ML20237G961
| ML20237G961 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/28/1987 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20237G919 | List: |
| References | |
| TAC-66054, NUDOCS 8709030051 | |
| Download: ML20237G961 (66) | |
Text
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LIMITING CON 0!TIONS FOR OPERATION AND_ SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4 3-60 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.............
METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE TABLE 4.3-5 3/4 3-61 REQUIREMENTS..........................................
3/' 3-62 Remote Shutdown System...................................
3/4 3-63 TABLE 3.3-3 REMOTE SHUTDOWN MONITORING INSTRUMENTATION............
TABLE 4.3-6 REMOTE SHUTOOWN MONITORING INSTRUMENTATION 3/4 3-64 SURVEILLANCE REQUIREMENTS................................
3/4 3-65 Accident Monitoring Instrumentation......................
3/4 3-66 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION..................
TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE 3/4 3-68 REQUIREMENTS.............................................
3/4 3-70 Chlorine Detection Systems...............................
,in n._ ~...:..
gfg,y 3/4 72 TABL; 3.3 11 'IRC ::T'.~.TIL U;',T R',~.:TATION..........
3/4 3-77 Loose-Part Detection System..............................
Radioactive Liquid Effluent Monitoring Instrumentation...
3/4 3-78 TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-79 TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING.
3/4 3-S1 INSTRUMENTATION SURVEILLANCE REQUIREMENTS................
Radioactive Gaseous Effluent Monitoring Instrumentation..
3/4 3-B3 TABLE 3.3-13 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING 3/4 3-84 INSTRUMENTATION..........................................
TABLE 4.3-9 RADI0 ACTIVE GASECUS EFFLUENT MONITORING 3/4 3-88 INSTRUMENTAL 10N SURVEILLANCE REQUIREMENTS...............
3/4 3-91 3/4.3.4 TURBINE OVERSPEED PROTECTION..............
3/4.A REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION 3/4 4-1 Startup and Power Operation.............................
3/4 4-2 Hot Standby..........................
3/4 4-3 Hot Shutdown.................................
3/4 4-5 Cold Shutdown - Loops Filled.............................
3/4 4-6 Cold Shutdown - Loops Not Fi11ed.........................
8709030051 G70828 PDR ADOCK 05000413' PDR p
CATAWBA - UNITS 1 & 2 VI
LfMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION Divider Barrier Personnel Access Doors and 3/4 6-47 Equipment Hatches......................................
Containment Air Return and Hydrogen Skimmer Systems......
3/4 6-48 Floor 0 rains.............................................
3/4 6-50 3/4 6-51 Refueling Canal 0 rains...................................
Divider Barrier Sea 1.....................................
3/4 6-52
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TABLE 3.6-3 OIVIDER BARRIER SEAL ACCEPTABLE PHYSICAL PROPERTIES...
3/4 6-53 3/4.6.6 CONTAINMENT VALVE INJECTION WATER SYSTEM................
3/4 6-54 3/4.7 PLANT SYSTEMS 3/4.7.1 TURSINE CYCLE Safety Va1ves............................................
3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVC OURING FOUR LOOP 0PERATION......................................
3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................
3/4 7-3 Auxiliary Feedwater System...............................
3/4 7-4 Soecific Activity........................................
3/4 7-6 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.....................................
3/4 7-7 Main Steam Line Isolation Va1ves.........................
3/4 7-S Condensate Storage System................................
3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LI!1ITATION..
3/4 7-IO 3/4.7.3 CCMPONENT COOLING WATER SYSTEM...........................
3/4 7-11 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM.............................
3/4 7-12 3/4.7.5 STANOBY NUCLEAR SERVICE' WATER PCNO..................
3/4 7-13 5
3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM....................
3/4 7-14 3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM...............
3/4 7-17 3/4 7-19 3/4.7.8 SNU88ERS.................................................
FIGURE 4.7-1 SAMPLE PLAN 2) FOR $ NUB 8ER FUNCTIONAL TEST...........
3/4 7-24 i
3/4 7-25 3/4,7.9 SEALF.D SOURCE CONTAMINATION...................
3/4. 7.10 -FfRC SUFFZC.'IT: 'YST~.":- DELETED 1" '-27
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CATAWBA - UNITS 1 & 2 IX
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U MITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE S_ECT_ ION a
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3/4.8 ELECTRICAL POWER SYSTEMS i
3/4.8.1 A.C. SOURCES 3/4 8-1 l
0perating................................................
3/4 8-9 l
l TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE........................
3/4 8-10 l
TABLE 4.8-2 LOAD SEQUENCING TIMES.................................
3/4 8-11 Shutdown.................................................
1 3/4.8.2 0.C. SOURCES 3/4 8-12 Operating................,................................
3/4 8-15 TASLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS.....................
3/4 8-16 Shutdown.................................................
1 r
3/4.8.3 ONSITE POWER DISTRIBUTION 3/4 8-17 Operating....................
3/4 8-18 l
Shutdown.................................................
l 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES I
Containment Penetration Conductor Overcurrent 3/4 S-19 Protective Devices.................................
TABLE 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT 3/4 8-21 P RO T ECTIV E D EVIC ES......................................
3/4.9 REFUELING OPERATIONS 3/4 9-1 3/4.9.1 BORON CONCENTRATION......................~............
3/4 9-2 1
3/4.9.2 INSTRUMENTATION..........................................
3/4 9-3 3/4.9.3 OECAY TIME...............................................
3/4 9-4 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................
3/4 9-7' 3/4.9.5 COMMUNICATIONS..........................................
3/4 9-8 3/4.9.6 MANIPULATOR CRANE........................................
1 3/4 9-9 i
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING..........
1 l
CATAWBA - UNITS 1 & 2 X
BASES PAGE SECTION TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS..........................
8 3/4 4-9 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF FULL POWER SERVICE LIFE..................................
8 3/4 4-11 FIGURE 8 3/4.4-2 EFFECT OF FLUENCE AND COPPER CONTENT ON SHIFT OF RT FOR REACTOR VESSELS EXPOSED TO 550*F............
B 3/4 4-12 NOT 3/4.4.10 STRUCTU RA L INTEGRITY.....................................
a 3/4 4-16 3/4.4.11 R EA CTO R C OO LANT SY ST EM V ENTS.............................
8 3/4 4-17 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 A C C UMU LAT O R S..............................................
B 3/4 5-1 I
3/4.5.2 and 3/4.5.3 ECCS SU85YSTEMS...............................
B 3/4 5-1 l
3/4.5.4 REFUELING WATER STORAGE TANK..............................
8 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.......................................
B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS......................
B 3/4 6-4 i
3/4.6.3 CO NTA I NMENT I S O LAT ION V A LV E 5..............................
B 3/4 6-4 l
3/4.6.4 COM8USTIBLE GAS CONTR0L...................................
B 3/4 6-4 3/4.6.5 ICE CON 0ENSER.............................................
B 3/4 6-5 3/4.7 PLANT SYSTEMS I
3/4.7.1 TURBINE CYCLE.............................................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION....
B 3/4 7-2 3/4.7.3 COMPONENT COOLING WATER 5YSTEM............................
B 3/4 7-3 i
3/4.7.4 NUCLEAR SERVICE WATER SY5 TEM..............................
B 3/4 7-3 3/4.7.5 STANDBY NUCLEAR SERVICE WATER PON0........................
B 3/4 7-3 l
3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM.....................
B 3/4 7-3 l
3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM................
B 3/4 7-4 l
B 3/4'7-4 i
3/4.7.3 5NUBBERS.................................................
B 3/4 7-6 3/4.7.9 SEALED SOURCE CONTAMINATION..........................
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CATAWBA - UNITS 1 & 2 XIV 1l
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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION As a minimum, the fire detection instrumentation for each fire 3.3.3.8 detection zone shown in Table 5.3-11 shall be OPERABLE.
Whenever equipment protected by the fire detection instrument APPLICABILITY:
is required to be OPERABLE.
ACTION:
]
With any, but not more than one-half the total in any fire zone, Function A fire detection instruments shown in' Table 3.3-11 inoperable, a.
restore the inoperable, instrument (s) to OPERABLE status within 14 days or within 1 nour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once'per hour, unless the
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instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment s
air temperature at least once per hour at the locations listed in Specification 4.6.1.5.
With more than one-half of the Function A fire detection instruments b.
in any fire zone snown in Table'3.3-11 inoperable, or with any J
Function B fire detection instruments shown in. Table 3.3-11 inoperable, or with any two or more adjacent fire detection instruments shown in i
Table 3.3-11 inoperable, 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 contain-ment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS Each of the above required smoke dettetion or flame detection instru-4.3.3.8.1 ments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months ey performance of a TRIP ACTUATING DEVICE OPERATIONAL Detectors which are not accessible during plant operation shall be comon-TEST.
strated OPERABLE by the' performance of a TRIP ACTUATING'0EVICE OPERATIONAL TEST during each COLD SHUTDOWN 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.
4.3.3.8.2 Each of the above required heat detection instruments shall be demon-strated OPERABLE as follows:
For nonrestorable spot-type detectors, at least two detectors out of a.
every hundred, or fraction thereof, snall be removed every 5 years For each failure that occurs on the detectors and' functionally tested.
removed, two addit';nal detectors shall be removed and tested; and CATAW8A - UNITS 1 & 2 3/4 3-71
~%
TMO VE~i>
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_t INSTRUMENTATION FIRE DETECTION INSTRUMENTATION J
SURVEILLANCE REQUIREMENTS (Continued)
For restorable spot-type heat detectors, at least one detector on b.
each signal initiating circuit shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE Different detectors shall be selected for each OPERATIONAL TEST.
