Text

Proposed Tech Specs,Relocating All Fire Protection Related Requirements from Tech Specs to FSAR While Adding Fire Protection Program to Items Included in Specs 6.5.1 & 6.8.1, Per Generic Ltr 88-12 Guidance
	ML20012D785
Person / Time
Site:	Catawba
Issue date:	03/13/1990
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20012D783	List: ML20012D782; ML20012D785;
References
	GL-88-12, NUDOCS 9003280367
	Download: ML20012D785 (38)
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Attachment i Proposed Technical Specification Chances l

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9003280367 900313 PDR ADOCK O'~000413 P

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS-SECTIQN.

PACE TA8LE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4 3-60 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................................

3/4 3-61 Remote Shutdown System...................................

3/4 3-62 TA8LE 3.3-9 REMOTE SNUTDOWN MONITORING INSTRUMENTATION............

3/4 3-63 TABLE 4.3-6 REMOTE SNUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................

3/4 3-64 Accident Monitoring Instrumentation......................

3/4 3-65 TA8LE 3,3-10 ACCIDENT MONITORING INSTRUMENTATION..................

3/4 3-66 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................................

3/4 3-68 Chlorine Detection Systems...............................

3/4 3-70 Oe ld eg f'r; 0;t;;;i;n In;tn nt:tien..........................

3/t 3-71 TAOL: 3.0 11 TIR: 00':CTIO" I"0T*.'"5"Tf ?!0".....

3/? +M-l Loose-Part Detection System..............................

3/4 3-77

. Radioactive Liquid Effluent Monitoring Instrumentation...

3/4 3-78 l'

TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-79 L

TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING.

INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-81 Radioactive Gaseous Effluent Monitoring Instrumentation..

3/4 3-83 TABLE 3.3-13 RADICACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION..........................................

3/4 3-84 TABLE 4.3-9 RADI0 ACTIVE GASEOUS EFFLUENT' MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-88 3/4.3.4 TUR81NE OVERSPEED PROTECTION..............................

3/4 3-91 3/4.4 REACTOR COOLANT SYSTEM l

~ 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION l

Startup and Power Operation..............................

3/4 4-1 l

l Hot Standby..............................................

3/4 4-2 j

l Hot Shutdown.......................

3/4 4-3 l

Cold Shutdown - Loops Fi11ed.............................

3/4 4-5 Cold Shutdown - Locos Not Fi11ed.........................

3/4 4-6 L

CATAW8A - UNITS 1 & 2 VI

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LIMITING CONDITION 5'FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE

Divider 8arrier Personnel Access Doors and Equipment Natches.......................................

3/4 6 47 t Containment Air Return and Nydrogen Skisumer Systems......

3/4 6-48

, Floor 0 rains.........................'....................

3/4 6-50 Refueling Canal 0 rains.............................

3/4 6-51 Divider Barrier Sea1.....................................

3/4 6-52 g

.TA8LE 3.6-3 DIVIDER BARRIER SEAL ACCEPTA8LE PNYSICAL PROPERTIES...

.3/4 6-53 i

3/4.6.6 CONTAINMENT VALVE INJECTION WATER SYSTEM................

3/4 6-54

~ 3/4.7 PLANT SYSTEMS 3/4.7.1 TUR81NE CYCLE tSafety Va1ves............................................

3/4 7-1 TA8LE 3; 7-1 MAXIMUM ALLOWA8LE POWER RANGE NEUTRON FLUX NIGM-SETPOINT WITN INOPERA8LE STEAM LINE SAFETY VALVES OURING

-FOUR LOOP 0PERATION......................................

3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................

3/4 7-3

p. Auxiliary Feedwater System...............................

3/4 7-4 Specific Activity........................................

3/4 7-6 TABLE 4.7-1 -SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE ANO~ ANALYSIS PR0 GRAM.....................................

3/4 7-7 I Nain Steam Line Isolation va1ves.........................

3/4 7-8 a

. Condensate Storage System.....................,..........

3/4 7-9 3/4.7.2 ?$ TEAM GENERATOR PRESSURE / TEMPERATURE LINITATION..........

3/4.7-10 3/4.7.3 'CONPONENT COOLING WATER SYSTEM...........................

3/4 7-11 3/4.7.4 i NUCLEAR SERVICE WATER SYSTEM.............................

3/4 7-12 3/4.7.5L, STAN08Y NUCLEAR SERVICE WATER PON0.......................

3/4 7-13 3/4.7.6. CONTROL ROOM AREA VENTILATION SYSTEM.....................

3/4 7-14 3/4.7.7 iAUXILIARY 8UILDING FILTERED EXNAUST SYSTEM...............

3/4 7-17 3/4.7.8 ' SNU88ERS.................................................

3/4 7-19

. FIGURE 4.7-1 SANPLE PLAN 2) FOR SNU68ER. FUNCTIONAL TEST...........

3/4 7-24 3/4.7.9 0 SEALED SOURCE CONTAMINATION................

3/4 7-25 3/4. 7. x, ==== :Y:=

Deid ecA P i r e 0.pp r e e s i e n Wart e r System............................

3/4 7-27

- Srty r-'/er 5;r%M:r Sy:::::.

/? 7-0 s

, w2 aystems..............................................

.U

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" ; M::: ::: tier.........

3/4 7

-CATAW8A

. UNITS 1 & 2 IX

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^1 LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

SECTION.

PAGE f

L

,C;.E 3. 7-3 FI*E "a!! STA.TIOMS......

3/* '-34 3/4. 7.11 o ""5 "'""' E' "9UJIO"S -

3/? 7-3C 3/4.7.12pGROUN0 WATER' LEVEL........................................

3/4 7-38 3/4.7.13oSTANDBY SHUTDOWN SYSTEM..................................

3/4 7-40 m

3/4.8 ELECTRICAL POWER SYSTENS 1

l N4.8.1 A.C. SOURCES Operating................................................

3/4 8-1 l

l TA8LE 4.8-1 DIESEL GENERATOR TEST SCHEDULE........................

3/4 8-9 TABLE 4.8-2 LOAD SEQUENCING TIMES.................................

3/4 8-10 Shutdown................................................

3/4 8-11 3/4.8.2 0.C. SOURCES Operating................,................................

3/4 8-12 L

TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS.....................

3/4 8-15 Shutdown.......................................

3/4 8-16 4

3/4.8.3 ONSITE P0WER DISTRIBUTION Operating................................................

3/4 8 --

Shutdown.................................................

3/4 8 3/4.9.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES L

Containment Penetration Conductor Overcurrent L

Protective 0evices.....................................

3/4 8-19 TABLE 3.8-1 CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECTIVE DEVICES.......................................

3/4 8-21 3/4.9 REFUELING OPERATIONS l

3/4.9.1 BORON CONCENTRATION......................................

3/4 9-1 3/4.9.2 INSTRUMENTATION..........................................

3/4 9-2 3/4.9.3 DECAY TIME...............................................

3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................

3/4 9-4 1

3/4.9.5-C0MUNICATIONS...........................................

3/4 9-7 L.

3/4.9.6 MANIPULATOR CRANE........................................

3/4 9-8 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING..........

3/4 9-9 h

L L

CATAWBA - UNITS 1 & 2 X

J BASES llll; s

SECTION PAGE v

TABLE 8 3/4.4-1 REACTOR VESSEL 70VGNNESS..........................

8 3/4 4-9 FIGURE 8 3/4.4 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 SNIFT OF RT FOR REACTOR VESSELS EXPOSED TO 550*F............

B 3/4 4-12 NOT 3/4.4.10 STRUCTURAL INTEGRITY.....................................

8 3/4 4-16 3/4.4.11 REACTOR C00LANT SYSTEM VENTS.............................

B 3/4 4-17

'3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS..............................................

8 3/4 5-1 3/4.5.2; and 3/4.5.3 ECCS SU85YSTEMS...............................

8 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK..............................

B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS sp. 3/4.6.1 PRIMARY CONTAINMENT.......................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS......................

B 3/4 6-4 3/4.6.3 CONTAINMENT ISOLATION VALVES..............................

B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L...................................

B 3/4 6-4 3/4.6.5 ICE CON 0ENSER.............................................

B 3/4 6-5 3/4. 7 - P LANT SYSTEMS 3/4.7.1 TUR8INE 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 SYSTEM............................

B 3/4'7-3 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM..............................

B 3/4 7-3 3/4.7.5 STAN08Y NUCLEAR SERVICE WATER PON0........................

B 3/4 7-3 3/4. 7. 6. CONTROL ROOM AREA VENTILATION SYSTEM......................

B 3/4 7-3 3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM................

B 3/4 7-4 4

3/4.7.B ' SNUB 8ERS..................................................

B 3/4 7-4 3/4.7.9 SEALED SOURCE CONTAMINATION...............................

B 3/4 7-6 3/4. 7.10 TIRC Our? :SSION SYST "S........ DW...WX.........

0-S/4 7 0 3/4.7.11-FERE BARRIER PENETRATIONS....

! 3/? 7-7 3/4.7.12 GROUNDWATER LEVEL.........................................

B 3/4 7-7 b

3/4.7.13 STAN08Y SHUT 00WN SYSTEM...................................

B 3/4 7-8

. CATAWBA - UNITS 1 & 2 XIV

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INSTRUMENTATION O.

h FIRE DETECTION INSTltVMENTATION' j

I P

LINITING CONDITION RATION

~3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required.to be OPERA 8LE.

ACTION:

a.-

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, restore the inoperable instrument (s) to OPERA 8LE status within 14 days or within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

b.

With more than one-half of the Function A fire detection instruments in any fire zone shown in Table 3.3-11 inoperable, or with any Os Function B fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detec*. ion instruments shown in Table 3.3-11 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months estaolish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at'least

-once per hour, unless the instrument (r.) is located inside the contain-ment, then inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above required smoke detection or flame detection instru-ments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST.

Detectors wtHch are not accessible during plant operation shall be demon-strated OPERA 8LE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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:

a.

For nonrestorable spot-type detectors, at least two detectors out of O

every hundred, or fraction thereof, shall be removed every 5 years and functionally testad.

For each failure that occurs on the detectore removed, two additional detectors shall be removed and tested; and CATAWBA - UNIT 1 & 2 3/4 3-71 Amendment No. 48 -(Uni Amendment No. 41 (Unit

L^'

{ Re mov ec}

INSTRUMENTATION-FIRE DETECTION INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) i b.

For restorable spot-type heat detectors, at least one detector on i

each signa) initiating circuit sha11 be demonstrated OPER OPERATIONAL TEST. Different detectors shall be selected for each test.

shall be demonstrated OPERABLE by the performance DEVICE-OPERATIONAL TEST during-each COLD SHUTDOWN exceeding unless performed in the previous 6 months.

