ML20212L319

Proposed Tech Specs Relocating All Fire Protection Requirements to FSAR While Adding Fire Protection Program to Items Included in Specs 6.5.1 & 6.8.1

ML20212L319
Person / Time
Site:	McGuire, Mcguire
Issue date:	03/09/1987
From:	DUKE POWER CO.
To:
Shared Package
ML20212L314	List: ML20212L310 ML20212L319
References
NUDOCS 8703100354
Download: ML20212L319 (64)

Text

.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQU SECTION

. PAG,_E TABLE 4.3-6 REMOTE SHUT 00WN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

3/4 3-54 Accident Monitoring Instrumentation.......................

3/4 3-55 TA8LE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION..................

3/4 3-56 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

3/4 3-57 M6 m huun :..= rr t:t i r 2/' M c

'*'"I 3. 0 11 T ": ^ T 0T:0.t" !" """!"I^"

2/^ ^. ; ~

~

Radioactive Liquid Effluent Monitoring Instrimentation....

3/4 3-66

\\

TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................

3/4 3-67 TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........

3/4 3-69

'l Radioactive Gaseous Effluent Monitoring Instrumentation...

3 / 4, 3,-17 1 TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION....................................

')/4 3-72 TA8LE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........

3/4 3-75 Loose-Part Detection Systes..............................

3/4 3-78 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................

3/4 3-79 3/4.4 RFACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Stactup and Power Operation..............................

3/4 4-1 Hot Standby..............................................

3/4 4-2 Hot Shutdown.............................................

3/4 4-3 Cold Shutdown - Loops Fi11ed.............................

3/4 4-5 8703100354 870309 PDR ADOCK 0500 9

P VII McGUIRE - UNITS 1 and 2

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION

~

PAGE 3/4.7.5 STAN08Y NUCLEAR SERVICE WATER PON0.......................

3/4 7-12 3/4.7.6 CONTROL AREA VENTILATION SYSTEM..........................

3/4 7-13 3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAU$T SYSTEM...

3/4 7-16 3/4.7.8 SNU88ERS.................................................

3/4 7-18 TA8LE 3.7-4a SAFETY-RELATED HYORAULIC SNUB 8ERS (UNITS 1 AND 2)....

3/4 7-23 TA8tE 3.7-4b SAFETY-RELATED MECNANICAL SNU88ERS (UNITS 1 AND 2)...

3/4 7-26 FIGURE 4.7-1 SAMPLING PLAN FOR SNU88ER FUNCTIONAL TEST...........

3/4 7-29 SEALED SOURCE C0MTAMINATION..............................

[

3/4.7.9 3/4 7-30 3/4.7.10 T::: CLT ::: !0" :"'!G,

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3/4 '1 '?

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'b t.A. LTE.b 3/4.7.11 T*:0 ^ ^.----, i;;,;.,;.7:::..

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3/4/7.12 AREA TEMPERATURE MONITORING.......................J.......

3/4 7-42 TABLE 3.7-6 AREA TEMPERATURE MONITORING............................

3/4 7-43 3/4.7.13 GROUN0 WATER LEVEL.........................................

3/4 7-44 TABLE 3.7-7 GROUN0 WATER LEVEL MONITORING STATIONS..................

3/4 7-46 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating................................................

3/4 8-1 s

TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE......................

3/4 8-8

\\

l XII McGUIRE - UNITS 1 and 2 l

t INDEX BASES SECTION PAGE 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................

8 3/4 7-3 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM..............................

8 3/4 7-3 3/4.7.5 STAN08Y NUCLEAR SERVICE WATER PON0........................

8 3/4 7-3 3/4.7.6 CONTROL AREA VENTILATION SYSTEM...........................

8 3/4 7-4 3/4.7.7 AUXILIARY 8UILDING FILTERED VENTILATION EXHAUST SYSTEM....8 3/4 7-4 3/4.7.8 SNU88ERS..................................................

B 3/4 7-5 3/4. 7: 9 SEALED SOURCE CONTAMINATION...............................

8 3/4 7-6

") t. A.t.7 t b 3/4.7.10 ":::

.'^.^. :::0" !"I' "!.

- ^'; 7-o l> t.A L T EJb i

3/4.7.11 :::: "?""!!" "E"I'"????"f...........

i

" C 't 7 7 3/4.7.12 AREA TEMPERATURE MONITORING...............................

8 3/4 7-7 3/4.7 13* GROUN0 WATER LEVEL.........................................

8 3/4 7-8

)

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS........................

8 3/4 8-J 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...................

8 3/4 8-3 3/4.9 REFUELING OPERATIONS 1

3/4.9.1 80RON CONCENTRATION......................................

8 3/4 9-1 2

3/4.9.2 INSTRUMENTATION...........................................

8 3/4 9-1 3/4.9.3 OECAY TIME................................................

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING, PENETRATIONS.........................

8 3/4 9-1 3/4.9.s COMMUNICATIONS............................................

8 3/4 9-2 3/4.9.6 MANIPULATOR CRANE.'........................................

8 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL 8UILDING...........

8 3/4 9-2 3/4.9.8 RESIOUAL HEAT REMOVAL AND COOLANT CIRCULATION............. 8 3/4 9-2

)

3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and i

i STORAGE P00L............................................

S 3/4 9-3 XVIII i

]

-.=

T]lf 5 sftcincdrrow AND 175 M S E S

~

/Enueo INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERA 8LE.

APPLICA81LITY: Whenever equipment protected by the fire detection instrument-is required to be OPERA 8LE.

ACTION:

With any, but not more than one-half the total in any fire zone, a.

Function A fire detection instruments shown in Table 3.3-11 1

inoperable', restore the inoperable instrument (s) to OPERA 8LE status within 14 days or within the next I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations given in Specification 4.6.1.5.1 or l

4.6.1.5.2.

b.

With more than one-half of the Function A fire detection instruments I

in any fire zone shown in Table 3.3-11 inoperable, or with any Function 8 fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detection instruments shown in Table 3.3-11 inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the i

instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the contain-ment air temperature at least once per hour at the lueations given in Specification 4.6.1.5.1 or 4.6.1.5.2.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of the above re' quired fire 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.

Fire detectors which are not accessible during plant operation shall be demonstrated OPERA 8LE by the performance of a TRIP ACTUATIJ4G DEVICE OPERATIONAL TEST durings i

each COLD SHUT 00WN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

1 Each of the above requf red fixed temperature / rate of rise detection instruments l'

shall'be demonstrated OPERA 8LE as follows:

i l

Amendment No. 1 (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 3-58 Amendment No. 20 (Unit 1) 4/13/83

.fE*0VEp INSTRUMENTATION SURVEILLANCE REQUIREMENTS For nonrestorable spot-type detectors, at least two detectors out of every hundred, or fraction thereof, shall be removed every 5 years a.

For each failure that occurs on the and functionally tested.

detectors removed, two additional detectors shall be removed and l

tested.

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

signal initiating circuit shall be demonstrated OPERA 8LE at least once b.

per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL Fire Different detectors shall be selected for each test.

l TEST.

l detectors which are not accessible during plant operation shall be demonstrated OPERA 8LE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

The NFPA Standard 72D supervised circuits supervision associated 4.3.3.7.2 with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERA 8LE at least once per 6 months.

The nonsupervised circuits, asTociated with detector alarms, between the instrument and the control room shall be demonstrated O 4.3.3.7.3 least once per 31 days.

62 3/4 3-59

l 1

l TABLE 3.3-11 g

1 j @

FIRE DETECTION INSTRUMENTATION 5

TOTAL NO. INSTRUMENTS

• DETECTOR DESCRIPTION LOCATION SM0KE FIXED TENP.

FUNCTION""

g ZONE RATE OF RISE i!A i

us 1

Reactor Coolant Pump 1A RCP-1A 0

1 A

lH 2

Reactor Coolant Pump IB RCP-1B 0

1 A

g 3

Reactor Coolant Pump IC RCP-1C 0

1 A

2 a

4 Reactor Coolant Pump 10 RCP-10 0

1 A

N 5

Reactor Coolant Pump 2A RCP-2A 0

1 A

i 6

Reactor Coolant Pump 2B RCP-28 0

1 A

7 Reactor Coolant Pump 2C RCP-2C 0

1 A

)

8 Reactor Coolant Pump 2D RCP-20 0

1 A

29 Aux. Bldg. Vent Filter KK52-53 EL. 767 2

0 A

l 30 Elec. Pen. Rs.

CC-51 EL. 767 9

0 A/

/

31 Elec. Pen. Re.

CC-51 EL. 750 10 0

A

/

i U

32 Elec. Pen. Rs.

CC-51 EL. 733 10 0

.A

/

33 Unit 2 Aux. Bldg. Vent. Filter KK-59/60 EL. 767 2

0

/A

/

[

i e

34 Unit 2 Elec. Penetration Room CC-61 EL. 767g 9

0 A

S 35 Unit 2 Elec. Penetration Room CC-61 EL. 750 10 0

A 1

36 Unit 2 Elec. Penetration Room CC-61 EL. 733 10 0

A i

37 Diesel Gen. IA CC-43 EL. 733 0(0) 8(4)

A(B) j 38 Diesel Gen. 2A CC-69 EL. 733 0(0) 8(4)

A(8) l 39 Cable Room CC-55 EL. 750 6

5

.A 40 Control Room CC-56 EL. 760 43 22 A

4 41 Swgr. Re. 1 ETA AA-49 EL. 750 8

0 A

Swgr. R. 1ET8 AA-49 EL. 733 9

1 A

42 9

43 SWG. Room 2 ETA AA-62 EL. 750 8

0 A

44 SWG. Room 2ETB AA-62 EL. 733 9

1 A

i 45A Battery Room EVCA CC-54 EL. 733 2

2 A

)N 45B Battery Room EVCB CC-55 EL. 733 2

2 A

co.

45C Battery Room EVCC CC-56 EL. 733 2

2 A

E 450 Battery Roon EVCD CC-57 EL. 733 2

2 A

o 45G Battery Chg. Equip. & Pnl.

CC-56 EL. 733 9

0 A

5 EVCA, EVCC g

i m

.I

i h

TA8tE 3.3-11 (Continued) l

!N FIRE DETECTION INSTRUMENTATION

g iE TOTAL NO. INSTRUMENTS

• j DETECTOR DESCRIPTION LOCATION SMDKE FIXE 0 IuiP.

FlmSION""

im RATE OF RISE ZONE jg l Q*

Battery Chg. Equip. & Pnl.

45H 88-56 EL. 733 6

0 A

t 88-43 EL. 733 0(0) 8(4)

A(8)

EVCS, EVCD j "

88-69 EL. 733 0(0) 8(4)

A(8) g 50 Diesel Gen. 18 n.

