ML20212L933

Proposed Tech Specs,Removing All Fire Protection Requirements as Recommended by Generic Ltr 86-10

ML20212L933
Person / Time
Site:	Fermi
Issue date:	03/06/1987
From:	DETROIT EDISON CO.
To:
Shared Package
ML20212L930	List: ML20212L926 ML20212L933
References
GL-86-10, NUDOCS 8703110005
Download: ML20212L933 (30)

Text

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(8) Study of Multiole Control Systen Fativres (Sejtion L7.7. 5tR) prior to startup following the first refueling estase OtCo shall

- provide the NRC staff for its review and approval, the necessary  ;

. analysis or modifications,needed to resolve the impact of' '

[ c,entrol system failures due to a failure or malfunction of power

, sources or sensors which provide power or signals to two or more control systems. ,

(g) Modifications for Fire Protect 1'on (Section g.5.1. 55tR #5 and

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fet Otto shall implement and maintain.in effect all provisions of the approved fire protection pr> gram as described in its

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Final Safety Analysis Report for the facility through Amend-ment 60 and as approved in the SER through Supplement No. 5 ,

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4) DCCo shall install and make operational, the inBependent alternate shutdown system in accordance with the schedule 4

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contained in its letter dated July 5.1945. The interim I

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INDEX

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LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SiCTION ,

PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............ 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.................. 3/4 3-9 l 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION...................................... 3/4 3-23 1 3/4.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM ACTUATION INSTRUMENTATION...................................... 3/4 3-32 l 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION......................................

3/4 3-36 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION.................... 3/4 3-41 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation................. 3/4 3-47

03 Seismic Monitoring Instrumentation................... 3/4 3-51 Meteorological Monitoring Instrumentation. . . . . . . . . . . . 3/4 3-54 Remote Shutdown System Instrumentation and Controls.. 3/4 3-57 Accident Monitoring Instrumentation.................. 3/4 3-60 Source Range, Monitors................................ 3/4 3-64 Traversi ng In-Cere Probe System. . . . . . . . . . . . . . . . . . . . . . 3/4 3-65 Chlorine Detection System............................ 3/4 3-66 F DELE.TED fir

C;t::ti:n In:trrr:.t:tien....................... 3/4 3-67

, Loose-Part Detection System.......................... 3/4 3-70 i Radioactive Liquid Effluent Monitoring Instrumentation...................................... 3/4 3-71 Radioactive Gaseous Effluent Monitoring Instrumentation...................................... 3/4 3-76 3/4.3.8 TUABINE OVERSPEED PROTECTION SYSTEM. . . . . . . . . . . . . . . . . . . 3/4 3-85 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUNENTATION....................................... 3/4 3-86 FERMI - UNIT 2 V

IhDE;'

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.6 PRIMARY CONTAIf# TENT ATMOSPHERE CONTROL Drywell and Suppression Chamber Hydrogen Recombiner Sy s tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 /4 6- 57 Drywell and Suppression Chamber Oxygen Concentration. 3/4 6-58 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System........... 3/4 7-1 ,

Emergency Equipment Cooling Water System............. 3/4 7-3 Emergency Equipment Service Water System. . . . . . . . . . . . . 3/4 7-4 Diesel Generator Cooling Water System................ 3/4 7-5 Ultimate Heat Sink................................... 3/4 7-6 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM. . . . . . . . . . . . . 3/4 7-8 3/4.7.3 SHORE BARRIER PROTECTION............................. 3/4 7-11 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM................ 3/4 7-14 3/4.7.5 SNUBBERS............................................. 3/4 7-16 3/4.7.6 SEALED SOURCE CONTAMINATION.......................... 3/4 7-22 3/4.7.7 tin: 0"??:::5I0" 0YST ".! DELETED -

Ti.e 0.ppre;;ien 'A t:r Sy:t::........................ 3/4 7-24

,s F Opr;j :nd/:r Spr'ahl:r Sy:t: :....................... 3/4 7-27 CO 0y;;;;;.......................................... 3/4 7-29 2

". 1 ;n Sy; t::: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-30

- Fir; "::: St:ti:nc................................... 3/4 7-31 4srd fir: "ydr:nt: :nd "ydre.t "ete "a"ee5............ 3/4 7-36 Cf LE TED 3/4.7.8 ,m -.. - . . ................................ 3/4 7-38 >

3/4.7.9 MAIN TUR8INE BYPASS SYSTEM........................... 3/4 7-40 l

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FERMI - UNIT 2 Vili l

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INDEX

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BASES SECTION PAGE INSTRUMENTATION (Continued)

MONITORING INSTRUMENTATION (Continued)

Meteorological Monitoring Instrumentation....... B 3/4 3-4 Remote Shutdown System Instrumentation and Controls........................................ B 3/4 3-4 Accident Monitoring Instrumentation............. B 3/4 3-4 Source Range Monitors........................... B 3/4 3-4 Traversing In-Core Probe System................. B 3/4 3-4 Chlorine Detection System....................... B 3/4 3-5 eb,r_L_ Ele n_ _ . , _ _ , _. . . .-- ^ - ' ' --

B 3/4 3-5 Loose-PartbetectionSystem..................... B 3/4 3-5 Radioactive Liquid Effluent Monitoring Instrumentation................................. B 3/4 3-5 Radioactive Gaseous Effluent Monitoring Instrumentation................................. B 3/4 3-6 l l( f 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM............. B 3/4 3-6 i 3/4.3.9 FEEDWATER/ MAIN TURa7!E TRIP SYSTEMS ACTUATIOh l INSTRUMENTATION................................. B 3/4 3-6 l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM............................ B 3/4 41

. 3/4.4.2 SAFETY / RELIEF VALVES............................ B 3/4 41 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE

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Leakage Detection Systems....................... B 3/4 4-2 Operational Leakage............................. B 3/4 4-2

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3/4.4.4 CHEMISTRY....................................... B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY............................... B 3/4 4-3 3/4.4.6 PRESSURE / TEMPERATURE LIMITS..................... B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES................ B 3/4 4-5 3/4.4.8 STRUCTURAL INTEGRITY............................ B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REM 0 VAL........................... B 3/4 4-5 FERMI - UNIT 2 xiii y- - a . . , , - - . - , - - - _ . , , - - , . - c- p, n.,,,---.--,,- .-,,, , , , - - - - - _ - - , . , , - , , , , , . _ , . , _ , _ , , , - , - . - _ , , , - , - - + , - _ - - - , . , - - _.