4.3.3.8.3 with,the detector alarms of each of the above required fire de I

shall be demonstrated OPERABLE at least once per 6 months, uments

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t CATAWBA - UNITS 1 & 2-3/4 3-72

TA8tE 3.3-11 k

5 FIRE DEIECTION INSIRINENIS F1RE MINIfENI INSTRt#ENTS OPERAStE* -

E 20NE DESCRIPIl0N LOCAll0N SfGEE FLAfE NEAT FINICTION**

e

[

1 R.H.R. Pump 18 GG-53 El.522 + 0 1

0 1

A 2

R.H.R. Pump 1A FF-53 El.522 + 0 1

0 1

A 3

Cont. Spray Pump 18 GG-54 El.522 + 0 3

0 3

A 4

Cont. Spray Pump 1A GG-55 El.522 + 0 2

0 2

A 5

R.H.R. Pump 28 GG-61 El.522 + 0 1

0 1

A 6

R.H.R. Pump 2A FF-61 El.522 + 0 1

0 1

A 7

Cont. Spray Pump 28 GG-60 El.522 + 0 3

0 3

A 8

Cont. Spray Pump 2A GG-59 EI.522 + 0 2

0 2

A 9

Aux. F. W. Pumps 88-51 El.543 + 0 14 0

12(6)

A(8) 10 Mech. Pene. Room JJ-52 El.543 + 0 3

0 3

A w

11 Corridor / Cables NN-51 El.543 + 0 6

0 6

A D

12 Recip. Chg. Pump JJ-53 El.543 + 0 1

0 1

A w

13 Safety inj Pump 18 HH-53 EI.543 + 0 1

0 1

A y

14 Safety inj Pump 1A GG-53 El.543 + 0 1

0 1

A i

15 Cent. Chg. Pump 18

.JJ-54 E1.543 + 0 2

0 2

A 16 Cent. Chg. Pump 1A JJ-55 El.543 + 0 2

.0 2

A 17 Aisles / Cables KK-56 El.543 + 0 18 0

18 A

l 18 Aisles / Cables EE-55 EI.543 + 0 6

0 6

A i

19 AFW Pumps (Unit 2) 88-63 El.543 + 0 14 0

12(6)

A(8) 20 Mech. Pene. Room JJ-62 El.543 + 0' 3

0 3

A 21 Aisles / Cables IIN-61 El.543 + 0

'6 0

6-A 22 Recip. Chg. Pump JJ-60 El.543 + 0 1

0 1

A 23 Safety inj. Pump 28 191-6 0 El.543 + 0 1

0 1

A yo 24 Safety inj. Pump 2A GG-60; El.543 + 0

.1 0

1 A

m 25 Cent. Chg. Pump 28 JJ-59 El.543 + 0 2

0 2

A 26 Cent. Chg. Pump 2A JJ-58 El.543

O

-2 0

2 A

27 Aisles / Cables KK-59 El.543 + 0 20 0

20 A

O 28 Aisles / Cables EE-58 El.543 + 0 6

0 6

A 4

29 SW Gear Equip. Room AA-50 El.560 + 0 7

0 0

A rb

.g 30 Elect. Pene. Room CC-50 El.560 + 0 8

0 0

A 31 Corridor / Cables EE-53 El.560 +'0 5

0 5

A 32 Corridor / Cables KK-52 El.560 + 0 8

0 8

A 33 Corridor / Cables NN-54.

El.560 + 0 10

^0 10 A

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.A

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-y y

IA8tE-3.3-11 (Continued)

FIRE DEIECTION IN51Rt01ENIS s

[

FIRE MINige01 INSTAL 0ENTS OPERA 0tE*

3 ZONE DESCRIPIl0N LOCATION 5-=E FLAfE NEAT FINICTIONa*

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[

34 Aisles / Cables JJ-56 El.560 + 0 14 0

14 A

35 Motor Control Centers GG-56 El.560 + 0 2

0 2

A 36 Cable Iray Access FF-56 -El.560 + 0 2

0 2

A 37 Equip. Batteries 00-55 El.554 + 0 5

0 4

A 30 Equip. Batteries CC-55 El.554 + 0 5

0 4

A 39 Battery Room CC-56 El.554 + 0 17 0

0 A

41 SW Gear Equip. Room AA-64 El.560 + 0 7

0

.O A

42 Elect. Pene. Room CC-65 El.560 + 0 0

0 0

A 43 Corrider/ Cables FF-61 El.560 + 0 5

0 5

A w

44 Aisles / Cables KK-63 El.560 + 0 0

0 0

A 45 Aisles / Cables 800-6 0 E1.560 + 0 13 0

13 A

w 46 Aisles / Cables 601-5 9 - El.560 + 0 13 0

13 A

O 47 Motor Control Center GG-50 El.560 + 0 2

0 2

A 40 Cable Tray Access FF-50 El.560 + 0 2

0 2

A 49 Equip. Batteries 00-60 El.560 + 0 5

0 4

A 50 Equip. Batteries CC-60 El.560 + 0 5

0 4

A 51 Battery Room CC-59 E1.560 + 0 17 0

0 A

53 SW Gear Equip. Room AA-49 El.577

0 7

0 0

A 54 Aisles / Cables' CC-50 El.577 + 0 10 0

0 A

55 Aisles / Cables NN-52 El.577 + 0 9

0 9

A 56 Aisles / Cables PP-55 El.577 + 0 13 0

13 A

h' 57 Aisles / Cables LL-55 El.577 + 0 11 0

11 A

y 50 Aisles / Cables HH-55 El.577 + 0 21 0

21 A

4 59 Motor Control Center EE-54 El.577 + 0 2

0 2

A 60 Cable Room CC-56 El.574 + 0 10 0

15 A

D 62 SW Gear Equip. Room AA-64 El.577 + 0 7

0 0

A O

63 Elect. Pene. Room CC-64 El.577 + 0 10 0

0 A

i 64 Aisles / Cables PP-62 El.577 + 0 9

0 9

A eb 65 Aisles / Cables PP-59 El.577 + 0 16 0

16 A

f) 66 Aisles / Cables LL-59 El.577 + 0 11 0

11 A

67 Aisles / Cables llH-59 El.577

O 21 0

21 A

68 Motor Control Center JF-60 El.577 + 0 2

0-2 A

[

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"i TA8tE 3.3-11 (Continued) 9 y

FIRE DETECT 10Bi INSTMBENTS t

1 h

FIRE MINI 8est INSTRtSENis OPEWABLE*

5 (01E DESCRIPTION LOCATICII 5BWRE FIJWE IEAT FtBICTION"*

U 69 Cele poem CC-59 E1.577 + 0 le 0

15 A

71 Elect Pene. Rose CC-51 E1.5M + 0 le 0

0 A

l 72 Control Room CC-M E1.594 + 0 23 0

6 A

=

73 Vent. Equip. Room FF-54 E1.594 + 0 9

0 0

A i!

74 Aisles / Cables LL-M E1.594 + 0 25 0

25 A

~i f

76 Aistas/Celes PP-54 EI.594 + 0 15 0

15 A

19 Elect. Pene. Room SR-63 E1.594 + 0 11 0

0 A

i!

80 Control Room 88-59 E1.594 + 0 22 4

6 A

'l 81 Ven. Equip. Room FF-58 E1.594 + 0 12 0

0 A

82 Aisles /Celes KK-58 E1.594 + 0 28 0

27 A

1 q

84 Aisles /Celes 886-SS E1.594 + 0 17 0

17 A

l 89 Fuel Pool Area #1 PP-50 El.605 + le 19 7

19 A

i y

90 Fuel Pool Area (Unit 2)

PP-64 E1.605 + le 19 7

19 A

y 128*

UNI Bldg.

Det-44 E1.550 + 0 2

3 2

A l

i 129 Fuel Pool Purge Roan Ist- % E1.631 + 6 6

0 6

A 130*

UNI Bldg. (Unit 2) 596-7 1 E1.594 + 0 2

3 2

A l

i 131 Reactor Bldg.

0*-45' sel. E1.%5 + 3 4

0 0

A i

l 132 Reac',or 81dg.

45*-90*

Be1. E1. M5 + 3 3

0 0

A l

133 Reactor 31dg.

90*-135*

Se1.

E1. M5 + 3 4

0 0

A l

l 134 Reactor Bldg.

135*-180 Be E.

E1. M 5 + 3 5

0 0

A i

135 Reactor sidg.

180*-225' Be1.

E1. M5 + 3 4

0 0

A I

136 Reactor Bldg.

270*-315' 0=1.

E1. M5 + 3 3

0 0

A p

j I

137 Reactor Bldg.

315*-0*

Se1. E1.565 + 3 0

-0 0

A l

138 Reactor Ridg.

0*-45*

Se1. E1.506 + 3 6

0 0

A EE 139 lieactor 81dg.

45*-90*

Se1. E1.506 + 3 4

0 0

A i

gg-140 Ileactor Bldg.

90*-135*

Be1.

E1.MS + 3 3

0 0

A i

141 Reactor $1dg.

135*-180 Se1. E1.506 + 3 0

0 0

A O

OM 142 Reactor Bldg.

180*-225*

Se1. E1.506 + 3 5

0 0

A

(

i 143 Reactor Bldg.

315*-8*

4el. E1.506 + 3 5

0 0

A

^^

EE 144 Reactor 81dg.

0*-45*'

Be1. E1.593 + 2%

14 0

0 A

95 Reactor 81dg.

45*-90*

8e 1.

E1.593 + 2's 17 0

0 A

b S

Reactor 81dg.90-135' 4el. E1.593 + 2%

11 0

G A

f n the disconnection of the UHI System from the Reacter Coolant System, these specifications are as

~

er applicable.

i a

-.. ---....-.-i -

~..

TABLE 3.3-11 (Cestinued) 9

-4 FIIE DEIECTION ISISTRtS;Elets FIAE 86888888 31 IIISTEISEIITS SPEGAgtE*

k Z0sIE DESCRIPileII LOCATIG81

{

SfSR FIAE IEAT FWETIWe**

l 3

f

-e

[

147 Reactor 31!4g.

135*-1FA*

Bel.[1.593+2%

10 S

e A

l its Reacter Bldg.

180*-225' Bel. El.593 + 2%

2 0

S A

i 149 Reacter 8143 315*-0*

Sel. El.393 + 2%

7 8

8 A

159 Reacter Bldg. (Unit 2) 9*-45' Sel. El.M5 + 3 4

0 0

A f

151 Seactor Sidg. (IInit 2) 45*-90*

Se1. El.565 + 3 3

e e

A i

152 lleacter Bldg. (Unit 2) 90*-135'-

ta;t. El.M5 + 3 4

8 e

A 153 Seacter 8143. (Unit 2) 135*-189*

3el. E1. M5 + 3 5

e e

A l

I 154 Reacter Side. (IInit 2) 180*-225' 3el. El.M5 + 3 3

0 0

A 155 Reacter Bldg. (Unit 2) 278*-315*

tel. El. M 5 + 3 4

8 9

A 156 seacter aldg. (unit 2) 315*-o*

sel. El. M5 + 3 6

e e

A R

157 Reacter 814g. (Ifnit 2) 0*-45*

Se1. EI.586 + 6 6

0 S

A l

15s neacter side. (unit 2) 45*-9e*

rel. El.586 + 6 4

e o

A y

159 seacter Side. (unit 2) 98*-135' Se1. El.586 + 6 3

e e

A

~

16e seacter aldg. (Unit 2) 135*-189*

set. El.5e6 + 6 e

o o -

A 161 seacter 814g. (unit 2) 1e0*-225' sel. fl.bes + 6 5

e o

A j

162 seacter side. (unit 2) 315*-o*

sel. El.5GE + 6 5

0 0

A 163 neacter eles. (unit 2) e*-45' eel. 0.593 + 2%

13 e

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lhe fire detection instruments !ocated within the centainment are not required to be OPEKMLE during the performance of lype A Containment teakage Rate tests.

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Q W D \\) @ C PLANT SYSTEMS FIRE H0SE STATIONS LINITING CON 0! TION FOR OPERATION 3.7.10.4 The fire hose stations given in Table 3.7-3 shall be OPERABLE.

t APPLMCA81LITY: Whenever equipment in the areas protected by the fire hose stat'ons is required to be OPERA 8LE.

