ML20205H453

Proposed Tech Specs,Reducing Auxiliary Feedwater (AFW) Flow Requirement for Steam Driven AFW Pumps from 800 to 600 Gpm

ML20205H453
Person / Time
Site:	Davis Besse
Issue date:	03/23/1987
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20205H413	List: ML20205H409 ML20205H453
References
TAC-65068, NUDOCS 8704010057
Download: ML20205H453 (1)

Text

3 Docket No. 50-346 r

4 s

Lice,nse No. NPF-3

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.g Serial No. 1360 i5 h

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PLANT SYSTEMS

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BASES

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3/4.7.1.2 AUXILIAM FEEDWATER SYSTEMS 3,

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The OPI.RABILITY of the Auxiliary Feedwater Systems ensures tbt the C Reactor Coolant System can be cooled down to less than 280*F froe' normal operating conditions in the event of a total loss of offsite power.

~

600 c

Each steam driven aux iary feedwater pump is capable of. delivering )

1 a total feedwater flow of sps at a pressare of 1050 psig to the

,l entrance of the steam generators. This capacity is sufficient to ensure y

that adequate feedwater flow is available to remove decay heat and reduce,/

i the Reactor Coolant System temperature to less than 280'T where the Decay Heat Removal System may be placed into operation.

Following any modifications or repairs to the Auxiliary Feedwater Systes piping from the Condensate Storage Tank through auxiliary feed pumps to the steam generators that could affect the system's capability to deliver water to the steam generators, following extended celd shutdown, a flow path verification test shall be performed. This test may be conducted in NODES 4, 5 or 6 using auxiliary steam to drive the auxiliary feed pumps turbine to demonstrate that the flow path exists from the Condensate Storage Tank to the steam generators via auxiliary ' -

feed pumps.

t 3/4.7.1.3 CONDENSATE STORAGE FACTI. TIES i

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The OPERABILITY of the Condensate Storage Tank with the minimum s

water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> with steam discharge to atmosphere and to cooldown the Reactoi Coolant Systed to less than 280'F in the event of a total loss of offrite power or of the main feedwater system. The contained water volume limit includes an allowance,.

for water not usable because of tank discharge line location or other c

physical characteristics.

3/4'.7.1.4 ACTIVITY

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The limitations on secondary system specific activity chsure that the resultant offsite radiation dose will be limited to a small'iractioa of 10 CFR Part 100 limits.in the event of a steam line rupture. This dose includes the effects of a coi.ncident 1.0 GPM primary to secondary tube leak in the steas generator,of the'affected steam line. These values are consistent with the assumptions used in the safety analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES l

The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) ainimize the 8704010057 870323 A

ADOCK 0500 6

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ll DAVIS-BESSE, UNIT 1 B 3/4 7-2 Amendment No. 38, 96

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