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Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22257A1272022-09-14014 September 2022 Biennial Defueled Safety Analysis Report Update, and Regulatory Commitment Change Summary - September 2020 to September 2022 ML20259A2022020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 1, Introduction and Summary ML20259A2072020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 6, Safety Analysis ML20259A2152020-09-14014 September 2020 Defueled Safety Analysis Report, Table of Contents ML20259A2122020-09-14014 September 2020 Defueled Safety Analysis Report, Appendix a, License Renewal ML20259A2112020-09-14014 September 2020 Updated Final Safety Analysis Report, Chapter 11, Figures ML20259A2032020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 2, Site and Environment ML20259A2012020-09-14014 September 2020 Summary Report of Indian Point Unit 2 Updated Final Safety Analysis Report, Revision 27 to Defueled Safety Analysis Report, Revision 0, Changes ML20259A2142020-09-14014 September 2020 Defueled Safety Analysis Report, Instructions and Key to Unit 2 DSAR Revision 0 ML20259A2062020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 5, Conduct of Facility Activities ML20259A2102020-09-14014 September 2020 Updated Final Safety Analysis Report, Chapters 3 Through 5, Figures ML20259A2092020-09-14014 September 2020 Updated Final Safety Analysis Report, Chapter 2, Figures ML20259A2132020-09-14014 September 2020 Defueled Safety Analysis Report, Appendix B, Technical Requirements Manual (TRM) ML20259A2082020-09-14014 September 2020 Updated Final Safety Analysis Report, Chapter 1, Figures ML20259A2052020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 4, Waste Disposal and Radiation Protection System ML20259A2042020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 3, Facility Design and Operation ML20259A2162020-09-14014 September 2020 Defueled Safety Analysis Report, Appendix a, Permanently Defueled Technical Specifications Bases NL-18-069, Submittal of Revision 27 to Updated Final Safety Analysis Report2018-09-17017 September 2018 Submittal of Revision 27 to Updated Final Safety Analysis Report ML17354A0152017-11-28028 November 2017 Enclosure 2 - NET-28091-003-01NP, Rev. 0, Criticality Safety Analysis for the Indian Point Unit 2 Spent Fuel Pool with No Absorber Panel Credit IR 05000247/20160092016-11-21021 November 2016 Davis-Besse Nuclear Power Station, Unit 1, Revision 31 to Updated Final Safety Analysis Report, Drawing E-0058B, Rev 12, Sheet 0015A ML16280A2082016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 9, Auxiliary and Emergency Systems, Drawing No. 9321-F-2736-130 to Drawing No. 138248-9 ML16280A1652016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 3, Reactor, Figures ML16280A2072016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 9, Auxiliary and Emergency Systems, Figures 9.2-1 to 9.9-1 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 16, Instructions and Key2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 16, Instructions and Key NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis, Figures 14.0-1 to 14.1-672016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis, Figures 14.0-1 to 14.1-67 ML16280A1952016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 7, Instrumentation and Control, Drawings NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 17, Table of Contents2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 17, Table of Contents NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System, Drawing No. 9321-F-2719-136 to Drawing No. 9321-F-2730-752016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System, Drawing No. 9321-F-2719-136 to Drawing No. 9321-F-2730-75 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 12, Conduct of Operations2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 12, Conduct of Operations NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 10, Steam and Power Conversion System, Figure 10.1-1, Revision 21 to Figure 10.2-92016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 10, Steam and Power Conversion System, Figure 10.1-1, Revision 21 to Figure 10.2-9 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 10, Steam and