ML20138L026
| ML20138L026 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/09/1985 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML20138K988 | List: |
| References | |
| TAC-60355, TAC-60356, NUDOCS 8512190144 | |
| Download: ML20138L026 (47) | |
Text
e e s INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-12 shall be OPERABLE.
APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
ACTION:
With the number of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-12:
- a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.
- b. Restore the inoperable instrument (s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrunent(s) to OPERABLE status,
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9.1 Each of the above required fire detection instruments which are accessible during plant operation shall be denonstrated OPERABLE at least
- once per 6 months by performance of a function test which includes subjecting the detector to test aerosol or heat source, as appropriate.
Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of this functional test during each COLD SliUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.
4.3.3.9.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alaims of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.
FARLEY-UNIT 1 3/4 3-59 AMENDMENT NO.
0512190144 851209 fDR ADOCK 05000348 PDR
p.- - _
TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION Auxiliary Building Total Minimum Room / Smoke of Operable Fire Zone Description Elevation Detectors Smoke Detectors 128 RHR Heat Exchanger Room 83'-0" 10 5 129 RHR Low Head Pump Room 77'-0" 1 1 131 RHR Low Head Pump Room 77'-u" 1 1
- 160 Hatch Area 100'-0" 3 2 161,162,163 South Corridor 100'-0" 7 4 172 Hallway 100'-0" 3 2 173 Charging /SI Pump Room 100'-0" 2 1 174 Charging /SI Pump Room 100'40" 2 1 175 . Hallway 100'-0" 2 1 181 Charging /S! Pump Room 100'-0" 2 1 184 Mechanical Penetration Room 100'-0" 8 4 185 CCW Heat Exchanger and Pump 100'-0" 13 7 186 Boric Acid Trans. PPS 100'-0" 3 2 188 Boric Acid Tanks 121'-0" 2 1 190 MCC Panel Room 100'-0" 4 2 191 Auxiliary Feedwater Pump Room 100'-0" 1 1 192 Auxiliary Feedwater Pump Room 100'-0" 1 1 193 Auxiliary Feedwater Pump Room 100'-0" 2 1 202 Cmumunications Rooms 121'-0" 4 2 208,207 Corridor 121'-0" 4 2 209 Hallway 121'-0" 4 2 210,211,228, South Corridor 121'-0" 7 4 234 212 Battery Room 1B 121'-0" 1 1 213 Battery Service Room 121'-0" 1 1 214 Battery Room 1A 121'-0" 1 1 223 Mechanical Penetration Room 121'-0" 9 5 224 DC Switchgear Room 121'-0" 1 1 225 Battery Charger Room 121'-0" 1 1 226 DC Switchgear Room 121'-0" 1 1 227 West Cable Chase 128'-0" 7 4 229 AC Switchgear Room Train B 121'-0" 4 2 233 AC Switchgear Room Train B 121'-0" 3 2 241 Main Steam and FDW Valve Room 127'-0" 8 4 244 Mezzanine - Battery Room 131'-0" 3 2 245 Mezzanine - Battery Room 131'-0" 3 2 254~ Hot Shutdown Panel Room 121'-0" 1 1 300 West Cable Chase 139'-0" 7 4 312 Corridor 139'-0" 3 2 316,322 Corridor 139'-0" 3 2 318 rable Spreading Room 139'-0" 8 4 319,339,345 n ,t Corridor 139'-0" 6 3 333 Electrical Penetration Room 139'-0" 1 1 334 Electrical Penetration Room 139'-0" 6 3 335 AC Switchgear Room Train A 139'-0" 3 2 343 AC Switchgear Room Train B 139'-0" 3 2 347 Electrical Penetration Room 139'-0" 2 1 FARLEY - UNIT 1 3/4 3-60 AMENDMENT N0.
___________,,,J
TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION (continued)
Auxiliary Building Total Minimum Room / Smoke of Operable Fire Zone Description ' Elevation Detectors Smoke Detectors
,401- Control Room (above ceiling) 155'-0" 8 4 401 Control Room (below ceiling) 155'-0" 5 3 440, 455, Clean Toilet, Laundry and
' 456- Drying Areas 155'-0" 3 2 462 .Non-Radioactive Vent Equip. Rm. 155'-0" 5 3 465- Vertical Cable Chase 155'-0" 3 2 466 Vertical Cable Chase 155'-0" 4 2
-500 Vertical Cable Chase 168'-2" 7 4 416 Ctrl. Rm. Inst. Racks .(above/ ceil.) 155'-0" 9 5 416 Ctrl. Rm. Inst. Racks (below/ ceil.) 155'-0" 6 3
~ Containment
- 55 Containment Coolers 155'-0" 12/ Fan 6/ Fan 55 Containment 155'-0" 11 6 Service Water Intake Structure 72 A** Pump Room Area 188'-9" 12 6
-72 A** Strainer Bay 167'-0" 18 6
-72 B** Switchgear Room - Train B 188'-9" 3 2 72 C** Foyer - Train B 188'-9" 1 1 72 D** Foyer - Train A 188'-9" 1 1
.72 E** Switchgcar Room --Train A 188'-9" 3 2 73 ** Battery Room - Train B 188'-9" 1 1 74 ** Battery Room - Train A 188'-9" 1 1 Diesel Generator Building 56 A Switchgear F;oom - Train A 155'-0" 12 6 56 B Foyer 155'-0" 4 2 56 C Switchgear Room - Train B 155'-0" 12 6 71 Hallway 155'-0" 9 5 Diesel Generator Building (Heat Detectors) 57 Diesel Driven Generator 2C 155'-0" 5 3 58 Diesel Driven Generator 18 155'-0" 5 3 60 Diesel Driven Generator 1C 155'-0" 5 3 61 Diesel Driven Generator 1-2A 155'-0" 5 3 62 Day Tank Room 2C 155'-0" 1 1 63 Day Tank Room 1B 155'-0" 1 1 65 Day Tank Room IC 155'-0" 1 1 66 Day Tank Room 1-2A .55'-0" 1 1
- The Fire Detection instruments located within the Contairment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.
C3 These circuits alarm in the Unit 1 control room area but service both units, and appear in the Technical Specifications for both units.
FARLEY-UNIT 1 3/4 3-60a AMENDMENT NO.
h EERGENCY CORE C00 LING' SYSTEMS
!- SURVEILLANCE; REQUIREMENTS *
-4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the
! applicable Surveillance Requirements of 4.5.2.
"4.5.3.2- At least once per 31 days verify that the following valves are in t the indicated position with the breaker or disconnect device for the valve k
operator locked open:
Valve Number Valwe' Function Position 8706~A, 8706 B RHR pump discharge to Closed charging pump suction 8884, 8886 Charging pump discharge Closed to RCS hot legs e
FARLEY-UNIT 1 3/4 5-8 AMEN 0 MENT NO.
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-PLANT SYSTEMS'
- s 3/4.7.7-CONTROL ROOM EMERGENCY VENTILATION SYSTEM
[' ,
LIMITING CONDITION FOR OPERATION
~
3.7.7 -Two independent control room emergency air cleanup systems shall be J. , ,
10PERA8LE. ,
APPLICABILITY: ALL MODES.- ,
ACTION:
MODES 1, 2, 3 and 4:
With one control room emergency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
M00ES 5 and 6 (during irradiated fuel movement, or movement of loads over irradiated fuel):
L
- a. With one control room emergency air cleanup system inoperable, restore
- the inoperable system to OPERABLE' status within 7 days or initiate and 4
maintain operation of the control room emergency ventilation system jn the recirculation mode.
~
, b. With both control room. emergency air cleanup systems inoperable, suspend all operations involving the movement of irradiated fuel or movement of loads over irradiated fuel.
- c. Th'e provisions of Specification 3.0.3 are not applicable in MODE 6.
SURVEILLANCE REQUIREMENTS 4.7.7 Each control room' emergency ventilation system shall be demonstrated 0PERABLE:
- 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 that the control room air temperature is less than or equal to 120*F.
- b. ' At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the pressurization and recirculation system HEPA filters and charcoal adsorbers and verifying that the pressurization system has operated for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heater'.on during the past 31 days.
t
- c. At least once per 18 months or (1) after any structural maintenance on
, the HEPA filter or charcoal adsorber housings, or-(2) following painting, fire or chemical release that could have contaminated the charcoal adsorbers or.HEPA filters in any ventilation zone communicating with the system by:
FARLEY-UNIT 1 ~3/4 7-16 AMEN 0 MENT NO.
