Text

Proposed Tech Specs,Allowing Continued Plant Operation & Necessary Compatibility Between Fuel Cycles & Surveillance Intervals
	ML20073C392
Person / Time
Site:	Farley
Issue date:	04/05/1983
From:	; ALABAMA POWER CO.
To:	;
Shared Package
ML20073C378	List: ML20073C375; ML20073C392;
References
	NUDOCS 8304130132
	Download: ML20073C392 (98)
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- b TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY I

S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.

M At least once per 31 days Q

At least once per 92 days.

SA At least once per 184 days.

A At least once per 365 days.

At least once perhths.

0 R

l 1

S/U Prior to each reactor startup.

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P-Completed prior to each release.

)

N.A.

Not applicable.

l 5

FARLEY-UNIT 1 1 _..

l i

l REACTIVITY CONTROL SYSTEMS.

M ROD DROP TIME I

l LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) rod drop time from the fully withdrawn position shall be less than or equal to 2.2 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:

T,yg greater than or equal to 541*F, and a.

b.

All reactor coolant pumps operating.

APPLICABILITY:

MODES 1 and 2.

/,CTION:

a.

With the' drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b.

With the rod drop times within limits but determined with 2 reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to 66% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full length rods shall be demonstrated through measurement prior to reactor criticality:

a.

For all rods following each removal of the reactor vessel head, b.

For specifically affected individual rods following any maintenance on or modification to the control rod drive system which could affect the drop time of those specific rods, and c.

At least once per M months.

I k

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FARLEY-UNIT 1 3/4 1-19

3/4.3 INSTRUMENTATION 1

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION

(

-3.3.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in 4

Table 3.3-2.

i APPLICABILITY:

As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

4 SURVEILLANCE REOUIREMENTS 4.3.1.1 Each reactor trip system instrumentation channel shall be demonstrated k}

OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and 4

CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown 4

in Table 4.3-1.

l 4.3.1.2 The logic for the interlocks shall be demonstrated OPERABLE prict to each reactor startup unless performed during the preceding 92 days.

The total interlock function shall be demonstrated OPERABLE at least once per M months.

4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function i

shall be demonstrated to be wi. thin its limit at least once pert _ : months.

E Each test shall include at least one logic train such that both logic trains are tested at least once per-emonths and one channel per function such that l

l all channels are tested at 1 'ast once every N timesq 3rmonths where N is W

the total number of redunda t channels in a specific reactor trip function as shown in the " Total No. of hannels" column of Table 3.3-1.

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FARLEY-UNIT 1 3/4 3-1

l

, TABLE 4.3-1 (Continued)

..]

I TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

If not performed in previous 7 days.

(1)

Heat balance only, above 15% of RATED THERMAL POWER.

Adjust channel (2) i if absolute difference greater than 2 percent.

Compare incore to excore axial flux difference above 15% of RATED (3) l THERMAL POWER.

Recalibrate if the absolute difference greater than or equal to 3 percent.

Manual ESF functional input check every months.

I (4)

Each train or. logic channel shall be tested at least every 62 days (5) on a STAGGERED TEST BASIS.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(6)

Below the P-6 (Block of Source Range Reactor Trip) setpoint.

(7) 1 Logic only, if not performed in previous 92, days.

}

(8)

CHANNEL FUNCTIONAL TEST will consist of verifying that each channel (9) indicates a turbine trip prior to latching the turbine and indicates no turbine trip after latching the turbine.

(10) -

If not performed in the previous 31 days, d

4

)

FARLEY-UNIT 1 3/4 3-14

INSTRUMENTATION

]

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 4

3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

l 3

APPLICABILITY:

As shown in Table 3.3-3.

l ACTION:

1 a.

With an ESFAS instrumentation channel or interlock trip setpoint j

less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With an ESFAS instrumentation channel or interlock inoperable, take i

the ACTION shown in Table 3.3-5.

lI -

SURVEILLANCE REOUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.

The total interlock function shall be E

demonstratedOPERABLEatleastoncepergmonths.

p 4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESF S function shall be demonstrated to be within the limit at least once per months.

Each test shall include at least one logic train such that both logic trains are tested at least once per; months and one channel per function such that 3

all channels are tested at 1 st once per N times iqtmonths where N is the B

total number of redundant ch nnels in a specific ESI S function as shown in the " Total No. of Channels" olumn of Table 3.3-3.

k 46

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FARLEY-UNIT 1 3/4 3-15

TABLE 4.3-2 (Continued)

Q TABLE NOTATION (1) Manual actuation switches shall be tested at least once per months I

during shutdown. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days.

(2) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(3) Channel calibration shall exclude actuation of the final trip actuation relay."

(4) Functional testing shall consist of verification of relay operation upon removal of input voltage and operation of 2-out-of-3 logic excluding the final trip actuation relay.*

(5) If not performed in the previous 92 days.

(6) Excluding automatic actuation logic for trip of main feedwater pumps.

" Actuation of tne final trip act

ion relay shall be included in response time testing.

FARLEY-UNIT 1 3/4 3-37 l

INSTRUMENTATION b

HIGH ENERGY LINE BREAK ISOLATION SENSORS LIMITING CONDITION FOR OPERATION 3.3.3.7 The high energy line break isolation instrumentation listed in Table 3.3-10 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

With the number of OPERABLE high energy line break isolation instruments less than required by Table 3.3-10, restore the inoperable instrument (s) to OPERABLE status within 7 days or be in HOT STANDBY within the n. ext 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 REOUIREMENTS 9

'i 4.3.3.7 Each of the above high energy line break isolation instruments shall l

be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST at least once per M months.

5 N

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FARLEY-UNIT 1 3/4 3-53

i I

REACTOR COOLANT SYSTEM

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3/4.4.4 PRESSURIZER

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l LIMITING CONDITION FOR OPERATION L

3.4.4 The pressurizer shall be OPERABLE with a water volume of less than or equal to 868 (63.5% indicated) cubic feet *, and two groups of pressurizer heaters each having a capacity of at least 125 Kw.

l APPLICABILITY: MODES 1, 2 and 3 I

ACTION:

j r

a.

With one group of pressurizer heaters inoperable, restore at least two i

groups to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the pressurizer otherwise inoperable be in at least HOT STANDBY i

with the reactor trip breakers open within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN i

within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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SURVEILLANCE REOUIREMENTS

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l 4.4.4.1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

j 4.4.4.2 The emergency power bus for the p ssurizer heaters shall be demonstrated OPERABLE at least once per months by transferring power from I

the normal to the emergency power bus and energizing the heaters.

4.4.4.3 The capacity of each of the above required groups of pressurizer heaters shall be verified by measuring circuit current at least once per 92 days.

P I

Limit not applicable during either a THERMAL POWER ramp change in excess of f

5% RATED THERMAL POWER per minute or a THERMAL POWER step change in excess of 10% of RATED THERMAL POWER.

i I

j FARLEY-UNIT 1 3/4 4-7 l

..m.

i REACTOR COOLANT SYSTEM

'3/4.4.5 RELIEF VALVES l

LIMITING CONDITION FOR OPERATION i

f 3.4.5 All power relief valves (PORVs) and their associated block valves

I shall be OPERABLE.

j i

l APPLICABILITY: MODES 1, 2, and 3.

ACTION:'

f a.

With one or more PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, 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 .

b. ' With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valve (s) to OPERABLE status or close the block l

valve (s) and remove power from the block valve (s); otherwise, be l

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 .

[

c.

The provisions of Specification 3.0.4 are not applicable.

f SURVEILLANCE REQUIREMENTS l

t 1+

4.4.5.1 Each PORV shall be demonstrated OPERABLE at least once per M months l

by performance of a CHANNEL CALIBRATION and operating the valve through one

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cycle of full travel.

4.4.5.2 Each block valve shall be demonstrated OPERABLE at least once per.

92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with the power removed in order to meet the ACTION requirements of a. above.

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FARLEY-UNIT 1 3/4 4-8 r

s REACTOR COOLANT SYSTEM

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,3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE i

r LEAKAGE DETECTION SYSTEMS l

t LIMITING CONDITION FOR OPERATION f

l 3.4.7.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:

l a.

The containment atmosphere particulate radioactivity monitoring I

systim (R-11), and b.

Either the containment air cooler condensate level monitoring system or a containment atmosphere gaseous radioactivity monitoring system (R-12).

APPLICABILITY: MODES 1, 2, 3 and 4.

' ACTION:

With only one of the above required leakage detection systems O'PERABLE, operation may continue for up to 7 days provided grab. samples of the

);;.

containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous or particulate radioactive monitoring system is inoperable; otherwise, 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 RkOUIREMENTS I

4.4.7.1 The leakage detection systems shall be demonstrated OPERABLE by:

f a.

Containment atmosphere gaseous and particulate monitoring system performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, t

b.

Containment air cooler condensate level monitoring system performance of CHANNEL CALIBRATION at least once per M months.

E 4

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FhRLEY-UNIT 1 3/4 4 !

l

l l

l REACTOR COOLANT SYSTEM

)

i l

SURVEILLANCE REOUIREMENTS l

4.4.10.3.1 Each RHR relief valve shall be demonstrated OPERABLE by:

a.

Verifying the RHR relief valve isolation valves (8701a, 870lb, 8702a and 8702b) are open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the RHR relief valve is being used for overpressure protection.

b.

Testing in pursuant to Specification 4.0.5.

I c.

Verification of the RHR relief valve setpoint, of at least one RHR relief valve, at least once per'43rmonths on a rotating basis.

I 2f" 4.4.10.3.2 The RCS vent shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent is being used for overpressure protection.

N)

Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

i e

FARLEY-UNIT 1 3/4 4-33

EMERGENCY CORE COOLING SYSTEMS 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 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 breaker.

,GVf d.

At least once per 49 months by verifying that each accumulator 9

isolation valve opens automatically under each of the following conditions:

i 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.

4

)

FARLEY-UNIT 1 3/4 5-2

l EMERGENCY CORE COOLING SYSTEMS l

SURVEILLANCE REOUIREMENTS 4

i 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

i a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with the breaker to the valve i

operators locked open:

Valve Number Valve Function Valve Position a.

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

8132A, 8132B Charging Pump Open*

discharge isolation I

c.

8889 RHR to RCS Hot Closed Leg Injection 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 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 i

2.

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

d.

At least once per months by:

I 1.

Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor

, Coolant System pressure is above 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 1A is declared inoperable.

FARLEY-UNIT 1 3/4 5-4

EMERGENCY CORE COOLING SYSTEMS

.Q SURVEILLANCE REOUIREMENTS (Continued) 2 i

e.

By verifying the correct position of each mechanical position stop for the following ECCS throttle valves:

1.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems j

are required to be OPERABLE.

2.

At least once per 5 months.

I 2-t i

Valve Number CVC-V-8991 A/B/C CVC-V-8989 A/B/C CVC-V-8996 A/8/C j

CVC-V-8994 A/B/C l

f.

At least once per Ar months, during shutdown, by:

l.

2ff 1.

Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.

)

2.

Verifying that each of the following pumps start automatically

)

upon receipt of a safety injection test signal:

a)

Centrifugal charging pump b)

Residual heat removal pump g.

By verifying that each of the following pumps develops the indicated differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1.

Centrifugal charging pump

> 2458 psig 2.

Residual heat removal pump

> 136 psig h.

Prior.to entry into Mode 3 from Mode 4, verify that the mechanical stops on low head safety injection valves RHR-HV 603 A/B are intact.

