Text

Amends 70 & 62 to Licenses NPF-2 & NPF-8,respectively, Involving Administrative Changes to Tech Specs,Including Correcting Fire Hose Station Designations & Hydrant Numbers & Correcting Size of mini-purge Valves in Ventilation Sys
	ML20209E563
Person / Time
Site:	Farley
Issue date:	04/10/1987
From:	Rubenstein L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20209E571	List: ML20209E563; ML20209E598;
References
	TAC-60355, TAC-60356, NUDOCS 8704300076
	Download: ML20209E563 (73)
	v • d • e

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o ces UNITED STATES o,,

NUCLEAR REGULATORY COMMISSION 8

g W A$HINGTON, D. C. 20555 e-E

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ALARAMA POWER COMPANY DOCKET No.50-34R JOSEPH M. FARLEY NUCLEAR DLANT, UNTT NO. 1 AMENDMENT TO FACILITY OPFRATING LICENSE Amendment No. 70 4

License No. NPF-?.

4 The Nuclear Regulatory Comission (the Comissioni has found that:

^

1.

The application for amendment bv Alabama Power Company (the i

A.

licensee) dated December 9,1985, supplemented February 18, 1986, complies with the standards and requirements of the Atomic Enercy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; l

The facility will operate in confamity with the application, as 4

B.

amended, the provisions of the Act, and the regulations of the l

Comission; (i) that the activities authorized by There is reasonable assurance:

C.

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted j

in compliance with the Comission's regulations; l

The issuance of this license amendnent will not be inimical to the D.

comen defense and security or to the health and safety of the 1

public; and i

The issuance of this amendment is in accordance with 10 CFR Part 51 E.

of the Comission's regulations and all applicable requirements have been satisfied.

Accordingly, the license is amended by thanges to the Technical 2.

Specifications as indicated in the attachment to this license amendment, and paragraph ?.C.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follows:

I 1

I DfA3 & K 05000348 b B70430 P

PDR

a i

2-(?) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 70, are hereby incorporated in the licerse. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendrent is effective as of its date of issuance and shall be implemented within 30 days of receipt of the amendment.

FOR THE NUCLEAR REGULATORY COMMISSION Lester S. R benstein, Director PWR Proiect Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Pegulation i

Attachment:

Changes to the Technical Specifications Date of Issuance: April 10, 1987 1

6 6

e

e ATTAC4 MENT TO LICENSE AMENnMFNT NO. 70 TO FAC'LITY ODERATING LICENSE N1. NPF 7 pnCKET NO.50-34R Replace the following eages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised paces are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pa9es are also provided to maintain document conpieteness.

Remove Pages Insert Pages 3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 3-60a 3/4 3-60a 3/4 5-8 3/4 5-8 3/4 7-16 3/4 7-16 3/4 7-17a 3/4 7-17a 3/4 7-84 3/4 7-84 3/4 7-87 3/4 7-87 3/4 7-88 3/4 7-8R 3/4 7-89 3/4 7-89 3/4 7-91 3/4 7-91 3/4 7-91a 3/4 7-93 3/4 7-93 3/4 9-16 3/4 9-16 3/4 11-4 3/4 11-4 3/4 11-9 3/4 11-9 3/4 11-11 3/4 11-11 P3/4 6-2 R3/4 6-2 5 54 5-5 5-5 6-19 6-19 6-21 6-21 9

S I

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t INSTRUME NT ATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 As a minimum, the fire detection instrumentation for each f re detection zone shown in Table 3.3-12 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

Witn the number of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-12:

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) a.

with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

c.

Tne provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

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4. 3. 3. 9.1 Eacn of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a function test which includes subjecting the detector to test aerosol or heat source, as appropriate.

Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of this functional test during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

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

FARLEY-UNIT 1 3/4 3-59 AMENDMENT NO. El,70 i

e i

4 TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION Auxiliary Buildinc 7

Total MiWinur Room /

Smoke

'of Operable Fire Zone Description Elevation' Oetectors -

Smoke Detectors 128 RHR Heat Exchanger Room 83'-0" 10 5,

129 RHR Low Head Pump Room 77'-0" 1

1>

131 RHR Low heac Pump Room 77'-0" 1

-1 i

100'-0" 3

2 160 Hatch Area 161,162,163 South Corridor 100'-0" 7

4

,172 Hallway 100'-0" 3

2 173 Charging /S! Pump Room 100'-0" 2

1 Cnarging/SI Pump Room 100'-0" 2

1 174 17b Hallway 100'-0" 2

1 188 Charging /SI Pump Room 100'-0" 2

l, 1

184 Mechanical Penetration Room 100'-0" 8

4 185 CC'.: Mcc Exchanger and Pump 10n' n" 13 7

s 186' Boric Acid Trans. PPS

,/

100'-0"y 3

f 2

121'-U" 2

1 188 Boric Acid Tanks s

190 M:C Panel Room 100'-0" 4

2 191 Auxiliary Feedwater Punp Room 100'-U" 1

1 192 Auxiliary Feedwater Pump Room 100'-0" 1

1 193 AJxiliary Feedwater Pump Room 100'-0" 2

1 202 Communications Rooms 121'-0" 4

2 208,207 Corridor 121'-0" 4

2 209 Hallway 121'-0" 4

2 210,211,228, South Corridor 121'-0" 7

4 234 212 Battery Room IB 121'-0" 1

1 l

213 Battery Servf.ce Room 121'-0" 1

1 1

214 Battery Room 1A 121'-0" 1

1 223 Mechtnical Penetration Room 121'-0" 9

5 224 DC Switchgear Reom 121'-0" 1

1 225 Battery Cnarger* Room i 121'-0" 1

1 DC Switchgear Room 121'-0" 1

1 226 227 West Cable Chase 128'-0" 7

4 a

229 AC Switchgear Room Train B 121'-0" 4

2 233 AC Switchgear Room Train B 121'-0" 3

2 4

241 Main Steam and F0W Valve Room 127'-0" 8

4 s

244 Mezzanine - Battery Room 131'-0" 3

2 245 Mezzanine ', Battery Room 131'-0" 3

2 253 Hot Sh:Jtddtn Panel Room 121'- 0" 1

1 j

300 West Cable Chase' 139'-0" 7

4 f

2-l 312 Corridor 139'-0" 3

k 386,322 Corrio'o r 139'-0" 3

2 318 Cable Spreading Room 139'-0" 8

Pc 4

j 319,339,345 West Corridor 139'-0" 6

/4 3

333 Electrical Penetration Room 139'-0" 1

1 334 Electrical Penetration Room 139'-0" 6

3 335 AC Switchgear Room Train A 139'-0" 3

2 343 AC Switchgear Room Train B 139'-0" 3

2 347 f? ac*,tical Penetration Room 139'-0" 2

1 FARLEY - UNIT 1,

3/4 3-60 AMENDMENT NO. 33. 7C

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a

I TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION (continued)

Auxiliary Building Total Mintrum Smoke

'of Operable Room /

Elevation Detectors Smoke Detectors Fire Zone Description 401 Control Room (above ceiling) 155'-0" 8

4 401 Control Room (below ceiling) 155'-0" 5

3 440, 455, Clean Toilet, Laundry and 155'-0" 3

2 456 Drying Areas 462 Non-Radioactive Vent Equip. Rm.

155'-0" 5

3 466 vertical Cable Cnase 155'-0" 3

2 465 Vertical Cable Chase 155'-0" 4

2 500 Vertical Cable Chase 168'-2" 7

4 9

5 Ctri. Rn. Inst. Racks (above/ ceil.) 155'-0" 416 6

3 Ctri. Rn. Inst. Rack s (below/ ceil.) 155'-0" 416 contain ent' 55 Containment Coolers 155'-0" 12/ Fan 6/ Fan 155'-0" 11 6

56 Containment Service Water Intake Structure 188'-9" 12 6

7 2 A" Pump Roon Area 7 2 A*

Strainer Eay 167'-0" 18 6

72 B**

Switchgear Room - Train B 183'-9" 3

2 72 C**

Foyer - Train B 188'-9" 1

1 188'-9" 1

1 72 D**

Foyer - Train A 72 E**

Switchgear Room - Train A 188'-9" 3

2 Battery Room - Train B 186'-9" 1

1 73 **

Battery Room - Train A 188'-9" 1

1 74 **

Diesel Generator Building 56 A Switcngear Room - Train A 155'-0" 12 6

155'-0" 4

2 56 B Foyer 56 C Switchgear Room - Train B 155'-0" 12 6

155'-0" 9

5 71 Hallway Diesel Generator Building (Heat Detectors) 57 Diesel Driven Generator 2C 155'-0" 5

3 58 Diesel Driven Generator 1B 155'-0" 5

3 60 Diesel Driven Generator 1C 155'-0" 5

3 61 Diesel Driven Generator 1-2A 155'-0" 5

3 155'-0" 1

1 62 Day Tank Room 2C 155'-0" 1

1 63 Day Tank Room 1B 155'-0" 1

1 65 Day Tank Room IC 66 Day Tank Room 1-2A 155'-0" 1

1 Ine Fire Detection instruments located within the Containment are not required to be w

OPERABLE curing the performance of Type A Containment Leakage Rate Tests.

These circuits alarm in the Unit 1 control room area but service both units, and appear in the Technical Specifications for both units.

AMENDMENT NO. 33,7 FARLEY-UNIT 1 3/4 3-60a

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T

< 350*F LIMITING CONDITION FOR OPERATION i

3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

One OPERABLE centrifugal charging pump, b.

One OPERABLE residual heat removal heat exchanger, c.

One OPERABLE residual heat removal pump, and d.

An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

a.

With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the

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refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months if at least cne RHR loop is OPERABLE.

b.

With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T"V9 less than 350*F by use of alternate heat removal methods.

c.

