ML20066J370

Application for Amend to License NPF-3,changing TS to Correct Inconsistency in TS Bases 3/4.7.1.3,as Compared to Dated SAR & SER (NUREG-0136) Re Condensate Storage Tanks,Per Generic Ltr 81-21

ML20066J370
Person / Time
Site:	Davis Besse
Issue date:	02/15/1991
From:	Shelton D CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20066J373	List: ML20066J370 ML20066J391
References
RTR-NUREG-0136, RTR-NUREG-136 1876, GL-81-21, TAC-M79671, NUDOCS 9102260097
Download: ML20066J370 (2)

Text

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%pm,w Totedo. OH 4E20001 gg (419)2 4 2.100 Docket Number 50-346 License Number hPF-3 Serial Number 1876 February 15, 1991 United States Nuclear Regulatory Commission Document Control' Desk Vashington, D. C. 20555

Subject:

Administrative Change to Technical Specification Bases 3/4.7.1.3, Condensate Storage Tanks (TAC Humber H79671)

Gentlement The attached administrative change to the Davis-Besse Nuclear Power Station (DBNPS), Unit 1 Technical Specifications (TS) Bases is being made to correct an. inconsistency which exists in TS Bases 3/4.7.1.3 as compared to the Updated Safoty. Analysis Report (USAR), NUREG-0136 (Safety Evaluation Report

.Related to Operation of DBNPS, Unit 1, December 1976), and the Safety Evaluation Report received accepting Toledo Edison's (TE's). response to Generic Letter (GL) 81-21 (Toledo Edison (TE) letter Log Number 3163, dated February 2, 1990).

The DBNPS TS Bases 3/4.7.1.3 presently states, in part, " ...that sufficient vater is available (in the condensate storage tanks] to maintain the Reactor Coolant System (PCS) 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 thrstmosphere and to cooldown the RCS to less than 280*F in the event of a total loss (f offsite power or of the main feedvater system..." (emphasis added). The cited emphasis portion of the above is inconsistent with USAR Section 9.2.6.1 which states, " Condensate storage is provided..., under normal conditions, for hot shutdown or cooldown of the reactor." NUREG-0136, Section 9.3.4, states "For a normal hot shutdovn or cold shutdown of the reactor, the condensate storage capacity is sufficient to remove decay heat for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> plus a subsequent cooldown to 280'F." In each of the documents, " normal conditions" or " normal shutdown" is used to qualify the design basis capacity of the condensate storage tanks. As used therein, " normal" refers to the availability of onsite power during the shutdown.

This is further evidenced by TE's response (TE letter Serial Number 969 dated August 2, 1983) to CL 81-21 Natural Circulation Cooldown, dated May 5 L 1981 (TE letter Log Number 714), and the subsequent Request for Additional 9102260097 910215 PDR ADOCK 05000346 i P PDR I 010 1 Operating Compames rs q . e Clevetono flectne mummati ng I r o i b h, p.,( weoetomon

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w_ 1 Dockoc Nu:ber 50-346 1 licenm.. U...ab:r NPF-3 LedM J;isber 1876 l hp ;j Information dated June 1, 1983 (TE letter 1,og Number 1300), in which it was stated that natural circulation cooldovn was supported fort 1) 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> j 9 assuming the condensate storage tanks contained the TS minimum volume of  ;

250,000 gallons, and 2) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with both condensate storage tanks filled to a level corresponding to the low level setpoint. The response also stated that the time required to cool the RCS to decay heat removal (DHR) entry conditions, assuming a loss of offsite power and a cooldovn rate of l l-%'F per hour, vas approximately 150-200 hours. Upon depletion of the l inventory in the condensate storage tanks, additional cooling vater capaelty to support auxiliary feedvater system operation during natural circulation cooldovn vould be provided by the Seismic Category I service water system, which has 1.ake Erie as its source. The svitehover to the service vater system is automatic on auxiliary feedvater pump lov suction pressure.

The Nuclear Regulatory Commission (NRC) staff accepted TE's response to GL 81-21 by Safety Evaluation Report (SER) transmitted on February 2, 1990  !

(TE letter 1,og Number 3163, NRC TAC Number 47182). Based on TE's response and NRC's acceptance, as well as the information contained in the DBNPS USAR ,

and NUREG-0136, it is evident that the DBNPS TS Bases 3/4.7.1.3 is inconsistent with the original and continued licensing basis of the plant.

Therefore, the attachment provides a change to the DBNPS TS Bases reflecting that the condensate storage tank capacity is sufficient to cool down the RCS to DHR entry conditions "...under normal conditions (no loss of offsite power)".

The above cited change is administrative in nature as it corrects an error in the DBNPS TS Bases and is consistent with the original DBNpS design as accepted by NRC for addressing natural circulation cooldovn events. TE requests that this change be issued by June 1, 1991.

Should you have any questions regarding this matter, please contact Mr. R. V. Schrauder, Manager - Nuclear hicensing, at (419) 249-2366.

Very truly yours, l- g KAS/mmb attachment cci P. H. Byron, DB-1 NRC Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III D. C. Di Ianni, DB-1 NRC Senior Project Manager General J. Villiams, Chief of Staff, Ohio Adjutant General's Office Utility Radiological Safety Board

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