4

)

FARLEY-UNIT 1 3/4 5-5

CONTAINMENT SYSTEMS h

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

r With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 ; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREM'ENTS i

T'

-l 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

l a.

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.

b.

By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 210 psig when tested q

pursuant to Specification 4.0.5.

c.

At least once per eimonths during shutdown, by:

g M

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a Phase B test signal.

l l

2.

Verifying that each spray pump starts automatically on a 4

Phase B test signal.

d.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

)

FARLEY' UNIT 1 3/4 6-11

CONTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The spray additive system shall be OPERABLE with:

A spray additive tarx containing a volume of between 3600 and a.

4000 gallons of between 30 and 32 percent by weight NaOH solution, and

~

b.

Two spray additive eductors each capable of adding NaOH solution from the chemical additive tank to a containment spray system pump flow.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the spray additive system inoperable, restore the system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STAND 3Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the spray additive system to GPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.2.2 The spray additive syst'em shall be demonstrated OPERABLE:

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

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

b.

At least once per 6 months by:

1.

Verifying the contained solution volume in the tank, and 2.

Verifying the concentration of the NaOH solution by chemical

. analysis.

c.

At least once per months during shutdown, by verifying that each I

automatic valve in the flow path actuates to its correct position on a Phase B signal.

d.

At least once per 5 years by verifying each solution flow rate from drain valve 1CS-V-8834:

1.

Via the additive tank 2.

Via 1CS-MOV-8836A 3.

Via 1CS-MOV-8836B

)

FARLEY-UNIT 1 3/4 6-12

CONTAINMENT SYSTEMS

]

CONTAINMENT COOLING SYSTEM LIMITING CONDITIONS FOR OPERATION 3.6.2.3 Two independent groups of containment cooling fans shall be OPERABLE with one fan in each group.

APPLICABILITY: MODES 1, 2,.and 3.

ACTION:

a.

With one group of the above required containment cooling fans inoperab e and both containment spray systems OPERABLE, restore the inoperable group of cooling fans to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HCT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With two groups of the above required containment cooling fans inoperable, and both containment spray systems ORERABLE, restore at least one group of cooling fans to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 HOT SHUTDOWN wit'iin the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Restore both above required groups of cooling fans to OPERABLE status within 7 days of initial loss 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

)

HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one group of the above required containment cooling fans inoperable and one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Restore the inoperable group of containment cooling fans to OPERABLE status within 7 days of initial loss 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS 4.6.2.3 Each group of containment cooling fans shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1.

Starting each fan group (unless already operating) from the control room, and verifying that each fan group operates for at least 15 minutes.

i.

2.

Verifying a cooling water flow rate of greater than or equal to

~

1600 gpm to each cooler group.

2 At least once per M + months by verifying that each fan group starts I

i }

b.

I automatically on a safety injection test signal.

FARLEY-UNIT 1 3/4 6-13

f CONTAINMENT SYSTEMS i(

SURVEILLANCE REOUIREMENTS (Continued) i 4.6.3.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated j

OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per(4GLM l

months by:

)

a.

Verifying that on a Phase A containment isolation test signal, each j

Phase A isolation valve actuates to its isolation position.

i b.

Verifying that on a Phase B containment isola' tion test signal, each j

Phase B isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power operated or automatic valve of q

Table 3.6-1 shall be determined to be within its limit when tested pursuant to j

Specification 4.0.5.

i 4.6.3.4 The containment purge isolation valves shall be demonstrated OPERABLE prior to startup after each COLD SHUTDOWN if not performed in the previous 3,

j months by verifying that when the measured leakage rate is added to the leakage 1

rates determined pursuant to Specification 4.6.1.2.d for all other Type B and l

C penetrations, the combined leakage rate is less than or equal to 0.60L,s.

j-In addition, the leakage rate for.the containment purge isolation valves hall 1

be compared to the previously measured leakage rate (for the containment purge j

}

isolation valves) to detect excess valve degradation.

)

An engineering evaluation shall be performed to determine what corrective

~

l action, if any, is necessary.

j h

J 1

i i

l j

FARLEY-UNIT 1 3/4 6-15 i

c-

-.,--.--c

=----,.-,:..~.,_.--_.,--,.,,

.,,%s-

,n.

v.,

-w

CONTAINMENT SYSTEMS ELECTRIC HYOROGEN RECOMBINERS - W

)

LIMITING CONDITION FOR OPERATION-3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

~

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying during a recombiner system functional test that the minimum heater sheath temperature increases

),

to greater than or equal to 700 F within 90 minutes.

Upon reaching 700 F, increase the power setting to maximum power for two minutes and verify that the power meter reads greater than or equal to 60 KW.

b.

At least once per months by:

l 1.

Performing a CHANNEL CALIBRATION of all recombiner instrumenta-tion and control circuits.

2.

Verifying through a visual examination that there is no evidence

j of abnormal conditions within the recombiners (i.e., loose wiring or structural connections, deposits of foreign materials, etc.)

3.

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

)

FARLEY-UNIT 1 3/4 6-20 7

m

.-c yy-.

,-----d m

g-

-u- --

CONTAINMENT SYSTEMS s

i HYDROGEN MIXING SYSTEM J

i LIMITING CONDITION FOR OPERATION i

3.6.5.4 Two independent hydrogen mixing systems shall be OPERABLE.

]

APPLICABILITY: MODES 1 and 2.

i ACTION:

)

With one hydrogen mixing system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS i

4.6.5.4 Each hydrogen mixing system shall be demonstrated OPERABLE:

a.

At least once per 92 days on a STAGGERED TEST BASIS by starting each system from the control room and verifying that the system operates

),

for at least 15 minutes.

b.

At least once per months by verifying a fan speed of at least l

1320 rpm.

i t

r i

i

)

FARLEY-UNIT 1 3/4 6-22

PLANT SYSTEMS i

h SURVEILLANCE REOUIREMENTS (Continued) 2.

Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER.

3.

Verifying that the stop check valves 3350A, 33508, and 3350C are in the open position with the breaker to the valve operators locked open.

j b.

At least once per inonths during shutdown by:

l 1.

Verifying that each automatic valve in the flow path actuates

[

to its correct position on an auto pump start signal.

2.

Verifying that each motor driven pump starts automatically upon I

receipt of each of the following test signals-a)

Safety injection, l

b)

Steam generator water level low-low in any steam generator, and c)

Loss of Site Power (LOSP).

h 3.

Verifying that the steam turbine driven pump starts automatically i

upon receipt of each of the following test signals:

a)

Undervoltage on 2 out of 3 reactor coolant pump buses, and t

b)

Steam generator water level low iow in two steam generators.

4.

Verifying that the turbine-driven auxiliary feedwater pump steam admission valves Q1N12V001A-A and Q1N12V001B-B will open when air is supplied from their respective air accumulators.

c.

The auxiliary feedwater system shall be demonstrated OPERABLE prior to entry into MODE 2 following each COLD SHUT 00WN by performing a

[

flow test to verify the normal flow path from the emergency condensate l

storage tank through each auxiliary pump to its a'ssociated steam generator. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

i 1

FARLEY-UNIT 1 3/4 7-5 y

w

,,,--.-r,_.,

c

-.~ -..., _

..,,--v-

PLANT SYSTEMS

{

3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 REOUIREMENTS 4.7.3 At least two component cooling water loops shall be demonstrated OPERABLE:

T a.

At least once.per 31 days by verifying that each accessible valve (manual, power operated or automatic) in the flow path, servicing

/

safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position,

~ At least once per yh nonths during shutdown, by verifying that each I

b.

automatic valve servicing safety related equipment actuates to its correct position on a safety injection test signal.

FARLEY-UNIT 1 3/4 7-11 i

a

4 i

I PLANT SYSTEMS i

l 3/4.7.4 SERVICE WATER SYSTEM i

LIMITING CONDITION FOR OPERATION l

i j

3.7.4 At -least two independent service water loops shall be OPERABLE with at least two service water pumps per loop.

APPLICABILITY: MODES 1, 2, 3 and 4.

t j

ACTION:

i i

With only one service water loop OPERABLE, restore at least two loops to s

OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 l

l i

4.7.4 At least two service water loops shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each accessible valve

)

j (manual, power operated or automatic) in the flow path, servicing j

safety related equipment that is not locked, sealed, or otherwise i

secured in position, is in its correct position.

I At least once per:;gmonths during shutdown, by:

l b.

1.

Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a safety injection test signal.

2.

Verifying that the buried piping is leak tight by a visual inspection of the ground area.

i 4

FARLEY-UNIT 1 3/4 7-12

4 PLANT SYSTEMS

}

3/4.7.5 RIVER WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.5 At least two independent river water loops shall be OPERABLE with at least two river water pumps per loop.

APPLICABILITY:

MODES 1, 2, 3 and 4.

(

ACTION:

With only one river water loop OPERABLE, restore at least two loops to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.7.5 Each river water icop shall be demonstrated OPERABLE:

T a.

At least once per 31 days by verifying that each valve (manual, 1

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

b.

At least once per months during shutdown, by:

l 1.

Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a low pond level

signal, 2.

Verifying that the buried piping is leak tight by a visual inspection of the ground area.

)

FARLEY-UNIT 1 3/4 7-13

I l'

+

f PLANT SYSTEMS 2

j 3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM

')

j LIMITING CONDITION FOR OPERATION i

i 4

3.7.8 Two independent penetration room filtration systems shall be OPERABLE.

p APPLICABILITY:

MODES 1, 2, 3 and 4.

i l

ACTION:

i With one penetration room filtration system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within j

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 .

t l

SURVEILLANCE REOUIREMENTS I

i 4.7.8 Each penetration room filtration system shall be demonstrated OPERABLE:

I a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, j

from the control room, flow through the HEPA filters and charcoal T

j adsorbers and verifying that the system has operated for at least

/

j 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on during the past 31 days.

b.

At least once per months or (1) after any structural maintenance I

on the HEPA filter or charcoal adsorber housings, or (2) following j

painting, fire or chemical release that could have contaminated the charcoal adsorbers or HEPA filters in any ventilation zone communi-cating with the system by:

4 1.

Verifying that the cleanup system satisfies the in place testing j

acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c and C.S.d of Regulatory Guide 1.52, I

Revision 2 March 1978, and the system flow rate is 5000 cfm +

j 10 1 l

1 1

i 4

FARLEY-UNIT 1 3/4 7-18

PLANT SYSTEMS h

SURVEILLANCE REQUIREMENTS (Continued) i 2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

3.

Verifying a system flow rate of 5000 cfm 1 10% during system operation when tested in accordance with ANSI N510-1975.

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

d.

At least once per %S months by:

I 1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks of less than 6 inches Water Gauge while operating the system at a flow rate of 5000 cfm 1 10%.

)

2.

Verifying that the system starts on a Phase B Isolation test signal.

3.

Verifying that the heaters dissipate 25 1 2.5 kw when tested in accordance with ANSI N510-1975.

e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the 00P when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 5000 cfm 10%.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 5000 cfm 1 10%.

FARLEY-UNIT 1 3/4 7-19 l

4 i

PLANT SYSTEMS t

I 3/4.7.9 SNUBBERS

')

LIMITING CONDITION FOR OPERATION i

i 3.7.9 All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE.

i APPLICABILITY:

MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

ACTION:

l With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the l

inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

I i

SURVEILLANCE REOUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a.

Visual Insoections

).

4 The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b.

If less than two (2) snu.bbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months 25% from the date of the first inspection.

Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers Subsequent Visual,

per Insoection Period Insoection Period

montns 25%

g a$4(L months O

1 istE 25%

B 2

9 aSLmonths 25%

3,4

/8ptet days 25%

5,6,7 62 days 25%

8 or more 31 days 25%

The snubbers may be categorized into two groups:

Those accessible and those inaccessible during reactor operation.

Each group may be inspected independently in accordance with the above schedule.

'g aThe inspection interval shall not be lengthened more than one step at a time.

,/

The provisions of Specificat;on 4.0.2 are not applicable.

FARLEY-UNIT 1 3/4 7-20 o

m

- ~ _, + -

l PLANT SYSTEMS

(

SURVEILLANCE REOUIREMENTS (Continued)

'O b.

Visual Insoection Accentance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are secure.

Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in tha as found condition and deter-mined OPERABLE per Specifications 4.7.9.d or 4.7.9.e, as applicable.

However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and cannot be determined OPERABLE via functional testing unless the test is started with the piston in the as found setting, extending the piston rod in the tension and compression mode directions.

All snubbers connected to an inoperable ccmmon hydraulic fluid reservoir shall be counted as inoperable snubbers.

c.

Functional Tests 24 At least once per:E months during shutdown, a representative sample I

[s of 88 snubbers shall be functionally tested either in place or in a J

bench test.

If more than 3 snubbers do not meet the functional test acceptance criteria of Specification 4.7.9.d or 4.7.9.e, an additional sample selected according to the expression 22(a-3) shall be func-tionally tested, where a is the total number of snubbers found

- inoperable during the functional testing of the initial representative sample.

Functional testing shall continue according to the expression (22)b where b is the number of snubbers found inoperable in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers in Table 3.7-4a and 3.7-4b have been functionally tested.

Snubbers greater than 50,000 lb. capacity may not be excluded from functional testing requirements.*

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.

At least 25% of the snubbers in the initial representative sample shall include snubbers from the following three categories:

1.

The first snubber away from each reactor vessel nozzle

^This portion of the specification is not effective until the fifth refueling l) outage or when a commercial in place testing device is available whichever is later.

FARLEY-UNIT 1 3/4 7-21 1

4 1

PLANT SYSTEMS 5

1 SURVEILLANCE REOUIREMENTS (Continued) i j

f.

Snubber Service Life Monitoring 4

A record of the service life of each snubber, the date at which the designated service life commences and the installe. tion and main-tenance records on which the designated service life is based shall f

be maintained as required by Specification 6.10.2.n.

i 1+

Concurrent with the first inservice visual inspection and at least 4

i once per, l months, the installation and maintenance records for I

each snubber listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been exceeded or will 2

not be exceeded prior to the next scheduled snubber service life review.

If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records, i

~

4 9

k 4

FARLEY-UNIT 1 3/4 7-24

i

}

PLANT SYSTEMS l9 I

SURVEILLANCE REQUIREMENTS i

i i

i 4.7.11.1.1 The fire suppression water system shall be demonstrated OPERABLE:

i a.

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

volume.

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

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

c, 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.

d.

At least once per

' months by performance of a system flush I

e.

At least once per months by cycling each testable valve in the E

~

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

At least once per months by performing a system functional test which includes simulated automatic actuation of the system throughout its op'etating sequence, and:

b I

1.

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

Cycling ea,.5 valve in the flow path that is not testable during plant operation through at least one complete cycle of full i

travel, and 1

3.

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

g.

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

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

]

4

-4.7.11.1.2-The fire pump diesel engine shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying:

1.

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

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

l

'a

~

FARLEY-UNIT 1 3/4 7-83

,,,,-n.,--,

,n,.

y.

,_n.n.,,

+

1 PLANT SYSTEMS I

SPRAY AN0/0R SPRINKLER SYSTEMS I

i LIMITING CONDITION FOR OPERATION 4

j 3.7.11.2 The spray and/or sprinkler systems listed in Table 3.7-5 shall be t

OPERABLE.

APPLICABILITY: Whenever equipment in the spray / sprinkler protected areas is l

required to be OPERABLE.

1 ACTION:

a.

With one or more of the above required spray and/or sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant l

systems or components could be damaged; for other areas, establish a hourly fire watch patrol.

Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specifi-cation 6.9.1, prepare and submit a Special Report to the Commission 4

pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the,cause of the inoperability and the plans and l

schedule for restoring the system to OPERABLE st. as.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

]}

1 SURVEILLANCE REOUIREMENTS 4.7.11.2 Each of the'above required spray and/or sprinkler systems shall be demonstrated OPERABLE:

a.

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

position.

l$

b.

At.least once per 40Lmonths by cycling each testable valve in the l

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

1 1

FARLEY-UNIT 1 3/4 7-85

PLANT SYSTEMS

)

SURVEILLANCE REQUIREMENTS (Continued) l c.

At least once per.4 months:

1.

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

a)

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

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

2.

By a visual inspection of the dry pipe spray and sprinkler headers to verify their integrity, and 3.

By a visual inspection of each nozzle's spray area to verify the spray pattern has not become obstructed beyond design conditions.

l e

]

P J

FARLEY-UNIT 1 3/4 7-86

l

}

PLANT SYSTEMS 4

CO SYSTEMS 2

l LIMITING CONDITION F6R OPERATION 1

3.7.11.3 The following high pressure and low pressure CO systems shall be 2

l OPERABLE.

I a.

Service Water Intake Structure (each 4160 volt bus and each 600 volt load center - HP.

b.

Turbine Building 13 ton unit and distribution system in the Auxiliary i

Building - L.P.

c.

Diesel Building 5 ton unit and distribution system.

l APPLICABILITY: Whenever equipment protected by the CO systems in required to 2

j be OPERABLE.

ACTION:

a.

With one or more of the above required C0 systems inoperable, withinonehourestablishacontinuousfihewatchwithbackupfire i

suppression equipment for those areas in which redundant systems or

)

components could be damaged; for other areas, establish an hourly fire watch patrol.

Restore the system to OPERABLE status within

)

14 days or, lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to m

1 Specification 6.9.2 within the next 30 days outlining the action

)

taken, the cause of the inoperability and the plans and schedule for q

restoring the system to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

3 SURVEILLANCE REQUIREMENTS 4.7.11.3.1 Each of the above required CO systems shall be demonstrated OPERABLE at least once per 31 days by ver,fying that each manual valve T

j in the flow path is in its correct position.

4.7.11.3.2 Each of the above required low pressure CO systems shall be 2

demonstrated OPERABLE:

a.

At least once per 7 days by verifying the CO, storage tank level to be greater than 50% and pressure to be greattr than 250 psig, and b.

At least once per months by verifying:

l 1.

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

Flow from each nozzle during a " Puff Test."

)

FARLEY-UNIT 1 3/4 7-88

= _ _ -

4 PLANT SYSTEMS

~22*

SURVEILLANCE REQUIREMENTS (Continued) l 4.7.11.3.3 Each of the above required high pressure CO systems shall be 2

demonstrated OPERABLE:

4 a.

At least once per 6 months by verifying the CO storage tank weight 2

to be at least 90% of full charge weight.

1 N

a b.

At least once per GR. months by:

E 4

1 1.

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

2.

Performance of a flow test through headers and nozzles to assure no blockage.

J j

FARLEY-UNIT 1 3/4 7-89

.-.._,-w, 3

e 9-g y

c-

i PLANT SYSTEMS

q e

j FIRE HOSE STATIONS

(

i LIMITING CONDITION FOR OPERATION I

j 3.7.11.4 The fire hose stations shown in Table 3.7-6 shall be OPERABLE.

j APPLICABILITY:

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

\\

1 ACTION:

a.

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

^

inoperable, route

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

otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore the fire hose station to OPERABLE status within 14 days or, in lieu of l

any other report required by Specification 6.9.1, prepara and submit a Special Report to the Commission pursuant to Specification 6.9.2 1

within the next 30 days outlining the action taken, the cause of the

{

inoperability and the plans and schedule for restoring the station to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

/

)

j SURVEILLANCE REQUIREMENTS l

i 4.7.11.4 Each of the fire hose stations shown in Table 3.7-6 shall be t

demonstrated OPERABLE:

4 a.

At least once per 31 days by visual inspection of the fire hose stations accessible during plant operation to assure all required equipment is at the station.

o b.

At least once per months by:

l I

1.

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

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

c.

At least once per 3 years by:

i 1.

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

2.

Conducting a hose hydrostatic test at a pressure at.least 50 psig greater than the maximum pressure available at that hose station.

i

If routing of tne hose would require rendering a fire barrier penetration p

inoperable,. hose will be routed up to but not through the penetration with

~

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

4 FARLEY-UNIT 1 3/4 7-90

PLANT SYSTEMS YARD FIRE HYDRANTS AND HYORANT HOSE HOUSES h

LIMITING CONDITION FOR OPERATION 3.7.11.5 The yard fire hydrants and associated hydrant hose houses shown in Table 3.7-7 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the yard fire hydrants is required to be OPERABLE.

ACTION:

a.

With one or more of the yard fire hydrant or associated hydrant hose houses shown in Table 3.7-7 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months have sufficient additional lengths of 2 1/2 inch diameter hose located in an adjacent OPERABLE hydrant hose house to provide service to the unprotected area (s) if the inoperable fire hydrant or associated hydrant hose house is the primary means of fire suppression; otherwise provide the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore the hydrant or hose house to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the hydrant or hose

)

house to OPERABLE status.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

4 SURVEILLANCE REQUIREMENTS 4.7.11.5 Each of the yard fire hydrants and associated hydrant hose houses shown in Table 3.7-7 shall be demonstrated OPERABLE:

a.

At least once per 31 days by visual inspection of the hydrant hose house to assure all required equipment is at the hdse house.

b.

At least once per 6 months (once during March, April or May and once during September, October or November) by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and that the hydrant is not damaged.

Atleastoncepergmonthsby:

l c.

1.

Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure available at any yard i

fire hydrant.

2.

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

)

3.

Performing a flow check of each hydrant to verify its OPERABILITY.

b FARLEY-UNIT 1 3/4 7-92

r

.L PLANT SYSTFMS 4

s 3/4.7.12 FIRE BARRIER PENETRATIONS s

l

)

4 l

LIMITING CONDITION FOR OPERATION All fire barrier penetrations (including cable penetration barriers, 1

3.7.12 firedoors and fire dampers) in fire zone boundaries protecting safety related areas shall be functional.

APPLICABILITY:

At all times.

ACTION:

With one or more of the above required fire barrier penetrations a.

non-functional, within one hour either, establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier and establish a hourly fire watch patrol.

Restore the non-functional fire barrier penetration (s) to functional status within 7 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of tne non-functional penetration and plans and schedule for restoring the fire barrier penetration (s) to functional status, The previsions of Specifications 3.0.3 and 3.0.4 are not applicable.

b.

s SURVEILLANCE REQUIREMENTS Each of the above required fire barrier penetrations shall be verified 4.7.12 to be functional:

a.

At least once per; months by a visual inspection.

l b.

Prior to returning a penetration fire barrier to functional status following repairs or maintenance by performance of a visual inspection of the affected penetration fire barrier (s).

l 1

(

FARLEY-UNIT l'

' ~ " ~ " ~ ~ -

' - ' 3/4 7-94

l ELECTRICAL POWER SYSTEMS ACTION (Continued) 1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 if (DG 1-2A and DG-2C) or(DG-1B and DG-1C) or (DG-1C and DG-2C) are inoperable; or 2.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 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 if DG 1-2A and DG-1B are inoperable; or 3.

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 if three or more diesel generators are inoperable.