INDEX i SASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS........................... 8 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM........ 8 3/4 7-1 3/4.7.3 SMORE BARRIER PROTECTION........................ 8 3/4 7-1

, 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM........... 8 3/4 7-1 3/4.7.5 SNU88ERS........................................ 8 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION..................... 8 3/4 7-4 CELETcb 3/4.7.7 f!"E :;T7%00:0" SYST "0........................ 8 3/4 7-4

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bELETrn 3/4.7.8 F4AE-AATED-ASSEMBLIES. . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3/4 7-4 3/4.7.9 MAIN TUR8INE BYPASS ~ SYSTEM...................... 8 3/4 7-5 3/4.8' ELECTRICAL POWER SYSTEMS O 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and DNSITE POWER DISTRIBUTION SYSTEMS............................ 8 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES......... 8 3/4 8-3 I- 3/4.9 REFUELING OPERATIONS t

I 3/4.9.1 REACTOR MODE SWITCH............................. 8 3/4 9-1

. 3/4.9.2 INSTRUMENTATION................................. 8 3/4 9-1 3/4.9.3 CONTROL ROD P0SITION............................

8 3/4 9-1 3/4.9.4 DECAY TIME......................................

8 3/4 9-1 3/4.9.5 C00090NICATIONS.................................. 8 3/4 9-1 3/4.9.6 REFUELING PLATF0RM..............................

8 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L. . . . . . . . . . . . 8 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L. ... . . . 8 3/4 9-2 8 3/4 9-2 3/4.9.10 CONTROL R00 REM 0 VAL.............................

3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION... 8 3/4 9-2 FERMI - UNIT 2 xv

INDEX LIST OF TABLES (Continued)

. TA8LE. PAGE DELETED 3.3.7.9-1 ................. 3/4 3-68 3.3.7.11-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ................................ 3/4 3*72 4.3.7.11-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ...... 3/4 3-74 3.3.7.12-1 RADI0 ACTIVE GASE005 EFFLUENT MONITORING INSTRUMENTATION ........................ ....... 3/4 3-77 .

i 4.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ...... 3/4 3-81 l

3.3.9-1 FEEDWATER/ MAIN TUR8INE TRIP SYSTEh ACTUATION INSTRUMENTATION ................................ 3/4 3-87 3.3.9-2 FEEDWATER/ MAIN TUR8INE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS ...................... 3/4 3-88 4.3.9.1-1 FEEDWATER/ MAIN TUR8INE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS ...... 3/4 3-89 .

g 3.4.3.2-1 REACTOR COOLANT SYSTEM PRES $URE ISOLATION VALVES ......................................... 3/4 4-12

. 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE MONITORS .............................. 3/4 4-12 3.4.4-1 REACTOR COOLANT SYSTEM CNEMISTRY LIMITS ........ 3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANA LYS I S P ROG RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 /4 4-18 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--

WITHDRAWAL SCHEDULE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-22 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES ........... 3/4 6-22 3.6.5.2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS .................... 3/4 6-53 3.7.3-1 SURVEY POINTS FOR SHORE 8ARRIER ................ 3/4 7-12 DELETE D 3.7.7.5-1 PfAEMNHHHR*T49NS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7- 32 DELETED 3.7.7.6-1 l

H95E-H996ES .................................... 3/4 7-37

! 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE ................. 3/4 8-8

FERMI - UNIT 2 xxiv

q INSTRUMENTATION

' 3l4. 3. 7.9 DELETED LfMITING CONDITION FOR OPERATION j 3.3.7. As a minimum, the fire detection instrumentation for each fire -

detecti zone shown in Table 3.3.7.9-1 shall be OPERABLE.

APPLICABI TY: Whenever equipment protected by the fire detection in rument is require to be OPERABLE.

ACTION:

With number of OPERABLE fire detection instrumen in one or more l' a .-

zones:

1. Less han, but more than one-half of, the T al Number of Instr nts shown in Table 3.3.7.9-1 for F nction A, restore the inopera e Function A instrument (s) to O RABLE status within 14 days o within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a re watch patrol to inspect the zone (s with the inoperable instr nt(s) at least once per hour, unless the instrument (s) is 1 ated inside the containment, then inspect at containment zon 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 con inment air temp rature at least once per hour at the locations isted in ,Spe fication 4.6.1.7.

I 2. One less than the tal N r of Instruments shown in Table 3.3.7.9-1 for ncti B, or one-half or less of the Total n sa T ei 2 3.7 s-1 <ar r octi # a.

O a 6er or 1 tr #t-or with any two or mor djacent instruments 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 fi wa h patrol to inspect the zone (s) with the inoperable inst ent( at least once per hour, unless the instrument (s) is cated ins e the containment, then inspect that containment zone t least onc r 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the con-tainment air t erature at lea once per hour at the locations

listed in Sp ification 4.6.1.7.

b. The provisions Specifications 3.0.3 a 3.0.4 are not applicable.

. SURVEILLANCE REQUIREM S 4.3.7.9.1 Each the above required fire detection instr nts which are accessible dur g unit operation shall be demonstrated OPE LE at least once per 6 months y performance of a CHANNEL FUNCTIONAL TEST. Fi detectors which are not acc sible during unit operation shall be demonstrated PERABLE by the performan of a CHANNEL FUNCTIONAL TEST during each COLD SHUTD0 exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

4.3.7 9.2 The NFPA Standard 72D supervised circuits supervision asso iated f wit the detector alarms of each of the above required fire detection struments sh I be demonstrated OPERABLE at least once per 6 months.

