ML20064F522

Proposed Changes to Tech Specs Reducing Diesel Generator Load Testing & Deleting River Water Sys

ML20064F522
Person / Time
Site:	Farley
Issue date:	12/30/1982
From:	ALABAMA POWER CO.
To:
Shared Package
ML20064F518	List: ML20064F515 ML20064F522
References
NUDOCS 8301060398
Download: ML20064F522 (22)

Text

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I ATTACHMENT 3 Diesel Generator Technical Specification 4.8.1.1.2.c.5 Unit 1 Unit 2 -

Proposed pages: 3/4 8-5 3/4 8-5 Revised pages: 3/4 8-5 3/4 8-5 River Water System Technical Specification 3/4.7.5 and 3/4.7.6 Unit 1 Unit 2 Proposed pages: 3/4 7-13 3/4 7-13 3/4 7-14 3/4 7-14 B3/4 7-3 B3/4 7-3 B3/4 7-4 B3/4 7-4 Revised pages: 3/4 7-13 3/4 7-13 3/4 7-14 3/4 7-14 B3/4 7-3 B3/4 7-3 B3/4 7-4 B3/4 7-4 8301060398 821230 DR ADOCK 0500034 i

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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS = =(Continued)

================_===============-===-

operates for greater than or equal to 5 minutesAfter while its

( generator is loaded with the emergency loads.

I energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 + 420 volts

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and 60 1 1.2 Hz during this test.

l c) Verifying that all automatic diesel generator trips, except engine overspeed and generator differential and low lube oil pressure, are automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection test signal.

5. Verify that the diesel generators operate continuously for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of which 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> will be at a load of 4075 kw (continuous rating) for the 4075 kw diesels and 2850 kw (continuous rating) for the 2850 kw diesels and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will be at the maximum calculated accident load condition or the continuous load rating, whichever is greater. After completing this 24-hour test, reduce load, trip the diesel generator and demonstrate hot restart capability by performing Surveillance Requirement 4.8.1.1.2.a.4 within 10 minutes.

6. Verifying that the auto-connected loads to each diesel generator do not exceed the 2000-hour rating of 4353 kw for the 4075 kw generator and 3100 kw for the 2850 kw generator.

7. Verifying the diesel generator's capability to:

a) Synchronize with the offsite power source while the gener-ator is loaded with its emergency loads upon a simulated restoration of offsite power.

b)

Transfer its loads to the offsite power source, and c) Be restored to its standby status.

8. Verifying that with the diesel generators operating in a test mode (connected to its bus), a simulated safety injection signal i

1 overrides the test mode by returning the diesel generator to standby operation.

I

9. Verifying that the automatic load sequence timer is OPERABLE with each load sequence time within i 10% of its required value or 0.5 seconds whichever is greater.

10. Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

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i a) 011 Temperature High (OTH)

FARLEY-UNIT 1 3/4 8-5

ELECTRICAL POWER SYSTEMS

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SURVEILLANCE REQUIREMENTS (Continued) 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 busses shall be maintained at 4160 i 420 volts and 60 i 1.2 Hz during this test.

c) Verifying that all automatic diesel generator trips, except engine overspeed and generator differential and low lobe oil pressure, are automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection test signal.

Ysi'h"5M Veri at the

• diesel ener ate for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while

'kv5 W

• loaded to for 4075 kw diesels and 3100'for the 2850 died After completing this 24-hour w.4y $w 19 kows kw diesels (2000 trip ur the diesel gen to from the 2000-hous aldk ttkom M test, manu loac emonstrate hot restart capability forming k at A dl + 9 0 W M eillance Requirement 4.8.1.1.2.a.4 within 10 m n s.

