ML20141M132

Proposed Tech Specs Associated W/Spent Fuel Pool Storage

ML20141M132
Person / Time
Site:	Sequoyah
Issue date:	03/27/1992
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20141M131	List: ML20141M130 ML20141M132 ML20141M134
References
NUDOCS 9204010286
Download: ML20141M132 (30)

Text

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t ENCLOSURE 1 PROPOSED TECIDiICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-92-01)

LIST OF AFFECTED PAGES Unit 1 3/4 9-la, 3/4 9-7, B 3/4 9-2, 5-5 Unit 2 3/4 9-2, 3/4 9-8, B 3/4 9-2, 5-5 l

l 9204010286 920327 PDR ADOCK 05000327 P PDR

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l 3/4.9 = REFUELING OPERAIIONS C

SURVEILLANCE REQUIREMENTS (Continued) 4.9.1.3 One of the following valve combinations shall be verified closed under administrative control at least once per 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:

Combination A Combination B Combination C Combination 0

a. 1-81-536 a. 1-81-536 a. 1-81-536 R16

a. 1-81-536

b. 1-62-922 b. 1-62-922 b. 1-62-907 b. 1-62-907

c. 1-62-916 c. 1-62-916 c. 1-62-914 c. 1-62-914

d. 1-62-933 d. 1-62-940 d. 1-62-921 d. 1-62-921

e. 1-62-696 e. 1-62-933 e. 1-62-940

f. 1-62-929 f. 1-62-929

g. 1"62-932 q. 1-62-932

h. 1.FCV-62-128 h. 1-62-696

. 1. 1-FCV-62-128 4.9.1.4 The boron concentration in the spent fuel pool shall be det rmined by chemical analysis to be greater than or equal to 2,000 parts per million (ppm) at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during fuel movement and until the configuration of R148 the assemblies in the storage racks is verified to com ly with-the c ittealt loading criteria specified in Design Feature 5.6.1.1. 4 35. 4, l . l j[ .

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l SEQUOYAH - UNIT 1 3/4 9-la Amndmegjj390 '

Insert A to the Sequoyah Technical , Specification 4.9.1.5 The boron concentration in the cask loading area of the cask pit l shall be determined by chemical analysis to be greater than or enual to 2000 parts ; .r million (ppm) at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during fuel movemer.t-in that area ar.d until the assemblies in that storage rack are verified to comply with the criticality 10ading criteria specified in Design Feature 5.6.1.1.e. '

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(d td REFUELING OPERATIONS t

3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2100 pounds

• shall be prohibited from travel over fuel assemblies in the storage pool. R95 3

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION: J With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.

)

SURVEILLANCE REQUIREMENTS 2

4.9.7 Crane irterlocks and physical stops which prevent crane travel with loads in excess of 2100 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days R95l thereafter during crane operation, n

The spent fuel pool transfer canal gate and the spent fuel pool divider gate -\

may travel over fuel assemblies in the spent fuel pool. R95

_J N ,A I SEQUOYAH - UNIT 1 3/4 9-7 Amendment No. 91 December 5, 1988

Insert B to the Sequoyah Technical Specification REFUELING OPERATIONS I

l 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA LIMITING CONDITION FOR OPERATION 3.9.7 Loads traveling over fuel assemblies in the spent fuel pit area shall be restricted as follows:

a. Spent fuel storage pools Loads in excess of 2100 pounds

• shall be prohibi:ed from travel over fuel assemblies in the spent fuel steenge pool.

b. Cask loading area of the cask pits

1. Loads which meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 may be carried over fuel ascemblies stored in the cask loading area of the cask pit if the impact shield is in place over the cask loading area.

2. Loads which do not meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9 shall be prchibited f rom travel over the cask loading area of the cask pit when fuel is stored in it.

APPLICABILITY: With fuel assemblies in the spent fuel storage pool or in the cask loading area of the cask pit.

ACTION:

Wit the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.7.1 Crane interlocks and physii>.1 stops which prevent crane hook travel over the storage pool shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation.

4.9.7.2 When fuel is stored in the cask pit area. verify administrative a

requirements concerning the impact shield are met prior to moving loads in excess of 2100 pounds across the cask pit area.

• The spent fuel pool transfer canal gate and the spent fuel pool divider gate may travel over fuel assemblies in the spent fuel pool.

