ML21307A201

2 to Updated Safety Analysis Report, Section 5, Figures 5.1-1 to 5.4-21

ML21307A201
Person / Time
Site:	Perry
Issue date:	10/28/2021
From:	Energy Harbor Nuclear Corp
To:	Office of Nuclear Reactor Regulation
Shared Package
ML21307A174	List: L-21-018, 2 to Updated Safety Analysis Report, Section 4, Figures 4.2-1 to 4.6-9 ML21307A176 ML21307A177 ML21307A178 ML21307A179 ML21307A180 ML21307A181 ML21307A182 ML21307A183 ML21307A184 ML21307A185 ML21307A186 ML21307A187 ML21307A188 ML21307A189 ML21307A190 ML21307A191 ML21307A193 ML21307A194 ML21307A195 ML21307A196 ML21307A197 ML21307A198 ML21307A200 ML21307A201 ML21307A202 ML21307A204 ML21307A205 ML21307A207 ML21307A208 ML21307A209 ML21307A210 ML21307A211 ML21307A213 ML21307A214 ML21307A215 ML21307A216 ML21307A217 ML21307A218
References
L-21-018
Download: ML21307A201 (61)

Text

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=.loocc 302-0243-0000 FOR VALVE F051D J-7

3 P57 F036 1" 1 *" F574B A005 1" F573B 302-0271-0000 C-3 1" 1" NC D0022 (F047F) F572B 2" D0025 (F041G)

P57 B21 2" A 1" F571B 1" "C" CLASS F081 L2-3 L2-4 NC EMERGENCY F078 CONTAINMENT AIR SUPPLY f" VB DRYWELL B21P52 1 *"L2-3 1"F029A 1" (H-1 & H-2) A002 302-0271-0000 SEE DC DC AO F037 6"G1-3 DRYWELL HEAD 2" A F567B NOTE VB TYPICAL NON-ADS VALVE EXCEPT FOR F051D SEE DETAIL-1 "C" CLASSIFICATION 3 B21P57 15 B A 2"E1-3 FOR QTY SEE TABLE I (302-0608-00000) S S O D030 1 *" 2" 1" P52 2" SEE P52 SCV SCV A001 302-0244-0000 2" NOTE 302-0243-0000

P52F036 1" 1*" D0022 (F047F) A 2"F024A *" (H-5, 6, 7) f" 21 & 22 *" J-6 C 302-0244-0000 A004 D0025 (F041G) P628 D0021 (F047F) (H-5, 6, 7)1" A VALVE CONTROL VALVE CONTROL O O ANCHOR D0024 (F041G) DIAGRAM B21-F022/28 F084A DIAGRAM B21-F022/28 O 10" G1-3D2-2 3 B 2" f" SEE NOTE 16 AMM AMM RMS SEE NOTE 16 C F100 L2-4L2-3 2" F078 D F083A 4 RMS 4 P631 C VB R659 RMS R661 RMS C G1-3 P52B21 2" A A 2" D1-1 EXCEPT B.W. f" F0376" E TO ITEMS TO ITEMS RMS RMS F587 B13D020 TR AMM AMM f" ND ND VB A B21EC071 5 P601 5 P601 4" SEE DC DC"C" CLASS H TE NOTE 11 AO R614 P680 R660 R662 NOTE TO ITEM6 A TO ITEM6 A TT P631 P601 D E 2" D1-1 15 S B S A E N004 B21EC070 STEAM LINE N601 SEE TABLE I P&ID DATA SCV SCV D0021 (F047F) POS SCRAM SIG "A" ONLY B RELIEF VALVE O D030 10" REF. 808-0302 DWG. 302-0608-00000 PIPING G005 D0024 (F041G) O C

• AO AO

O O O 2"E1-3 f" O C TT TE C F022 F028 P628 O PRESSURE VESSEL C C A A N601 N040 TO DRYWELL P631 F100 C P680 D1-2 A REFUELING SEAL F587 C f" STEAM LINE "D" RMS RMS G1-3 SCRAM SIG REF. 808-0302 O f" PX P631 P601 POS DETAIL-1 SEE TABLE I TE E FE E32 R720 1 '" E31-1010 P&ID DATA DWG INTERLOCK STEAM LINE POS C F556A 302-0651-0000 ELBOW TAP 302-0608-00000 PIPE GUIDEG009

• GUARD PIPE F527A A SEE DETAIL THIS N004 N005A RESTRAINT H-7 3" * *" D-14 2" D1-1 EXCEPT B.W. GR. C DWG. (TYP OF 4) PRIMARY STEAM 26"-D1-1 STEAM LINE "A" P124 TO STEAM 302-0011-0000 2"D1-1 LINE "A" ONLY PIPING G001 TO 1 *" 2" 1"-D2-1 2" STEAM O A003 NC TURBINE REACTOR F039 E F079A VESSEL A004 RELIEF D007A B21EC082 C MO B13D003 302-0271-0000 TE VALVE 2" f" D1-2 (A-3, B-3, C-3, 1" PIPING f"-D2-2 NC NOTES:

F-3, G-3,) N004 G005 F080A F005 2" 2" E 2" 1. STEAM LINES, ENCLOSED IN BOXES HAVE PART NUMBERS CORRESPONDING TO G1-3 B21EC083 TEST THEIR RESPECTIVE LINE NUMBER, UNLESS OTHERWISE NOTED. RMS f" "C" CLASS f" f" D006A EXAMPLE - XXXB IS ON LINE "B"

302-0961-00000 f" XXXC IS ON LINE "C" ND f"-D2-2 B-8

SEE DC F619A 2. ALL EQUIPMENT AND INSTRUMENTS AND INPUT SIGNALS TO THE DISPLAY CONTROL P601 NOTE AO 1"-D2-1 302-0961-00000 LX SYSTEM ARE PREFIXED BY SYSTEM NUMBER B21, UNLESS OTHERWISE SPECIFIED. 15 S S D008A B-8

O E SCV SCV 3. DELETED 2"E1-3 f"-D2-2 302-0961-00000 B21EC117 O O C-8 4. SEE DWG 302-0608-00000 FOR QUANTITY AND ORIENTATION OF SAFETY RELIEF C B21EC118 F100 F620A P631 C E 1"-D2-1 f"-D2-2 LX VALVES AND ASSOCIATED EQUIPMENT. O D009A 302-0961-00000 C C O F037 6" C-8 MO RMS 5. DELETED. VB TO F002 C F078 DRAIN 6. FOR OTHER MODES OF OPERATION, SEE NUCLEAR BOILER SYSTEM PROCESS DIAGRAM AND P628 VB PROCESS DATA GE DWGS 131C7911 (08 -0030-00000) AND 131C7911C (08 -0031-00000). P601 RMS RMS

302-0964-0000 SEE TABLE I A PX TEST 7. TO BE CONNECTED INTO THE STRAIGHT RUN OF PIPE DOWNSTREAM OF F026 WITH A-5 2 UPSTREAM AND DOWNSTREAM STRAIGHT LENGTH FROM THE TAP TO GIVE AS ACCURATE P601 P&ID DATA DWG O E P631 302-0608-00000 R720 B A PRESSURE MEASUREMENT AS FEASIBLE. TAPS TO MEET ASME PTC 6 1964 "STEAM D2-2G1-3 F556B F060B TURBINES" PARAGRAPH 4.74. B21EC115 TYPICAL ADS VALVE E PT C B21EC116 FOR QTY SEE NOTE 4 EA360 f" f" D1-2 8. AN EXPANSION LEG SHALL BE PROVIDED IN INSTRUMENT SENSING LINE BETWEEN POT P416 N733 F527B F079B (PART D002) AND THE WATERTIGHT PENETRATION THROUGH THE VESSEL TO DRYWELL FOR NUMBER OF SAFETY/RELIEF STEAM LINE "B" SAME AS STEAM TO STEAM G-14 REFUELING SEAL. THE EXPANSION LEG AND PIPING INSTALLATION SHALL BE MO RMS VALVES & ASSOCIATED PARTS SEE LINE "A" UNLESS OTHERWISE NOTED 302-0011-00000 DESIGNED TO ALLOW FOR MAXIMUM CHANGE OF VESSEL LENGTH WITH TEMPERATURE TO NOTE 4 AND DETAIL STEAM LINE "A" (SEE NOTE 1) TURBINE F001 PX AVOID OVER STRESSING THE PIPING OR THE SEAL OR DAMAGE TO THE INSULATION AROUND THE VESSEL. THE CONDENSING CHAMBER, D002, SHALL BE LOCATED ABOVE P601 f" F556C R720 THE HEAD VENT CENTER LINE IN ACCORDANCE WITH SPEC. A62-4070. P122 C 302-0964-0000 F527C A-5 SEE NOTE STEAM LINE "B" STEAM LINE "C" SAME AS STEAM C-14 9. PROVISION FOR INSTRUMENT LINE ISOLATION SHALL BE IN ACCORDANCE WITH CURRENT LINE "A" UNLESS OTHERWISE NOTED TO STEAM LICENSING PRACTICES. ONE ORIFICE SHALL BE INSTALLED IN EACH INSTRUMENT 2" (SEE NOTE 1) 302-0011-00000 LINE CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY (RCPB). ORIFICE TURBINE SHALL BE AS CLOSE AS FEASIBLE TO THE RCPB. ORIFICE SIZE IS '" AND TE F079C MAXIMUM NUMBER OF ORIFICES PER LINE IS ONE. F040 B N061 P415 f" D1-2

10. VALVE MOTOR OPERATORS AND PILOT SOLENOIDS ARE AC OPERATED, UNLESS OTHERWISE SEE NOTE STEAM LINE "B" STEAM LINE "D" SAME AS STEAM F080C F-14 SPECIFIED.