I
. . 1, x r PLANT SYSTE S SURVEILLANCE REQUIREMENTS (Continued)
- 3. Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8 inch water gauge relative to,the outside atmosphere during system operation.
~
,4. Verifying.that the pressurization system heater dissipates 7.5 +
y T' O.8 kw when tested in accordance with Section 14 of ANSI N510-1Y80.
..y
- f. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.5% of the 00P when they are tested in-place in accordance with Section 10 of ANSI N510-1980 while operating the system at a flow rate indicated in Note 1.
- g. After' each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.5% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with Section 12 of ANSI N510-1980 while operating the system at a flow rate indicated in Note 1.
Note 1. a. Control Room Recirculation Filter Unit 2000 cfm + 10%
- b. Control Room Filter Unit 1000 cfm T 10%
- c. Control Room Pressurization Filter Unit 300cfm110%
Note 2. a. Control Room Recirculation Filter Unit > 99%
- b. Control Room Filter Unit Y 99%
- c. Control Room Pressurization T 99.825%
FARLEY-UNIT 1 3/4 7-17a AMENDMENT NO.
PLANT' SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- b. At ~least once per 92 days by verifying that a sample of diesel fuel from the fuel' storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM 0975-74 when checked for viscosity, water and sediment.
- c. At least once per 18 months by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.
4.-7.11.1.3 The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:
- a. At.least once per 7 days by verifying that:
1.- The electrolyte level of each battery is above the plates, and
- 2. The overall battery voltage is greater than or equal to 24 volts,
- b. At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery.
- c. At least once per 18 months by verifying that:
-1. The batteries and battery racks show no visual indication of physical damage or abnormal deterioration, and
- 2. The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.
FARLEY-UNIT 1 3/4 7-84 AMENDMENT NO.
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, : TABLE 3.7-5 % ff LIST 0FNSPRINKLER SYSTEMS ,
, g 9
. Location- , ..
Sprikkl'er
-Room / Fire - Zone t
~Descriptioni ..
Elevation System'
. >>r, , 3
_ 4
~
- c Auxil1ary Building .
l161- _ LNorth West Corridok s/ $3l-0"
.1 A-2.5
'161 -North. East Corridor 1100'-0"' 1A-118~
-185- ~
. North West-. Corner.of CCW Pump Rm.~ 100'-0" 1A-119-
{185' , CCWl Heat Exchanger.and Pump Room 100'-0" 1At27
.:190 Aux.- Feedwater Pumps' Cable Area 100'-0" 1A "
209 North Corridor. 4- 121'-0" 1A-35
- 210- L Auxiliary B1dg'.,-Wes' t Corridor- 121'-0" 1A '
223" -
, Pipe Penetration Room and
~ -
1 Tendon Access 121'-0" 1A-45' 227 . Vertical' Cable Chase '128'-0" 1A-23'
^ 244 Battery Room Mezzanine 131'-0" 1A-36
_. 2451 ~ : Battery Room Mezzanine 131'-0" 1A '300~ . 7 Vertical Cable Chase -139'-0" 1A-23~
2312 North _. Corridor 139'-0" 1A _3162 North Corridor, 139'-0" 1A-48' 1318L . Cable Spreading Room 139'-0"~-
' ~ ,
~
., '4621 Environmental Low Activity Lab _.
, . . . .and-Non-Radioactive Vent Rooms 155'-0"' 1A 466 . Vertical 1 Cable Chase 155'-0" '1A-23.
- '1500: Vertical Cable Chase' '168'-2"
~
1A ,
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,. . -Serv' ice Water g . Intake Structure:
~
4 ' - 72A ..Seivice Water Pump Protection .102'-0" <1SW-111
' 7 2A' ; Service, Water Pump Deck and- 188'-9" &- ISW-111A-CStrainer. Pit, East Side ._
167'-0"
.e : 72A': Service Water Pump Deck and- 188'-9" & -1SW-1118
'. Strainer-Pit, West Side 167'-0" v .; .
, 4
^ ,.
, =
-Wi<_ s
,' , FARLEY-UNIT.1' 3/4 7-87 AMENDMENT N0.
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s G PLANT SYSTEMS C0p SYSTEMS LIMITING CONDITION FOR OPERATION o 3.7.11.3 The following high pressure and low pressure CO2 systems shall be OPERABLE.
- a. Service Water Intake Structure (each 4160 volt bus and each 600 volt load center) - H.P.
- b. Turbine Building 13 ton unit and distribution system in the Auxiliary Building - L.P.
- c. Diesel Building 5 ton unit and distribution system.
APPLICABILITY: Whenever equipment protected by the CO2 systems is required to
.be OPERABLE.
ACTION:
. a. With one or more of the above required CO2 systems inoperable, within one hour-establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other. areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
.b. The provisions 'of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.11.3.1 ' Each of. the above requi red C02 systems shall be demonstrated OPERABLE at least once per 31 days by verifying that each manual valve in the
' flow path is in its correct. position.
4.7.11.3.2 Each of the above required low pressure CO2 systems shall be demonstrated OPERABLE:
a.: At least once per 7 days by verifying the CO2 storage tank level to be greater than 50% and pressure to be greater than 250 psig, and
- b. At least once per 18 months by prifying:
- 1. The system valves and associated ventilation dampers and fire door release mechanisms actuate nianually and automatically, upon receipt of a simulated actuation signal, and
- 2. Flow during ~ a "Pu ff Test."
'FARLEY-UNIT 1 3/4 7-88 AMENDMENT NO.
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.-~
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)-
4.7.11.3.3' Each of the'above required high pressure C02 systems shall be ,
demonstrated OPERABLE:
- a. At least once per 6. months by verifying the CO2 storage tank weight to be.at least 90% of full charge weight.
~b. At least once per 18 months by:
- 1. Verifying the system, including associated ventilation dampers and
- fire door release mechanisms, actuates manually and automatically,
- . ' upon receipt of. a simulated actuation signal, and
- 2. ' Verifying flow during a " Puff Test".
l-FARLEY-UNIT 11 -3/4 7-89 AMENDMENT NO.
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- TABLE 3.7-6 LIST OF. FIRE HOSE STATIONS-s.; LOCATION:(Room No.) '.
tELEVATION H0SE CABINET N0.
- Au$11'iary. Building 103 83'-0" N1V43-D-103
~_
110 83'-0" N1V43-D-102 L. 161. 100'-0" N1V43-D-110 163 100'-0" N1V43-D-109
~184 -100'-0" N1V43-D-124 E185 100'-0" :N1V43-D-108
.186 '
100'-0" N1V43-D-131-
$100'-0"
- 189
JN1V43-D-107:
- 208- "121'-0".
~,
209_ -121'-0" N1V43-D-104 Sthirway No'. 2 :121'-0". , <- 'N1V43-D-127-210 121'-0" '
~234- 121'-0" N1V43-D-125 237 -
l121'-0" N1V43-D-132.
- 312- t139'-0" N1V43-D-114 316 - .139'-0"- N1V43-D-111
- 319 139'-0" , N1V43-D-115 g
- 332- 1139'-0"'
- 1390"-
334~. -
N1V43-D-117 339 139'-0" 4 N1V43-D-116.
2345; 139'-0" N1V43-D-112
'409 155'-0"- N1V43-D-122
- 409 155'-0" . Containment Fire Hose Storage Locker *'
408' 155'-0" 'N1V43-D-123 432- 155'-0" .N1V43-D-121 1446 155'-0" N1V43-D-105 '
454 155'- 0" N1V43-D-120 y ;;.
- 462'; 155'-0" N1V43-D-106-1501'. 175'-0" N1V43-D-101-:
^505- 184'-0" -
-602 130'-0" . N1V43-D-118 LService' Water' Intake Structure-72D 167'-0" HC-2-D010A 72C: :167'-0"' HC-2-0010B 1 Diesel Generator Building -
f ' 5 6C '. 155'-0" HC-2-129-56A- -
~155'-0" HC-2-130:
4
- The requirements. of Specification 4.7.11.4 Item (c)(1) are not -applicable'.
JF RLEYi UNIT l' .3/4 7-91 . AMENDMENT N0.
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Table 3.7-6 '(Continued)
LIST OF FIRE HOSE STATIONS
'l
.. .. . H0SE CABINET
- F, ,
- LOCATION"(Room No.). ELEVATION ~ . ISOLATION VALVE N0.