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, Note: These curves are ap-

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plicable to carried loads

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exceeding 2100 lbs. and are noi applicable if there are 10 '1 static loads resting on the impact shield.

d 2 32 4

.2 10 ::

c  : .

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Impact Over An Area 23 . of 144 sq.ft.

o 10 ,=:

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b -

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l'npact r Over An Area U ~

of 8 sq.ft.

30 10 's -

Impact Over An ' Area of 1 sq.ft.

10 i i c . . ..: > > .

..iii . . i i . ...i 1 10 -

10* 10' Allowable Heiaht Above Shield Surface in.

FIGURE 3.9-1 RELATIONSilIP BETWEEN LOAD, ALLOWABLE IIEIGHT AND IMPACT AREA FOR OBJECTS TO BE CARRIED OVER THE IMPACT SHIELD

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REFUELINGOPERATIOM BASES 3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:

1) manipulator cranes will bc used for movement of drive rods and fuel assemblies,

2) each crane has sufficient load capacity to lift a drive rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped:

1) the activity release will be limited to that contained in a single fuel assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

lustRT b >

743T RESIDUAL HEAT REMOVAL 40 COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that; 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and 2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. The minimum required flow rate of 2000 gpm ensures decay heat removal, minimizes the probability of losing an RHR pump by air-entrainment from pump vortexing, and minimizes _the potential R138 for valve damage due to cavitation or chatter. Losing an RHR pump is a particular concern during reduced RCS inventory operation. The 2000 gpm value is limited by the potential for cavitation in the control valve and chattering in the 10-inch check valve.

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating RHR loop will not result _in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the cor2.

i SEQUOYAH - UNIT l' B 3/4 0-2 Amendment No. 134 April 2, 1990 l

. .t' It'Aert C to the Sequoya,h Technical Specification Assurance against load drops over fuel stored in the cask loading area of the cask pit is achieved-by observance of the calculated load criteria which will prevent penetration of the impact shield in the event of a load drop.

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7 DESIGNFEAp)RES ,,,

5. 6 FUEL STORAGE gg k):7y CRlTIC Y-S FUEL

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5. 6.1.1 The spent fuel storage racks are designed for fuel enriched t9 5.0 weight percent U-235 and $ hill be maintained with: gi43

a. Ak ,

vivalent to less than 0.95 when flooded with unborated wat , .11ch includes a conservative allowance of 3.06% delta k/k for uncertainties.* R148 b.

A nominal 10.375 inch center-to-center distance between fuel assemblies placed in the storage racks.

c.

Fuel assemblies with enrichment greater than 4.0 weight percent U-235 and burnup less than 7,500 megawattday/ metric ton (mwd /mtu) shall be placed in cells in the spent fuel storage racks that face

( adjacent cells containing either:

1. R148 Fuel assemblies with accumulated burnup of at least 22,000 mwd /mtu, or

2. Water  % > ~[

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CRITICALITY - NEW FUEL

5. 6.1. 2 The new fuel pit storsge racks are desinned and shall be maintained with a nominal 21.0 inch center-to-center distance between new fuel assemblies such that k,ff will not exceed 0.98 when fuel having an enrichment of 4.5 weight percent U-235 is in place and optimum acnievable moderation is assumed. gica DRAINAGE 5.6.2 The spent fuel pit is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.

CAPACITY NEPtALE Id tTH 1s DUT-E

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5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1386 fuel assemblies.

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5. 7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are cesigned and shall be maintained within the cyclic or transient limits of Table 5.7-1.

• For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double contingency principle which giy requires two unlikely, independent, concurrent events to produce a criticality accident. '

SEQUOYAH - UNIT 1 5-5 Amendment No. 13, 60, 114 , 144 August 1, 1990

Insert D to the Sequoyah Technical Specifiention 5.6.1.1 The spent fuel storage racks are designed for fuel enriched to 5%

weight percent U-235 and shall be maintained with:

a. A Ke gg equivalent to less than 0.95 when ficoded with unborated water.*

b.

A nominal 8.972 inch center-to-center distance between fuel assemblies placed in the storage racks.

c. A three region arrangement in the 67ent fuel storage pool with the following definitions:

1. Region 1 is designed to accommodate new fuel with a maximem enrichmer.t of 4.95 + 0.05 wt1 U-235, or spent fuel regardless of the fuel burnep.

