ML20059K594

Proposed Tech Specs 5.5.1.1, Criticality & 5.5.3, Capacity, Supporting Implementation of Mod to Install New High Density Spent Fuel Storage Racks in Each Spent Fuel Pools at LGS

ML20059K594
Person / Time
Site:	Limerick
Issue date:	01/14/1994
From:	AFFILIATION NOT ASSIGNED
To:
Shared Package
ML20059K588	List: ML20059K587 ML20059K594 ML20059K626
References
NUDOCS 9402020176
Download: ML20059K594 (4)

Text

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ATTACHMENT 3 LIMERICK GENERATING STATION UNITS 1 AND 2 Docket Nos. 50-352 50-353 License Nos. NPF-39

• NPF-85 N

TECHNICAL SPECIFICATIONS CHANGE REQUEST No. 93-19-0 i

LIST OF AFFECTED PAGES ,

UNIT 1 UNIT 2 5-8 5-8 1

9402020176 940114 PDR ADOCK 05000352 P_- PDR <

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DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE' (Continued).

b. For.a pressure!of:

' I '. 1250 'psig on ~the suction side.of the' recirculation pump'.

2. 1500 psig from the recirculation pump discharge to.the outlet.- ,

side of the discharge shutoff valve.

3. 1500 psig from the discharge shutoff valve to the jet pumps'.

c. For.a temperature of 575 F.

VOLUME' -i 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 22,400 cubic feet at a nominal steam dome saturation. l

. temperature of 547'F.  !

'5.5 FUEL STORAGE i CRITICALITY 5.5.1.1 The spent fuel storage racks are designed and shall be maintained'with:

k.,, equivalent to less than or equal to 0.95 when flooded with

a. A unborated water, including all calculational' uncertainties and biases as described in Section 9.1.2 of the FSAR.

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

placed in the storage racks of. greater than or equal to 6.25 inches.

5.5.1.2 The k,j, for new fuel for the first core loading stored dry in the 1 spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation o

is assumed.

DRAINAGE  :

5.5.2 The spent fuel storage pool is designed and shall be maintained to prevent.

inadvertent draining of the pool below elevation 346'0".

-CAPACITY  ;

5.5.3 The spent fuel storage pool is designed and shall be maintained with.a storage capacity limited to no more than 4117 fuel assemblies. l 5.6 COMPONENT CYCLIC OR TRANSIENT LIMIT  ;

.5.6.1 The components identified in _ Table 5.6.1-1 are' designed and shall b'e maintained within the cyclic or transient limits of Table 5.6.1-1. '

l LIMERICK - UNIT 1 5-8

.i y ... ._.-

M' .

DESIGN FEATURES . _ _ _ ,

DESIGN PRESSURE AND TEMPERATUP1 (Continued). j

b. For a pressure of: l

1. 1250 psig on the suction side of'the recirculation pump.

2. 1500 psig from the recirculation pump discharge to the outlet-side of the discharge shutoff. valve. i

3. -1500 psig from the discharge shutoff valve to the jet pumps.

c. For a temperature of 575 F.

VOLUME  :

5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 22,400 cubic feet at a nominal steam dome saturation  :

temperature of 547'F. i 5.5 FUEL STORAGE i

CRITICALITY '

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

a. A k ,, equivalent to less than or equal to 0.95 when flooded with j unborated water, including all calculational uncertainties and ~

biases' as described in Section 9.1. 2 of the FSAR, ,

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b. . A nominal center-to-center distance between fuel . assemblies 1 placed in the storage racks of- greater than or. equal. to 6.25 inches. '

1 5.5.1.2 The k,,, for new fuel for the first core loading stored dry in the  ;

spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed. ,

DRAINAGE  :

5.5.2 The spent fuel storage pool is designed and shall be maintained to prevent

' inadvertent draining of the pool bel'w elevation 346'0".

CAPACITY l

5.5.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 4117 fuel assemblies. l-5.6 COMPONENT CYCLIC OR TRANSIENT LIMIT -

. 5.6.1.The components identified in Table 5.6.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.6.1-1.

LIMERICK - UNIT 2 5-8 l i

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I l i ATTACHMENT 2 l '

i HOLTEC INTERNATIONAL LICENSING REPORT .)

SPENT FUEL STORAGE

- CAPACITY EXPANSION FOR LIMERICK GENERATING STATION, UNITS 1 AND 2 i

e SAFETY ANALYSIS REPORT LICENSING REPORT FOR SPENT FUEL STORAGE CAPACITY EXPANSION ,

LIMERICK GENERATING STATION

/

UNITS 1 AND 2  ;

I Prepared by HOLTEC INTERNATIONAL  !

Report No. Hi-931012  !

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