51 Diesel Gen. 28 CC-57 EL. 750 6

5 A:

m 52 Unit 2 Cable Room 61 Cont. Spray Pump 1A/ Corridor GG-55 EL. 695 2

2 A

62 Cont. Spray Pump 18/ Corridor GG-56

.EL. 695 2

2 A

FF-54 EL. 695 1

1 A

GG-54 EL. 695 1

1 A

63 RHR Pump 18 66 Cont. Spray Pump 28/ Corridor GG-56 EL. 695 2

2 A

64 RHR Pump 1A 67 Cont. Spray Pump 2A/ Corridor GG-57 EL. 695 2

2 A

GG-58 EL. 695 1

1 A

FF-58 EL. 695 1

1 A

l) 68 RHR Pump 2A 88-51 EL.716l 8(2) 8(0)

A(8) l 69 RHR Pump 28 JJ-51 EL. 716 4

4 A

I l,4 70 Aux. F. W. Pumps e

72 Mech. Pen. Rs./ Cables HH-53 EL. 716 5

5 A

73 Corridor / Cables EE-55 EL. 716 5

5 A

74 Sample Panel / Cables JJ-55 EL. 716 2

2 A

75 Cent. Chg. Pump 18 JJ-55 EL. 716 2

2-

.A 76 Cent. Chg. Pump 1A JJ-54 EL. 716 2

2 A

77 Recip Chg. Pump 18 HH-54 EL. 716 2

2 A

78 Safety Inj. Pump 1A GG-54 EL. 716 2

2 A

79 Safety Inj. Pump 18 GG-55 EL. 716 12 12 A

GG-57 EL. 716 10 10 A

80 Aisle / Cables JJ-57 EL. 716 2

1.

A 81 Aisle / Cables h~

82 Cent. Chg. Pump 28 JJ-57 EL. 716 2

2 A-83 Cent. Chg. Pump 2A JJ-58 EL. 716 2

2 A

g l

84 Recip. Chg. Pump 28 HH-58 EL. 716 2

2 A

e, 3

l 85 Safety Inj. Pump 2A GG-58 EL. 716 2

2 A

D 86 Safety Inj. Pump 28 C

i TABLE 3.3-11 (Continued)

N FIRE DETECTION INSTRUMENTATION TOTAL NO. INSTRLMENTS*

DETECTOR DESCRIPTION LOCATION SMOKE FIXE 0 TEW.

FUNCTION **

E ZONE RATE OF RISE Q

87 Aux. F.W. Pumps CC-60 EL. 716 8(2) 8{0)

A(8) 88 Mech. Penetration Room / Cables JJ-61 EL. 716 4

4 A

is 9

90 Corridor / Cables NN-59 EL. 716 5

5 A

91 Corridor / Cables EE-53 EL. 733 4

4 A

N 92 Corridor / Cables JJ-51 EL. 733 6

6 A

93 Corridor / Cables NN-52 EL. 733 11 11 A

94 Aisle / Cables JJ-55 EL. 733 8

8 A

95 600V MCC IEMX8-1EMXB3 FF-55 EL. 733 1

1 A

96 Cable Tray Access EE-55 EL. 733 1

1 A

97 Cable Tray Access EE-57 EL. 733 1

1 A

98 600V MCC 2EMXB-2EMX83 FF-57 EL. 733 1

1 A

)

99 Aisle / Cables JJ-57 EL. 733 8

8 A

m 100 Corridor / Cables NN-58 EL. 733 12 12 A

a 101 Corridor / Cables JJ-61 EL. 733l 6

6 A

w N

102 Corridor / Cables EE-59 EL. 733 4

4 A

103 Corridor / Cables NM-51 EL. 750 6

6 A

104 Hatch Area Cables LL-53 EL. 750 7

7 A

106 600V MCC IEMXA FF-54 EL. 750 2

2 A

107 600V MCC 2EMXA FF-57 EL. 750 3

3

.A 108 Aisle / Cables JJ-55 EL. 750 13 13 A'.

109 Hatch Area Cables PP-57 EL. 750 14 14 A

110 Corridor / Cables PP-60 EL. 750 8

8 A

111 Corridor / Cables LL-59 EL. 750 6

6 A

b 112 Aisle / Cables JJ-57 EL. 750 12 12 A

{~

113 HVAC Equip. Area / Cables FF-56 EL. 767 7

7 A

114 Respiratory Equip. Room GG-54 EL. 767 1

1 A

o 115 Corridor / Cables JJ-54 EL. 767 13 13 A

q 116 HVAC Equip. Area / Cables NN-52 EL. 767 7

7 A

P 120 Environmental Lab PP-55 EL. 767 1

1 A

D 122 HVAC Equip. Area NN-59 EL. 767

-7 7

A 123 Corridor / Cables JJ-57 EL. 767 13 13 4

/

/

/

1 l

i TABLE 3.3-11 (Continued) 4

'N FIRE DETECTION INSTRUMENTATION ~

jg TOTAL NO. INSTRtBENTS*

fk l*

DETECTOR DESCRIPTION LOCATION SMDKE FIXE 0 TEMP.

FUNCTION **

RATE OF RISE

!E ZONE I%

f*

125 Fuel Pool Area NN-62 EL. 778+10 18 14 A

i" 127 Fuel Pool Area M-50 EL. 731+6 18 14 A

'E 128 Aisle / Cables EE-57 EL. 716 5

5 A

129 600V MCC 2EMMH KK-56 EL. 733 1

1 A

130 Cables /011 Fuel Pool PP-52 EL. 750 4

4 A

131 Clean Towel Storage HH-56 EL. 767 1

1 A

134 R8 Pipe corridor - Unit 1 215* - 270*

5 0

A 135 R8 Pipe Corridor - Unit 1 270* - 315*

5 0

A 136 R8 Pipe Corridor - Unit 1 315' - 0*

6 0

A i

137 R8 Pipe Corridor - Unit 1 0* - 44*

4 0

A i

138 R8 Pipe Corridor - Unit 1 44' - 90*

4 0

A

!T 139 R8 Pipe Corridor - Unit 1 90* - 126*

4 0

A 140 R8 Pipe Corridor - Unit 1 126* - 173*

7 0

A T

141 R8 Below Oper. Floor - Unit 1 329' - 349*

I 7

0 A

O 142 R8 Below Oper. Floor - Unit 1 13* - 29*

4 0

A 143 R8 Below Oper. Floor - Unit 1 34' - 51*

3 0

A 144 R8 Below Oper. Floor - Unit 1 51* - 124*

13 0

A j

145 RB 8elow Oper. Floor - Unit 1 124* - 143*

3 0

A "i

j l

146 R8 Below Oper. Floor - Unit 1 143

.167*

8 0

A

{

147 R8 Below Oper. Floor - Unit 1 RCP - IA Motor 4

1 A

148 R8 Below Oper. Floor - Unit 1 RCP - 18 Motor 1

1 A

149 R8 Below Oper. Floor - Unit 1 RCP - IC Motor 3

1 A

150 RB Below Oper. Floor - Unit 1 RCP - 10 Motor 4

1 A

151 RB Below Oper. Floor - Unit 1 Purge Filter Bed 2

2 A

152 R8 Below Oper. Floor - Unit 1 Purge Filter Bed 2

2 A

h 153 R8 Annulus - Unit 1 293* - 331*

10 10 8

(

154 R8 Annulus - Unit 1 324* - 0*

4 4

8 155 R8 Annulus - Unit 1 0* - 50*

5 5

8 w

156 R8 Annulus - Unit 1 50* - 80*

4 4

8

'{.

157 R8 Annulus - Unit 1 80* - 123*

24 24 8

158 R8 Annulus - Unit 1 123* - 165*

22 22 8

1 TABLE 3.3-11 (Continued)

!I FIRE OETECTION INSTRUMENTATION j g I

e-o

!5 TOTAL NO. INSTRtBENTS*

[

DETECTOR DESCRIPTION LOCATION SM0KE FIXED TEMP.

FUNCTION **

RK.E OF RISE ZONE l

159 R8 Annulus - Unit 1 333* - 16*

13 13 8

L j

160 R8 Annulus - Unit 1 16* - 54*

23 23 8

g

! g 161 R8 Annulus - Unit 1 122* - 180*

16 16 8

n l

162 R8 Annulus - Unit 1 180* - 256*

13 13 8

163 Unit 2 R8 Pipe Corridor 215* - 270*

5 0

A l

164 Unit 2 R8 Pipe Corridor 270* - 315' 5

0 A

165 Unit 2 R8 Pipe Corridor 315* - 0*

6 0

A 166 Unit 2 R8 Pipe Corridor 0* - 44' 4

0 A

167 Unit 2 R8 Pipe Corridor 44* - 90*

4 0

A 168 Unit 2 RB Pipe Corridor 90* - 126' 4

0 A

A 169 Unit 2 R8 Pipe Corridor 126* - 173*

7 0

g 170 Unit 2 R8 Below oper. Floor 329* - 347*

7 0

A i

171 Unit 2 R8 Below Oper. Floor 13* - 29*

4 0

A l

Y 172 Unit 2 R8 Below Oper. Floor 34* - 51*

l 3

0 A

I 173 Unit 2 R8 Selow Oper. Floor 51* - 124*

, 13 0

A 174 Unit 2 RB 8elow Oper. Floor 124* - 143*

3 0

A 175 Unit 2 R8 Below Oper. Floor 143* - 167*

8 0

A 176 Unit 2 RB Below Doer. Floor RCP 2A Motor 3

1 A.

l 177 Unit 2 R8 Below Oper. Floor RCP 28 Motor 2

1 A

)

178 Unit 2 RB Below Oper. Floor RCP 2C Motor 2

1

.A 179 Unit 2 RB 8elow Oper. Floor RCP 20 Motor 4

1 A

i I

180 Unit 2 R8 8elow Oper. Floor Purge Filter Bed 2

2 A

2 2

A i

181 Unit 2 R8 Below Oper. Floor Pury Filter Bed l

182 Unit 2 R8 Annulus 293 331*

10 10 8

183 Unit 2 R8 Annulus 324* - 0*

4 4

8

} A

..o l

184 Unit 2 R8 Annulus 0* - 50*

5 5

8-185 Unit 2 R8 Annulus 50* - 88*

4 4

8 P

1 i

186 Unit 2 R8 Annulus 88* - 123*

24 24 8

i

)

187 Unit 2 R8 Annulus 123* - 165*

22 22 8

Q 188 Unit 2 R8 Annulus 333* - 16*

13 13 8

i THi5 s fec ir=< c & 7e w 4^! b

' 7

3tfSLG AC M CVC b PLANT SYSTEMS 3/4.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION NATER SYSTEM LIMITIM CONDITION FOR OPERATION 3.7.10.1 The Fire Suppression Water System shall be OPERA 8LE with:

a.

At least two fire suppression pumps (either A and C or 8 and C),

l each with a capacity of 2500 gpe, with their discharge aligned to the fire suppression header; and b.

An OPERA 8LE flow path capable of taking suction from Lake Norman and transferring the water through distribution piping with OPERA 8LE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alare device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each Deluge or Spray System required to be OPERA 8LE per Specifications 3.7.10.2 and 3.7.10.4.

APPLICA8ILITY:

At all times.

ACTION:

M a.

With one of the above required pump and/or one water supply inoperable, restore the inoperable equipment to OPERABLE status within 7 days or provide an alternate backup pump or supply.

The provisions of Specifi-cations 3.0.3 and 3.0.4 are not applicable.

b.

