ML20069K028

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Revised TS Pages Supporting TS Change Request 92-03-0
ML20069K028
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 06/09/1994
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20069K026 List:
References
NUDOCS 9406150219
Download: ML20069K028 (21)
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ATTACHMENT 1 LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS.

50-352 50-353 LICENSE NOS.

NPF-39 NPF-85 REVISED TECHNICAL SPECIFICATIONS PAGES SUPPORTING TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 92-03-0 THE FOLLOWING PAGES ARE CONTAINED WITHIN LGS UNIT 1 LGS UNIT 2 TS PAGES TS PAGES 3/43-1 3/43-1 3/4 6-14 3/4 6-14 3/4 6-18 3/4 6-18 3/4 6-56 3/4 6-56 3/47-4 3/47-4 3/47-6 3/4 7-6a 2/48-3 3/48-3 B 3/4 6-5 3/48-4 83/48-2 3/48-5 83/46-5 i B 3/4 8-2 I

l 9406150219 940609 PDR ADOCK 05000352 i P PDR l j

k 3/4.3 INSTRUMENTATION 3/4.3.I REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

a. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition
  • within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The provisions of Specification 3.0.4 are not applicable.
b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system 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 4.3.1.1-1.

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

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 24 months. Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 24 months where N is the total number of redundant channels in a specific reactor trip system.

  • An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel  ;

shall be restored 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 the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.

    • The trip system need not be.placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip ,

(ystem with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.

LIMERICK - UNIT 1 3/4 3-1 i

_ 4 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 <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 24 months, 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

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
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 5 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 vacnum 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 J 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 1 3/4 6-14

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.3.1 Each primary containment isolation valve shown in Table 3.6.3-1 shall be demonstrated OPERABLE prior to returning the valve to service after mainte-nance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.

4.6.3.2 Each primary containment automatic isolation valve shown in Table 3.6.3-1 shall be demonstrated OPERABLE at least once per 24 months by verifying that on a containment isolation test signal each automatic isolation valve actuates to its isclation position.

4.6.3.3 The isolation time of each primary containment power operated or automatic valve shown in 7able 3.6.3-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 Each reactor instrumentation line excess flow check valve shown in l Table 3.6.3-1 shall be demonstrated OPERABLE at least once per 24 months by l Verifying that the valve checks flow.

4.6.3.5 Each traversing in-core probe system explosive isolation valve shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying the continuity of the explosive charge.
b. At least once per 24 months by removing the explosive squib from the explosive valve, such that each explosive squib in each explosive valve will be tested at least once per 120 months, and initiating the j explosive squib. The replacement charge for the exploded squib shall be from the same manufactured batch as the one fired or from another ,

batch which has been certified by having at least one of that batch successfully fired. No squib shall remain in use beyond the expiration of its shelf-life and/or operating ' life, as applicable.

LIMERICK - UNIT 1 3/4 6-18  ;

I

)

CONTAINMENT SYSTEMS o

SURVEILLAN[EREQUIREMENTS(Continued) ,

c. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of. a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%. I
d. At least once per 24 months by:
1. Verifying that the pressure drop across the combined prefilter,  ;

upstream and downstream HEPA filters, and charcoal adsorber i banks is less than 6 inches water gauge while operating the filter train at a flow rate of 60,000 cfm 10%, verifying that the prefilter pressure drop is less than 0.8 inch water gauge and that the pressure drop across each HEPA is less than 2 inches water gauge.

2. Verifyird that the filter train starts and the isolation valves which ake suction on and return to the reactor enclosure open on each of the following test signals: ,
a. Manual initiation from the control room, and  ;
b. Simulated automatic initiation signal.
e. After each complete or partial replacement of a HEPA filter bank by '

verifying that the HEPA filter bank satisfies the inplace penetration and leakage testing acceptance criteria of less than 0.05% in '

accordance with ANSI N510-1980 while operating the system at a flow i rate of 60,000 cfm i 10%.  !

f. After each complete or partial replacement of a ' charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the .

inplace penetration and leakage testing acceptance criteria of less  !

than 0.05% in accordance with ANSI N510-1980 for a halogenated hydro- ,

carbon refrigerant test gas while operating the system at a flow '

rate of 60,000 'cfm 10%.

h

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d l

LIMERICK - UNIT 1 3/4 6-56 l

ELANT SYSTEMS .

