ML20148R752

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Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis
ML20148R752
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/30/1997
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20148R740 List:
References
NUDOCS 9707080014
Download: ML20148R752 (69)
v • d • e


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ATTACHMENT III i

l FARLEY NUCLEAR PLANT l TECHNICAL SPECIFICATIONS CHANGE REQUEST j SPENT FUEL POOL SOLUBLE BORON CREDIT 1

FNP Unit 1 Technical Specifications Changed Pages List FNP Unit 1 Technical Specifications Typed Pages

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t FNP Unit 1 Technical Specifications Marked-up Pages FNP Unit 2 Technical Specifications Changed Pages List FNP Unit 2 Technical Specifications Typed Pages FNP Unit 2 Technical Specifications Marked-up Pages l

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  • l 9707080014 970630 j PDR ADOCK 05000348- l P PDR .;

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l l FNP Unit 1 l Technical Specincations Chanced Pacn ILnill Revision Page IX Replace Page XIV Replace Page 3/4 7-95 Add Page 3/4 7-96 Add Page 3/4 7-97 Add Page 5-7 Replace Page 5-7a Add Page 5-9 Add ,

Page 5-10 Add Page 5-11 Add Page 5-12 Add Page 5-13 Add Page 5-14 Add Page B 3/4 7-7 Replace Page B 3/4 7-8 Add l

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t FNP Unit 1 Technical Specifications Tvned Pages )

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INDEX t LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

, SECTION PAGE 3/4.7.13 FUEL STORAGE POOL BORON CONCENTRATION .............. 3/4 7-95 j 3/4.7.14 FUEL ASSEMBLY STORAGE .............................. 3/4 7-96 a

3/4.8 ELECTRICAL POWER SYSTEMS 1

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j 3/4.8.1 A.C. SOURCES 4 l Operating............................................ 3/4 8-1 i j Shutdown........................ .................... 3/4 8-6b i

j 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS j

A.C. Distribution - Operating........................ 3/4 8-6c A

A.C. Distribution - Shutdown......................... 3/4 8-7 l

4 Auxiliary Building D.C. Distribution -

Operating............................................. 3/4 8-8 -

Auxiliary Building D.C. Distribution - l

Shutdown............................................. 3/4 8-11 i

i Service Water Building D.C. Distribution -

Operating............................................ 3/4 8-12 4

4 FARLEY-UNIT 1 IX AMENDMENT NO.

. . . - . . - - - - - - . - . . - - . ~ . . - . . . . . . - _ . . - . . . ~ . - . - - , . - . . - . . ~ . . , - - .

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i INDEX l BASES I

a SECTION PAGE 3/4.7 PLANT SYSTEMS l 3/4.7.1 TURBINE CYCLE.........................................B 3/4 7-1 i

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! 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION............................................B 3/4.7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM..................................B 3/4 7-3 l l

i 3/4.7.5 RIVER WATER SYSTEM....................................B 3/4 7-3 )

i 3/4.7.6 ULTIMATE MEAT SINK....................................B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION S Y S T EM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 7 - 4 3/4.7.8 ECCS PUMP ROOM EXMAUST AIR FILTRATION S Y S T EM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 7 - 4 II i

l 3/4.7.9 SNUBBERS..............................................B 3/4 7-5 i 3/4.7.10 SEALED SOURCE CONTAMINATION...........................B 3/4 7-6 3/4.7.11 F!n: C"PPn:CCION SYSTEMC (Deleted)....................B 3/4 7-6 3/4 7.12 Fin: Sn~t En PENETnnTIONS (Deleted)...................B 3/4 7-7 l

1 3/4 7.13 FUEL STORAGE POOL BORON CONCENTRATION ................B 3/4 7-7 3/4 7.14 FUEL ASSEMBLY STORAGE ................................B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS......................................B 3/4 8-1  ;

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l FARLEY-UNIT 1 XIV AMENDMENT NO.

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i PLANT SYSTEMS 3/4.7.13 FUEL STORAGE POOL BORON CONCENTRATJON LIMITING CONDITION FOR OPERATION i

3 3.7.13 The fuel storage pool boron concentration shall be greater than or equal to '

I 2000 ppm.  !

APPLICABILITY: When fuel assemblies are stored'in the fuel storage pool. l 1

I ACTION: I With the fuel storage pool boron concentration less than 2000 ppm, immediately  ;

suspend movement of fuel assemblies in the fuel storage pool, and initiate action to restore the fuel storage pool boron concentration to within its limit. The provisions of Specification 3.0.3 are not applicable. j I

SURVEILLANCE REQUIREMENTS 4.7.13 The boron concentration of the fuel storage pool shall be determined to be within the limit at least once per 7 days.

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FARLEY-UNIT 1 3/4 7-95 AMENDMENT NO.

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PLAWT SYSTEMS 3/4.7.14 FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.7.14 The combination of initial enrichment and burnup of each fuel assembly stored in the spent fuel storage pool shall be within the Acceptable 3urnup Domain of Figure 3.7-1, or shall be stored in accordance with Specification 5.6.1.1.

APPLICABILITY: Whenever any fuel assembly is stored in the spent fuel r,torage pool.

ACTION:

With the requirements of the above specification not satisfied, initiate action to move the noncomplying fuel assembly to an acceptable storage location. The provisions of specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.14 The combination of initial enrichment and burnup of each fuel assembly shall be verified to be in accordance with Figure 3.7-1 or Specification 5.6.1.1 within 7 days following the relocation or addition of fuel ass *emblies to the spent fuel storage pool.

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i FARLEY-UNIT 1 3/4 7-96 AMENDMENT NO.

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i DESIGN FEATURES I

5.6 FUEL STORAGE CPITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained withs

a. K,gg less than 1.0 when flooded with unborated water, which includes I

conservative allowances for uncertainties.

b. Ke gg less than or equal to 0.95 when flooded with water borated to 400
ppm, which includes conservative allowances for uncertainties and i

biases.

c. A nominal 10.75 inch center-to-center distance between fuel l assemblies placed in the storage racks.
d. A maximum nominal enrichment of 5.0 w/o U-235.
e. New or partially spent fuel assemblies with a combination of discharge burnup and initial enrichment in the " acceptable range" of Figure 3.7-1 may be allowed unrestricted storage in the spent fuel racks (also shown as the All Cell Storage configuration in Figure 5.6-2).
f. New or partially spent fuel assemblies with a combination of discharge burnup and initial enrichment in the " unacceptable range" of Figure 3.7-1 will be stored in compliance with Figures 5.6-1 through 5.6-5.

The high enrichment fuel assemblies shown in the Burned / Fresh Storage configuration in Figure 5.6-2, with maximum nominal enrichments greater than 3.9 w/o U-235, shall contain sufficient integral burnable  :

absorbers such that a maximum reference fuel assembly k, less than or equal to 1.455 at 68 F is maintained.

g. Damaged fuel assemblies F02, F05, F06, FIS, F17, F18, F19, F20, F30, F31, and F32 shall be stored in accordance with Figure 5.6-6.

5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with:

a. Ke gg less than or equal to 0.98, assuming aqueous foam moderation,
b. A nominal 21 inch center-to-center distance between new fuel assemblies placed in the storage racks,
c. A maximum nominal enrichment of:
1. 4.25 weight percent U-235 for Westinghouse fuel assemblies with l Standard Fuel Assembly fuel rod diameter.
2. 5.0 weight percent U-235 for Westinghouse fuel assemblies with
l. Optimized Fuel Assembly fuel rod diameter. Westinghouse fuel l with Optimized Fuel Assembly fuel rod diameter and maximum nominal enrichments greater than 3.9 weight percent U-235 shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly K, less than or equal to 1.455 at 68'F is maintained.

( FARLEY-UNIT 1 5-7 AMENDMENT NO.

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DESIGN FEATURES DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent >

inadvertent draining of the pool below elevation 149.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

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i FARLEY-UNIT 1 5-7a AMENDMENT No.

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45000  !

. _ _ j 40000

-h , 4 ,s_ ,

~+- . . . . _-

3 35000 g

g

[ ._.._._ _ _

s - . - . . _ . - . _ _ . _

C -

3 g

30000 ACCEPTABLE --- - - - .----

4 . . , . _ . . _ . . . . , _ _ _ . . _ . . . . _ _ _ . . . . , , . . . , ,

3 _ . . _ _ . . . . . .

. c 25000 u . . - - - . - - _ . - - . . _ _ . - -

3 m _ .. . __._ _ - _

t

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.x.

.o 20000 g . . . . . _ _ _ _ . _ _ _. _ _ _ _ , _ . . . _

e g .

4: 15000 . ...-,_ .._ _ . _ _ . - _-. .

e . _ _ . . . . _ _ _ __

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3 . - . . a_- - .t - , - _ .-- . _ . . ..

LL, .

1 10000 UNACCEPTABLE

. _ ._ g .

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.._.-..s..- ~ + . _ , . _ . _ _g..4__... . - . - . - . , _ - .

5000

~.a= _ _. .

0 1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (nominal w/o)

Figure 5.6-1 Fuel Assembly Burnup Limit Requirements for Low Enrichment (L)

Assembly of the BurnedTresh Checkerboard Storage (see Figure 5.6-2)

FARLEY - UNIT I 5-9 AMENDMENT NO.

