ML20010D911

Independent Design Review of Palo Verde Nuclear Generating Station Auxiliary Sys I:Before Auxiliary Sys Review Board, Vol Ii,App

ML20010D911
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Site:	Palo Verde
Issue date:	04/08/1981
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
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{{#Wiki_filter:. - _ INDEPENDENT DESIGN REVIEW of the PALO VERDE NUCLEAR GENERATING STATION AUXILIARY SYSTEMS I Before the AUXILIARY SYSTEMS I REVIEW BOARD i VOLUME II APPENDIX l l l l l l l l Phoenix, Arizona April 8, 1981 l t I GRUMLEY REPORTERS PilOENIX, ARIZONA 8109020109 810826 ADOCK05000g PDR A

l O O O I PALO VERDE NUCLEAR GENERATING STATION AUXILIARY SYSTEMS I REVIEW BOARD i i l l i i l PHOENIX, AZ APRIL 8,1981 i c [

AUXILIARY SYSTEliS I INDEPENDENT DESIGN REVIEW 4/08/81 BOARD CONVENES FOR BECHTEL PRESENTATION 4/15/81 APS LICENSING REVIEWS TRANSCRIPT 4/22/81 FINAL TRAllSCRIPT SEllT TO [lRC, REVIEW BOARD AtlD BECHTEL 5/06/81 BECHTEL'S DRAFT RESP 0ilSE SENT TO APS FOR INFORMAL REVIEW 5/13/81 APS COMMENTS ON DRAFT RESP 0:1SE SENT TO BECHTEL 5/27/81 BECHTEL SENDS RESPONSES TO BOARD 6/03/81 APS SEllDS BOARD'S COMMENTS ON RESP 0f1SES TO BECHTEL 6/10/81 THOSE BOARD MEMBERS WITH COMMEllTS WILL REC 0tiVEllE TO MEET WITH BECHTEL* i 6/17/81 LETTER TO NRC CLOSING OUT REVIEW t

• REC 0l1VENING MAY BE FULFILLED WITH CONFERENCE CALL I

SCHEDULE I j

l O O O I AUXILIARY SYSTEMS I REVIEW BOARD AGENDA I l. GENERAL INTRODUCTION II. FUEL POOL COOLING AND CLEANUP FUEL STl' RAGE AND HANDLING 3 I 1. IN'lRODUCTION i 2. SY' TEM OVERV;EW A. DESIGN CRITERIA B. CESSAR INTERFACES C. SYSTEM DESCRIPTION D. OPEh% TION i 3. CONFORMANCE WITH REGULATORY REQUIREMENTS 1 l A. SRP 9.1.1, 9.1.2, 9.1.3, 9.1.11 B. GDC 2, 3,11, 5,1111,115,116, 61, 62, 63 i C. RG 1.13, 1.26, 1,29, 1.102, 1.115, 1.117, 8.8 l D. BTP ASB 3-1, ASB 9-1 E. IlVREG-0612 j F. 10CFR71 i j III. ESSENTIAL COOLING WATER SYSTEM (COMPONENT COOLING WATER SYSTEM) l 1. INTRODUCTION i 2. SYSTEM OVERVIEW l EXHIBIT i )

O O O 1 A. DESIGN CRITERIA ) B. CESSAR INTERFACES C. SYSTEM DESCRIPTION I D. OPERATION 4 3. C0tiFORMANCE WITH REGULATORY REQUIREMENTS I A. SRP 9.2.2 B. GDC 2, 4, 5, 44, IIS, Il6 l l C. RG 1.26, 1.29 D. BTP ASB 3-1 IV. ESSENTI AL SPRAY POND SYSTEM (SERVICE WATER SYSTEM AND ULTIMATE IlEAT SINK) i I 1. INTRODUCTION l 2. SYSTEM OVERVIEW i i A. DESIGN CRITERIA T B. SYSTEM DESCRIPTION C. OPERATION i t 3. CONFORMANCE WITH REGULATORY REQUIREMENTS [ i i i A. SRP 9.2.1, 3 2,5 I B. GDC 2, 4, 5, litt, 45, Il6 C. RG 1.26, 1.27, 1.29, 1.72, 1.102, 1.117 j D. BTP ASB 3-1, ASB 9-2 EXillBIT ii i

AUXILIARY SYSTEMS BRANCH REVIEW BOARDS Q AUXILIARY FEEDWATER SYSTEM 8/21-22/80 AUXILIARY SYSTEMS I 4/8/81 e FUEL POOL COOLING AND CLEANUP e FUEL STORAGE AND HANDLING e ESSENTIAL COOLING WATER SYSTEM e ESSENTIAL $ PRAY POND SYSTEM A'JXILIARY SYSTEMS II 8/5/81F e REACTOR DRAIN IANK l e DEMINERALIZED WATER SYSTEM e POTABLE AND SANITARY WATER SYSTEM O co"oe"S^Te Stoa ^ee e COMPRESSED AIR e FLOOR DRAINAGE e MAIN STEAM e CIRCULATING WATER SYSTEM e CONDENSATE AND FEEDWATER e HEATING, VENTILATION AND AIR-CONDITIONING SYSTEMS AUXILIARY SYSTEMS III 9/2/81F e FLOOD PROTECTION e MISSILE PROTECTION ~ e HIGH AND MODERATE ENERGY LINE BREAKS O EXHIBIT 1-1 l l

O O O AUXILIARY FEE 0 WATER SYSTEM 1 REFUEUNG ATM ESSENTIAL SHUT 00WN POOL ATM C00LlhG COOLING

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f , r ESPS ECWS RS HEACIGH I i CS CWS l l FEE 0r7ATER SPRAY COOLING PD:40 l l TOWER l l REACTOR 1 r a g g l l g COOLANT i PUMP AND l I l AUXlLIARIES 4 w yn l l l l 8 OlESEL GENERATOR l l kj j, 1 r I H -X *S l l h FUEL l l = POOL l l m l l 8 COOLING g g = H.x l I I I I NLWS PCWS FPCS g I: = i SPENT l l l NUCLEAR COOLING l L______4-___] FUEL WATER l POOL L________#_____J H-x TURBINE COOLING i WATER l g H-X FdEL POOL COOLl'NG SYSTEM (FPCS), ESSENTIAL COOLiiJG WATER SYSTEM (ECWS), ESSENTI AL SPRAY POND SYSTEM (ESoS), AND ASSOCIATED SYSTEMS FIGURE 1-1

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l O o o J FUEL STORAGE N1D I!ANDLING NSSS/B0P SCOPE OF SUPPLY it l NSSS (CESSAR) B0P l i e REFUELING MACHINE e NEW FUEL STORAGE RACKS e CEA CHANGE PLATFORM e SPENT FUEL STORAGE RACKS e FUEL TRANSFER SYSTEM (INCLUDES e NEW FUEL HANDLING CRANE UPENDERS AND CARRIAGE) e CASK HANDLING CRANE l e SPENT FUEL HANDLING MACHINE e CONTAINMENT POLAR CRANE l e NEW FUEL ELEVATOR e f11SCELLANEOUS i i E i I l 1 I EXilIBIT 1-2 l

O O O SPENT FUEL SPENT NEW FUEL H ANDLIN G FUEL POOL HANDLING CASK H ANDLING MACHINE AND STORAGE CRANE CONTAINMENT CRANE (CESSAR) RACKS (10 TON) BUILDING (150 TON) (BOP) (BOP) STEAM (BOP) { GENERATOR C ASK LO ADING PIT { REtUELING CEA i i MACHINE H 1 "^ 0 r'j _R - (CESSAR) H PLATFORM ,I \\[, _{ l a (CESSAR) A i 7 4 DECON PIT r-J l %\\ 5 EY...=.1 t[b,. Q NEE =i40 Lc ) .8 N i FUEL INSP y M REACTOR 8 STATION / VESSEL r -- - ,e I NEW FUEL i STORAGE RACKS 'l l (BOP) NEW FUEL k RE ACTOR C00 LENT STEAM ELEVATOR PUMP (TYP) GENERATOR FUEL BUILDING (CESSAR) i A FUEL TRANSFER SYSTEM (INCLUDES UPENDERS & CARRIAGE) (CESSAR) f FUEL STORAGE AND H ANDLING SYSTEMS-PLAN VIEW FIGURE 1-2

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O O O PVNGS CLASSIFICATIONS A. QUALITY CLASS "O" e FULL COMPLIANCE WITH 10CFR50, APPENDIX B, PER ANSI N45.2-1971. (ALL ENGINEERED SAFETY FEATURES (ESF) AND/0R ASME SECTION III COMPONENTS ARE "0") B. QUALITY CLASS "R" i e SIMILAR TO 10CFR50, APPENDIX B, BUT REQUIRES LESS EXTENSIVE DOCUMENTATION. 1 C. QUALITY CLASS "S" i e INDUSTRY STANDARD EQUIPMENT. D. SEISMIC CATEGORY I e REMAIN FUNCTIONAL FOR SSE AND FUNCTIONAL AND WITHIN ELASTIC RANGE FOR OBE i E. SEISMIC CATEGORY ll 4 ) e COMPONENTS ESSENTIAL TO POWER GENERATION DESIGNED TO NOT MALFUNCTION FOR AN l EQUIVALENT STATIC LOAD OF 0.13G HORIZONTAL AND 0.09G VERTICAL F. SEISMIC CATEGORY III e DESIGNED FOR AN EQUIVALENT STATIC LOAD OF 0.05G OR TO MEET UNIFORM BUILDING i CODE FOR SEISMIC ZONE 2 G. SEISMIC CATEGORY IX I e DESIGN ANALYZED FOR NON-COLLAPSE FOR SSE. i EXHIBIT 1-3

l O O O b i 1 i t j 1 I I l t t l I 1' II. FUEL P0OL COOLING AND CLEANUP l FUEL STORAGE AND llANDLING I l 1 l t i i i i i i 1 I l l EXillBIT 2-i l

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D O V V DESIGN CRITERIA FUEL POOL C00LIllG AtID CLEANUP SYSTEM 1. THE FUEL POOL COOLING SYSTEM (FPCS) REMOVES HEAT FROM THE SPENT FUEL POOL (SFP). 2. THE FUEL POOL CLEANUP SYSTEM MAINTAINS WATER CLARITY IN THE SFP, FUEL TRANSFER CANAL, AND DEFUELING POOL, AND PROVIDES CLEANUP CAPABILITY FOR THE REFUELING WATER TANK (RWT). i 3. THE FPCS IS DESIGNED TO LIMIT THE SFP TEMPERATURE TO 125F WITH 1/3 CORE OF SPENT FUEL PLACED IN THE POOL 6 DAYS AFTER SHUTDOWN, PLUS THE DECAY HEAT FROM 12 ONE-THIRD CORES OF SPENT FUEL STORED IN THE POOL FROM THE PREVIOUS 12 REFUELINGS. IT SHALL BE ASSUMED THAT URANIUM OXIDE FUEL IS USED. IN THE EVENT OF FAILURE OF A SINGLE COOLING SYSTEM COMPONENT, THE POOL TEMPERATURE IS LIMITED TO lil5F, II. THE FPCS, IN CONJUNCTION WITH THE SHUTDOWN COOLING SYSTEM (SCS), IS DESIGNED TO LIMIT THE SFP TEMPERATURE TO 125F WITH 1/3 CORE OF 90 DAY IRRADIATED, 6 DAY ( DECAYED FUEL; 1/3 CORE OF 1-1/Il YEAR IRRADIATED, 6 DAY DECAYED FUEL; l/3 CORE OF 2-1/2 YEAR IRRADIATED, 6 UAY DECAYED FUEL; PLUS 1/3 CORE ASSUMED TO HAVE BEEN IN THE POOL FOR 90 DAYS FROM A PREVIOUS SHUTDOWN, AND THE SPENT FUEL FROM 12 PREVIOUS ANNUAL REFUELINGS. IT SHALL BE ASSUMED THAT URANIUM OXIDE FUEL IS USED. 5. Tile SYSTEM DESIGH SHALL NOT CAUSE THE WATER LEVEL TO FALL BELOW THE MINIMUM LEVEL OF9FEETABOVETHETOPOFSPENTFUELASSE'MbESDURINGFUELHANDLING. s- / EXHIBIT 2-1 y

O O O DESIGN CRITERIA FUEL P0OL COOLING AND CLEANUP SYSTEM 6. THE FPCS IS DESIGNED TO SEISMIC CATEGORY I AND THE FUEL 000L CLEANUP LOOP IS DESIGNED TO SEISMIC CATEGORY lli REQUIREMENTS. 7. NORMAL MAKEUP TO THE SFP SHALL BE SUPPLIED FROM THE LIQUID RADWASTE RECYCLED WATER. A SEISMIC CATEGORY I MAKEUP SOURCE AND SUPPLY SHALL BE PROVIDED TO THE SFP FROM THE RWT. A BACKUP MAKEUP SOURCE SHALL BE AVAILABLE FROM THE l CONDENSATE STORAGE TANK. 8. THE SFP SHALL PROVIDE AN ALTERNATE SOURCE OF BORATED WATER FOR THE CHEMICAL AND VOLUME CONTROL SYSTEM (CVCS). 9. THE FUEL P0OL CLEANUP SYSTEM SHALL BE DESIGNED FOR THE FOLLOWING WATER CHEMISTRY: (1) PH (77F) 4.5 TO 10.2 (2) BORIC ACID, MAXIMUM WT PERCENT 2.5 (3) AMMONIA, MAXIMUM PPM 50 (4) LITHIUM, MAXIMUM PPM 0 TO 0.5 (5) DISSOLVED AIR, MAXIMUM SATURATED (6) CHLORIDE, MAXIMUM PPM 0.15 (7) - FLUORIDE, MAXIMUM PPM 0.1 EXillBIT 2-2

O O O DESIGN CRITERIA FUEL POOL COOLING AND CLEANUP SYSTEM 10. THE FUEL POOL CLEANUP SYSTEM SHALL CONTAIN TWO EQUIPMENT TRAINS. EITHER OR BOTH TRAINS SHALL BE ABLE TO CLEAN UP THE SFP, THE REFUELING POOL, OR THE RWT. l 11. THE FUEL POOL CLEANUP SYSTEM SHALL BE ABLE TO PROCESS THE CONTENTS OF THE SPENT l FUEL POOL IN 211 HOURS. I i 12. THE FUEL POOL CLEANUP SYSTEM SHALL BE DESIGNED TO LIMIT THE ' RADIATION LEVEL IN THE VICINITY OF THE POOL TO LESS THAN 2.5 MREM /HR. SUCTION AND DISCHARGE N0ZZLES SHALL BE LOCATED ON OPPOSITE SIDES OF THE POOL TO FACILITATE MORE EFFECTIVE CLEANUP. 13. FOLLOWING THE LOSS OF 0FFSITE POWER (LOP), THE FPCS CAN BE POWERED FROM THE EMERGENCY POWER SUPPLY. i i 1 11. THE FOLLOWING DESIGN CODES AND STANDARDS SHALL BE MET: A. PUMPS e FUEL POOL COOLING SYSTEM i i i AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), BOILER AND PRESSURE VESSEL CODE, SECTION III, CLASS 3 j e FUEL POOL CLEANUP SYSTEM ASME BOILER AND PRESSURE VESSEL CODE, SECTION VIII, AND ANSI B31.1 j EXHIBIT 2-3

4 i O O O i i DESIGN CRITERIA ) FUEL P0OL COOLING AND CLEANUP SYSTEM B. HEAT EXCHANGERS e ASME BOILER AND PRESSURE VESSEL CODE, SECTION 111, CLASS 3 j j e TUBULAR EXCHANGER MANUFACTURERS ASSOCIATION (TEMA) C. FILTERS AND ION EXCHANGERS e ASME BOILER AND PRESSURE VESSEL CODE, SECTION Vill a D. PIPING e FUEL POOL COOLING SYSTEM ASME BOILER AND PRESSURE VESSEL CODE, SECTION llI. CLASS 3 l e FUEL POOL CLEANUP SYSTEM i ASME BOILER AND PRESSURE VESSEL CODE, SECTION lli (CONTAINMENT ISOLATION: DESIGN REQUIREMENTS SPECIFIED BY DESIGNER WITH l APPROPRIATE CONSIDERATION OF THE INTENDED SERVICE AND OPERATING CONDITIONS.) ANSI, B31.1, FOR POWER PIPING i I i j EXHIBIT 2-4

O O o l DESIGN CRITERIA FUEL STORAGE AND llANDLING SYSTEfi l 1) IHE STORAGE OF NEW FUEL SHALL BE DESIGNED TN ACCORDANCE WITH THE FOLLOWING DESIGN BASES: i i A. ACCIDENTAL CRITICALITY SHALL BE PREVENTED FOR THE MOST REACTIVE ARRANGEMENT OF NEW F' EL STORED, WITH OPTIMUM MODERATION, BY ASSURING THAT K IS LESS THAN J ggp l ~ 0.98. THIS DESIGN BASIS SHALL BE MET UNDER ANY NORMAL OR ACCIDENT CONDITIONS. B. THE REQUIREMENTS OF REGULATORY GUIDE 1.29 SHALL BE MET. C. THE STORAGE RArVS AND FACILITIES SHALL BE SEISMIC CATEGORY I. D. STORAGE SHALL 65 PROVIDED FOR AT LEAST 1/3 CORE OF NEW FUEL. .i i i I l i EXilIBIT 2-5 1

O O o DESIGN CRITERIA FUEL STORAGE AND HANDLING SYSTEM i 2) THE STORAGE OF SPENT FUEL SliALL BE DESIGNED IN ACCORDANCE WITH THE FOLLOWING DESIGN i BASES: i A. ACCIDENTAL CRITICALITY SHALL BE PREVENTED FOR THE MOST REACTIVE ARRANGEMENT i 0F FUEL STORED WITH OPTIMUM MODERATION BY AVOIDING A K GREATER THAN 0.95. gpp i THIS DESIGN BASIS SHALL BE MET UNDER ANY NORMAL OR ACCIDENT CONDITIONS. 1 3. THE REQUIREMENTS OF REGULATORY guide 1.13 SHALL BE MET. i i i C. THE STORAGE RACKS AND FACILITIES SHALL BE SEISMIC CATEGORY I. I i D. STORAGE SHALL BE PROVIDED FOR UP TO 1329 FUEL ASSEMBLIES. E. THE STORAGE RACKS AND SPENT FUEL POOL FACILITIES SHALL PREVENT EXTENSIVE BULK BOILING IN THE FUEL RACKS AND PREVENT FUEL ASSEMBLY PEAK CLAD TEMPERATURES FROM EXCEEDING 650F, i F. SHIELDING OF SPENT FUEL SHALL BE ADEQUATE TO ENSURE THAT THE RADIATION ZONE l CRITERIA ARE MET. i i i' EXHIBIT 2-6 i i

. _ _ = U O DESIGN (_JTERIA ({') o i FUEL STORAGE AND HANDLING SYSTEM 4 i i ) 3) THE NEW FUEL HANDLING CRANE IS DESIGNED IN ACCORDANCE WITH THE FOLLOWING DE BASES: j i A. THE LOAD BEARING MEMBERS OF THE NEW FUEL HANDLING CRANE SHALL BE SEISMIC CATEGORY I. i THE CRANE SHALL BE DESIGNED IN ACCORDANCE WITH CMAA SPECIFICAT B. ELECTRIC OVERHEAD TRAVELLING CRANES. I l 1 C. THE NEW FUEL HANDLING CRANE SHALL BE DESIGNED TO PREVENT TROLLEY OPER OVER THE SPENT FUEL POOL EXCEPT BY THE USE OF A KEY-OPERATED INTERLOC OVERRIDE. D. l HOISTING LOAD LIFT FORCE SHALL BE RESTRICTED TO 5000 POUNDS WHEN FUEL 1 ASSEMBLIES ARE BEING LIFTED. I l E. THE NEW FUEL HANDLING CRANE SHALL BE RESTRAINED AND SUPPORTED i DOES NOT BECOME A HAZARD, IN THE EVENT OF AN SSE, TO SAFETY GRADE i l l COMPONENTS, SYSTEMS, OR STRUCTURES. EXHIBIT 2-7 4 e

l DESIGN CRITERIA FUEL STORAGE AND HANDLING SYSTEM f0 THE CASK HANDLING CRANE IS DESIGNED IN ACCORDANCE WITH THE FOLLOWING DESIGN BASES: A. THE LOAD BEARING MEMBERS OF THE CASK HANDLING CRANE SHALL BE SEISMIC l CATEGORY I. I B. THE CRANE SHALL BE DESIGNED IN ACCORDANCE WITH CMAn SPECIFICATION ll0. 70 - l ELECTRIC OVERHEAD TRAVELLING CRANES. l C. THE CASK HANDLING CRANE SHALL BE DESIGNED TO MEET THE DROP LIMIT REQUIREMENTS OF 10CFR71, APPENDIX 0. D. THE CASK HANDLING CRANE SHALL BE DESIGNED NOT TO OPERATE OVER THE SPENT 3 FUEL POOL. j E. THE CASK HANDLING CRANE SHALL BE RESTRAINED AND SUPPORTED SUCH THAT IT l DOES NOT BECOME A HAZARD, IN THE EVENT OF AN SSE, TO SAFETY GRADE COMPONENTS, j SYSTEMS, OR STRUCTURES. 1 4 i i i 1 EXillBIT 2-8 l j I