- Codainmenti 105'-6" .N1T43V001*
--- < 105'-6" N1T43V002*-
-- . 105'-6". N1T43V003*
4 ---
105'-6" N1T43V004*
^
--- '129'-0" N1T43V005*
r - 155 'A 0" ' N1T43V006*
c 155'-0" N1T43V007*
-155'-0" N1T43V008*
-n-
- 4 1
-e k
si' 4
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-* .Only the. requirements _ of; Specification 4.7.11.4 Item (c)(1): are. applicable. .
FARLEY -10 NIT 1: 3/4 7-91a AMENDMENT NO.
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i TABLE 3.7 ' ~ ~
~
. YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE-. HOUSES
(" ,
. LOCATIONI HYDRANT NUMBER
~
- 1. . West'of Auxiliary Building
. N1Y43V103*
-- - 2.' East: of -Service . Water Intake N1Y43V121*
D3. West of; Service Water Intake
~
N1Y43V122*'
- 4. North :of Diesel. Generator Building . N1Y43V120*
- 5. . East ofLAuxil'1ary-Buil'ing d N1Y43V089~
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? : 6... . Northeast (of ' Diesel Generator- Building -N1Y43V090 q
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- Shared.between Unit'1'and Unit.2'l
, 'f ?N FARLEY - UNIT;1 3/4 7-93 AMENDMENT NO.
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-REFUELING OPERATIONSt I 13/4.9.14=-CONTAINMENT PURGE EXHAUST FILTER-LIMITING CONDITION FOC OPERATION 6 . 3.9.14l -The ' containment purge' exhaust filter shall be OPERABLE and valve N1P13V293. closed.
i APPLICAB'ILITY: During CORE; ALTERATIONS and Fuel Movement'inside containment s e with any containment purge isolation valve open.
~
' ACTION':' iWithith'e containment; purge exhaust filter inoperable either:-
_ c- q, s .
11.' :Immediately close the 48 -inch containment purge isolation valves
.(CBV-HV-3196, 3197,~3198A and 31980) .and the 8 inch containment mini-purge isolation. valves (CEV-HV-2866C, 2866D, 2867C and 2867D), or
- 2. ' Cease all CORE ALTERATIONS and fuel, movement.
. s - , .
oSURVEILLANCE REQUIREMENTS-14.9.141 The above. required containment purge exhaust filter shall be' demonstrated OPERABLE:
- a. : At least once 'per.18 months or (1) after'any structural maintenance on
. the HEPA filter or charcoal .adsorber. housings, or (2) following
. painting. fire or-' chemical release that could have ' contaminated the charcoal adsorbers or HEPA filter in-any ventilation zone communicating-with the-system by:
4 m
I W :
'FARLEY-UNIT li 3/4 9-16 AMENDMENT NO. c It
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Table 4.11-1 (Continued) i TABLE NOTATION
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which,.
the. method of. sampling employed results in a specimen which is representative of the liquids released. Deviations from composite sampling requirements shall be reported per Specification 6.9.1.8. -
~
- c. A batch release is the discharge of liquid wastes of a discrete-
-volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a~ method described in the ODCM, to assure representative sampling,
- d. A contismous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the effluent release.
- e. The principal gamma emitters for which the MDC specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and
-reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
- f. Sampling will be performed only if the effluent will be discharged to the environment.
- g. Deviation from the MDC requirements of: Table 4.11-1 shall be reported per Specification 6.9.1.8.~
~
FARLEY-UNIT 1 3/4 11-4 AMENDMENT NO.
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'? TABLE! 4111-2 '
u n .RADI0ACTIVEEGASE00S WASTE SAN LING AND ANALYSIS PROGRAM [ ~ '>
' - y
- IR -Minimum.- '
Minimum Detectable ; ~
, '7~
Gaseous Release Type' . Sampling: : Analysis; " .. ; Type L of J. .
' ConcentrationL (MDC) J Q
.z.
Frequency Frequency ._ Activity.Analysist pCi/ml)a.n
' M- P. .P- .
+ A. '.Waste Ga's Storage- '
Each Tank Grab Each Tank'. . Principal Gama[ Emitters 9 d- 1x10-4L- -
~
Tank' >
Sample. ,
'P . . ,'P .
B. .Containmen't Purge ~~
Each Purge .b. .Each'Purgeb. -
Principal Gama Emitters 9.d ilx10-4~
Grab -Sample -
H-3 1x10 C. Condenser' Steam Jet- Mbce gb . Principal GamaiEmitters9. j 1x10-4~
Ai r Ejector, Plant - Grab
-Vent. Stack Sample H 1x10-6 D. P1 ant Vent Stack, Continuousf- .. Wd , I-131 1x10-12
- Containment Purge - Charcoal- Charcoal
{ : Sample ~I-133 1x10-10 Continu'ousf ._
Wd . Principal Gama Emitters 9 -1x10-ll-Pa rticulate Sample Continuous; f M Gross Alpha - 1x10-ll Compositei-Particulate.
~ Sample
. m Continuousf 'Q Sr-89, Sr-90 1x10-ll Compositei E Particulate j .Sampie-Continuousf Noble Gas. Noble Gases 1x10-6
[ ,
. Monitor Gross. Beta and Gamma _
g
. s Table 4.11-2 (Continu:d)
TABLE NOTATION b.- Analyses ~ shall also be performed following shutdown from > 15% RATED THERMAL POWER, startup to > 15% RATED THERMAL POWER or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.
- c. Tritium grab samples shall be taken from the plant vent stack at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
- d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be-performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 2 days following each shutdown from > 15% RATED THERMAL POWER, startup to > 15% RATED THERMAL POWER or THERMAL POWER chango exceeding 15 perce'nt of RATED THERMAL POWER in one hour and analyses shall be. completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding MDC may be increased by a l factor of 10.
t
- e. Tritium grab samples shall be taken at least once per.7 days from-the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
- f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose _or dose rate
' calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
- g. . The principal gamma emitters for which the MDC specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
'h. Deviations from MDC requirements of Table 4.11-2 shall be reported per Specification 6.9.1.8.
- i. A composite particulate sample is one in which the quantity of air sampled is proportional to the quantity of air discharged. Either a specimen.which is representative of the air discharged may be
- accumulated and analyzed or the individual samples may be analyzed and weighted in proportion to their respective volume discharged.
Deviations from composite sampling requirements shall be reported per Specification 6.9.1.8.
- j. The principal gamma emitters for which the MDC specification applies ~
exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135-and Xe-138 for~ gaseous emissions. This does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall. also-be identified and reported.
FARLEY-UNIT 1 3/4 11-11 AMENDMENT NO.
^
R~ ,
CONTAINMENT SYSTEMS:
.c 1 sBASES1
- s hThe maximum peak. pressure expected to be obtained from a LOCA event is 45 --
lpsig.. :.The . limit;of 3 psig for initial positive containment pressure will limit
'+', (the total:: pressure _ to 48 psig whichLis -less than design pressure and is fconsistent with the. accident. analyses.:
~3/4.6.1.5~ AIR TEMPERATURE-
_ The limitations.on containment average air temperature ensure that the
+
- overall ~ containment average air. temperature does not exceed the initial
- temperature condition = assumed in the accident analysis for a LOCA cn steam line break' accident.
-3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY.
1This limitation ensures that the structural integrity of.the containment
- will .be maintained. comparable to the original. design standards for the life of
- the facility.' Structural integrity is required to. ensure that the containment LWill withstand.the maximum pressure of 48 psig in the event of a LOCA. The
- measurement.of the containment lift 'off force, visual examination of tendons,
- anchorages and exposed . interior and exterior surfaces of the containment, and
, , the Type A leakage test, is . sufficient to demonstrate this capability.
The surveillance requirements-for demonstrating the containment's
. structural integ'rity a're in compliance with the. recommendations of paragraph
~
'C.1.3 of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in
, ~ Prestressed Concrete Containment Structures," January 1976.
'3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM LThe.48-inch containment purge supply and exhaust . isolation valves are
. required to'be closed during plant operation since these valves have-not been demo'strated n capable of. closing during a .LOCA or steam -line-break accident.
+
- Maintaining.these valves closed during plant operations ensures that excessive (quantities of radioactive materials will not be ' released via the containment-Lpurge. system.
