RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 4, Reactor
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055-.....TOP GRID ad TYP MID GRIDSIl'.173 FUEl..aSS£MBL T AltO ACeA PITCM i=l21.m(340.jr14325)
JR1432S@jrI432S.FtiJun 28 EDT 1996 SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Fuel Assembly Cross Section 17x17 Figure 4.2-1 AMENDMENT 96-02 JULY 1996 055-.....TOP GRID ad TYP MID GRIDS I l'.173 FUEl..aSS£MBL T AltO ACeA PITCM i=l21.m(340.jr14325)
JR1432S@jrI432S.FtiJun 28 EDT 1996 SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Fuel Assembly Cross Section 17x17 Figure 4.2-1 AMENDMENT 96-02 JULY 1996 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION 17 x 17 Vantage+with Performance
+Fuel Assembly Figure 4.2-2 I SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION 17 x 17 Vantage+with Performance
+Fuel Assembly Figure 4.2-2 I t:1);rn Fuel Rod Figure 4.2-3 TQP 17 x 17 Vantage+with Performance
+SOUTH CAROLINA ELECTRIC l..GAS CO.VIRGIL C.SUMMER NUCLEAR 5T ATlON BOTTOM 1 I-:"'J C fi1 r--...j X-'l-...j C 1Tl<r>C'I'---Z:::::J-i p-, 0>-...........
""" OC">..-, tJ fi1......,..'--.-+r--,}-,---.........d 1 , I"-eno-p......>3: I'n:::::n l'r.f'Tl I Z c:J-i..J..--1 I\1, I ,-:"'J C JTlr-o03: or JTl Z GJ V+with P+Features 152.670 in 7.410 in 144.00 in 0.315 in 0.360 in DIM A B C DIA D DIAE t:1);rn Fuel Rod Figure 4.2-3 TQP 17 x 17 Vantage+with Performance
+SOUTH CAROLINA ELECTRIC l..GAS CO.VIRGIL C.SUMMER NUCLEAR 5T ATlON BOTTOM 1 I-:"'J C fi1 r--...j X-'l-...j C 1Tl<r>C'I'---Z:::::J-i p-, 0>-...........
""" OC">..-, tJ fi1......,..'--.-+r--,}-,---.........d 1 , I"-eno-p......>3: I'n:::::n l'r.f'Tl I Z c:J-i..J..--1 I\1, I ,-:"'J C JTlr-o03: or JTl Z GJ V+with P+Features 152.670 in 7.410 in 144.00 in 0.315 in 0.360 in DIM A B C DIA D DIAE
-I i.ar424.m(343.jr1432S) 1Rl4325@jr14325.Fri1un2813,05,06EDT1996 ZIRLO THIMBLE FUEL ROD MID GRID EXPANSION.JOINT DESIGN SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Vantage*fuel Pion Vie", figure 4.2-4 AMENDMENT 96-02 JULY 1996-I i.ar424.m(343.jr1432S) 1Rl4325@jr14325.Fri1un2813,05,06EDT1996 ZIRLO THIMBLE FUEL ROD MID GRID EXPANSION.JOINT DESIGN SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Vantage*fuel Pion Vie", figure 4.2-4 AMENDMENT 96-02 JULY 1996 EXPANSION LOBE f.aN25.m(339J<14325)
JR14325@jrl4325.FriJun28 1201J,03 EDT 1996 ZIRLO THIMBLE SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Elevation View*vantage-Fuel Figure 4.2-5*AMENDMENT 96-02 JULY 1996 EXPANSION LOBE f.aN25.m(339J<14325)
JR14325@jrl4325.FriJun28 1201J,03 EDT 1996 ZIRLO THIMBLE SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Elevation View*vantage-Fuel Figure 4.2-5*AMENDMENT 96-02 JULY 1996
\---, I)/AMENDMENT 96-02 JULY 1996 Figure 4.2'6 ASSEMBLED Vantage-FuelTop Grid Ta N022el Attachment SOUTH CAROLINA ELECTRIC 8r GAS CO.VIRGIL C.SUMMER NUCLEAR STATION ADAPTt.R°LA i;::*I:...SST NOZZLE INSERT ROOVE ADAPTER PLATE THRU HOLE.Or""'K..,..,'-'",.U:...>='---4 LOBE BULGE THIMBLE TUBE TOP GRID UNASSEMBLED fsar 4 26.ro(337.jr1 4 32S).JR.l4325@jr1432S.
fri Jun 28 11:$9:05 EDT 1996\---, I)/AMENDMENT 96-02 JULY 1996 Figure 4.2'6 ASSEMBLED Vantage-FuelTop Grid Ta N022el Attachment SOUTH CAROLINA ELECTRIC 8r GAS CO.VIRGIL C.SUMMER NUCLEAR STATION ADAPTt.R°LA i;::*I:...SST NOZZLE INSERT ROOVE ADAPTER PLATE THRU HOLE.Or""'K..,..,'-'",.U:...>='---4 LOBE BULGE THIMBLE TUBE TOP GRID UNASSEMBLED fsar 4 26.ro(337.jr1 4 32S).JR.l4325@jr1432S.
fri Jun 28 11:$9:05 EDT 1996 r THIMBLE/END PLUG INERT-GAS FUSION WELD INSERT/END PLUG WELD 55 THIMBLE SCREW WITH INTEGRAL LOCKING CAP&..r427.m(342.jd432S)
JRI432S@j,1432.1.FriJun2813,0222EDT1996 ZIRLO THIMBLE GRID SPOT WELD S5 INSERT ZIRCALOY THIMBLE END.PLUG S5 BOTTOM NOZZLE SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Vantage-r uel Guide Thimble To Boltom Nozzle Joint Figure 4.2-7 AMENDMENT 96-02 JULY 1996 r THIMBLE/END PLUG INERT-GAS FUSION WELD INSERT/END PLUG WELD 55 THIMBLE SCREW WITH INTEGRAL LOCKING CAP&..r427.m(342.jd432S)
JRI432S@j,1432.1.FriJun2813,0222EDT1996 ZIRLO THIMBLE GRID SPOT WELD S5 INSERT ZIRCALOY THIMBLE END.PLUG S5 BOTTOM NOZZLE SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Vantage-r uel Guide Thimble To Boltom Nozzle Joint Figure 4.2-7 AMENDMENT 96-02 JULY 1996 0.330 ,-----, 0.328 (/)LLJ::I: U:z: IX LLJ.....LLJoc(I::)0.326 0.321J I...._PELLET 00 EXPOSURE END OF LI FE SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUClEAR STA TlON Typical Clad and Pellet Dimensions as a Function of Exposure Figure 4.2-8 0.330 ,-----, 0.328 (/)LLJ::I: U:z: IX LLJ.....LLJoc(I::)0.326 0.321J I...._PELLET 00 EXPOSURE END OF LI FE SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUClEAR STA TlON Typical Clad and Pellet Dimensions as a Function of Exposure Figure 4.2-8 1800<I: U"l 1600UJ c::::::::l (/')(/')1400 UJ c:::....J CI: z: c::: UJ....1200 z: 0 0 c:::..J UJ::>1000 I.L..r--I I I I I I..J-------REPRESENTAT IVE LEAD BURN UP ROD-------OPERATING RANGE FOR ALL RODS IN REGION 3CYCLE I-L CYCLE 2-J...-CYCLE 3.,.I--r",P'ESENTAT IV'LEAD BURNUP ROD POWER, REGION 3 I--""L..-I I I I 800 8....I.L..-3:::..:: c::: 7 UJ 3: 0UJ Co!:'CI: c::: 6 UJ:>CI: 0 0 c::: 5 o 5 10 15 TIME (10 3 HOURS)20 25 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Representive Fuel Rod Internal Pressure and Linear Power Density for the Lead Burnup Rod as a Function of Time Figure 4.2-9 1800<I: U"l 1600UJ c::::::::l (/')(/')1400 UJ c:::....J CI: z: c::: UJ....1200 z: 0 0 c:::..J UJ::>1000 I.L..r--I I I I I I..J-------REPRESENTAT IVE LEAD BURN UP ROD-------OPERATING RANGE FOR ALL RODS IN REGION 3CYCLE I-L CYCLE 2-J...-CYCLE 3.,.I--r",P'ESENTAT IV'LEAD BURNUP ROD POWER, REGION 3 I--""L..-I I I I 800 8....I.L..-3:::..:: c::: 7 UJ 3: 0UJ Co!:'CI: c::: 6 UJ:>CI: 0 0 c::: 5 o 5 10 15 TIME (10 3 HOURS)20 25 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Representive Fuel Rod Internal Pressure and Linear Power Density for the Lead Burnup Rod as a Function of Time Figure 4.2-9
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c::>:3-c:::>c::=::::>L£3\I--c::=::::>c::=::::>S-F c:::::..-F-l-c:::>c::......., GUIDE lutE-l-F-l 13 l-I=>b SV'POIl PlaT(SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Upper Core Support Assembly Figure 4.2-11""(1 (Oaf PlaT(, p-F-, I=>-f---I-u"u 13-fi-3 c:::=..SV"OaT III III I-.I I-c;::ic=COl_l II--.---.I'/" 13-EEJ-......c:::::::::>
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c::>:3-c:::>c::=::::>L£3\I--c::=::::>c::=::::>S-F c:::::..-F-l-c:::>c::......., GUIDE lutE-l-F-l 13 l-I=>b SV'POIl PlaT(SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Upper Core Support Assembly Figure 4.2-11 SUPPORT COLUMNS DEEP BEAM WELDMENTS GUIDE TUBEASSEMBLY LOCATIONS IHEAD AND VESSEL ALIGNMENT PIN LOCATION SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Plan View of Upper Core Support Structure Figure 4.2-12 SUPPORT COLUMNS DEEP BEAM WELDMENTS GUIDE TUBEASSEMBLY LOCATIONS IHEAD AND VESSEL ALIGNMENT PIN LOCATION SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Plan View of Upper Core Support Structure Figure 4.2-12 RCC ASSEM8L Y WITHDRAWN CHOM DRIVE ROO ASSEMBLY FULL RCC ASSEMBL Y GU I DE TUBE ASSEMBL Y FUEL ASSEMBLY SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Full length Rod Cluster Control and Drive Rod Assembly with Interfacing II'Components I Figure 4.2-13 RCC ASSEM8L Y WITHDRAWN CHOM DRIVE ROO ASSEMBLY FULL RCC ASSEMBL Y GU I DE TUBE ASSEMBL Y FUEL ASSEMBLY SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Full length Rod Cluster Control and Drive Rod Assembly with Interfacing II'Components I Figure 4.2-13 S Pi DE R 0.361 DIA 161.0 0.385 D IA MAX LENGTH ABSORBERSILVER 15"1.I ND I UM 5'1, CADMI UM SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION full Length Rod Cluster Control Assembly Outline Figure 4.2-14 S Pi DE R 0.361 DIA 161.0 0.385 D IA MAX LENGTH ABSORBERSILVER 15"1.I ND I UM 5'1, CADMI UM SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION full Length Rod Cluster Control Assembly Outline Figure 4.2-14 0.381 OIA.HOM'1 1l12.00 ABOSRBER MATERIAL.1'J-...
I::: I 151.73 I I t-SOUTH CAROLINA ElECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STA TION Full length Absorber Rod Figure 4.2-15 0.381 OIA.HOM'1 1l12.00 ABOSRBER MATERIAL.1'J-...