In the event the SCCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

FARLEY-UNIT 1 3/4 5-7 AMENDMENT NO. 26 l

EMERGENCY CORE COOLING SYSTEMS SURVEILLAN;E REQUIREMENTS

4. 5. 3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.2 At least once per 31 days verify that the following valves are in the indicated position with the breaker or disconnect device for the valve operator locked open:

Valve Number Valve Function Position 8706 A, 8706 B RHR pump discharge to Closed charging pump suction 8884, 8886 Charging pump discharge Closed to RCS hot legs FARLEY-UNIT 1 3/4 5-8 AMENDMENT NO. gg, 70 l

l t

PLANT SYSTEMS ULTIMATE HEAT SINK POND LIMITING CONDITION FOR OPERATION 3.7.6.2 The ultimate heat sink (pond) shall be OPERABLE with:

A minimum water level at or above 184'-0" mean sea level, and a.

b.

A water temperature of less than or equal to 95'F at the discharge of the service water pumps.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the requirements of the above specification not satisfied, be in HOT SHUTOOWN within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and COLD SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.6.2.1 The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the water temperature and water level to be within their limits.

4.7.6.2.2 The spillw y channel and adjacent areas shall be verified to be free of erosion damage after each storm that raises the pond level greater than or equal to 187', mean sea level.

4.7.6.2.3 The spillway channel and structure shall be verified to be intact at least once each 2 years.

4.7.6.2.4 The ground water seepage from the pond shall be determined to be less than 15 cfs at least once per 5 years.

FARLEY-UNIT 1 3/4 7-15 AMENDMENT NO. 26

e 4

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l PLANT SYSTEMS 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION v

3.7.7 Two independent control room emergency air cleanup systems shall be OPERABLE.

APPLICABILITY: ALL MOUES.

ACTION:

MODES 1, 2, 3 and 4:

With one control room emergency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MUULS 5 and 6 (during irradiated fuel movement, or movement of loads over irradiated fuel):

With one control room emergency air cleanup system inoperable, restore a.

the inoperable system to OPERABLE status within 7 days.or initiate anc maintain operation of the control room emergency ventilation system in the recirculation mode, b.

With both control room emergency air cleanup systems inoperable, suspend all operations involving the movement of irradiated fuel or movement of loads over irradiated fuel.

Tne provisions of Specification 3.0.3 are not applicable in MJ3E 6.

c.

SURVEILLANCE REQUIREMENTS 4.7.7 Each control room emergency ventilation system shall be demonstrated OPERABLE:

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air a.

temperature is less tnan or equal to 120'F.

b.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the pressurization and recirculation system HEPA filters and charcoal adsorbers and verifying that the pressurization system has operated for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heater on during the past 31 days, At least once per 18 months or (1) after any structural maintenance on c.

the HEPA filter or charcoal adsorber housings, or (2)' following painting, fire or chemical release that could have contaminated the charcoal adsorbers or HEPA filters in any ventilation zone communicating with the system by:

FARLEY-UNIT 1 3/4 7-16 AMENDMENT NO. $6, 70

o PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

~

3.

Verifying that the system maintains the control room at a positiv pressure of greater than or equal to 1/8 inch water gauge relative to the outside atmosphere during system operation.

4 Verifying that the pressurization system heater dissipates 7.5 +

0.8 kw when tested in accordance with Section 14 of ANSI N510-178U.

f.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.5% of the DOP when they are tested in-place in accordance with Section 10 of ANSI N510-1980 while operating the system at a flow rate indicated in Note 1.

g.

Af ter each complete or partial replacement of a charcoal adsorber bank by verifying that the chcrccci adsorbers remove greater than or equel to 99.5% of a halogenated hydrocarbon ref rigerant test gas when they are testec in-place in accordance with Section 12 of ANSI N510-198U while operating the system at a flow rate indicated in Note 1.

Note 1.

a.

Control Room Recirculation Filter Unit 20U0 cfm + 10%

b.

Control Room Filter Unit 1000 cfm 7 10%

c.

Control Room Pressurization Filter Unit 300cfm}[10%

Note 2.

a.

Control Room Recirculation Filter Unit

> 99%

b.

Control Room Filter Unit T 99%

c.

Control Room Pressurization

][99.825%

FARLEY-UNIT 1 3/4 7-17a AMENDMENT NO. 75, 70

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.11.1.1 The fire suppression water system shall be demonstrated OPERABLE:

~

At least once per 7 days by verifying the contained water supply a.

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

pump and operating it for at least 15 minutes on recirculation flow.

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

power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

d.

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

At least once per 12 months by cycling each testable valve in the e.

flow path through at least one complete cycle of full travel.

f.

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 pump develops at least 2500 gpm at a system head of 125 psig, 2.

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and 3.

Verifying that each high pressure pump starts (sequentially) to maintain the fire suppression water system pressure greater than or equal to 70 psig.

At least once per 3 years by performing a flow test of the system in g.

accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.

4.7.11.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying:

1.

The fuel storage tank contains at least 50% of full volume, and 2.

The diesel starts from ambient conditions and operates for at least 20 minutes on recirculation flow.

l FARLEY-UNIT 1 3/4 7-83 AMENDMENT NO. 26

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

=

b.

At least once per 92 days by verifying that a sample of diesel fhal from the fuel storage tank, obtained in accordance with ASTM-D270-65 i

is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.

At least once per 18 months by subjecting the diesel to an inspection c.

i in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.

4.7.11.1.3 be demonstrated OPERABLE:The fire pump diesel starting 24-volt battery bank and charger s At least once per 7 days by verifying that:

a.

1.

Tne electrolyte level of each battery is above the plates, and 2.

The overall battery voltage is greater than or equal to 24 volts b.

At least once per 92 days by verifying that the ' specific gravity is appropriate for continued service of the battery.

At least once per 18 months by verifying tnat:

c.

1.

The batteries and battery racks show no visual indication of physical damage or abnormal deterioration, and P.

free of corrosion and coated with anti-corrosion material l

l l

FARLEY-UNIT 1 3/4 7-84 AMENDMENT NO. 25,#2, 70

TABLE 3.7-5 LIST OF SPRlhKLER SYSTEMS Sprinkler Location Room / Fire Zone Description Elevation / System Auxiliary Buildina 161 North West Corridor 100'-0" 1A-25 161 North East Corridor 100'-0" 1A-118 185 North West Corner of CCW Pump' Rm.

100'-0" 1A-119 185 CCW Heat Exchanger and Pump Room 100'-0" 1A-27 190 Aux. Feedwater Pumps Cable Area 100'-0" 1A-62 209 North Corridor 121'-0" 1 A-35 210 Auxiliary Bldg., West Corridor 121'-0" 1A-36 223 Pipe Penetration Roon and Tendon Access 121'-0" 1A-45 227 Vertical Cable Chase 128'-0" 1A-23 244 Battery Room Mezzanine 131'-0" 1A-36 245 Battery Room Mezzanine 131'-0" 1A-36 300 Vertical Cable Chase 139'-0" 1A-23 312 North Corridor 139'-0" 1A-48 316 North Corridor 139'-0" 1A-48 318 Cable Spreading Room 139'-0" 1A-43 319 West Corridor 139'-0" 1A-59 404 West Corridor at EL 155'-0" 155'-0" 1 A '.14 462 Environmental Low Activity Lab and Non-Radioactive Vent Rooms 155'-0" 1A-51 466 Vertical Cable Chase 155'-0" 1A-23 500 Vertical Cable Chase 168'-2" 1 A-23 Service Water Intake Structure 72A Service Water Pump Protection 102'-0" ISW-111 72A Service Water Pump Deck and 188'-9" &

1SW-111A Strainer Pit, East Side 167'-0" 72A Service Water Pump Deck and 188'-9" &

ISW-111B Strainer Pit, West Side 167'-0" FARLEY-UNIT 1 3/4 7-87 AMENDMENT NO. 33 70 l

PLANT SYSTEM C0p SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.3 Tne following high pressure and low pressure CO OPERABLE.

2 systems shall be

,~

a.

Service Water load center) - H.P. Intake Structure (each 4160 volt bus and each 6 b.

Turbine Building 13 ton unit and distribution system in the Auxiliary Building - L.P.

Diesel Building 5 ton unit and distribution system.

c.

APPLICABILITY: Whenever equipment protected by the C02 systems is required to be OPERASLE.

ACTION:

With one or more of the above required CO a.

2 systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in whicn redundant systems or components could be damaged; for other areas, establish an hourly fire watch pat rol.

Restore tne system to OPERABLE status within 14 days or prepare and submit a Special Report to the Conmission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.3.1 Each of the above required C02 systems shall be demonstrated UPERABLE at least once per 31 days by verifying that each manual valve in the flow patn is in its correct p,osition.

4.7.11.3.2 Eacn of the above required low pressure CO2 systems snall be demonstrated OPERABLE:

At least once per 7 days by verifying the CO a.

2 storage tank level to be greater than 50% and pressure to be greater than 250 psig, and b.

At least once per 18 months by verifying:

1.

The system valves and associated ventilation dampers and fire door release mechanisms actuate manually and automatically, upon receipt of a simulated actuation signal, and 2.

Flow during a " Puff Test."

FARLEY-ViilT 1 3/4 7-88 AMENDMENT NO. E7, 70 l

l l

l

PLANT SYSTEMS SURVEILLAtiCE REQUIREMENTS (Continued) 4.7.11.3.3 Each of the above required high pressure C02 systems shall be'

~

demonstrated OPERABLE:

At least once per 6 months by verifying the CO2 storage tank weight to a.

be at least 90% of full charge weight.

b.

At least once per 18 months by:

Verifying the system, including. associated ventilation danpers and 1.

fire door release raechanisms, actuates manually and automatically, upon receipt of a simulated actuation signal, and 2.

