ML20199E535
| ML20199E535 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/27/1998 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20199E533 | List: |
| References | |
| NUDOCS 9802020182 | |
| Download: ML20199E535 (33) | |
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ENCLOSURE 1 TYPED TECIINICAL SPECIFICATION PAGES I
P PDR
TABLE OF CONTENTS (continued)
Il PLANT SYSTEMS .....................
- 7-1 .
3.7.1 Main Steam Safety Valves (MSSVs) . . . . . ._. . . . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . . . 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated
> Bypass Valves . . . . . . , . . . . . . . . . . .
_ 3.7-7 3.7.4 Atmospheric Relief Valves (ARVs) . . . . . . . . . . . 3.7-9 3.7.5 Auxiliary feedwater (AFW) System . . . . . . . . . . . 3.7-11 3.7.6 Condensate Storage Tank (CST) - (Redundant CSTs) . . . 3.7-15 3.7.6a Condensate Storage Tank (CST) - (Non-redundant CSTs) . 3.7-16 3.7.7 Component Cooling Water (CCW) System . . . . . . . . . 3.7-17 3.7.8 Nuclear Service Cooling Water (NSCW) System . . . . . 3.7-19 3.7.9 Ultimate Heat Sink (VHS) . . . . . . . . . . . . . . . 3.7-21 3.7.10 Control Room Emergency Filtration System (CREFS) - Both Units Operating . . . . . . . . . . . . . . . . . 3.7-24 3.7.11 Control Room Emergency Filtration System (CREFS) - One Unit Operating . . . . . . . . . . . . . . . . . . 3.7-27 3.7.12 Control Room Emergency Filtration System (CREFS) - Both Units Shutdown . . . . . . . . . . . . . . . . . . 3.7-30 3.7.13 Piping Penetration Area Filtration and Exhaust System (PPAFES) . . . . . . . . . . . . . . . . . 3.7-33 3.7.14 Engineered Safety Features (ESF) Room Cooler and Safety Related Chiller System . . . . . . . . . . 3.7-35 3.7.15 fuel Storage Pool Water Level ...... . . . . . 3.7-37 3.7.16 Secondary Specific Activity . . . . . . . . . . . . . 3.7-38 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . . . 3.7-39 3.7.18 Fuel Assembly Storage in the fuel Storage Pool . . . . 3.7.40 (continued)
Vogtle Units 1 and 2 v Amendment No. (Unit 1)
Amendment No. (Unit 2)
J
l TABLE OF CONTENTS (continued)
LIST 0F TABLES 1.1-1 MODES . . . . . . . . . . . . . . . . . . . . . . . 1.1-7 3.3.1-1 Reactor Trip System Instrumentation . . . . . . . . . 3.3-14 3.3.2-1 Engineered Safety Feature Actuation System Instrumentation . . . . . . . . . . . . . . . . . 3.3-30 3.3.3-1 Post Accident Monitoring Instrumentation . . . . . . . 3.3-42 3.3.4-1 Remote Shutdown System Instrumentation and Controls . 3.3-45 3.3.6-1 Containment Ventilation Isolation Instrumentation . . 3.3-53 3.3.7-1 CREFS Actuation Instrumentation . . . . . . . . . . . 3.3-59 3.7.1-1 Maximum Allowable Power Range Neutron Flux High Trip Setpoint with inoperable Main Steam Safety Valves . 3.7-3 3.7.1-2 Main Steam Safety Valve lift Settings . . . . . . . . 3.7-4 3.8.4-1 Discharge Test Surveillance Requirements . . . . . . . 3.8-29 3.8.6-1 Battery Cell Parameters Requirements . . . . . . . . . 3.8-35 5.5.9-1 Minimum Number of Steam Generators to Be Inspected During Inservice Inspection . . . . . . 5.0-18 5.5.9-2 Steam Generator Tube Irspection . . . . . . . . . . . 5.0-19 LIST OF FIGURES 2.1.1-1 Reactor Core Safety Limits . . . . . . . . . . . . . . 2.0-2 3.4.16-1 Reactor Coolant Dose L3 uivalent I-131 Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specific Activity > 1 Ci/ gram Dose Equivalent I-131 . . . 3.4-44 3.7.18-1 Vogtle Unit 1 Burnup Credit Requirements for All Cell Storage . . . . . . . . . . . . . . . . . 3.7-42 3.7.18-2 Vogtle Unit 2 Burnup Credit Requirements for All Cell Storage . . . . . . . . . . . . . . . . . 3.7-43 ,
4.3.1-1 Vogtle Unit 1 Burnup Crodit Requirements for 3-out-of-4 Storage . . . . . . . . . . . . , . c . . 4.0-4 4.3.1-2 Vogtle Unit 2 Burnup Cr!dit Requirements for 3-out-of-4 Storage . . . . . . . . . . . . . . . . 4.0-5 Vogtle Units 1 and 2 viii Amendment No. (Unit 1)
Amendment No. (Unit 2)
t TABLE OF CONTENTS (continued) 4.3.1-3 Vogtle Unit 2 Burnup Credit Requirements for 3x3 Storage . . . . . . . . . . . . . . . . . . . . . 4.0-6 4.3.1-4 Vogtle Units 1 and 2 Empty Cell Checkerboard Storage Configurations . . . . . . . . . . . . . . 4.0-7 4.3.1-5 Vogtle Unit 2 3x3 Checkerboard Storage Configuration . 4.0-8 4.3.1-6 Vogtle Units 1 and 2 Interface Requirements (All Cell to Checkerboard Stcrage) . . . . . . . . 4.0-9
(.3.1-7 Vcgtle Units 1 and 2 Interface Requirements (Checkerboard Storage Interface) . . . . . . . . . 4.0-10 4.3.1-8 Vogtle Unit 2 Interface Requirements (3x3 Checkerboard to All Cell Storage) . . . . . . 4.0-11 4.3.1-9 Vogtle Unit 2 Interface Requirements (3x3 to Empty Cell Checkerboard Storage) . . . . . 4.0-12 l
l l
l Vogtle Units 1 and 2 ix Amendment No. (Unit 1)
Amendment No. (Unit 2) i
Fuel Storage Pool Boron Concentration 3.7.17 3.7 -PLANT SYSTEMS 3.7.17 Fuel Storage Pool Boron Concentration LCA 3.7.17 The fuel storage pool boron concentration shall be k 2000 ppm.