I::: I 151.73 I I t-SOUTH CAROLINA ElECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STA TION Full length Absorber Rod Figure 4.2-15 STA INLESS STL 151.60 142.0 REF.r PO I SON LENGTH 2.,&::.I-r.......-------_.-I-=---r-l-----fA.1\I I r I.(ti1itiIiJ I"" IlIl!III!77/"7_?r--f-------....----'" I I///-L---'---"'t:I I-J-/,J;:.'--SPRINGS J---II--" BURNABLE POISON ROO TH IMBLE PLUG AMENDMENT6 AUGUST,1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Borosilicate Absorber Assembly Figure 4.2-17 STA INLESS STL 151.60 142.0 REF.r PO I SON LENGTH 2.,&::.I-r.......-------_.-I-=---r-l-----fA.1\I I r I.(ti1itiIiJ I"" IlIl!III!77/"7_?r--f-------....----'" I I///-L---'---"'t:I I-J-/,J;:.'--SPRINGS J---II--" BURNABLE POISON ROO TH IMBLE PLUG AMENDMENT6 AUGUST,1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Borosilicate Absorber Assembly Figure 4.2-17 0 z:<r 0-..00'" 0 r" t1">r--I.--00 l.L.W 0"'"<.!J.....z t.Jww"'"....J o cr:<o UJ<Na:l::t'cr:-0 (/)a:l<l: o o 1..'"<i-<z: oe;.;>w (/)-'-wll'l:w'..L.AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Borosilicate Absorber Rod Cross Section Figure 4.2-180 z:<r 0-..00'" 0 r" t1">r--I.--00 l.L.W 0"'"<.!J.....z t.J w w"'"....J o cr:<o UJ<Na:l::t'cr:-0 (/)a:l<l: o o 1..'"<i-<z: oe;.;>w (/)-'-wll'l:w'..L.AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Borosilicate Absorber Rod Cross Section Figure 4.2-18 150.0 TYPICAL FLOW'ATH f*UPPER END PLUG ZlRCALOY lUBES....._HOlDDOWN DEVICE FLOW PATH 1.0 TYPICAl.ABSORBER LENGTH AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Wet Annular Burnable Absorber Rod Figure 4.2*18a 150.0 TYPICAL FLOW'ATH f*UPPER END PLUG ZlRCALOY lUBES....._HOlDDOWN DEVICE FLOW PATH 1.0 TYPICAl.ABSORBER LENGTH AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Wet Annular Burnable Absorber Rod Figure 4.2*18a
""'150.4 1.5 NOM.\-CALIFORNIUM
-,-
142.0 REF PO'SON LENGTH------------lI1lOO1 NOTE ALL OIMENSIONS ARE IN INCHES 0.381 o I A.JBl OIA PRIMARY SCOURCE BURNABLE POISON BOROS III CA TE GLASS TUBE SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Primary Source Assembly Figure 4.2-19""'150.4 1.5 NOM.\-CALIFORNIUM
-,-
142.0 REF PO'SON LENGTH------------lI1lOO1 NOTE ALL OIMENSIONS ARE IN INCHES 0.381 o I A.JBl OIA PRIMARY SCOURCE BURNABLE POISON BOROS III CA TE GLASS TUBE SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Primary Source Assembly Figure 4.2-19 ANTIMONY BERYLLIUM 88.0 SECONOARY SOURCE SECONOARY SOURCE , 0.381 OIA STAINLESS STU L THIMBLE*PLUG*FITS ONLY LOPAR ASSEMBLY THIMBLE TUBES.TO FIT INTO VANTAGE 5 THIMBLE TUBES, MUST USE OUALLY COMPATIBLE PLUG DESIGN WITH 0.424 INCH DIAMETER.NOTE ALL OIMENSIONS ARE IN INCHES AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Secondary Source Assembly Figure 4.2-20 ANTIMONY BERYLLIUM 88.0 SECONOARY SOURCE SECONOARY SOURCE , 0.381 OIA STAINLESS STU L THIMBLE*PLUG*FITS ONLY LOPAR ASSEMBLY THIMBLE TUBES.TO FIT INTO VANTAGE 5 THIMBLE TUBES, MUST USE OUALLY COMPATIBLE PLUG DESIGN WITH 0.424 INCH DIAMETER.NOTE ALL OIMENSIONS ARE IN INCHES AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Secondary Source Assembly Figure 4.2-20 0.424" OIA.(BOTH LOPAR ANO VANTAGE 5 ASSY.)-----.,E:::7-
--D c:(]---[0.434" OIA.(lOPAR ASSY ONLY)
AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Thimble Plug Assembly Figure 4.2-21 0.424" OIA.(BOTH LOPAR ANO VANTAGE 5 ASSY.)-----.,E:::7-
--D c:(]---[0.434" OIA.(lOPAR ASSY ONLY)
AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Thimble Plug Assembly Figure 4.2-21 ROD TRAVEL ,\OPERATING COIL STACK ASSEMBLY CABLE CONNECTION SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Full Length Control Rod Drive Mechanism Figure 4.2-22 ROD TRAVEL ,\OPERATING COIL STACK ASSEMBLY CABLE CONNECTION SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Full Length Control Rod Drive Mechanism Figure 4.2-22
__--DRIVEASS'" SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION HOUSING LATCH HOUSING IMIII IiIOVA.LI:
11111010(11 llOtIl...LOCKIOLU_II
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_lOIN:l<:'iIM"'+----LOCK Wltlll:
TUM:_ILl: LATCH
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II[T"II[II LATCH 10111 AIIII i§LOCK IOLU"[11 ITATIllIIAIIT LATClt II LATCH LIIIK LIIIKIOIII IUIOIOOIIT TUIII: ITAT_IIT LATCH*""".,....,o+----LATCH ITOI'Full Length Control Rod Drive Mechanism Schematic Figure 4.2-23__--DRIVEASS'" SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION HOUSING LATCH HOUSING IMIII IiIOVA.LI:
11111010(11 llOtIl...LOCKIOLU_II
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11111010(11 llOtIl...LOCKIOLU_II
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r LJ..J..--U COIL lA'
-.....1..;..Jo,.-\t:'!""-_IOLU_1I HALLUll 11111I1 LOCll WillI:.u..::.t-_-L.,T II[TIHIII 1101I_
II[T"II[II LATCH 10111 AIIII i§LOCK IOLU"[11 ITATIllIIAIIT LATClt II LATCH LIIIK LIIIKIOIII IUIOIOOIIT TUIII: ITAT_IIT LATCH*""".,....,o+----LATCH ITOI'Full Length Control Rod Drive Mechanism Schematic Figure 4.2-23 BEFORE LOAD TRANSFER AFTER LOAD TRANSFER M6 LIFT COIL ON 16.258 16.203 A AT 650°A B CD LIFT COIL OFF 15.679 0.038 LI FT COl L ON 16.387 16.291 0.01656 (SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Nominal Latch Clearance at Minimum and Maximum Temperature Figure 4.2-26 LIFT COIL OFF 15.625 15.578 A B 1I FT COl L OFF LI FT COl L ON LI FT COl L OFF II FT COl L ON 56 AT 70°A B (0 15.6 1 W 15.625 0.01516.26516.250 0.015 AT 650°A B C0 15.725 15.679 16.375 16.387 0.068 B A B BEFORE LOAD TRANSFER AFTER LOAD TRANSFER M6 LIFT COIL ON 16.258 16.203 A AT 650°A B CD LIFT COIL OFF 15.679 0.038 LI FT COl L ON 16.387 16.291 0.01656 (SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Nominal Latch Clearance at Minimum and Maximum Temperature Figure 4.2-26 LIFT COIL OFF 15.625 15.578 A B 1I FT COl L OFF LI FT COl L ON LI FT COl L OFF II FT COl L ON 56 AT 70°A B (0 15.6 1 W 15.625 0.01516.26516.250 0.015 AT 650°A B C0 15.725 15.679 16.375 16.387 0.068 B A B 0.080 700 600------500--------300 1100 TEMPERATURE (OF)LIFT COIL OFF l MG CLEARANCE AFTER'LIFT COIL ON f LOAD TRANSFER 200 100 ,,-//--/----.A'..----/-\L lIFT COIL 0'}SG CLEARANCE BEFORE LIFT COIL OFF LOAD TRANSFER (/)0.070 UJ:x: c:...>z: 0.060 UJ:>0 C 0::: 0.050w:>0::: 0.01l0 Cl 0:z: e((/)0.030 UJ:x: c:...>l-e(0.020-J UJ c:...>z: e(0.010 0::: e(UJ-J c:...>0.000 0 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Control Rod Drive Mechanism Latch Clearance Thermal Effect Figure 4.2-27 0.080 700 600------500--------300 1100 TEMPERATURE (OF)LIFT COIL OFF l MG CLEARANCE AFTER'LIFT COIL ON f LOAD TRANSFER 200 100 ,,-//--/----.A'..----/-\L lIFT COIL 0'}SG CLEARANCE BEFORE LIFT COIL OFF LOAD TRANSFER (/)0.070 UJ:x: c:...>z: 0.060 UJ:>0 C 0::: 0.050w:>0::: 0.01l0 Cl 0:z: e((/)0.030 UJ:x: c:...>l-e(0.020-J UJ c:...>z: e(0.010 0::: e(UJ-J c:...>0.000 0 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Control Rod Drive Mechanism Latch Clearance Thermal Effect Figure 4.2-27 LEGEND: tVV\IMPACT SPRING ELEMENT-n-VI SCOUS DAMP I NG ELEMENT-lGAP ELEMENTMASS ELEMENT......4-F 3 (t)UPPER CORE PlATE FUEL ASSEMBLY..1-tJ-f1 IIII II LI II F 2{t)LOWER CO.RE PLATE F 3 (t)......BARREL AT UPPER CORE PLATE£LEVATI ON<Vl-0:x:I e r-I (\f"'l Vl>>e:x:l m Z:x:I>>em f"'lf"'l r--I m:x:l:x:If"'l Vl QO-I">>>>:::!Vl Of"'l z9 Vl ('\:::r ro 3 OJ r+n':x:I f"'lro 0"0roro II> oQ.OJ ro r+-o'::J o....:x:I ro OJ ('\r+o"T1\C c:roIV N 00 tVV\IMPACT SPRING ELEMENT-n-VI SCOUS DAMP I NG ELEMENT LEGEND:-lGAP ELEMENTMASS ELEMENT F 2 (t) F 3 (t}....BARREL AT UPPER CORE PLATE ELEVATI ON VI<VI-0 ('\:x:I c:::r ro 3 r-I OJ t""It""I z..>>('\VI:x:I:x:I Co"T1 t""I ro\C 0"Q c:roro II>roIV o.....cm N Q.OJ t""It""I ro z.r--l 00-0 m:x:l::J>>n 0....:x:IQO:x:I ro OJ>>>>('\-lVl.....Ot""l 0z9 FUEL ASSEMBLY UPPER CORE PlATE
4.3-53 Reformatted Per Amendment 02-01 TABLE 4.3-3 REACTIVITY REQUIREMENTS FOR ROD CLUSTER CONTROL ASSEMBLIES (Typical Reload Cycle)
Reactivity Effects, Percent Beginning of Life End of Life
- 1. Control Requirements Fuel temperature (Doppler), % 1.11 1.06 Moderator temperature (1), % 0.06 1.06 Redistribution, % 0.85 1.00 Rod Insertion Allowance, % 0.50 0.50 2. Total Control, % 2.52 3.62 3. Estimated Rod Cluster Control Assembly Worth (52 Rods)
- a. All assemblies inserted, % 10.18 8.40 b. All but one (highest worth) assemblies inserted, % 6.43 7.61 4. Estimated Rod Cluster Control Assembly credit with 10 % adjustment to accommodate uncertainties (3b - 10 percent), % 5.79 6.85 5. Shutdown Margin Available (4-2), % 3.27 3.23 (2) (1) Includes void effects.
(2) The design basis minimum shutdown is 1.77%.
4.3-54 Reformatted Per RN 03-017 TABLE 4.3-4
SUMMARY
OF SPENT FUEL RACK CRITICALITY BIASES AND STATISTICAL UNCERTAINTIES REGION 1 REGION 2 CALCULATIONAL & METHODOLOGY BIASES Methodology (Benchmark) Bias +0.0009 +0.0009 Pool Water Temperature Variation +0.0016 +0.0021 Axial Burnup Distribution N/A +0.0062 TOTAL Bias
+0.0025 +0.0092 TOLERANCES & UNCERTAINTIES UO 2 Enrichment Tolerance +0.0016 +0.0032 UO 2 Density Tolerance +0.0022 +0.0030 Storage Cell ID Tolerance N/A +0.0011 1 Boral Width Tolerance +0.0006 +0.0008 Boral Minimum B10 Content +0.0019 +0.0028 Depletion Uncertainty N/A +0.0146 Calculational Uncertainty (95/95) +0.0016 +0.0012
Methodology Bias Uncertainty
+0.0011 +0.0011 TOTAL Uncertainty (statistical)
+0.0086 +0.0157 TOTAL OF BIASES & UNCERTAINTIES +0.0111 +0.0249
1 As the box I.D. and cell pitch are interre lated a change in one of these parameters will necessarily the other param eter. It is assumed that both the cell pitch and box I.D. are manufactured at their minimum.
2 This assumes the maximum possible change in the water gap, predicated on the box I.D. and cell pitch being manufactured at their greatest tolerance in opposition to each other (i.e. maximum box I.D. and minimum cell pitch).