Restore both diesel generator sets to OPERABLE status within 18 days from time of initial loss 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 REOUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and 3

(

b.

Decmonstrated OPERABLE at least once per months during shutdown l

by transferring unit power supply from the~ normal circuit to the alternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day tank.

2.

Verifying the fuel level in the fuel storage tanks.

3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4.

Verifying the diesel starts and accelerates to at least 900 rpm for the 2850 kw generator and 514 rpm for the 4075 kw generators in less than or equal to 12 seconds. The generator voltage and frequency shall be 13952 volts and 3 57 Hz within 12 seconds after the start signal and operates for 5 minutes.

5.

Verifying the generator is synchronized, loaded to 2700-2850 kw for the 2850 kw generator and 3875-4075 kw for the 4075 kw generator and operates for greater than or equal to 60 minutes.

}

FARLEY-UNIT 1 3/4 8-3

i l

l l

ELECTRICAL POWER SYSTEMS

}

l l

SURVEILLANCE REQUIREMENTS (Continued) 6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

b.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank obtained in accordance with ASTM-D270-65 is within the acceptable limits'specified in Table 1 of ASTM 0975-74 whencheckepf.orviscosity,waterandsediment, c.

At least once per 18 months by subjecting the diesel to an inspection and maintenance in accordance with procedures prepared in conjunction with its man d ions.

Rt lens +ufacturer's recoence per Mnwn

[

s 1

Simulating a loss of offs e power by itself, and:

a)

Verifying de-energization of the emergency busses and load shedding from the emergency busses.

b)

Verifying the diesel startsi on the auto-start signal, energizes the emergency busses with permanently connected loads within 12 seconds, energizes the auto-connected

_)

shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads.

After energization of all loads, the steady state voltage and frequency of the emergency busses shall be maintained at 4160

420 volts and 60

1.2 HI during this test.

Q, Verifying that on a Safety Injection test signal (without loss of offsite power) the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall be 1 3952 volts and 1 57 Hz within 12 seconds after the auto-start signal; the steady state generator voltage and frequency shall be maintained between 4160

420 volts and 60 1.2 Hz during this test.

j, Sieulating a loss of offsite power in conjunction with a Safety Injection test signal, and:

a)

Verifying de-energization of the emergency busses and load shedding from the, emergency busses.

b)

Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 12 seconds, energizes the auto-connected G.,,

emergency (accident) loads through the load sequencer and W

FARLEY-UNIT 1 3/4 8-4

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) operates for greater than or equal to 5 minutes while its

~

generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 + 420 volts and 60 + 1.2 Hz during this test.

c)

Verifying that all automatic diesel generator trips, except engine overspeed and generator differential and low lube oil pressure, are automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection test signal.

Y.

Verify that the diesel generators operate for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while loaded to 4353 kw* for the 4075 kw diesels and 3100* for the 2850 kw diesels (2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months rating). After completing this 24-hour test, manually trip the diesel generator from the 2000-hour

load and demonstrate hot restart capability by performing Surveillance Requirement 4.8.1.1.2.a.4 within 10 minutes.

6 Verifying that the auto-connected loads to each diesel generator l

do not exceed the 2000-hour rating of 4353 kw for the 4075 kw generator and 3100 kw for the 2850 kw generator.

[p.

Verifying the diesel generator's capability to:

a)

Synchronize with the offsite power source while the gener-ator is loaded with its emergency loads upon a simulated restoration of offsite power.

b)

Transfer its loads to the offsite power source, and

~

c)

Be restored to its standby status.

7-Verifying that with the diesel generators operating in a test l

mode (conn 3cted to its bus), a simulated safety injection signal overrides'the test mode by returning the diesel generator to standby operation.

Verifying that the automatic load sequence timer is OPERABLE with each load sequence time within + 10% of its required value

~

or 0.5 seconds whichever is greater.

7 9, -

Verifying that the following diesel generator lockout features

~

prevent diesel generator starting only when required:

a) 011TemperatureHigh(OTH)

For a one-time period only that expires on September 1,1983, the load shall beasshown(i.e.,the2000-hourratings)foraminimumof2hoursandforthe remainder of the 24-hour period, the loads shall be at the continuous rating.

Reduct' ion of load as necessary immediately prior to tripping is acceptable.for this one-time period.

^

FARLEY-UNIT 1-3/4 8-5

(-

N l

l i

l ELECTRICAL POWER SYSTEMS 7

l SURVEILLANCE REQUIREMENTS (Continued) b)

Coolant Temperature High (CTH) c)

Coolant Pressure Low (CPL) d)

Crankcase Pressure High (CCPH)

/0.

Verifying the capability to reject a load of greater than or equal to the largest single load associated with that diesel i

generator (approximately 1000 kw); while maintaining voltage between 3740 and 4580 volts and speed less than or equal to 75%

of the difference between nominal speed and the overspeed trip

setpoint, e,

At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting the diesel generators simultaneously, and verifying that the diesel generators accelerate to at least 900 rps, for the 2850 kw generator and 514 rpm for the 4075 kw generator, in less than or equal to 12 seconds.

M At least once per 5 years, on a staggered basis, by verifying that the diesel generator can reject a load of 1200-2400 kw without tripping. The diesel generator output breaker (s) must remain closed g

such that the diesel generator is connected to at least one emergency bus. Verify that all fuses and breakers on the energized emergency bus (es) are not tripped. The generator voltage shall remain within 3330 and 4990 volts during and following the load rejection.

4.8.1.1.3 Reports - All diesel generator failures, valid or nonvalid, shall be reported to the Commission pursuant to Specification 6.9.1.

Reports of diesel generator failures shall include the information recommended in Regu-latory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977. If

. the number of failures in the last 100 valid tests (on a per diesel basis) is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory

~

Guide 1.108, Revision 1, August 1977.

O

_ 1ARLEY-UNIT 1 3/4 8-6

-..~ - -

n

ELECTRICAL POWER SYSTEMS IQ SURVEILLANCE REQUIREMENTS (Continued) 2.

The voltage of each connected cell is greater than or equal to 1

1 2.02 volts under float charge and has not decreased more than 0.1 volts from the value observed during the original acceptance test.

i 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, and 4.

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

24-At least once per(98 months by verifying that:

l c.

1.

The cells, cell plates and battery racks show no visual l

indication of physical damage or abnormal deterioration, l

2.

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

/ T 3.

The battery charger will supply at least 536 amperes at

)

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

N d.

At least once per 98 months during shutdown, by verifying that the E

1 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 Loads Are Current Duration Acolied (amos)

(min.)

1 920 1

2 430 58 3

920 1

4 430 59 5

920 1

FARLEY-UNIT 1 3/4 8-9 9'

ELECTRICAL POWER SYSTEMS b

SURVEILLANCE RE0VIREMENTS (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.

At least once per months by verifying that:

l 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

s I

di At least once per months, during shutdown, by verifying that the l

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 Acolied (amos)

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 t

l l

FARLEY-UNIT 1 3/4 8-13

l REFUELING OPERATIONS 3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER

(

h LIMITING CONDITION FOR OPERATION 3.9.14 The containment purge exhaust filter shall be OPERABLE and valve N1P13V293 closed.

APPLICABILITY:

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

l ACTION: With the containment purge exhaust filter inoperable either:

1.

Immediately close the 48 inch containment purge isolation valves (CBV-HV-3196, 3197, 3198A and 31980) and the 18 inch containment i

mini purge _ isolation valves (CBV-HV-2866A, 2866B, 2867A and 28678),

Or 2.

Cease all CORE ALTERATIONS and fuel movement.

SURVEILLANCE REOUIREMENTS 4.9.14 The above required containment purge exhaust filter shall be i

demonstrated OPERABLE:

a.

At least once per ~ months or (1) after any structural maintenance I

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

L e

FARLEY-UNIT 1 3/4 9-16

REFUELING OPERATIONS N

=

SURVEILLANCE REQUIREMENTS (Continued) i 1.

Verifying that with the main purge system operating and ex-hausting through the HEPA filters and charcoal adsorbers, the i

total bypass flow of the system to the facility vent, including j

leakage through the syst.em diverting valves, is less than or i

equal to 1% when the system is tested by admitting cold DOP at i

the system intake.

1 l

2.

Verifying that the cleanup system satisfies the in place

~

testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a C.S.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, with the main purge system operating.

3.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory

]

Guide 1.52, Revision 2, March 1978, meets the laboratory j

testing criteria of 75% efficiency.

IS i

b.

After every g months of charcoal adsorber operation by verifying I

}

within 31 days after removal that a laboratory analysis of a repre-1 sentative carbon sample obtained in accordance with Regulatory j

Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, i

meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

1 c.

At least once per months by verifying that the pressure drop l

j across the combined HEPA filters and charcoal adsorber banks is j

less than 6 inches Water Gauge while operating the main purge system.

ll i

i FARLEY-UNIT 1 3/4 9-17

POWER DISTRIBUTION LIMITS ik BASES additional assurance that the holy (Z), is measured periodically to provide The radial peaking factor F channel factor, F (Z), remains within its 9

RTP limit.

The F limit for RATED THERMAL POWER (Fxy ) as provided in the Radial xy Peaking Factor limit report per Specification 6.9.1.14 was determined from expected power control maneuvers over the full range of burnup conditions in the core.

3/4.2.4 QUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during startup testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x y, plane power tilts.

The two hour time allowance for operation with a tilt condition greater

)

than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod.

In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by q

reducing the maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.

3/4.2.5 DNB PARAMETERS

-l The Timits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses.

The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

The

2. g S ' month periodic measurement of the RCS total flow rate is adequate to detect l

flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months basis.

FARLEY-UNIT 1 B 3/4 2-5

i l

PLANT SYSTEMS U

BASES J

l 3/4.7.9 SNUBBERS j

All snubbers are required OPERABLE to ensure that the structural integrity j

of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.

Snubbers excluded from this inspection program are those installed on nonsafety related systems and then only if their failure or failure of the system on j

which they are installed, would have no adverse effect on any safety related l

system.

l The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.

Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.

However, the results of such early t

inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.

Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and 4

)

remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.

Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or j

are similarly located or exposed to the same environmental conditions such as j

temperature, radiation, and vibration.

When a snubber is found inoperable, an engineering evaluation is performed.

The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the attached component.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant.

I shutdowns at month intervals.

Selection of a representative sample according l

totheexpression35(1+f)providesaconfidencelevelofapproximately95%

1 i

that 90% to 100% of the snubbers in the clant will be OPERABLE within acceptance

~

limits.

Observed failures of these sample snubbers shall require functional testing of additional units.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.

I FARLEY-UNIT 1 B 3/4 7-5

.n-

..n

,.m--,--ne--.n.

TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.

M At least once per 31 days

Q At least once per 92 days.

SA At least once per 184 days.

A At least once per 366 days.

l R

At least once per months.

S/U Prior to each reactor startup.

P-Completed prior to each release.

}

N.A.

Not applicable.

9 e

1.

FARLEY-UNIT 2 1-9

.m..

')

REACTIVITY CONTROL SYSTEMS J

i R00 OR0p TIME i

LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) rod drop time from the fully withdrawn position shall be less than or equal to 2.2 seconds from i

beginning of d.ecay of stationary gripper coil voltage to dashpot entry with:

1 T,yg greater than or equal to 541*F, and a.

b.

All reactor coolant pumps operating.

l l

APPLICABILITY:

MODES 1 and 2.

ACTION:

a.

With the drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit J

prior to proceeding to MODE 1 or 2.

l b.

