Text

Proposed Tech Specs,Revising Suppression Pool Temp Limit
	ML20154D557
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Site:	Hatch
Issue date:	09/06/1988
From:	; GEORGIA POWER CO.
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ML20154D553	List: ML20154D550; ML20154D557;
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' Georgia Power d ENCLOSURE 3 PLANT HATCH - UNITS 1, 2 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

SUPPRESSION POOL TEMoERATURE LIMIT PAGE CHANGE INSTRUCTIONS The proposed changes to the Plant Hatch Units 1 and 2 Technical Specifications (Appendix A to Operating Licenses OPR-57 and NPF-5) will be incorporated as follows:

Remove Page Insert Pagg UNIT 1:

3.7-1 3.7-1 3.7-la 3.7-la 3.7-30 3.7-30 UNIT 2: 3/4 6-11 3/4 6-11 3/4 6-12 3/4 6-12 3/4 6-13 3/4 6-13 0 3/4 6-3 B 3/4 6-3 PkE 2107C E3-1 9/06/P.8 HL-31

__ LIMITING CONEl.TIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.

C.ONTAINMENT SYSTEMS 4.7.

CONTAINMENT SYSTEMS toolicability Applicability The Limiting Conditions for Operation The Surveillance Requirements associated with containmen' avstems associated with containment systems apply to the operating stacus of the apply to the pr; mary and secondary orimary 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 verif y the integrity of the primary and secondary containrent of the primary and secondary contain-systems.

ment.

Soecifications goecifications A.

Primary Containment A.

Primary Containment 1.

Pressure SuDDression Chambe,r, 1.

Pressure Suporession Chamber At any time that irradiated a.

The pressure uppressiun chambtr 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 recorde( 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 abcte the level 1 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 1,vels once per operating cycle.

not to exceed 5 Hwt.

In addition, the external surfaces of the pressuie a.

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

be v:sually inspected on a routine basis for evidence b.

Maximum water level - 12 feet, of corro.ston or leakage.

6 inches, c.

Whenever there is indicat;on c.

During norral power operation, that a significant amount of the suppression chamter sater heat is being added to the temperature shall be maintained pressure suppression pool, the 5 100'c.

If this temperature pool temperature shall be con-limit is exceeded, 0o:1 cooling tinually monitored and also shall be initiated immediately, observed and logged every 5 minutes until the heat addition if the water temperature cannot is terminated.

be restored to $ 100'F within l

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor shall be shut down using nornal shutdown procedures.

HATCH - UNIT 1 3.7-1 Prv;;ted T5/02430/224-16 l

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIREMENTS d.

During relief valve operation or d.

Whenever there is testing of RCIC, HPCI, or other indication that there testing which add 3 heat to the was relief valve operation

'uppression pool, the maximum

. with the temperature of

'ter temperature shall not

' the suppression pool exceed 105'F.

In conntetton exceeding 160'F and the with such testing, the pool reactor primary coolant temperature must be reduced system pressure greater t

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to $ 100'F.

l than 200 psig, an ex-ternal visual examination e.

The reactor shall be scrammed of the pressure suppres-from any operating condition sion chamber shall be when the suppression pool conducted before resuming temperature reaches 110'F.

power operation.

Ope *

tion sh611 not be re-Sun : until the pool te rsrature is reduced to i

bei u the normal power oe s. ration limit specified iii c. above, f.

During reactor isolation conditions the reactor pressure vessel shall be depressurized to < 200 psig at normal cooldowq rates if the pool temperature reaches'120'F.

i I

i HATCH - UNIT 1 3.7-14 Proposed T5/0243q/224-16 i

BASES FOR LIMITING' CONDITIONS FOR 09ERATION 3.7 A.I.

Pressure Sucorc? tion Chamber (Continued)

The maximum pool temperature based on the consideration of complete condensa-tion 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 (conservatively assumes no pressurization of the a.r 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 needed for complete condensation. Therefore, the 100'F limit on operating pool temperature is justified.

For an initial suppression poc1 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. Therefore, the 100'F limit on oper-ating pool temperature is justified.

Limiting prassure suppression chamber water temperature to 120'F during RCIC, l

HPCI or relief valve operation when decay heat and stored energy are removed f rom the primary system by dischargirig reactor steam directly to the sup-a 1

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 < 120'F, the 195'F limit is not exceeded.

If a loss-of '.oolant 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 Je necessary to drain the pressure suppression Chamber, this should only be done when there is no requirement fo* core standby cooling systems operability, as explained in basis 3.5.G.

2.

Primary Containment Intearity i

Discussed under Bases for Specification 3.7.A.. Primary Containment.

3.

