ML20199F875

Amends 133 & 125 to Licenses NPF-02 & NPF-08,respectively, Changing Plant TS to Incorporate Requirements Necessary to Change Basis for Prevention of Criticality in FSP

ML20199F875
Person / Time
Site:	Farley
Issue date:	01/23/1998
From:	Berkow H NRC (Affiliation Not Assigned)
To:
Shared Package
ML20199F881	List: ML20199F875 ML20199F893
References
NUDOCS 9802040150
Download: ML20199F875 (35)

Text

- _ _ _ _ _ _

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UNITED STATES j

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NUCLEAR REGULATORY COMMISSION p

WASHINGTON, o.C. sones-ecoi SQUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH.M. FARLEY NUCLEAR PLANT. UNIT 1 0

MNDMENT TO FACILITY OPERATING LICENSE Amendment No.133 License No. NPF-2 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Southern Nuclear Operating Company, Inc.

(Southen: Nuclear), dated June 30,1997, as supplemented September 25, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chnpter I; B.

The facility i - I 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; D.

The issuance of this license 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.

2.

Accordingly, the license is amended by 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-2 is hereby amended to read as follows:

9802040150 990123 PDR ADO (,K 05000348 P

PDR I

t 2

(2)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendr: ant No.133, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION a

rbert N. Berko, Director Project Directorate ll-2 Division of Reactor Projects -1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of lasuance: January 23, 1998 a

ATTACHMENT TO LICENSE AMENDMENT NO.133 TO FACILITY OPERATING LICENSE NO. NPF-2 l

DOCKET NO. 50-348 l

1 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remova insert IX IX XIV XIV 3/4 7-95 3/4 7-96 3/4 7-97 5-7 5-7 5-7a*

5-9 5-10 5-11 5-12 5-13 5-14 8 3/4 7-7 8 3/4 7-7 B 3/4 7-8

' overflow page - no chang.

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_________.._.J

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

l l

SECTION R&gl 3/4.7.13 FUEL STORAGE POOL BORON CONCENTRATION.............. 3/4 7-95 3/4.7.14 FUEL ASSEMBLY STORAGE.............................. 3/4 7-96 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES ope r a t i ng............................................ 3 / 4 8 - 1 Shutdown............................................. 3/4 8-6b 3/4.8.2 ONSITC POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating........................ 3/4 8-6c A.C. Distribution - Shutdown......................... 3/4 8-7 Auxiliary Building D.c. Distribution -

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

Auxiliary Building D.C. Distribution -

Shutdown............................................. 3/4 8-11 Service Water Building D.C. Distribution -

Operating............................................ 3/4 8-12 FARLEY-UNIT 1 IX AMENDMENT NO.'E6 '98--

i 133 l

)

e INDEX BASES SECTION Fl&E 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYTLE.........................................B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...............................

............B 3/4 7-3 3/4.7.3 COMPONENT OOOLING MATER SYSTEM.........................B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM..................................S 3/4 7-3 3/4.7.5 RIVER WATER SYSTEM....................................B 3/4 7-3 3/4.7.6 ULTIMATE HEAT SINK....................................H 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................................................B 3/4 7-4 3/4.7.8 ECC9 PUMP ROOM EXMAUST AIR FILTRATION SYSTEM................................................B 3/4 7-4 3/4.7.9-SNUBBERS..............................................B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION...........................B 3/4 7-6 3/4.7.11 (Deleted)....................B 3/4 7-6 3/4 7.12 (Deleted)...................B 3/4 7-7 3/4 7.13 FUEL STORAGE POOL BORON CONCENTRATION

................b 3/4 7-7 3/4 7.14 FUEL ASS EMBLY STORAGE............................... 3 3 / 4 7-7 3/4.8 ELECTRICAL POWEP SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS......................................B 3/4 8-1 FARLEY-UNIT 1 XIV AMENDMENT NO.-26 -9E 7

T 133 L1

_.. _ -.~. _____

e PLANT SYSTEMS 3/4.7.13 FUEL STORAGE POOL BORON OONCENTRATION LIMITING CONDITION FOR OPER.J, ' '

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

APPLIC ABILITY:

When fuel assemblies are stored in the fuel storage pool.

ACTION:

With the fuel storage pool boron concentration less than 2000 ppm, imsrodiately -

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

• rovisions of Specification 3.0.3 are not-applicable.

