ML20070U196

Proposed Administrative Tech Spec Changes Which Will Allow for Better Scheduling of Certain Surveillance Testing

ML20070U196
Person / Time
Site:	Farley
Issue date:	02/01/1983
From:	ALABAMA POWER CO.
To:
Shared Package
ML20070U192	List: ML20070U191 ML20070U196
References
NUDOCS 8302100248
Download: ML20070U196 (29)

Text

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TABLE 3.3-3 (Continued)

ACTION 18 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to CPERABLE st~atus within 48 hou'rs or be in at least HOT STANDBY *

- within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specification 4.3.2.1. ,

t ACTION 20 - With the interlock inoperable to the extent that a safeguards function which should not be blocked in the current MODE is blocked, declare the safeguard function (s) inoperable and follow the aopropriate ACTION statement (s) of Table 3.3-3 for the '

affected function (s).

i Interlo Affacted Channels on Table 3.3-3

1. P I a. Pressurizer Pressure - Low l g

2. P- a. Steam Line Pressure - Low l

b. Steam Flow in Two Steam Lines High Coincident With T,yg-Lw-Low

' ACTION 21Channels - With the number of OPERABLE Channels one less than the Minim OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however; one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for l surveillance testing provided the other channel is OPERABLE.

ACTION 22Number - Withofthe number of OPERABLE Channels one less than the Tota Channels restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 23Minimum - With the number of OPERABLE channels one less than the Number of Channels, operation may proceed until i

performance of the next required CHANNEL FUNCTIONAL TEST.

~ g8 8302100248 830201 PDR ADOCK 05000348 -

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AMEN 0 MENT P0.

FARLEY-UNIT 1 3/4 3-24

TA8LE 3.3-10

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E HIGH ENERGY LINE BREAK ISOLATION INSTRIMEN1ATION

Q.

i a MINIMUM

! 5 OPERABLE

• " INSTRUMENT CHANNEL ' SENSOR LOCATION CHANNELS l

! 1. Pressure Switches RNR /ksrExcHws.

d'- %n G.89 Pr. 1 s

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a. PDSH 3367 A,B

b. 'PSH 2850 A,0 Auxiliary Feedwater Pump Room El. 100 ft. I j

j B,F Equipment Room E1. 100 ft. 1 C,E Auxiliary Feedwater Pump Room Corrider El. 100 ft., 1 i

c. PSH 2851 A,F f

MtCCLtHoldup Tack Room El. 1 1 ft. 1 I l B,C Moderating Heat Exchanger Rom E1.121 ft. 1 DE Moderating Heat Exchanger Valve Room El. 121 ft. 1

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Y d. PSH 2852 A.H Piping Penetration Hoca El. 100 ft. 1

E B,C,0,E Letdown Heat Exchanger Rooe E1. 100 ft. 1 F,G, h Holdup Tank Race El. 121 ft. 1 l

) &M I i e. PSH 2853 A,B Piping Penetratio1 Ro.nu FL. 121 f t.

C,0 Blowdown Heat Excl anpar 'Aoom El 120 f t. 1 E.F Corridor El. 121 ft. 1 l

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f TABLE 3.3-10 (Continued) .

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MINIMIM Q OPERABLE a

' CHANNELS SENSOR LOCATION

. 5 INSTRUMENT CHANNEL

• PSH-2853 G,H Recycle Evaporator Room El. 121 ft. 1 j .- 1,J Corridor (1. 121 ft.CI) m o .1 l

Scusce FewsA Moom EL.111 FT.(d.

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2. . Flooding Detectors i

Main Steam Room El. 127 ft. 2 1 a. LSH 2828 A.B.C t '

LSH 2829 A,8,C Main Steam Room E1. 127 ft. . 2 I b.

