Text

Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec
	ML20148Q104
Person / Time
Site:	Farley
Issue date:	06/30/1997
From:	; SOUTHERN NUCLEAR OPERATING CO.
To:	;
Shared Package
ML20148Q102	List: ML20148Q098; ML20148Q104;
References
	NUDOCS 9707030298
	Download: ML20148Q104 (87)
	v • d • e

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l 4-Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes 1

Unit 1 Technical Specification Pages j

i i

i 9707030298 970630 PDR ADOCK 05000348 P

PDR

b d

Ik FNP Unit i Technical Specifications Control Room, Penetration Room, and Co::cainment Purge Filtration Systems and Radiation Monitoring Instrumentation Chanced Pages 4

X Replace XIV Replace XV Replace 3/4 3-39 Replace 3/4 3-40 Replace 3/4 716 Replace 3/4 7-17 Replace 3/4 717a Replace 3/4 718 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 1

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i INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

SECTION PAGE'

]

3/4.9 REFUELING CPERATIONS 3/4.9.1 BO RON CONC ENT RATI ON.................................. 3 / 4 9-1 4

3/4.9.2 INSTRUMENTATION......................................

3/4 9-2 i

3/4.9.3 DECAY TIME............................................ 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.................... 3/4 9-4 3/4.9.5 COMMUNICATIONS.......................................

3/4 9-5 3/4.9.6 MAN I PU LATO R C RAN E.................................... 3 / 4 9 - 6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING Bridge Crane.........................................

3/4 9-7

]

Spent Fuel Cask Crane................................

3/4 9-8

)

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Water Levels.....................................

3/4 9-9 Low Water Level...................................... 3/4 9-10

)

l 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION S Y S T EM............................................... 3 / 4 9 - 1 1 l

3/4.9.10 WATER LEVEL - REACTOR VESSEL l

Fuel Assemblies......................................

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

3/4 9-12a 3/4.9.11 WATE R LEVEL - STO RAG E PO0L........................... 3 / 4 9-13 J

3/4.9.12 STORAGE POOL VENTILATION ( FU EL STO RAG E).............. 3 / 4 9-14 j

3/4.9.13 STORAGE POOL VENTILATION ( FU EL MOVEMENT )............. 3 / 4 9 - 15 3/4.9.14 CONTAINMEK* P"nCE EXHAUST FILTED (Deleted)..........

3/4 9-16 l

3/4.10 SPECIAL TEST EXCEPTIONS 1

3/4.10.1 SHUTDOWN MARGI'.1......................................

3/4 10-1 l

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS..

.................. 3/4 10-2 l

1 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 SYSTEMS - SHUTDOWN............... 3/4 10-5 FARLEY-UNIT 1 X

AMENDMENT NO.

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l l-I l

INDEX BASES SECTION PAGE l

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 1

I 3/4.7.4 SERVICE WATER SYSTEM..................................B 3/4 7-3 3/4.7.5 RIVER WATER SYSTEM....................................B 3/4 7-3 3/4.7.6 U LT I MAT E H EAT S I N K.................................... B 3 / 4 7 - 4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM..

.......B 3/4 7-4 3/4.7.8 P ENETRATION ROOM FI LT RATION SYST EM.................... B 3 / 4 _ 7-4 l

3/4.7.9 SNUBBERS...........................

..................B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION...........................B 3/4 7-6 l

3/4.7.11 FIRE SUPPRESSIO" SYSTEMS (Deleted)....................B 3/4 7-6 3/4.7.12 FIRE EAnnIED PE"ETRATIO"5 (Deleted)...................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 4

j EARLEY-UNIT 1 XIV AMENDMENT NO.

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INDEX l

BASES I

I SECTION PAGE 3/4.9 REFUELING O?ERATIONS

)

l 3/4.9.1 BO RON CONC ENT RATI ON....................

..............B 3/4 9-1 3/4.9.2 INSTRUMENTATION.......................................B 3/4 9-1 3/4.9.3 DECAY TIME............................................B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS..................... B 3/ 4 9-1 i

3/4.9.5 COMMUNICATIONS........................................B 3/4 9-1 3/4.9.6 MAN I PU LATO R C RAN E..................................... B 3 / 4 9 - 1 3/4.9.7 SPENT FUEL STORAGE BUILDING - BRIDGE CRANE a nd S P ENT FU EL CAS K C RAN E............................. B 3 / 4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION

..........................................B 3/4 9-2 i

3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM..

.............................................B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL a nd S TO RAG E POO L..................................... B 3 / 4 9 - 3 1

3/4.9.12 and 3/4.9.13 STORAGE POOL VENTILATION SYSTEM...............................................B 3/4 9-3 I

3/4.9.14 GOMTAINMENT PURCE EXRAUET FILTED (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 R EACTO R COO LANT LOO P S................................. B 3 / 4 10 - 1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN.................B 3/4 10-1 l

t FARLEY-UNIT 1 XV AMENDMENT NO.

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h TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION a

-t M

MINIMUM.

CHANNELS APPLICABLE-ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION f

1.

AREA MONITORS

_1 4

z a.

Fuel Storage Pool 1

(a) 5 15 mR/hr 10

-10 mR/hr 23 y

Area (R-5) b.

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

PROCESS MONITORS a.'

Fuel Storage Pool Area Gaseous Activity-l Ventilation System Isolation (R-25A&B) 1 (b) s 8.73 x 10 3 pCi/cc(c)10-106 25 3

cpm 2

(g,i) 5 8.73 x 10-pC1/cc(c) 25 l

b.

Containment

i. Gaseous Activity-a) Purge & Exhaust Isolation (R-24A&B) 1 1,2,3,4,5,6 (d) 5 2.27 x 10-2 yci/cc(c)10-106 26 cpm 2

6 (d,h,1) s 2.27 x 10-2 pCi/cc(c) 26 l

w-1 1,2,3,4,5,6 (e)

$ 4.54 x 10-3 Ci/cc(c) 26 r

2 2

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

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

6 (f,h,1) s 2.27 x 10-3 pCi/cc(c) 26 g

w b)RCS Leakage 1

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

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

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

{

c.

Control Room Isolation (R34A&B) 1 1,2,3,4 s 800 - pm 10-106 27 cpm 2

1,2,3,4,.~. 6 ( g, h,1)s %u cpm 27 l

g O

V1 r

5 2

h l

I

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=

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_m.

m__..

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TABLE 3.3-6 (Continued) l ACTION STATEMENTS With the number of channels UPERABLE less than required by ACTION 23 the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring l

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.

ACTION 25 With one channel inoperable return both channels to OPERABLE status within 7 days or suspend all movement of fuel and crane operation with loads over the spent fuel in the pool.