4.3.7.9.3 The non-supervised circuits associated with detector alarms bet en the instruments and the control room shall be demonstrated OPERABLE at least once per 31 days.

FERMI - UNIT 2 3/4 3-67

::L . - . -- - -- - . . _.. -- . _ - - . - . - . - . . . _ - _.____

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TABLE 3.3.7.9-1 DELE.TED N FIRE DETECTION TOTAL NUNBER OF INSTRUMENTS

• IA6TRUMENT LOCATION ZONE IONIZATION PHOTOELECTRIC FIXED THERMAL INF8 RED (x/y) (x/y) (x/y) (x/y)

a. \Retor Buildinaf

1. T s Area 1 8/0

2. NW rner Rooms, 2 4/0 .

RHR P

3. SW Cor Rooms, RHR Pump 3 ,

4/0

4. SE Corner s, CR0 HPCI 4 9/0

5. NE Corner Room RCIC 5 5/0 l 6. First Floor 7- 20/0 8/0

7. EECW System Area Second Floor 10 21/0

8. Third Floor 15 15/0 -

9. Fourth Floor 17 8/0 2/0 t"

10. Refueling Area, Fifth Floor 17 10/0

b. Auxiliary Buildino

-1. Basement, N Control Air -

Equipment 4 6/

2. Corridors, 562',

563' 5 2/0 /0

3. First Floor l Mezzanine, Cable l Trays, 583' , 603' 6 17/0 *

4. Switchgear Room, Corridor Area 9 9/0 Second Floor

5. Cable Tunnel 9 10/0

6. Cable Tray Area Second Floor Mezzanine 9A 0/22

1. DC/NCC R

. Third Flo 14 0/10

8. Switc r, Batte and M-G ooms.

T rd Floor 14 14/0

9. urth Floor 16 6/0

10. Fifth Floor 16 25/0 FERMI - UNIT 2 3/4 3-68 7, n,-,--n-,---,--,.w ,.--,nn-,..- ,,. w,,,,,,.,-,,-nn _..,--...,..,,,,r~w-.-n,-,-~.,,.----,_.----n,,.- - - - , , - - - - , - , - , - - - - -

. .~ . . . ... .-. . - .

e TABLE 3.3.7.9-1 (Continued)

T: d 0 T CT:0" I'::T E = T:0" FIRE

\

INSTRUMENT LOCATION DETECTION 20NE IONIZATION TOTAL NUISER OF INSTRUMENTS

• PHOT 0 ELECTRIC FIXED THERMAL INFJtAREC

[

(x/y) (x/y) (x/y) x/y)

c. Cent 1 Center .

1. Re y Roos 8 0/27

2. Cab Spreading Room 11 0/28

3. Contro Room li 50/0 4/0 2/

4. Computer oon 13 0/13

5. Computer 13 5/0 2/0 above Drop .

ceiling

d. RHR Complex I

1. Division I Pump Room 0 8/0 0 2-_

3.

ai i i Pump Roon 51 8/0 EQG 11 Room Suppression 0/8

4. EDG 12 Room Suppression 0/8

5. EDG 13 Room Suppression 0/8

6. EDG 14 Room Suppression 0/8

7. EDG 11 .

Switchgear Roos 52 6/0

. 8. EDG 12 A Switchgear Roon 53 6/0

9. EDG 13 Switchgear Room 6/0

10. EDG 14 -

Switchgear Roon 55 6/0

e. General Service Wa r Pump House

1. First Floor 31 2/0 3/0 i

• (x/y): x is ueber of Function A (early warning fire detection a notification only) i truments.

y s number of Function B (actuation of fire suppression sys es and early warning and notification.) instruments.

1. The f re detection instruments located within the containment are not re fred to be ERA 8LE during the performance of Type A Containment Leakage Rate Test FERMI - UNIT 2 3/4 3-69 4

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PLANT SYSTEMS i 3/4.7.7 FIRE SUPPRESSION SYSTEMS

7

:: =77:c;;;= .it,7;; 37372e; 3/4.'7.'7.1 DELE TED Lb!TINGCONDITIONFOROPERATION f

, 3.7. 1 The fire suppression water system shall be OPERABLE with;

a. Two fire suppression pumps, each with a capacity of 2500 g , with heir discharge aligned to the fire suppression header, Th general service water intake structure water leve ) 558 feet, b.

and

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c. An OPE BLE flow path capable of taking suction f om the general '

service ter intake structure and transferrin he water through i

distribut n piping with OPERA 8LE sectionaltz g control or I isolation v ves to the yard hydrant curb v es, the last valve ahead of the ater flow alare device on es sprinkler or hose standpipe and a last valve ahead of th spray system required to be OPERABLE per ecifications 3.7.7.2, .7.7.5, and 3.7.7.6.

APPLICABILITY: At all times.

ACTION:

a. With one pump inoperable, res re the inoperable pump to OPERABLE status within 7 days or pr ., de an alternate backup pump. The provisions of Specificatto 3.0.3 and 3.0.4 are not applicable.

1

b. With the fire suppressi n wate system otherwise inoperable, establish a backup fi suppress n water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

, ~

SURVEILLANCE REQUIREMENTS , , 4.7.7.1.1 The fire s pression water system shall demonstrated OPERABLE:

a. At least nee per 7 days by verifying the mi mum water supply I level.

l b. At ast once per 31 days by starting the electr motor-driven nutes on fire i s pression pump and operating it for at least 15 ecirculation flow.