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TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION I

Auxiliary Building Total Minimum Room / Smoke Of Operable Fire Zone Description Elevation Detectors Smoke Detectors 128 RHR Heat Exchanger Room 83'-0" 10 5 129 RHR Low Head Pump Room 77'-0" 1 1 131 RHR Low Head Pump Room 77'-0" 1 1 160 Hatch Area 100'-0" 3 2 161, 162, 163 South Corridor 100'-0" 7 4 172 Hallway 100'-0" 3 2 173 Charging /SI Pump Room 100'-0" 2 1 174 Charging /SI Pump Room 100'-0" 2 1 175 Hallway 100'-0" 2 1 181 Chargir.g/SI Pump Room 100'-0" 2 1 384 Mcchanical Penetration Room 100'-0" 8 4 i 185 CCW Heat Exchanger and Pump 100'-0" 13 7 186 Boric Acid Trans. PPS 100'-0" 3 2 188 Boric Acid Tanks 121'-0" 2 1 100'-0" 190 MCC Panel Room .4 2 191 Auxiliary Feedwater Pump Room 100'-0" 1 1

192 Auxiliary Feedwater Pump Room 100'-0" 1 1 193 Auxiliary Feedwater Pump Room 100'-0" T 2. 1 l 202 Communications Rooms 121'-0" 4 2 208, 207 Corridor .- 121'-0" 4 2 j

(' 209 Hallway , 121'-0" 4 2 210, 211, 228 234 South Corridor 121'-0" X7 %It l 212 Battery Room 1A 121'-0" 1 1 213 Battery Service Room 121'-0" 1 1 214 Battery Room 18 121'-0" 1 1 223 Mechanical Penetration Room 121'-0" 9 5 224 DC Saitchgear Room 121'-0" 1 1 225 Battery Charger Room 121'-0" 1 1

! 226 DC Switchgear Room 121'-0" 1 1 227 West Cable Chase 128'-0" 7 4 229 AC Switchgear Room Train B 121'-0" 4 2 i

233 AC Switchgear Room Train B 121'-0" 3 2 1

241 Main Steam and FDW Viv. Rs. 127'-0" 8 4 244 Mezzanine - Battery Room 131'-0" 3 2 j 245 Mezzanine - Battery Room 131'-0" 3 2 254 Hot Shutdown Panel Room. 121'-0" 1 1 l 300 West Cable Chose 139'-0" 7 4 312 Corridor 139'-0" 3 2 316, 322 Corridor 139'-0" 3 2 318 Cable Spreading Room 139'-0" 8 4 319, 339,3 45 West Corridor 139'-0" TJo T3 l 333 Electrical Penetration Roca 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 Electrical Penetration Room 139'-0" 2 1 FARLEY-UNIT 1 3/4 3-60 AMENDMENT NO.

. - - _ _ _ __,..-y_ . _ . . _ _ ,,. .- ------ ,--, - - - - - - -

TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION

}

(Continued)

Auxiliary Building Total Minimum Room / Smoke Of Operable Fire Zone Description Elevation Detectors Smoke Detectors 401 Control Roorn (dove ceilid 155'-o" 13 7 401 Control Room (.below esih'nf) 155'-0" X3 K 2.

440, 455, 456 Clean Toilet, Laundry and Drying Areas 155'-0" 3 2 462 Non-Radioactive Vent Equip. Rs. 155'-0" 5 3 465 Vertical Cable Chase

• 155'-0" 3 2 466 Vertical Cable Chase 155'-0" 4 2 500 Vertical Cable Chase 168'-2" 7 4 414 Canbt Roorn Instevenent Racks 15 5'-o" S 4 l

, Containment

• 55 Containment Coolers 155'-0" 12/ Fan 6/ Fan 55 Containment 155'-0" 11 6 Service Water Intake _, Structure 72 A Pun.p Room Area 186'-9" 12

• 6 72 A Strainer Bay 167'-0" 12 6 72 B Switchgear Room - Train B 188'-9" #3 E 2. I 72 C Foyer - Train B 188'-9" 1 1 g

72 D Foyer - Train A 188'-9" 1 1 72 E Switchgear Room - Train A 188'-9" K3 X 2. l 73 Battery Room - Train B 188'-9" ~

1 1 74 B utery Room . Train A IB8'-9" 1 1 Diesel Generator Buildino l'

56 A Switchgear Room -Train A 155'-0" 12 6 56 B Foyer 155'-0" 4 2 l 56 C Switchgear Room - Train B 155'-0" 12 6 71 Hallway 155'-0" 9 5 Diesel Generator Buildina (Heat Detectors) 57 Diesel Driven Generator 2C 155'-0" 5 3 58 Diesel Driven Generator 18 155'-0" 5 3 60 Diesel Driven Generator 1C 155'-0" 5 3 61 Diesel Driven Generator 1-2A 155'-0" 5 3 62 Day Tank Room S.C. 155'-0" 1 1 63 Day Tank Room tB 155'-0" 1 1 65 Day Tank Room tc.