With the Fire Suppression Water System otherwise inoperable establish a backup Fire Suppression Water System within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I

\\

McGUIRE - UNITS 1 and 2 3/4 7-32 Amendment No.55 (Unit 1)

Amendment No. 36 (Unit 2) l

- - - - ~ -

[Es+ ton /CD Pt. ANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.10.1 The Fire Suppression Water System shall be demonstrated OPERA 8LE:

At least once per 31 days on a STAGGERED TEST BASIS, by starting each a.

electric motor-driven pump and operating it for at least 15 minutes on recirculation flow, b.

At least once per 31 days, by verifying that each valve (manual, power-operated, or automatic) in the flow path is in its correct

position, c.

At least once per 6 months, by performance of a system flush of the outside distribution loop to verify no flow blockage, d.

At least once per 12 months, by cycling each testable valve in the flow path through at least one complete cycle of full travel, e.

At least once per 18 months, by performing a system functional test which includes simulated automatic actuation of the system throughout 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 gpa at a system pressure of 125 psig, 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 (sequentially) to maintain the Fire Suppression Water System pressure greater than or equal to 125 psig.

f.

At least once per 3 years, by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook,14th Edition, published by the National Fire Protection Association.

i Amendment No. 1 (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 7-33 Amendment No. 20 (Unit 1) 4/13/83

/2in< o V L b 4

PLANT M SPRAYAlW/0RSPEINKLERSYSTEMS LIMITIN8 CONDITION FOR OPERATION 3.7.10.2 The following Spray and/or,5prinkler Systems shall be OPERA 8LE:

a.

Elevation 695 ft. - Auxiliary Building Room No.

Eauionent 501 RHR Pump 1A 500 RHR Pump 18 506 RHR Pump 2A

+

507 RHR Pump 25 504 Corridor b.

Elevation 716 ft. - Auxiliary Building 1

Room No.

Equinment 600 Aux. FW Pump Room - Unit 1 649 Nuclear Services Water Pumps 627 Centrifugal Charging Pump 1A l

630 Centri 4ugal Charging Pump 18 601 Aux. FW Pump Room - Unit 2 634 Centrifugal Charging Pump 2A g

637 Centrifugal Charging Pump 28 644 Cable Shaft c.

Elevation 733 ft. - Auxiliary Butiding l

Roon No.

Equipment 723 Component Cooling Pumps 701 Battery Room Trench Area l

d.

Elevation 750 ft. - Auxiliary Butiding Room No.

Eautonent 801 Cable Room - Unit 1 801C Cable Room - Unit 2 l~

806 Component Cooling Pumps e.

Elevation 725 ft. - Reactor Building 1)

Pipe Corridor 2)

Lower Containment Ventilation Filters f.

Elevation 738 ft. - Reactor Building Annulus McGUIRE - UNITS 1 and 2 3/4 7-34

4 EE*oV(_b PLANT SYSTEMS LIMITING CONDITIS FOR OPERATION (Continued)

APPLICABILITY: Wheneve'r equipment protected by the Spray / Sprinkler System is required to be OPERABLE.

ACTION:

a.

With one or more of the above required Spray and/or Sprinkler Systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish a hourly fire watch patrol.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.10.2 Each of the above required Spray and/or Sprinkler Systems shall be demonstrated OPERA 8LE:

At least once per 31 days, by verifying that each valve (manual, a.

power-operated, or automatic) in the flow path which is accessible during plant operation is in its correct position, b.

At least once per 12 months, by cycling each testable valve in the flow path through at least one complete cycle of full travel, c.

At least once per 18 months:

1)

By performing a system functional test which includes simulated automatic actuation of the system, and:

a)

Verifying that the automatic valves in the flow path actuate to their correct position on a Fire Detection test signal, and b)

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 the dry pipe spray and sprinkler headers to verify their integrity; and 3)

By a visual inspection of each nozzle's spray area to verify the spray pattern is not obstructed.

4)

By verifying that each valve (manual, power-operated, or automatic) in the flow path which is inaccessible during plant operation is in its correct position.

ears, by performing an air flow test through At least once per 3 y/ sprinkler header and verifying each open head d.-

each open head spray spray / sprinkler nozzle is unobstructed.

~

~

w

2EMD t/ E D

' PLANT SYSTEMS HALON SYSTEMS s

LINITING CONDITION FOR OPERATION 3.7.10.3 The following Halon Systems shall be OPERA 8LE:

f a.

Elevation 716 ft. - Auxiliary Building f

Roon No.

Eauipment 600 B Turbine Driven Aux. FW Pump - Unit 1 6018 Turbine Driven Aux. FW Pump - Unit 2 I

b.

Elevation 733 ft. - Auxiliary Building Room No.

Eautoment l

703-704 Diesel Generators - Unit 1 714-715 Diesel Generators - Unit 2 j

APPLICASI.ITY: Whenever equipment protected by the Halon System is required to be OPEllABLE.

j ACTION:

With one or more of the above required Halon Systems inoperable,

~

a.

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

)

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

i SURVEILLANCE REQUIRENENTS l

4.7.10.3 Each of the above required Halon Systems shall be demonstrated j

OPERA 8LE:

At least once per 31 days, by verifying that each valve (manual, a.

power-operated, or automatic) in the flow path is in its correct

position, b.

At least once per 6 months, by verifying Halon storage tank weight to be at least 955 of full charge weight and pressure to be at least 905 of full charge pressure, and i

I c.

At least once per 18 months, by:

I 1)

Verifying the system, including associated wentilation dampers and fire door release mechanisms, actuates manually and auto-l matica11y, upon receipt of a simulated actuation signal, and r

I l

2)

Perfomance t,,f a flow test through headers and nozzles to assure no blockage.

)

3/4 7-34 i.

McGUIRE UNITS 1 and 2

1

$LMDv'lb i

PLANT SYSTEMS 4

FIRE H0SE STATIONS LIMITING CONDITION FOR OPERATION 3.7.10.4 The fire hose stations shown in Table 3.7-5 shall be OPERA 8LE.

l APPLICA8tLITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

With one or more of the fire hose stations shown in Table 3.7-5 l

a.

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 l

outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station. Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazard to l

' operating technicians, plant equipment, or the hose itself, the fire hose shall be stored in a roll at the outlet of the OPERABLE hose

{

Signs shall be mounted above the gated wye (s) to idertify l

station.

the proper hose to use.

The above action shall be accomplished l

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVE!LLANCE REQUIREMENTS 4.7.10.4 Each of the fire hose stations shown in Table 3.7-5 shall be demonstrated OPERA 8LE:

At least once per 31 days, by a visual inspectiun of the fire hose a.

stations accessible during plant operations to assure all required equipment is at the station, b.

At least once per 18 months, by:

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 re-racking, and 3)

Inspecting all gaskets and replacing any degraded gaskets in the couplings.

c.

At least once per 3 years, by:

1)

Partially opening each hose station valve to verify valve OPERASILITY and no flow blockage, and 2)

Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.

McGUIRE - UNITS I and 2 3/4 7-37

lEMDVFD PLANT SYSTEMS Table 3.7-5 FIRE HOSE STATIONS NO.

LOCATION ELEVATION (FT) 157 55-FF 695 180 52-CC 716 181 54-GG 716 176 52-CC 716 175 52-CC 716 893 40-AA 733 891 40-CC 733 892 43/44-DD 733 895 46 BB 733 889 51/52-DD 733 888 52-EE 733 171 54-HH 733 167 51-JJ 733 168 52-MM 733 169 55-NN 733 962 46-CC 750 964 51-CC 750 965 54-8B 750 e

966 56-DD 750 971 58-BB 750 303 52-GG 750 162 54-LL 750 161 50-MM 750 164 56-QQ 750 974 51-BB 767 191 56-GG 767 184 54-KK 767 186 51-MM 767 158 57-FF 695 183 59-CC/DD 716 182 58-GG 716 178 58/59-MM 716 179 61-LL 733 900 68-AA/BB 733 901 72-DD 733 902 68/69-00 733 903 72-DD 733 914 66-BB 733 l

898 61-8B 733 i

899 66-BB 733 897 60-00 733 896 60-EE 733 904 58-CC/DD 733 172 58-HH 733 174 61-JJ/KK 733 170 57-LL 733 Amendment No.10(Unit 2)

McGUIRE - UNITS 1 and 2 3/4 7-38 Amendment No.29(Unit 1)

AL A 0 t/ E.b PLANT SYSTEMS TA8LE 3.7-5 (continued)

FIRE HOSE STATIONS LOCATION ELEVATION (FT) 173 60-M/M 733 967 67-B8 750 968 66-CC 750 969 61-CC 750 750 970 61-88 972 57-00 750 1185 58-JJ 750 302 60-KK 750 750 166 61-M 165 58-LL/M 750 767 975 61-88 767 192 58-JJ 767 193 60-M 767 194 61-M 177 55-QQ 716 894 44-AA/88 733 913 45-AA/88 733 733 890 51-88 733 887 53-D0 733 1184 56-JJ 750 163 54-JJ 750 961 45-88 750 963 51-88 767 185 54-M l

l l

l l

l l

McGUIRE - UNITS 1 and 2 3/4 7-39 i

"TH t 5 Sfcc tPi cArrosj AA) D i 73 a

E cwov c o

_ _3 +3 c s PLANT SYSTEMS 3/4.'/.li' FIRE BARRIER PENETRATION _S N :

Mf1TINGCONDITiONFOROPERATION j.

3.7.11 All fire barrier penetrations (walls, floor / ceilings, 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 OPERA 8LE.

APPLICA8ILITY: At all times.

ACTION:

a.

With one or more of the above required fire barrier penetrations and/or sealing devices inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either establish a continuous fire watch on at least one side of the affected assembly, or verify the OPERA 81LITY of fire detectors on at least one side of the inoperable assembly and establish an hourly fire watch patrol.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.1 At least once per 18 months the above required fire barrier j

penetration sealing devices shall be verified OPERABLE, by performing a visual l

inspection of:

The exposed surfaces of each fire rated assembly, a.

l b.

Each fire window / fire damper /and associated hardware, and l

c.

At least 10% of each type of sealed penetration.

If apparent l

changes in aopearance or abnormal degradations are found, a visual inspection of'an additional 10% of each type of sealed penetration 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 penetration seal will be inspected every 15 years.

j McGUIRE - UNITS 1 and 2 3/4 7-40

[

i 2 LIMDv' Ll>

t PLANT SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) n 4.7.11.2 Each of the above required fire doors shall be verifled OPERA 8LE by inspecting the automatic ht1d-open, release and closing mechanism and latches at least once per 6 months, and by verifying:

That each unlocked fire door without electrical supervision is a.

closed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

That doors with automatic hold-open and release mechanisms are free of obstructions at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and performing a functional test at least once per 18 months, That each locked closed fire door is closed at least once per c.

7 days, and s

d.

The OPERA 8ILITY of the Fire Door Supervision System for each electrically supervised fire door by performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least onv per 31 days.

I

~

1 i

i i

n!

i l

l 3/4 7-41 McGUIRE

. UNI.TS 1 and 2.

6.0 ADMINISTRATIVE CONTROLS y

6.1 RESPONSIBIEITY a t 6.1.1 The Station Manager shall be responsible for overall unit operation and shall delegate in writing the suc. cession to this responsibility during his absence.