MM re@ M y M rk d ade e o S

6. Verifying that the auto-connected loads to each diesel genera-2550 bM 2.t50 MW"W tor do not exceed the 2000-hour rating of 4353 kw for the 4075 kw generator and 3100 kw for the 2850 kw generator.

qH')@$LMws c % da n j tuM %.m 7. Verifying the diesel generator's capability to:

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cJcJL},:o uu.:batloa 9s.d4A w4 ws% :e.Jv&p a) Synchronize with the offsite power source while the genera-tor is loaded with its emergency loads upon a simulated wLd.ew n p h Afgut restoration of offsite power.

co,phh j/w 2y4 gr

• ra k toQ p A b) Transfer its loads to the offsite power source, and 7%g gy%

l /tv rdmd u c) Be restored to its standby status.

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Verifying that with the may &./ d Noperating diesel generators q %in~a test mode (connected to its bus), a simulated safety injection Q /,2 /p % 4 - signal overrides the test mode by returning the diesel gen-erator to standby operation.

9. Verifying that the automatic load sequence timer is OPERABLE with each load sequence time within i 10% of its required value or 0.5 seconds whichever is greater.

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l 10. Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) 011 Temperature High (OTH) i

! FARLEY-UNIT 1 3/4 8-5 AMENDHENT NO. 26 l

.* ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)= = = = = = = = = = = = = = = = '

operates for greater than or equal to 5 minutes After while its i generator is loaded with the emergency loads.

energization, the steady state voltage41601 and frequency 420 volts of the emergency busses shall be maintained at and 60 1 1.2 Hz during this test.

Verifying that all automatic diesel generator trips, except c) engine overspeed and generator differential and low lube l

! oil pressure, are automatically bypassed up l signal.

( 5.

Verify that the diesel generators operate continuously fo. 24 '

! hours rating) of for which the 407522kw hours willand diesels be 2850 at a load of 4075 kw kw (continuous rati(

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for the 2850 kw diesels and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will be at the max calculated accident load condition After completing or thisthe continuous 24-hour l rating, whichever is greater.

test, reduce load, trip the diesel generator and demonstrate ho restart capability by performing Surveillance Requirement i

4.8.1.1.2.a.4 within 10 minutes.

6. Verifying that the auto-connected loads to each diesel genera do not exceed the 2000-hour rating of 4353 kw for the 4075 kw generator and 3100 kw for the 2850 kw generator.

7. Verifying the diesel generator's capability to:

a)

Synchronize with the offsite power source while the gener-ator is loaded with its emergency loads upon a simulated restoration of offsite power.

Transfer its loads to the offsite power source, and b)

Be restored to its standby status.

c) l Verifying that with the diesel generators op i

8.

l overrides the test mode by returning the diesel generator to standby operation.

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9. Verifying that the automatic load sequence or 0.5 seconds whichever is greater.

10.

Verifying that the following diesel generator lockout features prevent diesc1 generator starting only when required:

011 Temperature High (OTH) a)

l 3/4 8-5 FARLEY-UNIT 2 L- , - - - --

ELECTRICAL POWER SYSTEMS ,

, _ SURVEILLANCE REQUIREMENTS (Continued) operates for greater than or equal to 5 minutes while its

! generator is loaded with the emergency loads. After j

energization, the steady state voltage and frequency of

- the emergency busses shall be maintained at 4160 1 420 volts and 60

• 1.2 Hz during this test.

c) . Verifying that all automatic diesel generator trips, except engine overspeed and generator differential and low lube oil pressure, are automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection test signal.

hat the diesel generators operateff4h e # while Yuhyie d 5. Vert loaded to 35(kw for the 4075 kw fter fesels and 3100this for24-hour the 2850 gF4, kw diesels (20001 ou~ ragng). completing yth issel generator from the 2000-hour

• ' Il test, manually l

cfoSF p 1.9 6 uf ""M load an dem nstrate hot restart m pability by performing lance Requirement 4.8.1.1.2.ahithin ,10 minutes.

.gm M bc.d' .gur l

Q , tju)r(&>w"'

Verifying tliat the auto-connected loads to each diesel genera-I W ) k, 4 qug 6. tor do not exceed the 2000-hour rating of 4353 kw for the 4075 W 34MM kw generator and 3100 kw for the 2850 kw generator.