APPLICABILITY: When fuel assemblies are stored in the fuel storage pool.
ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool -------------NOTE------------
boron concentration LCO 3.0.3 is not applicable, not within limit.- -----------------------------
A.1 Suspend movement of Immediately fuel assemblies in the fuel storage pool.
8!iQ t A.2.1 Initiato action to immediately restore fuel storage pool boron concentration to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
-SR 3.7.17.1 Verify the fuel storage pool boron -7 days concentration is within limit.
Vogtle Units 1 and 2 3.7-39 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Fuel Assembly Storage in the fuel Storage Pool 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Fuel Assembly Storage in the Fuel Storage Pool LCO 3.7.18 The combination of initial enrichment-burnup and configuration of fuel assemblies stored in the fuel storage
-pool shall b2 within the Acceptable Burnup Domain of Figures 3.7.18-1 (Unit 4.3.
Specification 1),1.1.3.7.18-2 (Unit 2), or in accordance with APPLICABILITY: Whenever any fuel assembly is stored in the fuel storage pool.
ACTIONS CONDITION REQUIRED ACTION !COMPLETIONTIME A. Requirements of the A.1 --------NOTE---------
LCO not met. LCO 3.0.3 is not applicable.
Initiate action to immediately move the aoncomplying fuel assembly to an acceptable storage location.
Vogtle Units 1 and 2 3.7-40 Amendment No. (Unit 1)
Amendment No. (Unit 2) l
. _ _ _ _ _ _ _ _ i
Fuel Assembly Storage in the fuel Storage Pool 3.7.18 SURVEILLANCE RE0VIREMENTS SURVEILLANCE FREQUENCY l
SR 3.7.18.1 Verify by a combination of visual Prior to inspection and administrative means that storing the the initial enrichment, burnup, and storage fuel assembly location of the fuel assembly is in in the fuel accordance with figures 3.7.18-1 (Unit 1), storage pool 3.7.18-2 (Unit 2), or location.
Specification 4.3.1.1.
I Vogtle Units 1 and 2 3.7-41 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Fuel Assembly Stcrage in the Fuel Storage Pool 3.7.18 40000
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--l 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial U 235 Enrichment (nominal w/o)
Figure 3.7.18-1 Vogtle Unit 1 Burnup Credit Requirements for All Cell Storage Vogtle Units 1 and 2 3.7-42 Amendment No. (Unit 1)
Amendment No. (Unit 2) 1
Fuel Assembly Storage in the Fuel Storage Pool 3.7.18 50000 , , , , , ,
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0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial U 235 Enrichment (nominal w/o)
Figure 3.7.18-2 Vogtle Unit 2 Burnup Credit Requirements for All Cell Storage Vogtle Units 1 and 2 3.7-43 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; l
- b. K , < 1.0 when fully flooded with unborated water wh,ichincludesanallowanceforuncertaintiesas described in Section 4.3 of the FSAR.
c, k ,, s 0.95 when fully flooded with water borated to 450 ppm (Unit 1) or 500 ppm (Unit 2), which includes an allowance for uncertainties as described in Section 4.3 of the FSAR;
- d. New or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figures 3.7.18-1 (Unit 1) or 3.7.18-2 (Unit 2) may be allowed unrestricted storage in the Unit 1 or Unit 2 fuel storage pool, respectively.
- e. New or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-1 may be stored in the Unit 1 fuel storage pool in a 3-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4.
New or partially spent fuel assemblies with a maximum initial enrichment of 5.0 weight percent U-235 may be stored in the Unit 1 fuel storage pool in a 2-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4.
