ML20034F771

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Proposed Stated TS Section Re Steam & Power Conversion Sys
ML20034F771
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 02/26/1993
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20034F769 List:
References
NUDOCS 9303040267
Download: ML20034F771 (7)


Text

.

a 15.3.4 STEAM AND POWER CONVERSION SYSTEM Apolicabilit_y Applies to the operating status of steam and power conversion system.

Ob.iective i

To define conditions of the steam and power conversion system steam-relieving I

capacity. Auxiliary Feedwater System and Service Water System operation is j

necessary to ensure the capability to remove decay heet from the core.

Soecification 1

A.

When the reactor coolant is heated above 350 F the reactor shall not be

{

taken critical unless the following conditions are met:

1.

A minimum steam-relieving capability of eight (8) main steam safety valves available, except for low power physics testing.

2.

Auxiliary Fcedwater System a.

Two Unit Operation - All four auxiliary feedwater pumps together with their associated flow paths and essential instrumentation shall be operable.

i b.

Single Unit Operation - Both motor driven auxiliary feedwater j

pumps and the turbine driven auxiliary feedwater pump associated with that unit together with their associated flow paths and essential instrumentation shall be operable.

i i

9303040267 930226 DR ADOCK 05000266 i

p PDR Unit 1 - Amendment No. yo Unit'2 - Amendment No. 99 15.3.4-1 August 15, 1985

+

3.

A minimum of 13,000 gallons of water per operating unit in the i

condensate storage tanks and an unlimited water supply from the lake via either leg of the plant Service Water System.

4.

System piping and valves required to function during accident conditions directly associated with the above components operable.

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B.

The iodine-131 activity on the secondary side of the steam generator.shall i

not exceed 1.2 pCi/cc.

C.

During power operation the requirements of 15.3.4. A.2.a and b may be modified to allow the following components to be inoperable for a specified l

time.

If the system is not restored to meet the requirements of 15.3.4.A.2.a and b within the time period specified, the specified action i

must be taken.

If the requirements of 15.3.4.A.2.a and b are not sati.sfied t

within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the appropriate reactor (s) shall be cooled down to less than 350 F.

1.

Two Unit Operation - One of the four operable auxiliary feedwater pumps may be out-of-service for the below specified times. A turbine driven auxiliary feedwater pump may be out of service for up to l

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

If the turbine driven auxiliary feedwater pump cannot be restored to service within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> time period the associated reactor shall be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. A motor driven auxiliary feedwater pump may be out of service for up to 7 days.

If the inoperable' motor driven auxiliary feedwater pump cannot be restored to service within the 7 day time period both of the reactors shall be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Unit 1 - Amendment No. 130 Unit 2 - Amendment No. 134 15.3.4-2 April 8, 1992

. = -

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2.

Single Unit Operation - One of the three operable auxiliary feedwater pumps associated with a unit may be out-of-service for the below specified times.

The turbine driven auxiliary feedwater pump may be j

out-of-service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

If the turbine driven auxiliary feedwater pump cannot be restored to service within that 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> time period, the reactor shall be in hot shutdown within the next 12 I

hours.

Either one of the two motor driven auxiliary feedwater pumps may be out-of-service for up to 7 days.

If the motor driven auxiliary feedwater pump cannot be restored to service within that 7 day period the operating unit shall Se in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D.

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l Basis A reactor shutdown from power requires removal of core decay heat.

Immediate decay heat removal requirements are normally satisfied by the steam bypass to the I

4 condenser. Therefore, core decay heat can be continuously dissipated via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorption. Normally, the capability to return feedwater flow to Unit 1 - Amendment No. 133 Unit 2 - Amendment No. 137 15.3.4-2a July 31,1992

f f

the steam generators is provided by operation of the turbine cycle feedwater t

system.

