Text

Proposed Tech Specs Revising Surveillance Intervals to Facilitate Change in Refueling Cycles from 18 to 24 Months
	ML20070N562
Person / Time
Site:	Limerick
Issue date:	04/29/1994
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20070N544	List: ML20070N542; ML20070N562;
References
	NUDOCS 9405090011
	Download: ML20070N562 (16)
	v • d • e

. .

1 ATTACHMENT 1 UMERICK GENERATING STATION UNITS 1 AND 2 J

DOCKET NO.

50452 50453 LICENSE NO.

NPF-39 NPF-85 REVISED TECHNICAL SPECIFICATIONS PAGES SUPPORTING TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 92-03-0 THE FOLLOWING PAGES ARE CONTAINED WITHIN 5 LGS Unit 1 LGS Unit 2 TS Paaes TS Paaes 3/41-5 3/41-5 3/4 1-20 3/4120 3/4342 3/4 3-42 3/4390 3/4 3-90 2/4 3-112 3/43112 3/447 3/447 3/4614 3/4 6-14 ;

ei l

1 l

l 9405090011 940429 PDR ADOCK 05000352 p PDR

4 COMMONWEALTH OF PENNSYLVANIA :

ss.

COUNTY OF CHESTER :

W. H. Smith, Ill, being first duly sworn, deposes and says:

That he is Vice President of PECO Energy Company, the Applicant herein; that he has read the revised information for Technical Specifications Change Request No. 92-03-0 to facilitate a change in the Limerick Generating Station, Unit 1 and Unit 2, License Nos. NPF-39 and NPF-85, refueling cycles from 18 months to 24 months , and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

,, . i:- /

v'

/

Vice President Subscribed and sworn to before me thish ay of 1994.

.s VLNew % - L ' N!

~

//

Notary Public Natanalseal Tre n MyConmsson ExpresJJy 995

. =.

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.1.3'l.4

. The scram discharge volume shall be determined OPERABLE by -

demonstrating:

a. The' scram discharge volume drain and vent v:lves OPERABLE, when control rods are scram tested from a normal control rod configura-tion of less than or equal to 50% R00 DENSITY at least once per 24 months, by verifying that the drain and vent valves:

1. Close within 30 seconds after receipt of a signal for control l rods to scram, and

2. Open when the scram signal is reset.

b. Proper level sensor response by performance of a CHANNEL FUNCTIONAL TEST of the scram discharge volume scram and control rod block level instrumentation at least once per 92 days.

LIMERICK - UNIT 1 3/4 1-5

l REACTIVITY CONTROL SYSTEMS l

SURVEILLANCE RE0VIREMENTS (Continued) I

b. At least once per 31 days by: _

l

1. Verifying the continuity of the explosive charge, j

2. Determining b chemical analysis and calculation

that the available wei ht of sodium pentaborate is greater than or equal ;

he concentration of sodium pentaborate in !

to 3754 lbs;less solution is than or equal to 13.8% and within the limits ;

of Figure 3.1.5-1 and; the following equation is satisfied:

C E O 13% wt.

29 atom %

86 gpm 21 where C - Sodium pentaborate solution (% by weight)

Q = Two pump flowrate, as determined per surveillance requirement 4.1.5.c.

E - Boron 10 enrichment (atom % Baron 10)

3. Verifying that each valve (manual, power-operated, or automatic) ,

in the flow path that is not locked, sealed, or otherwise secured i in position, is in its correct position.

l

c. Demonstrating that, when tested pursuant to Specification 4.0.5, the minimum flow requirement of 41.2 gpm per pump at a pressure of greater than or equal to 1190 psig is met. ,

1

d. At least once per 24 months during shutdown by:

i 1. Initiating at least one of the standby liquid control system l loops, including an explosive valve, and verifying that a flow l l

path from the pumps to the reactor pressure vessel is available i by pumping demineralized water into the reactor vessel. The !

replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of the batch success-fully fired. All injection loops shall be tested in 3 operating !

cycles. l l 2. Verify all heat-traced piping between storage tank and pump suction is unblocked.**

e. Prior to addition of Baron to storage tank verify sodium pentaborate enrichment to be added is 2 29 atom % Boron 10.

oThis test shall also be performed anytime water or boron is added to the solu-tion or when the solution temperature drops below the limits of Figure 3.1.5-1 for the most recent concentration analysis, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or boron i addition or solution temperature is restored.

i MThis test shall also be performed whenever suction piping temperature drops below l the limits of Figure 3.1.5-1 for the most recent concentration analysis, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored.

