ML20079C741

Proposed Tech Specs Re Reactor Coolant Leakage Detection Sys

ML20079C741
Person / Time
Site:	Pilgrim
Issue date:	06/13/1991
From:	BOSTON EDISON CO.
To:
Shared Package
ML20079C714	List: ML20079C713 ML20079C741
References
NUDOCS 9106260023
Download: ML20079C741 (2)

Text

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LIBilLNJi_CQMll10NS FOR ODfiUON SUAylluAtitLRLOUJEEHENTS j

3.6.C.1 Operational leak 1Lqe (Cont'd) l I

4.

12 gpm increase in l

Unidentified Leaksge I

within any 24 l

hour period when in RUN l mode.

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b.

With any reactor coolant I

system leakage greater than I the limits of 2. and/or 3,

I above, reduce the leakage to I within acceptable limits l

within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at i

least Hot Shutdown within l

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

Cold Shutdown within the l

following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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c.

With any reactor coolant i

system leakage greater than I the limits of 4. above, I

identify the source of l

leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be 1 in at least Hot Shutdown I

within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and I in Cold Shutdown within the l following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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d.

When any Pressure Boundary I

Leakage is detected be in at l least Hot Shutdown within I

the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in I Cold Shutdown within the l

next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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2. Leakaae Detection Systems l

2.

Leakage Detection Systemi i

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a.

The following reactor i

The following reactor coolant I

coolant system leakage l

leakage detection systems shall i detection systems shall be i

be demonstrated Operable:

1 Operable:

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I a.

For each required drywell i

1.

One drywell sump I

sump monitoring system i

monitoring system, and l

perform:

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An instrument i

functional test at i

least once per 31 days, l and j

Amendment No.

125a 9106260023 910613 PDR ADOCK 05000293 P

PDR

MSES:

MLDnLUnC CQolant Lech ge (Continued) another for the floor sump, comprise the basic instrument system, and are used I to record the flow of liquid from the drywell sumps.

A manual system whereby l the time interval between sump pump starts is utilized to provide a back-up to I the flow integrators if the instrumentation is found to be inoperable.

This l

time interval determines the leakage flow because the c6pacity of the pump is l

known.

l The capacity of each of the two drywell floor sump pumps is 50 gpm and the l

Capacity of each of the two drywell equipment sump pumps is also 50 gpm.

I Removal of 25 gpm from either of these sumps can be accomplished with considerable margin.

In addition to the sump monitoring of coolant leakage, airborne radioactivity I levels of the drywell atmosphere is monitored by the Reactor Pressurt Boundary l Leak Detection System.

This system consists of two panels capable of l

monitoring the primary containment atmosphere for particulate and gaseous l

radioactivity as a result of coolant leaks.

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The 2 gpm limit for coolant leakage rate increase within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is I a limit specified by the NRC in Generic Letter 88-01:

"NRC Position on IGSCC l in BWR Austenitic Stainless Steel Piping".

This limit applies only during the l RUN mode to accommodate the expected coolant leakage increase during l

pressurization.

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The total leakage rate consists of all leakage, which flows to the drywell 1

equipment drain sump (Identified leakage) and floor drain sump (Unidentificd l

leakage).

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Amendment No.

144