With the rod drop times within limits but determined with 2 reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to SEE of RATED THERMAL i

POWER.

SURVEILLANCE REOUIREMENTS i

i' 4.1.3.4 The rod drop time of full length rods shall be demonstrated through measurement prior to reactor criticality:

a.

For all rods following each removal of the reactor vessel head, b.

For specifically affected individual rods following any maintenance on or modification to the control rod drive system which could affect the drop time of those specific rods, and c.

At least once per' TSP. months.

\\

f.+.

I FARLEY-UNIT 2 3/4 1-19

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY:

As shown in Table 3.3-1.

ACTION':

As shown in Table 3.3-1.

SURVEILLANCE REOUIREMENTS

[

4.3.1.1 Each reactor trip system instrumentation channel shall be demonstrated

}'

OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and

)

CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown j

in Table 4.3-1.

4.3.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days.

The total interlock function shall be demonstrated OPERABLE at least once per et months.

l 41 4

4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor ip function 1

i shall be demonstrated to be w ithin its limit at least once per

. months.

Each test shall include at le ist one logic train such that both logic trains are tested at least once perj b months and one channel per function such that l

all channels are tested at.leist once every N times 4p months where N is the I

total number of redundant channels in a specific reac tor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

-zt

[

')-

\\

i FARLEY-UNIT 2 3/4 3-1

TABLE 4.3-1 (Continued)

TABLE NOTATION 4

~

With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

(1)

If not performed in previous 7 days.

Heat balance only, above 15% of RATED THERMAL POWER.

Adjust channel (2) if absolute difference greater than 2 percent.

Compare incore to excore axial flux difference above 15% of RATED (3)

THERMAL POWER.

Recalibrate if the absolute difference greater than or equal to 3 percent.

Manual ESF functional input check every 8 months.

l (4)

Each train or logic channel shall be tested at least every 62 days (5) on a STAGGERED TEST' BASIS.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(6)

Below the P-6 (Block of Source Range Reactor Trip) setpoint.

~

(7)

Logic only, if not performed in previous 92 days.

(8)

CHANNEL FUNCTIONAL TEST will consist of verifying that each channel (9) indicates a turbine trip prior to latching the turbine and indicates no turbine trip after latching the turbine.

(10) -

If not performed in the previous 31 days.

l I

FARLEY-UNIT 2 3/4 3-14

~_

INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICABILITY:

As shown in Table 3.3-3.

ACTION:

a.

With an ESFAS instrumentation channel or interlock trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With an ESFAS instrumentation channel or interlock inoperable, take-the ACTI,0N shown in Table 3.3-3.

SURVEILLANCE REOUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.

The total interlock function shall be I

demonstratedOPERABLEatleastonceperJgemonths.

4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESF S function shall be demonstrated to be within the limit at least once pert months.

l Each test shall include at least one logic train such that both logic trains are tested at least once per

months and one channel per function such that I

all channels are tested at 1 st once per N times @ months where N is the

[

total number of redundant c nnels in a specific ESl AS function as shown in the " Total No. of Channels" Column of Table 3.3-3.

h l )

FARLEY-UNIT 2 3/4 3-15

w TABLE 4.3-2 (Continued)

TABLE NOTATION II",

l (1) Manual actuation switches shall be tested at least once per M aonths l

j during shutdown. All other circuitry associated with manual safeguards l

actuation shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days.

(2) Each train or logic channel shall be tested at least every 62 days on a q

STAGGERED TEST BASIS.

3 l

(3) Channel calibration shall exclude actuation of the final trip actuation j

relay."

)

(4) Functional testing shall consist of verification of relay, operation upon i

removal of input voltage and operation of 2-out-of-3 logit: excluding the i

final trip actuation relay."

(5) If not performed in the previous 92 days.

1 (6) Excluding automatic actuation logic for trip of main feedwater pumps.

A J

i 1

f 4

t i

i l

^ Actuation of the final trip actuation relay shall be included in response j

time testing.

}

FARLEY-UNIT 2 3/4 3-37

i.

INSTRUMENTATION

-w HIGH ENERGY LINE BREAK ISOLATION SENSORS LIMITING CONDITION FOR OPERATION 4

4 3.3.3.7 The high energy line break isolation instrumentation listed in Table 3.3-10 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2 and 3.

l ACTION:

With the number of OPERABLE high energy line break isolation instruments less than required by Table 3.3-10, restore the inoperable instrument (s) to j

OPERABLE status within 7 days or be in 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 .

1 4

SURVEILLANCE REOUIREMENTS

~

i 4

4.3.3.7 Each of the above high energy line break isolation instruments shall j

be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST at j

least once per 35' months.

l 4

i J

I i

.,Y 3/4 3-53 FARLEY-UNIT 2

INSTRUMENTATION

~

SURVEILLANCE REOUIREMENTS (Continued) c.

At least once per 31 days by direct observation of the movement of each of the ~above valves through one complete cycle from the running position.

N d.

At least once per W months by performance of a CHANNEL CALIBRATION l

s on the turbine oveispeed protection systems.

e.

At least once per months by disassembling at least one of each of l

~

the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or Corrosion.

h

)

l

~/

FARLEY-UNIT 2 3/4 3-73

l i

REACTOR COOLANT SYSTEM f

-4 3/4.4.4 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.4 The pressurizer shall be OPERABLE with a water volume of less than or equal to 868 (63.5% indicated) cubic feet *, and two groups of pressurizer heaters each having a capacity of at least 125 Kw.

APPLICABILITY:

MODES 1, 2 and 3 i

ACTION:

a.

With one group of pressurizer heaters inoperable, restore at least two groups to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STA'4DBY within the next 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 , b.

With the pressurizer otherwise inoperable be in at least HOT STANDBY with the reactor trip breakers open 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 .

[*

SURVEILLANCEREOUiREMENTS A

4.4.4.1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

N 4.4.4.2 The emergency power bus.for the p essurizer heaters shall be demonstrated OPERABLE at least once per

, months by transferring power from the i

normal to the emergency power bus and energizing the heaters.

4.4.4.3 The capacity of each of the above required groups of pressurizer heaters shall be verified by measuring circuit current at least once per 92 days.

Limit not applicable during either a THERMAL POWER ramp change in excess of 5% RATED THERMAL POWER per minute or a THERMAL POWER step change in excess of 10% of RATED THERMAL POWER.

(

J-FARLEY-UNIT 2 3/4 4-7

REACTOR COOLANT SYSTEM i

)

r 3/4.4.5 RELIEF VALVES

(

'~)

]

(

...~.. LIMITING-CONDITION FOR OPERATION 35.5 All power relief valves (PORVs) and their associated block valves j

shall be OPERABLE.

1 l

APPLICABILITY: MODES 1, 2, and 3.

I ACTION:

With one or more PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore a.

l the PORV(s) to OPERABLE status or close the associated block valve (s) j and remove power from the block valve (s); otherwise, 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 SHUTD0hH within the i

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

i b.*

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either l

restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, be 4

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 l

SHUTD0hH within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

\\-

The provisions of Specification 3.0.4 are not applicable.

{ {

c.

l

()

SURVEILLANCE REOUIREMENTS

~_

4.4.5.1 Each PORV shall be demonstrated OPERABLE at least once per.

months l

by performance of a CHANNEL CALIBRATION and operating the valve through one l

cycle of full travel.

4.4.5.2 Each block valve shall be demonstrated OPERABLE at least once per.

92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with the power removed in order to meet the ACTION requirements of a. above.

i 1

FARLEY-UNIT 2 3/4 4-8 o'

g I

c

REACTOR COOLANT SYSTEM 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE l

LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.7.l The following Reactor Coolant System leakage detection systems shall be OPERABLE:

a.

The containment atmosphere particulate radioactivity monitoring system (R-11), and b.

Either the containment air cooler condensate level monitoring " system or a containment atmosphere gaseous radioactivity monitoring system (R-12).

4 APPLICABILI3:

MODES 1, 2, 3 and 4.

ACTION:

With only one of the above required leakage detection systems OPERABLE, operation may con.tinue for up to 7 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous / or particulate radioactive monitoring system is inoperable; otherwise, 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 REOUIREMENTS 4.4.7.1 The leakage detection systems shall be demonstrated OPERABLE by:

a.

Containment atmosphere gaseous and particulate monitoring system performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, b.

Containment air cooler condensate level monitoring system performance of CHANNEL CALIBRATION at least once per # months.

l 2+

i s

FARLEY-UNIT 2 3/4 4-16

REACTOR COOLANT SYSTEM s

SURVEILLANCE REQUIREMENTS-4.4.10.3.1 Each RHR relief valve shall be demonstrated OPERABLE by:

a.

Verifying the RHR relief valve isolation valves (8701a, 870lb, 8702a and 8702b) are open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the RHR relief valve is being used for overpressure protection.

b.

Testing in pursuant to Specification 4.0.5.

c.

Verification of the RHR relief valve setpoint, of at least one RHR relief valve, at least once per GS; months on a rotating basis.

5 4.4.10.3.2 The RCS vent shall be verified to be open at least once per 12 neurs" when the vent is being used for overpressure protection.

'N)

RExcept when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves.open at least once per 31 days.

M FARLey-UNIT 2-

-3/44-2

=

EMERGENCY CORE COOLING SYSTEMS w

SURVEILLANCE RE0VIREMENTS (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 i

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 Ly verifying that power to each isolation valve operator is disconnected by a locked open breaker.

d.

At least once per months by verifying that each accumulator l

isolation valve opens automatically under each of,the following conditions:

1.

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

Upon receipt of.a safety injection test signal.

l

../

i FARLEY-UNIT 2 3/4 5-2

EMERGENCY CORE COOLING SYSTEMS N

SURVEILLANCE REQUIREMENTS

~I 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 breaker to the valve operators locked open:

Valve Number Valve Function

-Valve Position a.

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

8132A, 8132B Charging Pump Open*

discharge isolation c.

8889 RHR to RCS Hot Closed Leg Injection b.

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

~

power operated or autematic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct 3[

positio'n.

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 months by:

{

1.

Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure ~is above 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 1A is declared inoperable.

FARLEY-UNIT 2 3/4 5-4

EMERGENCY CORE COOLING SYSTEMS

~

\\-

SURVEILLANCE REQUIREMENTS (Continued)

By verifying the correct position of each mechanical position stop e.

for the following ECCS throttle valves:

1.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following' completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.

2.

At least once perj W months.

N

~

Valve Number CVC-V-8991 A/B/C CVC-V-8989 A/B/C CVC-V-8996 A/8/C CVC-V-8994 A/B/C f.

At least once per months, during shutdown, by:

f 1.

Verifying that each automatic valve in the flow path actuates.

to its correct position on a safety injection test signal.

2.

Ve'rifying that each of the following pumps start automatically upon receipt of a safety injection test signal:

a)

Centrifugal charging pump b)

Residual heat removal pump g.

By verif;ing that each of the following pumps develops the indicated differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1.

Centrifugal charging pump

> 2458 psig 2.

Residual heat removal pump

> 136 psig h.

Prior to entry into Mode 3 from Mode 4, verify that the mechanical stops on low head safety injection valves RHR-HV 603 A/B are intact.

b FARLEY-UNIT 2 3/4 5-5

-s CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 ; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a.

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.

b.

By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 210 psig when tested pursuant to Specification 4.0.5.

Atleastonceperjemonthsduringshutdown,by:

g c.

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a Phase B test signal.

2.