Interfaces between storage configurations in the Unit 1 fuel storage pool shall be in compliance with Figures 4.3.1-6 and 4.3.1-7. "A" assemblies are new or partially spent fuel assemblies with a (continued)
Vogtle Units 1 and 2 4.0-2 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 3.7.18-1. "B" assemblies are new or partially spent fuel assemblies with a combination of burnus and initial nominal enrichment in the "accesta)1e burnup domain" of Figure 4.3.1-1. "C" assem)1ies are assemblies with initial enrichments up to a maximum of 5.0 weight percent U-235.
New or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-2 may be stored in the Unit 2 fuel storage pool in a 3-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4.
New br partially spent fuel assemblies with a maximum initial enrichment of 5.0 weight percent U-235 may be stored in the Unit 2 fuel storage pool in a 2-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4.
New or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-3 may be stcred in the Unit 2 fuel storage pool as " low enrichment" fuel assemblies in the 3x3 checkerboard storage configuration as shown in Figure 4.3.1-5 New or partially s)ent fuel assemblies with initial nominal enricaments less than or equal to 3.20 weight percent U-235 or having a maximum reference fuel assembly K. less than or equal to 1.410 at 68'F may be stored in the Unit 2 fuel storage pool as "high enrichment" fuel assemblies in the 3x3 checkerboard storage configuration as shown in Figure 4.3.1-5.
Interfaces between storage configurations in the Unit 2 fuel storage pool shall be in compliance with Figures 4.3.1-6, 4.3.1-7, 4.3.1-8, and 4.3.1-9. "A" assemblies are new or partially spent fuel assemblies with a combination of burnup and (continued)
Vogtle Units 1 and 2 4.0-3 Amendment No. (Unit 1)
Amendment No. (Unit 2) l
Design Features 4.0 l-4.0 DESIGN FEATURES 4.3 -Fuel Storage (continued) initial nominal enrichment in the " acceptable burnup domain" of Figure 3.7.18-2. "B" assemblies are new or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-2. "C" assemblies are assemblies with initial enrichments up to a maximum of 5.0 weight percent U-235. "L" assemblies are new or partially spent fuel assemblies with a combination of burnup and initial nominal enrl:hment in the " acceptable burnup domain" of Figure 4.3.1-3. "H" assemblies are new or partially spent fuel assemblies with initial nominal enrichments less than or equal to 3.20 weight percent U-235 or having a maximum reference fuel assembly K. less than or equal to 1.410 at 68'F.
- f. A nominal 10.6 inch center to center pitch in the l Unit I high density fuel storage racks; and
- g. A nominal 10.58-inch center to center pitch in the l north-south direction and a nominal 10.4-inch center to center ) itch in the east-west direction in the Unit 2 higi density fuel storv'a racks.
4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 5.05 weight percent;
- b. k , s 0.95 if fully flooded with unborated water, wh,ich includes en allowance for uncertainties as described in Section 4.3 of the FSAR;
- c. k,,, s 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 4.3 of the FSAR; and
- d. A nominal 21-inch center to center distance aetween fuel assemblies placed in the storage racks.
Vogtle Units 1 and 2 4.0-3a Amendment No. (Unit 1)
Amendment do. (Unit 2)
Design Features 4.0 ,
4.0 DESIGN FEATURES 4.3. Fuel Storage- (continued) 4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 194 foot-1 1/2 inch.
4.3.3 Canacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 288 fuel assemblies in the Unit I storage pool and no more than 2098 fuel assemblies in the Unit 2 storage pool.
l 1
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e Vogtle Units 1 and 2 4.0-3b Amendment No. (Unit 1)
Amendment No. (Unit 2)
Design Features 4.0 30000 25000
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15000 ACCEPTABLE /
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Figure 4.3.1-1 Vogtle Unit 1 Burnup Credit Requirements for 3-out-of-4-Storage Vogtle Units 1 and 2 4.0-4 Amendment No. (Unit 1)
Amendment No. (Unit 2)
_ _ _ - _ _ _ - _ _ _ l
Design Features 4.0 30000 e
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0 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial U 235 Enrichment (nominal w/o)
Figure 4.3.1-2 Vogtle Unit 2 Burnup Credit Requirements for 3-or of ' Storage Vogtle Units 1 and 2 4.0-5 Amendment No. (Unit 1)
Amendment No. (Unit 2)
l Design Features 4.0 50000
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O 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial U 235 Enrichment (nominal w/o) figure 4.3.1-3 Vogtle Unit 2 Burnup Credit Requirements for 3x3 Storage Vogtle Units 1 and 2 4.0-6 Amendment No. (Unit 1)
Amendment No. (Unit 2) l
-_________J
Design Features 4.0 ZZ Z Z Z Z Z Z Z Z Z Z lZ Z Z Z Z Z Z Z Z Z Z Z 3 out of 4 Checkerboard Storage Z Z Z
Z Z Z 2 out of 4 Checkerboard Storage Empty Storage Cell Fuel Assembly in Storage Cell Figure 4.3.1-4 Vogtle Units 1 and ? Empty Cell Checkerboard Storage Configurations Vogtle Units 1 and 2 4.0-7 Amendment No. (Unit 1)
Amendment No. (Unit 2)
l Design Features 4.0 1
1 i.
