Text

Amends 33 & 26 to Licenses NPF-2 & NPF-8,respectively,making Administrative Changes to Tech Specs Re Administrative Controls for Onsite & Offsite Organization & Environ Qualification Audits
	ML20081B596
Person / Time
Site:	Farley
Issue date:	10/14/1983
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20081B599	List: ML20081B596; ML20081B625;
References
	TAC-51999, NUDOCS 8310280092
	Download: ML20081B596 (46)
	v • d • e

a b

f UNITED STATES j g

[ }

NUCLEAR REGULATORY COMMISSION s..A / ;j WASHINGTON. O. C. 20555 s

~ "

%,.....f ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPHMFARLEYNUCLEIRP[ ANT,UNITNO.1

~

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. NPF-2

1. T.he Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Alabama Power Company (the licensee) dated November 16, 1982 supplemented by letters dated February 1, 1983 and June 29, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I;

~

B.

The facility will operate 1n conformity with the application, the provisions of the act, and the rules and regulations of the Comission; 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; v

and E.

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

s s

8310280092 831014 PDR ADOCK 05000348 P

PDR

a 2

2.

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

(2)

Technical Scecifications The Technical Specifications contained in Aopendices A and B, as revised through Amendment No. 33, are hereby incorporated in the license.

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

3.

This license amendment is effective as cf the date of its issuance.

FOR THE NUCLEAR REGULATORY CCMMISS:CN J

teven a.\\hb@l lar f

Operating Reactors ranch fl Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: October 14, 1983

4

,u n r.,,

"6 UNITED STATES J

-[ j. q/' j NUCLEAR REGULATORY COMMISSION 4 'J, y WASHINGTON. D. C. 20555 3

1 ""

./ /

i ALABAMA POWER COMPANY DOCKET NO. 50-364-JOSEPH M.FARLEY NUCLEAR PLANT, UNIT NO. 2

' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.26 License No. NPF-8

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

A.

The application for amendment by Alabama Power Company (the licensee) dated November 16, 1982 supplemented by letters dated February 1, 1983 and June 29, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and rdgulations set forth in 10 CFR Chapter I;

~

B.

The facility will operate in conformity with the application, the provisions of the act, and the rules and regulations of 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 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 requirements have been satisfied.

c-,

r

,. - - -,, +.., -,,. -.

,e-c.

2 2.

Acccedingly, the -license is amended by enanges to ne Tecnnical Specifications as in41cated in the attachment tc this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is herecy amended to read as folicws:

)

(2) Technical Scecifications The Technical Specifications centained in Accencices A and 3, as revised thrcugn Amencment No. 26, are hereby incer; crated in the license. The licensee snail operate the facility in acccrdance with the Tecnnical Scecifications.

This license amendment is effec-ive as of the cate of 1:s issuance.

3.

FOR THE '4UCLEAR REGULATCRY CCMNISS:CN O\\

i i.

--~

teven A. Varga,'Y L

s

Chief, Operating Reacters Bran'em #1 Oivision of Licensing l

~

Attachment:

Changes to the Technical Specifications Date of Issuance: October 14, 1983

~

G\\

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0. 33 i0 FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-24 3/4 3-24 3/4 3-54 3/4 3-54 3/4 3-55 3/4 3-55 3/4 3-60 3/4 3-60 3/4 3-60a 3/4 3-60a 3/4 5-2 3/4 5-2 3/4 5-4 3/4 5-4 3/4 6-10 3/4-6-10 3/4 7-87 3/4 7-87 3/4 7-93 3/4 7-93 3/4 8-12 3/4 8-12 3/4 8-13 3/4 8-13 3/4 8-14 3/4 8-14 6-2 6-2 6-3

'6-3 6-4 6-6 6-9 6-9 6-10 6-10

[

6-11 6-11 6-13 6-13 l

6-14 3-14:

6-27' deleted l'

l

\\

.-- ~.

.--., + -.--

l TABLE 3.3-3 (Continued) n 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANOBY 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 .

ACTION 19 - With the number of OPERABLE Channels one less than the Tut.a1 Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

The inoperable channel is placed in the tripped condition a.

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel m2y be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per Specification 4.3.2.1.

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 appropriata ACTION statement (s) of Table 3.3-3 for the affected function (s)..

i Intarlock Affected Channels on Table 3.3-3

1. P-11

a.. Pressurizar Pressure - Low

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however; one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other channel is OPERA 8LE.

ACTION 22 - With the number of OPERABLE Channels one less than the Total Number of Channels restore the inoperable channel to OPERA 8LE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

1 e

AMENDMENT NO. 33 FARLEY-UNIT 1 3/4 3-24

i 4

TA8tE 3.3 0 HIGH ENERGY LINE BREAK 150LA110N INSTRUMENTATION

~

2,..

MINIHuH OPEIMLE CHNINELS

4 SENSOR LOCATION f"

INSTRUMENT CHANNEt.

1.

Pressure Switches I

POSH 3367 A,8 RilR lleat Excitanger Room El. 83 f t.

1 e.

Auxtilary Feedwater Pump Room E1 100 ft.

1 b.

'PSH 2850 A,0 Equipment Room El. 100 ft. Aux 111ary Fee & ater Pump Rose Corrid I

~

B.F C,E 1

1 Recycle 11oldup T nk Room Eb.12N.t121 ft.

~

HoderatingHeatkuchangqr PSH 2851 A.F oom 1

Haderating Heat Exchanghr Valve Room E1. 121 ft.

c.

8,C DE 1

riping Penetration Room E1. 100 ft.