6.1.2 The Shift Supervisor (or during his absence from the control room, a designated individual) shall be responsible for the control room command A management directive to this effect, signed by the Vice-President ([

function.

Nuclear Production shall be reissued to al.1 Nuclear Production Department y

/s station personnel on an annual basis.

o.

6. 2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as described in the FSAR, Chapter 13.

f UNIT STAFF.

1 6.2.2 The unit organization shall be as shown in the FSAR, Chapter 13, and:

9 Each on-duty shift shall be composed of at least the minimum shift a.

i crew composition shown in Table 6.2-1; b.

At least one licensed Operator for each unit shall be in the control room when fuel is in either recctor.

In addition, while either unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room; A Health Physics Technician # shall be on site when fuel is in either c.

reactor; d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibil-t ities during this operation; a.44 l

^ :iu F'n ri; 9 t 1 et # %e :-here she!' be eetate -ed f

ea;f t; et ;?? ti; ;.p' Th: Fir: Sric:d:

a

h:11 n t include thr :

-- ':r; cf th: ;ini rr :hift err ; ;;;;;ry f;r ;;f; ;hutd;;; ef th; unit ;;d ;ay i;;;;;ar.;l rquired f;r ;th r ;;; atial f;;;ti ;; dur' ;

...a a s.. - - _.,- _,, -._

The Health Physics Technician ;ad Fi = Srt;:d composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order i

to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

(

)

McGUIRE - UNITS 1 and 2 6-1 AmendmentNo.b(Unit 1)

- _, - _. -.M (Unit 2) ---

Amendment No.

i l

No c.A ADMINISTRATIVE CONTROLS 6.5 REVIEW ANO-AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.1.1 - Each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, shall be prepared by a qualified individ1al/ organization.

Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual /

group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual / group which prepared the procedure, or changes thereto.

.6.5.1.2 Proposed changes to the Appendix A Technical Specifications shall be prepared by a qualified individual / organization.

The preparation of each proposed Technical Specifications change shall be reviewed"by an individual /

group other than the individual / group which prepared the proposed change, but who may be from the same organization as the individual / group which prepared the proposed change.

Proposed changes to the Technical Specifications shall be approved by the Station Manager.

'. 6,5.1.3 Proposed modifications to unit nuclear safety-related structures,

• systems and components shall be designed by a qualified individual / organization.

Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same...

organization as the individual / group which designed the modification.

Proposed modifications to nuclear safety-related structures, systems, and components shall be approved prior to implementation by the Station Manager; or by the Operating Superintendent, the Technical Services Superintendent, the Superintendent of Integrated Scheduling, or the Maintenance Superintendent,

.I as previously designated by the Station Manager.

6.5.1.4 Individuals responsible for reviews perfomed in accordance with Specifications 6.5.1.1, 6.5.1.2, and 6.5.1.3 shall be members of the station supervisory staff, previously designated by the Station Manager to perform such reviews.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.

If deemed necessary,

(

such review shall be performed by the appropriate designated station review personnel.

6.5.1.5 Proposed tests a'nd experiments which affect station nuclear safety l

and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager; or by the Operating Superintendent, the Technical Services Superintendent the Maintenance Superintenden't, or the -

Superintendent of Integrated Scheduling as previously designated by the Station Manager.

McGUIRE - UNITS 1 a,nd 2 6-8 Amendment No.52(Unit 1)-

(

Amendment No.33 (Unit 2)

i ADMINISTRATIVE CONTROLS i

~

ACTIVITIES (Continued)

6. 5.1. 6 ALL REPORTABLE 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 reviewed at least once per 12 months.

Recommended changes shall be approved 4

by the Station Manager or Superintendent of Station Servires and transmitted

/

to the Vice President, Nuclear Production, and to the Director of the Nuclear Safety Review Board.

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 Produc-tion, and to the Director of the Nuclear Safety Review Board.

6.5.1.10 The Station Manager shall assure the performance of a review by a qualified individual / organization of every unplanned onsite release of radio-~~

active material to the environs including the preparation and forwarding of-reports covering evaluation, recommendations, and disposition of the corrective' ACTION to prevent recurrence to the Vice President, Nuclear Production and to the Nuclear Safety Review Board.

~

6.5.1.11 The Station Manager shall assure the performance of a review by a t

qualified individual / organization of changes to the PROCESS CONTROL PROGRAM, gg OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems.

l}

g j 4 *;,1 s L P6.5.1.R" Reports documenting each of the activities performed under Spe l

cations 6.5.1.1 through 6.5.1. X,sha11 be maintained.

Copies shall be provided i

to the Vice President, Nuclear Pr > duction, and the Nuclear Safety Review Board.

Ib 6.5.2 NUCLEAR SAFETY REVIEW 80ARdNSR8)

FUNCTION 6.5.2.1 The NSR8 shall function to provide independent review and audit of designated activities in the areas of:

j a.

Nuclear power plant operations, i

l b.

Nuclear engineering, c.

Chemistry and radiochemistry, McGUIRE - UNITS 1 and 2 6-9 Amendment No. 52(Unit 1)

- 6.5.1.12 The Station Manager shall ensure the performance of a review by a qualified individual / organization of the Fire Protection Program and

.implesqpting procedures and submittal of recommended changes to the Nuclear Safety Review Board.

1 #

?

t l

1 i

4 Y

' ' ~ '

4

1 NO

%= w ADMINISTRATIVE CONTROLS FUNCTION (Continued) d.

Metallurgy, e.

Instrumentation and control, f.

Radiological safety, g.

Mechanical and electrical engineering, and h.

Administrative control and quality assurance practices.

ORGANIZATION 6s5.2.2 The Ofrector, members and alternate members of the NSR8 shall be appointed in writing by the Vice President, Nuclear Production, and shall have an academic degree in an engineering or physical science fie1d; and in addition, shall have a minimum of 5 years technical experience, of which a minimum of 3 years shall be in one or more areas given in Specifica-tion 6.5.2.1.

No more than two-alternates shall participate as voting members in NSR8' activities at any one time.

6.5 Dir 4 3 The NSR8 shall be composed of at least five members, including the ector. Members of the NSR8 may be from the Nuclear Production Department, y

from other departments within the Company, o'r from external to the Company.

A maximum of one member of the NSR8 may be from the McGuire Nuclear Station staff.

6.5.2.4 ' Consultants shall be utilized as determined by the NSRB Director to provide expert advice to the NSR8.

6.5.2.5 Staff assistance may be provided to the NSR8 in order to promote the proper, timely, and expeditious performance of its functions.

6.5.2.6 The NSRB shall meet at least once per calendar quarter during the

~

initial year of unit operation following fuel loading and at least once per 6 months thereafter.

6.5.2-t-The7uorum or the N5R8 necessary for the performance of the MSRB review and audit functions of these Technical Specifications shall consist of the Director, or his designated alternate, and at least four other NSRB members including alternates.

No more than a minority of the quorum shall have line responsibility for operation of McGuire Nuclear Station.

I

~

McGUIRE - UNITS 1 and 2 6-10

~

NO Ch=: /**

M f7 ADMINISTRATIVE CONTROLS

(

7 REVIEW 6.5.2.8 The NSR8 shall review:

a.

The safety evaluations for:

(1) changes to procedures, equipment, or systems, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR to verify that such actions did not constitute an unreviewed safety question; b.

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR; Proposed tests or experiments which involve an unreviewed safety c.

question,as defined in Section 50.59, 10 CFR; 3

d.

Proposed changes in Technical Specifications or-this Operating License; Violations of Codes, regulations, orders, Technical Specification.s, e.

license requirements, or of internal procedures or instructions having nuclear safety significance; k-f.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; h

g.

All REPORTABLE EVENTS;

~~.

i h.

All recognized indications of an unanticipated deficiency in s'ome aspect of design or operation of structures, systems or components that could affect nuclear safety; 1.

Quality Assurance Department audits relating to station operations and actions taken in response to these audits; and J.

Reports of activities performed under the provisions of Specifi-cations 6.5.1.1 through 6. 5.1.11.

AUDITS 6.5.2.9 Audits of unit activities shall be performed under the cognizance of the NSR8.

These audits shall encompass:

I a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; l

b.

The performance, training, and qualifications of the entire unit staff at least once per 12 months; Amendment No. 32 (Unit 1).'

McGUIRE - UNITS 1 and 2 6-11 Amendment No.13 (Unit 2)

I AJo ADMI'NISTRATIVE CONTROLS

[%t

~

AUDITS -(Continued)~

The results of actions taken to correct deficiencies occurring in c.

unit equipment, structures, systems, or method of operation that affect nuclear safety at least once per 6 months; d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix 8,10 CFR Part 50, at least once per 24 months; The Emergency Plan and implementing procedures at least once per e.

12 months; f.

The Security Plan and implementing procedures at least once per 12 months; g'.

The Facility Fire Protection programmatic controls including the implementing procedures at least once per 24 month's by qualified licensee QA personnel;

h.. The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite ifcensee fire protection engineer or an outside independent fire protection consultant.

An outside independent fire protection consultant shall i

\\g be used at least every third year; i.

The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; j.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; k.

The PROCESS CONTROL PROGRAM and implementing procedures for

)

SOLIDIFICATION of radioactive wastes at least once per 24 months; l

1.

The performance of activities required by the Quality Assurance j

Program for effluent and environmental monitoring at least once per 12 months; and Any other area of unit operation considered appropriate by the NSRB m.

or the Vice President, Nuclear Production.

AUTHORITY t

l 6.5.2.10 The NSR8 shall report to and advise the Vice President, Nuclear l

Production, on those areas of responsibility specified in Specifications 6.5.2.8 l

and 6.5.2.9.

l I

l l

McGUIRE - UNITS 1 and 2 6-12

1,

/P ADMINISTRATIVE CONTROLS RECORDS

~

6.5.2.11 Records of NSR8 activities shall be prepared, approved, and distributed as indicated below:

a.

Minutes of each NSR8 meeting shall be prepared, approved, and forwarded to the.Vice President, Nuclear Production, and to the Executive Vice President, Engineering, Construction, and Production, within 14 days following each meeting; b.

Reports of reviews encompassed by Specification 6.5.2.8 above, shall be prepared, approved and forwarded to the Vice President, Nuclear Production, and to the Executive Vice President, Engineering, Construction, and Production, within 14 days following completion of the review; and c.

Audit reports encompassed by Specification 6.5.f.9 above, shall be forwarded to the Vice President, Nuclear Production, and to the Executive Vice President, Engineering, Construction, and Production, and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to '

the requirements of Section 50.73 to 10 CFR Part 50, and

(

b.

