ML20154B598

Proposed Tech Specs Re Suppression Pool Temp Limit

ML20154B598
Person / Time
Site:	Hatch
Issue date:	05/13/1988
From:	GEORGIA POWER CO.
To:
Shared Package
ML19302D608	List: ML20154B589 ML20154B598
References
NUDOCS 8805170245
Download: ML20154B598 (8)

Text

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t LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.

CONTAfNMENT SYSTEMS 4.7.

CONTAfNMENT SYSTEMS Applicability Applicability The Limiting Conditions for Operation The Surveillance Requirements associated with containment systems associated with containment systems apply to the operating stc.us of the apply to the primary and secondary primary and secondary containment containment integrity.

systems.

Objective Objective The objective of the Limiting Conditions The objective of the Surveillance Re-for Operation is to assure the integrity quirements is to verify the integrity of the primary and secondary containment of the primary and secondary contain-systems.

ment.

Specifications Specifications A.

Primary Containment A.

Primary Ccntainment 1.

Pressure Suppression Chamber 1.

Pressure Suppression Chamber At any time that irradiated a.

The pressure suppression chamber fuel is in the reactor vessel, and water level, water temperature the nuclear system is pressurized and air temperature shall be above atmospheric pressure or measured and recorded daily, work is being done which has the potential to drain the vessel, the pressure suppression chamber b.

The interior painted surfaces water level and water temperature above the level one foot below shall be maintained within the the normal water line of the following limits except while per-pressure suppression chamber forming low power physics tests at shall be visually inspected atmospheric pressure at power levels once per operating cycle, not to exceed 5 Mwt.

In addition, the external surfaces of the pressure a.

Minimum water level - 12 feet, suppression chamber shall 2 inches.

be visually inspected on a routine basis for evidence b.

Maximum water level - 12 feet, of corrosion or leakage.

6 inches.

c.

Whenever there is indication c.

During normal power operation, that a significant amount of if the suppression chamber water heat is being added to the temperature reaches 100*F, pool pressure suppression pool, the cooling shall be initiated pool temperature shall be con-immediately.

tinually monitored and also observed and logged every 5 minutes until thu heat addition is termir;atud.

8805170245 880513 PDR ADOCK 05000321 P

DCD HATCH - UNIT 1 3,7-1 Proposed TS/0206q/l')3-16

LIMITING CONDITIONS FOR OPERAfl0N SURVEllLANCE REQUIREMENTS d.

The reactor shall be scrammed l d.

Whenever there is from any operating condition indication that there when the suppression pool was relief valve operation temperature reaches 110*F.

with the temperature of the suppression pool e.

During reactor isolation exceeding 160'F and the conditions the reactor reactor primary coolant pressure vessel shall be system pressure greater depressurized to less than than 200 psig, an ex-200 psig at normal cooldowr.

ternal visual examination rates if the pool tempera-of the pressure suppres-ture reaches 120*F.

sion chamber shall,

conducted before resuming power operation.

HATCH - UNIT 1

3. 7 -l a Proposed TS/0206q/103-16

BASES FOR LIMITING CONDITIONS FOR OPERATION 3.7.A.1.

Pressure Suppression Chamber (Continued)

The maximum pool temperature based on the consideration of complete condensation has been determined by evaluating the blowdown test data f rom the Mark 1 Full Scale Test Facility. Based on these analyses, a pool temperature of 195'F can provide complete steam condensation (conservatively assumes no pressurization of the air space over the pool). Analyses for Plant Hatch have shown that with an initial pool temperature of Il0'F, the pool temperature followirl a blowdown will be below that needed for complete condensation.

For an initial suppression pool temperature of 110*F and assuming that one loop of the RHR system is available for containment cooling (2 RHR and 2 RHR service water pumps) adequate net positive suction head (NPSH) is maintained f or the core spray, RHR, and HPCI pumps.

Limiting pressure suppression chamber water temperature to 120'F during RCIC, HPCI or relief valve operation when decay heat and stored energy are removed f rom the primary system by discharging reactor steam directly to the sup-pression chamber assures adequate margin for controlled blowdown anytime during RCIC operation.

Using a 50*F rise (Table 5.2-1 FSAR) in the pressure suppression chamber water temperature and an initial temperature of less than 120*F, the 195'F l

limit is not exceeded.