At least once per 31 days by verifying that each valve anual, c.

power-operated, or automatic) in the flow path is in its orrect position.

l FERMI - UNIT 2 3/4 7-24

_ . . _ . . . _ _ . . . _ _ , . . - _ . _ _ _ _ _ _ _ _ _ _ . . , . _ _ . - _ , - , , . . _ , , , . _ . _ _ . , , , , _ , , , _ . _ _ _ . - _ _ _ _ _ _ , . _ _ _ _ . - - _ , . , _ ___,_m,.-..

f PLANT SYSTEMS

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a SbtVEILLANCEREQUIREMENTS(Continued)

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d. At least once per 12 months by performance of a system flush.

e. t least once per 12 months by cycling each testable valve the ow path through at least one complete cycle of full trav .

f. At ast once per 18 months by performing a system func onal test i

~

which includes simulated automatic actuation of the sy tem throughout '

its op ating sequence, and:

1. Veri ing that each fire pump develops a dis arge of 150% of rated a acity at 65% of rated pressure (37 1 10% gpm at 104 i 1 psig), and recording measured p formance at minimum and rate loads.

2. Cycling eac valve in the flow path t t is not testable during plant operat n through at least one emplete cycle of full travel, and <

3. Verifying that ea fire suppres on pump starts sequentially to maintain the fi suppressi water system pressure greater i than or equal to 10 sig.

g. At least once per 3 years b e orming a flow test of the system in accordance with Chapter 8, Se on 16 of the Fire Protection Handbook, 15th Edition, publ d by the National Fire Protection i

l Association. .

4.7.7.1.2 The diesel-driven fire pression ump shall be demonstrated OPERABLE:

a. At least once per 31 ays by:

- 1. Verifying th fuel storage tank conta ns at least 150 gallons l

of fuel.

I

2. Startin the diesel driven pump from ambie t conditions and operat g for greater than or equal to 30 m utes on .

recir ulation flow.

I

b. At less once per 92 days by verifying that a sample f diesel fuel  ;

from e fuel storage tank, obtained in accordance wit ASTM-D270-65 (rea roved 1980), is within the acceptable limits spec ied in l

I Ta e 1 of ASTM-D975-77 when checked for viscosity, wate and sediment.

c. least once per 18 months, during shutdown, by subjecting he diesel to an inspection in accordance with procedures prepare ins of conjunction with its manufacturer's recommendations for the cl service.

FERMI - UNIT 2 3/4 7-25

. = - _

_ - - . - ~ - . .- . .

PLANT SYSTEMS

, SDRVEILLANCEREQUIREMENTS(Continued) ,-

4.7.7.1.3 T diesel-driven fire pump starting 24-volt battery ba and

, charger shall be nstrated OPERABLE:

a. At least onc er 7 days by ve-ifying that:

1. The electroly level of each batt is above the plates,

2. The battery speci ravity, rected to 77'F, is greater than or equal to 1.20

3. The battery voltage i re r than or equal to 24 volts, and

b. At least once per 18 nths by verify that: .

1. The batt and battery racks show no v ual indication of physi damage or abnormal deterioration, nd i 2. attery-to-battery and terminal conr.ections are - an, tight, free of corrosion and coated with anticorrosion mat al.

O 4

9 FERMI - UNIT 2 3/4 7-26

. . . - . -------.,-,--,,,-.,.,.--,.,,,,,_,en_,,---ee , - . - - , - --,_-,---.--.--..--g- ,. , , ,

,n-------,, n. , ~ ~ , . .,- - ,,y ~ - , - -

s PLANT SYSTEMS 0""JJ ""/0" 5""I. W LE" SMTEM, 3 N.O.2 bELE.%D blMITING CONDITION FOR OPERATION /

3.7. 2 The following spray and sprinkler systems shall be OPERABLE:

AR ELEVATION TYPE

a. hactorBuilding

1. Torus Room 560' Wet P' e Sprinkler

2. ement NE Corner Room 540' We ipe Sprinkler

3. HPC Turbine and Pump Room 540' t Pipe Sprinkler

4. First loor, Railroad Bay 583' Wet Pipe Sprinkler

5. Second F or, Cable Trays 613' Wet Pipe Sprinkler

6. Fourth Floo , MG Sets 641'6" Wet Pipe Sprinkler

b. Auxiliary Buildin

1. Basement 551' nd 562' Wet Pipe Sprinkler

2. Mezzanine and Cabl Tray 58 - 603' Wet Pipe Sprinkler Area

3. Ventilation Equipment 677' Manual Flooding System sao's" a mu i sPrie'ier O 4-5.

c bi sPre ei a eem Corridor a

62' Wet Pipe Sprinkler

c. RHR Complex

1. Fuel Oil Storage ank Rooms - Wet Pipe Sprinkler (4)

d. General Service ter Pumphouse

1. Diesel Fir Pump Room

- Wet Pipe Sprinkler APPLICABILITY: Whene r equipment protected by the spra and/or sprinkler systems is required o be OPERABLE.

ACTION:

a. Wit one or more of the above required spray and/or sp inkler systems i perable, 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 wa ch with ckup fire suppression equipment for those areas in whic redundant systems or components could be damaged; for other areas, es blish an hourly fire watch patrol.

The provisions of Specifications 3.0.3 and 3.0.4 are not applica le.

(

FERMI - UNIT 2 3/4 7-27

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 7.2 Each of the above required spray and sprinkler systems shall demo ated OPERABLE:

a. At once per 31 days by verifying that each ve (manual, power-ope d, or automatic) in the flow pat s in its correct position.

b. At least once per 12 mon by cy g each testable valve in the flow path through at least o splete cycle of full travel.

c. At least once per 18 s by perform a system functional test which includes sim ed autematic actuatio each system, except -

the ventilatio om manual flooding system, by ing the inspectors test valve verifying the water flow alarm annunci .

d. At st once per 18 months by a visual inspection of the sprin er ader to verify its integrity.

O FERMI - UNIT 2 3/4 7-28 l

h PLANT SYSTEMS eey-systens- 2 N .'1.1.3 OELETED k!MITING CONDITION FOR OPERATION p 3.7. 3 The following low pressure C0 systems shall be OPERABLE:

2

a. Emergency diesel generators, RHR complex.

b. Standby gas treatment system charcoal filters, Auxiliary 8 1 ding, levation 677'6".

c. Ca e tray area, Auxiliary Building, elevation 631'.

d. Outs Division II switchgear room, Auxiliary Build g, elevation l

643'6'.

