Text

Proposed Tech Specs 3/4 9-3 Increasing Spent Fuel Pool Capacities for Units 1 & 2 from 1170 to 1632 Fuel Assemblies & Extending Decay Time from 100 to 168 H
	ML18100A339
Person / Time
Site:	Salem
Issue date:	04/28/1993
From:	; Public Service Enterprise Group
To:	;
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ML18100A338	List: ML18100A337; ML18100A339; ML18100A340;
References
	NUDOCS 9305100017
	Download: ML18100A339 (12)
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ATTACHMENT B REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 11~/6 3.9.3 The reactor shall be subcritical for at least)JJ'tr'hours.

APPLICABILITY: During movement of irradiated fuel in the reactor pr~ssure vessel.

ACTION:

JbB With the reactor subscri ti ca 1 for 1ess than ..J.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, suspend a 11 operations involving movement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least .J.0fr hours by verification of the date and time of subcriticality prior to~movement of irradiated fuel in the reactor pressure vessel.

,,s SALEM-UNIT 1 3/4 9-3

DESIGN FEATURES

- - - - =*====*=**=a*******************=~***===============

a. In accordance with the code requirements specified in section 4.1 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pre**ure of 2485 p*ig, and

c. For a temperature of 650°F, except for the pressurizer which is 6B0°F.

VOLUME 5.4.2 Th* total water and steam volume of th* reactor coolant system is 12 1 811 : 100 cubic feet at a nominal Tavg of 576.7°F.

5.5 HETEOBQLOGICAL TOWER LOCATION

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S.5.1 Th* meteorological tower ahall be located a* *hown on Figure s.1-1.

5.6 FUIL STORAQI CRITICALITY The and *pent fuel 1torage rack* are d**igned and *hall

a. equivalent to l*** than or equal ll*d with unborated water. Thi*

con**rva v* allowance of:

1. 2.2\ d ta k/k uncertainty and VSH fuel a**embli* , and

~F-ftf~ 2. for *tandard and VSH fuel aHemblie* Burnable Abaorber LV ,1'1" (IFBA) pin*.

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b. A nominal 10.5 inc.Jt'center-to-cent*r'cl.l*tance betw..n fuel in th* spent fuel *to

c. ~

inch center-to-center di*tance S fuel i** placed in th* new fuel *toraqe rack*.

or Vantage SH fuel a**embli** with maximum enric 4.55 w/o. 0235 and a Kinf l*** than or equal to.1.453 in th* c geometry at 68°r with no soluble boron.

DMUWjl S.6.2 The *pent fuel 1toraqe pool is de*iqned and *hall be maintained to prevent inadvertent draining of the pool below elevation 124'8*.

SALEK - UNIT 1 5-5 Amendment Ho. 128

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DESIGN FEATURES

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CAPAC I TX 5.6.3 The *pent fuel storage pool is designed and shall be maintained with a stora9* capacity limited to no more than ~ fuel aseemblie*.

Ho32.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.l The component* identified in Table 5.7-l are de*igned and shall be maintained within th* cyclic or transient limit* of Table 5.7-l *

SALEM - tJNIT 1 5-6 Amendment Ho.128

INSERT 1 5.6.1.1 The new fuel storage racks are designed and shall be maintained with:

a. A maximum Keff equivalent of 0.95 with the storage racks flooded with unborated water.

b. A nominal 21.0 inch center-to-center distance between fuel assemblies.

c. A maximum unirradiated fuel assembly enrichment of 4.5 w/o U-235.

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

a. A maximum Keff equivalent of 0.95 with the storage racks filled with unborated water.

b. A nominal 10.5 inch center-to-center distance between fuel assemblies stored in Region 1 (flux trap type) racks.

c. A nominal 9.05 inch center-to-center distance between fuel assemblies stored in Region 2 (non-flux trap) racks.

d. Fuel assemblies stored in Region 1 racks shall meet one of the following storage constraints.

1. Unirradiated fuel assemblies with a maximum enrichment of 4.25 w/o U-235 have unrestricted storage.

2. Unirradiated fuel assemblies with enrichments greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o U-235, that do not contain Integral Fuel Burnable Absorber (IFBA) pins, may only be stored in the peripheral cells facing the concrete wall.