Power Conversion System, Figures 10.2-1 to 10.2-72016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 10, Steam and Power Conversion System, Figures 10.2-1 to 10.2-7 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System, Figure 11.1-1 to Figure 11B-52016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System, Figure 11.1-1 to Figure 11B-5 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 13, Tests and Operations2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 13, Tests and Operations NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis ML16280A2202016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis, Figures 14.2-0 to 14.2-18 ML16280A2242016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 17, Table of Contents ML16280A2232016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 16, Instructions and Key ML16280A1962016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 8, Electrical Systems ML16280A2222016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 15, Appendix a, License Renewal ML16280A1532016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 ML16280A2142016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System, Drawing No. 9321-F-2719-136 to Drawing No. 9321-F-2730-75 ML16280A1682016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 4, Reactor Coolant System, Drawings ML16280A1892016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 5, Containment Systems, Drawing ML16280A2122016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System ML16280A1592016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 1, Introduction and Summary ML16280A2172016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis ML16280A2062016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 9, Auxiliary and Emergency Systems ML16280A1872016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 5, Containment Systems ML16280A1602016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 1, Introduction and Summary, Figures 2022-09-14
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90 -(!) in 80 -a... I 70 -w a: 60 -Ul w a: 50 -a.. t-z 40 -w ::::E z 30 ..... <;:: t-z 20 -0 u 10 -*40.6 PSIG BASED ON MAY 21, 1981 NRC STAFF SER AND CONSOLIDATED EDISON RESPONSE OF SEPTEMBER 4, 1981 (REFERENCE
- 11) TO THAT SER. 47 PSIG REMAINS THE CONTAINMENT DESIGN BASIS AND PROVIDES ADDITIONAL MARGIN ENVIRONMENTAL CONDITIONS FOR EQUIPMENT TESTING PRESSURE VS TIME 60 PSIG TEST CO ND CT IO NS ;.47 PSIG INDIAN ?OiNO 2 CONDITIONS I 10 SEC 20 PSIG 5 PSIG I I I I 10,000 I DAY HOUR SECS. TIME INDIAN POINT UNIT No. 2 UFSAR FIGURE 7.1-1 ENVIRONMENTAL CONDITIONS FOR EQUIPMENT TESTING -PRESSURE vs TIME MIC. No. 1999MC3869 I REV. No. 17 A 400 -* 350 -:J ._. <{ 300 -a: w 250 -w ._. 200 -._. z w :::E 150 -z .:.... <{ ._. z 100 -8 50 I *287°F BASED ON THE MAY 21, 1981 NRC STAFF SER AND CONSOLIDATED EDISON RESPONSE OF SEPTEMBER 4, 1981 (REFERENCE
- 11) TO THAT SER (BASED ON 40.6 PSIG AND SATURATED CONDITIONS)
ENVIRONMENT AL CO N:JITIO NS FOR EQUIPMEN'T TESTING TEMPERATURE VS TIME 286 *F TEST CONDITIONS
- 271 "F INJlAN' POINT 2 CONDITIONS I 10 SEC TIME I I I 10,000 I DAY HOUR SECS. INDIAN POINT UNIT No. 2 UFSAR FIGURE 7 .1-2 ENVIRONMENTAL CONDITIONS FOR EQUIPMENT-TEMPERATURE vs TIME MIC. No. 1999MC3870 I REV. No. 17 A n:: (/) 0 <( n:: I 106 w "( a: hJ (/) 0 0 "( 105 -C> u w n: ----0 102 fl DYt f I Wl<J TIME AFTER RELEASE -HRS. 103 _J Li... z 0 a: :> LIJ z a: w ::x:: I-10 12 JO II 2.5XIO IO 1010 6 10 105 5.0XlO 4 4 10 2.SXIO 3 103 2.SXIO z 10 2 10 I 0 10 -2 10 _.__ -3 10 --AMPS LLJ <( -Cl LIJ ::::E a: LIJ 1-a: LLJ 0 a.. --4.2SXI0-3 AMPS l.7XI0-6 AMPS DETECTOR SENSITIVITY J l.7XIQ-13 AMP/N/CM2/SEC.
<EACH SECTION OF LONG ION CHAMBER l 106 CPS LLJ (.) a: :::> 0 en I 1 --I0-11 AMPERES DETECTOR SENSITIVITY 4XJ0-14AMP/N/CM2/SEC.
_.._ 10° COUNTS PER SECOND DETECTOR SENSITIVITY 10 CPS/N/CM2/SEC.
INDIAN POINT UNIT No. 2 UFSAR FIGURE 7 .4-1 NEUTRON DETECTORS AND RANGE OF OPERATION MIC. No. 1999MC3877 I REV. No. 17 A
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LL 01 Q) 640 3 620 Q) !.... ::::! -+-' 0 !.... Q) CL E 600 Q) I-Q) 01 0 ,_ g; 580 <( Q) !.... 0 0 560 Jv rte p 2440 osio ate L i mi r a t u re d ta-Nominal Full Power Operating Tavg {549°F -572°F, 2250 psia) x x 540-r-...........