The 'use of-the. containment purge lines is restricted to the 8-inch purge vis l supply:and exhaust isolation valves to ensure that the site boundary dose guide-111nes of 10CFR=Part'100 would not be exceeded in the~ event of a loss-of-coolant accident-during purging operations.
~
- FARLEY- UNITf1 B 3/4 6-2 AMENDMENT N0.
./
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, ~ AND AUXILIARY SUILDING
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PROPERTY WNE NOTE. set PSAR PfGUREI.14 PCR TCPOGRAPHICAL MAP OF SITE j .
Fign=e 5.1-3 Plant Farley Sita Nap Saseous Effluents FARLEY-UNIT 1 5-4 AMEEMDC E.
g 6 ..!L.."!!L8.55tT.11!'L'EL88.1818.e!E.T!n!9!!L* agy!:!!g13. A s
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Fifare 3.1-4 Plant Farley Site May -
Emslusica Area and Liquid Effisan.as FARLEY-UNIT 1 5-5 AMENDMENT N0.
i .
1 t
ADMINISTRATIVE CONTROLS gg .... .......... .......... . .
- e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
- f. . Solidification agent (e.g., cement, urea formaldehyde).
~The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.
The' radioactive effluent release reports shall include any changes to the-PROCESS C0.NTROL PROGRAM (PCP) made during the reporting period.
MONTHLY OPERATING REPORT .
6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 205S5, with a copy to the .
Regional 0ffice of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
- Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective. In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the change was implemented.
RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.11 The Fx limitforRatedThermalPower(Ffy P ) shall be provided to the Director of [he Regional Office of Inspection and Enforcement, with a copy to the Director, Nuclear Reactor Regulation, Attention Chief of the Core Performance Branch, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 for all core planes containing bank "D" control rods and all unrodded core planes at least 60 days prior to cycle initial criticality. In the event that the limit would be submitted at some other time during core life, it will be submitted 60 days prior to the date the limit would become effective unless otherwise exempted by the Commission.
Any information needed to support FkyP. will be by request from the NRC and need not be included in this report.
ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT 6.9.1.12 The number of tests (valid or invalid) and the number of failures to start on demand for each diesel generator shall be submitted to the NRC annually. This report shall.contain the information identified in Regulatory
- Position C.3.b of NRC Regulatory Guide 1.108, Revision 1,1977.
FARLEY - UNIT 1 6-19 -
AMENDMENT NO.
v.
. t,- ,'
ADMINISTRATIVE. CONTROLS e ,
.h. Records of annual physical . inventory of _all sealed source material of record.
6.10.2 The following records shall be retained for the ouration of'the Unit Operating License.
- a. Records an'd drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.
- b. ; Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
b
- c. Records of. radiation exposure for all individuals entering radiation control' areas.
- d. 'Re' cords of 'ga'seous' and liquid radioactive material released to the environs.
- e. Records of transient or operational cycles for those unit components identified in Table 5.7-1.
- f. ~ Records of reactor tests and experiments.
- g. -Records of training and qualification for current members of the facility staff.
h._' Records of in-service inspections performed pursuant to these Technical
-Specifications.
- 1. Records of _ safety-related Quality Assurance activities required by the Operations Quality Assurance Policy Manual (0QAPM) and not specifically described in Technical Specification 6.10.1.
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59.
- k. Records of meetings of the PORC and the.NORB.
- 1. Records of secondary water sampling and water quality.
- m. Records of analyse's required by the radiological environmental monitoring program.
- n. . Records of the service lives of all hydraulic and mechanical snubbers
_in service af ter.07-01-84 within the scope of 3/4.7.9 including the date at which the service life commences and associated installation
=and maintenance records.
. 6.11 RADIATION-PROTECTION PROGRAM Procedures for- personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered
. to for all operations involving personnel radiation exposure.
FARLEY- UNIT 1 6-21 AMENDMENT NO.-
+
u ,
n; . ,
~
.g ' I ~ y,u R %, .i.
~
IINSTRUENTATION 1 ~ . FIRE DETECTION INSTRUMENTATION
% 'l .- . -
LIMITING CONDITION'FOR_0PERATION: .
(3.3.3.9[Asf a' minimum, the' fire ~ detection instrumentation for each fire m -detectionfzone shown:in. Table 3.3-12 shall be OPERABLE.
JAPPLICABILITY: !.Wh'enever equipment protected by the fire detection
- instrument is; required to be OPERABLE.
- ACTION::
^
~
With the number of 0PERABLELfire detection. instrument (s) less than the
, , : minimum number _ .0PERABLE: requirement of _ Table 3.3-12:
,(
'~
~a. s Withinf1 hour-estdblish'~a. fire watch patrol to. inspect the zone (s)
. wi_th the inoperable instrument (s) at least once per hour, unless -
'the instrument (s) is located inside the containment, then monitor the' containment.' air _ temperature at least once per hour at the
' locations 111sted _ in Specification 4.6.1.5.
b.eRestore the inoperable; instrument (s) to OPERABLE status within 14 idays;or- prepare and-submit a Special Report to the- Commission pursuant to Specification 6.9.2 within the next 30 days outlining 2.' the action.taken,-the cause of the inoperability_and the plans'and c
schedule for: restoring the' instrument (s) to OPERABLE status.
m -c. ~ The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
/SORVEILLANCE:REQUI'REMENTS 4.3.3.9.1- Each~of the above required fire detection instruments which are
. accessible during plant' operation _shall _ be demonstrated.0PERABLE 'at tleast' Jonce' per.6 months by performance of!a function test which includes subjecting'the detector to test aerosol .or heat source..as appropriate. ,
? Fire detectors which are not accessible during plant operation.shall be '
r .-
~
demonstrated OPERABLE.by the performance of this functional test during
- each COLD SHUTDOWN. exceeding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sjunless performed in the previous 6 Emonths.~
. 4.3.3.9.2 : The NFPA Standard 72D supervised circuits supervision _ associated.
'with the detector alarms of each of the above required fire detection .
~. instruments shall. be demonstrated OPERABLE at .least once per. 6 months.
r t
-FARLEY-UNIT 2 3/4 3-59 AMENDMENT NO.
4 i ;
- 1 ~
t-TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION Auxiliary Building Total Minimum Rrom/ Smoke of Operable Fira Zone. Description Elevation Detectors Smoke Detectors 2128 RHR Heat Exchanger Room 83'-0" 10 5 2129 RHR Low Head Pump Room 77'-0" 1 1 2131 RHR Low Head Pump Room 77'-0" 1 1 2160 Hatch Area 100'-0" 2 1 2161 South Corridor 100'-0" 2 1 2172 Hallway 100'-0" 3 2 2173 Charging /SI Pump Room 100'-0" 2 1 2174 Charging /SI Pump Room 100'-0" 2 1 2175 Hallway 100'-0" 2 1
.2181 Charging /SI Pump Room 100'-0" 2 1 2184 Mechanical Penetration Room 100'-0" 8 4 2185 CCW Heat Exchanger and Pump 100'-0" 13 7 2186 Boric Acid Trans. PPS 100'-0" 3 2 2188 Boric Acid Tanks 121'-0" 2 1 2190 MCC Panel Room 100'-0" 4 2 2191 Auxiliary Feedwater Pump Room 100'-0" 1 1
.2192- -Auxiliary Feedwater Pump Room 100'-0". 1 1 2193 Auxiliary Feedwater Pump Room 100'-0" 2 1 2202 Hot Shutdown Panel Room 121'-0" 4 2 2208 Corridor 121'-0" 2 1 2209 Hallway 121'-0" 3 2 2210 South Corridor 121'-0" 2 1 2212 Battery Room 2B 121'-0" 1 1 2213 Battery Service Room 121'-0" 1 1 2214 Battery Room 2A 121'-0" 1 1 2223 Mechanical Penetration Room 121'-0" 9 5 2224 DC Switchgear Room 121'-0" 1 1 2226 DC Switchgear Room 121'-0" 1 1 2227 West Cable Chase 128'-0" 7 4 2229 AC Switchgear Room Train B 121'-0" 4 2 2233 AC Switchgear Room Train B 121'-0" 3 2 2241 Main Steam and FDW Valve Room 127'-0" 8 4 2244 Mezzanine 131'-0" 3 2 2245 Mezzanine 131'-0" 2 1 2254 Hot Shutdown Panel Room 121'-0" 1 1
.2300 West Cable Chase 139'-0" 7 4 2309 Hatch Area 139'-0" 1 1 2312 Corridor 139'-0" 4 2 2316 Corridor 139'-0" 2 1 2318 Cable Spreading Room 139'-0" 8 4 2319 West Corridor 139'-0" 2 1 2333 Electrical Penetration Room 139'-0" 1 1 2334 Electrical Penetration Room 139'-0" 3 2 2335- AC Switchgear Room Train A 139'-0" 3 2 2343 AC Switchgear Room Train B 139'-0" 3 2 2347 Electrical Penetration Room 139'-0" 2 1 FARLEY - UNIT 2 3/4 3-60 AMENDMENT NO.
