ML20236F891
| ML20236F891 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/29/1998 |
| 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 | |
| ML20236F894 | List: |
| References | |
| NPF-68-A-102, NPF-81-A-080 NUDOCS 9807060004 | |
| Download: ML20236F891 (32) | |
Text
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UNITED STATES p
NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. SegeMOD1 i
SOUTHERN NUCI FAR OPERATING COMPANY. INC.
L GEORGIA POWER COMPANY i
I' OGLETHORPE POWER CORPORATION s
MUNICIPAL Fl FCTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA VOGTLE Ft FCTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. NPF-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 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 September 4,1997, as supplemented by letters dated November 20,1997, May 19 and June 12,1998, 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 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; 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 satisfied.
9907060004 990629 PDR ADOCK 05000424 P
- PDR,
_ - _ _ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ 2.
Accordingly, 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-68 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.102, 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.
In addition, paragraph 2.C.(10) to Facility Operating License No. NPF-68 is hereby amended to read as follows:
(10)
Additional Conditions The Additional Conditions contained in Appendix D, as revised thr$ ugh Amendment No. 102.
, are hereby incorporated into this license.
Southem Nuclear shall operate the facility in accordance with the Additional Conditions.
3.
This license amendment is effective as of its date of issuance and shall be implemented on a schedule consistent with the receipt and storage of new fuel in the fall of 1998, for the spring 1999 refueling outage of Vogtle Unit 1.
FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berlkow, Director roject Directorate ll-2 Division of Reactor Projects - till Office of Nuclear Reactor Regulation Attachments:
- 1. Appendix D Changes i
- 2. Technical Specification
. Changes Date ofissuance:
June 29,1998 I
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NUCLEAR REGUL.ATORY COMMISSION wAsHWGTON, D.C. sages eun
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SOUTHERN UCI FAR OPERATING COMPANY. INC.
N GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL FI FCTRIC AUTHORITY OF GEORGIA y
CITY OF DALTONI GEORGIA i::
l
' VOGTLE FI FCTRIC GENERATING PLANT. UNIT 2 4
AMENDMENT TO FACILITY OPERATING LICENSE l
l Amendment No.80 '-
' License No. NPF-81 l.
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 2 i
(the facility) Facility Operating License No. NPF-81 filed by the Georgia Power c
' 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 SMember 4,1997, as supplemented by letters dated November 20,1997, L
May 19 and June 12,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and f aulations as set forth in 10 CFR Chapter I; P
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; o
C.
There is reasonable assurance (i) that the activities authorized by this I
amendment can be conducted ' ithout endangering the health and safety of the w
public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.'
The iss'uance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and o
E.'
The issuance of this amendment is in accordance with 10 CFR Part 51 of the O
Commission's regulations and a!! applicable requirements have been satisfied.
I L
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=-
. _ -. 1 2.
Accordingly, 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 Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 80
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with th9 Techriical Specifications and the Environmental Protection Plan.
In addition, paragraph 2.C.(3) to Facility Operating Lioanse No. NPF-81 is hereby amended to read as follows:
(3)
Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 80. are hereby incorporated into this license. Southem Nuclear shall operate the facility in accordance with the Additional Conditions.
3.
This license amendment is effective as of its date of issuance and shall be implemented on a schedule consistent with the receipt and storage of new fuel in the fall of 1998 for the spring 1999 refueling outage of Unit 1.
FOR THE NUCLEAR REGULATORY COMMISSION bl
)'
He rt N. Berkow, Director Project Directorate ll-2 Division of Reactor Projects -1/11 -
Office of Nuclear Reactor Regulation i
U Attachments:
- 1. Appendix D Changes 2.' Technical Specification j
Changes i
f i
Date ofissuance:
June 29, 1998 i-I h
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ATTAChA#.NT TO LICENSE AMENDMENT NO.102 FACILITY OPERATING LICENSE NO. NPF-88 DOCKET NO. 50-424 AblQ TO LICENSE AMENDMENT NO. 80 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace Appendix D of Facility Operating License Nos. NPF-68 and NPF-81 with the enclosed revised Appendix D.
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identihed by Amendment number and contain vertical lines indicating the areas of change.