3. Unirradiated fuel assemblies with enrichments (E) greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o U-235, that contain IFBA rods with a nominal 2.35 mg B-10/linear inch loading, and a number of IFBA rods equal to or greater than the number determined by the equation below, have unrestricted storage

N = 42.67 (E-4.25)

4. Irradiated fuel assemblies with enrichments (E) greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o, that have attained the minimum burnup (BU) as determined by the equation below, have unrestricted storage.

BU (MWD/kg U) = -26.212 + 6.1677E

e. Fuel assemblies stored in Region 2 racks shall meet one of the following storage constraints.

1. Unirradiated fuel assemblies with a maximum enrichment of 5.0 w/o U-235 may be stored in a checkerboard pattern with intermediate cells containing only water or non-fissile bearing material.

2. Unirradiated fuel assemblies with a maximum enrichment (E) of 5.0 w/o U-235 may be stored in the central cell of any 3x3 array of cells provided the surrounding eight cells are empty or contain fuel assemblies that have attained the minimum burnup (BU) as determined by the equation below.

2 BU (MWD/kg U) = -15.48 + 17.SOE - 0.7038E In this configuration, none of the nine cells in any 3x3 array shall be common to cells in any other similar 3x3 array. Along the rack periphery, the concrete wall is equivalent to 3 outer cells in a 3x3 array.

3. Irradiated fuel assemblies with a maximum enrichment (E) of 5.0 w/o U-235 that have attained the minimum burnup (BU) as determined by the equation below, have unrestricted storage.

2 BU (MWD/kg U) = -32.06 + 25.21E - 3.723E +

3 0.3535E

4. Irradiated fuel assemblies with a maximum enrichment (E) of 5o0 w/o U-235 that have attained the minimum burnup (BU) as determined by the equation below, may be stored in a peripheral cell facing the concrete wall.

BU (MWD/kg U) = -25.56 + 15.14E - 0.602E 2

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ATTACHMENT C

REFUELING OPERATIONS

3/4.9.3 DECAY TIME*

LIMITING CONDITION FOR OPERATION

/be, 3.9.3 The reactor shall be subcritical for at least.J.eff'hours.

APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.

ACTION:

/b'O With the reactor subscritical for less than .J.Q-trhours, suspend all operations involving movement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least lbtO .JOO"'hours by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.

SALEM - UNIT 2 3/4 9-3

DESIGN FEATURES S.S MITIQRQLQGICAL TOWER LOCATION S.S.l The meteorological tower shall be located a* *hown on Figure S.l-l.

5.6 rtl!jL STQBAGI CRITICALITY Th* new and spent fuel *torag* rack* are de*igned and shall b with:

a. equivalent to l*** than or equal illed with unborated water. Thi*

l.

2. An additional for *tandard and VSH fuel a**embli** Burnable 1J:)*orber (Il'BA) pin*.

b. A center-to-center *tanc* between fuel in th* *pent fuel *tor

rack*.

c. A ncmi inch center-to-center di*tanc* fuel li** placed in th* new fuel *toraqe racX..

Standard or Vantage SH fuel ***embli** with maximum enric ent 4.55 w/o 0235 and a Kinf l*** than or equal to 1.453 in th*

geometry at 68*P with no *olubl* boron.

DMIQCI 5.6.2 Th* *pent fuel *torag* pool i* de*igned and *hall be maintained to prevent inadvertent draining of th* pool below elevation 124'8*.

CAEACitx 5.6.3 ':be ci-nt fuel *torag* pool i* d**igned and *hall be maintained with a

tor&98 capacity limited to no more than ~fuel a**emblie*.

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5.7 COMPORQ'1' CXc::LIC QB TMNSIENT LIMIT 5.7.1 Th& ccmpon~at~ id~fitified in Table 5.7-1 are d**igned and *hall be maintained within the cyclic or tran*i*nt limit* of Table 5.7-1 *

SALEH - tJHIT 2 s-s Amendment No. 107