1 lT d.

PSH 2852 A.H Letdown Heat Exchanger Room E1. 100 ft.

I B.C.D.E Recycle lloidup Tank Room El.121 f t.

F,G 1

l Piping Penetration Room EL. 121 ft.

1 PSH 2853 A,8 Blowdown Heat Exchanger Room El 130 ft.

1 e.

C,0 Corridor El. 121 ft.

l E.F

~

1 i.

b I '8 i

3 i

I l

1

i i

TA8tE 3.3-10 (Continued)

.m l E

!5 Miniani i 4 OPERABLE

~

I

INSTRUMENT CHAMEL SENSOR LOCATION CHANNELS l 4 PSH-2853 G,H Recycle Evaporator Room E1. 121 ft.

1 l

I,J Corridor E1. J21 ft. (1) and I

Sluice Filter Room El.121 Ft. (J) j

2.. Flooding Detectors a.

LSH 2828 A,8,C Main Steam Rome E1. 127 ft.

2 i

b.

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

~

l e'

5:'.

I I

I m

i 9

g H

?

i I

U I

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 An RHR Low Head Pump Roos 77'-0" 1

1 160 Hatch Area 100'-0" 3

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

4 0

100'-0" 3

2 Hallway /SI Pump Room 172 100'-0" 2

1 Charging /SI Pump Room 173 Charging 100'-0" 2

1 174 100'-0" 2

1 Hallway /SI Pump Room 175 Charging 100'-0" 2

1 181 184 Mechanical Penetration Room 100'-0" 8

A 4

185 CCW Heat Exchanger and Pump 100'-0" 13 7

186 Boric Acid Trans. PPS 100'-0" 3

2 4

188 Boric Acid Tanks 121'-0" 2

1 190 MCC Panel Room 100'-0" 4

2

. 191 Auxiliary Feedwater Pump Room 100'-0" 1

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

1 193 Auxiliary 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, 228 234 South Corridor 121'-0" 7

4 212 Battery Room 1A 121'-0" 1

1 Battery Service Room 121'-0" 1

1 213 214 Battery Room 1B 121'-0" 1

1 223 Mechanical Penetration Room 121'-0" 9

5 224 DC Switchgear Room 121'-0" 1

1 225 Battery Charger Room 121'-0" 1

1 4

l 226 DC Switchgear Room 121'-0" 1

1 227 West Cable Chase 128'-0" 7

4 229 AC Switchgear Room Train 8 121'-0" 4

2 233 AC Switchgear Room Train B 121' -0

3 2

241 Main Steam and FDW V1v. Rs.

127'-0" 8

4 244-Mezzanine - Battery Room 131'-0" 3

2 245 Mezzanine - Bai.t.ary Room 131'-0" 3

2 254 Not Shutdown Panel Room 121'-0" 1

1 300 West Cable Chase 139'-0" 7

4 i

312 Corridor 139'-0" 3

2 316, 322 Corridor 139'-0" 3

2 318 Cable Spreading Room 139'-0" 8

4 l

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

3-333 Electrical Penetration Room 139'-0" 1

1 334 Electrical Penetration Roos

'139'-0" 6

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

2 3

343 AC Switchquar Room Train B 139'-0" 3

2 347 Electrical Penetration Room 139'-0" 2

1 b/43-60 AMENDMENT NO. 33 FARLEY-UNIT 1

inous s.s ic FIRE DETECTION INSTRUMENTATION (Continued)

Auxiliary Building Total Minimum Room /

Smoke of Operable Fire Zone Description Elevation Detectors Smoke Detectors 401 Control Room (above ceiling) 155'-0" 13 7

401 Control Room (below ceiling) 155'-0." __ _

3 2

440,455,456 Clean Toilet, Laundry and Drying Areas 155'-0" 3

2 462 Non-Radioactive Vent Equip. Rm.

155'-0" 5

3 465 Vertical Cable Chase 155'-0" 3

2 466 Vertical Cable Chase 155'-0" 4

2 500 Vertic e Cable Chase 168'-2" 7

4 416 Contro Room Instrument Racks 155'-0" 8

4 Containment

55 Containment Coolers 155'-0" 12/ Fan 6/ Fan 55 Containment 155'-0" 11 6

Service Water intake Structure 72 A**

Pump Room Area 188'-9" 12 6

72 A**

Strainer Bay 167'-0" 12 6

72 B **

Switchgear Room - 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 73 **

Battery Room - Train B 188'-9" 1

1 74 **

Battery Room - Train A 188'-9" 1

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

56 B Foyer 155'-0 4

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

71 Hallway 155'-0" 9

5 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 62 Day Tank Room 2C 155'-0" 1

1 63 Day Tank Room 18 155'-0" 1

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

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

1 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 No.1 control room area but service coth Units, andi appear in tne Tecnnical Specifications for both units.

FARLEY-UNIT 1 3/4 3-60a AMENDMENT 10.

33

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i b,

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

l f

At least once per 31 days when the RCS pressure is above the c.

P-11 setpoint by verifying that power to each isolation valve

, operator is disconnected by a locked open disconnect device.

l d.

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

1.

When the RCS pressure (actual or simulated) exceeds the P-11 (Pressurizar Pressure Block of Safety Injection) setpoint, 2.

Upon receipt of a safety injection test signal.

P, e

e 4

~

l l

p

)

FARLEY-UNIT 1 3/4 5-2 AMENDMENT NO. 33

A EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem 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 following valves c.

are in the indicated positions with the disconnect device to the valve operators locked open:

Valve Function Valve Position Valve Number a.