Fire detectors which are not accessible during plant operation test.
shall be demonstrated OPERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST during each COLD StiUT00WN 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.
4.3.3.8.3 The NFPA Standard 720 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.
i CATAWBA - UNITS 1 & 2 3/4 3-72
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-- 1 Pl. ANT SYSTEMS Q
3/4.7.10 FIRE SUPPRESSION SYSTEMS _
FIRE SUPPRESSION WATER SYSTEM _
LIMITING CONDITION FOR OPERATION 3.7.10.1 The Fire Suppression Water System shall be OPERABLE with:
At least two fire suppression pumps, each with a capacity of-a.
2500 gpm, with their discharge aligned to the fire suppression header, and An OPERABLE flow path capable of taking suction from Lake Wylie b.
and transferring the water through distribution piping with OPERABLE sectionalizing control valves and isolation valves for each sprinkler, hose standoipe, or Spray System riser recuired to be OPERABLE per Specifications 3.7.10.2 and 3.7.10.4.
APPLICABILITY:
At all times.
1 ACT'ON:
With one of the above required pumps and/or one Water Supply /Distri-a.
bution System inoperable, restore the inoperable equipment to OPERABLE status within 7 days or provide an alternate backuo pumo or supply.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
With the Fire Suppression Water System otherwise inoperaole establisn b.
a backup Fire Suppression Water System within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4 i
CATAWBA - UNITS 1 & 2 3/4 7-27
N EMOVEh L_.
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS The Fire Suppression Water System shall be demonstrated OPERABLE:
4.7.10.1 At least once per 31 days on a STAGGERED TEST BASIS by starting each a.
electric motor-driven pump and operating it for at least 15 minutes on recirculation flow, At least once per 31 days by verifying that each valve (manual, power-b.
operr.ted, or automatic) in the flow path which is accessible during plant operations is in its correct position, At least once per 6 months by performance of a system flush of the c.
outside distribution loop to verify no flow blockage by fully opening the hydraulically most remote hydrant, At least once per 12 months by cycling each testable valve in the d.
flow path through at least one complete cycle of full travel, At least once per 18 months by verifying that each valve (manual, e.
power-operated, or automatic) in the flow path wnich is inaccessible during plant operations is in its correct position, f.
At least once per 18 months by. performing a system functional test which includes simulated automatic actuation of the system tnroughout its operating sequence, and:
1)
Verifying that each automatic valve in the flow path actuates to its correct position, 2)
Verifying that each pump develops at least 2500 gpm at a net pressure of 144 psig by testing at three points on the pump performance curve, Cycling each valve in the ficw path that is not testable during 3) plant operation through at least one complete cycle of full travel, and Verifying that each fire suppression pumo starts within 10 psig
.1) of its intended starting pressure (A pumo, primary switch-95 psig; B pump, primary switch-90 psig; and C pump, primary switch-85 psig).
At least once per 3 years by performing a flow test of the system in g.
accoroance with Chapter 8, Section 16 of the Fire Protection Hancocok.
15th Edition, published by the National Fire Protection Association.
l l
CATAWBA - UNITS 1 & 2 3/4 7-28
m
% oves
~
PLANT SYSTEMS SPRAY AN0/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION j
The following Spray ano/or Sprinkler Systems snail oe OPERA 8uE:
'j 3.7.10.2 i
Elevation 522 + 0 ft - Auxiliary Building a.
Equipment Room No.
l RHR & Containment Spray Sump Pump' Area 100-101 Corridor RHR Pump 18 104 105 RiiR Pump 1A 106 Corridor 109 RHR Pump.2B 110 RHR Pump 2A 111 Corridor 112 Corridor b.
Elevation 543 + 0 ft - Auxiliary Building 230 Cent. Chg. Pump 1A 231 Cent. Chg. Pump 18 l
240-
. Cent..Chg. Pump 2A l
i 241 Cent. Chg. Pump 2B Unit 1 Aux. Feedwater Pumo Room 250 Unit 2 Aux.' Feedwater Pump Room 260 Elevation 554 + 0 ft - Auxiliary Building.
c.
340 Battery Room Corridor (00-EE) 350 Battery Room Corridor (00-EE) d.
Elevation 560 + 0 ft - Auxiliary Building Component Cooling Pumps 1A1, 1A2, 1B1 & 182 300 Elevation 574 + 0 ft - Auxiliary Building e.
Cable Room Corridor (00-EE) 480 Cable Room Corridor.(00-EE) 490 f.
Elevation 577 + 0 ft
. Auxiliary Building Component Cooling Pumps 2A1, 2A2, 2B1 & 2B2 400 g.
Reactor Buildings Annulus Pipe Corridor l
APPLICA_BILITV:
Whenever equipment protected by the Spray / Sprinkler System is l-required to se OPERABLE.
ACTION:
With one or more of the above required Spray ~and/or Sprinkler Systems a.
inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> estaolish a continuous' fire waten witn cackup fire suppression equipment for those areas in whicn recundant systems or components could be damaged; for other areas, establish an hourly fire waten patrol.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
b.
CATAWBA - UNITS 1 & 2 3/4 7-29
$ M o v' E b
~
PLANT SYSTEMS
~
SURVEILLANCE REQUIREMENTS Each of the above required Spray and/or Sprinkler Systems shall be 4.7.10.2 demonstrated OPERA 8LE:
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path which is accessible.during s.
l plant operations is in its correct position, At least once per 12 months by cycling each testable valve in the l
b.
flow path through at least one complete cycle of full travel, I
l At least once per 18 months by verifying that each valve (manual, f
c.
power-operated, or automatic) in the flow path which is inaccessible-durit:g plant operations is in its correct position, and d.
At least once per 18 months:
By performing a system functional test which includes simulated 1) automatic actuation of the system, and cycling eacn valve in tne flow path that is not testable during plant operation tnrough at
'least one complete cycle of full travel.
By a visual inspection of each Sprinkler System starting at the 2) system isolation valve to verify the system's integrity; and l
1 3)
By a visual inspection of each nozzle's spray area to verify the spray pattern is not obstructed.
l l
I 1
l l
l l
l r
CATAWBA - UNITS 1 & 2 3/4 7-30
GN DVE1)
PLANT SYSTEMS 0 SYSTEMS C,02 LIMITING CONDITION FOR OPERATION Systems shall be 3.7.10.3 The following Higb Pressure and Low Pressure CO2 OPERABLE:
System - Diesel generator rooms, and a.
Low Pressure CO2
' System - Auxiliary feedwater pump rooms.
b.
High Pressure CO2 Systems is required to l
APPLICABILITY:
Whenever equipment protected by the CO2 I
be OPERABLE.
I ACTION:
Systems inoperable, With one or more of the above required CO2 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 continuous fire watch with backup fire l
l suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly l
fire watch patrol, The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
b.
SURVEILLANCE REQUIREMENTS l
Systems shall be demonstrated Each of the above required CO2 4.7.10.3.1 CPERABLE at least once per 31 days by verifying that each valve (manual, power ocerated, or automatic) in the flow path is in its correct position.
Systems snal.1 be 4.7.10.3.2 Each of the above reouired Low Pressure CO2 demonstrated OPERABLE:
storage tank level to At least once per 7 days by verifying the CO 2 l
a.
be greater than 44% of full capacity, and b.
At least once per 18 months by verifying:
1)
Each system actuates manually and automatically, upon receipt of a simulated actuation signal, 2)
Dameer closure devices receive an actuation signal upon system operation, and 3)
By a visual inspection of discharge nozzles to assure r.o blockage.
l C&ILWBA - UNITS 1 & 2 3/4 7-31
TEM 6VEb PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Systems shall be 4.7.10.3.3 Each of the above required High Pressure CO2 demonstrated OPERABLE:
At least once per 6 months by verifying the weight of each CO l
2 a.
storage cylinder to be at least 90% of full charge weight, and
" b.
At least once per 18 months by:
1)
Verifying each system actuates manually and automatically upon receipt of a simulated actuation signal, 2)
Verifying that damper closure devices receive an actuation-signal upon system operation, and 3)
A visual inspection of the discharge nozzles to assure no blockage.
4 I
1 1
CATAWBA - UNITS 1 & 2 3/4 7-32
- - - _.. - - _.. _ _ - _ - _.. _ ~ _ _ - - _ _ - - - - _ - - _ _ _. _ _ - _
$MOVEb PLANT SYSTEMS FIREHOSESTATf0N5 LIMITING CONDITION FOR OPERATION The fire hose stations given in Table 3.7-3'shall be'09ERABLE.'
l 3.7.10.4 AP9LICA81LITY:
hhenever 'iqui ment in,tne. areas protected by the fire hose l
stations is required t'~be.0PE~RABLE.
o ACTION:
~
With one or more of the fire hose stations given in Table 3.7-3 l
a.
inoperable, provide gated wye (s) on the nearest OPERABLE hose I
station (s).
One' outlet of the wye shall be conner.ted to the standard length of hose p'rovided for/the hose station.
The second outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left. unprotected by the inoperable hose station.
Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazara to station personnel, plant equipment, or the hose itself, the fire hose shall-be stored in a roll at the outlet of the OPERABLE, nose l
station.
Signs shall be mounted above the qated wye (s) to' identify the proper hose to use.
The above ACTION recui sment shall be accomplished within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoperable fire nose is trte primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
b.