APPLICABILITY: Whe ver equipment protected by the CO 2 s tems is required to be OPERABLE. .

ACTION:

i a. With one or more of the above required C systems inoperable, 2

! within I hour est lish a continuous f e watch with backup fire

! suppression equipse t for those areas n which redundant systems or components could be ged; for et r areas, establish an hourly fire watch patrol.

b. The provisions of Specif ation 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS , s i

l l 4.7.7.3.1 Each of the above re ired C0 sy ens shall be demonstrated OP,ERABLE at least once per 31 aysbyvefifyi that each valve (manual, power operated, or automatic) in t flow path is in s correct position.

4.7.7.3.2 Each of the e required low pressure systems shall be l 2

- demonstrated OPERABLE:

a. At least on per 7 days by verifying the C0 storage tank level to be greate than 50% full for systems a and b ove and greater than 40% full or systems c and d above, and pressur to be greater than 250 ps but less than 330 psig for all of the s tems.

b. At I st once per 18 months by verifying: l

1. The system, including associated ventilation sys m fire dampers and fire door release mechanisms, actuates, manua and/or  !

automatically, upon receipt of a simulated actuatio signal, and

2. Flow from each nozzle during a " Puff Test."

FERMI - UNIT 2 3/,4 7-29 ,

_-.ym-.. .--.-- ---, ,,..-_--, , - - - ,___,_-g,nwm _ _ _r %e,c , . , . . . - . _ - . _ _ _ _ _ _ . _ _ _

- . - . . . . - - . .. .. ... . . . - . _ - - - . _ - - - _ - ~.-- -

PLANT SYSTEMS N .3 hl. 77.4 bELE TEb M MITING CONDITION FOR OPERATION ,

, 3.7. 4 The following Halon systems shall be OPERABLE with the storage t ks of ett r the main bank or the reserve bank having at least 95% of the in

'; bank or he reserve bank full charge weight and 90% of the main bank the reserve b k full charge pressure:

a. Ra. room, elevation 613'6".

b. Cable reading room, elevation 630'6".

c. Computer om, and under floor, elevation 655'6" APPLICABILITY

Wheneve equipment protected by the Ha n systems is required -

to be OPERABLE.

i ACTION: ,

, a. With one or more of t above requir Halon systems inoperable, i

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish continuo fire watch with backup fire

! suppression equipment for hose eas in which redundant systems or

- ccaponents could be damage fo otner areas, estaolish an hourly fire watch patrol.

b. The provisions of Specific tons .0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

, +

4.7.7.4 Each of the above quired Halon systems s 11 be demonstrated OPERA 8LE: -

a. At least one per 31 days by verifying that ea valve (manual, power-opera d, or automatic) in the flow path in its correct position.

b. At leas once per 6 months by verifying Halon storag tank weight

• and p ssure.

c. At east once per 18 months by:

. Verifying the system, including associated ventilatio system fire dampers and fire door release mechanisms, actuates, manually and automatically, upon receipt of a simulated actuation gnal, and

2. Performance of a puff test through all headers and nozzles to assure no blackage. [

FERMI - UNIT 2 3/4 7-30

~.

PLANT SYSTEMS IIEC Z E STATIO"5 .3N. '7.~7.5 DE.LE.TED L ITING CONDITION FOR OPERATION  ;

t 3.7. 5 The fire hose stations shown in Table 3.7.7.5-1 shall be OPERABL .

APPLICA LITY: Whenever equipment in the areas protected by the fire ose stations required to be OPERABLE.

ACTION

. 4. With e or more of the fire hose stations shown in T le 3.7.7.5-1 inopera le, provide gated wye (s) on the nearest OPE BLE hose sta-4 tion (s). One outlet of the wye shall be connecte o the standard length of se provided for the hose station. T second outlet of the wye shall b connected to a length of hose suff cient to provide cover-age for the a a left unprotected by the inopt able hose station.

Where it can b demonstrated that the physic routing of the fire hose would result in recognizable hazard to o rating technicians, plant equipment, the hoste itself, the re hose shall be stored in a roll at the ou et of the OPERABLE ose station. Signs shall be mounted above the ted wye (s) to i ntify the proper hose to i

use. The above ACTION hall be acc ished 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 e primary ans of fire suppression; otherwise route the addit n&l hos within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l

b. The provisions of Specificat n 3.0.3 and 3.0.4 are not applicable.

I l SURVEILLANCE REQUIREMENTS - ,

• 4.7.7.5 Each of the fire hose st ions shown Table 3.7.7.5-1 shall be demonstrated OPERABLE:

l

a. At least once per 3 days by a visual ins ection of the fire hose

- stations accessibl during plant operation o assure all required equipment is at e station.

! b. At least once r 18 months by:

1. Visual spection of the fire hose stations ot accessible during plant peration to assure all required equip nt is at the station.

Rem ing the hose for inspection and re-rackin and 2.

3. I pecting all gaskets and replacing any degrade askets in he couplings.

c. At east once per 3 years by:

e

! . Partially opening each hose station valve to verify va OPERABILITY and no flow blockage.

