Text

Proposed Tech Specs Correcting Typos & Errors in Spec Numbering
	ML18095A870
Person / Time
Site:	Salem
Issue date:	04/03/1991
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18095A869	List: ML18095A868; ML18095A870;
References
	NUDOCS 9104150028
	Download: ML18095A870 (4)
	v • d • e

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 23 -

With the number of channels OPERABLE les' than required by the Minimu~ Channels OPERABLE requirement, perform area surveys of the roonitored area with portable roonitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 24 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comp<f wit~~e ACTION requirements of Specification.4.6.l

~3,L/, ?.I.

ACTION 25 -

With the AJ~ber of channels OPERABLE less than required by the Mini111Jm Channels OPERABLE requirement~ comply with the ACTION requirements of Specification 3.9.9.

ACTION 26 -

With the number of OPERABLE Channels' less than required by the Mini~um Channels OPERABLE requirements, initiate tne preplanned alternate method of nl)nitoring the appropriate parameter(s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

SALEM - UN IT 2 3/4 3-40 Amendment No. 53

'-/,'-/, 7, 2. /

REACTOR COOLANT SYSTEM OPERATIOML LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.7.2 Reactor Coolant Systall leakage shall be li*ft.d to:

a.

No PRESSURE BOUNDARY LEAKAGE,

b.

1 GPM UNIDEHTIFIEO LEAKAGE,

c.

1 GPM tot&l pr1ury-to-sacondary leakage through all st.* generators and 500 gallons per day through any one st** generator,

d.

10 GPM IDEHTIFIEO LEAKAGE fro11 the Reactor Coolant System, and

1.

40 GPM CONTROLLED LEAKAGE at a Reactor Coolant Syst* pressure of 2230 z 20 psig.

f.

1 GPfli leakage at a Reactor Coalant System pl"essure of 22,30 ! 20 psig from any Reactor Coolant Systell Pressure Isolation Valve specified in Table 3.4-1.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at 11ast HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With any Reactor Coolant System leakage greater than any one of the above limits, txcluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant Systa Pl"essure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or b* in at least HOT STANDBY within th* next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and fn COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With any Reactor Coolant System Pressure Isolation Valve leakage greater.than th* above li*ft, isolate th* high pressure portion of the affected systell from the 'low pl"essure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, or be f n at least HOT STAHOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTllOWt(within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS

--=--=~..-'.y.

CA.4.7.2 J Reactor Coolant System leakages shall be demcnstrated to be within each of th* above limits by;

a.

Monitoring th* contain11ent atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

Monitoring the containment sump inventory at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SALEM - UHIT 2 3/4 4-17

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Contin~ed)

c.

Measurement of the CONTROLLED LEAKAGE from the reactor coolant pump seals at least once per 31 days when the Reactor Coolant System pressure is 2230 +/- 20 psig and valve 2CV71 is fully closed,

d.

Performance of a Reactor Coolant System water inventory balance ~l least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The water inventory balance shall be performed with the plant at steady state conditions. The provisions of specifica-tion 4.0~4 are not applicable for entry into Mode 4, and

e.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

lf, '/. 7. 2.za. 4. 7. r5 Each Reactor Cool ant System Pressu.re I sol at ion Valve specified in Table 3.4-1 shall be demonstrated OPERABLE pu~uant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

At least once per 18 months.

b.

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or more and if leakage testing has not been performed in the previous 9 months.

c.

Prior to returning the valve to service following maintenance repair or replacement work on the valve.

d.

For the Residual Heat Removal and Safety Injection Systems hot and cold leg injection valves and accumul~tor valves listed in Table 3.4-1 the testing will be done within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve.

For all other systems testing will be done once per refueling.

The provisions of specification 4.0.4 are not ~pplicable for entry into MOOE 3 or 4.

SALEH - UN IT 2 3/4 4-18 Amendment No. 27 I

_J

REACTOR COOL.ANT SYSTEM VALVE NO.

21SJ43 22SJ43 23SJ43 24SJ43 21SJ55 22SJ55 23SJ55 24SJ55 21SJ56 22SJ56 23SJ56

.24SJ56 21SJ17 22SJ17 23SJ17 24SJ17 2SJ150 21SJ139 22SJ139 23SJ139 24SJ139 21SJ156.

22SJ156 23SJ156 24SJ156 21SJ144 22SJ144 23SJ144 24SJ144 2RH1 2RH2 23RH27 24RH27 SALEM - UNIT 2 TABLE 3. 4-1.

REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES FUNCTION Safety Injection (L.P. from RHR Pumps to Cold Legs)

Safety Injection (L.P. from RHR Pumps to Cold Legs)

Safety Inject.ion (Accumulator Discharge to Cold Legs)

Safety Injection (Accumulator Discharge to Cold Legs)

Safety Injection (Boron Injection to Cold Legs)

Safety Injection (H.P. from SI Pumps to Hot Legs)

Safety Injection (H.P.

from SI from SI from SI from SI from SI from SI from SI Safety Injection (H.P. from SI Pumps to Hot Legs)

Pumps to Hot Legs)

Safety Injection (H.P. from SI Pumps to Hot Legs)

RHR Suction from Hot Leg No: 21 RHR Suction from Hot Leg No. 21 RHR Discharge to Hot Leg No. 23 RHR Discharge to Hot Leg No. 24 3/4 4-19

ML18095A870

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