ML18022A158

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Updated Final Safety Analysis Report (Ufsar), Amendment 27, 3.4 Figure - Reactivity Control Mechanical Design
ML18022A158
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/05/2017
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML18018A778 List: ... further results
References
Download: ML18022A158 (25)
v • d • e


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COUPLING RELEASE HANDLE

-'-'------ttANOLE OA BAIL ITVPICALI N!UTRON A DSOR BER COMPACTED IN STAINLESS STEEL TUllES BLADE VELOCin* LIMITeR AMENDMENT 16 BROWNS FERRY NUCLEAR rt.AHT FINAL SAFETY A.HAL YSIS REPORT ConrrDI Rod - hom*llic FIGURE J.4*f

COUPt.IIIG RElEASE IWIDL£ AMENDMENT 1 6 BROWNS FERRY NUCLEAR PLANT FINAL S.t.FE'TY ANALYSIS REPORT Control Rod - Isometric FIGURE 3.4-2

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CONTROL ROC ASSEMBLY w/VELOCITY LIMITER PLUG NI-l._- UNLOCKING TUBE INDEX TUBE

  • DRIVE COUPLE~

ACTUATING SHAFT AMENDMENT 16 BROWNS FERRY NUCt.!AR PL.AHT FINAL SAFETY ANALYSIS REPORT Control Rod to Control RDd Drive Coupling -

lsomlltl'ic FIGURE 3.4-3

BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTROL ROD VOLOCITY LIMITOR-ISOMETRIC FIGURE 3.4-4

80TTOII OY REACTOR YESJEL ORIVE HOUSINCI DftiVt INSUT LIN£ "-----"'1 AMENDMENT 16 ORIY£ WITHilRAW LIME ARft011S SIIOI IATEI FLOI WHU tHE ORIYE IS 111 THE 'IITKORAI'AL IICIOE OF.OPERATION.

PRESSURES SHDfll ARE IIAXIIIUII.

Pfi*REACTOR PRESSUR£ BROWNS FERRY NUCLEAR PLANT FlHAL SAFETY ANALYSIS REPORT Control Rod Drive, Simplified Component lllultra1ion FIGURE 3.4-6 I

NOTE; A CIRCLEO NUMBER INDICATES A PRESSURE POINT.

GUIDE __

CAP PISTON _ _.:.:..:=-

TUBE PRESSURE OVER PORT DRIVE WITHDRAW LINE ttOtJSIHG FLANGE GUIDE TUBE 0,...

COTTER PIN COLLEf.FINGERSr~

COLLEHPRING COLLEHiSJDH AND RINGS DRIVE PISTON AND ~EALS TO F'LANGE fiElD HUB PRESSURE UNDER PORT DRIVE INSERT LINE BALL CHECK VALVE POSITION INDICATOR HOUSING AMENDMENT 16 BROWNS FERRY NUCLEAR PLAHT FINAL SAFETY ANALYSIS REPORT Control Rod Drive, Schematic Diagram FIGURE 3.4-6

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.-,re,loLllltAW:'I.Mlk1 'Aat,.r*"~~t RJ> f1[ACTNti'IIESAJRf AMENDMENT 22 BROWNS FERRY NUCLEAR PLANT r I NAL SAFETY ANAL YSJ S REPORT CONTROL ROO DRIVE HYORAUi.. IC CONT~OL SYSTEU SIM?lJ r I CD COUPOHENT Ill USTRATION F IGURE 3. 4-7

BROWNS f ERRY NUCLEAR PLANT F I NAL S-'FETY -'NALYSI S REPORT CRD HYORALL JC SYSTE ~

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F!CURE 3. 4-Se SH 1

AMENDMENT 24

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AME NDMENT 27 BROWNS FERRY NUCLEAR PLANT F INAL SAFE TY ANALYS I S REPORT CONTROL ROD DRIVE HYDRAULIC SYSTEM MECHA NICAL CONTROL DIAGRAM FI GURE J. 4-Bo SH 3