Verifying flow during a " Puff Test".

t i

FARLEY-UNIT 1 3/4 7-89 AMEND!iENT I40. 26, 70 1

PL ANT SYSTEMS f!RE HOSE STATI0t:S LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-6 shall

~

ASPLICAEILITY:

stations is required to be OPEJABLE.Whenever equigr:ent in the areas protect ACTION:

With one or more of the fire hose stations shown in Table 3 a.

inoperable, route

an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if th inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

hose station to OPERABLE status within 14 days or prepare and s Restore the fire Special Report to the Comission pursuant to Specification 6 9 2 wit l

the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the station to OPERAELE status.

b.

Tne provisions of Specifications 3.0.3 and 3.0.4 are not applicable

_ SURVEILLANCE REQUIREMENTS demonstrated OPERABLE:4.7.11.4 Each of the fire hose st e

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

stations accessible during plant operation to assure all required equipment is at the station.

b.

At least once per 18 months by:

1.

Removing the flose for inspection and re-racking, and 2.

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

At least once per 3 years by:

c.

1.

OPERASILITY and no flow blockage. Partially opening eac 2.

greater than the ' maximum pressure available a

=1t routing of inoperable, hose will be routed up to but not through the pene I

sufficient hose length to reach the unprotected area (s),

ration with t

FARLEY-UNIT 1 3/4 7-90 A'ENDtENT NO.57

(

l l

TABLE 3.7-6 LIST OF FIRE HOSE STATIONS LOCAi,0N (Room No.)

ELEVATION HOSE CABINET NO.

~

Auxiliary Building 103 83'-0" N1V43-D-103 110 83'-0" N1V43-D-102 161 100'-0" N1V43-D-110 163 100'-0" N1V43-D-109 184 100'-0" N1V43-D-124 185 100'-0" N1V43-D-108 186 100'-0" N1V43-D-131 189 100'-0" N1V43-D-107 208 121'-0" N1V43-D-128 209 121'-0" N1V43-D-104 Stairway ha. 2 121'-0" N1V43-D-127 210 121'-0" N1V43-D-126 234 121'-0" N1V43-D-125 237 121'-0" N1V43-D-132 312 139'-0" N1V43-D-114 316 139'-0" N1V43-D-111 319 139'-0" N1V43-D-115 332 139'-0" N1V43-D-113 33 139'-U" N1V43-D-117 339 139'-0" N1V43-D-116 345 139'-0" N1V43-D-112 409 155'-0" N1V43-D-122 409 155'-0" Containment Fire Hose Storage Locker

402 155'-0" N1V43-D-123 432 155'-0" N143-D-121 446 155'-0" N1V43-D-105 45a 155'-0" N1V43-D-120 462 155'-0" N1V43-D-106 501 175'-0" N1V43-D-101 SOS 184'-0" N1V43-D-100 602 130'-0" N1V43-D-118 Service Water Intake Structure 72D 167'-0" HC-2-D010A 72C 167'-0" HC-2-D01'0B i

Diesel Generator Building 56C 155'-0" HC-2-129 56A 155'-0" HC-2-130

Ine requirements of Specification 4.'/.11.4 Item (c)(1) are not applicable.

FARLEY - UNIT 1 3/4 7-91 AMENDMENT NO. 26, 70

Table 3.7-6 (Continued)

LIST OF FIRE HOSE STATIONS HOSE-EABihET LOCATION (Room ho.)

ELEVATION ISOLATION VALVE NO.

Containment 105'-6" N1T43V001*

105'-6" N1T43V002*

105'-6" N1T43V003*

105'-6" N1T43V004*

129'-0" N1T43V00d*

155'-0" N1T43V006*

155'-0" N1T43V007*

155'-0" N1T43V0J3*

l

Only the requirements of Specification 4.7.11.4 Item (c)(1) are applicable.

FARLEY - UNIT 1 3/4 7-91a AMENDMENT NO. 70

TABLE 3.7-7 YARD FIRE HYDRANTS AN3 ASSOCI ATED HYDRANT HOSE HOUSES LOCATION HYDRANT NUMBER 1.

West of Auxilia y Building N1Y43V103*

2.

East of Service Water Intake N1Y43V121' 3.

West of Service Water Intake N1Y43V122*

4.

North of Diesel Generator Building N1Y43V120*

N1Y43V089 5.

East of Auxiliary Building 6.

hortheast of Diesel Generator Building N1Y43V090

Snarec Detween Unit 1 and Unit 2 i

FARLEY - UNIT 1 3/4 7-93 AMENDMENT NO. 33, 70 l

l

REFUELING OPERATIONS 3/4.9.13 STORAGE POOL VENTILATION (FUEL MOVEMENT)

LIMITING CONDITION FOR OPERATION f

4 3.9.13 Two independent penetration room filtration systems (Specification 3.7.8) shall be OPERABLE and aligned to the spent fuel pool room:

APPLICABILITY:

During crane operation with loads, over the fuel in the spent l

fuel pit and during fuel movement within the spent fuel pit.

ACTION With one penetration room filtration system inoperable return boths a.

systems to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or suspend all movement of fuel and crane operation with loads over the spent fuel in the storage pool room.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

)

SURVEILLANCE REQUIREMENTS 4.9.13.1 Two penetration room filtration systems shall be verified to be aligned to the spent fuel pool room within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to fuel handling or crane operations in the storage pool room and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter until fuel movement operations in the storage pool room are suspended.

4.9.13.2 The penetration room filtration system shall be demonstrated OPERABLE per the requirements of Specification 4.7.8.

i 4.9.13.3 At least once per 18 months verify that the normal spent fuel pool j

system ventilation system will isolate upon receipt of either; The spent fuel pool ventilation low differential pressure test a.

signal, or b.

A spent fuel pool high radiation test signal.

i t

AMENDMENT NO.- 26 FARLEY-UNIT 1 3/4 9-15 l

..~ _ __

REFUELING OPERATIONS

_3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER LIMITIhG CONDITION FOR OPERATION 3.9.14 N1P13V293 closed.The containment purge exhaust filter shall be OPERABLE

~

APPLICABILITY:

with any containment purge isolation valve open.During CORE ALT

_ ACTION:

With the containment purge exhaust filter inoperable either:

1.

(CBV-HV-3196, 3197, 3198A and 3198D) and th mini-purge isolation valves (CBV-HV-28660, 28663, 2867C and 2

, or 2.

Cease all CORE ALTERATIONS and fuel movement.

SURVEILLANCE REQUIREMENTS 4.9.14 3

oemonstrated OPERABLE:Tne above required containment purge exhaust filte the HEPA filter or charcoal adsorber housings, o a.

nce on painting, fire or chemi,al release that could have contaminated the w ng charcoal adsorbers or HEPA filter in any ventilation zone com witn the system by:

FARLEY-UNIT 1 3/4 9-16 AMENDMENT NO. 26 70

,e

TABLE 4.11-1 (Continued)

TABLE NOTATION

~

The MDC is the smallest concentration of radioactive material in a' sample that will be detected with 95% probability with 5% probability of falsely a.

concluding that a blank observatio'n represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb MDC = E V

2.22 x 105 Y

exp (-Aat)

Where:

MDC is the "a priori" lower limit of detection as defined abcVe (as microcurie per unit mass or volume),

is the standard deviation of the background counting rate or of stne counting rate of a blank sample as appropriate (as counts per b

minute),

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

is the number of transformations per minute per microcurie, 6

2.22 x 10 Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of s, used in the calculation of the MDC for a detection system shall bV based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted Typical values of E, V, Y, and at shall be used in the variance.

calculation.

i 1

3/4 11-3 AMENDMENT NO. 26 FARLEY-UNIT I

Table 4.11-1 (Continued)

TABLE NOTATION-b.

A composite sample is one in which the quantity of liquid sampled is the method of sampling employed results in a specime representative of the liquids released. Deviations.from composite sampling requirements shall be reported per Specification 6.9.1.8.

A batch release is the discharge of liquid wastes of a discrete c.

volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling, volume; e.g., from a volume of system that has a d.

effluent release.

exclusively are the following radionuclides:The principal gam e.

Co-50, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144Mn-54, Fe-59, Co-58, does not mean that only these nuclides are to be detected and This list reported.

with the above nuclides, shall also be identified and rep f.

Sampling will be performed only if the effluent will be discharged to the environment, Deviation from the MDC requirements of Table 4.11-1 shall be reported g.

per Specification 6.9.1.8.

i FARLEY-UNIT 1 3/4 11-4 AMENDMENT NO. 2f, E7, 70 1

1 l

e TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM m

E h

Minimum Minimum Detectable l-Gaseous Release Type Sampling Analysis Type of Concentration (MDC)

Frequency frequency Activity Analysis pCi/ml)a h z

-a P

P A.

Waste Gas Storage Each Tank Grab Each Tank Principal Gamma Enitters9 3 1x10-4 Tank Sample P

P b

b Principal Gamma Emitters 9 3 1x10-4 B.

Containment Purge Each Purge Each Purge Grab Sample H-3 1x10 6 C.

Condenser Steam Jet Mbce gh Principal Gamma Emitters 9 J 1x10-4 Air Ejector, Plant Grab Vent Stack Sample H-3 1x10-6 w

D.

Plant Vent Stack, Continuousf Wd 1-131 1x10-12 7

Containment Purge Charcoal Charcoal Sample I-133 1x10-10 Continuousf Wd Principal Gamma Emitters 9 1x10-Il Particulate l

Sample f

M Gross Alpha 1x10-Il Continuous l

Composite Particulate Sample g

E Continuousf Q

Sr-89, Sr-90 1x10-Il i

k Composite i

Particulate z

[

Sample Continuousf Noble Gas Noble Gases 1x10-6 Monitor Gross Beta and Gamma t

5 4

TABLE 4.11-2 (Continued).

TABLE NOTATION that will be detected with 95% probabiThe MDC is the smalle a.

sample concluding that a blank observation re.lity with 5% probability of-falseiy presents a "real" signal.