RN 03-017 4.3-55 Reformatted Per Amendment 02-01 TABLE 4.3-5 AXIAL STABILITY INDEX PRESSURIZER WATER REACTOR CORE WITH A 12 FOOT HEIGHT Stability Index (hr
-1) Burnup (MWD/T) F Z C B (ppm) Exp Calc 1550 1.34 1065 -0.041 -0.032 7700 1.27 700 -0.014 -0.006 Difference +0.027 +0.026 02-01 4.3-56 Reformatted Per Amendment 02-01 TABLE 4.3-6 TYPICAL NEUTRON FLUX LEVELS (n/cm 2 - sec) AT FULL POWER
E s1.0 Mev 5.53 Kev E 1.0 Mev 0.625 ev E 5.53 Kev E 0.625 ev (nv)0 Core Center
6.73 x 10 13 1.18 x 10 14 8.92 x 10 13 3.14 x 10 13 Core Outer Radius
at Midheight
3.39 x 10 13 6.03 x 10 13 4.85 x 10 13 9.03 x 10 12 Core Top, on Axis
1.60 x 10 13 2.54 x 10 13 2.20 x 10 13 1.71 x 10 13 Core Bottom, on Axis
2.48 x 10 13 4.13 x 10 13 3.67 x 10 13 1.53 x 10 13 Pressure Vessel Inner Wall, Azimuthal Peak, Core Midheight 2.90 x 10 10 6.03 x 10 10 6.32 x 10 10 8.78 x 10 10 02-01 4.3-57 Reformatted Per Amendment 02-01 TABLE 4.3-7 COMPARISON OF MEASURED AND CALCULATED DOPPLER DEFECTS Plant Fuel Type Core Burnup (MWD/MTU) Measured (pcm) (1) Calculated (pcm) 1 Air - Filled 1800 1700 1710 2 Air - Filled 7700 1300 1440 3 Air and Helium - Filled 8460 1200 1210 (1) pcm = 10 5 x ln k 1/k 2 02-01 4.3-58 Reformatted Per Amendment 02-01 TABLE 4.3-8 SAXTON CORE II ISOTOPICS ROD MY, AXIAL ZONE 6 Atom Ratio Measured (1) 2 Precision (%)
LEOPARD Calculation U-234/U 4.65 x 10
-5 29 4.60 x 10-5 U-235/U 5.74 x 10
-3 0.9 5.73 x 10-3 U-236/U 3.55 x 10
-4 5.6 3.74 x 10-4 U-238/U 0.993816 0.01 0.99385 Pu-238/Pu 1.32 x 10
-3 2.3 1.222 x 10
-3 Pu-239/Pu 0.73971 0.03 0.74497 Pu-240/Pu 0.19302 0.2 0.19102 Pu-241/Pu 6.014 x 10
-2 0.3 5.74 x 10-2 Pu-242/Pu 5.81 x 10-3 0.9 5.38 x 10-3 Pu/U (2) 5.938 x 10
-2 0.7 5.970 x 10
-2 Np-237/U-238 1.14 x 10-4 15 0.86 x 10-4 Am-241/Pu-239 1.23 x 10-2 15 1.08 x 10-2 Cm-242/Pu-239 1.05 x 10
-4 10 1.11 x 10-4 Cm-244/Pu-239 1.09 x 10
-4 20 0.98 x 10-4 (1) Reported in Reference [31]
(2) Weight ratio
02-01 02-01 4.3-59 Reformatted Per Amendment 02-01 TABLE 4.3-9 CRITICAL BORON CONCENT RATIONS, HZP, BOL Plant Type Measured Calculated 2-Loop, 121 Assemblies 10-foot Core
1583 1589 2-Loop, 121 Assemblies
12-foot Core
1625 1624 2-Loop, 121 Assemblies
12-foot Core
1517 1517 2-Loop, 157 Assemblies
12-foot Core 1169 1161 4.3-60 Reformatted Per Amendment 02-01 TABLE 4.3-10 COMPARISON OF MEASURED AND CALCULATED ROD WORTH 2-Loop Plant, 121 Assemblies, 10-foot Core Measured (pcm) Calculated (pcm) Group B Group A Shutdown Group
1885 1530 3050 1893 1649 2917 ESADA Critical (1), 0.69" Pitch, 2 w/o Pu0 2 8% Pu-240 9 Control Rods 6.21" Rod Separation
2.07" Rod Separation
1.38" Rod Separation 2250 4220 4100 2250 4160 4019 (1) Reported in Reference [32]
02-01 4.3-61 Reformatted Per Amendment 02-01 TABLE 4.3-11 COMPARISON OF MEASURED AND CALCULATED MODERATOR COEFFICIENTS AT HZP, BOL Plant Type/ Control Bank Configuration Measured iso (1) (pcm/ F) Calculated iso (pcm/ F) 3-Loop, 157 Assemblies, 12-foot Core
D at 160 steps -0.50 -0.50 D in, C at 190 steps -3.01 -2.75 D in, C at 28 steps -7.67 -7.02
B, C, and D in
-5.16 -4.45 2-Loop, 121 Assemblies, 12-foot Core
D at 180 steps +0.85 +1.02 D in, C at 180 steps -2.40 -1.90 C and D in, B at 165 steps -4.40 -5.58
B, C, and D in, A at 174 steps -8.70 -8.12
(1) Isothermal coefficients, which incl ude the Doppler effect in the fuel.
F T/k k ln 10 1 2 5 in 02-01
- p II..L"a,*DC.***.-**11 D*-
11/1/-----
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1/1/1---------------------------------...----------------------------
0---
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---
1/1/1-
D no au..-un AMENDMENTS AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Typical Reload Core Fuel Loading Arrangement Figure 4.3-1*p II..L" a ,*DC.***.-**11 D*-
11/1/-----
---
1/1/------
..------------
1/1/1---------------------------------...----------------------------
0---
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1/1/1-
D no au..-un AMENDMENTS AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Typical Reload Core Fuel Loading Arrangement Figure 4.3-1 9 0 8-It-;::)..,-!i: (-8;::)-!i: O'l-::0.::: O'l::0.::: C.?6-12 LI.J enLI.J 0....0 0 5---....en 0-16 en c::: LI.J"-I:::z::: LI.J c;J It//;::)-20 u..:::z::: Pu239 u..u..7 0 0 z: z: 3 0 0-21t-I l-I-(,.)S;::)/c en 0 2 z: 0:::-28 0 Q.(,.)I
.....
-32."".."".--
---0-36 0 8 12 16 20 21t 283236 itO BURNUP, (GWD/MUT)SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Production and Consumption of Higher Isotopes Figure 4.3-2 9 0 8-It-;::)..,-!i: (-8;::)-!i: O'l-::0.::: O'l::0.::: C.?6-12 LI.J enLI.J 0....0 0 5---....en 0-16 en c::: LI.J"-I:::z::: LI.J c;J It//;::)-20 u..:::z::: Pu239 u..u..7 0 0 z: z: 3 0 0-21t-I l-I-(,.)S;::)/c en 0 2 z: 0:::-28 0 Q.(,.)I
.....
-32."".."".--
---0-36 0 8 12 16 20 21t 283236 itO BURNUP, (GWD/MUT)SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Production and Consumption of Higher Isotopes Figure 4.3-2 18000 15000'200D 1000 1000 3000 o c+----r----r-----r----,..---..,---....-iIl!
100 uoo 2000 I t i I I CYCU BIJRNUP lMWD/M'TlJ)
SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Boron Concentration Versus Burnup For Transition and Equilibrium Cores Figure 4.3-3 AMENDMENT 96-02 JULy 1996 fsar433.n:(359.jr14325}
JRl432S@jrl4325.
Wed Jul310:.$8:54 EDT 1996 18000 15000'200D 1000 1000 3000 o c+----r----r-----r----,..---..,---....-iIl!
100 uoo 2000 I t i I I CYCU BIJRNUP lMWD/M'TlJ)
SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Boron Concentration Versus Burnup For Transition and Equilibrium Cores Figure 4.3-3 AMENDMENT 96-02 JULy 1996 fsar433.n:(359.jr14325}
JRl432S@jrl4325.
Wed Jul310:.$8:54 EDT 1996 10 IF'8A ASSEIIBL T 121 InA lSSDeLT LECE!I): o FUEL ROD O GUIDE TUBE OR INSTRUMENT AT 1011 TUBE'.'InA ROD i.:<"'_1.DJ(335.jd432S)
JRl432S@jrl432S.FriJun28I1,39"'EDTI996 104 JF'IA NOTE: ALL FIGURES ARE lOP VIEI SOUTH CAROLINA ELECTRIC S.GAS CO.VIRGIL C.SUMMER NUCLEAR ST AlION Integral Fuel Burnable Absorber Rod Arrongement Within on Assembly (Sheet 1 of 2)figure 4.3-4 AMENDMENT 96-02 JULy 1996 10 IF'8A ASSEIIBL T 121 InA lSSDeLT LECE!I): o FUEL ROD O GUIDE TUBE OR INSTRUMENT AT 1011 TUBE'.'InA ROD i.:<"'_1.DJ(335.jd432S)
JRl432S@jrl432S.FriJun28I1,39"'EDTI996 104 JF'IA NOTE: ALL FIGURES ARE lOP VIEI SOUTH CAROLINA ELECTRIC S.GAS CO.VIRGIL C.SUMMER NUCLEAR ST AlION Integral Fuel Burnable Absorber Rod Arrongement Within on Assembly (Sheet 1 of 2)figure 4.3-4 AMENDMENT 96-02 JULy 1996
,:iII**.IeIIII e*I*1 J r-II*1I e:***\II:II:*I lIII1:*e', Ie: I:.!;I::.:III1:II.IIII , eo I i i;e, ,: III!, I:**;I I.,II I., I*I i I I 1 I!, j I.I I I I: , ,:: 16 InA ASSD8LY ,::: I.I i I i.!;!: I II III I I rJf*: e.:I°°e I!*III.1 j I I i I'..0!i.iI, e;ff..'I.!I Ie,IIII I: I!i..;i..;I**e'l;.: I,I i:!it i ei cit I!I..I:III I Ie., I: '.: I ,.1:., Ie!.: I Ie i I I I ItII***1 lei*.i°e:.1 iif-II I I:*I I I!I1III I I I..InA ASSDeLY LEGEND: o FUEL ItOO[J GUIDE TUIE OR ItlSTRUlEMUTION YUlE=e: IFBA ROD-fsr434_2.m(336.jr14325)
JR14325@jd432S.FriJun2811:43:59EDT1996 32 1F8A ASSEMBLY'14 I FlA*ASSEWLT MOTE: ALL F'ICURES ARE TOP VIEW SOUTH CAROLINA ELECTRICGAS CO.VIRGIL C.SUMMER NUCLEAR STATION Integral Fuel Burnable Absorber Rod Arrongement Within on Assembly<Sheet 2 of 2)Figure4*.3-4 AMENDMENT 96-02 JULY 1996 ,:iII**.IeIIII e*I*1 J r-II*1I e:***\II:II:*I lIII1:*e', Ie: I:.!;I::.:III1:II.IIII , eo I i i;e, ,: III!, I:**;I I.,II I., I*I i I I 1 I!, j I.I I I I: , ,:: 16 InA ASSD8LY ,::: I.I i I i.!;!: I II III I I rJf*: e.: I°°e I!*III.1 j I I i I'..0!i.iI, e;ff..'I.!I Ie,IIII I: I!i..;i..;I**e'l;.: I,I i:!it i ei cit I!I..I:III I Ie., I: '.: I ,.1:., Ie!.: I Ie i I I I ItII***1 lei*.i°e:.1 iif-II I I:*I I I!I1III I I I..InA ASSDeLY LEGEND: o FUEL ItOO[J GUIDE TUIE OR ItlSTRUlEMUTION YUlE=e: IFBA ROD-fsr434_2.m(336.jr14325)
