ML20203H644
| ML20203H644 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/20/1998 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | Southern Nuclear Operating Co, Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20203H648 | List: |
| References | |
| NPF-68-A-99, NPF-81-A-77 NUDOCS 9803030279 | |
| Download: ML20203H644 (37) | |
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NUCLEAM REGULATORY COMMISSION WAsHINSToN, 0.c. asseHeM SOUTHERN NUCI EAR OPERATING COMPANY. INC.
GEORGIA POWER COMPANY OfM FTHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA VOGTLE El ECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILIW OPERATING LICENSE Amendment No. 99 License No. NPF48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
' A.
The application for amendment to the Vogtle Electric Generiting Plant, Unit 1 (the facility) Facility Operating License No. NPF48 filed by the Georgia Power Company and Southem Nuclear Operating Company, Inc. (Southem Nuclear),
acting for themselves, Calethorpe Power Corporation, Mur scipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated
' August 8,1997, as supplemer"ed October 10,1997, January 16, 23, and 27, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and reg'f.ations as set forth ln 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the
. public, and (ii) that such activPies will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfed.
DO 424 p
PDR u
2-2.
Accordingly, the license h hereby amended by page changes to the Techrkal Specifications as indicate, in the attachment to this license amendment, and paragraph 2.C.(2) of Facilit, Operating License No. NPF 68 is hereby amended to read as follows:
1 Technical Specifications and Environmental Protection Q30 l
The Technical Specifications contained in Appendix A, as revised through l
Amendment No. 99. and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southem Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION H bort N. Berkow, Director Project Directorate 112 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of lasuance: F e.'
ary 20, 1998
l p* %g\\
UNITED STATES g
g NU0 LEAR REGULATORY COMMIS810N WASHINGTON, D.C. speeHoM i.
i j
SOUTHERN NUCI FAR OPERATING COMPANY. INC.
P GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA 4'
CITY OF DALTON. GEORGIA VOGTLE ELECTRIC GENERATING PLANT. UNIT _2 l
AMENDMENT TO FACILITY OPERATING LICENE i
k Amendment No. 77 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Facility Operating Lloonse No. NPF-81 filed by the Georgia Power Company and Southem Nuclear Operating Company, Inc. (Southem Nuclear),
. acting for themselves, Oglethorpe Power Corporation, Municipal Electric.
Authority of Georgia, and City of Dalton, Georgia (the licensees), dated August 8,1997, as supplemented October 10,1997, January 16,23, and 27, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.'
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this e
amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; i
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 4-E.
The issuance of this amendment is in accordance with 10 CFR Pa:t Si of the 1
Commission's regulations and all applicable requirements have been satisfied, j
2-2.
Accdrdingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF 81 is hereby amended to read as follows:
Technical Snecifications and Environmental Protection Plan j
The Technical Specifications contained in Appendix A, as revised through Amendment No. 77, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southem Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ff 1kw He
. N. Berkow, Director Pr ject Directorate ll-2 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation
Attachment:
Technical Specificat!on Changes Date of lasuance: February 20, 1998
ATTACHMENT TO LICENSE AMENDMENT NO.99 FACILITY OPERATING LICENSE NO. NPF-88 DOCKET NO. 50-424 AblQ TO LICENSE AMENDMENT NO 77 FACILITY OPERATING LICENSE NO. NPF-B1 DOCKET NO. 50-425 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain verticallines indicating the areas of change.
Remove lated v
v vill viil lx 3.7 39 3.7 40 3.7-41 3.7-42 3,7 43 4.0-2 4.0-2 4.0 3 4.0-3
' 4.0-3a*
4.0-3b 4.0-4 4.0 5 4.0-6 4.0-7 4.0-8 4.0 9 4.0 10 4.0-11 4.0-12 Bases iv Bases iv B 3.7 92 B 3.7-93 B 3.7 94
l 2-Bem0MB M
B 3.7 95:.