For a particular measurement system (which may include radiochemi -

separation):

cal MDC =

D E

V 2.22 x 10' Y

exp (-Aat)

Where:

MDC is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

is the standard deviation of the background counti sb tne counting rate of a blank sample as appropriate (as counts ng rate or of minute),

per E is the counting efficiency (as counts per transformation)

V is the sample size (in units of mass or volume) 2.22 x 108 is the number of transformations per minute per microcurie Y is the fractional radiochemical yield (when applicable)

A is the radioactive decay constant for the particular radionuclid e, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sa mples).

The value of s used in the calculation of the MDC for a detection s

system shall bV based on the actual observed variance of the back counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

Typical values of E, V, Y, and at shall be used in the calcalation.

FARLEY-UNIT 1 3/4 11-10 AMENDMENT NO, 26 i

i

Table 4.11-2 (Continued)

TABLE NDTATION b.

Analyses shall also be performed following shutdown from > 15% RATED THERMAL POWER, startup to > 15% RATED THERMAL POWER or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a,one-hour period.

c.

Tritium grab samples shall be taken from the plant vent stack at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canas is flooded.

d.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 2 days following each shutdown from > 15% RATED THERMAL POWER, startup to > 15% RATED THERMAL POWER or.THTRMAL POWER change exceeding 15 perceiit of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples _ collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding MDC may be increased by a factor of 10.

e.

Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool, f.

Tne ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.

g.

The principal gamma emitters for which the MDC specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and r.eported.

h.

Deviations from MDC requirements of Table 4.11-2 shall be reported per Specification 6.9.1.8.

1.

A composite particulate sample is one in which the quantity of air sampled is proportional to the quantity of air discharged. Either a specimen which is representative of the air discharged may be accumulated and analyzed or the individual samples may be analyzed and weighted in proportion to their respective volume discharged.

Deviations from composite sampling requirements shall be reported per Specificati on 6.9.1.8.

j. The principal gamma emitters for which the MDC specification applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions.

This does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

FARLEY-UNIT 1 3/4 11-11 AMENDMENT NO. 57,70 l

3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage This restric-paths and associated leak rates assumed in the accident analyses.

tion, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P As an added conservatism, the measuredoverallintegratedleakagerateis. further limited to less than or equal to 0.75 L,for possible, as applicable, during performance of the periodic or 0.75 L test to account degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50, 3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on' closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.

Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive'due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.0 psig and 2) the containment peak pressure does not exceed the design pressure of 54 psig during LOCA conditions.

FARLEY-UNIT 1 8 3/4 6-1 AMENDMENT NO. 26

,,--n.

CONTAINMENT SYSTEMS BASES The maxinun peak pressure expected to be obtained from a LOCA event is 45 psig.

The limit of 3 psig for initial positive containment pressure will limit the total pressure to 48 psig which is less than design pressure and Js consistent with the accident analyses.

3 /4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break accident.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards f or the life of the facility.

Structural integrity is required to ensure that the containment will withstand the maximan pressure of 48 psig in the event of a LOCA.

Tne measurement of the containment lif t off force, visual examination of tendons, anchorages and exposed interior and exterior surf aces of the containment, and the Type A leakage test, is sufficient to demonstrate this capability.

Tne surveillance requirements for demonstrating the containment's structural integrity are in compliance with the recommendations of paragraph C.1.3 of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures," January 1976.

3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 48-inch containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been deronstrated capable of closing during a LOCA or steam line break accident.

Maintaining these valves', closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.

The use of the containment purge lines is restricted to the 8-inch purge supply and exhaust isolation valves to ensure that the site boundary dose guide-lines o.f 100FR Part 100 would not be exceeded in the event of a loss-of-coola accident during purging operations.

4 FARLEY-UNIT 1 B 3/4 6-2 AMENDMENT NO. 26, 70

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l FARLEY - UNIT 1 5-5 AMENCMENT NO. 26,70

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3 DESIGN FEATUPES

=======================================

f r

5.3 REACTOR CORE r i

_FL'EL A55EM5;1ES s

5.3.1 The reactor core shall contain 257 fuel assenclies with each fuel y

assembly containing 264 fuel rods cla'd with Zircaloy -4.

Each fuel rod

)

sna11 have a nominal active fuel lengtn of 144 inches.

loading shall have a maximuT. enrichment of 3.2 weight percent U-235.The initial core k j.

2 fuel shall be similar in physical design to the initial core loading and Reloac 3 s

shall have a maximu. enrichment of 4.3 seight percent U-235.

^. 3

_ CONTROL R03 ASSEMBLIES

'r 5.3.2 The reactor core shall contain 48 full length and no part length contrci roc asset: lies.

contein a no-inal 142 inches of absor6er material.The full lencth contr absorber material shall be 80 percent silver,15 percent indium and 5The nominal values of,i percent cadmiu..

i tuoing.

All control rods shall be clad with stainless steel

.7 5.4 REACT 0k C00LAt.T SYSTEM \\

s A

\\

DESIGN PRES 5URE AND TEM ERATURE

(

k

'5.4.1 Tne reactor coolant system is designed and shall be maintainec '

1 i

In accordance witn the code requirements specified in Sectio. 5.2 a.

)

Lapplicable Surveillance Requirements,of the FSAR, with allowanc b.

For a pressure of 24S5 psig, and For a tempera \\ure of 650*F, except for the pressurizer which is c.

660*F.

i JOLUME 5.4.2 The total water and stea ; volume of the re' actor coolant system is i

9723 + 100 cubic feet at a nominal Tavg of 525'F.

_5.5 METEOROLOGICAL TOWER LOCATION s

5.5.1 The meteorological tower shall be located as shown on Figurg 5.

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FARLEY-UN:T 1 5-6 AMENDMENT NO. If, II.# ff 70 s

g s

ADMINISTRATIVE CONTROLS e.

Type of container (e.g., LSA, Type A, Type B, Large Quantity), and f.

Solidification agent (e.g., cement, urea fornaldehyde).

Tne radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive rnaterials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CO.NTROL PROGRAM (PCP) made during the reporting period.

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. haclear Regulatory Comission, Washington, D.C. 20555, with a copy to the Regional Of fice of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made j

effective.

In accition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the pe-ict in w'.ich the change was imple.ented.

RADIAL PEA 61rG FACTOR LIMIT REPORT TP 6.9.1.11 The F limit for Rated Thermal Power (F[y

) shall be provided to tne Director of [ne Regional Office of Inspection and Enforcement, with a copy x

to the Director, huclear Reactor Regulation, Attention Chief of the Core Perfe mance Branch, U.S. Nuclear Regu'e+ory Commission, Washingtor., D.C. 20555 for all core planes containing bank "D" control rods and all unrodded core planes at least 60 days. prior to cycle initial criticality.

In the event that the limit would be submitted at some otner time curing core life, it will be submitted 60 days prior to the date the limit would become effective unless otherwise exempted by the Comission.

Any information needed to support F[y will be by request from the NRC and neec P

not be included in this report.

ANNUAL DIE 5EL GENERATOR RELI ABILITY DATA REPORT 6.9.1.12 Tne number of tests (valid or invalid) and the number of failures to start on demand for each diesel generator shall be submitted to the NRC annually. This report shall contain the information identified in Regulatory Position C.3.b of NRC Regulatory Guide 1.108, Revision 1,1977'.

FARLEY - UtilT 1 6-19 AMEN 3 MENT NO.

, 70

ADMINISTRATIVE C0t TROLS h.

Records-of annual physical inventory of all sealed source material of recoro.

6.10.2 Tne f ollowing records shall be retained for the duration of the Unit-Operating License.

Records and drawing changes reflecting unit design modifications made a.

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

b.

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

Records of radiation exposure for all individuals entering radiation c.

control areas.

d.

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

Records of transient or operational cycles for those unit components e.

identifieJ in Table 5.7-1.

f.

Records of reactor tests and experiments.

Records of training and qualification for current members of the g.

facility staff.

Records of in-service ins;;ec^ ions performed pursuant to these Technical h.

Speci fi cations,

i. Records of safety-related Quality Assurance activities required by the Operations Quality Assurance Policy Manual (00APM) and not specifically described in Tecnnical Specification 6.10.1.

j. Records of reviews performed for changes made to ptudures or equipment or rev,iews of tests and experiments pursuant to 10CFR50.59.

k.

Records of meetings of the PORC and the NORB.

1.

Records of secondary water sampling and water quality.

I Records of analyses required by the radiological environmental m.

monitoring program.

)

Records of the service lives of all hydraulic and mechanical snubbers n.

in service af ter 07-01-84 within the scope of 3/4.7.9 including the date at which the service life commence 5 and associated installation and maintenance records.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adnered to for all operations involving personnel radiation exposure.

FARLEY-UNIT 1 6-21 AMENDMENT NO. 57, 70 O

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UNITED STATES d

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NUCLEAR REGULATORY COMMISSION

. E W ASHINGTON, D. C. 20555 a

9

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w ALA9AMA DOWER C0YDA"Y DOCKET NO. 50-364 JOSEPW M. FADLEY NilCLEAR PLANT, UNIT NO. 2 AMEND.wENT TO FACILITY OPERATING LICENSE Amendment No.'62 License No. NPF-8 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The apoli:ation for anendment by Alabama Power Company (the licenseel dated December 9, 1985, supplemented February 18, 1986, complies with the standards and requirements of the Atomic Eneroy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the reculaticns o' the Commission; C.

There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance Of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable recuirements have been satisfied.

P.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(?) of Facility Operating License No. NPF-8 is herebv amended to read as follows:

9

-?-

(2) Technical Specifications The Technical Specificatinrs contained-in Appendices

~

A and B, as revised throuch Amendment No.62, are hereby incorocrated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days of receipt of the amendment.