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A A i l

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A A i

l All Cell Storage  !

C Empty H L Empty C L L 2-out-of-4 Storage Burned / Fresh Storage  !

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l Note: i A = All Cell Enrichment (Figure 3.7-1) I l C = 2-out-of-4 Enrichment (No restriction on enrichment or burnup)

L = Low Enrichment of Burned / Fresh (Figure 5.6-1) i 11 = Ifigh Enrichment of Burned / Fresh (See section 5.6.1.1.f for IFBA requirement) l Empty = Empty Cell l l j Figure 5.6-2 Spent Fuel Storage Configurations l FARLEY - UNIT 1 5-10 AMENDMENT NO.

l A A A A A A l A A A A A A Interface -

1 A A A A A A l 1

6 L L L lA A A 1

L H L' A a A A 8

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L L L u A A A

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4 Note:

A = All Cell Enrichment L = Low Enrichment of Burned / Fresh i j 11 = Iligh Enrichment of l 1

Burned / Fresh

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1 i Boundary Between All Cell Storage and Burned / Fresh Storage 4

Note:

{ l. 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.

i Figure 5.6-3 Interface Requirements FARLEY - UNIT I 5-11 AMENDMENT NO.

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A A A A A A i 1

4 A A A A A A Interface A empty A A A A Empty C Empty l A A A l

i C Empty Cl empty A A j Empty C Empty l A A A

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Note I

l A = All Cell Enrichment C = 2-Out-Of-4 Enrichment j Empty = Empty Cell i

j Boundary Between All Cell Storage and 2-out-of-4 Storage i

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l 1. A row of empty cells can be used at the interface to separate the configurations.

2. It is acceptable to replace as assembly with an empty cell.

Figure 5.6-4 Interface Requirements FARLEY - UNIT I 5-12 AMENDMENT NO.

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l Empty C Empty C Empty C l

Interface C empty C empty b empty Empty C Empty C Empty C H smaty H empty C Empty L

L L empty C empty C H

H L H L empty C empty 1

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I Note:

C = 2-Out-Of-4 Enrichment L = Low Enrichment of Burned / Fresh II = liigh Enrichment of Burned / Fresh Empty = Empty Cell Boundary Between 2-out-of-4 Storage and Burned / Fresh Storage Note:

1. A row of empty cells can be used et th: interface to separate the configurations.
2. It is acceptable to replace an assembly with an empty cell.

( Figure 5.6-5 Interface Requirements FARLEY - UNIT 1 5-13 AMENDMENT NO.

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F31 Empty F30 F06 - '

i F18 F17 F19 F02

F15 F20 F05 F32 ,..

f l Water ,

, Note: All Assemblies are 3.0 w/c *U nominal enrichment 1

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l Figure 5.6-6 Damaged Fuel Assembly Configuration l l

. FARLEY - UNIT 1 5-14 AhENDMENT NO.

PLANT SYSTEMS BASES 3/4.7.12 FIRE BARRIER PENETRATIONS This specification deleted.

3/4.7.13 & 3/4.7.14 FUFL STORAGE POOL BORON CONCENTRATION & FUEL ASSEMBLY STORAGE The spent fuel storage racks contain storage locations for 1407 fuel assemblies.

The spent fuel racks have been analyzed in accordance with the methodology contained in WCAP-14416-NP-A, Westinghouse Spent Fuel Rack Criticality Analysis Methodology",. Revision 1, November, 1996. This methodology ensures that the spent fuel rack multiplication factor, keff is less than 0.95, as recommended by ANSI 57.2-1983 and the guidance contained in NRC Letter to All Power Reactor Licensees from B. K. Grimes, "OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications", April 14, 1978. The codes, methods, and techniques contained in the methodology are used to satisfy this keff criterion. The spent fuel storage racks are analyzed to allow storage of all Westinghouse 17X17 fuel assemblies with nominal enrichments up to 5.0 w/o U-235 utilizing credit for checkerboard configurations, burnup, Integral Fuel Burnable Absorbers, and soluble boron, to ensure that keft is maintained s 0.95, including uncertainties, tolerances, and accident conditions. In addition, the spent fuel pool keff is maintained < 1.0 including uncertainties and tolerances on a 95/95 basis without soluble boron.

The soluble boron concentration required to maintain keff 5 0.95 under normal conditions is 400 ppm.

The following storage configurations and enrichment limits were evaluated in the spent fuel rack criticality analysis:

Westinghouse 17X17 fuel assemblies with nominal enrichments less than or equal 2.15 w/o U-235 can be stored in any cell location as ebown in Figure 5.6-2. -Fuel assemblies with initial nominal enrichments greater than .hase limits must satisfy a minimum burnup requirement as shown in Figure 3.7-1.

Westinghouse 17X17 fuel assemblies with nominal enrichments less than or equal to 5.0 w/o U-235 can be stored in a 2 out of 4 checkerboard arrangement as shown in Figure 5.6-2. In the 2 out of 4 checkerboard storage arrangement, 2 fuel assemblies can be stored corner adjacent with 2 empty storage cells.

Westinghouse 17X17 fuel assemblies can be stored in a burned / fresh checkerboard arrangement of a 2X2 matrix of storage cells as shown in Figure 5.6-2. In the burned / fresh 2X2 checkerboard arrangement, three of the fuel assemblies must have an initial nominal enrichment less than or equal to 1.6 w/o U-235, or satisfy a minimum burnup requirement for highet, initial enrichments as shown in Figure 5.6-

1. The fourth fuel assembly must htra an initial naninal enrichment less than or equal to 3.9 w/o U-235, or satisfy a minimum Integral Fuel Burnable Absorber requirement for higher initial enrichments to maintain the reference fuel assembly
k. less than or equal to 1.455 at 68 F.

Eleven damaged Westinghouse 17X17 fuel assemblies can be stored in a 12 storage cell configuration surrounded by empty cells as shown in Figure 5.6-6. The eleven fuel assemblies contain a nominal enrichment of 3.0 w/o U-235.

FARLEY-UNIT 1 B 3/4 7-7 AMENDMENT NO.

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n PLANT SYSTEMS BASES Specifications 3.7.14 and 5.6.1.1 ensure that fuel assemblies are stored in the spent fuel racks in accordance with the configurations assumed in the spent fuel rack criticality analysis.

The most limiting accident with respect to the storage configurations assumed in the spent fuel rack criticality analysis is the misplacement of a 5.0 w/o U-235 fuel assembly into an empty storage cell location in the 2 out of 4 checkerboard storage arrangement. The amount of soluble boron required to maintain keff less than 0.95 due to this fuel misload accident is 850 ppm. The 2000 ppm limit specified in the LCO is consistent with the normal boron concentration maintained in the spent fuel pool, and bounds the 850 ppm required for a fuel misload accident.

Specification 5.6.1.1 b. requires that a boron concentration of 400 ppm in the spent fuel pool will maintain keff 5 0.95. A spent fuel pool boron dilution analysis was performed to determine that sufficient time is available to detect and mitigate dilution of the spent fuel pool prior to excecding the keff design basis limit of 0.95. The spent fuel pool boron dilution analysis concluded that an inadvertent or unplanned event that would result in a dilution of the spent fuel pool boron concentration from 2000 ppm to 400 ppm is not a credible event.

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1 FARLEY-UNIT 1 B 3/4 7-8 AMENDMENT NO.

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FNP Unit 1 Technical Specifications Marked-Up Paces '

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fNDEX LIMfTfNG CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENT SECTION

_P.AG.E 3/4.8 ELECTRICAL POWER SYSTEMS -

3/4.8.1 A.C. SOURCES 3

0perating................................................ 3/4 8-1 -

i Shutdown................................................. 3/4 8-6b l 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating............................ 3/4 8-6c l A.C. Distribution -

Shutdown............................. 3/4 8-7 Auxiliary Building 0.C. Distribution - Operating......... 3/4 8-8 Auxiliary Building 0.C. Distribution - Shutdown. . . . . . . . . .

3/4 8-11 Service Water Building 0.C. Distribution - Operating..... 3/4 8-12 i

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a FARLEY-UNIT 1 IX AMENDMENT NO. 25. 98 Y

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INDEI BASES SECTION 3/4.7 PLANT STSTEMS M

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3/4.7.1 TURBINE CTCLE............................................. . g 3,g y_g 3/4.7.2 5

STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION............. B 3/4 7-3 3/4.7.3 COMPONENT COOLING VATER I

SYSTEM.............................. B 3/4 7-3 3/4.7.4 SERVICE VATER STSTEM........................................ B 3/4 7-3 3/4.7.5 RIVER VATER SYSTEM.......................................... B 3/4 7-3 3/4.7.6 ULTIMATE HEAT SINK..........................................

B 3/4 7-4

. 3/4.7.7 CONTROL ROOM EMERGENCT VENTILATION SYSTEM. . . . . . 5 . .3/4

. . . 7-4 j 3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTIN................ 33/474

! 3/4.7.9 1

SNUBBERS.................................................... B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION................................. B 3/4 7-6 3 /4 . 7.11-+IR" O'.'? """0 "^" O!=1 (Dele t ed ) . . . . . . . . . . . . . . . . . . . . . . .B. 3/4 . . 7-6 3 / 4 . 7 .12 " ", " " ' =" "Jx~ .~~. . . . '.". . ^. ". ." ( De l e t ed ) . . . . . . . . . . . . . . . . . . . . . . . . .