LA w.va'Q W 7. Verifying the diesel generator's capability to:

2 950 /.w tLeah

.5 ,& 2ks Jk

.J A m y - c'J<.d 4 a) Synchronize with the offsite power source while the genera-tor is loaded with its emergency loads upon a simulated acffg g g g . restoration of offsite power.

.m. h % r.JL.

M "" " F"A- @q, b) Transfer its loads to the offsite power source, and agkb 1L. t%

NWAu lod 4pM' c) 8e restored to its standby status.

dd<lp~rdaA Verifying that with the diesel generators operating in a test M4'" M wiu. 8. mode (connected to its bus), a simulated safety injection

(*/lMO/ / / "'"'"f signal overrides the test mode by returning the diesel gen-erator to standby operation.

J 6 /// % p y

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9. Verifying that the automatic load sequence timer is CPERABLE DM- with each load sequence time within t 10% of its required value or 0.5 seconds whichever is greater.

10. Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) 011 Temperature High (OTH)

FARLEY-UNIT 2 3/4 8-5 -

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~3/4.7.5 RIVER WATER SYSTEM .

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. PLANT SYSTEMS BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES t

The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line.

l rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent I

with the assumptions used in the accident analyses.

i' 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced. stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70 F and 200 psig are based on steam generator average impact values taken at 10 F and are sufficient to prevent brittle fracture.

-1 3/4.7.3 COMPONENT 500 LING WATER SYSTEM

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i The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety The redundant cooling

. elate'd et uipment during normal and accident conditions.

cepacity,of this system, assuming a single failure, is consistent with the assamptions used in the accident. analyses.

3/2.7.4 SRVICE WATER SYSTEM ,

'he OPERFBILITY of the service water system ensures that sufficient coolin,1 capacity is available for continued operation of safety related The redundant cooling ,

equipment during' normal Snd accident conditions.

capacitj of this system, assuming a single failure, is consistent with the assumptions used in the accident conditipns within acceptable limits.

3/4.7.5 RIVER. WATER SYSTEM 3 This specification deleted.

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8 3/4 7-3 . AMENDMENT NO. 26 FARLEY-UNIT 1 em **

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l 3/4 7.6.2 ULTIMATE HEAT SINK (POND)

The limitations on the ultimate heat sink level and temperature ensure i

that sufficient cooling capacity is available to either 1) provide normal.

l cooldown of the facility, or 2) to mitigate the effects of accident conditions l

within acceptable limits.

The limitations on minimum water level and maximum temperature are based l

cn providing a 30 day cooling water supply The to safety related equipment without measurement of the ground water exceeding their design basis temperature.

seepage at least once per 5 years will provide assurance that the 30 day supply of water is available. ,

3 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM , , ,

The OPERABILITY of the control room ventilation syste'm ensures that ,

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- 1) the ambient air temperature does not exceed the allowable temperature for continuous, duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of '

this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the centrol room to-

%.5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",

10 CFR 50.

Cumulative operation of the system with the heaters on for at least '

10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM (PENETRATION FILTRATION ~ SYSTEM The OPERABILITY of the penetration, room air filtration system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to 1 aching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

Cumulative operation of the system with the heaters on for at least l

' 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

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4 B 3/4 7-4 AMENDMENT NO. 26 FARLEY-UNIT l' ' ,

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3/4 7-13 Amendment No. 13 '

FARLEY-UNIT 2 O e e

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PLANT SYSTEMS _

3/4.7.6 ULTI.VATE HEAT SINK . ,

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i PLANT SYSTEMS t

BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line

. rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses. '

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stress'es in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70 F and . _

200 psig are based on steam generator average impact values taken at 1D*F and '

are sufficient to prevent brittle fracture. ,5

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3/4.7.3 ' COMPONENT CCOLING WATER SYSTEM The OPERABILITY uf the component cooling water system ensures that sufficient cooling capacity is available for continued operation The redundant of safety cooling ,

related equipment during normal and accident conditions.

capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.