8884, 8586 Charging Pump Closed to RCS Hot Lag b.

8132A, 81328 Charging Pump Open*

discharge isolation c.

8889 RHR to RCS Hot Closed Lag Injection At least once per 31 days by verifying that each valve (manual, b.

power operated or automatic),in the flow path that is not locked,

. sealed, or otherwise secured in position, is in its correct position.

By a visual inspection which verifies that no loose debris (rags, c.

trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the This visual inspection shall pump suctions during LOCA conditions.

be performed:

\\-

1.

For all accessible anas of the containment prior to establishing CONTAINMENT INTEGRITY, and Of the areas affected within containment at the completion of 2.

each containment entry when CONTAINMENT INTEGRITY is established.

d.

At least once per 18 months by:

t Verifying automatic isolation and interlock action of the l

1.

RHR system from the Reactor Coolant System when the Reactor

, Coolant System pressure is between 700 psig and 750 psig.

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

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 ne verified if charging pump 1A is declared inoperable.

AMENDMENT NO.

33 nrnrR7-mT67 R 3/4 5 4

' CONTAINMENT' SYSTEMS CONTAINMENT VENTILATION SYSTE_M LIMITING CONDITION FOR OPERATION 3.6.1.7 The 48-inch contzinnent purge supply and exhaust isolation valvss (C8V-HV-3198A,31980,3196,3197) shall be closed.

The 8-inch containment vant supply and exhaust isolation valves may be open.

APPLICABILITY:

MODES.1, 2,' 3, and 4.

ACTION:

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

SURVEILLANCE REQUIREMENTS 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.

4.6.1.7.2 The valve seals of the 48-inch and the 8-inch v.ent. supply and l

exhrust isolation valves shall be replaced at least once per 5 years.

i i

t

)'

3/4 6 AMENDMENT NO. 3 3 i

F.ARLEY -U. NIT 1

- 10

TABLE 3.7-5 LIST OF SPRINKLER SYSTEMS Location Sprinker Room / Fire Zone Description Elevation System Auxiliary Building 161 North West Corridor 100'-0" 1A-25 161 North East Corridor 100'-G" 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 Purps Cable Area 100'-0" 1A-62 209 Nortn Corridor 121'-0" 1A-35 210 Auxiliary Bldg. West Corridor 121'-0" 1A-36 223 Pipe Penetration Rm & Tendon i

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" 1A-114 462 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" 1A-23 Service Water Intake Structure 72A Service Water Pump Protection 102'-0" 1SW-111 s

\\

FARLEY-UNIT 1 3/4 7-87 AMENCMENT 10. 33

TABLE 3.7-7 YARD FIRE HYORANTS AND ASSOCIATED HYORANT HOSE HOUSES LOCATION HYORANT NUMBER 1

West of Auxiliary Building N1Y43V103

2 West of Servica Water Intake N1Y43V121*

3.

East of Service Water Intake N1Y43V122*

4.

North of Diesel Generator Building N1Y43V120*

5.

East of kuiliary Building N1Y43V089 6.

Northeast of Diesel Generator Building N1Y43V090 l

Shared between Unit 1 and Unit 2 FARLEY-UNIT 1 3/4 7-93 MENDMENT NO. 33

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:

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

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

APPLICABILITY: MCOES 1, 2, 3 and 4 ACTION:

With one 125-volt D.C. distribution train inoperable *, restore the inoperable distribution system to OPERABLE and energized status witnin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 .

SURVEILLANCE REQUIREMENTS 4.8.2.5.1 Each D.C. train shall be determined OPERABLE and energized at least once per 7 days by verifying cofrect breaker alignment and indicated power availability.

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

At least once per 7 days by verifying that:

a.

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 eleccrolyte 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:

1.

The electrolyte level of eacn cell is between the minimum and maximum level indication marks.

Except curing performance of surveillance Requirement 4.8.2.5.2.d and 4.8.2.5.2.e.

During this test, one train may be inoperable until the battery is recnarged following completion of tne cattery discnarge test.

FARLEY-UNIT 1 3/4 3-12 AMEN 0 MENT '40.

33

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, cerraeted 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.

At least once per 18 months by verifying that:

c.

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, a.1d 3.

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

d.

At least once per 18 month, during a shutdown of either unit, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 Acclied (amps)

Duration 1

25 0 - 0.1 sec 2

1 0.1 sec - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months FARLEY-UNIT 1 3/a S-13 AMENOMENT NO. 33

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENT (Continued)

At least once per 60 month, during a shutdown of either unit, by e.

verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge This performance discharge test shall be performed subsequent test.

to the satisfactory completion of the required battery service test.

b FARLEY-UNIT 1 3/4 8-14 AMENCME17 NO. 23

~

Executive m

IS Vice President G;

?

E

)

Senior NORB Vice President r.

Vice President

Nuclear Generation Manager Manager Manager

?'

Safety Audit and Nuclear Operations Plant Manager Nuclear Engineering

^*

Engineering Review and Administration Farley

& Technical Support Onsite Supervisor Staff Plant Safety Audit and Staff Staff Engineering Review Onsite.

Staff

Corporate responsibility for fire protection program h,

Ons ite g

Staff 2

E k

Figure 6.2-1 Offsite Organization for Facility Management and Technical Support t!

I

p PLANT

.ra.