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

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l- The Fire Detection instruments located within the Containment are not required

( to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

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FARLEY-UNIT 1 3/4 3-60a -

AMENDMENT NO.

. EMERGENCY CORE COOLING SYSTEMS

')

SURVEILLANCE REQUIREMENTS (Continued)

b. At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the accumulator solution.

c. At least once per 31 days when the RCS pressure is above the P-11 setpoint by verifying that power to each isolation valve

, operator is disconnected by a locked opendisconnei irc:h;r. k dEv8CE - k

d. - At least once per 18 months by verifying that each accumulator isolation valve opens automatically under each of the following conditions:

1. When the RCS pressure (actual or simulated) exceeds the P-11 (Pressurizer Pressure Block of Safety Injection) setpoint,

2. Upon receipt of a safety injection test signal.

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FARLEY-UNIT 1 3/4 5-2 AMENDMENT NO.

. . EMERGENCY CORE COOLING SYSTEMS

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SURVEILLANCE REQUIREMENTS .

4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with the d x'ur to the valve y operators locked open: dscemed;ky[ce, s Valve Number Valve Function Valve Position

a. 8884, 8886 Charging Pump Closed to RCS Hot Leg

b. 8132A, 8122B Charging Pump Open*

discharge isolation

c. 8889 RHR to RCS Hot Closed Leg Inject ton

b. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c. By a visual inspcction which verifies that no loose debris (rags; trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1. For all accessible areas of the. containment prior to establishing CONTAINMENT INTEGRITY, and

2. Of the areas affected within containment at the completion of

each containment antry when CONTAINMENT INTEGRITY is established. ,

d. At least once per 18 months by:

1. Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure 1 750 psig.

g icopsig a,nd

2. A visual inspection of the containment Emp and verifying that

'the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, inner cages) are properly installed and show no evidence of structural distress or corrosion.

"Will be verified if charging pump 1A is declared inoperable.

3/4 5-4 AMENDMENT NO.

FARLEY-UNIT 1 .

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CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM y LIMITING CONDITION FOR OPERATION

3. 6.1. 7 The 48-inch containment purge supply and exhaust isolation valves (C8V-HV-3198A,31980,3196,3197) shall be closed. The g-inch containment lg peepgsupplyandexhaustisolationvalvesmaybeopen. 8 APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With one 48-inch containment purge supply and/or one exhaust isolation valve i open, close the open valve (s) within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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_S_URVEILLANCE REQUIREMENTS j

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4.6.1.7.1 The 48-inch containment purge supply and exhaust isolation valves shall be determined closed at least once per 31 days.

e verld 4.6.1.7.2 The valve seals of the 48-inch and the 16-inch peege supply and l-exhaust isolation valves shall be replaced at least once per 5 years.

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FARLEY-UNIT 1 3/4 6-10 AMENDMENT NO.

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'i I TABLE 3.7-7 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES

' LOCATION HYDRANT NUMBER

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N'^^^=~^^

E ". _ . .: . _ _ _

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=-F- -g West of Auxiliary Building N1Y43V103h 1.'% ,

West of Service Water Intake N1Y43V121 4 2.W N1Y43V122 k 3.ji$ East of Service Water Intake North of Diesel Generator Building N1Y43V120k 4.5$

5.)( East of Auxiliary Building N1Y43V089 Northeast of Diesel Generator Building N1Y43V090 4.%

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FARLEY-UNIT 1 3/4 7-93

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ELECTRICAL POWER SYSTEMS J

SERVICE WATER BUILDING D.C. DISTRIBUTION - OPERATING

_ LIMITING CONDITION FOR OPERATION 3.8.2.5 The following D.C. distribution systems shall be energized' and OPERABLE:

t TRAIN "A" consisting of 125-volt D.C. Distribution Cabinet 1M, 125-volt

battery bank No. 1 and a full capacity charger.

TRAIN "B" consisting of 125-volt D.C. Distribution Cabinet 1N, 125-volt battery bank No. 2, and a full capacity charger.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION

With one 125-volt D.C. distribution train inoperable restore the inoperable l distribution system to OPERABLE and energized status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

y SURVEILLANCE REQUIREMENTS W

4.8.2.5.1 Each D.C. train shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated , ,

power availability.

