ML20205M089

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Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp
ML20205M089
Person / Time
Site: Millstone Dominion icon.png
Issue date: 04/07/1999
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20205M088 List:
References
NUDOCS 9904150096
Download: ML20205M089 (5)


Text

'

ELANT SYSTEMS AUXILIARY FEEDWATER PUMPS LIMITING CONDITION FOR OPERATION 3.7.1.2 OPERABLE with:At least three steara generator auxiliary feedwater pLaps shall be Two feedwater pumps capable of being powered from separate a.

OPERABLE emergency busses, and b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2 and 3.

MJIO3:

With one auxiliary feedwater pump inoperable, restore the required a.

auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at lecst HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HLT I

SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6

hours and in HOT SHUTDOWN within the following 6 ho:rs, c.

With three auxiliary feedwater pumps inoperable, immediately i

initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible. Entry into an OPERATIONAL MODE or other specified condition under the provisions of Specification 3.0.4 shall not be made with three auxiliary feedwater pumps inoperable.

SURVEILLANCE REQUIREMENTS ~

4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

At least once per 31 days by:

e.

1.

Starting each pump from the control room, 2.

Verifying that:

a)

Each motor driven pump develops a differentia) pressure of 21144 psid on recirculation flow, and b)

The steam turbine driven pump develops a differential pressure of 2 tF3t psid, corrected to rated pump speed, recirculation flow when the secondary steam supply on jfj 3 pressure is greater than 800 psig. The provisions of Specification 4.0.4 are not applicable for entry into Mode 3.

H,ILLSTONE - UNIT 2 3/4 7-4 Amendment No. 77, 77, pp, JEJ.

9904150096 990407 PDR ADOCK 05000336 p

PDR s

PLANT SYSTEHji BASES 3/4.7.1.2 TUXILIARY FEEDWATER PUMPS Reactor Coolam. System can be cooled down to less tha operating conditions in the event of a total loss of off-site power.

Any single motor driven or steam driven pump ht.s the required heat and reduce the RCS temperature to 300*F where the shu cooling system may be placed into operation for continued cooldown.

The Technical Specification Surveillance Requirements provided to ensure OPERABILITY of each component ensuret that at a minimum, the assumptions used in the accident analysis ate met and that subsystem OPERABILITY is maintained.

The purpose of the auxiliary feedwater pumps differential pressure tests on recirculation, Surveillance Requirements 4.7.1.2.a.2.a and 4.7.1.2.a.2.b, is to ensure that s

degraded to a point where the accident analysis would bethe pumps have not or dg( n,ca The surveillance requirement acceptance criteria for thepauxiliary feedwater ersely impacted.

pumps was developed assuming a 5% degraded pump from the actual pump curves.

The surveillance requirement acceptance criteria for the turbine driven auxiliary feedwater (performance of varia tons in pump speed.can be adjusted to account for the affec i

um instrument Flow and pressure measurement

/

hydraulic analysis for the motor driven auxiliary feedwater pu

Flow, pressure, and speed measurement instrument inaccuracies have not been i

accounted for in the design basis hydraulic analysis fur the turbine driven auxiliary feedwater pump.

Corrections for flow, pressure, and speed i

(turbine driven pump only) measurement instrument inaccuracies will be applied to test data taken when verifying pump performance in the flow ranges credited in the accident analyses.

No corrections for flow, pressure, and speed (turbine driven pump only) measurement instrument inaccuracies will be applied to minimum recirculation flow type test data

}

since this portion of the curve is not credited in the accident analyses.

Corrections for fl ow, pressure, and speed (turbine driven pump only) measurement instrument inaccuracies are not reflected in the Technical pecification acceptanca criteria.

g gj,j g jy g

3/4.7.1.3 CONDENSATE STORAGE TANK

((

[1 g,

y,j The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available for cooldown of the Reactor Coolant System to less than 300*F in the event of a total loss of off-site power.

The minimum water volume is sufficient to maintain the RCS at HOT STANDBY conditions for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with steam i

discharge to atmosphere.

The contained water volume limit includes an j

allowance for water not usable due to discharge nozzle pipe elevation above tank bottom, plus an allowance for vortex formation.

3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resuitant off-site radiation dose will be limited to a small fraction j

HILLSTONE - UNIT 2 8 3/4 7-1.