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CONTROL AIR CONTROL AIR 2

PCV 85-67 PCV 85-66 TO SCRAM VOLUME DRAIN FCV'S 3

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LOG SEE TABLE 1

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ITR-85-7A-1 THRU -50 I

TYP FOR ONE 47 CONTROL ROD TE 5-7-1 THRU -50 TYP OF 4 (1-185)

RECORDERS 7

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SEE NOTE 1 TYPICAL FOR 185 UNITS SEE NOTE 1---IL FCV 85-40D (1-185) s -----}

SEE NOTE 1 FCV 85-408 s (1-185) 10 EXHAUST WATER HEADER 3-47E610-85-1,G9 I

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I TYPICAL FOR 185 UNITS L. SEE NOTE 1 L-,

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HIGH POINT VENT VALVE (WITHDRAW)

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r--------r-----1 3-45E763-20 DRIVE WATER (INSERT)

PRIMARY CONTAINMENT HIGH POINT VENT VALVE (INSERT}

REACTOR PROTECTION SYSTEM 13-730E915-13 t--"""'1 FCV 85-40C (1-185) s SCRAM OUTLET VALVE FCV;-...._,,,__~,,,__-l 85-398 {1-185)

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1 1 INITIATION 1r--------r-i3-47E610-as-s _

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SEE NOTE 1 o't--...__

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SEE NOTE 1

{1-185) FC 85-39A TYPICAL FOR 185 UNITS HEADER

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COOLING WATER 14-1....-'1-l><I~ **

  • --(~3_-_47_E_6_10_-_8_s-_1~.K_8~I SCRAM INLET TO SCRAM DISCHARGE INSTRUMENT VOLUME VALVE'------~~~~~~~2::::;

