ML18039A448

Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions

ML18039A448
Person / Time
Site:	Browns Ferry
Issue date:	07/17/1998
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18039A447	List: ML18039A446 ML18039A448
References
NUDOCS 9807290352
Download: ML18039A448 (8)

Text

ENCLOSURE 2

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 2 AND 3 PROPOSED TECHNICAL SPECIFICATION (TS)

CHANGE TS-384, SUPPLEMENT 2 MARKED PAGES 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.

9807290352 980717 PDR ADOCK 05000260 P

POR

3.4 REACTOR COO T SYSTEM (RCS)

Reac'-

Stoic'. Ocr;e r ress.;

3.4.10 3.4. 10 Reactor Steam Dome Pressure

/0 5-O I

LCO 3.4. 10 The reactor steam dome pressure shall be <

psig.

APPLICABILITY:

ACTIONS'ODES 1 and 2.

CONDITION A.

Reactor steam dome pressure not within limit.

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

COMPLETION TIME f5 minutes B.

Required Action and associated Completion Time not met.

B.1 Bein MODE 3.

f2 hours SURVEILLANCEREQUIREMENTS SURVEILLNVCE FREQUENCY SR 3.4.10.1 Ve 'eactor steam dome pressure is 0

sig.

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 COO NT SYSTEM (RCS)

B 3.4. 10 Reactor Ream Dome Pressure BASES Re 'team Dome t ressure B 3.4.10 BACKGROUND The reactor steam dome pressure is an assumed value in the determination ofcompliance with reactor pressure vessel overpressure protection cn'teria andis also an assumedinitial condition ofdesign basis accidents and transients.

IO~~

APPLICABLE SAFETYANALYSES

((nay p~g as/

IOH'gg',wcspec i i>G/p)

IO~o~

The reactor steam dome pressure of <

sigis an initial condition ofthe vessel overpressure protection analysis of Reference

1. This analysis assumes an initialmaximum reactor steam dome pressure and evaluates the response ofthe pressure reliefsystem, primarilythe safetylrelief valves, during the limng pressun'zation transient.

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

Reference 2 also assumes an inNaireactor steam dome pressure forthe analysis ofdesign basis accidents and transients used to determine the limitsforfuel dadding integnty (see Bases forLCO 3.2.2, "MINIMUMCRITICALPOWER RATIO (MCPR)") and 196 cladding plastic strain (see Bases forLCO 3.2. 1, "AVERAGEPLANARLINEARHEATGENERATIONRATE (APLHGR)"). Since the design basis accident and the tran

'nal es are performed at nominal operatiri g pressures '~

i a reactor steam dome pressure limitischosen at sig, to ensure the plantis operated within the bounds ofthe uncertainties ofthe design basis accident and transient analyses.

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

X LCO The speci%ed reactor steam dome pressure limitof < 02 psig ensures the plant is operated within the assumptions ofthe transient analysis.

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

continued BFN-UNIT2 B 3.4-56 Amendment 'R1

BA'SES Reac'.~i S:ear;,

";.,e P;e APPLICABILITY

" In MODES 1 and 2, the reactor steam dome pressure is required to be less than or equal to 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 limitisnot applicable because the reactoris shut down. In these MODES, the reactor pressureis well below the required limit, and no anticipated events willchallenge the overpressure limits, ACTIONS A.1 With the reactor steam dome pressure greater than the limit, prompt action should be taken to reduce pressure to below the limitand return the reactor to operation within the bounds ofthe analyses.

The 15'minute Completion Time is reasonable considering the 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 fo restore the reactor steam dome pressure to

.'elow the limit, then the reactor should be placedin MOPE 3 to be operating within the assumptions ofthe transient analyses.

B.1 Ifthe reactor steam dome pressure cannot be restored to within the limitwithin the associated Completion Time, the plant must be brought to a MODEin which the LCO does not apply.

To, achieve this 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 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />sis reasonable, based on operating experience, to reach MODE 3 from fullpower conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE REQUIREMENTS SR 3.4.10.1 Verification that reactor steam dome pressureis (

0 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 />.