Each REPORTABLE EVENT shall be reviewed by the Station Manager; or by:

(1) the Operating Superintendent, (2) the Technical Services Superintendent, (3) the Maintenance Superintendent, or (4) the Superintendent of Integrated Scheduling, as previously designated by the Station Manager, and the results of the review shall be submitted to the NSRB and the Vice President, Nuclear Production.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as l

possible and in all case's within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Vice President, Nuclear l

Production, and the NSRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the Operating Superintendent and the Station Manager.

l This report shall describe:

(1) applicable circumstances preceding l

the violation, (2) effects of the violation upon facility components, systems. or structures, and (3) corrective action taken to prevent recurrence; l

McGUIRE - UNITS 1 and 2 6-13 Amendment No.52(Unit 1)

Amendment Nn.33(Unit 2)

I ADMINISTRATIVE CONTROLS SAFETYLIMITVIOLETION(Continued)

The Safety Limit Violation Report si:all be submitted to the Commission, the NSR8 and the Vice President, Nuclear Production, c.

within 14 days of the violation; and Critical-operation of the unit shall not be resumed until authorized d.

by the Commission.

6.8 PROCEDURES AND PROGRAMS Written procedures shall be established, implemented, and maintained 6.8.1 covering the activities referenced below:

The applicable procedures recommended in Appendix A of Regulatory a.

Guide 1.33, Revision 2, February 1978; The applicable procedures required to implement the requirements b.

of NUREG-0737; h

Security Plan implementation;*

t c.

Emergency Plan implementation; d.

PROCESS CONTROL PROGRAM implementation; e.

OFFSITE DOSE CALCULATION MANUAL implementation; and f.

Quality Assurance Program for effluent and environmental monitorin

p ~ h%

g.

I fh o!&% As W j,EachprocedureofSpecification6.8.1above,andchangesthereto,shall (1) the Operating 78.2 be reviewed and approved by the Station Manager; or by:

l Superintendent, (2) the Technical Services Superin l

L 7

f designated by the Station Manager; prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

Temporary changes to procedures of Specification 6.8.1 above may be 6.8.3 made provided:

The intent of the original procedure is not altered; a.

The change is approved by two members of the plant management s at least one o,f whom holds a Senior Operator license on the unit b.

affected; and p

• Review and approval may be performed by the Superintendent of Statio I

I Services.

N h '*

l

[

L',

m & $ C-m W k k SS/M-1 Amendment No.

(Unit 1) 6-14 McGUIRE - UNITS 1 and 2 Amendment No.

(Unit 2)

i ATTACHMENT 3 REVISION TO THE BASES OF TECHNICAL SPECIFICATIONS l

(RLG177) i

INSTRUMENTATION

~

BASES 3/

RE DETECTION INS

( [,,

E.

OPERA 8ILITY of the detection instrumentation ensures that both adequa warning capability is available for prompt detection of fires and that fire suppression systems, that are actuated by fire detectors, will discharge extinguishing agent in a timely manner. Prompt detection and suppression of fires will reduce the potential for damage to safety-related equipment and is-an integral element in the overall facility fire protection program.

Fire detectors that are used to actuate Fire Suppression Systems represent a more critically important component of a plant's fire proteccion i

program than detectors that are installed solely for early fire warning and notification.

Consequently, the minimum number of OPERA 8LE fire detectors

'must be greater.

The loss of detection capability for Fire Suppression Systems, actuated by fire detectors, represents a significant degradation of fire protection for any area. As a result, the establishment of a fire watch patrol must be initiated at an earlier stage than would be warranted for the loss of detectors that provide only early fire warning. The establishment of frequent ire patrols in the affected areas is required to provide detection capability

'., un e inoperable instrumentation is restored to OPERABILITY.

3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid ef fluents during actual or potential releases of liquid effluents.

The Alare/

Trip Setpoints for these instruments shall be calculated and adjusted in

~

accordance with the methodology and parameters in the 00CM to ensure that the Alarm / Trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Crfteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The purpose of tank level indicating devices is to assure th'e detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

3/4.3.3.9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents ~ during actual or potential releases of gaseous effluents.

The Alarm / Trip Setparints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the 00CM to ensure that the Alare/ Trip will occur prior to exceeding the limits of 10 CFR Part 20.

This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE GAS liOLDUP SYSTEM. The OPERA 8ILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

McGUIRE - UNITS 1 and 2 B 3/4 3-4

PLANT SYSTEMS

(

BASES SNUB 8ERS (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 snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...).

The requirement to monitor the snubber service life is included to ensure t. hat 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.

The requirements for the maintenance of records and the snubber service life review not intended to affect plant operation.

f 3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium:

This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.

' Sealed sources are classified into three groups according to their use.

with Surveillance Requirements commensurate with the probability of damage to a

[

source in that group.

Those sources which are frequently handled are required to be tested more often than these which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored.

and need not be tested unless they are removed from the shielded mechanism.

3/4.7.10 " ": C'r a""O Z:: 0 5 ::^.0 304E.7ED The OPERASILITY of the Fire Suppression Systems ensures that adeq fire ression capability is available to confine and extingu es cccurring portion of the facility where safety-related 1f uipment is located. The Suppression System consists of the wethe system, spray, and/or sprinklers,

, and fire hose station

• The collective capability of the Fire Suppression ens is adequat minimize potential damage to safety-related equipment and a mai enent in the facility fire protection program.

In the event that of the F uppression Systems are inoperable, citernate backup ffr ighting equipment is red to be made available in the affected ar until the inoperable equipment stored to service.

When the i able fire-fighting equipment is intende use as a backup means of re suppression, a longer period of time is allowe o provide an alter e means of fire fighting than if the inoperable equipmen the pr ary means of fire suppression.

McGUIRE - UNITS 1 and 2 8 3/4 7-6

~

'l PLANT SYSTEMS I

BASES

-4LlRE SUPPRESSION SYSTEMS (Continued)

N.,

TheSurveiIlance Requirements provide assurance that tjgatrif1Gm OPERABILITY requirements of the Fire Suppression Systems ~are met.

An allowance is made for ensuting a sufficient volume of Halon in the Halon storage tanks by verifying either,,the-weight or the level of the tanks.

Level measurements are made by ej ther'a U.L. or F.M. approved method.

In the, event "the Fire Suppression Water System becomes inoperable, immed

~

' corrective measures must be taken since this system provides the fire suppression capability of the plant.

sq 3/4.7.11 c ! 9 E " " "G G ^ CC" * "^": ' E. A. E. 7 f. D

/

site functional integrity of the penetration fire barriers ensure,s-t6at fires wit 1.be confined or adequately retarded from spreading to adjacent portions of the' facility.

This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment.

The penetration fire barriers 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 and dampers 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.

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 l

af fected barrier, or (2) the fire detectors on at least ohe side of the SFficted barrier must be verified OPERABLE and an hourly fire watch patrol established until the barrier is restored to functional status.

~,

-~

3/4.7.12 AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures.

Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITY.

The temperature limits include an allowance for instrument error of 3.9'F.

I 1

l l

McGUIRE - UNITS 1 and 2 8 3/4 7-7

ATTACHMENT 4 PROPOSED REVISION TO McGUIRE NUCLEAR STATION FINAL SAFETY ANALYSIS REPORT l

i l

l l

1 l

(RLG177) l

A description of this ventilation system is exhaust it to station vent.

The Control Room has an independent ventilation described in Section 9.4.6.

This system system which maintains the area at a slight positive pressure.

prevents any exterior contaminants c4 smoke from entering the Control Room.

The ventilation and air conditioning system for the Control Room is described If hazardous conditions arise due to a lack of ventilation

-in Section 9.4.1.

in any particular area, self-contained breathing apparatus are on the site and can be provided to personnel when necessary.

9. 5.1. 3 Safety Evaluation The fire protection system provides a reliable source of water or gaseous Three 100 percent capacity extinguishing agent to all portions of the plant.

fire pumps are designed to start in sequence with a drop in pressure in the The source of fire protection water does not affect fire protection system.

the ultimate heat sink.

To provide a reliable power supply for the fire pumps, diverse power sources are used.

The emergency diesel generators are protected by an automatic Halon 1301 extinguishing system and backed up by hose stations.

Pressure is maintained in the fire protection header in the Auxiliary Building.

Water flow alarms are provided to alert operators of a possible pipe break and Deluge valves in the header may prevent possible flooding due to pipe break.

be opened from the control room, at stations throughout the Auxiliary Buf1 ding or manually at each valve.

In addition to sprinkler systems, manual hose stations and portable extinguish-ers are provided throughout the plant.

Automatic detection with local alarm and alarm and annunciation in the con room is provided over cable trays, in areas containing combustibles, over motor Detectors are also provided control centers and in normally unoccupied areas.

in ventilation ducts.

An expanded safety evaluation is presented in the "McGuire Nuclear Station Fire Protection Review" dated September 1977 revised January 1979, revised September 1982, revised September 1985, in response to Appendix A to Branch Technical Position APCS 8 9.5-1 and 10CFR50 Appendix R.

9. 5.1. 4 Tests and Inspections The installation of the Fire Protection System is in accordance with approved engineering drawings supplied by Duke Power Company or experienced fire protec-tion system manufacturers contracted to supply the engineered e l

construction.

functional checks, including alarms and detectors, to insure their proper All hose stations, racks, and hydrants receive inspection and N g functioning. testing to insure their proper operation.

Flow tests for all fire pumps are held annually using the eight 2 1/2 inch hose During this test, a connections and flow element provided for this purpose.

g pump is started automatically by opening its test valve on the 1/2 inch line i

1985 Update 9.5-8

i-Specific comitments related to the-operation 'and testing of fire protection i

( ystem equipment are contained in FSAR Chapter 16.0.

s

=

8 4

i i

i 3

I t

i i

Fire protection program and procedures g.

New Employee Orientation (Portions of other General Employee Training h.

may be included.)

~

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 of station employees skilled in fire prevention, fire fighting They are trained group techniques, first aid procedures, and emergency response.

The station and equipped to function as a team for the fighting of fires.

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.

l 13.2.2.2 Technical Training 9

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 performT assigned work in a umpetent manner.

segments:

Initial Training On-the-Job Training & Qualification Continuing Training 13.2.2.2.1 Initial Job Training basic principles, and procedures involved in work in w assigned.

This training may consist of, but is not ifmited to, live. lectures, taped and filmed lectures, guided self-study, demonstrations, laboratories and 4

i workshops, on-the-job training, and where applicable, simulator train ng and/or training on a research reactor.

Certain new employees or employees transferred from other department locations may be partially qualified by reason of previous applica is determined by appifcable regulations, performance in review sessions, training or experience.

comprehensive examinations, or other techniques designed to identify the employee's present level of ability.

Initial job training and qualification programs are developed for operatio Training for maintenance and technical services non-exempt classifications.

each program is grouped into logical blocks or modules and presented Trainee progress manner that specific behavioral objectives are accomplished.

1985 Update 13.2-3

Specific commitments related to the Fire Brigade are contained in FSAR Chapter i

16.0.

l l

l l

l w

t MCGUIRE NUCLEAR STATION FINAL SAFETY ANALYSIS REPORT CHAPTER 16.9

' SELECTED LICENSEE COMMITMENTS AUXILIARY SYSTEMS Table of Contents 16.9 Fire Suppression Water Systems 16.9-2 Spray and/or Sprinkler Systems 16.9-3 Halon Systems 16.9-4 Fire Hose Stations 16.9-5 Fire Barrier Penetrations 16.9-6 Fire Detection Instrumentation 16.9-7 Standby Shutdown System 16.9-0

16.9 AUXILIARY SYSTEMS FIRE PROTECTION SYSTEMS 16.9-1 FIRE SUPPRESSION WATER SYSTEM COMMITMENT' The Fire Suppression Water System shall be OPERABLE with:

At least two' fire suppression pumps,_(either A and C or B and C) a.

each with a capacity of 2500 gpa, with their discharge aligned to the fire suppression header; and b.