r 3-47E610-85-5,A11 LOOP SEAL TYPICAL FOR 185 UNITS 1 1 TEMP ELEMENT LOG 3-TE-85-7-001 A857001 3-TE-85-7-002 A857002 3-TE-85-7-003 A857003 3-TE-85-7-004 A857004 3-TE-85-7-005 A857005 3-TE-85-7-006 A857006 3-TE-85-7-007 A857007 3-TE-85-7-008 A857008 3-TE-85-7-009 A857009 3-TE-85-7-010 A857010 3-TE-85-7-011 A857011 3-TE-85-7-012 A857012 3-TE-85-7-013 A857013 3-TE-85-7-014 A857014 3-TE-85-7-015 A857015 3-TE-85-7-016 A857016 3-TE-85-7-017 A857017 3-TE-85-7-018 A857018 3-TE-85-7-019 A857019 3-TE-85-7-020 A857020 3-TE-85-7-021 A857021 3-TE-85-7-022 A857022 3-TE-85-7-023 A857023 3-TE-85-7-024 A857024 3-TE-85-7-025 A857025 3-TE-85-7-026 A857026 3-TE-85-7-027 A857027 3-TE-85-7-028 A857028 3-TE-85-7-029 A857029 3-TE-85-7-030 A857030 3-TE-85-7-031 A857031 3-TE-85-7-032 A857032 3-TE-85-7-033 A857033 3-TE-85-7-034 A857034 3-TE-85-7-035 A857035 3-TE-85-7-036 A857036 3-TE-85-7-037 A857037 3-TE-85-7-038 A857038 3-TE-85-7-039 A857039 3-TE-85-7-040 A857040 3-TE-85-7-041 A857041 3-TE-85-7-042 A857042 3-TE-85-7-043 A857043 3-TE-85-7-044 A857044 3-TE-85-7-045 A857045 3-TE-85-7-046 A857046 3-TE-85-7-047 A857047 3-TE-85-7-048 A857048 3-TE-85-7-049 A857049 3-TE-85-7-050 A857050 3-TE-85-7-051 A857051 3-TE-85-7-052 A857052 3-TE-85-7-053 A857053 3-TE-85-7-054 A857054 3-TE-85-7-055 A857055 3-TE-85-7-056 A857056 3-TE-85-7-057 A857057 3-TE-85-7-058 A857058 3-TE-85-7-059 A857059 3-TE-85-7-060 A857060 3-TE-85-7-061 A857061 3-TE-85-7-062 A857062 TABLE 1 TEMP ELEMENT LOG 3-TE-85-7-063 A857063 3-TE-85-7-064 A857064 3-TE-85-7-065 A857065 3-TE-85-7-066 A857066 3-TE-85-7-067 A857067 3-TE-85-7-068 A857068 3-TE-85-7-069 A857069 3-TE-85-7-070 A857070 3-TE-85-7-071 A857071 3-TE-85-7-072 A857072 3-TE-85-7-073 A857073 3-TE-85-7-074 A857074 3-TE-85-7-075 A857075 3-TE-85-7-076 A857076 3-TE-85-7-077 A857077 3-TE-85-7-078 A857078 3-TE-85-7-079 A857079 3-TE-85-7-080 A857080 3-TE-85-7-081 A857081 3-TE-85-7-082 A857082 3-TE-85-7-083 A857083 3-TE-85-7-084 A857084 3-TE-85-7-085 A857085 3-TE-85-7-086 A857086 3-TE-85-7-087 A.857087 3-TE-85-7-088 A857088 3-TE-85-7-089 A857089 3-TE-85-7-090 A857090 3-TE-85-7-091 A857091 3-TE-85-7-092 A.857092 3-TE-85-7-093 A857093 3-TE-85-7-094 A857094 3-TE-85-7-095 A857095 3-TE-85-7-096 A.857096 3-TE-85-7-097 A857097 3-TE-85-7-098 A857098 3-TE-85-7-099 A857099 3-TE-85-7-100 A857100 3-TE-85-7-101 A857101 3-TE-85-7-102 A857102 3-TE-85-7-103 A857103 3-TE-85-7-104 A857104 3-TE-85-7-105 A857105 3-TE-85-7-106 A857106 3-TE-85-7-107 A857107 3-TE-85-7-108 A857108 3-TE-85-7-109 A857109 3-TE-85-7-110 A857110 3-TE-85-7-111 A857111 3-TE-85-7-112 A857112 3-TE-85-7-113 A857113 3-TE-85-7-114 A857114 3-TE-85-7-115 A857115 3-TE-85-7-116 A.857116 3-TE-85-7-117 A.857117 3-TE-85-7-118 A857118 3-TE-85-7-119 A857119 3-TE-85-7-120 A857120 3-TE-85-7-121 A.857121 3-TE-85-7-122 A857122 3-TE-85-7-123 A857123 3-TE-85-7-124 A857124 12 TEMP ELEMENT LOG 3-TE-85-7-125 A857125 3-TE-85-7-126 A857126 3-TE-85-7-127 A857127 3-TE-85-7-128 A.857128 3-TE-85-7-129 A.857129 3-TE-85-7-130 A857130 3-TE-85-7-131 A857131 3-TE-85-7-132 A857132 3-TE-85-7-133 A.857133 3-TE-85-7-134 A.857134 3-TE-85-7-135 A857135 3-TE-85-7-136 A857136 3-TE-85-7-137 A857137 3-TE-85-7-138 A857138 3-TE-85-7-139 A857139 3-TE-85-7-140 A857140 3-TE-85-7-141 A857141 3-TE-85-7-142 A857142 3-TE-85-7-143 A857143 3-TE-85-7-144 A857144 3-TE-85-7-145 A857145 3-TE-85-7-146 A857146 3-TE-85-7-147 A857147 3-TE-85-7-148 A857148 3-TE-85-7-149 A857149 3-TE-85-7-150 A857150 3-TE-85-7-151 A857151 3-TE-85-7-152 A857152 3-TE-85-7-153 A857153 3-TE-85-7-154 A857154 3-TE-85-7-155 A857155 3-TE-85-7-156 A857156 3-TE-85-7-157 A857157 3-TE-85-7-158 A857158 3-TE-85-7-159 A.857159 3-TE-85-7-160 A857160 3-TE-85-7-161 A.857161 3-TE-85-7-162 A857162 3-TE-85-7-163 A.857163 3-TE-85-7-164 A.857164 3-TE-85-7-165 A.857165 3-TE-85-7-166 A.857166 3-TE-85-7-167 A857167 3-TE-85-7-168 A.857168 3-TE-85-7-169 A.857169 3-TE-85-7-170 A.857170 3-TE-85-7-171 A.857171 3-TE-85-7-172 A857172 3-TE-85-7-173 A.857173 3-TE-85-7-174 A.857174 3-TE-85-7-175 A.857175 3-TE-85-7-176 A857176 3-TE-85-7-177 A857177 3-TE-85-7-178 A857178 3-TE-85-7-179 A857179 3-TE-85-7-180 A857180 3-TE-85-7-181 A857181 3-TE-85-7-182 A857182 3-TE-85-7-183 A857183 3-TE-85-7-184 A.857184 3-TE-85-7-185 A857185 I