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B 3.7 96 83.797
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B 3.7 98 83.799 t
B 3.7100*
- no change
. = =
=
TABLE OF CONTENTS (continued) i L.Z RLAKr$YSTEMS 3.7-1 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 Feedwatar Isolation Yalves (MFIVs) and Main i
Feedwater Regulation Valves (MFRVs) and Associated Bypas4 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 Condentate 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) 'iystem.........
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 Ct. iller System..........
3.7-35 3.7.15 Fuel Storage hol 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. 99 (Unit 1)
Amendment No. 77 (Unit 2)
9 TABLE OF CONTENTS (continued)
LIST OF 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 tystem Instrumentation 3.3-30 3.3.3-1 Post Accident Monitoring Instrumentatio........
3.3-42 3.3.4-1 Remote Shutdown System Instrumentation cn1 Controls 3.3-45 3.3.6-1 Containment Ventilation Isolation Instrumentation 3.3-53 3.3.7-1 CREFS Actuttion 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 Requiremer.ts.........
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 Inspection 5.0-19 LIST OF FIGUR63 2.1.1-1 Reactor Core Safety Limits..............
2.0-2 3.4.16-1 Reactor Coolant Dose Equi /alent I-131 Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specitic Activity > 1 pCi/ gram Dose Equivalent I-131
.4-44 3.7.18-1 Yogtle 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 "orage.................
3.7-43 4.3.1-1 Vogtle Unit 1 Burnup Credit Requirements for 3-cut-of-4 Storage................
4.0-4 4.3.1-2 Vogtle Unit 2 Burnup Credit Requirements for 3-out-of-4 Storage................
4.0-5 Vogtle Units 1 and 2 viii Amendment No.99 (Unit 1)
Amendment NO.77 (Unit 2)
TA8LE 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 i
4.3.1-5 Vogtle Unit 2 3x3 Cl.eckerbos+J Storage Configuration.
4.0-8 4.3.1-6 Vogtle Units 1 and 2 Interface Requirements (All Cell to Checkerboard Storage)........
4.0-9 4.3.1-7 Vogtla Units 1 and 2 Interface Requirements (Checkerboard Storage Interface).........
4.0-10 4.3.1-8 Vogtle Unit 2 Interface Requirements j
(3x3 Checkerboard to All Cell Storage)......
4.0-11 4.3.1-9 Vogtle Unit 2 Interface Requirements j
(3x3 to Empty Cell Checkerboard Storage).....
4.0-12 Vogtle Units 1 and 2 ix Amendment No. 99 (Unit 1) l Amendment No. 77 (Unit 2) m
Fuel Storage Pool Boron' Concentration 3.7.17 i
3.7 PLANT SYSTEMS 3.7.17 Fuel Storage Pool Boron Concentration LCO 3.7.17 The fuel storace pool boro 1 concentration shall be a: 2000 ppe.
APPLICABILITY:
When fuel assemblies are stored in the fuel storage pool.
4
$TIONS 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.
AND A.2.1 Inif N e action to Immediately res;.
fuel storage pool ooron concentration to within limit.
SURVEILLANCE REQUIREMENTS l
SURVEILLANCE FREQUENCY SR 3.7.17.l_
Verify the fuel storage pool bonn 7 days concentration is within limit.
Vogtle Units 1 and 2 3.7-39 Amendment No. 99 (Unit 1) l Amendment Nt,. 77 (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 be within the Acceptable Burnup Domain of Figures 3.7.18-1 (Unit 1), 3.7.18-2 (Unit 2), or in accordance with Specification 4.3.1.1.
3 APPLICABILITY:
Whenever any fuel assembly is stored in the fuel storage pool.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the A.1
NOTE---------
LCO not met.
LCO 3.0.3 is not applicable.
Initiate action to Immediately
+
move the noncomplying fuel assembly to an acceptable storage location.