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

I FERMI - UNIT 2 3/4 7-31 i

l i

.----..-.,-._-_-.--------v,------ - - - - . . . _ _ _ . _ _ _ . . __ _ - -.. --. _______ --

TABLE 3.7.7.5-1 LELETEh IIRC =[ CC bCATION ELEVATION HOSE RAC

a. Reactor Building

. Fire hose at top of stairway in northwest aux building 736' R 1

2. ire hose at northwest corner b elevator - 684'-6" RB-2

3. Fire ose at southwest corner 684'-6" RB-3

4. Fire ho e at northeast stairway 684' "

RB-4

5. Fire hose n sdutheast walkway 6 '-6" RB-5

6. Fire hose at orthwest corner outside elevat r 659'-6" RB-6

7. Fire hose at nor east corner in stairway 659'-6" RB-7

8. Fire hose at southwes corn (h at stairway 659'-6" RB-8

9. Fire hose at southeast ner at stairway 659'-6" RB-9

10. Fire hose at northe t corner at stairway '641'-6" RB-10

11. Fire hose at nor hwest corner at stairway by levator 641'-6" RB-11

12. Fire hose a southwest corner l at stairwa 64 '-6" RB-12 l .

13. Fire ho at southeast corner at sta ay 641'-6 RB-13

14. Fir hose at northwest corner ne elevator 613'-6" RB-14

15. ire hose at southwest corner at bottom of stairway 613'-6" RB 5

. Fire hose near drywell instrument

' monitoring rack (east walkway) 613'-6" RB-16 t

l

FERMI - UNIT 2 3/4 7-32

=-n , . .-- - ,-..---m , - - - - - - - , . - - , - - , , , . , , . , - - - -. , , - - . - - - , - . _ ,- ,

s TABLE 3.7.7.5-1 (Continued)

LELFTEb 7::: O~; " TAT:^o3

~

ELEVATION HOSE RACF4 LdBATION

7. Fire hose in the northeast corner 613'-6" RB-17

18. Fire hose at southeast corner RB B by aux b1dg access 613'-6"

19. F e hose at northwest corner ne elevator 583'-6" RB-19

20. Fire se at northeast corner 583'-6" RB-20 near s irway

21. Fire hose t railroad bay 583' 6" RB-21

22. Fire hose at southeast corner 83'-6" RB-22 near stairway

23. Fire-hose at ent ance to containment (sout est) 583'-6" RB-23 0 24. Fire hose at northwe t corner near elevator 562'-0" RB-24

25. Fire hose at northeast c r r 562'-0" RB-25 4

near stairway

26. Fire hose at southwest orne 562'-0" RB-26 near stairway l: 27. Fire hose at south st corner 562'-0" RB-27 o

near stairway 9

28. Fire hose at n thwest corner O'-0" RB-28 near stairway

29. Fire hose northeast corner "

l near stai ay 540' RB-29 j

30. Fire ho e at southwest corner 540'-0" RB-30 near airway

31. Fir hose at southeast corner 540'-0" -31 n r stairway

32. ire hose in HPCI toom 540'-0" RB- 2

3. Fire hose in CRD pump room 562'-0" RB-33 l

FERMI - UNIT 2 3/4 7-33

. . _ , . . . ._ . _ . . , . , m. _ . _ _. _ , _ _ . . . . , _ . . , . . . . _ . . . . , . _ , ,

_ . , . . . . . _ ,,m.,_.,-,_.,_.,m.. ._._._.,-,__,,-._r, ,._.._,,7-,

___m . . . . . . . _ . - _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ - - .__ .__

.b TABLE 3.7.7.5-1 (Continued) ,

DELETEb f!"E "^5E ST^T""!

40 CATION ELEVATION OSE RACIW

b. Auxiliary Building

1. Fire hose at southwest corner in -

control center air conditioning equipment room 677'-6" -1

2. re hose at northwest corner in v tilation equipment area 677'-6" AB-2

3. Fire ose at southwest wall in -

venti tion equipment area 677' A8-3

~

4. Fire hos at north side in ventilatio equipment area 9'-6" A8-4

5. Fire hose at outh side in ventilation eq ipment area 659'-6" AB-5

6. Fire hose outside control room near center stairw 643'-6" AB-6 g

7. Fire hose outside cab e spr ding room in stairway from nt ol room 630'-6" A8-7

8. Fire hose south wall ca tray room near stai,rway 630'-6" AB-8

9. Fire hose near col line H- $13'-6" A8-9 l' 10. Fire hose in wal ay from reacto building 613'-6" AB-10

11. Fire hose in tairway from relay room to lo cable tray area 3'-6" AB-11 l

12. Fire hos at southeast corner by *

R8CCW h t exchanger 583' " AB-12

13. Fire ose at column G, 14 R8CCW pum area 583'-6" AB-13

14. F e hose near compressor receiver or Division II 551'-0" A -14 15 Fire hose near compressor receiver for Division I 551'-0" AB-15 i

j FERMI - UNIT 2 3/4 7-34

3. r TABLE 3.7.7.5-1 (Continued)

DELETED N LdL4 TION ELEVATION H0SE RACMS

c. idual Heat Removal (RHR) Complex

1. e hose at top of stairway to RHR switchgear room 617'-0" RR-1

2. Fire hos at top of stairway to RHR-2 swit ear room 6 '-0" RR-2

3. Fire hose in R -1 near diesel generator service ater pump 590'-0" RR-3

4. Fire hose in RHR-2 ne di 1 generator service water 590'-0" RR-4

5. Fire hose in RHR-1 r dies generator #12 590'-0" RR-5

6. Fire hose in -2 near diesel generator # O'-0" RR-6 V 7. Fire h e in RHR-1 near diesel gene tor #11 590'-0' RR-7

8. re hose in RHR-2 near diesel generator #14 590'-0" R l

2, e

e FERMI - UNIT 2 3/4 7-35

. . .- ._. --._._.._ -_ - --_- _ - _ , , _ _ - - . . . . - - ~

PLANT SYSTEMS YA00 T! 0 ;;YOCA!T; A%0 ;;YORA%T l00: ;;00000 .3 /4 ,7,7. (, D Et.ETE D LV ITING CONDITION FOR OPERATION -

~

3.7. . The y'ard fire hydrants and associated hydrant hose houses sho n in Table 7.7.6-1 shall be OPERABLE.

APPLICABIL Y: Whenever equipment in the areas protected by the rd fire hydrants is quired to be OPERABLE.