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VENT CHARGING WATER HEADER 14---.--t........ -t><;--,-*----:(

3-47E61 0-85-1.K4 I 243 262 244 263 DISABLED IN PLACE 3

312 VENT 246 310 DISABLED IN PLACE 4

VENT 329 REACTOR PROTECTION SYSTEM BACK UP SCRAM VALVE B (5A-K29B) t--t 0-730E915-14 I I

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3-47E610-46-2. 87 REACTOR PROTECTION SYSTEM BACK UP SCRAM VALVE A

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Pl 85-33A TYPICAL FOR 185 UNITS ACCUMULATOR PORTABLE ACCUMULATOR N 2 CHARGING SYSTEM A (TYPICAL FOR SYSTEM 8) 8 BARRIER HzO 9

CRW BARRIER STOP Pl 85-34 SEE NOTE 1.t: 5 (1-185)

SEE L-----YR< 25-4 {EAST)

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25-22 (WEST)

NOTES 1.t. 5 COMPANION DRAWINGS:

3-47E610-85-1,-5 10 FOR NOTES SEE 3-47E610-85-1.

SYMBOLS:

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GENERAL NOTE:

THE CONTROL ROD DRIVE {CRD) SYSTEM IS DESIGNED TO PROVIDE THE REACTOR WITH POSITIVE REACTIVITY CONTROL WHILE MAINTAINING A CONSTANT QUANTITY OF CONDENSATE TO THE REACTOR VESSEL IN THE FORM OF DRIVE SEAL LEAKAGE DRIVE COOLING, AND FLOW TO THE REACTOR VIA RWCU RETURN LINE.

THE PUMP SUCTION IS FROM THE CONDENSATE STORAGE SYSTEM AND IS RAISED TO A PRESSURE ABOVE THE REACTOR OPERATING PRESSURE BY THE DRIVE WATER PUMPS.

THE PRESSURE IS THEN REDUCED TO THE THREE PRESSURES NEEDED FOR DRIVING, CHARGING AND COOLING.

NOTES:

1. HYDRAULIC CONTROL UNIT (HCU) DEVICES AND CONTROL ROD DRIVE UNIT (CRDU)

DEVICES ARE SHOWN FOR A SINGLE UNIT AND ARE TYPICAL OF 185 SUCH UNITS. THE DRIVES ARE NUMBERED IN ACCORDANCE WITH TABLE 3 ON 1-73DE321-4. UNIDS OF ALL COMPONENTS AFFILIATED WITH A PARTICULAR DRIVE WILL HAVE A SUFFIX THE SAME AS THE DRIVE COORDINATE. FOR EXAMPLE, THE UNID FOR FLOW CONTROL VALVE 39B ASSOCIATED WITH DRIVE 2-43 WOULD BE 1-FCV-85-39B/243, AND FOR CYLINDER 718 WOULD BE 1-CYL-85-718/243.

