ML20210H073

Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F

ML20210H073
Person / Time
Site:	Davis Besse
Issue date:	07/28/1999
From:	CENTERIOR ENERGY
To:
Shared Package
ML20210H053	List: ML20210H049 ML20210H063 ML20210H073
References
NUDOCS 9908030271
Download: ML20210H073 (9)

Text

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LAR 9668 Page 18 PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5.1 The ultimate heat sink shall be OPERABLE with:

a. A minimum water level at or above elevation 562.0 feet Intemational Great Lakes Datum, and

b. An average water temperature of s 2Q 86' F.

APPLICABILITY: MODES 1,2,3 and 4.

ACTION:

With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEIILANCE REQUIREMENTS 4.7.5.1 The ultimate heat sink shall be determined OPERABW at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average water temperature and water level to be within their limits.

DAVIS-BESSE, UNIT 1 3/4 7-16 Amendment No.

9900030271 990728 PDR ADOCK 05000346 P PDR T

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LAR 96-0008 THIS PAGE PROVIDED BASES FORINFORMA110N DNlY the flow path can be established. The ability for local, manual operation is demonstrated by verifying the presence of the handuheels for all manual valves and t.he precence of either handvheels or available power cupply for motor operated valves. -

3/4.7.2 STEHi CENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on etcam generator pressure and temperature enoures that the pressure induced stresses in the steam generators do not exceed the maximum allovable fracture toughneos streco 11mitc. The limitations of 110'F and 237 poig are based on a steam generator RTHDT of 40*F and are sufficient to prevent brittle fracture.

3/4.7.3 COMPONENT COOLING VATER SYSTE, Th'e' OPERABILITI of the component cooling water cystem ensures that sufficient cooling capacity is availabic for continued operation of safety related-equipment during. normal and accident conditions. The redundant cooling capacity of thia syatem, assuming a eingle failure, is consihtent with the assumptiona used in the cafety analysee.

3/4.7.4 SERVICE UATER SiSTEM The OPERAsILITY of:the setvice water cyatem ensures that sufficient cooling capacity is ava(lable for continued operation of safety related equipment during notual'and accident conditions. The redundant cooling capu.ity of thic system, assuming a single failure, is concistent with the . assumptions used. in the safety analycpS; l 3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide notmal cooldovn of the facility, or'2) to uitigate the effects of accident conditions within acceptable limits.

The limitations on minimum vater level and maximum temperature are based on providing a 30 day cooling vater supply to safety related equipment without exceeding their design basis temperature and is consistent with the recocuendations of Regulatory Guide 1.27. " Ultimate Heat Sink for Nuclear Plants" Harch 1944.

3/4.7.6 CONTROL ROOH EMERGENCY VElfrILATION SYSTEM The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allouable temperature for continuous duty rating for the equipment and instrumentation cooled by this system.and 2) the control room vill

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remain habitable for operations personnel during and folleving all '

credible accident conditions. The OPEPABILITY of this system in ,

conjunction with control room design provisiono is baced on limiting the radiation exposure to personn'el occupying the control room to 5 rem or lesc whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A",

10 CFR 50.

DAVIS-BESSE. UNIT 1 B 3/4 7-4 Amendment Ho.103 ;

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Docket Number 50-346 License Number NPF-3 Serial Number 2397 Attachment 2 DRAWINGS (5 pages follow)

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Docket Number 50-346 License Number NPF-3 Serial Number 2397 j Enclosure 2 COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMITTED TO BY DAVIS-BESSE NUCLEAR POWER STATION IN THIS DOCUMENT. ANY OTHER ACTIONS DISCUSSED IN THE SUBMITTAL REPRESENT INTENDED OR PLANNED ACTIONS BY DAVIS-BESSE. THEY ARE DESCRIBED ONLY AS INFORMATION AND ARE NOT REGULATORY COMMITMENTS. PLEASE NOTIFY THE MANAGER - REGULATORY AFFAIRS (419-321-8466) AT DAVIS-BESSE OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.

COMMITMENTS DUE DATE None N/A 1