SURVEILLANCE REQUIREMENIS i

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.

i 4

d i

-FARLEY-UNIT 1 3/4 7-95 AMENDMENT No.133

e PLANT SYSTEMS 3/4.7.14 FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION s

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 5.6.1.1.

APPLICABILITY:

Whenever any fuel assembly is storeo in the spent fuel storage pool.

ACTION:

jlg 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.

SURVEILLANC2 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.

FARLEY-UNIT 1 3/4 7-96 AMENDMENT NO.133

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45000 40000 35000 3

F-2 li

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O 30000 3

ACCEPTABLE E

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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 Requirements For All Cell Storage FARLEY-UNIT 1 3/4797 AMENDMENT NO.133 l

DESIGN FEATURES 5.6 FUEL STORAGE 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.

i New or partially spent fuel assemblies with a combination of discharge

.e.

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.

1 assemblies with a combination of. discharge 1

- burnup and initial enrichment in the " unacceptable range

• of Figure 3.7-1 will-be stered'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 fue1< assembly k less than or equal to 1.455 at 68'F is maintained.

g.

' Damaged fuel assemblies F02, F05, F06, F15, F17, F18, F19, F20, F30, F31, and F32 shall be stored in accordance with Figure 5.6-6..

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

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

a.

b.

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

c.

A maximum nominal-enrichment of:

1.

4.25 weight percent U-235 for Westinghouse fuel assemblies with Standard Fuel. Assembly fuel rod diameter.

2.

5.0 weight percerit U-235 for Westinghouse feel assemblies with Optimized Fuel Assembly fuel rod diameter.

Westi ghoure fuel withl Optimized Fuel Assembly fuel rod diameter ale maximum ncininal enrichments greater than 3.9 weight percent U-235. sha1.1 contain sufficient integral burnable absorbers auch 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.-52r947410r133

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 ce 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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FARI.EY-UNIT 1 5-7a AMENDMENT No.

133 1

45000 40000 3

35000 g

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30000 ACCEPTABLE

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

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

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

FARLEY UNIT 1 59 AKarDMENT NO 133

G A

A A

A All Cell Storage C

Empty H

L Empty C

L L

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

A = All Cell Enrichment (Figure 3.71)

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

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

H = High 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 I 5-10 AMENDMENT NO.133 l

i A

A A

A A

A A

A A

A A

A Interface

\\__- A A

A A

A A

L L

L A

A.A L

H L

A A

A L

L L

A A

A l

1 I

Note:

A = All Cell Enrichment L = Low Enrichment of Burned / Fresh H = 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 FARLEY - UNIT I 5-11 AMENDMENT NO. 133 l

._______________l

i A

A

.A A

A A

A A

A A

A A

Interface

\\__ _A_

Empw A A

A A

Emph C Empty A A

A C'

C Empw Empy A A

l A A

A Emph C Empty l

l 1

Note:

A

= A ; Cell Enrich ent 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 1 3-12 AMENDMENT NO. 133 m

Empty C Empty C Empty C Interface C

empty C empty C empty k

Empty C Empty C Empty C

=.- --

h Empty H

. empty C empty h

h L

L empty C empty C l

H L

H L empty C empty h

I Note:

C 2-Out Of-4 Enrichment

=

L Low Enrichment of Burned / Fresh

=

H Hi;;h Enrichment of Burned / Fresh

=

Empty =

Empty Cell Boundary Betw :n 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 conSgurations.

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

Figure 5.6-5 Interface Requirements FARLEY - UNIT 5-13 AMENDMENT NO. 133

F31 Empty F30 F06 ;l:;

\\

F18 F17 F19 F02 F15 F20 F05 F32 l':l.

. Water i

t Note: All Assemblies are 3.0 w/o2nU nominal enrichment Figure 5.6-6 Damaged Fuel Assembly Configuration FARLEY - UNIT I 5-14 AMENDMENT NO. 133

PLANT..5YSTLMS BASES

- 2/W 2 FIRE BARRIG PENETRATIONS This specification deleted.

3/4.7.13 & 3/4.7.14 FUEL STORAGE POOL RORON CONC 2NTRATION & 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 Analysts Methodology *,. Revision 1, November, 1906.- This methodology ensures that the spent fuel rack multiplication factor, keft-is less than 0.95, am recommended by ANSI 57.2-1983 and the guidarce 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 l

~ fuel storage racks are analysed to allow storage of all Westinghouse 17X17 fuel asivmblies with nominal enrichments up to 5.0 w/o U-235 utilising credit for cLw;kerboard configurations, burnup, Integral Fuel Burnable Absorbers, and

. soluble boron, to ensure that kogf is maintained 1 0.95, including uncertainties,.

tolerances, and accident condt.tions.