Verifying that each spray pump starts automatically on a Phase B test signal.

d.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

/

y FARLEY-UNIT 2 3/4 6-11

.r

s

\\

CONTAINMENT SYSTEMS i

SPRAY ADDITIVE SYSTEM i

LIMITING CONDITION FOR OPERATION 3.6.2.2 The spray additive system shall be OPERABLE with:

a.

A spray additive tank containing a volume of between 3600 and i

4000 gallons of between 30 and 32 percent by weight Na0H solution, and b.

Two spray additive eductors each capable of adding NaOH solution from the chemical additive tank to a containment spray system pump flow.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

j With the spray additive system inoperable, restore the system to OPERABLE j

status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 ; i

restore the spray additive system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4 SURVEILLANCE REQUIREMENTS 4.6.2.2 The spray additive system shall be demonstrated OPERABLE:

i a.

At least o'nce 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.

i b.

At least once per 6 months by:

1.

Verifying the contained solution volume in the tank, and 2.

Verifying the concentration of the NaOH solution by chemical analysis.

c.

At least once per months during shutdown, by verifying that each l

automatic valve in the flow path actuates to its correct position on a Phase B signal.

d.

At least once per 5 years by verifying each solution flow rate from drain valve 2CS-V-8834:

1.

Via the additive tank 12 2 gpm i

2.

Via 2CS-MOV-8836A 23 1 4 gpm i

3.

Via 2CS-MOV-8836B 23 4 gpm

)

FARLEY-UNIT 2 3/4 6-12

L CONTAINMENT SYSTEMS j

CONTAINMENT COOLING SYSTEM LIMITING CONDITIONS FOR OPERATION l

3.6.2.3 Two independent groups of containment cooling fans shall be OPERABLE with one fan in each group.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With one group of the above required containment cooling fans inoperable a.

and both containment spray systems OPERABLE, restore the inoperable group of cooling fans to OPERABLE status wi":in 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With two groups of the above required containment cooling fans inoperable, and both containmeilt spray systems OPERABLE, restore at least one group of cooling fans to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 HOT SHUTDOWN within the.following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Restore both above required groups of cooling fans to OPERABLE status within 7 days of initial loss 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one group of the above required containment cooling fans c.

inoperable and one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Restore the inoperable group'of containment cooling fans to OPERABLE status within 7 days of initial loss 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 i

- s I

H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0UIREMENTS 4.6.2.3 Each group of containment cooling fans shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by:

a.

j 1.

Starting each fan group (unless already operating) from the control room, and verifying that each fan group operates for at least 15 minutes.

2.

Verifying a cooling water flow rate of greater than or equal to 1600 gpm to each cooler group.

b.

At least once per months by verifying that each fan group starts l

automatically on a safety injection test signal.

FARLEY-UNIT 2 ~

3/4 6-13 i

. N CONTAINMENT SYSTEMS

)

1 i

SURVEILLANCE REQUIREMENTS (Continued)

)

4.6.3.2 Each isolation valve specified in Table 3.6-1 shall_be demonstrated l

i 0PERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per.

2 months by:

1 i

a.

Verifying that on a Phase A containment isolation test signal, each j

Phase A isolation valve actuates to its isolation position.

1 b.

Verifying that on a Phase B containment isolation test signal, each 3

i Phase B isolation valve actuates to its isolation position.

i

~

j 4.6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within_its limit when tested pursuant to Specification 4.0.5.

l I

4.6.3.4 The containment purge isolation valves shall.be demonstrated OPERABLE.

prior to startup after each COLD SHUTOOWN if not performed in the previous 3 mor. tic by verifying that when the measured leakage rate is added to the leakage -

rates determined pursuant to Specification 4.6.1.2.d for all other Type B and

)

C penetrations, the combined leakage rate' is less than or equal to 0.60L

a In addition, the 1,eakage rate for the containment purge isolation valves shall i

be compared to the previously measured leakage rate (for the containment purge isolation valves)~to detect excess valve degradation.

An engineering evaluation shall be performed to determine what corrective i

action, if any, is necessary.

i I

i i

r i

}

i l

t b

I 4

FARLEY-UNIT 2-3/4 6-15~

CONTAINMENT SYSTEMS N

i

)~.

i ELECTRIC HYDROGEN RECOMBINERS - W i

j LIMITING CONDITION FOR OPERATION i

3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY:

MODES 1 and 2.

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the 1

next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

j SURVEILLANCE RE0VIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying during a recombiner system functional test that the minimum heater sheath temperature increases togreaterthanorequalto700Fwithin90 minutes.

Upon reaching 700 F, increase the power setting to maximum power for two minutes and verify that the power meter reads greater than or equal to 60 KW.

2.+

b.

Atleastonceperd!S;monthsby:

l 1.

Performing a CHANNEL CALIBRATION of all recombiner instrumenta-tion and control circuits.

2.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiners (i.e., loose wiring or structural connections, deposits of foreign materials, etc.)

3.

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test.

The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

3

-)l FARLEY-UNIT 2 3/4 6-20

CONTAINMENT SYSTEMS 4

HYDROGEN MIXING SYSTEM i

LIMITING CONDITION FOR OPERATION 1

3.6.5.4 Two independent hydrogen mixing systems shall be OPERABLE.

j APPLICABILITY:

MODES 1 and 2.

ACTION:

I With one hydrogen mixing system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 j

hours.

SURVEILLANCE REOUIREMENTS 4.6.5.4 Each hydrogen mixing system shall be demonstrated OPERABLE:

a.

At least once per 92 days on a STAGGERED TEST BASIS by starting each i

system from the control room and verifying that the system operates for at least 15 minutes.

b.

At least once per 98 months by verifying a fan speed of at least l

1320 rpm.

FARLEY UNIT 2 3/4 6-22

PLANT SYSTEMS i

SURVEILLANCE REOUIREMENTS (Continued) 2.

Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER.

3.

Verifying that the stop check valves 3350A, 3350B, and 3350C are in the open position with the breaker to the valve operators locked open.

2k b.

At least once per K months during shutdown by:

l I

1.

Verifying that each automatic valve in the flow path actuates to its correct position on an auto pump start signal.

2.

Verifying that each motor driven pump starts automatically upon i

receipt of each of the following test signals:

a)

Safety injection, b), Steam generator water level low-low in any steam generator,

' -and c)

Loss of Site Power (LOSP).

3.

Verifying that the steam turbine driven pump starts automatically upon receipt of each of the following test signals:

a)

Undervoltage on 2 out of 3 reactor coolant pump buses, and b)

Steam generator water level low-low in two steam generators.

4.

Verifying that the turbine-driven auxiliary feedwater pump steam admission valves Q2N12V001A-A and Q2N12V001B-B will open when air is supplied from their respective air accumulators.

c.

The auxiliary feedwater system shall be demonstrated OPERABLE prior to entry into MODE 2 follcwing each COLD SHUTDOWN by performing a flow test to verify the normal flow path from the emergency condensate storage tank through each auxiliary pump to its associated steam generator.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

FARLEY-UNIT 2 3/4 7-5

PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

}

ACTION:

t With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANOBY within i

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 , t

SURVEILLANCE REQUIREMENTS

)

7) 4.7.3 At least t'wo component cooling water loops shall be demonstrated j

J OPERABLE:

At least once per 31 days by verifying that each accessible valve a.

(manual, power operated or automatic) in the flow path, servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per months during shutdown, by verifying that each l

automatic valve servicing safety related equipment' actuates to its t

correct position on a safety injection test signal.

)

i 4

s FARLEY-UNIT 2 3/4 7-11

s PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 At least two independent service water loops shall be OPERABLE with at least two service water pumps per loop.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 REOUIREMENTS 4.7.4 At least two service water loops shall be demonstrated OPERABLE:

a.

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

b.

At least once per honths during shutdown, by:

l 1.

Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a safety injection test signal.

2.

Verifying that the buried piping is leak tight by a visual inspection of the ground area.

FARLEY-UNIT 2 3/4 7-12

l 1

1 I

PLANT SYSTEMS

(

3/4.7.5 RIVER WATER SYSTEM is)

_ LIMITING CONDITION FOR OPERATION 3.7.5 At least two independent river water loops shall be OPERABLE with at least two river water pumps per loop.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one river water loop OPERABLE, restore at least two 1. oops to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE0VIREMENTS 4.7.5 Each river water loop shall be demonstrated OPERABLE:

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

a.

power operated or automatic), in the flow path, servicing safety

)

related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

- At least once per 9 months during shutdown, by:

l 1.

Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a low pond level signal.

2.

Verifying that the buried piping is leak tight by a visual inspection of the ground area.

[

T J'

FARLEY-UNIT 2 3/4 7-13

PLANT SYSTEMS m

3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.8 Two independent penetration room filtration systems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one penetration room filtration system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at 1sast 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 .

l

~

SURVEILLANCE REQUIREMENTS l

4.7.8 Each penetration room filtration system shall be demonstrated OPERABLE:

~

)

a.

At leas.t once per 31 days on a STAGGERED TEST BASIS by initiating,

~

from the control room, flow through the HEPA filters and charcoal i

adsorbers and verifying that the system has operated for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on during the past 31 days.

b.

At least once per months or (1) after any structural maintenance I

on the HEPA filteror charcoal adsorber housings, or (2) following painting, fire or chemical release that could have contaminated the charcoal adsorbers or HEPA filters in any ventilation zone communi-4 cating with the system by:

1.

Verifying that the cleanup system satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a, C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 5000 cfm +

101 FARLEY-UNIT 2 3/4 7-18

(-).~.PLANTSYSTEMS 3

SURVEILLANCE REOUIREMENTS (Continued) 4 2.

Verifying within 31 days after removal that a laboratory analysis

.of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

3.

Verifying a system flow rate of 5000 cfm + 10% during system operation when tested in accordance with XNSI N510-1975.

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.G.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

d.

At least once per months by:

{

l.

Verifying that the pressure drop across the combined HEPA

/ =4 filters and charcoal adsorber banks of less than 6 inches Water Gauge while operating the system at a flow rate of 5000 cfm 1 10%.

2.

Verifying that the system starts on a Phase B Isolation test signal.

3.

Verifying that the heaters dissipate 25 1 2.5 kw when tested in accordance with ANSI N510-1975.

e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the 00P when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 5000 cfm 10%.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 5000 cfm 1 10%.

FARLEY-UNIT 2 3/4 7-19 w-o-

iPLANTSYSTEMS 3/4.7.9 SNU8BERS a

p.*LINITINGCONDITIONFOROPERATION All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE.

3.7.9 APPLICABILITY

MODES 1, 2, 3 and t.

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber (s) to OPE 'ABLE status and perform an engineering evaluation per Specification 4.7.9.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS Each snubber shall be demonstrated OPERABLE by performance of the 4.7.9 following augmented inservice inspection program and the requirements of Specification 4.0.5.

a.

Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of POWER OPERATION and shall l.

include all snubbers listed in Tables 3.7-4a and 3.7-4b.

If less than two (2) snubbers are found' inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months i 25% from the date of the first inspection.

Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers Subsequent Visual,

per Inspection Period Inspection Period

O s.4. M months 2 25%

1 1836 months t 25%

9 -:$teonths t 25%

2 3,4

/lfo325. days

25%

5,6,7 62 days i 25%

8 or more 31 days

25%

The snubbers may be categorized into two groups:

Those accessible j

and those inaccessible during reactor operation.

Each group may.:be inspected indeperdently in accordance with the above schedule.

The inspection interval shall not be lengthened more than one step at a time.

A

The provisions of Specification 4.0.2 are not applicable.