2. Region 2 is designed to accommodate-fuel of 4.95% initial enrichment burned to at least 50 MWD /KgU (assembly average), or fuel of other enrichments with a burnup yielding an equivalent reactivity in the fuel racks. The minimum required assembly average burnup in MWD /KgU la given by Y1 when Y = -23.761 +

22.075E - 2.0165E 2 + 0.1152E 3 where E is the initial enrichment in the axial zone of highest enrichment.

3. Re-lon 3 is designed to accommodate fuel of 4.95% initial enrichment burned to at least 41 MWD /KgU (assembly average). or fuel of other enrichments with a burnup yielding an equivalent reactivity in the fuel racks. The ainimum required assembly average burnup is given by Y(MWD /KgU) where Y = -25.7',25 + 18.76E

- 1.3933E 2 + 0.0666E 3

, where E is the initial enrichment in the axial zone of highest enrichment.

An empty cell is less reactive than any cell containing fuel and therefore may be used as a Region 1, Region 2, or Reglen 3 cell in any arrangement.

d.

The _

pools following arrangement of regions apply in the spent fuel storage

1. Region 1 fuel assemblies located along the periphery of the storage modules adjacent to the pool walls must be isolated from each other and from the inner Region 3 cells by at least one (1)

Region 2 spent fuel assembly (i.e., fuel of 50 MWD /KgU burnup or equivalent).

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• For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident.

n i Inaert D to the Sequoyah Technical 3pecification (continued) 2.

Itegion 1 fuel assemblies lecated along the wide water-gaps **

between storage modules must be isolated from each other and from the inner Region 3 cells by at least one (1) Region 2 spent fuel assembly (i.e., fuel of 50 MWD /KgU assembly average burnup or equivalent).

3.

Region 1 fuel assemblies located along the narrow water-gaps **

between storage modules must be isolated from each other by at least two (2) Region 2 spent fuel assemblies and from the inner Region 3 cells by at least one (1) Region 2 spent fuel assembly (i.e., fuel of 50 MWD /KgU assembly average burnup or equivalent).

4 A checkerboard pattern of fresh fuel and empty cells may be used throughout any storage module, or internal to any storage module in lieu of Reglon 3 f uel as shown in Figure 5.6-2.

! Figure 5.6-1 shows a typical arrangement of regions. Figure 5.6-2 illustrates internal module checkerboarding of fresh fuel with empty cells in a portion of the feel pool. F13 ure 5.6-3 illustrates the two burnup-enrichment equations (5.6.1.1.C.2 and 5.6.1.1.C.3) in graphical form.

e. Only spent fuel meeting the Region 3 burnup requirements shall be stored in any module in the cask loading area of the cask pit.

• • The nominal gap (2-1/8 inches) running in the E-W direction between the -

adjacent modules is rwferred to as the " wide gap." The N-S direction gap (1.5 inch) is referred to as the " narrow gap."

Insest E to the Sequoyah Techgeal Specification 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2091 fuel assemblies. In addition, no more than 225 fuel assemblies will be stored in a rack module in the cask loading area of the cask pit.

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2.s la as 4.s 4s s,. e INITIAL ENRIC-TENT. 50-235 Domain I:

Puel assemblies with initial enrichment-burnup combinations in Domain I may be placed in either Region 1, 2, or 3 ,

storage cells.

Domain II: ruel assemblies witt initial enrichment-burnup combinations in Domain II shall be placed only in Region 1 or 3 storage cells.

Domain III: Fuel assemblies with initial enrichment-burnup combinations in Domain III shall be placed only in Region 1 storage cells FIGURE 5.6-3

REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued)

4. 9.1. 2 The boron concentration of the reactor coolant system and the refueling canal.shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

4.9.1.3 One of the following valve combinations shall be verified closed under administrative control at least once per 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:

Combination A Combination B Combination C Combination 0

a. 2-81-536 a. 2-81-536 a. 2 81-536 a.