Kl 9l Vogtle Units 1 and 2 3.7-40 Amendment No.99 (Unit 1)
[
d Amendment No.77 (Unit 2)
Fuel Assembly Storage in the Fuel Storage Pool 1
3.7.18
)
i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1
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.
l l
(
Vogtle Units 1 and 2 3.7-41 Amendment No. 99 (Unit 1) l Amendment No. 77 (Unit 2)
Fuel Assembly Storage in the Fuel Storage Pool 3.7.18
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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.99 (Unit 1)
Amendment No.77 (Unit 2)
Fuel Assembly Storage in the Fuel Storage Pool 3.7.18 50000 7
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Figure 2.7.18-2 Vogtle Unit 2 Burnup Credit Requirements for All Cell Storage Vogtle Units 1 and 2 3.7-43 Amesidment No.99 (Unit 1)
Amendment No.77 (Unit 2)
Design Features l
4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storago 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
l a.
Fuel assemblies having a a:.ximum U-235 enrichment-of 5.0 weight percint; l
b.
K,, < l.0 when fully flooded with unborated water wIiichincludesanallowanceforuncertaintiesas 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 tuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup donidn" of Figure 4.3.1-1 may be stored in the Unit I fuel storage pool in a 3-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4.
New or partially spant fuel assemblies with a maximum initial enrichment of 5.0 weight percent U-235 may be stored in the Unit I 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 I 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.99 (Unit 1)
Amendment No. 77 (Unit 2) y
Design Features 4.0
{
4.0 DESIGN FEATURES
-4.3.
Fuel Storage (continued) combination of burnup and initial nominal
- l enrichment in the " acceptable burnup domain" of Figure 3.7.18-1.
"B" assemblies are new or i
partially spent fuel assemblies with a combination.
I of burnup and initial nominal-enrichment in the "acce) table burnup domain" of Figure 4.3.1-1.
"C"
.assem> lies are assemblies with initial enrichments.
up to a maximum of-5.0 weight percent U-235.
l New'or partially spent fuel assemblies with a combination of burnup and initial nominal l
l enrichment in the " acceptable burnup domain" of l
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 or partially spent fuel assemblies with a-l maximum initial enrichment of 5.0 weight percent; 1
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 stored 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 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 66'F may be stored in the Unit 2 fuel storage pool:as "high enrfchment" fuel assemblies in the 3x3 checketboard 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)
Vogtie Units 1 and 2 4.0-3 Amendment No.99 (Unit 1)
Amendment No.77 (Unit 2)
Design Features 4.0 4.0 DESIGN FEATllRES 4.3 Fuel Storage (continued) initial nominal enrichment in the "acceptab1c-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 assen:alies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-3.
"H" assemblies l
are new or partially spent fuel assemblies with l
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 eaual to 1
l 1.410 at 68'F.
L f.
A nominal 10.6 inch center to center pitch in the l
[.
Unit I high density fuel storage racks; and l
9 A nominal 10.58-inch center to center-pitch in the l
north-south direction and a nominal 10.4-inch L
center to center pitch in the east-west direction in the Unit 2 high density fuel storage-racks.
4.3.1.2 The new fuel storage racks are designed and shall be mairtained with:
Fuel assemblies having a maximum U-235 enrichment a.
of 5.05 weight percent; J
b.
k.,, s 0.95 if fully flooded with unborated water, which includes.an 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 between fuel assemblies placed in the storage racks.
Vogtle Units 1 and 2 4.0-3a Amendment No.99 (Unit 1)
Amendment No.77 (Unit 2) c._--
Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.2 Drainaoe 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.
i 4.3.3 Canacity Tlie 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 Vogtle Units 1 and 2 4.0-3b Amendment No. 99 (Unit 1)
Amendment No. 77 (Unit 2)
Design Features 4.0 30000 l
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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. 99 (Unit 1)
Amendment No. 77 (Unit 2)
Design Features 4.0
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Figure 4.3.1-2 Vogtle Unit 2 Burnup Credit Requirements for 3-out-of-4 Storage Vogtle Units 1 and 2 4.0-5 Amendment No. 99 (Unit 1)
Amendment No. 77 (Unit 2)
Design Features 4.0 50000 t
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Figure 4.3.1-3 Vogtle Unit 2 Burnup Credit Requirements for 3x3 Storage
. Vogtle Units 1 and 2 4.0-6 Amendment No.99 (Unit 1)
Amendment No.77 (Unit 2) g.