An OPERABLE flow path capable of taking suction from Lake Norman and transferring the water through d.stribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each Deluge or Spray System required to be OPERABLE per Commitments 16.9-2 and 16.9-4.

APPLICABILITY: At all times.

REMEDIAL ACTION:.

a.

With one of the above required pumps and/or one water supply inoperable, restore the inoperable equipment to OPERABLE status within 7 days or provide.an alternate backup pump or supply.

l 1

With the A or B pump INOPERABLE for more than 7 days, the acceptable alternate backup pumps are B and A, respectively.

11 With the C pump INOPERABLE for more than 7 days, the acceptable alternate backup pump is provided.by having the capability to I

align the A and B pump to the blackout diesel generator.

b.

With the Fire Suppression Water System otherwise inoperable establish a backup Fire Suppression Water System within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

TESTING PROCEDURES:

1)

PT/0/A/4400/01D Fire Pump Operability Test 2)

PT/0/A/4400/01C Fire Protection System Monthly Test 3)

PT/0/A/4400/01E Fire Hydrant Operability Test t

4)

PT/0/A/4400/01K Fire Protection Annual Valve Test 5)

PT/0/A/4400/01A Fire Protection System Test 6)

PT/1-2/A/4400/01L Fire Protection Containment Header Test 16.9-1

7)

PT/0/A/4400/01M

' Fire Protection System Flow

REFERENCES:

1)

McGuire FSAR, Chapter 9.5.1 2)

McGuire SER Supplement 2, Chapter 9.5.1 and Appendix D 3)

McGuire SER Supplement 5 Chapter 9.5.1 and Appendix B 4)

McGuire Fire Protection Review, as revised 5)

McGuire Fire Protection Commitment Index.

-6)

Fire Protection System OP/1/A/6400/02A f

16.9-2

---

.-me--

.,-m,-.

-..-,-,w--

^

16.9 AUXILIARY SYSTEMS FIRE PROTECTION SYSTEMS 16.9-2 SPRAY AND/OR 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.

REMEDIAL ACTION:

With one or more of the above required Spray and/or Sprinkler a.

Systems inoperable, within I hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

TESTING PROCEDURES:

1)

PT/0/A/4400/1C Fire Protection System Monthly Test 2)

PT/0/A/4400/01K Fire Protection Annual Valve Test 3)

PT/1/A/4400/01L Fire Protection Containment Header Test i

4)

PT/0/A/4400/01A Fire Protection System Test 5)

PT/0/A/4400/01M Fire Protection System Flow

REFERENCES:

l 1)

McGuire FSAR, Chapter 9.5.1 l

l 2)

McGuire SER Supplement 2, Chapter 9.5.1 and Appendix D 3)

McGuire SER Supplement 5, Chapter 9.5.1 and Appendix B 4)

McGuire Fire Protection Review, as revised 5)

McGuire Fire Protection Commitment Index l

6)

MC-1599 1.0 through 3.0 1

I I

16.9-3

m t

Table 16.9-1 Spray and Sprinkler Systems a.

Rievation 695 f t. - Auxiliary Building Room No.

Equipment 501 RHR Pump 1A 500 RHR Pump 1B 506 RHR Pump 2A 507 RRR Pump 2B 508 Corridor b.

Elevation 716 ft. - Auxiliary Building Roon No.

Equipment 600 Aux. FW Pump Room - Unit 1 649 Nuclear Service Water Pumps 627 Centrifugal Charging Pump 1A 630 Centrifugal Charging Pump 1B 601 Aux. FW Pump Room - Unit 2 634 Centrifugal Charging Pump 2A 637 Centrifugal Charging Pump 2B 648 Cable Shaft c.

Elevation 733 ft. - Auxiliary Building Room No.

Equipment 723 Component Cooling Pumps 701 Battery Room Trench Area d.

Elevation 750 ft. - Auxiliary Building Room No.

Equipment 801 Cable Rcom - Unit 1 801C Cable Room - Unit 2 806 Component Cooling Pumps e.

Elevation 725 ft. - Reactor Building 1)

Pipe Corridor 2)

Lower Containment Ventilation Filters f.

Elevation 738 ft. - Reactor Building Annulus

16.9 AUXILIARY SYSTEMS FIRE ~ PROTECTION SYSTEMS 16.9-3 HALON SYSTEMS COMMITMENT The following Halon Systems shall be OPERABLE:

a.

Elevation 716 ft. - Auxiliary Building Room No.

Equipment 600B Turbine Driven Aux. FW Pump - Unit 1 601B Turbine Driven Aux. W Pump - Unit 2 b.

Elevation 733 ft. - Auxiliary Building Room No.

Equipment 703-704 Diesel Generators - Unit 1 714-715 Diesel Generators - Unit 2 APPLICABILITY: Whenever equipment protected by the Halon System is required to be OPERABLE.

REMEDIAL ACTION:

a.

With one or more of the above required Halon Systems inoperable, within I hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

TESTING PROCEDURES:

1)

PT/1-2/A/4400/01N Halon 1301 System Periodic Test 2)

PT/0/A/4600/16B Halon Fire Detectors Semi-Annual Test 3)

PT/1/A/4450/10B Diesel Generator Halon System Annual Test PT/2/A/4450/19 4)

PT/1/A/4450/13B Auxiliary Feedwater Pump Turbine Halon System PT/2/A/4450/20 Annual Test 5)

MP/0/A/7400/49 Halon Pressure and Weight 6)

MP/0/A/7200/13 Aux Feed Pump Halon 16.9-4

4

REFERENCES:

1)

McGuire FSAR, Chapter 9.5.1 2)

McGuire SER Supplement :2, Chapter 9.5.1 and Appendix D 3)

McGuire SER Supplement 5, Chapter 9.5.1 and Appendix B i

4)

McGuire Fire Protection Review, as revised 5)

McGuire Fire Protection Commitment Index 6)

MCM-1206.07-35 7)

MC-1599 4.0, MC-2599-4.0 8)

MCEE-120.08.07 9)

MCEE-120.16.07

10) MCEE-133-00.17 4

t 16.9-5 t.

-16.9 AUXILIARY-SYSTEMS FIRE PROTECTION SYSTEMS

-16.9-4 FIRE HOSE STATIONS i

COMMITMENT The fire hose stations shown 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:

a.

With one or more of the fire hose stations shown 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 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 operating technicians, 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 action shall be accomplished within i hour if-the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

TESTING PROCEDURES:

1)

PT/1/A/4700/42 Unit 1 Fire Hose Station Valve Operability Test 2)

PT/2/A/4700/43 Unit 2 Fire Hose Station Valve Operability Test 3)

PT/0/A/4400/02 Fire Hose Inspection 4)

PT/0/A/4400/11 Contaminated Fire Area Protettf on Equip. Ck.

5)

PT/0/A/4250/03 Fire Hose Reracking 6)

PT/0/A/4400/08 Hydrostatic Test for Fire Hose

REFERENCES:

L 1)

McGuire FSAR, Chapter 9.5.1 l

2)

McGuire SER Supplement 2, Chapter 9.5.1 and Appendix D 3)

McGuire SER Supplement 5, Chapter 9.5.1 and Appendix B l

16.9-6

4)

McGuire Fire Protection Review, as revised 5)

McGuire Fire Protection P.ommittnent Index t

n l

l l

16.9-7 1

PLANT SYSTEMS s

1. 4

_.,.h.1'-

-Table 16.9-2 f

,A" FIRE HOSE STATIONS NO.

' LOCATION-ELEVATION (FT) 157 55-FF 695

" 158 57-FF 695 175 51-LL/MM 716 L176 '

55-MM 716 x

y_

177 55-QQ 716 2

'178 58/59-MM 716

.179' 61-LL 716 180 52-CC 716

^

181 54-GG 716 182 58-GG -

716 183-59-CC/DD 716 167 51-JJ/KK 733 168 52-MM/NN 733 169.

55-NN 733 170 57-LL 733 171 54-HH 733 172 58-HH 733

^

173 60-MM/NN 733

-174 61-JJ/KK 733 887 53-DD 733 888 52-EE 733 889 51/52-DD 733 890 51-BB 733 i'

891 40-CC 733 892 43/44-DD 733 893 40-AA/BB 733 j

894 44-AA/BB 733 895 46-BB 733 896 60-EE 733 897 60-DD 733 898 61-BB 733 7_

899 66-BB 733 900 68-AA/BB 733 901 72-BB 733 902 68/69-DD 733 903 72-DD 733 904 58-CC/DD 733 913 45-AA/BB 733 914 6 6-BB 733 1184 56-JJ 733 161 50/51-MM 750 162 54/55-LL 750 h..

163 54-JJ 750 164 56-QQ 750 i

165 58-LL/MM 750 166 61-MM 750 i

302 60-KK 750

)

303 52-GG 750 McGuire - UNITS I and 2

PLANT SYSTEMS' Table 16.9-2 (continued)

FIRE HOSE STATIONS' NO.

LOCATION ELEVATION (FT) 961 45-BB 750 962 46-CC 750 963 51-BB 750 964 51-BB 750 965-51-CC 750 966-56-DD 750 967 67-BB 750 968 66-CC 750 969 61-CC 750 970 61-BB 750 971 5 8-BB 750 972 57-DD 750 1185 58-JJ 750 184 54-KK 767 185 54HMH 767 186 50/51-MM 767 191 5 6-GG 767 192 58-JJ 767 193 60-MH 767 194 61/62-MM 767 974 51-BB 767 975 61-BB 767 McGuire - UNITS 1 and 2

16.9 AUXILIARY SYSTEMS FIRE PROTECTION SYSTEMS.

16.9-5 FIRE BARRIER PENETRATIONS COMMITMENT' All fire barrier penetrations (walls, floor / ceilings, 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:

a.

With one or more of the above required fire barrier penetrations and/or_ sealing devices inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either establish a continuous fire watch on at least one side of the affected assembly, or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly and establish an hourly fire watch patrol.

TESTING PROCEDURES:

1)

PT/0/A/4250/04 Fire Barrier Inspection 2)

PT/0/A/4250/11 Fire Door Inspection 3)

PT/0/A/4400/01G Fire Door Semi-Annual Test 4)

PT/0/A/4250/04 Fire Door Test 5)

PT/0/A/4250/11 Fire Door Inspections

REFERENCES:

1)

McGuire FSAR, Chapter 9.5.1 L

2)

McGuire SER Supplement 2, Chapter 9.5.1 and Appendix D l

L 3)

McGuire SER Supplement 5, Chapter 9.5.1 and Appendix B 4)

McGuire Fire Protection Review, as revised 5).

McGuire Fire Protection Commitment Index l-L i

l 16.9-8 1

1 16.9 AUXILIARY SYSTEMS FIRE PROTECTION SYSTEMS 16.9-6 FIRE DETECTION INSTRUMENTATION 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.

