Text

Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details
	ML20207C245
Person / Time
Site:	Farley
Issue date:	02/22/1999
From:	; SOUTHERN NUCLEAR OPERATING CO.
To:	;
Shared Package
ML20207C235	List: ML20207C227; ML20207C245;
References
	NUDOCS 9903080406
	Download: ML20207C245 (109)
	v • d • e

.. - -

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

D

. i*

i i

i INDEX "I

i i

f FNP Unit 1 Technical Specifications i

Control Room, Penetration Room, and Containment Purge Filtration Systems l

and Ra6ation Monitoring Instrumentation Replacement Pages i

i X

Replace l

XIV Replace XV Replace 3/4 3-39 Replace 3/4 3-40 Replace 3/4 7-16 Replace 3/4 7-17

' Replace 3/4 7-17a Replace 7i 3/4 7-18 Replace i

3/4 7-19 Replace 3/4 9-14 Replace

{

3/4 9-15 Replace 3/4 9-16 Replace l

3/4 9-17 Replace 3/4 9-18 Replace 83/4 7-4 Replace i

B 3/4 7-4a Replace j

B 3/4 9-3 Replace i

L 1

i i

1 4

j s

i 9903080406 990221 PDR ADOCK 05000348 0

. P' PDR 3 t i

8

. J,

i. :.

1,. _

i INDEX

?

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 4

l SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BO RON CONC ENT RATION.................................. 3 / 4 9-1 3/4.9.2 INSTRUMENTATION...................................... 3/4 9-2 i

3/4.9.3 D ECAY T I ME........................................... 3 / 4 9 - 3 t

I 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.................... 3/4 9-4 i

l 3/4.9.5 COMMUNICATIONS..................................

.... 3/4 9-5 3/4.9.6 MANI PU LATO R CPANE.................................... 3 / 4 9-6 1

i 3/4.9.7 CRANE TRAVEL - SPENT MIEL STORAGE POOL BUILDING 1

I B ri dg e C r a n e......................................... 3 / 4 9 - 7 Sp ent Fuel Ca s k Crane................................ 3 / 4 9-8 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Water Leve1s..................................... 3/4 9-9 l

1...................................... 3/4 9-10 Low Water Leve 1

j 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM............................................... 3/4 9-11 3/4.9.10 WATER LEVEL - REACTOR VESSEL Fuel Assemblies...................................... 3/4 9-12 Co nt ro l Rods......................................... 3 / 4 9 -12 a i

4 3/4.9.11 WATER LEVEL - STORAGE POOL........................... 3/4 9-13 3/4.9.12 STORAGE POOL VENTILATION (FUEL STORAGE).............. 3/4 9-14 3/4.9.13 STORAGE POOL VENTILATION ( FUEL MOVEMENT )............. 3 / 4 9 - 15 1

l 3/4.9.14 CO!!T?.I""2?T P"SCE EX".""ST FILTES

.(Deleted).......... 3/4 9-16 l

i 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...................................... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS............................ 3/ 4 10-2 3/4.10.3 PHYSICS TESTS........................................ 3/4 10-3 3/4.10.4 REACTOR COOLANT LOO PS................................ 3 / 4 10- 4 3/4.10.5 POSITION INDICATION SYSTEMS - SHUTDOWN............... 3/4 10-5 FARLEY-UNIT 1 X

AMENDMENT No.

t INDEX BASES SECTION' PAGE 3/4.7 PLANT SYSTEMS a

3/4.7.1 TURBINE-CYCLE....

....................................B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION....... B 3/4 7 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................ B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM..................................B 3/4~7-3 3/4.7.5 MVER-WAMR-4WNiM ( Deleted).......................... B 3 / 4 7-3

. l 3/4.7.6 ULTIMATE HEAT SINK....................................B 3/4 7-4 9

3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.............B 3/4 7-4 3/4.7~8 PENETRATION ROOM FILTRATION SYSTEM....................B 3/4 7-4 3/4.7.9 SNUBBERS..............................................B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION...........................B 3/4 7-6 3/4.7.11

( Deleted).................... B 3/ 4 ' 7-6 3/4.7.13 F+RE-BARMER-MN89BANGHS (Deleted)................... B 3/ 4 7-7 3/4.7.13 FUEL STORAGE POOL BORON CONCENTRATION................. B 3/4 7-7 3/4.7.14 FUEL ASSEMBLY STORAGE.................................B 3/4 7-7 1

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER J

DISTRIBUTION SYSTEMS..................................B 3/4 8-1 i

a 4

l d

d W

FARLEY-UNIT 1 XIV AMENDMENT NO.

l i

i 1

=

o 2 -E.

-s 4

.s

.+

INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION...................................B 3/4 9-1 3/4.9.2 INSTRUMENTATION.......................................B 3/4 9-1 3/4.9.3 D ECAY T I ME............................................ B 3 / 4 9 - 1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.....................B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................B 3/4 9-1 3/4.9.6 MANIPUIATOR CRANE.....................................B 3/4 9-1 3/4.9.7 SPENT FUEL STORAGE BUILDING - BRIDGE CRANE and SPENT EVEL CASK CRANE.............................B 3/4 9-2 J

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION..........................................B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION S Y ST EM................................................ B 3 / 4 9 - 3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL.....................................B 3/4 9-3 3/4.9.12 and 3/4.9.13 STORAGE POOL VENTILATION SYSTEM...............................................B 3/4 9-3 3/4.9.14 GONTAIr". J:T runCE E5'.AUST FILTER (Deleted)...........B 3/4 9-3 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS...................................B 3/4 10-1 3/4.10.3 PHYSICS TESTS.........................................B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS.................................B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN.................B 3/4 10-1 FARLEY-UNIT 1 XV AMENDMENT NO.

.. ~.._. -.

l Table 3.3-6 RADIATION MONITORING INSTRUMENTATION g

MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION g.

.1.

AREA MONITORS 6

_i e-e a.

Fuel Storage Pool 1

(a) f 5 15 mR/hr 10

-10, mR/hr 23 4

Area (R-5) b.

Containment Area (R-27A&B) 2 1,2,3,4 N/A 1 - 10' R/hr 27a 2.

PROCESS MONITORS a.

Fuel Storage Pool Area Gaseous Activity-Ventilation S stem Isolation (R-5AEB) 1 (b) s 8.73 x 10-3 pcl/cc (c)10-106 25 cpm 2

(g,1) s 8.73 x 10-3 pCi/cc (c) 25 l

b.

Containment

i. Gaseous Activity-a)Pur e & Exhaust Iso ation (R-24A&B) 1 1,2,3,4,5,6 (d) s 2.27 x 10-2 pCi/cc(c)10-106 26 cpm w

2 (dsh) s 2.27 x 10-2 pC1/cc(c) 26

}

1 1,2,3,4,5,6 (e) s 4.54 x 10-3 pC1/cc(c) 26 2

(e&h) s 4.54 x 10-3 pCi/cc(c) 26 1

1,2,3,4,5,6 (f) s 2.27 x 10-3 pCi/cc(c) 26 W

w 2

(f&h) s 2.27 x 10-3 pC1/cc(c) 26

.e b)RCS Leakage 1

1,2,3 & 4 N/A 10-106 cpm 24 Detection (R-12)

11. Particulate Activity

)

RCS Leakage 1

1,2,3 & 4 N/A 10-106 cpm 24 Detection I

(R-11) c.

Control Room Isolation (R35AEB) 1 1,2,3,4 s 800 cpm 10-106 cpm 27 2

1,2,3,4,5,6(g&h)-

s 800 cpm 27 l

a N

5 8

e i

TABLE 3.3-6 (Continusd)

ACTION STATEMENTS ACTION 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 24 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1 With one channel inoperable return both channels to OPERABLE ACTION 25 status within 7 days or suspend all movement of irradiated fuel and crane operation with heavy loads over the spent fuel in the pool. With no channels CPERABLE, suspend all movement of irradiated fuel and crane operation with heavy loads over the spent fuel in the pool until at least one channel is restored to OPERABLE status.

ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the emergency recirculation l

mode of operation.

ACTION 27a -

With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1)

Elther restore the inoperable Channel (s) to OPERABLE status within 7 days, or 2)

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

a.

With fuel in storage pool.

b.

With irradiated fuel in the storage pool.

c.

Above background with no flow.

d.

With mini-purge in operation.

e.

With slow speed main purge in operation.

f.

With fast speed main purge in operation.

g.

During movement of irradiated fuel or movement of heavy loads over irradiated fuel in the fuel storage pool area.

h.

During movement of irradiated fuel or movement of heavy loads over irradiated fuel in containment.

FARLEY-UNIT 1 3/4 3-40 AMENDMENT No.

PLANT SYSTEMS 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM CONTROL ROOM EMERGENCY FILTRATION / PRESSURIZATION. SYSTEM (CREFS)-

LIMITING CONDITION FOR OPERATION 4 i

h 3.7.7.1 Two Control Roem Emergency Filtration / Pressurization System (CREFS) trains shall be OPERABLE.

l APPLICABILITY:

ALL MODES, during movement of irradiated fuel assemblies, and during movement of loads over irradiated fuel, i'

ACTION:

MODES 1, 2, 3 and 4:

With one CREFS train inoperable, restore the inoperable train to OPERABLE' status within 7 days or be in at least HOT STANDBY within the l

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

4 MODES 5, 6, during movement of irradiated fuel assemblies, and during movement of loads over irradiated fuel:

a.

With one-CREFS train inoperable, restore the inoperable system to l

l OPERABLE status within 7 days or immediately place the OPERABLE CREFS train in the emergency recirculation mode or immediately suspend movement of irradiated fuel assemblies and movement of loads over irradiated fuel.

b.

With both CREFS trains inoperable, immediately suspend movement of i

irradiated fuel assemblies and movement of loads over irradiated fuel.

SURVEILLANCE REQUIREMENTS 4.7.7.1 Each CREFS train shall be demonstrated OPERABLE:

a.

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

days.

'l FARLEY-UNIT 1

.3/4 7-16 AMENDMENT NO.

t PLAMT SYSTEMS I

SURVEILLANCE REQUIREMENTS.(Continued) b.

At least once per 18 months or (1) after.any structural maintenance on the HEPA filter or charcoal adsorber' housings, or j

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

4 I

a j

1.

Verifying that the cleanup system satisfies the in-place j

testing acceptance criteria of greater than or equal to 99.5% filter efficiency while operating the system at a flow j

rate indicated in Note 1 and using the following' test l

procedures:

4

(

(a)

A visual inspection of the control room emergency air l

cleanup system shall be made before each DOP test or activated carbon adsotSer section leak test in accordance with ASME N510-1989*.

j i

l (b)

An in-place DOP test for the HEPA filters shall be i

performed in accordance with ASME N510-1989*.

l t

1 (c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be performed l

in accordance with ASME N510-1989*.

l 4

i

)

2.

Verifying within 31 days after removal that a laboratory I

analysis of a representative carbon sample, obtained in accordance with ASME N510-1989* and tested in accordance

{

with ASTM D3803-1989, meets the laboratory testing i

efficiencies criteria given in Note 2 when tested with i

methyl iodide at 30*C and 70% relative humidity.

3.

Verifying a system flow rate as indicated in Note 1 during system operation when tested in accordance with ASME N510-l 1989*.

l After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by

)

c.

j verifying within 31 days after removal that a laboratory analysis of a representative carbon sample, obtained in I

accordance with ASME N510-1989* and tested in accordance with ASTM D3803-1989, meets the laboratory testing efficiencies criteria i

given in Note 2 when tested with methyl iodide at 30*C and 70%

i relative humidity.

1 m

1 The FNP Final Safety Analysis Report identifies the relevant surveillance j

testing requirements.

1 J

FARLEY-UNIT 1 3/4 7-17 AMENDMENT No.

1 r

1 m

-i y

w m m m m

a

--a a

a-

-u-m

-r

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than that indicated in Note 3 while operating the system at a flow rate indicated in Note 1.

2.

Verifying that the filter train starts on a Safety Injection Actuation test signal.#

3.

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

4.

Verifying that the pressurization system heater dissipates 2.5 i 0.5 kw when tested in accordance with ASME N510-1989*.

l After each complete or partial replacement of a HEPA filter bank e.

by verifying that the HEPA filter banks remove greater than or equal to 99.5% of the DOP when they are tested in-place in accordance with ASME N510-1989* while operating the system at a l

flow rate indicated in Note 1.

f.

Af ter each conclete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.5% of a halogenated hydracarbon refrigerant test gas when they are tested in-place in accordance with ASME N510-l 1989* while operating the system at a flow rate indicated in Note 1.

Note 1.

a.

Control Room Recirculation Filter Unit 2000 cfm i 10%

b.

Control Room Filter Unit 1000 cfm i 10%

c.

Control Room Pressurization Filter Unit 300 cfm +25% to

-10%

Note 2.

a.

Control Room Recirculation Filter Unit 2 97.5%

b.

Control Room Filter Unit 2 97.5%

c.

Control Room Pressurization (6 in. bed depth) 2 99.5%

Note 3.

a.

Control Room Recirculation Filter Unit 2.3 in. Water Gauge b.

Control Room Filter Unit 2.9 in. Water Gauge c.

Control Room Pressurization Filter Unit 2.2 in. Water Gauge

Surveillance Requirement 4.7.7.1.d.2 does not apply in MODES 5 and 6.

The FNP Final Safety Analysis Report identifies the relevant surveillance testing requirements.

l FARLEY-UNIT 1 3/4 7-17a AMENDMENT NO.

-... - -_ ~...-.__.___

_ _ _. ~ _.. _

i PLANT SYSTEMS i

j 3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION l

3.7.8-Two independent penetration room filtration systems shall be. OPERABLE.

l APPLICABILITY:

MODES 1, 2, 3 and 4, 1

ACTION:

1-t 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 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 i

SURVEILLANCE REQUIREMENTS 4

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

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

a.

from the control room, the flow through the HEPA filters and.

charcoal adsorbers and verifying that the system has operated for at least 15 minutes in its post.LOCA alignment.

2 i

b.

At least once per 18 months or (1) after any structural

{

l maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release that could have l

contaminated the charcoal adsorbers or HEPA filters in any j

ventilation zone communicating with the system by:

3j-1.

Verifying that the cleanup system satisfies the in-place testing acceptance criteria of greater than or equal to

l 99.5% filter efficiency while operating the system at a flow j

rate of 5000 cfm +20 to -10 percent and using the following l

j test procedures:

(a)

A visual inspection of the penetration room filtration system shall be made before each DOP test or activated 2

carbon adsorber section leak test in accordance with f

ASME N510-1989*.

(b)

An in-place DOP test for the HEPA filters shall be performed in accordance with ASME N510-1989*.

(c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be performed g

in~accordance with ASME N510-1989*.

l

{

w

The FNP Final Safety Analysis Report identifies the relevant surveillance 4

testing requirements.

h.

1 f

FARLEY-UNIT 1 3/4 7-18 AMENDMENT No.

9 w

y 4

s......

m

- ~,..

-~.. -..

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample, obtained in accordance with ASME N510-1989* and tested in accordance with ASTM D3803-1989, meets the laboratory testing criterion of greater than or equal to 90% efficiency when tested with methyl iodide at 30*C and 95% relative humidity.

3.

Verifying a system flow rate of 5000 cfm +20% to -10% during system operation when tested in accordance with ASME N510-1989*.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying c.

within 31 days after removal that a laboratory analysis of a representative carbon sample, obtained in accordance with ASME N510-1989* and tested in accordance with ASTM D3803-1989, meets the laboratory testing criterion of greater than or equal to 90%

efficiency when tested with methyl iodide at 30*C and 95% relative humidity.

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks of less than 2.6 inches Water Gauge while operating the system at a flow rate of 5000 cfm +20% to -10%.

2.

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

At least once per 36 months on a STAGGERED TEST BASIS by verifying e.

one PRF train can maintain a pressure s -0.125 inches water gauge relative to adjacent areas during the post LOCA mode of operation at a flow rate of 5 6000 cfm.

f.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.5% of the DOP when they are tested in-place in accordance with ASME N510-1989* while operating the systen at a flow rate of 5000 cfm +20% to -10%.

g.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.5% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ASME N510-1989* while operating the systen at a. flow rate of 5000 cfm +20% to -10%.

The FNP Final Safety Analysis Report identifies the relevant surveillance testing requirements.

I FARLEY-UNIT 1 3/4 7-19 AMENDMENT NO.

REFUELING OPERATIONS 3/4.9.12 STORAGE POOL VENTILATION (E1JEL STORAGE)

LIMITING CONDITION FOR OPERATION 3.9.12 One penetration room filtration system (Specification 3.7.8) shall be OPERABLE and aligned to the spent fuel pool room.

APPLICABILITY:

Whenever irradiated fuel is in the storage pool.

l ACTION:

1 l

With no penetration room filtration system OPERABLE, suspend all a.

operations involving movement of irradiated fuel within the l

storage pool until at least one penetration room filtration system is' restored to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS l

4.9.12.1 A penetration room filtration system shall be verified to be aligned to the spent fuel pool room within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to storage of fuel in the spent fuel pool and at least once per 7 days thereafter while fuel is stored in the storage pcol.

{

4.9.12.2 The penetration room filtration system shall be demonstrated OPERT 3LE:

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

from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system has operated for at least i

15 minutes in its fuel handling accident alignment.

b.

Filter testing per requirements of Specification 4.7.8.b, c, d.1,

{

i and g.

1 i

4.9.12.3 At least once per 18 months, verify that the normal spent fuel pool ventilation system will isolate upon receipt of either; a.

The spent fuel pool ventilation low differential pressure test signal, or b.

A spent fuel pool high radiation test signal.

EARLEY-UNIT 1 3/4 9-14 AMENDMENT NO.

I

PEFUELING OPERATXONS 3/4.9.13 STORAGE POOL VENTILATION (FUEL MOVEMENT)

LIMITING CONDITION FOR OPERATION 3.9.13 Two independent penetration room filtration r,ystams (Specification 4

3.7.8) shall be CPERABLE

and aligned to the spent fue's pool room:

L

=

APPLICABILITY:

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

l

^

l ACTION:

With one penetration room filtration system inoperable return both a.

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

fuel in the storage pool room.

I b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS i

a l

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

i 4.9.13.2 The penetration room filtration system shall be demonstrated OPEAABLE per the requirements of Specifications 4.9.12.2 and 4.9.12.3.

4 i

4 J

4

The normal or Omergency power source may be inoperable in MODE 5 cr 6 provided that the requirements of TS 3.8.1.2 are satisfied.

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

i

REE1JELING OPERATIONS 3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER This specification deleted.

l FARLEY-UNIT 1 3/4 9-16 AMENDMDrf NO.

This page intentionally left blank.

3/4.9.14 Deleted O

TARLEY-UNIT 1 3/4 g-17 AMENDMENT NO.

l This page intentionally left blank.

3/4.9.14 Deleted F

FARLEY-UNIT 1 3/4 9-18 AMENDMENT NO.

-.__m PLANT SYSTEMS

.f BASES L

3/4 7.6;l ULTIMATE HEAT SINK (RIVER)

This specification deleted.

