ML20006B706

Proposed Tech Specs,Clarifying Revised Method of Suppression Pool Average Temp Determination

ML20006B706
Person / Time
Site:	Hatch
Issue date:	01/26/1990
From:	GEORGIA POWER CO.
To:
Shared Package
ML20006B705	List: ML20006B704 ML20006B706
References
NUDOCS 9002050274
Download: ML20006B706 (9)

Text

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ENCLOSVRE 3-PLANT HATCH - UNITS 1, 2 -

NRC DOCKETS-50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 ,

REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

SUPPRESSION POOL TEMPERATURE MONITORING

_ PAGE CHANGE INSTRUCTIONS 2

UNIT 1 Remove Paae Insert Paae 3.7-1 3.7 .

3.7-la 3.7-la.

3.7-28 3.7-28 r

- 3.7-29 3.7-29 UNIT 2 Remove Paae Insert Paae 3/4 6-11 3/4 6-11 3/4 6-12 3/4 6-12 3/4 6-13 3/4 6-13 ,

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P 000115 i HL-911 E3-1 L 9002050274 900126' ~ '

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h LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIkEMENTS 3.7. CONTAINMENT SYSTEMS- ,

4.7. CONTAINMENT SYSTEMS ADDlicability Applicability s The Limiting Conditions for Opera- The Surveillance Requirements tion associated with containment associated with containment systems '

systems apply to the operating apply to the primary and secondary "

t status of the primary and secondary containment integrity. *

' containment systems.

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

Specifications .;

SDecifications A. Primary Containment A. Primary Containment

1. Pressure SuDDression Chamber-

1. Pressure SuDDression Chamber

a. The pressure suppression At any time that irradiated chamh r water level, average l ,

fuel is in the reactor vessel, water temperature and air.

and the nuclear system is temperature shall be measured pressurized above atmospheric and recorded daily. The pressure or work is being done average suppression chamber which has the potential to water temperature shall be drain the vessel, the pressure determined using a weighted L suppression chamber water level average of the suppression L and average water temperature l pool temperature sensors, as I shall be maintained within the described in Bases paragraph l- following limits except while 3.7.A.I.

performing' low-power physics tests at atmospheric pressure ,

at power levels not to exceed b. The interior painted surfaces -

5 Nt. above the level 1 foot below L the normal water line of the

a. Minimum water level - pressure suppression chamber l 12 feet, 2 inches. shall be visually inspected I once per operating cycle.

I b. -Maximum water level - In addition, the external L 12 feet, 6 inches. surfaces of the pressure

! suppression chamber shell l- c. During normal power opera- be visually inspected on a L tion, the average suppression l routine basis for evidence chamber water temperature of corrosion or leakage.

L i shall be maintained 5 100'F.

If this temperature limit .c. Whenever there is indication is exceeoed, pool cooling that a significant amount of 1: shall be initiated heat is being added to the immediately, pressure suppression pool, l

I the pool temperature shall  !

l Iftheaveragewatertempera-l be continually monitored ture cannot be restored to and also observed and logged l 5 100*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the every 5 minutes until the l- reactor shall be shut down heat addition is terminated.

using normal shutdown l

procedures.

L l NATrH - HNIT 1 3. 7 -1 ProDosed TS/03400/016-165 1

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

.d. During' relief ~ valve operation or d .' Whenever there is testing of RCIC.'HPCI, or other indication that there testing which adds heat to the was relief valve operation suppression pool, the maximum with the average tempera- l average water temperature shall ture of the suppression

, not exceed 105*F. In connection l pool exceeding 160'F and with such testing, the average - l' the reactor primary cool-pool temperature must be reduced ant system pressure. greater.

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 5100'F. than 200 psig, an external visual examination of the

e. The reactor shall be scrammed pressure suppression .

from any operating conditlec chamber shall be conducted-

- when the average suppression l before resuming power pool temperature reaches 110*F. ~ operation.-

Operation shall not be re-suned until the pool temperature is reduced to below the nornal power operation limit specified in c. above.

f. During reactor isolation conditions the reactor pressure vessel shall be 3 depressurized to < 200 psig 1 at ruonmal cooldown rates ~

if the average pool-tempera- l ture reaches 120*F.