ACTION:

a. With one r more of the yard fire hydrants or ass ciated hydrant hose houses sho in Table 3.7.7.6-1 inoperable, wit n 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> have sufficient a itional lengths of 2 1/2 inch di eter hose located in

• anadjacent0 RABLE hydrant hose house to pr vide service to the unprotected are s) if the inoperable fire drant or associated hydrant hose hous is the primary means of fire suppression; otherwise provide t e additional hose wi in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. The provisions of Spec ications 3.0. and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS ~ z 4.7.7.6 Each of the yard fire hydrant and ssociated hydrant hose houses shown in Table 3.7.7.6-1 shall be demonstra d OPE LE:

a. At least once per 31 days by visual in ection of the hydrant hose house to assure all req red equipment i at the hose house.

b. At least once per 6 nths, during March, A 11 or May and during

• September, October November, by visually i cpecting each yard fire hydrant and verif ng that the hydrant barrel dry and that the hydrant is not d ged.

c. At least once er 12 months by:

1. Condu ing a hose hydrostatic test at a pressure o 150 psig or at 1 st 50 psig above the maximum fire main operat pressure, whi ever is greater. ,

2. eplacement of all degraded gaskets in couplings.

3. Performing a flow check of each hydrant.

FERMI - UNIT 2 3/4 7-36

s TABLE 3.7.7.6-1 -

bELETED O FI E "YOS"'"5 ^"O ".5500!^TEC "Y02".i ;iO2 WJusEs EtHADON HYDRA

a. Between HR complex and the 9 Reactor Buil

b. Southwest of the Re ng 10

c. Southwe the Reactor Building 1 d outheast of the Reactor Building 12 F

I .

t l

I I

FERMI - UNIT 2 3/4 7-37 l

PLANT SYSTEMS 3/4.7.8 H4HET46-466EMDbHi6 .BE.L FTE.h h!MITING CONDITION FOR OPERATION '

3.7. All fire rated assemblies, including walls, floor / ceilings, cable t y enclos es and other fire barriers, separating safety related fire areas e separat portions of redundant systems important to safe shutdown wi n a fire ar and all sealing devices in fire rated assembly penetrati s including f doors, fire dampers, cable, piping and ventilation d t penetration s is and ventilation seals, shall be OPERABLE.

APPLICABILITY: A all times.

ACTION:

~

a. With one or no of.the above required fire r ed essemblies and/or sealing devices operable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> e ablish a continuous fire watch on at st one side of the aff ted assembly (s) and/or sealing device (s) o erify the OPERABIL Y of fire detectors on at least one side of the noperable assem y(s) and sealing device (s) and establish an hourly ire watch p ol.

b. The provisions of Specifica ons .3 and 3.0.4 are not appli, cable.

f SURVEILLANCE REQUIREMENTS ,

! 4.7.8.1 Each of the above require fire rated semblies and penetration sealing devices shall be verifie PERABLE at lea once per 18 months by performing a visual inspection  :

l a. The exposed surfa s of each fire rated.asse ly.

p b. Each fire damp and associated hardware.

c. At least 1 of each type of sealed penetration. I pparent changes l

in appear ce or abnormal degradations are found, a v ual inspection i

of an a itional 10% of each type of sealed penetration hall be made.

This spection process shall continue until a 10% sample ith no

- app ent changes in appearance or abnormal degradation is nd.

S les shall be selected such that each penetration seal wi be

[

spected at least once per 15 years.

l i

l i

I FERMI - UNIT 2 3/4 7-38

( PLANT SYSTEMS A

' , s

'50RVE!LLANCE REQUIREMENTS (Continued) 3 ed 0PERABLE by 4.7.8.2 fach Bf4he above required fire doors shall be ve chanism and latches inspcting the aut' ic hold-open, release and clost at least once per 6 mon and by verifying:

a. The OPERABILITY of the ite supervision system for each electrically supervised f or by performing a CHANNEL FUNCTIONAL TEST at least once p days.

each locked-closed fire r at least once per 7 days,

b. The positio ach unlocked fire door without electrical s rvision is

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

(O(

e i

/

FERMI - UNIT 2 3/4 7-39

INSTRUMENTATION 8ASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.8 CHLORINE DETECTION SYSTEM The OPERABILITY of the chlorine detection system ensures that an accidental chlorine release will be detected promptly and the necessary protective actions will be automatically initiated to provide protection for control room personnel.

Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically be placed in the chlorine mode of opera-tion to provide the required protection. The detection system required by this specification is consistent with the recommendations of Regulatory Guide 1.95 " Protection of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release", Revision 1 January, 1977.

3/4.3.7.9 6 DELETED

____....._m m mm_ m ._____. .,__ __m_. m... m___._

var capability is available for prompt detection of fires and that f i uppress systems, that are actuated by fire detectors, will dist e atinguishin ent in a timely manner. Prompt detection and s ess on of ires will reduce potential for damage to safety-relat quiprneit and is a n integral element e overall facility fire prot on program.

Fire detectors that are d to actuate f suppression systems represen1 a more critically important compo of nt's fire protection program thar l detectors that are installed solely arly fire warning and notification.

I onsequently, the minimum number PERA ire detectors must be greater.

The loss of detectic pability for fire su ssion systens, actuated s by fire detectors, r ents a significant degradat f fire protection for:

ony area. As a t, the establishment of a fire watch rol must be nitiated a earlier stage than would be warranted for the of detector hat pr e only early fire warning. The establishment of frequen re l '8 I the affected areas is required to provide detection capabilit

,,m_ _

3/4.3.7.10 LOOSE-PART DETECTION SYSTEM .

The OPERABILITY of the loose part detection system ensures that sufficient capability is'available to detect loose metallic parts in the primary system I and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

3/4.3.7.11 RADICACTIVE L10010 EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM 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 Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

FERMI - UNIT 2 8 3/4 3-5

)

l PLANT SYSTEMS .