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- i j 3x3 Checkerboard Storage I
i Low Enrichment Fuel liigh Enriclinient Fuel O
j Assembly in Storage Cell Assembly in Storage Cell i l l l
1 I
, Figure 4.3.1-5 Vogtle Unit 2 3x3 Checkerboard Storage Configuration 1
, Vogtle Units 1 and 2 4.0-8 Amendment No. (Unit 1) 3 Amendment No. (Unit 2) 4 1
-- + .,y -,.--,~,..,.,,_,.e.,,,, ,,,,,,,.,.m,, ,.,,,..%._ ,my,,,,,___y,_..,,.._._,,.&wr- ym m .w e. g y -
w vv--w- -*-'wvw----e-w-++-r-w+
Design Features 4.0 A A A A A A Note:
A A A A A A A . AiiCeli Enrichment
"'""'" " " 3 ""' M N A A A A A A Enrichment Empty = Einpty Cell Emr t> 11 Empiy A A A 11 11 11 A A A Empty II Empty A A A a
lloundary lletween All Cell Storage and 3 out of 4 Storage A A A A A A Note:
A A A A A A A = All Cell Enrichment I" "k" m_ ___
A A
A A A A " " 3' "' N Enrichment C = 2 Out Of 4 Empty II Empty I i A A Enrichment Empty a Empty Cell C Emp:3 11 A A A Emp:3 C Empi> 1 A ,A A 1
lloundary lletween All Cell Storage and 2 out of 4 Storage Note:
- 1. A row of empty cells can be used at the interface to separate the configurations.
- 2. It is acceptable to replace an asseinbly with an empty cell.
Figure 4.3.1-6 Vogtle Units 1 and 2 Interface Requirements (All Cell to Checkerboard Storage)
Vogtle Units 1 and 2 4.0-9 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Design features 4.0 B tmpiy B Empty B Empty Note:
B B B B B 11 n = 3. oui.or.4 Enrichment 7
g" "Q" Il Empiy B tmpiy B tmpiy C 2. oui or.4 Enrichment m_ ___ __
Empty Empty Cell Empiy C tmpiy l B B B 3 C tmpir C' tmpey B tmpiy Empty C tmpty l B B B s
lloundary lletween 2 out of-4 Storage and 3 out of-4 Storage I:mpiy N Empiy B B l}
Note:
11 B B, B tmpey B tr ., 3. oui.or.4
. Enrichment Empiy B Empiy~ l'B . .B- B Cs 2.out.or.4 m_ _ __ __
Enrichment Empty = Empty Cell C tmpiy C1 cmpiy ' B' tmpiy Empty C tmpi) B B ,B C tmpty C i omr3 8 cmpiy j '.
e lloundary Between 2 out-of 4 Storage and 3 out of-4 Storage Note:
- 1. A rim of empty cells can be used at the interface to separate the configurations.
- 2. It is acceptable to replace an assembly with an empty cell, figure 4.3.1-7 Vogtle Units 1 and 2 Interface Requirements (Checkerboard Storage Interface)
Vogtle Units 1 and 2 4.0-10 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Design Features 4.0 7
I A A A A A A Note:
A A A A A A A = All Cell Enrichment L = Lww Enrichment of Intuface L L L A 3t3 Checkerboard N L A 11 = liigh Enrichment cf
"- --~ - - - ~- '
313 Checkerboard L L LI L A A L 11 L' L A A L L L L A A a
Note:
- 1. A row of empty cells can be used at the interface to separate the conagurations.
- 2. It is acceptable to replace an assembly with an empty cell.
Figure 4.3.1-8 'Jogtle Unit 2 Interface Requirements (3x3 Checkerboard to All Cell Storage)
Vogtle Units 1 and 2 4.0-11 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Design Features 4.0 B B B B B B* Not" B = 3 Out Of-4 Empty B tmpty B tmpty B , [ic[m ni Interface L L L L B B of 3:3 storage N ,_ __ _ _
1t = IUgh Enrichment L L LI L tmpn B of 33 storage
_ Empty = Empty Cell L H L L B B L L L L tmpt3 B Boundary Between 3x3 Storage and 3-out-of-4 Storage Note:
C tmpti -
C tmpty C tmp
. Endehment L L w Enrichment empty B tmpn B Empty C of 3:3 Storage Interface { g',, g' g', , g tmpn H = IUgh Endchment N of 313 storage C = 2-Out-Of 4 L L Ll L tmpo C gori,3m,,,
L 11 L L*
- B tmpts
" " ~ *
- L L Li L tmpty C Boundary Between 3x3 Storage and 2-out-of-4 Storage Note:
- 1. .\ row of empty cells can he used at the interface to separ te the configurations.
- 2. It is acceptable to replace an assembly with an empty ceh.
