.

A DASH I S PR l NTED I N DATA SPACES THAT DO NOT APPLY TO THE PENETRAT ION BE I NG DESCRIBED.

I I I I 2.

AN M AT THE END OF A CONTA l NMENT OR S H l E L 0 D U l LO ING PENETRAT ION NUMBER INDICATES THE PENETRATION WAS MORE THAN ONE L l N E GOING THROUGH I T.

I I 3.

P l P l N G SYSTEMS ISOLATED BY A CONTAINMENT V E N T I L A T I O N (CV) SIGNAL ARE ALSO ISOLATED B Y A PHASE A S I G N A L.

1 4.

P I P I N G I N S I D E THE CONTAINMENT VESSEL HAS F I V E BRANCHES.

IDENTICAL ISOLATION VALVES ARE I N S T A L L E D I N EACH BRANCH.

ONE VALVE I S NORMALLY OPEN.

THREE OTHER VALVES ARE NORMALLY I

CLOSED AND ALSO RECEIVE PHASE A SIGNAL.

THE F I F T H VALVE I S A R E L I E F VALVE WHICH R E L I E V E S l NTO CONTA I NMENT.

5.

THE P I P I N G I S J O I N E D BY A L l N E LEADlNG T O THE NITROGEN SUPPLY OUTSIDE OF THE S H I E L D B U I L D I N G.

T H I S L I N E I S ISOLATED BY AN A I R OPERATED GATE 'V'AL'v'E f i i T i i PiiASE A ISOLATION.

I I 6.

DUCTING OUTSIDE THE S H I E L D B U I L D I N G HAS TWO BRANCHES.

IDENTICAL SECONDARY CONTAINMENT I S O L A T I O N VALVES ARE INSTALLED I N EACH BRANCH.

7.

P I P ! N G OIITS!DE OF THE SHIELD B U i L D i N G HAS N ~ N E BRANCHES.

EACH L I N E I S ISOLATED BY A R E L I E F VALVE.

I I 8.

I N S I D E THE CONTAINMENT VESSEL A L l N E I S PROVIDED FOR PRESSURE R E L I E F OF THE VOLUME BETWEEN THE I S O L A T I O N VALVES.

T H I S L l N E I S ISOLATED B Y A CHECK VALVE.

9.

THE P l P l N G I S JOINED BY A L l N E USED FOR S. 1. S.

TESTING OUTSIDE OF THE S H I E L D B U I L D I N G.

T t i I S L I N E I S ISOLATED BY AN A I R OPERATED GLOBE VALVE W I T H REMOTE MANUAL ACTUATION FROM THE M A I N CONTROL ROOM.

I I 1 0.

THE P I P I N G HAS A BYPASS L l N E ATTACHED TO I T I N S I D E THE ANNULUS.

T H I S BYPASS L!?JE I S i;aiAiED

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I I 1 1.

I S O L A T I O N I N S I D E CONTAINMENT I S ACCOMPLISHED BY A CLOSED SYSTEM.

1 2.

THE DP SENSORS ARE CLOSED SYSTEMS OUTSIDE OF CONTAINMENT THAT ARE ATTACHED D I R E C T L Y TO TI-1E CONTAINMENT. NO I N L l N E ISOLATION VALVES ARE EMPLOYED FOR THESE SENSORS REFER TO S E C T I O N 6. 2. 4. 3.

AND BARRIERS-TABLE 6.2.4-1 AMENDMENT 85

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I I 1 3.

POST ACCIDENT MONITORING SYSTEM (PAMS) WIDE RANGE PRESSURE SENSORS ALSO MONITOR PRESSURE THROUGH T H l S PENETRATION.

1 4.

THE SECONDARY CONTAINMENT ISOLATION VALVE(S),

WIiICH REPRESENT AN ADDITIONAL BOUNDARY OUTSIDE CONTAINMENT I N HVAC SYSTEMS, ARE USED 7'0 PREVENT BYPASS LEAKAGE FROM THE ANNULUS.

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15.

l SOLAT ION VALVES CAN BE MANUALLY ACTUATED ELECTR ICALLY OR PNEUMAT ICALLY.

I.

16.

TWO B L I N D FLANGES ARE EMPLOYED I N THE ANNULUS, ONE ACTS AS A PRIMARY CONTAINMENT ISOLATION BARRIER AND OTHER AS A.SECONDARY CONTAINMENT ISOLATION BARRIER.

THE PRIMARY AND SECONDARY CONTAINMENT PENETRATIC)NStARE NOT CONNECTED EXCEPT FOR THE TYPE A TEST PRESSURIZATION.

I I

1 7.

OUTSIDE CONTAINMENT, 'RELIEF VALVES RELEASE INTO THIS L l N E I N THE EVENT OF S I S OVERPRESSURE, THUS THE SYSTEM I S ALMOST ALWAYS CLOSED, BUT COULD OPEN FOR PRESSURE RELIEF ANYTIME S I S I S ON.

I I i

18.

OUTSIDE CONTAINMENT, A ONE INCH L l N E T I E S I N BETWEEN THE OUTER ISOLATION VALVE AND PRIMARY CONTAINMENT.

T H l S L I N E I S ISOLATED BY A MANUALLY LOCKED CLOSED CONTAINMENT ISOLATION VALVE.

9 THE CONTAINMENT ISOLATlON VALVES I N T H l S L l N E REQUIRE SIMULTANEOUS OPEN SIGNALS FROM TWO SEPARATE SWITCHES I N ORDER TO OPEN.