If a loss-of-coolant accident were to occur when the reactor water temperature is below 330*F, containment pressure will not exceed the 62 psig maximum pressure even if no condensation were to occur. The maximum allowable pressure suppression chamber water temperature, whenever the reactor is above 212*F, shall be governed by this specification. Thus specifying combinations of water volume and temperature requirements applicable for reactor-water temperatures above 212'F provides additional margin above that available at 330'F.

Should it be necessary to drain the presiure suppression chamber, this should only be done when there is no requirement for core standby cooling systems operability, as explained in basis 3.5.G.

2.

Prfmary Containment Integrity Discussed under Bases for Specification 3.7.A.,

Primary Containment.

3.

Reactor Buildinq to Pressure Suppression Chamber Vacuum Relief System The purpose of the reactor building to pressure suppression chamber vacuum relief system is to equalize pressure so that the structural integrity of the containment is assured.

The vacuum relief system from the reactor building to the pressure suppression chamber consists of two 100-percent vacuum relief lines, each of which has an air operated valve and a vacuum breaker (check valve) in series. Operation of either line will maintain the pressure differential less than 2 psid, the external design pressure. Reference Section 5.2.3.6.2 of the FSAR.

HATCH - UNIT 1 3.7-30 Proposed TS/0206q/103-0

i EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 SUPPRESSION CHAMBER LIMITING CONDITION FOR OPERATION 3.5.4 The suppression chamber shall be OPERABLE with a minimum water level of 12 ft 2 in., and the water level instrumentation channels alarms l

adjusted to actuate at a low water level 2 12 ft 2 in., except that the suppression chamber may be drained:

a.

In OPERATIONAL CONDITION 4, provided that; 1.

No work is performed which has a potential for draining the reactor vessel, 4

2.

The reactor mode switch is locked in the Shutdown position, and 3.

The core spray system is OPERABLE per Specification 3.5.3.1 with an OPERABLE flow path capable of taking suction from the OPERABLE condensate storage tank and transferring the water through the spray sparger to the reactor vessel.

b.

In OPERATIONAL CONDITION 5, provided that the reactor mode switch is locked in the Refuel position, and:

1.

The core spray system is OPERABLE per Specification 3.5.3.1 with an OPERABLE flow path capable of taking suction from the OPERABLE condensate storage tank and transferring the water through the spray sparger to the reactor vessel, or 2.

The reactor vessel head is removed and the cavity is flooded, the spent fuel pool gates are removed, and the water level is maintained within the limits of Specifica-tions 3.9.9 and 3.9.10 APPLICABILITY:

CONDITION 1, 2 3, 4 and 5.

ACTION:

a.

In CONDITION 1, 2 or 3 with the suppression chamber water level less than the above limit, restore the water level to within the limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

j b.

In CONDITION 4 or 5 with the suppression chamber drained j

and the conditions of Specification 3.5.4.a or 3.5.4.b, as l

applicable, not satisfied, suspend all operations in the reactor vessel and all positive reactivity changes.

The i

provisions of Specification 3.0.3 are not applicable.

i' l

11 HATCH - UNIT 2 3/4 5-9 Proposed TS/0213q/12F 35 l

'l

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i CONTAINMENT SYSTEMS 3/4 6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER LIMITING CONDITION-FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with the pool water:

a.

Maintained at a level between 12 ft 2 in. and 12 ft 6 in., and a l

b.

Maximum temperature of 110 F during OPERATIONAL CONDITION 1 or l

2, except that the maximum temperature may be permitted to increase to 120*F with the main steam line isolation valves closed following a scram from OPERATIONAL CONDITION 1 or 2.

c.

Level instrumentation channels alarms adjusted to actuate at:

1.

High water level of 5 12 ft 6 in.

2.

Low water level of 2 12 ft 2 in.

APPLICABILITY:

CONDITIONS 1, 2 and 3.

ACTION:

t a.

With the suppression chamber water volume outside the above limits, restore the volume to within the limits within I hour or be in at least 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 /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

In OPERATIONAL CONDITION 1 or 2 with the suppression chamber water temperature 2 100 F, initiate suppression pool cooling.

t i

l I

1 1

b i

HATCH - UNIT 2 3/4 6-11 Proposed TS/0204q/127-0

m CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) c.

In OPERATIONAL CONDITION 1 or 2 with THERMAL POWER > 1 percent l

of RATED THERMAL POWER and the suppression chamber water temper-ature > 110 F, place the reactor mode switch in th Shutdown 1

position.

d.