SURVEILLANCE REQUIREMENTS EachofthefirehosestationsgiveninThele3.7-3shallbe 4.7.10.4 demonstrated OPERABLE:
At least once per 31 days, by a visual inspection of the fire hose a.
stations accessible during plant operations to assure all required equipment is at the station, b.
At least once per 18 months, by:
Visual inspection of the stations not accessible during plant 1) operations to assure all required equipmer.t is at tne station, 2)
Removing.the hose for inspection and reracking, and 3)
Inspecting all gaskets and replacing any degraded gaskets in the couplings.
c.
At least once per 3 years, by:
1)
Partially opening each' hose sta:fon valvs to verify valve OPERABILITY and no flow 11ockage, and l
l 2)
Conducting a hose hydrostatic test-at a pressure of 200 psig or l
l at least 50 psig aco'.:e maximum fier. main operating pretsure, j
whichever is greater.
i CATAWBA - UNITS 1 & 2 3/4 7-33
~..
-GA-( D VD y
s
^'%
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TABLE 3[T-3,
)
" FIRE HOSE STATIdis'5s y 5
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ELEVATION LOCATION 3
s,,
g, a,
7
" ' ' i-
'1r 1.
Auxiliary Building 59, FF,
522+0 1RF235 1
2 522+0 - :
1RF248 55, FF -
's
.. 54 3 +0 ik
'E 1RF210 V f.
63k64, YK.
d'.,
IRF211
~
' b43+0.
63, MM ~
'[~
.,l
~
1RF212 543+0"i 60, M.
, cs D
^
1RF218
- n" v
58, PP-543M i
,'1RF236 f
59, GG-HH 543+0
.J 60'-61, FF-GG 543+0
'b 1RF237.~-
[
]
1RF238 O
63, CC 543+0"
'i
'1RF247 e 57, JJ 5+3+0
~
x 54-55, GG L
543+0
',i
?11RF24?k 1RF250
- 57,FF 543+0 4
543+0
['b-S, 1RF255N 52-53, GG g
1RF256 a-51, CC 563+0 s
50-51, JJ-KK s
" 543+0 t5 1RF262 i
I 50-51, NN 1a 5'43+0 1RF268 'V a
,i 53,. MM O
543+0
%s 1RF271 s
s 1RF203 62, MM-NN 560+0
\\
x,"
63, JJ-KK 560+0
- '^
1RF213 4
1 58, PP 560+0 1RF219-56, NN 560+0 i 1RF220 1NF239%'
59, HH 560+0
'm 57, KK 560+0
- R(2d J
1RE251 54-55, FF-GG 560+0
'1 Rp263 52, MM-NN 560+0
['*
-().
1
- 51. KK 560+0 4 1RF269 s
1 58, BB 554+0 i
11RF484-I 65, BB-CC
$60+0' 1RF485 62, AA-88 560+0 N. " i*
1RF486 56, BB 554+0 5
,s 1RF487 sjlRF488' 52, AA-BB 560+0 3
49, BB-CC 560+0 1RF489 5
68-69, BB 560+0
\\1RF996 45-46, BB 560+0
,'IRF997.
63, NN 577+0
>1RF204 61 LL 577+0 1MF214 63, KK-LL 577+0 1RF215 1RF221-58, PP
~
577+0 s
59, JJ 577+0 1RF230 58, GG 577+0 1RF240 56, KK 577+0 1RF244 54, GG 577+0 1RF252 52-53, KK 577+0 1RF258 51, KK 577+0 1RF264 51-52, NN 577+0 1RF272 1
56, PP 577+0 1RF278 68-69, BB 577+0 1RF478 CATAWBA - UNITS 1 & 2 3/4 7-34 4
t!
TEHoVEb TABLE 3.7-3 (Continued)
~
FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #
k
65, 88-CC 577+0 1RF479 59, 00 574+0 1RF480 60, AA 574+0 1RF481 49, 88-CC 577+0 1RF490 45, 88 577+0 1RF491 55, OD 574+0 1RF492 So, AA 574+0 1RF493 63, AA 577+0 1RF993 51, AA 577+0 1RF998 62, NN 594+0 1RF205
'S7, MM 594+0 1RF222
., 63, J.J
'594+0 1RF231
' 57; HH 594+0 1RF245 57, EE 594+0 1RF253 51, JJ 594+0 1RF259 53, NN.
E94+0 1RF275 64, 88 '
594+0 1RF984 50, BB 594+0 1RF985 51, KK 605+10 1RF265 63, JJ 605+10 1RF233 61-64, ' MM 631+6 1RF483 50-51, MM 631+6 1RF495 2.
Fuel Po61s 65, TT-UU 605+10 1RF208 i
48, TT-UU 605+10 1RF276 63-64, MM 605+10 1RF482 50-51, MM 605+10 1RF822 3.
Nuclear Service Water Pump Structure East Section 600+0 1RF939 West Section 600+0 1RF940 CATAWBA - UNITS 1 & 2 3/4 7-35
-i__ ___
ECIFICAT10Al kAlb lTS U
h36. S fEMOVEh PLANT SYSTEMS NI J
3/4.7.11 FIRE BARRIER PENETRATIONS.
LIMITING CONDITION FOR OPERATION All fire barrier penetrations (walls, floor / ceilings, cable tray 3.7.11 enclosures.and.other fire barriers) separating safety-related fire areas or separating portions of redundant systems important to safe shutdown within a fire area and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable, piping, and ventilation duct pene-tration seals) shall be OPERABLE.
APPLICA8ILITY:
At all times.
ACTION:
With one or more of the above required fire barrier penetrations a.
and/or sealing devices inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either establish a continuous fire watch on at least one side of the affected pene-trat. ion, or verify the OPERABILITY of fire detectors on at least one side of the inoperable penetration and establish an hourly fire watch patrol.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
b.
SURVEILLANCE RE0VIREMENTS At least once per 18 months the above required fire barrier 4.7.11.1 penetrations and sealing devices shall be verified OPERABLE by performing a visual inspection of:
The exposed surfaces of each fire rated assemoly; a.
b.
At least 10% of all fire dampers.
If apparent changes in aopearance or acnormal degradation are found, a visual inspection of an additional 10% of the dampers shall be mace.
This inspection process shall continue until a 10% sample with no apparent changes in appearance or abnormal degradation is found.
Samples snall be selected sucn that each fire damper will br., inspected every 15 years;.and At least 10% of each type of sealed penetration.
If accarent changes c.
in accearance or aonormal degradations are found, a visual inspection of an additional 10% of eacn type of sealed penetration snail be mace.
This inspection process snali continue until a 10% samole with no apparent enanges in accearance or abnormal degradation is found.
Samples snail ce selected sucn that each penetration seal will ce inspected every 15 years.
CATAWBA - UNITS 1 & 2 3/4 7-36
fEMOVED PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Each of the above required fire doors shall be verified OPERABLE by 4.7.11.2 inspecting the closing mechanism and latches at least once per 6 months, and by verifying:
The position of each interior closed fire door at.least once per 24 a.
- hours, The OPERABILITY of the fire door ' supervision system for each b.
electrically supervised fire door by performing a TRIP ACTUATING-DEVICE.0PERATIONAL TEST at least once per 31 days, and That each locked closed fire door is closed at least once per c.
7 days.
CATAWBA - UNITS 1 & 2 3/4 7-37
\\S EC Fl
~7]OA)
A) 7~$
I 3 tG".S hA0VO PLANT SYSTEMS m-3/4.7.13 STAN08Y SHUTOOWN SYSTEM LIMITING CONDITION FOR OPERATION The $tandby Shutdown Sy. tem (SSS) shall be OPERABLE.
3.7.13 s
APPLICABILITY: NODES 1, 2, and 3.
s.
ACTION: (Onfts1and.2) 1-With the Standby'Srhutchown System. inoperable, restore the inoperable a.-
ecui'pment to OPERAB1.E status within 7 days or be in at least HOT STANOBY 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 at least HOT SHUTOOWN within the.following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, Withtheto'tal"l'eakageIremUNIDENTIFIEDLEAKAGE,IDENTIFIEDLEAKAGE b.
and reactor.:oolant pump seal leakage greater than 26 gpm, declare the Standby Makeup Pump inoperable and take ACTION a., above.
1 The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
1 SURVEILLANCE REQUIREMENTS 4.7.13.1 The Standby Shutdown System diesel generator shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying:
1)
The fuel level in the fuel storage tank is greater than or equal to 67 inches, and 2)
The diesel starts from ambient conditions and coerates for at least 30 minutes at greater than or equal to 700 kW.
b.
At least once per 92 days by verifying that a sample of diesel fuel from tne fuel storage tank, obtained in accordance with ASTH-0270-1975, is within the acceptable limits specified in Table 1 of ASTM-0975-1977 when checked for viscosity and water and sediment; and At least once per 18 months, during shutdown, by subjecting the diesel c.
to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.
4.7.13.2 The Standby Shutdown System diesel starting 24-volt battery bank anc cnarger shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that:
1)
The electrolyte level of eacn battery is above the plates; and 2)
The overall battery voltage is greater than or equal to 24 volts.
CATAWBA - UNITS 1 & 2 3/4 7-40
M OVEb i
PLANT SYSTEMS -
SURVEILLANCE REQUIREMENTS (Continued)
At least once per 92 days,by verifying that the specific gravity.is -
b.
appropriate for continued service of the battery, and At least once per 18 months by verifying that:
c.
l The batteries, cell plates, and battery racks show no visual 1) indication of physical damage or abnormal deterioration, and The battery-to-battery and terminal connections are clean, 2) tight, and free of corrosion.