Design Features 4.0 Z Z Z Z Z Z Z X
~
Z Z
Z l2
=
Z Z Z Z Z' E Z E Z
Z Z
Z 3-out of-4 Checkeiboard Storage i
l Z
Z l
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2-out of 4 Checkerboard Storage Empty Storage Cell Fuel Assembly in Storage Cell Figure 4.3.1-4 Vogtle Units 1 and 2 Empty Cell Checkerboard Storage Configuraticns Vogtle Units 1 and 2 4.0-7 Arc.endment No. 99 (Unit 1)
Amendment No. 77 (Unit 2) 1
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liigh Enrichment Fuel O
Assembly in Storage Cell Assembly in Storage Cell I
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Figure 4.3.1-5 Vogtle Unit 2 3x3 Checkerboard Storage Configuration 1
'J Vogtle Units 1 and 2 4.0-8 Amendment No.99 (Unit 1)
Amendment No.77 (Unit 2)
Design Features 4.0 A
A lA A
A A
Note:
A A
A A
A A
Am AH Ceu Interface Endchment
\\
A A-A A
N A
8 " 3'
"04 Endchment
-~
Empty = Empty Cell Empty B
Empty A
A A
I B
B B
A A
A 4
Empty B
Empty,
A A
A l
a Boundary Between All Cell Storage and 3-out-of-4 Storage t
A A
A A
A A
Note:
A A
A A
A A
A = AU CeH Interface Endchment N
A A
A A
A A
- n. Soute I
Endchment a_
C = 2 Out Of-4 Empty B
Empty i A
A A
Endchment Empty = Empty Cell C
Empty B'
A A
A Empty C
Empty A
A A
1 e
Boundary Between 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 assembly 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.99 (Unit 1)
Amendment No.77 (Unit 2)
Design Features 4.0 B
Empir B
Empiy B
Empty Note:
B B
B B
B B
s. 3. oui.o u Enrichment B
Empiy B
Empty D
Empiy c
- 2. oui oM Enrichment
=m.
Empt> = Empty Cell Empty C
Empty B
B B
C Empty C'
Empty B ' Empty Empty C
Empty B
B B
1 s
Boundary Between 2-out-of-4 Storage and 3-out-of-4 Storage Empty B
Empty B
B B
Note:
B B
B, B
En.pty B
a - 3.out.ow Enrichment Empty B
Empty' I. 'B.,
1.B.
B c. 2.out.o w Enrichment a _.
Empty = Empty Cell C
Empty CI Empty B'
.Empiy Empty C
Empty '
B B
.B C
Empy C
Empty B
Empty s
Boundary Between 2-out-of-4 Storage and 3-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 assembly with an empty cell.
Figure 4.3.1-7 Vogtle Units 1 and 2 Interface Requiretoents (Checkerboard Storage Interface)
Vogtle Units 1 and 2 4.0-10 Amendment No. 99 (Unit 1)
Amendment No. 77 (Unit 2) l
Design features 4.0 A
A A
A A
A Note:
A A
A A
A A
A = All Ceu Enrichawat L = Low Enrichment of
==
N L
L L
L A
A 3x3 Chrckerboard a_
II = High Enrichment of 3x3 Checkerboard L
L Ll L
A A.
l L
H L
L A
A
.l L
L L,
L,A A
a Note:
I
- 1. A row of empty cells can be used at the interface to separate the con 6gurations.
- 2. It is acceptable to replace an assemb!y with an empty cell.
Figure 4.3.1-8 Vogtle Unit 2 Interface Requirements (3x3 Checkerboard to All Cell Storage)
Vogtle Units 1 and 2 4.0-11 Amendment No.99 (Unit 1)
Amendment No.77 (Unit 2)
Design Features 4.0 B
B B
B B
B*
N:
B = 3 Out Of-4 Empn B
Empty B
Empo B
, [e at Interface N
L L
L L
B B
ofs 3 sionne H = High Enrichment L
L Ll L
tm,n B
of 3:3 stonne Empty = Empty Celt L
H Li L
B B
L L
Li L
tmpo B
i a-Boundary Between 3x3 Storage and 3-out-of-4 Storage Note:
- est, c
em,o c
tm.,
c tm,n Empn B
Empn B
Empre C
L = Low Enrichment of 3:3 Storage Integce I,
L*
- L L*
- B tmpo
" " " *h Ea ment "2
f 3,3 s, i
C = 2-Out Of-4 L
L Ll L
trepo C
Enrichment
"" W"#
L H
L L*
- B tmpn L
L Li L
t=po C
i a
Boundary Between 3x3 Storage and 2-out-of-4 Storage Note:
- 1. \\ row 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.
