ML20102B248

Proposed TS 3.9.C & 4.9.C Re out-of-svc Times for Emergency Svc Water Sys

ML20102B248
Person / Time
Site:	Peach Bottom
Issue date:	07/20/1992
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20102B239	List: ML20102B237 ML20102B248
References
NUDOCS 9207280281
Download: ML20102B248 (13)

Text

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e ATTACllMENT 2 PEACllllOTTOM ATOMIC POWER STATION UNITS 2 AND 3 Docket Nos. 50-277 50-278 License Non. DPR-44 DPR-66 TECllNICAL SPECIFICATION CilANGES I

i.ist of Attached Pages

i Unit 2 Unit 3 I

221 221 tl 223 223 R

224 224 J

234 234

)

i 235a 235a s i 236a 236a L

D 9207280291 920720 PDR ADOCK 05000277 PDR p

Unit 2 pl!APS LIMITING CONDil10N5 FOR OPEkAl10N SURV[ll1ANCE RfQUIRtMEN1S 3.9.C tmeraency Service Water 4.9.C Emergency Service Water Syf R m Systtg

1. The Emergency Service Water

1. The [SW5 shall be tested System (ESWS) shall be opertble once every 3 months as at all times when the reactor follows:

coolant temperature is greater than 212 F.

a. Pump operability -

the pump shall be

2. If one ESW pump becomes manually started and inoperable, the reactor flow capability tested in may remain in operaticn accordance with the Section for a period not to XI of the ASME Boiler exceed seven (7) days, if Pressure Vessel Code and this requirement canact be applicable addenda except met, an orderly thutdoan shall where relief has been be initiated and the reactor

granted, shall be placed in the cold shutdown condition

b. Valve operability -

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the automatic valves shall be stroked

3. If two ESW pu/, ', become individually from inoperable, int reacto* shall their control switches, be placed in hot shutdown within six (6) hours

2. The associated pump room and in cold shutdown fans shall be tested for within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

operability every 3 months.

4. To consider the ESW pump

3. Each manual val' and operable the associated each electric mot 3r pump room fans must be operated valve,na is available for normal operation in the system f'.w except that a) one pump path and that is not room suppl) and/or exhaust locked, sealed or fan for each compartment otherwise secured in may be out of service for position, shall be one month or b) temporary verified monthly to be fans may be used in place of in its correct position, permanently installed fans to provide room peratures at less than 120

4. Once per refuel outage the bottom of the 'A' ESW pump intab structure will be Int

d and cleaned as nec

.ary to remove excessive silt.

-221-

Unit 3 e

PBAPS LIMITING CONDillbHS FOR OPERM10N SURVElLLANCl R(QUIR!MLNIS 3.9.C [inergerg Service Water 4.9.C [mergency Service Water jJtem _Sy s t ern

1. The Emergency Service Water

1. The LSWS shall be tested System (ESWS) thall be operable once every 3 months as at all times when the reactor follows:

coolant ternperature is greater than 212 f.

a. Pump operability -

the pump shall be

2. If one ESW pump becomes manually started and inoperable, the reactor f low capability tested in may remain in operation accordance with the Section for a period not to Al of the A!ME Boiler exceed seven (7) days, if Pressure Vessel Code and this requirement cannot be applicable addenda except met, an orderly shutdown shall where relief has been be initiated and the reactor granted.

shall be placed in the cold shutdown condition

b. Valve operability -

within 24 hours. the automatic valves shall be stroked

3. If two ESW pumps become individually from inoperable, the reactor shall their control switches, be placed in hot shutdoan within six (6) hours

2. The associated pump room and in cold shutdown fans shall be tested for within 36 hours.

operability every 3 months.

4. To consider the ESW pump

3. Each manual valve and operable the associated each electric motor pump room fans must be operated valve that is available for normal operation in the system flow except that a) one pump patn and that is not room supply and/or exhaust locked, sealed or fan for each compartment otherwise secured in may be out of service fur posit ion, shall be one month or b) temporary verified monthly to be fans may be used in place of in its correct position.

permanently installed fans toprovidercomgemperatures at less than 120

4. Once per refuel outage the bottom of the 'B' ESW pump intake structure will be inspected and cleaned as necessary to remove excessive silt.