b. 2 62-922 2-81-536

b. 2-62-922 b. 2-62-907 b. 2-62-907

c. 2 62-916 c. 2-62 916 c. 2-62-914 c. 2-62-914

d. 2-62-933 d. 2-62-940 d. 2-62-921 d. 2-62 921

e. 2-62-696 e. 2-62-933 e. 2-62-940

f. 2-62-929 f. 2-62-929

g. 2-62 932 g. 2-62-932

h. 2-FCV-62-128 h. 2-62-696

1. 2-FCV-62-128 4.9.1.4 The boron concentration in the spent fuel pool shall be determined by chemical analysis to be greater than or equal to 2000 ppm at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during fuel niovement and until the configuration of the assembifes in the storage racks is verified to comp 1 g(('

specified in Design Feature 5.6.1.1. a44(t. hap 4ticalityloadingcriteria s

s (,,l, j f ,

m-Insart ~

A r-v p

SEQUL'AH - UNIT 2 3/4 9-2 Amendment No.125 August 1, 1990 i

__________.___-_______m__

Insert A to the Sequoyah Technical Specificatip3 4.9.1.5 The boron concentration in the cask loading area of the cask pit shall be determined by chemical analysis to be greater than or equal to 2000 parts per million (ppm) at laast onca per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during fuel movement in that area and until the assemblies in that storage rack are verified to comply with the criticality loading criteria specified in Design Feature 5.6.1.1.e.

s 4

t i

h

r

.c ym s f ~~ ^ ,* m - -

REFUEtit4G OPERATIONS i

3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA tx) [.-

LIMITINC CONDITION FOR OPERATION

}

3.9.7 Loads in excess of 2100 pounds

• shall be prohibited from travel over x81 fuel assemblies in the storage pool.

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

N With the requirements of the above specification not satisfied, place the \

crane load in a safe condition. The provisions of Specification 3.0.3 are not )

applicable. <

SURVEILLANCE REOUIREMENTS 4.9.7 Crane interlocks and physical stops which prevent crane travel with f$b R$1' loads in excess of 2100 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation.

)

• The spent fuel pool transfer canal gate and the spent fuel pool divider gate R81 may travel over fuel assemblies in the spent fuel pool.

,A A-SEQUOYAH - UNIT 2 ' 3/4 9-8 Amendment No. 81 December 5, 1988 k@ TAC,t 'lhMI ISERT b

_ - - _ - - _ _ - - - - - - - -Y

Insert B to the Sequoyah Technical Specification REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL - SDENT FUEL PIT AREA LIMITING CONDITION FOR OPERATION 3.9.7 Loads traveling over fuel assemblies it. the spent fuci pit area shall be restricted as follows:

a. Spent fuel storage poo11 Loads in excess of 2100 pounds

• sball ba prohibited from travel over fuel assemblies in the spent fuel storage pool,

b. Cask loading area of the cask pitt

1. Loads which meet the weight, cross-sectional impact area, and allowable travei helE ht critoria of Figure 3.9-1 may be carried over fuel assemblies stored in the cask loading area of the cask pit if the impact shield is in place over the cask loading t area.

2. Loads which do not meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 shall be prohibited from travel over the cask loading area of the cask pit when fuel is stored in it.

APPLICABILITY: With fuel assemblies in the spent fuel storage pool or in the cask loading area of the cask pit.

ACTION:

With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.7.1 Crane interlocks and physical stopa which provent crane hook travel over the storage pool shall be demonstrated OPERA 3tE within 7 days prior to crane use and at least once per 7 days thereaf ter during crane operatien. ,

4.9.7.2 When fuel _is stored in the cask pit area, verify administrative requirements concerning the impact shield are met prior _to moving loads in excess of 2100 pounds across the cask pit area.

• The spent fuel pool transfer _ canal gate and the spent fuel pool divider gate may travel over fuel assemblies in the spent fuel pool, e

a -

10*? -

,~ Note: These curves are ap-

~

plicable to carried loads ss

~

exceeding 2100 lbs. and are not applicable if there are 10 '?; otatic loads resting on the impact shisld.

.A-2v1 0 * =-

'E _

.(n -

, u g -

~. Impact Over An Area o 3 . of 144 sq.ft.

o 10 3 _

.o  : ~

b -

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m pact Over An Area of 8 sq.ft.

3O 10 *1' -

N '%

Impact Over An 'Areo of 1 sq.ft.

~

! 10  : . . . . ....i .. . . . , , . . . . . . . . ...,

-1 10 - +

10 2 10' Allowable Heiaht Above Shield Surface.. in.