The Standby Makeup Pump water supply shall be demonstrated OPERABLE 4.7.13.3 by:
Verifying at least once per 7 days:
a.
That the requirements of Specification 3.9.10 are met and the 1) boron concentration in the storage pool is greater than o.r equal to 2000 ppe, or That a contained borated water volume of at least 112,320 gallons 2) with minimum baron concentration of 2,000 ppm is available and capable of being aligned to the Standoy Makeup Pump.
j Verifying at least once per 92 days that the Standby Makeup Pump b.
develops a flow of greater than or equal to 26 gpm at a pressure greater than or equal to 2488 psig.
The Standby Shutdown System 250/125-Volt Battery Bank and its i
4.7.13.4 associated charger shall be demonstrated OPERA 8LE:
At least once per 31 days by verifying:
a.
That the electrolyte level of each battery is above the plates, 1) and The total battery terminal voltage is greater than or equal to 2) 258/129 volts on float charge.
At.least once per 92 days by verifying that the specific gravity is b.
appropriate for centinued service of the battery, and At least once per 18 months by verifying that:
c.
The batteries, cell plates, and battery racks show no-visual 1) indicati'ons of physical damage or abnormal deterioration, and The battery-to-battery and terminal connections are clean, tight, 2) free of corrosion and coated with anti-corrosion material.
CATAWBA - UNITS 1 & 2 3/4 7-41
\\
/
EMd VEb PLANT SYSTEMS _
SURVEILLANCE REQUIREMENTS (Continued)
The Steam Turbine Driven Auxiliary Feedwater Pump and associated 4.7.13.5 components shall be demonstrated OPERA 8LE at least once per 18 months by veri-fying that the system functions as designed from the Standby Shutdown System.
Eat.h Standby Shutdown System instrumentation device shall be 4.7.13.6 demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per g
31 days and a CHANNEL CALIBRATION at least once per 18 months.*
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- The CHANNEL CALIBRATION requirement of this surveillance need not be performed for lovel transmitter 1 CFLT5632 until prior to entering HOT STANOBY following 1
the Unit 1 first refueling.
(This applies to Unit 1 only.)
Amendment No.((Unit 1)
CATAWBA - UNITS 1 & 2 3/4 7-42 Amendment No.KIUnit 2) 911/9A
INSTRUMENTATION BASES l
REMOTE SHUTDOWN SYSTEM (Continued) l control and power circuits and transfer switches necessary to eliminate effects of tne-fire and allow operation of instrumentation, control and power circuits l
required to achieve and maintain a safe snutdown condition are independent of areas where a fire could damage systems normally used to shutdown the reactor.
l This capability is consistent with General Oesign Criterion 3 and Appendix R l
to 10 CFR Part 50.
j 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor This capacility is consis-and assess these variables following an accident.
tent with the recommendations of Regulatory Guide 1.97, Revirion 3, " Instruments-1 tion for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions Dur-ing and Following an Accident," May 1983 and NUREG 0737, " Clarification of TMI Action Plan Requirements," November 1980.
3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the Chlorine Detection Systems ensures that suf ficient capability is available to promotly detect and initiate protecti.ve action.in the event of an accidental chlorine release.
This capability is required to protect control room personnel and is consistent with the recommendations of-Regulatory Guide 1.95, Revision 1, " Protection of Nuclear. Power Plant Control Room Operators Against an Accidental Chlorine Release," January 1977.
N I 5 ftL 3
.3.8 FIRE DETECTION INSTRUMENTATION OPER TY of the detection instrumentation ensures that both acecuate is available for prompt detection of fires and tnat Fire
{
warning ;apabi Sucoression Systems, hat are actuated by fire detectors, will discharge extinguishing agents in timely manner.
Prompt detection and suooression of l
fires will reduce the poten 1 for damage to safety-related equipment and is an integral element in the over facility Fire Protection Program.
Fire detectors that are used to ac te Fire Suppression Systems reeresent a more critically important component of a - ant's Fire Protection Program-than detectors that are installed solely for e ly fire warning and notifica-tion.
Consequently, the minimum number of OPERA fire detectors must be -
greater.
The loss of detection capability for Fire Suppression tems, actuated otection for L by fire detectors, represents a significant degradation of fire CATAWBA - UNITS 1 & 2 8 3/4 3-5
INSTRUMENTATION 8ASES
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rFIRE DETECTION INSTRUMENT E T (Continued) any area.
As esult, the establishment ire watch patrol must be ini tiate an earlier stage than be warranted for the loss of cetectory l-that ovide only early fire ing.
The establishment of frecuent f' l
p ois in the affected,ar s is required to provide detecti ty j
until the inoperable instrumentation is restored to OP
/.
u 3/4.3.3.9 LOOSE-PART DETECTION SYSTEM The OPERA 8AILITY of the loose-part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the Reactor System and avoid or mitigate damage to Reactor System components.
Tne allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Lignt-Water-Cooled Reactors," May 1981.
3/4.3.3.10 RAOI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The l
Alarm / Trip Setpoints for these instruments shall be calculated and adjustec in accordance with the methodology and parameters in the ODCN to ensure Anat tne alarm / trio will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Oesign Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/a.3.3.11 RAOICACTIVE GASECUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to mehiter and control, as applicable, the releases of radioactive materials in gasecus effluents during actual or potential releases of gaseous effluents.
The l-Alarm / Trip Setpoints for these instruments shall be calculated and adjustec in accordance with the methodology and parameters in the 00CM to ensure that tne alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation a~lso includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLOUP SYSTEM.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Apcendix A to 10 CFR Part 50.
The sensitivity of any noble gas activity monitor used to snow"comoliance with the gaseous effluent release requirements of Specifica-tion 3.11.2.2 snall be suen tnat concentrations as low as 1 x 10-6 Ci/cc are measuraole.
CATAWBA - UNITS 1 & 2 S 3/4 3-6
i PLANT SYSTEMS BASES l
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SNUB 8ERS (Continued)
The service-life of a snubber is established via manufacturer input and l
information through consideration of the rnubbar service conditians and associated-i: installation andf maintenance records (newly 4nstalled snubnersi seal replace'd, spring repTaced,'in 'high radi'acfon. area,. in high' temp'etature area,
~
The requirement to monitor the snubber service life is included to etc.).
ensure that the snuboers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for This limitation will ensure that leakage from Byproduct, Source, plutonium.
and Special Nuclear Material sources will not exceed allowacle intake values.
Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the procacility of damage to a Those sources which are frequently handled are required source in that group.
to be tested more often tnan those which are not.
Sealed sources wnich are continuously enclosed within a shielded mechanism (i.e., sealed sources witnin radiation monitoring or boren measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
% UPT::::" :YSTM PG.LETE.D.
3/4.7.10 ihe OPERABILITY of the Fire Suppression Systems ensures that adecuate fire suppression capability is availanle to confine and extinguish fires occurring in any portion of the f acility where safety-related equipment is The Firi Suppression S'ystem consists of the water system, spray, l ocated.
The collective capability of and/or sprinklers, CO, and fire hose stations.
2 tne Fire Suppression Systems is adequate to minimize potential damage to safety-related equipment and is a major element in the f acility Fire Protec-f tion Program, In the event that portions of the Fire Suppression Systems are inoceracie, alternate backup ~ fire-fighting equipment is required to be made available in the affecttd areas until the inoperable equipment is restored to service.
When the inoperaole fire-fighting equipment is intended for use as a backuo means of fire suppression, a longer period of time is allowed to provice an alternate means of fire fighting than if the inoperaole equipment is tne primary means of fire suppression.
t CATAWBA - UNITS 1 & 2 B 3/4 7-6
b-76D PLANT SYSTEMS BASES
/
E FIRE SUPPRESSI(LMTSTEMS (ContinueM In e, event the Fi uppression Water em becomes inoperac
(
immedi e corrective asures.must-be.t since this system p ices the j
- maio fire.1uppr ton capability e,pi ant, 3/4.h.n 'rE r-~x- ~ Erne T)ELETED 1
The functional integri of the f' e barrier p netrations nsures that fires wil1 be. confined or daquately tarded fr spreading adjacent portion of.the facility.
These sign featu es minimize he possibi ty of a single f' e rapidly involving sever areas of he facility rior to de etion and extin-guishing of the fire.
The fire b rier penetr ions are a passive element i tne facility fire pr taction pro ram and are ubject to riodic inspectic Fire barrie penetrations, including ble penetr tion barriers, fi e doors. fire d ers, and otn fire barri s are cons dered functional nen the visuaily obse ed condition is the same the as-d.igned condition.
For those fire barrier penetrations hat are not i the as-d igned condition, an evalua-tion shall e performed show that th modifica on has not degr ed tne fire rating of the fire barri e penetration 0 ing periods o time when a b reier is n t functional, ei er:
(1) a conti uous fire watc is required t be maintai ed in the vicini y of the affe ted barrier, o (2) the fire
.tectors on at least one sid of the af f cted barrier m st be verified PERABLE and an hourly fire w tch patrol esgaelished, until, the barrier is estored to,unctional statu.
/
3/4.7.12 GROUNDWATER LEVEL This specification is provided to ensure that groundwater levels will be monitored and prevented from rising to unacceptable levels.
High gro.ind-water levels could result in unacceptable structural s*resses in tne Co.itain-ment and/or Auxiliary Building due to uplif t and hydrostatic forces during cesign basis events.
Although these buildings have ceen statically analy:ed to withstand soil pressure along with the uolift and hydrostatic forces resulting from groundwater rebound to yard elevation (593'6"), this analysis did not include.any other loadings and was not a design condition for enese buildings.