FARLEY-UNIT 2 3/4 7-20

-,..--__,,,-,_%.m

.-,my,,,

.-,e_,,__,._

,,.,,-,_,_.-,m_,-n_.

PLANT SYSTEMS

]

SURVEILLANCE REQUIREMENTS (Continued) b.

Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY and (2) attachments to the Snubbers which foundation or supporting structure are secure.

appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and deter-mined CPERABLE per Specifications 4.7.9.d or 4.7.9.e.,as applicable.

However, when the fluid port of a hydraulic snubber is found to be

)

uncovered, the snubber shall be declared inoperable and cannot be determined OPERABLE via functional testing unless the test is started with the piston in the as found setting, extending the piston rod in the tension and compression mode directions. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

c.

Functional Tests At least once per months during shutdown, a representative sample l

)-

of 88 snubbers shall be functionally tested either in place or in a bench test.

If more than 3 snubbers do not meet the functional test acceptance criteria of Specification 4.7.9.d or 4.7.9.e, an additional sample selected according to the expression 22(a-3) shall be func-tionally tested, where a is the total number of snubbers found inoperable during the functional testing of the initial representative sample.

Functional testing shall continue according to the expression (22)b where b is the number of snubbers found inoperable in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers in Table 3.7-4a and 3.7-4b have been functionally tested.

Snubbers greater than 50,000 lb. capacity may not be excluded from 1

functional testing requirements.*

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of sn bers. At least 25% of the snubbers in the initial representative san.ple shall include snubters from the l

following three categories:

1.

The first snubber away from each. reactor vessel nozzle

)

"This portion of the specification is not effective until the second refueling outage or when a commercial in place testing device is available,whichever is

.later.

FARLEY-UNIT 2 3/4 7-21 o

i PLANT SYSTEMS

/

(

v SURVEILLANCE REOUIREMENTS (Continued) 4

{

]

f.

Snubber Service Life Monitoring i

A record of the service life of each snubber, the date at which the i

designated service life commences and the installation and main-tenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.n.

M Concurrent with the first inservice visual inspection and at least once per S Fmonths thereafter, the installation and maintenance l

records for each snubber listed in Tables 3.7-4a and 3.7-4b shall be I

reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.

If the indicated service llfe' will be exceeded prior to the next scheduled snubber service life review, the snubber i

service life shall be reevaluated or the snubber shall be replaced or reconditioned so as-to extend its service life beyond the date of the next scheduled service life review.

This reevaluation, replacement or reconditioning shall be indicated in the records.

f 5-1 l

i l

.)

l i

i FARLEY-UNIT 2 3/4-7-24

/

PLANT SYSTEMS W

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

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

volume.

b.

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

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

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

d.

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

l e.

At least once per months by cycling each testable valve in the l

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

f.

At least once per months by performing a system functional test' l-which includes simi6ated automatic actuation of the system throughout its operating sequence, and:

1.

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

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

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

g.

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

4.7.11.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

At least once per 31 days by verifying:

a.

1.

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

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

FARLEY-UNIT 2 3/4 7-53

PLANT SYSTEMS l

' SPRAY AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.2 The spray and/or sprinkler systems listed in Table 3.7-5 shall be OPERABLE.

1 i

APPLICABILITY:

Whenever equipment in the spray / sprinkler protected areas is required to be OPERABLE.

i ACTION:

a.

With one or more of the above required spray and/or sprinkler systems i

inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant l

systems or components could be damaged; for other areas, establish a hourly fire watch patrol.

Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specifi-cation 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining 4

the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.7.11.2 Each of the above required spray and/or sprinkler systems shall be demonstrated OPERABLE:

I a.

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

l$

b.

At least once per M ! months by cycling each testable valve in the l

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

-)

FARLEY-UNIT 2 3/4 7-55

i PLANT SYSTEMS s

SURVEILLANCE REQUIREMENTS (Continued)

M c.

At least once per GF. months:

1.

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

a)

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

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

2.

By a visual inspection of the dry pipe spray and sprinkler headers-to verify their integrity, and 3.

By a visual inspection of each nozzle's spray area to verify the spray pattern has not become obstructed beyond design conditions.

9 6

.l j

k,

.e**

3 FARLEY-UNIT 2 3/4 7-56

PLANT SYSTEMS CO SYSTEMS 2

LIMITING CONDITION FOR OPERATION 3.7.11.3 The following high pressure and low pressure CO systems shall be 2

OPERABLE.

a.

Service Water Intake Structure (each 4160 volt bus and each 600 volt load center - HP.

b.

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

c.

Diesel Building 5 ton unit and distribution system.

APPLICABILITY: Whenever equipment protected by the CO systems in required to 2

be OPERABLE.

+

ACTION:

a.

With one'or more of the above required C0 systems inoperable, 7

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

Restore the system to OPERABLE status within 1

14 days-or, lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.7.11.3.1 Each of the above required C0 systems shall be demonstrated 9

OPERABLE at least once per 31 days by verifying that.each manual valve in the flow path is in its correct position.

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

2 At least once per 7 days by verifying the CO, storage tank level to a.

be greater than 50% and pressure to be great 8r than 250 psig, and b.

At least once per months by verifying:

l 1.

The system valves and associated ventilation dampers and fire door release mechanisms actuate manually and automatically, 3

upon receipt of a simulated actuation signal, and

)l l

2.

Flow from each nozzle during a " Puff Test."

FARLEY-UNIT 2 3/4 7-58 C

PLANT SYSTEMS j

SURVEILLANCE REQUIREMENTS (Continued) 4.7.11.3.3 Each of the above required high pressure CO systems shall be 2

demonstrated OPERABLE:

storage tank weight a.

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

At least once per rmonths by:

l 1.

Verifying the system, including associated ventilation dampers and fire door release mechanisms, actuates manually and auto-matica11y, upon receipt of a simulated actuation signal, and 2.

Performance of a flow test through headers and nozzles to assure no blockage.

4 t

i l

l

\\

l j

i i

4 i

./

FARLEY-UNIT 2 3/4 7-59

PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-6 shall be OPERABLE.

APPLICABILITY:

Whenever equipment in the areas protected by the fire hose stations is required to be CPERABLE.

ACTION:

a.

With one or more of the fire hose stations shown in Table 3.7-6 inoperable, route

an additional equivalent capacity fire hose to 4

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

Restore the

~

fire hose station to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the

~

inoperability and the plans and schedule for restoring the station ~

to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.11.4 Each of the fire hose stations shown in Table 3.7-6 shall be demon-strated OPERABLE:

4 a.

At least once per 31 days by visual inspection of the fire hose stations accessible during plant operation to assure all required equipment is at the station.

b.

At least once per months by:

l 1.

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

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

c.

At least once per 3 years by:

1.

Partially opening en::h hose station valve to verify valve I

OPERABILITY and no flow blockage.

2.

Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure available at that hose station.

"If routing of the hose would require rendering a fire barrier penetration inoperable, hose will be routed up to but not through the penetration with sufficient hose length to reach the unprotected area (s).

l FARLEY-UNIT 2 3/4 7-60

i i

PLANT SYSTEMS j

YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES t

i

/

l LIMITING CONDITION FOR OPERATION i

J 3.7.11.5 The yard fire hydrants and associated hydrant hose houses shown in j

Table 3.7-7 shall be OPERABLE.

l APPLICABILITY:

Whenever equipment in the areas protected by the yard fire j

hydrants is required to be OPERABLE.

I j

ACTION:

{

a.

With one or more of the yard fire hydrant or associated hydrant hose t

houses shown in Table 3.7-7 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months have sufficient additional lengths of 2 1/2 inch diameter hose located in an adjacent j

OPERABLE hydrant hose house to provide service to the unprotected area (s) if the inoperable fire hydrant or associated hydrant hose i

house is the primary means of fire suppression; otherwise provide the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore the hydrant or hose house to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Specia1 l

Report to the Commission pursuant to Specification 6.9.2 within the next 30. days outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the hydrant or hose house to OPERABLE status.

j b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

/

SURVEILLANCE REOUIREMENTS I

4.7.11.5 Each of the yard fire hydrants and associated hydrant hose houses

};

shown in Table 3.7-7 shall be demonstrated OPERABLE:

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

house to assure all required equipment is at the hose house.

2 P

b.

At least once per 6 months (once during March, April or May and once during September, October or November) by visually inspecting each i

I yard' fire hydrant and verifying that the hydrant barrel is dry and that the hydrant is not damaged.

AtleastonceperMmonthsby:

l c.

l 1.

Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maxiinum pressure available at any yard '

fire hydrant.

l 2.

Inspecting all the gaskets and replacing any degraded gaskets N

j in the couplings.

j j

3.

Performing a flow check of each hydrant to verify its OPERABILITY.

../

i' FARLEY-UNIT 2 3/4 7-62

PLANT SYSTEMS i

3/4.7.12 FIRE BARRIER PENETRATIONS

/ N,

., y' LfMITING CONDITION FOR OPERATION i

3.7.12 All fire barrier penetrations (including cable penetration barriers, firedoors and fire dampers) in fire zone boundaries protecting safety related areas shall be functional.

1 APPLICABILITY:

At all times.

i ACTION:

a.

With one or more of the above required fire barrier penetrations

]

non-functional, within one hour either, establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier.and establish a hourly fire watch patrol.

Restore the non-functional fire barrier penetration (s) to functional status within 7 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the non-functional penetratioa and plans and schedule for restoring the fire barrier penetration (s) to functional status.

I b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

i j

SURVEILLANCE REQUIREMENTS i

4.7.12 Each of the above required fire barrier penetrations shall be verified to be functional:

a.

At least once per months by a visual inspection.

-l i

b.

Prior to returning a penetration fire barrier to functional status following repairs or maintenance by performance of a visual inspection of the affected penetration fire barrier (s).

i

/

FARLEY-UNIT 2 3/4 7-64

_~

.w

ELECTRICAL POWER SYSTEMS 3

ACTION (Continued) 7 l

1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 if (DG 1-2A and DG-2C) or(DG-2B and DG-1C) or (DG-1C and l

DG-2C) are inoperable; or 2.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 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 if DG 1-2A and DG-2B are inoperable; or 3.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if three or more diesel generators are inoperable.

Restore both diesel generator sets to OPERABLE status within 18 days from time of initial loss 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 REOUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the o.nsite Class 1E distribution system shall be:

a., Determined 0PERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and b.

Deomonstrated OPERABLE at least once per months during shutdown

(

}

by transferring unit power supply from the norrial circuit to the a1, ternate circuit.

~

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day tank.

2.

Verifying the fuel level 1,n the fuel storage tanks.

3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4.

Verifying the diesel starts and accelerates to at least 900 rpm for the 2850 kw generator and 514 rpm for the 4075 kw generators in less than or equal to 12 seconds. The generator voltage and frequency shall be > 3952 volts and > 57 Hz within 12 seconds after the start siglial and operates Tor 5 minutes.

5.

Verifying the generator is synchronized, loaded to 2700-2850 kw for the 2350 kw generator and 3875-4075 kw for the 4075 kw generator and operates for greater than or equal to 60 minutes.

l FARLEY-UNIT 2 3/4 8-3 9

,.r---,-

ELECTRICAL POWER SYSTEMS

}

l SURVEILLANCE REQUIREMENTS (Continued) 5.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

l

' b.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank obtained in accordance with ASTM-D270-65 is within the acceptable limits specified in Table 1 of ASTM 0975-74 when r.hecked for viscosity, water and sediment, c.

