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. I I

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 />. I l

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 />. l l

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 />. l I

2. Leakaae Detection Systems l 2. Leakage Detection Systemi i l I

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: l 1 I a. For each required drywell i

1. One drywell sump I sump monitoring system i monitoring system, and l perform: I either l l

1. 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. l I

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. l l

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). I l

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Amendment No. 144