1 CATAWBA - UNITS 1 & 2 B 3/4 7-7
PLANT SYSTEMS BASES 3/4.7.13 T"T"" :""T000 OYSTEM DSLNO C he Standby Sht d System (5
) is design to mitigat the consequen es of. certain postulated tre inc'ide s by providi capability a maintain H ing and" mon' aring vital-' ystems from - 1 ca-
-STAND 8Y conditions d by contr,l room. ~Th s capabilt ' is consistent ith he main'co ro tions external the requiremen of 10 CFR P t 50, Append' R.
The eillance R uirements ens
- i. hat the S systems and mponents are cap e of perfo ng their inte ed functions The required evel in the
,555 di sei. generator fdel storage nk ensures s ficient fuel f
- 72. hours l
unin rrupted ope ti on.
It is sumed that; w' tiin.7Z hours,. 1 ther ~o f f si te.
p r can be re ored or additi al fuel can b added to the orage tank.
Althoug the Standby M euo Pump is n nuclear safet related and w not designed a ording to ASM code requirem ts, it is test quarterly to nsure its OPERA LITY.
The 5 eillance Requ' ement concerni the Standby akeue Pumo wa r suoply ens es that an ad. ate water vol is available a sucaly the p continuousi for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
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CATAWBA - UNITS 1 & 2 8 3/4 7-8
ADM!NTSTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1. The Station Manager shall be responsible for overall unit coera-tion and shall. delegate in writing the succession to this responsibility L
during his absence.
The Shift Supervisor (or during his absence from the control room, a 6.1. 2 designated individual) shall be responsible for the control room com function.
of Nuclear Production, shall be reissued to all Nuclear Production Department station personnel on an annual basis.
6.2 ORGANIZATION OFFSITE ihe offsite organization for unit management and technical support 6.2.1 shall be as shown in Figure 6.2-1.
UNIT STAFF 6,2.2 The unit organization shall be as shown in Figure 6.2-2 and:
Each on-duty shift shall be composed of at least the minimum sni f t a.
crew composition shown in Table 6.2-1; At least one licensed Operator for each unit shall be in the control b.
room when fuel is in the reactor.
In addition, while either unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator snall be in the control room; A Health Physics Technician
- thall be on site wnen fuel is in eitne'r c.
reactor; All CORE ALTERATIONS shall be observed and directly sucervisec cy d.
either a licensed Senior Operator or licensed Senior Operator Limitec to Fuel Handling who has no other concurrent responsibilities during nis operation; q M
' :it:
- Srig:d: c' :t !:::t ;; :::t: :" :F:1' t: ::fet;' :: :-
- !!: :t :l' tic::.
'5: "' : Sr';::: :r:
- t ' :'; : th: tr ::
- t:r: : f th: ci ':ur :hift cr;;
- ry 3:r ::': : rut::ur :'. :
_rit : t : ) ;;r::rm:1 r;.i :: f r ::n:r ::: n;f:: '.n::f: : : r; ;
- r;
- r;;n;3, :nd b
I "Tne Healtn Physics Technician TjEE~fi e B-ig:d; ::m ::i:ic )may be less than the minimum requirements.for a period or time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in orcer to accommodate unexpected absence, provided immediate action is taKen to.fil' tne required pos1tions, CATAWBA - UNITS 1 & 2 6-1
_a
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l ADMINTSTRAT1VE CCNTROL5 i
l TECHNICAL REVIEW-AND CONTROL ACTIVITIES (Continued)
All REPORTA8LE EVENTS and all violations of Tecnnical Specifications shall be investigated and a report prepared which evaluates tne occurrence and 6.5.1.6 l
Sucn reports snali ce which provides recommendations to prevent recurrence. approved by t Production, and to the Director of the Nuclear Safety Review Board.
The Station Manager shall assure the performance of special reviews I
6.5.1.7 and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President, Nuclear Production.
The station security program, and implement.ing procedures snall be 6.5.1.8 Recommended changes snall be accroved reviewed at least once per 12 months.
by the Station Manager and transmitted to the Vice President, Nuclear Production, and to the Oirector of the Nuclear Safety Review Board.
The station emergency plan, and implementing procedures, shall be l
- 6. 5.1. 9 reviewed at least once per 12 months.
Recommended changes snall be approvec
'c by the Station Manager and transmitted to the Vice President, Nuclear Production, and to the Director of the Nuclear Safety Review Board.
}-x The Station Manager shall assure the performance of a review by a 6.5.1.10 qualified individual / organization of every unplanned onsite release of racio-active material to the environs including the preparation and forwarding of
. %[ recorts cc.vering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence to the Vice President, Nuclear Production and to tne Nuclear Safety Review Board.
The Station Manager shall assure the performance of a review cy a 6.5.1.11 cualifed individual / organization of changes to the PROCESS CONTROL PROGRAM, i
to
[3 0FFSITE 005E CALCULATION MANUAL, and Radwaste Treatment Systems.
}1 N
- 6. 5.1.g13 Reports documenting each of the activities performed under Cocies snail ::e 5c'eci,1 cations 6.5.1.1 througn 6.5.1.11 shall be maintained.
provided to tne Vice President, Nuclear Production, and One Nuclear $afety l
)
Review Board.
- 6. 5. 2 NUCLEAR SAFETY REVIEW BOARO (N5RB)
FUNCTION The NSRS shall function to provide independent review and audit of
- 6. 5. 2.1 designated activities in the areas of.
l Nuclear power plant operations, l
a.
D.
Nuclear engineering, Chemistry and radiochemi stry,
c.
i CATAWBA - UNITS 1 & 2 6-8 l
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6.5.1.12 The Station Manager shall assure the performance of a review by a qualified individual / organization of the Fire Protection Program and implementing procedures and submittal of recommended changes to the Nuclear Safety Review Board.
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-vm _ - I-L CAmmMmards c nb.ineA In F5AA c.hdhe b0.
ADMINISTRATIVE CONTROLS i
6.8 PROCEDURES AND PROGRAMS 6.8.1. Written procedures shall be established, implemented, and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix A of Regulatory a.
Guide 1.33, Revision 2, February 1978; b.
The emergency operating procedures required to implement the require-ments of NUREG-0737 and Supplement No. 1 to NUREG-0737 as stated in Generic Letter No. 82-33; c.
Security Plan implementation; d.
Emergency Plan implementation; PROCESS CONTROL PROGRAM implementation;-
e.
f.
OFFSITE DOSE CALCULATION MANUAL implementati n;.antf g.
Quality Assuranc regram implementation for effluent and environ-mental monitori g3 6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed and approved by the Station Manager; or by:
(1) Operating Superin-tencent, (2) Technical Services Superintendent, or (3) Maintenace Superinten-'
dent, as previously designated by the Station Manager; prior to implementation and shall be reviewed perHdically as set forth in administrative procedures.
6.8.3 Temporary changt, to procedures of Specification 6.8.1 may be made pro-viced:
a.
The intent of the original procedure is not altered; b.
The change is approved by two memoers of.the plant management staff, at least one of whom holds a Senior Operator license on tne unit affected;-and The change is documented, reviewed, and acoroved by the Station c.
Manager; or by:
(1) Operating Superintendent, (2) Technical Services Superintendent, or (3) Maintenance Superintendent, as previously designated by the Station Manager; within 14 days of implementation.
1 6.8.4 Thefollohingprogramsshallbeestablished, implemented,andmaintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems _outsice contain~ ment that could contain highly radioactive. fluids during a serious transient or accident to as low as practical levels.
The systems include the containment spray, Safety Injection, enemical CATAWBA - UNITS 1 & 2 6-13
I ATTACHMENT 3 PROPOSED FSAR REVISION 1
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1~A/ SEAT % NEXT%E
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CNS' 1
Portable fire extinguishers shall be inspected periodically for full charge and physical condition.
Extinguishers shall be checked on a programmed schedule.
9.5.1.5 Personnel Qualification and Training i
Fire brigade training and refresher training is conducted in accordance with guidelines from NFPA 27.
Administrative procedures, controls and fire brigade are discussed in a separate submittal, " Response to Appendix A to Branch Technical Position APCSB 9.5-1".
Station directives require each shift to have members to perform specified duties on the' fire brigade which include fire drills on a scheduled and un-scheduled basis.
Fire drills are reviewed and evaluated by plant personnel and insurance representatives.
9.5.2 COMMUNICATIONS SYSTEMS 9.5.2.1 Design Bases The Catawba communication systems are designed to provide reliable intraplant and plant-to-offsite communications, and offsite emergency communications with public safety agencies.
The private automatic business'exc'hange telephone system and the public address system provide diverse means of communication to all critical areas of the station during normal and emergency conditions.
Additionally, a sound powered telephone system is provided between the auxiliary shutdown panel and selected locations in the plant.
These diverse communication systems are independent of each other to assure effective communications assuming a single failure.
9.5.2.2
System Description
9.5.2.2.1 Intraplant Telephone System The private automatic business exchange (PABX) telephone system provides independent private intraplant telephone communications throughout the vital areas of the station.
The locations of PABX telephone stations are indicated on Figures 9.5.2-1 through 9.5.2-15.
To assure its functional operability, the PABX telephone switch is provided with redundant common controls, critical electronics, and power supplies.
Additionally, at least one backup circuit for each of the telephone switch modules is maintained in spares.
The PABX system is connected to the Intraplant Public Address System through an isolation device to preserve the independence of the two systems.
This connec-tion allows telephone system communications over the paging channel of the PA system as described below.
The PABX system is also connected to the commercial telephone system and the Duke microwave telephone system.