4.8.2.5.2 Each 125-volt battery bank and charger shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that:

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! 1. The electrolyte level of the pilot cell is between the minimum and maximum level indication marks. .

2. The pilot cell specific gravity, corrected to 77'F and full -

i electrolyte level, is greater than or equal to 1.190, and ,

3. The pilot cell voltage is greater than or equal to 2.02 volts. .

4. .The total battery terminal voltage is greater than or equal to 121.2 volts.

b. At least once per 92 days by verifying that:

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1. um and .

I Theelectrolytelevelofeachcellisbetweenthed maximum level indication marks, 4.g2.G.2 j 4 Excs.pt duciw3 pertermance oF Surw.il\nme. Requ{mmeE44 4.2 5 2 e. . D u r m, g %, ,

l tast, one, tmin may be. inopuabk ontI the. lodtery is rtcharged Ollowiy eom$7et/so i FARLEY-UNIT 1 AMEN 0 MENT NO.

j of the. behy Ssaav3 test.3/4 8-12 l

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. ELECTRICAL POWER SYSTEMS I

SURVEILLANCE REQUIREMENTS (Continued)

2. The voltage of each connected cell is greater than or equal to 2.02 volts under float charge and has not decreased more than 0.1 volts from the value observed during the original acceptance test, and

3. The specific gravity, corrected to 77'F and full electrolyte level, of each connected cell is greater than or equal to 1.190 and has not decreased more than 0.08 from the value observed during the previous test.

- c. kt least once per 18 months by verifying that:

1. The cells, cell plates and battery racks show no visual ,

indication of physical damage or abnormal deterioration,

2. The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material, and

3. The battery charger will supply at least 3 amperes at > 125 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. gjg ,

d.' At least once per 18 months r fr ' ; dutfr , by verifying that the I battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when the battery is subjected to a battery service test or the individual cell voltage does not decrease below 1.75 volts when the battery is subjected to the following equivalent load profile:

Order in Which Current Loads are Applied (amps) Duration  !

j .

1 25 0 - 0.1 sec 2 1- 0.1 sec - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> i

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- FARLEY-UNIT 1 3/4 8-13 AMENDMENT NO.

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ELECTRICAL POWER SYSTEMS

'l SURVEILLANCE REQUIREMENTS (Continued)

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e. At least once per 60 months, dur':;; eu"- ; by verifying that the l battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. This performance discharge '

test shall be performed subsequent to the satisfactory completion of the required battery service test.

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FARLEY-UNIT 1 3/4 8-14 AMENDMENT NO.

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Figure 6.2-2 Facility Organization

• "In routine matters, the Chemistry and llealth Physics Supervisor reiports' direct 19"to the Technical superintendent, in matters of radiation policy determination, interpretation or implementation (based upon the Chemistry and llealth Physics Supervisor's judgment) the Chemistry and llealth Physics Supervisor may report directly to the Assistant Plant flanager.

ADMINISTRATIVE CONTROLS

g. ReportsandmeetingsminutesofthePORC.

h. Proposed changes to Technical Specifications or this Operating License.

i. The safety evaluations for proposed 1) procedures 2) changes to procedures, equipment or systems and 3) test or experiments completed under the provision of Section 50.59 10 CFR, to verify that such actions did not ccnstitute an unreviewed safety question.

AUDITS 6.5.2.8 The following audits shall be conducted under the direction of APCO's Manager - Safety Audit and Engineering Review:

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire facility staff at least once per 12 months.

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c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

(.( The performance of activities required by the Operational Quality I( d.

Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.

e. The Facility Emergency Plan at least once per 24 months.

f. The Facility Security Plan at least once perg months. l

g. Any othe'. area of facility operation considered appropriate by the NORB or the Senior Vice President.

h. The Facility Fire Protection Program and implementing procedures at l 1 east once per 24 months.

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1. An independent fire protection and loss prevention program inspection and audit of the unit at least once per 12 months utilizing either i

qualified offsite licensee personnel or an outside fire protection ffrm.

j. An inspection and audit of the unit fire protection and loss prevention program by a qualified outside fire consultant at least I once per 36 months.

k. The radiological effluent and environmental monitoring programs and the results thereof at least once per 12 months.

6-11 AMENDMENT NO.