JR14325@jd432S.FriJun2811:43:59EDT1996 32 1F8A ASSEMBLY'14 I FlA*ASSEWLT MOTE: ALL F'ICURES ARE TOP VIEW SOUTH CAROLINA ELECTRICGAS CO.VIRGIL C.SUMMER NUCLEAR STATION Integral Fuel Burnable Absorber Rod Arrongement Within on Assembly<Sheet 2 of 2)Figure4*.3-4 AMENDMENT 96-02 JULY 1996 II*IIMLKMa,*DC.t.I a***7*iii'**111 11 D'iii*....10..10 10*IS 10 10 10 10 10 10....10 10............................10 10....*101010 10 10 10*as 10..10....AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Typical Burnable Absorber Loading Pattern Figure 43*5 II*II M L KM a,*DC.t.I a***7*iii'**111 11 D'iii*....10..10 10*IS 10 10 10 10 10 10....10 10............................10 10....*10 10 10 10 10 10*as 10..10....AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Typical Burnable Absorber Loading Pattern Figure 43*5 I-1.031 1.2111 1.12'1.011 1.111 1.254 0**1.0.3'3-1.21.1.0521.2381.144 1.2'11.1811.057 0.3341.1211.232 1.138 1.281 1.171 1.232 0.801 1.011 1.1.3 1.210 1.181 1.252 1.014 G 1.111 1.21.1.1'731.2531.133 0**'7'1.254 1.1'71 1.238 1.01'7 0**'0 CALCULATED to*1.428 0.81'1.081 0.813 0**'0.313 0.331 I AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of life.Unrodded Core.Hot full Power.No Xenon (Transition Core)figure 4.3-6 I-1.031 1.2111 1.12'1.011 1.111 1.254 0**1.0.3'3-1.21.1.052 1.238 1.144 1.2'1 1.181 1.057 0.334 1.121 1.232 1.138 1.281 1.171 1.232 0.801 1.011 1.1.3 1.210 1.181 1.252 1.014 G 1.111 1.21.1.1'73 1.253 1.133 0**'7'1.254 1.1'71 1.238 1.01'7 0**'0 CALCULATED to*1.428 0.81'1.081 0.813 0**'0.313 0.331 I AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of life.Unrodded Core.Hot full Power.No Xenon (Transition Core)figure 4.3-6 I-1.031 1.227 1.133 LOll 1.1111 1.250 0.1" 0."00-1.227 1.OS1 1.2.3 1.1.1.211 1.1112 1.0411 0.3lIO 1.133 1.2410 1.1.3 1.213 1.1117 1.222 0.1112 1.011 1.141 1.212 1.1110 1.2.'1.011 0.31'1.1.1.212 1.181 1.2.1 1.1a 0.02 1.250 1.1" 1.22.1.013 0.413 CALQlLATID..1.413 0.1" 1.080 0**,1 0.311 0.*00 0.3" I AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Transition Core)Figure 4.3-7 I-1.031 1.227 1.133 LOll 1.1111 1.250 0.1" 0."00-1.227 1.OS1 1.2.3 1.1.1.211 1.1112 1.0411 0.3lIO 1.133 1.2410 1.1.3 1.213 1.1117 1.222 0.1112 1.011 1.141 1.212 1.1110 1.2.'1.011 0.31'1.1.1.212 1.181 1.2.1 1.1a 0.02 1.250 1.1" 1.22.1.013 0.413 CALQlLATID..1.413 0.1" 1.080 0**,1 0.311 0.*00 0.3" I AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Transition Core)Figure 4.3-7 I-1.037 1.227 1.130 1.081 1.11'1.241 0.*1.0.3131.227 100M 1.231 1.143 1.214 1.182 1.048 0.337 1.130 1.233 1.111 1.2.0 1.172 1.231 0.*,4 1.081 1.142 1.2'1 1.'8'1.2.1 1.021 0.311 1.'11 1.217'.174 1.280 1.13'0.417 1.241 1.1.'1.231 1.023 0.41'CALQlLAT!D r...*1.430 0.11.1.01'7 0.817 0.382 0.313 0.340 I AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of Life, Group D at HFP Insertion limit, Hot Full Power, Equilibrium Xenon (Transition Core)Figure 4.3-8 I-1.037 1.227 1.130 1.081 1.11'1.241 0.*1.0.3131.227 100M 1.231 1.143 1.214 1.182 1.048 0.337 1.130 1.233 1.111 1.2.0 1.172 1.231 0.*,4 1.081 1.142 1.2'1 1.'8'1.2.1 1.021 0.311 1.'11 1.217'.174 1.280 1.13'0.417 1.241 1.1.'1.231 1.023 0.41'CALQlLAT!D r...*1.430 0.11.1.01'7 0.817 0.382 0.313 0.340 I AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of Life, Group D at HFP Insertion limit, Hot Full Power, Equilibrium Xenon (Transition Core)Figure 4.3-8 I-1.041 1.213 1.103 1.047 1.131 1.231 0."1O*.ae r--1.253 l.OU 1.271 1.101 1.214 1.103 0.174 0.344 1.103 1.273 1.124 1.321 1.14'1.23.0**24 1.047 1.101 1.324 1.1111.3081.013 0.3" 1.1.1.211 1.141 1.308 1.110 0.117 1.2311.1081.231 1.01..0.11'CALCULATED to*1.3110*.,1 0.1'0 o.al 0.31'O.<iOII 0.347 I AMENDMENT6 AUGUST,1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Middle of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Transition Core)Figure 4.3-9 I-1.041 1.213 1.103 1.047 1.131 1.231 0."1O*.ae r--1.253 l.OU 1.271 1.101 1.214 1.103 0.174 0.344 1.103 1.273 1.124 1.321 1.14'1.23.0**24 1.047 1.101 1.324 1.111 1.308 1.013 0.3" 1.1.1.211 1.141 1.308 1.110 0.117 1.231 1.108 1.231 1.01..0.11'CALCULATED to*1.3110*.,1 0.1'0 o.al 0.31'O.<iOII 0.347 I AMENDMENT6 AUGUST,1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Middle of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Transition Core)Figure 4.3-9 I-1.(M1 1.212 1.017 1.03.1.11'1.230 0.'41 0.4"--.1.212 1.011 1.224 1.01.1.2....1.112 1.031 0.41'1.017 1.223 1.010 1.210 1.122 1.227 0**11 1.03'1.01.1.2411.1121.247 1.011 0.412 1.11'1.241 1.122 1.24'7 1.014 0.117 1.230 1.114 1.221 1.011 0.11'7 CALCULATED t.,.1.338 0.'41 1.031 0....0.4U[J AlSe-LV POWER..0.411 0.420 I AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near End of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Transition Core)Figure 4.3*10 I-1.(M1 1.212 1.017 1.03.1.11'1.230 0.'41 0.4"--.1.212 1.011 1.224 1.01.1.2....1.112 1.031 0.41'1.017 1.223 1.010 1.210 1.122 1.227 0**11 1.03'1.01.1.241 1.112 1.247 1.011 0.412 1.11'1.241 1.122 1.24'7 1.014 0.117 1.230 1.114 1.221 1.011 0.11'7 CALCULATED t.,.1.338 0.'41 1.031 0....0.4U[J AlSe-LV POWER..0.411 0.420 I AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near End of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Transition Core)Figure 4.3*10 0.811 1.131 1.019 1.293 1.196 1.384 0.855 0.304 1.131 BBBBBEJ 0.285 1.019 88BBB88B8B 0.318 1.I%BB8BB 1.384 888B 0.855 81 0.5610.3 17 1 CALCULATEDP""=15560.3040.282 soum CAROLINA ELEClRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of Life, Unrodded Core, Hot Full Power, No Xenon (Equilibrium Core)Figure 4.3-11 AMENDMENT 96-02 JULY 1996 0.811 1.131 1.019 1.293 1.196 1.384 0.855 0.304 1.131 BBBBBEJ 0.285 1.019 88BBB88B8B 0.318 1.I%BB8BB 1.384 888B 0.855 81 0.5610.3 17 1 CALCULATEDP""=15560.3040.282 soum CAROLINA ELEClRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of Life, Unrodded Core, Hot Full Power, No Xenon (Equilibrium Core)Figure 4.3-11 AMENDMENT 96-02 JULY 1996 0.837 1.155 1.034 1.296 1.191 1372 0315 1155 BBBBBB 0.293B8BBB 0570 1.296 BBBBB 0.324 1191BBBEJB L372BBBB 0.859 81 0567 11 0.3 23 1 CALCULATED F""=1530 0.315 0.291 SOum: CAROLINA ELEC1RlC&GAS CO.VIRGil..C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Equilibrium Core)Figure 4.3-12 AMENDMENT 96-02 JULY 1996 0.837 1.155 1.034 1.296 1.191 1372 0315 1155 BBBBBB 0.293B8BBB 0570 1.296 BBBBB 0.324 1191BBBEJB L372BBBB 0.859 81 0567 11 0.3 23 1 CALCULATED F""=1530 0.315 0.291 SOum: CAROLINA ELEC1RlC&GAS CO.VIRGil..C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Equilibrium Core)Figure 4.3-12 AMENDMENT 96-02 JULY 1996 0.837 1.157 1.0331.2981.1931.369 0.836 0.310 1.157 BBBBBB1033 BBBBB 0573 1298 BBBBB 0.327 1.193 BBBI 0.764 18 1.369BBB8 0.836 Ell 0570 II 0.3 27 1 CALCULAlED F AH=1.484 0.310 0.289 soum: CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of Life, Group D at HFP Insertion Limit, Hot Full Power, Equilibrium Xenon (Equilibrium Core)Figure 4.3-13 AMENDMENT 96-02 JULY 1996 0.837 1.157 1.0331.2981.1931.369 0.836 0.310 1.157 BBBBBB1033 BBBBB 0573 1298 BBBBB 0.327 1.193 BBBI 0.764 18 1.369BBB8 0.836 Ell 0570 II 0.3 27 1 CALCULAlED F AH=1.484 0.310 0.289 soum: CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Beginning of Life, Group D at HFP Insertion Limit, Hot Full Power, Equilibrium Xenon (Equilibrium Core)Figure 4.3-13 AMENDMENT 96-02 JULY 1996 0.933 1.288 1.087 1.355 1.149 1.326 0.843 0.346 1.288 BB8BBB 0.318 1.087 BBBB8 0580 1.355 888BB 0.341 U49BBBBEJ 1.326B8BB 0.843 BI 0.5790.341 I CALCULATlIDF",,=
1.439 0.346 0.316 soum CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Middle of llie, Unrodded Core, Hot Full Power, Equilibrium Xenon (Equilibrium Core)Figure 4.3-14 AMENDMENT 96-02 JULY 1996 0.933 1.288 1.087 1.355 1.149 1.326 0.843 0.346 1.288 BB8BBB 0.318 1.087 BBBB8 0580 1.355 888BB 0.341 U49BBBBEJ 1.326B8BB 0.843 BI 0.5790.341 I CALCULATlIDF",,=
1.439 0.346 0.316 soum CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near Middle of llie, Unrodded Core, Hot Full Power, Equilibrium Xenon (Equilibrium Core)Figure 4.3-14 AMENDMENT 96-02 JULY 1996 L 0.955 1.269 1.063 1.277 1.107 1.312 0.919 0.448 1.269 BBBBBB 0400 1.063 BBBBB 0.653 1.277 BBBBB 0.403 l.lWBBBBEJ 1.312BBBEJ 0.919 BI 0.652 1 0.403 1 CALCULATEDF",,=
1.373 0.448 0.400 SOurn: CAROLINA ELEC1RIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near End of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Equilibrium Core)Figure 4.3-15 AMENDMENT 96-02 JULY 1996 L 0.955 1.269 1.063 1.277 1.107 1.312 0.919 0.448 1.269 BBBBBB 0400 1.063 BBBBB 0.653 1.277 BBBBB 0.403 l.lWBBBBEJ 1.312BBBEJ 0.919 BI 0.652 1 0.403 1 CALCULATEDF",,=