3/4 7.6.2 ULTIMATE HEAT SINK (POND) i The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to micigate the effects of accident i

conditions within acceptable limits.

The limitations on minimum water level and maximwn temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature. The measurement of the i

ground water seepage at least once per 5 years will provide assurance that the 30 day supply of water is available.

3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM-The control room emergency filtration / pressurization system (CREFS) consirr

wo independent, redundant trains that recirculate and filter the contre ir, and two independent, redundant trains that pressurize the cont I teca

.he OPERABILITY of this system in conjunction with control room desj s p er;vi

'ns is based on limiting the radiation exposure to personnel ocet

"- tr' ontrol room to 5 rem or less whole body, or its equivalent.

This an is consistent with the requirements of General Design Criteria

.anaix

'A',

10CFR50.

19 of When one CREFS train is inoperable, action must be taken to restore OPERABLE status within 7 days. In this condition, the remaining OPERABLE CREFS train is adequate to perform the control room protection function.

However, the overall reliability is reduced because a single failure in the OPERABLE CREFS train could result in loss of CREFS function. The 7 day Completion Time is based on the low probability of a DBA occurring during this period of time, and ability of the remaining train to provide the required l

capability.

Operation of the pressurization unit with the heater circuits energized for at least 10 continuous hours over a 31 day period is sufficient l

l to reduce the buildup of moisture on the adsorbers and HEPA filter and to l

l verify system stability.

The control room air conditioning system (CRACS) consists of two independent, redundant trains that provide cooling of recirculated control room air.

Each centrol room air conditioning (CRAC) train is inoperable if it is not capable of removing the required heat load for plant conditions.

The actual heat load and the heat removal capability needed to adequately cool the j

control room is dependent upon factors such as outdoor air temperature.

i l

l I

EARLEY-UNIT 1 B 3/4 7-4 AMENDMENT NO.

I

PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (continued)

With one CRAC train inoperable, the inoperable train must be returned to OPERABLE status within 30 days. This Allowed Outage Time is based on the low probability of complete loss of control room cooling due to the redundancy of the support systems, the capability of the OPERABLE train to provide the required cooling, the potential that plant staff actions can restore or mitigate the effects of component failures, and the time available to respond as loss of contral room cooling does not have an immediate, irreversible impact.

While in MODES 5 and 6 during movement of irradiated fuel assemblies or movement of loads over irradiated fuel, if both trains of CRAC cannot be restored to OPERABLE status within 30 days, an OPERABLE CRAC train must be placed in operation immediately; otherwise, immediately suspend movement of irradiated fuel assemblies and movement of loads over irradiated fuel.

The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

3/4.7.8 PD4ETRATION ROOM FILTRATION SYSTEM The OPERABILITY of the penetration room filtration system provides reasonable assurance that radioactive materials leaking from ECCS pump rooms during post LOCA recirculation are filtered prior to reaching the environment.

The minimum system flow rate maintains a slightly negative pressure in the penetration room area and ECCS pump rooms assuming only one filter train is operating. The maximum system flow rate ensures that the pressure drop across filters is not excessive and adequate residence time is attained in the charcoal filter. The PRF system is tested periodically in its post LOCA

)

alignment.

Periodic testing of the RHR heat exchanger room pressure to less than or equal to -0.125 inch water gauge with respect to adjacent area pressure (as measured by the AP between the PRF mechanical equipment room and l

the RHR Heat Exchanger room) at a flow rate of s 6000 cfm verifies the integrity of the PRF system pressure boundary and is consistent with the guidance for standard technical specifications in NUREG 1431.

Functional testing of proper PRF system operation and pressure boundary integrity provides reasonable assurance that unfiltered release to adjacent areas of any ECCS leakage will be minimized. The operation of this sysrem and the resultant effect from the ECCS leakage on offsite dosage calculations was assumed in the accident analyses. Although not credited in the accident analyses, the PRF system also provides filtration of containment leakage into the penetration room areas.

J FARLEY-UNIT 1 B 3/4 7-4a AMENDMENT NO.

l REFUELING OPERATIONS BASES 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.12 and 3/4.9.13 STORAGE POOL VENTILATION SYSTEM The OPERABILITY of the penetration room filtration system ensures that radioactive materials leaking from the spent fuel pool area following a Fuel Handling Accident (FRA) are filtered prior to reaching the environment. The PRF system is tested periodically in its FRA alignment to ensure the system functions properly. ' Testing of HEPA filter performance, charcoal adsorber efficiency, and the physical properties of the activated charcoal is bounded by testing performed per 4.7.8.

The OPERABILITY of this system and the resulting lodine removal c.pacity are consistent with the assumptions of the accident analyses.

The note regarding PRF electrical system OPERABILITY is provided for clarification to specification 3/4.9.13.

In MODES 5 and 6, the electrical power requirements do not require considering a single failure coincident with a loss of all offsite or all onsite power. The design basis for electrical sources during refueling requires at least one offsite circuit through the lE distribution system be operable and at least one of the emergency diesels be operable. The electrical requirements of 3.8.1.2 meet the electrical sources OPERABILITY requirements for two independent PRF systems.

3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER This specification deleted.

FARLEY-UNIT 1 B 3/4 9-3 AMENDMENT NO.

i l

j 1

1 i-i Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems J

and Radiation Monitoring Instrumentation Technical Specification Changes Unit 2 Revised Technical Specification Pares d

l i

j

- ~..

i.

1 a

1 4

i

- 1 i

4 FNP Unit 2 I

Technical Specificanons Control Room, Penetration Room, and Containment Purge Filtration Systems i

and Radiation Monitonng Instrumentation Insert Pares l

x Replace 1

XIV Replace l

XV Replace i

3/4 3-39 Replace 3/4 3-40 Replace 3/4 7-16 Replace 3/4 7-17 Replace 3/4 7-17a

- Replace 3/4 7-18 Replace 3/4 7-19 Replace 3/4 9-14 Replace 3/4 9-15 Replace -

3/4 9-16 Replace 3/4 9-17 Replace 3/4 9-18 Replace B 3/4 7 4 Replace B 3/4 7-4a Replace -

B 3/4 9-3 Replace eP e

w i

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

.~-

8NDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION..................................

3/4 9-1 3/4.9.2 INSTRUMENTATION......................................

3/4 9-2 9

3/4.9.3 DECAY TIME........................................... 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.................... 3/4 9 3/4.9.5 COMMUNICATIONS....................................... 3/4 9-5 3/4.9.6 MANI PULATOR CRAN E.................................... 3 / 4 9 - 6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING Bridge Crane......................................... 3/4 9-7 Sp ent Fuel Ca s k Crane................................ 3 / 4 9-8 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Water Levels..................................... 3/4 9-9 Lo w Wa t e r Le ve l...................................... 3 / 4 9-10 3/4.9.9 CONTAINMENT PURGE AND EXHAb ; ISOLATION SYSTEM............................................... 3/4 9-l'1 i

3/4.9.10 WATER LEVEL - REACTOR VESSEL Fuel Assemblies...................................... 3/4 9-12 control Rods......................................... 3/4 9-12a 3/4.9.11 WATER LEVEL - STORAGE POOL........................... 3/4 9-13 3/4.9.12 STORAGE POOL VENTILATION ( MIEL STORAGE).............. 3/ 4 9-14 3/4.9.13 STORAGE POOL VENTILATION (FUEL MOVEMENT)............. 3/4 9-15 3/4.9.14 CCt?Tf.!n'~:T r"nCE E c'.*"ST FII.TED. (Deleted).......... 3/4 9-16 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...................................... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS............................ 3/4 10-2 3/4.10.3 PHYSICS TESTS........................................ 3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS................................ 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN................ 3/4 10-5 FARLEY-UNIT 2 X

AMENDMENT NO.

INDEX e

BASES PAGE SECTION 3/4.7 PLANT SYSTEMS I

3/4.7.1 TURBINE CYCLE.........................................B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................B 3/4 7-3~

t 3/4.7.4 S ERVI C E WAT ER S YSTEM.................................. B 3 / 4 7-3 3/4.7.5 nn~n '3*. ten SYSTE (Dele ted).......................... B 3/4 7-3 l

4 1

3/4.7.6 ULTIMATE HEAT SINK....................................B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.............B 3/4 7-4 3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM....................B 3/4 7-4 l

7 3/4.7.9 SNUBBERS..............................................B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION...........................B 3/4 7-6 i

3/4.7.11 F!nE S"P PRES!!^" SYST"'I (Dele ted)..................... B 3/ 4 7-6 3/4.7.12 FIri ".*.nn:En rE"ET"*.T:^"

(Deleted)...................B 3/4 7-7 3/4.7.13 AREA TEMPERATURE MONITORING...........................B 3/4 7-7 3/4.7.14 FUEL STORAGE POOL BORON CONCENTRATION................. B 3/4 7-7 l

3/4.7.15 FUEL ASSEMBLY STORAGE.................................B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS..................................B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTION DEVICES...............B 3/4 8-1

]

FARLEY-UNIT 2 XIV AMENDMENT NO.

a.

r

... ~.

. ~. - -

.. -... ~ --

s INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS.

3/4.9.1 BORON CONCENTRATION...................................B 3/4 9-1 3/4.9.2

' IN ST RUMENTATION....................................... B 3 / 4 9 - 1

~

3/4.9.3 DECAY TIME.............................................B 3/4 9-1 i

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.....................B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE.....................................B 3/4 9 3/4.9.7 SPENT FUEL STORAGE BUILDING - BRIDGE CRANE and SPENT FUEL CASK CRANE.............................B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION..........................................B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM................................................B 3/4 0-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL.....................................B 3/4 9-3 3/4.9.12 and 3/4.9.13 STORAGE POOL VENTILATION SYSTEM...............................................B 3/4 9-3 3/4.9.14 (Deleted)...........B 3/4 9-3 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS...................................B 3/4 10-1 3/4.10.3 PHYSICS TESTS.........................................B 3/4 10-1 i

3/4.10.4 REACTOR COOLANT LOOPS.............a...................B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN.................B 3/4 10-1 FARLEY-UNIT 2 XV AMENDMENT NO.

I u

s

. _ -. ~.

~-. - -.

Table 3.3-5 RADIATION MONITORING INSTRUMENTATION

-g MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT l-INSTRUMENT OPERABLE MODES SETPOINT RANGE I

ACTION g

I Q

1.

AREA MONITORS

_i y

w a.

Fuel Storage Pool 1

(a) 5 15 mR/hr 10

-10 mR/hr la H

Area (R-5) l u

b.

Containment Area (R-27A&B) 2 1,2,3,4 N/A 1 - 10' R/hr 27a 2.

PROCESS MONITORS a.

Fuel Storage Pool Area Gaseous Activity Ventilation S stem Isolation (R-SA&B) 1 (b) 5 8.73 x 10-3 pCi/cc(c)10-106 25 i

cpm 2

(g,1) 5 8.73 x 10-3 pCi/cc(c) 25

[

b.

Containment

i. Gaseous Activity-a)Pur e & Exhaust Iso ation (R-24A& B) 1,2,3,4,5,6 (d) 5 2.27 x 10-2 pCi/cc(c)10-106 26 cpm (dsh) 5 2.27 x 10-2 pC1/ce(c) f6 1,2,3,4,5,6 (e)

S 4.54 x 10-3 pCi/cc(c)

(e&h) s 4.54 x 10-3 pCi/cc(c) w 1,2,3,4,5,6 (f) s 2.27 x 10-3 pCi/cc(c) f6 6

(f&h) s 2.27 x 10-3 pC1/cc(c) 26 e

'e e3 4

N/A 10-106 24 b)RCS Leakage 1

cpm Detection (R-12) ii. Particulate Activity RCS Leakage 1

1,2,3 & 4 N/A 10-106 cpm 24 Detection (R-11) 1 c.

Control Room Isolation (R35A&B) 1 1,2,3,4 s 800 cpm 10-106 27 i

cpm 2

1,2,3,4,5,6(gsh) s 800 cpm 27

'l.

I R

5 5

-2

TABLE 3.3-6 (Continued)

ACTION STATEMENTS With the number of channels OPERABLE less than required by ACTION 23 the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With the number of channels OPERABLE less than required by ACTION 24 the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1 ACTION 25 With one channel inoperable return both channels to OPERABLE status within 7 days or suspend all movement of irradiated fuel and crane operation with heavy loads over the spent fuel in the pool. With no channels OPERABLE, suspend all movement of irradiated fuel and crane operation with heavy loads over the spent fuel in the pool until at least one channel is restored to OPERABLE status.

ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of specification 3.9.9.

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the emergency recirculation l

mode of operation.

ACTION 27a -

With the number of OPERABLE Channels less than required by the Minimum Channels OPF9ABLE requirement, initiate the preplanned alternate me od of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1)

Either restore the inoperable channel (s) to OPERABLE status within 7 days, or 2)

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, j

the cause of the inoperability and the plans and I

schedule for restoring the system to OPERABLE status.

a.

With fuel in storage pool.

i b.

With irradiated fuel in the storage pool.

c.

Above background eith no flow, d.

With mini-purge in operation.

e.

With slow speed main purge in operation.

f.

With fast speed main purge in operation.

g.

During movement of irradiated fuel or movement of heavy loads over irradiated fusi in the fuel storage pool area.

h.

During movement of irradiated fuel or movement of heavy loads over irradiated fuel in containment.

FARLEY-UNIT 2 3/4 3-40 AMENDMENT NO.

e i

PLANT SYSTEMS 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM-CONTROL ROOM EMERGENCY FILTRATION / PRESSURIZATION SYSTEM (CREFS )'

i LIMITING ' CONDITION FOR OPERA, TION 1

3.7.7.1 Two Control Room Emergency Filtration / Pressurization System (CREFS) trains shall be OPERABLE.

4 1

APPLICABILITY:

ALL MODES, during movement of irradiated fuel assemblies,

]

and during movement of loads over irradiated fuel.

ACTION:

MODES 1, 2, 3 and 4:

With one CREFS train inoperable, restore the inoperable train to j

OPERABLE status within 7 days or be in at least HOT STANDBY within the l

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 .

4 MODES 5, 6, during movement of irradiated fuel assemblies, and during movement I

of loads over irradiated fuels a.

With one CREFS train inoperable, restore the inoperable system to OPERABLE status within 7 days or immediately place the OPERABLE CREFS train in the emergency recirculation mode or immediately suspend movement of irradiated fuel assemblies and movement of loads over irradiated fuel.

b.

With borh CREFS trains inoperable, immediately suspend movement of irradiated fuel assemblies and movement of loads over irradiated fue1.

SURVEILLANCE REQUIREMENTS 4.7.7.1 Each CREFS train shall be demonstrated OPERABLE:

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

from the control room, flow through the pressurization and recirculation system HEPA filters and charcoal adsorbers and verifying that the pressurization system has operated for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heater circuits energized during the past 31 l

days.

i FARLEY-UNIT 2 3/4 7-16 AMENDMENT NO.

1

_.___4

._._.____-m

_m.

i i

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

]

b.

At least once per 18 months.or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or

)

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

i 1.

Verifying that the cleanup system satisfies the in place testing acceptance criteria of greater than or equal to 99.5% filter efficiency while operating the system at a flow-1 rate indicated in Note 1 and using the.following test.

procedures:

(a)

A visual inspection of the control room emergency air cleanup system shall be made before each DOP test or activated carbon adsorber section leak test in i

accordance with ASME N510-1989*.

(b)

An in-place DOP test for the HEPA filters shall be performed in accordance with ASME N510-1989*,

l (c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be performed-in accordance with ASME N510-1989*.

l 2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample, obtained in accordance with ASME N510-1989* and tested in accordance with ASTM D3803-1989, meets the laboratory testing efficiencies criteria given in Note 2 when tested with methyl iodide at 30*C and 70% relative humidity.

3.

Verifying a system flow rate as indicated in Note 1 during system operation when tested in accordance with ASME N510-1989*.

c.

Af ter 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 representative carbon sample, obtained in accordance with ASME N510-1989* and tested in accordance with ASTM D3803-1989, meets the laboratory testing efficiencies criteria given in Note 2 when tested with methyl iodide at 30*C and 70%

relative humidity.

s The FNP Final Safety Analysis Report identifies the relevant surveillance testing requirements.

1 FARLEY-UNIT 2 3/4 7 AMENDMENT NO.

I 1

a

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

1 PLANT SYSTEMS i

i SURVEILLANCE REQUIREMENTS (Continued) j d.

At least once per 18 months by:

i 1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than that i

indicated in Note 3 while operating the system at a flow rate indicated in Note 1.

j 2.

Verifying that the filter train starts on a safety Injection Actuation test signal.#

s 3.

Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8 inch water gauge relative to the outside atmosphere during system 3

operation.

i t

4.

Verifying that the pressurization system heater dissipates 2.5 i 0.5 kw when tested in accordance with ASME N510-1989*.

l After each complete or partial replacement of a HEPA filter bank i

e.

5 by verifying that the HEPA filter banks remove greater than or l

equal to 99.5% of the DOP when they are tested in-place in l'

accordance with ASME N510-1989* while operating the system at a l

flow rate indicated in Note 1.

1 l

f.

After each complete or partial replacement of a charcoal adsorber i

i bank by verifying th'at the charcoal adsorbers remove greater than l

or equal to 99.5% of a halogenated hydrocarbon refrigerant test i

gas when they are tested in-place in accordance with ASME N510-l 1989* while operating the system at a flow rate indicated in Note i

1.

l Note 1.

a.

Control Room Recirculation Filter Unit 2000 cfm i 10%

b.

Control Room Filter Unit 1000 cfm i 10%

{

c.

Control Room Pressurization Filter Unit 300 cfm +25% to

-10%

i i

Note 2.

a.

Control Room Recirculation Filter Unit 2 97.5%

b.

Control Room Filter Unit 2 97.5%

c.

Control Room Pressurization (6 in. bed depth) 2 99.5%

]

5 Note 3.

a.

Control Room Recirculation Filter Unit 2.3 in. Water Gauge b.

Control Room Filter Unit 2.9 in. Water Gauge 4

c.

Control Room Pressurization Filter Unit 2.2 in. Water Gauge

)

Surveillance Requirement 4.7.7.1.d.2 does not apply in MODES 5 and 6.

The FNP Final Safety Analysis Report identifies the relevant surveillance testing requirements.

l i

l FARLEY-UNIT 2 3/4 7-17a AMENDMENT NO.

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

PLANT SYSTEMS 3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM LIMITING CONDITION [0R 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 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 4.7.8 Each penetration room filtration system shall be demonstrated OPERABLE:

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

from the control room, the flow through the HEPA filters and charcoal adsorbers and verifying that the system has operated for at least 15 minutes in its post LOCA alignment.

b.

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

1.

Verifying that the cleanup system satisfies the in place testing acceptance criteria of greater than or equal to 99.5% filter efficiency while operating the system at a flow rate of 5000 cfm +20 to -10 percent and using the following l

test procedures:

(a)

A visual inspection of the penetration room filtration system shall be made before each DOP test or activated carbon adsorber section leak test in accordance with ASME N510-1989*.

1 4

(b)

An in-place DOP test for the HEPA filters shall be performed in accordance with ASME N510-1989*.

l (c)

A charcoal adsorber section leak test with a gaseous i

halogenated hydrocarbon refrigerant shall be performed in accordance with ASME N510-1989*.