NANAGER m

-s e-*

ASSISTANT STAFF PLANT MANAGER ASSISTANT STAFF l

I i

l I

i l

i i

1-OPERAhl0NS MAINTENANCE TECHNICAL

' TRAINING PERFORMANCE SUPERINTENDENT SUPERINTENDENT SUPERINTElGENT ADMINISTRATIVE DIRECTOR A6e PLANNING q

SUPERINIDDENT SUPERINTEIOENT l

l l

SUPERVISOR OPERATIONS l&C MAINTENANCE e

hurEHylSOR SUPERVISOR SUPERVISOR tea mlCAL NATERIALS SECURITY OOCUMENT SUPERVISOR SUPERVi50R SUPERVISOR CONTROL STAFF

{

StFERVISOR StilFT ht IAC MAINTENANCE SUPEHVISOR f0 HEMAN FORENAN

{

REACTOR FIRE SECURITY ENGINEER MARSHALL staff FORENAN STAFF se l

staff staff STAFF 3

staff GUARDS PLANNING PLANT SYSTEMS j

SUPERVISOR MODIFICATION PERFORMANCE SUPERVISOR SUPERVISOR ItutHICAL HEALTil PHYSICS CHEMISTRY AuviSON SUPERVISOR SUPERVISOR SL - Senior Operator's License a - Reactor Operators will have Operator's License 88 - Onsite Responsibility for Fire Protection Program staff staff FIGamE 6.2-2 FACILITV ENGANIZAtl0N

la routine matters, the Health Physics Supervisor reports directly to the Tochalcal Superintendent, in matters of radiation policy deteelnation, Interpretation or laplementation Ibesed upon the llealth Physics Superviser's judgement) the llealth Physics Supervisor may rooort directly to the A>>1stant Plant Manager.

6

a ADMIN!STRATIVE CONTROLS 6.2.3 SAFETY AUDIT AND ENGINEERING REV*EW GROUP (SAERG)

FUNCTION 6.2.3.1 The SAERG shall function to conduct operational evaluations, engineering reviews, and audits for the purpose of improving safety.

COMPOSITION 6.2.3.2 The SAERG shall be composed of a multi-disciplined dedicated onsite group with a minimum assigned complement of five engineers or appropriate specialists.

RESPONSIBILITIES 6.2.3.3 The SAERG shall be responsible for the following:

Participating in operational evaluations for improvement of safety a.

wherein such evaluations and recommendations therefrom are not limited to the fulfillment of existing programs, policies, procedures, or capabilities of existing equipment and installations.

b.

Systematic engineering reviews of plant performance and activities with results reported independently of onsite operational management to offsite upper management.

Comprehensive plant audits in accordance with audit requirements set c.

fortn in quality assurance programs, licensing documents, and other policies and procedures.

AUTHORITY 6.2.3.4 The onsite SAERG shall carry out its function reporting offsite directly to the Manager-Safety Audit and Engineering Review who in turn reports directly to the Vice President-Nuclear Generation.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor primarly in the assessment of accident and transient occurrences.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the i

supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for (1) the Health Physics Supervisor who shall meet or exceed tne qualifications of Regulatory Guide 1.8, September 1975.

FARLEY-UNIT 1 6-6 AMENOMENT NO. 33

d ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The PORC shall:

Recommend to the Plant Manager in writing, approval or disapproval of a.

items considered under 6.5.1.6(a) through (e) and (j) and (k) above, b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a), (C) and (d) above constitutes an i

unreviewed safety question.

Make recommendations to the Plant Manager in writing that actions c.

reviewed under 6.5.1.6(b) above did not constitute an unreviewed safety question.

RECORDS 6.5.1.8 The PORC shali maintain written minutes of each meeting and copies shall be provided to the Vice President-Nuclear Generation and Chairman of the Nuclear Operations Review Board.

6.5.2 NUCLEAR OPERATIONS REVIEW BOARD (NORB)

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

a.

Nuclear power plant operations b.

Nuclear engineering c.

Chemistry and radiochemistry d.

Metallurgy e.

Insrumentation and control f.

Radiological safety g.

Mechanical and electrial engineering h.

Quality assurance practices COMPOSITION 6.5.2.2 The NORB shall be composed of at leat five persons including:

Chairman:

Senior Vice President Vice Chairman:

Vice President-Nuclear Generation Secretary:

Manager-Safety Audit & Engineering Review Member:

Manager-Nuclear Operations and Administration Member:

Manager-Nuclear Engineering and Technical Support i

and other appointed personnel having an academic degree in an engineering or physical science field and a minimum of five years technical experience, of wnich a minimum of three years snall be in one or more of the areas given in 6.5.2.1.

FARLEY-UNIT 1 6-9 Amendment No. 33

ADMINISTRATIVE CONTROLS ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NORB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NORB activities at any one time.

4 CONSULTANTS 6.5.2.4 Consultants shall ha utilized as determined by the NORB Chairman to provide expert advice to the NORB.

MEETING FREQUENCY 6.5.2.5 The NORB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.2.6 A quorum shall consist of the Chairman or Vice Chairman plus enough voting members to constitute a majority of the NORB. No more than a minority of the quorum shall have line responsibility for operation of the facility.

For the purpose of a quorum those considered to have line reponsibility will include the Plant Manager and~ personnel reporting to the Plant Manager.

REVIEW 9

6.5.2.7 The NORB shall review:

Proposed changes to procedures, equipment or systems whict. involve an a.

unreviewed safety question as defined in Section 50.59, 10 CFR.

b.

Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

c.

Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance or abnormal degradation of systems designed to contain radioactive material.

d.

Significant operating abnormalities or deviations from normal ar :

expected performance of plant equipment that affect nuclear safety.

e.