' LIMYTING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

4. With three ESW pump / diesel generator pairs ** inoperable, .

restore at least one inoperable ESW pump / diesel generator . .  :

pair ** to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 />.

5. With four ESW pump / diesel generator pairs ** inoperable, restore at least one inoperable ESW pump / diesel generator pair ** to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 i 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 4 or 5: I
1. With only one emergency service water pump and its associated .

. flowpath OPERABLE, restore at least two pumps with at least one i flow path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the associated safety related equipment inoperable and take the ACTION required by Specifications 3.5.2 and 3.8.1.2.

c. In OPERATIONAL CONDITION *
1. With only one emergency service water pump and its associated i flow path OPERABLE, restore at least two pumps with at least  !

one flow path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or verify adequate cooling remains available for the diesel generators ,

required to be OPERABLE or declare the associated diesel generator (s) inoperable and take the ACTION required by Specification 3.8.1.2. The provisions oi 3pecification 3.0.3  ;

are not applicable. 1 SURVEILLANCE RE0VIREMENT  ;

4.7.1.2 At least the above required emergency service water system loop (s) shall be demonstrated OPERABLE

a. At least once per 31 days by verifying that each valve (manual, power- .

operated, or automatic) that is not locked, sealed, or otherwise secured in position, is in its correct position. i

b. At least once per 24 months by verifying that:

- 1. Each automatic . valve actuates to its correct position = on its  !

appropriate ESW pump start signal. r

2. Each pump starts automatically when its associated diesel f generator starts.  !
  • When handling irradiated fuel in the secon dary con ti a nment .  :
    • An ESW pump / diesel generator. pair consists of an ESW pump and its

- associated diesel generator. If either an ESW pump or its associated diesel  !

generator becomes inoperable, then the ESW pump / diesel generator pair is  !

inoperable.

LIMERICK - UNIT 1 3/4 7-4 l

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T

PLANT SVSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM - COMMON SYSTEM LIblTINGCONDITIONFOROPERATION >

3.7.2 Two independent control room emergency fresh air supply system subsystems shall be OPERABLE. i All OPERATIONAL CONDITIONS and *. i APPLICABILITY:

ACTION: i i

a. In OPERATIONAL CONDITION I, 2, or 3 with one control room emergency fresh air supply subsystem inoperable, restore the inoperable  :

subsystem to OPERABLE status within 7 days or be in at least HOT l 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 />,

b. In OPERATIONAL CONDITION 4, 5, or *:
1. With one control room emergency fresh air supply subsystems  ;

inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE  :

subsystem in the radiation isolation mode of operation. j

2. With both control room emergency fresh air supply subsystems i inoperable, suspend CORE ALTERATIONS, handling of irradiated -

fuel in the secondary containment and operations with a .

potential for draining the reactor vessel. l,

c. The provisions of Specification 3.0.3 are not applicable in i OPERATIONAL CONDITION *.  ;

5 SURVEILLANCE REQUIREMENTS  ;

4.7.2 Each control room emergency fresh air supply subsystem shall be demonstrated OPERABLE: ,

I

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the control room air tempera-  !

ture to be less than or equal to 85 F effective temperature.

b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers .j and verifying that the subsystem operates with the heaters OPERABLE. l 1
c. At least once per 24** months or (1) after any structural maintenance l I on the HEPA filter or charcoal adsorber housings, or (2) following l

. painting, fire, or chemical release in any ventilation zone -  !

communicating with the subsystem by:

1. Verifying that the subsystem satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions l C.5.a, C.S.c, and C.S.d of Regulatory Guide 1.52,. Revision 2,  !

/ March 1978, and the system flow rate is 3000 cfm 10%.  !