1.373 0.448 0.400 SOurn: CAROLINA ELEC1RIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Power Density Distribution Near End of Life, Unrodded Core, Hot Full Power, Equilibrium Xenon (Equilibrium Core)Figure 4.3-15 AMENDMENT 96-02 JULY 1996 1.2.1 1.2410 l.i**I.HI 1.2'" ,.*, I.U'1**2 1.101 1**a I.U'1**'I.UI l.na 1.211 1.212 1.211.1.22'1.'" 1.200 t***t.21t t....'.lI..t.nl t.170 1.117'.210 t.11I t**'t.1OI 1.2tO t.'80 1.211'.2.'t.,.,.lt2 t.1I2 ,.4102'.11't....'**t t.llt ,.." t.lla 1.12.t.21.t.2"'.lMO t....t.1IO'**21'.aI t.lIt t.182t."t." t."1**17 t...t.'"'.2" I.HI I.'" 1." 1**2.t.I2'I.C'" 1.17.1." t.COI 1.'" 1.1n t....1."'.610 t..." 1.:an 1.2M ,.11IO t....1**t.t**2.t**21 I**" 1**" I.'" 1....t....1.171 l.al2 1.2'70 1.2" I.In 1.214 1.172 1...n 1**'1.1" 1**U 1.11't.lla I.C" 1.'" 1.102 I.COI l.na 1._1.2" 1.11'1.17'1.211 I.U'1.<<Ie 1._1." I.C" 1....1.1" t."22 1.102 t**'1.C02 1.111 1.112 t.27't.....1.171 1.111 ,...,, 1...t1....,..*,.C11 t.4102 1.11'1.120 I.HI 1."1 I.NT I.HI 1.DO l.co.-1.10<1 1.11I 1.ft2 t**, 1.IIC I.C20 1.100 1.280 I.COI 1.....1.110 1.2" l.n1 1.112 1.271 1.110 ,.*,1 1."" 1.101 I**" 1.110 ,....t**', 1....1._1....1.270 1.102 1.2" 1.121 ,..., 1."'" 1**,1 1.*>>'.CI2 t.cn l.cn t.CII t.NT 1.107 I.UI 1.211 1....1." 1.107 I.COI 1.M2 I.U2 1." t....1.17.I.C.l.nl t.....t.C12 I.H2 1.180 1.217 1.2M 1.....1.21" 1.2M I.M2 1.27..1....1**n l.cal 1.180 1._1.271 1.182 1.'" 1.1'1 1....1.172 ,....1.172'.110 t.1I2 l.co.-1."'.1" 1.20'1.2" 1."" 1.,lIl 1..., l.lMO 1.220 1.12'1.2171.117 1....1.121 t.1a I.HI 1.2111 1.101 t.20" 1.,.a 1.2" 1.111 1.t.I" 1.221 1.2.2 1.H4 I.Ha 1.21'1.2" 1.111 1.210 1.211 1.27'1.2..1.212 1.2.'t.112 AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Rodwise Power Distribution in a Typical Assembly (G-10)Near BOL, HFP, Equilibrium Xenon, Unrodded Core Figure 4.3-16 1.2.1 1.2410 l.i**I.HI 1.2'" ,.*, I.U'1**2 1.101 1**a I.U'1**'I.UI l.na 1.211 1.212 1.211.1.22'1.'" 1.200 t***t.21t t....'.lI..t.nl t.170 1.117'.210 t.11I t**'t.1OI 1.2tO t.'80 1.211'.2.'t.,.,.lt2 t.1I2 ,.4102'.11't....'**t t.llt ,.." t.lla 1.12.t.21.t.2"'.lMO t....t.1IO'**21'.aI t.lIt t.182 t." t." t."1**17 t...t.'"'.2" I.HI I.'" 1." 1**2.t.I2'I.C'" 1.17.1." t.COI 1.'" 1.1n t....1."'.610 t..." 1.:an 1.2M ,.11IO t....1**t.t**2.t**21 I**" 1**" I.'" 1....t....1.171 l.al2 1.2'70 1.2" I.In 1.214 1.172 1...n 1**'1.1" 1**U 1.11't.lla I.C" 1.'" 1.102 I.COI l.na 1._1.2" 1.11'1.17'1.211 I.U'1.<<Ie 1._1." I.C" 1....1.1" t."22 1.102 t**'1.C02 1.111 1.112 t.27't.....1.171 1.111 ,...,, 1...t 1....,..*,.C11 t.4102 1.11'1.120 I.HI 1."1 I.NT I.HI 1.DO l.co.-1.10<1 1.11I 1.ft2 t**, 1.IIC I.C20 1.100 1.280 I.COI 1.....1.110 1.2" l.n1 1.112 1.271 1.110 ,.*,1 1."" 1.101 I**" 1.110 ,....t**', 1....1._1....1.270 1.102 1.2" 1.121 ,..., 1."'" 1**,1 1.*>>'.CI2 t.cn l.cn t.CII t.NT 1.107 I.UI 1.211 1....1." 1.107 I.COI 1.M2 I.U2 1." t....1.17.I.C.l.nl t.....t.C12 I.H2 1.180 1.217 1.2M 1.....1.21" 1.2M I.M2 1.27..1....1**n l.cal 1.180 1._1.271 1.182 1.'" 1.1'1 1....1.172 ,....1.172'.110 t.1I2 l.co.-1."'.1" 1.20'1.2" 1."" 1.,lIl 1..., l.lMO 1.220 1.12'1.217 1.117 1....1.121 t.1a I.HI 1.2111 1.101 t.20" 1.,.a 1.2" 1.111 1.t.I" 1.221 1.2.2 1.H4 I.Ha 1.21'1.2" 1.111 1.210 1.211 1.27'1.2..1.212 1.2.'t.112 AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Rodwise Power Distribution in a Typical Assembly (G-10)Near BOL, HFP, Equilibrium Xenon, Unrodded Core Figure 4.3-16
.t.ta..'1.'1.t.tM'1.'1.2 t.tI.'1.'1"'1.'110'I.'"'1.'1" t.'" 1.'10 t.'111 1.tH 1.tn 1.'111 1.tl1'1.1.'1.111 t.1'" t..., 1.tl1 t.U" t.JII 1.IM'1.112 1.1_1.21'1.1.1.111'1.'1.'1.'1"'1.'1.0 1.,n 1.'.t.n.1.'110 t.a**t.HI'I.....'I.....t.HI t.HI t.an 1." t.JOoI 1.'1"'1.'110'1.'1" 1.'1" 1.'.I."'I." t.nl 1.n.t.n.1.an t.Jl2 1."'I." 1.IU 1.1M.1.'In'I.'.t.U1 t.1a 1.11I'I." t.1n t.1SI 1....1."'I." 1.....'1.101'1.'11 1.101 t.1eO 1.1.I.'" 1.'1" 1.Ut1'I....t.1eO'1**2'I.*'t.IM t.1SI t.1Ot'1.101'1.1110 t.'.I.'" t.U'1." t.no'I." 1***1.HI'1**'1 t**'1**'1.170'1.100 t.HI 1.UI 1.1'1 1.1S2 t.'M t.ta 1.U't.:an'.nl t.J"'1.111 t**H t."'1.1'0'I."'1.100 t**1.111.211 1.U'1.'.'t.tH t.Ut t.HI 1.n.t**2'I." 1.100 t.IO'1.IM 1.11I'1.1"'1.101'1.'1'" 1.tn 1.a.1'1**1 1.n.t.IU t.aH 1.114'I."'I."'I."'1.100 t**1.11I t.nl t.JU t.t**.t.tl2 1.Jt.'I.*"'1.1412'I.**1.1" 1**"'1.1" t**'t....1.21.t.1OO 1.211'1**10 t.211 1.1"'1.'1.1.'112 t**,0'1.1'2'1.110 1**'t.all t.1IM'I.'" 1.eo.t.1Ot'1.112 t.101 t.'.1.100 t.....t.no 1.all t**1 1.no 1.an 1....1....t.HI'1.10'1 1.111 1.1Oa'I.*'t**" t:'10'1.'20 1.tlt t.220'.171 t.2n'I....t." t.n.'.n.'1**'1 t**1.100 1.211'1.101'1.'1"'1.'102 1.'.'t.tn'1.112'1.1.'t.8a'1.:11I 1.HI 1.HI 1.an 1.110'1.101 t.102'1.1" t.on'1.'111'1.'1**'1.'1" 1.101'1.1'1't.Ut'1.102 t.UI'1.1'10 t.a.'1.111'1.'1"'I.'.'I.'.'t.ttaO 1.011'1.01'1 1.'101'1.'121 t.'" t.tlt t.,n'1.'1" t.'" t.,n t.tlO t.,.,'I.I.'" t.'10 1.'" t.tI.AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Rodwise Power Distribution in a Typical Assembly (G-10)Near EOL, HFP., Equilibrium Xenon, Unrodded Core Figure 4.3-17.t.ta..'1.'1.t.tM'1.'1.2 t.tI.'1.'1"'1.'110'I.'"'1.'1" t.'" 1.'10 t.'111 1.tH 1.tn 1.'111 1.tl1'1.1.'1.111 t.1'" t..., 1.tl1 t.U" t.JII 1.IM'1.112 1.1_1.21'1.1.1.111'1.'1.'1.'1"'1.'1.0 1.,n 1.'.t.n.1.'110 t.a**t.HI'I.....'I.....t.HI t.HI t.an 1." t.JOoI 1.'1"'1.'110'1.'1" 1.'1" 1.'.I."'I." t.nl 1.n.t.n.1.an t.Jl2 1."'I." 1.IU 1.1M.1.'In'I.'.t.U1 t.1a 1.11I'I." t.1n t.1SI 1....1."'I." 1.....'1.101'1.'11 1.101 t.1eO 1.1.I.'" 1.'1" 1.Ut1'I....t.1eO'1**2'I.*'t.IM t.1SI t.1Ot'1.101'1.1110 t.'.I.'" t.U'1." t.no'I." 1***1.HI'1**'1 t**'1**'1.170'1.100 t.HI 1.UI 1.1'1 1.1S2 t.'M t.ta 1.U't.:an'.nl t.J"'1.111 t**H t."'1.1'0'I."'1.100 t**1.111.211 1.U'1.'.'t.tH t.Ut t.HI 1.n.t**2'I." 1.100 t.IO'1.IM 1.11I'1.1"'1.101'1.'1'" 1.tn 1.a.1'1**1 1.n.t.IU t.aH 1.114'I."'I."'I."'1.100 t**1.11I t.nl t.JU t.t**.t.tl2 1.Jt.'I.*"'1.1412'I.**1.1" 1**"'1.1" t**'t....1.21.t.1OO 1.211'1**10 t.211 1.1"'1.'1.1.'112 t**,0'1.1'2'1.110 1**'t.all t.1IM'I.'" 1.eo.t.1Ot'1.112 t.101 t.'.1.100 t.....t.no 1.all t**1 1.no 1.an 1....1....t.HI'1.10'1 1.111 1.1Oa'I.*'t**" t:'10'1.'20 1.tlt t.220'.171 t.2n'I....t." t.n.'.n.'1**'1 t**1.100 1.211'1.101'1.'1"'1.'102 1.'.'t.tn'1.112'1.1.'t.8a'1.:11I 1.HI 1.HI 1.an 1.110'1.101 t.102'1.1" t.on'1.'111'1.'1**'1.'1" 1.101'1.1'1't.Ut'1.102 t.UI'1.1'10 t.a.'1.111'1.'1"'I.'.'I.'.'t.ttaO 1.011'1.01'1 1.'101'1.'121 t.'" t.tlt t.,n'1.'1" t.'" t.,n t.tlO t.,.,'I.I.'" t.'10 1.'" t.tI.AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Rodwise Power Distribution in a Typical Assembly (G-10)Near EOL, HFP., Equilibrium Xenon, Unrodded Core Figure 4.3-17 1.50 TRANSIEO\J AO=4.66 US, I E Cl.70..J I Q.lSO 0.25 100 90 80 70 dO so o
'0 20 30 40 PERCE"'T Of ACTIVC CORE HEIGHT FROM BOTTOM SOUTH CAROLINA ELECTRICGAS CO.VIRGIL C.SUMMER NUCLEAR STATION Typicol Axiol Power Shopes Occurring ot Beginning of Life Figure 4.3-18 AMENDMENT 96-02 JULY 1996 isar431Sm(360.jr1432S)JRl432S@ir14325.WodJul311:03:1SEDT1996 1.50 TRANSIEO\J AO=4.66 US, I E Cl.70..J I Q.lSO 0.25 100 90 80 70 dO so o
'0 20 30 40 PERCE"'T Of ACTIVC CORE HEIGHT FROM BOTTOM SOUTH CAROLINA ELECTRICGAS CO.VIRGIL C.SUMMER NUCLEAR STATION Typicol Axiol Power Shopes Occurring ot Beginning of Life Figure 4.3-18 AMENDMENT 96-02 JULY 1996 isar431Sm(360.jr1432S)JRl432S@ir14325.WodJul311:03:1SEDT1996 1.50-y---------
__1.25 1 VANTAGE5/VANTAGE+./AO=-4.11fD.7S;:j I O.so 0.25 100 90 80 70 ISO&0 40 30 10 o-1.-----"""1-----------------------.....1
.20 f>£RCENT OF ACTIVE CORE H£IGHT FROM BO'TTOM SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Typicol Axiol Power Shopes Occurring ot Middle of Life Figure 4.3-19 AMENDMENT 96-02 JULY 1996 fsar.4319.m(361Jr14325)
JR14325@jrl432S.
WedJul311:06:12 EDT 19%1.50-y---------
__1.25 1 VANTAGE5/VANTAGE+./AO=-4.11fD.7S;:j I O.so 0.25 100 90 80 70 ISO&0 40 30 10 o-1.-----"""1-----------------------.....1
.20 f>£RCENT OF ACTIVE CORE H£IGHT FROM BO'TTOM SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Typicol Axiol Power Shopes Occurring ot Middle of Life Figure 4.3-19 AMENDMENT 96-02 JULY 1996 fsar.4319.m(361Jr14325)
JR14325@jrl432S.
WedJul311:06:12 EDT 19%
1..25 0..25 1.,"'....tttOl"l/'I&0--3.61 f E 0.76 i I cue 100 90 70 eo 150 30 20 10 o o__"""__-""I__...J 80 PERCENT OF ACifVE CORE HEIGHT FROM BOTTOW: SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Typical Axial Power Shapes Occurring at End of Life Figure 4.3*20 AMENDMENT 96-02 JULY 1996 r..,.3211.0l(358.jd4325)
JR14325@jd4325.
WedJul310,;'<,09 EDT 1996 1..25 0..25 1.,"'....tttOl"l/'I&0--3.61 f E 0.76 i I cue 100 90 70 eo 150 30 20 10 o o__"""__-""I__...J 80 PERCENT OF ACifVE CORE HEIGHT FROM BOTTOW: SOUTH CAROLINA ELECTRIC 8<GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Typical Axial Power Shapes Occurring at End of Life Figure 4.3*20 AMENDMENT 96-02 JULY 1996 r..,.3211.0l(358.jd4325)
JR14325@jd4325.