The FNP Final Safety Analysis Report identifies the relevant surveillance testing requirements.

i i

I EARLEY-UNIT 2

'3/4 7-18 AMENDMENT NO.

_m__

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l

)

2.

Verifying within 31 days after removal that a laboratory

)

analysis of a representative carbon sample, obtained in accordance with ASME N510-1989* and tested in accordance j

with ASTM D3803-1989, meets the laboratory testing criterion j

of greater than or equal to 90% efficiency when tested with methyl iodide at.30*C and 95% relative humidity.

3.

Verifying a system flow rate of 5000 cfm +20% to -10% during system operation when tested in accordance with ASME N510-1989*.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying c.

within 31 days after removal that a laboratory analysis of a representative carbon sample, obtained in accordance with ASME N510-1989* and tested in accordance with ASTM D3803-1989, meets the laboratory testing criterion of greater than or equal to 90%

e efficiency when tested with methyl iodide at 30*C and 95% relative humidity.

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks of less than 2.6 inches Water Gauge while operating the system at a flow rate of 5000 cfm +20% to -10%.

l 2.

Verifying that the system starts on a Phase B Isolation test

signal, At least once per 36 months on a STAGGERED TEST BASIS by verifying e.

one PRF train can maintain a pressure s -0.125 inches water gauge relative to adjacent areas during the post LOCA mode of operation at a flow rate of s 6000 cfm.

f.

Af ter each complete or partial replacement of a HEPA filter bank

)

by verifying that the HEPA filter banks remove greater than or equal to 99.5% of the DOP when they are tested in-place in accordance with ASME N510-1989* while operating the systen at a flow rate of 5000 cfm +20% to -10%.

g.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than l

or equal to 99.5% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ASME N510-

]

1989* while operating the system at a flow rate of 5000 cfm +20% to -10%.

The FNP Final Safety Analysis Report identifies the relevant surveillance testing requirements.

I FARLEY-UNIT 2 3/4 7-19 AMENDMENT NO.

l l

1

REE11ELTNG OPERAT20NS 3/4.9.12 STORAGE POOL VENTILATION (FUEL STORAGE)

LIMITING CONDITION FOR OPERATION 3.9.12 One penetration room filtration system (Specification 3.7.8) shall be OPERABLE and aligned to the spent fuel pool room.

APPLICABILITY:

Whenever irradiated fuel is in the storage pool.

ACTION:

With no penetration room filtration system OPERABLE, suspend all a.

operations involving movement of irradiated fuel within the l

storage pool until at least one penetration room filtiation system is restored to OPERABLE status, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12.1 A penetration room filtration system shall be verified to be aligned to the spent fuel pool room within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to storage of fuel in the spent fuel pool and at least once per 7 days thereafter while fuel is stored in the storage pool.

4.9.12.2 The penetration room filtration system shall be demonstrated OPERABLE:

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

from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the' system has operated for at least i

15 minutes in its fuel handling accident alignment.

b.

Filter testing per requirements of Specification 4.7.8.b, c, d.1, f and g.

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

a.

The spent fuel pool ventilation low differential pressure test signal, or b.

A spent fuel pool high radiation test signal.

i, i

FARLEY-UNIT 2 3/4 9-14 AMENDMENT NO.

i I

-w I

i t

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

LIMITING CONDITION FOR OPERATION 3.9.13 Two independent penetration room filtration systeam (Specification 3.7.8) shall be OPERABLE

and aligned to the spent fuel pool-room:

APPLICABILITY:

During crane operation with loads, over the fuel in the g

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

I ACTION:

With one penetration room filtration system inoperable return both a.

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

fuel in the storage pool room, b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

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

4.9.13.2 The penetration room filtration system shall be demonstrated l

OPERABLE per the requirements of Specifications 4.9.12.2 and 4.9.12.3.

I s

i

The normal or emergency power source may be inoperable in MODE' S or 6 provided that the requirements of TS 3.8.1.2 are satisfied.

b FARLEY-UNIT 2 3/4 9-15 AMENDMENT NO.

REFUELING OPERATIONS 3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER This specification deleted.

FARLEY-UNIT 2 3/4 9-16 AMENDMENT No.

This page intentionally left blank.

3/4.9.14 Deleted FARLEY-UNIT 2 3/4 9 AMENDMENT NO.

1

This page intentionally left blank.

3/4.9.14 Deleted FARLEY-UNIT 2 3/4 9-10 AMENDMENT NO.

PLANT SYSTEMS BASES 3/4 7.6.1 ULTIMATE HEAT SINK (RIVER)

This specification deleted.

3/4 7.6.2 ULTIMATE HEAT SINK (POND)

The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature. The measurement of the ground water saepage at least once per 5 years will provide assurance that the 30 day supply of water is available.

3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The control room emergency filtration / pressurization system (CREFS) consists of two independent, redundant trains that recirculate and filter the control room air, and two independent, redundant trains that pressurize the control room. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.

This limitation is consistent with the requirements of General Design Criteria 19 of Appendix

'A',

10CFR50.

When one CREFS train is inoperable, action must be taken to restore OPERABLE status within 7 days.

In this Condition, the remainir.g OPERABLE CREFS train is adequate to perform the control room protection function.

However, the overall reliability is reduced because a single failure in the OPERABLE CREFS train could result in loss of CREFS function. The 7 day Completion Time is based on the low probability of a DBA occurring during this period of time, and ability of the remaining train to provide the required l

capability.

Operation of the pressuriz'ation unit with the heater circuits energized for at least 10 continuous hours over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter and to verify system stability.

The control room air conditioning system (CRACS) consists of two independent, redundant trains that provide cooling of recirculated control room air.

Each control room air conditioning (CRAC) train is inoperable if it is not capable of removing the required heat load for plant conditions.

The actual heat load and the heat removal capability needed to adequately cool the centrol room is dependent upon factors such as outdoor air temperature.

FARLEY-UNIT 2 B 3/4 7-4 AMENDMENT NO.

I i

PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (continued)

With one CRAC train inoperable, the inoperable train must be returned to OPERABLE status within 30 days. This Allowed Outage Time is based on the low probability of complete loss of control room cooling due to the redundancy of the support systems, the capability of the OPERABLE train to provide the required cooling, the potential that plant staff actions can restore or mitigate the effects of component failures, and the time available to respond as loss of control room cooling does not have an immediate, irreversible impact.

While in MODES 5 and 6 during movement of irradiated fuel assemblies or movement of lo' ads over irradiated fuel, if both trains of CRAC cannot be restored to OPERABLE status within 30 days, an OPERABLE CRAC train must be placed in operation immediately; otherwise, immediately suspend movement of irradiated fuel assemblies and movement of loads over irradiated fuel.

The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM The OPERABILITY of the penetration room filtration system provides reasonable assurance that radioactive materials leaking from ECCS pump rooms during post LOCA recirculation are filtered prior to reaching the environment.

The minimum system flow rate maintains a slightly negative pressure in the penetration room area and ECCS pump rooms assuming only one filter train is operating. The maximum system flow rate ensures that the pressure drop across filters is not excessive and adequate residence time is attained in the charcoal filter. The PRF system is tested periodically in its post LOCA alignment.

Periodic testing of the RHR heat exchanger room pressure to less than or equal to -0.125 inch water gauge with respect to adjacent area pressure (as measured by the AP between the PRF mechanical equipment room and the RHR Heat Exchanger room) at a flow rate of s 6000 cfm verifies the integrity of the PRF system pressure boundary and is consistent with the guidance for standard technical specifications in NUREG 1431.

Functional testing of proper PRF system operation and pressure boundary integrity provides reasonable assurance that unfiltered release to adjacent areas of any ECCS leakage will be minimized. The operation of this system and the resultant effect from the ECCS leakage on offsite dosage calculations was assumed in the accident analyses. Although not credited in the accident analyses, the PRF system also provides filtration of containment leakage into the penetration room areas.

J i

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

REFUELING OPERATIONS BASES

\\

3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations will be automatically isolated upon detection of high radiation levels within the containment.

The OPERABII*TY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accioent analysis.

3/4.9.12 and 3/4.9.13 STORAGE POOL VENTILATION SYSTEM The OPERABILITY of the penetration room flitration system ensures that radioactive materials leaking from the spent fuel pool area following a Fuel Handling Accident (FRA) are filtered prior to reaching the environment. The PRF system is tested periodically in its FRA alignment to ensure the system functions properly. Testing of HEPA filter performance, charcoal adsorber efficiency, and the physical properties of the activated charcoal is bounded by testing performed per 4.7.8.

The OPERASILITY of this system and the resulting lodine removal capacity are consistent with the asswmptions of the accident analyses.

The note regarding PRF electrical system OPERABILITY is provided for clarification to specification 3/4.9.13.

In MODES 5 and 6, the electrical power requirements do not require considering a single failure coincident with a loss of all offsite or all onsite power. The design basis for electrical sources during refueling requires at least one offsite circuit through the 1E distribution system be operable and at least one of the emergency diesels be operable. The electrical requirements of 3.8.1.2 meet the electrical sources OPERABILITY requirements for two independent PRF systems.

3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER This specification deleted.

FARLEY-UNIT 2 B 3/4 9-3 AMENDMENT NO.

l i

i Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes Units 1.12 Revised Marked-Up Technical Specification Pares l

l l

l

i Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes Unit 1 Revised Marked-Un Technical Specification Pages

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

I DecEX LIMITIM CCNOITICNS FOR CPERATICN AND SURVEILLAreCE RECUIR!DaEVT5

i SECTION PAGE 4

3/4.9 REFUELING CPERATICNS i

1 l

3/4.9.1 80RCN C:NCENTRATICN..........................

3/4 9-1 l

3/4.9. 2 IMST111MV. TATION..........................................

3/4 F 2 1

4. 9. 3 O ECAY T1M.'.........{.....................................3/4 P 3 l

}

3/4.9.4 C0$(TAD 64ENT SUILD ING PEMET1tATIONS........................

3/4 P 4 j

3/4.9.5 CDP 9tJNICATIONS...........................................

3/4 9-5 3/4.9.6 NAMIPULATOR CRAME........................................

3/4 9-6 i

3/4.9.7 CRANE T1tAVEL - SPENT FUEL STORAGE POOL BUILDING Sridge Crane.............................................

3/4 9-7 5 pent fue1 Cask Crane....................................

3/49-8

{

3/4.9.8 RESIDUAL MEAT ASCVAL AM C00t#ff CIACULATION All Water Lave 1s.................................... 7...

3/4 9-9 l

Law Water Lave 1.............

3/4 9-10 3/4.9.9 CONTADestT PUAGE AM OHAUST 150tATiON SY37EM...........

3/4 t=11 l

v4.9.10 m r u t m t - aEAcTon vEssa.

\\

Fue l As sme 1 1 es..........................................

3/4 9-12

]

Control Reds.............................................

3/4 Fua v 4.9. n m TER t m L - STo a st P00t................

v4 *13 3/4.9.12 STORAGE POOL V9tTILATIM (FUEL STORAGE)..................

3/4 bl4 i

j 3/4.9.13 STORAGE POOL V9tTILATION (PUEL Mv9 err).................

3/4 9-15 l

3/4.9.14 GINFAffset?- PM -GetW5t PttfER... b 3/4 9-18 3/4.10 SPECIAL TEST DCEPTIONS u4.10.1 m Tocm G1n..........................................

u4 10-1 i

l 3/4.10.2 G200P HEIGNT INSEXTION AND P0htt DISTRIBUTION LIMIT 3....

3/4 10-2

$N kk 3

.......................................e....

J v4.10.4 nEAcm C00uNr to0,5....................................

v4 10-4 i

3/4.40.5 POSITION IN0! CATION SYSTEMS - SHUTDOW...................

3/4 10-5 FMtLEY-UNIT 1 x

AMDOIENT NO. 25 4

(

a 4

. - ~

~-

M Eh172 i

L%I srrioN 3/4.7 PLAN

SYSM MS 7-1 3/4.7.1 TURRINE CT CLE.................................. *..... B 3 / 4 3/4.7.2 STEAM GENERATOR FRZs3URE/ TEMPERATURE 7-3 LI MITATI ON........................................... 3 3 / 4 7-3 c0MPONENT cooI.ING WATER SYSTEM....................... 3 3 /4 3/4.7.3 sERVIc2 wkTER 5YsTZM..................................E 3/4 7-3 3/4.7.4

- (b.4/.e.d.......................... 3 /4 7-3 3/4.2.s cI.TIx m nur sI,x....................................

3/4 2-4 3/4.7.4 3/4.7.7 coWTBot ROOM EMERGENc7 VENTILATION SYSTEM..................................... a.......... B 3 / 4 7 -4 PGNf?fyAT* &

3/4.7.s ases-asser moon assenvee-Ma FILTRATIow sYs;Ex................................................a 3/4 7-4 sNUssERs............................................. 3 3/4 7-5 3/4.7.9 SEALED socRet coNTAMINATIcet.......................... 5 3 /4 7-4 3/4.7.10 I

(Deleted)....................a 3/4 7-6 3/4.7.11 (Deleted)...................a 3/4 7-7 3/4.7.12 3/4,7.13 FUEL s70 RACE P00L mo::cei CONCENTRATIOff............... 3 3 /4 7-7 3/4,7.14 rcEL AssEMstr sTonAct................................s 3/4 7-7 J

m rtrenic11 Powen systems 7

f 3/4.8.1 and 3/4.s.2 A.C. socacEs AND cutsITE power DIsTRiseTIca srsTans......................................

3/4 s-1 j

a 4

5 i

i amusentwT me.-Nr-96,133 FAaLET-owIT 1 xry l

l s

!NCO BASES SECMCM pgg 3/4.9 REFUEL.IMG CPERATIONS 3/4.9.1 BC RC N CCNCDTRATI 0M..................'....................8 3/4 9-1 3/4.9.2 I M5TRWOTA TI CN..........................................83/49 3/4.9.3 Q E CA Y TIM............................................... 8 3/4 9-1 3/4.9.4 CC8(TAI)#40ff SUItJING PetETRATION5........................

8 3/4 9-1 3/4.9.5 CCI94 MI CATIosts...........................................

83/49-1 3/4.3.6 MNIIPut.ATOR C2AME........................................

8 3/4 9-1 3/4.9.7 SpefT FUEL STORAGE Su!LODeG - 8AIDGE C2ANE and 599tT FUEL CASK CSNeE..................................

8 3/4 9-3 3/4.9.3 RESIDUAL HEAT RENNAL Afl0 CDOUNT CIRCULATICII............

8 3/4 9-2 3/4.9.9 CONTAIJOErr PUNGE AfG EDWET ISct.ATION SYSTDt...........

8 3/4 9-3 3/4.9.10 and 3/4.9.11 idATER LEVEL - REACTOR VE15EL and if08 AGE PO0L............................................

8 3/4 9-3 3/4. 9.12 and 3/4. 9.13 STOAAGE POOL V0fTILATI0ft 5YSTDt.............. 8 3/4 9-3 3/4.9.14 48NYAHoqENy-PvaGE-OeWis?-Pig.TR...(.k'8h............

8 3/4 9-3 3/4.10 SPECIAL TEST OCEPTICIts

~

j 3/4.10.1 SitJTD0hst MAAGIN.......................................... 3 3/4 10-1 t

j 3/4.10.2 GADUP MEIGNT, DtBERTION AfG POWER DISTRIBUTION LDtITS....

3 3/4 10-1 i

i 3/4.10.3 MtYSICS TE575............................................ S'3/4 10-1 3/4.10.4 REAC7Ct C000ftf 1.00PS....................................

t 3/4 10-1 j

3/4.10.5 POSITI0lt INDICATI0ft SYSTEM - SNitTD0W....................

8 3/4 10-1

~

4 4

\\

PAaLEY-WIT 1 AMeWMetf NO. 25 1

l l

l s

m

_ _ ~. - _ _

TABLE 3.3-6 h

RADIATION MONITORING INSTRilHENTATION 6

MINIMUN k

CHAftlELS APPLICA8LE ALARM / TRIP MEAStlREMENI i

d INSTRttlENT OPERABLE

' MODES

_SETPOINT RANGE ACTION l

s*

r 1.

AREA IGNITORS

~

a.

Fuel Storage Pool 1

(a) i 15 mR/hr 10-1 4

-10 rR/hr 23 Area (R-5)

~

7 b.

Centainment Area (R-27A&B) 2 1.2,3,4 N/A 1 - 10 R/hr 27a 2.

PROCESS MONITORS s.

Fuel Storage Pool Area Gaseous Activity-Ventilation Systen w

-3 6

)

Isolation (R-25A&B)

(b) 1 8.73-x 10~ pCl/cc(c) 10-10 cpm 25

-y,,W /

- - -]

w

.i.

b.

Containment 1.

Gaseous Activity-a) Purat b Ex

- 6 i

~

solat'on

-24

)

1

') 2.3 (d) i 2.27 x 10',

pCl/cc(c) 10-10 cpm 26 4.5.6 (d) i 2.27 x lo, pCl/cc(c) 26 L pfpf y 1.2.3.4.5.6 (e) i 4.54 x 10, pCl/cc(c) 26 i

1.2.3.4.5.6 (f) 1 2.27 x 10 pCl/cc(c)

_26) r 6

b) RCS Leakage.

I 1.2.3 & 4 N/A 10-10 cpm 24 j

Detection (R-12) 11.

Particulate Activity 6

RCS Leakage 1

1.2.3 & 4 N/A 10-10 cpm 24 i

Detection (R-11)

E c.

Control Room 6

< 800 cpm

_10-10 com 21 Isolation (R35A&B)

_l, _ _ _l.2 3 M _

7

~ ;;' ;1 pn""

j

+ay u==.

T L'".. c r "'

ih:555555?id

r e

i 1

d TABLE 3.3-6 (Continued) i ACTICN STATE.wCMIS ACT*:N 23 -

Wf th tne numoer of channels OPERA 3LE less than es;uf red by tne Minirum Channels CPERAELE retuirement, perform ares j

surveys of the monitored area with porta 01e monit: ring instramentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTICN 24 - With the number of channels OPERABLE less than required by the Minimum Channels CPERA8LE requirement, comply with the ACTICN requirements of Specification 3.4.7.1.

1 ACTICM 25 -

' " ". 'i.. _' a;. _', ; A s e 6. J. e. T.'i l - - _.

5 :... u

- ~'- -

vi

-..., :, r r.. ".. ". '.,...'. '.. --.......i..~ ;, ' m

, ~ 's/ Ge./ /-

' ' ' i.."

m.

_; ::.,.m L,

.-.~ -.....

ACTICN 25 -

With the number of channels OPERA 8LE less than required by the Minimus Channels CPERA8LE requirement, comply with tne ACTICN requirements of specification 3.9.9.

ACTICN 27 - With the number'of chalinels CPERABLE less than required t)y the Minimum Channels OPERA 8LE requirement, within i hour inttf ate and maintain operation of the control room 1

emergency ventilation system in the2 recirculation mode of operation.

j ACTION 274 - With the nunter of OPERA 8LE Channels less than required by tne Minimus Channels OPERA 8LE requirement, initiate the

~

preplanned alternate method of monitoring the appropriate U[

parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) Either restore the inoperable Channelks) to OPERA 8LE status within 7 days, or

2) Prepare and submit a Special Report to the Cosmission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the systes to CPERA8LE status.

l a.

wf.tn fuel in storage pool.