C continued BFN-UNIT2 B 3,4-57

- Amendment 'R1

3.4 REACTOR COOLOf'YSTEM (RCS)

React~

Steam Daq-<e pressure 3.4.10 3.4.10 Reactor Steam Dome Pressure I

LCO 3.4.10

/$ 5 0 The reactor steam dome pressure shall be s sig.

APPLICABILITY'CTIONS MODES 1 and 2.

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 associated Completion Time not met.

8.1 Be in 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 Ve 'eactor 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 />

/NV BFN-UNIT3 3.4-26 Amendment 'R1

B 3.4 REACTOR CO NT SYSTEM (RCS)

B 3.4.10 Reactor Steam Dome Pressure BASES Rea

-.r Scheer.:Ocr;.e F.s-r=

8 3.4.10 BACKGROUND

.The reactor steam dome pressureis an assumed value in the determination ofcompliance with reactor pressure vessel overpressure protection critena andis also an assumed initial condition ofdesign basis accidents and transients.

IPSE+

APPLICABLE SAFETYANALYSES OPS pk) 4vJ lOWPp~ >~ope~fi'~i~y) loan The reactor steam dome pressure ofa psig is an initial condition ofthe vessel overpressure protector'on analysis of Reference f. This analysis assumes an initialmaximum reactor steam dome pressure and evaluates the response ofthe pressure reliefsystem, pn'manly the safetylrelief valves, during the limiting pressurization transient.

The determination. ofcompliance with the overpressure criteriais dependent on theinl'tl'al reactor steam dome pressure; therefore, the limiton this pressure ensures that the assumptions ofthe overpressure protection anal~s arp conserved.

Reference 2 also assumes an initialre'actor steam dome pressure forthe analysis ofdesign basis accpdents and transients used to determine the limitsforfuel cladding integrit (see Bases forLCO 3.2.2, "MINIMUMCRITICALPOPOVER RATIO (MCPR) ) and 496 cladding plastic strain (see Bases forLCO 3.2. 1, "AVERAGEPLANARLINEARHEATGENERATIONRATE (APLHGR)"). Since the design basis accident and the fransi es are performed at nominal operating pressures

~ Wiv a reactor steam dome pressure limitischosen at psrg, to ensure the plantis operated within the bounds ofthe uncertainties ofthe design basis accident and transient analyses.

Reactor steam dome pressure satisfies the requirements of Cri te'on 2 ofthe NRC Policy Statement (Ref. 3).

]05"D LCO The specihed reactor steam dome pressure limitof <'

psig ensures the plant is operated within the assumptions o e

transient analysis.

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

continued BFN-UNIT3 B 3.4-56 Amendment 'R1

'BASES Re-r S(ear.", Ccr",e pr<<~'e 8 3.<.>O L

APPLICQQILITY In MODES 1 and 2, the reactor steam dome pressureis required to be less than or equal fo the limit. In these MODES, the reactor may be generating significant steam and the design basis accidents and fransients are bounding.

In MODES 3, 4, and 5, fhe limitis nof applicable because fhe reactoris shut down. In fhese MODES, the reactor pressure is well below fhe required limit, and no anticipated events willchallenge fhe overpressure limifs.

ACTIONS A.1 With the reactor steam dome pressure greater than the limit, prompt action should be taken to reduce pressure fo below fhe limitand return the reactor to operation within fhe bounds offhe analyses.

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

operatoris unable to restore the reactor steam dome pressure to below the limit, then the reactor should be placedin MODE3 to be operating within the assumptions ofthe transient analyses.

B.1 Ifthe reactor steam dome pressure cannot be restored to within the limitwithin the associated Completion Time, the plant must be brought to a MODEin which the LCO does nof apply.

To achieve this status, the planf must be brought to af least MODE3 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from fullpower conditionsin an orderiy manner and without challenging plant systems.

SURVEILLANCE REQUIREMENTS SR 3.4.10.1 X

Verificatithat reacfor steam dome pressureis 1

0 sig ensures that the initialconditions ofthe design basis amdenfs and transients are mef. 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 /> I

continued BFN-UNIT3 B 3.4-57 Amendment 'R1