.6 7 *I .8 .9 Core Power INDIAN POINT UNIT No. 2 CORE AVERAGE TEMPERATURE vs FRACTION OF NOMINAL POWER UFSAR FIGURE 7.2-19 IREV. No. 19 PROCESS SENSORS QR
( P! } PENETRATIOM
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WALL .,...t---A*C POWER PROTECTION PROTECTION PROTECTION PROTECTION RA.CIC 1111 RACIC *2 RACK *3 RACK *-4 CH *I CH *Z CH f3 CH *4 AKALOG PROTECTION RACKS __ ,___ REACTOR TRIP BISTASLES J I l I 1-----, __ _.._. ___ L_-_-__ t----, I I L--------,
1 L-----------,
I UV TRJP COIL LOGIC RELAY COILS LOGIC RELAY CONTACTS (MATRIX9 I I L.. ocnc RACKS-LOGIC CH. *2 UV TRIP COIL SHUNT TRIP COIL CONTROL....,._......,.
ROD POWER SUPPLY .....,.l
__ -_* TR IP BREAKER *l TR IP BREA!<ER
- Z INDIAN POINT UNIT No. 2 UFSAR FIGURE 7.2-23 DESIGN PHILOSOPHY TO ACHIEVE ISOLATION BETWEEN CHANNELS MIC. No. 1999MC3901 REV. No. 17 A ST ST-1 'FEACT'OR TIP BLOCK AUTO SHUNT TRIP I o---------.r--1 t----. I TO ALL REACTOR TRIP ANO M-G SETS C TR IP 1' 1' BYPASS BREAK:R -r 52A "'-, ) 52 52 ) TRIP CIRCUITS
..v ' RTB
' J, ' BYS J, ',' Ji-------<{
RPS LOGIC TRAIN "A" ' 1'
// I i' 52 ) BYA J.. TEST AUTO _..._...
SHUNT UV ST UNOERVOLTAGE TRIP COIL ROD DRIVE POWER BUS INDIAN POINT UNIT No. 2 UFSAR FIGURE 7 .2-30 REACTOR TRIP BREAKER ACTUATION SCHEMATIC MIC. No. 1999MC387 4 REV. No. 17 A 70 ,--.,,. Lt... 60 0-. (!) -0 .._...,-I-I 0 ::!:::::'.
(!) 50 -0 40 30 560 Reactor Core Sa ety Limi ve temperature del ta-T Se Overpower de ta-T Se point po in 2250 psia 2440 psi \ ' \ \ x ' \ I \ \ \ \ \ \ \ \ \ \ \ Nominal High-Tavg
\ \ Operating Point, \ \ 2250 psla \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \, 570 580 590 600 610 620 Tavg (deg INDIAN POINT UNIT No. 2 ILLUSTRATION OF OVERPOWER and OVERTEMPERATURE T TRIPS HIGH TEMPERATURE OPERATION UFSAR FIGURE 7.2-33,sht.11 REV. No. 19 Reactor Core s f e t y Limit ----Over temperature delta Se t oi n ---Overpower el ta-T Se po in 80 _ _.l._-l \ \ ,----..>...
__ \ \ \ -\ \ \ \ 70 \ \ \ \ \ \ \ \ \ \ \ \ x \ \ \ \ \ \ .----.. \ \ \ \ \ LL. 60 \ \ \ \ 01 \ \ \ Q) \ \ \ \ -0 ,._.....
\ \ \ \ I-Nominal Low-Tavg \ \ \ \ I \ \ \ \ 0 Operating Point, \ \ \ \ ::!:::'.
50 2250 psia \ (],) \ \ \ -0 \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \ 40 \ \ \ \ \ \ \ \ \ <6-\ 0 v \ 'S \ -0 \ \ % \ \ \ \ \ \ \ \ 30 \ 540 560 580 600 620 Tavg (deg INDIAN POINT UNIT No. 2 ILLUSTRATION OF OVERPOWER and OVERTEMPERATURE T TRIPS LOW TEMPERATURE OPERATION UFSAR FIGURE REV. No. 19 NOTES: I. TEMPERATURES AAE MEASURED AT STEAM CJENERATOR'S INLET AND OUTLET. 2. PRESSURE IS MEASURED AT THE PRESSURIZER.