1 b.

With f rradiated fue? fn the storage pool.

c.

Above background with no flow.

d.

With mini-purge in operation.

Wf th slow speed nain purge in operatf on.

e.

f.

Wi_th fast speed sain purge in operaticaC feMW FATLEY-UNIT 1 3/4 3-40 __

Amendment No. 47 I..

\\

1

.~...-

Insert 1 for Table 3.3-6 2

(g,1) 5 8.73 x 10-3 pCi/cc(c) 25 Insert 2 for Table 3.3-6 --

Isolation (R-24A&B) 1 1,2,3,4,5,6 (d) s 2.27 x 10 2 pCi/cc(c)10-106 2

cpm 26 2

(d&h) 5 2.27 x 10'3 pCi/cc(c) 26 1

1,2,3,4,5,6 (e) s 4.54 x 10 3 pCi/cc(c) 26 s

2 (e&h)

$ 4.54 x 10' pCi/cc(c) 26 I

1,2,3,4,5,6 (f) s 2.27 x 10'3 pCi/cc(c) 26 2

(f&h) s 2.27 x 10'3 pC1/cc(c) 26 Insert 3 for Table 3.3-6 2

1,2,3,4,5,6 (gsh)s 800 cpm 27 Insert 4 for Table 3.3-6

- With one channel ~ inoperable return both channels to OPERABLE s

ctatus within 7 days or suspend all movement of irradiated fuel

- cnd crane operation with heavy loads over the spent fuel in the pool.

With no channels OPERABLE, suspend all movement of irradiated fuel and crane operation with heavy loads over the

, cpent Iuel in the pool until at least one channel is restored to OPERABLE. status.

- Insert 5 for Table 3.3-6 g.

. During movement of irradiated fuel or movement of heavy-loads over irradiated fuel in the fuel storage pool' area.

h.

During movement of irradiated fuel or movement of heavy loads over irradiated fuel in containment.

,e a

w'a-e 9.weww--

r

=de-

-==s eegr

'w

-as7--r.,

w--

4

i l

PLAN" SYSTD(3 l

l 3/4.Y.7 CON *ROL PCCM EMERGEN"Y VDr"ILATION SYSTD4 CON ROL pocM D<ERcENcY rILTRATION/ PRE 35URIZATICN SYSTD4 (CRETS) l LIMITING CONDI* ION FOR OPERATION 3.7.7.1 Two Control Room Emergency Filtration / Pressurization System (CRETS) trains shall be OPERABLE.

APPLICABILITY:

ALL McDr.5, during movement of irradiated fuel assemblies, and during movement of loads over irradiated fuel.

ACTICN:

MODE 3 1, 2, 3 and 4:

With one CREFS train inoperable, restore the inoperable train to

/

CPEPABLI status within 7X days or be in at least NOT STANDBY within the l

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

MODES 5, 6, during smvement of 1 :adiated fuel assemblies, and during movemen o' loads over 1::adtated fuel:

a.

With one CRIFS train inoperable, restore the inoperable system to' OPERABLE status within 7 days or immediately place the OPERA 5LE CRITS train in the emergency recirculation mode or immediately suspend movement of irradiated fuel assemblies and movement of leads over irradiated fuel.

)

With both CREFS trains inoperable, innediately suspend movement off./

b.

irradiated fuel assemblies and movement of loads over irradiated fuel.

V SURVEILLANCE REQUIREMENTS 4.7.7.1 Each CRITS train shall be demonstrated OPERA 3LE:

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

3 from the control room, flow through the pressurization and recirculation system HEPA filters and charcoal adsorbers and verifying that the pressurization system has operated for at least g

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

I hltcril) 29 t0 I

. s..._.1..........w....

...,.. 1..,..

r..

.......t.,

j af 1..m H an a,,,. 4... s,-n e re ir ; ---- g ;;; 4 ; _,,;,,...

w ; wou m i s wog-

?"'I!"; '?

i;9 ?'"-

Tr

't pr="i-i- ? -f ? Otifia**'i"" 2"'

!!! "" 0 5 "r.-'i- 'le '"rit; -Mir 2^ > y c----.:L:n

hi: ::

c'-

x;;;;i ; ;;,.i;;;

- r n-vl:21:- :f it: "rit i l'-'

rfu '!_;

r-_;c '57-ir;

'P' FARLEY-UNIT 1 3/4 7-16 AMENDMENT N0119 l

PLANT SYSTD'.S SURVEILLANCE REQUIRD4ENTS (Continued) b.

, At least once per 18 months or (1) after any structural maintenance on the HIPA filter or charcoal adsorber housings, or (2) following painting, fire or ene.ical release that could have contaminated the charcoal adsorbers or HEPA filters in any j

ventilation zone communicating with the system by:

)

J 1.

Verifying that the cleanup systes satisfies the in-place testing acceptance criteria of greater than or equal to 1

99.5% filter efficiency while cperating the system at a j

flow rate indicated in Note 1 and using the following test procedures:

1 (a)

A visual inspection of the control room emergency air cleanup system shall be made before each DOP test or activated carbon adsorber section leak test in accordance with ASMI N510-1989*.

(b)

An in-place DOP test for the HEPA filters sgbe i

performed in accordance with 0,Gim. 1".: -,.. N510-l 1+Ifif.#

(c) A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall b performed in accordance with ::; tie. 12 e: g

.. N510-l 5996v 11M Y 2.

Verifying within 31 days after r'emoval that a laboratory

+

j analysis of a representative cg samp ained in f

Ilj gj 7 accordance with 5:: tic 12 cf -. N510-ets the i

17 4 laboratory testing efficiencies criteria given in Note 2 pj//g Aff71 fl8d eben tested with methyl iodide at

'C and 700 relative l

]

humidity.

t 3.

Verifying a system flow rate as indicated in Note 1 during 4

system operation when tested in accordance with ASME M510-f 1989*.

I c.

Af ter 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 representative g s ined in w

-ad-m with 0;nin 12 ;f -,_. N510-ts the-l laboratory testing eZZiciencies criteria given in Note 2 when tested with methyl iodide at

c and 70% relative humidity.

The FNP Final safety Analysis Report identifies the relevant i

aurveillance testing requirements.

FARIJZ-UNIT I 3/4 7-17 N g8GDENT WO,127

. ~_

i PLANT SYSTEMS SURVEILLANCE RIQUIREMENTS (Continued) d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combi ja Mc D:ilters and charcoal adsorber banks is less than.

f

..'. U l

.:n Co w while operating the system at a flow rate indicated in Note 1.-M-

}

2.

Verifying that the filter train starts on a Safety j

Injection Actuation test signal.#

j 3.

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

i 3

i Verifying t g gh g p urization system heater 4.

..... when tested in accordance with J

dissipates ASME N 510-19 8 9 *.-+-

e.

After each complete or partial replaceanent of a HEPA filter bank by verifying that the NEPA filter banks remove greater than or equal to 99.5% of the DOPgn they ested in-pIace in accordance with 5:--1 2 10 :f.__. N510-hile operating l

l the system at a flow rate indicated in Note 1.

l f.

Af ter each complete or partial replacement of a charcoal i

adsorber bank by verifying that the charcoal adsorbers remove l

greater than or equal to 99.5% of a halogenated hydrocarbon accordance with n;;i;a 1".' g teste

- lace in refrigerant test gas when they

. N510-hile operating

(

l the system at a flow rate indicated in Note 1.

Note 1.

a.

Control Room Recirculation Filter Unit 2000 cfm t lot b.

Control Room Filter Unit 1000 cfm t lot g

l c.

Control Room Pressurization Filter Unit 0 0. ' 1 10 ^. =

h"M e

+b% dr4Y Note 2.

a.

Control Room Recirculation Filter Unit 2 -994-If7,/~7, b.

Control Room Filter Unit 2 -994 fa ControlRoomPressurization[fk.$dl/

2 ?"."25 TV/s c.

s surveillance Requirement 4.7.7.1.d.2 does not apply in ps3DE1 1 and 6.

The FWF Final 54"-ry Analysis Report identifies thm salevant

)

surveillanew testJ r. % quirt ~. ries.

t h

w.w h

=r e e e a

a q.R a; i e J 1007 ;e- ' ';;; ;per.ifi ;ie; ; '

';.7.4.. _

';;ed 1; "- ;;.e

" e1 ;' e 1.;;.. J ;.4 fv.11 ;"., G7.

4

' ~

,,.I IOL A6 A 6 OII O.,, ' '.00 NQ h.;.

N E b.

^

e pea'._,'

1 ;. '_',,-

1 ;i..' C.

1;. I l'.ii..

t 1

(

FARLET-UNIT 1 3/4 7-17e.

AMENDMEW NO-Whe, J, d

Ce*fnri A k -< Mec*> cele fin < I"l1f** AIl 23 'E Mf**faf b,

4,f,,j gm p;tfs. ya;F g9l4,y,fa.ye Co<tGvf Me*m frugue:e* fin Alh-M t.2 k. seh pp,e C

%,w

. m

=__.-. _ __.

I

.s t

i i

b j

PLANT SYSTEMS l

3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM J

LIMITING CONDITION FOR OPEPATION 1

l 3.7.8 Two independent penetration room filtration systems shall be J

OPERABLE.

1 APPLICABILITY:

MODES 1, 2, 3 and 4.

i l

ACTION:

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

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 .

4 l

SURVEILIANCE REQUIREMENTS 4.7.8 Each penetration room filtration system shall be demonstrated OPERABLE:

l j

a.

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

initiating, from the control room, the flow through the NEPA filters and charcoal adsorber * -

"4--

'" t the system Indif_ Jf'AnTANN51 has operated for at_. w ;..

. - - -... J.... g I

Tb ; :: Il-Qn~ its pitt /dCA O )""t*"&

b.

At least once per 18 months or (1) after any structural j

maintenance on the NEPA filter or charcoal adsorber housings, i

or (2) following painting, fire or chemical release that could f

have contaminated the charcoal adsorbers or HEPA filters in any ventilation zone communicating with the system by:

i

.1.

Verifying that the cleanup system satisfies the in-place i

testing acceptance criteria of greater than or equal to

'j m 99.5% filter efficiency while operating the system at a goda c/ /td flow rate of "'"" -'

- * ^ percent and using the

-/d following test procedures.

1

\\

+

l (a)

A visual inspection of the penetration room I

i filtration system shall be made before each DOP test or activated carbon adsorber section leak test in accordance with ASME N510-1999*.

(b)

An in-place DOP test for the EEFA fittaza shall be performed in accordance with " c-irr 10 cf ?ff! AS/f/

l 1

N510-1460,#

l164 1

(c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall.

he perfonned in accordance with ":--'-- ",:".?f"!M N510-4444 i

lY' l

The FWP Final safety Analysis Report identifies the relevant surveillance testing requirements.

t FARLEY-UNIT 1 3/4 7-14 AMENEMENT NO. N

',+...i-e

,..,-r+~

,e.

. ~.-

l PIANT SYSTD(3

_SURVEII.IANCE RZ0tfIRDENT5 (Continued) 2.

Verifying within 31 days after, removal that a laboratory i

analys11 of a representative g sampi painedin i

}

accordance with 5::ti:n !? cf.---. N510-ecs the g,,) [cjfgj hr detAdsw/6 y--

Aaboratory testing criterion of greater tnan or equal to gj//r/ffff8J$0),//gf 464 efficiency when tested with methyl iodide at

'C and

)

j relative humidity.

10 3.

erifying a system flow rate of 1000 ri E105 durin[

/

l j

system operation when tested in accordance with ASME O

T M510-1989*.

V.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by.

c.

j verifying within 31 days after removal that a laboratory analysis of e representative g s umpi gainedin 3

h I

accordance with 0;;;i;; !! ef -.. N53 0-meets the j

laboratory testing criterion of greater than'or equal to Pff i

efficiency when tested with methyl iodide at

C and zelative humidity.

ff" i

d.

At least once per 18 months by:

hva g/,.y /fgh fo -/#<$

l 1.

rifying that the pressure drop across the combined MEFA y filters and charcoal adsorber banks of less than Finches Water Gauge while o rating the system at a flow rate of

'0^^

100. 8 2.

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

2.

/;.ifying th:t th: '.:: ::: dir:17:t ?? e ? 5 E : "':-

kf l tsp / p*cd fer" $$ MhdkJ et 4. $MNf0f0 i..n.a....

.m J....... C. ;,. ;;; ;;"a 0 - a ^ ^ ; ^

\\

6.

l l

./ p.

After each complete or partial repladement of a IF.PA filter l

hank by verifying that the RF.PA filter banks resnove greater than or equal to 97.5% of the DOPg they pested in-place l

in accordance with 0;;ti;; 10

f.____ N510-while operating g pg g,4.[fdg [p,/gj the systes at a flow rats of i

y/.

After.each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove l

greater than or equal to 99.5% of a halogenated hydrocarbon refrigerant test gas when they g teste place in

]

accordance with 5;;-i;; 1: ;f.____ N510-while operating the systma at a flaw sata of "j ; 10^.

i The PNP Final Safety Analysis Report identifies the relevant surveillance testing requirements.

i 00

(:]-

.....f.

= xi'1.;3-1

=..._.... 7..p::g:{ : ]fp f { thi g 111;..;;

I e

1 is "

the-- ? 1 tr' 1:tt : it:f "g d :, 1000.

i

'"-*9 L--

a 1 1 - ; -- ;y

_ _a_g and t m _t aea_ 419 k-.

p;.i -- f ;- 1 t;; " -- - ;1eti:: f the " ' t 1 15th ::t !ir; ;n- :-

.)

(/

' " - '_ M ' - -_' :

20 1:00.

~

FARLEY-UNIT 1

~ _

3/4 7-19 AMENDHDIT N0 N oae w fni.< m mau<r a pt.a,,,,.e 6 -e.ar heks ufejwp*

rehns to adjaca a,.eu as, s,ss ua msk & ys.fe af a. //s./ afe of 4 far efn m

i REFUELING OPERATIONS l

3/4.9.12 STORAGE POOL VENTILATION (FUEL STORAGE) i LIMITING CONDITION FOR OPERATION 4-i 3.9.12 One penetration room filtration system (Specification 3.7.8) shall be -

j, OPERA 8LE and aligned to the spent fuel pool room.

(

1 APPLICA81LITY: Whenever irradiated fuel is in the' storage pool.

l

,,ry,,g "CT10n:

With no penetration room filtration system OPERABLE, suspend all l

a.

operations involving movement o fuel within the storage pool until at least one penetration room filtration system is restored to

)

OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

j i

i j -

j SURVEILLANCE REQUIREMENTS s

i, 4.9.12.1 A. penetration room filtration system shall be verified to be aligned j

to the spent, fuel pool room within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to storage of fuel in the spent fuel pool and at least once, per 7 days thereafter while fuel is stored in th# storage pool.

I'15"/ /

1 0.12.2 'h: ;;;;tr:ti:n ::: f'1tr:ti:n :y:t:r :h:!' 5: in:::tr: :d CPE"*"LE

r th

r;;;;ic;;;nt: :f S;;;ffi ;ti:n ?.7,0.

.'f//,f, /A 4.9.12.3 At least once per 1-8 months, verify that the normal spent fuel pool ventilation system will isolate upon receipt of either; a.

The spent fuel pool ventilation low differential pressure test signal, or b.

A spent fuel pool high radiation test signal.

i i

FAALEY-UNIT 1 3/4 9-14 AMENOMENT NO. 26

^

-ii--__-________.____________________,,________________,_

^

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

i i

1 INSERT 1 TO TS SURVEILLANCE PAGE 3/4 9-14 3/4.9.12 Storage Pool Ventilation System -

4.9.12.2 The penetration room filtration system shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by initiating. from -

a.

the control rcom. tiow through the HEPA tilters and charcoal adsorbers and i

verifying that the system has operated for at leas: 15 minutes in its fuel handling accident alignment.

b.

Filter testing per requirements of Specification 4.7.8.b. c, d.l. f and g.

A W

4 1

K e

~

l

),

i i

j -

m

, _____.._._ _._.~_.

. = _ _

FJEFU" ING OP!PATToN5 i

3/4.9.13 STOPACE PCCL VTN-!!.ATION ' f'UT' MOWMEN* t I.IMITING CONDITION FOR OPERATION 3.9.13 Two independent penetration room filtration systems fuel l

(Specification 3.7.8) shall be OPERABI.E

and aligned to the spent pool room:

APPLICABILITY:

During crane operation with loads, over the fuel in the spent fuel pit and duringffu11 movement within the spent fuel pit.

ACTION:

/pyd

's b i

~

a.

With one net:stion room filtration system (noperable return l

both sysj ems to OPERABI.E status withirf 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or suspend all j

movement E!V uel and crane operation wIth idade over the spent f

fuel in the storage pool room.

l b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

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

suspended.

I

[

4.9.13.2 The penetration room filtration a em sha_11 be_ d-natraced f./7,I M O /I*

OPERARI.E *per the requirements of Specificati F

E W

W ggg g

,g g

gg g

g w

yw w

l p^cl ry-t-- r-t!! stir cyet- "ill icel te up-- rece p Of O!?'^r; i

i i

O 2..!

-UO

~

YONI II

_I' Y---

g w

.s..,

i Y

=

ww N =

I_

i

~

4 j

r/

a r

, n r

rabl. tn, u.c.

,h.

r.ai -

Pewided that the swquirements of 23 3.8.1.2 are satisfied.

Q

'l t

+

rami.rr-crI,1 3/4 s-15 anzuznamr No.26,134

3'a.?.la W A:wis? s;;ct II aus? ett Es

' limit!.% COCITION FOR 0; era 7I0fl 3.9.14 The containment purge exnaust filter snall ev OPERAaLE an valve filP13V293 closec.

A88LICA3!LITY: Ouring CORE ALTERATIONS anc Fuel Movement nsice containment witn any c:ntainment purge isolation valve open.

ACT!ON: Witn tne containment purge exhaust filter noperable eitner:

1.

Immectately close the 48 inen contai t purge isolation valves (CSV-HV-3196, 3197, 3198A and 31980) nd the 8 inen containment mini-purge isolation valves (C8V-N 2566C, 28660, 2867C and 28670), or 4

2.

Cease all CORE ALTERAi!ONS and wel movement.

SURVEILLAtiCE REQUIREMENTS 4.9.14 The 40cve required c afnment purge exhaust filter shall be cemenstrated OPERABLE:

At least once per 18 monens or (1) after any structural maintenance on a.

tne HEPA filgar or enarcoal adsorner housings, or (2) following painting, ftte or enemical release snat could have contaminatec tne charcoal adsorcers or HEPA filter in any ventilation zone communicating with t.ne system by:

\\

711/s yec.ARu le(dei, i

l FAALEY-UNIT 1 3/4 9-16 AMEN 0 MENT NO. 28 70 i

)

i RETUELING OPERATIONS SURVEII. LANCE REQUIREMENTS (Continued) 1.