LINE "A" UNLESS OTHERWISE NOTED TEST TO STEAM (SEE NOTE 1) 302-0011-00000 f" TURBINE 11. LOCATE TEE AS CLOSE AS POSSIBLE TO REACTOR VESSEL.

2 F527D F079D 12. SEE TABLE I AND II DATA DWG 302-0607-00000.

PROVIDE A SEPARATE PX DISCHARGE LINE FOR f" D1-2 13. ALL INDICATOR LAMPS LOCATED ON H13P601, UNLESS OTHERWISE SPECIFIED. EACH SAFETY/ D RELIEF VALVE F556D R720 14. FOR CONTROL ROOM, LOCAL OR REMOTE PANEL AND RACK IDENTIFICATION NUMBERS A F080D FOR INSTRUMENT, SEE THE INSTRUMENT INDEX. D0023 (F047F)

SEE A62-4350 C D0026 (F041G) TEST 15. FOR SOLENOID IDENTIFICATION NUMBERS, SEE INSTRUMENT INDEX. FOR NOZZLE E ORIENTATION PT EA361 16. MSIV ACTUATOR CONTROL DIAGRAM: N734 MSIV B21F022A-D DWG 816-0620-00901 MSIV B21F028A-D DWG 816-0620-00000

17. ANNUNCIATOR IS COMMON TO ALL SAFETY RELIEF VALVES POSITION SWITCHES.

18. DELETED.

SEE 302-0602-00000 FOR 19. FOR PENETRATION NUMBERS, SEE INSTRUMENTATION INSTALLATION DWG 814-0665-00000 BALANCE OF VESSEL SUPPRESSION AND 814-0666-00000.

POOL

20. TEMPERATURE ELEMENTS THAT ARE ASSOCIATED WITH ERIS FUNCTION SHALL USE STRAP-ON CHROMEL CONSTANTAN THERMOCOUPLES. THE THERMOCOUPLES SHALL BE MOUNTED APPROXIMATELY HALFWAY BETWEEN THE CONDENSING CHAMBER AND THE

SUPPRESSION DRYWELL TO CONTAINMENT PENETRATION. THE STRAP-ON THERMOCOUPLES SHALL BE POOL WELL INSULATED SUCH THAT THE AMBIENT CONDITION WILL NOT BE A FACTOR TO THE QUENCHER MEASURED INSTRUMENT LINE TEMPERATURE. B21G024 PROVIDE RESTRAINT 21. B21 PIPING CONFIGURATION IS TYPICAL FOR A, B, C, AND D AIR ACCUMULATORS. AGAINST WATER HOWEVER, THE P57 PIPING CONFIGURATION IS THE COMMON SAFETY RELATED AIR DISCHARGE & BLOW-SUPPLY FOR ALL OUTBOARD ACCUMULATORS. DOWN REACTION FORCE

22. CHECK VALVE INTERNALS REMOVED FROM 1B21-F029A, 1B21-F029B, 1B21-F029C &

1B21-F029D (VALVE FUNCTIONS AS STRAIGHT PIPE). REFERENCE ECP 19-0187.

O P-601

SEE C NOTE F589 f" 19 A REFERENCE DRAWINGS: REFERENCE DOCUMENTS: (TYPICAL 19 PLACES)E P-601 (SEE NOTE 17) 208-0015-00000 REACTOR RECIRCULATION SYSTEM ELEMENTARY A62-2050 REACTOR SYSTEM OUTLINE DRAWINGS DIV 4 DIV 1 F588 208-0025-00000 FEEDWATER CONTROL SYSTEM A62-4050 ELECTRICAL EQUIPMENT SEPARATION E 302-0011-00000 MAIN STEAM SYSTEM A62-4070 PROCESS INSTRUMENTATION DESIGN SPEC. 302-0121-00000 MAIN, REHEAT EXTRACTION AND MISCELLANEOUS DRAINS A62-4350 MECHANICAL EQUIPMENT SEPARATION 302-0602-00000 REACTOR RECIRCULATION SYSTEM A62-4430 NSSE DESIGN SPECIFICATION PS 302-0603-00000 REACTOR RECIRCULATION SYSTEM B13-2020 REACTOR ICO DIV 2 DIV 3 302-0604-00000 REACTOR RECIRCULATION SYSTEM B13-D020 HEAD COOLING SPRAY NOZZLE (REV. 22 10/2021)

N410 302-0631-00000 RCIC SYSTEM B21-1020 NUCLEAR BOILER PROCESS DIAGRAM 302-0632-00000 RCIC SYSTEM B21-1050 NUCLEAR BOILER PROCESS INSTRUMENT ELEMENTARY SEE NOTE 4 302-0651-00000 FUEL POOL COOLING AND CLEAN-UP SYSTEM B21-F022/28 ISOLATION VALVE INTERFACE CONTROL DRAWING 302-0671-00000 REACTOR WATER CLEANUP SYSTEM B33-1010 REACTOR RECIRCULATION SYSTEM P AND ID DATA 302-0691-00000 STANDBY LIQUID CONTROL SYSTEM B33-1080 JET PUMP ELEMENTARY 302-0739-00000 LIQUID RADWASTE SUMPS SYSTEM C22-1050 REDUNDANT REACTIVITY CONTROL SYSTEM ELEMENTARY PERRY NUCLEAR POWER PLANT 302-0872-00000 CONTROL ROD DRIVE HYDRAULIC SYSTEM C22-4010 REDUNDANT REACTIVITY CONTROL DIVISION ORIENTATION 302-0961-00000 LEAK DETECTION SYSTEM C91-4030 PERFORMANCE MONITORING SYSTEM OF THE VESSEL 302-0964-00000 LEAK DETECTION SYSTEM C94-4030 DCS I/O LIST 10 CENTER RD., PERRY, OHIO 44081 INSTRUMENTATION 808-0301-00000 REMOTE SHUTDOWN SYSTEM H22-4010 LOCAL PANEL DESIGN SPECIFICATION

& NOZZLES (SEE A62-4350 & H22-4010) 808-0302-00001 REACTOR PROTECTION SYSTEM 808-0302-00002 REACTOR PROTECTION SYSTEM 808-0302-00003 REACTOR PROTECTION SYSTEM 808-0302-00004 REACTOR PROTECTION SYSTEM REACTOR 302-0606-00000 NUCLEAR BOILER SYSTEM B21 NUCLEAR BOILER VESSEL 302-0244-00000 PARALLEL INSTRUMENT AIR DISTRIBUTION SYSTEM P52 302-0271-00000 SAFETY RELATED INSTRUMENT AIR SYSTEM P57 302-0243-00000 INSTRUMENT AIR P52 SYSTEM 302-0608-00000 NUCLEAR BOILER SYSTEM 1" D2-1. SUPPORTING DOCUMENTS:

A42-1010 PIPING AND INSTRUMENT SYMBOLS FIGURE 5.1-3 (SHEET 1 OF 4) A62-4030 PRESSURE INTEGRITY OF NUCLEAR COMPONENTS

DETAIL (DWG. D-302-0605-00000)

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V F606 -872

E-10 F003A TABLE I: PRESSURE INSTRUMENT CONTACT UTILIZATION TABLE II: WATER LEVEL INSTRUMENT CONTACT UTILIZATION

MECH MECH TRANS LEVEL PI TRANSMITTER DIV ELEC TRIP UNIT SYSTEM TRANSMITTER DIV ELEC E/S MPL TRIP UNIT SYSTEM TRIP R003 LOC DIV LOC DIV NUMBER POINT ** A

F PR PR F

PIS N678A RPS (A) LT N027 2 - B21-K615 - SHUTDOWN LEVEL * - PT N078A 1 1 4 FI PC PC FI PS N679A NS (A)(RHR ISOL) LT N044C 3 1 - LI R610C FUEL ZONE * - R012 D013 R010 R006 D011 R011 A A A A A A PIS N678B RPS (B) LT N044D 4 2 - LI R610D FUEL ZONE * - PT N078B 2 2 4 PS N679B NS (B)(RHR ISOL) LT N490 4 3 - LR R615 FUEL ZONE -

PIS N678C RPS (C) LIS N691A ADS (A)/ RHR (A)/ LPCS 1 **

PT N078C 3 3 4 LT N091A 1 1 E21-PS2 PI PS N679C NS (C)(RHR ISOL) LS N692A RCIC 2 R013 ** A ** PIS N678D RPS (D) LIS N691B ADS (B)/ RHR (B)/ RHR (C) 1 ** PT N078D 4 4 4 LT N091B 2 2 E12-PS2 PS N679D NS (D)(RHR ISOL) LS N692B RCIC 2

PT N403A 1 1 ATM RRCS ( )* LIS N691E ADS (A)/ RHR (A)/ LPCS 1 **

PT N403E 1 1 ATM RRCS ( )* LT N091E 1 1 E21-PS2 LS N692E RCIC 2

PT N403B 2 2 ATM RRCS ( )* LS N693E RCIC 8 A006A PT N403F 2 2 ATM RRCS ( )* LIS N691F ADS (B)/ RHR (B)/ RHR (C) 1

PT N067C 3 3 PIS N667C HPCS LT N091F 2 2 E12-PS2 LS N692F RCIC 2

PT N067G 3 3 PIS N667G HPCS LS N693F RCIC 8 A007A

PT N067L 4 3 PIS N667L HPCS LIS N673C HPCS **** 2 1H51-P1432A LT N073C 3 3 E22-PS2 PT N067R 4 3 PIS N667R HPCS LS N674C HPCS 8 C-7 RO ** ** PT N094A 1 1 PIS N694A RHR (A)/ LPCS/ RCIC LIS N673G HPCS 2 TC ** LT N073G 3 3 E22-PS2 -606 TC PT N094E 1 1 PIS N694E RHR (A)/ LPCS LS N674G HPCS 8 **