2. UNITS 1 AND 2 SHARE THE SPARE DRIVE WATER PUMP {18) WHILE UNIT 3 HAS ITS OWN SPARE. EACH PUMP IS CAPABLE OF SUPPLYING 100 GPM AT 1500 PSIG.
3. THE CRO HYDRAULIC SYSTEM PROVIDES CRD OPERATING FLUID, CRD COOLANT, ACCUMULATOR CHARGING AND EXHAUST WATER TO THE REACTOR.
4. THREE STAGES OF WATER PRESSURE ARE DERIVED BY TWO SEPARATE REGULATING SYSTEMS. THE SCRAM ACCUMULATOR CHARGING WATER IS AUTOMATICALLY REGULATED TO 1400 PSIG. THE FLOW CONTROL SYSTEM USING FCV-85-11A OR BAND FE-85-11 MAINTAINS APPROXIMATELY 65 GPM TO THE SYSTEM CRD DRIVE WATER IS MAINTAINED AT REACTOR PRESSURE. (Pr) + 250 TO 270 PSIG BY CONTROLLING PCV-85-23 AND THE AUTOMATIC CLOSING OF FCV-85-20A OR 21A DURING ROD MOVEMENT. THE COOLING WATER HEADER PRESSURE IS APPROXIMATELY Pr+ 20 PSIG. SIXTY-FIVE GALLONS PER MINUTE (65 GPM)

FLOWS INTO THE REACTOR WHETHER OR NOT THE CONTROL RODS ARE t.tDVING OR AT REST.

5. EACH CRD IS EQUIPPED WITH A SEPARATE SCRAM ACCUMULATOR WHICH IS CHARGED WITH NITROGEN. ACCUMULATOR CHARGE PRESSURES ARE MONITORED BY LOCAL PRESSURE GAUGES PI-85-34/219 THRU 5843 AND PS-85-34/219 THRU 5843 WHICH ALARM ON LOW PRESSURE.

ACCUMULAiOR PISTON INTEGRITY IS ALA~MED WITH THE USE OF LS-85-34/219 THRU 5843.