Verifying that the cleanup system satisfies the 1 place testing acceptant

ariteria of greater than or al to 99.5% filter effic4ency while operating the ma a purge system and using the following test procedur (a)

A visual inspection of the contai t purge eahaust filter system shall be ma before each DOP test or activated carbon adsorbe section leak test in accordance with ASME N510-1 9*.

l (b)

An in place DOP test for th REPA filters shall be performed in accordance w h Section 10 of ANSI M510-1980.

(c)

A charcoal adsorber etion leak test with a gaseous halogenated ydrocarbon refrigerant shall be performed in a ordance with Section 12 of ANSI N510-1980.

tfC /M

/f/)p/g Verifying.within 3 days after removal that a laboratory analysis of a rep esentative carbon sample obtained in

/dg'

/

accordance with ection 13 of ANSI N510-1980 meets the g g g /t h d laboratory to ing criterion of greater than or equal to 904 efficien when tested with methyl iodide at 80*C and 704 relati humidity.

b.

After.every 1 months of charcoal adsorber operation by verifying w a 31 days after removal that a laboratory analysis o a representative carbon sample obtained in accordan. with section 13 of ANSI N510-1980 meets the labora ry testing criterion of greater than or equal.co 904 effic ncy when tested with methyl iodide at 80*C and 704 rol ive humidity.

I c.

least once-per 18 months by verifying that the pressure drop

}

across the combined HEFA filters and charcoal adsorber banks is less than 6 inches water Gauge while operating the main purge j

system.

a i

The FNP Final Safety Analysis Report identifies the relevant rveillance testing reauirements.

i ranLEv-UwzT 1 3/4 3-17 AnExonEwr no.127 1

i.

~

-.m.

1 REPJELING CPERAT:CNS SURYEILLMCE REQUIRE.MENTS (Continued)

~

r d.

Af ter each complete or partial replacement of PA filter bank by verifying that the HEPA filter bank etnove greater 1

than or equal to 99.5: of the OOP wnen t are tested in-place in accordance with Section 10 of M51.)t510-1980.

/

e.

Af ter each complete or partical,, replacement cf a enarcoal adsorter bank by verifying

s't tne charcoal Edsorcers remove greater than or equal to 55 of a halogenated hydeccaroon refrigerarit test gas n they are tested in-place in accordance with Se on 12 of MSI N510-1980 while operating the main purge stem.

e 9

J w

a 744 pp ink %/f, !cH blet.

3/+ si+ 9/chl i

4 6

e FARLEY-UNIT 1 3/4 9 13 AE NOMENT NO. 46

9'xr m~ m

!!Asgs t

3f4 7.< _t en - w s-e we s s nee to vesi This specification deleted.

2 2 ~ 4_1

- - - v u x-e un~ e yr ru m The limitations cn the ultimate hea; sink leve' and temperature ensure tha sufficien: cocling capacity is availab;e to et:her li provide normal cooldown of :he facilicy, or 21 to miciga:e che effe::s of acciden:

condi: ions wichin acceptable limi:s.

The limica:icns on minimum water level and maxi: um cemperature are based on providing a 30 day cooling water supply to safe:y related equipmen: wi:hou:

exceeding their design basis temperature. The measuremen: of the ground water seepage a: leas: once per 5 years will provide assurance tha: the 30 day supply of water is available.

1/4 7 7 ccN om accM rweowv vem TrricN m*eM f

The con:rol room emergency filtration /pressuriza: ion system (CREFS) consists of cwo independen:, redundan: crains chac recirculace and filter the control roem air, and two independent, redundan: crains cha: pressurize the con:rol room.

The OPERASILITY of this system in conjunction with control roch design provisic.s is based on limi ing the radia:ica exposure to personnel j

occupying the control room to 5 rem or less whole body, or its equivalent.

This limitation is consisten: with the requirements of General Design Criteria 19 of Appendix

A*,

10CFR50.

1 When one CRETS train is inoperable, action must be taken to restore OPERABLE scatus within 7 days. In this Condition, the remaining OPERABLE

)

CREES train is adequate to perform the control room pro ection function.

However, the overall reliability is reduced because a single failure in the OPERA 3LE CRIiS train could result in loss of CREFS function. The 7 day Comple: ion Time is based on the low probability of a CSA occurring during this period of time ;;;ied, and abili:y of the remaining crain cc provide _ the required capabili:y.

estuvlss N4.< g/

NC"' / C'_'Q' Sul:: L;: [pera: ion o' che ayeLun with the hea:er/

for at leas: 10 gpfjapNS hours over a 3

day period is s' icien: eo reduce the buildup of moiscure on

~

c5s adsorbers and HEPA filter it hrMfr/y~fMrfhA*/ip,

\\

The con:rol room air condicioning sys:em (CMCSI consists of two independent, redundan: trains that provide cooling of recirculated control room air.

Each con:rol room air condicioning (C MC) ::ain is inoperable if i:

is not capable of removing the reqdired hea: load for plant conditions. The ac ual hea; load and the hea removal capability needed to adequacely cool the con ro'. rocm is dependen: upon f ac: ors such as outdoor air ce=perature.

June 119

p ts f,- eve-ews BASE 3 3 '4 7 - 7 crir see occw evenceirev efr. ru reg evg-ew g ee-,..o Wi:h one C.u0 train inoperable, che ineperable train r/Js: be re:urned to C75RA3LE s:4:us wi:hin 30 days. This Allowed cutage Time is based on :he low procability of comple:e loss of con:rol room cooling due to :he redundancy of the support systems, che capability of the OPERA 3LE crain to provide the required ecoling, the poten:ial cha: plan: s:sf f actions can restore or mitigate che effec:s of componen: failures, and the ci.se available to respond as loss of con:rol room cooling does no: have an imedia:e, irreversible impact.

While in MO IS 5 and 6 during movemen: of irradiated fuel assemblies or movement of loads over irradiated fuel, if both trains of CRAC canno: be restored to CPERA3:.I stacus within 30 days, an CPERABLZ CRAC crain mus: be placed in operacion imediately; otherwise, imediately suspend movement of irradiated fuel assemblies and movemen: of loads over irradiated fuel.

The OPERASILI*Y of the con:rol room emergency ven:lla: ion system ensures cha:

1) che ambient air compera:ure does not exceed the allowable temperature for-continuous duty ra:ing for the equipmen: and inscrumentation cooled by this sys:em and 21 che con:rol room will remain habicable for opera: ions personnel during and following all credible accident condicions.

1 1

}/4_7 $

g# 7 me o.g n

n; ***> + r a e e m a*==

a. e e a.se a m

Qf G4 i. 4 e%lT'T"#J* TOM efViw f ? -

P'" *!"#A*fr5N sverwy T'

C?"l'"'i'"*

cf th ; ::* r *ien :::--_ :I filtr*"1?" 27 *^- ^"

"r^'

4h:: : fi;;;;ic; 4;;;i;;; 1 :';ing f;;;.. :h; =000 ;quie.a..; richin :h; e Tg

'"Ile -! ; : 100.' ::: fil :: d ;;i:: :: ::::hin; th: :ncirc r:nt.

The

~""

WSg j e----

s - u i _...;....

.a as-so-. e-s s : -

2--

3 Tlleul Ci::: >: :: -

d ir thd 22 id:n: 2n 1:.

j u:=i

g::=i:n :f :h; :y:= =i:h :.2 hen;.

-- f;. a :.n a t; -. ; - e...

21 day p;;i;d i: -cu f f.ici:n- :: :: duce -he h"'1'"7 a' =^4 - **

_a__

=-'= -

--.2 ___ _.........____,

9 4

e FARLZY. UNIT 1 8 3/4 7-4a AMENCMENT N0419 l S

h

Insert 1 To TS Bases Page B 3/4 7 4a 4

3/4.7.8 Penetration Room Filtration System 1

i

)

The OPERABILITY of the penetration room filtration system provides i

reasonable assurance that radioactive materials leaking from ECCS pump

]

rooms during post LOCA recirculation are filtered prior to reaching the 1

environment. The minimum system flow rate maintains a slightly negative pressure in the penetration room, area and ECCS pump rooms l

assuming only one filter train is operating. The maximum system flow rate ensures that the pressure drop across filters is not excessive and adequate residence time is attained in the charcoal filter. The PRF system is tested periodically in its post LOCA alignment. Periodic l

testing of the RHR heat exchanger room pressure to less than or equal j

to -0.125 inch water gauge with respect to adjacent area pressure (as

]

measured by the AP between the PRF mechanical equipment room and the RHR Heat Exchanger room) at a flow rate cf 5 6000 cfm verifies the integrity of the PRF system pressure boundary and is consistent with 3

the guidance for standard technical specifications in NUREG 1431.

a J

Functional testing of proper PRF system operation and pressure boundary integrity provides reasonable assurance'that unfiltered release to adjacent areas of any ECCS leakage will be minLnized. The operation of this system and the resultant effect from the ECCS leakage on offsite dosage calculations was assumed in the accident analyses. Although not credited in the accident analyses, the PRF system also provides 4

filtration of containment leakage into the penetration rcom areas.

t e

i 1

d e

4

1 1

PU UELING OPEPATIONS i

i BASES l

}

t I

3/4.9.9 CONTAINMEr' PURCE AND EXHAUST ISOLATION SYSTEM The OPERABILITY of - this system ensures that the containment vent and

]

purge penetrations will be automatically isolated upon detection of high i

radiation levels within the containment. The OPERASILITY of this system is required to restrict the release of radioactive material from the j

containment atmosphere to the environment.

u.

i 3 /4.9.10 and 3 /4.9.11 WATER LEVEL - REACTOR VESSEL and STORACE POOL l

The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum j

water depth is consistent with the assumptions of the accident analysis.

l i

f 3/4.9.12 and 3/4.9.13 STORACE POOL VENTILA':' ION SYSTEM m

sh. 4! it:ti;..; = th; =:::;: ;::1 :::licti:: -ict r :::=: th:d g7

=11 : iirecti:: :::::L:L ::L=::2 ::: = L:: iL tzi : ; =:

'Li ulLL h:

b iLLt;;;i th::;;h th; _ ^. ! Lit;;; ;-i :' :==L ;':::h;; i:L;; t; iL;;h; p f/f.9.1$ h t; th C :;h;;;. Th; 07 :"."!!.:T Of thi: ;y;tz :: th: :;;;lti-; iciin: g,/3 l

--"rl r-"rity " e erreirtert eith "

20:~.tir-c' " Crri'r t

-ly:::.

t i

j The note regarding FRF electrical system OPERABILITY is provided for l

clarification to specification 3/4.9.13.

In MODES 5 and 6, the electrical power requirements do not require considering a single failure coincident with a loss of all offsite or all oneite power. The design basis for l

electrical sources during refuellag requires at least one of f site-circuit i

through the 1E distribution system be operable and at least one of the i

emergency diesels be operable. The electrical requirements of 3.8.1.2 meet the electrical sources OPERASILITY requirements for-two independent FRF i

systems.

l 3/4.9.14 CONTAINMENT PURCE trMAUST FILTER T'? :,:r"'ility Of t'-

T t"#_----.!

- ;; cr' ^ ^

rt 'iltOr Orrr ::

"t

-t

fuei '--211-22:sf:n in tt: ;; n z i - -- - -.: th: ;;;i:;n;::

8_ -

k-

-e 4

-^TT

Z l- :-f cr

l' ;;f T ' ' rt:f ;;ir t:.:- - "-

- ' ~ -

-',_.y

% reipan hidd.

,y..

AMENDMENT NO.M, @

FMtLET-UNIT 1.

3 3/4 9 3

.r.

INSERT 3 TO TS BASES PAGE B 3/4 9 3 3/4.9.12 and 3/4.9.13 Storage Pool Ventilation System The OPERABILITY of the penetration room filtration system ensures that radioactive materials leaking frcm the spent fuel pool area following a rHA)re filtered pner to reaching the environment. The PRF system is tested periodically its FHA alignment to ensure the system functions property. Testing of HEPA filter perf rmance, charcoal adsorter efficiency, and the physical properties of the activat charcoalis bounded by testidj performed per 4.7.8. The OPERABILITY of this sy em and the resulting iodine removal capacity are censistent with the assumptions of t e accident analyses.

i L/

1 f

4 Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation 3

Technical Specification Changes i

J Unit 2 Revised Marked Up Technical Specification Pares a

1 a

4 4

I i

1 I

a 4

-m---

m

e INDEX i

LIMITING CCHOITICNS FOR OPERATION AND SURVEILLANCE REQUIREMEN l

SECTION PAGE 3/4.9 REFUELING OPERATIONS i

3/4.9.1 BO RO N CO NCENT RAT I O N...............................

3/4 9-1 3/4.9.2 INST m En4 TION..........................................

3/4 9-2 3/4.9.3 DECAY TIME...............................................

3/4 9-3 j

3/4.9.4 CONTAINMEVT BUILDING PENETRATIONS........................

3/4 9-4 i

3/4.9.5 C0MJN ICATIONS...........................................

3/4 9-5 i

3/4.9.6 NAM I PU LATO R C RANE........................................

3/4 9-6 i

}

3/4.9.7 CRANE TRAVEL - SPENT. FUEL STORAGE POOL BUILDING i

j Bridge Crane.................................

3/4 9-7 Spent Fue l Cas k Crane...................................

3/4 9-8 i

3/4.9.8 RESIDUAL HEAT RDCVAL AAS COOLANT CIRCULATION 1

-)

All Water Levels.

i 3/4 9-9 i

Low Wa te r Leve l..........................................

3/4 9-10 I

3/4.9.9 CONTAIl0ENT PURGE Ale EXHAUST ISCLATION SYSTEM........... 3/4 9-11 1

i j

3/4.9.10 WATER LEVEL - REACTOR VESSEL Fuel Assemblies...............................

3/4 9-12 Control Rods...........................................

3/4 9-12a 3/4. 9.11 WATER LEVEL - STORAGE P00L...............................

3/4 9-13 4

{

3/4.9.12 STORAGE POOL VENTILATION (FUEL STORAGE)..................3/4 9-14 3/4.9.13 STORAGE POOL vExTitATION (Putt N0vseMT).................3/4 9-15 3/4. 9.14. -ananNEnT-PasE-eemsm.e.@rMd...............

3/4 9-Is 1

3/4.10 SPECIAL TEST EXCEPTIONS 4

i i

j 3/4.10.1 $NUTDOW NAAG IN...........,..............................

3/4 10-1 3/4.10.2' GA6UP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMIT 3....

3/4.10-2 3/4.10.3 PHYSICSTEST5............................................

3/4 10-3 3/4.10.4 REACTOR COOLANT-L00PS....................................

3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0W................... '

3/4 10-5

]

FARLEY-UNIT 2 X

I Pf'J EX BASES src*foN EAgI 3 / 4. '1 PLAtt* SYs rMs 3/4.7.1 TURBINE CYCLE............................................ B 3/4 7-1 3/4.7.2 STEAM CINERATOR PRESSURE / TEMPERATURE LIMITATION.......... B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................... B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM..................................... B 3/4 7-3 4h.

............................ B 3/4 7-3 3/4.7.5

- R549R-WA99R-sysTEMr.

3/4.7.6 ULTIMATE HEAT SINK....................................... B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................ B 3/4 7-4 Pr W TFAmod 3/4.7.8 See6-PwHe Room 5ENheet-htR FILTRATION SYSTEM............. E 3/4 7-4 3/4.7.9 SNUB 3ERS................................................

5 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION.............................. S 3/4 7-6 3/4.7.11 (Deleted)....................... R 3/4 7-6 ~

k, 3/4.7.12 (Dn1sted)......................

B 3/4 7-7 j

l 3/4.7.13 AREA TEMPERATURE M0KITORING..............'................ B 3/4 7-7 3

3/4,7.14 FUEL STORAGE POOL SORON CONCENTRATION....................B 3/4-7-7 3/4.7.15 FUEL ASSEMBLY STORAGE....................................B 3/4 7-7 g

3/4.8 ftFCTRICAL POWER SYSTEMS i

4 3/4.8.1 and 3/4.8.2 A.C.

SOURCES AND ONSITE POWER i

i UTSTRIBUTIOK STETEMS.................................... 3 3 /4 8-1 3/4.8.3 EI2CTRICKr. EQEIFEENT PROTECTION DEVICES................. 3 3 /4 '8-1 I

E e

t 1

FARLEY-UNIT 2-EzV AMENDNENT N0.007125 6

iMii

...N I

u:

I/1. 3 IEET..*NG *ITS AI$.*M_5 f

J/S...f..

3 P,.N b.NL O.N,I -

...N.......

8..

3 J/

3*.

3/4.9.2

N 5 73 LN D 7A 7 : 0 N..........................................

3 3/4 9.*

)

3/4.9.3

ECAY T: .9E..........................................

13/49*.

3/4.9.4 CONTAINMDT IUI'.D ING 7 9ETRAT!CNS........................

3 3/4 9 *.

3/4.9.5 C.W NICA7! NS...........................................

3 3/1 9 *.

3/4.9.5 MAN i ? U V TC R CRAN E........................................

3 3/4 9 *.

4 3/4.917 5707 PJEL ITCRAGE SUIL3!NG - 3RI GE CXANE and

$ 7 9T, FJ E L CA 5 X C3AN E..................................

3 3/4 9-2 3/4.9.8 RESIGUAL MEAT REMOVAL ANO CCOUNT CIRCUUTICN............

3 3/4 9-1 3/4.9.9 CONTA:NNOT PURGE ANO EXHAUST I30uTION SYSTZM...........

3 3/1 9-3 3/4.9.10 and 3/4.9.'1 VATU LIVEL - ADCTCR VE53EL and STO RAG E FC C L............................................

3 3/4 i-3 3/4. 9.12 and 3/4. 9. '.3 STORAGE ? COL VD* uTION SYSTEM..............

! 3/J.9-3 l

3/4.9.14.GCN*rA IM*e7 MRGE-DMLUGT4*+TE.. CAe/f N 3 3/4 9-3 3/4.10 57EC*AL 757 EXCEPTIONS 3/4.10.1 SHUTCCW MAAG IN.'......................................... S 3/4 1C-1 3/4.10.2 GRCUP HUGHT, INSUTION ANO 7CWG OISTXI3UTICN L*MIT3.... 3 3/4 10-1 i

3/4.10.3 PHYSICS TE575............................................

! 3/4 10 *.

j 3/4.10.4 R UCTOR CCC UNT LCCPS....................................

3 3/4 *.C j

3/4.10.5 705!T*:N INDICATION S'(STIM - SHU*:CWN....................

3 3/4 '. *.

t FARLiY-UNIT 2

Cl

TABLE 3.3-6 k

RADIATION #GNITORING INSTRtstENTATION 5

g MINIMLSI CHANNELS APPLICARLE ALARM / TRIP MEAStiREMENT INSTRLSENT OPERA 8tE

__ MODES

_SE1PolNT RANGE ACTION 1.

AREA #GNITORS t

Fuel Storage Peel 1

(a) i 15 mR/hr 10-1-104 mR/hr 23 Area (R-5) b.

Containment Area (R-27AAS) 2 1.2.3.4 N/A 1 - 10 R/hr 27a 7

2.

PRDCESS MINITDR$

a.