FARLEY-UNIT 1

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. ADMINISTRATIVE CONTROLS

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EN NMENT ALIFICATION /

1 16 By no 1 ter than June 0,1982 all safety related eJectrical equipment l 6./he in facili). .shall be quqTified in ach' dance with the provisions of: /

Division of Operating React 6rs "Guidelipes for Evaluating / Environmental /

ualification of Class 1E/tlectrical Equipment in Operating Reactors" (00R /

lifi-Guidelines); or, NUREG-0588 " Interim Ataff Position on Environmental Qua/ these cation f Safety-Related Electrical Equipment," f December 1979. Copies docu nts are attached to the Order for Modification of License No. NP -2 dated ucto er 24, 1980. f

/

6.2 By no later than December 1,1980, comple and auditibl ecords mus

[beavailableapdmaintainedatacentrallocati,gnwhichdescribe/e he environ mentalqualificationmethodj6sedforallsafety-relatedelecttjcalequipnen, in sufficient petail to docunjent the degree of compliance with the 00R Guide}fnes orNUREG-9588. Thereaftei- suchrecordsstd'uldbeupdatedgdmaintained 3

current ([s equipment 1/ rep, laced, furtherft ested, or othe ise further qualified. ( , /

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6-27 AMENDMENT NO.

FARLEY-UNIT 1

. I TABLE 3.3-3 (Continued) ._

ACTION 18 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following

.- . 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b. The Minimus Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 - With the interlock inoperable to the~extrat that a safeguards function which should not be blocked in the current MODE is blocked, declare the safeguard function (s) inoperable and follow the appropriate ACTION statement (s) of Table 3.3-3 for the affected function (s).

Interlock Affected Channels on Table 3.3-3

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. 1. gig a. . Pressurizar Pressure - Low l

2. P-12 a. Steam Line Pressure - Low

b. Steam Flow in Two Steam Lines High Coincident With T,,g-Low-Low ACTION 21 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the followinsi 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however; one channel may be bypassed for.up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE Channels one less than the Total Number of Channels restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 23 - With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST.

( . .

3/4 3-24 Amendment No.

FARLEY-UNIT 2 I

< TABLE 3.3-10 HIGH ENERGY 'LINE BREAK ISOLATION INSTRUMENTATION r- '

i Q e E MINIMUM Q OPERABLE m INSTRUMENT CHANNEL SENSOR LOCATION CHANNELS

1. Pressure Switches

• AM2 Henr[scinac a

a. PDSH 3367 A,B  ?'~"_'.""" L;; f. .; yat &m GL.83 fr.

i [

1

b. PSH 2850 A,0 Auxiliary Feedwater Pump Room El. 100 ft. 1 B,F Equipment Room E1. 100 ft. .

1 C,E Auxiliary Feedwater Pump Room Corrider El. 100 ft. I

c. PSH 2851 A,F Holdup Tank Room E1. 121 ft. 1 I

] B,C Moderating Heat Exchanger Room E1. 121 ft. 1 i w D,E Moderating Heat Exchanger Valve Room E1. 121 ft. 1 w d. PSH 2852 A.H Piping Penetration Room E1. 100 ft. 1 di B,C,D,E Letdown Heat Exchanger Room El. 100 ft. 1

• F,G, isoste Holdup Tank Room El.121 ft. 1 l

e. PSH 2853 A,B i Penetration Room EL. 121 ft. 1 C,D Blowdown Heat Exchanger Room El 130'ft. I

! EF C:rr Mer E!. ??? ft. 1

$2Cfew SYM)90KMbd M GL./ZJ ff.

\ \ '

1. 1-

.- m TABLE 3.3-10 (Continued)

S n MINIMUM-Q .-

OPERABLE cE CHANNELS SENSOR LOCATION t 3

-4 INSTRUMENT CHANNEL 1

N PSH-2853 G,H Recycle Evaporator Room E1. 121 ft.

i . . i2; 'i. 1  ;

I,J 0;.;cm . ;ii., a 5 Camm Et I2.1 Yf.Ct) Ana b TADOWA b*%*

2. Flooding Detectors g oew n g g ,/3 0 p r. (; f) 2

a. LSH 2828 A,B,C Main Steam Room E1. 127 ft.

2

b. LSH 2829 A,B,C Main Steam Room El. 127 ft.

R.