BASES 3/4.7.6 SEALE0 SOURCE CONTAMINATICN ,

The limitations on removable contamination for sources requiring leak l

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 l

j 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 those which are not. Sealed sources which are  ;

continuously enclosed within a shielded mechanism, i.e., sealed sources within radiation monitoring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

• 3/4.7.7 T "' "O . ^ ~ ~ ~ ' 0^; ^,7 ~ ~ ~C bELETCh ou ession capability is available to confine and extinguish fires occurri he r n an ortion of the facility where safety-related equipment is located ire sup sion system consists of the water system, spray and/or sp klers l stems, Halon systems, and fire hose stations. The lective l ystems, CO2

~

fire suppression systems is adequate to mini e potential capability of t e facility fire ted equipment and is a major element i damage to safety-r protection program. h  !

In the event that port s of the fire suppr on systems are inoperable, l red to be made available in

a lternate backup fire fighting uipment is re '

J uhe affected areas until the inope le equ nt is re:tored to service. When she inoperable fire fighting equipmen ntended for use as a backup means l of fire suppression, a longer period is allowed to provide an alternate l eans of fire fighting than if th noperab equipment is the primary means ,

i ,

c of fire suppression. l I

The surveillance r rements provide assurance at the minimum

? OPERASILITY requir s of the fire suppression systems e met. An allowance l l storage tanks

! s made for ensu g a sufficient volume of Halon in the Ha by verifying weight and pressure of the tanks.

\

I e event the fire suppression water system becomes inoperable, ate corrective measures must be taken since this system providescthe or

'..; _;;- n :' :-- d t, ;' .: ;' .-t.

i l

j 3/4.7.8 T:" ^^'00 " "."'::' . DELETEb

,__ - ._.. ___ . ~

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, 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONS18!LITY 6.1.1 The Assistant Manager-Nuclear Production shall be responsible for overall e.

unit operation and shall delegate in writing the succession to this responsibility during his absence.

' 6.1.2 The Nuclear Shift Supervisor or, during his absence from the control roce, a designated individual shall be responsible.for the control room ,

command function. A management directive to this effect, signed by the Vice President-Nuclear Operations shall be reissued to all station personnel on an i annual basis, i I 6.2 ORGANIZATION 4 0FFSITE 6.2.1 The offsite organization for unit management and technical support i

shall be as shown on Figure'6.2.1-1.

! J j UNIT STAFF ,

i 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and: j

a. Each en duty shift shall be cc m osed of at least the minimum shift

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crew risposition shown in Table 6.2.2-1;

b. At least one licensed Operator shall be in the control room when fuel is ir, the reactor. In addition, while the unit is in OPERATIOML CNITION 1, 2 or 3, at least one licensed Senior

- Operator s ull be in the control room;

! c. A Health Physics Technician / shall be on site when fuel is in the j

I reactor: s

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! v d. All CORE ALTERATIONS shall be observed and directly supervised by

' either a licensed Senior Operator or licensed Senior Operator .

J l ,I Limited to Fuel Handling who has no other concurrent responsibilities during this operation; y l m___ __,_..,__2

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= :n. ,_ :/, ::d DELETEb .

NThe Health Physics Technician : f M r bM :f: composition may be 7ess 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, provided immediate action is taken to fill ,

the required positions. ,

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FERMI - UNIT 2 6-1 i

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ADMINISTRATIVE CONTROLS ,

RESPONSIBILITI'ES(C$ tin $ed)

k. Review of any accidental, unplanned or uncontrolled radioactive release including the preparation and forwarding of reports covering evaluation, c recommendstions ar.d disposition of the corrective action to prevent recurrence'to the Vice President-Nuclear Operations and to the Nuclear safety Review Group; and E 1. Review of changes to the' PROCESS CONTROL PROGRAM and the OFFSITE DOS! CALCULATION MANUAL.

Tu sea.r -.-- - m. fr.wam or m Cias. Pecmu P,.<..

6.5.1.7 The OSRO shall:

'a. Recommend in writing to the Assistant Manager-Nuclear Production

' approval or disapproval of items considered under Specifica-tion 6.5.1.6a. through d. prior to their implementation.

j.b Render ' determinations in writing to the Nuclear Safety Review Group with regard to whether or not each item considered under Specifica-tion 6.5.1.6a. through e. constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager-Nuclear Operations and the Nuclear Safety Review Group of disagreement betwee's the OSRO and the Assistant Manager-Nuclear Production; however, the Assistant Manager-Nuclear Production shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The OSR0 shall maintain written minutes of eact. OSR0 meeting that, at a minimum, document the resbits of all OSRO activities performed under thd responsibility provisions of these Technical Specifications. Copies shall be

' provided to the Manager-Nuclear Operations and the Nuclear Safety Review Group.

6.5.2 _ NUCLEAR SAFETY REVIEW GROUP (NSRG)

FUNCTION ,

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

a. Nuclear power plant operations,

b. Nuclear engineering,

c. Chemistry and radiochemistry,

d. Metallurgy,

e. Instrumentation and control,

f. Radiological safsty,

g. Mechanical and ele:trical engineering, and

, . h. Quality assurance practices, e

The NSRG shall report to and advise the Vice President-Nuclear Operations on l3

! those orcas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.

FERMI - UNIT 2 G-9

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AN11NISTRATIVECON 4

PECIAL REPORTS 6.9. ,$pecial reports shall be submitted to the Regional Administrator of the Regio 1 Office of the NRC within the time period specified for each report, lo.9.1 l 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level. .

b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety. .

c. ALL REPORTABLE EVENTS.

, d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications.

( e. Records of changes made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material <

of record. .

6.10.3 The following records shall be retained for the duration of the unit Operating License:

a. Records and drawing changes reflecting unit design modifications made l

to systems and equipment described in the Final Safety Analysis Report.

l

.b. Records of n4w and irradiated fuel inventory, fuel transfers, and assembly burnup histories.

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

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e. Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.

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FERMI - UNIT 2 6-19 l

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