With the suppression chamber water temperature >.120 F and the l

i main steam isolation valves closed following a scram from OPERATIONAL CONDITION 1 or 2, depressurize the reactor pressure vessel to < 200 psig at normal cooldown rates.

e.

With one suppression chamber water level instrumentation channel l

inoperable, restore the inoperable channel to OPERABLE status within 30 days or be in at least 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

f.

With both suppression chamber water level instrumentation l

channels inoperable, restore at least one inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least 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 /> and in COLD SHUT 00WN within the follow-ing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

8 SURVEILLANCE REQUIREMENTS 4.6.2.1 The suppression chamber shall be demonstrated OPERABLE:

a.

By verifying the suppression chamber water volume to be between 12'2" and 12'6" at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in OPERATIONAL CONDITION 1 or 2 by verifying the suppression chamber water temperature to be s 105 F.

l At least once per 5 minutes in OPERATIONAL CONDITION 1 or 2 c.

during testing which adds heat to the suppression chamber, by verifying the suppression chamber water temperature < 110 F.

l d.

At least once per 60 minutes when THERMAL POWER > 1 percent of RATED THERMAL POWER and suppression chamber water temperature

> 105*F, by verifying suppression chamber water temperature

< 110'F.

l HATCH - UNIT 2 3/4 6-12 Proposed TS/0204q/103-0

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

At least once per 30 minutes following a scram from OPERATIONAL CONDITION 1 or 2 with the main steam line isolation valves closed, and suppression chamber water temperature > 110 F, by l

verifying suppression chamber water temperature < 120 F.

f.

By an external visual examination of the suppression chamber after there has been indication of safety / relief valve opera-tion with the suppression chamber water temperature 2: 160*F and reactor coolant system pressure > 200 psig.

g.

At least once per 18 months by a visual inspection of the accessible interior and exterior of the suppression chamber.

h.

By verifying two suppression chamber water level instrumenta-tion channels (2T48-R607A,B) OPERABLE by performance of a:

1.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.

CHANNEL CALIBRATION at least once per 6 months.

I HATCH - UNIT 2 3/4 6-13 Proposed TS/0204q/103-0

CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION SYSTEMS The specifications of this section ensure that the primary containment pressure will not exceed the maximum allowable internal pressure of 62 psig during primary system blowdown from full operating pressure.

The suppression chamber water provides the heat sink for the reactor coolant system energy release following a postulated rupture of the system.

The suppression chamber water volume must absorb the associated decay and structural sensible heat released during reactor coolant system blowdown from 1040 psig.

Since all of the gases in the drywell are purged into the suppression chamber air space during a loss-of-coolant accident, the pressure of the liquid must not c4ceed 62 psig, the suppression chamber maximum pressure.

The design volume of the suppression chamber, water and air, was obtained by considering that the total volume of reactor ccolant to be condensed is discharged to the suppression chamber and that the drywell volume is purged to the suppression chamber.

Using the minimum or maximum water levels given in the specification, l

containment pressure during the design basis accident is approximately 57.5 psig which is below the maximum allowable internal pressure of 62 psig.

Maximum water level results in a downcomer submergence of 4 ft 4 in and the minimum water level results in a submergence approximately 4 in. less.

The Mark I Full Scale Test Facility tests were performed at several submergence levels which bound this variance, all with complete condensation.

Thus, with respect to the downcomer submergence, this specification is adequate.

The maximum pool temperature based on the consideration of complete condensation has been determined by evaluating the blowdown test data from the Mark I Full Scale Test Facility.

Based on these analyses, a pool temperature of 195 F can provide complete steam condensation (conser-vatively assumes no pressurization of the air space over the pool).

Analyses for Plant Hatch have shown that with an initial pool temperature of 110 F, the pool temperature following a blowdown will be below that j

needed for complete condensation.

For an initial suppression pool temperature of 110 F and assuming that one loop of the RHR system is available for containment cooling (2 RHR and 2 RHR service water pumps), adequate net positive suction head (NPSH) is maintained for the core spray, RHR, and HPCI pumps.

When it is necessary to make the suppression chamber inoperable, this shall only be done as provided in Specification 3.5.4.

l HATCH - UNIT 2 B 3/4 6-3 Proposed TS/0205q/127-0 1

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