PT N094B 2 2 PIS N694B RHR (B)/ RHR (C)/ RCIC LIS N673L HPCS 2 ** LT N073L 4 3 E22-PS2 ** PT N094F 2 2 PIS N694F RHR (B)/ RHR (C) LS N674L HPCS 8 TC

• 1 PIS N668A PRESS RELIEF LIS N673R HPCS 2 LT N073R 4 3 E22-PS2 NOTE 2 1 PS N669A PRESS RELIEF LS N674R HPCS 8

PT N068A 1 1 PS N670A PRESS RELIEF LT N402A 1 1 ATM RRCS ** 2

1 PS N617A RE-OPEN / RE-CLOSE (MID) LT N402E 3 1 ATM RRCS ** 2 LOW LOW SET 1 PS N618A RE-OPEN / RE-CLOSE (HIGH) LT N402B 2 2 ATM RRCS ** 2

2 PIS N668B PRESS RELIEF LT N402F 4 2 ATM RRCS ** 2

2 PS N669B PRESS RELIEF LIS N695A ADS (A) 3 LT N095A 1 1 E21-PS2 PT N068B 2 2 PS N670B PRESS RELIEF LS N693A RCIC 8 -872

2 PS N617B RE-OPEN / RE-CLOSE (MID) LIS N695B ADS (B) 3 E-11 LOW LOW SET LT N095B 2 2 E12-PS2 F003B 2 PS N618B RE-OPEN / RE-CLOSE (HIGH) LS N693B RCIC 8

PT N076A 1 1 PIS N676A NS 4 LIS N681A NS (MSIV) 4*** 1

4 LT N081A 1 1 C71-K613A 4 PT N076B 2 2 PIS N676B NS LS N682A NS 2 PI

PT N076C 3 3 PIS N676C NS 4 LIS N681B NS (MSIV) 4*** 1 R003 LT N081B 2 2 C71-K613B ** B PT N076D 4 4 PIS N676D NS 4 LS N682B NS 4 2 **

PT N075A 1 1 PIS N675A NS 4 LIS N681C NS (MSIV) 4*** 1 F PR PR F

4 LT N081C 3 3 C71-K613C 4 PT N075B 2 2 PIS N675B NS LS N682C NS 2 FI PC PC FI 4 4 R012 D013 R010 R006 D011 R011 PT N075C 3 3 PIS N675C NS LIS N681D NS (MSIV) *** 1 B B B B B B 4 LT N081D 4 4 C71-K613D 4 PT N075D 4 4 PIS N675D NS LS N682D NS 2

dPT N032 - - - CORE PLATE dP LIS N680A RPS (A) (RHR ISOLATION) 3 ** LT N080A 1 1 C71-K613A PT N062A 1 1 - - POST ACCIDENT MON. LS N683A RPS (A) 8 PI R013 ** PT N062B 2 2 - - POST ACCIDENT MON. LIS N680B RPS (B) (RHR ISOLATION) 3 B ** LT N080B 2 2 C71-K613B ** 1 PIS N668E PRESS RELIEF LS N683B RPS (B) 8

1 PS N669E PRESS RELIEF LIS N680C RPS (C) (RHR ISOLATION) 3 LT N080C 3 3 C71-K613C ** PT N068E 1 1 PS N670E PRESS RELIEF LS N683C RPS (C) 8

PS N616E RE-OPEN/ RE-CLOSE (LOW) LIS N680D RPS (D) (RHR ISOLATION) 3 1 LOW LOW SET LT N080D 4 4 C71-K613D PS N618E RE-OPEN/ RE-CLOSE (HIGH) LS N683D RPS (D) 8 A006B

2 PIS N668F PRESS RELIEF

2 PS N669F PRESS RELIEF PT N068F 2 2 PS N670F PRESS RELIEF A007B

PS N616F RE-OPEN/ RE-CLOSE (LOW) 1H51-P1432B 2 LOW LOW SET

• REFERENCE B21-1050 PS N618F RE-OPEN/ RE-CLOSE (HIGH) C-11 RO ** **

** REFERENCE C22-4010/ 1050 TC **
-606 TC ATM - ANALOG TRIP MODULE **
*** ADDITIONAL FUNCTIONS ** **

REFERENCE C22-4010/ 1050 - CLOSE DRYWELL FAN COOLER'S COOLING WATER ISOLATION VALVES

• TC
• NS - NUCLEAR STEAM SUPPLY SHUTOFF4 - ISOLATE THE MSIV'S AIR SUPPLY NOTE 2

CONTAINMENT ISOLATION FUNCTION

**** ALSO FEEDS 2-PEN RECORDER R615

NOTES:

1. FOR NOTES AND REFERENCES, SEE DRAWING D-302-605.

V 2. SAFETY RELATED NON-CODE SEISMIC CATEGORY I.*

-872 F607 -872 3. 1/4"O.D. x.049 WALL SEAMLESS STAINLESS STEEL TUBING

E-10 E-12 ASTM A213 TP-304.

F003C F003D 4. THESE VALVES ARE TAGGED PER THE APPROPRIATE 803 SERIES DRAWING.

5. THE FOLLOWING REACTOR VESSEL LEVEL PURGE CONTROL PANELS PI PI SHALL BE ISOLATED FROM THE PARENT LOCAL CONTROL PANELS R003 R003 PRIOR TO CLOSING THE ASSOCIATED PENETRATION ISOLATION VALVES:

** C ** D F PR PR F F PR PR F PURGE CONTROL LOCAL CONTROL ISOLATION PANEL PANEL VALVE

FI D013 PC PC D011 FI FI D013 PC PC D011 FI H51-P1432A H22-P004A B21-F553 R012 C R010 R006 C R011 R012 D R010 R006 D R011 C C C C D D D D H51-P1432B H22-P027 B21-F514

H51-P1432C H22-P005 B21-F505

** ** H51-P1432D H22-P026 B21-F510

PI ** PI ** R013 R013 C ** D **

A006C A006D (REV. 21 10/2019)

A007C A007D

1H51-P1432C 1H51-P1432D PERRY NUCLEAR POWER PLANT

RO ** ** RO ** C-11 TC ** C-7 TC ** ** TC -606 TC 10 CENTER RD., PERRY, OHIO 44081

-606 **

TC TC

• NOTE 2 NUCLEAR BOILER SYSTEM

NOTE 2

FIGURE 5.1-3 (SHEET 3 OF 4)