- 3. For the 3-out-of-4 configurction, the row beyond the Low enrichment can swap empty and Il assemblics, however the next outer row must change the indicated assembly (*) to an empty cell.
- 4. For the 2-out-of-4 configuration, the row beyond the Low enrichment can swap empty and B assemblies, however the next outer row of empty and C assemblies must also swap locations.
- 5. If empty cells are in indicated locations (**), then the face adjacent B assemblies can be C assemblics.
Figure 4.3.1-9 Vogtle Unit 2 Interface Requirements (3x3 to Empty Cell Checkerboard Storage)
Vogtle Units 1 and 2 4.0-12 Amendment ha, (Unit 1)
Amendment No. (Unit 2)
TCLE OF CONTENTS I
l B 3.7 PLANT SYSTEMS .................... B 3.7-1 l
B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) ....... . B 3.7-7 8 3.7.3 Main Feedwater Isolation Valves _(MFIVs) and Hait.
Feedwater Regulation Valves (MFRVs) and j Associated Bypass Valves . . . . . . . . . . . . . B 3.7-14 8 3.7.4- Atmospheric Relief Valves (ARVs) . . . . . . . . . . . B 3.7-21 B 3.7.5 Auxiliary feedwater (AFW) System . . . . . . . . . . . B 3.7-26 B 3.7.6 CondensateStorageTank(CST) . . . . . . . . . . . . B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System . . . . . . . . . B 3.7-40 B 3.7.8 Nuclear Service Cooling Water (NSCW) System . . . . . B 3.7-45 B 3.7.9 Ultimate Hett Sink (VHS) . . . . . . . . . . . . . . . B 3.7-50 B 3.7.10 Control Room Emergency Filtration System (CREFS) -
Both Units Operating . . . . . . . . . . . . . . . B 3.7-55 B 3.1.11 Control Room Emergency Filtration System (CREFS) -
One Unit Operating . . . . . . . . . . . . . . . . B 3.7-64 B 3.7.12 Control Room Emergency Filtration System (CREFS) -
Both Units Shut Down . . . . . . . . . . . . . . . B 3.7-70 B 3.7.13 Piping Penetration Area Filtration and Exhaust System (PPAFES) ................. B 3.7-75 B 3.7.14 Engineered Safety Feature (ESF) Room Couler and Safety-Related Chiller System . . . . . . . . . . B 3.1-80 B 3.7.15 Fuel Storage Pool Water Level . . . . . . . . . . . . B 3.7-85 B 3.7.16 Secondary Specific Activity . . . . . . . . . . . . . B 3.7-88 8 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . . . B 3.7-92 8 3.7.18 fuel Assembly Storage in the Fuel Storage Pool . . . . B 3.7-97 (continued)
Vogtle Units 1 and 2 iv Revision No.
Fuel Storage 9001 Boron Concentration B 3.7.17 i
! B 3.7 PLANT SYSTEMS B 3.7.17 fuel Storage Pool Boron Concentration BASES BACKGROUND Fuel assemblies are stored in high density racks. The Unit I spent fuel storage racks contain storage locations for 288 fuel assemblies, and the Unit 2 spent fuel storage racks contain storage locations for 2098 fuel assemblies.
Westinghouse 17x17 fuel assemblies with initial enrichments of up to and including 5.0 weight percent U-235 can be stored in any location in the Unit 1 or Unit 2 fuel storage pool provided the fuel burnup-enrichment combinations are within the limits that are specified in Figures 3.7.18-1 >
(Unit 1) or 3.7.18-2 (Unit 2) of the Technical Specifications. Fuel assemblies that do not meet the burnup-enrichment combination of Fiqures 3.7.18-1 or 3.7.16-2 may be stored in the storage pools of Units 1 or 2 in accordance with checkerboard storage configurations described in Figures 4.3.1-1 through 4.3.1-9. The acceptable fuel assembly storage Configurations are based on the Westinghouse Spent fuel Rack Criticality Methodology, described in WCAP-14416-NP-A, Rev. 1, (Reference 4). This methodology includes competer code benchmarking, spent fuel rack criticality calculations methodology, reactivity equivalencing methodology, accident methodology, and soluble boron credit methodology.
The Westinghouse Spent Fuel Rack Criticality Methodology ensures that the multiplication factor, K ,,, of the fuel and
, spent fuel storage racks is less than or equal to 0.95 as recommended by AllSI 57.2-1983 (Reference 3) and NRC guidance (References 1, 2 and 6). The codes, methods, and techniques contain9d in the methodology are used to satisfy this criterion on K.,,.
The methodology of the NITAWL-II, XSDRNPM-S, and KENO-Va codes is used to establish the biar and bias uncertainty.
PHOENIX-P, a nuclear design code used primarily fs core reactor pnysics ca'.culations is used to simulate spent fuel storage rack geometries.
(continued)
Vcgtle Units 1 and 2 B 3.7-92 Revision No.