Remove Insert viii viii ix lx 3.7-40 3.7-40 3.7-41 3.3-41 3.7-42 3.7-42 4.0-2 4.0 2 4.0-3 4.0-3 4.0-3a 4.0-3a 4.0-3b 4.0-3b 4.0-4 4.0-4 4.0-7 4.0-7 4.0-9 4.0-9 4.0-10 4.0-10 B 3.7-92 8 3.7-92 l-B 3.7-93 B 3.7-93 B 3.7-94 8 3-7-94 8 3.7-95 B 3.7-95 B 3.7-97 B 3.7-97 B 3.7-98 8 3.7-98 B 3.7-99 B 3.7-99 fE _ -_
l
APPENDIX D ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-88 Amendment Implementation Number 6dditional Condition Date 100 The licensee shall implement a procedure that Prior to '
will prohibit entry into an extended Emergency Diesel implementation of Generator Allowed Outage Time (14 days), for Amendment scheduled maintenance purposes, if severe weather No.100 conditions are expected, as described in the licensee's
. application dated January 22,1998, as supplemented by letter dated March 18,1998, and evaluated in the stafs Safety Evcluation dated May 20,1998.
102 The spent fuel pool heat loads will be managed by Before administrative controls. These controls will be transferring irradiated placed in applicable procedures as described in fuelinto the Unit 1' the licensee's letters dated September 4,1997, spent fuel pool May 19 and June 12,1998, and evaluated in the stars Safety Evaluation dated June 29,1998.
102 The UFSAR will be updated to include the heat To be included in load that will ensure the temperature limit of 170*F will the next appropriate not be exceeded, as well as the requirement to perform UFSAR update
- a heat load evaluation before transferring irradiated fuel following the to either pool, as described in the licensee's letters dated installation of the September 4,1997, May 19 and June 12,1998, and Unit 1 spent fuel L
evaluated in the stafs Safety Evaluation dated racks June 29,1998.
102 A temporary gantry crane, with a hoist rated for 20 tons, Before commencing will be erected on the existing fuel handling bndge rails reracking operations
[l to move the racks within the spent fuel pool area, as described in the licensee's letters dated September 4, 1997, May 19 and June 12,1998, and evaluated in the stafs Safety Evaluation dated June 29,1998.
(
Amendment No.102
! Amendment implementation Number Additional Condition Date 102 The licensee will implement all applicable crane, Before and during l
load path and height, rigging and lo i testing guidelines reracking operations,
)
of NUREG 0612 and ANSI Standard B30.2, as described as appropriate in the licensee's letters dated September 4,1997, May 19 l J!:
and June 12,1998, and evaluated in the staffs Safety Evaluation dated June 29,1998.
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Amendment No.102
APPENDIX D ADDITIO'NAL CONDITIONS 1
FACILITY OPERATING LICENSE NO. NPF-81 Amendment implementation Number Additional Condition Date l
78 The licensee shall implement a procedure that Prior to will prohibit entry into an extended Emergency Diesel implementation of Generator Allowed Outage Time (14 days), for Amendment I
scheduled maintenance purposes, if severe weather No. 78 l
conditions are expected, as described in the licensee's application dated January 22,1998, as supplemented l
by letter dated March 18,1998, and evaluated in the staffs Safety Evaluation dated May 20,1998.
80
. The UFSAR will be updated to include the heat To be included in I
load that will ensure the temperature limit of 170*F will the next appropriate not be exceeded, as well as the requirement to perform UFSAR update a heat load evaluation before transferring irradiated fuel following the to either pool, as described in the licensee's letters dated installation of the September 4,1997, May 19 and June 12,1998, and Unit 1 spent fuel l
evaluated in the staffs Safety Evaluation dated racks June 29,1998.
l 1-l' l
l l
Amendment No. 80
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 Inspection 5.0-19 LIST OF FIGURES 2.1.1-1 Reactor Core Safety Limits..............
2.0-2 3.4.16-1 Reactor Coolant Dose Equivalent I-131 Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specific Activity > 1 pCi/ gram Dose Equivalent I-131 3.4-44 3.7.18-1.
Vogtle Unit 1 Burnup Credit Requirements for l
All Cell Storage.................