In addition,:the spent fuel pool kegg is maintained < 1.0 including uncertainties and tolerances on a 95/95 basis without soluble boron. No credit is taken for the presence of Boraflex absorber in any of

.these analyses.

The soluble boron concentration required to maintain keff 1 0.95 under normal conditions is 400 ppm.

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

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 assembliec with initial nominal enrichments greater than these limits must satisfy a minimum burnup requirement as shown in Figure 3.7-1.

Westinghouse J7X17 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 emr ; 9torage cells.

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

In the hurned/ fresh 2X2 checkerboard arrangement, three of the' fuel assemblies must ha've an initial nominal enrichment less than or equal to 1.6 w/o U-235, or satisfy a 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 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 NO26 96,132 7

j

e PLANT SYSTEMS BASES Specifications 3.7.14 and 5.6.1.1 ensure that fuel asseniblies 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 ff less than 0.95 due to this fuel mieload 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 exceeding the k,ff design basis limit of 0.95.

The spent fuel pool boron dilucion analysis concluded-that an inadvertent or unplanned event that would result in a dilution of theospent fuel pool boron concentration from 2000 ppm to 400 ppm is not a credible event.

1 FARLEY-UNIT 1 B 3/4 7-8 Amendment NO. 133 j

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t UNITED STATES

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NUCLEAR REGULATORY COMMISSION.

WASHINGTON, D.C,3088H001

\\.....J SOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 r

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 125 License No. NPF-8 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A The application for amendment by Southem Nuclear Operating Company, Inc.

1 (Southem Nuclear), dated-June 30,1997 as supplemented September 25,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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; D.

The issuance of this license amendment will not be inimical to the common defensa 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 requiremer.ts have been satisfied.

2.

Accordingly, the license is amended by 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-8 is hereby amended to read as follows:

o

o 2-(2)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.125, are hereby incorporated in the license. Southem Nuclear shall operate the facility in accordance with the Technical Specifications.

3.

This license amendmeniis effective as of its datt,f issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGUl.ATORY COMMISSION H rbert N. Berkow, Director Project Directorate 112 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of lasuance:

January 23, 1998 e

e ATTACHMENT TO L:0ENSE AMENDMENT NO.125 TO FACILITY OPERATING, LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginallines.

Remove 10and IX IX XIV XIV 3/4 7-67 3/4 7-68 3/4 7-69 5-7 57 5-7a*

5-9 5-10 5-11 5-12 5-13 r '/4 7-7 B 3/4 7-7 B 3/4 7-8

• overflow page - no change

e INDEX LIMITING COND!*.'!ONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

-sany.

alt.U.CLM 2AGI S'/4.7.14 FUEL STORACE POOL BORON CONCENTRATION.................. 3/4 7-67 3/4.7.15 FUEL ASSEMBLY STORAGE.................................. 3/4 7-68 Mfa9, EttCTRICAL l'0WER SYSTEMS 3/4.8/1 A.C. SOURCES o pe r a t i n g............................................... 3 / 4 8 - 1 Shutdown................................................

3/4 8-8 l

3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Di st ribution - Ope rating........................... 3 / 4 8-9 A.C. Distribut ion - Shutdown............................

3."4 8-10 Auxiliary Building D.C. Distribution - Operating........ 3/4 8 Auxiliary Building D.C. Distribution - Shutdown.........

3/4 8-14 Service Water suilding D.C. Distribution - Operating.... 3/4 8-15 3/4.8.1 ELECTRICAL EQUIPMENT PROTECT!0.4 DEVICES Containment Penetration conductor overcurrent Protective Devices......................................

3/4 B-18 Motor-operated Valves Thermal overload Protectior.

and/or Bypass Devices...................................

3/4 8-29 FARLEY-UNIT 2 IX AMENDMENT No.125 1

e INDEX BASES SECTION P. Mil 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE............................................ B 3/4 7-1 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 3/4.7.5 RIVER WATER SYSTEM....................................... B 3/4 7-3 3/4.7.6 ULTIMATE HEAT SINK....................................... B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................ B 3/4 7-4 3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM............. B 3/4 7-4 3/4.7.9 SNUBBERS................................................. B 3/4 7-5 l

3/4.7.10 SEALEO SOURCE CONTAMINATION..............................