3 3/4 7-7 i

$N2k 5 3/4.8 ELECTRICAL POVER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POVER DISTRIBUTION SYSTEMS......................................... B 3/4 8-1 i

4 FARLET-UNIT 1 ZIV AMENDMENT NO. 26. 96

a 4 .om._ .4M_A aa .4..p_.$ a-se A ., Aa_a .- 1.M.e 4 mwe.4%_J. s_L4 Ah.S*%4~u.A. 4 .E.6 4 m. .a.4 e _. -_F*.A.2 Msp.aA.Ea_2-, _ _ .-'1+_sy 4.A.4 _A4 4

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? Insert 1 3/4.7.13 FUEL STORAGE POOL BORON CONCENTRATION. ... 3/4 7-95

, 3/4.7.14 FUEL ASSEMBLY STORAGE ..... ...... .. .. ............. .. .. 3/4 7-96 Insert 2 3/4.7.13 FUEL STORAGE POOL BORON CONCENTRATION......B 3/4 7 7 3/4.7.14 FUEL ASSEMBLY STORAGE............ ........................B 3/4 7 7 4

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PLANT SYSTEMS 3/4.7.13 FUEL STORAGE POOL BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.7.13 The fuel storage pool boron concentration shall be greater than or equal to 2000 ppm.

APPLICABILITY: When fuel assemblies are stored in the fuel storage pool.

ACTION:

With the fuel storage pool boron concentration less than 2000 ppm, immediately suspend movement of fuel assemblies in the fuel storage pool, and initiate action to restore the fuel storage pool boron concentration to within its limit. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS

~

4.7.13 The boron concentration of the fuel storage pool shall be determined to be within the limit at least once per 7 days.

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l FARLEY-UNIT 1 3/4 7-95 AMENDMENT NO. 1 i

U PLANT SYSTEMS  ;

, f g 3/4.7.14 FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION  ;

] 3.7.14 The combination of initial enrichment and burnup of each fuel assembly stored in the spent fuel storage pool shall be within the Acceptable Burnup Domain of Figure 3.7-1, or shall be stored in accordance with Specification B.6.1.1.

j APPLICABILITY: Whenever any fuel assembly is stored in the spent fuel storage I pool.  ;

1 ACTION: ,

5 With the requirements of the above specification not satisfied, initiate action to

move the noncomplying fuel assembly to an acceptable storage location. The

! provisions of Specification 3.0.3 are not applicable.

1 i SURVEILLANCE REQUIREMENTS i i j 4.7.14 The combination of initial enrichment and burnup of each fuel assembly  !

shall be verified to be in accordance wi,th Figure 3.7-1 or Specification 5.6.1.1  !

2 within 7 days following the relocation or addition of fuel assemblies to the spent l

fuel storage pool.

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1 FARLEY-UNIT 1 3/4 7-96 AMENDMENT NO.

l 45000 f i I

40000 '

l

' I 35000 ,

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F- l  ! i 3 -

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l O 30000 3 ACCEPTABLE E

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a  ! : i i 3 25000 .

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.Cl 20000 - .

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g , i i i i i i/ f I !  !  :

W i i !

i i  ! i j ! /i j i i i l E 15000 i  !'i i< i i i i  ! ! /r i i  ! , i i  ! i 5  ! l ! '

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E i i i i i i ! /i; : i I i ! i 10000 ll lllj/'' .

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5000 ,  ; , ,

if l UNACCEPTABLE l i i I / i i i i i i /; t l  ! i i !

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1.0 2.0 3.0 4.0 5.0 )

i Initial U-235 Enrichment (nominal w/o) l figure 3.71 Fuel Assembly Burnup Limit Requirements For All Cell Storage '

FARLEY - UNIT I 3/4 7-97 AMENDMENT NO.

. _ _ _ . _ __ _ - _ . _ _ _ _ _ _ . . _ __ _ __ _ _ _ _ _ m ___ _ ._ _ - . _ _ _ . _ _ . . _ __ _ . _ . .

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DESIGN FEATURES 5.6 ftEL STORAGE 4  %

CRITICALITY 5.6.1.1 The spent

" fuel storage racks are designed and shall be maintained gg3

' ~

b. / .

hored%]9. Moo pp Ne gf less than or egaal to 0.95 when flooded with Me<'stVwate ,

which includes conseevative allowances for uncertainties and biases.

e, )[.

4 A nominal 10.75 assemblies placed inch center-to-center in the storage racks, distance between fuel l

/

dJ. A maximum nominal enrichment o

S.o Wl* ()- 2.3 6.

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[ 4.25 eig perce. U-235 or West ghouse FAR f 1 as 1 s.

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[ 5 we he per ent U-2 for We tingho e OTA o VANTAG uel ssembi s. W inghous OTA a max n VANTAG 5 fuel ith U- 35 sha nal one chments rester than 3.9 eight ec contai suffic nt in gral bu able a orb a ch tha a ma refer nee fu assemb y X,e le a th a or

{ grH i

  • 1ual 1.455 64*F i maintained.

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' 5.6.1.2 The new fuel pit storage racks are designed and shall be i maintained with: l

'1 a.

K,gg less than or equal to 0.98, assuming aqueous foam moderation.

b.

{ A nominal 21placed assemblies inch center-to-center in the storage racks. distance between new fuel c.

A maximum nominal enrichment of 1.

[w b y 4.25 weight percent U-235 for Westinghou e M fuel assembliesg ut R .5+a4uJ F%t Asu.% Q twd d
ameW.

i gpg Q r*& 2. 5.0 weight ' at U-235 for Westinghouse i VAlWF4 ruei asseet le . Westinghouse $ g$h fuel with

. d_" *C maximma nominal enrichtsents greater than 3 we ght percent 1

U-235 shall catain aufficient integral burnable absorbers g,3 -

such that a === M reference fuel assembly K ,less than or

] equal to 1.455 at 68'r is maintained. i DRAINAGE

j. 5.6.2 The spent fuel storage pool is designed and shall be maintained to j prevent inadvertent draining of the pool below elevation 149.

a CAPACITY

5.6.3 The spent fuel storage pool is designed and shall be maintained with j a storage capacity limited to no more than 1407 fuel assemblies.

j 5.7 COMPONENT CYCLIC OR TRANSIDfT LIMIT 4

5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

FARLEY - UNIT 1 5-7 AMENDMENT NO.

t 52,9I,110 I

4

i i

I

. Insert 3

a. k,,less than 1.0 when flooded with unborated water, which includes conservative allowances for uncertainties.  !'

Insert 4 l

e. New or partially spent fuel assemblies with a combination of discharge burnup and initial f

enrichment in the " acceptable range" of Figure 3.7-1 may be allowed unrestricted storage in l

the spent fuel racks (also shown as die All Cell Storage configuration in Figure 5.6-2).

f. New or partially spent fuel assemblies with a combination of discharge burnup and initial
enrichment in the "unacceptaHe range" of Figure 3.7-1 will be stored in compliance with Figures 5.6-1 through 5.6-5. The high enrichment fuel assemblies shown in the Burned / Fresh l Storage configuration in Figure 5.6-2, with maximum nominal enrichments greater than 3.9 w/o U-235 shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly k., less than or equal to 1.455 at 68* F is maintained. '
g. Damaged fuel assemblies F02, F05, F06, FIS, F17, F18, F19, F20, F30, F31, and F32 shall be stored in accordance with Figure 5.6-6.

1 1

l l

l l

t. . ' i i

i

. 1

t 45000 ,

l 40000 - -

d a 35000 '

f'.-

E s

~

Q ' '

3 30000 ACCEPTABLE E

, l

, i

' +'I , I  !

25000

/ '

, . 1 . ,

, , , l , , .

3 I I I I i i I i i l i

!/

> l .  !

3 20000 ,

f , , ,,,

E  : i i 1/ >

W '

! !  ! r t/ ; i I l :  !

! I e -

! i '

i

! /~ i  : i , ; ,

, 4 (A ,f 15000 l, lfli; l l,;

g i < l l i f!  !

i ii i,i>

3 i l I t/ i

'  ! 'i  !

i 1 I  ! /! ' ' ' t 10000 l' UNACCEPTABLE l' l'

/ -

,. i ; i  !

i i ! '/  ! iii i i ! 1 i'i,

~~I i i J/  ! : ! i i i ; i , i  :

i i if , iii i  ! I i ,

5000  ; ,

i f i ,,, ,

i I i .

i iii  ! i i i i  ! i  :

I

. +~

l i I i t i t I i I 3  ! ,

i '

I y  ! I f<. l .I 0

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (nominal w/o) l Figure 5.6-1 Fuel Assembly Burnup Limit Requirements for Low Enrichment (L)

Assembly of the Burned / Fresh Checkerboard Storage (see Figure 5.6-2) i FARLEY - UNIT 1 5-9 AMENDMENT NO.

l

A A i

A A All Cell Storage C Empty H L Empty C L L 2-out-of-4 Storage Burned / Fresh Storage Note:

A = All Cell Enrichment (Figurr. 3.7-1)

C = 2-out-of-4 Enrichment (No restriction on enrichment or burnup)

L = Low Enrichment of Burned / fresh (Figure 5.6-1)

II = Iligh Enrichment of Burned / Fresh (See section 5.6.1.1.f for IFBA requirement)

Empty = Empty Cell Figure 5.6-2 Spent Fuel Storage Configurations FARLEY . UNIT 1 5-10 AMENDMENT NO.