6. CRO POSITIONING IS ACCOMPLISHED BY ELECTRICAL CONTROL OF THE INSERT VALVES FCV-85-4DA/219 THRU 584.3 AND FCV-85-400/219 THRU 584.3 OR THE WITHDRAWAL VALVES FCV-85-40B/219 THRU 584.3 AND FCV-85-40C/219 THRU 584.3.
7. EACH CONTROL ROD, AS IT TRAVELS UP (INSERT) OR DOWN (WITHDRAW) PASSES A NUMBER OF SWITCHES. THE TOP TWO POSITION SWITCHES ZS-85-41A/219 THRU 5843

~~~Iff0~55~l~6~t~ X~~U.. iff~o~~j ~~/s~~~A;Q~E~s!~~~~~/21~H~H~8T~~3T~2o "WITHDRAW DISCONNECT", ZS-85-4.3/219 THRU 584.3. THERE ARE 48 SWITCHES BETWEEN t~§s~E~~~ItAEzBD~ 5N~~6~~~oT~e~TE~~~ AR~ t~~u*R6~>oRI~fIN~R~w~f~A~~Q l~6°THE EVEN NUMBERED SWITCHES ARE THE "LOCKED POSITION SWITCHES".

THE ABOVE SWITCHES ARE ACTUATED BY A MAGNET IN THE POSITION PROBE. THE ROD POSITION IS DISPLAYED IN THE MAIN CONTROL ROOM ON REACTOR PANEL 9-5.

8. INSTRUMENTATION ASSOCIATED WITH BACKUP CONTROLS IS LOCATED AS SHOWN ON THE DIAGRAM. IF A LOCATION IS NOT SHOWN, THE DEVICES WILL BE LOCATED ON THE APPROPRIATE 4160V AC BOARD, 480V AC BOARD OR 250V DC BOARD. (REF GE DESIGN SPEC 22A1470)
9. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT 1 UNLESS OTHERWISE NOTED. LEADING ZEROS SHOWN IN MEL AS PART OF THE UNIO ARE NOT DEPICTED. FOR ADDITIONAL GUIDANCE REFER TO NEDP-4.

EXAMPLE:

MEL UNID 8FN-1-STN-085-0707 BFN-1-Zl-085-00BA DRAWING UNID STN-85-707 Zl-85-8A

10. PARTIAL LOGIC FOR CONTROL ROD DRIVE SYSTEM IS SHOWN ON THE MECHANICAL LOGIC DIAGRAM LISTED IN REFERENCE DRAWINGS.

REFERENCE DRAWINGS:

MEL.................. CRD INSTRUMENT TABULATION 0-47W60D-224A-224A... RPS-CRD CONTROL AIR PRESSURE PANELS 0-47E61D-2-2......... CONTROL DIAGRAM-CONDENSATE 2-47E610-24-10....... CONTROL DIAGRAM-RAW COOLING WATER 1-47E610-68-1........ CONTROL DIAGRAM-RECIRCULATION SYSTEM 1-47E610-69-1........ CONTROL DIAGRAM-RWCU SYSTEM 2-47E610-85-1........ CONTROL OIAGRAM-CRD HYO 1-47E610-85-2........ CONTROL DIAGRAM-CRD HYO 2-47E610-85-4........ CONTROL DIAGRAM-CRD HYO 0-47E800-1........... FLOW DIAGRAM-GENERAL PLANT SYSTEMS 0-47E800-2........... MECHANICAL SYMBOLS A FLOW DIAGRAM DRAWING INDEX 0-47E847-1 THRU -3... FLOW DIAGRAM-CONTROL AIR 0-45E763-4........... 4160V UNIT AUX POWER SCHEMATIC DIAGRAM 2-45E779-7........... 480V SHUTDOWN AUX POWER 2-47E611-85-SERIES... MECHANICAL LOGIC DIAGRAM CONTROL RCO DRIVE SYSTEM 2-47E611-99-SERIES... MECHANICAL LOGIC DIAGRAM REACTOR PROTECTION SYSTEM 0-47E610-43-3........ MECHANICAL CONTROL DIAGRAM SAMPLING A WATER QUALITY SYSTEM GE DRAWINGS:

1-7.30E.321-14......... REACTOR MANUAL CONTROL SYSTEM 1-791E201-2,-3....... CRD HYO INSTR SYSTEM SYMBOL:

c::::>-+-cDNTROL AIR 25-18 L..../!T) 9-5 85-16 @

85-15A 85-208 -----+

~

I PI t--!85-29 r------r-,--,-i1-45E779-8,F31

th:~ :

~dis ~I FI 68-!252 TO RECIRCN PUMP A SEAL INJECTION 1-47E817-1 AB ( -

I I

r 25-18 PI 85-9 5-18 PI 68-1051

~

TO RECIRCN PUMP B SEAL INJECTION I

( 1-47E817-1 A2 l~-1-©9-5 J.....,...-_..;;.:::zt:~I ~r.*"'14,t{ ~

ff ;;~ 5 -

CRW

~x--19

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L~25-18B I

[""---

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-18