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l HATCH - UNIT 1 3.7-la Proposed TS/0340q/016-165 l

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BASES FOR LIMINhn~ CONDITIONS FOR OPERATION 3.7 CONTAINMENT SYSTEMS A.. Primary Containment-The integrity.of the primary containment and operation of the emergency core cooling systems in combination, limit the off-site doses to values less than those suggested in 10 CFR 100 in the event of a-break in the primary system piping. Thus, containment integrity is specified whenever the potential for violation of the primary reactor system

-integrity exists. Concern about such a violation exists whenever the

' reactor is critical and above atmospheric pressure. An exception is made to this requirement during initial core-loading and while the -

initial startup test program is being conducted. There will be no pressure on the sy'. tem at this time, which greatly reduces the changes of a pipe break. The reactor may be taken critical during this period; however, restrictive operating procedures will be in effect to minimize the probability of an accident occurring. Procedures for rod withdrawal and patterns programmed into the Rod Worth Minimizer and Rod Sequence Control System would limit control rod worth to less than 1.25% ak.

A drop of such a rod does not result in any fuel damage. In addition in the unlikely event that an excursinn did occur, the secondary contain-ment (reactor building) and standby gas treatment system, which shall be operational during this time, of fers a suf ficient barrier to keep of f-site doses well below 10 CFR 100 limits.

1. ' Pressure Suporession Chamber l

The pressure suppression chamber water provides the heat sink-for the reactor primary system energy release following a postulated rupture of the_ system. _ The pressure suppression chamber water volume must j absorb the associated decay and structural sensible heat released

during primary system blowdowns. l 1

Since all of the non-condensable gases in the drywell are purged into  !

the pressure suppression chamber air space during a loss-of-coolant 1 accident, the pressure resulting from isothermal compressure plus the $

vapor pressure of the liquid must not exceed 62 psig, the maxi.num f pressure. The design volume of the pressure suppression chamber (water j and air) was obtained by considering that the total volume of reactor  ;

coolant to be condensed is discharged to the suppression chamber and 1 that the drywell volume is purged to the suppression chamber. Reference j FSAR Section 5.2.3.

Using the minimum or maximum water levels given in the specification, containment W Aure during the design basis accident is less than 59 psig which is tulow the maximum pressure of 62 psig. The minimu:n i water level of 12 f t 2 in. corresponds to a water volume of 87,300 ft* and a downcomer submergence of 3 ft 8-1/2 in. The maximum water level of 12 f t 6 in. corresnonds to a water volume of 90,380 fts. The .orresponding downcomer submergence .

is 4 ft 1/2 in. Since the majority of the Bodega tests l

(Reference 1) were run with a submergence of 4 ft and with complete d condensation, this specification is adequate with respect to downcomer i submergence.  !

HATCH - UNIT 1 3.7-20 Proposed TS/0340q/016-0

BASES FOR LIMITING CONDITIONS FOR OPERATION i

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3.7.A.I. Pressure SuDDression Chamber (Continued)

Experimental data indicate that excessive steam condensing loads can be avoided if the peak temperature of the pressure suppression pool is-maintained below 160*F during any period of relief valve operation with sonic conditions at the discharge exit. Specifications have been placed ,

on the envelope of reactor operating conditions so that the reactor can.  ;

be depressurized in a timely manner to avoid the regime of potentially If high pressure suppression chamber loadings. "

In addition to the limits on temperature of the suppression chamber pool ,

~ water, operating proceosiis define that action to be taken in the event a relief valve inadvertetitly opens or sticks open. As a minimum this ,

action shall include: (1) use of all available means to close the valve,

-(2) initiate suppression pool water cooling heat exchangers, (3) initiate reactor shutdown, and (4) if other relief valves are used to depressurize the reactor, their discharge shall be separated from that of the stuck-open relief valve to assure mixing and uniformity of energy insertion to the pool. .