3/4.7.4 SERVICE WATER SYSTEM The OPERABILITY of the service water system ensures that sufficient ,

cooling capacity is available for continued operation of safety related The redundant cooling equipment during normal and accident conditions.

capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within' acceptable limits.

3/4.7.5 RIVER WATER SYSTEM ..

This specification deleted.

N FARLEY-UNIT 2 B 3/4 7-3

PLANT SYSTEMS BASES _ ,_

3/4.7.6.1 ULTIMATE HEAT SINK (RIVER 1 This specification deleted.

3/4 7.~6.2 ULTIMATE HEAT SINK (POND)

The limitations on the ultimate heat sink level and temperature . ensure that sufficient cooling capacity is available to either 1) provide no. mal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their-design basis temperature. The measurement of the ground water -

seepage at least once per 5 years will provide assurance that the 30 day supply of water is available. +

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3/4.7.7 C0NTROL ROOM EMERGENCY VENTILATION SYSTEM . p ..

The OPERABILIiY of the control rocm ventilation system ensures that

1) the abfent. air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY o'f this system in conjunction with control room design provisions is based on

- limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This -limitation is "A", consistent 10 CFR 50.

with the requirements of General. Design Criteria 19 of Appendix Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

~

3/4.7.8 TCCS PUMP _ ROOM EXHAUST AIR FILTRATION SYSTEM (PENETRATION R FILTRATION SYSTEM _

.Thh OPElfABILITY of the penetrat' ion room air filtration system ensures

- that radioactive materials leaking from the ECCS equipment within the pump inom following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

Cumulative operatinn of the system with the heaters on for at least

. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> uver a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

FARLEY-UNIT 2 8 3/4 7-4

PLANT SYSTE

( 3/4.7.5 RIVER

• R SYSTEM LIMITING ~CONDITIO PERATION m

3.7.5 At least two inde river water loops shall be OPERAB ith at least two river water pumps p. loop.

g APPLICABILITY: MODES 1, 2, 3 an X .

'" TION:

Wit bJi,1y one river water loop OPERABLE, tore at least two loops to OPERABL stat "dithin 7 days or b at least HOT ANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in t.0 SHUTOOWN wi nt following 30 urs.

S SURVEILLANCE 'UI R w

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m 4.7.5 Each river wa' loop s onstrated OPERABL

a. At least once 3 31'd fying that each val (manual, lg power operated 'utom c T 'he flow path, servic - safety related equipment at is n loc sealed, or otherwi secured in position, is in

}orrect $

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b. . At least once per 18 mo ss duri shutdown,'by:

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1. Verifying that each au N tic valve servicing safety related i equipment actuates to it orrect position on a low pond level signal.

Verifying that the~ buried pipi Qsleaktightbyavisual inspection of the ground area.

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FARLEY-UNIT 1 3/4 7-13 AMENDMENT NO. 26 z.......... 1

PLANT SYS 3/4.7.6 ULTI SEAT SINK RIVER LIMITING CONDITION FOR OP $JON 7,. 6.1 The ultimate heat sink er) shall be OPERABLE with a mi um water 1

at or above 70'-0" Mean Sea 1 USGS datum, and a maximum wa evel at o low 127' Mean Sea Level.

APPLICABILIkg 2, 3 and 4.

ACTION: x With the requirements specification not s fled, be in at least HOT STANDBY within 6 ho HUTDOWN within t Yfo110 wing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

4 SUR LANCE REQUIREMENTS 4.7.6.1 dmate heat sink shall he , mined OPERABLE at least once 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by ver ing the water level to be _in limits. ,

i 3/4 7-14 ' AMENDMENT NO. 26 FARLEY-UNIT 1

. PLANT SYSTEMS l%

BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses. .