3.7-42 3.7.18-2 Vogtle Unit 2 Burnup Credit Requirements for All Cell Storage.................
3.7-43 i
4.3.1-1 Deleted.......................
4.0-4 l
l i
4.3.1-2 Vogtle Unit 2 Burnup Credit Requirements for 3-out-of-4 Storage................
4.0-5 l
Vogtle Units 1 and 2 viii Amendment No.102 (Unit 1)
Amendment No. 80 (Unit 2)
_ ________j
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 I and 2 Interface Requirements (All Cell to Checkerboard Storage)........
4.0-9 4.3.1-7 Vogtle Unit 2 Interface Requirements l
(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 Vogtle Units 1 and 2 ix Amendment No.102 (Unit 1)
Amendment No. 80 (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 (Unit 1) or 4).3.1.2 (Unit 2).
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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---------
LC0 not met.
LCO 3.0.3 is not applicable.
Initiate action to Immediately move the noncomplying fuel assembly to an acceptable storage location.
Vogtle Units 1 and 2 3.7-40 Amendment No.102 Unit 1)
Amendment No. 80 ((Unit 2)
Fuel Assembly Storage in the Fuel Storage Pool 3.7.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 Specification 4.3.1.1 location.
(Unit 1) or 4.3.1.2 (Unit 2).
l i
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i 4
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[
Vogtle Units I and 2 3.7-41 Amendment No. 102(Unit 1)
Amendment No. 80(Unit 2)
Fuel Assembly Storage in the Fuel Storage Peol 3.7.18 15000 a
o 10000 ACCEPTABLE
.g
/
5
/
E r
N l
/
=
/
4
/
5000
/
/
/
/
/
UNACCEPTABLE --
1
/
0 3.0 3.5 4,o 4.5 5.0 Initial U-235-Enrichment (nominal w/o)
I I
figure 3.7.18-1 te n Burnup Credit Requirements for l
l-Vogtle Units I and 2 3*7-42' Amendment No.102 (Unit 1)
Amendment No. 80 (Unit 2) l 1
l Design Features l
4.0 l
4.0 CESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality l
I l
(Unit 1) 4.3.1.1 The spent fuel storage racks are designed and shall be l
maintained with:
a.
Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;
)
i b.
K,,, < l.0 when fully flooded with unborated water i
which includes an allowance for uncertainties a*
described in Section 4.3 of the FSAR.
c.
K.,, s 0.95 when fully flooded with water borated to 600 ppm, which includes an allowance for 4
uncertainties as described in Section 4.3 of the FSAR; i
d.
New or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 3.7.18-1 or having a maximum reference fuel assembly roo less than or equal to 1.431 at 68'F may be allowed unrestricted storage in the Unit I fuel j
storage pool.
L e.
New or partially spent 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 3-out-of-4 checkerboard storage configuration l.
as shown in Figure 4.3.1-4.
l l
Interfaces between storage configurations in the Unit I fuel storage pool shall be in compliance with Figure 4.3.1-6.
"A" assemblies are new or l
L partially spent fuel assemblies with a combination l
of burnup and initial nominal enrichment in the
" acceptable burnup domain" of Figure 3.7.18-1, or which have a maximum reference fuel assembly roo less than or equal to 1.431 at 68'F.
"B" assemblies are assemblies with initial enrichments up to a maximum of 5.0 weight percent U-235.
(continued)
Vogtle Units 1 and 2 4.0-2 Amendment No.102 (Unit 1)
Amendment No. 80(Unit 2)
L.
Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) l f.
A nominal 10.25 inch center to center pitch in the l
Unit I high density fuel storage racks.
(Unit 2) 4.3.1.2 The spent fuel storage racks are designed and shall be l
maintained with:
l a.
Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; b.
K.,, < 1.0 when fully flooded with unborated water which includes an allowance for uncertainties as described in Section 4.3 of the FSAR.
c.
K.,, s 0.95 when fully flooded with water borated to 500 ppm, 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 Figure 3.7.18-2 may be allowed unrestricted storage l
in the Unit 2 fuel storage pool.
I e.