I

    • Surveillance interval is an exception to the guidance provided in  ;

Regulatory Guide 1.52, Revision 2, March 1978.  ;

I LIMERICK - UNIT 1 3/4 7-6

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  • w m , 3 r vv7 v ==-

ELECTRICAL POWER SYSTEMS 1

)

SURVEILLANCE RE0VIREMENTS 1 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be:  ;

a. Determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability, and
b. Demonstrated OPERABLE at least once per 24 months by _

transferring, manually and automatically, unit power supply from the l normal circuit to the alternate circuit. l 4.8.1.1.2 Each of the above required diesel generators shall be demonstrated l OPERABLE

  • t
a. In accordance with the frequency specified in Table 4.8.1.1.2-1 on a  !

STAGGERED TEST BASIS by:

1. Verifying the fuel level in the day fuel tank. l
2. Verifying the fuel level in the fuel storage tank.
3. Verifying the fuel transfer pump starts and transfers fuel from 1 the storage system to the day fuel tank.
4. Verify that the diesel can start
  • and gradually accelerate to  :

synchronous speed with generator voltage and frequency at j 4285 420 volts and 60 1.2 HZ.

5. Verify diesel is synchronized, gradually loaded
  • to an indicated 2700-2803 KW** and operates with this load for at l

(

1 east 60 minutes.

6. Verifying the diesel generator is aligned to provide standby )

power to the associated emergency busses. i t

7. Verifying the pressure in all diesel generator air start j receivers to be greater than or equal to 225 psig.  :

i This test shall be conducted in accordance with the manufacturer's 1

recommendations regarding engine pre-lube and warmup procedures, and as applicable regarding loading and shutdown recommendations. .

    • This band-is meant as guidance to avoid routine overloading of the engine. l Loads in excess of this band for special testing under direct monitoring by-  !

the manufacturer or momentary variations due to changing bus loads shall not' t invalidate the test. l i

l l

I i

e LIMERICK - UNIT 1 3/4 8-3

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3 y w r. y y- . .---- - . -. -. -- . _________- - - _--------

CONTAINMENT SYSTEMS BASES 3/4.6.5 SECONDARY CONTAINMENT Secondary containment is designed to minimize any ground level release of radioactive material which may result from an accident. The Reactor Enclosure and associated structures provide secondary containment during normal operation when the drywell is sealed and in service. At other times the drywell may be open and, when required, secondary containment integrity is specified.

Establishing and maintaining a vacuum in the reactor enclosure secondary containment with the standby gas treatment system once per 24 months, along with the surveillance of the doors, hatches, dampers and valves, is adequate to ensure that there are no violations of the integrity of the secondary containment.

The OPERABILITY of the reactor enclosure recirculation system and the standby gas treatment systems ensures that sufficient iodine removal capability will be available in the event of a LOCA or refueling accident (SGTS only). The reduction in containment iodine inventory reduces the resulting SITE B0UNDARY radiation doses associated with containment leakage. The operation of this system and resultant iodine removal capacity are consistent with the assumptions used in the LOCA and refueling accident analyses. Provisions have been made to continuously purge the filter plenums with instrument air when the filters are not in use to prevent buildup of moisture on the adsorbers and the HEPA filters.

Although the safety analyses assumes that the reactor enclosure secondary containment draw down time will take 135 seconds, these surveillance require-ments specify a draw down time of 121 seconds. This 14 second difference is due to the diesel generator starting and sequence loading delays which is not part of this surveillance requirement.

The reactor enclosure secondary containment draw down time analyses assumes a starting point of 0.25 inch of vacuum water gauge and worst case SGTS dirty filter flow rate of 2800 cfm. The surveillance requirements satisfy this as-sumption by starting the drawdown from ambient conditions and connecting the adjacent reactor enclosure and refueling area to the SGTS to split the exhaust flow between the three zones and verifying a minimum flow rate of 2800 cfm from the test zone. This simulates the worst case flow alignment and verifies ade-quate flow is available to drawdown the test zone within the required time.

The Technical Specification Surveillance Requirement 4.6.5.3.b.3 is intended to be a multi-zone air balance verification without isolating any test zone.

The SGTS fans are sized for three zones and therefore, when aligned to a single zone or two zones, will have excess capacity to more quickly drawdown the affected zones. There is no maximum flow limit to individual zones or pairs of zones and the air balance and drawdown time are verified when all three zones are connected to the SGTS.