Because of the large volume and thermal capacity of the suppression pool, the volume and temperature normally changes very slowly and monitoring these Larameters daily is sufficient to establish iny temperature trends.

By re4diring the suppression pool temperature to be continually monitored and frequently logged during periods of significant heat addition, the temoerature trends will be closely followed so that appropriate action can be taken. The requirement for an external visual examination following any event where potentially high loadings could occur provides-assurance that no significant damage was encountered. Particular attention should be focu>ad on structural discontinuities in the vicinity of the relief valve dischsrge since these are expected to be the points of highest stress.

The average (or bulk) suppression pool teraperature limits specified in paragraphs 3.7.A.1 and 4.7.A.1 are normally monitored using a weighted

. average of 15 temperature sensors. Four sensors, T48+N009A through N0090, are located in the lower half of the suppression pool and 11 4

sensors, T48-N301 through N311, are located in the upper half of the suppression pool. The 4 lower sensors are averaged and the 11 upper ,

sensors are averaged. The bulk suppression pool temperature is the average of the upper and lower average temperature. Should ona or more of these sensors he determined inoperable when the suppression chamber is required, a preplanned alternate method of determining as average temperature may be used. One alternate method is to average the operable sensors, as long as at least one upper temperature element in each quadrant of the suppression pool is operable. In this case, the operable N009 elements would be combined to yield an average lower pool temperature and the operable N300 elements would provide an average upper pool temperature. If each quadrant does not have at least one operable N300 element, a second alternate method is to take the average of operable T48-N009A through N009D instruments and add 5'F. (The 5'F adder is not necessary during normal operation if at least one RHR pump is operating in the suppression pool cooling mode and neither HPCI, RCIC, or SRVs are in operation.)

HATCH - UNIT 1 3.7-29 Proposed TS/03404/016-16 v

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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. 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 average temperature of 100 F during OPERATIONAL CONDITION 1 or 2, except that the maximum average temperature may be permitted to increase to:

1. 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.

c. Level instrumentation channels alarms adjusted to actuate at:

1. High water level of s 12 ft 6 in.

2. Low water level of 2 12 ft 2 in.

APPLICABILITY: CONDITIONS 1, 2 and 3.

ACTION:

a. With the suppression chamber water volume outside the above limits, restore the volume to within'the limits 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 rfext 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 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 average suppression l chamber water temperature > 100 F, except as permitted above, initiate suppression pool cooling and restore the temperature.to s 100 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUT 00WN 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 SHU100WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. In OPERATIONAL CONDITION 1 or 2 with the average suppression chamber water temperature > 105 F during testing which adds heat l to the suppression chamber, stop all testing, initiate suppres-sion pool cooling, and restore the temperature to s 100 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUT 00WN 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 />.

HATCH - UNIT 2 3/4 6-11 Proposed TS/03390/016-102 L a. _ _ . - _ _ _ _

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. CONTAINMENT SYSTEMS-LIMITING CONDITION FOR OPERATION (Continued) {

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ACTION: (Continued)

d. In OPERATIONAL CONDITION 1 or 2 with THER:1AL POWER > 1 percent of '

RATED THERMAL POWER a'nd the average suppression chamber water l

. temperature > 110 F, place the reactor mode switch in the.

Shutdown position,

e. With the average suppression chamber water temperature > 120.F l and the main steam isolation valves closed following a scram from OPERATIONAL CONDITION 1 cr 2, depressurize the reactor pressure vessel to < 200 psig at normal cooldown rates, With one suppression chamber water level instrumentation channel

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inoperable, restore the inoperable channel to OPERABLF rtatus 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 />.

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 <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 SHUTDOWN within the follow-ing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 ft 2 in, and 12 ft 6 in. 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 average

• suppression chamber water temperature to be l s 100 F.

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 average

• suppression chamber water temperature s 105 F.

d. At least once per 60 minutes when THERMAL POWER > 1 percent t of RATED THERMAL POWER and average

• suppression chamber water temperature > 100 F, by verifying average

• suppression chamber water temperature < 110 F.