Reactor Build _ina to Pressure SuDDression Chamber Vacuum Relief System The purpose of the reactor building to pressure suppression chamber vacuum relief system is to equalize pressure to 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 pressuro dif ferential less than 2 psid, the external design pressure. Reference Section 5.2.3.6.2 of the FSAR.

l HATCH - UNIT 1 3.7-30 Proposed TS/0243q/2244/224-0 I

i

i l

CONTAINMENT SYSTEMS i

3/4 6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER f

LIMITING CONDITION FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with the pool water:

a.

Volume between 87,300 ft*, and 90,550 ft*, equivalent to a level between 12 ft 2 in, and 12 ft 6 in., and a b.

Maximum temperat' ire of 100*F during OPERATIONAL CONDITION 1 or l

2, except that the maximum temperature may be permitted to 4

increase to:

i.

105'F during testing which adds heat to the suppression chamber during OPERATIONAL CONDITION 1 or 2, 2.

120'F with the main steam line isolation valves closed following a scram from OPERATIONAL CONDITION 1 or 2.

l c.

Level instrumentation channels alarms adjusted to actuate at:

)

1.

High water level of s 12 ft 6 in.

l 2

2.

Low water level of 2 12 ft 2 in.

APPLICABILITY:

CONDITIONS 1, 2 and 3.

i ACTION:

a.

With the suppression chamber water volume outside the above l

4 limits, restore the volume to within the limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In OPERATIONAL CONDITION 1 or 2 witt, the suppression chamber i

water temperature > 100'F, except as permitted above, initiate suppression pool cooling and restore the temperature to s 100*F i

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2 c.

In OPERATIONAL CONDITION 1 or 2 with the suppression chamber l

water temperature > 105'F during testing which adds heat to the suppression chamber, stop all testing, initiate suppres-sion pool cooling and restore the temperature to s 100'F within l

{

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

)

and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i HATCH - UNIT 2 3/4 6-11 Proposed TS/0244q/224-0 j

I

QN'C'.MENTSYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued) d.

In OPERATIONAL CONDITION 1 or 2 with THERMAL POWCR > 1 percent of RATED THERMAL POWER and the suppression chamber water temperature

> 110*F, place the reactor mode switch in the Shutdown position.

e.

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

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.

f.

With one suppression chan.ber water level instrumentation channel 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the 'ollowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

g.

With both suppression chamber water level instrumentation channels inoperable, restore at least one inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the follow-ing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.2.1 The suppression chamber shall be demonstrated OPERABLE:

j a.

By verifying the suppression chamber water volume to be between 12 ft 2 in, anu 12 ft 6 in at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in OPERATIONAL CONDITION 1 or 2 by verifying the suppression chamber water temperature to be 5 100'F.

j c.

At least once per 5 minutes in OPERATIONAL CONDITION 1 or 2 during testing which adds heat to the suppression chamber, by verifying the suppression chamber water temperature s 105'F.

d.

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

> 100*F, by verifying suppression chamber water temperature l

< 110*F.

t I

HATCH - UNIT 2 3/4 6-12 Proposed TS/0244q/224-0 i

3 -

CON" *dNMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Co-tinued) 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 > 100 F, by l

verifying suppression chamber water temperature < 120'F, f.

By an external visual examination of the suppressica chcmber after there has been indication of safety / relief valve opera-tion with the suppression chamber water temper,ture 2 160 F and reactor ceolant system pressure > 200 psig, g.

At least once per 18 months by a visual' inspection of the accessible interior and extr.rior 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 2.

CHANNEL FUNCTIONAL TEST at least once p

31 days, and 3.

CHANNEL CALIBRATION at least once per 6 months.

4 i

i i

1 i

l l

l 2

1

}

1 j

i HATCH - UNIT 2 3/4 6-13 Proposed TS/0244q/224-0 i

CONTAINMENT SYSTEMS BASES 3/4.6.2 _DEPRES3URIZATION SYSTEMS The specifications of this section ensure that the primary containment pressure will not exceed the marimum 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 blowduwn from 1040 psig.

Since all of the gases in the drywell are purged into the suppression chamber air space during a LOCA, the pressure of the liquid must not exceed 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 coolant 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, 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.gecification 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 i

temperature of 195*F can provide complete steam condensation (conser-vatively assumes no pressurization of the air space ever 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 needed for complete condensation.

Therefore, the 100*F limit on operating pool temperature is justified.

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 l

maintained for the core spray, RHR, and HPCI pumps.

Therefore, the 100*F limit on operating pool temperature is justifiec'.

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

HATCH - UNIT 2 B 3/4 6-3 Proposed TS/0245q/224-0 1

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ML20154D557

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