ONE SWITCH I S LOCATED I N THE MAIN CONTROL ROOM AND I

THE OTHER IS LOCATED I N THE REMOTE SAMPLiNG STATION.

2 0.

T H l S PENETRATION CONTAINS BOTH THE INTAI<E AND RETURN LINES FOR A HYDROGEN ANALYZER.

THESE L I N E S FORM A CLOSED SYSTEM OUTSIDE CONTAINMENT AND EACH HAS A CONTAINMENT ISOLATION VALVE 114s I DE AND OUTS l DE CONTA I NMENT 2 1.

THIS L I N E TRANSMITS PRESSURE FROM THE PRIMARY COOLANT SYSTEM TO PRESSURE INSTRUMENTATION FOR DETERMINING THE REACTOR VESSEL FLUID LEVEL.

THE L I N E I S FLUID FILLED AND DOUBLE DIAPHRAGMED TO PREVENT COMMUNICATION BETWEEN THE PRIMARY SYSTEM FLUID AND THE AUXILIARY BUILDING.

NO PRIMARY SYSTEM FLUID TRAVELS THROUGH THE PENETRATION SINCE THE INNER DIAPHRAGM I S LOCATED NEAR THE REACTOR VESSEL.

SINCE DOUBLE DIAPHRAGMS ARE EMPLOYED FOR CONTAINMENT ISOLATION, NQ C Q ~ \\ ! T P. !

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\\I'AC\\*/ES ARE 'JSED.

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22.

T H l S L l N E JOINS THE SECONDARY SIDE OF THE STEAM GENERATOR(S)

INSIDE CONTAINMENT AND I S THEREFORE CONSIDERED A CLOSED SYSTEM INSIDE CONTAINMENT.

THE ISOLATION VALVES WHICH EXIST OUTBOARD OF CONTAINMENT ARE NOT LEAKRATE TESTED DUE TO FLOODING OF THE STEAM GENERATORS POST LOCA.

WATTS BAR NUCLEARPLANT CONTA I NMENT PENETRAT I O N ~

69 oF 6 9 1 AND BARRIERS-TABLE 6.2.4 AMENDMENT 2 3.

BETWEEN PRIMARY CONTAINMENT AND THE OUTER ISOLATION VALVE I N Tt-iIS L I N E, AN A U X I L I A R Y FEEDWATER L l N E ADJOINS.

THE A U X I L I A R Y FEEOWATER L l N E HAS ISOLATI0t.I VALVES WHICH ARE ISOLATED I N THE SAME MANNER AS THE A U X I L I A R Y FEEDWATER ISOLATION VALVES L I S T E D FOR X-40A AND X-408.

25.

AZIMUTH INFORMATION FOR THESE L I N E S CAN BE FOUND I N CHICAGO BRIDGE & IRON CO.

STEEL CONTAINMENT VESSEL DATA PACKAGE ( R I M S #B48850425301).

I I

2 4.

ONE WET LAYUP L l N E T I E S INTO T H l S L l N E INBOARD OF THE OUTER ISOLATION VALVE.

THE LAYUP L I N E I S.

ISOLATED W I T H A MANUAL CON'TAINMENT ISOLATION VALVE WHICH I S LOCKED CLOSED PRIOR TO C R I T I C A L I T Y.

26.

NO TYPE C LEAKAGE RATE TEST I S PERFORMED ON T H l S L I N E, BUT A WATER INVENTORY LEAKAGE RATE TEST I S PERFORMED ON THE MOV LOCATED OUTSIDE CONTAINMENT. T H I S WATER LEAKAGE TEST ASSURES TtiAT THE WATER LEG, LOCATED IMMEDIATELY INBOARD OF THE MOV, W I L L M A ! N T A ! N !', SUFFlClENT iNVENTORY TO M A l N T A l N A BRESSURE OF A T L E A S T 1. 1 TIMES THE MAXIMUM CALCULATED CONTAINMENT ACCIDENT PRESSURE ON THE MOV FOR 30 DAYS AFTER AN ACCIDENT.

I 1

2 7.

PENETRATION X-118 I S OPENED BY REMOVING THE B L I N D FLANGE I N THE ANNULUS TO ALLOW THE WATER WHICH HAS COLLECTED I N THE ANNULUS FROM LEAKAGE THROUGH THE PENETRATIONS OR SEEPAGE THROUGH THE CONCRETE TO D R A I N T H E REACTOR B U l L O f N G FLOOR AND EQUiPMENi DRAIN SUMP.

28.

T H l S L l N E TRANSMITS PRESSURE FROM THE PRIMARY COOLANT SYSTEM TO PRESSURE INSTRUMENTATION.

TIiE L l N E I S F L U I D F I L L E D AND DOUBLE DIAPHRAGMED TO PREVENT COMMUNICATION BETWEEN THE PRIMARY SYSTEM F L U I D AND THE A U X I L I A R Y B U I L D I N G.

NO PRIMARY SYSTEM F L U I D TRAVELS THROUGH THE PENETRATION SINCE THE INNER DIAPHRAGM I S LOCATED NEAR THE REACTOR VESSEL, SINCE DOUBLE DIAPHRAGMS ARE EMPLOYED FOR CONTAINMENT ISOLATION, NO CONTAINMENT I S O L A T I O N VALVES ARE USED.

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