Written reports concerning events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission.

f.

Recognized indications of an unanticipated deficiency in some-aspect of design or operation of safety related structures, systems, or components.

FARLEY-UNIT 1 6-10 AMENOMENT N0. 33

ADMINISTRATIVE CONTROLS 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 er systarus 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 fo11owing 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 I

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.

d.

The performance of activities required by the Operational Quality l

Assurance Program to meet the criteria of Appendix "B",10 CFR 50, j

at least once per 24 months.

l e.

The Facility Emergency Plan at least once per 24 months.

f.

The Facility Sacurity Plan at least once per 12 months.

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.

1.

An independent fire protection and loss prevention program inspection and audit of the unit at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.

j.

An inspection and audit of the unit fire protection and loss prevention 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.

I FARLEY-UNIT 1 6-11 AMEN 0 MENT NO. 33 u

ADMINISTRATIVE CONTROLS Reactor Operator's License.

For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedure shall approve the change.

b.

Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the Plant Manager.

Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as tne individual /grcup which dasigned the modifications.

Proposed modifications to plant nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant Manager.

Proposed tests and experiments which affect plant nuclear safety and c.

are not addressed in the Final Safety Analysis Report shall be prepared, reviewed, and approved.

Each such test or experiment shall be reviewed by an individual / group other than the individual / group

' which prepared the proposed test or experiment.

Proposed test and experiments shall be approved before implementation by the Plant

Manager, d.

Occurrences reportable pursuant to the Technical Specification 6.0 and violations of Technical Specifications shall be investigated and a report pr.epared wnich evaluates the occurrence and which provides recommendations to prevent recurrence. Such reports shall be approved by the Plant Manager and forwarded to the Vice President, Nuclear Generation with a copy to the fianager of Nuclear Operations and Administration; and to the Chairman of the Nuclear Operations Review

. Board.

e.

Individuals resonsible for reviews performed in accordance with 6.5.3.1.a, 6.5.3.1.b, 6.5.3.1.c, and 6.5.3.1.d shall be members of the plant supervisory staff previously designated by the Plant Manager. Each such review shall include a determ nation of whether i

or not additional, cross-disciplinary, review is necessary.

If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline.

f.

Each review will include a determination of whether or not an unreviewed safety question is involved.

Pursuant to 10 CFR 50.59 NRC approval of items involving unreviewed safety question will be obtained prior to Plant Manager approval for inptementation.

RECORDS 6.5.3.2 Records of the above acitivites shall be provided to the Plant Manager, PORC and/or NORB as necessary for required. reviews.

9

{

FARLEY-UNIT 1 6-13 AMENDMENT NO. 33

ADMINISTRATIVE C0iiTROLS

=

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

The Commission shall be notified and/or a report submitted pursuant a.

to the requirements of Specification 6.9.

,b.

Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission shall be reviewed by the PORC and submitted to the NORB, and the Vice President - Nuclear Generation with a copy to the Manager of Nuclear Operations and Administration.

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

The facility shall be placed in at least H0T STANDBY within one a.

hour, b.

The NRC Operations Center shall be notified by telephone as soon as possible and all cases within one hour. The Vice President, Nuclear Generation shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

A Safety Limit Violation Report shall 'be prepared. The report c.

shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commission, and the Vice President, Nuclear Generation, with a copy to the Manager of Nuclear Operations and Administration, for NORB review within 14 days of the violation.

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

The applicable procedures recommended in Appendix "A" of Regulatory a.

Guide 1.33, Revision 2,1978.

i b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

e.

Emergency Plan imolementation.

FARLEY-UNIT 1 6-14 AMEN 0 MENT NO. 33

ATTACHMENT TO LI_C_EN_S_E,,A_MEllDM_ENT AMENDMENT NO. gg,TO FACILITY OPERATING LICENSE f40. NPF-8 DOCKET NO. 50-364 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-24 3/4 3-24 3/4 3-54 3/4 3-54 3/4 3-55 3/4 3-55 3/4 3-60 3/4 3-60 3/4 3-60a 3/4 3-60a 3/4 5-2 3/4 5-2 3/4 5-4 3/4 5-4 3/4 7-63 3/4 7-63 3/4 8-15 3/4 8-15 3/4 0-1C 3/4 8-16 3/4 8-17 3/4 8-17 G-2 6-2 6-3 6-3 66 6-6 6 6-3 6-10 6-10 6-1 y,

6-11 6 4-13 6 5-14 7-1 deleted 9

l O

i i

I

TABLE 3.3-3 (Continued)

ACTION 18 - With the number of CPERABLE Channels one less than the Minimus Channels CPERABLE requirement, restore the inoperable channel to CFERABLE status within 48 hou'rs or be in at least HOT STAND 8Y 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 e

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

A ACTION 19 - With the number of O WMABLE 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minfaus Channels GPERABLE requirement is met; however, the inoperable channel say be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 - With the interlock frIoperable to the extent that a safeguards i

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 i

1. P-11 a..

Pressurizar Pressure - Low

2. P-12 a.

Steam Line Pressure - Low b.

Steam Flow in Two Steam Lines High Coincident With T,,gh Low ACTION 21 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STAND 8Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however; one channel say be bypassed for'up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 OPERA 8LE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

l 2/4 3-24 Amendment No. 26 l

- F ARLEY-UNIT 2

TABLE 3.3-10 HIGH ENERGY LINE 8REAK ISOLATION INSTR M NTATION MINileM OPERA 8tE CHANNELS SEN508 LOCATION INSTRUNENT CHANNEL 1.