RENEDIAL ACTION:

With any, but not more than one-half the total in any fire zone, a.

Function A fire detection instruments shown in Table 16.9-3 inoperable, restore the inoperable instrument (s) to OPERABLE status within 14 days or within the next I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations given in Technical Specification 4.6.1.5.1 or 4.6.1.5.2.

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 Table 16.9-3 inoperable, within i hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations given in Technical Specification 4.6.1.5.1 or 4.6.1.5.2.

TESTING PROCEDURES:

1)

PT/0/A/4600/16A, 16B Fire Detection System Operational Tests 2)

PT/0/A/4600/15 Monthly Test

REFERENCES:

1)

McGuire FSAR, Chapter 9.5.1 2)

McGuire SER Supplement 2, Chapter 9.5.1 and Appendix D 3)

McGuire SER Supplement 5, Chapter 9.5.1 and Appendix B 16.9-9

4)

McGuire Fire Protection Review, as revised 5)

McGuire Fire Protection Connaitment Index 6)

NFPA Codes 72D and 72E r

i I

l l

l I

i 16.9-10

r 3

4 TABLE 16.9-3 FIRE DETECTION INSTRUMENTATION 4

4 TOTAL NO. INSTRUMENTS

• DETECTOR HEAT ZONE DESCRIPTION LOCATION SMOKE DETECTORS FUNCTION **

g 4

1 Reactor Coolant Pump 1A RCP-1A 0

1-A 2

Reactor Coolant Pump 1B RCP-1B 0

-1 A-I 3

Reactor Coolant Pump IC RCP-1C 0

1 A

4 Reactor Coolant Pump ID RCP-1D O'

1 A'

I 5

Reactor Coolant Pump 2A RCP-2A 0

1

'A 6

Reactor Coolant Pump 2B RCP-2B O'

1 A'

f 7

Reactor Coolant Pump 2C RCP-2C 0

1 A-i 8

Reactor Coolant Pump 2D RCP-2D 0

1 A

i 29 Aux. Bldg. Vent Filter KK52-53 EL. 767 2

0 A-30 Elec. Pen. Rs.

CC-51 EL. 767 9

0 A

31 Elec. Pen. Rs.

CC-51 EL. 750 10 0

A I

32 Elec. Pen. Rm.

CC-51 EL. 733 10 0

A 33 Unit 2 Aux. Bldg. Vent. Filter KK-59/60 EL. 767 2

0 A

34 Unit 2 Elec. Penetration Room CC-61 EL. 767 9

0 A

35 Unit 2 Elec. Penetration Room CC-61 EL. 750 10 0

A 36 Unit 2 Elec. Penetration Room CC-61 EL. 733 10 0

A 37 Diesel Gen. lA CC-43 EL. 733 0(0) 8(4)

A(B) 38 Diesel Gen. 2A CC-69 EL. 733 0(0) 8(4)

.A(B) 39 Cable Room CC-55 EL. 750 6

5 A.

]

40 Control Room-CC-56 EL. 767 24-

.19 A

41 Swgr. Rs. 1 ETA AA-49 EL. 750 8

0 A

42 Swgr. Rm. 1ETB AA-49 EL. 733 10 2

A 43 SWG. Room 2 ETA AA-62 EL. 750 8

0

'A 44 SWG. Room 2ETB AA-62 EL 733 10 2

A l

45A Battery Room EVCA CC-54 EL. 733 2

2 A

45B Battery Room EVCB CC-55 EL. 733 2

2 A

l 45C Battery Room EVCC CC-56 EL. 733 2

2 A

1 45D Battery Room EVCD CC-57 EL. 733 '

2 2

A 45G Battery Chg. Equip. & Pnl.

CC-56 EL. 733 9

0 A.

I EVCA, EVCC i

T TABLE 16.9-3 (Continued)

FIRE DETECTION INSTRUMENTATION l

TOTAL NO. INSTRUMENTS

• DETECTOR HEAT i

ZONE DESCRIPTION LOCATION SMOKE DETECTORS FUNCTION **

45H Battery Chg. Equip. & Pnl.

BB-56 EL. 733 6

0

'A l

EVCB, EVCD j

50 Diesel Gen. IB BB-43 EL. 733 0(0) 8(4)

A(B) 1 51 Diesel Gen. 2B BB-69 EL. 733 0(0) 8(4)

A(B)

I 52 Unit 2 Cable Room CC-57 EL. 750 6

5 A

l 61 Cont. Spray Pump 1A/ Corridor GG-55 EL. 695 2

2 A-62 Cont. Spray Pump IB/ Corridor GG-56 EL. 695 2

2 A.

4 63 RHR Pump IB FF-54 EL. 695 1

1 A

i 64 RHR Pump 1A

-GG-54 EL. 695 1

1 A'

66 Cont. Spray Pump 2B/ Corridor GG-56 EL. 695 2

2 A

67 Cont. Spray Pump 2A/ Corridor CC-57 EL. 695 2

2 A

68 RHR Pump 2A GG-58 EL. 695 1

1 A

69 RHR Pump 2B FF-58

.EL. 695 1

1 A-70 Aux. ' F. W. Pumps BB-51

'EL. 716 10(0) 8(1)

A(B) 72 Mech. Pen. Rm / Cables JJ-51 EL. 716 4

4

.A 73 Corridor / Cables HH-53 EL. 716 5

5 A-74 Sample Panel / Cables EE-55 EL. 716 5

5 A

4 l

75 Cent. Chg. Pump 1B JJ-55 EL. 716 2

2 A

J 76 Cent. Chg. Pump 1A JJ-55 EL. 716 2

2 A

77 P D Pump #1 JJ-54 EL. 716 2

2 A'

]

78 Safety Injection Pump 1A HH-54 EL. 716 2

2-A

]

79 Safety Injection Pump IB GG-54 EL. 716 2

2 A

80 Aisle / Cables GG-55 EL. 716 12 12 A

81 Aisle / Cables GG-57 EL. 716 10 10 A-i 82 Cent. Chg. Pump 2B JJ-57 EL. 716 2

2 A

83 Cent. Chg. Pump 2A JJ-57 EL. 716 2

2 A

84 P D Pump #2 JJ-58 EL. 716 2

2 A

85 Safety Injection Pump 2A HH-58 EL. 716-2 2

A 86 Safety Injection Pump 2B GG-58 EL. 716 2

2 A

i i

4

p J'

j TABLE 16.9-3 (Continued)

FIRE DETECTION INSTRUMENTATION TOTAL NO. INSTRUMENTS

• DETECTOR HEAT ZONE DESCRIPTION LOCATION SMOKE DETECTORS FUNCTION **

87 Aux. F.W. Pumps CC-60 EL. 716 10(0) 8(1)~

A(B) 88 Mech. Penetration Room / Cables JJ-61 EL. 716 4

4 A

90 Corridor / Cables NN-59 EL. 716 5

5

-A 91 Corridor / Cables EE-53 EL. 733 4

4 A

92 Corridor / Cables JJ-51 EL. 733 6

6 A.

93 Corridor / Cables NN-52 EL. 733 11 11-A 94 Aisle / Cables JJ-55 EL. 733 8

8 A,

95 600V MCC IEMXB-1EMXB3 FF-55 EL. 733 1

1 A

96 Cable Tray Access EE-55 EL'. 733 1

1 A

97 Cable Tray Access-EE-57 EL. 733 l'

1 A-98 600V MCC 2EMXB-2EMXB3 FF-57 EL. 733 1

1

.A 99 Aisle / Cables JJ-57 EL. 733 8

8 A

100 Corridor / Cables NN-58 EL. 733 12 12 A

101 Corridor / Cables JJ-61 EL. 733 6

6 A

102 Corridor / Cables EE-59 EL. 733 4

4 A

103 Corridor / Cables MM-51 EL. 750 6

6 A

104 Hatch Area Cables LL-53 EL. 750 7

7 A'

106 600V MCC IEMXA FF-54 EL. 750 2

2 A-107 600V MCC 2EMXA FF-57 EL. 750 3

3 A

108 Aisle / Cables JJ-55 EL. 750 13 13 A

109 Hatch Area Cables PP-57 EL. 750 15 15 A

~

110 Corridor / Cables PP-60 EL. 750 8

8 A

111 Corridor / Cables LL-59 EL. 750 6

6 A

112 Aisle / Cables JJ-57 EL. 750 12 12 A

113 HVAC Equipment Area / Cables FF-56 EL 767 8

8-A 114 Respiratory Equipment Room GG-54 EL. 767 1

1 A

115 Corridor / Cables JJ-54 EL. 767 13 13 A

116 HVAC Equipment Area / Cables NN-52 EL. 767

,7

. 7.

A 120 Environmental Lab PP-55 EL. 767 1

1 A.

122 HVAC Equipment Area NN-59 EL. 767' 7

7-A:

123 Corridor / Cables JJ-57 EL. 767-13-13 A

TABLE 16.9-3 (Continued)

FIRE DETECTION INSTRUMENTATION TOTAL NO. INSTRUMENTS

• DETECTOR HEAT l

ZONE DESCRIPTION LOCATION SMOKE DETECTORS FUNCTION **

125 Fuel Pool Area NN-62 EL. 778+10 18 14 A

127 Fuel Pool Area NN-50 EL. 731+6 18 14 A

128 Aisle / Cable EE-57 EL. 716 5

5 A

129 600V MCC 2EMXH KK-56 EL. 733 1

1 A

130 Cables /K7 Pumps PP-52 EL. 750 4

4 A

131 Respiratory HH-56 EL. 757 5

5 A

134 RB Pipe Corridor - Unit 1 215* - 270*

5 0

A 135 RB Pipe Corridor - Unit 1 270* - 315*

5 0

A 136 RB Pipe Corridor - Unit 1 315' - O' 6

0 A

137 RB Pipe Corridor - Unit 1 0* - 44*

4 0

A 138 RB Pipe Corridor - Unit 1 44' - 90*

4 0

A 139 RB Pipe Corridor - Unit 1 90* - 126' 4

0 A

140 RB Pipe Corridor - Unit 1 126* - 173*

7 0

A 141 RB Below Oper. Floor - Unit 1 329' - 3t)*

7 0

A 142 RB Below Oper. Floor - Unit 1 13' - 29' 4

0 A

143 RB Below Oper. Floor - Unit 1 34* - 51*

3 0

A 144 RB Below Oper. Floor - Unit 1 51* - 124*

13 0

A 145 RB Below Oper. Floor - Unit 1 124* - 143*

3 0

A 146 RB Below Oper. Floor - Unit 1 143* - 167*

8 0

A 147 RB Below Oper. Floor - Unit 1 RCP - 1A Motor 4

1 A

148 RB Below Oper. Floor - Unit 1 RCP - IB Motor 1

1 A

l 149 RB Below Oper. Floor - Unit i RCP - IC Motor 3

1 A

150 RB Below Oper. Floor - Unit 1 RCP - ID Motor 4

1

'A 151 RB Below Oper. Floor - Unit 1 Purge Filter Bed 2

2 A

152 RB Below Oper. Floor - Unit 1 Purge Filter Bed 2

2

'A 153 RB Annulus - Unit 1 293* - 331*

10 13-B 154 RB Annulus - Unit 1 324' - 0*

4 4

B 155 RB Annulus - Unit 1 0* - 50' 5

5' B

156 RB Annulus - Unit 1 50* - 88*

4 4

B 157 RB Annulus - Unit 1 88* - 123*

24 24 B

158 RB Annulus - Unit 1 123* - 165*

22 22 B

-mJ

2 TABLE 16.9-3 (Continued)

FIRE DETECTION INSTRUMENTATION TOTAL NO. INSTRUMENTS

• HEAT DETECTOR ZONE DESCRIPTION LOCATION SMOKE DETECTORS FUNCTION **

l 159 RB Annulus - Unit 1 333* - 16*

13 13 B

160 RB Annulus - Unit 1 16* - 54*

23 23 B

}

161 RB Annulus - Unit 1 122* - 180*

16 16 E

162 RB Annulus - Unit i 180* - 256*

13 13 B'