-221-

Unit 2 e pBAp5 3.9 BAS!] (Cont'd.) The I?S-Volt battery system shall have a minimum of 105 Vrlts at the battery terminals to be considered operable. lhe PS0-Volt prt ion of the 125/?bO-Volt battery system shall have a r-inimum of 210 Volts at the ba*.tery terminals to be considered operable. The ESWS has two 100 percent cooling capacity pumps, each powered from a separate standby power supply. In the event one of the ESW pumps becomes inoperable the 7 day allowable out of service time is conservative given the probability of an event requiring the use of both ISW pumps occurring in that amount of time. One ESW pump is capable of supplying the entire system. If both of the LSW pumps become inoperable placing the reactor in, shutdown condition is consistent with the severity of the situation. 4.9 BASES The monthly test of the diesel generator is conducted to check for equipment failures and deterioration. Testing is conducted up to equilibrium operating conditions to demonstrate prorc m ration at these conditions. The diesel generator will be manually si vic% wrv stied and connected to the bus and load picked up. The diesel 9 nta M c2 vid loaded to at least 75% of rated i + load to prevent fouling of tht e nf,4 b esper;ted that the diesel i generator will be run for one tw k. w. Die',el generator experience at other generating stations indicates that the testing frequency is adequate and provides a high reliability of operat,on should the system be required. Each diesel generator has one air compressor and two air receivers for starting. It is expected that the air compressors will run only infrequently. During the monthly check of the diesel generator, one receiver ir each set of receivers will be drawn down below the point at which the corresponding compressor automatically starts to check operation and the ability of the compressors to recharge the receivers. The diesel generator fuel consumption rate at full load is approximately 200 gallons per hour. Thus, the monthly load test of the diesel generators will test the operation and the ability of the fuel oil transfer pumps to refill the day tank and will check the operation of these pumps from the emergency source. The test of the diesel generator-during the refueling outage will be more comprehensive in that it will functionally test the system; i.e., it will check diesel generatt,r. starting and closure of diesel generator breaker and sequencing of load on the diescl generator. The diesel generator will be started by simulation of a loss-of-coolant accident. In addition, an undervoltage condition will be imposed to simulate a loss of of f-site power. The timing sequence will be checked to assure that the diesel generators can-operate the LPCl pumps at rated speed within 18 seconds. and the core spray pumps at rated speed within twenty-four seconds, t -223-l l l l 1 ( (

._ _.ii Unit 3 pBAPS

3. 9.

BA51S (Cont'd.) The 125-Volt battery system shall have a minimum of 105 Volts at the battery terminals to be considered operable, lhe PSO-Volt portion of the 125/250-Volt battery sysicm shall have a minimum of 210 Volts at the battery terminals to be considered operable. The ESWS has two 100 percent cooling capacity pumps, each powered from a separate standby power supply. In the event one of the ESW pumps becomes inoperable the 7 day allowable out of service time is conservative given the probability of an event requiring the use of both ESW pumps occurring in that amount cf time. One ESW pump is capable of supplying the entire system. If both of the ESW pumps become inoperable placing the reactor in a shutdown condition is consistent with the severity of the situation. 4.9 BASES The monthly test of the diesel generator is conducted to check for equipment failures and deterioration, lesting is conducted up to equilibrium operating conditions.to demonstrate proper operation at these conditions. The diesel generator will be manually started, synchronized and connected to the bus and load picked up. The diesel generator should be loaded to at least 75% of rated load to prevent fouling of the engine. It is expected that the diesel generator will be run for one to two hours. Diesel generator experience at other generating stations indicates that the testing frequency is adequate and provides a high reliability of operation should the system be required. s 3 Each diesel generator has one air compressor and two air receivers for starting. It is expected that the air compressors will run only infrequently. During the monthly check of the diesel generator, one receiver in each set of receivers will be drawn down below the point at which the corresponding compressor automatically starts to check operation and the ability of the compressors to recharge the receivers. The diesel generatnr f uel consumption rate at full load is appro> imately 200 gallons per hour. Thus, the monthly load test of the di sel (entrators will -test the operation and the ability of the fuel oli transfer pump. to ref ill the day tank and will check the operation of these pumps from the emergency source. The test of the diesel generatnr during the refueling outage will be more comprehensive in that it will functionally test the system; i.e., it will check diesel generator starting er.d closure of diesel generator breaker and sequencing of load on the diesel generatnr. The diesel generator will be started by simulation of-a loss-of-coolant accident, in addition, an undervoltage condition will be imposed to simulate a loss of off-site power. The timing sequence will be checked to assure that the diesel generators can operate the LPCI pumps at rated speed within 18 seconds, and the core spray . pumps at rated speed within twenty-four seconds. -223-mu m imi siw i i