FOR THE NUCLEAR REGULATORY CO*"ISSION

('

\\-

)

D Lester S. Ru nstein, Director PWR Pro.iect Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactnr Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 10, 1987 I

i

ATTACWVENT TO LICENSE AMFNDWENT NO. 62 TO FACILITY ODERATING LTCENSE NO. NPF-8 DACKET NO. 50-364 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified bv amendment number and contain vertical lines indicating the area e' change.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Daaes Insert Paaes 3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 3-60a 3/4 3-60a 3/4 5-8 3/4 5-8 3/4 7-16 3/4 7-16 3/4 7-17a 3/4 7-17a 3/4 7-54 3/4 7-54 3/4 7-57 3/4 7-57 3/4 7-58 3/4 7-58 3/4 7-59 3/4 7-59 3/4 7-61 3/4 7-61 3/4 7-61a 3/4 7-61a 3/4 7-63 3/4 7-63 3/4 8-18 3/4 8-18 3/4 8-19 3/4 8-19 3/4 8-20 3/4 8-20 3/4 8-21 through 3/4 8-28D 3/4 9-16 3/4 9-16 3/4 11-4 3/4 11-4 3/4.11-9 3/4 11-9 3/4,11-11 3/a 11-11 83/4 8-2 83/4 8-?

5-4 5-4 5-5 5-5 6-19 6-10 6-21 6-21 5

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION

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3.3.3.9 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-12 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

With the number of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-12:

Within I hour establish a fire watch patrol to inspect the Zone (s) a.

with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

Tne provisions of Specifications 3.0.3 and 3.0.4 are not c.

applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9.1 Each of the 4bove required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a function test which includes subjecting the detector to test aerosol or heat source, as appropriate.

Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of this functional test during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

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

i FARLEY-UNIT 2 3/4 3-59 AMENDMENT NO. ff, 62 l

TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION Auxiliary Building Total animum Smoke of Operable Room /

Fire Zone Description Elevation Detectors

, Smoke Detectors 2128 RHR Heat Exchanger Room 83'-0" 10

~

5 2129 RHR Low Head Pump Room 77'-0" 1

1 2131 RHR Low Head Pump Room 77'-0" 1

1 2160 Hatch Area 100'-0" 2

1 2161 South Corridor 100'-0" 2

1 2172 Hallway 100'-0" 3

2 2173 Charging /51 Pum; Room 100'-0" 2

1 2174 Charging /SI Pum; Room 100'-0" 2

1 2175 Hallway 100'-0" 2

1 2181 Charging /S! Pump Room 100'-0" 2

1 218 Mechanical Penetration Room 100'-0" 8

4 218E CCW Hea. exchanger and Pump 100'-0" 13 7

2186 Boric Ac 4 Trans. PPS 100'-0" 3

2 2188 Boric Ac:c 'anks 121'-0" 2

1 2190 MCC Panel hoom 100'-0" 4

2 2191 Auxiliary Feedwater Pump Room 100'-0" 1

1 2192 Auxiliary Feedwater Pump Room 100'-0" 1

1 2193 Auxiliary Feedwater Pump Room 100'-0" 2

1 2202 Hot Snutdown Panel Room 121'-0" 4

2 2208 Corridor 121'-0" 2

1 2209 Hallway 121'-0" 3

2 2210 South Corridor 121'-0" 2

1 2212 Battery Room 2B 121'-U" 1

1 2213 Battery Service Room 121'-0" 1

1 2214 Battery Room 2A 121'-0" 1

1 2223 Mechanical Penetration Room 121'-0" 9

5 2224 DC Switchgear Room 121'-0" 1

1 2226 DC Switchgear Room 121'-0" 1

1 2227 West Cable Chase-128'-0" 7

4 2229 AC Switchgear Room Train B 121'-0" 4

2 2233 AC Switchgear Room Train B 121'-0" 3

2 2241 Main Steam and FDW Valve Room 127'-0" 8

4 2244 Mezzanine 131'-0" 3

2 2245 Mezzanine 131'-0" 2

1 2254 Hot Shutdown Panel Room 121'-0" 1

1 2300 West Cable Chase 139'-0" 7

4 2309 Hatch Area 139'-0" 1

1 2312 Corridor 139'-0" 4

2 2316 Corridor 139'-0" 2

1 2318 Cable Spreading Room 139'-0" 8

4 2319 West Corridor 139'-0" 2

1 2333 Electrical Penetration Room 139'-0" 1

1 2334 Electrical Penetration Room 139'-0" 3

2

' 2335 AC Switchgear Room Train A 139'-0" 3

2 2343 AC Switchgear Room Train B 139'-0" 3

2 2347 Electrical Penetration Room 139'-0" 2

1 f

FARLEY - UNIT 2 3/4 3-60 AMENDMENT NO.2f, 62 r.

TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION (continued)

Auxiliary Evilding Total Mi ninum Room /

Smoke of Operable Fire Zone Description Elevation Detectors Smoke DJtectors 2401 #

Control Room (above ceiling) 155'-0" 8

4 2401 #

Control Room (below ceiling) 155'-0" 6

3 2452 Storage Area 155'-0" 7

4 2462 Non-Radioactive Vent Equip. Rm.

155'-0" 5

3 2466 West Cable Chase 155'-0" 7

4 2471 #

Ctrl. Rm. Inst. Racks (above/ ceil.) 155'-0" 8

4 2471 #

Ctr1. Rm. Inst. Racks (below/ ceil.) 155'-0" 6

3 2500 West Cable Chase 168'-2" 7

4 Containment

55 Containment Coolers 155'-9" 12/ Fan-6/ Fan 55 Containment 155'-0" 14 7

Service Water Intake Structure 72 A**

Pump Room Area 183'-9" 12 6

72 A**

Strainer Bay 167'-0" 18 6

1 72 B**

Switchgear Roon - Train B 188'-9" 3

2 72 C**

Foyer - Train B 188'-9" 1

1 72 D**

Foyer - Train A 188'-9" 1

1 72 E**

Switchgear Room - Train A 188'-9" 3

2 Battery Room - Train B 188'-9" 1

1 73 Battery Room - Train A 188'-9" 1

1 74 Diesel Generator Building 56 A Switcngear Roon - Train A 155'-0" 12 6

56 B Foyer 155'-0" 4

2 56 C Switchgear Room - Train B 155'-0" 12 6

7; Hallway 155'-0" 9

5 Diesel Generator Building (Heit Detectors) 57 Diesel Driven Gen'erator 2C 155'-0" 5

3 59 Diesel Driven Generator 2B 155'-0" 5

3 60 Diesel Driven Generato,1C 155'-0" 5

3 61 Diesel Driven Generator 1-2A 155'-0" 5

3 62 Day Tank Room 2C 155'-0" 1

1 64 Day Tank Room 2B 155'-0" 1

1 65 Day Tank Room IC 155'-0" 1

1 66 Day Tank Room 1-2A 155'-0" 1

1 Inese circuits alarm in the Unit 1 control room area, but service Unit 2 only and appear only in the Unit 2 Technical Specifications.

The Fire Detection instruments located within the Containment are not required to be OPERABLE during tne performance of Type A Containment Leakage Rate Tests.

- These circuits alarm in the Unit 1 control room area but service both units, and appear in the Technical Specifications for both units.

FARLEY-UNIT 2 3/4 3-60a AMENDMENT N3. H, 62

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T,yg < 350 F LIMITING CONDITION FOR OPERATION

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3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

One OPERABLE centrifugal charging pump, a.

b.

One OPERABLE residual heat removal heat exchanger, One OPERABLE residual heat removal pump, and c.

d.

An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY:

MODE 4.

ACTION:

With no ECCS subsystem OPERABLE because of the inoperability of a.

either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months if at least one RHR loop is OPERABLE.

b.

With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain thi Reactor Coolant System T less than 350'F by use of alternate hiat removal methods.

avg In the event the ECCS is actuated and injects water into the Reactor c.

Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

o FARLEY-UNIT 2 3/4 5-7

\\

EMERGENCY CORE COOLING SYSTEMS 1

SURVEILLANCE REQUIREMENTS

=

4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.2 At least once per 31 days verify that the following valves are in

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the indicated position with the breaker or disconnect device for the valve operator locked opsn:

Valve Number Valve Function Position 8706 A, 8706 B RHR pump discharge to Closed cnarging pump suction 8884, 8886 Charging pump discharge Closed to RCS hot legs 4

FARLEY-UNIT 2 3/4 5-8 AMENDMENT NO. 62

PLANT SYSTEMS 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION Two independent control room emergency air cleanup systems sha\\1 be 3.7.7 OPERABLE.

APPLICABILITY: ALL MODES.

ACTION:

MODES 1, 2, 3 and 4:

With one control room energency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDEY witnin tne next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MODES S and 6 (during irradiated fuel movement, or movement of loads over irraciatec fuel):

a.

With one control room emergency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the control room emergency ventilation system in the recirculation mode, b.

With botn control room emergency air cleanup systems inoperable, suspend all operations involving the movement of irradiated fuel or movement of loads over irradiated fuel.

c.

Tne provisions of Specification 3.0.3 are not applicable in MODE 6.

SURVEILLANCE REQUIREMENTS 4.7.7 Each control room mergency ventilation system shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is less than or equal to 120*F.

b.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the pressurization and recirculation system HEPA filters and charcoal adsorbers and verifying that the pressurization system has operated for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heater on during the past 31 days.

c.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release that could have contaminated the charcoal adsorbers or HEPA filters in any ventilation zone i

cwnnunicating with tne system by:

l FARLEY-UNIT 2 3/4 7-16 AMEf0 MENT NJ. 37, 62

PLANT SYSTEMS SURVEILLANCE REQUIREMEhTS (Continued)

=

3.

Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8 inch water gauge re,lative to the outside atmosphere during system operation.

4.