Fuel Storage Peel Area Gaseous Activity-Venttiation Systee w1 Isolatten (R-25A&R)

I b)

$ 8.73_x 10'3 pCf/cc(c) 10-10 cpe_

25 6

$oet I m

g b.

Contairment

^

1.

Gaseous Activity-a) Pu Ee-16

- -~

^6_

se atten (R-24A&R) 1 1,2.3 (d) i 2.27 x 10 pCi/cc(c) 10-10 cpe 26 4,5.6 (d) 1 2.27 x 10, pct /cc(c) 26 7guf 2 1.2.3.4.5.6 (e)

$ 4.54 x 10, pCl/cc(c) 26 g

1.2.3.4.5.6 (f) 1 2.27 x 10 pct /cc(c) 26 I

b) RCS Leakage 1

1.2.3 & 4 N/A 10-10 cpe 24 0

Detection (R-12) a**

11.

Particulate Activity RCS Leakage 1

1.2.3 & 4 N/A 10-10 cp, 74 6

Detection (R-11)

-a c.

Contral Roon Isolation (R35A&R) 1_

6 1.LL4_ -

< 800 cpe 10-10 cpe 27 j'YY'.t_

[

psd 3

___-t e u.a,.w iFeadiated N -I

l i

TABLE 3.3-6 (C:att uec) i.

i ACTICN STATE'OTi ACTICN 23 -

Witn ene nummer of channels UERA8LE 1ess tnan re;utred by ene Minimum Channels CPERA8CE re uirement per* arm area surveys of the manf tored arts.ita porticle ' monitor'ing instmmentation at least once ;er 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4CTICM 25 -

With the nummer of channels CERA8LE 1ess than re;utred by tMe Minimum Channets SPERABLE requirement, comply with the ACTICN requirements of Specification 3.4.7.1.

CTION 25 - w '- ' ' - - ' - - - - - ' - ' - - ' *

' ' ' ' - ' * = - - - ~ * - - ^ "

w i-d 5 E-E-'i F U 5 5 : # = rt. :- ;'y b :s n J* [ f i A'T * *".,. !, ;. -a d ",;;;i'i mi = 2.11C =4 2.2. ' L ACTION 25 -

Witn the nummer of channels CPERA8LE less than required by i

tne Minfmum Channels OPERA 8LE re;uf rament, comply wien the ACTICN requirements of Specification 3.9.9.

ACTICN 27 -

With the numeer of channels CP!2A8LE less than required by tne Minimum Channels CPERA8LE requirement, within L heur initiate and maintain operation of tae control room emergency ventilation systen in thesecf reulation made of operation.

{c,,eys,.sy]

ACTION 274 - Wit 3 the num0er of OPERA 8tE Cnannels less taan required by the Minfan Channels OPERA 8LE requirement, initiate the preplanned alternate method of sanitoring the appropriate I

3 parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1

1) Ettaer restore the inoperable Channels (s) to OPERA 8LE status within 7 days, or

2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, the cause of the inoperabfif ty and the plans and schedule for restoring the systes to CPERA8LE status, i

a.

n tn ruel in storage pool.

b.

With irradiated fuel in the storage pool.

+

c.

Above background with no flow.

d.

With mint-purge in operation.

1 With slow speed main pdrge in operation.

e.

j gf f.

Vith fast speed maingurga in operation.

~ _

FARLEY-UNIT 2

~

3 [4 3-20 Amendment No. 38 j

e vv

Insert I for Table 3.3-6 2

(g,1)

{ B.73 x 10-3 pC1/cc (c) 25 Insert 2 for Table 3.3-6 Isolation (R-24A&B) 1 1,2,3,4,5,6 (d) s 2.27 x 10-2 pCi/cc(c)10-106 cpm 26 2

(d&h)

$ 2.27 x 10-2 pCi/cc(c) 26 1

1,2,3,4,5,6 (e) s 4.54 x 10-3 pCi/cc(c) 26 2

(e&h) 5 4.54 x 10-3 pCi/cc(c) 26 1

1,2,3,4,5,6 (f) 5 2.27 x 10-3 pCi/cc(c) 26 2

(f&h) 5 2.27 x 10-3 pCi/cc (c) 26 Insert 3 for Table 3,3-6 2

1,2,3,4,5,6(g&h)s 800 cpm 27 lasert 4 for Table 3.3-6 With one channel inc,wrable return both channels to OPERABLE status within 7 days or suspend all movement of irradiated fuel cnd crane operation with heavy loads over the spent fuel in the pool. With no channels OPERA 51LE, suspend all movement of irradiated fuel and crane operation with heavy loads over the spent fuel in the pool until'at least one channel is~ restored to

~ OPERABLE status.

Insert 5 for Tahle 3.3-6 q.

During mcvement'of irradiated fuel or movement of heavy loads over Irradiated fuel in the fuel storage pool area.

h.

During movement of irradiated fuel or movement of heavy.

loads over irradiatad fuel in containment.

-...., - _ ~

. _ ~. -. -

i j

J 7*M SYr?!xs 3/4.?

00N""70L 7 CH IME20tNCY '/TN*:".A;;;N SYSTN i

i C: r"70L PCCM EXERSINCY C'.TPAT N/ PPISSUR: AT N SYSTIM t0RIrs t l

1 e

LIMIT:NO CONDITION TOR CPERATION i

3.7.7.1 Two cont :1 Room E::e:gency Tilt:acion/Pressur:.:ati:n System (CRITS) #

trains shall be CPERA8LE.

I i

h l

AJ P LICA3ILI*Y:

ALL MCDES, during movement of 12:adiated fuel assenclies, i

and during movement of loads over i :adiated fuel, j

l ACTION:

McCE3 1, 2, 3 and 4:

With one CRIT 3 c:ain inoperable, restore the inoperable train to f

l CPEPABLE status within 7T days or be in at Inast NOT STAND 8Y within the j

next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in CCLD SEUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

(

J'

/

0 MCDES 3, 6, during movement of irradiated fuel assemblies, and curing movemen"I j

of leads over irradiated fuel:

)

4 a.

With one CREF3 train inoperatie, restore cas inoperable system to f i

CPEFABLE status within 7 days or immediately piece the CPERABLE j

CREF3 train in the emergency recirculation made er immediateif q

suspend movement of irradiated fuel assemblies and movement of loads over irradiated fuel.

b.

With both CRETS t alas inoperable, immediately suspend movement eI j

irradiated fuel assemblies and movement of loads over irradiated fuel.

l l

SURVEILIANCE REQUIREMENTS 1

i 4.7.7.1 Each CREF3 train shall be demonstrated CPERABLE:

l 1

At least once per 31 days on a sM e m TEST SASIS by initiating,*

a.

from the centrol team, flow through the pressurization and

{

recirculation system MEPA filters and charcoal adsorbers and l-verifying that the pressurisaties systen has operated for at least l

10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heater e dud== the mast 31 days, b

NIN j.

A e-t t

iotr to 30 ys or ach r r

e on fil rati a f c'

s' an a

ti o

tz r

j co ing des Th p a

f

_4_4 3.

.4 are et agli le r g 30-y e i s a ion og ses en j

pose tio, o f e

1 4th of i

e g (3 r

).

l O

j I

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

a t

1 l

1 i

-l PIANT SYSTEMS j

SURVEILLANCE REQUIREMENTS (Continued) l b.

At least once per 18 months or (1) after any structural i

maintenance on the HEFA filter or charcoal adsorber housings, 4

or (2) following paincing, fire or chemical release that could have contaminated the charcoal adsorbers or HEPA filters in any ventilation zone caemunicating with the system by:

1.

Verifying that the cleanup system satisfies the in-place 1

{

testing acceptance criteria of greater than or equal to j

99.54 filter efficiency while operating the system at a

{

flow rate indicated in Note 1 and using the following test i

procedures:

j (a) A visual inspection of the control room emergency air j

cleanup system shall be made before each Dor test or activated carbon adsorber section leak test in accordance with ASME N510-1989*.

i l

(b) An in-place DOF test for the NEPA filters s g be performed in accordance with !: d :: 1" ;f -.. N510-l p

j (c)

A charcoal adsorber section leak test with a gaseous j

halogenated hydrocarbon refrigerant shall b g i

performed in accordance with ":::ir: 12 f --. N510-l l

TA 2.

Verifying within 31 days after removal that a laboratory j

analysis of a representative g saspi ained in j

[jg g M once \\

accordance with ": =i : 12 ef -.. N510-ets the l

dd laboratory testing efficiencies enteria given in Note 2 pj/k AIM g,f9ff f

j

, when tested with methyl iodide at

C and 704 relative l

f humidity.

8 3.

Verifyisg a system flow rate as indicated in Note 1 during i

syster. operation when tested in accordante with ASME N510-I j

19899

)

i c.

Af%r every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by g

verifying within 31 days after removal that a laboratory analysis of a representative ego,a samph med in accordance with ":=i;;.1 ef -_. N510-1 ets the l

laboratory teating efficiencies criteria given in Note 2 when l

4 tested with methyl iodide at

C and 704 relative humidity.

I j

The FNF Final Safety Analysia Report WaH *"= the relevant j

surveillance testing requirements.

i j

AMENDMENT No.1(/.

21 rARLEY-uMIT 2 3/4 7-17 i

~

(

6

~~

\\

4 1

i FIANT SYSTD43 SURVEILIANCE REQUIRIMENTS (Continued) i d.

At least once per is months by:

}.g., fg 1

o'd Ytfo $

1 1.

Verifying that the pressure drop across the combined gry j~

filters and charcoal adsorber banks is less than !.;..... d. l T;;;; 02;p while operating the system at a flow rate

]

indicated in Note 1.-M-l l

2.

Verifying that the filter train starts on a Safety Injection Actuation test signal.8 l

3.

Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8 inch 3

water gauge relative to the outside atmosphere during systemoperationf.-

5 CS 4.

Verifying that thegpressurization system heater I

dissipates 7." ;.." k when tested in accordance with l

{

Ash'E M510-1919*.-+ -

l

)

e.

After each complete or partial replacament of a REPA filter.

bank by verifying that the HEFA filter banks remove greater l

than or equal to 99.5% of the DOF they g gested in-place in accordance with _;;ier.10 ;; g". N510-MM while operating l

i the system at a flow rate indicated in Note 1.

I i

f.

After each complete or partial replacement of a charcoal l

adsorber bank by verifying that the charcoal adsorbers remove i

j greater than or equal to 99.5% of a halogenated hydrocarbon refrigerant test gas when they g teste glace in

" :f.__r. N510-while operating l

j accordance with f::rir:

the system at a flow rate indicated in Note 1.

Note 1.

a.

Control Room Recirculation Filter Unit 2000 cfm t 104 b.

Control Room Filter Unit 1000 cfm t lot I

c.

Control Room Pressurization Filter Unit 0^

' ; 10" j

(30d__Mf20$h-/#h I

Note 2.

a.

Control Room Recirculation Filter Unit 2-4M 9'/,fF '

b.

Control Room Filter Unit 1

Uff>

Control Room Pressurization [4/#,dr M [ 1 00. :. ff/$

l c.

i l

8 surveillance Requirement 4.7.7.1.d.2 doea not apply in seDE.5 5 and 6.

Y j

The FNF Final Safety Analysis Repart identifies the selevant surveillance j

testing requirements.

l l

00 cill...i;; -': C -- p.;;; ;; d;;p fe - :;_. 111- ::

l i

n:1:- - : i= = :: : :::: ::_-:;;l ;&_.i:: ;:.

- :;; 1..

ud i;. I__^' c T_.1;;;' ; le;.e. d_;e4 4 1*. ::, 1007.

{

_f __.-_i t_____

13,____

i

, _; 7_ _ yn ug, aq ::.g;; g l

s;.:_

;; 1;L. ^ '

, L -i = ;i _' - "- i __ 1 ll : f : ^ ' ' ;

^ ^ ^2

' * *:d f;. -'

p" ; ef 1^;^.

AMDIDMENT No 121 FARLEY-UNIT 2 3/4 7-17e- - -

r

pga,

a. c;,,4,*/ /m Mid/w Rife 0*if 2.3 4. *f"/9e-L b, ce,{,,) % Fa b Vao4 f.4 E". Wde A

c. caduel hm feraoriafiss Rfvdeif 2.214. *f* fof'~

t.

/* m v

L LANT SYSTEMS 3/4.7.8 PENETPATICN ROOM TILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.8 Two independent penetration room filtration systenu shall be OPERABLE.

APPLIC'.;LITY:

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 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 4.7.8 Each penetration room filtration system shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST RASIS by a.

initiating, from the control room, the flow through the HEPA filters and charcoal adsorbers and verifying that the system has operated for at least 40 t ::: rith thr ? 11:n- -- duria; 21 icy:.kS'nbre,fe,$ br Ib ffsf JJM dyd-r th: p::t b.

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

1.

' Verifying that the cleanup system satisfies the in-place testing acceptance criteria of greater than or equal to 99.5% filter efficiency while operating the system at a

j. pg 4 g fyp h Id flow rate of 5000*$f; i 10 percent-and using the l

f j

p tedf following. test procedures:

(a)

A visual inspection of the penetration room filtration system shall be made before each DOP test or activated carbon adsorber section leak test in accordance with ASME N510-1989*.

1 (b)

An in-place DoP test for the HEFA filters shall be performed in accordance with f: =i:n 10 f 72:0I A/N8 l

N510-t9eeY

/TIF (c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be performed in accordance with 2 : tic; 10 :f ?"!!-

l N510- N.

M 1919 '

The FNP rinal Safety Analysis Report identifies the relevant surveillane testing requirements.

FARLEY-UW T 2 3/4 7-18 AMENDMENT No.121

i I

FIANT SYSTEM.3 SURVEILIANCE RIQUIREMENTS (Continued) 2.

Verifying within 31 days after removal that a laboratory 1

m analysis of a representative g p sampi ined in M } g Q M gtr#rd W 6')

i accordance with 5 : 1:2 !? cf __._. N510-meets the tv/dt AM gggg laboratory testing criterion of greater than or equal to efficiency when tested with methyl iodide at

C and relative humidity.

J#

i 4

T 1

Verifying a system flow rate of 5000

g. 10" during I I

l 3.

system operation when tested in accordance with ASME

[

]

N510-1989*.

I /

L c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsarber operation by

{

verifying within 31 days after removal that a laboratory analysis of a representative eg g samp painedin aci.;ordance with 0;;;i;. 1 ;f.... N510-ets the laboratory tee 1.79 4:11::12 of greater than or equal to

<fficiency when tested with methyl iodide at C and relative humidity.

38 9

d.

At least once per 18 months by:

2b

]

1.

Verifying that the pressure drop across the combine HEPA I

filters and -" ~1 adsorber banks of less than inches 4

Nater Gauge while operating the system at a flow rate of l

7000 ;

100 7 l

l 2.

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

O.

".'e;if i.y th; e,. E:::::: d::i; :: 25 i 2.5 Er er f

i Af ltMf Oru yk* j$ arpuffrf Pt A SYN'WVO YI'IYNS b U26*ihly

sced i.. e e;,.;t..;; i;h M*: ::'.10-1^0^^.

6:

f l

ff.

After each complete or partial replacement of a MEFA filter bank by verifying that the azFA filter banks remove greater j

1 than or equal to 99.5% of the DOF g they gestad.in-place in accordance with !:--ir: 10 cf.... N510-while operating

.fg -ld$

the system at a flow rate of 00^ g f i 100.

/

j 9

After each complete or partial replacement of a charcoal 4

adsorber bank by verifying that the charcoal adsorbers remove j

greater than or equal to 99.5% of a halogenated hydrocarbon refrigerant test gas whan they g teste pacein accordance with 5:=in 1:

f.._.

N510 wb.1,le operating the system at a flow rate of 4C""

1 100.

/

1 The FNF Final safety Analysis Report identifies the relevent l

l j

surveillance testing requirements.

i a si a

=w e a yv OA

~~ ~ ~ ~

[

27((

f_[

l 6

pir-- et in : fr: !??"' t

'ri r! :;::ifientier :"_' t-d ;; ;

'tt;d i

" *^^"-

"---l ^- ': 1; ::; i;;d 4.11 ^ ^., 1;;^.

1 L -?.-7.ieel i- - ;; -^.;.. _ill __ - ^ _ -' ; p ::."l

"$ 10 - 10* " - ' ' ' i; p;;f; --- -_ f = 1-:::

, l e t i ef -2 : " ' t ? "-2

f-- ' ' ; _ _ x ;;

-b ^ M 2 f :

' - -- ' ; A-I?!!.

FARI.ET-UltTT 2 3/4 7-19 AMDIDMENT No. 121

-- /

$n& fRf [Ygitt Cet ettittlekt A pressure, f -C.WircNa Avefn jeft-rriefire fs asfjacer/ orces ddg(4s.f4e /Mt' 4M *b *N

'W P

af e 4foa tofe. of 4 see c

I REFUELING OPERATIONS 3/4.9.12 STORAGE POOL VENTILATION (FUEL STORAGE)

LIMITING CONDITION FOR OPERATION 3.9.12 One penetration room filtration system (Specification 3.7.8) shall be OPERA 8LE and aligned to the spent fuel pool room.

APPLICA8ILITY: Whenever. irradiated fuel is in the storage pool.

gg/

ACTION:

a.

With no penetration room filtrati system OPERA 8LE, suspend all operations involving movement of uel within the storage pool until at least one penetration room filtration system is restored to 1

OPERA 8LE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12.1 A penetration room filtration system shall be verified to be aligned to the spent fuel pool room within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to storage of fuel in the spent fuel pool and at least once per 7 days thereafter while fuel is stored i

in the storage pool.

t i

'. ?. !?. 2 'h: p:::tr:ti:r r::: ltr:ti:n ;y: :: :h:11 t; d:::n;tr:t;d Of:F.f"'

306*// l l

p-- *at t;M ::: t: :f Sp::i'i::ti:n 0.7.0.

y%ggggj

.\\

4.9.12.3 At least once per 18 months, verify that the normal spent fuel pool i

ventilation sy' stem will isolate upon receipt of either; l

a.

The spent fuel pool ventilation low differential pressure test-signal, or

~

b.

A spent fuel pool high radiation test signal.

l i

1 FARLEY-UNIT 2 3/4=9-14 l

INSERT 1 TO TS SilRVEILLANCE PAGE 3/4 9-14 3/4.9.12 Storage Pool Ventilation System 4.9.12.2 The penetration room tiltration system shall be demonstrated OPERABLE:

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

the control room. tiow through the HEPA filters and charcoal adsorbers and verifying that the system has operated for at least 15 minutes in its fuel handling accident alignment.

b.

Filter testing per requirements of Specification 4.7.8.6, c, d.1, f and g.

~

o m-

'l l

prFUELING OPEPATIONS 3/4.9.13 STOPAGE POOL ' VTN"'ILATION (FUEL MOVEMENTL

]

LIMITING CONDITION TOR OPERATION 3.9.13 Two independent penetration room filtration systeus (Specification 3.7.8) shall be OPERABLE

and aligned to the spent fuel l

pool room:

APPLICABTLTTY:

During crane operation with loads, over the fuel in the and duringf uel movement within the spent fuel pit.

f spent fuel pit ACTION:

[/r4 /dd a.