The three zone air balance verification and drawdown test will be done after any major system alteration, which is any modification which will have an effect on the SGTS flowrate such that the ability of the SGTS to drawdown thyreactor enclosure to greater than or equal to 0.25 inch of vacuum water gage in less than or equal to 121 seconds could be affected.

l LIMERICK - UNIT 1 8 3/4 6-5 l

l

4 ELECTRICRL POWER SYSTEMS BASE 3 A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION SYSTEMS (Continued)

" Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977 except for paragraphs C.2.a(3), C.2.c(1), C.2.c(2), C.2.d(3) and C.2.d(4), and the periedic testing will be performed at least once per 24 months. The exceptions to Regulatory Guide 1.108 allow for gradual loading of diesel generators during testing and decreased surveillance test frequencies (in response to Generic Letter 84-15).

The surveillance requirements for demonstrating the OPERABILITY of the unit batteries are in accordance with the recommendations of Regulatory Guide 1.129 " Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978 and IEEE Std 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations," except the test will be performed at least once every 24 months.

Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates and compares the battery capacity at that time with the rated capacity.

Table 4.8.2.11 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity. The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity. The normal limits for each connected cell for float voltage and specific gravity, greater than 2.13 volts and not more than 0.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery.

Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8.2.1-1 is permitted for up to 7 days. During this 7-day period: (1) the allowable value for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below the manufacturer's recommended full charge specific gravity ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity, ensures that an individual cell's specific gravity will not be more than 0.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capa-bility to perform its design function.

LIMERlii - UNIT 1 B 3/4 8-2

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

a. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition
  • within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The provisions of Specification 3.0.4 are not applicable.
b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within I hour and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system 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 4.3.1.1-1.

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

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 24 months. Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 24 months where N is the total number of redundant channels in a specific reactor trip system.

  • An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be. restored 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 the ACTION required bv Table 3.3.1-1 for that Trip Function shall be taken.
    • The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system jnthetrippedcondition.

LIMERICK - UNIT 2 3/4 3-1

CONTAINMENT SYSTEMS SURVEILLANCE RE0UIREMENTS (Continued)

c. 3y 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 <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 24 months, 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 IIO F d) Fourth setpoint s 120*F I

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
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 l 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 t 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 Jhe 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

CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS 4.6.3.1 Each primary containment isolation valve shown in Table 3.6.3-1 shall be demonstrated OPERABLE prior to returning the valve to service after mainte-nance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.

4.6.3.2 Each primary containment automatic isolation valve shown in Table 3.6.3-1 shall be demonstrated OPERABLE at least once per 24 months by verifying that on a containment isolation test signal each automatic isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each primary containment power operated or automatic valve shown in Table 3.6.3-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 Each instrumentation line excess flow check valve shown in Table 3.6.3-1 shall be demonstrated OPERABLE at least once per 24 months by verifying that the l valve checks flow.

4.6.3.5 Each traversing in-core probe system explosive isolation valve shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying the continuity of the explosive charge.
b. At least once per 24 months by removing the explosive squib from the explosive valve, such that each explosive squib in each explosive valve will be tested at least once per 120 months, and initiating the explosive squib. The replacement charge for the exploded squib shall be from the same manufactured batch as the one fired or from another batch which has been certified by having at least one of that batch successfully fired. No squib shall remain in use beyond the expiration of its shelf-life and/or operating life, as applicable.

LIMER[CK-UNIT 2 3/4 6-18

CONTAfNMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

c. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%.
d. At least once per 24 months by:
1. Verifying that the pressure drop across the combined prefilter, upstream and downstream HEPA filters, and charcoal adsorber banks is less than 6 inches water gauge while operating the filter train at a flow rate of 60,000 cfm 10%, verifying that the prefilter pressure drop is less than 0.8 inch water gauge and that the pressure drop across each HEPA is less than 2 inches water gauge.
2. Verifying that the filter train starts and the isolation valves which take suction on and return to the reactor enclosure open on each of the following test signals:
a. Manual initiation from the control room, and
b. Simulated automatic initiation signal.
e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetration and leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 while operating the system at a flow rate of 60,000 cfm 10%.
f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a halogenated hydro-carbon refrigerant test gas while operating the system at a flow rate of 60,000 cfm 10%.