9.5-5
Specific comitments related to the operation and testing of fire protection system equipment are contained in FSAR Chapter 16.0.
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CNS Emergency plan and procedures e.
f.
Station security program and procedures g.
Fire protection plan and procedures h.
New Employee Orientation (Portions of other General Employee Training may be included.)
Continuing training is conducted in these areas as it, necessary to maintain q) employee proficiency.
13.2.2.1.1 Fire Brigade Training h
The primary purpose of the Fire Brigade Training Program is to develop a group N
of station employees skilled in fire prevention, fire fighting techniques, E
first aid procedures, and emergency response.
They are trained and equipped to I
function as a team for the fighting of fires.
The station fire brigade organ-ization is intended to be self sufficient with respect to fire fighting 7
activities.
The Fire Brigade Training program provides for initial training of all new fire b-brigade members, quarterly classroom training and drills, annual practical g
training, and leadership training for fire brigade leaders.
{
Training is discussed in Duke Power Company, Catawba Nuclear Station, response to Appendix A, BTP APCSB 9.5-1.
- - +
13.2.2.2 Technical Training Technical Training is designed, developed and implemented to assist station employees in gaining an understanding of applicable fundamentals, procedures, and practices; and in developing manipulative skills necessary to perform assigned work in a competent manner.
Technical training consists of three segments:
Initial Training On-the-Job Training & Qualifications Continuing Training 13.2.2.2.1 Initial Job Training Initial job training is designed to provide knowledge of the fundamentals, basic principals, and procedures involved in work in which an employee is l
assigned.
l This training may consist of, but is not limited to, live lectures, taped and filmed lectures, guided self-study, demonstrations, laboratories and workshops, on-the-job training, and where applicable, simulator training and/or training on a research reactor.
13.2-3 i
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f 8
Specific commitments related to the Fire Brigade are contained in FSAR Chapter
]
\\1 16.0.
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CATAWBA NUCLEAR STATION FINAL SAFETY ANALYSIS REPORT CHAPTER 16.9 SELECTED LICENSEE COMMITMENTS AUXILIARY SYSTEMS Table of Contents 16.9-1 Fire Suppression Water Systems 16.9-2 Spray and/or Sprinkler Systems 16.9-3 CO Systems 2
16.9-4 Fire Hose Stations 16.9-5 Fire Barrier Penetrations 16.9-6 Fire Detection Instrumentation 16.9-7 Standby Shutdown System i
16.9-0
\\b.9 flulLlyf "L^,MT. SYSTEMS PRcrfge Tior) n 3,'" '.10 -FIRE JUrrR00 !0F SYSTEMS
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lb.M FIRE SUPPRESSION WATER SYSTEM
( CDHNITtfGA7" LIMITINO CONOITION FOR CICRATIGH--
The Fire Suppression Water System shall be OPERABLE with:
2.7.10.1 At least two fire suppression pumps, each with a capacity of a.
2500 gpm, with their discharge aligned to the fire suppression header, and An OPERABLE flow path capable of taking suction from Lake Wylie b.
and transferring the water through distribution piping with OPERABLE sectionalizing control valves and isolation valves for each j
sprinkler, hose standpipe, or Spray System riser required to be OPERABLE per# peci'ication: 2.7.10.0 :nd 3.7.10."
Scommitments /6,9-2 y //o,9 4/
APPLICABILITY:
At all times.
gege 4 ACTION:
With one of the above required pumps and/or one Water Supply /Distri-a.
bution System inoperable, restore the inoperable equipment to OPERABLE status within 7 days or provide an alternate backup pump or supply.
Th; prc.i; ion: 0' Specification: 3.0.2 and 2.0.; cra n;;
appl 1:21c.
b.
With the Fire Suppression Water System otherwise inoperable establish a backup Fire Suppression Water System within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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-27 c r wer - us:T: 112
i TESTING PROCEDURES:
- 1) PT/0/A/4400/01D Fire Pump Operability Test
- 2) PT/0/A/4400/01C Fire Suppression System Monthly Test
- 3) PT/0/A/4400/01E Fire Hydrant Operability Test
- 4) PT/0/A/4400/01K Fire Suppression System Valve Operability Check
- 5) PT/0/A/4400/01A Exterior Fire Protection Functional Capability Test
- 6) PT/1-2/A/4400/01M Fire Suppression System Containment Valve Operability
- 7) PT/0/A/4400/01S RY Fire Protection Flow Periodic Test
REFERENCES:
- 1) Catawba'FSAR, Section 9.5.1
- 2) Catawba SER, Section 9.5.1
- 3) Catawba SER, Supplement 2, Section 9.5.1 q
- 4) Catawba SER, Supplement 3 Section 9.5.1
- 5) Catawba Fire Protection Review, as revised
- 6) Catawba Fire Protection Commitment Index
- 7) Startup and Normal Operation of Fire Protection System - OP/1/A/6400/02A j
{
1 16A Auxiugy MommM SYST6M5
. % SYSTEMS f lb.M SPRAY AN0/0R SPRINKLER SYSTEMS )gjjgj7gggj7 m,...,~.
-, m., m,,., m..,, -. -
....,.,m,,
-3 '.1C.2 The following Spray and/or Sprinkler Systems snall De OPERA 8tE:
Elevation 522 + 0 ft - Auxiliary Building a.
Room No.
Equipment 100-RHR & Containment Spray Sump Pump Area 101 Corridor l
104 RHR Pump 1B l
105 RHR Pump 1A 106 Corridor 109 RHR Pump 28 110 RHR Pump 2A 111 Corridor 112 Corridor b.
Elevation ~543 + 0 ft - Auxiliary Building 230 Cent. Chg. Pump 1A 231 Cent. Chg. Pump 18 240 Cent..Chg. Pump 2A q
241 Cent. Chg. Pump 28 250 Unit 1 Aux. Feedwater Pump Room 260 Unit 2 Aux. Feedwater Pump Room c.
Elevation 554 + 0 ft - Auxiliary Building 340 Battery Room Corridor (00-EE) 350 Battery Room Corridor (00-EE) d.
Elevation 560 + 0 ft - Auxiliary Building I
300 Component Cooling Pumps 1A1, 1A2, 1B1 & 182 e.
Elevation 574 + 0 ft - Auxiliary Building 480 Cable Room Corridor (00-EE) 490 Cable Room Corridor (00-EE) f.
Elevation 577 + 0 ft
. Auxiliary Building 400 Component Cooling Pumps 2A1, 2A2, 2B1 & 2B2 i
g.
Reactor Buildings j
Annulus j
Pipe Corridor j
APPLICABILITY:
Whenever equipment protected by the Spray / Sprinkler System is required to be OPERABLE.
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gp eoat ACTION:
j i
A With one or more of the above required Spray and/or Sprinkler Systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with j
backup fire suppression equipment for those areas in whicn redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.
j b.
Th; pr:/i:i:n: cf M ciffe:ti^as 3.0.3 2.cd 3.0.# r; n:: pplicable.
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TESTING PROCEDURES:
- 1) PT/0/A/4400/01C Fire Suppression System Monthly Test
- 2) PT/0/A/4400/01K Fire Suppression System Valve Operability Check 1
- 3) PT/1-2/A/4400/01M Fire Suppression System Containment Valve Operability
- 4) PT/0/A/4400/01J Spray Valve Sprinkler System Functional Test
REFERENCES:
- 1) Catawba FSAR, Section 9.5.1
- 2) Catawba SER, Section 9.5.1
- 3) Catawba SER, Supplement 2, Section 9.5.1
- 4) Catawba SER, Supplement 3, Section 9.5.1
- 5) Catawba SER, Supplement 5 Section 9.5.1
- 6) Catawba Fire Protection Review, as revised
- 7) Catawba Fire Protection Commitment Index
\\bA AaxlLIM
- taw # SYSTEMS a
Fde P90rsc-nos SYSWIS lb.g.3 C0_2 SYSTEMS f
LIMITING CON 0! TION FOR OPERATION 2 Systems shall be
- 9. '. M. 3 The following High Pressure and Low Pressure CO OPERABLE:
System - Diesel generator rooms, and a.
Low Pressure CO2 System - Auxiliary feedwater pump rooms.
b.
High Pressure CO2 Systems is required to APPLICABILITY:
Whenever equipment protected by the CO2 be OPERABLE.
gf>E CTION:
\\
With one or more of the above required CO2 Systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with backup fire i
suppression equipment for those areas in which redundant systems or components could be. damaged; for other areas, establish an hourly fire watch patrol.
-b.
Th; pce.i5icas of Sp;;ificatlvn. 3. 0. 3 and 3. 0.4 ece act oggi metic.
LLANCE REQUIo.EMENTS
~
l 4.7.10.3.1 Eac f the above required CO2 Systems shall be dem strated
- OPERABLE at least o per 31 days by verifying that each v e (manual, power operated, or automatic the flow path is in its corre position.
4.7.10.3.2 Each of the above quired Low Pressur 0 Systems shal] be 2
demonstrated OPERABLE:
a.
At least once per 7 days by v ying the CO2 storage tank level to be greater than 44% of full pa 'ty, and b.
At least once per 18 ths by verifyi 1)
Each system ctuates manually and autem
'cally, upon receipt of a sim ted actuation signal, 2)
Damp closure devices receive an actuation sign upon system op ration, and 3)
By a visual inspection of discharge nozzles to assure no blockage.