B 3/4 7-6 3/4.7.11 m

(Deleted)....................... B 3/4 7-6 3/4.7.12 (Deleted)...................... B 3/4 7-7 3/4.7.13 AREA TEMPERATURE MONITORING.............................. B 3 / $ 7-7 l

3/4 7.14 FUEL STORAGE POOL BORON CONCENTRATION

....................B 3/4 7-7

}

3/4 7.15 FUEL ASSEMBLY S'.' SPACE

....................................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 8YSTEMS..................................... B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTION DEVIC?,5.................. B 3 /4 8-1 FARLEY-UNIT 2 XIV AMEN 0 MENT NO.88r125 l

ELANT SYSTEMS I

jf_{s 7.14 FUEL STOAACE POOL BQRON. CONCENTRATION LIMITING CONDITION FOR OPERATION

---...+c

..m W

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 l

to restore the fuel storage pool boron concentration to within its limit. The provisions of specification 3.0.3 are not applicable.

SURVEILLANCE REQUIRTMENTS

• 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 t

FARLEY-UNIT 2 3/4 7-67 AMENDMENT NO.125

)

PLANT SYSTEMS 3/4.7.15 FUEL ASSEMLLY STORACE LIMITING CONDITION FOR OPERATiuN 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 accordunce with specification 5.6.1.1.

&PPLicAaILITYs Whenever 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 ncncomplying fuel assembly to an acceptable storage location.

The provisions of specification 3.0.3 are n*t 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 F.6.1.1 within 7 days following the relocation or addition of fuel assemblies to the spent fuel storage pool.

i

=

4 FARLEY-UNIT 2 3/4 7-68 AKENDKENT135

45000 40000 35000

D E

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30000 l.

ACCEPTABLE z

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. i i i

/i j j i

l i

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- i 10000

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i i i i i

rf i i

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i 5000 l

lf UNACCEPTABLE

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i !

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/I i ;

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

Figure 3.71 Fuel Assembly Bumup Limit Requirements For All Cell Storage FARLEY. UNIT 2 3/4 7-69 AMENDMENT NO.125 A

a

\\

DESIGN FEATURES s.6 rurt sToRAcE CRITICALLIX 5.6.1.1 The spent fuel storage racks are designed and shall be maintained withs K,gg less than 1.0 when flooded with unborated water, which includes a.

conservative allowances for uncertainties.

b.

K,gg less thre or equal to 0.95 when flooded with water borated to 400 ppm, which includes conservative allowances for uncertainties and biases.

c.

A nom!nal 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 ebown 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:

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

a.

b.

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

c.

A maxiv.um nominal enrichmant 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 optimited Fuel Assembly fuel rod diameters.

Westinghouse fuel with Optimited Fuel Assembly fuel rod diameters 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 er equal to 1.455 at 68'F is mafatained.

FARLEY-UNIT 2 5-7 AMENDMENT No.-43,84r

-404,125

~

DESIGN FEATUP.E8 DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent dra.ning of the pool below elevation 149.

CAPACITY 5.6.3 The-opent fuel storage p.o1 is designed and shall be maintained with a-storage capacity limited to no more than 1407 fuel assemblies.

1.7 COMPONENT CfCLIC OR TRANEIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed _and shall be maintained within the cyclic or ts.ansient limits of Table 5.7-1.

m

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FARLEY-UNI" ?.

5-7a AMENDMENT No.125

45000 40000 p__

nD 35000

/.__.

F

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ACCEPTABLE 3

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c 25000

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UNACCEPTABLE 10000 l

5000 --

t k

~~I 0

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

Figure 5.61 Fuel Assembly Bumup Liniit Requirements for I.ow Enrichment (L)

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

FARLEY UNIT 2 59 AMENDMENT NO.125

e 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 = 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 5.61)

H = High 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 AhENDMENTgg.

1 o

i A

A A

A A

A A

A A

A A

A Interface

\\__-

L L

L A

A A

L H

L A

A A

L L

L A

A A

i 1

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.