With no channels OPERABLE, suspend all movement of fuel and crane operation with 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)

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 Specificatica 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.

l 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.

1.

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

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

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 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 .

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 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 irradiated fuel assemblies and movement of loads over irradiated fuel.

SURVEILLANCE REQUIREMENTS 4.7.7.1 Each CHEFS 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 days.

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FARLEY-UNIT 1 3/4 7-16 AMENDMENT NO.

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r PLANT SYSTEMS SURVEILLANCE REQD:9EMENTS (Continued)

.b.

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

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:

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 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 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 l

accordance with ASME N510-1989*.

2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with ASME N510-1989* 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.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with ASME N510-1989* meets the laboratory testing efficiencies criteria given in Note 2 when tested with methyl iodide at 30*C and 70% relative humidity.

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

i i

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

PLANT SYSTEMS SURVEILLANCE-REQUIREMENTS (Continued)

Ld.

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 7.5 2 0.8 kw when tested in accordance with ASME N510-1989*.+

e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.5% 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.

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*

l 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 i 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

+ Mechanical heater surveillance testing per ASME N510-1989 will be performed no later than completion of the Unit 1 15th refueling outage scheduled for the fall of 1998.

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

y-

a a.

~.... -..

.... ~ - - - -. _

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

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

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

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, the flow through the HEPA filters and charcoal adsorbers and verifying that the system has operated for at least 15 i

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 greator than or equal to 99.5% filter efficiency while operating the system at a flow rate of 5000 cfm 10 percent and using the following test procedures:

(a)

A visual inspection of the penetration room filtration system shall be made before each DOP *..ze or activated carbon adsorber section leak test in acc.; dance 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 l

accordance with ASME N510-1989*.

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

i FARLEY-UNIT 1 3/4 7-18 AMENDMENT NO.

1 PLANT SYSTEMS.

l SURVEILLANCE REQUIREMENTS (Continued) l

2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample ootained in accordance with ASME j

N510-1989* 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 10% during system l

operation when tested in accordance with ASME N510-1989*.

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with ASME N510-1989* 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 la 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 i 10%.

2.

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

I e.

At least once per 36 months on a STAGGERED TEST BASIS by verifying one PRF train can maintain a pressure 5 -0.125 inches w.g.

relative to atmosphere during the post LOCA mode of operation at a flow rate of s 5500 cfm.

f.

After each complete or partial replacement of a HEPA filter l

4 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 I

accordance with ASME N510-1989* while operating the system at a flow rate of l 5000 cfm i 10%.

g.

After each complete or partial replacement of a charcoal l

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 l

operating the systen at a flow rate of 5000 cfm i 10%.

The FNP Final Safety Analysis Report identifies the relevant surveillance testing

' requirements.

l l

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

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

LIMITING CONDITION FOR' OPERATION l

3.9.12 One penetration room filtration system (Specification 3.7.8) shall be l

OPERABLE and aligned to the spent fuel pool room.

l l

l APPLICABILITY:

Whenever irradiated fuel is in the storage pool.

ACTION:

l a.

With no penetration room filtration system OPERABLE, suspend all I

operations involving movement of 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.

SURVEILLANCE REQUIREMENTS 4.9.12.1 A penetration room filtration system shall be verifie,d 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:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow 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.b, c, d.1, f and i

g.

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.

l l

I l

l FARLEY-UNIT 1 3/4 9-14 AMENDMENT NO.

l l.

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

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

and aligned to the spent fuel pool room:

APPLICABILITY:

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

ACTION:

a.

With one penetration room filtration system inoperable return both systems to OPERABLE status within 7 days or suspend all movement of fuel and crane operation with loads over the spent fuel in the storage pool room.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

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

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

i

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

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

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

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

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This page intentionally left blank

3/4,9,14 Deleted i

FARLEY-UNIT 1 3/4 9-17 AMENDMENT NO.

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l This page intentionally left blank.

3/4.9.14 Deleted I

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

i ELAliT SYSTEMS BASES 3 /4 7.6.1 ULTIMATE HEAT SINK ( RIVEP. )

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 ecoling water supply to safety related equipment without 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 water is available.

3/4.7.7 CONTROL ROOM ENERGENCY 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 remaining OPERABLE CREFS train is adequate to perform the control room protection function.

However, the overall reliability is reduced because a single feilure in the OPERABLE CREES train could result in loss of CREFS function.

The 7 cay Completion Time is based on the low probability of a DBA occurring during this time period, and ability of the remaining l train to provide the required capability.

Operation of the pressurization 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.

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

1 I

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

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 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 assenblies 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 l

following all credible accident conditions.

j 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 flowrate 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 negative j

pressure to less than or equal to -0.125 inch water gauge with respect to atmosphere 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 provide reasonable assurance that unfiltered release to adjacent areas of any ECCS leakage will be nimized. Although not credited in the accident analyses, the PRF system also p.

ides filtration of containment leakage into the penetration room areas.

The oper tion of this system and the resultant effect from ECCS leakage on offsite dosage calcu.ations was assumed in the accident analyses.

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

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

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

~.

l

' REFUELING QEERATIONS BASES 3/4.9.9 CONTAINMENT PU~..

AND EXHAUST ISOLATION SYSTEM l

The OPERABILITY of this system ensures that the containment vent and purge l

penetrations will be automatically isolated upon detection of high radiation levels l

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 FHA are filtered prior to reaching the environment.

The PRF system is tested periodically in its FHA alignment to ensure the system functions properly.

Testing of HEPA filter performance, charcoal adsorber efficiency, and the physical proprieties of the activated charcoal is bounded by testing performed per 4.7.8.

The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

The note regarding PRF electrical system OPERABILITY is provided for clarification.

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.

With one PRF train inoperable, action must be taken to restore OPERABLE status within 7 days.

During this period, the remaining OPERABLE train is adequate to perform the PRF function. The 7 day completion time is based on the risk from an event occurring requiring the inoperable PRF train, and the remaining PRF train providing the required protection.

3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER This specification deleted.

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

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l r

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1 i

r h

l Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes Unit 2 Technical Specification Pages

)

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l "m

1 i

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FNP Unit 2 Technical Specifications Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Changed Panes X

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

3/4 7-17 Replace 3/4 7-17a Replace 3/4 718 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 I

i l

_.. ~ _. _. _

i INDEX 1

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

.SECTION PAGE

)

1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION...............

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

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

3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETPATIONS....................

3/4 9-4 l

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

3/4 9-5 l

3/4.9.6 MANIPULATOR CRANE....................................

3/4 9-6 j

j-

]

3/4.9.7 CRANt. TP'*?.L - SPENT FUEL STORAGE POOL BUILDING Bridge Crane.......................

............ 3/4 9-7 Spent-Fuel Cask Crane...............