O o o DESIGN CRITERIA 1 I FUEL STORAGE AND HANDLING SYSTEM 5) THE CONTAINMENT POLAR CRANE IS DESIGNED IN ACCORDANCE WITH THE FOLLOWING DESIGN BASES: A. THE LOAD-BEARING MEMEERS OF THE CONTAINttENT POLAR CRANE SHALL BE SEISMIC CATEGORY I. i 3. THE CRANE SHALL BE DESIGNED IN ACCORDANCE WITH CMAA SPECIFICATION 4 l fl0. 70 - ELECTRIC OVERHEAD IRAVELLING CRANES. C. THE CONTAINMENT POLAR CRANE SHALL BE RESTRAINED AND SUPPORTED SUCH THAT IT i DOES NOT BECOME A HAZARD, IN THE EVENT OF AN SSE, TO SAFETY GRADE COMPONENTS, f SYSTEMS OR STRUCTURES. 1 { D. THE CONTAINMENT POLAR CRANE SHALL BE DESIGNED NOT TO RAISE THE BOTTOM OF THE 4 REACTOR VESSEL HEAD HIGHER THAN 17 FEET ABOVE THE REACTOR VESSEL FLANGE WHILE THE CRANE HOOK IS OVER THE REACTOR VESSEL FLANGE, EXCEPT WITH A KEY-OPERATED i f INTERLOCK OVERRIDE USED WITH APPROPRIATE OPERATIONAL PROCEDURES. 4 i i EXHIBIT 2-9

O o o i l FUEL SYSTEll DESIGN i t CESSAR INTERFACE REQUIREMENTS l I

REFERENCE:

CESSAR SECTION 11.2.5 1 REQUIREMENT DESIGN FEATURE i PROTECTION FROM NATURAL PHENOMENA i t i e THE SPENT FUEL POOL SHALL BE A IN COMPLIANCE. j SEISMIC CATEGORY I STRUCTURE. e THE SPENT FUEL STORAGE RACKS SHALL IN COMPLIANCE. BE SEISMIC CATEGORY I. I i i i i 4 i i i I EXHIBIT 2-10 t

~ .._.m. m- !s O O O 4 FUEL SYSTEM DESIGN 1 CESSAR INTERFACE REQUIREMENTS

REFERENCE:

CESSAR SECTION 11.2.5 REQUIREMENT DESIGN' FEATURE i PROTECTION PROM PIPE FAILURE i e THE FUEL SHALL BE PROTECTED FROM NOT FPLICABLE AS THERE ARE THE EFFECTS OF PIPE WHIP WHILE IN ONLY MODERATE ENERGY PIPES STORAGE. IN THE FUEL BUILDING. i e SPENT FUEL SHALL BE PROTECTED IN COMPLIANCE. FROM THE EFFECTS OF PIPE RUPTURE. 1 i PROTECTION FROM MISSILES 0 IHE FUEL SHALL BE PROTECTED FROM IN COMPLIANCE. l-j THE EFFECTS OF MISSILES WHILE IN j STORAGE. i 1 l EXIIIBIT 2-11 i

i l O O O I FUEL SYSTEM DESIGN l j CESSAR INTERFACE REQUIREMENTS

REFERENCE:

CESSAR SECTION 4.2.5 i l REQUIREMENT DESIGN FEATURE i SEPARATION 1 i 1 i e THE NEW FUEL STORAGE RACKS SHALL IN COMPLIANCE BE DESIGNED SUCH THAT FUEL ASSEMBLIES I WILL NOT BE INSERTED IN OTHER THAN i PRESCRIBED LOCATIONS. e ADEUUATE MARGIN TO CRITICALITY SHALL IN COMPLIANCE l l BE PROVIDED FOR FULL RACK LOADINGS OF FUEL ASSEMBLIES HAVING A MECHANICAL I j DESIGN SIMILAR TO THAT DESCRIBED IN j CESSAR CHAPTER 4.0'AND ENRICHMENTS UP + l TO 3.7 WITHOUT U-235. i e THE DEGREE OF SUBCRITICALITY PROVIDED IN COMPLIANCE SHALL BE CONSISTENT WITH THE NcQUIRE-MENTS OF ANSI STANDARD N18.2 SECTION 5.7.4.l. j EXilIBIT 2-12

l O o o FUEL SYSTEM DESIGN j CESSAR INTERFACE REQUIREMENTS I

REFERENCE:

CESSAR SECTION 4.2.5 l DESIGN FEATURE REQUIREMEUI I THERMAL LIMITATIONS i e DRAINS, PERMANENTLY CONNECTED SYSTEMS, IN COMPLIANCE i AND OTHkR FEATURES OF THE SPENT FUEL i POOL SHALL BE DESIGNED SO THAT NEITHER f MALOPERATION NOR FAILURE CAN RESULT IN l LOSS OF COOLANT THAT WOULD UNCOVER THE f STORED FUEL. i l Il0NITORING i i l e LOW WATER LEVEL ALARMS SHALL BE PROVIDED IN COMPLIANCE FOR THE REFUELING POOL AND THE SPENT i FUEL POOL. ,i 1 l l I EXHIBIT 2-13 i

O o o j' FUEL SYSTEM DESIGN t i CESSAR INTERFACE REQUIREMENTS l

REFERENCE:

CESSAR SECTION 4.2.5 i. REQUIREMENT DESIGN FEATURE IllSPECTION AND TESTING e INSERVICE INSPECTION SHALL BE PERFORMED IN COMPLIANCE I l IN ACCORDANCE WITH SECTION XI 0F THE l ASME CODE. j RELATED SERVICES 1 e FOR REFUELi'1G OPERATIONS, THE CONTAINMENT IN COMPLIANCE l POLAR CRANE SHALL HAVE A MINIMUM l CAPACITY OF 225 TONS. i j A. A HOISTING SPEED OF 6 IN/ MIN IN COMPLIANCE. A HOIST i OR LESS SHALL BE UTILIZED SPEED OF 3 IN/ MIN IS i DURING REFUELING OPERATIONS. PROVIDED. i B. A LOAD MEASURING DEVICE SHALL BE IN COMPLIANCE i PROVIDED FOR USE DURING HEAVY LIFTS. 4 I 1 i EXHIBIT 2-14 i

O O O FUEL SYSTEM DESIGN d CESSAR INTERFACE REQUIREMENTS REFENNCE: CESSAR SECTION 4.2.5 REQUIREMENT DESIGN FEATURE i C. A LOW INCHING SPEED IS REQUIRED IN COMPLIANCE DURING THOSE PORTIONS OF THE LIFT i WHEN CLOSE TOLERANCE SURFACES ARE j ENGAGING EACH OTHER. i 8 AN OVERHEAD CRANE SHALL BE PROVIDED IN IN COMPLIANCE THE NEW FUEL STORAGE AREA TO FACILITATE f HANDLING OF NEW FUEL. l ] A. THE CRANE CAPACITY SHALL BE AT LEAST IN COMPLIANCE. THE NEW FUEL 1 TON TO ACCOMMODATE THE WEIGHT OF HANDLING CRANE HAS A 10-TON A FUEL ASSEMBLY. CAPACITY. B. A VERTICAL HOISTING SPEED OF 6 FT/ MIN IN COMPLIANCE. f OR LESS SHALL BE PROVIDED. C. THE CRANE LOAD SHALL BE CAPABLE OF IN COMPLIANCE. f j BEING LIMITED TO PREVENT THE HOIST LOAD FROM EXCEEDING 5000 POUNDS WHEN HANDLING FUEL ASSEMBLIES. EXHIBIT 2-15

O o o FUEL STORAGE AND llANDLING 1 i CESSAR INTERFACE REQUIREMENTS

REFERENCE:

CESSAR SECTION 9.1.4.6 REQUIREMENT DESIGN FEATURE POWER 1 e AT LEAST 24.0 KVA SHALL BE PROVIDED TO POWER IN COMPLIANCE THE FUEL HANDLING SYSTEM. 1 I e INSTRUMENT AIR AND POWER SHALL BE PROVIDED FOR IN COMPLIANCE THE REFUELING EQUIPMENT. PROTECTION FROM NATURAL PHENOMENA e PROTECTION SHALL BE PROVIDED IN ACCORDANCE IN COMPLIANCE WITH GDC 2 0F 10CFR50, APPENDIX A. OPERATIONAL / CONTROLS i IF A SINGLE FAILURE CAN CAUSE THE REACTOR IN COMPLIANCE 4 VESSEL CLOSURE HEAD ASSEMBLY TO DROP ON THE REACTOR VESSEL FLANGE, THE REACTOR VESSEL CLOSURE HEAD ASSEMBLY SHALL NOT BE RAISED TO l A HEIGHT GREATER THAN 17 FEET WHILE ABOVE j THE REACTOR VESSEL FLANGE. EXilIBIT 2-16 i 4

O O o FUEL STORAGE AND flANDLING 1 CESSAR INTERFACE REQUIREMENTS l

REFERENCE:

CESSAR SECTION 9.1.4.6 l i REQUIREMENT DESIGN FEATURE 4 e A MINIMUM WATER COVERAGE OF 9 FEET IN COMPLIANCE l ABOVE THE ACTIVE PORTION OF THE FUEL ASSEMBLY SHALL BE MAINTAINED DURING FUEL STORAGE AND HANDLING. A NOMINAL 2-F00T POOL FREEBOARD } SHOULD BE EMPLOYED. SYSTEM / COMPONENT ARRANGEMENT I j e THE DEPTH OF THE SPENT FUEL POOL SHALL BE A WATER DEPTH OF 22 FEET IS l SUCH THAT A FUEL ROD ASSEMBLY LYING HORIZON-PROVIDED RATHER THAN 23 FEET. I TALLY ON THE TOP OF THE FUEL RACKS SHALL BE COVERED BY A WATER DEPTH OF AT LEAST 23 FEET. i 1 i i i EXfilBIT 2-17

O O o I FUEL STORAGE AND HANDLING ( t CESSAR INTERFACE REQUIREMENTS

REFERENCE:

CESSAR SECTION 9.1.4 G 1 REQUIREMENT DESIGN FEATURE ] RELATED SERVICES ,i e REFUELING POOL i A. ihBEDMENT AND FOUNDATION SUPPORTS IN COMPLIANCE I WITHIN THE POOL SHALL BE DESIGNED TO J ACCOMMODATE THE DESIGN LOADS FROM THE EQUIPMENT' INSTALLED FOR REFUELING. B. ADEQUATE UNDERWATER AREAS SHALL BE IN COMPLIANCE l PROVIDED FOR STORAGE OF THE INTERNALS AND TOOLS WITHOUT INTERFERING WITH I THE REFUELING OPERATION. e SPENT FUEL POOL 1 ll A. EMBEDMENT AND FOUNDATION SUPPORTS IN COMPLIANCE i WITHIN THE POOL SHALL.BE DESIGNED To f ACCOMMODATE THE DESIGN LOADS FROM THE j EQUIPMENT-INSTALLED FOR REFUELING. l EXHIBIT 2-18 4 i'

O o o FUEL STORAGE AND HANDLING CESSAR INTERFACE REQUIREMENTS

REFERENCE:

CESSAR SECTION 9.1.4,6 j REQUIREMENT DESIGN FEATURE i i B. ADEQUATE UNDERWATER AREAS SHALL BE IN COMPLIANCE l l PROVIDED FOR STORAGE OF TOOLS AND EQUIPMENT f WITHOUT INTERFERING WITH THE REFUELING j OPERATION. C. DRAINS AND PERMANENTLY CONNECTED SYSTEMS IN COMPLIANCE I ASSOCIATED WITH THE SPENT FUEL POOL SHALL BE DEdIGNED SO THAT MALOPERATION/ f FAILURE CANNOT UNCOVER THE STORED FUEL. D. IHE FPCS SHALL BE CAPABLE OF REMOVING THE IN COMPLIANCE DECAY HEAT FROM ALL SPENT FUEL PLACED IN I THE POOL. I 4 'l 1 i 1 EXHIBIT 2-19 i

O o o 1 i FUEL STORAGE AND HANDLING 4 l CESSAR INTERFACE REQUIREMENTS

REFERENCE:

CESSAR SECTION 9.1.4.6 i REQUIREMENT DESIGN FEATURE i i e DURING REACTOR OPERATION, THE TOOLS IN COMPLIANCE AND EQUIPMENT ON CESSAR TABLE 9.1-1 SHALL BE STORED IN SUCH A MANNER AS TO MAINTAIN THE TOOLS IN A SAFE CONDITION AND TO PREVENT f THEM FROM DAMAGING SAFETY CLASS EQUIPMENT l DURING A SEISMIC EVENT. ) e Il0 TION BETWEEN THE FUEL TRANSFER TUBE IN COMPLIANCE l SUPPORT POINTS SHALL BE LIMITED TO l 3/4 INCH. A. SUPPORTS FOR THE TRANSFER TUBE SHALL IN COMPLIANCE l i ALLOW THERMAL EXPANSION AND l SEISMIC LOADINGS. 4 I EXHIBIT 2-20 e i 4

O o o i i i FUEL STORAGE AND HANDLING i CESSAR INTERFACE REQUIREMENTS i

REFERENCE:

CESSAR SECTION 9.1.4.6 l REQUIREMENT DESIGN FEATURE i l i e A FIRE PROTECTION SYSTEM SHALL BE PROVIDED TO PROTECT THE FUEL HANDLING i. SYSTEM CONSISTENT WITH THE REQUIREMENTG OF GDC 3, AND SHALL INCLUDE, AS A j MINIMUM, THE FOLLOWING FEATURES: .i h IN COMPLIANCE. l A. FACILITIES FOR FIRE DETECTION AND l ALARMING. I B. FACILITIES OR METHODS TO MINIMIZE THE IN COMPLIANCE. PROBABILITY OF FIRE AND ITS ASSOCIATED EFFECTS. 't C. FACILITIES FOR FIRE EXTINGUISHMENT. IN COMPLIANCE. i i } 2 j } EXHIBIT 2-21

O o o FUEL STORAGE AND HANDLING CESSAR INTERFACE REQUIREMENTS

REFERENCE:

CESSAR SECTION 9.1.4.6 REQUIREMENT DESIGN FEATURE D. METHODS OF FIRE PREVENTION SUCH AS USE IN COMPLIANCE. OF FIRE RESISTANT AND NON-COMBUSTIBLE MATERIALS WHENEVER PRACTICAL, AND MINIMIZING EXPOSURE OF COMBUSTIBLE MATERIALS TO FIRE HAZARDS. i E. ASSURANCE THAT FIRE PROTECTION SYSTEMS IN COMPLIANCE. DO NOT ADVERSELY AFFECT THE FUNCTIONAL I AND STRt'CTURAL INTEGRITY OF SAFETY RELATED S1RUCTURES, SYSTEMS, AND COMPONENTS. i F. CARE SHOULD BE EXERCISED TO ENSURE THAT IN COMPLIANCE. l THE RUPTURE OR INADVERTENT OPERATION OF FIRE PROTECTION SYSTEMS DOES NOT l SIGNIFICANTLY IMPAIR THE CAPABILITY OF SAFETY-RELATED STRUCTURES, SYSTEMS, AND COMPONENTS. i EXHIBIT 2-22 l 4

f_

A o o o I l! FUEL STORAGE AND HANDLING CESSAR INTERFACE REQUIREMENTS i l

REFERENCE:

CESSAR SECTION 9.1.14.6 1 REQUIREMENT DESIGN FEATURE ENVIRONMENTAL 0 DURING REFUELING OPERATIONS, THE IN COMPLIANCE. CONTAINMENT VENTILATION SYSTEM MUST BE CAPABLE OF MAINTAINING THE AMBIENT TEMPERATURE WITHIN THE RANGE OF 70F - 100F IN ORDER TO MAINTAIN THE POSITIONAL ACCURACY OF THE REFUELING EQUIPMENT. i i l I EXHIBIT 2-23

= O O O SYSTEf1 DESCRIPTION FUEL P0OL COOLING AND CLEANUP SYSTEM 1) Fuel POOL COOLING SYSTEM i l e CLOSED-LOOP SYSTEM CONSISTING OF TWO TRAINS, EACH CONSISTING OF ONE PUMP l AND ONE HEAT EXCHANGER, AND PIPING, VALVES, CONTROLS AND INSTRUME1TATION l REQUIRED TO FORM A COMPLETE FUNCTIONAL SYSTEM. e PUMPS ARE PIPED IN PARALLEL AND TAKE SUCTION FROM THE SFF THROUGH A l COMMON SUCTION HEADER. EACH PUMP DISCHARGES, THROUGH A SEPARATE HEAT EXCHANGER, INTO A COMMON DISCHARGE HEADER WHICH RETURNS COOLED WATER TO THE SFP. 2) FUEL POOL CLEANUP SYSTEM e THE FUEL POOL CLEANUP SYSTEM IS COMPOSED OF TWO FLOW TRAINS, EACH CONSISTING 1 0F STRAINER, PUMP, FILTER, AND MIXED BED ION EhCHANGER. EITHER ONE OR BOTH l l TRAINS CAN BE ALIGNED TO CLEAN WATER IN THE SFF, REFUELING POOL, OR RWT. e PROVISION IS MADE FOR TAKING SUCTION FROM ANY OR ALL OF THREE DIFFERENT l LEVELS, AND FR0t'i THE SURFACE SKIMMER IN THE SFP. I i 3 i i 4 i EXHIBIT 2-24 4

h K rJ IL Gk NAT R E UET F A ERW mr O,r L J .~ ] n . R O L T / E - CS AS L I EE O M RV O P E G N U M E UL E R E FO T M E O M RP S I Y K S S P U ]4 I NA EL C2 g j p D2 g 4 r NE j r% d N GI 1 AR L G U I L F + I O O N N ~ W W G R S G C S 0 0 N N R 0I 1 0I 2 E T L E T L P TL P F UOO U00 IL SL O NA HOO H00 F ~ 3" SCL S N O A C C P ~ L t E 4 U r k F s P U f S i P N M A ~ r U E ~ - 1 P L = C T V. Lt N L U oM M N E o IL O E 4 P O d C) SFp ~ 0 P ~. d S h 0 LPUur i C E u L Rm d N N O F P E W G W G O M 0 N g O N h P P 0I OI 2 M U L m-m' IK T LP TLP E N UOO UOO U A S ; s HOO HOO F E SCL SCL S L '4 C ? 7 LS s' K O R S P S S O E P M K A l M ~ ^ LA i N N P M EU CP OU TP A ER IP T C AR 1 ~ UT AP SE ER \\ q I l FS U N F LO CIE ES CT sfa a f 'u RK DN YI 0A NA CN C l 8M OR EO CT RM ll 4 "s ) } 1

SYSTEM DESCRIPTION 4 FUEL STORAGE AND HANDLING i 3) NEW FUEL STORAGE e RACK ASSEMBLIES ARE MADE UP OF INDIVIDUAL RACKS. MINIMUM SPACING IS MAINTAINED BETWEEN ASSEMBLIES IN ADJACENT R0WS, ALLOWING FOR RACK FABRICA-TION TOLERANCES AND PREDICTED DEFLECTIONS RESULTING FROM POSTULATED l ACCIDENT CONDITIONS. e STAINLESS STEEL CONSTRUCTION OF STORAGE RACKS IS COMPATIBLE WITH WATER j i AND ZIRCONIUM-CLAD FUEL. e TOP STRUCTURE OF RACKS HAS NO OPENING BETWEEN ADJACENT FUEL CAVITIES AS { l LARGE AS THE CROSS-SECTION OF THE FUEL BUNDLE. OUTER STRUCTURE OF RACKS PRECLUDES PLACEMENT OF A BUNDLE AGAINST THE RACK CLOSER THAN PRESCRIBED i SPACING. i lj) SPENT FUEL STORAGE i A) SPENT FUEL POOL e THE STAINLESS STEEL-LINED, CONCRETE-WALLED POOL IS AN INTEGRAL PART ] 0F THE FUEL BUILDING. i i EXillBIT 2-25 j