Pressure Switches I

a.

MSN 3W A,8 RHR Heat Exchanger Room E1.83 f t.

1 Auxlitary Feedwater Pump Room El. 100 ft.

b.

'PSH 2850 A.D 1

Equipment Room E1. 100 ft.

I 8,F Auxillary Feedwater Puep Room Corrider El. 100 ft.

C,E NbEratih"nat SIh5Eg"er h*ece N.'121 ft.

1 8,C Hoderating Heat Exchanger Valve Room El. 121 ft.

D.E 1

Piping Penetration Room E1.'100 ft.

1 d.

PSH 2852 A H Letdown Heat Exchanger Room El. 100 ft.

a 8,C,0,E I

Recycle lloidup Tank Room El. 121 ft.

)

F,G, 1

e.

P5H 2853 A,8 Piping Penetration Room EL. 121 ft.

1 Blowdown Heat Exchanger Room El 130 ft.

I.

C.D E.F Recycle Evaporator Room El. 121 ft.

E9 5

0 TA8tE 3.3-10 (Continued)

.,9 E

5 MINIM 31 E

OPERABLE INSTRUMENT CHAMIEL SENSOR LOCATION CHANNELS q

PSH-2853 G,H Recycle Evaporator Room El. 121 fL.

I

'a j

I,J Corridor El. 121 ft. (I) and I

l Blowdown Surge Tank Room El. 130.ft. (J)

2.. Flooding Detectora.

\\

l a.

,LSH 2828 A,8,C Main Steam Room El. 127 ft.

2 i

j b.

LSH 2829 A,B,C Main Steam Room E1, 127 ft.

2 u.

US i

I l

E i

G M

I 9-i k

)

5

TABLE 3.3-12 FIRE DETECTION INSTRUMENTATION 7

Auxiliary Building Total Minimum Room /

Smoke Of Operable Fire Zone Description Elevation Detectors Smoke Detectc.s 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 /SI Pump Room 100'-0" 2

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

1 2175 Hallway /SI Pump Room 100'-0" 2

1 2181 Charging 100'-0" 2

1 2184 Mechanical Penetration Room 100'-0" 8

4 2185 CCW Heat Exchanger and Pump 100'-0" 13 7

2186 Boric Acid Trans. PPS 100'-0" 3

2 2188 Boric Acid Tanks 121'-0" 2

1 2190 MCC Panel Room 100'-0" 4

2 t

2191 Auxiliary Feedwater Pump Room 100'-0" 1

1 7

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

1 2193 Auxiliary Feedwater Pump h.3om 100'-0" 2

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

2 2200 Corridor 121'-0" 2

1 2209 Hallway 121'-0" 3

2 2210 South Corridor 121'-0" 2

1 2212 Battery Room iA 121'-0" 1

1 2213 Battery Service Room 121'-0" 1

1 2214 Battery Room IB-121'-0" 1

1 2223 Mechanical PenetTation 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 Viv. Rm.

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 BV 139'-0" 3

2 2347 Electrical Penetration Room 139'-0" 2

1 FARLEY-UNIT _2 _ _ _ _,

3/,4_3_60 _ _.

"[ Y

FIRE DETECTION INdiRur1ENTATION (Continued)

Auxiliary Building Total Minimum Room /

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

Control Room (above ceiling) 155'-0" 16 8

2401 #

Control Room (below ceiling) 155'-0" 3

2 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 #

Centrol Roem (Instrument Racks) 155'-0" 9

5 2500 West Cable Chase 168'-2" 7

4 Containment

55 Containment Coolers 155'-9" 12/ Fan 6/ Fan 5"

Containemnt 155'-0" 14 7

Service Water Intake Structure 72 A**

Pump Room Area 188'-9" 12 6

72 A**

Strainer Bay 167'-0" 12 6

7 2 B **

Swtichgear Room - Train B 188'-9" 3

2 7 2 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 73**

Batte'ry Room - Train B 188'-9" 1

1 74**

Battery Room - Tra1m A '

188'-9" 1

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

56 B Foyer 155'-0" 4

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

71 Hallway 155'-0" 9

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

3 59 Diesel Driven Generator 28 155'-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 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 eThese 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 requireo to ce OPERABLE during 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.

FARLEY-UNIT 2 3/4 3-60a Arenacent No.

26

EMERGENCY CORE COOLING SYSTEMS a

SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 1% of tank volume by varifying the baron 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 disconnect device.

[

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 Infection) setpoint,

2., Upon receipt of a safety injection test signal.

L I

s

)

~

FARLEY-UNIT 2 3/4 5-2 AMENDMENT NO. 26

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem 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 following valves a.

are in the indicated positions with the disconnect device to the valve operators locked open:

Valve Number Valve Function Valve Position 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 LegInjection 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.

By a visual inspection which verifies that no loose debris (rags, c.

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 J

RHR system from the Reactor Coolant System when the Reactor l

~

Coolant System pressure is between 700 psig and 750 psig.

' 2.

A visual inspection of the containment sump 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 2 A is declared inoperable.

l

)

N Ae wAsseastla v

j TABLE 3.7-7 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES LOCATION HYORANT NUMBER 1.

Northeast of Auxiliary Building N1Y43V105 2.

Northwest of Auxiliary Building N1Y43V102 3.

West of Auxiliary Building N1Y43V103*

4 North of Diesel Generator Building N1Y43V120*

5.

West of Service Water Intake N1Y43V121*

6.