~

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8~..

85-11 85-11C 85-11 85-11 1.:.

y

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25-18 I-_._-! FE '---------+-------,...-+-I __.,.

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RWCU PUMP BEARING SEALS 6l::J9-5(PI\\ 25-1 8 85-13A 85-138 85.::2,_!,8 L.+---i~-......,

r~

25-10B s~ : r-m fl;;:s-y y

I I

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~ 85-13

~

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.__,,..."';::$:~1:::J,

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85~8 -i 25-18 FT 85-15

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.'fl.A I

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FI FE 85-22 85-2

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85-30A 85-30B

~85-50A 85-50B I

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I 9-5 I W 85-17A

~

L -i1-45E779-7, 871 25-18 DT

,--r:---r--

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~-5 ~S-l S,..l.._25-18.......,,,,.

lEQ.D {POI\\ (PX\\

85-18A 85-18B 85-18

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FE 85-25.

4 25-18 FT v----

85-25 9-19 9-19 mu 6?'i 85-25 1" 85-25

~ I

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_c9--5----T2~-1a Lt.U 25-18 (Fi'\\

85-25A

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85-258

[PI' 8~ TO COOLING WATER HEADER 11-47E1610-85-2,E6 RX VESSEL PRESSURE

/

1-47E610-68-1.A8 I 3

RWCU SYSTEM

""'"'41-47E610-69-1,H7 COMPANION DRAWINGS:

2-47E610-85-1 1-47E1610-85-2 AMENDMENT 26 REACTOR BUILDING UNIT 1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CRD HYDRAULIC SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 3.4-8a SH 5 H

G F

E D

c B

A

~

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1 8

AMENDME NT 22 r;;;;'"'=

~,------i BROII'NS fERRY !iUCLEAR PLANT f iNAL S).f ETY ANAL YSIS REPORT CON1 R::>L ROD HYC!'lt,!JLJC SYS'!W A

'"LOW D: AGRAM F'ICUR£. 3. 4-Sb

r--------------------------------------"1 5

3 AMENDMEN T 27 POWERHOUSE UNIT2 BROWNS FERRY NUCLEAR PLANT F INAL SAFETY ANALYSI S REPORT FLOW DIAGRAM CONTROL ROO DRIVE HYDRAULIC SYSTEM FI GURE J.4-8c H

G D

c 8

A

AMENDME NT 22 I B

BROWNS FERRY NUCLEAR PLMH F I NAL SAF E TY ANALYSIS REPORT CRD HYDRAULIC SYSTEM A

r-r;;i]~~~;~;::o*

MECHAN: CAL CONIRO_ Ol AGRAM FJGURF. J. 4-8d

==-.. *-::i__

.I

~

....,......_....... ~---

  • AMENDMENT z4 FJCUR( 3. 4-S*

~-----

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~---42 AMENDMENT 21 Mi'.JWll'S f" ERRY NUCLEAR PLANi fiN,l,L SAfET f MOiALYSi S RE PORi

<:Wli\\'.ll RiJ) &Fl\\'l ;1[':0U. IC :ir'STEl.i lil[Cl'WtJ:M. OOITROL l>JN.iR.l.M FJCURE J. 4*B f

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IROWMI PERRY NUCl.IMI *LANT .

FINAL SAFl!TY ANALVSIS RIPORT

  • -~~
  • CoMrol Rod Uol1 Dlfvt - ~'"°"'

lllulCndcm FIQURl!.U-D AMENDMENT 16

-~;.

,~;
  • ~
    • i.

2 - SEAL RrHG (INNER flLT!R )

J - FLAT HEAO SCREW fO*RIHG SPAUR MOUNTING\\

4 - STRAINER 5 - FLAT HEAO SCREW.

6 - OOWEL P!N l