O E N ~ 8- -i } 7/ i / 1 s~ n )H i 1 l l T / G N E L D 1- ~ L E U E F EV ITCA" 3 0 - 5 2 O 1 E ( R K U C G AI RF E GA 3 I R .O N e_ k TS t n U L N d . 7As p 4 ;( W N D E U F N w W q)-) E N N w i = / } / s-n U N C = 5 O 1

.l

O O O SYSTEM DESCRIPTION FUEL STORAGE AND HANDLING i B) SPENT FUEL STORAGE RACKS e RACKS ARE COMPRISED OF INDIVIDUAL MODULES. STORAGE RACKS ARE STAINLESS i STEEL HONEYCOMB STRUCTURES WITH RECTANGULAR FUEL STORAGE LOCATIONS. STAINLESS STEEL CONSTRUCTION OF STORAGE RACKS IS COMPATIBLE WITH FUEL ASSEMBLY MATERIALS AND SPENT FUEL BORATED WATER ENVIRONMENT. RACKS i HAVE THE CAPABILITY TO STORE NEW OR SPENT FUEL IN THREE MODES. 4 i 1. CHECKERBOARD FUEL STORAGE MODE e MINIMUM EDGE-TO-EDGE SPACING BETWEEN FUEL ASSEMBLIES IS MAINTAINED BY STORING FUEL IN A CHECKERBOARD PATTERN WHILE USING "L" INSERTS TO PROPERLY LOCATE A FUEL ASSEMBLY WITHIN A i STORAGE CAVITY. e FUEL ASSEMBLY BLOCKING DEVICES ARE USED IN RACK CELLS THAT ARE NOT WITHIN THE ACCEPTABLE CHECKERBOARD STORAGE PATTERN, i PREVENTING INSERTION OF A FUEL ASSEMBLY INTO AN INTERSTITIAL POSITION. i e STORAGE FOR UP TO 665 NEW OR SPENT FUEL ASSEMBLIES CAN BE PROVIDED IN THIS MODE. j EXHIBIT 2-26 >7

lj 1fll i! AAA// o A A A AA / A A// A A A A A AAf A A A A A / A A AA A A A A AAA/ AA A A A A A AfA/ A A~ A A A A A A A A A A A A A AA\\ A _AA A\\g\\ A A A \\ A=J _T A A A \\ i_ A A d A A A \\ A% ___A A \\ i i A\\\\ El AA\\ \\ <_MmA\\ X u E" \\ 1 = e\\4== n g s I Oe a m En w

==m s g Sa m s s s C m =1 -y o g =

== = 1 E

7

=

E 1 - ;q r r a 1 = _ 1 ~ g r ~ = - r = 7+ _e =-- i - = w~ f = i w =_ = = mr z z e' A pg-r= j x g ?= = )/ m / s J g r _s g / ( f//

= =ae 3 4

/ 4 / \\ / ww 4 f /

=v 4 s # s/

/ g _j;E*Em i v 4 / o ii y mi:s;g! r8a ? (ll'

l O O O i J ARRAWGEMENT OF STAINLESS STEEL "L"lNSERTS AND CELL BLOCKING DEVICES 1 I e g7 r STAINLESS STEEL r r "L" INSERT STAINLESS STtoL / MODULE l ta d' i l / 1 3 7 1 7 / j ] l l 4 / P r F F F / / ( / ~/ I g / / / /////// y 3 3 DETAll-A / r ( ~ I.l N s CELL BLOCKING DEVICE NEW OR SPENT FUEL STORED IN A CHECKERBOARD ARRAY FIGURE 2-5 i i

/5 ( l N,_,/ l I \\, [, I ' f'\\ l l, l!) Y l l ,e ~x, \\_, ' 'f% g, N,,,,, ' ' -{ I, il B I /^ I o N_,) ,./ CELL DETAILS OF "L" INSERT BOX FIGURE 2 6

SYSTEM DESCRIPTION FUEL STORAGE AND llANDLIrlG 2. BORATED FUEL STORAGE NODE e MINIMUM SPACING BETWEEN FUEL ASSEMBLIES IS MAINTAINED j BY STORING FUEL IN RACK LOCATIONS THAT HAVE BEEN LINED WITH A NEUTRON POISON TUBE (E.G., BORAL). l e STORAGE FOR UP TO 1329 NEW OR SPENT FUEL ASSEMBLIES CAN BE l PROVIDED IN THIS MODE. 3. MIXED MODE FUEL STORAGE i i e THIS MODE USES VARIABLE NUMBERS OF "L" INSERTS AND CELL BLOCKING DEVICES IN CONJUNCTION WITH CORRESPONDING NUMBERS z I 0F NEUTRON POISON TUBES TO PR3 VIDE A SEGREGATED MIX OF i CHECKERBOARD STORAGE AND NEUTRON POISON TUBES. i i I i i EXllIBIT 2-27 3

g [u m smuub 3o Z= s o H s O N O g2 s E H O \\ g a m$ \\ w wo \\ :< s w-Es s% a H s \\ < M s E \\ w w s a J N \\ 3 s \\ s N H 32 x x x x xx x xxx x x x N h a l m z I' m 4 o i O l J l J m W m i = W Z 2 N O b a mW ca. OE HD 2 j2 C m m 3 D' l y a m Q W i Z Q., m x W O e saammmmm. mem-mma m z l m 1 <g o ca. a W D l umm-mum

===mmmmm l 1 pumummmme r _' *s . -m-usa E l l ~------ -------- - -- --- n..--.--,

--s.,- O r 1 - i s l N gra f ,,,#'# N,%h( 1 i s' .... g 1 g l r 1l ....J 8 \\sf ,, ) / / f t l gO / i s CELL DETAILS OF POISON TUBE { FIGURE 2-8 1 l .. _. _.. -.. _, - -. _ _ _ _ ~ _ _ -. _.,.

O o o SYSTEM DESCRIPTION FUEL STORAGE AND HANDLING l 5) CASK HANDLING CRANE e THE 150-TON CASK HANDLING CRANE TRANSFERS THE SPENT FUEL CASK BETWEEN THE CASK LOADING PIT, THE DECONTAMINATION PIT, AND TRANSPORTATION VEHICLE. 6) llEw FUEL HANDLING CRANE l e THE 10-TON NEW FUEL HANDLING CRANE TRANSFERS NEW FUEL ASSEMBLIES BETWEEN THE i TRANSPORTATION CARRIER, NEW FUEL INSPECTION STATION, NEW FUEL STORAGE i FACILITY, AND NEW FUEL ELEVATOR. 1 i 7) CONTAINMENT POLAR CRANE i e IHE 225-TON CONTAINMENT POLAR CRANE IS USED DURING REFUELING OPERATIONS. IT i MAY ALSO BE USED FOR MAINTENANCE OPERATIONS FOR THE LIFTING AND REMOVAL 1 i 0F MAJOR ITEMS OF EQUIPMENT IF REQUIRED. 1 I i i 1 i l EXHIBIT 2-28 i 4

I ( "4 4 "4 4 4' 0' 0 9 7 4 89 1 1 1 L L L L E E E (' E. .g*. ? L G i EN U I ) N L LE F DN O A 'A WNA T N EAR 0 A NHC(1 i d N C L O E I U T F C l l E A S R Np ~ E

• e,

G Ao S / \\- N Rt T T N LL LK I CS N EO EC L E E P UO P UA D , [ N SFP SFR \\ \\ w _d A H E 9 D- ) 'l G N } 2 I O n L N N O LT I ) AER N 5 L D0 T E A (1 1 8 i, N ~

• e.'

U EE~ G E U G HE 7" l ( RF P AI SF K N r SA 5'L O AR u CC T ~- N L S E V i L A E R T U E F N R A O G L R O N A C D I M G R D L R N A I I C O L D R U N. N R B A L H E K U SA F C -a b. U Jr i f. ,U 'c. r O i

j ii I

4il!jili;i;j' ji! i li!} I,

U R,. L t i uTA F V V' Ap E FL NE P ~ E O f_ ,(', ~ c N T A S - ~ N -f1 s R L I lllJ J_ C I L G rIl t E N ) A i R U IL N d g' q' E E F D O H WN >m N W A ~ EA^ L E K R NH" kv _ A _ A N N O C A R O T L_y lC C HS i P A L E G O E E .t G N T I S U 7lI3_ Iyl S A L T E F l D C T L R N A A A O _ R O A T G L H N O E E _ E T L L P E G E O T U G N S S U N A _ U E K C L F A _ A D E A R F E R F R R P U - WU._ WO _ C N C E SF ET B M - NS _ T NS _ A F O - ~ (U G B _ ~ - / rIIL. IIt I 0 N G L lIlJ_ 1 I Y' llIIij N H D T 2 A D T ID N OU A / S A E T W H R O! I P P Ll 'r P _S E U K' N I T N L N G S-O A C I A E I L P R T C U F C E L 1,' D E U E C F V F E 4$l G P A e' S* R I N T IN I L D K E N L O UW I O F O U H &D B N Y T O I A L T PL "0 E 0 MR U 5 CV/ 1 7 OE F 6 L EO A DC M hM R xM l O G ) ~~/ N N N ~ I LEO KDNT S NA0 A AR5 ~- C 'H C (1 i -llIlIl glIIiIglli[ f :A, f,f I l Q 1 E l gp NA R C .h [I Af o !1 t i l l lj

O O O OPERATION FUEL P0OL COOLING AND CLEANUP SYSTEM l. COOLING SYSTEM I e .WITH 13 ONE-THIRD CORES FROM REFUELINGS IN THE FUEL POOL, TWO FUEL POOL COOLING PUMPS AND TWO FUEL POOL HEAT EXCHANGERS ARE IN CONTINUOUS i SERVICE. THE FUEL POOL COOLING LOOP CAN BE CONNECTED TO THE SHUTDOWN COOLING SYSTEM TO PROVIDE ADDITIONAL HEAT REMOVAL CAPACITY. i I e WITH 13 ONE-THIRD CORES FROM REFUELINGS AND ONE COMPLETE CORE FROM A 5 REACTOR VESSEL UNLOADING PRESENT IN THE FUEL POOL, ONE FUEL POOL PUMP 1 1 AND ONE FUEL POOL HEAT EXCHANGER, PLUS ONE LOW-PRESSURE SAFETY l INJECTION PUMP, ONE CONTAINMENT SPRAY PUMP, AND ONE SHUTDOWN COOLING HEAT EXCHANGER ARE IN CONTINUOUS SERVICE. i e THE SYSTEM IS MANUALLY CONTROLLED AND OPERATION IS MONITORED l AT THE LOCAL CONTROL PANEL. i e NUCLEAR COOLING WATER FLOW TO THE FUEL POOL HEAT EXCHANGERS IS INITIALLY ADJUSTED TO THE REQUIRED FLOW. i i e THE ECWS CAN BE MANUALLY ALIGNED WITH THE FUEL POOL HEAT EXCHANGER i ON A LOSS OF NUCLEAR COOLING WATER FLOW. LOSS OF WATER IN THE EVENT OF A PIPE AAEAK OUTSIDE THE SFP IS e PREVENTED BY ROUTING PIPES OVER THE SFP WALL AND USING SIPHON BREAKER l HOLES IN PIPES WHICH RUN BELOW THE MINIMUM WATER LEVEL. 1 i EXHIBIT 2-29 i;

o o o OPERATION FUEL POOL COOLING AflD CLEANUP SYSTEM } l 2. CLEAtluP SYSTEM e CLEANUP LOOPS ARE NORMALLY RUN ON AN INTERMITTENT BASIS WHEN REQUIRED BY THE WATER CONDITIONS FROM THE VARIOUS SOURCES. IT IS POSSIBLE TO OPERATE EACH LOOP INDEPENDENTLY. 4 i, e THE SYSTEM IS MANUALLY CONTROLLED AND THE OPERATION MONITORED AT THE j LOCAL CONTROL PANEL. I t e ONE OR BOTH CLEAtluP LOOPS CAN BE ALIGNED WITH THE REFUELING POOL DURING 4 REFUELING. e AT THE END OF REFUELING AFTER THE POOL LEVEL IS LOWERED TO THE REACTOR l VESSEL FLANGE, POOL CLEANUP PUMPS ARE USED TO PUMP DOWN THE WATER CON-TAINED IN THE FUEL TRANSFER CANAL AND UPPER GUIDE STRUCTURE PIT. I h i e CLEAtlVP PUMPS CAN ALSO BE USED TO FILL OR EMPTY THE CASK PIT AND THE FUEL TRANSFER CANAL. i i I I j EXHIBIT 2-30 3

O O O OPERATION FUEL POOL COOLING AND CLEANUP SYSTEM 3. MATER SUPPLY MAKEUP OF BORATED WATER CAN BE PROVIDED FROM THE RWT. e i e NON-B0 RATED WATER FROM THE LIQUID RADWASTE SYSTEM RECYCLE MONITOR TANKS CAN BE USED TO MAKE UP EVAPORATION LOSSES. 4 e CONDENSATE TRANSFER PUMPS CAN FURNISH AN ALTERNATE SUPPLY OF NON-BORATED l I WATER FROM THE CONDENSATE STORAGE TANK. THE CVCS BORIC ACID MAKEUP PUMPS CAN DRAW WATER FROM THE SFP TO PROVIDE e f AN ALTERNATE SOURCE OF BORATED WATER TO THE CVCS.THE VOLUME OF WATER AVAILABLE IS SUFFICIENT TO EFFECT A SAFE SHUTDOWN TO COLD CONDITION. l THE DRAWDOWN OF THE POOL IS LIMITED TO 5 FEET BELOW THE MINIMUM OPERATING WATEP LEVEL BY USE OF A SIPHON BREAKER HOLE AT THIS LEVEL. 11. EMERGENCY CONDITIONS 1 e DURING LOP, FUEL POOL COOLING PUMPS ARE SHED FROM THE POWER SUPPLY PUSES. AFTER DIESEL GENERATORS AND ENGINEERED-SAFEGUARDS EQUIPMENT ARE IN OPERATION, FUEL POOL PUMPS CAN BE OPERATED FROM THE LOCAL CONTROL PANEL TO REMOVE LECAY HEAT. i l EXHIBIT 2-31 1

4 l 0 o o I j OPERATION FUEL HANDLING AND STORAGE SYSTEM 1) NEW fuel HANDLING CRANE e THE NEW FUEL HANDLING CRANE TRANSFERS THE NEW FUEL CONTAINER BETWEEN THE I PAIL CAR AND THE NEW FUEL CONTAINER LAYDOWN AREA, AND FROM THE SHIPPING COMTAINER TO THE NEW FUEL INSPECTION STATION. t UPON COMPLETION OF NEW FUEL INSPECTION, THE CRANE TRANSFERS NEW FUEL INTO THE NEW FUEL STORAGE RACKS. i e DURING REFUELING THE CRANE TRANSFERS NEW FUEL FROM THE NEW FUEL STORAGE RACKS TO THE NEW FUEL ELEVATOR. 1 I EXilIBIT 2-32

-= ) O O O l OPERATION FUEL HAllDLIllG AND STORAGE SYSTEM 2) CASK HANDLING CRANE s e THE CASK HANDLING CRANE TRANSFERS THE SPENT FUEL CASK BETWEEN THE LOADING AREA, DECONTAMINATION PIT, AND SPENT FUEL LOAD PIT. j e UPON ARRIVAL AT THE FUEL BUILDING, THE CASK IS TRANSFERRED FROM THE RAIL CAR INTO THE DECONTAMINATION PIT FOR WASHDOWN. THE CASK IS NEVER MORE THAN l 30 FEET ABOVE THE FLOOR. IHE CASK IS MOVED FROM THE DECONTAMINATION PIT l i I INTO THE CASK LOADING PIT FOR SPENT FUEL LOADING. AFTER COMPLETION OF THE SPENT FUEL LOADING, THE CASK IS RETURNED TO THE DECONTAMINATION PIT FOR l WASHDOWN PRIOR TO SHIPPING AND SUBSEQUENTLY TRANSFERRED ONTO THE RAIL CAR. t i 1 I 1 1 i i i EXHIBIT 2-33

O o o OPERATION FUEL HANDLING AND STORAGE SYSTEM 3) CONTAINMENT POLAR CRANE THE CONTAINMENT POLAR CRANE TRANSFERS THE CONTROL ELEMENT DRIVE MECHANISM l e (CEDM) UNIT, MISSILE SHIELD, AND CEDM ESSENTIAL COOLING UNITS BETWEEN THEIR PERMANENT LOCATIONS AND DESIGNATED LAYDOWN AREAS DURING REFUELING. l THE CRANE IS USED DURING REFUELING FOR LIFTING AND LOWERING THE REACTOR e VESSEL CLOSURE HEAD AND TRANSFERRING IT BETWEEN THE REACTOR AND THE DESIGNATED LAYDOWN AREA. THE REACTOR VESSEL CLOSURE HEAD IS NEVER LIFTED MORE THAN 17 FEET ABOVE THE REACTOR VESSEL FLANGE. l 1 THE CRANE IS USED FOR INSTALLATION OR REMOVAL OF THE REACTOR INTERNALS, e CONTROL ELEMENT

• ASSEMBLIES, UPPER GUIDE STRUCTURE, AND TRANSFER OF THESE COMPONENTS BETWEEN THEIR PERMANENT LOCATION AND DESIGNATED LAYDOWN AREAS.

i l l l EXHIBIT 2-34

O O O REGULATORY REQUIREMENTS I 1 10CFR71 STANDARD REVIEW PLANS NUREG-0612 9.1.1 REV 1;9.1.2 REV 2; 9.1.3; 9.1.4 I I GENERAL 0"^ REGULATORY TECHNICAL DESIGN GUIDES POSITIONS CRITERIA _] I I ASB 3-1, PIPE BRE AKS 1.13, SPENT FUEL STOR AGE GDC-2, N ATUPAL PHENOMEN A ASB 91 HANDLING SYSTEMS 1.26, QUALITY CLASS GDC-3, FIRE PROTECTION 4 1.29, SEISMIC CLASS I G D C-4, ENVIRO NMENTAL/ MISSILE 1.102, FLOOD PROTECTION GD C-5, SH AR ED SYSTEMS I 1.115, TURBINE MISSILES GD C-44, CO O LING WATER 1.117, TORNADO CLASS GD C-45,1NSPECT10N I 8.8, RADI ATION EXPOSURE I G D C 46,T ESTING ~ GD C-61, F UE L,iTORAG E i G D C-62, CRITICALITY GD C-63, MONITO RING l STANDARD REVIEW PLANS 9.1.1 REV.1, 9.1.2 REV. 2, 9.1.3, 9.1.4 FIGURE 2-11 I

O O O SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 2, NATURAL PHENOMENA REQUIREf1ENT DESIGN FEATURE STRUCTURES, SYSTEMS AND COMPONENTS IN COMPLIANCE. THE COMPONENTS OF SPENT FUEL IMPORTANT TO SAFETY SHALL BE DESIGNED COOLING, AND NEW AND SPENT FUEL STORAGE AND TO WITHSTAND THE EFFECTS OF NATURAL HANDLING IMPORTANT TO SAFETY ARE HOUSED IN PHENOMENA SUCH AS EARTHQUAKES, TORNADOES, SEISMIC CATEGORY I, MISSILE-PROOF STRUCTURES HURRICANES, FLOODS, AND SEICHES WITHOUT AND DESIGNED TO SEISMIC CATEGORY l REQUIRE-LOSS OF CAPABILITY TO PERFORM THEIR MENTS. ALL COMPONENTS ARE BEYOND THE SAFETY FUNCTIONS. EFFECTS OF THE DESIGN BASIS FLOOD, TORNADO AND HURRICANE. i 't i I EXHIBIT 2-35 i

l 0 o o i i SRP ACCEPTANCE CRITERIA \\ Y l GENERAL DESIGN CRITERION 3, FIRE PROTECTION f REQUIREf1ENT DESIGN FEATURE ? I i STRUCTURES, SYSTEMS, AND COMPONENTS IN COMPLIANCE. l IMPORTANT TO SAFETY SHALL BE DESIGNED AND l LOCATED TO MINIMIZE THE PROBABILITY AND f EFFECT OF FIRES AND EXPLOSIONS. t i l l i i l i h i i. 1 i i l r EXHIBIT 2-36 4

O O O SRP ACCEPTAt!CE CRITERIA ) l GENERAL DESIGN CRITER10N 4, ENVIRONMENTAL AND MISSILE DESIGN l 1 REQUIREMENT DESIGN FEATURE i STRUCTURES, SYSTEMS, AND COMPONENTS IN COMPLIANCE. I IMPORTANT TO SAFETY SHALL BE DESIGNED FOR i l THE ENVIRONMENTAL CONDITIONS ASSOCIATED j WITH NORMAL OPERATION, MAINTENANCE, TEST-j l ING AND POSTULATED ACCIDENTS, INCLUDING j LOSS-OF-COOLANT ACCIDENT-THEY SHALL BE I APPROPRIATELY PROTECTED AGAINST DYNAMIC EFFECTS, INCLUDING THE EFFECTS OF MIS-l SILES, PIPE WHIPPING, AND DISCHARGING l FLUIDS, THAT MAY RESULT FROM EQUIPMENT FAILURES AND FROM EVENTS AND CONDITIONS } GUTSIDE THE NUCLEAR POWER UNIT. I 1 i 4 1 1 I l i l l EXHIBIT 2-37 i 1

.f O O O t SRP ACCEPTf.NCE CRITERIA i GENERAL DESIGN CRITERION 5, SHARED SYSTEMS i I REQUIREMENT DESIGN FEATURE j STRUCTURES, SYSTEMS, AND COMPONENTS IN COMPLI ANCE. t IMPORTANT TO SAFETY SHALL NOT BE SHARED t BETWEEN NUCLEAR POWER UNITS. i l i i i i i I i t i t I F 1 i I i EXHIBIT 2-38 i t k.