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70*F and 200 psig are based on steam generator average impact values taken at 10 F and are sufficient to prevent brittle fracture.

3/4.7.3 COMPONENT COOLING WATER SYSTEM f

The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure,.is consistent with the assumptions used in the accident analyses.

3/4.7.4 SERVICE WATER SYSTEM - -------

The OPERABILITY of the service water system ensures that sufficient cooling capacity is available for continued operation of safety relatted equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.

3/4.7.5 RIVER WATER SYSTEM OPERABILIT f the river ater system en res that su icient co ing capacit is available o the servic water system continued eration o vital co, nents and e ineered safe feature equip nt during n mal and accident c itions. Th redundant to ing capacity this system, assuming a single fai e, is cons 1 ent with the ssumptions us in the acci nt analyses.

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FARLEY-UNIT 1 B 3/4 7-3 AMENDMENT NO. 26

PLANT SYSTEMS BASES 3/4.7.6.1 ULTIMATE HEAT SINK (RIVER) 1 The limiq.ations on the ultimate heat si level ensure t t sufficient cooling capac is available to either 1) pr ide normal cool n of the facility, or 2 o mitigate the effects of acc ent conditions w hin acceptable limit n minimum water level is ba .d on providing a day The limitation cooling water supply safety related equipment.

3/4 7.6.2 ULTIMATE HEAT SINK (POND)

The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature. The measurement of the ground water seepage at least once per 5 years will provide assurar.ce that the 30 day supply of water is available.

3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that

1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A,10 CFR 50.

Cumulative operation of the system with the heaters on for at l' east 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM (PENETRATION ROOM AIR FILTRATION SYSTEM The OPERABILITY of the penetration room air filtration system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over.a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter. ,

9 3/4 7-4 AMENDMENT NO. 26 FARLEY-UNIT 1

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LIMITING C0f I _

PERATION ,

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7.5 At least t'.o N 7 depen triverwaterloopsshallbeOPs. ~ with at t two river wata' pumps p loop. ,/

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APPL SILITY: MODES 1, 2, 3 and c'

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N / ~s With only on %T'~ W ") loop CPERABLE, tore at least two loops to OPERA status within ,

• ou e in at least H0: 'TANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> the f 11owing 30 h s/

and in COLD SHUT

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SURVEILLANCE REOUIREMENT u

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- . 7.5 Each river water loop sha '" . m.onstrated OPERABLE:

. a, At least once per 31 days - erifying that each valve nual,

. N power operated or automatic),'a the f,1cw path, servicing (ety helatedequipmentthatisnot '

ed, sealed, or otherwise vred

' bp,osition, is in its correct po

• ion \ , ,

b. At ' once per 18 months during sh do'wn, by:

\ .

1. Ver 'ing that each automatic valve rvicing safety relate'd equip.. ' 'N actuates to its correct posis on a low pond level signal. /

.K the buried piping is leak \ti y a visual

2. - Verifying th specti,on of t 9: ground area.

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l Amendment No. 1 FARLEY-UNIT 2 _

3/4 7-13

4 PLANT SYSTEMS _

3/4.7.6 ULTIMATE HE k NK . ,

RIVER LIMITING CONDITION FOR OPERAT - =

't shall be OPERABLE with a minim water

.1 The ultimate heat sink (ri vel le t or above 70'-O" Mean Sea Lev 5 USGS datum, and a maximum water at o low 127' Mean Sea Level.

APPLICABIL  : MOD 2, 3 and 4.

ACTION:

! With the requirem ts he ove specification not s fied, be in at least in COLD SHUTDOWN within t 'o11owing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

HOT STAN0BY within ),,

~

I l

I VEILLANCE REOUIREMENTS s

w. si s~

)11 be determined OPERABLE at least on ' er 4.7.6. The ultimate heat sink .

~

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verifying the water le ' to be within limits. g, l

h I

s FARLEY-UNIT 2 3/4 7-14.

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-t-t'v--c v.w e ,,- g # g,--,

l'.