J COLO LEG T COLD LEG T COLO LEG T COLO LEG
- T HOT9 LEG AVERAGE AVERAGE AVERAGE AVERAGE TEMPERATURE TEMPERATURE TEMPERATURE TEMPERATURE UNIT UNIT UNIT UNIT LOOP I LOOP 2 LOOP 3 LOOP 4 T,wG = TH*Tc TAVG: TH*Tc T AVG" T H*T C TAVG: TH*Tc ---r---r---z---z-I I I AVERAGING p -PREF' UNIT PRESSURE SIGNAL NUCLEAR F'LUX TAVG COMPENSATION UNIT NUCLEAR COMPENSATION UNIT F'LUX SIGNAL TO PRlssuRIZER I CONTROL GROUP CONTROL LEVEL PROGRAMMER SIGNAL SPEED AND DIRECTION L ,l "T 1 LEAD-LAG
'-EAD-LA8 AVERAGE SEQUENTIAL ROD COMPENSATION COMPENSATION r--TEMPERATURE 1-CONTROL UNIT UNIT UNIT CONTROL UNIT !AUTOMATIC CONTROLJ TIU ROOS TN RODS OUT lCONTROL (CONTROL THf" AVERAGE GROUPJ GROUP I STEAM DUMP CONTROL TEMPERATURE PROGRAMMER f PERMISSIVE CIRCUITS
!ROD INTERLOCKSJ PERMISSIVE CIRCUIT TURBINE LOAD STEAM DUMP CUTOUT SIGNAL ..J < z STEAM DUMP MANUAL ROD ! VALVES CONTROL en IL -I cc ,._ STEAM GENERATOR PERMISSIVE CIRCUITS CONTROL ROD cc PRESSURE ROD lNTERLOCICSJ
-ACTUATORS 0 CONTROL ,._ 0 < w cc REACTOR TRIP i--BREAKER I CONTROL ROD DRIVE CONTROL ROD REACTOR TR lP MECHANISMS POWER SUPPLY -BREAKER Z INDIAN POINT UNIT No. 2 UFSAR FIGURE 7 .3-1 SIMPLIFIED BLOCK DIAGRAM OF REACTOR CONTROL SYSTEMS MIC. No. 1999MC3876 I REV. No. 17A lJ) 0 4: 0: hJ IOe -lJ) 0 Cl .ct: .ct: (!) Cl w t-.ct: l::l 7 -_J ::> :=E ::> u u .ct: 106 L__..L..
___ _i_ ____ .....L--...------.l---.--1*
102 103 10"" ll WKl (I MOI (I YRI 10° (I OYl TIME AFTER RELEASE -HRS. INDIAN POINT UNIT No. 2 UFSAR FIGURE 7.1 -4 INTEGRATED GAMMA DOSE RATE INSIDE THE CONTAINMENT AS A FUNCTION OF TIME AFTER RELEASE -TID-14844 MODEL MIC. No. 1999MC3872 I REV. No. 1 7 A POWER RANGE UPPER LOWER TO REMOTE INDICATION SO AND RECORDING TO REACTOR PROTECTION TO REMOTE TO INDICATION REACTOR AND CONTROL RECORDING ALARM ON DEVIATION INTERMEDIATE RANGE 12 CHANNELS!
SOURCE RANGE 12 CHANNELS!