- - = O O O 1 SRP ACCEPTANCE CRITERIA I GENERAL DESIGN CRITERION 44, COOLING WATER 1 REQUIREf1ENT DESIGN FEATURE i A SAFETY SYSTEM SHALL BE PROVIDED TO IN COMPLIANCE. DECAY HEAT FROM SPENT FUEL i TRANSFER THE COMBINED HEAT LOAD OF ESF IS NORMALLY TRANSFERRED BY THE NON-SAFETY SYSTEMS UNDER NORMAL OPERATING AND RELATED NUCLEAR COOLING WATER SYSTEM (NCWS) ACCIDENT CONDITIONS TO AN ULTIMATE TO THE PLANT COOLING TOWERS. DURING LOP, i HEAT SINK. SUITABLE REDUNDANCY IN WHEN THE NCWS IS N0Y AVAILABLE, COOLING CAN INTERCONNECTIONS, LEAK DETECTION, AND BE MANUALLY RE-ALIGNED TO THE SAFETY-RELATED ISOLATION CAPABILITIES SHALL BE ECWS OR SCS, PROVIDING REDUNDANT BACKUP i PROVIDED TO ASSURE THAT THE SYSTEM SYSTEMS. SAFETY FUNCTION CAN BE ACCOMPLISHED, ASSUMING A SINGLE FAILURE WITH OR WITHOUT A LOP. I t i l l 1 i i l EXHIBIT 2-39 i

O O O 1 SRP ACCEPTANCE CRITERIA i GENERAL DESIGN CRITERION 45, INSPECTION I REQUIREMENT DESIGN FEATURE i THE COOLING WATER SYSTEM SHALL BE IN COMPLIANCE. ALL ASME PIPING AND DESIGNED TO PERMIT APPROPRIATE COMPONENTS ARE CAPABLE OF IN-SERVICE- ) PERIODIC INSPECTION OF IMPORTANT INSPECTION PER ASME SECTION XI. ANSI COMPONENTS TO ASSURE THE INTEGRITY COMPONENTS AND NON-EMBEDDED ANSI PIPING AND CAPABILITY OF THE SYSTEM. CAN BE PERIODICALLY INSPECTED. 4 i i i i i ~ EXillBIT 2-40 i

O O O SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 46, TESTING REQUIREMENT DESIGN FEATURE i l THE COOLING WATER SYSTEM SHALL PERMIT IN COMPLIANCE. INSPECTION AND TESTING OF I APPROPRIATE PERIODIC PRESSURE AND ASME COMPONENTS WILL BE CONDUCTED IN FUNCTIONAL TESTING TO ASSHRE (1) STRUC-ACCORDANCE WITH ASME SECTION XI. TURAL AND LEAKTIGHT INTEGRITY OF 5, COMPONENTS, (2) OPERABILITY AND l PERFORMANCE OF ACTIVE COMPONENTS, AND (3) OPERABILITY OF THE SYSTEM AS A WHOLE AND PERFORMANCE OF THE FULL OPERATIONAL ] ] SEQUENCE FOR REACTOR SHUTDOWN AND FOR f LOSS-OF-COOLANT ACCIDENTS. EXilIBIT 2-41 l 4

O O O SRP ACCEPTANCE CRITERIA i GENERAL DESIGN CRITERION 61, FUEL STORAGE AND HANDLING AND RADI0 ACTIVITY CONTROL DESIGN FEATURE REQUIREMENT THE FUEL STORAGE AND HAMDLING SYSTEMS IN COMPLIANCE. ALL COMPONENTS ARE HOUSED j l SHALL BE DESIGNED TO ASSURE ADEQUATE IN SEISMIC CATEGORY I STRUCTURES. THE CONCRETE COMPARTMENTS / POOLS ASSURE PROTEC-l SAFETY UNDER NORMAL AND POSTULATED ACCIDENT CONDITIONS. THESE SYSTEMS TION AGAINST RADIATION EXPOSURE. A POOL SHALL BE DESIGNED TO PERMIT PERIODIC CLEANUP SYSTEM IS PROVIDED. THE FPCS HAS INSPECTION AND TESTING OF COMPONENTS REDUNDANT COMPONENTS. BACKUP COOLING IS PROVIDED BY THE ECWS AND SCS. IMPORTANT TO SAFETY, WITH SHIELDING FOR RADIATION PROTECTION, APPROPRIATE i l CONTAINMENT, AND FILTERING SYSTEMS, A RESIDUAL HEAT REMOVAL CAPABILITY a AND TO PREVENT REDUCTION IN FUEL STORAGE COOLANT INVENTORY UNDER 1 ACCIDENT CONDITIONS. l i i EXHIBIT 2 Il2

o o o SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 62, PREVENTION OF CRITICALITY IN FUEL STORAGE AND HANDLING REQUIREME;1T DESIGN FEATURE IN COMPLIANCE. CRITICALITY IN THE FUEL STORAGE AND HANDLING SYSTEM SHALL BE PREVENTED BY PHYSICAL SYSTEMS OR PROCESSES, l PREFER.G.LY BY USE OF GEOMETRICALLY SAFE CONFIGURATIONS. l l EXHIBIT 2 '13

O O O SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 63, MONITORING FUEL AND WASTE STORAGE REQUIREMENT DESIGN FEATURE ~- APPROPRIATE SYSTEMS SHALL BE PROVIDED IN IN COMPLIANCE. THE DESIGN OF THE FUEL STORAGE SYSTEM AND ASSOCIATED HANDLING SPENT FUEL POOL PRECLUDES UNCOVER-AREAS (1) TO DETECT CONDITIONS THAT MAY ING THE STORED FUEL. AREA RADIA-RESULT IN LOSS OF RESIDUAL HEAT REMOVAL TION MONITORS AND SPENT FUEL POOL CAPABILITY AND EXCESSIVE RADIATION LEVELS. TEMPERATURE INSTRUMENTS ARE AND (2) TO INITIATE APPROPRIATE SAFETY PROVIDED. ACTIONS. ) 1 i, I 4 i I i EXHIBIT 2 lill

O O O SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 1.13, SPENT FUEL STORAGE FACILITY DESIGN BASIS REQUIREMENT DESIGN FEATURE 1. THE SPENT FUEL STORAGE FACILITY 1. IN COMPLIANCE. f SHOULD BE DESIGNED TO SEISMIC l CATEGORY I REQUIREMENTS. J 2. IHE FACILITY SHOULD.BE DESIGNED 2. IN COMPLIANCE. A) TO KEEP TORNADIC WINDS AND ~ MISSILES FROM CAUSING LOSS OF WATERTIGHT INTEGRITY OF THE FUEL i STORAGE POOL AND B) TO KEEP MISSILES FROM CONTACTING FUEL WITHIN THE POOL. i i i i EXHIBIT 2115

O O o SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 1.13, SPENT FUEL STORAGE FACILITY DESIGN BASIS (CONT'D) REQUIREi1ENT DESIGN FEATURE 3. INTERLOCKS SHOULD BE PROVIDED TO 3. IN COMPLIANCE. PREVENT CRANES FROM PASSING OVER STORED FUEL WHEN FUEL HANDLING IS NOT IN PROGR,ESS. DURING FUEL HANDLING OPERATIONS, THE INTERLOCKS MAY BE BYPASSED AND ADMINISTRATIVE CONTROL USED TO PREVENT THE CRANE FROM CARRYING LOADS THAT ARE NOT NECESSARY FOR FUEL HANDLING OVER THE STORED FUEL OR OTHER PROHIBITED AREAS. 11. A CONTROLLED LEAKAGE BUILDING ll. IN COMPLIANCE. SHOULD ENCLOSE THE FUEL POOL. IHE ESSENTIAL HVAC SYSTEMS BUILDING SHOULD BE EQUIPPED WITH AN AND RADIATION MONITORING APPROPRIATE VENTILATION AND FILTRA-INSTRUMENTS ARE PROVIDED. TION SYSTEM TO LIMIT THE POTENTIAL RELEASE OF RADIOACTIVE IODINE AND OTHER RADI0 ACTIVE MATERIALS. EXilIBIT 2116

O o o SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 1.13, SPENT FUEL STORALE FACILITY DESIGN BASIS (CONT'D) REQUIREEtENT DESIGN FEATURE 5. THE SPENT FUEL STORAGE FACILITY SHOULD HAVE AT LEAST ONE OF THE l FOLLOWING: A. CRANES CAPABLE OF CARRYING HEAVY A. IN COMPLIANCE. 2 LOADS SHOULD BE PREVENTED FROM MOVING INTO THE VICINITY OF THE i P00LJ i OR ( B. CRANES SHOULD BE DESIGNED TO B. NOT APPLICABLE. PROVIDE SINGLE-FAILURE-PROOF HANDLING OF HEAVY LOADSJ OR C. THE FUEL POOL SHOULD BE DESIGNED C. NOT APPLICABLE. TO WITHSTAND, WITH('UT LEAKAGE i THAT COULD UNCOVER THE FUEL, j THE IMPACT OF THE HEAVIEST LOAD TO BE CARRIED BY THE CRANE FROM 1 THE MAXIMUM HEIGHT TO WHICH IT l CAN BE LIFTED. i EXHIBIT 2 f!7

O O O SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 1.13, SPENT FUEL STORAGE FACILITY DESIGN BASIS (CONT'D) REQUIREMENT DESIGN FEATURE 6. DRAINS AND PERMANENTLY CONNECTED 6. IN COMPLIANCE. ANY PIPING CONNECTION SYSTEMS THAT BY MALOPERATION OR FROM/INTO THE SPENT FUEL POOL IS OVER FAILURE COULD CAUSE LOSS OF THE TOP OF THE POOL. SIPHON-BREAKING COOLANT OVER THE FUEL SHOULD NOT HOLF.S PREVENT ACCIDENTAL EMPTYING OF BE INSTALLED. SYSTEMS FOR MAIN-iHE POOL BELOW A SAFE LEVEL. TAINING WATER QUALITY AND QUANTITY SHOULD BE DESIGNED SO THAT ANY MALOPERATION OR FAILURE OF SUCH SYSTEMS WILL NOT CAUSE FUEL TO BE UNCOVERED. 7. RELIABLE AND FREQUENTLY TESTED MON-7. IN COMPLIANCE. LEVEL INSTRUMENTATION AND SAFETY-RELATED AREA AND VENTILA-ITORING EQUIPMENT SHOULD BE PRO-VIDED TO ALARM IF THE WATER LEVEL TION RADIATION MONITORS ARE PROVIDED. IN THE FUEL STORAGE POOL FALLS BELOW A PREDETERMINED LEVEL OR IF HIGH LOCAL-RADIATION LEVELS ARE EXPERIENCED. EXHIBIT 2-48

o o o SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 1,13, SPENT FUEL STORAGE FACILITY DESIGN BASIS (CONT'D) REQUIREf1ENT DESIGN FEATURE 8. A SEISMIC CATEGORY I MAKEUP SYSTEM 8. IN COMPLIANCE. SEISMIC CATEGORY I SHOULD BE PROVIDED TO ADD COOLANT MAKEUP IS AVAILABLE FROM THE REFUELING TO THE POOL. APPROPRIATE STORAGE TANK. THE CONDENSATE STORAGE TANK SERVES AS A SEISMIC CATEGORY I REDUNDANCY OR A BACKUP SYSTEM FOR FILLING THE POOL FROM A RELIABLE BACKUP SOURCE. SOURCE SHOULD BE PROVIDED. i l EXHIBIT 2-49

o o o 4 i SRP ACCEPTANCE CRITERIA j REGULATORY GUIDE 1.26, QUALITY GROUP CLASSIFICATION REQUIREMENT DESIGN FEATURE r l COOLING WATER SYSTEMS IMPORTANT TO SAFETY IN COMPLIANCE. ( j THAT ARE DESIGNED FOR RESIDUAL HEAT i J REMOVAL FROM THE SPENT FUEL STORAGE POOL i I SHALL MEET THE REQUIREMENTS OF ASME P&PV CODE, SECTION III, CLASS 3. j 1 1 i 4 l i i l l 1 i 4 f EXHIBIT 2-50 i 1

4 O O O i SRP ACCEPTAtlCE CRITERIA REGULATORY GUIDE 1.29, SEISMIC DESIGN CLASSIFICATION i I i REQUIREMENT DESIGN FEATURE THE COOLING WATER SYSTEMS THAT ARE IN COMPLIANCE. REQUIRED FOR COOLING THE SPENT FUEL 1 STORAGE POOL SHALL BE DESIGNATED ) SEISMIC CATEGORY l AND SHALL BE l DESIGNED TO WITHSTAND THE EFFECTS OF l SSE AND REMAIN FUNCTIONAL. THE QUALITY ASSURANCE REQUIREMENTS OF APPENDIX B TO 10CFR50 SHALL APPLY. i EXHIBIT 2-51

O O O i i 4 SRP ACCEPTANCE CRITERIA coVLATORY GUIDE 1.102, FLOOD PROTECTION i i i REQUIREMENT DESIGN FEATURE l l SAFETY SYSTEMS SHOULD BE DESIGNED TO IN COMPLIANCE. f WITHSTAND THE MOST SEVERE FLOOD i CONDITIONS RESULTING FROM SEVERE HYDROMETEOROLOGICAL CONDITIONS, I { SEISMIC ACTIVITY, OR BOTH. l i } I h 1 i i k L t e EXilIBIT 2-52 t

O o o ~ SRP ACCEPTANCE CRITERIA 1 ) REGULATORY GUIDE 1.115, PROTECTION AGAINST LOW-TRAJECTORY TURBINE MISSILES i l REQUIREMENT DESIGN FEATURE ESSENTIAL SYSTEMS OF A NUCLEAR POWER IN COMPLIANCE. PLANT SHOULD BE PROTECTED AGAINST LOW-TRAJECTORY TURBINE MISSILES DUE TO l FAILURE OF MAIN TURBINE-GENERATOR SETS. i l EXHIBIT 2-53

i O O O ) SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 1.317, TORNi30 DESIGN CLASSIFICATION REQUIREMENT DESIGN FEATURE i THE SPENT FUEL POOL COOLING SYSTEM SHOULD IN COMPLIANCE. j BE DESIGNED TO MAINTAIN ITS CAPABILITY IN THE EVENT OF A DESIGN BASIS TORNADO. THE SPENT FUEL STORAGE POOL SHALL BE IN COMPLIANCE. DESIGNED TO PRECLUDE SIGNIFICANT LOSS OF WATERTIGHT INTEGRITY OF THE STORAGE POOL Att9 TO PREVENT MISSILES FROM CONTACTING FUEL WITHIN THE POOL. i l j i i l 1 i EXHIBIT 2-511

O O O SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 8.8, INFORMATION RELEVANT TO ENSURING THAT OCCUPATIONAL RADIATI0fl EXPOSURES AT NUCLEAR POWER STATIONS WILL BE AS LOW AS IS REASONABLY ACHIEVABLE (ALARA) REQUIREMENT DESIGN FEATURE 1. OCCUPATIONAL RADIATION EXPOSURE A MANAGEMENT COMMITMENT TO ALARA THAT IN COMPLIANCE. APS IS COMMITTED ~ INCLUDES 1) QUALIFIED RADIATION PROTECTION TO ESTABLISH AN OPERATIONAL PERSONNEL, 2) A PROGRAM TO TRnIN AND INSTRUCT PROGRAM FOR RADIATION PROTECTION ALL WORKERS INVOLVED IN RADIATION EXPOSURES, THAT WILL MEET ALARA OBJECTIVES. AND 3) FORMAL REVIEW OF FACILITY DESIGN CHANGES FOR ALARA SHALL BE ESTABLISHED. 2. ALARA DESIGN FEATURES A. CALCULATIONS OF RADIATION FIELDS DUE TO IN COMPLIANCE. RADIATION LEVELS 0.25% FUEL CLADDING DEFECT SOURCE TERMS ASSUME 1% FLEL CLADDING DEFECTS, SHALL BE USED TO DEFINE ACCESS ZONES. AND STORAGE OF PEAK IRRADIATED ACCESS CONTROL SHOULD AVOID TRANSIT FUEL IN THE SPENT FUEL POOL. THROUGH A HIGHER ZONE TO A LOWER THESE LEVELS ALLOW ACCESS TO FPCS COMPONENTS. ZONE. EXHIBIT 2-55

O O O SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 8.8, IllFORMATION RELEVAtlT TO ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES AT ilVCLEAR POWER STATI0tlS WILL BE AS LOW AS IS REAS0rlABLY ACHIEVABLE (ALARA) (CONT'D) REQUIREMENT DESIGN FEATURE B. PIPING, INSTRUMENTATION AND CONTROLS IN COMPLIANCE. MULTIDISCIPLINE SHALL BE ARRANGED TO FACILITATE REVIEWS WERE CONDUCTED TO ASSURE OPERATIONS AND MAINTENANCE AT LOWEST CONSIDERATION OF ACCESS, DOSE, POSSIBLE EXPOSURE. AND COMPONENT DESIGN IN THE PLANT LAYOUT. EXilIBIT 2-56

(' (-} p c) a SRP ACCEPTANCE CRITERIA i BTP ASB 3-1 PROTECTION AGAINST POSTULATED PIPING FAILURES IN FLUID SYSTEMS OUTSIDE CONTAINMENT i REQUIREMENT DESIGN FEATURE THE SYSTEMS AND COMPONENTS IMPORTANT TO IN COMPLIANCE. THE COMPONENTS OF THE SAFETY SHALL BE APPROPRIATELY PROTECTED FUEL POOL COOLING AND STORAGE SYSTEM AGAINST DYNAMIC EFFECTS, INCLUDING THE ARE HOUSED IN SEISMIC CATEGORY I EPM a OF MISSILES, PIPE WHIPPING AND STRUCTURE. THE SPENT FUEL POOL IS l DISCW^+?ING FLUIDS, THAT MAY RESULT ALSO A SEISMIC CATEGORY I STRUCTURE. FRC-ffbli '"ENT FAILURES AND FROM EVENTS PROVISIONS ARE MADE TO PREVENT EMPTYING AN'.; CONDin0NS OUTSIDE THE CONTAINMENT. THE SPENT FUEL POOL. IHE SYSTEM IS i CLASSIFIED AS A MODERATE ENERGY SYSTEM. THERE ARE NO HIGH ENERGY SYSTEMS IN THE AREA. TWO FUEL POOL COOLING f TRAINS ARE PROVIDED. 4 i l i EXHIBIT 2-57