TABLE 3.3-12 FIRE DETECTION' INSTRUMENTATION (continued)
Auxiliary Building Total Minimum
. Room /. .
Smoke of Operable Fire Zone Description Elevation Detectors Smoke Detectors 2401~# Control Room (above ceiling) 155'-0" 8 4 2401 #, Control-Room (below ceiling) 155'-0" 6 3 155'-0"
~
2452' ; Storage Area 7 4
- 2462 Non-Radioactive Vent Equip. Rm. 155'-0" 5 3 L2466 ' West-Cable Chase .
155'-0" 7 4 2471'# Ctrl. Rm. Inst. Racks (above/ ceil.) 155'-0" 8 4
-2471;#- Ctrl. -Rm. Inst. Racks (below/ ceil .) 155'-0" 6 3
-2500 West Cable Chase 168'-2" 7 4 Cintainment* . .
55- Containment Coolers 155'-9" 12/ Fan 6/ Fan
'55 Containment 155'-0" 14 7
- Service Water Intake Structure L72 A**. Pump Room Area 188'-9" 12 6 72-A**. Strainer Bay 167'-0" 18 6 72'B2*- Switchgear Room - Train B 188'-9" 3 2
-72 Ca*: Foyer - Train B 188'-9" 1 1 72'D**: Foyer - Train A 188'-9" 1 1 72 E** Switchgear Room - Train A 188'-9" 3 2 73 ** . Battery Room - Train B- 188'-9" 1 1 74 -** Battery Room - Train A 188'-9" 1 1 Dicsel Generator Building 56 A Switchgear Room - Train A 155'-0" 12 6 56 B Foyer ' 155'-0" 4 2 56 C' Switchgear Room - Train B 155'-0" 12 6 71~ Hallway 155'-0" 9 5 Diesel Generator Building (Heat Detectors) 57 Diesel Driven Generator 2C. 155'-0" 5 3
'59 . Diesel Driven Generator 2B 155'-0" 5 3
- 60 Diesel Driven Generator 1C 155'-0" 5 .3 61 Diesel Driven Generator 1-2A 155'-0" 5 3 62 Day Tank Room 2C 155'-0" 1 1 164 Day Tank Room 2B 155'-0" - 1 1 65 Day Tank Room IC 155'-0" 1 1
.66 Day Tank Room 1-2A 155'-0" 1 1
-# These circuits alarm in the Unit I control room area, but service Unit 2 only and appear 1 only in the Unit 2 Technical Specifications.
- The Fire Detection instruments located within the Containment are not required to be
~
'0PERABLE during the performance of Type A Containment Leakage Rate Tests.
'Co These circuits alarm in the Unit 1 control room area but service both units, and appear:in the Technical . Specifications for both units.
FARLEY-UNIT 2 3/4 3-60a AMENDMENT NO.
r; av ,. .-
1 i
- EDERGENCY CORE COOLING SYSTEMS
, LSURVEILLANCE' REQUIREMENTS,
- 4.5.3.1V The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of_4.5.2.
.4.5.3.2. At ,least once per 31 days verify that.the following valves.are in the_.. indicated position with the breaker or disconnect device for the valve operator . locked open:
~
Valve Number ,
~ Valve Function Position 4 :8706 A, 8706 8 -RHR pump discharge to Closed chargingpumpjsuction 8884, 8886 Charging pump discharge Closed
, to RCS hot legs t
1 a
/
d FARLEY-UNIT,2 3/4 5-8 AMENDMENT NO.
1
m
. . l l
PLANT SYSTEMS
_ l 1
3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7 Two independent control room emergency air cleanup systems shall be OPERABLE.
APPLICABILITY: ALL-MODES.
ACTION:
MODES 1, 2,'3 and 4:
With one control room emergency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY withia the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MODES S and 6 (during irradiated fuel movement, or movement of loads over irradiated fuel):
- a. With one control room emergency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the control room emergency ventilation system in the recirculation mode.
- b. With both control room emergency air cleanup systems inoperable, suspend all operations involving the movement of irradiated fuel or movement of loads over irradiated fuel,
- c. The provisions of Specification 3.0.3 are not applicable in MODE 6.
SURVEILLANCE REQUIREMENTS 4.7.7 Each control room emergency ventilation system 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 that the control room air temperature is less than or equal to 120"F.
- b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the pressurization and recirculation system HEPA filters and charcoal adsorbers and verifying that the pressurization system has operated for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heater on during the past 31 days.
- c. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release that could have contaminated the charcoal adsorbers or HEPA filters in any ventilation zone communicating with the system by:
FARLEY-UNIT 2 3/4 7-16 AMENDMENT NO.
~ PLANT SYSTEMS
. _ SURVEILLANCE REQUIREMENTS (Continued)
=
- 3. Verifying that the system maintains the control room at a positive pressure-of greater than or equal to 1/8 inch water. gauge relative to the. outside atmosphere during system operation.
- 4. Verifying that the pressurization system heater dissipates 7.5 +
0.8 kw 'when tested in accordance with Section 14 of ANSI N510-f780.
.f. After_ each complete or partial' replacement of a HEPA filter bank by verifying.that the HEPA filter banks remove greater than or equal to 99.5% of the DOP when they are tested in-place in accordance with Section 10 of ANSI N510-1980 while operating the system at a flow rate indicated in Note 1.
- g. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal '
<to 99.5% of a .halogenated hydrocarbon refrigerant test. gas when they are tested in-place in accordance with Section 12 of ANSI N510-1980 while operating the system at a flow rate. indicated in Note 1.
Note 1. a. Control Room Recirculation Filter Unit 2000 cfm + 10%
- b. ~ Control Room Filter Unit 1000 cfm T 10%
-c. Control Room Pressurization Filter Unit 300cfmi10%
. Note 2. a. Control. Room Recirculation Filter Unit > 99%
H
- b. Control Room Filter Unit T 99%
- c. Control Room Pressurization T 99.825%
-FARLEY-UNIT 2 3/4 7-17a AMENDMENT NO.
_a
r
' PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- b. At least once per 92 days by verifying that a sample of diesel feel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within' the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.
- c. At least once.per 18 months by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.
4.7.11.1.3 The ' fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:
.a. At least once per-7 days by verifying that:
- 1. The electrolyte level of each battery is above the plates, and
- 2. The overall battery voltage is greater than or equal to 24 volts.
- b. At-least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery.
- c. At least once per 18 months by verifying that:
- 1. The batteries and battery racks show no visual indication of physical damage or abnormal deterioration, and
- 2. The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.
FARLEY-UNIT 2 3/4 7-54 AMENDMENT NO.
I L.
m<
TABLE 3.7-5
, LIST-0F SPRINKLER SYSTEMS Location .