• The average suppression chamber water temperature shall be determined using a weighted average of the suppression pool temperature sensors, as described in BASES subsection 3/4.6.2.

HATCH - UNIT 2 3/4 6-12 Prnon wri Ts/n m q/n16-102 l n

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• 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 4 closed,~and average

• suppression chamber water temperature

> 100 F, by verifying average

• suppression chamber. water

/c temperature < 120 F. '

f. By an external: visual examination of the suppression' chamber after there has been indicatioli of safety / relief valve opera-tion with'the average

• suppression chamber water temperature l 1 2 160 F and reactor coolant system pressure > 200 psig,

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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' hours,

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

3. CHANNEL CALIBRATION at least once per 6 months.

T i

• The average suppression water temperature shall be determined using a weighted average of the suppression pool temperature sensors, as described in BASES subsection 3/4.6.2.

HATCH - UNIT 2 3/4 6-13 Proposed TS/0339q/016-102 s <

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. y CONTAINMENT SYSTEMS 4

BASES ,

by DEPRESSURIZATIONSYSTEMS(Continuedj.

C Emperime; u data indicates that excessive steam condensing loads can be avoided it t. peak temperature of the suppression pool is maintained below 160*F during any period of relief valve operation with sonic conditions at the discharge exit. Specifications have been placed on the envelope of reactor operating conditions so that the r1 actor can be ,

depressurized in a timely manner to avoid the regime of potentially high a suppression chamber loadings.

Because of the large volume and thermal capacity of the suppression pool, the volume and temperature normally changes very slowly and monitoring these parameters daily is suf ficient to establish any- temperature trends.

By requiring the suppression pool temperature to be frequently legged during periods of significant heat addition, the temperature trends will be closely followed so that appropriate action can be taken. The require-ment for en external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered. Particular attention should be focused on structural discontinuities in the vicinity of the relief valve discharge since

• these are expected to be the points of highest stress, in addition to the limits on temperature of the suppression chamber pool water, operating procedures define the action to be taken in the event a safety / relief valve inadvertently opens or sticks open. As a minimum, this action shall include: (1) use of all'available means to close the valve, (2) initiate suppression pool water cooling, (3) initiate reactor shutdown, and (4) if other safety / relief valves are used to depres-surize the reactor, their discharge shall be separated from that of the

' stuck-open safety / relief valve to assure mixing and uniformity of energy insertion to the pool.

The average (or bulk) suppression pool temperature limits specified in-paragraphs 3.6.2.1 and 4.6.2.1 are normally monitored usir.g a weighted average of 15 temperature sensors. Four sensors, 2T48-N009A through N0090, are located in the lower half of the suppression pool and 11 sensors, 2T48-N301 through N311, ~are located in the upper half of the suppression pool-. The 4 lower sensors are averaged and the 11 upper sensors are averaged. The bulk suppression pool temperature is the average of the upper and lower average temperature. Should one or more of these sensors be determined inoperable

-while in Conditions 1, 2, or 3, a preplanned alternate method of determining average temperature may be used. One alternate method is to average the operable sensors, as long as at least one upper temperature element in each' quadrant of the suppression pool is operable, in this case, the operable-N009 elements would be combined to yield an average lower pool temperature and the operable N300 elements would provide an average upper pool temperature.

If each quadraint does not have at least one operable N300 element, a sccond alternate method is to take tne average of operable 2f48-N009A through N0090 instruments and add 5'F. (The s*F adder is not necessary during normal operation if at least one RHR pump is operating in the suppression pool cooling mode and neither HPCI, RCIC, or SRVs are in operation.)

3/4.0.3 ' PRIMARY CONTAINMENT ISOLATION VALVES fhe OPERABILITY of the primary containtvnt isolation valves ensures that the primary containment atensphere will be isolated from the outside environment in the event of a release of radioactive material to the primary containment atmosphere or pressurization of the containment.

Primary containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consist-ent with the assumptions used in the analyses for a LOCA. Only one closed valve in each penetration line is required to maintain the integrity of the containment.

ilATCH - UNIT 2 0 3/4 6-4 Droposed TS/0336q/016-0

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