ML17229A916

Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases

ML17229A916
Person / Time
Site:	Saint Lucie
Issue date:	11/25/1998
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A915	List: ML17229A914 ML17229A916
References
NUDOCS 9811270124
Download: ML17229A916 (3)

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L-98-294 Attachment REFUELING OPERATIONS LIMITINGCONDITION FOR OPERATION 3.9.11

• iThe.Spent Fuel Storage:Pool shall be.rmaintain'ed'.with:

ag Tihe:fu'el storage. pool water level'-'greater than or equal to 23 ft over the.top of trraalate" fuel aslsemblies. :seate'diin the storage racks; and g ~fhe 1'uel,:storage po'oTboron con'centration greater,.than or,squat,to T720ippmJ APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel storage pool.

ACTION:

gas With the wttfer lev'el requirementeHtist~pecTfteastieit not satisfied, jininediateltf suspend all movement of fuel assemblies and crane operations wiih loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

I With,:;;the:;.,boron'. ,'concentration require'ment: not':::,satIsfied, Immediately. suspend,,:,'al movementiof fuel assemblies-.in the fuel.storage'pool and.initia'te.action-to restore:fue 9 pioioi:boion concentration to within the" ruequIred: limiitI storiage, k

TIhe'provisions of Specification 3.0.3 are not applicable~<

SURVEILLANCE REQUIREMENTS

'Verify 4.9.11 The water level in the spent fuel storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool.

4.0;1 1.1- thfuel storage pool boron concentrawtioii:iswithin,:[imit at leastonce per T,daysi ST. LUCIE - UNIT 2 3/4 9-12 Amenmdment'Ao j 98ii270i24 98ii25 PDR ADOCK 050003 9 P fDK

EFUELING OPERATIONS BASES 3/4. 9. 10 and 3/4.9.11 MATER LEVEL"REACTOR VESSEL and STORAGE POOL spy%'uc,l The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.

3/4.9. 12 SPENT FUEL CASK CRANE The maximum load which may be handled by the spent fuel cask crane is limited to a loaded multi-element cask which is equivalent to approximately 100 tons. This restriction is provided to ensure the structural integrity of the spent fuel pool in the event of a dropped cask accident. Structural damage caused by dropping a load in excess of a loaded multi-element cask could cause leakage from the spent fuel pool in excess of the maximum makeup capability.

The limit on soluble boron concentration in LCO 3/4.9.ii is consistent with the minimum boron concentration specified for the RWT, and assures an additional subcritical margin to the value of + i which is calculated in the spent fuel storage pool criticality safety analysis to satisfy the acceptance,

)criteria of Specification 5.6.1. Inadvertent dilution of the spent fuel storage pool by the quantity of, unborated water necessary to reduce the pool boron concentration to a value that would invalidate the i

criticality safety analysis is not considered to be a credible event. The surveillance frequency specified

-for verifying the boron concentration is consistent with NUREG-1432 and satisfies, in part, acceptance,

'criteria established by the NRC staff for approval of criticality safety analysis methods that take credit soluble boron in the pool water. The ACTIONS required for this LCO are designed to preclude

'or from happening or to mitigate the consequences of an accident in progress, and shall not,i an,'ccident "preclude moving a fuel assembly to a safe position.

ST. LUCIE - UNIT 2 B 3/4 9-3 Aeegdn e<4- Ro.

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