O o o SRP ACCEPTANCE CRITERIA BTP ASB 9-1 OVERHEAD HANDLING SYSTEMS FOR NUCLEAR POWER PLANTS REQUIREMENT DESIGN FEATURE OVERHEAD HANDLING SYSTEMS INTENDED TO PRO-VIDE SINGLE FAILURE-PROOF HANDLING OF LOADS SHOULD BE DESIGNED SO THAT NO SINGLE FAILURE OR MALFUNCTION '4ILL RESULT IN DROPPING OR LOSING CONTROL OF THE HEAVIEST LOADS TO BE HANDLED. SUCli HANDLING SYSTEMS SHOULD BE DESIGNED, FABRICATED, INSTALLED, INSPECTED, TESTED, AND OPERATED IN ACCORDANCE WITH THE FOLLOWING: 1. A. SEPARATE PERFORMANCE SPEC'l-IN COMPLIANCE. CONSTRUCTION LOADS ON FICATIONS SHOULD BE PREPARED THE CASK HANDLING CRANE AND NEW FUEL FOR A PERMANENT CRANE WHICH HANDLING CRANE WILL NOT EXCEED RATED IS TO BE USED FOR CONSTRUC-LOAD. A SPECIAL PERFORMANCE SPECIFICA-TION PRIOR TO USE FOR PLANI TION DEFINES THE POLAR CRANE CONSTRUC-OPERATION. TION REQUIREMENTS. AFTER CONSTRUCTION PHASE, THE CRANES WILL BE RE-CERTIFIED. B. THE OPERATING ENVIRONMENT IN COMPLIANCE. SHALL BE DEFINED (PRESSURE, TEMPERATURE., CORROSION ATMOSPHERE, ETC.) EXHIBIT 2-58 m

O O O SRP ACCEPTANCE CRITERIA BTP ASB 9-1, OVERHEAD HANDLING SYSTEMS FOR NUCLEAR POWER PLANTS (CONT'D) REQUIREMENT DESIGN FEATURE C. THE CRANE SHALL BE CLASSIFIED IN COMPLIANCE. AS SEISMIC CATEGORY I. D. ALL WELDS SHOULD BE INSPECTED IN COMPLIANCE; BY NON-DESTRUCTIVE EXAMINATION. E. A FATIGUE ANALYSIS SHOULD BE IN COMPLIANCE. THE CRANES HAVE BEEN DESIGNED IN ACCORDANCE WITH CMAA MADE. SPECIFICATION NO. 70. F. PREHEAT AND POSTHEAT TREAT-IN COMPLIANCE. MENT TEMPERATURES FOR ALL WELDS SHOULD BE SPECIFIED. 2. A. MALFUNCTION OF AUTOMATIC AND IN COMPLIANCE. MANUAL CONTROLS WILL NOT PRE-VENT THE HANDLING SYSTEM FROM BEING MAINTAINED AT A SAFE, NEUTRAL POSITION. EXHIBIT 2-59

O o o 1 SRP ACCEPTAtlCE CRITERIA l BTP ASB 9-L OVERHEAD HANDLING SYSTEMS FOR fluCLEAR POWER PLANTS (CONT'D) REQUIREMENT DESIGN FEATURE B. AUXILIARY OR ANCILLARY SYSTEMS IN COMPLIANCE. SHOULD BE PROVIDED SUCH THAT IN CASE OF COMPONENT FAILURE ~ THE LGAD WILL BE RETAINED AND HELD IN A SAFE POSITION. C. IlEANS SHOULD BE PROVIDED TO IN COMPLIANCE. THE CRANES CAN BE MOVED FACILITATE REPAIR OF FAILED AND THE LOAD MANUALLY LOWERED ONTO A f CRANE COMPONENTS WITH THE LOAD LAYDOWN AREA. SUPPORTED AND RETAINED IN THE I SAFE POSITION OR MOVING THE CRANE WITH THE LOAD TO A LAYDOWN AREA. 3. A. DUAL LOAD ATTACHING POINTS PARTIAL COMPLIANCE. THE CRANE HOOKS ARE SHOULD BE DESIGNED FOR STATIC DESIGNED FOR 2W. THE NEW FUEL HANDLING AND I LOAD OF 3W. POLAR CRANES HAVE SINGLE HOOKS. THE CASK HANDLING CRANE HAS A SISTER HOOK. i LIFTING DEVICES ARE WITHIN CESSAR SCOPE. B. LIFTING DEVICES SHALL BE REDUNDANT. EXHIBIT 2-60 l

O O O SRP ACCEPTANCE CRITERIA BTP ASB 9-1, OVERHEAD HANDLING SYSTEMS FOR flVCLEAR POWER PLAllTS (CONT'D) REQUIREl1ENT DESIGN FEATURE C. IHE VERTICAL HOISTING MECHANISM PARTIAL COMPLIANCE. THE REDUNDANCY SHOULD BE DESIGNED WITH REDUN-INVOL'/ES ONLY LOWERING, NOT LIFTING, DANT MEANS FOR HOISTING. MAX-THE LOAD. THE NEW FUEL PANDLING CRANE J IMUM HOISTING SPEED TO BE 5 FT/ HAS CAPABILITY OF MAXIMUM HOIST SPEED MIN. OF 10 FT/ MIN. D. IHE HEAD AND LOAD BLOCKS SHOULD PARTIAL COMPLIANCE. CRANE DESIGN IS IN HAVE A DUAL REEVING SYSTEM. ACCORDANCE WITH CMAA SPEC. #70 FOR A DUAL IHE LOAD BLOCK SHOULD BE ABLE REEVING SYSTEM. THE HEAD AND LOAD BLOCKS TO SUPPORT 3W. ARE DESIGNED TO SUPPORT 2W. E. [HE DESIGN OF THE R0PE REEVING IN COMPLIANCE. SYSTEM SHOULD BE DUAL. l F. IHE MAXIMUM FLEET ANGLE FROM IN COMPLIANCE. DRUM TO LEAD SHEAVE IN liiE LOAD BLOCK SHOULD NOT EXCEED i THREE AND ONE-HALF DEGREES. G. THE VERTICAL HOISTING SYSTEM IN COMPLIANCE. SHOULD BE DESIGNED TO SUSTAIN } A LOAD OF 2W. l EXHIBIT 2-61

O O O SRP ACCEPTAtlCE CRITERIA BTP ASB 9-1, OVERHEAD HAf1DLING SYSTEMS FOR NUCLEAR POWER PLANTS (CONT'D) REQUIREMEllT DESIGN FEATURE H. MEANS SHOULD BE PROVIDED TO IN COMPLIANCE. SENSE ITEMS LIKE ELECTRIC CURRENT, TEMPERATURE, OVER-i SPEED, OVERLOADING, OVERTRAVEL. I. IHE CONTROLS SYSTEM SHOULD BE IN COMPLIANCE. DESIGNED AS A COMBINATION OF ELECTRICAL AND MECHANICAL SYSTEMS. J. IHE MECHANICAL AND STRUCTURAL IN COMPLIANCE. LIMIT SWITCHES AND LOAD COMPONENTS SHOULD EITHER HAVE CELLS ARE PROVIDED. STRENSTH TO RESIST FAILURE SHOULD "TWO-BLOCKING" OR " LOAD HANGUP" OCCUR DURING HOISTING, l OR CONTROLS SHOULD PROVIDE POSITIVE MEANS TO STOP THE HOISTING DRUMS FROM EXPERIENCING .THESE OCCURRENCES. l EXHIBIT 2-62

o o o I SRP ACCEPTANCE CRITERIA 2 L l BTP ASB 9-1, OVERHEAD HANDLING SYSTEMS FOR NUCLEAR POWER PLANTS (CONT'D) REQUIREMENT DESIGN FEATURE I K. THE LOAD HOISTING DRUM ON THE IN COMPLIANCE. TROLLEY SHOULD BE PROVIDED WITH STRUCTURAL AND MECHANICAL SAFETY DEVICES TO PREVENT THE DRUM FROM DROPPING, DISENGAG-ING OR ROTATING. t L. THE HORSEPOWER RATING OF THE IN COMPLIANCE. l ELECTRICAL MOTOR DRIVE SHOULD NOT PR0'/IDE MORE THAN 110% OF CALCULATED llP TO LIFT DESIGN 1. LOAD AT MAXIMUM SPEED. i M. THE MINIMUM HOIST BRAKING IN COMPLIANCE. SYSTEM SHOULD INCLUDE ONE POWER CONTROL BRAKING SYSTEM AND TWO MECHANICAL HOLDING BRAKES. 1 { EXHIBIT 2-63 4

O O O SRP ACCEPTANCE CRITERIA ~ BTP ASB 9-1, 0VERHEAD HAND! TNG SYSTEMS FOR NUCLEAR POWER PLANTS (CONT'D) REQUIREMENT DESIGN FEATURE N. THE DYNAMIC AND STATIC ALIGNMENT IN COMPLIANCE. 0F ALL HOISTING COMPONENTS i SHOULD BE MAINTAINED THROUGH-I OUT THE RANGE OF LOADS TO BE LIFTED. l O. INCREMENT DRIVES FOR HOISTING IN COMPLIANCE. AN INCHING MOTOR MAY BE PROVIDED BY STEPLESS DRIVE IS PROVIDED. 4 CONTROL OR INCHING MOTOR DRIVES. 4 P. CONTROL AND HOLBING BRAKES IN COMPLIANCE. SHALL EACH BE RATED AT 100% 0F THE MAXIMUM DRIVE TOROUE. 4 ) Q. THE COMPLETE OPERATING CONTROL IN COMPLIANCE. THE NEW FUEL HANDLING SYSTEM FOR THE OVERHEAD CRANE CRANE HAS COMPLEi' OPERATING CONTROL HANDLING SYSTEM SHOULD BE LOCATED PROVIDED ON A PENDANT. THE CASK IN THE MAIN CAB ON THE BRIDGE. HANDLING AND CONTAINMENT POLAR CRANES L: MITING DEVICES SHOULD BE PRO-HAVE CONTROLS LOCATED IN THE MAIN VIDED TO INDICATE, CONTROL, PRE-CABIN OF THE BRIDGE. RADIO CONTROL OVERTRAVEL, OVERSPEED OF HOIST IS PROVIDED FOR THE CASK HANDLING AND/OR TROLLEY TRAVEL MOVEMENTS, AND POLAR CRANES. i EXHIBIT 2-6fl 3

4 O O O SRP ACCEPTANCE CRITERIA i 4 BTP ASB 9-1, OVERHEAD HANDLING SYSTEMS FOR NUCLEAR POWER PLANTS (CONT'D) i I i 1 l REQUIREMENT DESIGN FEATURE i i i R. SAFETY DEVICES, SUCH AS LIMIT IN COMPLIANCE. } SWITCHES, SHOULD BE PROVIDED. 1 l S. IHE OPERATING REQUIREMENTS FOR IN COMPLIANCE. ALL TRAVEL MOVEMENTS SHOULD BE 4' CLEARLY DEFINED IN THE OPERATING MANUAL. i T. WHEN THE PERMANENT CRANE IS TO IN COMPLIANCE. BELUSED FOR CONSTRUCTION, THE 2 CONSTRUCTION REQUIREMENTS ARE TO BE DEFINED SEPARATELY. U. INSTALLATION INSTRUCTIONS SHOULD IN COMPLIANCE. i BE PROVIDED BY THE MANUFACTURER. t l i l EXHIBIT 2-65 2

O o o SRP ACCEPTAtlCE CRITERIA j BTP ASB 9-1, OVERHEAD HAtlDLING SYSTEfiS FOR NUCLEAR POWER PLAllTS (CONT'D) L REQUIREl1ENT DESIGN FEATURE i II. IlECHANICAL CHECKS, TESTING AND IN COMPLIANCE. PREVENTATIVE MAINTENANCE. t A. CHECKING, TESTING AND MAIN-IN COMPLIANCE. f TENANCE OF CRANE COMPONENTS SHALL BE DONE IN ACCORDANCE l WITH MANUFACTURER'S INSTRUCTION MANUAL. i B. IHE CRANE SYSTEM SHALL BE IN COMPLIANCE. I PREPARED FOR A STATIC TEST OF 125% OF THE DESIGN RATED f LOAD. I C. THE MAXIMUM WORKING LOAD IN COMPLIANCE. SHALL BE PLAINLY MARKED ON EACH SIDE OF THE CRANE. 4 i I~ EXHIBIT 2-66 1

i O O O j 10CFR71, PACKAGING OF RADI0 ACTIVE MATERIAL FOR TRANSPORT AND TRANSPORTATION OF RADI0 ACTIVE MATERIAL UNDER CERTAIN CONDITIONS I REQUIREllENT DESIGN FEATURE j A FREE DROP THROUGH A DISTANCE OF 30 FEET IN COMPLIANCE. THE CASK HANDLING ONTO A FLAT, ESSENTIALLY UNYIELDING CRANE IS PROVIDED WITH LIMIT SWITCHES HORIZONTAL SURFACE, STRIKING THE SURFACE TO ASSURE THE CASK IS NOT RAISED IN A POSITION FOR WHICH MAXIMUM DAMAGE HIGHER THAN 30 FEET FROM THE FLOOR. i IS EXPECTED, SHOULD BE CONSIDERED. i f l l i l i EXilIBIT 2-67 i

O O O fluREG-0612, C0tlTROL OF HEAVY LOADS AT NUCLEAR POWER PLAT 1TS AtlD NRC LETTERS "T0 ALL LICENSEES OF OPERATIrlG LICENSES AND HOLDERS OF C0tlSTRUCTION PERMITS" DATED DECEMBER 22, 1980 Atl0 FEBRUARY 3, 1981. REQUIREMENT ACTI0tl i fluREG-0612 EtlCLOSURE TO LETTERS SEC. 5.1.1 Dec. 2.1, " GENERAL REQUIREMENTS FOR OVERHEAD APS WILL RESPOND ilANDLING SYSTEMS" BY JUNE, 1981 s SEC. 5.1.2 SEC. 2.2, " SPECIFIC REQUIREMENTS FOR OVERHEAD j llANDLING SYSTEMS OPERATING IN THE VICINITY OF FUEL STORAGE POOLS" i SEc. 5.1.3 Sec. 2.3, " SPECIFIC REQUIREMENTS OF HANDLING APS WILL RESPOND i SYSTEMS OPERATING IN THE CONTAINMENT" BY SEPTEMBER, 1981 i l SEC. 5.1.5 SEC. 2.4, " SPECIFIC REQUIREMENTS FOR OVERHEAD IIANDLING SYSTEMS OPERATING IN PLANT AREAS CON-ll TAINING EQUIPMENT REQUIRED FOR REACTOR SHUTDOWN, CORE DECAY IIEAT REMOVAL, OR SPENT FUEL POOL COOLING" l I EXIllBIT 2-68

i O O O i ? j III. ESSENTIAL COOLING WATER SYSTEM (COMP 0NEllT C00LIllG WATER SYSTEM) i i i } l l l I. i I i i EXHIBIT 3-1 j I

o O j i l ECWS SURGE l TAhK i ECWS H-X ) 4 N ECW PUMP } i i l { ~ L - - - -... ~] l l ESSEN. lAL m i m I l l CHILLE i l L _ J- - - - - - __ _ ] i i p----- f I SDC H-X [ \\_ _ _ _ ___ _ ( _ j 1 5 i' ] ESSENTIAL COOLING WATER SYSTEM (ONE OF TWO TRAINS) FIGURE 3-1 i

O O O ESSENTIAL COOLING WATER SYSTEM (ECWS) DESIGN CRITERIA 1) THE ECWS SHALL CONSIST OF TWO INDEPENDENT IDENTICAL CLOSED-LOOP TRAINS. EACH TRAIN SHALL BE CAPABLE OF REMOVING 100 P:P. CENT OF THE HEAT LOAD FROM THE SArETY-RELATED j REACTOR AUXILIARIES DURING NORMAL OR FORCED SHUTDOWN OF THE PLANT. 2) llEAT SHALL BE REMOVED FROM THE ECWS BY THE ESSENTIAL SPRAY POND SYSTEM (ESPS THE ECWS HEAT EXCHANGERS. THE ESPS SHALL BE PIPED TO THE TUBE SIDE OF THESE HEAT EXCHANGERS. 1 3) EACH TRAIN OF THE ECWS, IN CONJUNCTION WITH THE SAFETY INJECTION AND SHUTDOWN COOL-SHALL BE CAPABLE OF REMOVING SUFFICIENT HEAT FROM si;2 CONTAINMENT AND ING SYSTEM, SAFETY-RELATED REACTOR AUXILIARIES TO ENSURE SAFE REACTOR SHUTDOWN IN THE EVENT OF A LOSS OF COOLANT ACCIDENT (LOCA) COINCIDENT WITH A LOSS OF OFFSITE POWER (L 4) THE ECWS SHALL BE DESIGNED TO PERMIT THE DETECTION OF LEAKAGE INTO OR OUT OF THE SYSTEM. 5) THE MAXIMUM WATER TEMPERATURE AT THE SHELL SIDE OUTLET OF THE ECWS HEAT EXCHAN I SHALL NOT EXCEED 105F 27-1/2 HOURS AFTER A NORMAL SHUTDOWN, AND 120F DURING A LOCA. 6) DESIGN OF THE ECWS SHALL INCLU)E PROVISIONS FOR ACCOMMODATING THE CLOSED-LOOP WAT EXPANSION AND CONTRACTION DUE TO THERMAL CHANGES IN THE SYSTEM. EXHIBIT 3-1

O O O i 7) flAKEUP WATER TO THE ErWS SHALL BE PROVIDED BY THE DEMINERALIZED WATER SYSTEM AND THE CONDENSATE STORAGE AND TRANSFER SYSTEM. 8) THE ECWS WATER CHEMISTRY SHALL BE CONTROLLED FOR THE PREVENTION OF LONG-TERM CORROSION. l 9) THE ECWS SHALL BE CAPABLE OF PROVIDING COOLING WATER FOR lid FUEL POOL HEAT EXCHANGERS WHEN THEIR NORMAL COOLING SYSTEM IS NOT AVAILABLE. IRAIN A 0F THE ECWS SHALL BE PIPED TO ONE HEAT EXCHANGER, AND TRAIN B SHALL BE PIPED TO THE OTHER HEAT EXCHANGER. VALVES SHALL BE PROVIDED TO ISOLATE THE ECWS FROM THE NORMAL COOLING SYSTEM. 10) THE ECWS SHALL BE CAPABLE OF PROVIDING COOLING WATER TO THE REACTOR COOLANT PUMPS, i CEDM NORMAL AIR CONDITIONING UNITS (ACU), AND NORMAL CHILLERS WHEN THEIR NORMAL COOLING SYSTEM IS NOT AVAILABLE. APPROPRIATE VALVING SHALL BE PROVIDED TO ISOLATE THE ECWS FROM THE NORMAL COOLING SYSTEM DURING ALL MODES OF OPERATION. i 11) THE OPERATING PRESSURE OF THE ECWS SHALL BE LOWER THAN THAT OF THE ESPS AT THE ECWS HEAT EXCHANGER INTERFACE. i 12) THE ECWS CHEMICAL ADDITION TANKS SHALL BE DESIGNED TO SEISMIC CATEGORY III. PIPING FOR ECWS TO THE NUCLEAR COOLING WATER SYSTEM (i1CWS) INTERTIE SHALL BE SEIS I GORY ll. ALL OTHER COMPONENTS, VALVES, AND PIPING SHALL BE SEISMIC CATEGORY I. i ) EXillBIT 3-2 i

O O O i i 13) THE FOLLOWING DESIGN CODES AND STANDARDS SHALL BE MET: i A. PUMPS e AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), BOILER AND PRESSURE ] VESSEL CODE, SECTION lil, CLASS 3 e fiYDRAULIC INSTITUTE (III) STANDARDS 5. fiEAT EXCHANGERS 4 l e ASME BOILER AND PRESSURE VESSEL CODE, SECTION lil, CLASS 3 e TUBULAR EXCHANGER MANUFACTURER'S ASSOCIATION (TEMA), CLASS R l l C. SURGE IANKS i e ASME. BOILER AND PRESSURE VESSEL CODE, SECTION 111, CLASS 3 j l l D. CHEMICAL ADDITION IANKS i e ASME BOILER AND PRESSURE VESSEL CODE, SECTION VIII E. PIPING FOR NCWS INTERTIE i i t e AMERICAN NATIONAL STANDARDS INSTITUTE (ANSI), B31.1 EXilIBIT 3-3

l O O O i F. OTHER PIPING i i l e ASME BOILER AND PRESSURE VESSEL CODE, SECTION lil, CLASS 3 ,i fl. VALVES I e ASME BOILER AND PRESSURE VESSEL CODE, SECTION lil, CLASS 3 II. SYSTEM IESTING AND INSPECTION l e ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI I i i f i r i i i 1 1 5 1 i j EXlilBIT 3-4 7