............. 3/4 9 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Water Levels......................................T/4 9-9 Low Water Leve1...................................... 3/4 G-10 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM......

........................................ 3/4 9-11 3/4.9.10 WATER LEVEL - REACTOR VESSEL i

Fuel Assemblies...................................... 3/4 9-12 Centrol Rods......................................... 3/4 9-12a l

3/4.9.11 WATER LEVEL - STORAGE POOL...........................

3/4 9-13 3/4.9.12 STORAGE POOL VENTILATION (E'JEL STORAGE).............. 3/4 9-14 3/4.9.13 STORAGE POOL VENTILATION (FUEL MOVEMENT).............

3/4 9-15 3/4.9.14 CONTAI9ENT PURCE EX"J.UST FILTED

.(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.

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 BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 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 3/4.7.4 S E RVI C E WAT E R S YS T EM.................................. B 3 / 4 7 - 3 3/4.7.5 RIVER WAT E R S YS T EM.................................... B 3 / 4 7 - 3 3/4.7.6 ULTIMATE HEAT SINK..

..............................B 3/4'7-4

.3/4.7.7 CONTROL ROOM EMERGENCY VENTI LATION SYSTEM............. B 3/ 4 7-4 3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM....................B 3/4 7-4 l

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 FIRE SUPPnESSION SYSTEM (Deleted).....................B 3/4 7-6 3/4.7.12 FIRE EnnnIE" PENETR7.TIONS (Deleted)...............

...B 3/4 7-7 3/4.7.13 AREA TEMPERATURE MONITORING...........................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.

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

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INDEX i

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BASES 1

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SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9,1 BORON CONCENTRATION...................................B 3/4 9-1 3/4.9.2 I N S TRUMENTAT I ON....................................... B 3 / 4 9 - 1 3/4.9.3 DECAY TIME............................................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 MANIPULATOR CRANE...........................

.........B 3/4 9-1

]

3 / 4. 9. ~7 SPENT FUEL STORAGE BUILDING - BRIDGE CRANE a nd S P ENT FU EL CAS K CRAN E............................. B 3 / 4 9-2 1

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT l

l CIRCULATION

..........................................B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.......

........B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - RFACTOR VESSEL and STORAGE POOL.....................................B 3/4 9-3 l

3/4.9.12 and 3/4.9.13 STORAGE POOL VENTILATION SYSTEM...............................................B 3/4 9-3 3/4.9.14 CONTAI""ENT PUDCE EXHAUST FILTED (Deleted)...........B 3/4 9-3 l

3/4.10 SPECIAL TEST EXCEPTIONS 1

3/4.10.1 SHUTDOWN MARGIN....

e...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 l

3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN.......

.........B 3/4 10-1 1

FARLEY-UNIT 2 XV AMENDMENT NO.

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TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION

)

MINIMUM W

CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT

.E INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION E

1.

AREA MONITORS

_1 4

2 a.

Fuel Storage Pool 1

(a) 5 15 mR/hr 10

-10 mR/hr 23 e

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-

- f Ventilation System Isolation (R-25A&B) 1 (b) s 8.73 x 10-3 pCi/cc(c)10-106 25 cpm

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

b.

Containment

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

6 (d,h,i) 5 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 s

A 2

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

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

6 2

6 (f,h,1) s 2.27 x 10-3 pCi/cc(c) 26 e

b)RCS Leakage 1

1,2,3 & 4 N/A 10-106 24 cpm Detection (R-12) ii. Particulate Activity RCS Leakage 1

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

[

(R-11) c.

Control Room j

6 Isolation (R34A&B) 1 1,2,3,4 s 800 cpm 10-10 cpm 27 2

1,2,3,4,5,6(g,h,1)s 800 epm 27 l'

E M

B i

i 5

I P

P A

-.w.c n.

---.n v

v~

e w a

v--

-a a

-s-e--~

-e v--

m

.--m

, me

-e r

- -, ~

-ww.

---mr

TABLE 3.3-6 (Continued)

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.

ACTION 25 With one channel inoperable return both channels to OPERABLE status within 7 days or suspend all movement of fuel and crane operation with loads over the spent fuel in the pool.

With no channels OPERABLE, suspend all movement of fuel and crane operation with loads over the spent fuel in the pool until at least one channel is restored to OPERABLE status.

ACTION 26 With the number of channele 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 thu 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)

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, the cause of the inoperability and the plans and j

schedule for restoring the system to OPERABLE status.

a.

With fuel in storage pool.

j 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.

i 1.

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

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

= -

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

LIMITING CONDITION FOR OPERATION 3.7.7.1 Two control Room Emergency Filtration / Pressurization System (CREFS) trains shall be OPERABLE.

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 OPERABLE status within 7 days or ie 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 SHUTDOaN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 OPERABLE status within 7 days or immediately place the OPERABLE CREFS train in the emergency recirculation mode or immediately suspend movement of irradiated fuel essemblies and movement of 1

loads over irradiated fuel.

b.

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

SURVEILLANCE REQUIREMENTS j

l 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 days.

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

1

?

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 (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 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 tost in accordance with ASME N510-1989*.

(b)

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

in accordance with ASME N510-1989*.

l (c)

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

accordance with ASME N510-1989*.

2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with ASME N510-1989* 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.

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

verifying within 31 days after removal that a laboratory l

analysis of a representative carbon sample obtained in accordance with ASME N510-1989* meets the laboratory testing efficiencies criteria given in Note 2 when tested with methyl iodide at 30*C and 70% relative humidity.

l l

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

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

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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 t

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

2.

Ver3.y.ng 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 7.5 t 0.8 kw when tested in accordance with ASME N510-1989*.+

i e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.5% of the DOP when they are tested in-place in i

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

-l flow rate indicated in Note 1.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifyiro that the charcoal adsorbers remove greater than or equal to 99.!

of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ASME N510-1989*

l 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 i 10%

j 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 gacge c.

Control Room Pressurization Filter Unit 2.2 in. water gauge 1

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

1

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

requirements.

g

+ Mechanical heater surveillance testing per ASME N510-1989 will be performed no later than completion of the Unit 2 12th refueling nutage scheduled for the spring of 1998.

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

._m l.

PLANT SYSTEMS 3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION i

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 1

4.7.8 Each penetration room filtration system shall be demonstrated OPERABLE:

]

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, 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 poet 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 i 10 percent and using the 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*.

i (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 l

accordance with ASME N510-1989*.

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

FARLEY-UNIT 2 3/4 7-18 AMENDMENT NO.

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* meets the laboratory testing criterion of greater than or equal to 90% efficiency when tested with methyl iodide at 30*C and 95t relative humidity.

3.

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

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with ASME N510-1989* 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 t 10%.

2.

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

I e.