ACTION, With one or more of the fire hose stations given in Table 3.7-3 a.
inoperable, provide gated wye (s) on the nearest OPEP.A8LE hose station (s).
One outlet of the wye shall be connected to the standard length of hose provided for the hose station.
The second outlet of the wye shall be connected to a length of hose sufficient l
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 hazard to station personnel, plant equipment, or the home itself, the fire hese shall be stcred in a roll at the outlet of the OPERA 8LE hose station.
Signs shall be mounted above the gated wye (s) tc identify E
the proper hose to use.
The above ACTION requirement shall be I
accomplisnec within 1 bour if the inoperable fire hose is the
^
primary means of fire suppression; otherwise rauta the additioaal huse within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
b.
The provisions of Specification 3.0.3 art not applicable.
SURVEILLANCE RE0VI8tENENTS 4.7,10.4 Each of the fire hose staticns given in Table 3.7-3 shall be demonstrated OPERABLE:
a.
At least once per 31 days, by a visual inspection of the fire hose stations accessible during plant operations to assure all required equipment is at the station, b.
At least once per 18 months, by:
1). Visual inspection of the stations not accessible during plant oper,ations to assure all required equipment is at the station, 2)
Removing the hose for inspection and reracking, and 3)
Inspecting all gaskets and replacing any degraded gaskets in t
i the couplings.
l c.
At least once per 3 years, by:
1)
Partially opening each hose station valve to verify valve OPERA 81LITY and no flow blockage, and 2)
Conducting a hose hydrostatic test at a pressure of 200 psig or O
at least 50 psig above maximum fire main operating pressure, whichever is greater.
CATAWBA - UNITS 1 & 2 3/4 7-33 Amendment No. 48 (Unit 1)
Amendment No. 41 (Unit 2)
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TA8LE 3.7-3 FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #
1.
Auxiliary Building 59, FF 522+0 1RF235 55, FF 522+0 1ppggg 63-64 KK 543+0 1RF210 63, M 543+0 1RF211 60, M 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 54?.+0 1RF250 52-5?, GG 543+0 1RF255 51, CC b43*0 1P1256 50-51, JJ-KK 543*C 1RF262
\\
53, M 543+0 1RF268 50-5., NN 543+0 1RF271 62,.N-NW 560+0 1RF203 63, JJ-KK 560+0 1RF213
&t 58, PP 560+0 1RF219 y '-
56, NN 560+0 1RF220 59, HH 560+0 1RF239 57 KK 560+0 1RF283 54-55. FF-GG 560+0 1RF251 51, KK 560+0 1RF2G3 52, M-NN 560+0 1RF269 08, BB 554+0 1RF484 65, 88-CC 560+0 1RF485
.62, AA-88 560+0 1RF486.
l
56. 85 554+0 1RF487 52, AA-88 560+0 1RF488 49, 88-CC 560+0 1RF489' l-68-69, 88 560+0 1RF996 l
45-46, 88 560+0 1RF997 l
63, NN 577+0 1RF204 l
61, LL 577+0 1RF214 63, KK-LL 577+0 1RF215 58, PP 577+0 1RF221 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, 88
'577+0 IRF478 CATAWBA - UNITS I &'2 3/4 7-34
htMC\\Jfd i
TA8LE 3.7-3 (Continued) l
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FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #
65, BB-CC 577+0 1RF479 59, 00 574+0 1RF430 60 AA 574+0 1RF441 49, 88-CC 577+0 1RF490 45, 88 577+0 1RF491 55, 00 574+0 1RF492 l
54, AA 574+0 1RF493
63. AA 577+0 1RF993 51, AA 577+0 1RF998 62, NN 594+0 1RF205 57, M.
594+0 1RF222 63, JJ 594+0 1RF231 57, Hrt 594+0 1RF245 57 EE E94+0 1RF253 51, JJ 594+0 1RF259 53, NN 594+0 1kF275 i
64, BB 504+0 1RFf8?,
I 50, 88 594+0 1RF985 51, KK 605+10 1RF265 l
63. JJ 605*10 1RF233 p) 63 64, m 631+6 1RF483 50-51, m 631+6 1RF495 2.
Fuel Pools 65, TT-UU 605+10 1RF208 48, TT-UU 605+10 1RFP76 G3-64,
605+10 1RFd42 50-51, m 605+10 1RF822 3.
Nuclear Service Water Pump Structure
~
East Section 600+0 1RF939 West Section 600+0 1RF940 O
CATAWBA - UNITS 1,& 2 3/4 7-35
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3/4.7.11 FIRE' BARRIER PENETRATIONS LINITING CONDITION FOR OPERATION 3.7.11 All fire barrier penetrations
=
separating portions of redundant systems impor fire area and all sealing devices e y related fire areas or tration seals) shall be OPERA 8LE. doors, fire windows, fir o safe shutdown wi cable, piping, and ventilation duct pene-fire APPLICABILITY: At all times.
t t
ACTION:
4.
With orie or more of the above required fire b and/or sealing devicer inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months eitharrier ko t
a continuous fire waten on at letst one side of th tratica, or verify the OPERABILITY of fi er establish 3
1 one sidw of the inoperable penetration and establishre detect ected pene-watch patrol, an hourly fire b.
The provisions of Specification 3.0.3 are not applicable.
_SURVEILLANCILREQUIREMENTS l
4.7.11.1 At least once 1
penetrations and sealin';per 1B months the above requife; fire barrier s
visuai inspection of:
devices shall be verified OPERABLE by perfo rming a 6.
Tht exposed surfaces of each fire rated assembl b.
y; At least 10% of all fire dampers. -If appare t or abnormal de i
additional 10% gradation are found, a visual inspection of anchanges in a n
of the dampers shall be made.
process shall continue until a 10% sample with nThis inspection in appearance or abnormal degradation is fou d o apparent change selected such that each fire damper will be inspectedSamples n.
years; and every 15 i=
.c.
At least 10% of each type of sealed penetrati in appearance or abnormal degradations are f If apparent changes on.
of an additional 10 This inspection proc % of each type of sealed penetration shall b ess shall continue until a 10% sample with no apparent changes in appearance or abnormal degradatio Samples shall be selected such that each penetrati inspected every 15 years.
n is found.
on seal will be I
W CATAWBA - UNITS 1 & 2 3/4 7-36 Amendment No. 48 (Unit 1 Amendment No. 41 (Unit 2)
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PLANT SYSTEMS
$URVEILLANCE REQUIREMENTS (Continued) 4.7.11.2 Each of the above required fire doors shall be verified OPERABLE by inspecting the closing mechanism and latches at least once per 6 months, and by verifying:
a.
The position of each interior closed fire door.at least once per 24
hours, b.
The OPERA 81LITY of the fire door supervision system for each electrically supervised fire door by performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least once per 31 days, and c.
That each locked closed fire door is closed at least once per 7 days, i
l 4
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. CATAWBA - UNITS 1 & 2 3/4 7-37 l
INSTRUMENTATION BASES l
REMOTE SHUTCOWN SYSTEM (Continued) centrol and power circuits and transfer switches necessary to eliminate effects of the fire and allow operation of instrumentation, control and power circuits required to achieve and maintain a safe snutdown condition are incepencent of areas where a fire could damage systems normally used to shutdown the reactor.
This capability is consistent with General Design Critarion 3 and Appendix R to 10 CFR Part 50, 3/4.3.3.6 ACCIDENT MONIT0_ RING INSTRUMENTATION The OPERABILITY of the accident r.onitoring instrumentation ensures that sufficient information is available ca selected plant parameters to monitor and assess these variables following an accident.
This capability is consis-tent with the recommendations of Regulatory Guide 1.97, Revision 3, "Instrumenta-tion for Light-Water-Cooled Nuclear Power Plants to Assess Plc,nt Conditions Our-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 SYSTEHf The OPERABILITY of the Chlorine Detection Systems ensures that sufficient capability is available to promotly detect and initiate protective action in the event of an accidental chlorine release.
This capability is required to protect control room personnel and is consistant 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.
)
Oe M ec, 1
3/ b FIRE DETECTION INSTRUMENTATION GPERABILI the detection instrumentation ensur that both aceauate warning capability 1 ilable for prompt cetecti f fires and that Fire Suppression Systems, that,
actuated by fire ectors, will discharge extinguishing agents in a time nner.
pt detection and suporession of fires will reduce the potential for e to safety-related equipment and is an integral element in the overall cili tre Protection Program.
Fire detectors that a used to actuate Fire Su ssion Systems represent a more critically impo nt component of a plant's Fire action Program than detectors tha re installed solely for early fire warn 1 nd notifica-
. tion.
Consequ y, the minimum number of OPERABLE fire detectors must,be j
greater.
I he loss of detection capability for Fire Suppression Systems, actuated
.y fire detectors, represents a significant degradation of fire protection fr i
' CATAWBA - UNITS 1 & 2 B 3/4 3-5
t fNSTRUMENTATION BASES
+
e UMENTATION (Continued)
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any area.
As a result, lishment of a fir initiated at an earlier stage than rol must be that provide only earl f
j patrols in the g.
The rented for the loss of cetectors areas is required to provideheerrt of frecuent fire i
_A L Tnoperable instrumentation is restored to OPERAB< hL'fon cacability I
3/A.3.3.9 LOOSE-PART DETICTION SYSTEM sufficient capability is available to detect loose met Reactor System and avoid or mitigate damage to Reactor System comp allowable out-of-service times and surveillance requirements are con The with the recommendations of Regulatory Guice 1.133, " Loose-Part Det Program for the Primary Systam of Light-Watar-Cocied Reactors " May n
i 3/4.3.3.10 RADI0 ACTIVE LIOUID EFFLUENT MCN!TORING INSTRU and co.itrol, as applicable, the releases of radioac ef fluer>ts during actual or potential releases of liquid effluents.
Alarm / Trip Setpoints for these instruments shall be calculated and a The accordance with the methodology and para;eeters in the 00CM to ensure t ustec in alarm / trio will occur prior to exceeding the limits of 10 CFR Part 20.
OPERABILITY and use of this instrumentation is consistent with the r The of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50 s
3/4.3.3.11 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTR and control, as applicable, the releases of radioactiv effluents during actual or potential releases of gaseous effluents.
Alarm / Trip Setpoints for these instruments snal) be calculated and adj The accordance with the methodology and parameters in the 00CM to ensure that th usted in alarm / trip will occur prior to exceeding the limits. of 10 CFR Part 20.
concentrations of potentially explosive gas mixtures i This e
SYSTEM.' The OPERABILITY and use of this instrumentatio the requirements of General Design Criteria 60, 63, and 64 of Appendix A t 10 CFR Part 50.
The sensitivity of any noble gas activity monitor used to o tion 3.11.2.2 shall be such tnat concentrations as low as measurable.
re CATAWBA ~- UNITS 1 & 2 8 3/4 3-6
el PLANT SYSTEMS 9
, BASES 1
SNUBBERS (Continued)
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal I
replaced, spring replaced, in high radiation area, in high temperature area, e tc, ). - The requirement to monitor the snubber service life is included to ensure that the snubbers 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 i
The limitations on removable contamination for sources requiring loak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for plutonium.
This limitation will ensure that leakage from Byproduct. Scurce, and Special Nuclear Material sources will not exceed allowable intake values.
Sealed sources are classified into thr>e groups according to their use, with Surveillance Requirements commensurate with tne probability of damage to a source in that groep.
Those sources which are fn quently handled are required to be tested more often than those which are not.
Sealed cources whien are continuously enclosed within a shielded methanis:n (i.e.. sealed sources within radiation monitoring or boron measuring devices) a're considered to be storea i
and need not be tested unless they are removed from the shielded mechanism.
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" " C "Z:0% 0'",T;X The OPER TV of the Fire Suppression Systems ensure at adeouate fire suppression c ility is available to confine an inguish fires occurring in any portio the facility where sa
-related equipment is located.
The Fire Suppress stem consis the water system, spray, and/or sprinklers, CDs, and fire s
ons.