Unit 3 PBAPS 4.9 BASES (Cont'd.) Periodic tetts twt./een ref uelitg outages verify the ability of the diesel generator to run at full load and the core and ;ontainment cooling pumps to deliver full flow. Periodic testing of the various components, plus a functional test one-a-cycle, is sufficient to maintain adequate reliability. Although station batteries will deteriorate with time, utility experience indicates there it almost no possibility of precipitous failure. The type of surveillance described in this specification is that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure, in addition, the checks described also provide adequate indication that the batteries have the specified ampere hour Capability. The station batteries shall be subjected to a performance test every third refueling outage and a service test during ttic other refueling outages, lhis testing frequency complies with the testing requirements of the Institute of Electrical and Electronics Engineers (IEEE) Standard 450 (1975), " Recommended Practice for Maintenance, lesting and Replacement of Large Lead Storage Batteries," and Regulatory Guide 1.129. Revision 1 (february 1978), " Maintenance, lesting and Replacement of large lead Storage Batteries for Nuclear Power Plants." A performance test determines the ability of the battery to meet a specified discharge rate and duration based on the manuf acturer's rating. service test proves the capability of the battery to deliver the design requirerents of the dc systems; i.e., supply and maintain in operable status all of the actual emergency loads for the design basis accident. A performance test is the most severe test because the cycling on the battery at manufacturer's rating shortens the sen ice life of the battery. A service test is performed at design load instead of manutacturer's ratings. The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators. Water content should be minimized because water in the fuel could contrit,ute to excessive damage to the diesel engine. Amendment No. 134 centralized commitments related to Position C.? of Regulatory Guide 1.137, Revision 1 (uctober, 1979) " Fuel Oil Systems for Standby Diesel Generators". When it is deteimineJ that some auxiliary electrical equipment is out-of-service, the increased tuneillance r(quired in Section 4.5.I is deemed adequate to provide assuran a that the renaining equipment will be operoble. The test inter /al f or the f uergency Servite Water System, and pump room f ans assoCidted with the ESW pumps is deemed adequate to provide cssurance that the equipment will be operable based on good engineering judgment and system redundancy, plus the additional testing accomplished when the diesel generators dre tested. Pump flow tests during normal operation will be performed by measuring the head and flow in the system using suitable flow equipment and pressure instrumentation. -224-