LIMERICK - UNIT 1 3/4 1-20 t

. INSTRUMENTATION i

i 3/4$3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION 4

ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4.1 The anticipated transient without scram recirculation pump trip 3

(ATWS-RPT) system instrumentation channels shown in Table 3.3.4.1-1 shall be e OPERABLE with their trip setpoints set consistent with values shown in the Trip 4

Setpoint column of Table 3.3.4.1-2.

f APPLICABILITY: OPERATIONAL CONDITION 1.

! ACTION:

a. With an ATWS recirculation pump trip system instrumentation channel 4

trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.4.1-2, declare the channel inoperable until j the channel is restored to OPERABLE status with the channel trip

setpoint adjusted consistent with the Trip Setpoint value.

i b. With the number of OPERABLE channels one less than required by the

Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped

' condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , i c. With the number of OPERABLE channels two or more less than required i by the Minimum OPERABLE Channels per Trip System requirement for one

] trip system and:

1. If the inoperable channels consist of one reactor vessel water level channel and one reactor vessel pressure channel, place both inoperable channels in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or, if this action will initiate a pump trip, declare the trip system inoperable.

I 2. If the inoperable channels include two y essel water level channels or two reactor vessel pressure , declare the

} trip system inoperable.

j d. With one trip system inoperable, restore the inoperable trip system

to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP .tithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

4 j e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within I hour or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.3.4.1.1.Each ATWS recirculation pump trip system instrumentation channel

shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL 4

FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies-shown in

! Table 4.3.4.1-1.

4.3.4.7 1 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of

all channels shall be performed at least once per 24 months.

LIMERICK - UNIT 1 3/4 3-42

]

JNSTRUMENTATION CHL RINE DETECTION SYSTEM

. l LIMITING CONDITION FOR OPERATION -

3.3.7.8.1 Two independent chlorine detection system subsystems shall be i OPERABLE with their alarm and trip setpoints adjusted to actuate at a I chlorine concentration of less than or equal to 0.5 ppm APPLICABILITY: All 0?ERATIONAL CONDITIONS. l ACTION:

a. With one chlorine detection subsystem inoperable, restore the inoperable detection system to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of at least l one control room emergency filtration system subsystem in the chlorine isolation mode of operation.

b. With both chlorine detection subsystems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of at least one control room emer-gency filtration system subsystem in the chlorine isolation mode of operation. l l

SURVEILLANCE RE0VIREMENTS 4.3.7.8.1 Each of the above required chlorine detection system subsystems shall l be demonstrated OPERABLE by performance of a: I

a. CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

b. CHANNEL FUNCTIONAL TEST at least once per 92 days, and i

c. CHANNEL CALIBRATION at least once per 24 months. '

1 1

l LIMERICK - UNIT 1 3/4 3-90

INSTRUMENTATION 3/4'3.9

. FEE 0 WATER / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION l l

LIMITING LCNDITION FOR OPERATION l

3.3.9 The feedwater/ main turbine trip system actuation instrumentation channels shown in the Table 3.3.9-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.9-2. ,

l APPLICABILITY: As shown in Table 3.3.9-1.

ACTION:

a. With a feedwater/ main turbine trip system actuation instrumentation j channel trip setpoint less conservative than the value shown in the l Allowable Values column of Table 3.3.9-2, declare the channel inoper- ,

able and either place the inoperable channel in the tripped condition I until the chanael is restored to OPERABLE status with its trip set- i point adjusted consistent with the Trip Setpoint value, or declare !

the associated system inoperable,

b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, restore the inoperable channel l to OPERABLE status within 7 days or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels requirement, restore at least one of the !

inoperable channels to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0VIREMENTS 4.3.9.1 Each feedwater/ main turbine trip system actuation instrumentation channel shall be demonstrated OPERABLE

by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.9.I-1.

4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 24 months.

o A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance without placing the trip system in the tripped condition.