5 A A A A A A l

A A A A A A Interface

\__= = -

L L L  !

A A A L H L" A A A u

L L L" A A A ll l

l i

Note:

A = All Cell Enrichment L = Low Enrichment of Burned / Fresh H = Iligh Enrichment of l Burned / Fresh j

Boundary Between All Cell Storage and Burned / Fresh Storage i

! 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 5.6-3 Interface Requirements I FARLEY - UNIT 1 5 11 AMENDMENT NO.

f 1

b

A A A A A A i interface

^ ^ ^ ^ ^ ^

A e m pty A A A A Empy C Empty i

A A A C empty C' empty A A empty C Empty l l

A A A l

l Note:

A = All Cell Enrichment C = 2-Out-Of-4 Enrichment Empty = Empty Cell 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 as assembly with an empty cell.

Figure 5.6-4 Interface Requirements FARLEY - UNIT I 5 12 AMENDMENT NO.

i l

\

l l

Empty C Empty C Empty C l

l lntedaCO C Empty C Empty C Empty Empty C Empty C Empty C l

H Empty Hl . Empty C l Empty L L Empty ll ll C Empty C i l

H L HIi Empty C Empty I

I Note:

C = 2-Out-Of-4 Enrichment i L = Low Enrichment of Burned / Fresh 11 = Iligh Enrichment of Burned / Fresh  ;

Empty = Empty Cell  ;

i Boundary Between 2-out-of-4 Storage and Burned / Fresh 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.

I l

Figure 5.6 5 Interface Requirements i

FARLEY - UNIT I 5-13 AMENDMENT NO.

i

}

i l t

1

~

i i

h I

i i

k

  • I f

t i

l F31 Empty F30 F06 i

l l

1 F18 F17 F19 F02 I

i F15 F20 F05 F32 i

i i

t 4

i 235 Note: All Assemblies are 3.0 w/o U nominal enrichment i

l l

4 1 4 l

I

! l i i 1

j Figure 5.6-6 Damaged Fuel Assembly Configuration s

i

, FARLEY- UNIT 1 5-14 AMENDMENT NO.

l l

l I 1

1 I

... . . . . . . - . . . - . _ - - -. .-~. - _ . . _ . . . . _ . . - . - - . _.._.

c O PLANT SYSTEMS BASES

.................................. ...==........................................

! 3/4.7.12 FIRE BAIUtIER PENETRATIONS This specification deleted.

l l

'O ,

! FARLIT-UNIT 1 3 3/4 7 7 AWfDIENT NO. 26. 96 O

1

, insert 5 3/4.713 FUEL STORAGE POOL BORON CONCENTRATION  !

3/4.7.14 FUEL ASSEMBLY STORAGE !1 The spent fuel storage racks contain storage locations for 1407 fuel assemblies. The spent fuel racks I have been analyzed in accordance with the methodology contained in WCAP-14416-NP-A, i Westinghouse Spent Fuel Rack Criticality Analysis Methodology" Revision 1, November,19%. His i methodology ensures that the spent fuel rack multiplication factor, k.,is less than 0.95, as recommended by ANSI 57.2-1983 and the guidance contained in NRC Letter to All Power Reactor Licensees from B. K. Grimes, "OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications", April 14,1978. The codes, methods, and techniques contained in the  ;

methodology are used to satisfy this k., criterion. The spent fuel storage racks are analyzed to allow  !

storage of all Westinghouse 17X17 fuel assemblies with nominal enrichments up to 5.0 w/o U-235 >

utilizing credit for checkerboard configurations, burnup, Integral Fuel Burnable Absorbers, and  !

soluble boron, to ensure that k., is maintained 10.95, including uncertainties, tolerances, and '

accident conditions. In addition, the spent fuel pool k , is maintained < l.0 including uncertainties  !'

and tolerances on a 95/95 basis without soluble boron.

The soluble boron concentration required to maintain k ,10.95 under normal conditions is 400 ppm. i The following storage configurations and enrichmcr.t !!.Wts were evaluated in the spent fuel rack l criticality analysis: i Westinghouse 17X17 fuel assemblies with nominal enrichments less than or equal to 2.15 w/o U-235 ,

can be stored in any cell location as shown in Figure 5.6-2. Fuel assemblies with initial nominal . ~

enrichments greater than these limits must satisfy a minimum burnup requirement as shown in Figure  !

3.7-1. j i

Westinghouse 17X17 fuel assemblies with nominal enrichments less than or equal to 5.0 w/o U-235 can be stored in a 2 out of 4 checkerboard arrangement as shown in Figure 5.6-2. In the 2 out of 4 l 7

checkerboard storage arrangement,2 fuel assemblies can be storui corner adjacent with 2 empty {

storage cells. .

Westinghouse 17X17 fuel assemblies can be stored in a burned / fresh checkerboard arrangement of a l 2X2 matrix of storage cells as shown in Figure 5.6-2. In the burned / fresh 2X2 checkerboard 1 arrangement, three of the fuel assemblies must have an initial nominal enrichment less than or equal to j

- 1.6 w/o U-235, or satisfy a ninimum burnup requirement for higher initial enrichments as shown in  ;

Figure 5.6-1. The fourth fuel assembly must have an initial nominal enrichment less than or equal to 3.9 w/o U-235, or satisfy a minimum Intergral Fuel Burnable Absorber requirement for higher initial  ;

enrichments to maintain the reference fuel assembly k less than or equal to 1.455 at 68* F.  !

Eleven damaged Westinghouse 17X17 fuel assemblies can be stored in a 12 storage cell configuration surrounded by empty cells as shown in Figure 5.66. The eleven fuel assemblies contain a nominal i enrichment of 3.0 w/o U-235.

l 4

Spectications 3.7.14 and 5.6.1.1 ensure that fuel assemblies are stored in the spent fuel racks in accordance with the configurations assumed in the spent fuel rack criticality analysis.

The most limiting accident with respect to the storage configurations assumed in the spent fuel rack  !

criticality analysis is the misplacement of a 5.0 w/o U-235 fuel assembly into an empty storage cell  !

location in the 2 out of 4 checkerboard storage arrangement. De amount of soluble boron required to i maintain k ,less than 0.95 due to this fuel misload accident is 850 ppm. De 2000 ppm limit specified  !

in the LCO is consistent with the normal boron concentration maintained in the spent fuel pool, and i bounds the 850 ppm required for a fuel misload accident.  !

t k

I

-. ~..- . .- - - . . . . ..

i 1%r4 S j tbnk.

. Specification 5.6.1.1 b. requires that a boron concentration of 400 ppm in the spent fuel pool will  !

maintain L,.s. 0.95. A spent fuel pool boron dilution analysis was performed to determine that sufficient time is available to detect and mitigate dilution of the spent fuel pool prior to exceeding the

(, design basis limit of 0.95. The spent fuel pool boron dilution analysis concluded that an inadvertent or unplanned event that would result in a dilution of the spent fuel pool boron concentration from 2000 ppm to 400 ppm is not a credible event. ,

. 4

)

I i

P 4

P

. 4 i

i i

l , _ _ , ., .

J'  !

t 4

t-  !

k 7 i

4 f

! .I

i

}

A FNP Unit 2 i I  ;

, Technical Specifications Channed Panes  !

. Unit 2 Revision  ;

1 r j Page IX Replace Page XIV l

Replace

Page 3/4 7-67 Add I Page 3/4 7-68 Add  ;

2 i

Page 3/4 7-69 Add .