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The eight main steam safety valves have a total combined rated capability of 6,664,000 lbs/hr. The total full power steam flow is 6,620,000 lbs/hr, therefore 1

eight (8) main steam safety valves will be able to relieve the total full-power l

t steam flow if necessary, i

In the unlikely event of complete loss of electrical power to the station, decay heat removal would continue to be assured for each unit by the availability of either the steam-driven auxiliary feedwater pump or one of the two motor-driven auxiliary steam generator feedwater pumps, and steam discharge to the atmosphere s

via the main steam safety valves or atmospheric relief valves.

One motor-driven l

t 4

auxiliary feedwater pump can supply sufficient feedwater for removal of decay heat from a unit. The minimum amount of water in the condansate storage tanks ensures the ability to maintain each unit in a hot shutdown condition for at l

least one hour concurrent with a loss of all AC power.

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An unlimited supply is available from the lake via either leg of the plant service water system for an indefinite time period.

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- 15.3.4-2b July 31, 1992 1

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i Unit 1 - Amendment No. 133

' Unit Amendment No. 137 15.3.4-2c July 31, 1992

+

.. n,

l For the purposes of determining a maximum allowable secondary coolant activity, the steam break accident is based on a postulated release of the contents of one-steam generator to the atmosphere using a site boundary dose limit. The limiting dose for this accident results from iodine in the secondary coolant.

1-131 is the dominant isotope because of its low MPC in air and because the other iodine i

isotopes have shorter half-lives and therefore cannot buildup to significant concentrations in the secondary coolant, given the limitations on primary system leak rate and activity.

It is assumed that the accident occurs at zero load, which is when the maximum amount of water is contained in one steam generator.

f One tenth of the contained iodine is assumed to reach the site boundary, making l

allowance for plate-out and retention in water droplets.

It is conservative to measure gross beta-gamma activity except when the gross activity exceeds or equals 1.2 pCi/cc. At this time the iodine-131 activity must be measured.

The maximum inhalation dose at the site boundary is then as follows:

Dose (rem) =

CXE X B(t)x 3 x DCF 10 Q

l t

where:

secondary coolant activity (1.2 pCi/cc = 1.2 Ci/m')

{

C

=

\\

V

=

(2821 ft' = 80 m')

f breathing rate (3.47 x 10 m'/sec)

B(t)

=

3.0 x 10-' sec/m'

")

l x/Q

=

1.48 x 10' rem /Ci I-131 inhaled l

DCF

=

The resultant dose is slightly less than 1.5 rem.

I

References:

l FSAR Section 10 FSAR Section 14 l

15.3.4-3

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j 15.4.8 AUXILIARY FEEDWATER SYSTEM l

{

Apolicability Applies-to periodic testing requirements of the turbine-driven and j

motor-driven auxiliary feedwater pumps.

Ob.iective To verify the operability of the Auxiliary Feedwater System and its ability l

to respond properly when required.

{

t Specification l

1.

a.

Each motor driven auxiliary feedwater pump wili Le started quarterly.

b.

Each steam turl'ine driven auxiliary feedwater pump will be started quarterly provided steam is available. }Qf@s((Eij

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The auxiliary feedwater pumps discharge valves and the service j

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water supply valves on the suction side will be tested by operator action mentMy jURtsfly.

^

i 2.

These tests shall be considered satisfactory if control board I

indication and subsequent visual observation of the equipment i

demonstrate that all components have operated properly.

t Basis The quarterly testing of the auxiliary feedwater pumps will verify their f

operability.

The quarterly test of the steam driven pumps will be a fast start test with no prior warmup.

Proper functioning of the steam turbine admission valves and the stiftfoghj feedwater pumps stet will i

demonstrate the integrity of the steam driven pumpj. 16dlifijpyl[Q5jh2 Unit 1 - Amendment No. 133 15.4.8-1 July 31, 1992 Unit 2 - Amendment No. 137

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correct operation will be made both from instrumentation within the main control room and direct visual observation of the pumps.

Reference FSAR - Sections 10.4 FSAR - Section 14.1.7 FSAR - Section 14.2.5 Unit 1 - Amendment No. 133 15.4.8-la July 31, 1992 Unit 2 - Amendment No. 137