East of Service Water Intake N1Y43V122*

k

Shared between Unit 1 and Unit 2 FARLEY-UNIT 2 3/4 7-63 Amendment No. 26

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

ELECTRICAL POWER SYSTEMS SERVICE WATER BUILDING D.C. DISTRIBUTION - OPERATING 4

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

TRAIN "A" consisting of 125-volt D.C. Distribution Cabinet IM,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 distribution system to OPERABLE and energized status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 .

SURVEILLANCE REQUIREMENTS 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:

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 ; 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.

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:

1.

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

Except curing performance of surveillance Requirement 4.8.2.5.2.c and 4.8.2.5.2.e.

During this test, one train may be inoperaole until the battery ijg{gchggpedf1T*i"9#*P1*ti"3755"75 a ery scharge test.AMENOMENT N0.

26 2

ELECTRICAL POWER SYSTEMS l

SURVEILLANCE REQUIREMENTS,(Continued) e 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 J.

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.

At least once per -18 months by verifying that:

t 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 sapply at least 3 amperes at > 125 volts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

d.

At least once per 18 month, during a shutdown of either unit, by verifying that the batfery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 sec - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months e

FARLEY-UNIT 2 3/4 8-16 AMENDMENT NO. 26

o ELECTRICAL POWER SYSTEtiS SURVEILLANCE REQUIREMENT (Continued)

At least once per 60 month, during a shutdown of either unit, by e.

verifying that the 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 l

I.

I i

FARLEY-UNIT 2 3/4 d-17 At1ENDMENT NO. 26 l

l

))

Enecutive p>

Vice President Q

Ei

-l Senior NORB Vice President Vice President

Nuclear Generation Manager Manager Manager Safety Audit and Nuclear Operations Plant Manager Nuclear Engineering Engineering Review.

and Administration Farley

& Technical Support "O

I Onsite Supervisor Staff Plant Safety Audit and Staff Staff Engineering Review Onsite Staff

Corporate responsibility for fire protection program Onsite Staff z.

3 m

s Figure 6.2-1 Of fsite Organization for Facility Management and Technical Support 5

^

PLANT NANAGER je 9

PORC E

ASSISTANT. k staff I-PLANT MAN $ER ASSISTANT

$TAff l

I i

i I

l l

I i

1 5

W V

OPERATIONS SL MAINTENANCE TECHNICAL TR.llNIW PERFORNANCE SUPERINTENDENT SuPERINTDOENT SliPERINTE80ENT l

ADNINISTRATIVE DillECTOR Ale PLANNING SUPERINTEWENT SUPERINTENDENT i

QC 1

l l

.I SuPERvlSOR O

I, OPERATIONS 1&C NAINTENANCE SLSEHVISOR SUPERVISOR SUPERVISOR TECHNICAL.

NATERIALS SECURITY 00CUMEliT SWERVISOR SUPERVISOR SWERVISOR CONTROL staff m

f, SUPERVISOR ht SHIfI iAC NAINTENANCE i

SUPERVISON F0 HEMAN FOM MAN l

REACTOR flu SECURITY ENGINEER NARSHALL staff gf0 REMAN staff se I

b staff staff

$TAff staff GUARDS PLAleilNG PLANT SYSTEMS SUPERVISOR N00lflCAT10N PERf0RMANCE SUPERVISOR SUPERVISOR 6

SHlf T (1

IECHNICAL HEALTH PHYSICS C'tENISTRY ADViSon SUPERVISOR SuPERVlSOR ese SL - Senior Operator s License e

3

- Reactor Operators will have Operator's License g

u se - Onsite Responsibility for fire Protection Program staff staff flGERE 6.3-$ FACl4lTY ENGAlllIATidal ens in routine matters, the Health Physics Supervisor reports directly to the Techalcal Superintendent, la setters of radiation policy deteelnation, Interpretation or Implementation Ibesed upon the 14ealth Physics Supervisor's judgement) the Health Physics Supervisor any report directly to the Assistant Plant Nanager.

O S

ADftINISTRATIVE CONTROLS 6.2.3 SAFETY AUDIT AND ENGINEERING REVIEW GROUP (SAERG)

FUNCTION 6.2.3.1 The SAERG shall function to co'nduct operational evaluations,

~"

~

engineering reviews, and audits for the purpose of impriving safety.

COMPOSITION 6.2.3.2 The SAERG shall be composed of a multi-disciplined dedicated onsite group with aminimum assigned complement of five engineers or appropriate specialists.

RESPONSIBILITIES 6.2.3.3 The SAERG shall be responsible for the following:

Participating in operational evaluations for improvement of safety a.

wherein such evaluations and recommendations therefrom are not limited to the fulfillment of existing programs, policies, procedures, or capabilities of existing equipment and installations.

b.

Systematic engineering reviews of plant performance and activities with results reported independently of onsite operational management to offsite upper management.

Comprehensive plant audits in accordance with audit requirements set c.

forth in quality assurance programs, licensing documents, and other policies and procedures.

AUTHORITY 6.2.3.4 The onsite SAERG shall carry out its functicn reporting offsite directly to the Manager-Safety Audit and Engineering Review who in turn reports directly to the Vice President-Nuclear Generation.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Snift Supervisor primarly la the assessment of accident and transient occurrences.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for (1) the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

FARLEY-UNIT 2 6-6 AMEN 0 MENT N0. 26

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The PORC shall:

4 Recommend to the Plant Manager in writing, approval or disapproval of a.

items considered under 6.5.1.6(a) through (e) and (j) and (k) above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a), (C) and (d) above constitutes an unreviewed safety question.