3/4 7-31 NITS 1 & 2
~
I I
)
TESTING PROCEDURES:
i
- 1) PT/1-2/A/4450/10A DG CO System Annual Test 2
- 2) PT/1-2/A/4450/10B DG CO System Weekly Test
]
2 j
- 3) PT/1-2/A/4450/10D DG CO System Semi-Annual Test 2
J
- 4) PT/1-2/A/4450/13A Auxiliary Feeds.ater CO System Annual Test 2
- 5) PT/1-2/A/4450/13D Auxiliary Feedwater CO System Semi-Anbaal Test 2
Cylinder Weight
- 6) MP/0/A/7650/66 Auxiliary Feedwater Pumps CO2 Verification
REFERENCES:
- 1) Catawba FSAR, Section 9.5.1
- 2) Catawba SER, Section 9.5.1
- 3) Catawba SER, Supplement 3, Section 9.5.1
--.-___m.___
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^$4## SYSTEMS F~Itc PRO-recnd SYWM g,
16.9 t/jFIRE HOSE STATIONS
-LD' TING CON 0!T!O" c0" OPE""TIO"
- C6NMITM6MT 16.9 i
.10.
The fire hose stations given in Table 9-A=t shall be OPERABLE.
APPLICABILITY: hhenever e'quipment in.the'.. areas protected by the fire hose
>1 stations is required'tb~be 0PERABLE.
.e N - ACTION:
16 9-1 With one or more of the fire hose stati.ons given in Table t;:2=$:
inoperable, provide gated wye (s) on the nearest OPERABLE hose j
station (s).
One' outlet of the wye shall be connected to the j
standard length of hose provided for/the hose station.
The second outlet of the wye shall b'e connected to a length of hose. sufficient to provide coverage for the area left.. unprotected by the inoperable hose station.
Where it can be demonstrated that the physical i
routing of the fire hose would result in a recognizable hazard to f
station personnel, plant equipment, or the hose itself, the fire hose shall-be stored in a roll at the outlet of the OPERABLE hose station.
Signs snall be mounted above the gated wye (s) to identify the proper hose to use.
The abovefACTION requirement shall be accomplished within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the h'nopersble fire hose is the otherwise route the additional primary means of fire suppression;kSSMDAL-hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
_2.
The presisi= s ;f Specif kos.w...
a.v.a anu s.v.,
oi e not appiacao m.
LLANCE REQUIREMENTS 4.7.10.4 ch of the fire hose stations given in Table 3.7-3 shall b demonstrated ERABLE:
a.
At leas nce per 31 days, by a visual inspection ohe fire hose stations a ssible during plant operations to ure all required j
equipment is the station, j
b.
At least once per months, by:
j 1)
Visual inspection the stati ns not accessible during plant operations to assure 1r uired equipment is at the station, 2)
Removing the hose for 'ns tion.nd reracking, and 3)
Inspecting all ga Wets and rep ing any degraded gaskets in the couplings.
c.
At least once per yea'rs, by:
1)
Partiall opening each hose station valve to ify valve OPERA. ITY and no flow blockage, and i
i I
2)
C ucting a hose hydrostatic test at a pressure of 2 psig or t least 50 psig above maximum fire main operating press
,N whichever is greater.
f CAT WBA - UNITS 1 & 2 3/4 7-33 S O -3
I TFM ING PROCEDURES:
- 1) PT/0/A/4400/01M Monthly Visual Inspection of Fire Hose Stations
- 2) PT/1-2/A/4400/01V Containment Fire Protection Equipment Inspection
- 3) PT/0'A/4400/01N Hydrostatic Test for Fire Hose
- 4) PT/6/A/4400/01W Valve Operability and Water Availability Inspection REFERENCESe
- 1) Cataaba FSAR, Section 9.5.1
- 2) Catavba SER, Section 9.5.1 1
- 3) Catawba SER, Supplement 3, Section 9.5.1
- 4) Catawba Fire Protection Review, as revised
- 5) Catawba Fire Protection Commitment Index l
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8 26.fgoT6c.Tmg 5/5TEd5 1
4*UWW-SYSTEMS j l(,.9-S ~3/3 ' 11-FIRE BARRIER PENETRATIONS.
LIfi!TINC 00N0! TIC" E00 CP PATICW CMMrrME47 i,.J All fire barrier penetrations (walls, floor / ceilings, cable tray enclosures.and. other fire barriers) separating safety-related. fire areas or separating por Jons of redundant systems important to safe shutdown within a fire area and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable, piping, and ventilation duct pene-tration seals) shall be OPERABLE.
APPLICABILITY:
At all times.
gyspuu-ACTION:
With one or more of the above required fire barrier penetrations h
and/or sealing devices inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either establish a centinuous fire watch on at least one side of the affected pene-trat. ion, or verify the OPERABILITY of fire detectors on at least one side of the inoperable penetration and estaolish an hourly fire watch patrol.
The p.vv is iuna cf Spccificeticas 2.0.3 rd 3.0.
- cce not eppliccM c.
-b.
N
. RVEILLANCE RE0VIREMENTS f
4.7.11.1 At t once per 18 months the above required fire barr' penetrations and s ing devices shall be verified OPERABLE by rforming a visual inspection of:
f a.
The exposed surfaces f each fire rated ass b.
At least 10% of all / ire dai rs.
apparent changes in appearance or abnormal degradation are fou a visual inspection of an additional 10% of the damper al e made.
This inspection process shall continue un '
a 10% sam with no apparent changes in appearance or abno.
degradation is nd.
Samples snall be selected such that ch fire damper will be 1 ected every 15
{
years;.and c.
At least 1 of each type of sealed penetration.
If ap rent changes in appea nce or abnormr.1 degradations are found, a visua
'nspection of an dditional 10% of each type of sealed penetration snal e mace.
ThJ inspection process snali continue ijntil a 10% sample with n Apparent changes in appearance or abnormal degradation is found.
,/ Samples shall be selected such that eacn penetration seal will be inspected every 15 years.
l(o.3 - 9 l
-- _ NjIY_N 2 ~
3' 3
TESTING PROCEDURES:
- 1) PT/0/A/4200/48 Periodic Inspection of Fire Barriers And Related Structures
- 2) PT/0/A/4400/01H Fire Door Inspections
REFERENCES:
- 1) Catawba FSAR, Section 9.5.1
- 2) Catawba SER, Section 9.5.1
- 3) Catawba SER, Supplement 3, Section 9.5.1
- 4) Catawba Fire Protection Review, as revised f
- 5) Catawba Fire Protection Commitment Indey I
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llo.9 Au.xit 4Ay 5FT6M Ftte f7tcnccravJ SYS* TEM
-ItCTRut4CNTAT:Cr FIRE DETECTION INSTRUMENTATION S.9-6 i!"!TINC CON 0!?OF c0P OPEP^7?CF F 6 NN/ TN64T j
'^ As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 2.2 Q shall be OPERABLE.
1(o.cl-2.
I APPLICABILITY:
Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
WEpiAL-ACTION:
16 9 -
Withany,butnotmorethanone-halfthetotalinanyf:irezone, a.
Function A fire detection instruments shown in Table 9.
'd inoperable, restore the inoperable instrument (s) to OPERABLE status within 14 days or 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 inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations listed in 'TMnicer, Speci fication 4.6.1.5.
163-2.
b.
With more than one-half of the nction A fire detection instruments in any fire zone snown in Table =
11-inoperable, or with any, llo. M Function B fire detection instruments shown in Table 4,*r4t{ inoperable, or with any two or more adjacent fire detection instruments shown in b8,.3,, %M inoperable, 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 contain-ment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations listed inf5 specification 4.6.1.5. ' 'TEchnim!
N c
The provis'ons of pecific/tions3
.3 an 3.0.4 are not ap icable.
/
/
SU EILLANCE REO REMEN
.3.3.8.1 ach of e above equired make d ection flame d ection in eru-ments wh' h are cessible uring p1 nt oper tion sha be demo trated OP,ABLE j
at le once p 6 month by perf mance a TRIP CTUATING VICE OPER" IONAL TEST Detect s.which e not ac essible uring pl nt operat'on shall b demon-st ated OPE LE by th perform ce of a iRIP ACT TING DEVI E OPERATIO L TEST ring eac COLD SHU OWN exte ding 24 ours uni ss perform d in the p,vious 6 months.
- 4. 3. 3.
2 Each f the abov require heat det ction ins uments sh I be demo stra ed OPERAB as follow :
I a.
Fo nonrestora e spot-ty e detecto s, at le t two det ctors out of i
e ery hundred or fracti n thereof shall be removed e ry 5 yea s nd functiona ly tested.
For iaach failure at occurs on the d tectors removed, two additional detectors shall be emoved an tested; and i-i
-en
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i em gm
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1 TT. STING PROCEDURES:
i
- 1) IP/0/A/3350/03 Fire Detection System (EFA) Analog Channel Test Procedure q
l
- 2) IP/0/A/3350/04-15, Fire Detection System (EFA) Detector Test Procedure Data 23-34, 39 Gathering Panels 1-12, 20-31, 36 i
- 3) IP/0/A/3350/40 Alison Control Unit Calibration Procedure
)
- 4) IP/0/A/3350/45 Fire Detection System (EFA) Detector Test Procedure For All Detector Gathering Panels REFERENCES-f
- 1) Catawba FSAR, Section 9.5.1
- 2) Catawba SER, Section 9.5.1
- 3) Catawba SER, Supplement 2, Section 9.5.1 1
- 4) Catawba SER, Supplement 3, Section 9.5.1 l
- 5) Catawba Fire Protection Review, as Revised
- 6) Catawba Fire Protection Commitment Index t
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lb8 ALLkluAftY 6 SYSTEMS Fire Pfto-rec.Tjod sys7 ens a
e p_p d#4=>ter STANOBY SHUTDOWN SYSTEM LWITI."O C0"0!'r!0" "0" ^"C"AT!O" + - (dMM /TW EATT-C. 7. ;; The Standby Shutdown Sy. stem (SSS) shall be OPERABLE.