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SHIELD BLDG. 3.DELETED E 4.DELETED EC054 5.FOR VALVE STEM LEAK-OFF DETAIL,SEE DWG. 302-0964-00000. EC055 O 6.DELETED CONTAINMENT C E 7.DELETED EA001 -632 8.REMOTE RESET CAPABLE AFTER ALL TRIP SIGNALS EXCEPT MECHANICAL OVERSPEED TRIP. E-10 9.GUARD PIPE REQUIRED BETWEEN CONTAINMENT AND DRYWELL. RMS M FC FI 10.DELETED DRYWELL R600 R606 11.DELETED F522F521 MCV MCV F059 12.E51 LEVEL INSTRUMENTATION (LT-N035A,LT-N035E,LIS-N635A, 4" LIS-N635E) ON THE CONDENSATE STORAGE TANK IS SHOWN ON F022 DWG.D-302-102. 3/4" 1" RMS H51-P963 13.E51 LEVEL INSTRUMENTATION (LT-N036A,LT-N036E,LIS-N636A O ZS F090 RMS SQRT D1-2 L1-2 LIS-N636E) IMPULSE LINES FOR THE SUPPRESSION POOL ARE SHOWN H51-P963 D1-4 D1-2 M ON DWG.D-302-686 (AREA J-6). C N547 K601 AC 2 E 14.ALL INSTRUMENTATION TO BE FROM DC BATTERIES.AC INSTRUMENT-S O 1" C-14 ATION REQUIREMENTS MAY BE SATISFIED BY A DC TO AC INVERTER F547 F548 RMS EA004 -632 FROM THE DC BATTERY. 1" D1-4 1" C VENT O SEE E MCV 15.ALL MOTOR OPERATED VALVES,SOLENOIDS AND PUMP MOTORS ARE F546 C DC,UNLESS NOTED OTHERWISE. L2-4 3/4" NOTE 9 EC042 F013 EC043 RO 3/8" FT 3/8" TI F036 E O 16.DELETED EC048 M D006 N003 R005 ECO49 C E 17.DELETED PEN. P123# EC052 F050 3/4" D1-2 EC053 18.ROOT VALVES ARE LOCATED OUTSIDE DRYWELL. F065 1" 6" D1-1 D1-2 D1-2 6" F502 19.DELETED F550-1/4" 3/4" F545 F066 3/4" 3/4" F518 20.DELETED 911-0601-00000 D030 F520B F520A F-4 3" 3/4" F034 3/8" 3/4" C001 3/4" 21.ALL ALARMS,STATUS LIGHTS AND REMOTE MANUAL SWITCHES ARE LX F084 EL.574'-10" PI 1" 1" LOCATED ON PANEL 1H13-P601. R714 F544 PRB-3072 D1-2 1" F035 D1-1 D1-2 FT FE PI PT 3/4" 1" 22.ALL REMOTE MANUAL SWITCHES AND STATUS LIGHTS ARE DUPLICATED LX F085 ON THE REMOTE SHUTDOWN PANEL C61-P001,EXCEPT AS NOTED. 1/2" N051 N001 R001 N050 2" F051 3/8" PIS PT F532 23.ITEM NOT DUPLICATED ON C61-P001. 3/4" A 2 2 (V) FS L N653 N053 F037 1" 24.RING SPACERS D022 AND D023 TO BE PLACED DURING PLANT D1-4 D1-2 DRYWELL N659 OPERATION.SINGLE BLINDS D031 AND D032 TO BE TEMPORARILY D1-4 PI PI A L E F501 INSERTED DURING PERIODIC SYSTEM TESTING.SINGLE BLINDS TO 3/8" BE STORED BETWEEN TESTING. R0010 R0011 E EA005 D2-4 D2-4 RMS FIS PI PIS PI EA006 25.DELETED D2-4 D1-4 " N651 R601 N650 R002 A 26.STRAINER IS SAFETY RELATED NON-ASME INSTALLED H VIA DCP 960042. 3/4" G-6 2"L1-2 27.F046 IS DE-ENERGIZED AND ADMINISTRATIVELY E F519 -632 CONTROLLED OPEN. (REFERENCE NR 94-S-728) 2" 2" RO PI PIS PT -713 EC050 O PEN. P104 EC051 MCV D005 R604 N652 N052 28.ELECTRICAL POWER FOR MOV 1E51F0046 HAS BEEN DISCONNECTED G-13 F549 C005 # M F019 AND THE VALVE WILL BE OPERATED MANUALLY BY THE ACTUATOR AC C HANDWHEEL. THE ACTUATOR, THE MOTOR AND THE VALVE ARE 2" L1-2 F021 PS LEFT IN PLACE. D1-2 A 3/4" L N654 2 29.VENDOR SUPPLIED PIPING BELOW VALVE F505 SERVES BOTH AS A 3/4" F017 PUMP CASING VENT AND TO PROVIDE COOLING WATER TO THE PUMP SEAL. F507 F057 E LX R 1" 30.5" STORZ CONNECTION IS NON-SAFETY, NON-ASME, AND IS INSTALLED EC004 B-1 3" 6" L1-2 FOR RCIC PUMP SUCTION FOR VESSEL INJECTION IN SUPPORT OF THE G 4" L1-2 FLEX STRATEGY. NON-SAFETY, NON-ASME PIPING AND COMPONENTS ARE F508 L1-2D20-2 D1-2 F058 -643 LX RMS f" E12 E51 SEISMICALLY DESIGNED AND INSTALLED. REFERENCE DRAWING REACTOR 302-1000-00000. VESSEL F080 -643 SEE NOTE 23 L1-2 L1-4 C003 31.THE RCIC SYSTEM HAS BEEN EVALUATED FOR BEYOND DESIGN BASIS PEN. P115# E-9 1 1/2" D CONDITIONS PER CALCULATION X11-002. 3/4" WATER LEG F581 F0585 F081 F079 PUMP LX 2" L1-2 1 1/2" EL.574'-10" f" LX AC *" F061F062 2" AC 3/4" L1-4 L1-2 F082 F580 f" 1*" O LX 1/2" *" M MCV 3/4" LX 2" 1" RO L1-4 E-7 C F078 1X11F0013 2" L1-4 F542 F060 D011 -632 LX F543 F083 RMS F579B LX 1X11F0012 PP *" F506 E

REFERENCES:

A LX LX R796 3/4" E EC046 B f" FE EC047 MCV f" 302-0605-00000 NUCLEAR BOILER SYSTEM B21 EC028 RMS F010 N708 F067 EC029 f" F577 302-0642-00000 RHR SYSTEM E12 PP O M R796 F579A *" 302-0643-00000 RHR SYSTEM E12 C A LX 2" 1" 302-0964-00000 LEAK DETECTION SYSTEM E31

-102 L1-2 6"L2-2 A62-4350 MECHANICAL EQUIPMENT SEPARATION J-14 F011 L2-2 L1-2 302-0102-00000 CONDENSATE TRANSFER SYSTEM P11

3/4" 302-0124-00000 MAIN, REHEAT, EXTRACTION AND MISCELLANEOUS DRAINS N22

E O A F578 E51-1020 RCIC PROCESS DIAGRAM EC008 2 EC009 C E51-1050 RCIC ELEMENTARY DIAGRAM D022 RMS O 808-0314 SERIES RCIC FUNCTIONAL CONTROL DIAGRAM TC C E 302-0961-00000 LEAK DETECTION SYSTEM E31 RMS EC010 M EC011 302-0686-00000 SUPPRESSION POOL MAKE-UP AC F042

SEE MCV E51-4010 RCIC SYSTEM DESIGN SPEC NOTE 24 F068 M PEN. P106# A MCV F041 (GE DSP22A6089) F077 F040 A62-4070 PROCESS INSTRUMENTATION DESIGN SPEC 12" L1-2 12" L1-2 3/4" NORMAL WATER LEVEL -632 A62-4140 CLEANING OF PIPING & EQUIPMENT EL.593'-0" 3/4" 10" G-14 C95-1010 ERIS O F503 D023 E LX C C61-4010 RSS DESIGN SPEC GUARD PIPE EC044 L2-2 EC045 F504 302-0701-00000 HIGH PRESSURE CORE SPRAY MCV LX LIS LT F031 3/4" L1-2 V V 302-0705-00000 LOW PRESSURE CORE SPRAY

N636 A N036 A RMS F562 F563 302-0713-00000 MIXED BED DEMIN & DIST. M LX LX F584 F583 2 T.C. 302-0632-00000 REACTOR CORE ISOLATION COOLING SYSTEM,E51 A f f 6" L1-2 H SEE NOTE 13 -574 911-0601-00000 REACTOR BUILDING DRAINS SYSTEM,P68

G-4 F030 3/4" 911-0617-00000 AUXILIARY BUILDING DRAINS SYSTEM,P68 PEN. P101# F032

LIS LT 302-0574-00000 EMERGENCY CORE COOLING SYSTEM SEE N636 N036 NOTE 26 SUCTION STRAINER T21 E E 2 (REV. 20 10/2017) SUPPRESSION POOL PERRY NUCLEAR POWER PLANT 10 CENTER RD., PERRY, OHIO 44081

REACTOR CORE ISOLATION

COOLING SYSTEM FIGURE 5.4-9 (SHEET 1 OF 2)

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'.t/J.001 o.Tl 009 NOTES:

1.DELETED.

2.DELETED.

3.DELETED.

INACTIVE EQUIPMENT 4.DELETED.

(NOTE 39) 5.DELETED.

6.ALL EQUIPMENT AND INSTRUMENTS ARE PREFIXED BY SYSTEM E12, D1-2 G1-2 UNLESS OTHERWISE NOTED.

7.ALL MOTOR OPERATED VALVES ARE AC OPERATED, UNLESS OTHERWISE NOTED.

A AA AA 8.DELETED.

H HH HH 9.VALVE SHOULD BE INSTALLED WITH PACKING GLAND(S) ON UPSTREAM

B-1 D0505A M TRS SIDE OF DISK. ALTERNATIVELY, THE PACKING GLAND(S) CAN BE ON THE 10" F051A DOWNSTREAM SIDE OF THE DISK PROVIDED THE PACKING IS TESTED

-643 FOR LEAKAGE.

F052A 3/4" 10.DELETED. R601

SCV F523A 11.DELETED. 6" F451A 12.PROVISION FOR CONTAINMENT ISOLATION SHALL BE IN ACCORDANCE D-3 F0608 WITH CURRENT LICENSING REQUIREMENTS.

-632 3/4" S F451A PT E F D C B A 13.GUARD PIPE REQUIRED BETWEEN DRYWELL WALL AND CONTAINMENT.

10" SCH.80 SCH.100 14.DELETED. F087A M N026 A 15.DELETED.

B-1 4" 16.DELETED.

-643 17.DELETED.

I/P K003A 3/4" 18.DELETED. F551A L1-2 G1-2

19.DELETED.

20.DELETED. 6" FT M 21.DELETED. F026A N001 F025A 2" 22.DELETED.

NOTE 38 D0506A C61 G 23.FOR DESCRIPTION OF SAMPLE TYPES, SEE DWG. D-302-771. G1-2 L1-2 BLIND 24.HIGH CONTAINENT PRESSURE SIGNAL IN CONJUNCTION WITH A F505A 10" LOCA SIGNAL (AND 10 MINUTE TIME DELAY) OPENS (MO) F028A & B 3/4" 4" 1" AND (MO) F537A & B. D100A 10" F011A 25.DELETED. 4" (NOTE 9) 10" 26.ALL REMOTE MANUAL SWITCHES, ALARMS, AND INDICATING LIGHTS F612 ARE LOCATED ON H13-P601, UNLESS OTHERWISE NOTED. M LX E 27.DELETED. 3/4" EA005 FI FY 28.LOCKED OPEN TO PREVENT OVERPRESSURIZATION VIA LEAKAGE RMS POI O B FT ACROSS F071B.