Fuel Storage Pool Boron Concentration B 3.7.17 BASES BACKGROUND Referenct 4 describes how credit for fuel storage pool (continued) soluble boron is used under normal storage configuration ccnditions. The storage configuration is defined using K.,,
calculations to ensure that the K.,, will be less than 1.0 with no soluble boron under normal storage conditions including tolerances and uncertainties. Soluble boron credit is then used to maintain K.,, less than or equal to 0.95. The Unit 1 pool requires 450 ppm and the Unit 2 pool requires 500 ppm to maintain K.,, less than or equal to 0.95 for all allowed combinations of storage configurations, enrichments, and burnups. The analyses assumed 19.9% of the boron atoms have atomic weight 10 (B-10). The effects of B-10 der;letion on the boron concentration for maintaining K.,, s 0.95 are negligible. The treatment of reactivity equivalencing uncertainties, as well as the calculation of postulated accidents crediting soluble boron is described in WCAP-14416-NP-A, Rev. 1.
This methodology was used to evaluate the storage of fuel with initial enrichments up to and including 5.0 weight y}
i" percent U-235 in the Vogtle fuel storage pools. The resulting enrichmer,t, and burnup limits for the 'Init I and Unit 2 pools, respectively, are shown in Figures 3.7.18-1 and 3.7.18-2. Checkerboard storage configurations are defined to allow storage of fuel that is not within the acceptable burnup domain of Figures 3.7.18-1 and 3.7.18-2.
These storage requirements are shown in Figures 4.3.1-1 through 4.3.1-9. A boron ce9 centration of 2000 ppm assures that no credible dilution eunt will result in a K ,, of
> 0.95.
APPLICABLE Most fuel storage pool accident conditions will not result SAFETY ANALYSES in an increase in V,,,, Examples of such accidents are the drop of a fuel assembly on top of a rack, and the drop of a fuel assembly between rack modules, or between rack modules and the pool wall.
i, ,
From a criticality standpoint, a dropped assembly accident
( occurs when a fuel assembly in its most reactive condition is dropped onto the storage racks. The rack structure from a criticality standpoint is not excessively deformed.
Previous accident analysis with unborated water showed that the dropped assembly which comes to rest horizontally on top of the rack has sufficient water separating it from the (continued)
Vogtle Units 1 and 2 B 3.7-93 Revision No.
Fuel Storage Pool Boron Concentration B 3.7.17 BASES APPLICABLE active fuel height of stored assemblies to preclude SAFETY ANALYS:S neutronic interaction. For the borated water condition, the (continued) interaction is even less since the water contains boron, an additional thermal neutron absorber. ,
However, three accidents can be postulated for each storage configuration which could increase reactivity beyond the analyzM condition. The first postulated accident would be a change in pool temperature to outside the range of temperatures assumed in the criticality analyses (50*F to 185'F). The second accident would be dropping a fuel assen.bly into an already loaded cell. The third would be the misloading of a fuel assembly into a cell for which the restrictions on location, enri 5 ent, or burnup are not satisfied.
Ali increase in the temperature of the water passing through the stored fuel assemblies causes a decrease in water density which would normally result in an additio.. of negative reactivity. However, since Boraflex is not considered to be present and the fuel storage pool water has a high concentration of Mron, a density decrease causes a positive reactivity additiin. The reactivity effects of a temperature range from 3h F to 240 F were evaluated, i increase in reactivity due to the increase in temperature is bounded by the misload accident.
For the accident of dropping a fuel assembly into an already loaded cell, the upward axial leakage of that cell will be reduced, however, the overall effect on the rack reactivity will be insignifice.nt. This is because the total axial leakage in both the upward and downward directions for the entire fuel array is worth about 0.003 Ak. Thus, minimizing the upward-only leakage of just a single cell will not cause any significat ":rease in reactivity. Furthermore, the neutronic coup',as between the dropped assembly and the already loaded assembly will be low due to several inches of assembly nozzla structure which would seprate the active fuel regions. Therefore, this accident would be bounded by the misload accidtnt.
The fuel assembly misloading accident involves placement of a fuel assembly in a location for which it does not meet the requirements for enrichment or burnup, including the placement of an assembly in a location that is required to be left empty. The result of the misloading is to add positive reactivity, increasing K ,, toward 0.95. The (continued)
Vogtle Units 1 and 2 B 3.7-94 Revision No.
l Fuel Storage Pool Boron Concentration B 3.7.17
[ BASES (continued)
APPLICABLE maximum required additional boron to compensate for this SAFETY ANALYSES event is 1250 p)m for Unit 2, and 1150 ppm-for Unit I which
-(continued) is well below tie limit of 2000 ppm.
The concentration of dissolved boron in the fuel storage pool satisfies Criterion 2 of the NRC Policy Statment.