APPLICABIL'ITY: MODES 1,, 2, and 3.
(.
p'69tAL ACTION: P(Un4Ys 1 and.2)
. ',,./. -
l a.
With the Standby'Shutdow'n System. inoperable, restore the inoperable equi ~pment to OPERABLE status within 7 days or be in at least HOT STANOBY 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 at least HOT SHUT 00WN within the.following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
e li!e%74-b.
With the to'talMl'eakage trom UNIDENTIFIED LEAKAGE, IDENTIFIED LEAKAGE and reactor coolant pump seal leakage greate than 26 gpm, declare the Standby Makeup Pump inoperable and take ACTION a.,
- above, c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable SU ANCE RE0VIREMENTS
~
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4.7.13.1 The andby Shutdown System diesel generator shall be dem strated OPERABLE-i a.
At least once r 31 days by verifying:
1)
The fuel level the fuel storage tank i greater than or equal f
to 67 inches, and 2)
The diesel starts from ient co tions and operates for at least 30 minutes at greate tha or equal to 700 kW.
b.
At least once per 92 days by ver' yi thit a sample of diesel fuel from the fuel storage tank, ob ined in ccordance with ASTM-0270-1975, is within the acceptable lirr' s specified
- Table 1 of ASTM-0975-1977 when checked for viscosit and water and se ~ ent; and c.
At least once per 18 nths, during shutdown, by bjecting the diesel f
to an inspection in ccordance with procedures prepa d in conjunction I
1 with its manufact er's recommendations for the class service.
4.7.13.2 The Standby 5 tdown System diesel starting 24-volt battery ank and charger shall be demon rated OPERABLE:
j a.
At least nce per 7 days by verifying that:
~
1) e electrolyte level of each battery is above the plates; and The overall battery voltage is greater than or equal to 24 volts.
1 CATAWOA - whit 5 i & 2 3/4 7-4G
~
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TESTING PROCEDURES:
I l
- 1) PT/1-2/A/4200/02 Refueling Containment Integrity Verification
- 2) PT/0/A/4200/17 Standby Shutdown Facility Diesel Test l
l
- 3) CP/0/A/8800/05 Chemistry Procedure For Recording and Management of Data j
- 4) PM/IG-122 DG Preventive Maintenance l
- 5) PT/1-2/A/4150/01 Leakage Verification
- 6) PT/1-2/A/4600/02 Technical Specification 3.9.10
- 7) CP/0/A/8100/16 Boron Concentration
- 8) PT/1-2/A/4600/02 Refueling Water Storago Tank-Standby Makeup Pump l
Alignment f
- 9) PT/1-2/A/4200/07C Standby Makeup Pump Performance
- 10) PT/1-2/A/4250/03C Turbine Driven Auxiliary Feedwater Pump Performance Test 1
- 11) PT/0/A/4600/03 Channel Check on SSF
- 12) IP/0/B/3061/20 Battery Voltage Verification l
l
- 13) IP/0/B/3061/20 Battery Condition Check
- 14) IP/0/B/3061/02 Battery Electrolyte Level 15)
IP/0/B/3061/02 Total Battery Terminal Voltage
- 16) IP/0/B/3061/02 Average Specific Gravity
- 17) IP/0/B/3061/07A Battery Condition Check
- 18) IP/0/B/3216/02 Foxboro 13A Flow XMTR Calib
- 19) IP/0/B/3216/04 Foxboro E13DM D/P XHTR Calib
- 20) IP/0/B/3216/06 Foxboro E71GH XMTR Calib
- 21) IP/0/B/3250/08 Hays Rep V5A Indicator Calib
- 22) IP/0/B/3252/01 SSF S/G Level Calib
- 23) IP/0/B/3214/02 Rosemount 1153G XMTR Calib
- 24) IP/0/B/3007/10E Incore T/C SSF Temp Readouts
- 25) IP/0/B/3007/10F Incore T/C Ref JCT Temp Deviation
- 26) IP/0/B/3000/09N SSF NC Press Loop Calib
- 27) IP/0/B/3000/09P SSF Pressurizer Level Calib l
1 1
REFERENCES t_
- 1) Catawba FSAR, Section 9.5.1
- 2) Catawba SER, Section 9.5.1
- 3) Catawba SER, Supplement 4, Section 9.5.1
- 4) Catawba Fire Protection Review, as Revised l
- 5) Catawba Fire Protection Safe Shutdown Review
- 6) IEEE 308-1974 Class 1E Power Systems
- 7) IEEE 450-1975 Maintenance, Testing and Replacement of Large Lead Storage Batteries
- 8) OP/0/B/6350/11 Standby Shutdown Facility Diesel Operation
- 9) OP/0/B/6100/13 Standby Shutdown Facility Operations l
i i
CATAWBA NUCLEAR STATION FINAL SAFETY ANALYSIS REPORT
(
I CHAPTER 16.13 SELECTED LICENSEE COMMITMENTS CONDUCT OF OPERATIONS Table of Contents 16.13-1 Fire Brigade 1
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I 16.13-0 I
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I 16.13 CONDUCT OF OPERATIONS l
1 OPERATORS l
16.13-1 FIRE BRIGADE C0KMITMENT A site Fire Brigade of at least five members shall be maintained onsite at all l
times.
The Fire Brigade shall not include three members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
APPLICABILITY: At all times.
REMEDIAL ACTION:
With the Fire Brigade composition less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence, take immediate action to fill the required positions.
TESTING PROCEDURES:
- 1) Operations Management Procedure 2-2
REFERENCES:
- 1) Catawba FSAR, Chapter 13.2 l
- 2) Catawba SER, Section 9.5.1 and Appendix D
- 3) Catawba Fire Protection Review, as revised
- 4) Catawba Fire Protection Commitment Index l
l l
16.13-1
16.9-l, g.p l of 2.
TABLE + + t FIRE HOSE STATIONS i
LOCATION ELEVATION HOSE RACK #
1.
Auxiliary Building 59, FF 522+0-1RF235 522+0.- (
1RF248 55, FF 63, MM '
.543+0.'
1RF210
..- 543+0 63.64,'KK.
1RF211 60, MM.
543+0"'
1RF212 58, PP-543+0 1RF218 59, GG-HH 543+0 1RF236 60'-61, FF-GG 543+0 1RF237 63, CC 543+0-1RF238
)
57, JJ 543+0 1RF242 54-55, GG 543+0 1RF249 57,FF 543+0 1RF250 52-53, GG 543+0 1RF255 51, CC 543+0 1RF256 50-51, JJ-KK 543+0 1RF262 53, MM 543+0.
1RF268 50-51, NN 543+0 1RF271 62, MM-NN 560+0 1RF203 63, JJ-KK 560+0 1RF213 58, PP 560+0 1RF219 56, NN 560+0
.1RF220 59, HH 560+0 1RF239 57, KK 560+0 1RF243 54-55, FF-GG 560+0 1RF251 51, KK 560+0 1RF263 52, MM-NN 560+0 1RF269 58, BB 554+0 1RF484 65, BB-CC 560+0 1RF485 62, AA-BB 560+0 1RF486 56, BB 554+0 1RF487 52, AA-BB 560+0 1RF488 49, BB-CC 560+0 1RF489 68-69, BB 560+0 1RF996 45-46, BB 560+0 1RF997 63, NN 577+0 1RF204 61, LL 577+0 1RF214 577+0 1RF215 63, KK-LL 577+0 1RF221-58, PP 59, JJ 577+0 1RF230
'58, GG 577+0 1RF240 56, KK 577+0 1RF244 54, GG 577+0 1RF252 52-53, KK 577+0 1RF258 51, KK 577+0 1RF264 51-52', NN 577+0 1RF272 56, PP 577+0 1RF278 68-69, BB 577+0 1RF478 CA7AG A - UNIT 3 1 & 2
-3/^ W
1 e
[bS-I, p3e 2 f2.
i TABLE 9=pa9-(Continued)
FIRE HOSE STATIONS 1
d LOCATION ELEVATION HOSE RACK #
.i t
65, BB-CC 577+0 1RF479 j
59, DD 574+0 1RF480 l
60, AA 574+0 1RF481 j
49, BB-CC 577+0 1RF490 45, 88 577+0 1RF491 55, DD 574+0 1RF492 54, AA 574+0 1RF493 63, AA 577+0 1RF993 51, AA 577+0 1RF998 62, NN 594+0 1RF205 1
57, MM 594+0 1RF222 63, JJ 594+0 1RF231 57, HH 594+0 1RF245 57, EE 594+0 1RF253 61 JJ 594+0 1RF259 53, NN 594+0 1RF275 64, BB 594+0 1RF984 l
50, BB 594+0 1RF985 51, KK 605+10 1RF265 63, JJ 605+10 1RF233 I
J 63-64, MM 631+6 1RF483 50-51, MM 631+6 1RF495 2.
Fuel Pools 65, TT-UU 605+10 1RF208 48, TT-UU 605+10 1RF276 i
63-64, MM 605+10 1RF482 4
50-51, MM 605+10 1RF822 l
3.
Nuclear Service Water Pump Structure East Section 600+0 1RF939 r
I West Section 600+0 1RF940 l
l r uii---UNITS 1-M 7,l'7 1 o_______
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