The collective capability of {
the Fire Suppression Systems is a o minimize potential damage to safety-related equipment and i a major el in the facility Fire Protec-tion Program.
In the that portions of the Fire Suppression s are inoperabl,
alterna ckup fire-fighting equipment is required to be ma ailable in th acted areas until the inoperable equipment is restored to se e.
When the inoperable fire-fighting equipment is intended for use as a be means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression, i
g
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W CATAWBA - UNITS 1 & 2 B 3/4 7-6
. ~.. -. - -
l' PLANT SYSTEMS
(
JAJES A
S FIRE SUPPRESSION SYSTEMS (Con ued) k i, 1
b In event the Fire Suppres on Wa er System carees inoperae inuusdiate. ce tive measures.must-b taken.since this ates provide the
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E/4.7.11 FIRE BARRIER ETRATIONS' e functional integrity the fire barrie notrations ens es that firee-1 be confined or adeque ly.retanded reading to adj nt portions\\
_.. LofLthe f Tity.
These design fea s sin ze the seibility of a ingle fire rapidly involving several areas of th lity prior t detection and tin-guishing of the ire.
The fire barri etrations are assive elemen in the facility fire taction progr and a ubject to per die inspection >
Fire barrier penet ti
, including cable p tration bar rs, fi re doors, fire dampers, and er fire barriers are cori ered funct) al when the 4 viseall bserved con ion tne same as the as-desig condition.
For those fire barr penetr ions that not in the as designed dition, s. p alua-l tion shall b ormed to show th n the Inodification has not egracedt,hg\\
fire ating of th bhrrier penetratic ng pericd time when a barrier Q noi, functional, either:ned in the vicin M.
contin s fire watch 1 required tn be maint affected ref er, or (2) fire detectors.on least one side of the affected ba 1er aust be ver ied GPERA8LE and an reyrly tire watch patrol established, u il the barrier restored to furctiohal status.
.7.12 GROUNOWAh LEVEL This specification is provided to ensure that groundwater levels will l
be monitored and prevented from rising to unacceptable levels.
High ground-water levels could result in unacceptable structural stresses in the Contain-i l
ment and/or Auxiliary Building due to uplift and hydrostatic forces curing design basis events.
Although these buildings have been statically analyzed to withstand soil pressure along with the uplif t and hydrostatic forces resulting free groundwater rebound to yard elevation (593'6"), this analysis did not include any other loadings and was not a design condition for these buildings.
CATAWBA - UNITS 1 & 2 B 3/4 7-7 1
1.
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.o ADMINISTRATIVE CONTROL UNIT STAFF (Continued)
A Health Physics Technician
shall be on site when fuel is in either c.
reactor; AllCCREALTERATI6NSshallbeobservedanddirectlysupervisedby d.
either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handlin t
this operation;g who has no other concurrent responsibilities during
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Administrative procedures shall be developed and implemented to
)
limit the workin functions (e.g.,g hours of unit staff who perfom safat -related l
licensed Senior Operators, licensed retors health pnysicists, auxiliary operators, and key maintenance per,sonnel).
Adequate shift coverage shall be meintained without routine heavy a
i use of overtime.
The objective shall be to have operatin T
work a nominal 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months week while the unit is operating. g personnel
+
However the event that unforeseen roblems require substantial amounts of, in
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overtime to be uses, or du ing extenoed periods of shutdown for ce a
fueling ma or maintenance,idelines shall be followed:or major. pla rary bas,is he fo11 ewing gu 1)
An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.
i 2)
An individual should not be pemitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than,72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.
3)
A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between' work periods, including shif t turnover time.
4)
Except during extended shutdown periods, the use of overtime L
should be considered on an individual basis and not for the entire staff on a shift.
l Any deviation from the above. guidelines shall be authorized by the Station Manager or his designee, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included
.l in the procedures such that individual overtime shall be reviewed monthl y the Station Manager or his desi nee to assure that c
excess y hours have not been assigned.
R utine deviation from the above guidelines is not authorized.
"Ine Health Physics Technician - ' "'- " 'f ^ ------'" - =ay be less than the minimum requirements for a period of t'me not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order i
i to accommodate unexpected absence, provided immediate atetton is taken to fill the required positions.
u CATAWBA - UNITS 1 & 2 62 Amendee'nt No. 56 (Unit 1)
Amendment No. 49 (Unit 2)
L
~ ~~~
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i ADMINISTRATIVE CONTROLS g
TECHNICAL REVIEW AND CONTROL ACTIVITIES (Continued) 6.5.1.6 All REPORTA8LE EVENTS and all violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence.
Such reports shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production, and to the Director of the Nuclear Safety Review Board.
6.5.1.7 The Station Manager shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President, Nuclear Production.
6.5.1.8 The station security program, and implementing procedures shall be 4
reviewed at least once per 12 months.
Recommended changes shall be approved g
by the Superintendent of Station Services and transmitted to the Vice President.
[
4 g
Nuclear Production, and to the Director of the Nuclear Safety Review Board.
R 6.5.1.9 The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months.
Recommended changes shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production, and to the Director of the Nuclear Safety Review Board.
Q(g 6.5.1.10 The Station Manager shall assure the performance of a review by a i
L qualified individue.1/ organization of every unplanned onsite release of radio-
% g.
active material to the environs including the preparation *and forwarding of L
reports covering evaluation, recommendations, and disposition of the corrective O D ACTION to prevent recurrence to the Vice President, Nuclear Production and to l
d the Nuclear' Safety Review Board.
i k 6.5.1.11 The Station Manager shall assure the performance of a review by a k
qualifed individual / organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and Radwaste. Treatment Systems.
6.5.1.
eports documenting each of the activities performed under Specif' cations 6.5.1.1 through 6.5.1.11 shall be maintained.
Copies shall be provided to the Vice President, Nuclear Production, and the Nuclear Safety Review Board.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSR8)
FUNCTION 6.5.2.1 The NSR8 shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations, 1
b.
Nuclear engineering, c.
Chemistry and radiochemistry, CATAWBA - UNITS 1 & 2 6-8 Amendment No. 27 (Unit 1)
{
Amendment No.17 (Unit 2)
6.5.1.12 The Station Manager shall assure the performance of a review by a qualified individual /organisation of the Fire Protection Program and implementing procedures an @ ittal of recommended changes to the l
Nuclear Safety Review Board, i
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N TRAT 6.8 PROCEDURES Ale 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-monts of NUREG-0737 and Supplement No. I to NUREG 0737 as stated in Generic Letter No. 82-33; c.
Security Plan implementation;"
l d.
Emergency Plan implementation; e.
PROCESS CONTROL PROGRAM implementation; f.
OFFSITE CCSE CALCULATION MANUAL implementatio *.amr' g.
Quality Assurance Progr splementation for of uent and anvironmental monitor 1 g' 6.8.
ch procedure of Specifica ion 6.8.1, and changes thereto, shall be reviewed and appecved by the Station Manager; or by:
(1) Operating Superin-tendent, (2) Technical Services Superintendent. (3) Maintenance Superintendent,
)or(4)SuperintendentofIntegratedScheduling,aspreviouslydesignatedby the Station Mana as set forth in'ger; prior to implementation and shall be reviewed periodically administrative procedures.
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l 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made pro-vided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; and
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c.
The change is documented, reviewed, and approved by the Station Manager; or by:- (1) Operating Superintendent, (2) Technical Services Superintendent, (3) Maintenance Superintendent, or (4) Superintendent of Integrated Scheduling, as previously designated by the Station Manager; within 14 days of implementation.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment 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, chemical
" Review and approval may be performed by the Superintendent of Station Services.
CATAWBA - UNITS 1 & 2 6-13 Amendment No. 27 (Unit 1)
Amendment No.17 (Unit 2)
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ATTACHMENT !!
PROPOSED FSAR REVISION i
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E Portable fire extin physical condition.guishers shall be inspected periodically for full charge and Extinguishers shall be checked on a programmed schedule.
9.5.1.5 Personnel Qualification and Traininc 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".
l 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 t
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 exchange 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 Oescription 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 PA8X telephone switch is provided with redundant common controls, critical electronics, and power supplies.
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 PA8X system is also connected to the commercial telephone system and the Duke microwave / Fiber Optic Network.
9.5-5 1987 Update
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Specific comitments related to the operation and testing of fim protection
( ystem equipment are contained in F5AR Chapter 16.0.
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Industrial health, safety and first aid e.
Emergency plan and procedures f.
Station security program and procedures g.
Fire protection plan and procedures h.
Using procedures and performing independent verification 1.
New Employee Orientation (Portions of other General Employee Training may be included.)
l Continuing training is conducted in these areas as is necessary to maintain employee proficiency.
13.2.2.1.1 Fire Brigade Training The primary purpose of the Fire Brigade Training Program is to develop a group t
of station employees skilled in fire prevention, fire fighting techniques, U
first aid procedures, and emergency response.
They are trained and equipped to C'
function as a team for the fighting of fires.
The station fire brigade organ-f ization is intended to be self sufficient with respect to fire fighting C.
activities.
OJ The Fire Brigade Training program provides for initial training of all new fire brigade members, quarterly classroom training and drills, annual' practical h
training, and leadership training for fire brigade leaders.
4 Training is discussed in Duke Power Company, Catawba Nuclear Station, response v
h to Appendix A, BTP APCS 8 9.5-1.
_$ W 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 principais, and procedures involved in work in which an employee is assigned.
13.2-3 1987 Update x =
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'L TABLE OF CONTENTS SECTION NO.
TITLE PAGE NO.
16.0 SELECTED LICENSEE COMMITMENTS 16.1
16.1 INTRODUCTION
16.1-1 16.2 APPLICABILITY 16.2-1 o
16.3 DEFINITIONS 16.3-1 16.4 COMMITMENTS RELATED TO REACTOR COMPONENTS 16.4-0 16.5 COMMITMENTS RELATED TO REACTOR COOLANT SYSTEM 16.5-0
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16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES 16.6-0 i