LIMERICK - UNIT 1 3/4 3-112

BEAQTOR C0OLANT SYSTEM 3/4.4.2 SAFETY / RELIEF VALVES LTMITING' CONDITION FOR OPERATION 3.4.2 The safety valve function of at least 11 of the following reactor coolant system safety / relief valves shall be OPERABLE with the specWied code safety valve function lift settings:*#

4 safety / relief valves 01130 psig 1%

5 safety / relief valves 01140 psig 1%

5 safety / relief valves 01150 psig 1%

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With the safety valve function of one or more of the above required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than 105'F, close the stuck open safety / relief valve (s); if unable to close the stuck open valve (s) within 2 minutes or if suppression pool average water temperature is 110*F or greater, place the reactor mode switch in the Shutdown position.

c. With one or more safety / relief valve acoustic monitors inoperable, restore the inoperable acoustic monitors to OPERABLE status within 7 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 SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE0VIREMENTS 4.4.2.1 The acoustic monitor for each safety / relief valve shall be demonstrated OPERABLE eith the setpoint verified to be 0.20 of the full open noise leve1## by performance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 92 days, and a

b. CHANNEL CALIBRATION at least once per 24 months **.

4.4.2.2 At least 1/2 of the safety relief valves shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 24 months, and

they shall be rotated such that all 14 safety relief valves are removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested e d stored in accordance with manufacturer's recommendations at least once per 54 months.

o The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

The provisions of Specification 4.0.4 are not applicable provided the Surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure is adequate to perform the test.

0 Up to 2 inoperable valves may be replaced with spare OPERABLE valves with lower setpoints until the next refueling.

1. Initial setting shall be in accordance with the manufacturer's recommendation. Adjustment to the valve full open noise level shall be accomplished during the startup test program. !

LIMERICK - UNIT 1 3/4 4-7

. CONTAINMENT SYSTEMS SUR EILLANCE REQUIREMENT,S (Continued)

c. By verifying at least 8 suppression pool water temperature indicators in at least 8 locations, 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 per 31 days, and

3. CHANNEL CALIBRATION at least once per 24 months, with the temperature alarm setpoint for:

l 1. High water temperature:

a) First setpoint 5 95'F b) Second setpoint s 105'F c) Third setpoint s 110*F )

i 1 l d) Fourth setpoint s 120*F l l

l

d. By verifying at least two suppression chamber water level indicators !

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 , j

2. CHANNEL FUNCTIONAL TEST at least once per 92 days, and

3. CHANNEL CALIBRATION at least once per 18 months, with the water level alarm setpoint for high water level s 24'l-1/2"'

e. Drywell-to-suppression chamber bypass leak tests shall be conducted at 40 +/- 10 month intervals to coincide with the ILRT at an initial differential pressure of 4 psi and verifying that t.he A/(k calculated from the measured leakage is within the specified limit. If any drywell-to-suppression chamber bypass leak test fails to meet the specified limit, the test schedule for subsequent tests shall be reviewed and approved by the Commission. If two consecutive tests fail to meet the specified limit, a test shall be performed at least every 24 months until two consecutive tests meet the specified limit, at which time the test schedule may be resumed.

f. By conducting a leakage test on the drywell-to-suppression chamber vacuum breakers at a differential pressure of at least 4.0 psi and verifying that the total leakage area A/(k contributed by all vacuum breakers is less than or equal to 24% of the specified limit and the leakage area for an individual set of vacuum breakers is less than or equal to 12% of the specified limit. The vacuum breaker leakage test shall be conducted during each refueling outage for which the drywell-to-suppression chamber bypass leak test in Specification 4.6.2.1.d is not conducted.

LlMERICK - UNIT 1 3/4 6-14

- - = - - _ - = __. . _ - - - - - - . _ _ - . - _ _ _ _ -_- _ _ _ _ _ _ _ _

. REACTIVITY CONTROL SYSTEMS 1 .

j SVRVEILLANCE RE0VIREMENTS (Continued) i -

! 4.1.3'.1.4 The scram discharge volume shall be determined OPERABLE by ,

j demonstrating: ;

i

! a. The' scram discharge volume drain and vent valves OPERABLE, when

! control rods are scram tested from a normal control rod configura- ,

1 tion of less than or equal to 50% R0D DENSITY at least once per '

l 24 months, by verifying that the drain and vent valves:

i

1. Close within 30 seconds after receipt of a signal for control l l rods to scram, and j

! 2. Open when the scram signal is reset. j

b. Proper level sensor response by performance of a CHANNEL FUNCTIONAL ;

e TEST of the scram discharge volume scram and control rod block level i

, instrumentation at least once per 92 days. )

i e

l l

i 1

I ,

1 1

I i

LIMERICK - UNIT 2 3/4 1-5

REACT 1VIT.Y CONTROL' SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. 'At least once per 31 days by: -

1. Verifying the continuity of the explosive charge.

2. Determining by chemical analysis and calculation

that the available weight of sodium pentaborate in greater than or equal

to 5389 lbs; the concentration of sodium pentaborate in solution is less than or equal to 13.8% and within the limits of Figure 3.1.5-1 and; the following equation is satisfied

a C x 0 21 13% wt. 86 gpm where C - Sodium pentaborate solution (% by weight)

Q - Two pump flowrate, as determined per surveillance requirement 4.1.5.c.

3. Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position,

c. Demonstrating that, when tested pursuant to Specification 4.0.5, the minimum flow requirement of 41.2 gpm per pump at a pressure of greater than or equal to 1190 psig is met.

d. At least once per 24 months during shutdown by:

1. Initiating at least one of the standby liquid control system loops, including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is availabls by pumping demineralized water into the reactor vessel. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of the batch success-fully fired. All injection loops shall be tested in 3 operating cycles.

2. Verify all heat-treated piping between storage tank and pump suction is unblocked.**

oThis test shall also be performed anytime water or boron is added to the solu-tion or when the solution temperature drops below 70*F, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or boron addition or solution temperature is restored.

J MThis test shall also be perforn:ed whenever suction piping temperature drops below 70*F, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored.

LIMERICK - UNIT 2 3/4 1-20 i

_ , . , , ,,_ , , , ,_,,-,.,,.,,..,,g,,.w.wm..,,.,g.y, , m y .w ,,, , .cw y% w. m p

l i

I INSTRUMENTATION 3/4.3.4 RECIRCVLATION PUMP TRIP ACTUATION INSTRUMENTATION l l

ATWS RECIRCOLATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION J l

3.3.4.1 The anticipated transient without scram recirculation pum) tri) l (ATWS-RPT) system instrumentation channels shown in Table 3.3.4.1-1 s1all 3e OPERABLE with their trip setpoints set consistent with values shown in the Trip ,

Setpoint column of Table 3.3.4.1-2. l l

APPLICABILITY: OPERATIONAL CONDITION 1.

ACTION:

a. With an ATWS recirculation pump trip system instrumentation channel !

trip setpoint less conservative than the value shown in the Allowable l Values column of Table 3.3.4.1-2, declare the channel inoperable until l the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value. l

b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels 3er Trip System requirement for one or both trip systems, place tie inoperable channel (s) in the tripped l condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l

c. With the number of OPERABLE channels two or more less than required i by the Minimum OPERABLE Channels per Trip System requiremenc for one l trip system and:

1. If the inoperable channels consist of one reactor vessel water level channel and one reactor vessel pressure channel, alace both inoperable channels in the tripped condition within 241ours, or, if this action will initiate a pump trip, declare the trip system inoperable. .

2. If the inoperable channels include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip system inoperable.

d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0VIREMENTS 4.3.4.1.1 Each ATWS recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operatioqs at the frequencies shown in Table 4.3.4.1-1.

4.3.4.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 24 months.

LIMERICK - UNIT 2 3/4 3-42

INSTRUMENTATION CHLORINE DETECTION SYSTEM LIMITING C0$DITION FOR OPERATION 3.3.7.8.1 Two independent chlorine detection system subsystems shall be OPERABLE with their alarm and trip setpoints adjusted to actuate at a chlorine concentration of less than or equal to 0.5 ppm APPLICABILITY: All 0PERATIONAL CONDITIONS.

ACTION:

a. With one chlorine detection subsystem inoperable, restore the inoperable detection system to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of at least one control room emergency filtration system subsystem in the chlorine isolation mode of operation.

b. With both chlorine detection subsystems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of at least one control room emer-gency filtration system subsystem in the chlorine isolation mode of operation.

SURVEILLANCE REQUIREMENTS __

4.3.7.8.1 Each of the above required chlorine detection system subsystems shall be demonstrated OPERABLE by performance of a:

a. CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

b. CHANNEL FUNCTIONAL TEST at least once per 92 days, and

c. CHANNEL CALIBRATION at least once per 24 months.

LIMERICK - UNIT 2 3/4 3-90

INSTRUMENTATION 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION I 3.3.9 The feedwater/ main turbine trip system actuation instrumentation channels shown in the Table 3.3.9-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.9-2.

APPLICABILITY: As shown in Table 3.3.9-1.

