ML20065P307

Proposed Tech Spec 3/4.9.1, Boron Concentration

ML20065P307
Person / Time
Site:	Catawba
Issue date:	04/11/1994
From:	DUKE POWER CO.
To:
Shared Package
ML20065N743	List: ML20065N740 ML20065P307
References
NUDOCS 9404290034
Download: ML20065P307 (2)

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ATTACIIMENT 1 .

PROPOSED TECIINICAL SPECIFICATION AMENDMENTS FOR CATAWBA 9404290034 940411 PDR ADOCK 05000413 P PDR

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, 3/4.9 REFUELING OPERATIONS SASES ,

3/4.9.1 BORON CONCENTRATION

' The limitations on re' activity conditions during REFUELING ensure that:

! (1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a 2 uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitation's are consistent with the initial conditions assumed for the baron dilution incident l in the safety analyses. The value of 0.95 or less for'K , includes a 1% ak/k 1

conservative allowance fer uncertainties. Similarly, thN boron concentration f value of 2175 ppm-Tw Ua;; 1 end :000 pp: Or Unit or greater includes a l conservative uncertainty allowance of 50 ppm boron.

3/4.9.2 INSTRUMENTATION The OPERABILITY of the Boron Dilution Mitigation System ensures that  ;

monitoring capability is available to detect changes'in the reactivity ,

condition of the core. 1 3/4.9.3 OECAY TIME l

The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time 1 1

has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is-consistent with the assumptions used in the  ;

safety analyses.

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3/4.9.4 CONTAINMENT BUILDING PENETRATIONS l

The requirements on containment building penetration closure and OPERABILITY of the Reactor Building Containment Purge System ensure that a release of radioactive material within containment will be restricted from '

leakage to the environment or filtered through the HEPA filters and activated carbon adsorbers prict to release to the atmosphere. The OPERABILITY and-closure restrictions are sufficient to restrict radioactive material release l

from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE. Operation of the Reactor Building Con-

[ tainment Purge System and the resulting iodine removal capacity are consistent with the assumption of the safety analysis. Operation of the system with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. ANSI N510-1980 will be used as a procedural guide' for surveillance testing.

CATAWBA - UNITS 1 & 2 B 3/4 9-1 Amendment No. 1 Unit 1)

Amendment No.1 6 ((Unit 2

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