Y lN l

/

~

W t

TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION

'},

~

Auxiliary Building l Total Minimum Smoke Of Operable Room / Smoke Detectors Fire Zone Description Elevation Detectors

~

2128 RHR Heat Exchanger Room 83'-0" 10 5 2129 RHR Low Head Pump Room 77'-0" 1 1 RHR Low Head Pump Room 77'-0" 1 1 2131 1 2160 Hatch Area 100'-0" 2 100'-0" 2 1 l 2161 South Corridor 2 2172 100'-0" 3 2173 Hallway Charging /SI Pump Room 100'-0" 2 1 100'-0" 2 1 Charging /SI Pump Room l 2174 1 2175 100'-0" 2 Hallway 1 2181 Charging /SI Pump Room 100'-0" 2 4

2184 Mechanical Penetration Room 100'-0" 8 CCW Heat Exchanger and Pump 100'-0" 13 7 2185 2 1 2186 Boric Acid Trans. PPS 100'-0" 3 121'-0" 2 1 2188 Boric Acid Tanks 4 2 2190 MCC Panel Room 100'-0" Auxiliary Feedwater Pump Room 100'-0" 1 1 2191 2192 Auxi13ary Feedwater- Pump Room 100'-0" XI 1 l' 2193 Auxiliary Feedwater Pump Room 100'-0" $2. 1 y

( 121'-0" 4 2 2202 Hot Shutdown Panel Room 1 121'-0" 2 2208 Corridor 2 2209 Hallway 121'-0" 3

- 121'-0" 2 1 2210 South Corridor 1 1 2212 Battery Room 1A T121'-0" 121'-0" 1 1 2213 Battery Service Room 1 2214 Battery Room IB 121'-0" 1 121'-0" 9 5 2223 Mechanical Penetration Room 1 l 2224 DC Switchgear Room 121'-0" 1 121'-0" 1 1

! 2226 DC Switchgear Room 4 128'-0" 7 l

2227 West Cable Chase 2 AC Switchgear Room Train B 121'-0" 4

! 2229 2 2233 AC Switchgear Room Train B 121'-0" 3 l

127'-0" 8 4 2241 Main Steam and FDW Viv. Rs.

2244 Mezzanine 131'-0" T3 E 2. l

- 131'-0" 2 1 2245 Mezzanine 1 2254 Hot Shutdown Panel Room 121'-0" 1 139'-0" 7 4 2300 West Cable Chase 1 139'-0" 1 2309 Hatch Area 4 2 2312 Corridor 139'-0"

_139'-0" 2 1 2316 Corridor 8 4 2318 Cable Spreading Room 139'-0" 139'-0" 2 1 2319 West Corridor 1 1 2333 Electrical Penetration Room 139'-0" 139'-0" 3 2 ,s 2334 Electrical Penetration Room 2

( 2335 AC Switchgear Room Train A 139'-0" 3 139'-0" 3 2 s 2343 AC Switchgear Room Train B 1 2347 Electrical Penetration Room 139'-0" 2 FARLEY-UNIT 2 3/4 3-60

l TABLE 3.3-12 e FIRE DETECTION INSTRUMENTATION (Continued)

Auxiliary Building Total Minimum Room / Smoke of Operable Fire Zone Descriotion Elevation Detectors Smoke Detectors 200 # Oonhol Room (above ceilin 155 '-O lb B 240:.4 Control Room (belm ceili ') 155'-0" K3 K1 Storage Area 155'0" 7 4 2452 2462 Non-Radioactive Vent Equip. 155'-0" 5 3 Rm.

West Cable Chase 155'-0" 7 4 2466 2471 4 Control Rm. (Instrument 155'-0" KT K5 l Racks)

West Cable Chase 168'-2" 7 4 2500 Containment

• Containment Coolers 155'-9" 12/ Fan 6/ Fan 55 55 Containment 155'-0" 14 7 Service Water Intake Structure

'( N Pump Room Area 188'-9" 12 6 72 72 A* A+ Strainer Bay 167'-0" 12 6 4 Switchgear Room - Train B 188'-9" K3 %2.