At least once per 36 months on a STAGGERED TEST BASIS by verifying one PRF train can maintain a pressure 5 -0.125 inches w.g.

relative to i

atmosphere during the post LOCA mode of operation at a flow rate of 5 5500 cfm.

f.

After each complete or partial replacement of a HEPA filter l

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 system at a flow rate of l 5000 c&n i 10%.

g.

After each complete or partial replacement of a charcoal l

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 l

operating the system at a flow rate of 5000 cfm i 10%.

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

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

~.

l-l 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 LOPERABLE and aligned to the spent fuel pool room.

I

}-

APPLICABILITY:

Whenever irradiated fuel is in the storage' pool.

l ACTION:

I a.

With no penetration room filtration system OPERABLE, suspend all operations involving movement of fuel within the storage pool until at least one penetration room filtration system is restored to OPERABLE status.

l b.

The provisions of Specifications 3.0.3 and'3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

.I 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:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow 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.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; a.

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

A spent fuel pool high radiation test signal.

l l

l i

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

--. ~...

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

LIMITING CONDITION FOR OPERATION 3.9.13 Two independent penetration room filtration systems (Specification 3.7.8)

.shall be OPERABLE

and aligned to the spent fuel pool room:

1 APPLICAbsLITY:

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

ACTION:

a.

Witt one penetration room filtration system inoperable return both systems to OPERABLE status within 7 days or suspend all movement of fuel and crane operation with loads over the spent fuel in the storage pool.

room, b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

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

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

1

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

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

l l

l REFUELING OPERATIONS 3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER l

This specification deleted.

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

l t

I This page intentionally left blank.

3/4.9.14 Deleted 4

1 i

I I

I i

FARLEY-UNIT 2 3/4 9-17 AMENDMENT NO.

l l

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i 1

1 This page intentionally left blank.

3/4.9.14 Deleted i

L FARLEY-UNIT 2 3/4 9-18 AMENDMENT NO.

ELANT SYSTEMS BagEs 3 /4 7.6.1 ULTIMATE HEAT SINK (RIVER)

This specification deleted.

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

j 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 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 time period, and ability of the remaining l train to provide the required capability.

Operation of the pressurization 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.

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

t I

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

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 staf f actions can restore or ndtigate the ef fects i

of component failures, and the time available to respond as loss of control room cooling does not have an immediate, irreversible impact.

l 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 PENETRATION ROOM FILTRATICN SYSTEM The OPERABILITY of the penetration room filtration system provides reasonable assurance that radioactive mater!.als leaking from ECCS pump rooms during post LOCA recirculation are filtered prior to reaching the environment.

The minimum system flowrate maintains a slightly negative pressure in the penetration rcom area aad 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.

Patiodic testing of the RHR heat exchanger room negative pressure to less than or equal ts -0.125 inch water gauge with respect to atmosphere 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 provide reasonable assurance that unfiltered release to adjacent areas of any ECCS leakage will be minimized. Although not credited in the accident analyses, the PRF system also provides filtration of containment leakage into the penetration rocm areas.

The operation of this system and the resultant effect from ECCS leakage on offsite dosage calculations was assumed in the accident analyses.

I r

l I

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

l I

-. -. ~.

REFUELING OPERATIONS BASES l

J/4.9.9 CONTAINMENT PURCE AND EXHAUST ISOLATION SYSTEM i

r 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.

l 3/4.9.12 and 3/4.9.13 STORAGE POOL VENTILATION SYSTEM t

The OPERABILITY of the penetration room filtration system ensures that-radioactive materials leaking from the spent fuel pool area following a FHA are filtered prior to reaching the environment. The PRF system is tested periodically in its FHA alignment to ensure the system functions properly. Testing of HEPA filter j

performance, charcoal adsorber efficiency, and the physical proprieties of the activated charcoal is bounded by testing performed per 4.7.8.

The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses. The note regarding PRF electrical system OPERABILITY is provided for clarification.

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.

j With one PRF train inoperable, action must be taken to restore OPERABLE status within 7 days.

During this period, the remaining OPERABLE train is adequate to perform the PRF function.

The 7 day completion time is based on the risk from an event occurring requiring the inoperable PRF train, and the remaining PRF train providing the required protection.

3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER This specification deleted.

l I

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

l l

l

~

1 4

4 e

e 4

Joseph M. Farley Nuclear Plant Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes Units 1&2 Marked-Up Technical Specification Panes s

e j

Joseph M. Farley Nuclear Plant

' Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes IInit i Marked-110 Technical Specification Paees

l l

1N9.P LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRgMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 00 ROM CONCENTRATION..........................

3/4 9-1 3/4.9.2 INSTRIM NTATION..........................................

3/4 P 2 3/4.9.3 DECAY TIM........

4.....................................

3/4 9-3 3/4.9.4 CONTA!WENT SU!LO!NS PENETRATIONS........................

3/4 F 4 3/4.9.5 ComuM ! CATI ONS...........................................

3/4 F5 3/4.9.6 NAMIPULATOR CRAME........................................

3/4 9-4 3/4.9.7 CRAE TRAVEL - SPENT FUEL STORAGE POOL SUILDING Bri dge C rane.............................................

3/4 F7 Spent Fuel Cas k Crane....................................

3/4 9-4 1

3/4.9.8 RESIOUAL MAT REmvAL Am COOLANT CIRCULATION All idater Levels.....................................l...

3/4 F 9 Law Water Lave 1..........................................

3/4 F10 3/4.9.9 CONTAIl0ENT PUAGE AM DHAUST ISOLATION SYSTEM...........

3/4 F il 3/4.9.10 MTER LEVEL - REACTOR VE5SEL Fuel Assemb11es..........................................

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

3/4 P 12a 3/4.9.11 WATER LEVEL - STORAGE P00L................................

3/4 > 13 v4. 9. u STORAaE Po0t. vaTIi.ATIm gwL ST0RAaE)..................

v4' *14 v4. 9. u STuAn vanuTION uwt =vaar).................

v4',-15 3/4.9.14 GONTAHOWif-PURE @StW5? fit:TER... b.

3/4 -14 3/4.10 SPECIAL TEST Eh sriiONS 3/4.10.1 SHUT 00WN MARGIN..........................................

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AM0 POWER OISTRISUTION LIMITS....

3/4 10-2 3/4.10.3 PHYSICS TEST 5............................................

3/4 10-3 v4.10.4 REACTO: C00uMT to0Ps....................................

u4 10-4 3/440.5 POSITION IM ICATION SYST D5 - SHUT 00WN...................

3/4 10-5 FARLEY-UNIT 1 X

NG OENT N0. 26

_INDEX BASES SECTION PAGE 3/4.7 PLurT SYSTEMS 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 VATER SYSTEM..............................