WedJul310,;'<,09 EDT 1996 FREQUENCY OF GAPS PER ROD-F 9 AXIAL FREQUENCY DISTRIBUTION OF GAPS-F.)SIZE FREQUENCY DISTRIBUTION OF GAPS-F k SPIKE DUE TO SINGLE GAPS-S g\1-----1--------
7DRAW COMPUTER Y CODE MTG FROM DENSIFICATION MODEL (MAX.GAP SIZE AT GIVEN HEIGHT)MODE I PROBABILITIES OF EXCEEDING GIVEN SPIKE SIZE FOR EACH AXIAL LOCATION CONVOLUTION POWER SP IKE FACTOR-S(Z)MODE 2EXPECTED VALUES SEEN BY INCORE DETECTOR ROD CENSUS AMENDMENT6 AUGUST.1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGILC.SUMMER NUCLEAR STATION Flowchart for Determining Spike Model Figure 4.3-22 FREQUENCY OF GAPS PER ROD-F 9 AXIAL FREQUENCY DISTRIBUTION OF GAPS-F.)SIZE FREQUENCY DISTRIBUTION OF GAPS-F k SPIKE DUE TO SINGLE GAPS-S g\1-----1--------
7DRAW COMPUTER Y CODE MTG FROM DENSIFICATION MODEL (MAX.GAP SIZE AT GIVEN HEIGHT)MODE I PROBABILITIES OF EXCEEDING GIVEN SPIKE SIZE FOR EACH AXIAL LOCATION CONVOLUTION POWER SP IKE FACTOR-S(Z)MODE 2EXPECTED VALUES SEEN BY INCORE DETECTOR ROD CENSUS AMENDMENT6 AUGUST.1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGILC.SUMMER NUCLEAR STATION Flowchart for Determining Spike Model Figure 4.3-22 12.0 10.0 CI-8.0<[<.::l UJ....J c.::l z: en 0 f-UJ 6.0:=>0 UJ::w:: CI-V)f-z: UJ u 1t.0 a:::: UJ CI-2.0 o o 1.0 2.0 GAP SIZE (INCHES)3,0 ILO AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Predicted Power Spike Due to Single Non-Flattened Gap in the Adjacent Fuel Figure 4.3-23 12.0 10.0 CI-8.0<[<.::l UJ....J c.::l z: en 0 f-UJ 6.0:=>0 UJ::w:: CI-V)f-z: UJ u 1t.0 a:::: UJ CI-2.0 o o 1.0 2.0 GAP SIZE (INCHES)3,0 ILO AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Predicted Power Spike Due to Single Non-Flattened Gap in the Adjacent Fuel Figure 4.3-23 0 U"l:::r=t-O>">-I-(I)0 z: UJ N 0 u cr:: I-UJ::::E: 0 UJ 8-c;l_en....l UJ"":1:::z: l-t.)z: z: z:00 f-en 0 Q.....J<<0><1.0<<SOUTH CAROLINA ElECTRiC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION N o (z)s o 8 o N o AMENDMENT6 AUGUST, 1990 Power Spike Factor as a Function of Axial Position Figure 4.3-240 U"l:::r=t-O>">-I-(I)0 z: UJ N 0 u cr:: I-UJ::::E: 0 UJ 8-c;l_en....l UJ"":1:::z: l-t.)z: z: z:00 f-en 0 Q.....J<<0><1.0<<SOUTH CAROLINA ElECTRiC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION N o (z)s o 8 o N o AMENDMENT6 AUGUST, 1990 Power Spike Factor as a Function of Axial Position Figure 4.3-24 I i t o I*COAl HIJGHT.."*to 12 AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Maximum FQ x Power Versus Axial Height During Normal Operation Figure 4.3-25 I i t o I*COAl HIJGHT.."*to 12 AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Maximum FQ x Power Versus Axial Height During Normal Operation Figure 4.3-25 25r-----r-----r-----r------
20 t-----+------I------I------I 0-o 0...-)D 15...-I 0 l!t 0 i I W 10-.-I t-30 o AXIAL FLUX DIFFERENCE (I)30 AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Peak Power Ouring Control Rod Malfunction Overpower Transients Figure 4.3-26 25r-----r-----r-----r------
20 t-----+------I------I------I 0-o 0...-)D 15...-I 0 l!t 0 i I W 10-.-I t-30 o AXIAL FLUX DIFFERENCE (I)30 AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Peak Power Ouring Control Rod Malfunction Overpower Transients Figure 4.3-26 25.----.---------,.----..,.------...
...30 o AXIAL flUX DlmRENCE (I)30 60 AMENDMENT6 AUGUST.1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Peak Power During Boration/Dilution Overpower Transients Figure 4.3-2]25.----.---------,.----..,.------...
...30 o AXIAL flUX DlmRENCE (I)30 60 AMENDMENT6 AUGUST.1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Peak Power During Boration/Dilution Overpower Transients Figure 4.3-2]
0.759 0.792 4.3/1.217 1.224 0.67 0.774 1.255 0.800 1.249 3.41-0.5)1.229 1.229 1.225 I.2-0.37-0.9 1.109 L 077 I.107 1.092-0.2'/I*tt'1c, 1.202 1.223 I.1.256-2.7", 2.7'1: 0.523 1.217 1.221 1.217 0.548 1.203 1.233 1.210 4.6%I.I X 1.01-0.6'1 1.229 1.229 I.189 I.-3.3%-0.70 1.217CALCULATED 1.21 IMEASURED-0.5%DIFFERENCE
- 2.07 LOCATED AT M-8 SOUTH AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Comparison Between Calculated and Measured Relative Fuel Assembly Power Distribution Figure 4.3-28 0.759 0.792 4.3/1.217 1.224 0.67 0.774 1.255 0.800 1.249 3.41-0.5)1.229 1.229 1.225 I.2-0.37-0.9 1.109 L 077 I.107 1.092-0.2'/I*tt'1c, 1.202 1.223 I.1.256-2.7", 2.7'1: 0.523 1.217 1.221 1.217 0.548 1.203 1.233 1.210 4.6%I.I X 1.01-0.6'1 1.229 1.229 I.189 I.-3.3%-0.70 1.217CALCULATED 1.21 IMEASURED-0.5%DIFFERENCE
- 2.07 LOCATED AT M-8 SOUTH AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Comparison Between Calculated and Measured Relative Fuel Assembly Power Distribution Figure 4.3-28 o N o 8 Q..0 I-0 lJ.J I-0:: 0 lJ.J (/)0>z: z>00 z: f'-1;'Z lJ.J l.C)x l-N oCt 0 0 0 z: 0:: lJ.J"'" 00....J:3t z:00 oCt CO CL CO 0 ,.....a..oCt::::E lJ.J (.!)lJ.J<l: 0:: 0 0:: 0 lJ.J 0 I-lJ.J U I-c.o:::t::>-z:<l: Cl<l:-1>'Z....J N=:;,1>'Z u.J lJ.J::::E u M 0:: 0"....":r::: 0 0:: 0<l: 0 U w..<l: U<u.J Q:: 0 0 LO U u...0 I-z: u.J 0 U Q:::::r u.J 0..
lVIXV AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Comparison of Calculated and Measured Axial Shape Figure 4.3-29 o N o 8 Q..0 I-0 lJ.J I-0:: 0 lJ.J (/)0>z: z>0 0 z: f'-1;'Z lJ.J l.C)x l-N oCt 0 0 0 z: 0:: lJ.J"'" 00....J:3t z: 0 0 oCt CO CL CO 0 ,.....a..oCt::::E lJ.J (.!)lJ.J<l: 0:: 0 0:: 0 lJ.J 0 I-lJ.J U I-c.o:::t::>-z:<l: Cl<l:-1>'Z....J N=:;,1>'Z u.J lJ.J::::E u M 0:: 0"....":r::: 0 0:: 0<l: 0 U w..<l: U<u.J Q:: 0 0 LO U u...0 I-z: u.J 0 U Q:::::r u.J 0..
lVIXV AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Comparison of Calculated and Measured Axial Shape Figure 4.3-29 o o*o**o x REACTORI0 REACTOR\l REACTOR2*REACTOR 5*REACTOR 3 F Q 3.0 2.5*ii*x*o*o*2.0 8.xO.,.x 0**Q: o 9**x 1.5***o 00-50-ij5-40-35-30-25-20-15-10-505 10 152025 30 INCORE AXIAL OFFSET (%)AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Measured Values of FQ for Full Power Rod Configurations Figure 4.3-30 o o*o**o x REACTORI0 REACTOR\l REACTOR2*REACTOR 5*REACTOR 3 F Q 3.0 2.5*ii*x*o*o*2.0 8.xO.,.x 0**Q: o 9**x 1.5***o 00-50-ij5-40-35-30-25-20-15-10-505 10 152025 30 INCORE AXIAL OFFSET (%)AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Measured Values of FQ for Full Power Rod Configurations Figure 4.3-30
-1..,..-----------------------.
-1.2 It!-1A I EOL-1.'80L I-1.1-2 i-2.2-2.A-2.'+-..,..-..,..-.,...-...,--.,...-.,.--..,..-.,....-,....-,....----'
100 100 700 100 100'1000 1100 120013001400 1500 ,.00 IFFICTIVI PUIE1.TEMPERATURE Teff<<F)AMENDMENT 6 AUGUST, 1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Doppler Temperature Coefficient at BOl and EOl Versus T eft for a Typical Reload Core Figure 4.3-31-1..,..-----------------------.
-1.2 It!-1A I EOL-1.'80L I-1.1-2 i-2.2-2.A-2.'+-..,..-..,..-.,...-...,--.,...-.,.--..,..-.,....-,....-,....----'
100 100 700 100 100'1000 1100 1200 1300 1400 1500 ,.00 IFFICTIVI PUIE1.TEMPERATURE Teff<<F)AMENDMENT 6 AUGUST, 1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Doppler Temperature Coefficient at BOl and EOl Versus T eft for a Typical Reload Core Figure 4.3-31
-
100 10 10 20 o...,..-----------------------. t------,----,...---"'T"---...,..-----I I-.EOL i BOL I-to I i i-'2 POWER LEVEL o.RCENT OF FULL POWER)AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Doppler Only Power Coefficient Versus Power Level at SOL and EOL for a Typical Reload Core Figure 4.3 100 10 10 20 o...,..-----------------------. t------,----,...---"'T"---...,..-----I I-.EOL i BOL I-to I i i-'2 POWER LEVEL o.RCENT OF FULL POWER)AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Doppler Only Power Coefficient Versus Power Level at SOL and EOL for a Typical Reload Core Figure 4.3-32 O-.t'-------------------.-.
I I-..00 I i i-100 EOL BOL-1200-t-----r----..,..-----.----.,...----f o 20.-0 10 10 POWER LEVEL CPERCENT OF FULL POWER)100 AMENDMENTS AUGUST.1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Doppler Only Power Defect Versus Percent Power SOL and EOl for a Typical Reload Core Figure 4.3-33 O-.t'-------------------.-.
I I-..00 I i i-100 EOL BOL-1200-t-----r----..,..-----.----.,...----f o 20.-0 10 10 POWER LEVEL CPERCENT OF FULL POWER)100 AMENDMENTS AUGUST.1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Doppler Only Power Defect Versus Percent Power SOL and EOl for a Typical Reload Core Figure 4.3-33 10,.....--...,..----,----,..-----..,..---..,....---
5-i-...:lit loll-&oJ-I::0&oJ 000 PPU J 1700 PPM c i 1400 PPU!1100 PPM-5-10 IIlURATOR ttlF£RATlII: (or)AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Moderator Temperature Coefficient BOl, No Rods, for a Typical Reload Core Figure 4.3-34 10,.....--...,..----,----,..-----..,..---..,....---
5-i-...:lit loll-&oJ-I::0&oJ 000 PPU J 1700 PPM c i 1400 PPU!1100 PPM-5-10 IIlURATOR ttlF£RATlII: (or)AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Moderator Temperature Coefficient BOl, No Rods, for a Typical Reload Core Figure 4.3-34 5 0..........
..I-............1\....5""""""\1\:500 PPM , ,0 PPM , ," ,""""-20-25 o 100 200 JOO 400 IIIlERA TOIl 1'tIFtRA ME (or)500 600 AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C SUMMER NUCLEAR STATION Moderator Temperature Coefficient EOl for a Typical Reload Core Figure 4.3-35 5 0..........
..I-............1\....5""""""\1\:500 PPM , ,0 PPM , ," ,""""-20-25 o 100 200 JOO 400 IIIlERA TOIl 1'tIFtRA ME (or)500 600 AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C SUMMER NUCLEAR STATION Moderator Temperature Coefficient EOl for a Typical Reload Core Figure 4.3-35
- --,---...,.--....,r----.....---...,..---
AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C SUMMER NUClEAR STATION Moderator Temperature Coefficient as a Function of Boron Concentration BOl, No Rods, for a Typical Reload Core Figure 4.3-36**--,---...,.--....,r----.....---...,..---
AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C SUMMER NUClEAR STATION Moderator Temperature Coefficient as a Function of Boron Concentration BOl, No Rods, for a Typical Reload Core Figure 4.3-36 0...,..-----------------------_
li:-10 I 5/VA;'1TAGE+
Co,)!-20 , ,..'" C.', Ic: I-30-40
()3000 6000 9000 12000 1S000 1BOOO f=4337.m(362.jr14325)JRl4325@jrl4325.WedJul311,w,JSEDTI996 C'fC'J BURN'JP CMWO!MTUl SOUTH CAROLINA ELECTRIC S.GAS CO.VIRGIL C.SUMMER NUCLEAR ST AllaN Hot F'ullPower Temperature Coefficient at Critical Boron Concentration versus Burnup F'igure 4.3-37 AMENDMENT 96-02 JULY 1996 0...,..-----------------------_
li:-10 I 5/VA;'1TAGE+
Co,)!-20 , ,..'" C.', Ic: I-30-40
()3000 6000 9000 12000 1S000 1BOOO f=4337.m(362.jr14325)JRl4325@jrl4325.WedJul311,w,JSEDTI996 C'fC'J BURN'JP CMWO!MTUl SOUTH CAROLINA ELECTRIC S.GAS CO.VIRGIL C.SUMMER NUCLEAR ST AllaN Hot F'ullPower Temperature Coefficient at Critical Boron Concentration versus Burnup F'igure 4.3-37 AMENDMENT 96-02 JULY 1996
-10.,---------------------..