- 3. For the 3-out-of-4 con 6guration, the row beyond the Low e.rrichment can swap empty and B assemblies, howeser 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 assemHies must also swap locations.
- 5. If empty cells are in indicated locations (**), then the face adjacrnt B assemblies can be C assemblies.
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 No. 99 (Unit 1)
Amendment No. 77 (Unit 2)
TABLE OF CONTENTS 1_L.I PLANT SYSTEMS
.................... B 3.7-1 B 3.7.1 Main Steam hafety Valves (MSSVs)........... B 3.7-1 B 3.7.2 Main Steam isolation Valves (MSIVs)
......... B 3.7-7 B 3.7.3 Main Feedwater isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves.............. B 3.7-14 8 3.7.4 Atmospheric Relief Valves (ARVs)........... B 3.7-21 8 3.7.5 Auxiliary Feedwater (AFW) System........... B 3.7-25 B:3.7.6 Condensate Storage Tank (CST)
............ B 3.7-35 R 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 8 3.7.9 Ultimate Heat Sink (UHS)............... B 3.7-50 8 3.7.10 Control Room Emergency Filtration System (CREFS) -
Both Units Operating
............ B 3.7-55 l
8 3.7.11 Control Room Emergenc' ion System (CREFS)' -
One Unit Operatir.,..
............. B 3.7-64 8 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 Exhaut.t System (PPAFES)
................. B 3.7-75 B 3.7.14 Engineered Safety Feature (ESF) Aoom Cooler and Safety-Related Chiller System.......... B 3.7-80 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 B 3.7.1B Fuel A:sembly Storage in the Fuel Storage Pool.... B 3.7-97 (continued)
Vogtle Units-1 and 2 iv Amendment No. 99 (Unit 1)
Amendment No. 77 (linit 2)
Fuel Storage Pool Boron Concentration B 3.7.17 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 b'urnup-enrichment combinations are within the limits that are specified in Figuras 3.7.18-1 (Unit 1) or 3.7.18-2 (Unit 2) of th Technical Specifications.
Fuel assemblies that do not meet the burnup-enrichment combination of Figures 3.7.18-1 or 3.7.18-2 may be stored in the storage pools of Units I 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 computer code benchmarking, spent fuel l
rack criticality calculations methodology, reactivity l
equivalencing methodology, accident methodology, and soluble i
boron credit methodology.
The Westinghouse Spent Fuel Rack Criticality Methodology ensures that the multi)11 cation factor, K.,,, of the fuel and spent fuel storage rac(s is less than or squal to 0.95 as recommended by ANSI 57.2-1983 (Reference 3) and NRC guidance (References 1, 2 and 6).
The codes methods, and techniques contained in the methodology are use,d to satisfy this criterion on K.,,.
The methodology of the NITAWL-II, XSDRNPM-S, and KENO-Va codes is used to establish the bias and bias uncertainty.
PHOENIX-P, a nuclear design code used primarily for core reactor physics calculations is used to simulate spent fuel storage rack geometries.
(continued)
Vogtle Units 1 and 2 B 3.7-92 Amendment No. 99 (Unit 1)
Amendment No. 77 (Unit 2) e
Fuel Storage Pool Boron Concentration B 3.7.17 BASES BACKGROUND Reference 4 describes how credit for fuel storage pool (continued) soluble boron is used under normal storage configuration conditions. 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 4lio ppa 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 depletion 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 torage of fuel with initial enrichments up to and including 5.0 weight percent U-235 in the Vogtle fuel storage pools. The resulting enrichment, and burnup limits for the ' nit I and J
i Unit 2 pools, respatively, are shown in Figures 3.7.18 and 3.7.18-2.