Amendment No. J/, JJ, J/, /JJ.

oon 777.

I

\\

j Docket No. 50-336 B17737 1

h Millstone Nuclear Power Station, Unit No. 2 Modification to a Proposed Revision to Technical Specifications Engineered Safety Features Pump Testing Retyped Page l

April 1999

~

PLANT SY$1 EMS e

AUXILIARY FEFDWATER PUMPS LINITING CONDITION FOR OPERATION 3.7.1.2 At least three steam generator auxiliary feedwater pumps shall be OPERABLE with:

Two feedwater pumps capable of being powered from separate a.

OPERABLE emergency busses, and b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one auxiliary feedwater pump inoperable, restore the required a.

auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

)

b.

With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6

hours and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective actioin to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible. Entry into an OPERATIONAL N0DE or other specified condition under the provisions of Specification 3.0.4 shall not be made with three auxiliary feedwater pumps inoperable.

SURVEILLANCE REQUIRENENTS l

4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Starting each pump from the control room,

2.. Verifying that:

a)

Each motor driven pump develops a differential pressure of 11144 psid on recirculation flow, and b)

The steam turbine driven pump develops a differential pressure of 1 1113 psid, corrected to rated pump speed, on recirculation flow when the secondary steat supply pressure is greater than 800 psig. The provisions of Specification 4.0.4 are not applicable for entry into Node 3.

NILLSTONE - UNIT 2 3/4 7-4 Amendrient No. (J. 77, pp, Jpf, 0613

PLANT SYSTEMS SASES

-3/4.7.1.2 ~ AUXILLARY FEEDWATER PUMPS The OPERABILITY of the auxiliary feedwater pumps enes that the Reactor Coolant System can be cooled down to less -than 300'F from normal

' operating conditions in the event of a-total loss of off-site power.

-Any single motor driven or steam driven pump has - the required capacity to provide sufficient feedwater flow to remove reactor decay -

heat and reduce the RCS temperature to 300*F. where the ' shutdown cooling system may be placed into operation for continued cooldown.

The Technical Specification Surveillance Requirements provided to ensure OPERABILITY of each component ensures.that at a minimum, the assumptions used in the accident analysis are n.et and that subsystem OPERABILITY is maintained.

The purpose of the auxiliary feedwater pumps differential pressure tests on recirculation, Surveillance Requirements 4.7.1.2.a.2.a and 4.7.1.2.a.2.b, is to ensure that. the pumps have not degraded to a point where the accident analysis would be adversely impacted.

The serveillance requirement acceptance criteria for the motor driven

' auxiliary feedwater pumps was developed assuming a 5% degraded pump from the actual pump curves.

The surveillance requirement acceptance criteria for the turbine-driven auxiliary feedwater pump was. developed from high ' flow test. data extrapolated to minimum recirculation flow, and can be adjusted to account for the. affect on pump performance of variations in pump speed.

Flow' and pressure measurement instrument inaccuracies have not been accounted for in the design basis hydraulic analysis for the motor driven

. auxiliary feedwater pumps. Flow, pressure, and speed measurement instrument inaccuracies have. not been accounted for in the design basis hydraulic analysis for the turbine driven auxiliary feedwater pump.

Corrections for flow, pressure, and speed (turbine driven pump only) measurement instrument inaccuracies will be applied to test data taken when verifying - pump performance in the flow ranges credited in the accident analyses.

No corrections. for flow, pressure, and speed (turbiae driven pump only) measurement instrument inaccuracies will be applied to minimum recirculation flow type test data since this portion of the curve is not credited in the j

accident analyses.

Corrections for flow, pressure, and speed (turbine driven pump only) mmurement instrument inaccuracies are not reflected in the Technical Specification acceptance criteria.

1 3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available for cooldown of the Reactor Coolant System to less than 300*F in the event of a total loss cf off-site power. The minimum water volume is sufficient to maintain the RCS ~at HOT STANDBY conditions for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with steam discharge to atmosphere.

The contained water volume limit includes an allowance for water not usable due to discharge nozzle pipe elevation above tank' bottom, plus an allowance for vortex formation.

2/4.7.1.4 ACTIV1Tl The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction MILLSTONE - UNIT 2 8 3/4 7-2 Amendment No. pg, JJ, 77, 777, oen.

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