Verifying that the pressurization system heater dissipates 7.5 +

0.8 kw when tested in accordance with Section 14 of ANSI N510-1780.

f.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.5% of the D0P when they are tested in-place in accordance with Section 10 of ANSI N510-1980 while operating the system at a flow rate indicated in Note 1.

g.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.5t of a halogenated hydrocarbon refrigerant test gas when they

a. e tested in-place in accordance w-;ch Section 12 of ANSI N510-1983 woile operating the system at a flow rate indicated in Note 1.

Note 1.

a.

Control Room Recirculation Filter Unit 2000 cfm + 10%

b.

Control Room Filter Unit 1000 cfm 7 10%

c.

Control Room Pressurization Filter Unit 300cfm}[10%

hote 2.

a.

Control Room Recirculation Filter Unit

> 991 b.

Control Room Filter Unit I S9%

c.

Control Room Pressurization

][99.825%

FARLEY-UNIT 2 3/4 7-17a AMENDMENT NO. 37,62

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS

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4.7.11.1.1 The fire suppression water sy' stem shall be demonstrated 0PERABLE:

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At least once per 7 days by verifying the contained water supply a.

volume.

b.

At least once per 31 days on a STAGGERED TEST BASIS by starting each pump and operating it for at least 15 minutes on recirculation flow.

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

power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

d.

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

At least once per 12 months by cycling each testable valve in the e.

flow path through at least one complete cycle of full travel.

f.

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 pump develops at least 2500 gpm at a system head of 125 psig, 2.

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and 3.

Verifying.that each high pressure pump starts (sequentially) to maintain the fire suppression water system pressure greater than or equal to 70 psig.

l g.

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.

4.7.11.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying:

1.

The fuel storage tank contains at least 50% of full volume, and l

2.

The diesel starts from ambient conditions and operates for at least 20 minutes on recirculation flow.

I a

}

FARLEY-UNIT 2 3/4 7-53 ll

PLANT SYSTEMS-SURVEILLANCE REQUIREMENTS (Continued)

E b.

At least 3nce per 92 days by verif

- that a sample of diesel ' fuel from the fuel storage tank, obta-is within the acceptable limits n accordance with ASTM-0270-65,

ar in Table 1 of ASTM D975-74 r

when checked for viscosity, wat

,i sediment.

At least once per 18 months b; subjecting the diesel to an inspection c.

in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.

4.7.11.1.3 The fire pump diesel starting 24 '.91t battery bank and charger shall be demonstrated OPERABLE:

At least once per 7 days by verifying that:

a.

1.

The electrolyte level of each battery is above the plates, and 2.

Tne overall battery voltage is greater than or equal to 24 volts, b.

At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery, At least once per 18 months by verifying that:

c.

1.

The batteries and battery racks show no visual indication of physical damage or abnormal deterioration, and 2.

The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

FARLEY-UNIT 2 3/4 7-54 I

AMENDMENT NO. 33, 62 l

l

TABLE 3.7-5 2

LIST OF SPRINKLER SYSTEMS Location-Spriekler Room / Fire Zone Description Elevation

' System Auxiliary Building 2160 Hatch Area 100'-0" 2A-25 2161 South Corridor 100'-0" 2A-25 2172 Hallway 100'-0" 2A-101 2175 Hallway 100'-0" 2A-118 2185 CCW Heat Exchanger and Pump Room 100'-0" 2A-27 2193 MCC Panel Room 100'-0" 2A-62 2209 Hallway 121'-0" 2A-35 2210 South Corridor 121'-0" 2A-36 2223 Hecnanical Penetration Room 121'-0" 2A-45 2227 West Cable Chase 128'-U" 2A-23 2244 Mezzanine 131'-0" 2A-36 2245 Mezzanine 131'-U' 2A-36 2300 West Cable Cnase 139'-0" 2A-23 2312 Corridor 139'-0" 2A-48 2316 Corridor 139'-0" 2A-48 2318 Cable Spreading Room 139'-0" 2A-43 2319 West Corridor 139'-0" 2A-59 2452 Clean Storage Area 155'-0" 2A-52 2462 Non-Radioactive Vent Equipment Room 155'-0" 2A-51 2466 West Cable Chase 155'-0" 2A-23 2500 West Cable Chase 168'-2" 2A-23 Service Water Intake Structure 72A Servici Water Pump Protection 102'-0" ISW-111 72A Service Water Pump Deck and 188'-9"

& ISW-111A Strainer Pit, East Side 167'-0" 72A Service Water Pump Deck and 188'-9"

& ISW-111B Strainer Pit, West Side 167'-9" 4

6 FARLEY - UNIT 2 3/4 7-57 AMENDMENT NO. 33,62 6

PLANT SYSTEMS C07 SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.3 Tne following high pressure and low pressure C02 systems shall be OPERABLE.

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Service Water Intake Structure (eath 4160 volt bus and eachk00 volt a.

load center) - h P.

b.

Turbine Building 13 ton unit and distribution system in the Auxiliary Building - L.P.

Diesel Building 5 ton unit and distribution system.

c.

_APPLIC AB IL ITY: Whenever equipment protected by the C02 systems is required to be OPERABLE.

ACTION:

With one or more of the above required CO a.

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

Restore the system to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status, The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

b.

SURVEILLANCE REQUIREMENTS 4.7.11.3.1 Each of the above required C0g systems shall be demonstrated OPERABLE at least once per 31 days by verifying that each manual valve in the flow path is in its corr &ct position.

4.7.11.3.2 Each of the above required low pressure CO2 systems shall be demonstrated OPERABLE:

At least once per 7 days by verifying the CO a.

2 storage tank level to be greater than 507, and pressure to be greater than 250 psig, and b.

At least once per 18 months by verifying:

1.

The system valves and associated ventilation dampers and fire door release mechanisms actuate manually and automatically, upon receipt of a simulated actuation signal, and 2.

Flow during a " Puff Test."

FARLEY-UNIT 2 3/4 7-58 AMENDMENT NO. Me 62

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.7.11.3.3 Each of the above required high pressure CO2 systems shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying the CO2 storage tank weight to be at least 90% of full charge weight.

b.

At least once per 18 months by:

1.

Verifying the system, including associated ventilation dampers and fire door release mechanisms, actuates manually and automatically, upon receipt of a simulated actuation signal, and 2.

Verifying flow during a " Puff Test".

1 i

i FARLEY-UNIT 2 3/4 7-59 AMEN 0 MENT NO. 62

PL ANT SYSTEt3 FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-6 shall be OPER

_APPLICAEILITY:

stations is required to be OPERABLE.Whenever equipment in the areas protected by

_ ACTION:

With one or more of the fire hose stations shown in Table 3.7-6 a.

inoperable, route

an additional equivalent capacity fire hose to the inoperable fire hose is the primary means of fire suunprotecte otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .ppression; hose station to OPERABLE status within 14 days or prepare and submit aR Special Report to the Commission pursuant to Specification 6.9.2 within l

the next 30 days outlining the action taken, the cause of the OPERA 5LE status,inoperability and the plans and schedule for restoring b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable SURVEILLAN;E REQUIREMENTS demonstrated OPERASLE:4.7.11.4 Each of the fire hose stations At least once per 31 days by visual inspection of the fire hose a.

equipment is at the station. stations accessible during plant operation to At lehst once per.,18 months by:

b.

1.

Removing the hose for inspection and re-racking, and 2.

Inspecting all gaskets and replacing any degraded gaskets in the coupl ings.

At least once per 3 years by:

c.

1.

Partially opening each hose station valve to verify valve OPERASILITY and no flow blockage.

2.

greater than the maximum pressure available at th

=1t routing of the hose would require rendering a fire bar sufficient hose length to reach the unprotected area (s).

FARLEY-UNIT 2 3/4 7-60 AMENDMENT N3. 49 t

4 e

,,e

,-_,.-,n.

~,,, -

TABLE 3 7-6 LIST OF FIRE HOSE STATIONS AUXILIARY BUILDING LOCATION (Roon No.)

ELEVATION HOSE CABINET NO.

2103 83'-0" N2V43-D-103 2110 83'-0" N2V43-D-102,

2161 100'-0" N2V43-D-110.

2163 100'-0" N2V43-D-109

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2184 100'-0" N2V43-D-124 2185 100'-0" N2V43-D-108 2186 100'-0" N2V43-D-131 2169 100'-0" N2V43-D-107 2208 121'-0" N2V43-D-128 2209 121'-0" N2V43-D-104 2210 121'-0" N2V43-D-126 2223 121'-0" N2V43-D-127 2234 121'-0" N2V43-D-125 2237 121'-0" N2V43-0-132 2312 139'-0" N2V43-D-114 2316 139'-0" N2V43-D-111 2319 139'-0" N2V43-D-116 2319 139'-0" N2V43-D-119 2332 139'-0" N2V43-D-113 2334 139'-0" N2V43-D-117 2345 139'-0" N2V43-D-112 2409 155'-0" N2V43-D-122 2409 155'-0" Containment Fire Hose

Storage Locker 2408 155'-0" N2V43-D-123 2:46 155'-0" N2V43-D-106 2452 155'-0" N2V43-D-120 24b3 155'-0" N2V43-D-121 2452 155'-0" N2V43-D-106 2502 175'-0" N2V43-D-101 2505 184'-0" N2V43-D-100 2602 130'-0" N2V43-D-118 AUXILIARYBdILDIN3TODIESELGENERATORBUILDINGTUNNELS TRAIN A TUNNEL TRAIN B TUNNEL HOSE CABINET NO.

HOSE CABINET NO.

N2Y43D001A N2Y430001P N2Y430001B N2Y430001Q N2Y430001C N2Y430001R N2Y43D0010 N2Y43D0015 N2Y430001E N2Y43D001T N2Y43D001F N2Y430001U N2Y43D001G N2Y43D001V N2Y430001H N2Y430001W N2Y430001J N2Y43D001X N2Y430001K N2Y43D001Y N2Y430001L N2Y430001Z N2Y43D001M N2Y430002A N2Y43D001N N2Y43D002B

Ine requirements of Specification 4.7.11.4 Item (c)(1) are not applicable.