72 72 C4 B +4 Foyer - Train B 188'-9" 1 1 Foyer - Train A 188'-9" 1 1 72 DM 72 EM Switchgear Room - Train A 188'-9" 1<3 E 7-Battery Room - Train B 188'-9" 1 1 73M 1 74M Battery Room - Train A 188'-9" 1 Diesel Generator Building I 56 A Switchgear Room - Train A 155'-0" 1.2 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) l 57 Diesel Driven Generator 2C 155'-0" 5 3 155'-0" 5 3 59 Diesel Driven Generator 2B ~

60

• Diesel Driven Generator 1C 155'-0" 5 3 155'-0" 5 3 61 Diesel Driven Generator-1-2A 1 62 Day Tank Room '2C. 155'-0" 1 155'-0" 1 1 64 Day Tank Room 2.B 1 Day Tank Room ic 155'-0" 1 65 1 155'-0" 1

(( 66 Day Tank Room g -2. A

• N5e c.ir<dits <dArm in Unit i kot arc. not required by Onit i Tednial SpeJA'cd,* ens. i

• The Fire Detection instruments located within the Containment are not required-4 We. c.ivtsts akm in Unit I an A are required by 04t t Te&M spaAwns (

3/4 3-60a Amendment No.

FARLEY-UNIT 2

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) ,

b. At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tan.k volume by

... verifying the boron concentration of the accumulator solution.

c. At least once per 31 days when the RCS pressure is above the P-11 setpoint by verifying that power to each isolation valve operator is disconnected by a locked open, tree %- .Aev.

dsseaueN es.

I

d. At least once per 18 months by verifying that each accumulator isolation valve opens automatically under each of ,the following conditions:

1. When the RCS pressure (actual or simulated) exceeds the P-11 (Pressurizer Pressure Block of Safety Injection) setpoint,

2. Upon receipt of a safety injection test signal.

1 l le 1

I FARLEY-UNIT 2 3/4 5-2 l

__a____._

l _.. ., . , _ _ _ _ _ _ . .._.. .._ .~ .. _ _ .. ~.__ .___ _ _. _ _ _ - _ _ _ . . _ _ . . _ . _ - _ _ _ . _ . _

I EMERGENCY CORE COOLING SYSTEMS h)

SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS. subsystem shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with the "-"-- to the valve g operators locked open: Jiscoucci dvice. l Valve Number Valve Function Valve Position -

l

a. 8884, 8886 Charging Pump Closed .

to RCS Hot leg

b. 8132A, 81328 Charging Pump- Open*

discharge isolation

c. 8889 RHR to RCS Hot Closed Leg Infection

b. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct ,

( positio'n.

\

)}'

c. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present.in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1. For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and

2. Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.

d. At least once per 18 months by:

1. Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressureM l

. 700 is e psia muut750 ed psig. i

2. A visual inspection of the containment Yump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, inner cages) are properly installed and show no evidence of structural j

( distress or corrosion.

"Will be verified if charging pump is declared inoperable. l l

FARLEY-UNIT 2 3/4 5-4

~.

TABLE 3.7-7 g ,

YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES HYDRANT NUMBER LOCATION Northeast of Auxiliary Building N1Y43V105 1.

North of Auxiliary Building N1Y43V102 2.

N1Y43V103 Y i

3. West of Auxiliary Building North of Diesel Generator Building N1Y43V 4.

West of Service Water Intake N1Y43V121k 5.

N1Y43V122 k

6. East of Service Water Intake

\. \ _,

$$f h .

WR l 4.

s FARLEY-UNIT 2 3/4 7-63 p

.. ELECTRICAL POWER SYSTEMS

.(- i SERVICE WATER BUILDING D.C. DISTRIBUTION - OPERATING u'

LIMITING CONDITION FOR OPERATION 3.4.2.5 The following D.C. distribution systems shall be energized and OPERABLE:

TRAIN "A" consisting of 125-volt D.C. Distribution Cabinet 2M, 125-volt battery bank No.1 and a full capacity charger.

TRAIN "B" consisting of 125-volt D.C. Distribution Cabinet 2N, 125-volt battery bank No. 2 and a full capacity charger.

APPLICABILITY: MODES 1, 2, 3 and 4.

j ACTION:

With one 125-volt D.C. distribution system inoperable restore the inoperable _ l distribution system to OPERABLE and energized status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

i -

t SURVEILLANCE REQUIREMENTS 4.8.2.5.1 Each D.C. bus train shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated l

power availability with an overall voltage of greater than or equal to

! 121.2 volts. ,

l 4.8.2.5.2 Each 125-volt battery bank and charger shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that:

1. The electrolyte level of each pilot cell is between the minimum and maximum level indication marks,

2. The pilot cell specific gravity, corrected to 77*F and full electrolyte level, is greater than or equal to 1.190, and

3. The pilot cell voltage is greater than or equal to 2.02 volts.

b. At least once per 92 days by verifying that:

1. The electrolyte level of each cell is between tha sqinimum and

maximum level indication marks, .