R603A K610A N015A 29.RING SPACERS D006A AND B TO BE PLACED DURING PLANT R611A C OPERATION, SINGLE BLINDS D008A AND B TO BE TEMPORARILY F0621 N708A E 1C61P001

• INSERTED DURING PERIODIC SYSTEM TESTING. SINGLE BLINDS NOTE 40 TE N709A TO BE STORED IN BETWEEN TESTS.

F065A EC024 O O N710A SEE SEE NOTE 37 EC025 TE E N711ANOTE 34 O POT O EA126

• N712A 30.VALVES F018A, B AND C TO BE THROTTLED TO ACHIEVE REQUIRED RMS C C N027A N713A PUMP MINIMUM FLOW OF 1650 GPM (NOMINAL) BASED ON APPROPRIATE C C N714A CERTIFIED PUMP CURVE FOR EACH LOOP AND LOCKED IN THAT X 1/2" N715A POSITION. THE DESIGN MINIMUM PERMITTED PUMP FLOW IS 1250 GPM.

1C61P001 31.DELETED. RMS M RMS 18" RMS 32.STRAINER T21E0001 IS SAFETY RELATED NON-ASME.

F003A O 33.DELETED.

• N716A RMS 34.EIGHT (8) STRAP-ON RTD'S UTILIZED FOR RHR HEAT EXCHANGER O N717A F049 M FE C PERFORMANCE TESTING (89-13). TYPICAL 6 PLACES.

O N718A TE SEE RMS E N719A N014A 10" 35.CHECK VALVE INTERNALS REMOVED FROM 1E12F046B (VALVE C C O N720A NOTE 34 10" M F610 FUNCTIONS AS STRAIGHT PIPE).

EC018 N721A

• M S C EC019 N722A E F048A SPACER 36.D501A & B TO USE SPACER WHEN USE OF RHR UPPER POOL RETURN S N723A O PATH IS NEEDED DURING REFUEL OPERATION. D501A AND B MAY USE EC026 E D502A SPACER OR BLANK AT OTHER TIMES. SEE ECP 18-0092 FOR 3/4" 1C61P001 18" EC027 ADDITIONAL INFORMATION.

POT V 3/4" C EC111 E F075A F060A POI F567 EC112 37.THE DIAPHRAGM ACTUATOR, BONNET, YOKE, VALVE STEM AND J-9 8" 3/4" FT EC152 G1-2 L1-2 R612A X -643 EC153 PLUG HAVE BEEN REMOVED FROM VALVES F065A & F065B AND LOCAL SAMPLE N052A REPLACED WITH A BLIND BONNET. (VALVE FUNCTIONS AS STRAIGHT PIPE.)

TYPE B 38.VALVES FO26A/B HAVE BEEN DETERMINATED AT THE MCC (SEE NOTE 23) 18" COMPARTMENT. THEY ARE REQUIRED TO MAINTAIN THE

1C61P001 D015A D 3/4" STRUCTURAL AND SEISMIC INTEGRITY OF THE PIPING SYSTEM G2-2 G1-2 2" RMS C61P001 RMS AND TO MAINTAIN A PRESSURE BOUNDARY. O O CI CE E-9 FIS RMS O 39.THE PIPING AND COMPONENTS BETWEEN BLINDS D0505A/B AND G18-4 G2-2 C C F103A F104A R006 N025 D0506A/B ARE INACTIVE AND ARE REQUIRED ONLY FOR THE 4" -643 N652A SEISMIC AND STRUCTURAL INTEGRITY OF THE PIPING SYSTEM. 4" C F055A F549A F587A 3/4" H 1 1/2" F040 M O A 3/4" E O O 1C61P001 M F611 6" LX LX EC109 C LX EC110 O F609 C C E F-12 F024A E RMS G1-2 L1-2 1" 1C61P001 C M TC EC016 M -642 C EC150 EC017 A NC007 EC151 40.VALVE DISK MODIFIED TO ADDRESSOVER PRESSURE PROTECTION. CI CITS F047A L1-4 G1-2 41. RHR A/B PUMP BYPASS LINES, INCLUDING VALVES 1E12F0511A/B, 4" ARE SEISMICALLY QUALIFIED. REFER TO ECP 13-0519. VALVE R610A N020A L6-4 L2-4 1E12F0625A IS ALSO SEISMICALLY QUALIFIED.

TE O 42. HYDROLASE CONNECTION. E 6" N024 LOCAL SAMPLE EC020 G1-2 L1-4 F554 F555 TYPE B C EC021 3/4" RMS F553 3/4" 3/8" SEE NOTE 23 M 3/4" AP-235 F547A F546A F073A 3/4" CE LX 6" L2-4 G18-4 E-9

REFERENCES:

N001A -705 12" A42-1010 PIPING AND INSTRUMENT SYMBOLS

LPCS A62-4030 PRESSURE INTEGRITY OF NUCLEAR COMPONENTS 3/4" D F-6 1" 6" A62-4070 PROCESS INSTRUMENTATION F546C F547C O E -971 TO FDCT'S F512A A62-4140 CLEANING OF PIPING AND EQUIPMENT LX TE OR WCT'S 6" LX EC136 A62-4230 EMERGENCY EQUIPMENT COOLING WATER SPECIFICATION C EC137 G N004A B21-1030 NUCLEAR BOILER SYSTEM FCD

C91-4030 PROCESS COMPUTER SYSTEM INPUT/OUTPUT LIST E F018A D17-1010 PROCESS RADIATION MONITORING SYSTEM 20" 20" NOTE 30 F513A EA124 LX E12-1020 RHR PROCESS DIAGRAM

302-0001-00000 P&ID SYMBOLOGY

F548A RO 302-0002-00000 P&ID SYMBOLOGY 3/4" F514A F585A 302-0082-00000 FEEDWATER SYSTEM, N27 D001A 3/4" 302-0102-00000 CONDENSATE TRANSFER SYSTEM, P11

RMS LX LX 302-0431-00000 POST ACCIDENT SAMPLING SYSTEM, P87 1" F074A M 302-0574-00000 ECC SYSTEM SUCTION STRAINER, T21

E F046A 302-0601-00000 REACTOR RECIRCULATING SYSTEM, B33 O 302-0631-00000 RCIC SYSTEM, E51 EC044 EC045 302-0632-00000 RCIC SYSTEM, E51 1" O C SPACER 302-0642-00000 RESIDUAL HEAT REMOVAL SYSTEM, E12

302-0643-00000 RESIDUAL HEAT REMOVAL SYSTEM, E12 3/4" C F515A F586A 302-0651-00000 FUEL POOL COOLING AND CLEAN-UP SYSTEM, G41 C 3/4" O 302-0655-00000 FUEL POOL COOLING AND CLEAN-UP SYSTEM, G41 1C61P001 LX LX 302-0661-00000 CONTAINMENT SPRAY SYSTEM, E15 C RMS H M F064A 302-0671-00000 REACTOR WATER CLEAN-UP SYSTEM, G33

302-0701-00000 HIGH PRESSURE CORE SPRAY SYSTEM, E22 A A 302-0705-00000 LOW PRESSURE CORE SPRAY SYSTEM, E21 E E L TE 302-0731-00000 LIQUID RADWASTE SYSTEM, G50 EA022 EA030 8" N002A 302-0771-00000 NUCLEAR SAMPLING SYSTEM, P34 302-0792-00000 EMERGENCY SERVICE WATER SYSTEM, P45

PIS PS E B21-1030 302-0831-00000 COMBUSTIBLE GAS CONTROL SYSTEM, M51

EA017 302-0962-00000 LEAK DETECTION SYSTEM, E31 20" 18" 20" N653A N654A 302-0964-00000 E LEAK DETECTION SYSTEM, E31 G1-2 IPC-3N AL 302-0971-00000 FEEDWATER LEAKAGE CONTROL SYSTEM, N27

4" 320-0641-00000 DESIGN SPEC. RESIDUAL HEAT REMOVAL SYSTEM, E12 PIS PIS 320-0642-00000 DESIGN SPEC. RESIDUAL HEAT REMOVAL SYSTEM, E12

N656A N655A F-14 E 320-0643-00000 DESIGN SPEC. RESIDUAL HEAT REMOVAL SYSTEM, E12 6" 3/8" PIS 808-0301-00000 REMOTE SHUTDOWN SYSTEM, C61 TE PT -431 EA032 6" C F595A N684A N003A 1" N053A NC004 1"

3/4" F518A PI PT PT PT 3/4" (REV. 21 10/2019) P45 F085A TX R008A N056A N055A N084A

ELEV.586'-6" F502A F080A N401A F502C F092A LX LX LX LX 6" 1 1/2" F517A C002A F503C F093A F503A F081A TE PERRY NUCLEAR POWER PLANT 3/4" SEE PUMP "B" F

• F029A F031A ON 302-0643-00000 3/4" H-14 10 CENTER RD., PERRY, OHIO 44081 1" 1" 18" 24" N700A -642
• N701A 8" LO 1" N702A 2" N703A F072A A-4 TE N704A LX F0625A SUCT./DISCH.