4 Page 5-7 Replace  !

Page 5-7a Add  !

j- Page 5-9 Add i

Page 5-10 Add l Page 5-11 . Add Page 5-12 Add 1 Page 5-13 Add

'. Page B 3/4 7-7 Replace 1- Page B 3/4 7-8 Add 4

I e

i 4

b l

1 i

1 3

. . . . - . _ _ _ . . . _ . _._-- _ , , . . :__.__ ._. 1

FNP Unit 2 Technical Snecifications Tvoed Pages i

- - . . . - - . . ~ . ~ - - . - . . - . ~ . - ~ . - --..--.-.--..~.c-..-~.---..--a ..

l l

1 1

1 INDEX  ;

BASES i

l SECTION PAGE )

I 3/4.7 PLANT SYSTEMS i l

3/4.7.1 TURBINE CYCLE............................................ B 3/4 7-1 )

1 l 3/4.7.2 STEAM' GENERATOR PRESSURE / TEMPERATURE LIMITATION.......... B 3/4 7-3 i

j 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................... B 3/4 7-3 l l 1 l 3/4.7.4 SERVICE WATER SYSTEM..................................... B 3/4 7-3 1

3/4.7.5 RIVER WATER SYSTEM....................................... B 3/4 7-3 )

I i

3/4.7.6 ULTIMATE HEAT SINK....................................... B 3/4 7-4 3/4.7.7 l CONTROL ROOM EMERGENCY VENTILATION SYSTEM........s ....... B 3/4 7-4  !,

t 3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM............. B 3/4 7-4 I

3/4.7.9 SNUBBERS................................................. B 3/4 7-5 l 3/4.7.10 SEALED SOURCE CONTAMINATION.............................. B 3/4 7-6 I

3/4.7.11 fin: C"PPn CCION CYSTS.".C (Deleted)....................... B 3/4 7-6 9

'3/4.7.12 fin: S.'. PRIED PIMITn.'.TI^MC (Deleted)...................... B 3/4 7-7 3/4.7.13 AREA TEMPERATURE MONITORING.............................. B 3/4 7-7 6

3/4 7.14 FUEL STORAGE POOL BORON CONCENTRATION ....................B 3/4 7 I l

3/4 7.15 FUEL ASSEMBLY STORAGE ....................................B 3/4 7-7 )

3/4.8 ELECTRICAL POWER SYSTEMS )

i 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER

, DISTRIBUTION SYSTEMS..................................... B 3/4 8-1 o

1 l 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTION DEVICES.................. B 3/4 8-1 i

l.

1 J

i FARLEY-UNIT 2 XIV AMENDMENT NO.

. . . . _ - _ - . . - . . - - - _ ... . - - .. - .. - - . - _ - . ~ - ~ -. -- -

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.14' FUEL STORAGE POOL BORON CONCENTRATION .................. 3/4 7-67 3/4.7.15 FUEL ASSEMBLY STORAGE .................................. 3/4 7-68 .

3/4.8 ELECTRICAL POWER SYSTEMS ,

3/4.8/1 A.C. SOURCES Operating............................................... 3/4 8-1 Shutdown................................................ 3/4 8-8 ,

t 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS ,

A.C. Distribution - Operating........................... 3/4 8-9 ,

r l

A.C. Distribution - Shutdown............................ 3/4 8-10 l Auxiliary Building D.C. Distribution - Operating........ 3/4 8-11 Auxiliary Building D.C. Distribution - Shutdown......... 3/4 8-14 l i

Service Water Building D.C. Distribution - Operating.... 3/4 8-15 i 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTION DEVICES t Containment Penetration Conductor Overcurrent Protective Devices...................................... 3/4 8-18 Motor-Operated Valves Thermal overload Protection and/or Bypass Devices................................... 3/4 8-29 4

FARLEY-UNIT 2 IX AMENDMENT NO.

l l

PLANT SYSTEMS 3 /4.7.14 FUEL STORAGE POOL BORON CONCENTRATION

,L,IMITING CONDITION FOR OPERATION 3.7.14 The fuel storage pool boron concentration shall be greater than or equal to 2000 ppm.

APPLICABILITY: When fuel assemblies are stored in the fuel storage pool.

ACTION:

With the fuel storage pool boron concentration less than 2000 ppm, immediately suspend movement of fuel assemblies in the fuel storage pool, and initiate action to restore the fuel storage pool boron concentration to within its limit. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.14 The boron concentration of the fuel storage pool shall be determined to be within the limit at least once per 7 days.

l l

I i

l FARLEY-UNIT 2 3/4 7-67 AMENDMENT NO.

PLANT SYSTEMS 3/4.7.15 FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.7.15 The combination of initial enrichment and burnup of each fuel assembly stored in the spent fuel storage pool shall be within the Acceptable Burnup Domain of Figure 3.7-1, or shall be stored in accordance with Specification 5.6.1.1.

APPLIC A BILIT'." . P.1enever any fuel assembly is stored in the spent fuel storage pool.

ACTION:

With the requirements of the above specification not satisfied, initiate action to move the noncomplying fuel assembly to an acceptable storage location. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.15 The combination of initial enrichment and burnup of each fuel assembly shall be verified to be in accordance with Figure 3.7-1 or Specification 5.6.1.1 within 7 days following the relocation or addition of fuel assemblies to the spent fuel storage pool.

FARLEY-UNIT 2 3/4 7-68 AMENDMENT NO.

45000 _

_u _ _._

4 40000 , ,

i  ;

,  ! i 4 i ,  !  !

l

- 35000 , , , l l , ,  ; .'

o b ' '

i E

s i

O ' ' ' ' ' '

30000 3

g ACCEPTABLE ,

l i

t  ! ,, j 1

v i i i t i  ! I i ' i I t /

g  ! !  !  ! l l ! l  ! l I l[i 3 25000 i: i

/ ; i ch-
i i ! !

j l l

! i I , , I i ! 1 I/ i i I i i i i l i i

)i I

i i ! If f O i i . I I i i i j ! i / !

h  ! l , i i i i i i /i i- i

.c 20000 i i , 4

. i . . , .

1 ;

r . .

r i i>

l ' ' i ' ' i ' i i  !/ i

! !i E '

I i /

g  ! I ,  ! >

84  ; i !  : 1 i I I I /i l  ! l !

E 15000 ll'l , lll lI lff l llll i!

g i,i!

i I iI i / i i i I I i j s  !

i i i

! l i i  ! i i/! i  !

Lg, i

! i ii / i  ! . i i

[!'I 10000 i! i !

!'  ! ! I I j i  ! I i i  !

! I i i i if i i I ! I i i:

! I i i i i / j i i ! i i f ! i l l l l j i/ i ) i i i i i i j 5000 I '

l li i  ! ' 'l 'l i/

UNACCEPTABLE I i ' /! ! !  ! I ! I i i > t J i '/ i i ' I i ! l i i : i i i: / ,

i i i i  : i i  !

O i 1.0 2.0 3.0 4.0 5.0  !

Initial U-235 Enrichment (nominal w/o)

Figure 3.7-1 Fuel Assembly Burnup Limit Requirement: For All Cell Storage FARLEY - UNIT 2 3/4 7-69 AMENDMENT NO.

i DESIGN FEATURES i

5.6 FUEL STORAGE 1

CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. K,gg less than 1.0 when flooded with unborated water, which includes conservative allowances for uncertainties.
b. K,gg less than or equal to 0.95 when flooded with water borated to 400 ppm, which includes conservative allowances for uncertainties and biases.
c. A nominal 10.75 inch center-to-center distance between fuel l assemblies placed in the storage racks.
d. A maximum nominal enrichment of 5.0 w/o U-235.
e. New or partially spent fuel assemblies with a combination of discharge burnup and initial enrichment in the " acceptable range" of Figure 3.7-1 may be allowed unrestricted storage in the spent fuel racks (also shown as the All Cell Storage configuration in Figure 5.6-2).
f. New or partially spent fuel assemblies with a combination of discharge burnup and initial enrichment in the " unacceptable range" of Figure 3.7-1 will be stored in compliance with Figures 5.6-1 through 5.6-5.

The high enrichment fuel assemblies shown in the Burned / Fresh Storage configuration in Figure 5.6-2, with maximum nominal enrichments greater than 3.9 w/o U-235, shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly k, less than or equal to 1.455 at 68'F is maintained.

5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with:

a. K,ff less than or equal to 0.98, assuming aqueous foam moderation.
b. A nominal 21 inch center-to-center distance between new fuel assemblies placed in the storage racks.
c. A maximum nominal enrichment of:
1. 4.25 weight percent U-235 for Westinghouse fuel assemblies with Standard Fuel Assembly fuel rod diameters.
2. 5.0 weight percent U-235 for Westinghouse fuel assemblies with i Optimized Fuel Assembly fuel rod diameters. Westinghouse fuel with Optimized Fuel Assembly fuel rod diameters and maximum nominal enrichments greater than 3.9 veight percent U-235 shall contain sufficient integral burnable absorbers such that a j maximum reference fuel assembly K, lesa than or equal to 1.455 at 68'F is maintained.

l FARLEY-UNIT 2 5-7 AMENDMENT NO.

l

a 1

i DESIGN FEATURES DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with

a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT

, 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

l' i

l l

l FARLEY-UNIT 2 5-7a AMENDMENT NO.

l i

l l

1 f

l 45000 t

. i l

40000 - -

. ~ . - . . . - . ..__..._ _ ,..- ._ ._ . _ . _ . _ _ . __. _ _ _ _ _ _

l n - - -. .. . - . . - - _ . . -_._._

3 35000 L _

i E

s

- - . ~

. _. . _ (_ . . _ - .

j -

30000 3 ACCEPTABLE " - - -- - . - - . . . -

l - - -. ._ _ _ , . _ .

g, . - _ . . _ . . . . - . _ _ _ . . _ . - _ _ . _ . _ _ . . _ . _ . _ . . _ _ _ _ .

[

g . ... _ - - - . - . . . - . _ . . . . . _ __.__ ._. _

C 25000 m . .-. . s .. . . _ - - _ . _ . . . . . . . ,

. . - . . . . . _ . _._,,...4 . _ . _ . . . . _ _ _ _ , , _ _ _ , _ _ , , , _ ,

l .o 20000 g - . . . - - - -

[ g . - . . - . . _. -__ _ . . _ _ . . . _ _ _ . _ _ _ _

l aC 15000 . .- .

e , . . _ . _ . . _ . . . _ . . __._____ _ _ _ _ _ .