' Sprinkler
. Riom / Fire Zone Description Elevation System Auxiliary Building-
~2160 Hatch-Area 100'-0" 2A-25 2161 South Corridor 100'-0" 2A-25 2172 Hallway 100'-0" 2A-101
'2175 Hallway' 100'-0" 2A-118 2185 CCW Heat Exchanger and Pump Room. 100'-0" 2A-27 2190 MCC Panel Room 100'-0" '2A-62 2209 . Hallway 121'-0" 2A-35 2210 , South Corridor 121'-0" 2A-36 2223- Mechanical Penetration' Room 121'-0" 2A-45 2227 ~ West Cable ' Chase 128'-0" 2A-23 131'-0" 2A-36 12244 Mezzanine
-22451 Mezzanine 131'-O' 2A-36 2300' ' West Cable Chase 139'-0" 2A-23 2312 Corridor 139'-0" 2A-48
-2316 Corridor 139'-0" 2A-48
-2318 Cable Spreading Room 139'-0" 2A-43 2319 West Corridor 139'-0" 2A-59
'2452- Clean Storage Area 155'-0"' 2A-52 2462 Non-Radioactive Vent Equipment Room 155'-0" 2A-51 155'-0"
~
> 2466 West Cable Chase 2A-23 2500- West Cable Chase 168'-2" 2A-23
. ~ Service Water-
' Intake Structure
-7 72A Service Water Pump Protection 102'-0" _ISW-111 72A: Service Water Pump Deck and 188'-9" & 1SW-111A' Strainer Pit, East Side 167'-0" 72A Service Water Pump Deck and 188'-9" & 1SW-111B
- Strainer _ Pit, West Side 167'-9" t
c 1
'FARLEY _ UNIT 2 3/4 7-57 AMENDMENT N0.
c-
m 7
u ' PLANT SYSTEMS 0
?C02 SYSTEMS ,
LIMITING CONDITION-FOR OPERATION 13'.7.11.3:'The following high pressure and. low prassure CO2 systems shall be
~
4 OPERABLE. ,
as ' Service Water. Int'ake Structure-(each 4160 volt bus and each 600 volt
. load center) - H.P. .t b.. Turbine' Building 13 ton unit and distrib'u tion system in the Auxiliary J Building - L.P.
.c. Diesel Building 5 ton ' unit and distribution system.
. APPLICABILITY: . Whenever equipment protected by the CO2 systems is required to
-be OPERABLE.
m ' ACTION:-
- a. With one or.more of the above required C02 systems inoperable,-witihin
- one hour establish a continuous' fire watch with . backup fire suppression.
equipment for. those areas in which redundant ' systems or components could be damaged; for other areas, establish an hourly fire watch patrol. LRestore the system to OPERABLE status-within.14 days or.
) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause'of the inoperability and the plans and schedule for restoring
.the system to OPERABLE status.
-b. The provisions of Sp.ecifications 3.0.3 and 3.0.4 are not applicable..
SURVEILLANCE REQUIREMENTS 4.7.11.3.1 Each 'of the above required CO2 systems shall be demonstrated
~ 0PERABLE at least once per 31' days by verifying that each manual valve in the-
.. flow path is -in 'its correct position.
4.7.11.3.2 Each of the above required low pressure CO2 systems shall be
' demonstrated OPERABLE: I
- a. gat- least once per 7 days by verifying the' CO2 storage tank. level to be-
. greater than 50% and pressure to be greater than 250 psig, and ub. . At ;least once per'18 months by verifying:
~ 1. :The : system > valves and associated ventilation dampers and fire door.
. ' release mechanisms-actuate manually and automatically, upon receipt.
y of'a simulated actuation signal, and
- 2. . Fl ow during a' "Puf f . Test." ,
FARLEY-UNIT 2 3/4 7 AMENDMENT N0.
s d
, . f .x j
y PLANT-SYSTEMS-SURVEILLANCE. REQUIREMENTS (Continued) 4.7.11.3.3 Each'of.the above required high pressure CO2 systems shall be demonstrated OPERABLE:
- a. At least once per 6 months by verifying the CO2 storage tank weight to
'be at least 90% of full charge weight.
- b. At least once per 18 months by:
- 1. Verifying the system, including associated ventilation dampers and fire door release mechanisms, actuates manually and automatically, upon receipt of a simulated actuation signal, and
- 2. Verifying flow during a " Puff Test".
l
'FARLEY-UNIT 2 3/4 7-59 AMENDMENT NO.
- i
p TABLE 3.7-6
. LIST OF FIRE HOSE. STATIONS-AUXILIARY BUILDING LOCATION (Room No.~) ELEVATION HOSE CABINET NO.
^
2103 83'-0" N2V43-D-103 2110 83'-0" N2V43-D-102 7.161 100'-0" N2V43-D-110 2163' 100'-0" N2V43-D-109 2184 100'-0" N2V43-D-124 2185 <
100'-0" N2V43-D-108 2186- 100'-0" N2V43-D-131 2189 100'-0" N2V43-D-107-2208 121'-0" N2V43-D-128 2209 121'-0" N2V43-D-104 2210 121'-0" N2V43-D-126 2223' 121'-0" N2V43-D-127 2234' 121'-0" N2V43-D-125 2237 ~121'-0"' N2V43-D-132 2312 139'-0" N2V43-D-114 42316 139'-0" N2V43-D-111 2319 -139'-0" N2V43-D-116 2319 139'-0" N2V43-D-119 2332 139'-0" N2V43-D-113 2334' 139'-0" N2V43-D-117 2345- 139'-0" N2V43-D-112 2409 155'-0" N2V43-0-122 2409- 155'-0" Containment Fire Hose
- Storage Locker
-2408 155'-0" N2V43-D-123 2446 155'-0" N2V43-D-105 2452 155'-0" N2V43-D-120
'2453 155'-0" N2V43-D-121 H
2462 155'-0"- N2V43-D-106
, 2502 175'-0" N2V43-D-101 2505 184'-0" N2V43-D-100 2602 130'-0" N2V43-D-118 AUXILIARY BUILDING TO DIESEL GENERATOR BUILDING TUNNELS TRAIN A TUNNEL- TRAIN B TUNNEL HOSE' CABINET N0. H0SE CABINET NO.
N2Y430001A N2Y430001P LN2Y430001B N2Y43D001Q N2Y43D001C N2Y43D001R N2Y430001D N2Y430001S l l
N2Y430001E N2Y43D001T N2Y430001F. N2Y43D001U
-N2Y430001G N2Y43D001V N2Y43D001H N2Y430001W N2Y43D001J N2Y43D001X N2Y43D001K N2Y43D001Y N2Y43D001L N2Y43D001Z N2Y43D001M N2Y43D002A N2Y43D001N N2Y43D002B
- The requirements of Specification 4.7.11.4 Item (c)(1) are not applicable.
FARLEY - UNIT 2 3/4 7-61 AMENDMENT N0.
, 1. ,:
Table 3.7-6'(Continued)
LIST.0E FIRE H0SE STATIONS
.' HOSE CABINET
= ~ . LOCATION (Room No.) ELEVATION ISOLATION VALVE NO.
JContainment'
---. 105'-6" N2T43V001*
105'-6" N2T43V002*
-- . 105'-6" N2T43V003*
. -- . 105'-6" N2T43V004*
---v ' ~
129'-0" N2T43V005*-
155'20" 'N2T43V006*
155'-0" N2T43V007*
, ~--- 155'-0" N2T44V008*
1
/
J
- Only -the requirements of Specification 4.7.11.4 Item (c)(1) are applicable.
i
- FARLEY ' UNIT 2 3/4 7-61a AMENDMENT NO.
TABLE'3.7-7 j t
YARD FIRE. HYDRANTS-AND ASSOCIATED HYDRANT HOSE HOUSES 4
'^
u LOCATION HYDRANT NUMBER
'1._ Northeast of Auxiliary -Building - N1Y43V105
- - ~ 2. . Northwest of - Auxiliary Building N1Y43V102
- 3. West of Auxiliary Building - N1Y43'V103*
- 4. : ' North?of. Diesel. Generator Building N1Y43V120*
iY .5. ' East of Service Water Intake N1Y43V121*
7 ~ 6 ~.7 West of-Service Water Intake N1Y43V122*
-1 4
4 T
fi
,i.
,
- Shared between Unit 1 and Unit 2 FARLEY1- UNIT 2' 3/4 7-63 AMENDMENT.NO.
._ ,2 I. __
p
, .j ELECTRICAL POWER ~ SYSTEMS 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES
-CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT-PROTECTIVE DEVICES
' ; LIMITING CONDITION FOR :0PERATION .
L 3.8.3.1._- All containment' penetration conductor overcurrent protective devices
.shown in' Table:3.8-1 shall be OPERABLE. Circuits of devices indicated in Table
'3.8-1-by~an asterisk-(*) shall be deenergized.-
O APPLICABILITY: , MODES-1, 2, 3 and 4
. ACTION:.
- With.one or more of the containment _ penetration conductor overcurrent protective
- devices shown in Table 3.8-1 inoperable:
a; Restore the protective-device (s) to OPERABLE status or deenergize the circuit (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; the provisions of ' Specification 3.0.4 are -
not applicable to overcurrent devices in circuits which are deenergized, or b.-' Be in_ at least H0T STANDBY 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 COLD SHUTDOWN within the following 30. hours.