With one netration room filtration system inoperable return both systems to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or suspend all movement of fuel and crarie operation with loads over the spent fuel in the storage pool room.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

d l

SURVEILLANCE REQUIREMENTS i

4.9.13.1 Two penetration room filtration systems shall be verified to be aligned to the spent fuel pool room within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to fuel handling 8

or crane operations in the storage pool room and at,least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter until fuel movement operations in the storage pool room are i

f suspended.

f n

i 4.9.13.2 The penetration room filtration system shall be_demone*Jated OPERABLE per the requirements of Specification #

I,f./[,2 dadM f /2. 3]

4.0.12.2

.; 1;;;; ;;;; p;; 1" ;..;h;.;;1:j ;h;.; th; ;;. ;21 ;F;;; f;;l j

p ;l ;y;;;;..;..;il;;i;; ;y;;;; will i;;let; -F;000!U Of O!"^0 ^

e

'"he r;rri f" ' r ' :::til: tic: 1 = differrst'-'- - prrrrurr trrt c ign:1-r-ee -

5.

' :;:: ft:1 ;::1 hi;h radicti:: trrt -

a-

The normal or emergency power source may be inoperabia in MODE 5 or,,6 provided that the requirements of TS 3.8.1'2 are satisfied.

b FARLEY-UNIT 2 3/4 9-15 AMENDMENT No.126 j

>,e

EE JE' **iG 0: Eta 7MN!

i 3 / a. 9.14 C3N7a*NMENT 309GI In. UST TILIIA t

LIMITING CONDITION FOR 07ERATIcn i

i 3.9.14 The containment ; urge exnaust filter sna11 ee 07EAA3LE j

N2.813V293 closec.

. valve i

4

{

APPLICA3fL!?Y: Curing CCRE ALTERATIONS and Fuel Movecen i

witn any c:n ainment purge isolation valve open.

nside containment j

ACTION: Witn ene containment purge exaaust filt noperaele either:

1.

Imectately close tne 48 inen contat nt purge isolation valves (C8V-HV-3196, 3197. 2198A and 31980 and tne 8 inen containment mini-purge isolation valves (CAV

-2866C, 28660, 2867C and 23670), er 2.

Cease all CORE At.TERATIONS and uel movement.

1 SURVEILLANCE REqu!REMENTS i

i i

4.9.14 The above required c demonstrated OPERABLE:

tainment purge exhaust filter shall be At least once,per 18 montas or (1) a'fter any structural maintenance en a.

the MEPA filjde or enarcoal adsorner housings, or (2) following painting, fire or enemical release snat could have contaminated tne 1

enarcoal.adscreers or HEPA filter in any ventilation zone communicating j

with t s'systete ey:

I i

\\

This & a b u dafeh l.

i i

~

i i

i 4

4 FARtEY-UNIT 2 3/4 9-16 AMEN 0 MENT NO. I3-

g e 4

REFUELING OPERATIONS SURVEILLANCE REQUIRDENTS (Continued) 1.

Verifying that the cleanup system satisfies he in-place testing acceptance criteria of greater tha or equal to 9b.5% filter efficiency while operating e main purge system and using the following test pro dures:

tal A visual inspection of the con inment purge exhaust filter system shall b made before each DOP test or activated carbon ads rber section leak test J

in accordance with ASME N5

-1989*.

l (b)

An in-place DOP test for e HEPA filters shall be performed in accordane with Section 10 of ANSI H510-1980.

g/I / fI j fjggggg[/y (c)

A charcoal adsorbe section leak test with a 7

14

/

gaseous halogenat hydrocarbon refrigerant shall 4

[ggf h/hyk be performed in ccordance with Section 12 of ANSI N510-1980.

h.b/f 2.

Verifying within 3 days after removal that a laboratory analysis of a re esentative carbon sample obtained in accordance with ection 13 of ANSI N510-1980 meets the laboratory tes ing criterion of greater than or equal to 90% efficien when tested with methyl iodide at 80*C and 70% relativ humidity.

b.

After every 12 onths of charcoal adsorber operation by verifying wit in 31 days after removal that a laboratory analysis of representative carbon sample obtained in accordance ich Section 13 of ANSI N510-1980 meets the laborator testing criterion of greater than or equal to 904 ef ficie y when tested with methyl iodide at 80*C and 70%

relati humidity.

c.

At ast once per 18 months by verifying that the pressure drop ac ss the combined HEPA filters and charcoal adsorber banks is 1 ss than 6 inches Water Gauge while operating the main purge ystem.

~

Th FNP rinal Safety Analysis Report identifies the relevant surv 111ance testing requirements.

FARLEY-UNIT 2 3/4 S-17 AMENEMENT No.121 G

W

RE. JEL*NG CPERu iCNS SURYEILLMCE REQUIRD4ENTS (Continued) d.

Af*Jr eacn c:molete or partial replacement op HEPA f{lger bank by verifying taat ene HE?A filter cann remove greater enan or equal to 99.5% of tne 00P wnen eney are tested in-place in ace:rdance with Section 10 of Axs1 N510-1980.

After each complete or particaFr/'lacement of a charcoal e.

ep adsorcer bank by verifying,thit the enarcoal adsorcers remove greater taan or equal t:L99.55 of a haloganated hydrocaroon refrigerant test gas wHen they are testad in-place in accordance with Section 12 of AMSI N510-1980 while operating the main purge stem.

O e

1/+. 9.it oddd x

O e

e e

FARLEY-UNIT 2 3/4 9-13 NEMDMENT NO.37

I t.-

- ct-iv s**ws SASES 3/4 1.4_t r?*?w>-r wet-s ?'tv #s visi This specification dele:ed.

3/4 7 4?

rp_* ? w a-e w e_t-e mir iomtm The limita: Acts on the ul:imate hea: sink level and ce:pera ure e.sure

t.... : sufficien: ecol:,ng capaci:y is available to et:her 1) provide nor=41 cooldown of cne f acils:y. or 21 to matagate the effec:s of accident conditions wi:hin acceptable limits.

The limita:icns on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety rela:ed equipmen: wi:hou:

exceeding their design basis temperature. The measurement of the ground water seepage at least once per 5 years will provide assurance that the 30 day supply of wa:er is available.

3/a 71 cairaga acew rwrocrNey vnt*?fl-?cer sYsem f

The control room emergency filtration /pressurisation system (CREFS) consists of two independen:, redundan: trains that recirculate and filter the control rocm air, and two independen:. redundant trains that pressurize the control room. The CPERABffITY of this system in conjunc:Lon with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.

This limi:ation is consistent with the requirements of General Design Criteria 19 of Appendix ' A*,

10CFR50.

When one CREFS train is inor erable, action must be taken to restore j

OPERABI.E status within 7 days. In this Condicion, the remaining OPERABLE I

CREFS train is adequate to perform the control room protection function.

However, the overall reliability is reduced because a single failure in the 1

OPERABLE CREFS train could result in loss of CREFS function. The 7 day Completion Time is based on the low probability of a DBA occurring during this period of time ;;ri:4, and abili:y of the remaining train to provide che required capability.

lrtyiff GWfitt

{

Serie:Seg

'ruirrive.[perationofthe cyf t" with the heaterf-ed. for a: leas: 10 gggf/,yddf

. ours over a 31 day period is 88!-4=--

a

-ed"-m de buildup of moisture on the adsorbers and KEPk f11:er Qor) $d Veri [f ff_lont $Nh!lr*f h

-___ _ m _f The control room air conditioning system (CAACSI consists of two Andependent, redundant trains ena: provide cooling of rectr:ula:ed con:rol

)

room air.

E4ch con:rol room air condi:ioning (CRAC) train is inoperable if i:

is not capable of removing the required hea; load for plant conditions. The actual heat load and the hest removal capabili:y needed to adequately cool the control room is dependent upon f actors such as outdoor air temperature.

t FART.IY UN

2 8 3/4 7 4 AMENCMENT No.111

D'_1N" TYT*fue BASES l

2/4 9.4 CC?t*9 C L PCCM TU Y1C T'V*v 1/r f**A**?nt eve *TU

??**i='*=4' W1:h one CRAC crain ino'perable, che taogaradia :rsi. must be re:grned :o CPERABLE s:a:us wich:n JC days. This Allowed 5:4 e *: e as based en ene low

~

prooability of ecmple:e loss of control room c:ol:...; d.e :o cne redunda..:y of the supper: systems, che capamility of the OPE.uaLI crain co prov:de ene required cooling. the potencial cha: planc scaf f at: ions can restore or m;::ga:e che effec:s cf r:mponen: f ailures. and ens ::ne available to respond as loss of control room cooling does not have an immed: ace, irreversible impace.

While in MODES 5 and 6 during movement of irradiated fuel assemblies or movement of loads over irradiated fuel, if both crains of CRAC esanot be restored to OPERASLE status within 30 days, an CPE.2.tBLI CRAC crain must be placed in operation innediacely: otherwise, irrenediately suspend movement of irradiated fuel assemblies and movemen: of loads over irradiated fuel.

The OPERABILITY of the control room emergency ven:lla:Lon system ensures cha:

li che ambiene air comperacure does not exceed the allowable comperature for continuous duty aacing for the equipment and inscr.; men:a: ion cooled by this system and 2) che control room will remain habicab'e for operacions personnel during and following all creditie accident condicions.

3/4.7.9

, F _n-F m _ rs:a::r er: T.T

T n: T r Z-; 4 8'VP*RA*MN RocW M4 mm-wnm-m The OC.A"!LIU.I :h; ;;n;;se;ien.66 als fil i;G ci-l th:: ::di :::i : = :ri:!: 1:. ding f: n th: 5000 :;-i; : : rithi: 05: ; ---

^'- fellerin; : L T ::: f'.1 :::d ;;i;; :: ;;;hin; :h: :-". _ :::

h:

'; rt !:- -f -hi: cy: - :nf th: :::ul:::: :ff::: :- eff:it: d:::;:

M

.;;i;;; u;; ;;;c: d in :h: :::id:n: :n:;y:::.

y g

J.;., w.- ie.. af ;h; ;j;;;. ui ', :h; '.:::::: :n ft: : 1 ::" 1" - i

' cur: cr:: : :' 4 y ;;;;ied i: : ffici;n: :;.;n:: :n: cu:.du; cf rei ::re :

d t': ad:::t:r: tro "EP' filt::

)

t FARLEY-UNIT 2 53/4744 AMENDMDC NO. I11 l

Insert 1 To TS Bases Page B 3/4 7 4a 3/4.7.8 Penetration Room Filtration System The OPERABILITY of the penetration room filtration system provides reasonable assurance that radioactive materials leaking from ECCS pump rooms during post LOCA recirculation are filtered prior to reaching the environment. The minimum system flow rate maintains a slightly negative pressure in the penetration room area and ECCS pump rooms assuming only one filter train is operating. The maximum system flow rate ensures that the pressure drop across filters is not excessive and adequate residence time is attained in the charcoal filter. The PRF system is tested periodically in its post LOCA alignment. Periodic testing of the RHR heat exchanger room pressure to less than or equal to 0.125 inch water gauge with respect to adjacent area pressure-(as measured by the AP between the PRF mechanical equipment room and the RHR Heat Exchanger room) at a flow rate of 5 6000 cfm verifies the integrity of the PRF system pressure boundary and is consistent with the guidance for standard technical specifications in NUREG 1431.

Functional testing of proper PRF system operation and pressure boundary integrity provides reasonable assurance that unfiltered release to adjacent areas of any ECCS leakage will be minimized. The operation of this system and the resultant effect from the ECCS leakage on offsite dosage calculations was assumed in the accident analyses. Although not credited in the accident analyses, the PRF system also provides filtration of containment leakage into the penetration room areas.

i A

...... _..~._ _._.

.. ~ _. _ _ _ _ _.. _. ~ _ _ _.. _... _..

I f

- REFUELINC OPERATIONS i

}

~

BASES d

3/4.9.9 CONTAINMENT PURCE AND EXKAUST ISOLATION SYSTEM 4

i j

The OPERABILITY of this system ensures that the containment vent and j

purge penetrations will be_ automatically isolated upon detection of high i

radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the l

containment atmosphere to the environment.

1 i

i 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORACE POOL' s

The restrictions on minimum water level ensure that sufficient water l

i depth is available to remove 99% of the assumed 10% iodine gap activity

(

releasJd from the rupture of an irradiated fuel assembly. The minimum i

water depth is consistent with the assumptions of the accident analysis.

i l

3/4.9.12 and 3/4.9.13 STORACE POOL VENTILATION SYSTEM h

I

hr l'-'* tizz 22 t'- rt : ;r ;:21 :::til:tir cy: Cr ::::: :h:t

\\b *Yb

\\

Li ::il :::L:: :::: L 1 ::121:22 *:

1--T*

' ' 21

~2-

"is "Lii b j

(yjgqf

},

fLL:;;;i zh:::;b h: :::'. f LL:::: 22 zh;.:::L 22^::2;; i;L;; :; iL;;;;.5;

:h; ;

h

: :. T: er--- :L:T: ;f :ht: ;s:::= ;;i :h; ;;;1::=; ; :;

$[hf' i

.;l ;;;;;ity ::: ;;;;ict::: eith th; ::r-~ ;;izz Of :h: ;;;ii;;;

1 :::.

i 7

\\

I i

j.

The note regarding PRF elee rical system OPERABILITY is provided for l

clarification to specification 3,. 9.13.

In MODES 5 and 6, the electrical l

power requirements do not require considering a single failure coincident i

with a loss of all offsite or all onsite power. The design basis for j

electrical sources during refueling requires at least one offsite circuit through the 12 distribution system be operable and at least one of the j

j emergency diesels be operable. The electrical requirements of 3.8.1.2 seen the electrical sources OPERABILITY requirements for two independent PRF 3

j systems.

i 1

}-

3/4.9.14 CowTArwxEwr PuRCE ExnauST ritTER

---w------g

_____,____.,._____m.....- - - - - - - - _-_- __

.-_-__m,,,...

_,.m_

y-

_ _ f t _ _ t.,

,._.,1 m..ast__

__t2__..t 3,___..t---_

.m j

__,____2

___2

__2

_2___m_2

.w.

____m,__

.m_

L; --- -

}

Als peel $'reNos h{ ele [.

j i

J AMENDMENT NO.126 FARLEY-UNIT.2 3 3/4 9-3 N

i i

4 e

INSERT 3 TO TS BASES PAGE B 3/4 9 3 3/4.9.12 and 3/4.9.13 Storage Pool Ventilation System The OPEPABILITY of the penetration room filtration system ensures that radioactive matenals leaking from the spent fuel pool area following FHA)re filtered pner to reaching the environment. The PRF system is tested periodically ~ its FHA alignment to ensure the system functions propedy. Testing of HEPA fitter perfc ance. charcoal adsorter efficiency, and the physical properties of the activated Marcoalis bounded by test /9 performed per 4.7.8. The OPERABILITY of this syste l and the resulting iodine removal capacity are consistent with the assumptions of the a ' dent analyses.

-h gggJ #s J

9 e

f

I Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes Units 1&2 Tvoed and Marked-Up improved Technical Specification Pares 1

l I

I i

h t

Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes t

Units 1 & 2 Tvoed Improved Technical Specification Pages i

l i

j 5

l 4

9 t

i 4

4 i

i j

1 L..-.-.

PRF

~

3.7.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

Two PRF trains D.1 Suspend movement of immediately inoperable during irradiated fuel movement of irradiated assemblies in the spent fuel assemblies in the fuel pool room.

spent fuel pool room.

SURVEILLANCE REQUIREMENTS SURVElLLANCE FREQUENCY SR 3.7.12.1 NOTE Only required to be performed during movement of irradiated fuel assemblies in the spent fuel pool room.

Verify two PRF trains aligned to the spent fuel pool 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months room.

SR 3.7.12.2 Operate each PRF train for 215 minutes in the 31 days applicable mode of operation (post LOCA and/or refueling accident).

SR 3.7.12.3 Perform required PRF filter testing in accordance la accordance with the Ventilation Filter Testing Program (VFTP).

with the VFTP SR 3.7.12.4 Verify each PRF train actuates and the normal spent 18 months fuel pool room ventilation system isolates on an actual or simulated actuation signal.

SR 3.7.12.5 Verify one PRF train can maintain a pressure 18 months on a s -0.125 inches water gauge with respect to adjacent STAGGERED arens during the post LOCA mode of operation at a TEST BASIS flow rate s S000 cfm, Farley Units 1 and 2 3.7.12-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Progrrms cnd Minuals 5.5 5.5 Programs and Manuals 5.5.10 Secondary Water Chemistry Prooram This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation. The program shallinclude:

a.

Identification of a sampling schedule for the critical variables and control points for these variables; b.

Identification of the procedures used to measure the values of the critical variables; c.

Identification of process sampling points, which shallinclude monitoring the condenser hotweils for evidence of condenser in leakage; d.

Procedures for the recording and management of data; e.

Procedures defining corrective actions for all off control point chemistry conditions; and f.

A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

5.5.11 Ventilation Filter Testino Procram NFTP)

A program shall be established to implement the following required testing of '

Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in, and in accordance with, ASME N510-1989. The FNP Final Safety Analysis Report identifies the relevant surveillance testing requirements.

a.

Demonstrate for each of the ESF systems that an inplace test of the high l

efficiency particulate air (HEPA) filters shows a penetration and system l

bypass < 0.5% when tested in accordance with ASME N510-1989 at the system flowrate specified below.

j ESF Ventilation System Flowrate (CFM)

CREFS Recirculation 2,000 i 10 %

CREFS Filtration 1,000 i 10 %

CREFS Pressuritation 300 +25% to -10%

PRF Post LOCA Mode 5,000 +20% to -10%

(continued)

L Fadey Units 1 and 2 5.5-19

- Amendment No. (Unit 1)

Amendment No. (Unit 2).

l>

o

. Programs cnd Minu-Is 5.5 e

5.5 Programs and Manuals 5.5.11 y_entilation Filter Testino Prooram (VFTP) (continued) 4 b.

Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 0.5% when tested in accordance ASME N510-1989 at the system flowrate specified below.

ESF Ventitetion System Flowrate (CFM)

CREFS Recirculation 2,000 t 10%

CREFS Filtration 1,000 10%

CREFS Pressurization 300 +25% to -10%

PRF Post LOCA Mode 5,000 +20% to -10%

c.

Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in ASME N510-1989, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of s 30 C and greater than or equal to the relative humidity specified below.

ESF Ventilation System Penetration RH CREFS Recirculation 2.5%

70%

CREFS Filtration 2.5%

70 %

CREFS Pressurization 0.5%

70 %

PRF Post LOCA Mode 10%

95%

1 NOTE: CREFS Pressurization methyliodide penetration limit is based on a 8-inch bed depth, d.

Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters and the charcoal adsorbers is less than the i

value specified below when tested in accordance with ASME N510-1989 at the system flowrate specified below.

l Delta P Flowrate ESF Ventilation System (in. water oauce)

(CFM)

CREFS Recirculation 2.3 2,000 10 %

i CREFS Filtration 2.9 1,000 10%

CREFS Pressurization 2.2 300 +25% to -10%

PRF Post LOCA Mode 2.6 5,000 +20% to -10%

. Farley Units 1 and 2 5.5-20 Amendment No. (Unit 1)

Amendment No. (Unit 2)

'I l

Programs and Minu11s 5.5 5.5 Programs and Manuals 5.5.11 Ventilation FilterTestino Prooram (VFTP) (continued) l e.