3 . . . _ - . . . . _ _ . . . _ _ . _ . .____- _ _ . . _ _ _ _ _

LL _ _. . .. __. _ . _ _ . _ . . _

10000 UNACCEPTABLE l

[_._ _ __ __

l _,..:..___ ._... . _._ . _ _ _ _

5000 . .._ - _ _m _ . _ . _.

l

_ ._ , _ . . _ .__...._4_ -,__.4-__.._ ..._..e._.__.... I

_4

.,4...+. -

_ .l _.;-- . -- i . ..n-+._  : -.. __...-nm__._

, i i 0

l 1.0 2.0 3.0 4.0 5.0 l

Initial U-235 Enrichment (nominal w/o) i I

Figure 5.6-1 Fuel Assembly Burnup Limit Requirements for Low Enrichment (L)  :

Assembly of the Burned / Fresh Checkerboard Storage (see Figure 5.6-2)

FARLEY - UT 'lT 2 5-9 AMENDMENT NO.

i A A A A All Cell Storage C Empty H L Empty C L L 2-out-of-4 Storage Burned / Fresh Storage Note:

A = A!I Cell Enrichment (Figure 3.7-1)

C = 2-out-of-4 Enrichment (No restriction on enrichment or burnup)

L = Low Enrichment of Burned / Fresh (Figure 5.6-1) 11 = Iligh Enrichment of Burned / Fresh (See section 5.6.1.1.f for IFBA requirement)

Empty = Empty Cell l

Figure 5.6-2 Spent Fuel Storage Configurations FARLEY - UNIT 2 5-10 AMENDMENT NO.

A A A A A A A A A A A A Interface A A A A A A

\___

L L Lu A A A L H L A A A i

L L L ,A A A I

I Note:

A = All Cell Enrichment L = Low Enrichment of Burned / Fresh 11 = High Enrichment of Burned / Fresh Boundary Between All Cell Storage and Burned / Fresh 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 5.6-3 Interface Requirements l

l l

FARLEY - UNIT 2 5 11 AMENDMENT NO.

Y I

\

A A A A A A A A A A A A

. Interface

A empty A A A A empty C empty i

A A A l

Cl empty A A 1

l C e m pty

)

empty C emptyl l

A A A l

1 i

Note:

A = All Cell Enrichment C = 2-Out-Of-4 Enrichment

] Empty = Empty Cell Boundary Between All Cell Storage and 2-out-of-4 Storage Note: l

1. A row of empty cells can be used at the interface to separate the configurations. )
2. It is acceptable to replace as assembly with an empty cell.

l l

1 Figure 5.6-4 Interface Requirements I

FARLEY - UNIT 2 5-12 AMENDMENT NO.

4 Empty C Empty C Empty C Intedace C Empty C Empty C empty Empty C Empty C Empty C H Empty H Empty C Empty L

L L Emptv C Empty C

!1 H L Hi Empty C Empty L

I Note:

C = 2-Out-Of-4 Enrichment L = Low Enrichment of Burned / Fresh 11 = Iligh Enrichment of Burned / Fresh Empty = Empty Cell Boundary Between 2+ut+f-4 Storage and Burned / Fresh 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.

l I

I l

Figure 5.6-5 Interface Requirements l l

l l

FARLEY - UNIT 2 5 13 AhENDMENT NO.

l

-~ , .. - ,- . . , _ . -~ . - ~ . - - - - - - . - - - --. - _ - ._ . . . . . . -

i 4

PLANT SYSTEMS ,

I BASES l 3/4.7.12 FIRE BARRIER PENETRATION  !

4 i

j. This specification deleted. l l 3/4.7.13 AREA TEMPERATURE MONITORING ,

i The area temperature limitations ensure that safety-related equipment will  !

not be subjected to temperature in excess of their environmental qualification temperatures. Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITi. The temperature limits include an allowance for instrument error of 2*F.

e .

! 3/4.7.14 & 3/4.7.15 FUEL STORAGE POOL BORON CONCENTRATION & FUEL ASSEMBLY STORAGE The spent fuel storage racks contain storage locations for 1407 fuel assemblies.

The spent fuel racks have been analyzed in accordance with the methodology d.

contained in WCAP-14416-NP-A, Westinghouse Spent Fuel Rack Criticality Analysis Methodology", Revision 1, November, 1996. This methodology ensures that the spent fuel rack multiplication factor, kegg is less than 0.95, as recommended by ANSI ,

3 57.2-1983 and the guidance contained in NRC Letter to All Power Reactor Licensees from B. K. Grimes, "OT Position for Review and Acceptance of Spent Fuel Storage <

2 and Handling Applicat'ans", April 14, 1978. The codes, methods, and techniques contained in the mett Jology are used to satisfy this kegg criterion. The spent i fuel storage racks are analyzed'to allow storage of all Westinghouse 17X17 fuel

! assemblies with nominal enrichments up to 5.0 w/o U-235 utilizing credit for checkerboard configurations, burnup, Integral Fuel Burnable Absorbers, and l soluble boron, to ensure that kegg is maintained 1 0.95, including uncertainties, i s tolerances, and accident conditions. In addition, the spent fuel pool keff is >

maintained < l.0 including uncertainties and tolerances on a 95/95 basis without soluble boron.

j The soluble boron concentration required to maintain keff 5 0.95 under normal i 5 conditions is 400 ppm.  ;

. 6 l The following storage configurations and enrichment limits were evaluated in the ,

spent fuel rack criticality analysis

i Westinghouse 17X17 fuel assemblies with nominal enrichments less than or equal 2.15 w/o U-235 can be stored in any cell location as shown in Figure 5.6-2. Fuel ,

assemblies with initial nominal enrichments greater than these limits must satisfy  ;

a minimum burnup requirement as shown in Figure 3.7-1.

i Westinghouse 17X17 fuel assemblies with nominal enrichments less than or equal to

. 5.0 w/o U-235 can be stored in a 2 out of 4 checkerboard arrangement as shown in i - Figure 5.6-2. In the 2 out of 4 checkerboard storage arrangement, 2 fuel j assemblies can be stored corner adjacent with 2 empty storage cells.

Westinghouse 17X17 fuel assemblies can be stored in a burned / fresh checkerboard arrangement of a 2X2 matrix of storage cells as shown in Figure 5.6-2. In the -

burned / fresh 2X2 checkerboard arrangement, three of the fuel assemblies must have an initial nominal enrichment less than or equal to 1.6 w/o U-235, or satisfy a i

1 4

?

FARLEY-UNIT 2 B 3/4 7-7 AMENDMENT NO.

. - . _ - - - -- , . . - . . . . . . . . ~ . - - - - . . ~ - _ _ _ . ..-~ .-._.-.--.~ -- . . . _

l I

PLANT SYSTEMS i f

BASES l

minimum burnup requirement for higher initial enrichments as shown in Figure 5.6- {

1. The fourth fuel assembly must have an initial nominal enrichment less than or i equal to 3.9 w/o U-235, or satisfy a minimum Integral Fuel Burnable Absorber  ;

requirement for higher initial enriep.ments to maintain the reference fuel assembly i

k. less than or equal to 1.455 at 68 F.

l Specifications 3.7.15 and 5.6.1.1 ensure that fuel assemblies are stored in the  !

spent fuel racks in accordance with the configurations assumed in the 3 pent fuel .

rack criticality analysis. l The most limiting accident with respect to the storage configurations assumed in the spent fuel rack criticality analysis is the misplacement of a 5.0 w/o U-235

fuel assembly into an empty storage cell location in the 2 out of 4 checkerboard storage arrangement. The amount of soluble boron required to maintain keff less  ;

than 0.95 due to this fuel misload accident is 850 ppm. The 2000 ppm limit ,

specified in the LCO is consistent with the normal boron concentration maintained in the spent fuel pool, and bounds the 850 ppm required for a fuel.misload accident.

Specification 5.6.1.1 b. requires that a boron concentration of 400 ppm in the i spent fuel pool will maintain keff 5 0.95. A spent fuel pool boron dilution ,

-analysis was performed to determine that sufficient time is available to detect and mitigate dilution of the spent fuel pool prior to exceeding the keff design ,

basis limit of 0.95. The spent fuel pool boron dilution analysis concluded that t an inadvertent or unplanned event that would result in a dilution of the spent t fuel pool boron concentration from 2000 ppm to 400 ppm is not a credible event. j i

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FARLEY-UNIT 2 B 3/4 7-8 AMENDMENT NO.

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l FNP Unit 2 Technical Soccifications Marked-Up Paees ,

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1

DC'X i

L!MITING CCNOITICNS FOR OPERATICN M0 SURVEILLANCE f

SECTION

~E PAG l

3/1. S ELECTRICAL sCVER S'f5TEMS 3/4. S.1 A.C. SOURCES i 0cerating................................................ 3/4 a 1 5 h u tc ow n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 . . .8-3 3/4.S.2 CNSITE PCWER DISTRIBUTICN SYSTEMS A.C. Distribution - Cperating............................