Unit 2 PBAPS 4.9 BASE S (Cont 'd. ) Periodic tests between refucling outages verify the ability of the diesel generator to run at full load and the core and containment cooling pum;)s to deliver full flow. Periodic testing of the various components, plus a functional test one-a-cycle, is sufficient to maintain adequate reliability. Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure, lhe type of surveillance described in this specification is that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure. In addition, the checks described also provide adequate indication that the batteries have the specified ampere hour capability. The station batteries shall be subjected to a performance test every third refueling outage and a service test during the other refueling outages. This testing frequens.y complies with the testing requirements of the Institute of Electrical and Electronics Engineers (IEEE) Standard 450 (1975), " Recommended Practice for Maintenance, lesting and Replacement of large lead Storage Batteries," and Regulatory Guide 1.129, Revision 1 (February 1978), " Maintenance. lesting and Peplacement of large Lead Storage Batteries f or nuclear Power Plants." A performance test determines the ability of the battery to meet a specifled discharge rate and duration based on the manufacturer's rating. A service test proves the capability of the battery to deliver the design requirements of the dc systems; i.e., supply and maintain in operable status all of the actual emergency loads for the design basis accident. A performance test is the most severe test because the cycling on the battery at manufacturer's rating shortens the service life of the battery. A service test is performed at design lo&d instead of manufacturer's ratings. The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators. Water content should be minimized because water in the fuel could contribute to excessive damage to the diesel engine. Amendment No. 131 centralized commitments related to Position C.? of Regulatory Guide 1.137, Revision 1 (October, 1979) " fuel Oil Systems for Sten by Diesel Generators". a When it is determined that some auxiliary electrical equipment is out-of-service, the increased surveillance required in Section 4.5.f is deemed adequate to provide assurance Uiat the remaining equipment will be operable. The test interval f or the [mergency Service Water System, and pump room f ans associated with the ESW pumps is deemed adequate to provide assurante that the equipment will be operable based on gnod engineering Judgment and system redundancy, plus the additional testing accomplished when the diesel generators are tested. Dump flow tests during normal operation will be performed by measuring the head and flow in the system using suitable flow ecui' ment and pressure instrumentation. -224-

Unit 3 e 6 PBAPS LIMITlHG CONDITIONS FOR OPERA 110N SURVElttANCL ntQUIREMENTS 3.ll.A (Cont'd.) 4.ll.A (Cont'd.) d. A sample of the charcoal filter shall be analyzed once per year to assure halogen removal efficiency of at least of at least 99.5 percent. 2. At least 1 of the 2 main 2. Operability of the main control room intake air radiation control room aic intake monitors shall be operable with radiation monitors shall be the inoperable channel failed tested every 3 months. safe whenever the control room emergency ventilation air supply B. Emergency Heat _ yrd Iacility fans and filter trains are required to be operable by 3.ll.A.1 or 1. The level in the et.crgency filtration of the control room reservoir of the lmer'ency ventilation intake air must be lleat Sink facility shall be l_ initiated. checked once per month. [ B. Emergency lleat Sink facility 2. Once a year the portable fire pump which is used to The level in_the emergency provide makeup water to the l reservoir of the Emergency Heat emergency reservoir will be Sink facility shall not be less checked for operability and than 17'. Should the level availability. drop below this point action shall be taken to restore 3a. The Emergency Cooling Water the level to above the minimum, pump and ESW booster within 7 days, pumps shall he tested in accordance with Section XI C.. Emergency Shutdown Control Panel of the ASHE Boiler Pressure Vessel Code and applicable 1. At all times when not in use addenda, except where relief or being_ maintained, the has been granted, emergency shutdown control panels shall be secured. b. The Emergency Cooling Tower fant shall be tested every three months to verify operability. C. Emergency Shutdown Control Panel 1. The emergency shutdown control panels shall be visually checked once per week to verify _they are secured. 2. Operability of the switches on the emergency shutdown control panels shall be tested by electrical check l once per refueling outage. -?34- . ~, _.., _ _ _ _, _. _ _ _ _ _ _ _,.. _ _. _