LIMERICK - UNIT 2 3/4 6-56

PLANT SYSTEMS LIMITING' CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

4. With three ESW pump / diesel generator pairs ** inoperable, restore at least one inoperable ESW pump / diesel generator pair ** to OPE'ABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN with.n 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 />.
5. With four ESW pump / diesel generator pairs ** inoperable, restore at least one inoperable ESW pump / diesel generator pair ** to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 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 4 or 5:
1. With only one emergency service water pump and its associated flow path OPERABLE, restore at least two pumps with at least one flow path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the associated safety related equipment inoperable and take the ACTION required by Specifications 3.5.2 and 3.8.1.2.
c. In OPERATIONAL CONDITION *
1. With only one emergency service water pump and its associated flow path OPERABLE, restore at least two pumps with at least one flow path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or verify adequate cooling remains available for the diesel generators required to be OPERABLE or declare the associated diesel genera-tor (s) inoperable and take the ACTION required by Specifica-tion 3.8.1.2. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENT 4.7.1.2 At least the above required emergency service water system loop (s) shall be demonstrated OPERABLE: j

a. At least once per 31 days by verifying -that each valve (manual, power-operated, or automatic) that is not locked, sealed, or otherwise secured in position, is in its correct position.
b. At least once per 24 months by ver e.,ing thau
1. Each automatic valve actuates to its correct position on its appropriate ESW pump start signal. i
2. Each pump starts automatically when its associated diesel generator starts.
    • ' An ESW pump / diesel generator pair consists of an ESW pump and its associated ,

- diesel generator. If either an ESW pump or its associated diesel generator  !

becomes inoperable, then the ESW pump / diesel generator pair is inoperable.

l LIMERICK - UNIT 2 3/4 7-4 l l

. . j PLANT SYSTEMS j l

i SURVEILLANCE REQUIREMENTS 4.7.2 Each control room emergency fresh air supply subsystem shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the control room air tempera-ture to be less than or equal to 85 F effective temperature.
b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates with the heaters OPERABLE.
c. At least once per 24* months or (1) af ter any structural maintenance l on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the subsystem by:
1. Verifying that the subsystem satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.S.a, C.S.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 3000 cfm 10%.

E

  • Surveillance interval is an exception to the guidance provided in Regulatory Guide 1.52, Revision 2, March 1978.

LIMERICK - UNIT 2 3/4 7-6a  :

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ELECTRICAL POWER SYSTEMS {

SURVEILLANCE REQUIREMENTS  :

4.8.1.1.1 Each of the above required independent circuits between the offsite  !

transmission network and the onsite Class IE distribution system shall be: ,

a. Determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability, and  ;
b. Demonstrated OPERABLE at least once per 24 months by transferring, manually and automatically, unit power supply from the 3 normal circuit to the alternate circuit.

4.8.1.1.2 Each of the above required diesel generators shall be demonstrated OPERABLE:

a. In accordance with the frequency specified in Table 4.8.1.1.2-1 on a STAGGERED TEST BASIS by:
1. Verifying the fuel level in the day fuel tank. -
2. Verifying the fuel level in the fuel storage tank.
3. Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day fuel tank.
4. Verify that the diesel can start
  • and gradually accelerate .to synchronous speed with generator voltage and frequency at  ;

4285 420 volts and 60 1.2 Hz.  !

5. Verify diesel is synchronized, gradually loaded
  • to an indicated 2700-2800 kW** and operates with this load for at least 60 minutes.
6. Verifying the diesel generator is aligned to provide standby i power to the associated emergency busses.
7. Verifying the pressure in all diesel generator air start receivers to be greater than or equal to 225 psig.

I i

i

  • This test shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup procedures, and as

. applicable regarding loading and shutdown recommendations.

    • This band is meant as guidance to avoid routine overloading of the engine. l

/ Loads in excess of this band for special testing under direct monitoring by _ ,

the manufacturer or momentary variations due to changing bus loads shall not invalidate the test. ,

LIMERICK - UNIT 2. 3/4 8-3  !

. ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i

b. By removing accumulated water:
1) From the day tank at least once per 31 days and after each occa-sion when the diesel is operated for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and
2) From the storage tank at least once per 31 days.
c. By sampling new fuel oil in accordance with ASTM D4057-81 prior to addition to the storage tanks and:
1) By verifying in accordance with the tests specified in ASTM 0975-81 prior to addition to the storage tanks that the sample has:

a) An API Gravity of within 0.3 degrees at 60*F or a specific gravity of within 0.0016 at 60/60*F, when compared to the supplier's certificate or an absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or equal to 0.89 or an API gravity at 60*F of greater than or equal to 27 degrees but less than or equal to 39 degrees.

b) A kinematic viscosity at 40*C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, ,

if gravity was not determined by comparison with the supplier's certification.

c) A flash point equal to or greater than 125'F, and d) A clear and bright appearance with proper color when tested in accordance with ASTM D4176-82.

2) By verifying within 31 days of obtaining the sample that the other properties specified in Table 1 of ASTM D975-81 are met when tested in accordance with ASTM 0975-81 except that the analysis for sulfur may be performed in accordance with ASTM D1552-79 or ASTM D2622-82.
d. At least once every 31 days by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D2276-78, and verifying that total particulate contamination is less than 10 mg/ liter when -

checked in accordance with ASTM D2276-78, Method A, except that the filters specified in ASTM D2276-78, Sections 5.1.6 and 5.1.7, may have a nominal pore size of up to three (3) microns.

e. At the following frequency by:
1. Every 18 months subjecting the diesel to an inspection in accordance .

with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

2. Every 24 months verifying the diesel generator capability to reject a load of greater than or equal to that of the RHR Pump Motor (992

/ kW) for each diesel generator while maintaining voltage at 4285

, 420 volts and frequency at 60 1.2 Hz.

i LIMERICK - UNIT 2 3/4 8-4

. . ELECTRICAL POWER SYSTEMS ,

. SURVEILLANCE RE0UIREMENTS (Continued)

3. Every 24 months verifying the diesel generator capability to reject a load of 2850 kW without tripping. The generator voltage shall not exceed 4784 volts during and following the load rejection.
4. Every 24 months simulating a loss-of-offsite power by itself, and:l a) Verifying deenergization of the emergency buses and load shedding from the emergency buses, b) Verifying the diesel generator starts
  • on the auto-start signal, energizes the emergency buses within 10 seconds, >

energizes the auto-connected loads through the individual load timers and operates for greater than or equal to 5 minutes while its generator is loaded with the. shutdown loads. After energization, the steady-state voltage and frequency of the ,

emergency buses shall be maintained at 4285 420 volts' and 60 1.2 Hz during this test.

5. Every 24 months verifying that on an ECCS actuation test signal, without loss-of-offsite power, the diesel generator starts
  • on the  :

auto-start signal and operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall reach i 4285 i 420 volts and 60 1.2 Hz within 10 seconds after the auto-start signal; the steady state generator voltage and frequency shall be maintained within these limits during this-test. ,

6. Every 24 months simulating a loss-of-offsite power in conjunction with an ECCS actuation test signal, and:

a) Verifying deenergization of the emergency buses and load  :

shedding from the emergency buses.

b) Verifying the diesel generator starts

  • on the auto-start signal, energizes the emergency buses within 10 seconds,. .

energizes the auto-connected shutdown loads through the individual load timers and operates for greater than or equal to 5 minutes while its generator is loaded-with the emergency loads. After energization, the steady-state voltage and frequency of the emergency buses shall be maintained at 4285 420 volts and 60 1.2 Hz during this test.

7. Every 24 months verifying that all automatic diesel generator trips, .

except engine overspeed and generator differential over-current are .

automatically bypassed upon an ECCS actuation signal.

  • This test shall be conducted in accordance with the manufacturer's recommendations regarding-engine prelube and warm up procedures, and as

, applicable regarding loading and shutdown recommendations.