3/4 3-9 A.C. Distribution -

5hutdown............................. 3/4 8-10 Auxiliary Building 0.C. Distribution - Operating......... 3/4 8-11 Auxil iary Building 0. C. Dis ribution - Shutdown. . . . . . . . . . 3/4 8-14 Service Water Building 0. C. Distribution - Operating. . . . . 3/4 8-15 3/4.8.3 ELICTRICAL EQUIPMENT PROTECTICN OEVICES Containment Penetration C:nductor Overcurrent )

Protective 0evices..................................... 3/4 8-13 ,

Motor-Operated Valves Thermal Overicad Protaction and/o r Sypas s 0 ev i c e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .  !

3/4 3-29 '

I Lsv4 {

i e

FARLEY-UNIT 2 IX

l l

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4 INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CTCLE............................................... B 3/4 7-1 3/4.7.2 STEAM GENERATOR FRESSURE/ TEMPERATURE LIMITATICN............. B 3/4 7-3 3/4.7.3 COMPONENT COOLING VATER SYSTEN............... . ............ B 3/4 7-3 3/4.7.4 SERVICI VATER SYSTEM....................... . .............. 3 3/4 7 3 3/4.7.5 RIVER VATER SYSTEM....................~ ................... B 3/4 7-3 3/4.7.6 ULTIMATE HEAT SINK.......................................... B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCT VENTILATION SYSTEN. . . 5 . .3/4

. . .7-4 3/4.7.8 ECCS FUMP ROOM EZHAUST AIR FILfRATION SYSTEN................ B 3/4 7-4 3/4.7.9 SNUBBERS.................................................... B 3/4 7-5 l

3/4.7.10 SEALED SOURCE CONTAMINATION................................. B 3/4 7-6 3 / 4. 7.11 3P " *"""" S4444445EMG- ( De le t ed ) . . . . . . . . . . . . . . . . . .B. .3/4 . . .7-6 3/4.7.12 ." "" !???. "* ""'_..O!!050 (Deleted)......................... B 3/4 7-7 3/4.7.13 AREA TEMPERATURE MONITORING...........,..................... B 3/4 7-7 M44[ 2.,

3/4.8 ELECTRICAL POVER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POVER DI STRIBITTION SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3/4.8.3 ELECTRICAL EQUIPitENT FROTECTION DEVIC 33. . . . . . . . . . . . . . . . . . . . . 5 3 E

FARLEY-UNIT 2 IIV AMENDMENT NO. 88

. . . . - . . . . .- . - -.- ._ . _. . ...- -....-. -.~

l l

l Insen 1 i 3/4.7.14 FUEL STORAGE POOL BORON CONCENTRATION ..... 3/4 7-67 3/4.7.15 FUEL ASS EMBLY STORAGE . .......... . ............ .......... 3/4 7-68 Insen 2 3/4.7.14 FUEL STORAGE POOL BORON CONCENTRATION ......B 3/4 7-7 3/4.7.15 FUEL ASSEMBLY STORAGE.....................................B 3/4 7-7 l

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'l PLANT SYSTEMS 3/4.7.14 FUEL STORAGE POOL BORON CONCENTRATION l

LIMITING CONDITION FOR OPERATION i

l 3.7.14 The fuel storage pool boron concentration shall be greater than or equal to 2000 ppm.

APPLICABILITY: When fuel assemblies are stored in the fuel storage pool.

ACTION:

With the fuel storage pool boren concentration less than 2000 ppm, immediately suspend movement of fuel assemblies in the fuel storage pool, and initiate action l to restore the fuel storage pool boron concentration to within its limit. The

]

provisions of Specification 3.0.3 are not applicable. J SURVEILLANCE REQUIREMENTS <

l

)

4.7.14 The boron concentration of the fuel storage pool shall be determined to be within the limit at least once per 7 days.

i j

FARLEY-UNIT 2 3/4 7-67 AMENDMENT NO.

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pr mT cycTFve 1/d "1 iM FTTFT. ARCFMRT.Y CTnD hr:P l

LkMITING'CONDITIONFOROPERATION 3.7.15 The combination of initial enrichment and burnup of each fuel assembly stored in the spent fuel storage pool shall be within the Acceptable turnup Domain of Figure 3.7-1, or shall be stored in accordance with Specification 5.6.1.1.

a ppi.T ham it. TTY : Whenever any fuel assembly is stored in the a.:nt fuel storage l pool. I acTTnn:

With the requirements of the above specification not satisfied, initiate action to move the noncomplying fuel assembly to an acceptable storage location. The  !

! provisions of Specification 3.0.3 are not applicable. l I

SURVEILLANCE REQUIREMENTS '

i 4.7.15 The combination of initial enrichment and burnup of each fuel assembly l shall be verified to be in accordance with Figure 3.7-1 or Specification 5.6.1.1 within 7 days following the relocation o~r addition of fuel assemblies to the spent .

fuel storage pool. . .

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l FARLEY-UNIT 2 3/4 7-68 AMENDMENT NO.

l l l l l l

45000 . . . ._ _ -. . . ..

40000 - .- - - . . . . .. .-

. _ . . - - - - . - - - . . - - - , . - . . - .s- --n . - . . - . -n- + - . - . . + , -

+. . ~ . - , - . . _ . . - - - - - . _, .. . . - . _ _ . -n-..+ . _ . - . .

- 35000 ._-_._. -

3 . - - - _ . - . - . .. - - - -

g _ . . _ . .__ _ _ _ . _ -_

g _ _ _ . _ _ _ _ - - _ . . . _ .~ . _ . . . _ . . _ - __ _ _ . . . . . _ _

s __. __... . _._ _ . _ _ _ _ _ .- _ . _

O 30000 g _ . - -

ACCEPTABLE -- - ----

g _, .

- ~ __ _._.__ _

Q , _ . . . . _ . ._4 - _.+_ , .

3 25000 c

6 g __.._.n_ ___n........ . . _ , _ . . _ . . _ _ _ . _ _ _ . . _ . . . _ _ - .

g . . _ . - - . . - . . -.--. . - . . _----  :-_.-.-_

x

.c 20000 .

r E <

e _-_ a_ . _. - _

m i i m ' ' ,

<C 15000 .

. . . . ..%.~.-.% _. .__+__#. .., .- 4...+.--- .% 4-_...~.

s . - _ _ _ . _ . . _ . _ _ . - , . _ _. __ - __

IL -. . _ -- _ . . . - . . _ - - - .

10000 . ,

_u  !

i 2

. __1_. .

i 5000 UNACCEPTABLE

_+_ p 2__ -

_1_p _ 4 _. . . . - _ . __ ._2__. _; .-

0 1.0 2.0 3.0 4.0 5.0 initial U-235 Enrichment (nominal w/o) l Figure 3.7-1 Fuel Assembly Burnup Limit Requirements For All Cell Storage ,

1 FARLEY UNIT 2 3/4 7-69 AMENDMENT NO.

1

.- _ . -- - -_ - - - - - - - - - . - ,=. .

DESIGN TEATURES

' l 5.6 FUEL STORAGE _

CRITICALITY 5.6.1.1 The spent

=

  • ' fuel storage racks are designed and shall be maintained c,A 3 h/. (bor&sh he H00 Ph 5

K,gg less than or equal to 0.95 when flooded with $p64s'g/ wate , g l

which includes conservative allowances for uncertainties and biases. ,

i C. /. A nominal 10.75 inch center-to-center distance between fuel 4

assemblies placed in the storage racks.

A f. A maximum nominal enrichment af[$.o -l. U-256.

/ 4.25 wei he ere nt U- 35 fo Westi ghouse LOP as fuel 1 es.

[ 50w ght per nt U- 35 fo West nghous ora r

.uel sse lie AGE-

. We ting use o and .A -5 f 1 wi max omin 1 en chmen a gre ter th 3. weig per eat U-s ch 35 at s alla ontai suff cient integr be able ser ers xim ref rence fuel a semb1 K.,less e an or {

equa to 1 455 a 68'r is mai tained.

l 5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with:

a. [$

K,gg less than or equal to 0.98, assuming aqueous foam moderation. .

3.

A nominal 21 assemb11- inch center-to-center placed in the storage racks.distance between new fuel l c.

A maxim s r.minal enrichment of: .

1.

4.25 weight percent U-235 for Westinghouse /flPd(' fuel 4 % Opkwne9 2.

assembliesy u:% ;%4uo C.J Asw W L A r.k on w F.4 A e b g 5.0 weight percent U-235 for Westingfouse #9e yay?))CX-/

zuel assemblie7. westinghous APA png WMyy5 fuel with red diwcw maximum nominal enrichments greater char. 3.S weight percent U-235 shall contain sufficient integraJ, burnable absorbers l such that a mawimum reference fuel ass ambly K.,. less than or equal to 1.455 at 68'r is maintained.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1407 fdel assemblies.

5.7 CCMPCNENT CYCLIC CR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall' be maintained within the cyclic or transient limits of Table 5.7-1.

TAALEY - UNIT 2 5-7 AMENCMENT NO.

43,84,101

Insert 3

a. k ,,less than 1.0 when flooded with unborated water, which includes conservative allowances for uncertainties.