PLANT SYSTEMS

]

i 1 l~ / BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES l The OPERABILITY of the main steam line isolation valves ensures that no  !

more than one steam generator will blowdown in the event of a steam line  !

rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line ,

rupture occurs within containment. The OPERABILITY of the main steam 1>olation  ;

valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 10*F and . _

200 psig are based on steam generator average impact values taken at 10 F and are sufficient to prevent brittle fracture.

.(

( 3/4.7.3 COMPONENT COOLING WATER SYSTEM

' The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety l related equipment during normal and accident conditions. The redundant cooling l

capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.

3/4.7.4 SERVICE WATER SYSTEM The OPERABILITY of the service water system ensures that sufficient I cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the I assumptions used in the accident conditions within acceptable limits.

3/4.7.5 RIVER WATER SYSTEM The OPERABIL of the river wat system ens s that sufficie cooling ca ity is availa to the service w .r system fo ontinued opera on of vita components an gineered safety ture equipme during normal nd accid conditions. redundant cooli capacity o'f is system, ass ing

! a sing 1 ailure, is con tent with the as ptions used 'n the accident analyses.

FARLEY-UNIT 2 B 3/4 7-3

PLANT SYSTEMS -

BASES j

3/4.7.6.1 ULTIMATE HEAT SINK (RIVER)_

T limitations on the u timate heat sink le 1 ensure that sufficient either 1) provide ormal cooldown of the cooling apacity is available facility, or 2) to mitigate the ffects of accident onditions within g acceptabl limits.

l The li ations on minimum wa level is based o roviding a 30 day cooling water upply to safety relat equipment.

! 3/4 7.6.2 ULTI TE HEAT SINK (POND)

The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

l The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature. The measurement of the ground water -

l seepage at least once per 5 years will provide assurance that the 30 day supply of water is available.

3/4.7.7 CONTROL it00M EMERGENCY VENTILATION SYSTEM l

The OPERABILITY of the control room ventilation system ensures that ,

1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent l

with the requirements of General Design Criteria 19 of Appendix "A", 10 CFR 50.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM (PENETRATION ROOM AIR FILTRATION SYSTEM The OPERABILITY of the penetration room air filtration system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to. reaching the environment. The f operation of this system and the resultant effect on offsite dosage i

calculations was assumed in the accident analyses.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient.to reduce the buildup of moisture on the adsorbers and HEPA filter. ,

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s FARLEY-UNIT 2 8 3/4 7-4

._. ~_ , -

ATTACHMENT 4 , ,

Joseph M. Farley Nuclear Plant Diesel Generator Load Testing Summary Diesel Generator Test Date Duration of Load Testing 300-Hou r . R ati n g 2000-Hour Rating Continuous Rating 1-2A 1973 (1) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> .1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2/14/77 (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4/26/81 (3) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> (4) 5/2/81 (3) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> (5) 5/3/81 (3) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> (6) -

5/4/81 (3) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> 1B 1973 (1) 2 h'ours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2/18/77 (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2B 1975 (1) 2 ho'rs u 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 11/14/79 (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 5/6/,81 (3) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> (7)

~

5/7/81 (3). 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />

-1C 1974 (1) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

/ 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1/19-20/77(2) -

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4/30/81 (3) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> o  ;

,- 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> 2C 1973 (1) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />  ; I hour 4. hours m -

1/27/,77 (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />' -

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 5/6/81 (3) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -

22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />

- ~

1) ' Production (factory) testing. i -

!/(5) A clogged strain'r e caused

2) Pre-operation (field)' testing. tett' termination prior- to

3) 24-hour endurance; testing.' -

complation. -

. (4) Vo'?tage data recorder did,not (, , (6) N lube oil 11eak caused test document passing the acceptance criteria , termination prior 7to completion.

thus requiring a retesti <(1) A fuel oil leak cause test r, j ,

J ' termination prior to completion.

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