ML20066J391

Proposed Tech Spec Bases 3/4.7.1.3 Re Condensate Storage Facilities

ML20066J391
Person / Time
Site:	Davis Besse
Issue date:	02/15/1991
From:	CENTERIOR ENERGY
To:
Shared Package
ML20066J373	List: ML20066J370 ML20066J391
References
NUDOCS 9102260109
Download: ML20066J391 (1)

Text

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• Dbek:t Hu:ber 50-M6 Litense Nu:ber NPF-3 ADDil1QNAL CHANG 15 PR!vl00SLf '"'

Serial Number 1876 PROPOSCD Bf LtlHR  :

Attachment Strinl No._48 6 Date 02/15/9:t  !

PLANT SYSTEMS BASES

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3/4.7.1.2 AUXILIARY FEEDVATER SYSTEMS (Continued)

Following any modifications or repairs to the Auxiliary Feedvater System  !

piping f rom the Condensate Storage Tank through auxiliary f eed pumps to the steam generators that could affect the system's capability to deliver vater to the steam generators, following extended cold shutdown, a ihv path verification test shall be performed. This test may be conducted in H0 DES 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 isteam generators v$a auxiliary feed pumps. >

Verification of the turbine plant cooling vater valves (CV 196 and CV 197),

the startup feedvater pump suction valves (FV 32 and TV 91), and the startup feedvater pump discharge valve (FV 106) in the closed position is required to address the concerns associated with potential pipe failures in the auxiliary feedvater pump rooms, that could occur during operation of ti.e startup feedvater pump.

3/4.7.1.3 CONDENSATE STORAGE FACILITIES The OPERABILITY of the Condensate Storage Tank with the minimum vater volume ensures _that scificient vater 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_atingfa)htypd LR_.q9451 vn the o ei e. ;it:1 ;;; ;. ,

gt[90 GogANLI ~..;i siSyA, e.-;.,e Lag _.lo latmm

...y..i.1 ..

__t,W'L.';he e e,,; DTIIed ilaa{r volume e con Q ...;e . m .

lI M ERide's'"an aflovance fotr vater Tio h

,ause of tank discharge:

line location or other physical characteristics. g 3/4.7.1.4 ACTIVITT b" d *h [*M _

The limitations on secondary system specific activity ensure that the resultant offsite radiation dose vill be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose includes the ef fects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected staan line. These values are consistent with the assumptions used in the safety analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator vill blovdown in the event of a steam L line rupture. This restriction is required to 1) minimize the i

, 9:02260109 910215 PDR ADOCK 05000346 P PDR l

DAVIS-BESSE, UNIT 1 5 3/4 72 Amendment No. 58, 96, 122 l

L Rev. 11/18/87

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