Unit ? e 1 PDAPS LIMITING COND1110NS IOR OPERA 110N SURVElLLANCE RLQUIRIMll415 m _. _ 3.ll.A (Cont'd.) 4.ll.A (Cont'd.) -l d. A sample of the charcoal flitet shall be analyzed once per year to assure halogen remoYal efficiency 6f al l cast of at least 99.5 percent. P. At least 1 of the 2 main ?. Operability of the main control room Intake air radiation control room air intake monitors shall be operable with radiation monitors shall be the inoperabic~(.hannel failed tested every 3 months. -safe whenever the control room emergency ventilation air' supply B. E'nergency Heat Sink f acility fans and filter trains ~are required to be operable by 3.ll.A.1 or 1. The level in the emergency filtration of the control room reservoir of the Emergency ventilation intake air must be llcal Sink facility shall be initiated, checked once per month. l B. Emergency Heat Sink facility 2. Once a year the portable-I fire pump which is used to i The level in the emergency provide makeup water to the I: reservoir of the' Emergency Heat emergency reservoir will be i ' Sink facility shall not be less checked for operability and than 17'. $hould'the level availability. drop below this point actton shall be taken to restore 3a. The Emergency Cooling Water the level to above the minimum, pump and ESW booster within 7 days. pumps shell be tested in accordance with Section XI C. E,mergency Shutdown Control _ Panel of the ASME Boiler Pressure Vessel Code and applicable 1.

At all times when not in use addenda, except where relief or being maintained, the

has been granted.

emergency shutdown control panels shall be secured. b. The Emergency Cooling Tower fans shall be trst(d in accordance with Section XI o: the-ASME Boiler i Pressure Vessel Coce and applicable ^ addenda, except where relief has been granted. C. Emergency Shutdown Control Panel 1. 1he_ emergency shutdown control L panels shall be visually checked L once per week to verify they are secured. 2. Operability of the switches on the emergency shutdown control panels shall be tested by electri(.al check -once per refueling outage. t- -234-L, . -. w.- ,. -,a - - - - -.-.- _ =..

l Unit ? l I PBAPS 3.11 BASES E, megngJh at Sink l The emergency heat sink is provided as an alter nate tource of tooling water to the plants in the unlikely event of loss of the normal hcat sink (Conowingo Pond) or the maximum credible flooJ. For the condition of los; of t he normal heat sink, the contained volume of water (approximately 3.7 million gallons, which corresponds to a gauge reading of 17') provides a minimum of seven days cooling water to both plants for decay heat removal. C. Emergeancy Shut _down Control Panels The Emergency Shutdown Control Panels are provided to assure the capability of taking the plants to the hot shutdown condit lon esternal to the control room for the unlikely condition that the control room becomes unirhabitable. D. Shock Suppressors [SnubberQ onjaf ety Related Systems Snubbers are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems are maintained during and following a seismic or other event initiating dynamic loads. Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damagt to piping as a result of seismic or other event initiating dynamic loads. It is therefore required that all snubbers necessary to protect the primsry coolant system or any other safety system or components be operable during reactor operation. Because the snubber protection is required only during low probability events a period of 72 hours is alloned for repairs or replacements. A determined effort will be made to repair the snubber as soon as possible. This allowable repair period is consistent with the allowable repair items of other safety related 4 components such as RHR pumps, HPCI subsystems, ADS valves and diesel generators. An engineering analysis must be performed on supported components when a snubber is determined to be inouerable, lhe purpose of this analysis is to assure that the supported components have not been damaged as a result of the snubber inoperabiIity. -235a. 1

Unit 3 t-PBAPS 3.11 BASL] l {merJency Heat 51rA l The emergency heat sink is provided i's an alternate source of cooling water to the plants in the unlikely event of loss of the normal heat sink (Conowingo Pond) or the maximum credible flood. For the condition of loss of the normal heat sink, the contained v^.in m of water (approximately 3.7 million gallons, which corresponds to a gauge reading of 17') provides a minimum of seven days cooling water to both plants for decay heat removal. C. Emergency Shutdown Control Panels The Emcrgency $hutdown Control Panels are provided to assure the capability of taking the plants to the hot shutdown condition external to the control room for the unlikely condition that the control room becomes uninhabitable. ~ D. Shock Suppressors (Snubbers),on Safety _Related Systems Snubbers are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems sre maintained during and following a seismic or other event initiating dynamic loads. Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient while allowing normal thermal motion during startup and thutdown. The consequence of an inoperable snubber 'is an increase in the probability of structural damage to piping as a r esult of seismic or other event initiating dynamic loads. It is theret o required that all snubbers necessary to protect the primary Coolant system or any other safety system or components be operable during reactor operation. Because the snubber protection is required only during low probability events a period of 72 hours is allowed for repairs or replacements. A determined effort will be made to repair the snubber as soon as possible. lhis allowable repair period is consistent with the allowable repair items of other safety related components such as RHR pumps, HPCI subsystems, ADS valves and diesel generators. An engineering analysis must be performed on supported components when a snubber is determined to be inoperable, lhe purpose of this analysis is to assure that the supported components have not been damaged as a result of the snubber inoperability. -?35a-l l