B 3/4 7-3 3/4.7.4 SERVIC! VATER SYSTEM........................................

B 3/4 7-3 3/4.7.5 RIVER VATER SYSTEM..........................................

B 3/4 7-)

3/4.7.6 ULTIMATE BEAT SINR..........................................

B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VElfrILATION SYSTEM...................

lfkBfMfMW B 3/4 7-4 3/4.7.8 l4GGS-8UNS. ROOM EXEAUST A&R 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 -Mc 0'.'=": ~' ".. ="' ( De le t ed )..........................

B 3/4 7-6 3/4.7.12 6 (Deleted).........................

B 3/4 7-7 i

3/4.8 ELECTRICAL POVER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POVER DISTRIBUTION SYSTEMS.........................................

B 3/4 8-1

\\

e FARLEY-UNIT 1 IIV AMENDNENT NO. 26, 96

_.._m RNCEX 4

BASES i

~l l

i SECTION A

PAGE 4

3/4.9 REFUELING OPERATIONS 3/4.9.1 80RON CONCENTRATION..................'....................

8 3/4 9-1 3

3/4.9.2 IM5TRLMENTATION..........................................

B 3/4 9-1 i

i 3/4.9.3 DECAY TIM...............................................

t 3/4 9-1 3/4. 9. 4 CONTAlmefr =ItnIN: nwTRAn0=5........................

. 3/4 9-1 i

j 3/4.9.5 C0f0t*1 CATIONS...........................................

8 3/4 9-1 j

3/4. 9. 6 MAN ! WuTOR CRANE........................................

8 3/4 9-1 3/4.9.7

$Pe4T FUEL ST3 RAGE Su!LDING - SRIDGE CRANE and

$>ENT FUEL CASK CRAME..................................

t 3/4 9-2 a

3/4.L 6 f.E51 DUAL HEAT REMOVAL AND COOLANT CIRCULATION............

B 3/4 9-2

]

3/4.9.9 CONTADOWif PURGE Afe EXMAUST ISOUTION SYSTEM...........

8 3/4 9-3 3/4.9.10 and 3/4.9.u id4TElt LEVEL - REACTOR 455EL and l

STORAGE P00L............................................

8 3/4 9-3

{

3/4.9.12 and 3/4.9.13 STORAGE POOL VENTI u TION SYSTEM..............R 3/4 9-3 GBNFAfMMENF-PURSE-EXMAtts?-PS.TER...N.N.............

B 3/4 9 3 3/4.9.14 s'

3/4.10 SPECIAL TEST DCEPTIONS 3/4.10.1 SHUTDOWN MARG,IN..........................................

B 3/4 10-1 i

3/4.10.2 GWUP HEI9ff. INSENTION Afe POWER DISTRIStfrION LIMIT 3.... I 3/4 10 1 i

4 3/4.10.3 PHYSICS TEST 5............................................

5 3/4 10-1 i

i 3/4.10.4 m CMLANT m....................................

t 3/4 10-1 i

i 3/4.10.5 POSITION IMO! CATION SYSTEM - SHUTDOWN....................

8 3/4 10-1 i

4

)

i i

b FARLEY-UNIT 1 XV AMEM MENT NO. 26 i

)

I 4

4 4

TABLE 3.3-6 h

RADIATION MONITORING INSTRUMENTATION r-Q J-MINIMUM M

CHASMELS APPLICABLE ALARM / TRIP MEASUREMENT

[

INSTRLMENT OPERABLE

'M00ES SETPOINT RANGE ACTION 1.

AREA MONITORS a.

Fuel Storage Pool 1

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

-10 mR/hr 23 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 System

-3 6

wi Isolation (R-25A&B)

(b) 1 8.73 x 10 uCi/cc(c) 10-10 cpm 25 J

-formf /

w

-s J,

b.

Containment 1.

Gaseous Activity-

=

= - - -

a) Purae & Exh h )_=1 1,2,3 (d)

$ 2.27 x 10_2 pCl/cc(c) 10-10 cpm 26 6

Isolation TR-24A&B

~

4.5,6 (d)

$ 2.27 x 10,3 pCi/cc(c) 26 f,* pf y 1,2,3,4,5,6 (e)

$ 4.54 x 10_3 pCi/cc(c) 26 1,2,3,4,5,6 (f) 1 2.27 x 10 pCi/cc(c) 26 6

b) RCS Leakage.

I 1,2,3 & 4 '

N/A 10-10 cpm 24 g

Detection (R-12)

E 11.

Particulate Activity 6

k RCS Leakage 1

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

Control Room 6

Isolation (R35A&B)

_1 _ __ l.2.3.4 W _

< 800 cpm 10-10 com 27 nn a

=eum

}

m a

e 1 nen e r=3

m.._

l TABLE 3.3-6 (Continued)

ACTION STATEMENTS l

+

With the number of channels OPERABLE less than required by ACTION 23 -

the Mininum 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.

4 ACTION 25 -

* -"-'shii6siis'- ""EFHB i? i?%s s WM

- ^'

i TEM i-s i i

l e-AcT = m m.u nt: e :p uifi uti = 3.:.:2 aa: :.:.13.

ACTION 26 -

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

t ACTION 27 -

With the number'of channels OPERABLE less than required by i

3 the Mintinum Channels OPERABLE requirement, within i hour i

initiate and maintain operation of the control room emergency ventilation system in the2 recirculation made of opera ti on.

J 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) Either restore the inoperable Channel (s) to OPERABLE status within 7 days, or

2) Prepare and submit a Special Report to the Connission 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 OPERA 8LE status.

l 1

a.

With fuel in storage pool.

b.

With irradiated fuel in the storage pool.

c.

Above backgrcM with no flow.

d.

With mini-purge in operation, e.

With slow speed main purge in operation.

f. Jtth fast speed main purge in op_eratiok i

htW

_. -s-

-=

\\

FAE EY-UNIT 1 3/4 3-40 Amendment No. 47 i

J

Insert I for Table 334 2'

(g,1) s 8.73 x 10-3 pCi/cc(c) 25 insert 2 for Table 334 Isolation (R-24A&B) 1 EC c

10-106 26 cpm 2

'6' d,

,1) s, 7x

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

1,2,3,4,5,6 (f)

$ 2.27 x 10-3 pC1/cc(c) 6 (f,h,1) s 2.27 x 10-3 Ci/cc(c) 26

- Insert 3 for Table 334 4

2 1,2,3,4,5,6(g,h,ils 800 cpm 27

'l inseri 4 for Table 334 With one channel inoperable return both channels to OPERABLE status within 7 days or suspend all movement of fuel and crane operation with loads over the spent fuel in the pool.

With no channels OPERABLE, suspend all movement of fuel and crane operation with loads over the spent fuel in the pool until at least one channel is restored to OPERABLE status.