(NON-ESFSYSTEMS) i 16.7 COMMITMENTS RELATED TO INSTRUMENTATION 16.7-1 16.8 COMMITMENTS RELATED TO ELECTRICAL POWER SYSTEMS 16.8-0 16.9 COMMITMENTS RELATED TO AUXILIARY SYSTEMS 16.9-1 16.3-1.
FIRE SUPPRESSION WATER SYSTEMS 16.9-1 1
16.9-R SPRAY AN0/0R SPRINKLER SYSTEMS 16.9-3 C0 SYSTEMS 16.9-4 FIRE HOSE STATIONS 16.9-5 FIRE BARRIER PENETRATIONS l
'16.9-6 FIRE DETECTION INSTRUMENTATION 16.10 COMMITMENTS RELATED TO STEAM AND POWER CONVERSION SYSTEMS 16.10-0 16.11 COMMITMENTS RELATED TO RADIOACTIVE WASTE MANAGEMENT 16.11-0 L
16.12 COMMITMENTS RELATED TO RADIATION PROTECTION 16.12-0
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16.13 COMMITMENTS RELATED TO CONDUCT OF OPERATIONS 16.13-0 16.13-1 FIRE BRIGADE-16.13-1 16.14 COMMITMENTS RELATED TO REFUELING OPERATIONS 16.14-0 APPENDIX Catawba Nuclear Station Directive, " Control of Selected Licensee Commitments" l
16.0-1 a
p CNS 16.2 APPLICABILITY This section provides the general requirements applicable to each of the commitments and Testing Requirements within Section 16.0, Selected Licensee Commitoents(StCs)..
16.2.1 Compliance with the SLCs is required as specified. When a Commitment is not met, the associated Remedial Action (s) shall be met.
16.2.2 Noncompliance with a Commitment exists whcn the requirements of both the Commitment and the specified Remedial Action are not met within the specified time.
If compliance with a Commitment.is restored prior to expira-tion of the specified time interval complet1oh of the Remedial Action (s) is not required.
16.2.3 Where corrective measures are completed that permit operation under the Remedial Actions, the action may be taken within the specified time l
limits, as measured from the time of failtre to moet the Commitment.
16.2.4 Entry into an OPERATIONAL MODE or other specified applicability condition must be made with 1) all required systems, equipment or components OPERABLE, and all other parameters specified in Commitments Met.
Credit may not be taken for deviations and out-of-service provisions contained in Remedial Actions.
i Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the conditions for the Commitments are met without reliance on provi-sions contained in the Remedial Actions.
This provision shall not prevent passage through OPERATIONAL MODES as required to comply with Remedial Actions, l
Exceptions to these requirements are stated in the individual specifications.
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16.2.5 Commitments including the associated Remedial Actions shall apply to each unit. individually unless otherwise indicated as follows:
a.
Whenever the Commitment refors to systems or components which are shared by both units, the Remedial Actions will apply to both units L
simultaneously.
This will be indicated in the Remedial Actions; b.
Whenever the Commitment applies to only one unit, this will be identified in the APPLICABILITY section of the Commitment; and Whenever certain portions of a Commitment contain operating para -
c.
meters, setpoints etc., which are different for each unit, this will be identified in parentheses or footnotes.
(for example, "... flow rate of 54,000 cfm (Unit 1) or 43,000 cfm (Unit 2)...").
16.2.6-Testing Procedures shall be performed during the OPERATIONAL MODES i
or other conditions specified for an individual commitment unless otherwise stated in an individual Testing Procedure or Reference.
16.2.7 Each Testing Procedure shall be performed on its specified frequency with a maximum allowable extension not to exceed 50% of the test frequency.
The phrase "at least" associated #1th a testing frequency does not negate this tolerance value, and permits the performance of more frequent surveillance l
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This tolerance is necessary to provide operational flexibility because of scheduling and performance considerations.
16.2.8 Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated testing procedures have been satisfactorily performed within the specified test frequency.
Nothing is this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the testing requirements.
Failure to perform a Testing Procedure within the specified frequency shall constitute a failure to meet the OPERABILITY requirements for a commitment.
Exceptions to these requirements are stated in the individual commitments.
Testing Procedures do not have to be performed on inoperable equipment.
16.2.9 During initial plant startup or following extended plant outages,
-the applicable testing activities must be performed within the stated test frequency prior to placing or returning the system or equipment into OPERABLE status.
Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Testing Procedure (s) associated with the Commitment have been performed within the specified frequency.
16.2.10 Testing Procedures for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
Inservice inspection of ASME Code Class 1, 2, and 3 components and a.
inservice testing of ASME Code Class 1,.2,~and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable. Addenda as required by 10CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10CFR 50, Section t
l 50.fla(g)(6)(1);
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Testing Frequencies specified in Section XI of the ASME Boiler and i
pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frequencies for Code and applicable Addenda performing inservice terminology for inservice inspection and testing inspection and testino activities activities Weekly At least once per 7 days L
Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days l
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'The provisions of Section 16.2.7 are applicable to the above c.
required frequencies for performing inservice inspection and testing activities; d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Testing Procedures; and-The ASME Boiler and. Pressure Vessel Code supersedes'the requirements
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of any commitment unless an exception to the Code has been approved.
16.2.11 Testing Procedures shall apply to each unit individually unless otherwise indicated as stated in Section 16.2.5 for individual commitments or whenever certain portions of a specification contain testing parameters different for each unit, which will be identified in parentheses or footnotes.
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i 16,9 AUXILIARY' SYSTEMS FIRE PROTECTION SYSTEMS i
16,9-1 FIRE SUPPRESSION WATER SYSTEM COMMITMENT-The Fire Suppression Water System shall be OPERABLE with:
At least two fire suppression pumps, each with a capacity of 2500 gpm, a.
with their discharge aligned to the fire suppression header, and b.
An OPERABLE flow path capable of taking suction from Lake Wylie and transferring the water through distribution piping with OPERABLE sectionalizing control valves and isolation valves 'for each sprinkler, hose standpipe, or Spray System riser required to be OPERABLE per_
i Commitments 16,9-2 and 16,9-4.
APPLICABILITY:
At all times.
I R_EMEDIAL ACTION:
With one of the above required pumps and/or one We ter Supply / Distribution a.
System inoperable, restore the inoperable equipment to OPERABLE status within 7 days or provide an alternate backup pump or supply, i
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,With the Fire Suppression Water System otherwise inoperable-establish a backup Fire Suppression Water System within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
TESTING REQUIREMENTS:
i The Fire Suppression Water System shall be demonstrated OPERABLE:
a.
1.
At least once per 31 days on a STAGGERED TEST BASIS by starting each electric motor-driven pump and operating it for at least 15 minutes c
on recirculation flow, i
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At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path which is accessible during plant operations is in its correct position, 3
111. At least once per 6 months by performance of a system flush of the L
outside distribution ioop to veri fy no flow blockage by fully opening the hydraulically most remote hydrant, i
1 iv. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel, l.
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At least once per 18 months by verifying that each valve (manual, v.
power-operated, or automatic) in the flow path which is inaccessible during plant operations is in its correct position, vii.
At least once per 18 months by performing a system functional test which it,cludes simulated automatic actuation of the system through(ut 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, 3)
Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and 4)
Verifying that each fire suppression pump starts within 10 psig of its-intended starting pressure (A pump, primary switch-95.
psig; B pump, primary switch-90 psig; and C pump, primary switch-85 psig).
viii.
At least once per 3 years by performing a flow test of the system in accordance ~ with ; Chapter 8, Section 16 o f the Fire Protection Handbook,15th Edition, published by the National Fire protection 2
Association.
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, Supplemer t 3, Section 9.5.1 5)
Catawba Fire Protection Review, as revised 6)
Catawba Fire Protection Commitment Index i
7)
Startup and Normal Operation of Fire Protection System - OP/1/A/6400/02A BASES.:
The OPERABILITY of the Fire Suppression Systems ensures that adequate fire suppression capability is available to con'ine and extinguish fires occurring in any portion of the facility where safety-related equipment is located.
The Fire Suppression System consists of the water system, spray, and/or i
sprinklers, C0, and fire hose stations.
The collective capability of the 3
Fire Suppression Systems is adequate to minimize potential damage to 16.9-2
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f safety-related equipment and is a-major element in the facility Fire Protection Program.
In the event that portions of the Fire Suppression Systems are inoperable, alternate backup fire-fighting equipment is requireti to be made available in the affected areas until the inoperable equipment is restored to service.
When the inoperable. fire-fighting equipment is intended for use as a backup-means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.
In the event the Fire Suppression Water System becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.
This selected licensee commitment is part of the Catawba Fire Protection Program and therefore subject-to the provisions of the Catawba Facility Operating License Conditions #6 for NPF-52 and #8 for NPF-35.
16.9-3
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Y' 16.9 AUXILIARY SYSTEM,S.
FIRE PROTECTION SYSTEMS 16.9 -SPRAY AND/0R SPRINKLER SYSTEMS COMMITMENT Spray and/or Sprinkler systems in Table 16.9-1 shall be OPERABLE:
APPLICABILITY:
Whenever equipment protected by the Spray / Sprinkler System is required to be OPERABLE.
l RLMEDIAL ACTI_0N_:
L With one' or more of the above required Spray and/or Sprinkler Systems-inoperable, within I hour establish a continuous fire watch with backup fire surpression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.
TESTING REQUIREMENTS:
Each of the _ above required Spray and/or Sprinkler Systems shall be a.
demonstrated 0PERABLE:
1.
At least once per 31 days by verifying that each valve (manual, power-operated, or autometic)-in the flow path which is accessible during plant operations is in its correct position,
11. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel, iii.
At least once per 18 months by verifying that each valve (manual, power-operated, or automatic)- in the flow path which is inaccessible.
during plant operations is in its correct position, and iv.
At least once per 18 months:
1)
By performing a system functional test which includes simulatec automatic actuation of the system, and cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.
2)
By a visual inspection of each Sprinkler System starting at the system isolation valve to verf fy the system's integrity; and 3)
By a visual inspection of each nozzle's spray area to verify the spray pattern is not obstructed.
16.9-4
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MFERENCES