Make recommendations to the Plant Manager in writing that actions c.

reviewed under 6.5.1.6(b) above did not constitute an unreviewed safety question.

RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the Vice President-Nuclear Gdneration and Chairman of the Nuclear Operations Review Board.

6.5.2 NUCLEAR OPERATIONS REVIEW BOARD (NORB)

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

a.

Nuclear power plant operations b.

Nuclear engineering c.

Chemistry and radiochemistry d.

Metallurgy e.

Insrumentation and control f.

Radiological safety g.

Mechanical and electrial engineering h.

Quality assurance practices COMPOSITION 6.5.2.2 The NORB shall be composed of at leat five persons including:

Chai rman:

Senior Vice President Vice Chairman:

Vice President-Nuclear Generation Secretary:

Manager-Safety Audit & Engineering Review Member:

Manager-Nuclear Operations and Administration Member:

Manager-Nuclear Engineering and Technical Support and other appointed personnel having an academic degree in an engineering or physical science field and a minimum of five years technical experience, of which a minimum of three years shall be in one or more of the areas given in 6.5.2.1.

FARLEY-UNIT 2 6-9 Amendment No. 26

ADMINISTRATIVE CONTROLS ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NORB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NORB activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NORB Chairman to provide expert advice to the NORB.

MEETING FREQUENCY 6.5.2.5 The NORB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.2.6 A quorum shall consist of the Chairman or Vice Chairman plus enough voting members to constitute a majority of the NORB. No more than a minority of the quorum shall have line responsibility for operation of the facility.

For the purpose of a qtorum those considered to have line reponsibility will include the Plant Manager and personnel reporting to the Plant Manager.

l REVIEW 6.5.2.7 The NORB shall review:

Proposed changes to procedures, equipment cr systems which involve an a.

unreviewed safety question as defined in Section 50.59, 10 CFR.

b.

Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

Violations of codes, regulations, orders, Technical Specifications, c.

license requirements, or of internal procedures or instructions having nuclear safety significance or abnormal degradation of systems designed to contain radioactive material.

d.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

Written reports concerning events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to e.

the Commission.

f.

Recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.

FARLEY-UNIT 2 6-10 AtiENOMENT N0. 26

ADMINISTRATIVE CONTROLS g.

Reports and meetings minutes of the PORC.

h.

Proposed changes to Technical Specifications or this Operating License.

i.

The safety evaluatiens fer 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 APC0'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.

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 per 12 months.

g.

Any other area of facility operation considered appropriate by the NORB or the Senior Vice President.

. The Facility Fire Protection Program and implementing procedures at h.

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 qualified offsite licensee personnel or an outside fire protection firm.

j.

An inspection and audit of the unit fire protection 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.

FARLEY-UNIT 2 6-11 Amen hent No. 26

i ADMINTSTRATIVE CONTROLS 1

Senior Reactor Operator's License.

For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedure shall approve the change.

Proposed changes or modifications to plant nuclear safety-related b.

structures, systems and components shall be reviewed as designated by the Plant Manager. Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications. Proposed modifications to plant nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant Manager.

Proposed tests and experiments which affect plant nuclear safety and c.

are not addressed in the Final Safety Analysis Report shall be prepared, reviewed, and approved. Each such test or experiment shall be reviewed by an individual / group other than the individual / group whi'ch prepared the proposed test or experiment.

Proposed test and experiments shall be approved before implementation by the Plant Manager.

d.

Occurrences reportable pursuant to the Technical Specification 6.0 and violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence. Such reports shall be approved by the Plant Manager at!d forwarded to the Vice President, Nuclear Generation with a copy to the Manager of Nuclear Operations and Administration; and to the Chairman of the Nuclear Opsrations Review Board.

Individuals resonsible for reviews performed in accordance with e.

6.5.3.1.a, 6.5.3.1.b, 6.5.3.1.c, and 6.5.3.1.d shall be members of the plant supervisory staff previously designated by the Plant Manager. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.

If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline.

f.

Each review will include a determination of whether or not an unreviewed safety question is involved. Pursuant to 10 CFR 50.59 NRC approval of items involving unreviewed safety question will be obtained prior to Plant Manager approval for implementation.

RECORDS 6.5.3.2 Records of the above acitivites shall be proviced to the Plant Manager, PORC and/or NORB as necessary for required reviews.

FARLEY-UNIT 2 6-13 AMENDMENT NO. 26 e

l

i ADMINISTRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

The Commission shall be notified and/or a report submitted' pursuant a.

to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission shall be reviewed by'the PORC and submitted to the NORB Vice President - Nuclear Ge.neration with a copy to the ana tne Manager of Nuclear Operations and Administration.

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

a.

The faci.lity shall be placed in at least HOT STANDBY within one hour.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and all cases within one hour. The Vice President, Nuclear Generation shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , A Safety Limit Violation Report shall be prepared. The' report c.

shall be reviewed by-the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Comission, and the Vice President, Nuclear Generation, with a copy to the Manager of Nuclear Operations and Administration, for NORB review within 14 days of the violation.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities reference below; The applicable procedures recommended in Appendix "A" of Regulatory a.

Guide 1.33, Revision 2,1978.

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation, e.

Emergency Plan implementation.

FARLEY-UNIT 2 6-14 AMENDMENT NO. 26

v t e Letter Sequence Other
TAC:51999, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval Other: ML20081B596
MONTHYEAR1983-10-14 [Table View]

ML20081B596

Text

Attachment:

Attachment:

Navigation menu

Search