  • 0-RING SPACER 8 - SPUO I CYLINDER 9 - SOCKET *HEAD CAP SCREW (RING FLA,~GE MOUHTIHG) 10 - SEAL CUP f PART Of OR!VE P!SiON ASSEMBLY) 11 - SEAL RING (BUFFER PISTON) 12 - POSITION !HOICATOR P~OBE 1 J - FI LL! STER-HEAD SCREW (POSITION lNOICATOR PROBE llOUHTING) 14 - LOCXWASHER (FOR PART 13)

H - PISlOH TUBE ASSEMBLY 16 - NUT (PISTOH TUBE )

11 - RltlG ILAHGE 18 RING (PISTON TUBE) 19 - CYLINDER, TUBE, A/IP FLANGE 20 - !ALL (CHECK VAL VE) 21 * - BALL RETAINER 22 -

0-~ING (BALL RETAIHER) 2l -

COOLiHG WATER ORIFICE 24 - ORIVE PiSTOH ASSEJIBLY 25 - LOCKING BANO 16 - rnoEX TUBE 17 - SEAL RING (COLLET PISTON -

HTERHAL) 18 - SEAL R!MG (COLLET PISTON -

EXTERNAL) 19 - COLLET I P!STOH 30 - BUFFER SPR!llG JI - COLLET SPRING

JJ - STOP PISTON 34 - SEAL R!HG (STOP PISTON) 35 - BARREL 36

  • NUT (STOP PISTON) 31 - PLUG (GUIDE CAP) 38 - FILL!STER*HEAD SCREW (GUIOE CAP PLUG MOUNTING) 39 - GU IDE CAP 40 - DRILLED F ILLISTER-HEAO SCREW (OUTER Fil TER MOUNTING) 41 - INNER FILTER 42 - UNCOUPLING ROO 44 - LOCKING BAHD 45
  • OUTER FILTER
~ : im~~ ~mo~PART OF DRIVE p isTON) 48 - PI S10N COUPLING (PART Of DRIVE PISTON) 49 - MAGNET HOUSING (PART OF *oRIVE P!S10H)

SO - LOCKING 8AllD (ON DRIVE PISTON) 51 - COLLET HOUSING (PORTION Of I;

OUTER TUBE)

SI - NAMEPLATE 53 - DRIVE SCREW 54 - LOCKING CUP 55 - lHOEX TUBE NOTCH 56 - OUTER TUBE (PART Of CYLINDER, TUBE, A.~D FLANGE) 57 - rnNER TUBE (PART Of ClllNOER, TUBE, ANO FLANGE) se - THERHOCOUPLE (PART OF POSlT!OH INDICATOR PROBE) 59 : BUFFER SHAFT 60

  • COLLET FINGER (PART Cf COLLET

.RETAINER, AHO PISTON )

61 - INDICATOR TUBE (PART Of PlSTOH TUBE) 61

  • LOCKJNG BAND (OH DRIVE PISTON) 63 - INTERNAL BUSHING (DRIVE PISTON) 64 - EXTERNAL BUSH!nG (DRIVE PISTON) 65 - omR SEALS (PRIVE PJSTON) 66 - INSERT PORT (INSERT & SCIW\\

INLET/W!THORAW OVTLET) 67 -

~ING f\\AGHET (PART Of nRIVE* PISTGll) 68 - CABLES {POSJT ION l llDICATOR )

69 - PORT TO COLLET PISTON (WITHORAW PRESSURE TO COLLET PISTOH)

JO - WITHORAW PQRT (WITHDRAW INLET/

ltlSERT OUTLET & SC~ OISCHARGE) 71 - INHER SEALS (DRIVE PJSTOH - DRIVE 00\\IH SEALS) n - !HHER SEALS (DRIVE PISTON -

ORJVE-UP SEALS) 73

  • WATER PORTS IN COLLET HOUSING 14 - WATER PORTS lH COLLE1 PISTON 15 - VESSEL-WATER PORTS 76 - SHOULDER (PART OF CYLINDER, TUBE AHO FLAHGt) 11
  • IUFF!R ORIFICES IN PJSTOH TUBE ASSEMBLY 18 - COLLET RETAlHER ( HOLOS COLLET FINGERS) 79 - POSlTJOH INDICATOR SWITCHES ao - BUFFER SHAFT PORTS BROWNS FERRY NUCLEAR PLANT F INA~ SAFETY ANALYSIS REPORT AMENDMENT 16 MODIFIED CONTROL ROD DRIVE (0WR/6i FIGURE 3.4-9a

BFN-16 Figure 3.4-10 Deleted by Amendment 7.

BFN-22 Figure 3.4-11 (Deleted by Amendment 22)

0

()

HANDLE BLADE NEUTRON ABSORBER RODS COUPLING RELEASE HANDLE VELOCITY LIMITER COUPLING SOCKET AMENDMENT 16 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Marathon Control Rod -

Isometric FIGURE 3.4-12

ADMENDMENT 20 BROWNS F ERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT WESTINGHOUSE CR-B2M-l CON TROL ROD F I GURE 3. 4-13

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