Gwdarboard storage configurations are defined to allow d erage of fuel that is not within the acceptable burnup domain of Figures 3.7.18-1 and 3.7.18-2.
These f.torage requirements are shown in Figures 4.3.1-1 through 4.3.1-9.
A boron concentration of 2000 ppm assures that no credible dilution event will. result in a K.,, of
> 0.95.
L
!,PPLICABLE
- Most' fuel storage pool accident conditions will not result SAFETY ANALYSES in an increase in K Examples of such accidents are the drop of a fuel asse.,,.mbly on top of a rack, and the drop of a fuel assembly between rack modules, or between rack modules and the pool wall.
From a criticality standpoint, a dropped assembly accident occurs when a fuel assembly in 'ts most reactive condition is dropped onto the storage racu. 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 end 2 B 3.7-93 l4nendment No. 99 (Unit 1)
Amendment No. 77 (Unit 2)
Fuel Storage Pool. Boron Concentration B 3.7.17 BASES APPLICABLE active fuel height of stored assemblies to preclude SAFETY ANALYSES 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 analyzed 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 assembly into an already loaded cell. The third would be the misloading of a fuel assembly into a cell for which the restrictions on location, enrichment, or burnup are not satisfied.
An in.rease in the temperature of the water passing through the stored fuel assemblies causes a decrease-in water density which would normally result in an addition of negative reactivity. However, since Boraflex is not considered to be present and-the fuel storage pool water has a high concentration of boron, a density decrease causes a-positive reactivity addition. The reactivity effects of a temperature range from 32*F to 240*F were evaluated.
The increase in reactivity due to the increase in temperature is t
bounded by the misload accident.
For the accident of dropping a fuel assembly Nto an already-loaded cell, the upward axial leakage of that cell will be reduced, however, the overall effect on the rack reactivity will be insignificant.
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 significant increase in reactivity.
Furthermore, the neutronic coupling between the dropped assembly and the already loaded assembly will be low due to several inches of assembly nozzle structure wMeh would separate the active fuel regions. Therefore, thu accident would be bounded by the misload accident.
The fuel assembly mis!nading 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 pusitive reactivity, increasing K,, toward 0.95.
The (continued)
Vogtle Units 1 and 2 B 3.7-94 Amendment No. 99 Unit 1 Amendment No. 77 Unit 2
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 ppa for Unit 2, and 1150 ppe for Unit I which (continued) is well below the limit of 2000 ppa.
l The concentration of dissolved boron in the fuel storage pool satisfies Criterion 2 of the NRC Policy Statment.
LC0 The fuel storage pool boron concentration is required to be 1 2000 ppa. The specified concentration of dissolved boron in the fuel storage pool preserves the assumptions used in the analyses of the potential criticality aufdent 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 l
configurations. That evaluation established the amount of soluble boron necessary to ensure that K maintained less than or equal to 0.95 sh,, will be l
ould pool temperature exceed the assumed range or a fuel assembly misload occur.
The amount of soluble boron necessary to i
mitigate these events was determined to be 1250 ppm for Unit 2 and 1150 ppm for Unit 1.
The specified minimum baron 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 I and 500 ppm for Unit 2.
APPLICABILITY This LCO applies whenever fuel assemblies are stored in the spent fuel storage pool.
ACTIONS A J. A.2.1. and 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 or to mitigate the consequences of an accident in progress.
This is most (continued)
Vogtle Units 1 and 2 B 3.7-95 Amendment No. 99 (Unit 1)
Amendment No. 77 (Unit 2)
9 e
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 slicable.
