ML19256A714

Application for Amendment to App a of License DPR-34 to Change Tech Spec 4.2.18, Primary Coolant Depressurization & Limiting Condition for Operation Basis.

ML19256A714
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/03/1979
From:	Millen C PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19256A710	List: ML19256A709 ML19256A714
References
NUDOCS 7901090251
Download: ML19256A714 (8)

Text

'

BEFY)RE Tile UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of the Facility Operating License)

)

of ) Docket No. 50-267

)

PUBLIC SERVICE COMPANY OF COLORADO )

Application for Amendment to Appendix A of Facility Operating License License No. DPR-34 0F Ti!E PUBLIC SERVICE COMPANY OF COLORADO -

FT)R Tile R)RT ST. VRAIN NUCLEAR GENERATING S";'ATION This application for Amendment to Appendix A of Facility Operating License, License No. DPR-34, is submitted for NRC review and approval.

Respectfully submitted, PUBLIC SERVICE COMPANY OF COLORADO r ,?

s By 4

G y /,f t (c' C. K. Millen, Senior Vice President KELLY , STANSFIELD & 0' DONNELL Bryant O'Donnel Robert E. Thompson Public Service Company Building Denve r, Colo rado 80202 Attorneys for Applicant 7901090AS4

STNfE OF COI,0RADO )

) as.

CI'lY AND COUTIY OF DENVER)

C. K. Millen, being first duly sworn, deposes and says ;

That he is Senior Vice President of Operations of Public Service Company of Colorado, the Licensee herein; that he has read the foregoing Application for Amendment to Appendix A of Facility Operating License and knows the contents thereof, and that the s tatements and mat ters set forth therein ace true and correct to the best of his knowledge, information and belief.

-%)"'

. -.. . c .

C. K. Millen Subscribed and sworn to before me this s '"I day of January, 1979.

Witness my hand and of ficial seal.

My commission expires: . ' ' ' ' /*' .

t t . g n i

Notary Public

Specification LCO 4.2.18 - Primary Coolant Depressurization, Limiting Condition for Operations The reactor shall not be operated at power unless a flow path for depressurization of the primary system exists that includes the HTFA, Helium Purification Cooler, Helium Purification Dryer, Low Temperature Gas-to-Cas Exchanger, LTA, and associated valves and piping to the reactor building exhaust ducting to permit depressurization of the primary system as a function of time consistent with the basis of this LCO.

Basis for Specification LCO 4.2.18 In the event that a loss of forced circulation occurs, the time available prior to starting primary coolant depressurization shall be as follows:

1) As a function of the time f rom reactor shutdown as given in Figure 4.2.18-1

2) As a function of average core outlet temperature for thermal power levels less than 25% as given in Figure 4.2.18-2

3) As a function of reactor thermal power equal to or greater than 25% as given in Figure 4.2.18-3.

Start of depressurization following onset of loss of circulation is initiated as a function of prior power levels, two (2) hours from full power operation, and is completed in approximately seven hours. In order to permit greater operational flexibility, it is desirable to take credit for any idditional time which may be available under less than limiting conditions.

Page 2 Analyses indicate that there are less limiting plant conditions which significantly increase the 2-hour time limit to initiate PCRV depressuriza-tion following the onset of an LOFC. The greatest increase in the 2-hour time limit is obtained when the reactor has been shutdown and maintained in a shutdown condition for a period of time prior to the occurrence of the LOFC (Figure 4.2.18-1). Figure 4.2.18-1 summarizes the results for the time avail-able to initiate depressurization following an LOFC as a function of time from reactor shutdown. These results show that the time available increases signi-ficantly with hours of reactor shutdown. This is especially true beyond 550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br /> when the af terheat falls off rapidly (see FSAR Figure D.1-9) .

The next most significant increase is obtained when the average core outlet temperature is less than about 1000*F at the onsc of LOFC (Figure 4.2.18-2) .

The low tverage core outlet temperature can either be the result of low power operatit - (less than 25% of rated) at the onset of the LOFC, or as a result of temperature reductions after reactor scram from any power level prior to the onset of the LOFC. Figure 4.2.18-2 summarizes the results for the time available to initiate depressurization as a function of average core outlet temperature at the start of the LOFC. The figure shows that reducing average core outlet temperature has a minimal effect until temperatures talow about 1000*F are reached. .

The least amount of relief in the 2-hour delay time is obtained from the case where the LOFC occurs during power operation above 25% of rated. At 25% power operation, the delay time is 2-1/2 hours decreasing to 2-hours for power operation at 70% and above (Figure 4.2.18-3). Figure 4.2.18-3 summarizes

Page 3 the analysis results ass tming the LOFC occurs during power operation above 25% of rated and there is no forced circulation following the reactor scram.

An additional one-half hour is gained on the two-hour time limit at 25% power operation. There is no relief in the two-hour titae limit for power operation at or above 70% of rated.

Depressurization is completed by venting the purified gas to the atmosphere.

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