At least ence per 18 months by.

p;bjecting the diesel to an inspection and maintenance in accordance with procedures prepared in conjunction with its manufacturer's fecommen ations, f

A+ kas+ ace fer RY months 3.

Simulating a loss of of its power by itself, and:

a)

Verifying de-energization of the emergency busses and load shedding from the emergency busses.

b)

Verifying the diesel starts on the auto-start signal, energizes the egergency busses with permanently connected loads within 1Z7 seconds, energizes the auto-connected shutdown loads through the load sequencer and operates for t

3 greater than or equal to 5 minutes while its generator is loaded with the shutdown loads.

After energization of all loads, the steady state voltage and frequency of the emergency busses shall be maintained at 4160

420 volts and 60

1.2 Hz during this test.

A.

Verifying that on a Safety Injection test signal (without loss l

of offsite power) the diesel generator starts on the auto-start 1

signal and operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall be 1 3952 volts and 1 57 Hz within 12 seconds afuar the auto-start signal; the steady state generator voltage and frequency shall be maintained between 4160 t 420 volts and 60 1 1.2 Hz during this test.

Simulating a loss of offsite power in conjunction with a Safety l

~

y Injection test signal, and:

a)

Verifying de-energization of the emergency busses and load shedding from the, emergency busses.

Verifying the diesel starts on the auto-start signal, b) energizes the ejergency busses with permanently connected loads within irseconds, energizes the auto-connected emergency (accident) loads through the load sequencer and

Energization of the Unit 2 emergency bus for diesel generator 20,is, achieved within 26 seconds.

FARLEY-UNIT 2 3/4 8-4

.~

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

O operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the j

emergency busses shall be maintained at 4160,+ 420 volts and 60_+ 1.2 Hz during this test.

c)

Verifying that all automatic die'sel generator trips, except engine overspeed and generator differential and low lube oil pressure, are automatically bypassed upon loss of i

voltage on the emergency bus and/or a safety infection test signal.

j Y.

Verify that the diesel generators operate for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while l

loaded to 4353 kw* for the 4075 kw diesels and 3100* for the 2850 kw diese* s (2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months rating). After completing this 24-hour test, manually trip the diesel generator from the 2000-hour

load and demonstrate hot restart capability by performing Surveillance Requirement 4.8.1.1.2.a.4 within 10

minutes, Verifying that the auto-connected loads to each diesel generator l '

f do not exceed the 2000-hour rating of 4353 kw for the 4075 kw generator and 3100 kw for the 2850 kw generator.

I 5.

Verifying the diesel generator's capability to:

a)

Synchronize with the offsite power source while the gener-ator is loaded with its emergency loads upon a simulated restoration of offsite power.

b)

Transfer its loads to the offsite power source, and c)

Be restored to its standby status.

G.

Verifying that with the diesel generators operating in a test l

mode (connected to its bus), a simulated safety injectionssignal overrides the test mode by returning the diesel generator to j

standby operation.

8 Verifying that the automatic load sequence timer is OPERABLE l

with each load sequence time within + 10% of its required.value or 0.5 seconds whichever is greater.

Verifying that the following diesel generator lockout features l

prevent diesel generator starting only when required:

a)

Oil Temperature High (OTH)

For a one-time period only that expires on September 1,1983, the load shall be as shown (i.e., the 2000-hour ratings) for a minimum of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and for the remainder of the 24-hour period, the loads shall be at the continuous rating.

Reduction of load as necessary inanediately prior to tripping is acceptable for this one-time period.

FARLEY-UNIT 2 3/4 8-5 E

ELECTRICAL POWER SYSTEMS l

SURVEILLANCEREQUIREMENTS(Continued) b)

Coolant Temperature High (CTH) c)

Coolant Pressure Low (CPL)

I d)

Crankcase Pressure High (CCPH)

Verifying the capability to reject a load of greater than or

/0-equal to the largest single load associated with that diesel (approximately 1000 kw); while maintaining voltage generator between 3740 and 4580 volts and speed less than or pqual to 75%

l of the difference between nominal speed and the overspeed trip

/

setpoint.

At least once per 10 years or after any modifications which could l

o.-

affect diesel generator interdependence by starting the diesel generators simultaneously, and verifying that the diesel generators l

accelerate to at least 900 rps, for the 2850 kw generator and 514 rps for the 4075 kw generator, in less than or equal to 12 seconds.

,S.

At least once per 5 years, on a staggered basis, by verifying that l

the diesel generator can reject a load of 1200-2400 kw without tripping. The diesel generator output breaker (s) must remain closed r

such that the diesel generator is connected to at least one emergency 5

bus. Verify that all fuses and breakers on the energized emergency bus (es) are not tripped. The generator voltage shall remain within I

3330 and 4990 volts during and following the load rejection, 4.8.1.1.3 Reports - All diesel generator failures, valid or nonvalid, shall i

be reported to the Commission pursuant to Specification 6.9.1.

Reports of diesel generator failures shall include the information recommended in Regu-3 latory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977. If l

the number of failures in the last 100 valid tests (on a per diesel basis) is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

l l

l 1

i 3/4 8-6

)

FARLEY-UNIT 2 i

.,. - _. ~

.., -. _. - ~..

ELECTRIbALPOWERSYSTEMS SURVEILLANCE REOUIREMENTS (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.

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, and 4.

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

c.

At least once per months by verifying that:

1 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 536 amperes at

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

(

2.+

l) -

~

d.

At least once per SS months during shutdown, 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 Loads Are Current Duration Acolied (amos)

(min.)

~

1 920 1

a 2

430 58 3

920 1

4 430 59 5

920 1

I

(

rj FARLEY-UNIT 2 3/4 8-12

l l

ELECTRICAL POWER SYSTEMS i

~3 SURVEILLANCE REQUIREMENTS (Continued) 2.

The voltage of each connected cell is greater than or equal to j

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 i

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 l

during the previous test.

c.

At least once per 8 months by verifying that:

l 1.

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

2.

The cell-to-cell and terminal connections are clean, tight, and I

coated with anti-corrosion material, and 3.

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

I for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

.s Atleastonceperthmonths,duringshutdown,byverifyingthatthe 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 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 e'quivalent load profile Order in Which Current Loads are Apolied (amos)

Duration l

[

1 25 0 - 0.1 see

]

2 1-0.1 see - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months l

I

?

9 i

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f f

i FARLEY-UNIT 2 3/4 8-16 L

ELECTRICAL POWER SYSTEMS

)s 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES b

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.1 All containment penetration conductor overcurrent protective devices shown in Table 3.8-1 shall be OPERABLE.

Circuits of devices indicated in Table 3.8-1 by an asterisk (*) shall be deenergized.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one or more of the containment penetration conductor overcurrent protective device (s) shown in Table 3.8-1 inoperable:

a.

Restore the protective device (s) to OPERABLE status or deenergize the circuit (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which are deenergized, or b.

Be in at.least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD N

SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

)

With one or more of the containment penetration conductor overcurrent protective devices (s) indicated by an asterisk (*) in Table 3.8-1 energized except as shown:

a.

Deenergize the circuits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or b.

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

SURVEILLANCE REQUIREMENTS 4.8.3.1 All containment penetration conductor overcurrent protective devices shown in Table 3.8-1 shall be demonstrated OPERABLE:

a.

At least once per

! months:

l 1.

For at least one 4.16 KV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at least once per inonths, by performance of:

l (a) A CHANNEL CALIBRATION of the associated protective relays, and (b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed and as specified in Table 3.8-1.

FARLEY-UNIT 2 3/4 8-18

ELECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.2 The thermal overload protection devices, integral with the motor starter, of each valve listed in Table 3.8-2 shall be OPERABLE.

APPLICABILITY:

Whenever the motor operated valve is required to be OPERABLE.

ACTION:

With one or more of the thermal overload protection devices inoperable, declare the affected valve (s) inoperable and apply the appropriate ACTION Statement (s).

1 SURVEILLANCE REQUIREMENTS L+

Theaboverequiredthermalover1[dprotectiondevicesshallbe 4.8.3.2 demonstrated OPERABLE at least once per W months by the performance of a l_

CHANNEL CALIBRATION of a representative sample of at least 25% of all thermal overload devices,'such that each device is calibrated at least once per # years.

l 8

9 0

i f

J FARLEY-UNIT 2 3/4 8-29

REFUELING OPERATIONS 3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER 1

LIMITING CONDITION FOR OPERATION 3.'9.14 The containment purge exhaust filter shall be OPERABLE and valve N1P13V293 closed.

APPLICABILITY:

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

ACTION: With the containment purge exhaust filter inoperable either:

1.

Immediately close the 48 inch containment purge isolation valves (CBV-HV-3196, 3197, 3198A and 31980) and the 18 inch containment mini purge isolation valves (C8V-HV-2866A, 2866B, 2867A and 28678),

or 2.

Cease all CORE ALTERATIONS and fuel movement.

SURVEILLANCE REOUIREMENTS

~

(

4.9.14 The above required containment purge exhaust filter shall be

),

demonstrated OPERABLE:

~ months or (1) after any structural maintenance I

a.

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

e l

f FARLEY-UNIT 2 3/4 9-16 l

l l

] REFUELING OPERATIONS

}

~

SURVEILLANCE REQUIREMENTS (Continued) 1.

Verifying that with the main purge system operating and ex-hausting through the HEPA filters and charcoal adsorbers, the total bypass flow of the system to the facility vent, including leakage through the system diverting valves, is less than or equal to 1% when the system is tested by admitting cold DOP at the system intake.

2.

Verifying that ths cleanup system satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, with the main purge system operating.

3.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of 75%. efficiency.

Is b.

After every E months of charcoal adsorber operation by verifying l

within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

c.

At least once per months by verifying that the pressure drop l

across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the main purge system.

FARLEY-UNIT 2 3/4 9-17 l

POWER DISTRIBUTION LIMITS 7

BASES 4

The radial peaking factor F additional assurance that the ho Ec(Z), is measured periodically to provide hannel factor, F (Z), remains within its RTPq i

limit.

The F limit for RATED THERMAL POWER (Fxy ) as provided in the Radial xy Peaking Factor limit report per Specification 6.9.1.14 was determined from expected power control maneuvers over the full ringe of burnup conditions in

~

the core.

~

),

3/4.2.4 OVADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during startup testing and periodically during power operation.

4 The limit of 1.02, at which corrective action is required, provides DNB-and linear heat generation rate protection with x y plane power tilts.

The two hour T.ime allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod.

In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by q

reducing the maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.

3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses.

The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated

l adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

The

$ $F month periodic measurement of the RCS total flow rate is adequate to detect l

flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months basis.

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FARLEY-UNIT 2 B 3/4 2-5 lt

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,i l

E --

1

1 PLANT SYSTEMS i

C BASES N

3/4.7.9 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity

]

. of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.

Snubbers excluded from this inspection program are those installed on nonsafety related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety related system.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically g

susceptible, and verified by inservice functional testing, that snubber may be g) exempted from being counted as inoperable.

Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.

When a snubber is found inoperable, an engineering evaluation is performed.

The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the attached component.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at'40: month intervals.

Selection of a representative sample according l

A+

totheexpression35(1+{}providesaconfidencelevelofapproximately95%

that 90% to 100% of the snubbers in the plant will be OPERABLE within' acceptance limits, where c is the allowable number of snubbers not meetino the accaotance criteria.

Observed failures of these sample snubbers shall require functional testing of additional units.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surv~eillance programs.

(

J FARLEY-UNIT g B 3/4 7-5

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ML20073C392

Text

3.7.9 APPLICABILITY

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