Unit 3 v. PBAPS E 9 r 4.11. - BASES B. Emergency Heat Sink f ac t_ljty t 1he testing of the LSW Booster Pumps and the ECW pump is in accordan -with existing A$ME codes and applicable addenda except where relief has been granted and assures the required availability of the equipment. C. Emergency Shutdown-Control Panels Once per week verification.of the panels being properly secured is considered adequate. The associated equipment is proven operabl, Juring surveillance testing of that equipment. An operability verification by electrical test at each refuehng outage is adequate to assure that the panels are available and can perform their design function. { D. Shock Suppressors (Snubbers)_on Safety Related Systems All safety-relateo snubbers are visually inspected to verify, 1) proper orientation, 2) freedom of movement where possible to induce motion manually without disconnecting the snubber, 3) proper attachment to_ structures and equipmant,-and 4) proper hydraulic fluid level for hydraulic snubbers. Snubbers are categorized into two groups " accessible" or " inaccessible", based on their accessibility-for inspection during-reactor operation and _ drywell inertment. The required inspection interval varies inversely with the observed snubber failures. The number of inoperable snubbers found ~during a required Inspection determines the time interval for the ne t x required inspection. -Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.- However, the results of such early inspections will only De used to shorten the required interval and not to lengthen it. When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. ~ Generically susceptible snubbers are thuse which are of a specific make or model-and have the same design features directly related to rejection of the snubber by visual inspection or are similarly located or. exposed to the same environmental conditions such as temperature, radiation..and vibration. When a snubber is found inoperable an engineering evaluation is performed to determine a) snubber mode of fallure and,'b) if 1here.is any adverse effect or degradation on the supported piping or equipment due to the failure. To further increase the assurance of snubber reliability, functional tests will be performed once each operating cycle. -236a-l

Unit 2 PBAPS 4.11. BASES B. Emergency Heat Sink facility The testing of the E3W Booster Pumps and the ECW pump is in accordance with existing ASME codes and applicable addenda except where relief has been granted and assures the required availability of the equipment. C. Emergency Shutdown-Control Panels Once per week verification of the panels being properly secured is considered adequate. The associated equipment is proven operable during surveillance testing of that equipment. An operability verification by electrical test at each refueling outage is adequate to assure that the panels are available and can perform their design function. D._ _ Shock Suppressors (Snubbers) on Safety Related Systems All safety-related snubbers are visually inspected to verify, 1) proper orientation,-2) freedom of movement where possible to induce motion manually without disconnecting the snubber, 3) proper attachment to structures and equipment, and 4) proper hydraulic fluid-level for hydraulic snubbers.- Snubbers are categorized into two groups " accessible" or " inaccessible", based on their_ accessibility for inspection during reactor operation and drywell inertment. _The reoutred inspection interval varies inversely with the observed snubber failures. The number of inoperable snubbers found during a required inbpection determines the time interval for the next required inspection. Inspections performed before that interval has elapsed may be used as a:new reference point to determine the next inspection. a However, the results of such early inspections will only be used to shorten the required interval and not to lengthen it. When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verifled by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features-directly related to rejection of the snubber by visual inspection or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration. When a snubber is found inoperable an engineering evaluation is performed to determine a) snubber mode of failure and, b) if there is any adverse effect or degradation on the supported piping or equipment due to the failure. To further increase the assurance of snubber reliability, functional tests will be performed once each operating cycle. -236a- _....}}