New or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-2 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 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 stored in the Unit 2 fuel (continued)
Vogtla Units I and 2 4.0-3 Amendment No.102(Unit 1)
Amendment No. 80 (Unit 2)
i Design Features 4.0 4.0 ' DESIGN FEATURES 4.3 Fuel Storage (continued)
. 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 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 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 enrichment 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 10.58-inch center to center pitch in the l
north-south direction and a nominal 10.4-inch center to center pitch in the east-west direction in the Unit 2 high density fuel storage racks.
(continued) 4 TVogtle' Units 1 and 2 4.0-3a Amendment No.102 (Unit 1)
Amendment No. 80 (Unit 2)
L___-______-_-________-
Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.1.3 The new fuel storage racks are designed and shall be l
L 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, which includes an allowance for uncertainties as described in Section 4.3 of tne 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.
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 Caoacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1476 fuel l
assemblies in the Unit I storage pool and no more than 2098 fuel assemblies in the Unit 2 storage pool.
Vogtle Units 1 and 2 4.0-3b Amendment No.102 (Unit 1)
Amendment No. 80 (Unit 2)
Design Features 4.0 L
\\
l l
l
\\
(This figure has been deleted.)
l 1
l r-l Figure 4.3.1-1 Vogtle Unit 1 Burnup Credit Requirements for 3-out-of-4 Storage Vogtle Units 11and 2 4.0-4 Amendment No.102 (Unit 1)
Amendment No. 80 (Unit 2)
Design Features 4.0 Z Z Z Z Z Z Z Z Z Z Z Z Z Z YY Z
Z Z
Z 3-out-of-4 Checkerboard Storage (Units 1 and 2)
L--
j g
g Z
Z E
Z 2-out-of-4 Checkerboard Storage (Unit 2) l Empty Storage Cell Fuel Assembly in Storage Cell i
Figure 4.3.1-4 Vogtle Units I and 2 Empty Cell Checkerboard Storage Configurations Vogtle Units I and 2 4.0-7 Amendment No.102 (Unit 1)
Amendment. No. 80 (Unit 2)
Design Features 4.0 A
A A
A A
A Note:
A A
A A
A A
A = An ceu Interface Enrichment
\\
A A
A A
A A
8
- 3 0"'-O' 4 Enrichment
~-
Empty = Empty Ceu Empty B
Empty A
A A
B B
B A
A A
E.,ey B
E.,ey ;
A A
A i
s Boundary Between All Cell Storage and 3-out-of-4 Storage (Units 1 and 2) f l
A A
A A
A A
Nota:
A A
A A
A A
A = AB CeB l
Interface Enrichment N
A-A A
A A
A a
3 m a.4 Enrichment C = 2.out-or.4 l
Empty B
E.,ey !
A A
A Enrichment Empey = Empty Ceu C
mm B
A A
A Empty C
Emptyj A
A A
l l
s Boundary Between All Cell Storage and 2-out-of-4 Storage (Unit 2)
Note:
l
- 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) l Vogtle Units 1 and 2 4.0-9 Amendment No.102 (Unit 1) l Amendment No. 80 (Unit 2) i
Design Features 4.0 3l B
Empir B
Empiy B
Emp:
Note:
B B
B B
B B
a. 3.o..or :
Interface Enrichment B
Empty B
Empty B
Emp,,-
- c. 2.out.or-4 s,
Empty = Empty Cell Eatichment Empty C
Empty B
B B
C Emper C
En,iy B
En,y Empty C
Empty B
B B
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
Empty B
a - 3.out.or.4 y
Enrichment Empty B
Empty B
B B
c-2.om.or.4 ent Empty = Empty Cell C
Emper CI Emper B
Empey Empty C
Empty B
B B
C Empty C
Empty B
Empty i
a Boundary Between 2-out-of-4 Storage and 3-out-of-4 Storage Note:
I
- 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.
i Figure 4.3.1-7 Vogtle Unit 2 Interface Requirements (Checkerboard Storage Interface)
Vogtle Units I and 2 4.0-10 Amendment No.10280 (Unit 1)
Amendment No.
(Unit 2) l
/
Fuel Storage Pool Boron Concentration B 3.7.17 B 3.7 PLANT SYSTEMS B 3.7.17 Fuel Storage Pool Boron Concentration l-BASES BACKGROUND Fuel assemblies are stored in high density racks. The Unit'l spent fuel.' storage racks contain storage locations for 1476 fuel assemblies, and the Unit 2 spent fuel storage l-racks contain storage locations for 2098 fuel assemblies.