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
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Catawba.SER, Supplement 5, Section 9.5.1 6)
. Catawba Fire Pr'otection Review, as revised 7)
Catawba Fire Protection Commitment Index BASES:
The OPERABILITY of the Fire' Suppression Systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring 1n any~ portion of the facility where safety-related equipment is located.
The 1
, Fire'~ Suppression System consists of the water system, spray, and/or sprinklers, C0, and fire hose stations.
The collective capability of the 3
Fire' Suppression Systems is, adequate to minimize pctential damage to safety related equipment and is a major element in the facility Fire Protection Program.
In the-event that portions of the Fire Suppression Systems are inoperable, alternate backup fire-fighting equipment is-required to be made available in the affected areas until. the inoperable equipment is restored to service.
When' the inoperable. fire-fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.
This selected licensee commitment is part of the Catawba Fire Protection Program and therefore subject tc the provisions of the Catawba Facility Operating License Conditions #6 for NPF-52 and #8 for NPF-35, 16.9-5
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Table 16.9-1 Spray and Sprinkler Systems Elevation 522 + 0 it - Auxiliary Building a.
Room No.
Eouipment 100 RHR & Containment Spray Sump Pump Area 101 Corridor 104 RHR Pump 1B-105 RHR 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 1B 240 Cent. Chg. Pump 2A 241 Cent. Chg. Pump 2B 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 300 Component Conitng Pumps 1A1, 1A2, 181
& 182 e.
Elevation 574 + 0 ft - Auxiliary Building 480 Cable Room Corridor (00-EE) 490 Cable -Room Cori idor (00-EE) f.
Elevation 577 + 0 ft - Auxiliary Building 400 Component Cooling Pumps 2A1, 2A2, 2B1
& 2B2
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Reactor Buildings Annulus Pipe Corridor 16.9-6
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o 16.9 AUXILIARY SYSTEMS
' FIRE PROTECTION SYSTEMS 16.9-3 C0 SYSTEMS COMMITMENT L
The following High Pressure-and Low Pressure C0 Systems shall be OPERABLE:
a.
Low Pressure C0: System - Diesel generator rooms, and b.
High ' Pressure CO, System - Auxiliary feedwater pump rooms.
-APPLICABILITY:
Whenever equipment protected by the CO: Systems is required to be OPERABLE.
REMEDIAL ACTION:
'With.one or more of the above required C0 Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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.
TESTING REQ.UIREMENTS:
a.
Each of the above required C0 Systems.shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve (manual, power operated, sor automatic) in the flow path is~ in its correct position, b.
Each of the above required Low Pressure LO Systems shall be demonstrated OPERABLE:
1.
At least once per 7 days.by verifying the CO storage tank level to 2
be greater than 44% of full capacity, and l
11. At least once per 18 months by verifying:
1)
Each system actuates manually and automatically, upon receipt j
.of a simulated actuation signal, 2)
Damper closure devices receive an actuation signal upon system operation, and L
3)
By a visual inspection of discharge nozzles to assure no p
blockage.
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' Esch i of the above required. H1'gh Pressure C0: Systems shall be
. demonstrated OPERABLE:
1.
At least once per 6 months by verifying the weight of each C0 storage cylinder to be at least 90% of full charge weight, and 11, At-least once per 18 months by:
1)
Verifying each system actuates manually and automatically upon receipt of a simulated actuation signal, t
2)
~ Verifying that damper closure devices receive an actuation signal upon system operation, and-
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-3)
A visual inspection of the discharge nozzles to assure no blockage.
REFERENCES:
1)
Catawba FSAR, Section 9.5.1
-2)
Catawba SER, Section 9.5.1 1
3)
Catawba SER, Supplement 3, Section 9.5.1 BASES:
The OPERABILITY of the Fire Suppression Systems ensures _ that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment is located.
The Fire Suppression' System consists of the water system, spray, and/or sprinklers, C0s, and fire hose stations.
The collect _ive capability of the Fire. Suppression _ Systems is adequate to minimize potential damage to safety,related equipment and is a major element in the-facility Fire
' Protection Program.
In the event' that. portions of the Fire Suppression Systems are inoperable, alternate backup fire-fighting equipment is required to be made available in the_ affected areas until the inoperable equipment is restored to service.
.When the. inoperable fire-fighting _ equipment is intended for use as a backup means of fire suppression, a -longer period of time is allowed to provide an alternate means of fire fighting than if the-inoperable equipment is the primary means of fire suppression.
- This selected licensee commitment is part of the ' Catawba Fire Protection Program and.therefore subject to the provisions of the Catawba Facility Operating License Conditions #6 for NPF-52 and #8 for NPF-35, 16.9-8
l 16.9.
AUXILIARY SYSTEMS-FIRE PROTECTION SYSTEMS-16.9-4 FIRE HOSE STATIONS COMMITMENT
.The fire hose stations given in Table.16.9-2 shall be OPERABLE:
APPLICABILITY:
Whenever equipment in the areas protected by the-fire hose stations is required to be OPERABLE.
REMEDIAL ACTION:
With one or more of the fire hose stations given in Table 16.9-2 inoperable, provide gated wye (s) on the-nearest OPERABLE hose station (s).
One outlet of the. wye shall be connected to the standard length of hose provided 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 lef t unprotected by the inoperable hose station.
Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazard to 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 shall be mounted above the gated wye (s) to identify the proper hose to use.
The above REMEDIAL ACTION requirement shall be accomplished W thin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire supprersion; otherwise route the additional
-hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
TESTING RE0VIRE!4ENIS:
L a.
Each of the fire hose stations given in Table 16,9-2 shall be demonstrated u
. OPERABLE:
L i ~. At least once per 31-days, by a visual inspection of the fire hose L
stations accessible during plant operations to assure all required equipment is at the station, L
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11. At least once per 18 months, by:
li 1)
Visual inspection of the stations not accessible during plant operations.to assure all required equipment is at the station, 2)
Removing the hose for inspection and reracking, and 3)
Inspecting all gaskets and replacing any degraded gaskets in the couplings.
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At least once per 3 years, by:
1)-
Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage, and 2)
Conducting a hose hydrostatic test at a pressure of 200 psig or at.least 50 psig above maximum fire main operating pressure, 1
whichever'is greater.
REFERENCES:
1)
Catawba FSAR, Section 9.5.1 2)
Catawba SER, Section 9.5.1 3)
Catawba SER, Supplement 3, Section 9.5.1 t
4)
Catawba Fire Protection Review, as revised 5)
Catawba Fire Protection Commitment Index BASES:
The OPERABILITY of the Fire Suppression Systems ensures that adequate fire suppression capability is available to confine and extinguish. fires occurring in any portion of the facility where safety related equipment is located.
The Fire. Suppression System consists of the water system, spray, and/or sprinklers, C0,, and fire hose stations.
The collective capability of the Fire Suppression Systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility Fire Protection Program.
In the event that portions of ~the Fire Suppression Systems are inoperable, alternate backup fire-fighting equipment is required to be made available in the 4'fected areas until the inoperable equipment is restored to service.
When the inoperable fire-fighting equipment is intended for use as a backup means of fire suppression,. a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment-is the primary means of fire suppression.
t This selected licensee commitment is part of the Catawba Fire Protection Program and therefore subject to the provisions of the -Catawba Facility Operating License Conditions #6 for NPF-52. and #8 for NPF-35.
16.9-10
7
~
L*.
TABLE 16.9-2 Page 1 of 2 FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #
f 1.
Auxiliary Butiding 59, - FF 522+0 1RF235 55, FF 52240 1RF248 63-64, KK 543+0 1RF210
'63, MM 543+0 1RF211-60, MM 543+0 1RF212 4
k 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 56040 1RF489 68-69, BB 560+0 1RF996 45-46, BB 560+0 1RF997 63, NN 577+0 1RF204 61, LL 577+0 1RF214 63, KK-LL 577+0 1RF215 58, PP 577+0 1RF221 59, JJ 577+0 1RF230 1
58, GG-577+0 1RF240 56, KK 577+0 1RF244 54, GG 577+0 1RF252 L
52-53, KK 577+0 1RF258 51, KK 57740 1RF264 51-52, NN 577+0 1RF272 i-l.
16.9-11 L
l
g-q
' kit
1
,[
i g
.Y e
TABLE 16.9-2 Page 2 of 2 1
FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #
56, PP 577+0 1RF278 68-69, BB 577+0 1RF478 65, BB-CC 577+0 1RF479-
~
59, 00 574+0 1RF480 60, AA 574+0 1RF481 49, BB-CC 577+0 1RF490 45, BB 577+0
.IRF491 55,.DO 574+0 1RF492 54, AA 574+0 1RF493' 63,-AA 577+0 1RF993 51, AA 577+0 1RF998 62, NN 594+0 1RF205 57, MM 594+0 1RF222 63, JJ 594+0 1RF231 57, HH 594+0 1RF245 57,'EE 594+0 1RF253 51, JJ 594+0 1RF259 53, NN 594+0 1RF275 i
64, BB 594+0 1RF984 50, BB 594+0 1RF985-51, KK 605+10 1RF265 63, JJ 605+10 1RF233 63-64, MM-63146 1RF483
'50-51, MM 63146 1RF495 l
2.
Fuel Pools 65, TT-UU 605+10 1RF208 48, TT-UU 605+10 1RF276 63-64, MM 605+10 1RF482 50-51. MM 605+10 1RF822 3.
Nuclear Service Water Pump Structure l
East Section 600+0 1RF939 l
West Section 60040 1RF940 l
l l
l' 16.9-12
16.9 AUXILIARY SYSTEMS.
FIRE PROTECTION SYSTEMS 16.9-5 FIRE BARRIER PENETRATIONS COMMITMENT L
All fire barrier penetrations (walls, floor /ccilings, cable-tray 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 penetration seals) shall be OPERABLE.
APPLICABILITY:
At all times.
REMEDIAL-ACTION:
With one or more of the above required fire barrier penetrations and/or sealing devices inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either establish a-continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the inoperable penetration and establish an hourly fire watch patrol.
TESTING REQUIREMENTS:
At least once per 18 months the above required fire barrier penetrations a.
.and sealing devices shall be verified OPERABLE by performing a visual inspection of:
1.
fhe exposed surfaces of each fire rated assembly; i
11.
At least 10% of all fire dampers.
If apparent changes in appearance or abnormal degradation are found, a visual inspection of an additional 10% of the dampers shall be made.
This inspection process shall continue until a 10% sample with no apparent changes in appearance or abnormal degradation is found.
Samples shall be selected such that each fire damper will be inspected every 15 years; and L
111.
At least 10% of each type of sealed penetration.
If apparent l
changes in appearance or abnormal degradations are found, a visual l-inspection of an additional 10% of each type of sealed penetration j
shall be made.
This inspection process shall continue until a 10%
l sample with no apparent changes in appearance or abnormal L
degradation is found.
Samples shall be selected such that each l
penetration seal will be inspected every 15 years.
l l
l-16.9-13 I
\\c:
',N b.
Each of the above required fire doors shall be verified OPERABLE by i
inspecting the. closing mechanism and latches at least once per 6 months,-
