ML18039A409

Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt

ML18039A409
Person / Time
Site:	Browns Ferry
Issue date:	06/26/1998
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18039A408	List: ML18039A407 ML18039A409
References
NUDOCS 9807070226
Download: ML18039A409 (10)

Text

ENCLOSURE 2

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 2 AND 3 PROPOSED TECHNICAL SPECIFICATION (TS)

CHANGE TS 384 I SUPPLEMENT 2 MAEGCED PAGE S AFFECTED PAGE LIST The following pages have been marked and an 'X'as been placed in the right hand margin to indicate where changes occur.

The affected page list is identical for both Unit 2 and Unit 3 Technical Specifications 3.4-26 Bases B 3.4-56 B 3.4-57 II.

MARKED PAGES See attached.

980707022h 980b2b 7,.

PDR AoaCK 0S000abO' PD

3.4 REACTOR COOLANTSYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure Re r Steam Dome Pressure 3.4.10 LCO 3.4. 10 APPLICABILITY:

ACTIONS'he reactor steam dome pressure shall be <

psig.

MODES 1 and 2.

CONDITION REQUIRED ACTION COMPLETION TIME Reactor steam dome pressure nof within limit.

A.1 Restore. reactor sfeam dome pressure to within limit.

15 minutes B.

Required Action and associated Completion Time not met.

B.1 Bein MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCEREQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Veri reacfor steam dome pressureis 0 psig.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> BFN-UNIT2 3.4-26 Amendment *R1

B. 3.4 REACTOR COOLANTSYSTEM (RCS)

B 3.4.10 Reactor Ream Dome Pressure BASES..

~

Re Steam Dome Pressure B 3.4.10 BACKGROUND The reacfor steam dome pressure is an assumed value in the deferminafion ofcompliance with reactor pressure vessel overpressure protecfion criteria andis also an assumedinifial condition ofdesign basis accidents and transients.

lg~~

APPLICABLE SAFETYANALYSES

[Oldpi', r Gap ~c ~itsy) ioro The reacfor steam dome pressure of<'igis an initial condition ofthe vessel overpressure protection analysis of Reference

1. This analysis assumes an initialmaximum reactor steam dome pressure and evaluafes the response ofthe pressure reliefsystem, pnmarily fhe safety/relief valves, during fhe limifing pressurization transient.

The determinafion ofcompliance with the overpressure criteria is dependent on theinitial reactor steam'dome pressure; therefore, the limiton this pressure ensures that the assumptions offhe overpressure protection analysis are.

conserved.

Reference 2 also assumes an initialreactor steam dome pressure forthe analysis ofdesign basis accidents and transients used to determine the limitsforfuel cladding infegnfy (see Bases forLCO 3.2.2, "MINIMUMCRITICALPOLVER RATIO (MCPR)") and 1% cladding plastic strain,(see Bases forLCO 3.2. 1, "AVERAGEPLANARLINEARHEAT GENERA TIONRATE (APLHGR)"). Since the design basis accident and the trans anal ses are performed at nominal operafiri g pressures '>

i a reactor steam dome pressure limifischosen af sig, to ensure fhe plant is operafed within the bounds ofthe uncertainties ofthe design basis accident and transient analyses.

Reactor steam dome pressure satisfies the requirements of Critenon 2 ofthe NRC Policy Statement (Ref. 3).

LCO The specified reacfor steam dome pressure limitof<'2 psig ensures the plantis operated within the assumptions offhe fransienf analysis.

Operation above the limitmay resultin a transienf response more severe than analyzed.

continued BFN-UNIT2 B 3.4-56 Amendment *R1

BASES pea r Steam Dome Pressure B 3.4.10 APPLICABILITY In MODES 1 and 2, the reactor steam dome pressure is required fo be less than or equal to the limit. In these MODES, the react'or may be generating significant steam and the design basis accidents and fransients are bounding.

In MODES 3, 4, and 5, fhe limitis not applicable because the reacforis shuf down. In these MODES, the reactor pressure is well below the required limit, and no anficipafed events willchallenge fhe overpressure limits.

ACTIONS A.1 With the reactor steam dome pressure greatei than the limit, prompt action should be taken to reduce pressure to below fhe limifand return the reactor to operation within the bounds ofthe analyses.

The f5'minute Completion Timeis reasonable considering the importance ofmaintaining the pressure within limits. This Completion Time also ensures fhat the probabi%ty ofan.8ccident occurring while pressureis greafer than the limitisminimized. Ifthe operatoris unable fo restore fhe reactor steam dome pressure fo

..'elow the limif, then the reactor should be placedin MODE3 fo be operating within fhe assumptions ofthe transienf analyses.

'.4 Ifthe reactor steam dome pressure cannot be restored to within the limitwithin the associafed Completion Time, the plant must be brought to a MODEin which the LCO does not apply.