If moving irradiated fuel assemblies while in M00E 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 REQUIRENENTS l
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 place over such a short period of time. The gate between the Unit I and Unit 2 fuel storage pool ic 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 l
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 Amandment No. 99 (Unit 1)
?mendment No. 77 (Unit 2)
Fuel Assembly Storage in the Fuel Storage Pool 8 3.7.18 8 3.7 PLANT SYSTEMS 8 3.7.18-Fuel Assembly Storage in the Fuel Storage Pool BASES BACKGROUND 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 an enrichment of up to and including 5.0 weight percent U-235 can be s:ored 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 Westinghoure Spent Fuel Rack l
Criticality Methodology, described in WCAP-14416-NP-A, Rev. 1 (reference 1). Additional background discussion can i
be found in 8 3.7.17.
l Westinghouse 17x17 fuel assemblies with nominal enrichments no greater than 1.79 w/o'"U may be stored in all storage cell locations of the Unit 1 pool.
Fuel assemblies with initial nominal 6.,
.hment greater than 1.7g w/o*"U must satisfy a minimum turnup requirement as shown in Figure 3.7.18-1.
Westinghouse 17x17 fuel assemblies with nominal enrichments no greater-than 2.45 w checkerboard arrangemen/o'"U may be stored in a 3-out-of-4 t with empty cells in the Unit 1 pool.
Fuel assemblies with initial norainal enrichment greater than 2.45 w/o'"U must satisfy a minimum burnup requirement as shown in Figurc 4.3.1-1.
Westinghouse 17x17 fuel assemblies with nominal enrichments no greater that 5.0 w checkerboard arrangemen/o'"U may be stored in a 2-out-of-4 t 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 burpup requirement as shown in Figure 3.7.18-2.
(continued)
Vogtle Units 1 and 2 B 3.7-97 QQQQ{ Q % h[ h
Fuel Assembly Storage in the Fuel Storage Pool B 3.7.18 BASES-BACKGROUND-Westinghouse 17x17 fuel assemblies with nominal enrichments (continued) no greater than 2.40 w checkerboard arrangemen/o"'U may be stored in a 3-out-of-4 t 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 assen.olies may be stored in the Unit 2 pool in a 3x3 array.
The center assembi aninitialenrichmentnogreaterthan3.20w/o'gmusthave U.
Alternatively the center of the 3x3 array may be loaded with any assem,bly 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 nominal 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 Most 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 asse$bly on top of a rack and the drop of a fuel assembly between rack modules or between rack modules and the pool wall.
However, accidents can be pestulated for each stcrage configuration which could increase reactivity beyond the analyzed condition. A discussion of these accidents is contained in B 3.7.17.
The configuration cf fuel assemblies in the fuel storage pool satisfies Criterion 2 of the NRC Policy Statement.
LC0 Yne restrictions c: 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 3.7.18-1 and 3.7.18-2 for all cell storage in the Unit I and Unit 2 pools, respectively.
Other acceptaole enrichment burnup and checkerboard combinations are described in Figures 4.3.1-1 through 4.3.1-9.
(continued)
Vogtle Units 1 and 2 B 3.7-98 Amendment No. 99 (Unit 1)
Amendment No. 77 (Unit 2)
Fuel Assembly Storage in the Fuel Storage Pool B 3.7.18 BASES (continued)
APPLICA8ILITY This LCO applies whenever any fuel assembly is stored in the fuel storage pool.
ACTIONS L,1 Required Action A.) is modified by a Not.e indicating that LC0 3.0.3 does not-apply.
When the configuration of fuel assemblies stored in the fuel storage pool is not in accordance with the acceptable-combination of initial enrichnent, 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), 3.7.1C. (Unit 2), or Specification 4.3.1.1.
If unable to move irradiated fue's assemblie's 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 co -sistent with the specified fuel enrichment, burnup, and storage configurations.
These plans are administrative 1y verified prior to fuel movement.
Each assembly is verified by visual inspection to be in ar.cordance 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)
('N'N hhn" Vogtle Units I and 2 8 3.7-99
Fuel Assembly Storage in the Fuel Storage Pool i
B 3.7.18 BASES (continued)
REFERENCES 1.
WCAP-14416-NP-A, Revision 1, " Westinghouse Spent Fuel 4
Rack Criticality Analysis Methodology," November 1996.
Vogtle Units 1 and 2 B 3.7-100 Amendment No. 99 (Unit 1)
Amendment No. 77 (Unit 2)
-