__ _ _= - _. 4 l O O O j ESSENTIAL COOLING llATER SYSTEM l CESSAR INTERFACE REQUIREMEllTS REFEREllCE: CESSAR SECTI0tl 5.4.7.1 I l REQUIREMEllT DESIGli FEATURE l COOLING flATER SYSTEM REQUIREMENTS k l A. THE COOLING WATER SYSTEM DESIGN SHALL IN COMPLIANCE BE SUCH THAT COOLING WATER, CONSISTENT WITH THE REQUIREMENTS OF B. BELOW, IS 1 AVAILABLE TO SUPPLY THE SHUTDOWN COOLING l HEAT EXCHANGERS WHEN AN IRRADIATED CORE IS PRESENT IN THE REACTOR VESSEL OR THE f SPENT FUEL POOL. i i i L k i EXilIBIT 3-5 i

O O O ESSENTIAL COOLING WATER SYSTEM CESSAR INTERFACE REQUIREMENTS REFEREllCE: CESSAR SECTION 5.11.7.1 i ) REQUIREMEllI DESIGN FEATURE i B. COOLING WATER SHALL BE SUPPLIED AT THE FOLLOWING TEMPERATURES AND BE ABLE TO j j REMOVE THE HEAT LOADS LISTED FOR THE GIVEN CONDITIONS: } SHUTDOWN COOLING HEAT EXCHAN(iERji j DESIGN llEAT LOAD EXPECTED RANGE DESIGN HEAT LOAD l (MILLION btu / OF (MILLION BTU / l COOLING WATER HOUR) (INCLUDES COOLING WATER HOUR) (INCLUDES lj INLET BOTH HEAT INLET BOTH HEAT SITUATION IEMPERATURE EXCHANGERS) TEMPERATURE EXCHANGERS i POST-LOCA 65 - 120F 290 65 - 120F 290 SHUTDOWN COOLING: l 3-1/2 HOURS 65 - 120F 2117 65 - 120F 255 l l AFTER SHUTDOWN 27-1/2 HOURS 65 - 105F 87.6 65 - 105F 87.8 l AFTER SHUTDOWN i EXHIBIT 3-6

O O O ESSEllTIAL COOLING WATER SYSTEM CESSAR IllTERFACE REQUIREMENTS REFEREllCE: CESSAR SECTION 5.4.7.1 REQUIREMEllT DESIGN FEATURE C. FOR ALL CONDITIONS, COOLING WATER SHALL BE SUPPLIED AS FOLLOWS: REQUIRED VALUE VALUE l PARAMEIER PER ll EAT EXCHANGER PER HEAT EXCHANGER l NORMAL ALLOWABLE DELIVERY 100 PSIG 50 PSIG PRESSURE flAXIMUM ALLOWABLE DELIVERY 150 PSIG 88 PSIG PRESSURE REQUIRED ELOWRATE 11,000 GAL / MIN 14,000 GAL / MIN MAXIMUM ALLOWABLE ELOWRATE 13,000 GAL / MIN 14,000 GAL / MIN EXHIBIT 3-7

O O O ESSENTIAL COOLING WATER SYSTEM CESSAR INTERFACE REQUIREMENTS I

REFERENCE:

CESSAR SECTION 5.4.7.1 I REQUIREMENT DESIGN FEATURE i D. CCDLING WATER PIPING SUPPLYING THE SHUTDOWN IN COMPLIANCE l COOLING HEAT EXCHANGERS SHALL BE DESIGNED f AND FABRICATED IN ACCORDANCE WITt ASME B&PVC, SECTION lli, CLASS 3 AND SHALL BE DESIGNED AS SEISMIC CATEGORY I, SAFETY CLASS 3. l 1 j E. THE COOLING WATER SYSTEM WHICH SERVICES THE IN COMPLIANCE j SHUTDOWN COOLING SYSTEM (SCS) SHALL BE i DESIGNED WITH SUFFICIENT REDUNDANCY AND DIVERSITY SUCH THAT ONE SCS HEAT EXCHANGER TRAIN WILL ALWAYS BE SUPPLIED COOLING WATER. l I F. THE COOLING WATER SYSTEM WHICH SERVICES THE IN COMPLIANCE j SCS SHALL BE DESIGNED CONSISTENT WITH THE COOLING WATER CHEMISTRY. ) EXHIBIT 3-8

O O O SYSTEM DESCRIPTION ESSENTIAL COOLING WATER SYSTEM 1) ECWS CONSISTS OF TWO INDEPENDENT FLOW TRAINS THAT SUPPLY COOLING WATER TO SHUTDOWN COOLING HEAT EXCHANGERS AND ESSENTIAL CHILLERS. 2) EACH FLOW TRAIN INCLUDES A HEAT EXCHANGER, SURGE TANK, PUMP, CHEMICAL ADDITION TANK, PIPING, VALVES, CONTROLS, AND INSTRUMENTATION. EITHER TRAIN WILL' SUPPLY SUFFICIENT COOLING WATER TO THE SHUTDOWN COOLING HEAT EXCHANGER TO ALLOW A SAFE PLANT SHUTDOWN. ) 3) ECWS FLOW TRAINS ARE CONNECTED TO NCWS BY TWO TIE LINES. NCWS CAN THUS BE SERVED BY EITHER FLOW TRAIN OF ECWS IN EVENT NCWS IS NOT AVAILABLE. 4) EACH ECWS FLOW TRAIN HAS A SUPPLY AND RETURN LINE, WITH NORMALLY CLOSED VALVES, FOR EACH CORRESPONDING FUEL POOL HEAT EXCHANGER TO PROVIDE COOLING WHEN THE NCWS IS NOT AVAILABLE. 5) MAKEUP WATER IS SUPPLIED TO ECWS SURGE TANKS BY THE DEMINERALIZED WATER SYSTEM AND i THE CONDENSATE TRANSFER AND STORAGE SYSTEM. 4 i 1 EXilIBIT 3-9 4

O O O 4 N2 DEMINERAllZED m WATER E CW', ECWS CHEMICAL SURGE CONDENSATE ADDITION TANK 2 TANK TRANSFER A V ECWS H-X U ECW PUMP ) 4-df FROM FUEL POOL H-X'S NC q 7 1 FROM TR AIN B {~L_____f~] } l l CHILLER l --[ NC i 2 l ESSENTIAL L __ J- - -- '- -- ~- i_ _ ] If TO FUEL POOL H-X3 4 ' / l--- l l > TO NCWS M l 4-FROM NCWS NC NC l/, TO TRAIN B NC _ _ p - -,i [ SDC H-X l s._ 7 _ _._ _ _1_ _3 ESSENTIAL COOLING WATER SYSTEM -TRAIN A FIGURE 3-2 i

O R R O R IOT" O O E C A E S T G S A R TS A S A E R R T SA R IRE" K C N A G P LO C W M "B PA A C O O P N V B E O C X-C H gT T S N C P l F "A l 1/T N R M R A A E N E RS RE X S W ER EG I t E T N OX CLE SPA H 3./_b T N E D H E uPL AP K S S. V D T N MO G IRC C P X N E - AO TA N SC SP F U O L O A C 1#T N P O L G N I R U D M E T S Y 3 lI S _ O N lI N 3 A B R E E R N T N I 4 A U .,IA, 1 ,Y A ( x g R R WIG T T E F S K G G W N N C A I [/ R U q., [ [i_ IL S . / j N T l S S P O X M O H U C S P W S R C W A N C E N L P S C ~ W U 9 C N E ) P ) O 3 L R S L( E R AR G A I t ME NI E. ' (* R 0 L l' R S _r O 0 U A L L NI 0 N H 1 C ( ~ l lIa L "B, 1 J F 1 R ~ O "A ) 4 RT N ONSS( L I MA A TA P R U CLME OM R C AOUL ER A T EO P0 CO RC 0 N O C ~ L J j l I l

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O O O ESSENTIAL C00LIllG WATER SYSTEM OPERATION I 1) THE ECWS OPERATES ONLY DURING COLD SHUTDOWN, LUP, EMERGENCY, OR FAILURE OF THE HCWS. 2) THE ECWS IS INITI ALLY SUPPLIED WATER FROM THE DEMINERA'.IZED WATER SYSTEM. MAKEUP WATER IS ALSO OBTAINED FROM THIS SOURCE. AN ADDITIONAL SCURCE OF MAKEUP WATER IS FROM THE CCNDENSATE STORAGE TANKS. l 3) WATER IS ADDED TO THE SYSTEM AT THE SURGE TANKS, WHICH ARE LOCATED AT AN ELEVATION ABOVE THE HIGHEST COMPONENT IN THE TRAIN AND ESTABLISH THE PRESSURE LEVEL OF THE CIRCUIT. THEY SERVE AS A RESERVOIR FOR EXPANSION AND CONTRACTION OF THE COOLING WATER AND AS A CONVENIENT LOCATION TO INTRODUCE MAKEUP TO COMPENSATE FOR ANY SYSTEM LOSSES. THE MAKEUP LINE IS SIZED FOR A NOMINAL FLOW RATE OF 50 GAL / MIN. THE SURGE TANKS ARE PIPED TO THE SUCTION SIDE OF THE ECWS PUMPS. CHEMICALS FOR CORROSION AND PH CONTROL ARE ADDED TO THE SYSTEM FROM THE CHEMICAL ADDITION TANKS. 4) THE ECWS HAS TWO REDUNDANT AND SEPARATE TRAINS. EACH TRAIN IS C0HNECTED TO ITS CORRESPOND!::c ESPS TRAIN THROUGH THE ECWS HEAT EXCHANGER THAT SERVES AS A PRESSURE BARRIER BETWEEN THE ESPS AND THE ECilS. ALTHOUGH EITHER TRAIN HAS A l 100-PERCENT HEAT-DISSIPATION CAPACITY, AN EMERGENCY REACTOR SHUTDOWN IS NORMALLY ACCOMPLISHED WITH THE INITTAL OPERATION OF BOTH TRAINS OF THE ECWS AND ESPS. SHUTDOWN AND C00LDOWN WITH ONLY ONE TRAIN OVER AN EXTENDF3 PERIOD OF TIME IS POSSIBLE AND PERMISSIBLE. EXHIBIT 3-10

O O O 5) ONE ECUS PUMP IS PROVIDED FOR EACH OF THE TWO ECWS TRAINS. THE PUMPS ARE INSTALLED AT AN ELEVATION BELOW THE ECWS SURGE TANK TO ENSURE A FLOODED SUCTION. PUMP MOTORS l ARE CONNECTED TO SEPARATE CLASS IE 4.16 KV POKER SYSTEM BUSES WHICH HAVE STANDBY DIESEL-GENERATOR POWER AVAILABLE. IN THE EVEHi 0FFSITE POWER IS LOST DURING ECWS OPERATION, THE PUMPS ARE STOPPED AND RESTARTED IN ACCORDANCE WITH THE ENGINEERED SAFETY FEATURE ACTUATION SYSTEM LOAD SEQUENCIN6 6) IN THE EVENT ONLY ONE TRAIN IS IN OPERATION AND A COMPONENT IN THAT TRAIN FAILS CAUSING A LOSS OF THAT TRAIN'S FUNCTION, THE OPERATOR WILL MANUALLY START THE OTHER TRAIN. l 7) IN ADD' TION TO THE MANUAL START MODE FOR THE ECWS, ANY ONE OF THE FOLLOWING SIGNALS WILL AUTOMATICALLY START BOTH ECWS PUMPS: l l e LOP (LOSS OF OFFSITE POWER) e SIAS (SAFETY INJECTION ACTUATION SIGNAL) l e CREFAS (CONTROL ROOM ESSENTIAL FILTRATION ACTUATION SIGNAL) e CRVIAS (CONTROL ROOM VENTILATION ISOLATION ACTUATION SIGNAL) i e AFAS-1 (AUXILIARY FEEDWATER ACTUATION SIGNAL 1) e AFAS-2 (AUXILIARY FEEDWATER ACTUATION SIGNAL 2) I o) WHEN THE COOLING WATER LEVEL FALLS BELOW A PRESET LIMIT, A LEVEL CONTROL DEVICE l LOCATED IN THE ECWS SURGE TANKS WILL ACTIVATE A CONTROL VALVE IN THE DEMINERALIZED WATER SUPPLY LINE TO THE ECWS. A LOW LEVEL SIGNAL, INDICATING A LARGE LEAK OUT OF THE SYSTEM, WILL SOUND AN ALARM IN THE CONTROL ROOM. A HIGH WATER LEVEL IN THE l SURGE TANK WILL ALSO ALARM IN THE CONTROL ROOM INDICATING A LEAK INTO THE SYSTEM. l EXillBIT 3-11

O O O i 9) A RADI ATION MONITORING SYSTEtt THAT WILL ALARM IN THE CONTROL ROOM IS PROVIDED TO DETECT RADI0 ACTIVITY IN THE COOLING WATER. 10) THE WATER IN EACH TRAIN IS SAMPLED FOR QUALITY ON A SCHEDULED BASIS BY TAKING SAMPLES [ i AT THE SAMPLING POINT AND THE PH ADJUSTED, IF REQUIRED, BY THE ADDITION OF POTASSIUM i HYDROXIDE, K0H. l 11) IN THE EVENT THE NCWS FAILS, THE OPERATOR HAS THE OPTION OF STARTING EITHER TRAIN OF THE ECWS AND ESPS WHILE CROSSCONNECTING THE ECWS TO A PORTION OF THE NCWS THAT I NORMALLY SUPPLIES COOLING WATER TO THE REACTOR COOLANT PUMPS, CEDM NORMAL ACU'S, AND NORMAL CHILLERS. THIS IS ACCOMPLISHED BY MANUALLY OPENING OR CLOSING THE DESIRED VALVES. THE REMAINDER OF THE UCWS WILL BE ISOLATED FROM THE ECWS WITH APPROPRIATE VALVING DURING THIS MODE OF OPERATION. i l ) l } l i i i EXHIBIT 3-12 i

O O O i STANDARD REVIEW i PLAN 91.2 i 4 I I 4 i GENERAL BRANCH REGULATORY DESIGN TECHNICAL j GUIDES CRITERIA POSITIONS i l I I i ASB 3-1, PIPE BREAK 1.26, QUALITY CLASS GDC-2, NATURAL PHEN;JMENA 1.29, SEISMIC CLASS GDC-4, ENVIRDNMENTAL/ MISSILE i j GDC-5, SH ARED SYSTEMS GDC-44, CDOLING WATER i GD C-45, INSPECTION i GDC-46. TESTING 1 f STANDARD REVIEW PLAN 9.2.2 FIGURE 3 8 i i

O O O SRP ACCEPTAllCE CRITERIA GENERAL DESIGN CRITERION 2, NATURAL PHENOMENA REQUIREMENT DESIGN FEATURE STRUCTURES, SYSTEMS AND COMPONENTS IN COMPLIANCE. ECWS COMPONENTS ARE HOUSED IN A SEISMIC CATEGORY I, MISSILE-IMPORTANT TO SAFETY SHALL BE DESIGNED TO WITHSTAND THE EFFECTS OF NATURAL PROOF STRUCTURE. ALL COMPONENTS ARE PHENOMENA SUCH AS EARTHOUAKES, TORNADOES, LOCATED BEYOND THE EXTENT OF PROBABLE HURRICANES, FLOODS, AND SEICHES WITHOUT MAXIMUM FLOODING. LOSS OF CAPABILITY TO PERFORM THEIR SAFETY FUNCTIONS. EXilIBIT 3-13

O O O SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 4, ENVIRONMENTAL AND M'SSILE DESIGN REQUIREMENT DESIGN FEATURE I l STRUCTURES, SYSTEMS, AND COMPONENTS IN COMPLIANCE. j IMPORTANT TO SAFETY SHALL BE DESIGNED FOR THE ENVIRONMENTAL CONDITIONS ASSOCIATED t i WITH NORMAL OPERATION, MAINTENANCE, TEST-ING AND POSTULATED ACCIDENTS, INCLUDING l LOSS-OF-COOLANT ACCIDENTS. THEY SHALL BE APPROPRIATELY PROTECTED AGAINST DYNAMIC EFFECTS, INCLUDING THE EFFECTS OF MIS-SILES, PIPE WHIPPING, AND DISCHARGING i FLUIDS, THAT MAY RESULT FROM EQUIPMENT l l FAILURES AND FROM EVENTS AND CONDITIONS OUTSIDE THE NUCLEAR POWER UNIT. i 4 i i EXHIBIT 3-14

s l O O O l 2 i SRP ACCEPTAllCE CRITERIA i I GENERAL DESIGN CRITERION 5, SilARED SYSTEMS REQUIREMENT DESIGN FEATURE i f i STRUCTURES, SYSTEMS, AND COMPONENTS IN COMPLIANCE. f IMPORTANT TO SAFETY SHALL NOT BE SHARED BETWEEN NUCLEAR POWER UNITS UNLESS IT IS i j SHOWN THAT THEIR ABILITY TO PERFORM THEIR SAFETY FUNCTIONS, INCLUDING, IN THE EVENT l l OF AN ACCIDENT IN ONE UNIT, AN ORDERLY l SHUTDOWN AND C00LDOWN OF THE REMAINING t UNITS. i i I l i i l i i i EXillBIT 3-15

O O O i SRP ACCEPTAllCE CRITERIA I I l GE!!ERAL DESIGN CRITERION 44, C00LIllG WATER REQUIREMENT DESIGN FEATURE A SAFETY SYSTEM SHALL BE PROVIDED TO IN COMPLIANCE. EITHER OF THE TWO TRANSFER THE COMBINED HEAT LOAD OF ESF SEPARATE ECWS TRAINS WILL PROVIDE j STRUCTURES, SYSTEMS, AND COMPONENTS UNDER ADEQUATE COOLING WATER FLOW TO THE NORMAL OPERATING AND ACCIDENT CONDITIONb SHUTDOWN COOLING HEAT EXCHANGERS. l l TO AN ULTIMATE HEAT SINK. SUITABLE I i REDUNDANCY IN COMPONENTS AND FEATURES, AND SUITABLE INTERCONNECTIONS, LEAK DETECTION, AND ISOLATION CAPABILITIES SHALL BE PROVIDED TO ASSURE THAT THE SYSTEM SA.FETY FUNCTION CAN BE ACCOM-OR VI HOU A OS OF 0FFS TE POWER. 9 4 4 i f l EXilIBIT 3-16 4

l O O O I SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 45, INSPECTION l REQUIREMENT DESIGN FEATURE i i THE COOLING WATER SYSTEM SHALL BE IN COMPLIANCE. DESIGNED TO PERMIT APPROPRIATE PERIODIC l INSPECTION OF IMPORTANT COMPONENTS, SUCH j AS HEAT EXCHANGERS AND PIPING, TO ASSURE THE INTEGRITY AND CAPABILITY OF THE SYSTEM. l I l 2 l 1 4 i j EXilIBIT 3-17 i 4