and by verifying:
~
l 1
The position of'each interior closed fire door at least once per 24
hours,
11. The OPERABILITY of _ the fire door supervision system for each electrically supervised fire door by performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least once per 31 days, and 1
111.
That each locked closed fire door is closed at least once per 7 days.
REFERENCES:
1)
Catawba FSAR, Section 9.5.1 2)
Catawba SER, Section 9.5.1 3)
Catawba SER, Supplement 3, Section 9.5.1 i
4)
Catawba Fire Protection Review, as revised 5)
Catawba Fire Protection Commitment Index BASES:
The functional integrity of the fire barrier penetrations ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility.
These design features minimize the possibility of a single fire rapidly involving several areas of the facility' prior to detection and extinguishing of the fire.
The fire barrier penetrations are a passive element in-the facility fire protection program and are subject to periodic inspections.
Fire barrier penetrations, including cable penetration barriers, fire doors, fire dampers, and other fire barriers are considered functional when the visually observed condition is the same as the as-designed condition.
For those fire barrier penetrations that are not in the:as-designed condition, an evaluation shall be performed to show that the modification has not degraded the fire. rating of the fire barrier penetration.
c During periods of time when a barrier is not functional, either:
(1) a-continuous fire watch is required to be maintained in the vicinity of the af fected barrier, or (2) the fire detectors on at least one side of the affected barrier must be verified OPERABLE and an hourly fire watch patrol established, until the barrier is restored to functional status.
This selected licensee commitment is part of the Catawba Fire Protection
' Program and therefore subject to the provisions of the Catawba Facility Operating License conditions #8 for NPF-35.
16.9-14 i
d e
16.9 AUXILIARY SYSTEMS FIRE PROTECTION-SYSTEMS
~
16.9-6 FIRE DETECTION INSTRUMENTATION j
COMMITMENT
~
.As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 16.9-3 shall be OPERABLE.
APPLICABILITY:
Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
REMEDIAL ACTION:
With any, but not more then orie-half the total in any fire zone, Function a.
A fire detection instruments snowti in Table 16.9-3 inoperable, restore the inoperable instrument (s) to OPERABLE status within 14 days cr within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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, ther inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour.at the locations listed in Specification 4.6.1.5.
b.
With more than one-half of the Function A fire detection instruments in any fire zone shown in Table 16.9-3 inoperable, or with any Function B fire detection instruments shown in Table 16.9-3 inoperable, or with any two or more adjacent fire detection instruments shown in Taele 16.9-3 inoperable, within 1. hour establish a fire watch patrol to inspect the tone (s) with the inoperable instrument (s) at least once por hour, unless the instrument (s) is located inside the contair, ment, then inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.
T1 STING REQUIREMENTS:
l L
a.
Each of the above required smoke detection or flame detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST. Detectors which are not accessible during plant E
operation shall be demonstrated OPERABLE by the performance of a TRIP l
ACTUATING DEVICE OPERATIONAL TEST during each COLD SHUTDOWN exceeding 24 I
hours unless performed in the previous 6 months.
l l
l 16.9-15 L
m.
'.L l:i Each of the above ' required heat detection instruments shall be demonstrated OPERABLE as follows:
i.
For nonrestorable spot-type detectors, at least two detectors out of every hundred, or fraction thereof,' shall be removed every 5 years and functionally tested.
For each failure that occurs on the detectors removed, two additional detectors shall be removed and tested; ar.d it.
For restorable spot-type heat detectors, -at least one detector on each signal initiating circuit shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST.
Dif ferent detectors shall be selected for each -
test.
Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.
b.
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.
REFERENCES:
1)
Catawba FSAR, Section 9.5.1
?)
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 Fire Protection Review, as Revised 6)
Catawba Fire Protection Commitment Irdex BASES:
The 0PERABILITY of the Fire Suppression Systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any ~ portion of the facility where safety-related equipment is located.
The Fire Suppression System consists of the water system, spray, and/or
-sprinklers, CO, and fire hose stations.
The collective capability _ of the 2
Fire Suppression Systems is adequate to minimize potential damage to safety-related equipment and is a major element in the facility Fire Protection Program.
In the event that portions of the Fire Suppression Systems are inoperable, alternate backup fire-fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
When the inoperable fire-fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression, 16.9-16
.p a
.w.
j
- This selected licensee comitment is part of the Catawba Fire Protection-
~
Program and therefore subject to the provisions of ',he Catawba Facility Operating License Conditions #6 for NPF-52 and' #8' for. HPF-35.
~
i l
4 a
(.
(
I; P
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b w
16.9-17 1
1
~,c,
1 A
LTABLE 16.9-3, P gs 1 of 5-0 FIRE DETECTION -INSTRIMENTS FIRE MINIMUM INSTRUMENTS OPERABLE *-
ZONE DESCRIPTION-LOCATION SMOKE-FLAME. HEAT FUNCTION **
1 R.H.R. Pump 18-GG-53 E1.522 + 0 1
0 1
A 2
R.H.R. PumpL1A FF-53 E1.522 + 0 1
0 1
AL 3
Cont. Spray Pump 1B GG-54 E1.522 + 0 3
0 3
A:
4 Cont. Spray Pump 1A GG-55 E1.522 + 0 2
0 2
A 5
R.H.R. Pump 2B
-GG-61 E1.522 + 0 1
0 1
A 6
R.!!. R. Pump 2A ff-61 E1.522 2 0 1
0 1
A 7
Cont. Spray Pump 28 GG-60 E1.522 + 0 3
0 3
A 8
Cont. Spray Pump 2A GG-59 E1.522 + 0 2
0 2
A 9
Aux. F. W. Pumps BB-51 E1.543 + 0 14 0
12(6)
A(B) 10 Mech. Pene. Room JJ-52 E1.543 + 0 3
0 3 '
A 11 Corridor / Cables
.NN-51 E1.543 + 0 6
0 6
A 12 Recip. Chg. Pump JJ-53 E1.543 + 0 1
0 1
A 13 Safety Inj Pump IB HH-53 El.543 + 0 1
0 1
A 14 Safety Inj Pump IA GG-53 E1.543 + 0 1
0 1
A 15 Cent. Chg. Pump 1B
-JJ-54 E1.543 + 0 2
0 2
A 16 Cent. Chg. Pump 1A JJ-55 E1.543 + 0 2
0 2
A 17 Aisles / Cables KK-56 E1.543 + 0 18 0
18 A
18 Aisles / Cables EE-55 E1.543 + 0 6
0 6
A 19 AFW Dumps (Unit 2)
BB-63 E1.543 + 0 14 0
12(6)
A(B) 20 Mech. Pene. Room JJ-62 E1.543 + 0 3
0 3
A 21 Aisles / Cables NN-61 E1.543 + 0 6
0 6
A 22 Recip_ Chg. Pump JJ-60 E1.543 + 0 1
0 1
A 23 Safety Inj. Pump 2B HH-60 E1.543 + 0 1
0 1
A l
24 Safety inj. Pump 2A GG-60 E1.543 + 0 1
.0 1
A l
25 Cent. Chg. Pump 28 JJ-59 E1.543 + 0 2
0 2
A 26 Cent. Chg. Pump 2A JJ-58 E1.543 + 0 2
0 2
A 27 Aisles / Cables KK-59 E1.543 + 0 20 0
20 A
28 Aisles / Cables EE-58 E1.543 + 0 6
0 6
A 29 SW Gear Equip. Room AA-50 El 560 + 0 7
0 0
A 30 Elect. Pene. Room CC-50 E1.560 + 0 8
0-0 A-31 Corridor / Cables EE-53 E1.560 + 0 5
0 5
A 32 Corridor / Cables KK-52 E1.560 + 0 8
0 8
A 33 Corridor / Cables NN-54 E1.560 + 0 10 0
10 A
34 Aisles / Cables JJ-56
-E1.560 + 0 14 0
14 A
35 Motor Control Centers GG E1.560 + 0 2
0 2
A
'.. 36 Cable Tray Access FF-56
'E1.568 + 0-2 0'
2 A
w-y weg gr-g
~
yy
-TABLE'16.9-3, Psge;2 of 5i c
FIRE DETECTION INSTRUMENTS FIRE MINIMUM INSTRUMENTS OPERABLE
ZONE DESCRIPTION LOCATION SMOKE FLAME HEAT FUNCTION **
37-Equip. Batteries
DO-55 E1.554 + 0 5
0 4
A 38 Equip. Batteries CC-55 E1.554 + 0 5
0 4
'A 39 Battery Room CC-56 E1.554 + 0 17 0
0 A
t 41 SW Gear Equip. Room AA-64 E1.560 + 0 7
0 0
A-l 42 Elect. Pene. Room CC-65 E1.560 + 0 8
0 0
A l
43 Corridor / Cables FF-61
'E1.560 4 0 5
C 5
A i
44 Aisles / Cables KK-63 E1.560 + 0 8
0 8
A l
45 Aisles / Cables NN-60 E1.560 + 0 ^
13 0
13 A
46 Aisles / Cables HH-59 E1.560 + 0 13 0
13 A
47 Motor Control Center GG-58 E1.560 + 0 2
0 2
A 48 Cable Tray Access FF E1.560 + 0 2
0 2
A i
49 Equip. Batteries DD-60 E1.560 + 0 5
0 4
A 50 Equip. Batteries CC-60 E1.560 + 0 5
0 4
A 51 Battery Room CC E1.560 + 0 17 0
0 A
53 SW Gear Equip. Room
. AA-49 E1.577 + 0 7
0 0
A 54 Aisles / Cables CC-50 E1.577 + 0 10 0
0 A
55 Aisles / Cables NN-52 E1.577 + 0 9
0 9
A 56 Aisles / Cables PP-55 E1.577 + 0 13 0
13 A
57 Aisles / Cables LL-55 E1.577 + 0 11 0
11 A
58 Aisles / Cables HH-55 E1.577 + 0 21 0
- 21 A
59 Motor Control Center EE-54 E1.577 + 0 2
0 2
A 60 Cable Room.
CC-56 E1.574 + 0 18 0
15 A
62 SW Gear Equip. Room AA-64 E1.577 + 0 7
0 0
A 4
63 Elect. Pene. Room CC-64 E1.577 + 0 10 0
0 A
4 64 Aisles / Cables PP-62 E1.577 + 0 9
0 9
A 65 Aisles / Cables PP-59 E1.577 + 0 16 0
16 A
66 Aisles / Cables LL-59 E1.577 + 0 11 0
11 A
67 Aisles / Cables HH-59 E1.577 + 0 21 0
21 A
68 Motor Control Center FF-60 E1.577 + 0 2
0.
2 A
69 Cable Room CC-59 E1.577 + 0
. 18 0
15 A
71 Elect Pene. Room CC-51 E1.594 + 0 10 0
0 A
72 Control Room CC-56 E1.594 + 0 23 0
6 A
i 73
. Vent. Equip. Room FF-56 E1.594 + 0 9
0 0
A 74 Aisles / Cables LL-56 E1.594 + 0 25 0
25 A.
,, 76 Aisles / Cables PP-54 E1.594 + 0 15-0 A 79 Elect. Pene. Room BB-63 E1.594 + 0 11 0-0 A
~
....w w
s
+3 y.,
,c,
s
.TABLEi16.9-3,L ageL3 of 5 P
FIRE DETECTION INSTRUMENTS FIRE-MINIMUM INSTRUMENTS OPERABLE
ZONE DESCRIPTION
. LOCATION SMOKE
. FLAME HEAT.
FUNCTION **
80 Control Room BB-59 E1.594 + 0 22' 0
6' LA.
81 Ven. Equip. Room FF-58 E1.594 + 0 12-0 0-A 82 Aisles / Cables KK-58 E1.594 + 0 27 0
28 "A
~
84 Aisles / Cables NN-58 E1.594 + 0 17-0
,17 A
89 Fuel Pool Area #1 PP-50 E1.605 + 10
'19 7
19 A
90 fee! Pool' Area (Unit 2)
PP-64 E1.605 + 10 19 7
19 A-128 UHI Bldg.
HH-44 E1.550 + 0 2
3 2
A 129 Fuel Pool Purge Room (Unit 1)
NN-50 E1.631 + 6 6-0 6
A 130 UHI Bldg. (Unit 2)
HH-71 E1.594 + 0 2
3 2
A 131 Reactor Bldg.
O'-45' Be1. E1.565 + 3 4-0 0
A 132 Reactor Bldg.
45 -90*
Be1. E1.565 + 3
~3 0
0 A
133 Reactor Bldg.
90'-135' Be1. E1.565 + 3 4
0 0
A 134 Reactor Bldg.
135'-180' Be1. E1.565 + 3 5
0 0
A 135 Reactor Bldg.
180'-225*
Be1. E1.565 + 3 4
0 0
A 136 Reactor Bldg.
270'-315' Be1. E1.565 + 3 3
0 0
A 137 Reactor Bldg.
315 -0*
Be1. E1.565 + 3 8
0 0
A 138 Reactor Bldg.
0*-45' Be1. E1.586 + 3 6
0 0
A 139 Reactor Bldg.
45'-90' Be1. E1.586 + 3 4
0 0
A 140 Reactor Bldg.
90 -135 Be1. E1.565 + 3 3
0 0
A 141 Reactor Bidg.
135*-180*
Be1. E1.586 + 3 8
0 0
A 142 Reactor Bldg.
180*-225*
Be1. E1.586 + 3 5
0 0
A 143 Reactor Bldg.
315'-0 '
Be1. E1.586 + 3 5
0 0
A 144 Reactor Bldg.
0 -45' Be1. E1.593 + 2h 14 0
0 A
145 Reactor Bldg.
45'-90*
Be1. E1.593 + 2 17 0
0 A
146 Reactor Bldg.
90*-135'.
Be1. E1.593 + 2h 11 0
0 A
147 Reactor Bldg.
135'-180' Be1. E1.593 + 2h 10 0
0 A
148 Reactor Bldg.
180'-225' Be1. E1.593 + 2 2
0 0
A 149 Reactor Bldg.
315*-0' Be1. E1.593 + 2h 7
0 0
A 150 Reactor' Bldg. (Unit 2) 0'-45'-
Be1. E1.565 + 3 4
0 0
A 151 Reactor Bldg. (Unit 2) 45*-90*
Be1. E1.565 + 3 3
0 0
A 152 Reactor Bldg. (Unit 2) 90 -135' Be1. E1.565 + 3 4
0 0
A 153' Reactor Bldg. (Unit 2) 135'-180' Be1. E1.565 + 3 5
0 0
A 154 Reactor Bldg. (Unit 2)
'180*-225' Be1. E1.565 + 3
.3 0
0 A
155 Reactor Bldg. (Unit 2) 270'-315' Be1. E1.565 + 3 4
0 0
A~
.J56 Reactor Bldg. (Unit 2)-
315 -O' Be1. E1.565 + 3 6
0 0
A 157
Reactor Bldg. (Unit 2) 0'-45 5el. E1.586 + 6 6
0 0
A
.~
. TABLE'16'.9-3, Prge 4'of Si FIRE DETECTION INSTRUMENTS FIRE MINIMUM INSTRUMENTS OPERABLE
ZONE DESCRIPTION LOCATION SMOKE FLAME HEAT FUNCTION **
158 Reactor Bldg. (Unit 2) 45".90 Be1. E1.586 + 6 4.
0 0
A 159 Reactor B1dg. (Unit 2) 90*-135' Be1. E1.586 + 6 3
0 0
A.
160 Reactor B1dg. (Unit 2) 135'-180' Be1. E1.586 ' 6 8
0 O
A 161 Reactor B1dg. (Unit ~ 2) 180'-225' Be1. E1.586 + 6 5
0 0
A 162 Reactor B1dg. (Unit 2) 315'-O' Be1. E1.586 + 6 5