With one.or more of the containment penetration conductor overcurrent protective
'. devices-indicated by an. asterisk (*) in Table 3.8-1 energized except as shown:
a.. Deenergize the circuit (s)~ within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or
- b. . -Be'in at least H0T. STANDBY 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 COLD SHUTDOWN within.'the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
~
SURVEILLANCE-REQUIREMENTS-14.8.3.1.1 Circuit. breakers shown in Table 3.8-1 -shall be demonstrated OPERABLE:
- a. . AtLleast; once.per 18. months:
' 1. - For at-least one 4.16 KV reactor coolant pump circuit, such that all reactor coolant pump circuits 'are demonstrated OPERABLE at
'least once per.54 months, by performance of:
L(a) A CHANNEL CALIBRATION of the associated protective relays, and (b) An integrated system. functional test which includes simulated automatic actuation of-the system and verifying that each relay and associated circuit breake'rs and control circuits function as designed and-as specified in' Table 3.8-1.
2:
.FARLEY-UNIT 2 3/4 8-18 AMENDMENT NO.
' ; ,- ..- . O ELECTRICAL' POWER--SYSTEMS:
~
1
. SURVEIL' LANCE REQUIREMENTS /(Continued)
' ~
- (c) For each circuit' breaker found inoperable during these -
- functional tests, an' additional representative sample of at
.. e -least one of the circuit breakers of.the inoperab el type shall also be functionally; tested until no more failures are-found
-or allacircuit breakers of that type have been functionally
~ tested..
': 2. : By1 selecting and functionally testing a representative sample of at least 10% of each type ofulower voltage circuit breakers. Ci rcuit
- breakers selected for functional testing'shall be selected on a
- rotating basis. The functional _ test shall consist of injecting a current inputJat the specified-setpoint-to each selected circuit
~-
. breaker and verifying that each circuit breaker functions as 9 designed. For each ' circuit breake'r found inoperable during these functional ~-tests, an additional. representative sample of at least 10%-of all .the circuit. breakers of the inoperable type shall also .
~
be functionally tested until no more failures are found or all 4
' circuit breakers of that type have been functionally tested.
7.
b.-~ ~ At least.once per 60 months by subjecting each-circuit breaker to an -
inspection 'and preventive'_ maintenance in accordance with procedures
-prepared-in conjunction with its manufacturer's recommendations.
.- 4.8.3.1.2 . Power sources feeding circuits indicated by an asterisk (*), in Table 3.8-1 except as shown shall be verified-to be interrupted by an open breaker or -
< removed fuse 'at least. once 'every 31 days.
- 4.8.3.1.3. ; Verify, at 'least once per.18 months, proper fuse sizes for fuses .
~
- i denti fied ,in ' Table -3.8-1. -
~ ;e
't n
l 4
(FARLEY-UNIT 2 3/4 8-19 AMENDMENT NO.
v I
, , s rw-e ,,n- .se,,,,,, ,w,-n n , , , - +my ~r r--,+ a.<A----~-,---,.- -.m,em -mm -,w-w--,A emwe r o- ~ -
r-4 f.:
' TABLE 3.8-1~
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT' PROTECTIVE. DEVICES s
- The tabulation of' containment penetration conductor- overcurrent ' protective
-devices .which are within the scope of Technical Specification 3.8.3.1 are
' contained'in Farley Nuclear Plant" procedures.1The procedures include, as a base
-:line, the'overcurrent: protection-devices identified as of License Amendment 34.
, ' The procedures will be controlled in'accordance with 10CFR50.59.
n.
Pages 3/4 8-212 through 3/4 8-280 have been deleted -in their entirety.
~
5 ,
e 4
5 f.',
+
Y d
4 t
1 ,
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.{~
-FARLEY~-' UNIT l2 3/4 8-20 AMENDMENT NO.
f P =
. :i: \
~ sc =.
fREFUELING-0PERATIONS'
-g s
13/4.9.14 CONTAINMENT PURGE EXHAUST FILTER
' LIMITING. CONDITION FOR OPERATION
~
L3.9114 ~ . The containment' purge exhaust' filter shall be OPERABLE and . valve
.N2P13V293 closed.
' APPLICABILITY:' .During COREfALTERATIONS an'd Fuel Movement inside containment
' with any containment purge isolation valve open.
fACTIONi Withithe containment purge. exhaust filter inoperable.either:
l' . Immediately=close~ the 48 inch containment purge isolation valves 1(CBV-HV-3196',- 3197,- 3198A and - 31980) and ' the 8 i nch . containment -
- + mini-purge isolation: valves (CBV-HV-2866C, 2866D, 2867C and 28670), or -
- 2. ; Cease all CORE ALTERATIONS and fuel movement. -
SURVEILLANCE REQUIREMENTS ,
4 24;9.14 d Theiabove required containment purge exhaust filter-shall be
- demonstrated OPERABLE:
- a. At least'once:per 18 months .or (1) after any structural maintenance on
'the HEPA filter! or~ charcoal .adsorber housings, or (2) following painting,' fire or chemical release that-could have contaminated the
- charcoal adsorbers,or HEPA-filter in any ventilation-zone communicating
- with' the system'by
s 4,
- FARLEY-UNIT'2- 3/4 9-16 AMENDMENT N0.
V
1 J %
- -- , - . . , -n
~s .
~
m' . ,
, .. 1 Table 4.11-1 (Continu:d)
LTABLE'N0TATION b.. A' composite-sample is:one in which:the quantity of liquid! sampled is
^
proportional to the. quantity of tliquid waste. discharged and'in.which
.the method of ~ sampling employed results in:a' specimen which-is..
. rep'resentative of the liquids _ released. Deviations from composite
- sampling requirements shall be reported per Specification 6.9.1.8.
~
- c., A batch release isLthe discharge of liquid wastes 'of a discrete
. , volume. Priorf to sampling for, analyses, each-batch shall be isolated,
.and_ then thoroughly mixed, by.a method described in the' 00CM, to assure
, : representative sampling.
- d. A continuous release'is the discharge of liquid wastes of a nondiscrete
- volume; e.g., from a volume of system that has an input flow during the Veffluent release.-
- e. ?The principal- gamma ' emitters.for-which the MDC specificat' ion applies exclusively, are _the .following ~ radionuclides: Mn-54, Fe-59,.Co-58,
-Co-60,LZn-65, Mo-99, Cs-134, Cs-137, ice-141, and Ce-144. This list (does not'mean that only these;nuclides are to be detected and reported. :0ther peaks which'are' measurable and identifiable, together
- with the above nuclides, shall also be identified and reported.
, if. Sampling ~wil.1 -be performed only iff the effluent _will be discharged to
-the environment.-
. L g. _' Deviation from the' MDC requirements lof Table-4.11-1 shall be reported per- Specification 6.9.1.8.
y
! A
+
t w
D'..
1
[ 5-FARLEY-UNIT 2 - 3/4 11-4 AMENDMENT N0.
=
T
~
Y
7,j. .
^ '*
g.;
im
,;lb qf g_,
JTABLE:4d1E A f ,
- q ^
'[ ' y j;I((
t
^RADI0 ACTIVE GASEQUS WASTE ~SAW LING'AND ANALYSIS PROGRAM. m- Y 7: ,
.f
. : je L -
' J.Q , .1 iMinimum . . . .
Minimum Detectable:- f Analysisf
~ ~
Gaseous Release. Type : Sampling l : ..
Type ~of.. LConcentration (MDC) c , Frequency- Frequency. E Activity. AnalysisD _
1/ml)a n z
G _
.P P ,
N ro A. Waste' Gas Storage. Each Tank: Grab Each: Tank Principal . Gamma Emitters 9 d ~1x10-41 -
Tank. Sample-P .P _
s B. Containment Purge Each Purgeb ; - Each Purge - b.- - Principal Gamma Emitters 9 j ' 1'x10-4.
Grab Sampie:
, H-3' .