Insert 5 for Table 334 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.

i.

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

.....m.

4 PLAN

S Y97D49 3/4.7 ?

CONTROL ROCH EMERGENCY VEN*ILATTCH GYg;EM CCNTROL ROOM EMERGENCY TILTRATICN/ PRESSURIZATIC$1 SYSTEM (CREFS) j LIMITING CONDITION FOR OPEPATION 3.7.7.1 Two Control Room Emergency Filtration /3ressurization System (CREFS)

I trains shall be OPERABLE.

i 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 h

OPERABLE status within 7% days or be in at least HOT STAND 8Y within the; i

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 .

(/

j next 6,duringmovementofirradiatedfuelassemblies,andduringmeemen MODES 5, of loads over arradiated fuel:

j a.

With one CREF5 train inoperable, restoretheinoperablesystemcof OPERABLE status within 7 days or immeediately place the OPERABLE CREF5 train in the emergency recirculation mode or issnediately suspend movement of irradiated fuel assemblies and movement of loads over irradiated fuel.

h b.

With both CREF5 trains inoperable, immediately suspend movement o irradiated fuel assemblies and movement of loads over irradiated i

fuel.

\\

SURVEILLANCE REQUIREMENTS 4.7.7.1 Each CREFS train shall be demonstrated OPERABLE:

l 1

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

from the control room, flow through the pressurization and s

recirculation system HF.FA filters and charcoal adsorbers and verifying that the pressurization system has operated for at least j

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

fh

A ne-ime ten ion o3 day to es t ain of a oci cul ion fil rat on f ct1 of CREF is gra ted for imp ene at on fe tre to co lin desi n c nge T e p ovi ion of spe ifi t1 3 0.4 re et a lie ble ein th 30 day ext si hi on t e ten on xp1 s on mpi tion ft U t 1 4 ti re el g ta

( ri

).

FARLEY-UNIT 1 3/4 7-16 AMENDMENT No119l

n: s,sms l

SURVEIL ANCE REQUIREMENTS (Continuad) j 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 j

have contaminated the charccal adsorbers or HEPA filters in any ventilation zot;e communicating with the system by:

l 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 indicated in Note 1 and using the following test j

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 accordance with ASME N510-1989*.

(b)

An in-place DOP test for the HEPA filters s be perf ormed in accordance with 0;ni;n 10 ;f _ __ _ N510-

++e+.

l MM*

(c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall performed in accordance with :::i;: 1: ;f _ _ r: N510-

+96+.

t9ME 2.

Verifying within 31 days after removal that a laboratory 1

analysis of a representative cg sample ptained in accordance with 4eeP.i;; '

ef __~. N510 b meets the laboratory testing efficiencies crg eria given in Note 2 when tested with methyl iodide at 46*C and 70% relative l

humidity.

3.

Verifying a system flow rate as indicated in Note 1 during system operation when tested in accordance with ASME N510 '

j 1989*.

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days siter removal that a laboratory analysis of a representative c g samp gtained in l

accordance with 0;n.s.. O ef _. N510-meets the laboratory testing efficiencig criteria given in Note 2 when t

tested with methyl iodide at 46*C and 70% relative humidity.

l l

l

[

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

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

I

.-~_

-.~.-.-

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

- - ~

l p' Mr? svs-rvs SURVEIL,1.ANCE PEOUIREMENTS (Continusd) i d.

At least once per 18 months by:

s 1.

Verifying that the pressure drop across the combined HEPA g

QQd filters and charcoal adsorber banks is less than A 4--W l pin;_ Cr;: while operating the system v. a flow rate I

l a bT C 3 indicated in Note 1. M-l 2.

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

1 4

1 j

3.

Verifying that the system maintains the control room at a j

positive pressure of greater than or equal to 1/8 inch water gauge relative to the outside atmosphere during l

system operation.

4.

Verifying that the pressurization system heater dissipates 7.5 t 0.8 kw when tested in accordance with ASME N510-1999*.+

l j

f l

After each complete or partial replacement of a HEPA filter

{

e.

bank by verifying that the HEPA filter banks remove greater than or equal to 99.5% of the DOP g n they tested in-place in accordance with Oee;ie.. ;; ef Tr : N510-while operating l

the system at a flow race indicated in Note 1.

i I

f.

After each complete'or partial replacement of a charcoal i

adsorber bank by verifying that the charcoal adsorbers remove eroster than or equal to 99.5% of a halogenated hydrocarbon j

rr.trigerant test gas when they g teste

-place in accordance with 0;;.i;n 1 ;f._-_ N510-while operating l

the system at a flow rate indicated in Note 1.

l Note 1.

a.

Control Room Recirculation Filter Unit 2000 cfm e lot

)

b.

Control Room Filter Unit 1000 cfm 2 10%

i c.

Control Room Pressurization Filter Unit 300 cfm 2 10%

i Note 2.

a.

Control Room Recirculatica Filter Unit 2 9 M % G Te I

b.

Control Room Filter Unit 2 +M. t!.59, i

f c.

Control Room Pressurization lead kQ 2 +9 ee+4-91.5Te 6 e'as.

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

i i

The FNP Final Safety Analysis Report identifies the relevant j

surveillance testing requirements.

)

l tt FT uill... i;; ;'...; _,i. _ p;;;_ _;; d;;p f;; thi; ru; c;ill;;;;

i

g_i;;;;;; i.

J.; i: 0 ;;;.'.i;;l.,p;;ifi;;; ;. ;ii;t:1 ;; ;;;;.itt;d

{

i- %.C.... ::;;'.. ' ; ' ;^..;. d ~ ; d 4...' ;;, ' 0 0 ?

i (E

Mechanical heater surveillance testing per ASME N510-1389 will.be

+

performed no later than completion of the Unit 1 15th refueling cutage i

scheduled for the fall of 1998.

)

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

4 i

-- -N W 3,M ote 3.

a.

Control Room Recirculation Filter Unit 3 d in. water gauge b.

Control Room Filter Unit ad in, water gauge c.

Control Room Pressurization Filter Unit M in, water gauge

.]

..-_...-_.....m

}'JLNT SYE?D4S a/4.7.9 PKNTTRAT20N ROOM F7tTRATTON SYSTEM LIMITING CONDITION FOR OPERAT80N 3.7.8 Two independent penetration room filtration systems shall be OPERABLE.

1 APPLICABILI*Y:

MODES 1, 2,

3 and 4.

Ac* ION:

witn 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 .

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

l At least om:e per 31 days on a STAGGERED TEST BASIS 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.

L_.. _ J ;;. ;L_ '

b; r-

. M -,.

QH T*ST'S}eS LD}C.