FIGURE 3.9-1 RELATIONSHIP BETWEEN LOAD. ALLOWABLE HEIGMT AND IMPACT AREA FOR OBJECTS Td BE CARRIED OVER THE IMPACT SHIELD m -

REFUELING OPERATIONS k

i BASES 3/4.9.6 MANIPULATOR CRANE .i F

t The OPERABILITY requirements for the manipulator cranes ensure that:  ;

1) manipulator cranes will be used for movement of drive rcds and fuel assemblies  :

2) each crane has suf ficient load capacity to lif t a drive rod or fuel (15embly, , '

assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the st. rage pool ensures that in the event this Irad is dropped

1) the activity assembly, and release will be limited to that contained in a single fuel result in a critical ) anyarray.

possible distortion of fuel in the storage racks will not This assump 3isconQsj,t ith the activity release assumed in the accident analyse

+-y 3 g g -

3 /4. 9. 8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION .

The requirement that at least one residual heat removal (RHR) loop be in operation ensures that; 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 14 P F '

as required during the REFUELING H0DE, and 2) sufficient coolant circulation is maintained incident and prevent thru the stratification.

boron reactor core to minimize the effects of a boron dilution The minimum required flow rate of 2000 gpm ensures decay heat removal, minimizes the probability of losing an RHR pump by air entrainment from pump vortexing, and minimizes the potential for vdve damage due to cavitation or chatter. Losing an RHR pump is a R121 particular concern during reduced RCS inventory operation. The 2000 gpm value is in thelimited by the 10-inch checkpotential valve. for cavitation in the control valve and chattering The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. >

hHR the core. loop, adequate time is provided tr initiate emergency procedures to coolThus SEQUOYAH - UNIT 2 B 3/4 9-2 Amendeent No. 121 April 2, 1990

Insert C_._to the Sequoyah Technical Specification Assurance against load drops over fuel stored in the ersk loading area of the cask pit in achieved by observance of the calculated load cr1teria which will prevent penetration of the impact shield in the event of a load drop.

/

_ A..w

DE;iGN FEATURES

5. 6 FUEL STORAGE _ Re ptnc.c WiTil 0

$ .? ~ p(r Lsever b

5. 6.1.1 The spent fuel storage racks are designed for fuct enriched to 5.0 weight percent U-235 and sh.111 be maintained with: R125 a.

A k,f g equivalent te less than 0.95 when flooded with unborated

\

\ water, which includes a conservative allowance of 3.06% delta k/k for uncertainties.* 33 ".y b.

A nominal 10.375 inch center-to-center distance between fuel assemblies placed in the storage racks.

c.

Fuel assemblies with enrichment greater than 4.0 weight percent

\ U-235 and burnup less than 7,500 megawattday/ metric ton (mwd /mtu)

\N shall be placed in cells in the spent fuel storage racks that face adjacent cells containing either:

1. Fuel assemblies with accumulated burnup of at least . R125 22,000 mwd /mtu, or WateL ^

(M RITICALITY - NEW FUEL 5.6.1.2 The new fuel oit storage racks are designed and shall be maintained with a nominal 21.0 ir.ch cana

r tu center distance between new fuel assemblias such that k,7f will not exceed 0.98 when fuel having an enrichment of 4.5 weig'it percent U-235 is in place and optimum achievable moderation is assumed.

R125

! DRAINAGE

5. 6. 2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.

CAPACITY l -d W X

-~K,Y rREPLAtC ldnN 15 Err E i

5.6.3 The spent, fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than IS86 fuel assemblies.

-m_ w~ ^

5. 7 COMP 0NENT 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.

"For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double contingency. principle which requires two unlikely, independent, concurrent events to produce R4 criticality accident.*

SEQUOYAH '- UNIT 2 5-5 Amendment No. 4, 52. 125 August 1, 1990-

insert D_to the sequoyah Technical Specifly tton 5.6.t.1 The spent f uel :ter=;;; 4=d. cre designed for f uci enrichea to 5%

weight percent U-235 and shall be maintained with:

a. A Ke rg equivalent to less than 0.95 when flooded with unborated water.*

b. A nominal 8.972 inch center-toocenter distance betweer fuel assemblies placed in the storage racks.

c. A :hree region arrangement in the spent fuel storage pool with the following definitions:

1. Regien 1 is designed to accormnodate new fuel with a maximum enrichment of 4.95 + 0.05 wt% U-235, or spent iuel regardless of tb fuel burnup.