The Unit I racks use boral as a neutron absorber in a flux
. trap design.- The Unit 2 racks contain Boraflex, however, no credit is taken for Boraflex.
. westinghouse 17x17 fuel.
W
. 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.'
Figures 3.7.18-1 or 3.7.18-2 may be stored in the storage
' pools of. Units 1 or 2 in accordance with checkerboard -
. storage configurations described in Figures 4.3.1-2 through l
'(
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 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 ANSI 57.2-1983 (Reference'3) and NRC guidance (References 1,'2 and 6). The codes, methods, and techniques contained in the methodology are used.to satisfy this
- i. 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.
L (continued)
Vogtla Units.l'and 2 B 3.7-92 Amendment No. 102 (Unit 1)-
Amendment No. 80 (Unit 2) s.
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 600 ppm and the Unit 2 pool l
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 storage 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 Unit 1 and Unit-2 pools, respectively, are.shown in Figures 3.7.18 i 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 4.3.1-2 l
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.
APPLICABLE 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 assembly 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 its most reactive condition is dropped onto the storage racks. The rack structure from a criticality standpoint is not excessively deformed.
l 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 l
E.
(continued)
/
Vogtle Units 'I and 2 B 3.7-93 Amendment No.102 (Unit 1)
Amendment No. 80 (Unit 2)
L Fuel Storage Pool Boron Concentration B 3.7.17
. BASES l
i 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 increase in the temperature of the water passing through the stored fuel assemblies causes a decrease in water density which results in an addition of negative reactivity I
for flux trap design racks such as the Unit I racks.
However, since Boraflex is not considered to be present for
~ the Unit 2 racks and the fuel storage-pool water ~ has n' high concentration of boron, a density decrease causes a positive.
reactivity addition. The reactivity effects of a 1.
. temperature range from 32*F to 240*F were evaluated. The i
increase in reactivity due to the increase in temperature is bounded by the misload accident, for the Unit 2 racks. The increase in reactivity due to the decrease in temperature below 50*F is bounded by the misplacement of a fuel assembly between the rack and pool walls for the Unit I racks.
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 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 which would separate the active
. fuel regions. Therefore, this accident'would be bounded by the misload accident.
o (continued) i
~
Amendment No.102 (Unit 1 Vogtle. Units l'and 2 B 3.7-94 Amendment No. 80 (Unit 2 f
l I
l
Fuel Storage Pool Baron Concentration B 3.7.17 BASES APPLICABLE
. The fuel assembly misloading accident involves placement of SAFETY ANALYSES a fuel assembly in a location for which it does not meet the (continued) 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 i
positive reactivity, increasing K,,, toward 0.95. A fourth accident was evaluated for the Unit I fuel storage racks containing boral. The fourth accident was the misplacement of a fuel assembly between the rack and pool wall. This was i
the limiting accident for the Unit I racks. The j
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(continued)
. Vogtle Units 1 and 2 B 3.7-94a Amendment No. 102 Unit 1 Amendment No. 80 Unit 2
Fuel Storage Pool Boron Concentration B 3.7.17 l
BASES l
APPLICABLE SAFETY ANALYSES (continued)
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l (continued)
Vogtle Units 1 and 2 B 3.7-94b Amendment No.102 (Unit 1)
Amendment No. 80 (Unit 2)
Fuel Storage Pool Boron Concentration B 3.7.17 BASES (continued)
I APPLICABLF maximum required additional boron to compensate for this SAFETY ANALYSES event is 1250 ppm for Unit 2, and 800 ppm for Unit I which l
(continued) is well below the 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 2 2000 ppm. The specified concentration of dissolved 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 postuinted 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 misload occur. The amount of soluble boron necessary to mitigate these events was determined to be 1250 ppm for Unit 2 and 800 ppm for Unit 1.
The specified minimum baron l
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 600 ppm l
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.I. 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 g eg ment g. Ig n t n
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 I spent fuel storage racks contain storage locations for 1476 fuel assemblies, and the Unit 2 spent l
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 stored in the acceptable storage configurations that are specified in Figures 3.7.18-1 (Unit 1), 3.7.18-2.(Unit 2), and 4.3.1-2 l
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.