Pa l

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 chemical release that could have contaminated the charcoal adsorbers or HEPA filvers in any j

ventilation zone consnunicating with the system by:

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

.o 99.5% filter efficiency while operating the system at a flow rate of 5000 cfm 2 10 percent and using the following test procedures:

l (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*.

(b)

An in-place DOP test for the HEPA filters shall performed in accordance with 6 Hg N510-(c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be performed in accordance with eeeeeen-46-ee-M OE g g N510-MS "

i

The FNP Final Safety Anal s.e

.yort identifies the relovant surveillance;g testing requirements.

U l

I FARLEY-UNIT 1 3/4 7-18 AMENDMENT NO.

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

.. _. ~

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

l-p LAA** s YsEME SURVE:LLANCE REQUIREMENTS (Continuad) 2.

Verifying within 31 days after removal that a laboratory I

analysis of a re resentative carbon sample obtaia-d

n accordance with

ir-1: ;f Tl::: N510- d ts the N

l laboratory testing criterion of greater than or equal to

+64 effAciency when tested with methyl iodide at and relative humidity.

go*c i

3.

Verifying a system flow rate of 5000 cfm e lot during system operation when tested in accordance with ASME N510-1989*.

JsMG c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal doorber operation by verifying within 31 days afte emoval that a laboratory analysis of a representative arbon sample obtained in accordance with 2;;.... '.:.: ?;::: N510-4400- meets the laboratory testing criterion of greater han or equal to w 10%

efficiency when tested with methy ide at and relative humidity.

33*h 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 9 nches A.b Water Gauge while operating the system at a flow rate o 5000 cfm t 10% g h

2.

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

'?;. i f,.; ; : h_..:._ '.._'... d _ _ _ ;; ; ; _ :.: '. _ che..

_::;r ' ' -

r an _ -

v - --

p A T_

L E n vT-

e. ace' ?tq % N = ATWS o4 A.ST846ER.O Ten Kfter each comgilete or partial replacement of a HEPA filter G ars 5 bank by verifying that the MIPA filter banks remove greater than or equal to 99.5% of the DOP when they are tested in-place in accordance with 6 510-Deem while operating the system at a flow rate of 5000 cfm 2 After each complete or partial replacoment of a charcoal adsorber bank by verifying that,the charcoal adsorbers remove greater than or equal to 99.5% f a halogenated hydrocarbon refrigerant test gas when the are tested in-place in accordance with 9eeeeen=b6-ed-MI68 N510-ile operating the system at a flow rate of 5000 cfm 2 104.

S*

The FNP Final Safety Analysis Report identifies the relevant i

surveillance testing requirements.

= _.11..... ;te.._..._._

r..___..

.., Ce. :.hi_ ;_. _ill- ::

r r i----- : ir : ?_:

l'"' t:"-irri :;::ifi :rir; r i -itt:1 :: x i:::f i; 2 ; _. :......;.,. l...... u.s u.6 a aput u, 4,1<.

M.:._...;;'. h_;;;. ___.. 1';.;. ;;_....,,.. M:- ;;^; '. :: - . i; p f;... _ d..; 1_;;. ? - -

1;;i 20 ;h.

C..R.

. :. ;h ef_ 1...i FARLEY-UNIT 1 3/4 7-19

,__ AMENDMENT NO.

BT Vet #it AG t A 2. 'TW %.a ca.s MA aPTA.) 4 9e4 %.tS 4-0.t25 sac.4LS v.7, w amans MLAvivg p

Ava1 6 t5 tu't.4 75 yds 7-inca n og op ePERA-rso4 A'T /, Flea pia 7C of f. 5500 c.Fr4

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n

~

l 1

.4.".!:

STCMGE FOCL '/ENT:".AT:"N

'F"EL STORAGE; I

' *v'~ ~NG CONDITION FOR OPERAT:CN l

I l

3.9.12 One penetration room filtration system ;Spe:: fica::en 3.'.5; snal.

I be CPERASLE and aligned to ne spen: fuel pool :::m.

i AFFL::ABILIT" Whenever ;rras sted fuel is in :ne s: rnge po;;.

ACT:0N:

l a.

With,no' penetration room filtration system OPERABLE, suspend all operations involving movement of fuel within the storage p:c; until at least one penetration room filtration system :s res:cred to OPERABLE status.

(

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not l-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 h; p;..;;;;; i;r.. _ ;.; filt ;;;i;.- ;i;;;; ;h;11 b;

.2...

l'8 SCI"I I m<mnmmme r.

.r..........

.e.

3/4,5,,g,

(,4 9 12 1) 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.

l i

FARLEY-UNIT 1 3/4 9-14 AMENCMONT NO. 26

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:

a..

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

- the control room, flow through the HEPA filters and charcoal adsorbers and l

' 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.b, c, d.1, f and g.

l l

l.

l l.

I I

P EF'.JEL ING "dP D l

i 3p4.9.13 STOPX;E POCL YENTILATICM fFUEL MOVEMENT 1 LIMITING CONDITION FOR OPERATION l

3.9.13

?ao independent penetration room filtration systems tSpecificati:n 3.~.3 d[.

l shall be CPERABLE

and aligned to the spent fuel pool room:

l l

APPLICAEILITY:

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

ACTION:

With one penetration room filtration system inoperable return both a.

systems to OPERABLE status within 7 iays or suspend all movement of f

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

1 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 fue1 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 operat ns in the storage pool room are suspended.

0 4.9.13.2 The penetration room filteation system shall be demonstrated OPERABLE per the requirements of Specification"4,%ih f,9,//,2 dwM f,f,//..I, f 0.12.2

't 1:::t :n:: 7:: 19 :: nth: : ify th:t th; n;.;1 ;p;nt fu;l p;;l ey.e m unne41me4nn euerer mili 1 :1;;; up;,2ec ivi v'

.iLhwr; S.

The ep?"t f'^1 p^^1 "^"til*"i^"

1^" diff?!""5! 1p" Ur^ t?:t eign:, :r 5.

:;:nt fuel p::1 hi;;h radictir. t :t ri; 21.

The normal or emergency power source may be inoperable in MODE 5 or 6 provided

[

that the requirements of TS 3.8.1.2 are satisfied.

d i

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

l

3/4,?.14 CONTAINu!NT Dg4GI EXWAUS* FILTER

' LIMITING CONDITION FOR OPERATION 3.9.14 The containment purge exnaust filter snall be OPERABLE a valve l

N1P13V293 closed.

APPLICABILITY:

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

nside containment ACT!0N: Witn the containment purge exhaust filter noperable either:

1.

Imediately close the 48 inch contain t purge isolation valves l

(C8V HV-3196, 3197, 3198A and 31980) nd the 8 inen containment mini-purge isolation valves (C8V-H 2C56C, 28660, 2867C and 28670), or 2.

Cease all CORE ALTERATIONS and uel movement.