2" -792 N705A 4" BLIND FLANGE EL.571'-6 3/4" N005A N706A 1" F071A RESIDUAL HEAT N707A 1" LX

8" 8"

DRW F511A E LX REMOVAL SYSTEM

EA020 P45 1"

6" 6" 8" FIGURE 5.4-13 (SHEET 1 OF 3)

AUX. BUILDING CRW EQUIPMENT DRAIN SUMP (DWG. D-302-0641-00000) RMS 1H51 G1-2 L1-2 G1-2 L1-4 P275

SEE NOTE 42 S

12" 2*" F028A F537A G-11 1H51-

-661 P275 F306B f" L1-2 G1-2 RMS M 1" M CONTAINMENT E-9 O 1H51 E F536A LS SPRAY -831 2" C P C-13 P275 EC048O RMS 8" EC049 2" N200A -102 D-8 f" COMBUSTIBLE
-631 C RMS GAS CONTROL F044B F305B CONDENSATE O O F538A O E J-11 TRANSFER RCIC S 1C61-F537B F028B 12" C P001 C EC036 -661 1H51-C H EC037 O A CONTAINMENT M 1" M P275 SPRAY f" C F306A P LS C-13 F044A F560A N200B D1-2 D1-1 L2-3 G1-2 PT PIS AUTOMATIC
-102 8" RMS F536B RMS CNDS. F305A O CONTAINMENT TRANSFER G1-2L2-3 L1-4G1-2 E f" E N062 N662 SPRAY LOGIC F019 F561A EC078 C EC090 A A F0400A EC079 H EC091 F0400B LX A F538B D-3 D501B F037B LX CONTAINMENT PRESSURE MONITORING 3/4" F037A 12" 3/4

F062 F061 12" -651 D-3 DRYWELL HEAD -651 (TYPICAL OF 4) f" 2*" f" f" O LOCATED INSIDE CONTAINMENT D501A F560B CONTAINMENT M LX LX E M CONTAINMENT POOL COOLING C F510A POOL COOLING J-12 F510B 1*" 1*" EC032 G1-2G1-4 EC033 O O -246 1C61 8 F561B RMS P001 C FROM ADHR O C C RMS UPPER CONTAINMENT UPPER CONTAINMENT V O POOL POOL G1-2L1-2 1H51 RMS RMS E C EC074 F578 RMS P275 M F023 CONTAINMENT 1C61-EC075 LX P001 E RO E 12" EC094 2" EC107 O O EC095 D004C 1H51-O EC108 E F575 B S P275 L1-4G1-2 E C PEN O F025C C V C EC102 EC092 #411 LX M EC103 EC093 F041C f" 1" B-14 PEN #P123 12" 12" C F573 -643 F311 LX 6" F039C f" f" F042C f" V P SEE NOTE 13 DRYWELL f"

f" F509C F508C F583 RMS 6" f" 1" LX 1H51 F310 F086 P275

-962 f" E C-3 f F532A EC038 O D1-1G1-2 EC039 H51-RMS H51-FT *" FE P963 P963 F603C 1H51-S C P275 N013 *" N012 12" PT O

F532B RMS POS F301C G1-2 D1-1 N598C N058 C FI O F598C C 1C61 S R607 FULL CP001 E f" 1" P D004A BORE -631 1" 8" SPACER EC042 O O EC043 D010C PIS PLATE E E C-12 F597C F300C O O C C M M EC046 EC100 RMS N658C E-5 C f" C F041A EC047 EC101 F027A F042A 12" 12" RMS

-641 E 18" f" 12" 2*" F039A EC084 E A FULL BORE C-5 F506A f" f" EC085 D1-1G1-2 EC080 D004B SPACER PLATE LX F508A F509A O O EC081
-641 1" E E f" C C O O PEN #P113 f" f" -962 EC008 EC088 EC009 EC089F041B M M C-14 O A-6 12" C 12" f" 12" C 18" H51-RMS H51- -643 f"

F584 F603A C P963 P963 F039B f" F042B F027B V D f" F506B f" F509B F508B 1" PEN LX POS F056B #P412 REACTOR -962 f" LX FEEDWATER PT F598A N598A FEEDWATER D-12 S VESSEL B-3 O 1C61 -082 1" f" H51-RMS H51- -082 -643 6" 12" P001 A-10 N058A 1" -631 P963 P963 F603B F057B C LX C-9 O D010A F597A C-11 8"

C RWCU POS RWCU PIS N598B F598B f"

-672 V -672 RMS D-2 N658A S F588 D-2 f" 1" RMS
-631 1" PT 20" 12" D1-2 C-12 F597B D010B N058 E 1H51 V G1-2D1-2 6" 20" B D1-2 D1-2 G1-2 RMS P275 E 6" EC076 1H51 EC077 V O EC034 P275 RMS F574 M EC035 PIS O LX C M 12" C F053B F582 f" 12" SEE NOTE 13 N658 B LX F050A 1" SEE NOTE 13 F050B f S F053A 1" 8"

S 1H51-O 8" F058A F058B P275 1H51-F301B C f" P275

F059A PEN #P414 F059B O F301A P PEN #P121 PEN #P118 D007A P D-10 F-7 C

-641 1" D007B
-102 F-8 L1-2L2-2 F300A F558A 1" F300B CONDENSATE LX -643 TRANSFER F558B LX 1C61 F556BLX PEN #P431

G-4 P001

-641 18" O F557BLX *"
-431 G-5 PEN #P105 C E F596 6" F605A H-8
-641 O EC096 f F-9 EC097 PEN #P408 f" F-14
-643 PEN #P107 6" RMS C 18" RMS 2" V RO -643 1H51 O E REACTOR P275 S 1H51-RMS D003 P275 F620 EC006 RECIRC F-14 C A EC007 6" F581 B -643 D-10 P f" E -602 F316 EC004 RO F605B D-14 LX 10" F010 C-9 PEN #P429
-102 EC005 D003 6" 18" f" -643 F315 F020 1C61 O C CONDENSATE P001 M TRANSFER f" PEN #P407 O C A-5 D1-1

A M f" -964 NORMAL WATER D C F009 G1-2L1-4 LEVEL EL.593'-0" RO KEYLOCK

L1-4G1-2 20" F008 D003 f" B RMS f" PEN #P421 2" F001 (EA-0119) F550 DRW G-14 LX F501 E 2" EC104 F017C -643

F002 f" EC105 LX PEN G1-2D1-1 1" 18" 6" 10" #P403 O F507 E-4 M 1" H-14 F105 C 24" 2 T.C. -574 -643

G1-4 G1-2 f" F601 F602

T.C. GUARD PIPE L1-2G1-2 LX LX G1-2 L1-4 F067 KEYLOCK SUPPRESSION SUPPRESSION

E RMS POOL POOL KEYLOCK

EC012 F017B EC013 RMS 2"

E DRW 1C61 EC052 18" V F0106 16" P001 GUARD PIPE EC053 PEN O #P402 O K-3 M M 1" J-13 24" 3/4" C F004A J-5 C-5 F004B C

-641 -574 -574 24" -643

f" f" G1-2 IPC-3N IPC-3N G1-2 1" GUARD PIPE F599B 18" F0623B F0623A 18" 10" DRW LX ZS F066B 3/8" NOTES: 2" G1-2L1-2 LX 3/8" ZS F017A IPC-3NIPC-4 F066A G1-2L1-2 N466B 1. FOR NOTES AND DRAWING REFERENCES SEE DRAWING 302-0641-00000. IPC-4IPC-3N N466A LX FUEL POOL COOLING 2 2 F600B

& CLEAN-UP SYSTEM L1-4 G1-2 LX (FUEL STORAGE POOL)

T.C. 2" B T.C. RMS (REV. 22 10/2021) RMS FUEL POOL COOLING F005 302-0655-00000 M 302-0655-00000& CLEAN-UP SYSTEM B-4 M F006A B-5 (FUEL STORAGE POOL) L1-2 G1-2 SEE 302-0681-00000 NOTE 302-0681-00000 1" 42 F-2 20" F-3

O O

f" C C O O E PERRY NUCLEAR POWER PLANT 1C61 C C F533 EC054 P001 EC055 10 CENTER RD., PERRY, OHIO 44081 1C61 10 P001 E

EC014 PT EC015 PIS H A N057 N657 D-12

-246 RESIDUAL HEAT REMOVAL

TO ADHR SYSTEM

FIGURE 5.4-13 (2 OF 3)

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00zt gl NOTES:

1. EXCEPT AT POINT OF CONNECTION WITH BWRS SUPPLIED EQUIPMENT OR PIPING. THE PIPING DESIGNER SHALL SIZE PIPES IN CONFORMANCE WITH THE SYSTEM DESIGN SPECIFICATIONS AND PROCESS DIAGRAM.

2. DELETED.

3. MOUNT FLOW ELEMENT AS CLOSE TO ISOLATION VALVE AS PRACTICAL. LOCATION TO BE IN G-10 g-8 ACCORDANCE WITH ASME PTC 19.5.

302-0613-00000 302-0613-00000 4. ALL SMALL AUXILIARY PIPING CONTAINING PRIMARY FLUID SHALL BE SAME PIPE CLASS AS

MAIN PIPING, EXCEPT IF MAIN PIPING IS CLASS 1 AND AUXILIARY PIPING IS 3/4" OR LESS. THEN CLASS 2 PIPING MAY BE USED. SEE A62-4030.

SEE NOTE 15 5. CHEMICAL CLEANING AND DECONTAMINATION CONNECTIONS SHALL BE PROVIDED TO GIVE

OPTIMUM DECONTAMINATION. CONNECTIONS SHALL BE ARRANGED TO PROVIDE DECONTAMINATION OF THE FOLLOWING EQUIPMENT SEPARATELY FROM EACH OTHER. A. PUMPS B. HEAT EXCHANGERS - THE TUBE SIDE OF BOTH EXCHANGERS MAY BE CLEANED SEE NOTE 28 SEPARATELY FROM THE SHELL SIDE OF THE REGENERATIVE HEAT EXCHANGER OR TOGETHER. C. FILTER DEMINERALIZERS. D. PRESSURE TAP CONNECTIONS TO BE PROVIDED AT HEAT EXCHANGER INLET AND OUTLET A-11 FOR DETERMINING P ACROSS HEAT EXCHANGER DURING START-UP.