To. achieve this stafus, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The allowed Complefion Time of f2 hours is reasonable, based on operating expenence, fo reach MODE 3 from fullpower conditionsin an orderly manner and without challenging plant systems.

SURVEILLANCE REQUIREMENTS SR 3.4.10.1 Qsc Verification that reactor steam dome pressureis

<1 0

sig ensures that theinitial conditions ofthe design basis accidents and transients are mef. Operating experience has shown the f2 hour.

C continued BFN-UNIT2 B 3.4-57 Amendment 'R1

E 1

I

~

Q.4 'EACTOR COOLANT SYSTEM(RCS)-

Rea Steam Dome Pressure 3.4. 3 0 3 4.10 Reactor Steam Dome Pressure LC0 3.4.10 APPLICABILITY:

ACTIONS MODES 1 and 2.

/g$ 0 The reactor steam dome pressure shall be s 1

sig.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Reactor steam dome pressure not within limit.

A.1 Restore reactor steam dome pressure to within limit.

15 minutes Required Action and B.1 Be in MODE 3.

associated Completion Time not met.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCEREQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Veri reactor steam dome pressure is s 102 sig.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

/No BFN-UNIT3 3.4-26 Amendment *R1

Re

'or Steam Dome Pressure B 3.4.10 B 3.4.10 Reactor Steam Dome Pressure BASES BACKGROUND The reactor steam dome pressureis an assumed value in the determination ofcompliance with reactor pressure vessel overpressure protection criteria andis also an assumed initial condition ofdesign basis accidents and fransients.

IOWA.

APPLICABLE SAFETYANALYSES 00Ãp5c) 4vJ

}ggppS,

>V'lbpe~F>'rC ly) l0m The reactor sfeam dome pressure of(

psigis aninitial condition ofthe vessel overpressure protection analysis of Reference f. This analysis assumes an initialmaximum reactor steam dome pressure and evaluates the response ofthe pressure reliefsystem, primarilythe safety/relief. valves, during the limiting pressurizatjon transient.

The determinafion.of compliance with the overpressure criteria is dependent on the initialreactor steam dome pressure; therefore, the limiton this pressure ensures fhat the assumpfions ofthe overpressure protection analysis are conserved.

Reference 2 also assumes an initialre'actor steam dome pressure forthe analysis ofdesign basis accidents and transients used to determine the limits forfuel cladding integrit (see Bases forLCO 3.2.2, "MINIMUMCRITICALPOWER RATIO (MCPR)") and 1% cladding plastic strain (see Bases forLCO 3.2. f, "AVERAGEPLANARLINEARHEATGENERATIONRATE (APLHGR)"). Since the design basis accident and the fransi ses are performed at nominal operating pressures

~4kiu a reactor steam dome pressure limitischosen af ps', to ensure the plan(is operated within the bounds ofthe uncertainties ofthe design basis accident and transient analyses.

'H Reactor steam dome pressure satisfies the requirements of Critenon 2 ofthe NRC Policy Stafement (Ref. 3).

/05"4'CO

'he specified reactor steam dome pressure limitof(

0 psig ensures the plant is operafed within the assumptions o e

fransient analysis.

Operation above the limitmay resulf in a transient response more severe than analyzed.

continued BFN-UNIT3 B 3.4-56 Amendment *R1

BASES Re r Steam Dome Pressure B 3.4.10 APPLICABILITY In MODES 1 and 2, fhe reactor steam dome pressure is required fo be less than or equal fo the limit. In these MODES, the reactor may be generating significant steam and the design basis accidents and transients are bounding.

In MODES 3, 4, and 5, the limitis not applicable because the reactoris shut down. In these MODES, the reactor pressure is well below the required limit, and no anticipated events willchallenge the overpressure limits.

ACTIONS A. 1 With the reactor steam dome pressure greafer than the limit, prompt action should be taken to reduce pressure to below fhe limitand refurn the reactor to operation wifhinfhe bounds ofthe analyses.

The 15 minute Completion Time is reasonable considering fhe importance ofmaintaining the pressure within limits. This Completion Time also ensures that the probability ofan accident occurring while pressureis greater than the limitisminimized. Ifthe::

operator'is unable to restore fhe reactor steam dome pressure to below the limit, then the reactor should be placed in MODE3 to be operating within the assumptions ofthe transient analyses.

B.f Ifthe reactor steam dome pressure cannot be restored to within the limitwithin the associated Completion Time, the planf must be brought to a MODEin which the LCO does nof apply.

To achieve fhis status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The allowed Completion Time of f2 hoursis reasonable, based on operafing experience, to reach MODE 3 from fullpower conditionsin an orderly manner and without challenging plant systems.

SURVEILLANCE REQUIREMENTS SR 3.4.10.1 Verification fhat reactor steam dome pressureis (1 gO sig ensures that the initialconditions ofthe design basis accidents and transients are met.

Operating experience has shown the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> II continued BFN-UNiT3 8 3.4-57 Amendment *R1