LCO The fuel storage pool boron concentration is required to be 1 2000 ppm. The specified concentration of diss.'.ed boron in the fuel storage pool preserves the assumptions used in the analyses of the potential criticality accident scenarios as described in reference 5. The amount of soluble boron required to offset each of the above postulated accidents was evaluated for all of the proposed storage configurations. That evaluation established the amount of soluble boron necessary to ensure that K.,, will be maintained less than or equal to 0.95 should pool temperature _ exceed the assumed range or a fuel assembly l misload occur. The amount of soluble boron necessary to mitigate these events was determined to be 1250 ppm for Unit 2 and 1150 ppm for Unit 1. The specified minimum boron-concentration of 2000 ppm assures that the concentration will remain above these values. In addition, the boron concentration is consistent with the boron dilution evaluation that' demonstrated that any credible dilution event could be terminated prior to reaching the boron concentration for a K.,, of > 0.95. These values are 450 ppm for Unit 1 and 500 ppm for Unit-2.
APPLICABILITY This LCO applies whenever fuel assemblies are stored in the
-spent fuel-storage pool.
ACTIONS A.l. A.2.1. ar.d A.2.2 The Required Actions are modified by a Note indicating that LCO 3.0.3 does not apply.
When the concentration of boron in the fuel storage pool is less than required, immediate action must be taken to preclude the occurrence of an accident nr to mitigate the consequences of an accident in progr e This is most
, (continued)
Vogtle Units 1 and 2 B 3.7-15 Revision No.
4 _ _ _ _ _ _ _ _ _ _ _ _ . _ _
Fuel Storage Pool Boron Concentration B 3.7.17 BASES ACTIONS efficiently achieved by immediately suspending the movement (continued) of fuel assemblies. Immediate action to restore the '
concentration of boron is also required simultaneously with suspending movement of fuel assemblies. This does not preclude movement of a fuel assembly to a safe position.
If the LCO is not met while moving irradiated fuel assemblies in MODE 5 or 6, LC0 3.0.3 would not be ap)11 cable. If moving irradiated fuel assemblies while in HO)E 1, 2, 3, or 4, the fuel movement is independent of reactor operation. Therefore, inability to suspend movement of fuel assemblies is not sufficient reason to require a reactor shutdown.
=
SURVEILLANCE SR 3.7.17.1 REQUIREMENTS This SR verifies that the concentration of boron in the fuel storage pool is within the required limit. As long as this SR is met, the analyzed accidents are fully addressed. The 7 day Frequency is appropriate because no major replenishment of pool water is expected to take 31 ace over such a short period of time. The gate between tie Unit I and Unit 2 fuel storage pool is normally open. When the gate is open the pools are considered to be connected for the purpose of conducting the surveillance.
REFERENCES 1. USNRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Edition. NUREG-0800, June 1987.
- 2. USNRC Spent Fuel Storage Facility Design Bases (for Comment) Proposed Revision 2, 1981. Regulatory Guide 1.13.
- 3. ANS, " Design Requirements for Light Water Reactor Spent Fuel Storage Facilities at Nuclear Power Stations," ANSI /ANS-57.2-1983.
- 4. WCAP-14416 NP-A, Rev.1, " Westinghouse Spent fuel Rack Criticality Analysis Methodology," November 1996.
- 5. Vogtle FSAR, Section 4.3.2.
- 6. Nuclear Regulatory Commission, Letter to All Power Reactor Licensees from B. K. Grimes, "0T Position for Review and Acceptance of Spent Fuel Storage and Handling Applications," April 14, 1978.
Vogtle Units 1 and 2 B 3.7-96 Revision No.
Fuel Assembly Storage in the Fuel Storage Pool B 3.7.18 B 3.7 PLANT SYSTEMS B 3.7.18 fuel Assembly Storage in the Fuel Storage Pool BASES BACKGROUND The Unit 1 spent fuel storage racks contain storage locations for 288 fuel assemblies, and the Unit 2 spent fuel storage racks contain storage locations for 2098 fuel assemblies.
I Westinghouse 17X17 fuel assemblies with ar enrichment of up to and including 5.0 weight percent U-235 can be stored in the acceptable storage configurations that are specified in Figures 3.7.18-1 (Unit 1), 3.7.18-2 (Unit 2), and 4.3.1-1 through 4.3.1-9. The acceptable fuel assembly storage locations are based on the Westinghouse Spent Fuel Rack Criticality Methodology, described in WCAP-14416-NP-A, Rev. 1 (reference 1). Additional background discussion can be found in B 3.7.17. l
).
-Westinghouse 17x17 fuel assemblies with nominal enrichme-no greater than 1.79 w/o"'U may be stored in all storag cell locations of the Unit 1 pool. Fuel assemblies with initial nominal enrichment greater than 1.79 w/o"'u must satisfy a minimum burnup requirement as shown in Figure 3.7.18-1.
Westinghouse 17x17 fuel assemblies with nominal enrichments no greater than 2.45 w/o'"U may be stored in a 3-out-of-4 checkerboard arrangement with empty cells in the Unit 1 0001. Fuel assemblies with initial nominal enrichment greater than 2.45 w/o50 must satisfy a minimum burnup requi ement as shown in Figure 4.3.1-1.
Westinghouse 17x17 fuel assemblies with nominal enrichments no greater that 5.0 w/o'"U may be stored in a 2-out-of-4 checkerboard arrangement with empty cells in the Unit 1 or Unit 2 pool. There are no minimum burnup requirements for this configuration.