Figme 5.6-3 Interface Requirements FARLEY UNIT 2 5 11 AhENDhENT NO.125

4 I

A A

A A

A A

A A

A A

A A

Interface

\\__. _A_

empty A A

A A

emph C Emp*i A A

A C'

C emaw Empty A A

l Empty C

Empe A A

A l

l l

1 Note:

A

= All Cell Enrichment C

= 2 Out Of-4 Enrichment Empty = Empty Cell Boundary Betmen All Cc!! 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 replac*

• assembly with an empty cell.

l l

Figure $.64 Interface Requirements l

FARLEY - UNIT 2 5 12 ASIENDMENT NO.125 l

Empty C Empty C Empty C IntedaCO Empty C Empty C Empty Empty C Empty C Empty C H

Fmpty H Empty C Empty L

L Empty C Empty C I.

H L

HI Empty C Empty 1'

I 4

Note:

C 2 Out Of 4 Enrichment

=

L Low Enrichment of Burned / Fresh

=

l H

High Enrichment of Burned / Fresh

=

Empty =

Empty Cell Boundary Detween 2 outer 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.

Figure 5.6 5 Interface Requirements FARLEY UNIT 2 5 13 AhENDhENT N0125 I

s e

PLANT.SYSTEhd BASE 0

)/4.7.12 FIPf.RARRIER.PEFETRATION This specification deleted.

3/4.7.13 AREA TEMPERATURE MONITORING 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 oPERAsILITY. The temperature limits include an allowance for instrument error of 2*F.

2/4.7.14 & 3/4.7.15 FUEL STORAGE POOL SQSON CONCENTRATION & FUEL ASSEMBLY STORAGE l

The spent fuel storage racks contain storage locations for 1407 fuel assemblies.

The spent fuel racks have been analysed in accordance with the methodology contained in WCAP-14416-NP-A, Westinghouse Spent Fuel Rack Criticality Analysis Methodology", Revision 1, Novembos, 1996. This methodology ensures that the spent fuel rack multiplication factor, k ff is less than 0.95, as recommended by ANSI 57.2-1983 and ti.a guidance contained in NRC Letter to All Power Reactor Licensees from B. K. Grimou, "OT Position for Review and Acceptance of Spent Tuol Storage and Handling Applications", April 14, 1978. The codas, methods, and tr chniques contained in the methodology are used to satisfy this kegg criterion.

The spent fuel storage racks are analysed to allow storage of all Westinghouse 17F17 fuel assemblies with nominal enrichments up to 5.0 w/o U-235 utilising credit for checkerboard configurations, burnup, Integral Fuel Burnable Absorbers, and soluble boron, to ensure that kegg is maintained S 0.95, including uncertainties, tolerances, and accident conditions.

In addition, the spent fuel pool kegg is maintained < 1.0 includLng uncertainties and tolerances on a 95/95 basis without soluble boron. No credit is taken for the presence of Boraflex absorber in any of these analyses.

The soluble boron concentration required to maintain koft s 0.95 under normal conditions is 400 pum.

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

Westinghouse 17X17 fu21 assemblies with nominal enrichments less than or equal

-2.15 w/o U-235'=an 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.

Westinghouse 17X17 fuel assemblies with nominal enrichments less than or equal to 5.0 w/o U-235 can be ptored in a 2 out of 4 uheckerboard 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 FARLEY-UNIT 2 8 3/4 7-7 AMENDMENT NO.-88 125 T

- - ~ -.. _ -

l 4

PLANT SYSTEMS BASES minimura 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 Integral Fuel Burnable Abscrber requirement for higher initial enricpments to maintain the reference fuel assembly 4

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

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 spent fuel l

rack criticality analysis.

The most limiting accident with respect to the storage configurations assumed in the sper.: fuel rack criticality analysis is the misplacement of a 5.0 w/o U-235 fuel e.a' oly into an empty storage cell location in the 2 out of 4 checkerboard stora p arrangement. The amount of soluble boron required to maintain koft less than 0.95 due to this fuel mieload accident is 850 ppm. The 2000 ppm limit specified in the LCO is consistent with the normal boron concentrai: ton maintained in the spent fuel pool, and bounds the 850 ppm required for a fuel mis!oad accident.

specification 5.6.1.1 b. requires that a boron concentration of 400 ppm in the wpent fuel pool will maintain keff $ 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 prier to exceeding the kegg design basis limit of 0.95.

The spent fuel pool boron dilution analysis concluded that 4

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

E 4

i-FARLEY-UNIT 2 8 3/4 7-8 AMENDMENT No.125

_