ML20149E048

Proposed Tech Specs,Clarifying Boron Concentration Requirements for Refueling Conditions

ML20149E048
Person / Time
Site:	Davis Besse
Issue date:	01/04/1988
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20149E031	List: ML20149E029 ML20149E038 ML20149E048
References
1459, NUDOCS 8801130207
Download: ML20149E048 (3)

Text

.

. 3- ~" '"" THIS PAGE PROVIDED FORINFORMATION ONL TABLE 1.1 OPERATIONAL MODE _S_

REACTIVITY  % RATED AVERAGE COOLANT MODE CONDITION. K,ff THERMAL POWER

• TEMPERATURE

~

~

1. POWER OPERATION > 0.99 > 5% > 280*F

2. STARTUP  ; 0.99 < 53

> 280'F

3. HOT STANDBY < 0.99 0 > 280*F

4. HOT SHUTOOWN < 0.99 0 280'F > T avg > 200*F

5. COLD SHUTDOWN < 0.99 0 < 200*F

6. REFUELING ** < 0.95 0 < 140'F Excluding decay heat.

Reactor vessel head unbolted or removed and fuel in the vessel.-

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3/4.9 REFUELING OPERATIONS BORON CONCENTRATION l LIMITING CONDITION FOR OPERATION 3.9.1 - H th the n::ter M:::1 50:d 2nb:lt:d ;r = =;;d, The boron concen- l, tration of all filled portions of the Reactor Coolant System and the re- I fueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

a. Either a X ff of 0.95 or less, which includes a 1*. ok/k conservati,ve allowance for uncertainties, or j

b. A boron concentration of > 1800 ppm, which includes a 60 ppm conservative allowance for uncertainties.

APPLICABILITY:

MODE 6[ l ACTION:

With the requirements of the above specification not satisfied, innediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at > 10 gpm of 8750 ppm boric acid solution or its equivalent until Keft is r_ educed to < 0.95 or the boron concentration is restored to > 1800 ppm, whichever Ts the more restrictive. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The more r:strictive of the above two reactivity conditions shall i be determined pricr to: I

a. Removing or unbolting the reactor vessel head, and

b. Withdrawal of any safety or regulating rod in excess of 3 feet from its fully inserted position within the reactor pressure vessel.

4.9.1.2 The boron concentration of the reactor pressure vessel and the refueling canal shall be determined by chemical analysis at least once each 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• S rc::::r 05:11 b; nint;ined in "000 C h;n the r;;;ter i;;;;l h;;d h ;nb:lted Or = =;;d.

DAVIS-BESSE, UNIT 1 3/4 9-1

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,/4.9 REFUELING OPERATIONS p BASES 3/4.9.1 BORON CONCENTRATION

\ The limitations on reactivity conditions during REFUELING ensure that:

1) the reactor will remain subcritical'during CORE ALTERATIONS, and 2) a unifom boron concentration is maintained for reactivity control in the water: voluraes having direct access to the reactor vessel. These limita-tions are consistent with the initial conditions assumed for the boron dilution incident in the accident analysis.

3/4.9.2 INSTRUMENTATION The OPERABILITY of source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivii.y condition of the core.

3/4.9.3 OECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradicted fuel assemblies in the reactor pressure vessel ensures that sufficient time 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.

3/4.9.4 CONTAINMENT PENETRATIONS The reqttirements on containment penetration closure and OPERABILITY ensure.that e release of radioactive material within containment will be i restricted from leakage to the environment. The OPERABILITY and closure requirements are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressuriza-tion potential while in the REFUELING MODE.

l l

3/4.9.5 COMMUNICATIONS The requirement for comunications capability ensures that hefueling j station personnel can be promptly infomed of significant changes in the i facility status or core reactivity condition during CORE ALTERATIONS.

DAVIS-BESSE, UNIT 1 B 3/4 9-1