FARLEY - UNIT 2 3/4 7-61 AMENDMENT NO. Ife 62

Table 3.7-6 (Continued)

LIST OF FIRE H0SE STATIONS HOSE' CABINET LOCATION (Room ho.)

ELEVATION ISOLAT10h VALVE NO.

Containment 105'-6" N2T43V001*

105'-6" N2T43V002*

105'-6" N2T43V003*

105'-6" N2T43V004*

129'-0" N2T43V005*

155'-0" N2T43V006*

155'-0" N2T43V007*

155'-0" N2T44VUOB*

t

Only the requirements of Specification 4.7.11.4 Item (c)(1) are applicable.

FARLEY - UNIT 2 3/4 7-61a AMENDMENT NO. 62

TABLE 3.7-7 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES LOCATION HYDRANT N'JEBER 1.

Northeast of Auxiliary Building N1Y43V105 2.

horthwest of Auxiliary Building N1Y43V102 3.

West of Auxiliary Building N1Y43V103*

4.

horth of Diesel Generator Building N1Y43V120*

5.

East of Service Water Intake N1Y43V121*

6.

West of Service Water Intake N1Y43V122*

A 1

Snared between Unit 1 and Unit 2 FARLEY - UNIT 2 3/4 7-63 AMENDMENT NO. gg,62 i

~.

ELECTRICAL POWER SYSTEMS SERVICE WATER BUILDIN3 D.C. DISTRIBUTION - OPERATING SURVEILLANCE REQUIREMENTS (Continued) d.

At least once per 60 months by verifying that the battery ~

capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. Once per 60 month interval, this performance discharge test may be performed in lieu of the battery service test per 4.8.2.5.2.c.5.

e.

At least once per 18 months, performance discharge test of battery capacity Jhall be given to any battery that shows signs of degradation or has reached 17 years or 85% of the service life expected for the application, whichever comes fi rs t.

Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.

FARLEY-UNIT 2 3/4 8-17 AMENDMENT NO.50

ELECTRICAL P0';!ER SYSTEMS 3 /4.8. 3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATIOM CONDUCTOR OVERCURRENT PROTECTIVE DEVICE LIMITING C0fDITION FOR OPERATION 3.8.3.1 For each containment panetration provided with reouired oenetration

-3 conductor overcurrent protection, each device shall be OPERABLE.

Reouired circuits for all other containment penetrations.shall be deenergized unless energized undar administrative control.

APPLICABILITY: MODES 1, 2, 3 and 4 ACTI0ti:

With one or more of the reouired containment penetration conductor overcurrent protective devices inoperable:

Restore the protective device (s) to OPERABLE status or deenergize the a.

circuit (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; the provisions of Specification 3.0.4 are not apolicable to overcurrent devices in circuits which are deenercized, or b.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , i

With one or fore of tha containment penetration circuits, which are reouired to be deenergized, enercized:

Deenercize the circuit (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or a.

b.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 0 within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i SURVEILt.ANCE RE0VIREMENTS 4.8.3.1.1 Circuit breakers reouired to be OPERABLE as containment onnetration l

conductor overcurrent protective devices shall be demonstrated OPERABLE:

a.

At least once oer 18 months:

1.

For at least one 4.16 KV reactor coolant pump circuit, such that i

all reactor coolant our circuits are demonstrated OPERABLE at least once per 54 months, by oerformance of:

(a)

A CHANVEL CALIBRATION of the associated orotective relays, and (b)

An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and ass >ciated circuit breakers and control circuits function as disigned.

l FARLEY-U41T 2 3/4 8-18 AMENDMENT NO. 62

ELECTRICAL POWER SYSTEMS _

SURVEILLANCE REQUIREMENTS 33335535335EE3333333E335533333333333335535333333333333333333333EBEEEEEEEEEEEEEEEE (c)

For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least one of the circuit breakers of the inoperable type, shall also be functionally tested until no more failures are f ound or all circuit Dreakers of that type have-been functionally tested.

2.

By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers. Ci rcuit breakers selected for functional testing shall be selected on a rotating basis. The functional test shall consist of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed. For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have beer, functionally tested.

b.

At least once per 60 nonths by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.

4.8.3.1.2 Power sources feeding circuits required to be deenergized shall be verified to be interrupted by an open breaker or removed fuse at least once every 31 days.

FARLEY-UNIT 2 3/4 8-19 AMENDMENT NO. 62 i

Pages 3/4 8-20 through 3/4 8-28D have been delated in their entirety.

FARLEY-UNIT 2 3/4 8-20 AMENDMENT NO. 62 l

l

[

REFUELING OPERATIONS 3/4.9.13 STORAGE POOL VENTILATION (FUEL MOVEMENT)

LIMITING CONDITION FOR OPERATION j

3.9.13 Two independent penetration room filtration systems (Specification 3.7.8) shall be OPERABLE and aligned to the spent fuel pool room:

}

APPLICABILITY: During crane operation with loads, over the fuel in the spent fuel pit and during fuel movement within the spent fuel pit.

4 ACTION a.

With one penetration room filtration system inoperable return both

)

systems to OPERABLE status within 48 heurs or suspend all movement

)

of fuel and crane operation with loads over the spent fuel in the storage pool room.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

)

i j

SURVEILLANCE REQUIREMENTS i

4.9.13.1 Two penetration room filtration systems shall betverified to be aligned to the spent fuel pool room within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to fuel handling or crane operations in the storage pool room and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

{

thereafter until fuel movement operations in the storage pool room are suspended.

)

4.9.13.2 The penetration P'oom filtration system shall be demonstrated

]

ODERASLE per the reguirements of Specification 4.7.8.

i 4.9.13.3 At least once per 18 months verify that the normal spent fuel pool system ventilation system will isolate upon receipt of either; j

a.

The spent fuel pool ventilation low differential pressure test L

j signal, or l

b.

A spent fuel pool high radiation test signal.

4 i

e l

l FARLEY-UNIT 2 3/4 9-15

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

-REFUELIh3 OPERATIONS 3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER LIMITING CONDITION FOR OPERATION 3.9.14 The' containment purge exhaust filter shall be OPERABLE and valve N2P13V293 closed.

{

APPLICABILITY:

During CORE ALTERATIONS and Fuel Movement inside containment witn any containment purge isolation valve open.

ACTION:

With the containment purge exhaust filter inoperable either:

1.

Immediately close the 48 inch containment purge isolation valves (CBV-HV-3196, 3197, 3198A and 3198D) and the 8 inch containment mini-purge isolation kalves (CBV-HV-2866C, 2866D, 2867C and 28670), or 2.

Cease all CORE ALTERATIONS and fuel movement.

i e

SURVEILLANCE REQUIREMENTS

== ---

4.9.14 The above required containment purge exhaust filter shall be.

demonstrated OPERABLE:

\\

(

Q a.

At least once per 18 montns or (1) after any structural maintenance on il the HEPA filter or charcoal adsorber housings, or (2) following

,h;',

painting, fire or chemical release that could have contaminated the charcoal adsorbers or HEPA filter in any ventilation zone communicating with the system by:

+

I s

.e em.

i FARLEY-UNIT 2 3/4 9-16 AMENDMENT NO. 73,62

r i

l if s

TABLE 4.11-1 (Continued)

TABLE NOTATION s

The MDC is the smallest.cc,ncentration of radioactive materia'l in a. sample a.

that will be detected p'f.h 95% protability with 5% probabilfly of falsely 3

i concluding that a blank DbservatioT represents a "real" sighal.

For a particularl measurement system (which may inc1,udd r3dicdh mic h.

separation):

-'A' s

)

g 4.6' s A

/

6 MDC =

[

E V

2.22 x 106 Y

exp -Aat) 4 s

Where:

3 c

MDC is the a priori" lower limit of be(tettion as defined abchr' f

(as microcurie per unit mass or voluul, '

h g

y s is the standard deviaticci oiNthe baciq, bound counting rate' cr of tNe counting rate of a blank ssple as appropriate (as counts per t

)+

minute),

E is the counting efficiency (as counts per transformation),

V is the sample size (in, units of mass or volume),

2.22 x 108 is the number of transformations per minu'te per microcurie, Y is the fractionai radiochemical yield (when applicable),

sA is the radioactive decay constqt for the particular radionuclide, and

\\

At is the ejapsed time between midpoint cf. sample collectibn and time of counting (for plant effluents, not'environmenta'tsamples).

The value of s used in the calculation of the HDC for a detection systemshallbIbasedontheactualobservedvarianceofthebackground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted I

variance. Typical values of E, V, Y, and at shall be used in the calculation.

9 L

)

FARLEY-UNIT 2 3/4 11-3

Table 4.11-1 (Continued)

TABLE NOTATION b.

A composite sample is one in which the quantity of liquid sampled'is the metnoc of sampling employed results in a specimen wh representative of the liquids released.. Deviations from com.posite sampling requirements shall be reported per Specification 6.9.1.8.

A batch release is the discharge of liquid wastes of a discrete c.

volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

d.

A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the effluent release.

The principal gamma emitters for which the MDC specification applies e.

exclusively are the following radionuclides:

Co-60, 2n-65, Mo-99, Cs-134. Cs-137, Ce-141, and Ce-144.Mn-54, Fe-59, Co-58 This list does not mean that only these nuclides are to be detected and reported.

with the above nuclides, shall also be identified and report f.

Sampling will be performed only if the effluent will be discharged to

_ I the environmer.t.

Deviation from the MDC requirements of Table 4.11-1 shall be reported g.

per Specification 6.9.1.8.

P 4

e i

FARLEY-UNIT 2 3/4 11-4 i

AMENDMENT NO.7),62 e

5 TABLE 4.11-2 RADIDACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM n

Minimum Minimum Detectable l

fir; Gaseous Release Type Sampling Analysis Type of Concentration (MDC)

Frequency Frequency Activity Analysis jdCi/ml)*h z

U P

P n>

A.