302-0772-00000 6. INSTRUMENT LINE VALVING MUST COMPLY WITH INSTRUMENT PIPING SPECIFICATION. SEE

SEE NOTE 20 A62-4070.

7. ALL EQUIPMENT AND INSTRUMENTS ARE PREFIXED BY THE SYSTEM NUMBER G33, UNLESS OTHERWISE NOTED.

FILTER DEMINERALIZER SYSTEM 302-0675-00000 8. TEMPORARY STRAINER SCREENS SHALL BE PROVIDED ON THE SUCTION SIDE OF ALL PUMPS IN ACCORDANCE WITH A62-4140. L1-4 D1-3 F0020 9. ALL LOCATION AND IDENTIFICATION OF INSTRUMENTS, SEE INSTRUMENT DATA SHEET. N-9 TE F-9 302-0672-00000 10.LOCATE P TAPS FOR N0037 SUCH THAT: E-4 TE 1" N0006 A. FULL RANGE IS NOT EXCEEDED PER INSTRUMENT DATA SHEET. 302-0675-00000 3/4" E1-3 D1-3 F0502 B. ELEVATION SHOULD BE WITHIN 30 INCHES BELOW VESSEL 0.

N0019

-X-N-1 11.ALL MOTOR OPERATED VALVES ARE AC OPERATED, UNLESS OTHERWISE SPECIFIED.

N-2 1 1/4" 1 1/4" 2" 12.PROVISION FOR INSTRUMENT LINE ISOLATION BY CUSTOMER. THIS SHALL INCLUDE A 1/4" E-13 3/4" E-14 4"E1-3 N-5 N-5 4"D1-3 ORIFICE INSIDE THE DRYWELL. LINE SPECIFICATION CHANGE SHALL COMPLY WITH A62-4030. 302-0675-00000 302-0672-00000 AP-227 1/2" 13.VENTS AND DRAINS SHALL BE PROVIDED AT ALL HIGH AND LOW POINTS OF THE SYSTEM PIPING. 3/4" DOUBLE VALVING IS REQUIRED. 1" 1" 1" 1"

TE TS 14.GUARD PIPES TO BE QUALITY GR-B. F0550

SEE A62-4140 N0007 N0020 15.TO AVOID EXCESSIVE HEAT EXCHANGE TUBE VIBRATION. A FLOW METERING DEVICE SHALL BE PROVIDED SO THAT THE COOLING WATER FLOW VALUES SHALL NOT EXCEED THE VALUES SHOWN C-7 D-7 POI POT FLOOR EL.652'-2" ON THE PROCESS DATA G33-1030 BY MORE THAN 6%. 302-0675-00000 302-0675-00000 2 1/2" R0613 X 16.DRAIN CONNECTION FROM HIGH PRESSURE SOURCE SHALL BE DESIGNED TO ASME SECTION III F0551 CODE. PARAGRAPH ND3612.4. 1H13P0680 F0520 TIS AH 1H13P0680 17.DESIGN PRESSURE AND TEMPERATURE TO BE ESTABLISHED BY PIPING DESIGNER BASED ON H22P0004 F0029B F0024B F0029A F0024A FEED PUMP SHUTOFF PRESSURE AND SYSTEM ARRANGEMENT. N0008 V

18. THIS DRAWING WAS ADAPTED FROM GE DWG. NUMBER 945E614 SHEET 1, REVISION 0.

SEE ISOLATION K-7 NOTE 5 302-0672-00000 19.ITEMS MARKED X ARE FURNISHED WITH ASSOCIATE EQUIPMENT. FI FI RMS MO SIGNAL 1" 1" 1" 1" 20.CONDUCTIVITY INSTRUMENTS WITH G33 MPL NUMBERS ARE SHOWN ON THE REACTOR PLANT R0605 R0605 F0044 AH 1H13P0680 SAMPLING SYSTEM (P35) DIAGRAM (302-0772-00000). B A 3/4" 3/4" 1H13P0680 1H13P0680 1H13P0680 21.FOR CONTROL ROOM, LOCAL OR REMOTE PANEL AND RACK ID NUMBERS FOR INSTRUMENTS, SEE F0030B F0025B F0030A F0025A THE INSTRUMENT INDEX.

22.PORTIONS OF THE SYSTEM DESIGNATED WITH SAFETY CLASS 3 PIPE LINE SPECIFICATION E O 3/4" 3/4" (E.G. D1-3, E1-3) IN NON-SAFETY CLASS DESIGNATED AREAS (AS IDENTIFIED BY FLAG SYMBOL) WILL BE DESIGNED IN ACCORDANCE WITH THE FOLLOWING REQUIREMENTS: EC028 C A. PIPING AND COMPONENTS ARE NON-SAFETY CLASS AND NON-SEISMIC CATEGORY I. EC029 1H13P0680 B. PIPING AND COMPONENTS ARE DESIGNED, FABRICATED, INSPECTED, TESTED, AND

6"E1-3 INSTALLED IN ACCORDANCE WITH THE REQUIREMENTS OF ASME B AND PV CODE, SECTION III, SUBSECTIONS NA, ND, AND NF. C. PIPING SHALL BE INSTALLED BY SPECIFICATION 44.

1" 1" 1" 1" 1"L1-4 D. DELETED. H22P0002

PI 3"L1-4 3"L1-4 3"L1-4

R0008 SEE NOTE 26

F0552 23.PROVIDES CONTROL ROOM ISOLATION AND REMOTE SHUTDOWN CONTROL OF G33F0004 FOR (V) APPENDIX R REMOTE SHUTDOWN METHOD A. SWITCHES LOCATED ON MOTOR CONTROL CENTER EF1A07.

F0513 24.FOR ISOLATION SIGNALS, SEE NS4 ELEMENTARY DIAGRAM 208-0013-00000.

25.TEMPORARY STRAINERS D0016A AND B, USED FOR START UP ONLY, ARE REMOVED FOR 3/4" PLANT OPERATION. 6"E1-3 6"E1-3 C-14 302-0672-00000 26.THE 1" THREADED PLUGS ARE USED TO HELP DECONTAMINATE THE 3" HEADERS PRIOR TO PERFORMING WORK IN THE APPLICABLE AREAS. THEY ARE SIZED TO ALLOW HIGH PRESSURE FLUSHING OF THESE LINES.

27. OPERATION OF DOUBLE ISOLATION DRAIN VALVES 1G33F0505A/B & 1G33F0506A/B SHALL BE PERFORMED SO AS TO ASSURE THAT NO WATER IS TRAPPED IN THE PIPING BETWEEN THE DOUBLE ISOLATION VALVES.

28. RWCU REGENERATIVE / NON-REGENERATIVE HEAT EXCHANGERS AND THE

ASSOCIATED INTERCONNECTING PIPING ARE VENDOR SUPPLIED. REF. GEK-90388.

29. PIPING, FITTING & COMPONENTS ARE DESIGNED, FABRICATED, INSPECTED & INSTALLED 1H13P0680 TO ASME B & PV CODE SECTION III, SUBSECTION ND. PIPING LINE DESIGNATED

RMS NON-SEISMIC, NON-SAFETY CLASS BUT ANALYIZED FOR 2 OVER 1 REQUIREMENTS.

1 1H13P0680 E O DRYWELL D1-4 D1-1 EC036 MO

REFERENCES:

EC037 C F0106

F0505B 302-0102-00000 CONDENSATE TRANSFER AND STORAGE SYSTEM, P11 3/4"D1-4 A-5 302-0964-00000 302-0335-00000 ZINC INJECTION PASSIVATION SYSTEM, P85 F0506B 2" 302-0602-00000 REACTOR RECIRCULATION SYSTEM, B33 F-10 4"D1-1 302-0602-00000 4" 302-0606-00000 NUCLEAR BOILER SYSTEM, B21

D1-1 D25-1 302-0642-00000 RESIDUAL HEAT REMOVAL SYSTEM, E12

302-0672-00000 REACTOR WATER CLEANUP SYSTEM, G33 1H13P0680 RMS 302-0675-00000 FILTER DEMINERALIZER SYSTEM, G36

302-0731-00000 LIQUID RADWASTE SYSTEM, G50

302-0732-00000 LIQUID RADWASTE SYSTEM, G50 1 1H13P0680 302-0772-00000 REACTOR PLANT SAMPLING SYSTEM, P35 E F0508A D-7 D1-4 D1-1 O MO 3/4"D2-2 302-0962-00000 LEAK DETECTION SYSTEM, E31 EC030 302-0962-00000 EC031 C F0100 302-0964-00000 LEAK DETECTION SYSTEM, E31

F0505A E-7 911-0601-00000 REACTOR BLDG. DRAINS SYSTEM, P68 A-5 3/4"D2-2 302-0962-00000 3/4"D1-4 F0506A 302-0964-00000 1H13P0680 F0508B 911-0617-00000 AUXILIARY BLDG. DRAINS SYSTEM, P68 2" 3/4" F-6 O A62-4030 PRESSURE INTEGRITY OF NUCLEAR COMPONENTS 4"D1-1 4" 302-0602-00000 C E A62-4070 PROCESS INSTRUMENTATION

D1-1 D25-1 EC034 1H13P0601 EC035 1H13P0882 A62-4140 CLEANING OF PIPING AND EQUIPMENT O RMS A62-4240 WATER SAMPLING REQUIREMENTS C 1H13P0680 MO RMS G33-1020 REACTOR WATER CLEANUP SYSTEM FCD

RMS F0102 ISOLATION G33-1030 REACTOR WATER CLEANUP SYSTEM P.D.