Insert 4

e. New or partially spent fuel assemblies with a combination of discharge burnup and initial enrichment in the " acceptable range" of Figure 3.7-1 may be allowed unrestricted storage in the spent fuel racks (also shown as the All Cell Storage configuration in Figure 5.6-2).
f. New or partially spent fuel assemblies with a combination of discharge burnup and initial enrichment in the " unacceptable range" of Figure 3.7-1 will be stored in compliance with Figures 5.6-1 through 5.6-5. The high enrichment fuel assemblies shown in the Burned / Fresh Storage configuration in Figure 5.6-2, with maximum nominal enrichments greater than 3.9 w/o U-235 shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly k. less than or equal to 1.455 at 68' F is maintained.

0 e

I l

45000 t 40000 b

P n -

D

y. 35000 I

[

_=

2 s 9 -

O

' _ L._

3 30000 ,

3 ACCEPTABLE  ;

~

. P i 1 '

a

,  ! t

! I c

k.

25000 7;. .

3 ._

i -

g i t i i i , i i i I ' # '

I

! _a  ;

.A._ ,

i

/ i ,

.o 20000 ,

f  : , ,

i E > i i / it < ' i e i i i i 4 > 4

/!  ! ! i i , i -

N , i i I i / f I I i l e <

!  ; /:

i

, i i i i t ,

15000  ; , ,

! , 4 4 i i i

O s > '

=

i i i t l  ; i i  !

g . > , ,

4 UNACCEPTABLE 10000

. . , n/ l f, ll

{

~7 ' i/ l t l l l 1 i ! l l l

. i  !/  !

! I i 1 i i i ' i 5000 ,

ll7 llll llll ll,!

_i L i  !

!  ;  ! i i i i i

!  ; I  ! i i i i i i i! i i l i

! l i  ! I i I I !

_i '

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, I i i  : i i i , , i 0

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (nominal w/o)

Figure 5.6-1 Fuel Assembly Bumup Limit Requirements for Low Enrichment (L) f Assembly of the BurnedTresh Checkerboard Storage (see Figure 5.6-2) l I

l FARLEY - UNIT 2 3-9 AMENDMENT NO.

s A A A A All Cell Storage C Empty H L Empty C L L l

2-out-of-4 Storage Burned / Fresh Storage Note:

A = All Cell Enrichment (Figure 3.7-1)

C = 2-out-of-4 Enrichment (No restriction on enrichment or burnup)

L = Low Enrichment of Burned / Fresh (Figure 5.6-1)

II = Ifigh Enrichment of Burned / Fresh (See section 5.6.1.1.f for IFBA requirement)

Empty = Empty Cell Figure 5.6-2 Spent Fuel Storage Configurations FARLEY - UNIT 2 5-10 AMENDMENT NO.

l l

1 A A A A A A l l

l A A A A A A l Interface A A A A A A

- - = == == =

L L L ,A A A

L H L 'A l

A A L L L l A A A l l l l l

l Note:

A = All Cell Enrichment i

L = Low Enrichment of i Burned / Fresh i II = Illgh Enrichment of Burned / Fresh t

l l Boundary Between All Cell Storage and BumedTresh Storage i

Note:

l 1. A row of empty cells can be used at the interface to separate the configurations.

l 2. It is acceptable to replace an assembly with an empty cell.

Figure 5.6 3 Interface Requirements l

FARLEY - UNIT 2 5 11 AMENDMENT NO.

l l \

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1 l

l 1 l l ,

A A A A A A l i

i A A A A A A  !

Interface l A empty A A A A i "mP* C Empty i

A A A l l

C empty C empty A A Empty C Empty l l

A A A l

1 Note:

A = All Cell Enrichment C = 2-Out-Of-4 Enrichment Empty = Empty Cell 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 as assembly with an empty cell.

i Figure 5.6-4 Interface Requirements FARLEY - UNIT 2 5 12 AMENDhENT NO.

. l l

l l

Empty C empty C empty C Intedace C empty C empty C empty l

Empty C empty C Empty C H empty H h empty C empty ,

l L L empty C empty C .

H L H1 empty C empty  !

h i

Note:

C = 2-Out-Of-4 Enrichment L = Low Enrichment of Burned / Fresh II = Iligh Enrichment of Burned / Fresh Empty = Empty Cell Boundary Between 2-out-of-4 Storage and Burned / Fresh 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.

l l Figure 5.6-5 Interface Requirements I

l FARLEY- UNIT 2 5-13 AhENDhENT NO.

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e FUUff SYSTEMS

BASES 3/4.7.12 FIRE BARRIER PENETRATIONS This specification deleted. l 3/4.7.13 AREA TEHFERATURE MONITORING The area temperature limitations ensure that safety-related equipment vih not be subjected to temperatures in excess of their environmental qualification temperatures. Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERASIL}TT. The temperature limits include an allowance for instrument error of 2 F.

O/b h 1

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). FARLET-UNIT 2 5 3/4 7-7 ANENDMDff NO. 88

i Insert 5 )

1 3/4.7 14 FUEL STORAGE POOL BORON CONCENTRATION 3/4.715 FUEL ASSEMBLY STORAGE p The spent fuel storage racks contain storage locations for 1407 fuel assemblies. The spent fuel racks l have been analyzed in accordance with the methodology contained in WCAP 14416-NP A, i

Westinghouse Spent Fuel Rack Criticality Analysis Methodology", Revision 1. November,1996. This 4 l

methodology ensures that the spent fuel rack multiplication factor, k ,is less than 0.95, as <

recommended by ANSI 57.2-1983 and the guidance contained in NRC Letter to All Power Reactor j Licensees from B. K. Grimes, "OT Position for Review and Acceptance of Spent Fuel Storage and '

Handling Applications", April 14, 1978. The codes, methods, and techniques contained in the methodology are used to satisfy this k,, criterion. The spent fuel storage racks are analyzed to allow

, storage of all Westinghouse 17X17 fuel assemblies with nominal enrichments up to 5.0 w/o U-235

! utilizing credit for checkerboard configurations, burnup, Integral Fuel Burnable Absorbers, and soluble boron, to ensure that k,,is maintained 10.95, including uncertainties, tolerances, and accident conditions. In addition, the spent fuel pool k,,is maintained < 1.0 including uncertainties and tolerances on a 95/95 basis without soluble boron.

The soluble boron concentration required to maintain k,,10.95 under normal conditions is 400 ppm.

The following storage configurations and enrichment. limits were evaluated in the spent fuel rack criticality analysis:

Westinghouse 17X17 fuel assemblies with nominal enrichments less than or equal to 2.15 w/o U-235 can be stored in any cell location as shown in Figure 5.6-2. Fuel assemblies with initial nominal enrichments greater than these limits must satisfy a minimum burnup requirement as shown in Figure l 3.7-l.

1 Westinghouse 17X17 fuel assemblies with nominal enrichments less than or equal to 5.0 w/o U-235 can be stored in a 2 out of 4 checkerboard arrangement as shown in Figure 5.6-2. In the 2 out of 4 I checkerboard storage arrangement,2 fuel assemblies can be stored corner adjacent with 2 empty storage cells. ]

Westinghouse 17X17 fuel assemblies can be stored in a bumed/ fresh checkerboard arrangement of a 2X2 matrix of storage cells as shown in Figure 5.6-2. In the burned / fresh 2X2 checkerboard arrangement, three of the fuel assemblies must have an initial nominal enrichmbat less than or equal to l 1.6 w/o U-235, or satisfy a minimum burnup requirement for higher initial enrichments as shown in j Figure 5.6-1. The fourth fuel assembly must have an initial nominal enrichment less than or equal to i

3.9 w/o U-235, or satisfy a minimum Intergral Fuel Burnable Absorber requirement for higher initial l enrichments to maintain the reference fuel assembly k. less than or equal to 1,455 at 68* F.

f . .

Specncations 3.7.15 and 5.6.1.1 ensure that fuel assemblies are stored in the spent fuel racks in accordance with the configurations assumed in the spent fuel rack criticality analysis.

The most limiting accident with respect to the storage configurations assumed in the spent fuel rack criticality analysis is the misplacement of a 5.0 w/o U 235 fuel assembly into an empty storage cell location in the 2 out of 4 checkerboard storage arrangement. The amount of soluble boron required to maintain k,,less than 0.95 due to this fuel mistoad accident is 850 ppm. The 2000 ppm limit specified in the LCO is consistent with the normal boron concentration maintained in the spent fuel pool, and bounds the 850 ppm required for a fuel mistoad accident.

g Specification 5.6.1.1 b. requires that a boron concentntion of 400 ppm in the spent fuel pool will

maintain k,,10.95. A spent fuel pool boron dilution analysis was performed to determine that sufficient time is available to detect and mitigate dilution of the spent fuel pool prior to exceeding the k,, design basis limit of 0.95. The spent fuel pool boron dilution analysis concluded that an l

I.

}

l 1ssaA S) w t.. i l

inadvertent or unplanned event that would result in a dilution of the spent fuel pool boron concentration from 2000 ppm to 400 ppm is not a credible event.  !

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ATTACHMENT IV  ;

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FARLEY NUCLEAR PLANT i

TECHNICAL SPECIFICATIONS CHANGE REQUEST l

l SPENT FUEL POOL SOLUBLE BORON CREDIT l i ,

{

CRITICALITY ANALYSIS i i  !

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4

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