Waste Gas Storage Each Tank Grab Each Tank Principal Gamma Emitters 9 3 lx10-4 Tank Sample P

P h

b Principal Gamma Emitters 9 3 lx10-4 B.

Containment Purge Each Purge Each Purge Grab Sample lx10-6 H-3 C.

Condenser Steam Jet Mbce gb Principal Ganmu Emitters 9 J 1x10-4 Air Ejector, Plant Grab H-3 lx10-6 Vent Stack Sample f

Wd 1-131 lx10-12

$(

D.

Plant Vent Stack, Continuous Containment Purge Charcoal Charcoal Sample I-133 lx10-10 E

Continuousf Wd Principal Gamne Emitters 9 lx10-Il Particulate Sample Continuousf M

Gross Alpha Ix10-Il i

Composite Particulate Sample hk Continuousf Q

Sr-89, Sr-90 lx10-Il i

Composite

{g Particulate n,

5 Sample f

Noble Gas Noble Gases lx10-6 z

F)

Continuous i

Monitor Gross Heta and Gamma cn

. n) 1 J

TABLE 4.11-2 (Continued)

TABLE NOTATION The MDC is the smallest concentration of radioactive material 3n a sample a.

that will be detected with 95% probability with 5% probability of falsely l

concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

MDC =

D E

V 2.22 x 106 Y

exp (-Aat)

Where:

MDC is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

is the standard deviation of the background counting rate or of s b tne counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable).

A is the radioactive decay constant for the particular radionuclide, and at is the elap' sed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of s used in the calculation of the MDC for a detection b

system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

Typicci values of E, V, Y, and At shall be used in the calculation.

e 1

FARLEY-UNIT 2 i

3/4 11-10

\\

Table 4.11-2 (Continued)

TABLE NOTATION b.

Analyses shall. also be performed following shutdown from ).15% RATED THERMAL POWER, startup to > 15% RATED THERMAL POWER or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one

~

hour period.

c.

Tritium grab samples shall be taken from the plant vent stack at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months wnen the refueling canal is flooded.

d.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 2 days following each shutdown from > 15% RATED THERMAL POWER, startup to > 15% RATED THERMAL POWER or THIRMAL POWER change exceeding 15 perceiit of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding MDC may be increased by a factor of 10.

e.

Tritium grao samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool, f.

Tne ratio of the sample flow rate to the sampled stream flow rate shall be known for the time ;,eriod covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.

g.

The principal gamma emitters for which the MDC specifica1! ion applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported, n.

Deviations from MDC requirements of Table 4.11-2 shall be reported per Specification 6.9.1.8.

1.

A composite particulate sample is one in which the quantity of air sampled is proportional to the quantity of air discharged. Either a specimen which is representative of the air discharged may be accumulated and analyzed or the individual samples may be analyzed and weighted in proportion to their respective volume discharged.

Deviations from composite sampling requirements shall be reported per Specification 6.9.1.8.

j. Tne principal gamma emitters for which the MDC specification applies exclusively are the following radionuclides: Kr-87 Kr-88, Xe-133, i

Xe-133m, Xe-135 and Xe-138 for gaseous emissions. This does not mean i

that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

FARLEY-UNIT 2 3/4 11-11 AMENDMENT NO. M,62 l

r

3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C.' power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety-related equipment required for 1) the safe shutdown of the f acility and 2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix "A" to 10CFR50.

The ACTION, requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation comensurate with the level of degradation. The OPERABILITY of the power sources is consistent with the initial condition assumptions of the safety analyses and is based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C.

source.

The OPERABILITY of the minirrum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.

The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recomendations of Regulatory Guides 1.9 " Selection of Diesel Generator Set Capacity for Standby Power Supplies,"* March 10,1971 and 1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977.

The Surveillance Requirements for demonstrating the OPERABILITY of the Station batteries are based on the recommendations of IEEE Standard 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."

3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of overcurrent protection l

circuit breakers during periodic surveillance.

FARLEY-UNIT 2 B 3/4 8-1 AMENDMENT NO. 50 l

l

BASES

=

1.

TE The surveillance requirements aoplicable to lower voltape circuit breakers and fuses orovides assurance of breaker and fuse reliability by testina at least one representative samole of each manufacturer's brand of circuit breaker..and/or fuse.

Each manufacturer's rnided case and wetal case circuit breakers fuses are grouped into reoresentative samales which are then tested on a rotating basis to ensure that all breakers and/or fuses are tested.

it is necessary to divide that manufacturer's breakers and If a wide and treat each grouD as a separate type of breaker or fuses for surveillance purposes.

The OPERABIt.ITY of the motor operated valves thermal overload orotection devices ensures that these devices will not prevent safety related valves from performino their function.

OPERABILITY of these davices are in accordance with Regulatory Gu

" Thermal Overload Protection for Electric Motors on Motor Operated Valves" Revision 1, March 1977.

The tabulation of reouired containment penetration conductor overcurrent orotective devices and circuits which are within the scope of Technical Specification 3.8.3.1 are contained in Farley Nuclear Plant procedures.

circuits identified as of License Amendment 34. procedures include, as a The The crocedures will be controlled in accordance with 10CFR50.59.

e FARLEY-UNIT 2 B 3/4 8-2 AMENDMENT NO. 62 t

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ELEVATION - APPROX 300 FT.

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PROPERTY LINE NOTE: SEE FSAR FIGURE 2.14 FOR TOPOGRAPHICAL MAP OF SITE Figure 5.1-3 Plant Farley Site Map Gaseous Effluents FARLEY - UNIT 2 54 AMENDMENT N0.62

o g-I; a

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_ PROPE_R_TY LINE,(SITE BOLLN, DARY,FQR LIQUID,fFFLUENLS METEOROLOGICAL TOWER

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l Figure 5.1-4 Plant Farley Site Map Exclusion Area and Liquid Effluents FARLEY - UNIT 2 5-5 AMENDMENT NO.62

DESIGN FEATURES 5.3 REACTOR CORE a

FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 1$7 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy -4 Each fuel Tod shall have a nominal active fuel length of 144 inches. The initial core

~

loading shall have a maximum enrichment of 3.2 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.3 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length and no part length control rod assemblies.

The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be reintained:

In accordance with the code requirements specified in Section a.

5.2 of the FSAR, with allowance for norral degradation pursuant to the applicable Surveillance Requirements, b.

For a pressure of 2485 psig, and For a temperature of 650*F, except for the pressurizer which c.

is 680*F.

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9723 1100 cubic feet at a nominal Tayg of 525'F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The neteorological tower shall be located as shown on Figure 5.1-1.

FARLEY-UNIT 2 5-6 AMENDiENT NO. p2 56 i

i

e ADMINISTRATIVE CONTROLS m

E Type of container (e.g., LSA, Type A, Type B, Large Quantity), and e.

j f.

Solidification agent (e.g., cement, urea formaldehyde).

the site to unrestricted areas of radioactive mate effluents on a quarterly basis.

PROCESS CONTROL PROGRAM (PCP) made during MONTHLY OPERATINS REPORT 6.9.1.10 including documentation of all cnallenges to the PORV's U.S. haclear Regulatory Comission, Wasnington, D valves, shall n,

Regional Office of Inspection and Enforcement, no later than the 15th of ne montn following the calencar month covered by the report.

Msnthly Operating Report within 90 days in which th e

effective.

treatment systems shall be submitted with the Monthly period in which the changt was implemented.

or the RADI AL PEAKING FACTOR LIMli REPORT 6.9.1.11 The F limit for Rated Thermal Power (Ffy TP x

tne Director of (ne Regional Office of Inspection and Enforcement) shall b Performance Branch, U.S., haclear Regulatory Comi

, with a copy for ail core planes containing bank "0" control rods and all unrodded core

, D.C. 20555 planes at least 60 day.s prior to cycle initial criticality.

the limit would be submitted at some other time during core lifeIn the event that otherwise exempted by the Commission. submitted 60 days prior to

, it will be Any information needed to support Ffy will be by request from the NRC and neec TP not be included in this report.

ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT 6.9.1.12 start on demand for each diesel generator shall be subm annually.

Position C.3.b of NRC Regulatory Gaide 1.108, Revision 1, FARLEY - UNIT 2 6-19 AMENDMENT NO. 79, 62

\\

ADMIN 1STRATIVE CONTROLS o

h.

Records of annual physical inventory of all sealed source material cf record.

6.10.2 Operating License.Tne following records shall be retained for the duration of the Unit Records and drawing changes reflecting unit design modifications made a.

~

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

b.

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

Records of radiation exposure for all individuals entering radiation c.

control areas.

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

environs.

Records of transient or operational cycles for those unit components e.

identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

Records of training and qualification for current members of the g.

facility staff.

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

1 Records of safety-related Quality Assurance activities required by the Operations Quality Assurance Policy Manual (0QAPM) and not specifically described in Technical Specification 6.10.1.

j.

Records of reviews pe 'ormed for changes made to procedures or equipment or reviews tests and experiments pursuant to 100FR50.59.

k.

Records of meetings of the PORC and the NORB.

1.

Records of secondary water sampling and water quality, Records of analyses required by the radiological environmental m.

monitoring program.

Records of the service lives of all hydraulic and mechanical snubbers n.

within the scope of 3/4.7.9 including the date at which the service life commences and associated installation and maintenance records.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

FARLEY-UNIT 2 6-21 AMENDMENT NO. Q, 62

,

v t e Letter Sequence Other
TAC:60355, (Open) TAC:60356, (Open)
Initiation Request Acceptance... Supplement Administration Questions Answers Results Approval Other: ML20138L026, ML20151Z255, ML20154E847, ML20209E563
MONTHYEAR1986-02-07 [Table View]

ML20209E563

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