Westinghouse 17x17 fuel assemblies with nominal enrichments no greater than 1.77 w/o'"U may be stored in all storage cell locations of the Unit 2 pool. Fuel assemblies with initial nominal enrichment greater than 1.77 w/o'"U must satisfy a minimum burnup cequirement as shown in Figure 3.7.18-2.
(continued)
Vogtle Units 1 and 2 B 3.7-97 Revision No.
Fuel Assembly Storege in the fuel Storege Pool B 3.7.18 BASES BACKGROUND Westinghouse 17x17 fuel assemblies with nominal enrichments (continued) no greater than 2.40 w/o"'O may be stored in a 3-out-of-4 checkerboard arrangement with empty cells in the Unit 2 pool. Fuel assemblies with initial nominal enrichment greater than 2.40 w/o"'O must satisfy a minimum burnup requirement as shown in Figure 4.3.1-2.
Westinghouse 17x17 fuel assemblies may be stored in the Unit 2 pool in a 3x3 array. The center assembl must have aninitialenrichmentnogreaterthan3.20w/o'y'U.
Alternatively, the center of the 3x3 array may be loaded with any assembly which meets a maximum infinite multiplication factor (K.) value of 1.410 at 68*F. One method of achieving this value of K. is by the use of IFBAs.
The surrounding fuel assemblies must have an initial r minal l enrichment no greater than 1.48 w/o"'U or satisfy a minimum burnup requirement for higher initial enrichments as shown in Figure 4.3.1-3.
APPLICABLE Host fuel storage pool accident conditions will not result SAFETY ANALYSIS in an increase in K ,,, Examples of such accidents are the drop of a fuel assembly on top of a r.ick and the drop of a fuel assembly between rack nodules or between rack modules and the pool wall. However, accidents can be postulated for each storage configuration which could increase reactivity beyond the analyzed condition. A discussion of these accidents is contained in B 3.7.17.
The configuration of fuel assemblies in the fuel storage pool satisfies Criterion ? of the NRC Policy Statement.
LC0 The restrictions on the placement of fuel assemblies within the fuel storage pool ensure the K.,, of the fuel storage pool will always remain < 0.95, assuming the pool to be flooded with borated water.
The combination of initial enrichment and burnup are specified in Figures 3.7.19-1 and 3.7.18-2 for all cell storage in the Unit 1 and Unit 2 pools, respectively. Other acceptable enrichment burnup and chechrboard combinations are described in Figures 4.3.1-1 through 4.3.1-9.
(continued)
Vogtle Units 1 and 2 B 3.7-98 Revision No.
- b. _ - - - - - - - - - - - - - - - - - - - - - - - - -
Fuel Assembly Storage in the Fuel Storage Pool B 3.7.18 N BASEF (continued)
APPLICABILITY This LCO applies whenever any fuel assembly is stored in the fuel storage pool.
ACTIONS Ad Required Action A.1 is modified by a Note indicating that LC0 3.0.3 does not apply.
When the configuration of fuel assemblies stored in the fuel stoe ? pool is not in accordance with the acceptable cow .1ation of initial enrichment, burnup, and storage configurations, the immediate action is to initiate action to make the necessary fuel assembly movement (s) to bring the configuration into compliance with Figures 3.7.18-1 (Unit 1), 3.7.18-2 (Unit 2), or Specification 4.3.1.1.
If unable to move irradiated fuel assemblies while in MODE 5 or 6. LCO 3.0.3:would not be applicable. If unable to move irradiated fuel assemblies while in MODE 1, 2, 3, or 4, the action is independent of reactor operation. Therefore inability to move fuel assemblies is not sufficient reason to require a reactor shutdown.
SURVEILLANCE- SR 3.7.18.1 REQUIREMENTS This SR verifies by administrative means that the initial enrichment and burnup of the fuel assembly is within the acceptable burnup domain of Figures 3.7.18-1 (Unit 1) or 3.7.18-2 (Unit 2). For fuel assemblies in the unacceptable range of Figures 3.7.18-1 and 3.7.18-2, performance of this SR will also ensure compliance with Specification 4.3.1.1.
Fuel assembly movement will be in accordance with preapproved plans that are consistent with the specified fuel enrichment, burnup, and storage configurations. These plans are administratively verified prior to fuel movement.
Each assembly is verified by visual inspection to be in accordance with the preapproved plan prior to storage in the fuel storage pool. Storage commences following unlatching of the fuel assembly in the fuel storage pool.
(continued)
Vogtle Units 1 and 2 B 3.7-99 Revision No.
I Fuel- Asse:bly-Storage in the Fuel Storage Pool B 3.7.18
-BASES-(continued)
REFERENCES 1. WCAP-14416-NP-A . Revision 1, " Westinghouse' Spent Fuel Rack Criticality Analysis Methodology," November 1996.
.Vogtle Units .1 and 2 B 3.7-100 Revision No.
ENCLOSURE 2 WESTINGIlOUSE WCAP-14720, REV. 3
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