Demonstrate hat the heaters for the CREFS Pressurization System dissipate the value specified below when tested in accordance with.

ASME N51f-1989.

ESF Ventilation System Wattaoe (kW)

CREFS Pressurization 2.5 i 0.5 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.12 Explosive Gas and Storaoe Tank Radioactivity Monitorino Prooram This program provides controls for potentially explosive gas mixtures contained in the Waste Gas System, the quantity of rafoactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid j

storage tanks.

The program shallinclude:

a.

The limits for concentrations of hydrogen and oxygen in the Waste Gas System and a surveillance program to ensure the limits are maintained.

Such limits shall be appropriate to the system's design; b.

A surveillance program to ensure that the quantity of radioactivity 1

contained in each gas storage tank is less than the amount that would j

result in a whole body exposure of 2 0.5 rem to any individualin an unrestricted area, in the event of an uncontrolled release of the tanks' contents; and c.

A surveillance program to ensure that the quantity of radioactivity contcined in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste */reatment System is less than 10 curies.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

Farley Units 1 and 2 5.5-21 Amendment No. (Unit 1)-

Amendment No. (Unit 2)

PRF B 3.7.12 BASES SURVEILLANCE SR 3.7.12.2 REQUIREMENTS (continued)

Standby systems should be checked periodically to ensure that they function properly. As the environmental and normal operating conditions on this system are not severe, testing each train once every month provides an adequate check on this system. This Surveillance requires that the operation of the PRF System be verified in the applicable alignment (post LOCA and/or refueling accident). The surveillance is applied separately to each operating mode of the PRF System as required by plant conditions. In MODE 1-4, operational testing in the post LOCA alignment is required to verify the capability of the system to perform in this capacity.

Operational testing of the PRF System in the refueling accident alignment is only required to be performed to support the movement of irradiated fuel in the spent fuel pool storage room (when the potential exists for a fuel handling accident).

Systems that do not credit the operation of heaters need only be operated for 215 minutes to demonstrate the function of the system.

The system is initiated from the control room with flow through the HEPA and charcoal filters. The 31 day Frequency is based on the i

known reliability of the equipment and the two train redundancy available.

SR 3.7.12.3 This SR verifies that the required PRF System testing is performed in accordance with the Ventilation FilterTesting Program (VFTP). The PRF System filter tests are in accordance with ASME N510-1989 4

(Ref. 6). The VFTP includes testing HEPA filter performance, charcoal adsorber efficiency, system flow rate, and the physical properties of the activated charcoal (general use and following specific operations). Specific test frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.12.4 This SR verifies that each PRF train starts and operates on an actual or simulated Phase B actuation signal. In addition, the normal spent fuel pool ventilation system must be verified to isolate on an actual or simulated spent fuel pool ventilation low differential pressure signal and on an actual or simulated spent fuel pool high radiation signal.

The 18 month Frequency is consistent with Reference 7.

(continued)

Farley. Units 1 and 2 8 3.7.12-5 Revision 0

.. - - -. -. ~. -

PRF B 3.7.12 l

BASES l

j SURVElLLANCE SR 3.7.12.5

. REQUIREMENTS (continued)

This SR verifies the integrity of the ECCS pump rooms and penetration area boundary. The ability of the boundary to maintain -

4 negative pressure with respect to potentially uncontaminated adjacent areas is periodically tested to verify proper function of the l

PRF System. During the post-LOCA mode of operation, the PRF System is designed to maintain a slight negative pressure in the ECCS pump rooms and penetration area boundary, to prevent unfiltered LEAKAGE. The PRF System is designed to maintain s -0.125 inches water gauge with respect to adjacent area pressure (as measured by the Ap between the PRF mechanical equipment room and the RHR Heat Exchanger room) at a flow rate of 5 6,000 cfm.

An 18 month Frequency (on a STAGGERED TEST BASIS) is consistent with Reference 7, 9

REFERENCES

1. FSAR, Section 6.2.3.

2. FSAR, Section 9.4.2.

3. FSAR, Sections 15.4.1 and 15.4.5.

4. Regulatory Guide 1.25.

5. 10 CFR 100.

6. ASME N510-1989.

I

7. Regulatory Guide 1.52 (Rev. 2).

i i

i

- Fadey Units 1 and 2 B 3.7.12-6 Revision 0

1 Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes 4

Units 1 & 2 Marked Up Imoroved Technical Specification Pares i

i i

i n

4 n

a i

i t

i 4

l 4

4

,,e

PRF 3.7.12 ACTIONS CONDITION REOUIRED ACTION COMPLETION TIME D.

Two PRF trains inoperable D.1 Suspend movement of immediately during movement of irradiated fuel irradiated fuel assemblies assemblies in th?. scent l

in the spent fuel pool iuel pool room.

l room.

Sl;RVEILLANCE REQUIREMENTS I

SURVE LLANCE FREOUENCY l

SR 3.7.12.1 NOTE Only required to be performed during movement of irradiated fuel assemblies in the spent fuel pool room.

Verify two PRF trains aligned to the spent fuel pool 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months room.

SR 3.7.12.2 Operate each PRF train for 2 15 minutes ln the 31 days applicable mode of operation (post LOCA and/or refueling accident).

SR 3.7.12.3 Perform required PRF filter testing in accordance in accordance with with the Ventilation Filter Testing Program (VFTP).

the VFTP SR 3.7.12.4 Verify eaci PRF train actuates and the normal spent 18 months i

fuel pool room ventilation system isolates on an actual or simulated actuation signal.

i l

SR 3.7.12.5 Verify one PRF train can maintain a pressure

% months on a s -0.125 inches water gauge with respect to STAGGERED eh_'scuf deeds seewe during the post LOCA mode of TEST BASIS operation at a flow rate s460&cfm.

1 I

Farley Units 1 and 2 3.7.12-2 Amendment No. (Unit 1)

Amendmeai No. (Unit 2)

..- ~

l Programs arid Manuals 5.5 5.5 Programs and Manua^ls 5.5.10 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to -

i inhibit SG tube degradation. The program shallinclude; j

'1 a.

Identifica n of a sampling schedule for the critical variables and control ~

points for these variables-i b.

Identification of the procedures used to measure the values of the critical i

variables; c.

Identification of process sampling points, which shallinclude monitoring the condenser hotwells for evidence of condenser in leakage; d.

Procedures for the recording and management of data, j

i e.

Procedures defining corrective actions for all off control point chemistry conditions; and f.

A procedure identifying the authority. responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

j 5.5.11 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engincered Gafety Feature (ESF) filter ventilation systems at the frequencies specified in, and in accordance with, ASME N510-1989. The FNP Final S:My Analysis Report identifies the relevant surveillance testing requirements.

a.

Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 0.5% when tested in accordance with ASME N510-1989 at the system flowrate specified below

40%.

ESF Ventilation System Flowrate (CFM)

CREFS Recirculation 2,000 i /dfa CREFS Filtration 1,000

//P,'

CREFS Pressurization 300 ###7a /s-/#f, 1

- PRF Post LOCA Mode 5,000

/, (y -uf,

- i

)

(continued)

Farley Units _1 and 2.

5.5-19

. Amendment No._ (Unit 1) _

Amendment No. ; (Unit 2)

.1

.m-w-

w

-+y

+

o

1 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued) b.

Demonstrate for each of the ESF systems that an inplace test of tne charcoal adsorber shows a penetration and system bypass < 0.5% when -

tested in accordance ASME N510-1989 at the system flowrate specified below440Hr-ESF Ventilation System Flowrate (CFM)

CREFS Recirculat%n 2,000 /.! /#f, CREFS Filtration 1,000 4fis 5_

CREFS Pressurization 300 #p/7, /s -/vf, PRF Post LOCA Mode 5,000 //er,4-/#r, c.

Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in ASME N510-1989, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3303-1989 at.a temperature of 5 30*C and greater than or equal to the relative humidity specified below.

ESF Ventilation System Penetration M

j CREFS Recirculation 2.5%

70 %

CREFS Filtration 2.5%

70 %

CREFS Pressurization 0.5%

70 %

PRF Post LOCA Mode 10%

95 %

NOTE: CREFS Pressurization methyliodide penetration limit is based on I.

a 6-inch bed depth.

d.

Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters and the charcoal adsortnrs is less than the value specified below when tested in accordance with ASME N510-1989 at l

the system flowrate specified below *40%.

ESF Ventilation System Delta P (in. water guage) Flowrate (CFM 1,00043 //fa CREFS Recirculation 2.3 2,000 f /dfs 1

CREFS Filtration 2.9 CREFS Pressurization 2.2 300$#tr$ h d#fe 5,000{e hd#f' PRF Post LOCA Mode 2.6 (continued)

Farley Units 1 and 2 S.5-20 Amendment No. (Unit 1) j Amendment No. (Unit 2) j

+,,

~

J

' Programs and Manu21s 5.5 4

5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued) e.

Demonstrate that the heaters for the CREFS Preasurization System dissipate the value specified below4-4G% when tested in accordance with ASME N510-1989.

j j

ESF Ventilation System -

Wattage (kW)

]

CREFS Pressurization i

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to trie VFTP test -

frequencies.

i j

5.5.12 Explosive Gas and Storage Tank Radicactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained j

in the Waste Gas System, the quantity of radioactivity contained in gas storage j

tanks, and the quantity of radioactivity contained in unprotected outdoor liquid, storage tanks.

j The program shallinclude:

a.

The limits for concentrations of hydrogen and oxygen in the Waste Gas System and a surveillance program to ensure the limits are maintained.

Such limits chall be appropriate to the system's design; b.

A surveillance program to ensure that the quantity of radioactivity containod in each gas storage tank is less than the amount that would result in a whole body exposure of 2 0.5 rem to any individualin an l

unrestricted area, in ten event of an uncontrolled release of the tanks'

]

contents; and i

c.

A surveillance program to ensure that the quantity of radioactivity i

contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is less than 10 curies.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

L-1

- Farley Units 1 and 2 5.5-21 Amendment No. (Unit 1)

Amendment No. (Unit 2)

PRF-B 3.7.12 BASES 4

SURVE!LLANCE SR 3.7.12.2 REQUIREMENTS i

4 (continued)

Standby systems should be checked periodically to ensure that they function properly. As the environmental and normal operating conditions on this system are not severe, testing each train once every month provides an adequate check on this system. This Surveillance requires that the operation of the PRF System be verified l

in the applicable alignment (post LOCA and/or refueling accident).

j The surveillance is applied separately to each operating mode of the 1

PRF System as required by plant conditions. In MODE 1-4, operational testing in the post LOCA alignment is required to verify the capability of the system to perform in this capacity. Operational testing of the PRF System in the refueling accident alignment is only j

aquired to be performed to support the movement of irradiated fuel in the spent fuel pool storage room (when the potential exists for a fuel a

handling accident).

Systems that do not credit the operation of heaters need only be operated for 2 15 minutes to demonstrate the function rd the system.-

l The system is initiated from the ' control room with flow through the HEPA and charcoal filters. The 31 day Frequency is based on the known reliability of the equipment and the two train redundancy available.

4 SR 3.7.12.3 i

l This SR verifies that the required PRF System testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The i

PRF System filter tests are in accordance with ASME N510-1989 (Ref. 6). The VFTP includes testing HEPA fi!!er performance, charcoal adsorber efficiency, einumm. system flow rate, and the l

physical properties of the activated charcoal (general use and following specific operations). Specific test frequencies and additional l

Information are discussed in detailin the VFTP.

l SR 3.7.12.4 This SR verifies that each PRF train starts and operates on an actual 1

or simulated Phase B actuation signal, in addition, the normal spent fuel pool ventilation system must be verified to isolate on an actual or simulated spent fuel pool ventilation low differential pressure signal -

and on an actual or simulated spent fuel pool high radiation signal.

The 18 month Frequency is consistent with Reference 7.

c (continued) l Farley Units 1 and 2 8 3.7.12-5 Revision 0

i y

l PRF B 3.7.12 i

e BASES SURVEILLANCE SR 3.7.12.5 REQUIREMENTS l

(continued)

This SR verifies the integrity of the ECCS pump rooms and penetration area boundary. The ability of the boundary to maintain negative pressure with respect to potentially uncontaminated adjacent areas is periodically tested to verify proper function of the PRF System. During the post-LOCA mode of operation, the PRF System is designed to maintain a slight negative pressure in the ECCS pump rooms and penetration area boundary, to prevent unfiltered 4/8#p, 5,

LEAKAGE. The PRF System is designed to maintain 4-s -0.125 ingh,es water gauge with respect to St 0!Pe. ! pressure (as measured N, the PRF mechanical equipment roorn) at a flow rate of

'g

A P beh,wrx hire-]

@ A* @M$4' G

An month Frequency (on a STAGGERED TEST BASIS)is consistent with Reference 7.

REFERENCES

1. FSAR, Section 6.2.3.

2. FSAR, Section 9.4.2.

3. FSAR, Sections 15.4.1 and 15.4.5.

4. Regulatory Guide 1.25.

5. 10 CFR 100.

6. ASME N510-1989.

7. Regulatory Guide 1.52 (Rev. 2).

Fariey Units 1 and 2 B 3.7.12-6 Revision 0

~

4 4

1 1

Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems 4

and Radiation Monitoring Instr imentation Technical Specification Changes I

Additional Information Reauested From Conference Calls d

a t

4 O

4 i

1 k

-e.,

1 I

Answers to Request for AdditionalInformation Durine Conference Calls 1.

Provide a description of the volume of the containment used for mixing in the revised calculations to justify the deletion of the containment purge fdtration system.

During refueling, the containment may be purged using the main purge at high speed which has a flow rate of approximately 48,500 cfm plus 10%, drawing air from the 130'and 155' elevations of the contamment. The pool sweep system has been disconnected from the contamment purge exhaust system, so the activity released from the pool will be mixed with the containment atmosphere and then exhausted. Assuming mixing up to the elevation of the contamment cooling fan header (but no nuxmg outside this envelope which might be induced by operation of the fans), and 90% free space, this j

represents a volume of approximately:

x x 65 x 55 x 0.9 = 6.6 x 10' ft'.

2 This volume is shown in Table 2 of our submittal of June 30,1997 and represents approximately 33%

of the containment free volume. It conservatively ignores the area from elevation 105 to 130 directly served by the containment fun coolers and all elevations above the purge duct header elevation 185 including the dome. With credit for isolation of the contamment within 45 seconds, only a small portion of this volume is exhausted.

During fuel movement in the Auxiliary Building, on detection of high radioactivity, the PRF exhausts the area above the spent fuel pool. Two trains of flow (total flow of 8,000 cfm) exhaust the volume from the operating floor at elevation 155 to the ceiling at elevation 182 over the spent fuel pool, transfer canal, and cask washdown and storage pits. This volume is approximately-27 ft x 38 ft x 102 ft = 1 x 10' ft' This volume is shown in Table 2 of our submittal of June 30,1997. It does not include the volumes of the pump, demineralizer and heat exchanger rooms nor that of the new fuel storage areas which are separated by walls from the spent fuel pool area. With 8,000 cfm flow, the PRF system is assumed to exhaust this volume once every 12.5 minutes, with credit for isolation of the normal HVAC system as described in the FSAR.

2.

Provide the time responses of the radiation detection monitors which isolate the contamment in the event of a fuel handling accident.

The original fuel handling accident analysis inside containment (calculation 8.11) included a main purge isolation time of 11.5 seconds. This isolation time was constructed from 4 parameters (1. Time to reach detector,2. Air transport detector tubing,3. Detector response time, and 4. Valve closing time) discussed below.

2

Time to reach detector The time to reach the detector, RE-24A or B, was deternuned to be 4.3 seconds for the slowest time to result in the maximum release of air. His time is reasonable since the duct lengths evaluated in reference 1 are similar to the present layout and tl e flow rate used to determine time is conservatively low.

Air Transoort Time throveh Detector Tubing Reference 1 used an input of 1.4 seconds for the air transport time in the detector tubing. Review of the present layout shows the longest travel time from the process duct to the detector as 0.65 seconds, which shows the original input as conservative.

Detector Resnonse Time A monitor response time of 0.8 seconds is reasonable when assuming a relatively high dose type release indicative of a fuel handling accident.

Valve Closing Time Based on reference 2, the main purge isolation valves have an isolation time of 5 seconds, which is consistent with the original input in reference 1.

Conclusion Summing the four inputs listed above for the isolation time results in approximately 11.5 seconds, which is significantly less than the 45 second assumption modeled in the accident analysis used to support the proposed Technical Specification amendment.

References Calculation 8.11, Revision 2, Fuel Handling Accident Inside Containment.

SS-1102-50, Revision 15, Containment Purge System Butterfly Isolation Valves.

3. Clarify how the 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months run is performed to assure that the charcoal is dried during the test.

The heater control circuits are controlled by a humidistat which controls to a set humidity. There is a cutout switch to cut this humidistat out of the circuit when rurming the test. This cutout is used to place a constant demand on the heaters to stay on during the 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months run. The heaters are protected with thermal cutouts which interrupt power to the heaters at 160' F. Le thermal cutouts keep the charcoal from getting too hot and creating an ignition hazard.

3

4.

Provide justifistion that the PRF equipment room is representative of the boundary He PRF surveillance will require a minimum negative differential of 0.125" w.g. across the boundary with respect to adjacent areas and not to atmosphere. The low pressure tap for the differential measurement is located in the RHR HX room which is considered the highest pressure area within the PRF boundary. The PRF system discharges back to this room when the recirculation valve is open.

He high pressure tap is located in the PRF mechanical equipment room. He PRF mechanical equipment room is not contiguous with the PRF boundary and will represent adjacent areas pressure associated with the auxiliary building radw2ste ventilation system

5. Provide justification for the 0.5% bypass leakage being used in the TS instead of the 0.05% bypass leakage.

The TS bypass leakage value of 0.5% is explicitly modeled in the PRF and CREFS filter efficiencies assumed in the dose analyses. Results with this 0.5% bypass value are provided in the revised safety s

assessment, attachment El.

6.

Provide description of the dirty filter testing performed to establish the numbers in the TS submittal.

The Technical Specification dirty filter values were derived from data collected during field testing. On the PRF units, tne CREFS Pressurization Units, and the CREFS Recirculation Units, the HEPA filters were in stages and the systems placed in service. The filter differential pressures (DPs) and filter flows were recorded. By collecting several points and attempting to get the flow decreased as close as possible to the lower Technical Specification flow limit, we were able to obtain a best fit curve. This established the maxunum DPs across the HEPA and charcoal filters at wiiich the Technical Specification flow limits could be maintained. Rese DPs were placed in the TS amendment. He CREFS Filtration Units could not be opened; therefore, an opposing blade volume damperjust upstream of the filter housing was used to simulate the loading of the filters and the test data collected was used to derive the dirty filter number.

1 i

s

_

ML20207C245

Text

Li ::il :::L:: :::: L 1 ::121:22 *:

Navigation menu

Search