ACTION:

a. With a feedwater/ main turbine trip system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9-2, declare the channel inoper-able and either place the inoperable channel in the tripped condition until the channel is restored to OPERABLE status with its trip set-

, point adjusted consistent with the Trip Setpoint value, or declare the associated system inoperable.

l b. With the number of OPERABLE channels one less than required by the l Minimum OPERABLE Channels requirement, restore the inoperable channel

to OPERABLE status within 7 days or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1

c. With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels requirement, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at ,

least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . I 1

SURVEILLANCE REQUIREMENTS 4.3.9.1 Each feedwater/ main turbine trip system actuation instrumentation chhnnel shall be demonstrated OPERABLE

by the performance of the CHANNEL CHECK, CHANNEL i 1

FUNCTIONAL TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.9.1-1.

4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 24 months.

l l

l 0 A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required l surveillance without placing the trip system in the tripped condition.

LIMERICK - UNIT 2 3/4 3-112 r

REACTOR COOLANT SYSTEM I

374.4.2 SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION _

3.4.2 The safety valve function of at least 11 of the following reactor coolant system !

safety / relief valves shall be OPERABLE with the specified code safety valve function lift settings:*#

4 safety relief valves 0 1130 ps g 1%

5 safety relief valves 01140 ps g 1%

5 safety relief valves 01150 ps g 1%

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With the safety valve function of one or more of the above required i safety / relief valves inoperable, be in at least H0T SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than 105'F, close the stuck open safety / relief valve ; if unable to close the stuck open valve (s within 2 minutes or if suppre(s) ss ion pool average water temperature is 110*F)or greater, place the reactor mode switch in the Shutdown position.

With one or more safety / relief valve acoustic monitors inoperable, restore the c.

inoperable acoustic monitors to OPERABLE status within 7 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 following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

, SURVEILLANCE RE0VIREMENTS 4.4.2.1 The acoustic monitor for each safety / relief valve shall be demonstrated OPERABLE with the setpoint verified to be 0.20 of the full open noise level ## by performance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 92 days, and a CHANNEL CALIBRATION at least once per 24 months **.

d b.

i 4.4.2.2 At least 1/2 of the safety relief valves shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 24 months, and they shall be rotated such that all 14 safety relief valves are removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 54 months.

o The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

o* The provisions of Specification 4.0.4 are not applicable provided the Surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure is adequate to perform the test.

4

Up to 2 inoperable valves may be replaced with spare OPERABLE valves with

, lower setpoints until the next refueling.

1. Initial setting shall be in accordance with the mar 9facturer's recommendation. Adjustment to the valve full open noise level shall be accomplished during the startup test program.

4 LIMERICK - UNIT 2 3/4 4-7

. - - -. - - - - - - . . - . ~

l

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

c. By verifying at least 8 suppression pool water temperature indicators in at least 8 locations, 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 per 31 days, and

3. CHANNEL CALIBRATION at least once per 24 months, l with the temperature alarm setpoint for:

1. High water temperature:

a) First setpoint s 95'F b) Second setpoint s 105'F c) Third setpoint s 110*F d) Fourth setpoint s 120*F j

d. By verifying at least two suppression chamber water level indicators )

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 , j 1

2. CHANNEL FUNCTIONAL TEST at least once per 92 days, and

3. CHANNEL CALIBRATION at least once per 18 months, with the water level alarm setpoint for high water level s 24'l-1/2"

e. Drywell-to-suppression chamber bypass leak tests shall be conducted at 40 +/- 10 month intervals to coincide with the ILRT at an initial differential pressure of 4 psi and verifying that the A//k calculated from the measured leakage is within the specified limit. If any drywell-to-suppression chamber bypass leak test fails to meet the specified limit, the test schedule for subsequent tests shall be reviewed and approved by the Commission. If two consecutive tests fail to meet the specified limit, a test shall be performed at least every 24 months until two consecutive tests meet the specified limit, at which time the test schedule may be resumed.

f. By conducting a leakage test on the drywell-to-suppression chamber vacuum breakers at a differential pressure of at least 4.0 psi and verifying that the total leakage area A//k contributed by all vacuum breakers is less than or equal to 24% of the specified limit and the leakage area for an individual set of vacuum breakers is less than or equal to 12% of the specified limit. The vacuum breaker leakage test shall be conducted during each refueling outage for which the drywell-to-suppression chamber bypass leak test in Specification 4.6.2.1.d is not conducted.

LIMERICK - UNIT 2 3/4 6-14

ML20070N562

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