2. Region 2 is designed to accommodate fuel of 4.95% initial enrichment burned to at least 50 WD/KgU (assembly average), or fuel of other enrichments with a burnup yielding an equivalent reactivity in the fuel racks. The rainimum required assembly average burnup in WD/KgU is given by Y when Y = -23.761 +

22.075E - 2.0165E 2 + 0.1152E 3 , where E is the initial enrichment in the axial zone of highest enrichment.

3. Region 3 is designed _to accommodate fuel of 4.95% initial enrichment burned to at least 41 WD/KgU (assembly average), or fuel of other enrichments with a burnup yielding an equivalent reactivity in the fuel recks. The minimum required assembly average burnup is given by Y(WD/KgU) where Y = -25.7425 + 18.76E

- 1.3933E 2 + 0.0666E 3 , where E is the initial enrichment in the axin! zone of highest enrichment.

An empty cell is less reactive than any cell containing fuel and therefore may be used as a Region 1, Region 2, or Region 3 cell in any arrangement.

d. The following arrangement of regions apply in the spent fuel storage pools

1. Region 1 fuel assemblies located along the periphery of the storage modules adjacent to the pool walls must be isolated from each other and from the inner Region-3 cells by at least one (1)

Region 2 spent fuel assembly (i.e., fuel of 50 WD/KgU burnup or equivalent).

8For some accident conditions, the presence of' dissolved boron in the pool water may be Laken into account by applying the double contingency principle which requiren two unlikely, indeper. dent, concurrent events to produce a c r iticality a:cident.

~

R~~

Insert D to the Sequoyah Technical Specification (cont l4.ued )

2. Region 1 fuel assemblies located along the wide water-gaps **

between storage modules niost be isolated f rom each other and f rom the inner Region 3 cells by at least one (1) Region 2 spent fuel assembly (i.e., fuel of 50 MWD /Kgu assembly average burnup or equivalent).

3. Regisn 1 fuel assemblies located along the narrow water-gaps **

between storage modules must be isolated from each olhar by at least two (2) Region 2 spent fuel assemblies and from the inner Region 3 cells by at least one (1) Region 2 spent fuel assembly (i.e., fuel of 50 MWD /KgU assembly average burnup or equivalent).

4. A checkerboard pattern of fresh fuel and empty cells may be used throughout any storage module, or internal to any storage module in lieu of Region 3-fuel as shown in Figure 5.6-2.-

Figure 5.6-1 shows n' typical arrangement-of regions. Figure 5.6-2 illustrates internal module checkerboarding of fresh fuel with empty cells in a portion of the fuel pool. Figure 5.6-3 illustrates the two burnup-enrichment equations (5.6.1.1.C.2 and 5.6.1.1.C.3) in graphical form,

e. Only spent fuel meeting the Region 3 burnup requirements shall be stored in any module in the cask loading area of the cask pit.

• • The nominal gap (2-1/8 inches) running in the E-W direction between the adjncent modules is referred to as the " wide gap." The N-S direction gap (1.5 inch) 16 referred to as the " narrow gap."

Incert E to_the Sequoyah Technical Specification 5.6.3 The spent fuel storage pool la det*gned and shall be maintained wAth a storage capacity limited to no more than 2091 fuel assemblies. In addition.

no more than 225 fuel assemblies will be stored in a rack module in the cask loading area of the cask pit.

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ss ;-

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if i.S 2. 0 2. 5 10 3.n 4.a 4.6 6.8 INITIAL ENRICH 1ENT. 50-235 Domain I: Puel assemblies with initial enrictunent-burnup combinations in Domain I may be placed in either Region 1, 2, or 3 storage cells.,

Domain II: Fuel assemblies with initial enrichment-burnup combinations in Domain II shall be placed only in Region 1 or 3 storage cells.

Domain III: Fuel assemblies with initial enrichment-burnup combinations in Domain III shall be placed only in Region 1 storage cells FIGURE 5.6-3

.. - _ _ _ _ _ - _ - - - - -I

ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-92-01)

SPENT FUEL POOL MODIFICATION FOR '

INCREASED STORAGE CAPACITY i

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