0 0
A1 163 Reactor Bldg. (Unit 2) 0*-45 Be1. E1.593 4 2s.
13 0
0 A
164 Reactor Bldg. (Unit 2) 45 -90 Be1. E1.593 ^ 24 17 0
0 A
165 Reactor Bldg. (Unit 2) 90"-135' Be1. E1.593 + 2h 13 0
0 A
166 Reactor B1dg. (Unit 2) 135 -180' Be1. E1.593 + 2h 10 0
0 A
167 Reactor Bldg. (Unit.2) 180*-225*
Be1. E1.593 + 2h 2
0 0
A 168 Reactor B1dg. (Unit 2) 315*-0 Be1. E1.593 + 2h 7
0 0
A 169 RCP-1A Reactor B1dg.
E1.593 + 2; O
O 1
A 170 RCP-18 Reactor 81dg.
E1.593 + 2h 0
0 1
A 171 RCP-1C Reactor Bldg..E1.593 + 2h 0
0 1
A 172 RCP-ID Reactor. Bldg. E1.593 + 2 0
-0 1
A 173 RCP-2A 45*
Be1. E1.593 + 2 0
0 1
A 174 RCP-28 135' Be1. E1.593 + 2h 0
0 1
A 175 RCP-2C 225' Be1. E1.593 + 2h 0
0 1
A 176 RCP-2D 315' Be1. E1.593 + 2 0
0 1
A 177 Filter Bed Unit IB Reactor B1dg.
Be1. E1.565 + 3 2
0 2
A 178 Filter Bed Unit IA Reactor Bldg.
Be1. E1.565 + 3 2
0 2
A 179 Filter Bed Unit 2A Reactor Bldg. E1.565 + 3 2
0 2
A 180 Filter Bed Unit 2B Reactor B1dg.
E1.565 + 3 2
0 2
A 181a Annulus E1.561 + 0 0
0 1
A 181b Annulus E1.583 + 0 0
0 1
A 181c Annulus E1.604 + 0 0
0 1
A 181d Annulus E1.629 + 5 0
0 1
A 181e Annulus E1.649 + 5 0
0 1
A 181f Annulcs E1.664 + 0 0
0 1
A 182a Annulus E1.561 + 0 0
0 1
A 182b Annulus E1.583 + 0 0
0 1
A 182c Annulus E1.604 + 0 0
0 1
A 182d Annulus E1.629 + 5 0
0 1
A 182e Annulus E1.649 + 5 0
0 1
A 382f Annulus E1.664 + 0 0
0 1
A 183 Fuel Pool Purge Room (Unit 2)
NN-64 E1.631 + 6 6
0 6
.A
. _ _ _.. ~ _ _, _..
J TABLE 16.9-3, Pcge 5 of 5 FIRE DETECTION INSTRUMENTS FIRE MINIMUM INSTRUMENTS OPERABLE *-
ZONE DESCRIPTION LOCATION SMOKE FLAME HEAT FUNCTION **
212 Aisles / Cables
'GG-57 E1.522 + 0 2
0 2
A-213 Aux. Batt. Room AA-55 E1.544 + 0 4
0 4
A 214 Aux. Cont. Pwr. Batt.
'AA-59 E1.560 + 0 4
0 4
A 215 D/G Corridor BB-45 E1.556 + 0 3
0 3
A 216 D/G Corridor AA-45 E1.556 + 0 2
0 2
A-217 D/G Corridor CC-71 E1.560 4 0 3
0 3
A 218 D/G Corridor 88-71 E1.560 4'O 2
0 2
A 219 Mech. Pen. Room HH-52 E1.577 + 0 6
0 6
A 220 Mech. Pen. Room JJ-62 E1.577 + 0 6
0 6
A 222 Airlock Access JJ-51 E!.605 + 10 1
0 1
A 224 Airlock Access (Unit 2)
JJ-63 E1.605 + 10 1
0 1
A 225 RN Pump Structure West Section E1.600 + 0
.8 0
8 A
226 RN Pump Structure
- East Section E1.600 + 0 8
0 8
A 231 Reactor Bldg. (Unit 1) 260 -303*
Be1. E1.668 + 10 10 0
0 A
232 Reactor Bldg. (Unit 2) 260'-303' Be1. E1.668 + 10 10 0
0 A
184 HVAC Duct for Rooms 331 and 332 FF-53, 543 + 0 1(Duct) 0 0
A 185 HVAC Duct for Rooms 203, 205 MM-60, 543 + 0 1(Duct) 0 0
A 205A, 206A, 2068, 207 and 209A 186 HVAC Duct for Rooms 301, NN-60, 560 + 0 1(Duct) 0 0
A 302, 305, and 307 RFIA Diesel Generator IA EE-41, 556 + 0 0
0-0(10)
A(B)
RFIB Diesel Generator 1B AA-41, 556 + 0 0
0 0(10)
A(B) t i
RF2A Diesel Generator 2A EE-72, 556 + 0 0
0 0(10)
A(B)
RF2B Diesel Generator 28 AA-72, 556 + 0 0
0 0(10)
A(B)
I i
The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate tests.
Function A: Early warning fire detection and notification only.
Function B: Actuation of fire suppression system and early warning and notification.
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/q; IE 16.13 CONDUCT OF OPERATIONS OPERATORS 16.13-1 FIRE BRIDGADE COMMITMENT A site Fire Brigade of at least five members shall be maintained onsite at all times.
The Fire Brigade shall not include three members of the minimum shift crew necessary for safety shutdown of the unit and any personnel required for other essential ' unctions 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence, take innediate action to fill the required positions.
TESTING PROCEDURES:
1)
Operations Management Procedure 2-2
REFERENCES:
1)
Catawba FSAR, Chapter 13.2 2)
Catawba SER, Section 9.5.1 and Appendix 0 3)
Catawba Fire Protection Review, as revised 4)
Catawba Fire Protection Commitment Index BASES:
The primary purpose of the Fire Brigade Training Program is to develop a group of station employees skilled in fire prevention, fire fighting techniques, first aid procedures, and emergency response.
They are trained and equipped to function as a team for the fighting of fires.
The station fire brigade organization is intended to be self sufficient with respect to fire fighting activities.
The Fire Brigade Training program provides for initial training of all new fire brigade members, quarterly classroom training and drills, annual practical training, and leadership training for fire brigade leaders.
This selected licensee commitment is part of the Catawba Facility Operating License Conditions #6 for NPF-52 and #8 for NPF-35.
16.13-1 J
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1 4
L Attachment !!!
Discussion, No Significant Hazards' Analysis and Evironmental Impact Statement f
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JUSTIFICATION FOR PROPOSED CHANGE By letter dated April 24, 1986, NRC issued Ganeric Letter 86 10, i
" Implementation of Fire Protection Requirements." Guidance for implementation of this letter was provided on August 2, 1988 by Generic Letter 88-12. " Removal of Fire Protection Requirements from the Technical Specifications." This amendment request follows the guidance given in Generic Letter 88 12.
Following implementation of this proposed change, a significant reduction in the content of the fire protection related Technical Specifications (TSs) will be achieved. Such action is consistant with the objectives of the NRC Technical Specification Improvement Program i
by reducing both the size and complexity of current Technical Specifications.
Attachments 2 and 3 provide proposed revisions to the Catawba TSs, Bases, and FSAR. The following is a brief susanary of these changes (1) The Limiting Conditions for Operations (LCO) and Surveillance Requirements (SR) for Specification 3/4 3.3.8 - Fire Detection Instrumentation are removed from Technical Specifications.
(2) The LCOs and SRs for Specification 3/4.7.10 - Fire Suppression Systems Spray and/or Sprinkler Systems CO Systems and Fire Home 2
Stations are removed.
(3) The LCOs and SRs for Specification 3/4.7.11 - Fire Barrier Penetrations are removed.
(4) Specification 6.2.2e on Unit Staff fire brigade requirements is removed.
l (5) Specification 6.5.1.12 requiring the inclusion of the Fire Protection Program under the items requiring technical review and control is added.
(6) Specification 6.8.1h. requiring the inclusion of the Fire Protection Program under Procedures and Programs controls is added.
(7) Specification 6.8.11. requiring the inclusion of the Commitments contained in FSAR Chapter 16.0 under Procedures and Programs control is added.
(8) Items in the Index and applicable Bases sections are removed.
This proposed amendment removes the fire protection systems, and fire brigade staffing requirements from the TSs and adds administrative controls l
to support the fire protection program. The requirements in the deleted TSs currently exist in plant procedures. This prop) sed amendment will subject future chan,tes to these procedures to the added TS requirement on Administrative Cont:ols. S_ection 6.0.
2-i Duke will locate the requirements which will be removed from the TSs in Catawba FSAR Chapter 16.0, Catawba Nuc1sar Station Selected Licensee
~
Cossaitments. For the information of the Staff Attachment 3 provides the proposed revision to the Catawba FSAR.
It is our plan to locate a copy of FSAR Chapter 16.0 along with the TS: in the Control Room to allow ready access by the operators.
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The addition of the fire protection program to the defined list of items requiring technical review and control and to the procedures and programs requirements in Section 6.0 of the TSs on Administrative Controls reinforces the importance of the fire protection program on plant safety. Therefore.
these additions are appropriate and consistent with requirements established for similar programs such as the security and emergency plans. The changes to the Administrative Controls in Section 6.0 of the TSs assure a multi-discipline review of proposed changes to those requirements which are removed from the TSs and placed in plant procedures.
The standard fire protection license condition has been instituted for both i
Catawba Units 1 and 2.
For Unit 1 the standard license condition was implemented as Amendment $7 to Facility Operating License NPF-35. The Facility Operating License for Catawba Unit 2 NPF-52, included the standard license condition as License Condition (6).
The changes in this proposed amendment are consistent with requirements outlined in Generic Letter 88-12. This proposed amendment will remove fire protection systems and itre brigade staffing from the TSs. and will aid 4
administrative controls to support the Fire Protection Program. The operational conditions, remedial actions, test and fire brigade staffing i
requirements deleted from the TSs will be added to FSAR Chapter 16.0, Catawba Selected Licensee Commitments. The requirement to institute the standard fire protection license condition has already been met.
5 ANALYSIS OF SIGNIFICANT RAZARDS CONSIDERATIO_N This analysis is provided to justify that the proposed amendment involves no l
significant hazards considerations.
10CFR 50.92 states that an amendment contains no significant hazards cons 4derations if operation in accordance with the amendment would not 1)
Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2)
Create the possibility of a new or different accident from any previously evaluated; or 3)
Involve a significant reduction in the margin of safety.
This TS Amendment is proposed to implement Generic Letter 86-10 Implementation of Fire Protection Requirements. The proposed amendment i
follows the guidelines given in Generic Letter 88-12 Removal of Fire l
Protection Requirements from the Technical Specifications. This change is administrative, in that none of the technical requirements are being l
changed. The proposed change removes the existing requirements from the TS j
and puts them in FSAR Chapter 16.0.
Since the technical content of the Fire
l
+3-Protection requirements has not changed this amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The changes to the Fire Protection Requirements in this proposed amendment Since the technical requitaments have not changed, are administrative.
thin amendment does not create the possibility of a new or different type of accident f rom any previously evaluated.
The technical requirements for Fire Trotection will be moved from the TS to the PSAR Chapter 16.0.
Because requirements will not change, operating and testing procedures will remain the same.. Plant procedures, which already exist, will continue to provide the specific instructions for implementing LCOs Actions, and Surveillance Requirements. Since the technical requirements are not changing, this change does not involve a significant reduction in the margin of safety.
For all of the above reasons. Duke Power concludes that this proposed amendment does not involve a Significant Hazards Consideration.
The proposed TS change has been reviewed against the criteria of 10 CFR 51.22(c)(9) for environmental considerations. As shown above, the proposed change does not involve any significant hazards consideration, nor increase the types or amounts of affluents that may be released offsite, nor increase Based on the individual or cumulative occupational radiation exposure.
this. The proposed Technical Specification change meets.the criteria given in 10CFR 51.22(c)(9) for categorical exclusion from the requirement for an Environmental Impact Statement.,
.

ML20012D785

Contents

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16.1 INTRODUCTION

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ML20012D785

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16.1 INTRODUCTION

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