__"",..------------"""1 BOl-tIS I I-20 I..21 I EOl-30!e-31 o 20 10 10 100 POWER LEVEL PERCENT OF FULL POWER)*AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGllC.SUMMER NUCLEAR STATION Total Power Coefficient Versus Percent Power for BOl and EOl on a Typical Reload Core Figure 4.3-38-10.,---------------------..
__"",..------------"""1 BOl-tIS I I-20 I..21 I EOl-30!e-31 o 20 10 10 100 POWER LEVEL PERCENT OF FULL POWER)*AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGllC.SUMMER NUCLEAR STATION Total Power Coefficient Versus Percent Power for BOl and EOl on a Typical Reload Core Figure 4.3-38
-100 I-1000 I SOL I-'100-2000-2100 EOL-3000-t-----.,...----...----_
.....--_------..
o 20*eo 10 POWER LIVEl..(PERCENT OF FULL POWER)100 AMENDMENT 6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Total Power Defect BOl, EOl, for a Typical Reload Core Figure 4.3-39
-100 I-1000 I SOL I-'100-2000-2100 EOL-3000-t-----.,...----...----_
.....--_------..
o 20*eo 10 POWER LIVEl..(PERCENT OF FULL POWER)100 AMENDMENT 6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Total Power Defect BOl, EOl, for a Typical Reload Core Figure 4.3-39 23456789 10 II 12 13 14 15 270 0'"/"'"\"\....A...J r-....:..;18/,"\/B'"\/, ,B...I c-...J'-.../MV"""\(0G)/'\/'"\/" 0'-...J/,/,/\/'"\,D...I ,-C..,J\..c..J\..0...1V"""\I(B).C0/'"\/",/'"\'-.A...J0"A...J A---..-..,;;...l iCc)/",/",/, ,B...I\.B...I'-c./&"---'o.:...l V'"\/"'"\r--....A..,J
\....0..J A B C D E F G J K L M N p R FUNCTION CONTROL BANK D CONTROL BANK C CONTROL BANK B CONTROL BANK A SHUTDOWN BANK S6 SHUTDOWN BANK SA NUMBER OF CLUSTERS 8 8 8 8 8 8 AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Rod Cluster Control Assembly Pattern Figure 4.3*40 23456789 10 II 12 13 14 15 270 0'"/"'"\"\....A...J r-....:..;18/,"\/B'"\/, ,B...I c-...J'-.../MV"""\(0G)/'\/'"\/" 0'-...J/,/,/\/'"\,D...I ,-C..,J\..c..J\..0...1V"""\I(B).C0/'"\/",/'"\'-.A...J0"A...J A---..-..,;;...l iCc)/",/",/, ,B...I\.B...I'-c./&"---'o.:...l V'"\/"'"\r--....A..,J
\....0..J A B C D E F G J K L M N p R FUNCTION CONTROL BANK D CONTROL BANK C CONTROL BANK B CONTROL BANK A SHUTDOWN BANK S6 SHUTDOWN BANK SA NUMBER OF CLUSTERS 8 8 8 8 8 8 AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Rod Cluster Control Assembly Pattern Figure 4.3*40 I I i 8 II: 20 10 o-rc.......---r-----,r-----.,..
......--..,....-...l..---I o 10 tOO tlO 200 210 STEPS wrTHDRAWN AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Accidental Simultaneous Withdrawal of Two Control Banks EOL, HZP Banks D and B Moving in the Same Plane Figure 4.3-41 I I i 8 II: 20 10 o-rc.......---r-----,r-----.,..
......--..,....-...l..---I o 10 tOO tlO 200 210 STEPS wrTHDRAWN AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Accidental Simultaneous Withdrawal of Two Control Banks EOL, HZP Banks D and B Moving in the Same Plane Figure 4.3-41 U I U u I i 1.1 I Iu I I u I I 1.4 I I u I I JaSKIlt1r LZ I L1 I I.U U U U U!'H JIR:II.,QSE raax:s)AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Rod Position Versus Time on Reactor Trip Figure 4.3-42 U I U u I i 1.1 I Iu I I u I I 1.4 I I u I I JaSKIlt1r LZ I L1 I I.U U U U U!'H JIR:II.,QSE raax:s)AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Rod Position Versus Time on Reactor Trip Figure 4.3-42 1J u u 1.4 L2 u u.,....----------------_
u 1.7 u u 102 U 1.1 I I I AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Normalized RCCA Reactivity Worth Versus Percent Insertion Figure 4.3-43 1J u u 1.4 L2 u u.,....----------------_
u 1.7 u u 102 U 1.1 I I I AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STATION Normalized RCCA Reactivity Worth Versus Percent Insertion Figure 4.3-43
,:/-'I ACCEPTABLE,.'/" , 1..1'"..I'".I II'I"..I'" 1/NOT ACCEPTABLE I IT II I./II I V 1./1..1'" 5 45 40 35 30 25 20 15 10-:::>:?E Ci 3: (!J-a.:::>z a::::>en w (!J a:<<:::r: ()en o--'enw en en<<o 2.0 2.5 3.0 3.5 4.0 4.5 5.0 MAXIMUM NOMINAL U-235 ENRICHMENT (WIG)Notes 1.Fuel assemblies with enrichments less than 2.0 W/O must meet the burn-up requirements of 2.0 W/O assemblies.
2.Use of the following polynomial fit is acceptable where E=Enrichment W/O: Assembly Discharge burmlp=0.1246 E 3-1.91 E 2+20.9205 E-30.2482 RN 03-017 December 2003 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Required Fuel Assembly Burn-up as a Function of Initial Enrichment to permit Storage in Region 2 Racks Figure 4.3-44 ,:/-'I ACCEPTABLE,.'/" , 1..1'"..I'".I II'I"..I'" 1/NOT ACCEPTABLE I IT II I./II I V 1./1..1'" 5 45 40 35 30 25 20 15 10-:::>:?E Ci 3: (!J-a.:::>z a::::>en w (!J a:<<:::r: ()en o--'enw en en<<o 2.0 2.5 3.0 3.5 4.0 4.5 5.0 MAXIMUM NOMINAL U-235 ENRICHMENT (WIG)Notes 1.Fuel assemblies with enrichments less than 2.0 W/O must meet the burn-up requirements of 2.0 W/O assemblies.
2.Use of the following polynomial fit is acceptable where E=Enrichment W/O: Assembly Discharge burmlp=0.1246 E 3-1.91 E 2+20.9205 E-30.2482 RN 03-017 December 2003 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Required Fuel Assembly Burn-up as a Function of Initial Enrichment to permit Storage in Region 2 Racks Figure 4.3-44
Figure 4.3-45 Deleted per RN 03-017, December 2003 RN 03-017 AMENDMENT6 AUGUST, 1990 o 00 N o ('t)I-:::t-00 00,I>-'I--::>-'0-::x::: CO_<<I-U)X L.lJ o:z:_0-;;;-00:::::>a::: 0 L.lJ::x::: Q..-L.lJ0:::::>u o lVIXV SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Axial Offset Versus Time PWR Core with a 12-ft.Height and 121 Assemblies Figure 4.3-46 AMENDMENT6 AUGUST, 1990 o 00 N o ('t)I-:::t-00 00,I>-'I--::>-'0-::x::: CO_<<I-U)X L.lJ o:z:_0-;;;-00:::::>a::: 0 L.lJ::x::: Q..-L.lJ0:::::>u o lVIXV SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Axial Offset Versus Time PWR Core with a 12-ft.Height and 121 Assemblies Figure 4.3-46
- t-(,0I 0 W (,0 U , U 0
- : 1.0 ,!.O;N:!.O J', a::.fJj;;:t-::t:;.N;;:t-I:::t" UJ:z:<.DU U"'-..Cl:: 00!.L.0 0 , 1.0" ('t")...J x\.,<31: w<<=>N Cl:::z: ('t")0->-t-OO 3:...J N-Cl:: co UJ<>:;;:t-l-t-;)N u..en<enCl:::::::>0::I:..-" (,0.,...." N<00******;;:t-***0 0 00 (,0;;:t-N 0 N::::I"\0 00 0 N::::I" (,0---I I I I I%(n
-l 1111 INVMaVnO AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION XV Xenon Test Thermocouple Response Quadrant Tilt Difference Versus Time Figure 4.3-47;;:t-(,0I 0 W (,0 U , U 0::: 1.0 ,!.O;N:!.O J', a::.fJj;;:t-::t:;.N;;:t-I:::t" UJ:z:<.DU U"'-..Cl:: 00!.L.0 0 , 1.0" ('t")...J x\.,<31: w<<=>N Cl:::z: ('t")0->-t-OO 3:...J N-Cl:: co UJ<>:;;:t-l-t-;)N u..en<enCl:::::::>0::I:..-" (,0.,...." N<00******;;:t-***0 0 00 (,0;;:t-N 0 N::::I"\0 00 0 N::::I" (,0---I I I I I%(n
-l 1111 INVMaVnO AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION XV Xenon Test Thermocouple Response Quadrant Tilt Difference Versus Time Figure 4.3-47 (wJd)
M31ddOa lVM831NI000000 0 0000 0 000 0 0000:::t N 0 00 (J:):::t N 00000NNN-----00 (J:):::t N 0Iiiiii I I i IIi 0 0 o C1>o 00 0 a::: I.LJ (J:)0---'....J z:::>a 0I-!.C'l<<0 en z I-w:z: a..a:z::::::-, I.Ll a I-(.)u<I: 0 a::: en:::r I.LJ::.:::z: 0-:f w z a..I-a ex:>::::: z-0 w I-...J U:::::<I: a-....J IX:z: IX=::>0 I-a w u:z: IX a.....J ('t)a a x<<:(u ex:>w u 0<J 0 N o o(d%/wJd)1M3 1 J I M31ddOa o o (J:)I o o L{')I o o:::r I o o ('t)I o o N I o o-I o AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Calculated and Measured Doppler Defect and Coefficients at BOL, Two-Loop Plant, 121 Assemblies, 12-ft.Core Figure 4.3-48 (wJd)
M31ddOa lVM831NI 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0:::t N 0 00 (J:):::t N 0 0 0 0 0 N N N-----00 (J:):::t N 0Iiiiii I I i IIi 0 0 o C1>o 00 0 a::: I.LJ (J:)0---'....J z:::>a 0I-!.C'l<<0 en z I-w:z: a..a:z::::::-, I.Ll a I-(.)u<I: 0 a::: en:::r I.LJ::.:::z: 0-:f w z a..I-a ex:>::::: z-0 w I-...J U:::::<I: a-....J IX:z: IX=::>0 I-a w u:z: IX a.....J ('t)a a x<<:(u ex:>w u 0<J 0 N o o(d%/wJd)1M3 1 J I M31ddOa o o (J:)I o o L{')I o o:::r I o o ('t)I o o N I o o-I o AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Calculated and Measured Doppler Defect and Coefficients at BOL, Two-Loop Plant, 121 Assemblies, 12-ft.Core Figure 4.3-48 8:::r 8 0 00 0 0 0 to 0 0
0:::r 0 0 0 N 0:::;:)0 Q..:::;:)8 z: CII::: 00:::;:)QQ 0 0 0 to 0 8:::r 8 0 N 0 0 AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGllC SUMMER NUCLEAR STATION Comparison of Calculated and Measured Boron Concentration for Two-loop Plant, 121 Assemblies, 12-ft.Core Figure 4.3-49 8:::r 8 0 00 0 0 0 to 0 0
0:::r 0 0 0 N 0:::;:)0 Q..:::;:)8 z: CII::: 00:::;:)QQ 0 0 0 to 0 8:::r 8 0 N 0 0 AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGllC SUMMER NUCLEAR STATION Comparison of Calculated and Measured Boron Concentration for Two-loop Plant, 121 Assemblies, 12-ft.Core Figure 4.3-49 8 (\')Hdd8 00 a a N I'--a a::t-LD::::>a f-a::::e: LD-::t-o.Q..a::::>a z: to Cl::: (\')::::>00 o aN 8 to o AMENDMENT6 AUGUST, 1990 SOUTH CAROliNA ELECTRIC&GAS CO.VIRGIL C SUMMER NUCLEAR STATION Comparison of Calculated and Measured C B in Two-loop Plant, 121 Assemblies, 12*ft.Core Figure 4.3*50 8 (\')Hdd8 00 a a N I'--a a::t-LD::::>a f-a::::e: LD-::t-o.Q..a::::>a z: to Cl::: (\')::::>00 o aN 8 to o AMENDMENT6 AUGUST, 1990 SOUTH CAROliNA ELECTRIC&GAS CO.VIRGIL C SUMMER NUCLEAR STATION Comparison of Calculated and Measured C B in Two-loop Plant, 121 Assemblies, 12*ft.Core Figure 4.3*50 88 o o o en 8 00 o o CD 8 LO 8:::T 8 (Y)o o N 8 o 0 0 0:::T 0 0
0 (Y)0 0 0 N 0 0 0§0 8 en 8::>00_0 00 0 f'-..0-::>0 z: 0 oc:: 0::>CD 00 0 0 0 LO 0 0
0:::T 0 0 0 (Y)0 0 0 N 0 0 0 o AMENDMENT6 AUGUST,1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Comparison of Calculated and Measured C B in Three-Loop Plant, 157 Assemblies, 12*ft.Core Figure 4.3-51 8 8 o o o en 8 00 o o CD 8 LO 8:::T 8 (Y)o o N 8 o 0 0 0:::T 0 0 0 (Y)0 0 0 N 0 0 0§0 8 en 8::>00_0 00 0 f'-..0-::>0 z: 0 oc:: 0::>CD 00 0 0 0 LO 0 0 0:::T 0 0 0 (Y)0 0 0 N 0 0 0 o AMENDMENT6 AUGUST,1990 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Comparison of Calculated and Measured C B in Three-Loop Plant, 157 Assemblies, 12*ft.Core Figure 4.3-51
0.07 r'--------------------------
- 3200 96.0 96.5 96.5 97.9 97.0 95.0 97.0 PERCENT TH EO R ET I CAL DENSITY 2800.A 2qOO o 6.1200 1600 2000 TEMPERATURE (Oc)LEGEND: PERCENT THEORETICAL DEN SITY o GYLLANDER 96.ij 0 HOWARD&GULVIN*ASAMOTO 95.0*LUCKS&DEEM o GODFREY 93.ij<>DAN I EL ET AL 6.STORA 92.2.FEITH*A.D.BUSH 9ij.ij 0 VOGT ET AL*ASAMOTO 91.0 6.N1 SH IJ IMA V KRUGER 93.7" WHEELER&AI NSCOUGH SEE REFERENCES FOR THERMAL-HYDRAULIC SECTION 800 qOO*.*
A\J\J v*6.6.o 0.01 0.06 I-0 0 I E ()--..0.05..--I--::.:::.O.Oq:>--I-0::::)c:z;0 o 0.03...J<0::: Ul:t: I-0.02<V1-0;:l:lc ,...:3:V1;:l:l Co 3:,...3:-m Z;:l:l>>cm ("'1("'1 ,...-i m;:l:l;:l:l("'l V1 120-i>>_V1 0("'1 z9 ("'I o-i.,:r., l1)l1).,:4.3 l1)OJ....("'1 o 0 VlQ..on-i!:t.:r<l1);:+: 0,<., 0.....n" Cl1)0:J OJ'$.:n IQ C., l1).e:o:.:..\AI 0.07 3200 96.0 96.5 96.5 97.9 97.0 95.0 97.0 PERCENT TH EO R ET I CAL DENSITY 2800 2qOO o 1200 1600 2000 TEMPERATURE (OC)LEGEND: PERCENT THEORETICAL DEN SITY o GYLLANDER 96.ij 0 HOWARD&GULVIN*ASAMOTO 95.0*LUCKS&DEEM o GODFREY 93.ij<>DAN I EL ET AL 6.STORA 92.2.FEITH*A.D.BUSH 9ij.ij 0 VOGT ET AL*ASAMOTO 91.0 6.N 1 SH IJ IMA\l KRUGER 93.7" WHEELER&AI NSCOUGH SEE REFERENCES FOR THERMAL-HYDRAULIC SECTION 800 qOO o 0.01 0.060 0 I E ()--..0.05 I--::.:::O.Oq:>-I-0::::)c:z;0 0.03 0...J<0::: Ul:c I-0.02<V1-0::l:lc ,...:3:V1::l:l Co 3:,...3:z m>>::l:lm Z,...cm ("'1("'1 ,...-i>>("'1::l:l12O>>>>-iV1 0("'1 z9 ("'I o-i.,:r iD III n.,.-+3 III OJ Q..-'-+("'1 o 0 VlQ.. o n-i!:t.:r<III_.., III 0.-+.....n" C 0'":J 0 VI OJ_*.-+.-+OJ'$.