4.94 5Ad. and .

~/ -(t Except durmg performance. d Soncittanca. Rex lutftmentgt4.9.2 5'.2.e. . Durt this tes,t, one. tmin ma.y be inopemWe until Be bottery is rec.hese.

fol%iwa completion d h bettsvy disches.Mt.

FARLEY-UNIT 2 3/4 8-15

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. The voltage of each connected cell is greater than or equal to 2.02 volts under float charge and has not decreased more than

- 0.1 volts from the value observed during the original acceptance test, and

3. The specific gravity, corrected to 77'F and full electrolyte level, of each connected cell is greater than or equal to 1.190 and has not decreased more than 0.08 from the value observed

1. during the previous test.

c. ,

At least once per 18 months by verifying that:

1. The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration,

2. The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material, and

3. The battery charger will supply at least 3 amperes at > 125 volts _

. for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. g At least once per 18 montht; * ' z f f '- . by verifying that the l di battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when the battery is subjected to a battery service test or the individual cell voltage does not decrease below 1.75 volts when the battery is subjected to the following equivalent load profile:

Order in Which Current Loads are Applied (amps) Duration 1 25 0 - 0.1 sec

(

. 2 1- 0.1 see - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> O

l

(

FARLEY-UNIT 2 3/4 8-16 Amendment No.

r .

. ELECTRICAL POWER SYSTEMS

(

SURVEILLANCE REQUIREMENTS (Continued) g-dekEc

e. At least once per 60 months,~" ' ; '- ^f:.: ., by verifying that the I battery capacity is at least 80% of the manufacturer's rating when -

subjected to a performance discharge test. This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test.

l FARLEY-UNIT 2 3/4 8-17

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• a Yo *"aY

• • SL- Senior Operator's License

"" * - Reactor Operators wHi have Operator's L8eense -

l 1. ** - Oneite Responenduty f6r Fire Protection Progreen

Figure 6.2-2 Facility Organization - Joseph M. Farley - Unit No. 2

• • • In routine matters, the Chemistry and Health Physics Supervisor reports directly to the Technical Superintendent, in matters of radiation policy determination, interpretation or implementation (based upon the Chemistry and Health Physics Supervisor's judgment) the Chemistry and Health Physics Supervisor may report directly to the Assistant i

Plant Manaaer.

ADMINISTRATIVE CONTROLS

.(.

i.; p g. Reports and meetings minutes of the PORC.

h. Proposed changes to Technical Specifications or this Operating -

License.

1. The safety evaluations for proposed.1) procedures 2) changes to procedures, equipment or systems and 3) test or experiments completed under the provision of Section 50.59 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

AUDITS ,

6.5.2.8 The following audits shall be conducted under the direction of APCO's Manager - Safety Audit and Engineering Review:

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire facility staff at least once per 12 months. _

c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

t

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.

e. The Facility Emergency Plan at least once per 24 months.

f. The Facility Security Plan at least once pe months. l

g. Any other area of facility operation considered appropriate by the

! NORB or the Senior Vice President.

h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

i. An independent fire protection and loss prevention program inspection and audit of the unit at least once per 12 months utilizing either I

qualified offsite licensee personnel or an outside fire protection I firm.

! j. An inspection and audit of the unit fire orotection and loss preven-tion program by a qualified outside fire consultant at least once per 36 months.

( k. The radiological effluent and environmental monitoring programs and the results thereof at least once per 12 months.

7 l

J .

6-11 FARLEY-UNIT 2

E m

POWER STPROGk /

AUGMTED .

I r the co ucting o the augm ted low ower tes program nly (lic ee letter o November 8, 1980) the lice ee has been grant d an exem ion from t require nts of th e Techni al Spec' Ications dentifie in

. Table of the RC Safety valuatio Repor closed w h Amendm t2 the acility icense NPF .

f (

S e

(

i l

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t k

FARLEY-UNIT 2 7-1

, 1