11x1.0 6-8 C. Condenser Steam Jet Mb c.e Mb Principal Gamma Emitters 9 ji 1x10 '
' Air Ejector, Plant : Grab . ,
- Vent Stack Sample ' 1 H 1x10 ;
w '*
5 D. Plant Vent Stack,- Continuousf Wd 'I-131 1x10-12 p Containment Purge Charcoal -
Charcoal 4
Sample I-133 1x10-10 Continuousf iW. d ' Principal Gamma Emitters 9 1x10-ll Pa rticulate Sample Continuousf M. Gross Alpha 1x10-ll Compositei
.Pa rti culate Sample Continuousf- Q- Sr-89, Sr-90 1x10-ll 3
Compositei
- : Particulate s 3 Sample l
Continuousf Noble. Gas Noble Gases. -
1x10-6 y Monitor Gross Beta and' Gamma ~
-i 1
! i
- j. c. .
p 4yy qw - - , - - - . >y-- - - - . y-w- % ,' f y-
p Table 4.11-2'(Continued)
- l TABLE-NOTATION p b. Analyses shall also be performed following shutdown from > 15% RATED
[ THERMAL POWER, startup to > 15% RATED THERMAL POWER or a THERMAL POWER l . , change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.
- c. LTritium grab samples shall be taken from the plant vent stack at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
- d. Samples shall. be changed at least .once per 7 days and analyses shall be
! completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler) . Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 2 days following each shutdown from > 15% RATED THEiMAL POWER, startup to > 15% RATED THERMAL POWER or THERMAL POWER chE nge
. exceeding 15 perceiit of RATED THERMAL POWER in one hour and anasyses
. shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed,-the corresponding MDC may be increased by a factor of 10.
- e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel
-is in the spent fuel pool.
- f. The ratio of the sample flow rate to the sampled stream flow rate shall
- be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2
.and 3.11~.2.3.
- g. The principal gamma emitters for which the MDC specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60,- Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for, particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides shall also be identified and reported.
- h. - Deviations from MDC requirements of Table 4.11-2 shall be reported per
-Specification 6.9.1.8.
' ~, 1. A composite particulate sample is one in which the quantity of air sampled is proportional to the quantity of air discharged. Either a specimen .which is -representative of the air discharged may be accumulated and analyzed or the individual samples may be analyzed and weighted in proportion to their respective volume discharged.
~
Deviations from composite sampling requirements shall be reported per Specification 6.9.1.8.
7 p j. The principal gamma emitters for which the MDC specification applies r- exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, L Xe-133m, Xe-135 and Xe-138 for gaseous emissions. This does not mean
! that only these nuclides'are to be detected and reported. Other peaks g which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
.FARLEY-UNIT 2 3/4 11-11 AMENDMENT N0.
l~
b
7_ _ _ .
BASES w The surveillance requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one representative sample of each manufacturers brand of circuit breaker. Each manufacturer's molded case and metal case circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested. If a wide variety exists within any manufacturer's brand of circuit breakers, it is necessary to divide the manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes.
The surveillance requirements applicable to fuses provide assurance of fuse reliability by verifying proper fuse size periodically.
The OPERABILITY of the motor operated valves thermal overload protection devices ensures that these devices will not prevent safety related valves from performing their function. The Surveillance Requirements for demonstrating the
'0PERABILITY of these devices are in accordance with Regulatory Guide 1.106
" Thermal Overload Protection for Electric Motors on Motor Operated Valves",
Revision 1, March 1977.
FARLEY-UNIT 2 B 3/4 8-2 AMENDMENT NO.
..- =
g' I.
n . .
w , PROPERTY LINE,(SITE BOUNDARY FO,R GASEOUS _ EFFLUENTS)
N M,M g[ METEOROLOGICAL TOWER
\
N 287,000 .
{ N I i ELEVATION PPROX 150 FT 6
BOTH UNITS, %. ,
RELEASE POINT
, UNIT NO.2 CONTAINMENT ELEVATION . APPROX 300 FT.
AND, AUXILIARY BUILDING '
4240 p7
, \ UNIT.2 CONTAINMENT VENT $
CO TAINME VENT # RO FT /
/ MNIT NO.1 A CONTAINMENT AND
[ AUXILIARY [
TEAINING/ EOF. CENTER , -
BUILDING '
f RIVER 7 INTAKE \
i g SERVICE WATER g INTAKE STRUCTURE
\*
1
-i L __. ;
RESERVOIR t
i -
/
/
PROPERTY LINE NOTE:SEE FSAR FIGURE 2.14 FOR TOPOGRAPHICAL MAP OF SITE
, Figure 5.1-3 Plant Farley Site Map Gaseous Effluents .
FARLEY-UNIT 2 5-4
- o .' .
f .
PROQRTY LINE1Sf7E SOUNDARY POR LIQUID,EP, FLUENT 3) ,
N 288,000 ' $ Ns METEOROLOGICAL TOWER N 287,000 ,
i T _ .
i i , ,
s g\
' UNIT NC. 2- CONTAINMENT 1
AND AUXILIARY SUILDING f,
a f WASTE LINE UNIT NO.1 g
'
- y
" WASTE LINE UNTT NO.1 7 (
/ '
UNIT NO.1 CONTAINMENT AND -
[
[ TRAIN %NG/ EOF CENTER _
AUX 1LIARY [
- SUILDING f
RIVER ' 7 INTAKE j SERVICE WATER - STRUCTURE $1FFUSION INTAKE STRUCTURE PIPE INTO
\
i RIVER N200800
\ '
~
{
{"'
.A.TE /
OlSCHARGE I :
RESERVol8 POINT I
\ '
.j i
~~ ~
PROPEdY LINE
'~
~~ j ~
i Figure 5.1-4 Plar. Farley site kap Ex=1usion Area and Liquid Effluents FARLEY-UNIT 2 5-5 ^" " *
,_+,
-ADMINISTRATIVE' CONTROLS
- e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
- f. - Solidification agent (e.g., cement, urea formaldehyde).
The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.
The radioactive effluent release reports shall include any changes to the PROCESS CO.NTROL PROGRAM (PCP) made during the reporting period.
MONTHLY OPERATING REPORT .
6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the .
Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective. In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the. Monthly Operating Report for the period in_ which _the changt. was implemented.
RADIAL PEAKING FACTOR LIMIT REPORT RTP 6.9.1.11 The Fx limit for Rated Thermal Power (Fxy ) shall be provided to the Director of fhe Regional Office of Inspection and Enforcement, with a copy to the Director, Nuclear Reactor Regulation, Attention Chief of the Core Performance Branch, U.S. Nuclear Regulatory Comission, Washington, D.C. 20555 for all core planes containing bank "D" control rods and all unrodded core planes at least 60 days prior to cycle initial criticality. In the event that the limit would be submitted at some other time during core life, it will be submitted 60 days prior to the date the limit would become effective unless otherwise exempted by the Comission.
RTP Any information needed to support Fxy . will be by request from the NRC and need not be included in this report.
i
- ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT 6'.9.1.12 The number of tests (valid or invalid) and the number of failures to start on. demand for each diesel generator shall be submitted to the NRC annually. This report shall contain the information identified in Regulatory Position C.3.b of NRC Regulatory Guide 1.108, Revision 1,1977.
FARLEY - UNIT 2 6-19 AMENDMENT NO.
iga.g ,
l7 . ADMINISTRATIVE CONTROLS' L h.. Records of annual physical inventory of all sealed source material of record.
- 6.10.2. - The following. records shall be retained ~fot 'he duration of the Unit Operating License.
' ~
- a. Records and drawing changes reflecting unit design-modifications made to systems and equipment described in the Final Safety Analysis Report.
- b. Records of new and irradiated fuel inventory, fuel transfers and assembly.burnup histories,
- c. ~ Records of radiation exposure for all individuals entering radiation control areas. '1;,
- d. Records of gaseous and liquid radioactive material released to the environs.-
- e. Records of transient or operational cycles for those unit components identified in Table 5.7-1.
- f. Records of reactor tests and experiments.
.g. Records of training and qualification for current members cf the facility: staff.
k h. Records of in-service inspections performed pursuant to these Technical Specifications.
- 1. Records of safety-related Quality Assurance activities required by the Operations Quality Assurance Policy Manual . (0QAPM) and not specifically described in Technical Specification 6.10.1. ,
J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59.
- k. Records of meetings of the PORC and the NORB.
- 1. Records of secondary water sampling and water quality.
- m. Records of analyses required by the radiological environmental monitoring program.' ;
.'n. Records of the = service lives of all hydraulic and mechanical snubbers '
within the scope of 3/4.7.9 including the date at which the service life commences and associated installation and maintenance records.
6.11 RADIATION PROTECTION PROGRAM
_ Procedures for personnel radiation protection shall be prepared consistent with
- the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
- FARLEY- UNIT 2 6-21 AMENDMENT NO.
O _. ~ ._