Westinghouse 17x17 fuel assemblies with nominal enrichments no greater than 3.50 w/o"'O may be stored in all storage l
cell locations of the Unit I pool.
Fuel assemblies with initial nominal enrichment greater than 3.50 w/o"'u must l
satisfy a minimum burnup requirement as shown in Figure 3.7.18-1.
Fuel assemblies having a Km of 1.431 at cold reactor core conditions may also be stored in all cells of fhe Unit I fuel storage racks.
Westinghouse 17x17 fuel assemblies with nominal enrichments no greater than 5.0 w/o"50 may be stored in a 3-out-of-4 l
checkerboard arrangement with empty cells in the Unit 1 pool. There are no minimum burnup requirements for this configuration.
Westinghouse 17x17 fuel assemblies with nominal enrichments no greater that 5.0 w/o"'O may be stored in a 2-out-of-4 checkerboard arrangement with empty cells in the Unit 2 pool. There are no minimum burnup requirements for this configuration.
l (continued)
Vogtle Units 1 and 2 B 3.7-97 Amendment No.102 (Unit 1 Amendment No. 80 (Unit 2
- __-_ ____=____________ _ ____ - - - - __ __ _,_ _ - _ __. _,..
1 i
Fuel Assembly Storage in the Fuel Storage Pool B 3.7.18
]
BASES i
i BACKGROUND Westinghouse 17x17 fuel assemblies with nominal enrichments j
(continued) no greater than 1.77 w/o"'O 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"'O must satisfy a minimum burnup requirement as shown in Figure 3.7.18-2.
e i
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(continued)
Vogtle Units ~I and 2 B 3.7-97a Amendment No.102 (Unit 1)
Amendment No. 80 (Unit 2)
i l-l-
Fuel Assembly Storage in the Fuel Storage Pool B 3.7.18 BASES
' BACKGROUND.
(continued) i I
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s (This page intentionally left blank.)
a.
1
)
(continued)
Vogtle' Units 'I and 2 B 3.7-97b Amendment No.102 (Unit 1)
Amendment No. 80 (Unit 2)
I Fuel Assembly Storage in the Fuel Storage Pool B 3.7.18 BASES i
BACKGROUND Westinghouse 17x17 fuel assemblies with nominal enrichments (continued) no greater than 2.40 w/oU 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'*50 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 an initial enrichment no greater than 3.20 w/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 688F. One method of achieving this value of K. is by the use of IFBAs.
The surrounding fuel assemblies must have an initial nominal 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.
l APPLICABLE Most fuel storage pool accident conditions will not res' ult SAFETY ANALYSIS in an increase in K.,,.
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. 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 2 of the NRC Policy Statement.
LCO -
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 3.7.18-1 and 3.7.18-2 for all cell storage in the Unit I and Unit 2 pools, respectively. Other acceptable enrichment burnup and checkerboard combinations are described in Figures 4.3.1-2 through 4.3.1-9.
l (continued)
I NONR{ $- @ M h Vogtle Units 1 and 2 B 3.7-98 L--__-____-________
Fuel Assembly Storage in the Fuel Storage Pool B 3.7.18 BASES (continued)
APPLICABILITY This LCO applies whenever any fuel assembly is stored in the I
fuel storage pool.
ACTIONS AJ Required Action A.1 is modified by a Note indicating that LCO 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 enrichment, burnup, and storage I
configurations, the immediate action is to initiate action to make the necessary fuel assembly movement (s) to bring the l
configuration into compliance with Figures 3.7.18-1 (Unit 1), 3.7.18-2 (Unit 2), or Specification 4.3.1.1
)
(Unit 1) or 4.3.1.2 (Unit 2).
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 I
action is independent of reactor operation. Therefore inability to move fuel assemblies is not sufficient reason to require a reactor shutdown.
3 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 (Unit 1) or 4.3.1.2 (Unit 2).
l 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 administrative 1y 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.
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(continued) g eQ g eng g. Ig g g Vogtle Units 1 and 2 B 3.7-99 i
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