O O O SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 116, TESTIllG REQUIRENEllT DESIGN FEATURE THE COOLING WATER SYSTEM SHALL PERMIT IN COMPLIANCE. APPROPRIATE PERIODIC PRESSURE AND FUNC-TIONAL TESTING TO ASSURE (1) STRUCTURAL AND LEAKTIGHT INTEGRITY OF COMPONENTS, (2) OPERABILITY AND PERFORMANCE OF ACTIVE COMPONENTS, AND (3) OPERABILITY OF THE SYSTEM AS A WHOLE AND PERFORMANCE OF THE FULL OPERATIONAL SEQUENCE FOR REACTOR SHUTDOWN AND FOR LOSS-OF-COOLANT ACCIDENTS. EXHIBIT 3-18

i O O O SRP ACCEPTANCE CRITERIA i REGULATORY GUIDE 1.26, QUALITY GROUP CLASSIFICATION i REQUIREi1ENT DESIGN FEATURE COOLING WATER SYSTEMS THAT ARE NOT IN COMPLIANCE. 4 l PART OF THE REACTOR COOLANT PRESSURE BOUNDARY AND ARE DESIGNED FOR EMER-GENCY CORE COOLING, POST-ACCIDENT CONTAINMENT ATMOSPHERE CLEANLP OR RESIDUAL HEAT REMOVAL FROM THE REACTOR SHALL MEET THE REQUIREMENTS l OF ASi1E B8PV CODE, SECTION 111, i CLASS 3. l 1 l i EXI!IBIT 3-E i

l O O O a I SRP ACCEPTANCE CRITERIA ~ j REGULATORY GUIDE 1.29, SEISMIC DESIGN CLASSIFICATION REQUIREMENT DESIGN FEATURE THE COMPONENT COOLING WATER SYSTEM IN COMPLIANCE. THE ECWS IS SEISMIC ~ SHALL BE DESIGNATED SEISMIC CATEGORY I CATEGORY Is EXCEPT FOR THE CHEMICAL AND BE DESIGNED TO WITHSTAND THE EFFECTS ADDITION TANKS WHICH ARE SEISMIC 0F THE SSE AND REMAIN FUNCTIONAL. THE CATEGORY Ill AND ECWS TO NCWS PIPING 4 l QUALITY ASSURANCE REQUIREMENTS OF WHICH IS SEISMIC CATEGORY ll. PIPING l APPENDIX B TO 10CFR50 SHALL APPLY. T0/FROM THE FPCS HEAT EXCHANGERS IS I SEISMIC CATEGORY I. ALL REQUIREMENTS j OF APPENDIX B TO 10CFR50 ARE MET FOR SEISMIC CATEGORY l COMPONENTS. f SEISMIC CATEGORY ll COMPONENTS MEET i SIMILAR QUALITY ASSURANCE REQUIREMENTS. 1 1 i } I i i I i EXillBIl 3-20 i i i

l O O O BTP ASB 3-1, PROTECTION AGAINST POSTULATED PIPING FAILURES IN FLUID SYSTEMS OUTSIDE CONTAIRMENT. REQUIREMENT DESIGN FEATURE i THE SYSTEMS AND COMPONENTS IMPORTANT IN COMPLIANCE. ECWS IS COMPRISED OF TO SAFETY SHALL BE APPROPRIATELY TWO SEPARATE TRAINS SEPARATED BY PROTECTED AGAINST DYNAMIC EFFECT, CONCRETE WALLS AND/0R, DISTANCE. INCLUDING THE EFFECT OF MISSILES, THE COMPONENTS ARE SHI.ELDED FROM PIPE WHIPPING AND DISCHARGING FLUIDS, POTENTIAL PIPE FAILURES BY CONCRETE THAT MAY RESULT FROM EQUIPMENT FAIL-WALLS OR DISTANCE. IHE SYSTEM COM-URES AND FROM EVENTS AND CONDITIONS PONENTS ARE LOCATED AT AUXILIARY OUTSIDE THE CONTAINMENT. BUILDING ELEVATIONS OF 70 FEET AND HIGHER AND ARE PROTECTED FROM EFFECT OF PIPE BREAK-GENERATED FLOODING. EXIllBIT 3-21 ~

O O O I 1 1 1 1 IV. ESSENTIAL SPRAY PollD SYSTEM j (SERVICE WATER SYSTEM AND ULTIMATE 11 EAT SIllK) i i i i i EX111 BIT 4-i

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(}) l ( (3 / \\ ) DESIGil CRITERIA ESSEllTIAL SPRAY P0ilD SYSTEM 4 1) THE ESSENTIAL SPRAY POND SYSTEM (ESPS) SHALL CONSIST OF TWO REDUNDANT FULL CAPACITY 4 FLOW TRAINS. EACH TRAIN SHALL INCLUDE A SPRAY POND AND ALL EQUIPMENT NECESSARY FOR SAFE SHUTDOWN OF THE PLANT DURING NORMAL OPERATIONS, AND FOLLOWING A LOSS-OF-COOLANT ACCIDENT (LOCA) OR /0RCED SHUTDOWN. 2) EACH TRAIN OF THE ESPS, IN CONJUNCTION WITH THE ESSENTIAL COOLING WATER SYSTEM (ECWS), SHALL BE CAPABLE OF REMOVING SUFFICIENT HEAT FROM THE CONTAINMENT AND REACTOR EMERGENCY CORE COOLING AUXILIARIES TO ENSURE A SAFE REACTOR SHUTDOWN COINCIDENT WITH A LOSS OF OFFSITE POWER (LOP). 3) EACH TRAIN OF THE ESPS, IN CONJUNCTION WITH THE ECWS, SHALL BE CAPABLE OF REMOVING SUFFICIENT HEAT FOLLOWING A POSTULATED LOCA TO MITIGATE THE CONSEQUENCES OF THE LOCA COINCIDENT WITH A LOP. 4) THE ESPS SHALL BE DESIGNED TO PREVENT OR MITIGATE THE CONSEQUENCES OF AN ACCIDENT THAT COULD RESULT IN POTENTIAL OFFSITE EXPOSURES COMPARABLE TO THE GUIDELINE l EXPOSURE OF 10CFR100. 5) THE ESPS SHALL BE DESIGNED TO ENSURE MINIMUM WATER INVENTORY. 6) THE ESPS SHALL BE DESIGNED TO MINIMIZE THE EFFECTS OF LONG-TERM CORROSION AND ORGANIC FOULING. 7) THE ESPS, IN CONJUNCTION WITH THE ECWS, SHALL BE CAPABLE OF COOLING THE REACTOR COOLANT FROM 350 TO 125F WITHIN 27-1/2 HOURS DURING NORMAL SHUTDOWN. EXHIBIT 4-1

3) ALL COMPONENTS OF THE ESPS SHALL BE CAPABLE OF BEING FULLY TESTED DURING NORMAL PLANT OPERATION. IN ADDITION, ALL PARTS AND COMPONENTS SHALL BE DESIGNED TO CON-FORM TO THE REQUIREMENTS OF ASME CODE, SECTION XI, RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS. 9) [1AKEUP WATER TU THE ESPS SHALL BE PROVIDED BY THE COOLING TOWER MAKEUP AND BLOWDOWN SYSTEM AND THE DOMESTIC WATER SYSTEM. 10) THE ESPS SHALL BE CAPABLE OF OPERATING FOR 30 DAYS FOLLOWING A LOCA WITHOUT REQUIRING ANY MAKEUP WATER OR BLOWDOWN. BOTH SPRAY PONDS COMBINED SHALL CONTAIN A WATER VOLUME SUFFICIENT FOR 30 DAYS OF OPERATION. PROVISIONS SHALL BE MADE TO TRANSFER WATER FROM ONE POND TO THE OTHER AT A SUFFICIENT RATE TO MEET THE SYSTEM'S 30-DAY OPERABILITY REQUIREMENT IN THE EVENT THAT ONE SPRAY SYSTEM TRAIN FAILS. l 11) THE ESPS SHALL BE CAPABLE OF MAINTAINING THE ECWS TEMPERATURE INTO THE SHUTDOWN COOLING HEAT EXCHANGERS AT OR BELOW 125F FOLLOWING 1) A FORCED SHUTDOWN OR j

2) THE DESIGN BASIS LOCA UNDER THE MOST ADVERSE HISTORICAL METEOROLOGICAL CONDITIONS CONSISTENT WITH THE REQUIREMENTS OF REGULATORY GUIDE 1.27.

t l 12) THE ESPS, IN CONJUNCTION WITH THE ECHS, SHALL PROVIDE COOLING CAPABILITY FOR THE SPENT FUEL POOL, REACTOR COOLANT PUMPS, CONTROL ELEMENT DRIVE MECHANISM (CEDM) AIR 4 COOLING UNITS (ACUS), AND THE NORMAL CHILLERS WHEN THE NUCLEAR COOLING WATER SYSTEM l IS NOT AVAILABLE. 13) ALL NON-SEISMIC CATEGORY I EQUIPMENT AND PIPING INTERFACING THE SPRAY PONDS SHALL BE DESIGNED TO PRECLUDE INADVERTENT DRAINAGE OF THE PONDS. EXIjlBIT4-2 s

O O O I 14) ALL 0 CLASS ELECTRICAL AND CONTROL CABLING, MOTOR CONTROL CENTERS, LOAD CENTERS, AND SWITCHGEAR ASSOCIATED WITH THE ESPS SHALL BE LOCATED IN A SEISMIC CATEGORY I STRUCTURE OR PROVIDED WITH ADEQUATE MISSILE PROTECTION. 15) THE ESPS, IN CONJUNCTION WITH THE ECWS, SHALL BE DESIGNED TO PROVIDE A MAXIMUM COOLING WATER TEhPERATURE OF 105F TO THE SHUTDOWN COOLING HEAT EXCHANGER 27-1/2 HOURS AFTER A NORMAL SHUTDOWN. I 16) THE COMPONENTS, VALVES, AND PIPING ASSOCIATED WITH POND WATER CLEANUP AND CHEMISTRY CONTROL SHALL BE DESIGNED TO SEISMIC CATEGORY lll. THE REMAINDER OF THE SYSTEM SHALL BE DESIGNED TO SEISMIC CATEGORY I. 17) THE FOLLOWING DESIGN CODES AND STANDARDS SHALL BE MET: A. SPRAY HEADERS e AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), BOILER AND PRESSURE VESSEL CODE, SECTION lil, CLASS 3. I. B. PUMPS, PIPING, AND VALVES FOR POND WATER CLEANUP AND CHEMISTRY CONTROL e ASME, BOILER AND PRESSURE VESSEL CODE, SECTION Vill, DIVISION 1 e AMERICAN NATIONAL STANDARDS INSTITUTE (ANSI), B31.1 i 4 d EXHIBIT 4-3

O O O C. FILTER UNITS t i e AMERICAN PETROLEUM INSTITUTE (API), STANDARD 650 i D. SPRAY N0ZZLES AND ALL OTHER PUMPS, PIPING, AND VALVES e ASME BOILER AND PRESSURE VESSEL CODE, SECTION lil, CLASS 3 l E. IlYP0 CHLORITE AND SULFURIC ACID TANKS I e llYP0 CHLORITE TANKS: NATIONAL BUREAU OF STANDARDS, VOLUNTARY PRODUCT I STANDARD PS 15-69. I e SULFURIC ACID TANKS: ASME BOILER AND PRESSURE VESSEL CODE, i SECTION Vill. l l F. 0-CLASS COMPONENTS AND PIPING TESTING AND INSPECTION e ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI { 1 r i EXHIBIT 4-4 l

O O O SYSTEM DESCRIPTIOl1 ESSEllTIAL SPRAY P0llD SYSTEM l 1) ESPS i e DOES NOT OPERATE DURING NORMAL POWER GEllERATION e REMOVES HEAT FROM ECWS AND DIESEL GENERATOR (DG) COOLING WATER HEAT EXCHANGERS I e DISSIPATES HEAT TO ATMOSPHERE VIA ESP e CAPABLE OF SUPPORTING 100 PERCENT OF COOLING FUNCTIONS REQUIRED FOR SAFE SHUT-DOWN FOLL0wlilG LOCA l i e CONSISTS OF TWO REDUNDANT SPRAY PONDS AND TWO SEPARATE, REDUNDANT FLOW TRAINS, j ONE FLOW TRAIN TAKING SUCTION FROM AND RETURNING WATER TO EACH SPRAY POND. EACH SPRAf POND HAS A FILTRATION TRAIN AND CHEMICAL ADDITION EQUIPMENT. 2) ESSENTIAL SPRAY PONDS (ESP) l e FUNCTION AS SEPARATE, INDEPENDENT, REDUNDANT UNITS i e COMBINED WATER INVENTORY OF BOTH PONDS REQUIRED FOR 30-DAY EMERGENCY SHUTDOWN WITHOUT MAKEUP e TWO BUTTERFLY VALVES IN COMMON WALL BETWEEN PONDS ALLOW TRANSFER OF WATER FROM ONE POND TO ANOTHER. THE VALVES ARE NORMALLY OPENJ THEY CAN BE CLOSED WHEN MAINTENANCE OF ONE POND IS REQUIRED AND DRAINAGE OF BOTH PONDS IS UNDESIRABLE. 1 EXHIBIT L1-5

O O O l 3) FILTRATION IRAIN I l e CONSISTS OF ONE ESPS FILTER PUMP, TWO FILTER UNITS PIPED IN PARALLEL, ONE ) FILTER BACKWASH SUMP PUMP, PIPING, CONTROLS, AND INSTRUMENTATION. 4 i 4) CHEMICAL ADDITION EQUIPMENT r a \\ i e CONSISTS OF ONE SULFURIC ACID METERING PUMP, ONE HYPOCHLORITE METERING PUMP, PIPING, VALVES, CONTROLS AND INSTRUMENTATION 2 i e METERING PUMPS FOR THE SPRAY PONDS TAKE SUCTION FROM COMMON HYPOCHLORITE AND SULFURIC ACID TANKS I l 5) MAKEUP WATER SOURCES e DOMESTIC WATER SYSTEM (NORMAL SOURCE) i l e STATION RESERVOIR (BACKUP SOURCE) 1 i i I i 'I I EXHIBIT 4-6 i

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dt O O O OPERATION ESSENTIAL SPRAY P0llD SYSTEM 1) Tut ESPS OPERATES ON!!Y DURING COLD SHUTDOWN, AN EMERGENCY, OR MHEN THE DIESEL GENERATOR IS RUNNING. 2) THE ESPS OPERATES TO SUPPLY COOLING WATER TO THE ECWS AND DG HEAT EXCHANGERS. l 3) COOLING WATER FOR THE ESPS IS SUPPLIED FROM THE ESP. COOLING WATER FROM j COMPONENTS SERVICED BY THE ESPS IS RETURNED TO THE ESP. i l 4) THE ESPS WILL OPERATE FOR 30 DAYS FOLLOWING A POSTULATED LOCA WITHOUT REQUIRING MAKEUP WATER. 5) ALTHOUGH AN EMERGENCY REACTOR SHUTDOWN IS USUALLY ACCOMPLISHED BY INITIAL OPERATION 0F BOTH ESPS TRAINS, CCOLDOWN AND SHUTDOWN OVER AN EXTENDED PERIOD OF' TIME IS i POSSIBLE AND PERMISSIBLE WITH THE USE OF A SINGLE TRAIN. 6) DURING OPERATION OF THE ESPS, FLOW CAN BE DIVERTED PERIODICALLY FROM THE SPRAY N0ZZLE HEADERS DIRECTLY INTO THE POND. THIS PROCEDURE MINIMIZES THE WATER CON-l SUMPTION DUE TO EVAPORATION AND DRIFT WHEN THE POND WATER TEMPERATURE IS l SUFFICIENTLY LOW TO ALLOW THIS DIVERSION. IEMPERATURE INSTRUMENTATION AT THE i PUMP INTAKE STRUCTURE IN EACH POND, WITH TEMPERATURE SET POINT ALARMS IN THE CONTROL ROOM, INFORM THE OPERATOR OF THE NEED TO CLOSE/0 PEN THE BYPASS. i l EXHIBIT 4-7

O O O 7) THE ESPS' IS ACTUATED BY ANY ONE OR ALL OF THE FOLLOWING: 1 e LOP (LOSS OF OFFSITE POWER) i e DIESEL GENERATOR RUNNING SIGNAL e SIAS (SAFETY INJECTION ACTUATION SIGNAL) l e CRVIAS (CONTROL ROOM VENTILATION AND ISOLATION ACTUATION SIGNAL) e CREFAS (CONTROL ROOM ESSENTIAL FILTRATION ACTUATION SIGNAL) e MANUAL START FROM THE SWITCHGEAR OR THE CONTROL ROOM 8) BOTH TRAINS OF THE ESPS AND THE ECWS ARE AUTOMATICALLY AND SIMULTANEOUSLY STARTED BY EITHER THE SIAS, CRVIAS, OR CREFAS. A MANUAL OVERRIDE IS PROVIDED TO PERMIT MANUAL START AND STOP ACTUATION FROM THE SWITCHGEAR OR THE CONTROL ROOM. MANUAL 3 l START AND STOP CONTROLS ARE PROVIDED FOR EACH OF THE TWO ESPS TRAINS. THIS FEA-TURE PERMITS THE REMOVAL OF A TRAIN FROM OPERATION AFTER THE AUTOMATIC OPERATION ACTUATION, IF THE TRAIN IS NOT REQUIRED. 9) ALL MANUALLY OPERATED CONTROL VALVES ON THE INLET AND Ot!TLE^ LINES OF THE ECWS HEAT EXCHANGERS AND THE INDIVIDUAL DIESEL GENERATOR HEAT EXCHANGERS ARE LOCKED OPEN. THE MOTOR-0PERATED SPRAY HEADER VALVES ARE NORMALLY OPEN, WHILE THE MOTOR-0PERATED j RETURN FLOW BYPASS VALVE IS NORMALLY CLOSED. EXHIBIT 4-8 i

(- i O O O i i 10) WHILE IN OPERATION, A LOP RESULTS IN THE SHUTDOWN AND RESTARTING OF THE ESPS IN ACCORDANCE WITH THE DG LOAD SEQUENCING. i l 11) FLOW DIFFERENTIAL IS MONITORED BETWEEN THE ESPS PUMP DISCHARGE AND THE RETURN LINE TO THE ESP TO DETECT A PIPE BREAK. EACH SYSTEM BEING SERVICED BY THE ESPS IS MONI-j TORED TO DETECT SIGNIFICANT INLEAKA3E FROM THE ESPS. LEVEL INSTRUMENTATION IN EACH POND, WITH Al. ARMS IN THE CONTROL ROOM, INFORM THE OPERATOR OF.HE NEED FOR ADDING f MAKEUP WATER TO THE PONDS. i 12) EACH TRAIN WILL BE PERIODICALLY STARTED AND STOPPED TO TEST SYSTEM OPERABILITY AND 1 COMPONENT PERFORMANCE. J i i i 1 l 4 i EXilIBIT 4-9

O O O l i STANDAnd REVIEW i PLANS 9.2.1 REV.1; 9.2.5 REV.1 l l BRANCH GENERAL REGULATORY TECHNICAL DESIGN GUIDES l CRITERIA POSITIONS l l ASB 3-1, PIPE BREAKS 1.26, QU ALITY CLASS GDC-2, N ATUR AL PHENOMEN A ASB 9-2, DECAY ENERGY 1.27, UHS DESIGN GDC-4, ENVIRONMENTAL / MISSILE 1.29, SEISMIC CLASS GDC-5, SHARED SYSTEMS ) GDC-44, COO LING WATER 1.72, PLASTIC PIPE GDC-45, INSPECT 10rj 1.102, FLOOD PR01ECT10N 1.117. TORNADO CLASS G D C-46, TESTING i STANDARD REVIEW PLAN 9.2.1 REV.1 AND 9.2.5 REV.1 FIGURE 4-7 l i

1 O O O SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 2, NATURAL PHENOMENA REQUIREllENT DESIGN FEATURE STRUCTURES, SYSTEMS AND COMPONENTS IN COMPLIANCE. IMPORTANT TO SAFETY SHALL BE DESIGNED TO WITHSTAND THE EFFECTS OF NATURAL PHENOMENA SUCH AS EARTHQUAKES, TORNADOES, HURRICANES, FLOODS, TSUNAMI, AND SEICHES WITHOUT LOSS OF CAPABILITY TO PERFORM j l THEIR SAFETY FUNCTIONS i G EXHIBIT 4-10

O O O j SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 4, ENVIRONMENTAL AND MISSILE DESIGN REQUIREMENT DESIGN FEATURE 4 i STRUCTURES, SYSTEMS, AND COMPONENTS IN COMPLIANCE. IMPORTANT TO SAFETY SHALL BE DESIGNED FOR THE ENVIRONMENTAL CONDITIONS ASSOCIATED WITH NORMAL OPERATION, MAINTENANCE, TEST-ING AND POSTULATED ACCIDE:s fS, INCLUDING LOSS-OF-COOLANT ACCIDENTS. THEY SHALL BE hPPROPRIATELY PROTECTED AGAINST DYNAMIC ] EFFECTS, INCLUDING THE EFFECTS OF MIS-SILES, PIPE WHIPPING, AND DISCHARGING f FLUIDS, THAT MAY RESULT FROM EQUIPMENT FAILURES AND FROM EVENTS AND CONDITIONS OUTSIDE THE NUCLEAR POWER UNIT. i i 1 4 EXHIBIT 4-11

O O O i SRP ACCEPTANCE CRITERIA i i GENERAL. DESIGN CRITERION 5, SilARED SYSTEMS i REQUIREMENT DESIGN FEATURE STRUCTURES, SYSTEMS, AND COMPONENTS IN COMPLIANCE. l IMPORTANT TO SAFETY SHALL NOT BE SHARED l BETWEEN NUCLEAR POWER UNITS UNLESS IT IS l SHOWN THAT THEIR ABILITY TO PERFORM THEIR l SAFETY FUNCTIONS, INCLUDING, IN THE EVENT I 0F AN ACCIDENT IN ONE UNIT, AN ORDERLY SHUTDOWN AND C00LDOWN OF THE REMAINING UNITS. l 1 i l 1 3 i i EXilIBIT 4-12 i 4

