Text

Proposed Tech Specs,Revising TS 3/4.7.5.1 Re Ultimate Heat Sink
	ML20087K831
Person / Time
Site:	Davis Besse
Issue date:	08/18/1995
From:	; CENTERIOR ENERGY
To:	;
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ML20087K804	List: ML20087K800; ML20087K808; ML20087K831;
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	NUDOCS 9508240168
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LAR 95-0016 Page 9

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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 International Great Lakes Datum, and b.

An average water temperature of < 85 F.#

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the requirements of the above specification not satisfied, be in at I

least HOT STANDBY within 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.5.1 The ultimate heat sink shall be detennined OPERABLE at least l

once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water temperature and water level to be within their limits.

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From August 18, 1995, 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months , to September 17, 1995, 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months , the ultimate heat sink shall be OPERABLE with an average water j

temperature of < 90'F.

L-L DAVIS-BESSE,ONIT1 3T4726 Amendment No.

9508240168 950818 PDR ADOCK 05000346 P

PDR

LAR 95-0016 HIS PAGE PROVIDED FORINFORBil0N ONLY BASES i

the flow path can be established. The ability for local, manual operation is demonstrated by verifying the presence of the handwheels for all manual valves and the presence of either handvheels or available power supply for motor operated valves.

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION

'Ihe limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 110*F and 237 peig are based on a steam generator RT NDT of 40*F and are sufficient to prevent brittle fracture.

3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

3/4.7.4 SERVICE WATER SYSTEM The OPERABILITY of the service water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal'and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

3/4.7.5 ULTIMATE HEAT ! INK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants" March 1974.

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allovable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in j

conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less 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 No. 103

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Dockst'Nunbar 50-346 1 Licensa Number NPF-3

'Sarial Numbar 2319 I

Pag,e 1?

e ENVIRONMENTAL ASSESSMENT i

. 1 Identification of Proposed Action This' proposed action involves the Davis-Besse Nuclear Power Station

.(DBNPS), Unit' Number.1, Operating License Number NPP-3, Appendix A, Technical Specifications (TS).. A license amendment is proposed to i

increase the allovable ultimate heat sink (UHS) average water i

temperature, as specified in TS Limiting Condition for Operation-(LCO) 3.7.5.1.b, from f 85'F.to 5 90*F, for a period from August 18,.1995, 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months , to September 17, 1995, 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months . The current TS Action statement requires that the plant be placed in Hot Standby (Mode 3) vithin 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and Cold shutdown (Mode 5) within the following 30' l

hours, in the event that UBS average temperature exceeds 85'F.

Need for the Proposed Action

-The changes proposed are needed to allow continued plant operation

.in the event that UHS average temperature exceeds 85'F.

j Environmental Impact of the Proposed Action Toledo Edison has determined that the structures, systems and components which could be affected by the proposed increase in allovable UHS average temperature vill continue to be capable of performing their safety functions. Therefore, removal of the requirement to shutdown the plant in the event the UHS average temperature exceeds 85'F, for a period from August 18, 1995, 1800_

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , to September 17, 1995, 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months , has no adverse effect on safety.

The proposed change vill reduce the potential for unduly requiring cooldown and heatup transitions of plant equipment, thus preserving the cycling margin between plant design and actual operating history.

The proposed amendment involves a change to a requirement with respect i

to the use of facility components located within the restricted area as defined in 10CFR Part 20.

As discussed in the Significant Hazards-Consideration, this proposed amendment does not involve a significant hazards consideration. The proposed change to allow continued plant operation in the event the UHS average temperature exceeds 85'F does i

not alter source terms, containment isolation or allowable releases.

In addition, the proposed change does not involve an increase in the amounts, and no change in the types, of any radiological effluents that may be allowed to be-released offsite.

Furthermore, there is no i

increase in the individual or cumulative occupational radiation t

exposure.

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Docket Nunb;r 50-346 Liccnsa Nurbar NPF-3 S: rial Nurbar 2319 Pag,e 2 Vith regard to potential non-radiological impacts, the proposed amendment involves no increase in the amounts or change in types of any ncn-radiological effluents that may be released offsite, and has no other environmental impact.

Based on the above, Toledo Edison concludes.that there are no significant radiological or non-radiological environmental impacts associated with the proposed amendment.

Alternatives to the Proposed Action Since Toledo Edison has concluded that the environmental effects of the proposed action are not significant, any alternatives vill have only similar or greater environmental impacts. The principal alternative vould be not to amend the TS.

This vould not reduce the environmental impacts attributable to the facility.

Furthermore, it vould force a shutdown of the facility in accordance with the present TS in the event UHS average temperature exceeds 85'F during the 30-day period.

Alternative Use of Resources This action does not involve the use of resources not previously considered in the Final Environmental Statement Related to the Operation of the Davis-Besse Nuclear Power Station, Unit Number 1 (NUREG 75/097).

Finding of No Significant Impact j

Toledo Edison has reviewed.the proposed license amendment against the criteria of 10CFR51.30 for an environmental assessment. As demonstrated above, the proposed amendment does not involve a significant hazards consideration, does not increase the types or amounts of effluents that may be released offsite, and does not increase individual or cumulative occupational radiation exposures.

Accordingly, Toledo Edison finds that the proposed license amendment,

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if approved by the Nuclear Regulatory Commission, vill have no significant impact on the environment and that no Environmental Impact Statement is required.

Dockat Nuibar 50-346~

- Lic;nco Numb 2r NPF-3

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- Serial Number 2319,

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