COMPENSATED ION CHAMBER TO REMOTE INDICATION AND RECORDING TO REACTOR PROTECTION OVERPOWER BLOCK ROD WITHDRAWAL RT } BLOCKED * * -BY P-10 AND BLOCK ROD MANUAL WITHDRAWAL ACTION TO SOURCE RANGE CUT OFF !SOURCE RANGE TRIP BLOCK PERMISSIVE)
TO REMOTE INDICATION.RATE AND RECORDING ITYP ICAL FOR ONE PERMISSIVE SIGNAL -lOA: POWER CHANNELi LOW HIGH RANGE RANGE R.T. DROPPED PERMISSIVE ROD 70XPOWER
[BLOCKED]
ALARM ROD DROP BLOCK ROD WITHDRAWAL BY P-10 AND MANUAL ACTION FROM THER CHANNEL LOG INTEGRATOR F ILOG AMPLIFER-01 BLOCKED BY P-6 NC R.T. ANO MANUAL ACTION TO HIGH SHUTDOWN FLUX ALARM TO REMOTE INDICATION.RATE AND RECORDING (TYPICAL FOR ONE CHANNELi INDIAN POINT UNIT No. 2 UFSAR FIGURE 7.4-2 NUCLEAR INSTRUMENTATION SYSTEM MIC. No. 1999MC3878 REV. No. 17 A PROPORTIONAL COUNTER COMPENSATED IONIZATION CHAMBER LONG ION CHAMBER PROPORTIONAL*o COUNTER LONG ION CHAMBER 0 FLAT CORE 0 0 PROPORTIONAL COUNTER COMPENSATED IONIZATION CHAMBER
- PART OF THE ALTERNATE SAFE-SHUTDOWN SYSTEM INSTRUMENTATION.
LONG ION CHAMBER CORNER oSPARE WELL LONG ION CHAMBER INDIAN POINT UNIT No. UFSAR FIGURE 7.4-3 2 PLAN VIEW INDICATING DETECTOR LOCATION RELATIVE TO CORE MIC. No. 1999MC3879 IREV. No. 17A
0 III III ---10 SAS AMJ PROlloUS CCRRACK[31 p -----I L _____ g ______ _'. __
I I *l'NL "SF" L
- -----TO HEA' RD10VAL I VLV730CI'<CJITS
: -I : 1----1--1 I I I I ;--------ro RVLlS CAl>. "LCI"
---rn SAS AND PRmrus CCR
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---IJ '-iloAI RloMOVAL I -VLV 731 -------r --I I 1----: I : r----.J I i14* \I L_ _ --
3116" O.D.TUBit-£;
INDIAN POINT UNIT No. 2 UFSAR FIGURE 7.5-1 REACTOR COOLANT WIDE RANGE PRESSURE INSTRUMENT SYSTEM -FLOW DIAGRAM MIC. No. 1999MC3543 REV. No. 17A VALVE POSITIONS ARE NOT CONTROLLED BT THIS FIGURE LEGEND:
rrcLDMOUNTCD
!1'$TR, E-:J "crn. X FILLEJ CAPILLARY TUBH.i:>
0 /\
VESSEL SEAL REACTOR VESSEL SEAL TABLE INDIAN POINT UNIT No. 2 UFSAR FIGURE 7.6-1 TYPICAL ARRANGEMENT OF MOVABLE MINIATURE NEUTRON FLUX DETECTOR SYSTEM MIC. No. 1999MC3880 IREV. No. 17A REACTOR CAW TY FOR DRJ'J'E UN--ITS ---
LJ PLATFORM TRANSFER DEll'I CES EttCLOSURE ACCESS Pt....AN CRANE WALL ,,..--WITHDRAW LIMIT SWITCHES
,-FIVE-PATH TRANSFER
- >EVICES f" ,-WYE UN-ITS I TEN'-PATH TRANSFER OEWCES PATH INDICATOR SWI;"CHES ISOLATION" VALVES SEAL LIN'E ' TO REACTOR ELEY.AT ION INDIAN POINT UNIT No. 2 UFSAR FIGURE 7.6-2 ARRANGEMENT OF INCORE FLUX DETECTOR MIC. No. 1999MC3881 REV. No. 17 A THERMOCOUPLE CONDUIT ..----::;::i._u_L_,;.:'..__L:........L___L__,
SU PP ORT THERMOCOUPLE INSTALLATION 0 MIXING DEVICE MI CONNECTOR ASSEMBLY (4/1 OR 5/1)
COLUMN I . \ T/C CONNECTOR THERMOCOUPLE CONNECTOR TO MI CABLE CONNECTOR ASSEMBLY INDIAN ,..._., , I ' ... I ' ' I ------1!
\
\) . I I I ""-
c--rCQ:o">,
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POINT UNIT No. 2 UFSAR FIGURE 7.6-3 INCORE INSTRUMENTATION
-DETAILS MIC. No. 1999MC3882 IREV. No. 17A