.LItiERICK - UNIT 2 3/4 8-5 1

]

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CONTAINMENT SYSTEMS ,

BASES 3/4.6.5 SECONDARY CONTAINMENT Secondary containment is designed to minimize any ground level release of '

radioactive material which may result from an accident. The Reactor Enclosure and associated structures provide secondary containment during normal operation >

when the drywell is sealed and in service. At other times the drywell may be ,

open and, when required, secondary containment integrity is specified.

Establishing and maintaining a vacuum in the reactor enclosure secondary containment with the standby gas treatment system once per 24 months, along with l the surveillance of the doors, hatches, dampers and valves, is adequate to ensure that there are no violations of the integrity of the secondary containment.

The OPERABILITY of the reactor enclosure recirculation system and the standby gas treatment systems ensures that sufficient iodine removal capability will be available in the event of a LOCA or refueling accident (SGTS only). The

  • reduction in containment iodine inventory reduces the resulting SITE BOUNDARY radiation doses associated with containment leakage. The operation of this system and resultant iodine removal capacity are consistent with the assumptions used in the LOCA and refueling accident analyses. Provisions have been made to continuously purge the filter plenums with instrument air when the filters are not in use to prevent buildup of moisture on the adsorbers and the HEPA filters.

Although the safety analyses assumes that the reactor enclosure secondary containment draw down time will take 135 seconds, these surveillance require-ments specify a draw down time of 121 seconds. This 14 second difference is due to the diesel g< arator starting and sequence loading delays which is not i part of this surveO'.ance requirement.

The reactor enclosure secondary containment draw down time analyses assumes a starting point of 0.25 inch of vacuum water gauge and worst case SGTS dirty filter flow rate of 2800 cfm. The survei.llance requirements satisfy this as-sumption by starting the drawdown from ambient conditions and connecting the '

adjacent reactor enclosure and refueling area to the SGTS to split the exhaust flow between the three zones and verifying a minimum flow rate of 2800 cfm from the test zone. This simulates the worst case flow alignment and verifies ade- <

quate flow is available to drawdown the test zone within the required time.

The Technical Specification Surveillance Requirement 4.6.5.3.b.3 is intended l to be a multi-zone air balance verification without isolating any test zone.  ;

1 The SGTS is common to Unit I and 2 and consists of two independent subsystems.. The power supplies for the common portions of the subsystems are from Unit 1 safeguard busses, therefore the inoperability of these Unit 1 supplies are addressed in the SGTS ACTION statements in order to ensure adequate onsite power sources to SGTS for its Unit 2 function during a loss of offsite power event. The allowable out of service times are consistent with those in the Unit 1 Technical Specifications for SGTS and AC electrical power supply out of service condition combinations.

/' .

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r LIMERICK - UNIT 2 B 3/4 6-5

  • ,= -

r e .:,,.. ,,

ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION SYSTEMS (Continued)

Supplies," March 10, 1971, Regulatory Guide 1.137 " Fuel-Oil Systems for Standby Diesel Generators," Revision 1, October 1979 and Regulatory Guide 1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977, except for paragraphs C.2.a(3), C.2.c(1),

C.2,c(2), C.2.d(3) and C.2.d(4), and the periodic testing will be performed at least once per 24 months. The exceptions to Regulatory Guide 1.108 allow for gradual loading of diesel generators during testing and decreased surveillance test frequencies (in response to Generic Letter 84-15).

The surveillance requirements for demonstrating the OPERABILITY of the unit batteries are in accordance with the recommendations of Regulatory Guide 1.129 " Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978 and IEEE Std 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations," except the test will be performed at least once every 24 months.

Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates and compares the battery capacity at that time with the rated capacity.

Table 4.8.2.1-1 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity. The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity. The normal limits for each connected cell for float voltage and specific gravity, greater than 2.13 volts and not more than 0.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery.

Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8.2.1-1 is permitted for up to 7 days. During this 7-day period: (1) the allowable value for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below the manufacturer's recommended full charge specific gravity ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity, ensures that an individual cell's specific gravity will not be more than 0.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4)-the allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capa-bility to' perform its design function.

LIMERICK - UNIT 2 B 3/4 8-2 i

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