163 Unit 2 RB Pipe Corridor 215' - 270*

5 0

A 164 Unit 2 RB Pipe Corridor 270* - 315' 5

0 A'

165 Unit 2 RB Pipe Corridor 315* - 0*

6 0

A 166 Unit 2 RB Pipe Corridor 0* - 44*

4 0

A 167 Unit 2 RB Pipe Corridor 44* - 90*

4 0

A j

168 Unit 2 RB Pipe Corridor 90* - 126' 4

0 A

169 Unit 2 RB Pipe Corridor 126* - 173*

7 0

A 170 Unit 2 RB Below Oper. Floor 329* - 347*

7 0

A l

171 Unit 2 RB Below Oper. Floor 13* - 29' 4

0 A

172 Unit 2 RB Below Oper. Floor 34' - 51*

3 0

A' 173 Unit 2 RB Below Oper. Floor 51* - 124*

13 0

A 174 Unit 2 RB Below Oper. Floor 124* - 143' 3

0 A

175 Unit 2 RB Below Oper. Floor 143* - 167*

8 0

A 176 Unit 2 RB Below Oper. Floor RCP 2A Motor 3

1 A

177 Unit 2 RB Below Oper. Floor RCP 2B Motor 2

1 A

178 Unit 2 RB Below Oper. Floor RCP 2C Motor 2

1 A

179 Unit 2 RB Below Oper. Floor RCP 2D Motor 4

1 A

180 Unit 2 RB Below Oper. Floor Purge Filter Bed 2

2 A

181 Unit 2 RB Below Oper. Floor Purge Filter Bed 2

2 A

182 Unit 2 RB Annulus 293* - 331*

10 10 B

4 l

133 Unit 2 RB Annulus 324' - 0*

4 4

B 184 Unit 2 RB Annulus 0* - 50' 5

5 B

185 Unit 2 RB Annulus 50' - 88*

4 4

B 186 Unit 2 RB Annulus 88* - 123*

24 24 B

187 Unit 2 RB Annulus 123* - 165*

22 22 B

188 Unit 2 RB Annulus 333* - 16*

13 13 B

l

TABLE 16.9-3 (Continued)

FIRE DETECTION INSTRUMENTATION 4

TOTAL NO. INSTRUMENTS

• j 1

DETECTOR HEAT j

ZONE DESCRIPTION LOCATION SMOKE DETECTORS FUNCTION **

189 Unit 2 RB Annulus 16' - 54' 23 23 B

190 Unit 2 RB Annulus 122' - 180*

16 16 B

i 191 Unit 2 RB Annulus 180* - 256*

13 13~

B 197 Mech. Pen. Rm./UHI Valves JJ-52 EL. 750 5

5 A

198 Mech. Pen. Ra./UHI Valves JJ-60 EL. 750 5

5 A

206 Control Room Control Board AA EL. 767 20 5

A i

l f

1 i

'l d

t 1

1 1

I i

• The fire detection instruments located within 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 cystem and early warning and notification.

i i

g:

-16.9 AUXILIARY SYSTEMS FIRE PROTECTION SYSTEMS 116.9-7 STANDBY SHUTDOWN SYSTEM-COMMITMENT The Standby' Shutdown System (SSS) shall be OPERABLE.

APPLICABILITY:- MODES 1, 2, and 3.

REMEDIAL ~ ACTION:

With the Standby Shutdown System inoperable for more than 7 days,

a. '

prepara and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the cause of '

the inoperability, corrective actions being taken, and plans for restoring the system to OPERABLE status; and b.

With one or more SSS components inoperable, as determined'by the performance of testing requirements of this commitment, within I hour verify the OPERABILITY of fire detection'and suppression systems (if installed) in areas as identified in Table 16.9-4 and, as appropriate, perform the actions identified in notes 3 and 4 of the table.

I c.

With the total leakage from UNIDENTIFIED LEAKAGE, IDENTIFIED

- LEAKAGE and reactor coolant pump seal leakoff greater than 26 gpa, declare the Standby Makeup Pump inoperable and take ACTIONS a. and b., abov3 d.

If equipment which constitutes inoperable component of SSS is located inside containment, then repairs shall be effected at the first outage which permits containment access.

l e.

If the diesel generator is inoperable, repairs shall be effected within 60 days, or a repot t shall he prepared within the next 14 days which:

1) details the extent of repairs required, 2) outlines the schedule for completion of those repairs, and 3) provides a l_

basis for continued operation.

TESTING PROCEDURES:

1)

PT/0/A/4200/02 Fuel Level Verification i

2)

PT/0/A/4200/02 D/G Operability Test 3)

CP/0/B/8600/27 Viscosity, Water and Sediment, Specific Gravity l

4)

CP/0/B/8600/27 Analysis by off-site lab Chem. Man. Encl. 3.5.1, p. 7 l

of 10 l.

l 1:

l 16.9-11

TESTING PROCEDURES (Cont'd) 5)

MP/0/A/7400/66 D/G Preventive Maint.

6)

IP/0/B/306{/20 Battery Voltage Verification 7)

IP/0/B/3061/20

. Battery Condition Check

-8)

PT/1-2/A/4150/01B Leakage Verification 9)

PT/1-2/A/4600/03C T.S. 3.9.10

10) CP/0/A/8100/05 Boron Concentration Chem. Man. Sect. 3.5.2

11) PT/1-2/A/4600/03C Refueling Water Storage Tank - Standby Makeup Pump Alignment Chem. Man. Sect. 3.5.2

12) PT/1-2/A/4209/01C Standby Makeup Pump Operability Test 13)

IP/0/B/3061/02 Battery Electrolyte Level 14)

IP/0/B/3061/02 Total Battery Terminal Voltage 15)

IP/0/B/3061/02 Average Specific Gravity 16)

IP/0/B/3061/07A

' Battery Condition Check

17) PT/1-2/A/4252/07 Steam Turbine Driven Aux. FW Pump Operability

18) PT/0/A/4200/02 Channel Check 19)

IP/0/B/3216/02 Foxboro 13A Flow Xmtr Calib 20)

IP/0/B/3216/04 Foxboro E13DM D/P Xmtr Calib 21)

IP/0/B/3216/06 Foxboro E71GH Xmtr Calib 22)

IP/0/B/3250/08 Hays Rep V5A It.aicator Calib 23)

IP/0/B/3252/01 SSF Steam Gen Level Calib 24)

IP/0/B/3214/02 Rosemount 1153G Xmtr Calib 25)

IP/0/B/3007/10E Incore T/C SSF Temperature Readouts 26)

IP/0/B/3007/10F Incore T/C Ref Jet Temp Deviation 27)

IP/0/B/3000/09N SSF NC Press Loop Calib 28)

IP/0/B/3000/09P SSF Pressurizer Level Calib 16.9-12

REFERENCES:

1)

McGuire FSAR, Chapter 9.5.1 2)

McGuire SEst Supplement 2, Chapter 9.5.1 3)

McGuire sed Supplement 5, Chapter 9.5.1 and Appendix B 4)

McGuire SER Supplement 6 Chapter 9.5.1 and Appendix C 5)

McGuire Fire Protection Review, as revised 6)

McGuire Fire Protection Safe Shutdown Review 7)

IEEE 308-1974, Class 1E Power Systems 8)

IEEE 450-1975, Maint. Testing & Replacement of Large Lead Storage Batteries 9)

OP/0/B/6350/04 Standby Shutdown Facility Diesel Operation 1

i I

I l-I h

I l

16.9-13

--.---....-,,--n.

-.n.-,,,,.

-.,-.- n.n _,

..-.,.,,,,,...n-

.-,_n,,

-,,.,--ne-,---,

n--,-. - -, - - - -.

l

. I 4

Table 16.9-4 STANDBY f>H11TDOWN SYSTEM COMPONENT ACTION STATE!ENTS ilth one er more of the following Verify operability II) of fire detectors and ESS components inoperable suppression systems (if installed) in'the

,y

.following areas:

EL 716 EL 733 EL 750 control Battery Cable Turbine Driven Motor Driven Containment Other.

EE-KX EE-KX EE-KK Room Room Rooms AFW Pump AFW Pump Actions L

Diesel Generator X

X X

X X

X

.X X

(2)

(3),(4)

B.

Diesel starting 24-Volt battery X

X X

X X

X X

X (2)

(3),(4).

b:nk and charger Stradby makeup pump and water supply X

X X

).

250/125 V battery bank and associated X

X X

(2)

(4) charger E.

Steam Turbine Driven Auxiliary Feedwater X

Pump Solenoid "C" F.

Izztrumentation Resctor Coolant Pressure X

X X

(2)

Pressurizer Level X

X X

(2)

Steam Generator Level X

X X

(2)

Incore Temperature X

X X

(2)

NOTES: (1) If fire detection and/or suppression systems are inoperable, then the ACTION statement (s) of the applicable fire detection.and/or suppression technical specification (s) shall be complied with.

2, (2) Honitor containment air temperature at least once per hour at the locations specified in Specification 4.6.1.5.1 or 4.6.1.5.2, in lieu of verification of operability of systems inside containment.

(3) 'With this component inoperable, verify operability of off-site power and one blackout diesel generator.

(4) With this component inoperable, then denoted areas of both units are affected.

e McGUIRE NUCLEAR STATION FINAL SAFETY ANALYSIS REPORT CHAPTER 16.13 7-SELECTED LICENSEE COMMITMENTS CONDUCT OF OPERATIONS Table of Contents 16.13-1 FIRE BRIGADE 16.13-0

-=

16.13 CONDUCT OF OPERATIONS OPERATORS 16.13-1 FIRE BRIGADE t

ColetITMENT 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 safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

APPLICABILITY: At'all times.

REMEDIAL ACTION:

With the Fire Brigade composition less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence, take immediate action to fill the required positions.

TESTING PROCEDURES: 1)

Operations Nhnagement Procedure 2-2

REFERENCES:

1)

McGuire FSAR, Chapter 13.2 2)

McGuire SER Supplement 2, Chapter 9.5.1 and Appendix D 3)

McGuire SER Supplement 5, Chapter 9.5.1 and Appendix B 4)

McGuire Fire Protection Review, as revised 5)

McGuire Fire Protection Commitment Index 16.13-1