r\WWT I..-rT" I 1\\\*-Iol'I C\-"lI......-VI**Iol'I JI-**J
- ..1ol'I-..0\*..,.,-..-\.">.a:: ""'**.8"C: III.........-'"-o*JI"'Cl.:j-.,....1ol'I_C:C:
1".C\.-C.....-""'..*-.*
- ...*...:**\*'\....r\c.-.-c c.c c.....ei C f"'l.C C N.C c.C.c c-*-8*-C 0\*C-N t: c I CIQ a::*::: c.....i=-=-e....)<c:i:=...J a.r..l-e.c loW\C:.*cu-l-e-!on a::*u c c...,....u c-..c-*..., C a:: Q".C C M...,*a:: C c..-\C C-C"-N w-*::::: 11:1&U cr-c-*c AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Measured Versus Predicted Critical Heat Flux*WRB-2 Correlation Figure 4.4-6 r\WWT I..-rT" I 1\\\*-Iol'I C\-"lI......-VI**Iol'I JI-**J
- ..1ol'I-..0\*..,.,-..-\.">.a:: ""'**.8"C: III.........-'"-o*JI"'Cl.:j-.,....1ol'I_C:C:
1".C\.-C.....-""'..*-.*
- ...*...:**\*'\....r\c.-.-c c.c c.....ei C f"'l.C C N.C c.C.c c-*-8*-C 0\*C-N t: c I CIQ a::*::: c.....i=-=-e....)<c:i:=...J a.r..l-e.c loW\C:.*cu-l-e-!on a::*u c c...,....u c-..c-*..., C a:: Q".C C M...,*a:: C c..-\C C-C"-N w-*::::: 11:1&U cr-c-*c AMENDMENT6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Measured Versus Predicted Critical Heat Flux*WRB-2 Correlation Figure 4.4-6
.._.0.12 0.10-0.08'-LEGENO: o 26" SPACING I-PHASE o 26" SPACING 2-PHASE o o I 1.0 I 2.0 I 3.0II IJ.O 5.0 G De Re='T (10-5)I I 7.0 8.0 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION TOC versus Reynolds Number for 26" Grid Spacing Figure 4.4-8
.._.0.12 0.10-0.08'-LEGENO: o 26" SPACING I-PHASE o 26" SPACING 2-PHASE o o I 1.0 I 2.0 I 3.0II IJ.O 5.0 G De Re='T (10-5)I I 7.0 8.0 SOUTH CAROLINA ElECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION TOC versus Reynolds Number for 26" Grid Spacing Figure 4.4-8 I ct-I.1631.000-KEY: r-!:J.h/!:J.h G/G Q B wr-;:l.'968r::lFOR RADIAL POWER DISTRIBUTION NEAR BEGINNING OF LIFE.HOT FULL POWER.EQUILIBRIUM XENON N CALCULATED F!:J.H=1.33 1.00 II.142 QQQQQ G DDDDDD DDDD DDD r-::lDQr::lQQQQ B I I I 1.094 1.001 I 1.204 1.000 I.109 1.001 I 1.209 1.001 1.179 1.002 I 1.050 1.001 0.803 0.998 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Radial Flow and Enthalpy.Distribution at 4 ft.Elevation Figure 4.4-9I ct-I.1631.000-KEY: r-!:J.h/!:J.h G/G Q B wr-;:l.'968r::lFOR RADIAL POWER DISTRIBUTION NEAR BEGINNING OF LIFE.HOT FULL POWER.EQUILIBRIUM XENON N CALCULATED F!:J.H=1.33 1.00 II.142 QQQQQ G DDDDDD DDDD DDD r-::lDQr::lQQQQ B I I I 1.094 1.001 I 1.204 1.000 I.109 1.001 I 1.209 1.001 1.179 1.002 I 1.050 1.001 0.803 0.998 SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Radial Flow and Enthalpy.Distribution at 4 ft.Elevation Figure 4.4-9 CL I CL-1.164 0.991-I-KE Y: f-GIG FOR RADIAL POWER DISTRIBUTION NEAR BEGINNING OF LIFE.HOT FULL POWER.EQUILIBRIUI1 XENON CALCULA TED F=1.33 r::l 0Q G QL.:J r::lQH L:J Qo 8 DDDDDD DDDD DDDQ G r-::lL:Jt:j QR L:J Q EJ I I I I 1.092 0.997 I 1.206 0.987 I.109 0.99, 1.211 0.986'.182 0.988 1.050 0.998 0.800 1.019 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Radial Flow and Enthalpy Distribution at 8 ft.Elevation Figure 4.4*10 CL I CL-1.164 0.991-I-KE Y: f-GIG FOR RADIAL POWER DISTRIBUTION NEAR BEGINNING OF LIFE.HOT FULL POWER.EQUILIBRIUI1 XENON CALCULA TED F=1.33 r::l 0Q G QL.:J r::lQH L:J Qo 8 DDDDDD DDDD DDDQ G r-::lL:Jt:j QR L:J Q EJ I I I I 1.092 0.997 I 1.206 0.987 I.109 0.99, 1.211 0.986'.182 0.988 1.050 0.998 0.800 1.019 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Radial Flow and Enthalpy Distribution at 8 ft.Elevation Figure 4.4*10 KEY: I-t::.h 16': GIG QFOR RADIAL POWER DISTRIBUTION NEAR BEGINNING OF LIFE.HOT FULL POWER.EQUILIBRIUM XENON CALCULATED=1.33Qr::lI:.:lI-QQQDDDDDD DDDD DDDI.146 0.9921::1.I I III.i oS o 990 I 1.209 0.968 I.I 10 0.994 I.OSO 0.998 1.093 0.99S I.214 0.988 0.797 1.01 I 8.20:+0.90t 1...--+_-'
SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Radial Flow and Enthalpy Distribution at 12 ft.Elevation Core Exit Figure 4.4-11 KEY: I-t::.h 16': GIG QFOR RADIAL POWER DISTRIBUTION NEAR BEGINNING OF LIFE.HOT FULL POWER.EQUILIBRIUM XENON CALCULATED=1.33Qr::lI:.:lI-QQQDDDDDD DDDD DDDI.146 0.9921::1.I I III.i oS o 990 I 1.209 0.968 I.I 10 0.994 I.OSO 0.998 1.093 0.99S I.214 0.988 0.797 1.01 I 8.20:+0.90t 1...--+_-'
SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized Radial Flow and Enthalpy Distribution at 12 ft.Elevation Core Exit Figure 4.4-11 z: o(.)<t Q:: u..o o>-REGION I NO BUBBLE DETACHMENT LOCAL BO III NG".-,a....J<<I:z: w:z: o>-a..0::..J:::><<I<<I-(I):z: W en..J"'"<<:5 is CO W REGION II BUBBLE DETACHMENT W 0:::z::::>0<<I-0::<<W 0:: a..:::>W:::<:1-0::
W<<:::>I-en I-<<o en 0::-..J W::::><Q..C>':::>:::<:_C>'W..J WI-BULK BOILING VOID FRACTION PREDICTED FROM THERMODYNAMIC QUALITY WITH NO SLI P o THERMODYNAMIC QUALITY, X=H-H SAT I Hg-H SAT SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Void Fraction versus Thermodynamic Quality H-HsAT/Hg-HsAT Figure 4.4-12 z: o(.)<t Q:: u..o o>-REGION I NO BUBBLE DETACHMENT LOCAL BO III NG".-,a....J<<I:z: w:z: o>-a..0::..J:::><<I<<I-(I):z: W en..J"'"<<:5 is CO W REGION II BUBBLE DETACHMENT W 0:::z::::>0<<I-0::<<W 0:: a..:::>W:::<:1-0::
W<<:::>I-en I-<<o en 0::-..J W::::><Q..C>':::>:::<:_C>'W..J WI-BULK BOILING VOID FRACTION PREDICTED FROM THERMODYNAMIC QUALITY WITH NO SLI P o THERMODYNAMIC QUALITY, X=H-H SAT I Hg-H SAT SOUTH CAROLINA elECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Void Fraction versus Thermodynamic Quality H-HsAT/Hg-HsAT Figure 4.4-12 234 5 6789 10 II 270 0 12 13 14 15 T 0 TO 0 0 TO TO TO TO TO 0 0 0 T 0 T T T 0TT 0 T 0 T 0 0 TO TO TO T T T 0 T 0 0 T 0 TO 0 T 0TT TO TO T T 0 0 0 TO TO 0 T T T T 0 0 TO TO 0 0 T TO TO T T T 0 T 0 TO TO 0 T T T DT-THERMOCOUPLE (51)o-MOVABLE IHCORE DETECTOR (50)A B c o E F G H J K L M N p R SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Distribution of Incore Instrumentation Figure 4.4-19 2 3 4 5 6789 10 II 270 0 12 13 14 15 T 0 TO 0 0 TO TO TO TO TO 0 0 0 T 0 T T T 0TT 0 T 0 T 0 0 TO TO TO T T T 0 T 0 0 T 0 TO 0 T 0TT TO TO T T 0 0 0 TO TO 0 T T T T 0 0 TO TO 0 0 T TO TO T T T 0 T 0 TO TO 0 T T T DT-THERMOCOUPLE (51)o-MOVABLE IHCORE DETECTOR (50)A B c o E F G H J K L M N p R SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Distribution of Incore Instrumentation Figure 4.4-19