1H13P0680 SEE NOTE 24 1H13P0882

F0108 F0109 MO O E

D C EC012 1H13P0680 1 2 F0001 EC013 E (REV. 20 10/2017) O MO D1-1 D2-2 3/4" 2 1 EC032 EC033 C F0101 3/4"D1-4 A-5 D1-2 D1-1 302-0964-00000

A-9 6"D1-1 6"D1-1 H-11 f" D1-4302-0964-00000 302-0672-00000 PERRY NUCLEAR POWER PLANT

D-8 2"D1-1 3" 3" GUARD PIPE (SEE NOTE 14) 302-0602-00000 PEN. NO.131 10 CENTER RD., PERRY, OHIO 44081

FE

F0103 N0035 1 1/2" 1 1/2" SEE NOTE 12 F0523 H22P0009 SEE NOTE 3

D-8 3/4"D2-2 F0507 3/4" FT G-13 REACTOR WATER

302-0602-00000 302-0606-00000

N0037 CLEANUP SYSTEM D2-2 D2-4 SEE NOTE 10 D-8

302-0672-00000

2 FIGURE 5.4-16 (SHEET 1 OF 2)

FI

R0610 (DWG. D-302-0671-00000)

H13P0680 H13-P680

D-13 FI

302-0962-00000 E1-4 L1-4 R602

RMS 4" L1-4 4" E-9 302-0731-00000TO WASTE H13-P882 COLLECTOR TANK

RMC RMS 3" H13-P680 H13-P680 H13-P680 H13-P680 REMOVABLE SPOOL FOR R606 F036 H13-P680 H13-P680 SEE NOTE 24 O CHEMICAL DECONTAMINATION E RMS RMS H E H13-P680 MCV M

EC038 A EC040 F028 C EC039 L MCV H13-P601 F031 O RMS

E M O E H13-P881 E H13-P680 EA100 C M MCV EC004 EC020 F035 MCV C EC005 EC021 O F107 E ISOLATION M S 4" EC026 PS SEE NOTE 24 SCV H22-P002 C PS F433 EC027 N014 H13-P882 MCV H22-P002 D F034 N013 H13-P601 RO 4" F554 NON-ASME SAFETY RELATED D001 RELIEF VALVES INSTALLED O E MCV (V) F555 F068 22 2 PER DCP 97-5074 & M F046 E D1-3 4" (V) GENERIC LETTER 89-09 C EC006 H13-P680 EC007 F516A F516B H13-P680 EC024 F515 3/4" E1-3 E1-2 O O EC025 RO

RMS D5001 FE H13-P881 1/2" 1/2" M 4" F514 F647 F067 F646 N606 C C F033 3/4" 1/4" 1/4" SEE NOTE 3 F-2 E1-3 3/4" 4" 4" E1-3E1-3E1-3 4"E1-2 E1-4 4" L1-4 4" TO CONDENSER 302-0732-00000(NO VALVES BEYOND THIS POINT)

E-14 F636A F636B E-14 PEN# 302-0962-00000 302-0962-00000 SEE NOTE 5 4" PI P424 F071 E1-4 L1-4

*" *" D1-4 D1-3 R005 H22-P002 E1-2 E1-4 F524 2 3/4" F041 SEE FE FE 1" 1"D1-3 A62-4140 (V)

N011 N040 F517 2 F072 F518 D1-3 D1-2 F017A F016A 2 1/2" E1-4 L1-4 3/4" (D) 6" D1-3 D1-2 6" D1-2 F051B 1"D1-3 1"D1-3

D1-3 L1-4 3/4" 3/4" SEE NOTE 3 6" B A MCV 1 1/4" PEN# O F051A P132 N-9 N-7 F042 F037 F057 H13-P680 N-7 N-7 H13-P680 H13-P882 H13-P881 1/2" 1/2" F032 N-3 4" MCV C O POT TE O F039 O F503 M M MCV M F519A F519B

N-4 X N015 C C F052A F052B C F038 F040 F058

-X-

1" (V) E-7 4" 3/4" H13-P601 H13-P601 E S 6" 6" 302-0671-00000 (D) (D) O EC142 SCV 4" F564 RMS POI EC143 F441 6"E1-3 R612 C

H13-P680 H13-P680 K-5 RMS RMS F561 PI F073 302-0671-00000 R600 RMS

f" H13-P882 H13-P881

SEE NOTE 28 E/S E E H13-P680 E1-3 D1-3 MCV EC018 EC016 K600 SEE NOTE 17 F104 EC019 CONTAINMENT SHIELD BUILDING EC017 H13-P680 H13-P613

O M C

1" PT H22-P002 N005 (D) (D) E F553 FLOW LIMITER SEE NOTE 5 (V) (V) EA001 RMS (LOCATED CLOSE TO VALVE) N-6 N-6 N-6 4" F060 F064 SEE NOTE 28 SEE 2 2

A62-4140 F563 F511 H13-P680 3/4" 3/4" N043 F512 D1-3 D1-2 D1-2 D1-3

N-1 F562 F059 F063 N-2 2 1/2" 3/4" PEN#P419

C-4 4" F105 4" f" 4"D1-3 D1-2 4"D1-3 302-0671-00000 N-5 4" N-5 N-5 4" 4"

1" 1" 1" 1 1/4"

H13-P601 MCV MCV H13-P881

O F053 F054 O TE 1" 1" N004 M M E F558A 1" 1" 1" C C 3" FLUSH CONNECTION EC010 SEE NOTE 5 AND EC011 A62-4140 FLOOR EL.652'-2" H13-P882 H13-P601 3/4" 4" F010A F011A H-14 3/4" O O 302-0335-00000 3/4"D1-3 3/4"D1-3 3/4" F045A F012A C C 3/4" F510A PI H51-3/4"D1-3 P1144 RO R001 ABANDONED RMS RMS A IN PLACE F014C F018A D002 F022B A F022C F022A F014A D1-3 L1-4 H13-P882 H13-P881

H22-P002 H22-P002 P43 EL.599'-0" E " F650A F651A

F023C F015C F023B F023A F015A TT TT TT TT EC008 COOLING LOOP F019A EC009 " F652A F653A VENT N609 N608 N607 N610 L1-4 L1-4 CASING VENT

3/4" F654A F655A

" CASING FILL D1-3 H13-P680H13-P680 AND DRAIN D20-2 C001A SEE NOTE 29 TRTR TE F008A AA 3/4" E E C C HH R617R617 C001A 1" 1" 1" 1" 1" 1" 1" EA002 EA003 MA002 MA001 AA F009A F0010B f

3" 1" H51-P5317H51-P5317 STATOR RTDs 4 (TE-N019) (TE-N015) (TE-N015) (TE-N004) THERMOWELL RTD 3" F0011B

SEE NOTE 26 PEN.

PI T/SS MAB2015 3" BASE F0510B R001 N601 3/4" B 3"L1-4 F509A L1-4 PLATE H51-PI f" DRAIN H13-P680 H51-P1144 P1144 RHR HX R009 A C-5 ROOM B

TI H13-P680 B 1" A 1" TO PUMP "B" 911-0617-00000 C-4 R B-7 3" 911-0617-00000 R607 3/4" 1" 1" DRW 302-0612-00000 H13-P680 S PEN. SEE NOTE 25 L1-4 L6-4 MAB2015 RMS D1-3 L1-4 G33 P68 F556B F0521B F0522B f H13-P680 4

3/4" F521A*F522A* J-14 L1-4 D1-3

H13-P613 302-0335-00000 FS H13-P680 A 4" N600 L 3" FLUSH CONNECTION D1-3 D20-2 (V) SEE NOTE 5 AND SEE NOTE 29 A62-4140 D-11 F557A F066 3 3 ABANDONED 1" 1" 1" 1 3 302-0962-00000 IN PLACE 3/4" PUMPS LOCATED

GUARD PIPE NOTE 14 D1-1 D1-3 FI F043A IN AUXILIARY F065 R609 H13-P680 BUILDING

J-4 4" 6"D1-1 6"D1-3 6" 6" 4" 302-0671-00000

PEN# P131 H13-P881 NOTES: MCV F004 O 1. FOR NOTES AND REFERENCES, SEE DRAWING 302-0671-00000. M (REV. 22 10/2021)

C

H13-P601

O PERRY NUCLEAR POWER PLANT RMS RMS C

RMS D1-3 L1-4 10 CENTER RD., PERRY, OHIO 44081

NOTE 23 NOTE 23 EL.599'-0" H13-P881 " F650B F651B COOLING LOOP VENT E " F652B F653B

EC014 CASING VENT

EC015 F654B F655B

" CASING FILL REACTOR WATER H13-P680 AND DRAIN C001B

A TR TE H R617 C001B CLEANUP SYSTEM A H51-P5317 C-4 STATOR RTDs 911-0617-00000 THERMOWELL RTD C-7 FIGURE 5.4-16 (SHEET 2 OF 2) 302-0612-00000

L1-4 L6-4

G33 P68 (DWG. D-302-0672-00000)

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