O O SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 44, COOLING WATER REQUIREMENT DESIGN FEATURE A SAFETY SYSTEM SHALL BE PROVIDED TO IN COMPLIANCE. IWO REDUNDANT TRAINS TRANSFER THE COMBINED HEAT LOAD OF ESF ARE PROVIDED. EACH TRAIN IS CAPABLE STRUCTURES, SYSTEMS, AND COMPONENTS UNDER OF REMOVING HEAT FROM THE REACTOR NORMAL OPERATING AND ACCIDENT CONDITIONS COOLANT AND BRINGING THE REACTOR TO TO AN ULTIMATE HEAT SINK. SUITABLE COLD SHUTDOWN CONDITIONS, AS WELL AS REDUNDANCY IN COMPONENTS AND FEATURES, PROVIDING COOLING FOR THE EMERGENCY AND SUITABLE INTERCONNECTIONS, LEAK DGS. DETECTION, AND ISOLATION CAPABILITIES SHALL BE PROVIDED TO ASSURE THAT THE SYSTEM SAFETY FUNCTION CAN BE ACCOMPLISHED, ASSUMING A SINGLE FAILURE WITH OR WITHOUT A LOSS OF 0FFSITE POWER. EXHIBIT 4-13

O O O l SRP ACCEPTANCE CRITERIA i GENERAL DESIGN CRITERION 45, INSPECTION i l REQUIREMENT DESIGN FEATURE l THE COOLING WATER SYSTEM SHALL BE IN COMPLIANCE. ALL ASME PIPING AND 4 DESIGNED TO PERMIT APPROPRIATE PERIODIC COMPONENTS ARE CAPABLE OF INSERVICE ) INSPECTION OF IMPORTANT COMPONENTS, SUCH INSPECTION EXCEPT FOR THE PORTIONS OF i AS HEAT EXCHANGERS AND PIPING, TO ASSURE SUPPLY / RETURN LINES WHICH ARE BURIED. THE INTEGRITY AND CAPABILITY OF THE ANSI COMPONENTS AND NON-EMBEDDED ANSI SYSTEM. PIPING CAN BE PERIODICALLY INSPECTED. 1 l i 4 i i i i i EXilIBIT 4-14 j l

O O o SRP ACCEPTANCE CRITERIA GENERAL DESIGN CRITERION 46, TESTING REQUIREflENT DESIGN FEATURE THE COOLING WATER SYSTEM SHALL PERMIT IN COMPLIANCE. APPROPRIATE PERIODIC PRESSURE AND FUNC-TIONAL TESTING TO ASSURE (1) STRUCTURAL AND LEAKTIGHT INTEGRITY OF COMPONENTS, (2) OPERABILITY AND PERFORMANCE OF ACT14E i COMPONENTS, AND (3) OPERABILITY OF THE SYSTEM AS A WHOLE AND PERFORMANCE OF THE FULL OPERATIONAL SEQUENCE FOR REACTOR SHUTDOWN AND FOR LOSS-OF-COOLANT ACCIDENTS. 1 EXHIBIT 4-15

O O O SRP ACCEPTANCE CRITERIA i REGULATORY GUIDE 1.26, QUALITY GROUP CLASSIFICATION REQUIREl1ENT DESIGN FEATURE i j COOLING WATER SYSTEMS THAT ARE NOT IN' COMPLIANCE. PART OF THE REACTOR COOLANT PRESSURE f BOUNDARY AND ARE DESIGNED FOR EMERGENCY i CORE COOLING, POST-ACCIDENT CONTAINMENT ATMOSPHERE CLEANUP OR RESIDUAL HEAT Il REMOVAL FROM THE REACTOR SHALL MEET THE REQUIREMENTS OF ASME B&PV CODE, SECTION lli, CLASS 3. i i i } i i j EXHII)IT I4-16

O O O i SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 1.27, ULTIMATE HEAT SINK REQUIRE"ENT DESIGN FEATURE i 1) A SUFFICIENT CONSERVATISM SHOULD BE IN COMPLIANCE. COMBINED WATER l PROVIDED TO ENSURE THAT A 30-DAY SUPPLY INVENTORY OF TWO ESPS SUFFICIENT OF WATER IS AVAILABLE AND THAT THE TO PROVIDE NECESSARY COOLING i DESIGN BASIS TEMPERATURE OF SAFETY-FOLLOWING A DESIGN BASIS LOCA FOR RELATED EQUIPMENT ARE NOT EXCEEDED. 30 DAYS WITHOUT WATER MAKEUP UNDER i WORST HISTORICAL METEOROLOGICAL CONDITION. THE METEOROLOGICAL i DATA FOR PH0ENIX, ARIZONA, FROM 1948 TO 1973 WERE USED. j 1 J EXilIBIT 4-17

O O O SRP ACCEPTANCE CRITERIA i REGULATORY GUIDE 1.27, ULTIMATE HEAT SINK (CONT'D) REQUIREMENT DESIGN FEATURE 4 l THE METEOROLOGICAL CONDITIONS RESULTING IN COMPLIANCE. THE WORST DAY FOR j IN MAXIMUM EVAPORATION AND DRIFT LOSS THE ESP WATER MASS IS AUGUST 8, SHOULD BE THE WORST 30-DAY AVERAGE 1969. THE WORST 29 CONSECUTIVE COMBINATION OF CONTROLLING PARAMETERS, DAYS FOR THE ESPS POND WATER MASS SUCH AS DEWPOINT, DEPRESSION, WINDSPEED, ARE FROM JULY 12, 1971, TO SOLAR RADIATION. AUGUST 9, 1971. THE FACTOR CONSIDERED FOR THE i SELECTION PROCESS WAS THE l MAXIMUM DIFFERENCE BETWEEN DRY BULB TEMPERATURE AND DEW-POINT TEMPERATURE CONCURRENT WITH THE HIGHEST WIND SPEEDS. I i i I 1 I l ) EXHIBIT 4-18

i O O O SRP ACCEPTAllCE CRITERIA REGULATORY GUIDE 1.27, ULTIMATE HEAT SIllK (CONT'D) 2 REQUIREMEllT DESIGN FEATURE i THE METEOROLOGICAL CONDITIONS RESULTING IN COMPLIANCE. THE WORST DAY l'OR IN MINIMUM WATER COOLING SHOULL BE THE THE ESP THERMAL DESIGN IS WORST COMBINATION OF CONTROLLING PARAM-AUGUST 14, 1955. THE WORST 29 CON- ~ ETERS FOR THE CRITICAL TIME PERIOD UNIQUE SECUTIVE DAYS FOR THE ESP THERMAL TO THE SPECIFIC DESIGN OF THE SINK. DESIGN ARE FROM JULY 30, 1955, TO l AUGUST 27, 1955. l THE FACTOR CONSIDERED FOR THE l SELECTION PROCESS WAS THE MINIMUM l DIFFERENCE BETWEEN DRY BULB j TEMPERATURE AND DEWPOINT TEMPERATURE. t i i EXHIBIT 4-19 I

O O O 1 SRP ACCEPTANCE CRITERIA REGULATORY GUIDE 1.27, ULTIMATE HEAT SINK (CONT'D) ^ i i REQUIREMENT DESIGN FEATURE I 2) ULTIMATE HEAT SINK SHOULD BE CAPABLE OF WITHSTANDING, WITHOUT LOSS OF SINK l SAFETY FUNCTION, THE FOLLOWING EVENTS: I A) IHE MOST SEVERE EXTERNAL PHENOMENA A) IN COMPLIANCE. ESP IS SEISMIC 1 EXPECTED AT THE SITE, WITH APPRO-CATEGORY I STRUCTURE LOCATED PRIATE AMBIENT CONDITIONS, BUT WITH BEYOND EXTENT OF PROBABLE NO TWO OR MORE SUCH PHENOMENA OCCUR-MAXIMUM FLOOD. HIGHLY f RING SIMULTANEOUSLY. IMPROBABLE THAT TORNADO AND i DBA WOULD OCCUR SIMULTANE-J 5 OUSLY. AS SuCH, NO WATER ALLOWANCE OR PROTECTION OF fa SPRAY HEADERS IS PROVIDED. FOR MORE PROBABLE CASE OF j! TORNADO OCCURRING SIMULTANE-OUSLY WITH NORMAL SHUTDOWN, ESP PUMPS AND LINES ARE PRO-TECTED AGAINST TORNADO, MAKEUP WATER LINES TO THE ESP ARE UNDERGROUND AND TWO INDE-4 PENDENT ON-SITE SOURCES OF WATER AVAILABLE. EXHIBIT 4-20 l

_ _ = O O O SRP ACCEPTAllCE CRITERIA l REGULATORY GUIDE 1.27, ULTIMATE IlEAT SIllK (C0tlT'D) REQUIREMEllT DESIGN FEATURE B) IHE SITE-RELATED EVENTS THAT B) IN COMPLIANCE. THE FOLLOWING HISTORICALLY HAVE OCCURRED OR EVENTS HAVE LOW PROBABILITY ? THAT MAY OCCUR DURING THE PLANT LIFETIME. e AIRPLANE CRASH i e RAIL CAR ACCIDENT e OIL SPILL INTO ESP I FIRE DETECTION IN THE ESPS INTAKE STRUCTURES IS PROVIDED. REMAINING i ESPS COMPONENTS DO NOT CONTAIN COMBUSTIBLE MATERIALS. i C) IASONABLY PROBABLE COMBINATIONS C) I:J COMPLIANCE. THE SEISMIC l OF LESS SEVERE NATURAL PHENOMENA CATEGORY I DESIGN OF THE ESPS l AND/OR SITE-RELATED EVENTS. ST~UCTURE AND COMPONENTS, fl CONCURRENT WITH CONSERVATIVE THERMAL / WATER MASS ESP DESIGN, PRECLU. LOSS OF ESP INTEGRITY j OR CAPABILITY TO FUNCTION. i TWO REDUNDANT TRAINS ARE PROVIDED. i EXIIIBIT L1-21

O O O 2 SRP ACCEPTAUCE CRITERIA 2 REGULATORY GUIDE 1.27, ULTIMATE llEAT SIHK (CONT'D) i REQUIREMENT DESIGN FEATURE D) A SINGLE FAILURE OF MANMADE D) IN t0MPLIANCE. FAILURE OF A l STRUCTURAL FEATURES. SINGLE STRUCTURE CANNOT RESULT IN THE LOSS OF THE ESP SAFETY FUNC-TION. REDUNDANT ESP AND THE REDUNDANT VAL'/ES BETWEEN THE TWO ESPS PROVIDE THB CAPABILITY TO SUPPLY COOLING WATER IN THE EVENT OF FAILURE OF ONE TRAIN. 4 l 3) THE ULTIMATE HE%T SINK SHOULD IN CJMPLIANCE. IWO SEPARATE MAKEUP CONSIST OF AT LEAST TWO SOURCES WATER LINES WERE PROVIDED TO EACH ESP OF WATER, UNLESS IT CAN BE DEMON-FROM DOMESTIC WATER SYSTEM (PRIMARY STRATED THAT THERE IS EXTREMELY SOURCE), AND STATICH MAKEUP WATER LOW PROBABILITY OF LOSING THE RESERVOIR VIA COOLING TOWER MAKEUP AND CAPABILITY OF A SINGLE SOURCE. BLOWDOWN SYSTEM (BACKUP SOURCE). 4 I i EXilIBIT 4-22

i O o o j SRP A.CCEPTANCE CRITERIA i REGULATORY GUIDE 1.29, SEISMIC DESIGN CLASSIFICATION REQUIREMENT DESIGN FEATURE l THE COOLING WATER SYSTEMS THAT ARE IN COMPLIANCE. j REQUIRED FOR POST-/sCCIDENT HEAT ~ REMOVAL SHALL BE DESIGNATED SEISMIC j CATEGORY I AND BE DESIGNED TO WITH-STAND THE EFFECTS OF THE SSE AND REMAIN FUNCTIONAL. THE QUALITY i ASSURANCE REQUIREMENTS OF l APPENDIX B TO 10CFR50 SHALL APPLY. i i i i i EXHIBIT 11-23 i

l O O O i SRP ACCEPTANCE CRITERIA i REGULATORY GUIDE 1,72, PLASTIC PIPE REQUIREMENT DESIGN FEATURE t l SAFETY-RELATED SPRAY POND PIPING NOT APPLICABLE. THE SPRAY POND PIPING COMPONEN1S MADE FROM FIBERGLASS-ON THE PVNGS IS FABRICATED l REINFORCED THERM 0 SETTING RESIN FROM AUSTENITIC STAINLESS STEEL, i SHOULD COMPLY WITH ASME CODE CASE GRADE 316L. Il-155-1 (1972-1), t i 4 I i i l 1 l l l i EXHIBIT 4-24 j 1

I O O O SRP ACCEPTAllCE CRITERIA REGULATORY GUIDE 1.102, FLOOD PROTECTI0fl i REQUIREf4EllT DESIGN FEATURE i 1 j SAFETY SYSTEMS SHOULD BE DESIGNED TO IN COMPLIANCE. WITHSTAND THE MOST SEVERE FLCOD CONDITIONS RESULTING FROM SEVERE HYDROMETEOROGICAL CONDITIONS, SEISMIC ACTIVITY, OR BOTH. 1 i I i l 1 i EXilIBIT 4-25 ii.

O O O SRP ACCEPTANCE CRITERIA I REGULATORY GUIDE 1.117,10RNAIJO DESIGN CLASSIFICATION i REQUIRB1ENT DESIGN FEATURE THE ULTIMATE HEAT SINK SYSTEMS SHOULD IN COMPLIANCE. THE ESPS IS PROTECTED BE DESIGNED TO MAINTAIN THEIR CAPA-FROM THE EFFECT OF A DESIGN BASIS BILITY IN THE EVENT OF A DESIGN BASIS TORNADO IN CONJUNCTION WITH A NORMAL TORNADO. SHUTDOWN. SINCE THE ESP PUMPS AND LINES ARE PROTECTED AGAINST TORNADOES, THE MAKEUP WATER LINES TO THE ESP ARE UNDERGROUND, AND TWO INDEPENDENT e OH-SITE SOURCES OF WATER ARE AVAILABLE, A TORNADO WOULD NOT IMPAIR ESP. IT IS HIGHLY IMPROBABLE THAT A TORNADO AND DBA WOULD OCCUR SIMULTANEOUSLY AND THEREFORE NO WATER ALLOWANCE OR PROTEC-TION OF THE SPRAY HEADERS IS PROVIDED. i i i 1 i EXilIBIT 4-2G OT

O O O BTP ASB 3-1, PROTECTION AGAlllST POSTULATED PIPING FAILURES Ill FLUID SYSTEMS OUTSIDE CONTAltlMEllT REQUIREMENT DESIGN FEATURE THE SYSTEMS AND COMPONENTS IMPORTANT IN COMPLIANCE. TO SAFETY SHALL BE APPROPRIATELY PROTECTED AGAINST DYNAMIC EFFECT, INCLUDING THE EFFECT OF MISSILES, PIPE WHIPPING AND DISCHARGING FLUIDS, THAT MAY RESULT FROM EQUIP-MENT FAILURES AND FROM EVENTS AND CONDITIONS OUTSIDE THE CONTAINMENT. EXilIBIT 4-27

i o o o ~ BTP ASB 9-2: RESIDUAL DECAY ENERGY REQUIREMENTS DESIGN FEATURE \\ THE AUXILIARY SYSTEMS BRANCH 4AS IN COMPLIANCE. DECAY HEAT IS COMPUTED I DEVELOPED ACCEPTABLE ASSUMPT ONS AND FROM EQUATIONS GIVEN IN BTP ASB 9-2. FORMULATIONS THAT MAY BE USED TO CALCULATE THE RESIDUAL DECAY ENERGY 1 t i RELEASE RATE FOR LIGHT-WATER-COOLED i j REACTORS FOR LONG-TERM COOLING OF 1 THE REACTOR FACILITY. i l t } l i i 1 l } i l l EXIllBIT 11-28 1

} i l i i h t i i l l l i i i l V. BACKGROUND INFORf1ATION 1 i IG

• l e

i i 0 EXHIBIT 5-i E w w.me - emse mwswm - m --w--e. m' eN-w--- +

i O PVNGS DESIGN DEVELOPMENT THE PVNGS DESIGN DEVELOPMENT, REPRESENTED IN FIGURE B-1, IS CENTERED AROUND THE DESIGN CRITERIA, WHICH ACT AS THE HUB 0F THE DESIGN. THESE CRITERIA ARE REVIEWED AND APPROVED BY THE OWNER AND ESTABLISH THE SCOPE OF THE SYSTEM. THEY ARE ASSEMBLED IN THREE VOLUMES ENTITLED " DESIGN CRITERIA MANUAL - PALO VERDE UNITS 1, 2 AND 3" AND REFLECT ALL THE DESIGN CRITERIA FOR THE PLANT. THIS IS A DYNAMIC DOCUMENT THAT IS UPDATED AS NEW CRITERIA ARE INCORPORATED INTO THE PLANT DESIGN. AS SHOWN IN FIGURE B-1, A SERIES OF DOCUMENTS ESTABLISH THE CRITERIA, INCLUDING UTILITY OR OWNER-APPLICANT'S SPECIFIC REQUIRE-MENTS, STANDARD NSSS SYSTEM 80 LICENSING AND BALANCE OF PLANT (B0P) INTERFACE REQUIREMENTS, AND THE ENGINEER'S B0P INFORMATION (SCHEDULE, INTERFACES, LICENSING, BASIC CRITERIA, P& IDS, AND SINGLE LINE DRAW-INGS). THESE ALL SERVE AS INPUT TO THE DESIGN CRITERIA HUB, WHICH BY AN ITERATIVE PROCESS RESULTS IN APPLICANT LICENSING DOCUMENTS, DEVEL-, OPMENT OF THE MODULAR PLANT ARRANGEMENT AND THE STANDARD DESIGN, AND FEEDBACK FROM THE REGULATORS. FRDM THIS, PROCUREMENT SPECIFICATIONS. SYSTEM DESCRIPTIONS, SCHEDULES, CONSTRUCTION SPECIFICATIONS, TEST SPECIFICATIONS, AND THE STATION MANUAL ARE DEVELOPED. THE PLANT ARRANGEMENT IS ALSO DERIVED FROM THE DESIGN CRITERIA, AS REPRESENTED BY A THREE-QUARTER INCH TO THE FOOT SCALE MODEL OF THE PVNGS POWER BLOCK. THE MODEL IS USED TO DERIVE DETAILED CONSTRUCTION DRAWINGS AND PLANNING PH000 GRAPHS. IN

SUMMARY

, ONE SET OF DOCUMENTS ESTABLISH THE CRITERIA. FROM THIS SET, DESCRIPTIONS ARE PUT INTO LICENSING DOCUMENTS AND KEPT CURRENT BY CONTINUING REVIEW. MULTI-DISCIPLINE REVIEWS ARE CARRIED OUT WHERE DIFFERENT DISCIPLINES GET TOGETHER AT THE MODEL AND ANALYZE THE SYSTEMS, ASSESSING THE DESIGN, SAFETY, SEPARATION AND ALL CRITERIA, TO ENSURE THAT THE SYSTEM MEETS THE ESTA3LISHED CRITERIA. THIS PROCESS GENERALLY TAKES TWO TO THREE YEARS TO ASSURE THAT THE DESIGN IS CORRECT AND REFLECTS ALL THE REQUIREMENTS. O EXHIBIT 5-1 l 1n. -.

O O O UTILITY 4 APPLICANT SPECIFIC REQUIREMENTS STANDARD j NSSS UTILITY APPLICANT LICENSING

• ST AN D A R D DOCUMENTS

, r tlCENSING APPROVAL BOP e INTERFACE REQUIREMENTS ^ggg,g - g il CRITERI A ii DEVELOPMENT OF STANDARD DESIGN I t j 9 r ENGINEERS PLANT ARRANGEMENT i BALANCE OF PLANT DESIGN e PROCUREMENT IN FO RM ATION MODULAR MODEL SPECIFICATIONS e SYSTEM DESCRIPTIONS

• SCHEDULE e ENGINEERING e BOPINTERFACE i

SCHEDULE { e LICENSING , r e CONSTRUCTION e BASIC CRITERI A SPEtWICATIONS DETAILED l e P&lD'S e e ST CONSTR UCTION SINGLE LINES p p e e STATION e PLANNING AN N PHOTOGRAPHS i PVNGS DESIGN DEVELOPMENT FIGURE 5-1 1 .}}