SURVEILLANCE REQUIREMENTS 4.9.14 The above required c ainment purge exhaust filter shall be oemonstrated OPERABLE:

a.

At least once r 18 montns or (1) after any structural maintenance on the HEPA filgar or charcoal adsorcer housings, or (2) following painting, ftte or chemical release that could have contaminatea tne charcoal adsoroers or HEPA filter in any ventilation zone communteating with t.no system by:

fl tis y ecll<br/i lclefCI*

I FARLEY-UNIT 1 3/4 9-16 AMEN 0 MENT NO. 25 70 l

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

~ ~.

l l

R FFT'T' ?Md O DFWi* ??Mt:

StrRVEILIANCE REQUIREMENTS (Continued) ra 1.

Verifying that the cleanup system satisfies the 1 -place testing acceptance criteria of greater than or 1 to 99.5% filter efficiency while operating the purge system and using the following test procedur i

(a)

A visual inspection of the_ containment purge exhaust filter system shall be mad / before each DOP test or activated carbon adsorber'section leak test in accordance with ASME N510-1 9*.

l i

(b)

An in-place DCP test for t HEPA filters shall be perforined in accordance wi Section 10 of ANSI N510-1980.

(c)

A charcoal adsorber s tion leak test with a gaseous halogenated ydrocarbon refrigerant shall be perforined in ac rdance with Section 12 of ANSI l

j H510-1980.

/

[IliS QR & Inft. dos

/e// &[a46, Verifying within 31 ys after removal *that a laboratory b *N O#[#!#/

analysis of a rep sentative carbon sample obtained in accordance with etion 13 of ANSI N510-1980 meets the laboratory tes ng criterion of greater than or equal to 904 efficien when tested with methyl iodide at 80*C and 70% relativ humidity.

I b.

After every 12 nths of charcoal adsorber operation by l

verifying wi n 31 days after removal that a laboratory l

analysis of representative carbon sample obtained in accordanc with Section 13 of ANSI N510-1980 meets the laborato testing criterion of greater than or equal to 90%

offici cy when tested with methyl iodide at 80*C and 70%

relati4e humidity.

c.

A east once per 18 months by verifying that the pressure drop ross the combined NIFA filters and charcoal adsorber banks is ees than 6 inches Nater Gauge while operating the main purge system.

FNP Final Safety Analysis Report identifies the relevant s

eillance testing requirements.

FARLEY-UNIT 1 3/4 9-17 AMENDMENT NO.

I i

l

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

i REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continuad) d.

After each complete or partial replacement of A filter bank by verifying that the HEPA filter bank emove greater than or equal to 99.51, of the 00P when t.

are tested in-place j

in accordance with Section 10 of ANSI.N510-1980.

/

e.

After each complete or partical, replacement of a charcoal adsorber bank by verifying e't the charcoal adsorbers remove greater than or equal to

.Si of a halogenated hydrocarbon refrigerant tr.st gas n they are tested in-place in accordance with Se on 12 of ANSI NS10-1980 while operating the main purge stem.

1 l

Y a

hts fofe infMOktf lcll blM$.

3/+, 9, l+ ikleteJ x

i a

i t

I FARLEY-UNIT 1 3/4 9-18 AE NDMENT NO. 46

4 CASES l

3f4 a.gt Ut ?wA?r wrA* f?MY M

Vr H This specification deleted.

4 i

j 4

4_2 UL"?wA?r MEA? ETNX f PONS

)

l The limitations on the ultimate heat sank level and temperature ensure j

that sufficient cocling capacity is available to either il provide normal J-cooldown of the facility, or 21 tL meigate the ef fects of accident conditions within acceptable limits.

d The limitations on minimum water level and maximum temperature are based j

on providing a 30 day ecoling water supply to safety related equipment without

{

exceeding their design basis' temperature. The measurement of the ground water i

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

3 / a,1_ S fvarrnN d W VetrPf f 19fM mw___

i w

The control room emergency filtration /pressurisation system (CREFS) consists of two independent. redundant traias that recirculate sad filter the control room air, and two independent, redundant trains that pressurize the i

control roon.. Tha, OpsRAaZLITY of this system in cemjuddties with control room design previsier.sjee.) seed on limiting the radiation esWeeure te personnel. 4

~

occugyJq, g,, con 4gol room to. 5 ran or less whole undy,' or its espsivalent.' #

This u473,pgy,sensi. stent with the requirassets of Osmere! Design criteria i

19 of Appendix *A*.

10CFR50.

~

k When one CREFS train is inoperable, action muet' be t'aken to reatore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE l

CREFS train is adequate to perform the control rocer protection function.

4 However, the overall reliability is rechaced because a' single failure in the OPERABLE CREFS train could result in loss of CREFS t' nction. The 1 day u

Completion Time is based on the low probability of a DBA occurring during this

= d :f time period, and ability of the remaining train to provide the required capability.

rtWlNM b'Nb W' ess=4eeeve /peration of the em van the heater es( for at least le

]

cedias,e hours over a 31 day period is sufficient to ren fB hugI d einfsture en the adsorbers and IIEPA filter.

1 The control room air conditieming system (CRAcS1 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 centro; room is dependent upon f act=rs such as outdoor att temperature.

i n

a i

FAR!.!Y-UNIT ;

B 3/4 7-4 AMENDMENT NO.

119 4

(

i 1

)

,f 1

... _.. ~. _.

k p* n ;- sv e'?r n t

BASES i

i i

3 4_*

7 e n ne*_ ROOp rwr9dENCY VEM*??1?!ON MYS? M f ce*

i ued l W th one O M tra n inoperacle. the anoperable train ;;st ce returned to i

t

FIMBLE status w:t.:n 30 days. This Allowed Outage Time ts cased on the low procent11ty of complace loss of control room cooling due te t..e redundancy of the support systems, the capability of the OPERABLE train to provide the i

required coaling, the potential that plant statf actions can restore or i

mitagate the effects of component failures, and the came avatlable to respond as loss of control room cooling does not have an immediate, irreversible

ispect, i

i while in NODES $ and 6 during movement of irradiated fuel assemblies or I

movement of loads over irradiated fuel, if both traiu of CRAC cannot be restored to OPERABLE status within 30 days, an OPERABZ2 CRAC train must be

}

placed in operation immediately; ocherwise, ismediately suspend movement of j

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

2 f

i The OPERABILITY of the control room emergency ventilation system ensures that I-

1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this 1

system and 2) the control room will remain habitable for operations personnel

]

during and following all credible accident condit11ms.

i M

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FTLTRAffCW SYSTEMA i

d 0,. _.

II C 2 -- - I I

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th:t ::di::: tin = t:ri:12 1r9i-- f: n the -: - C in- "i"" - "" m

(

- f 11 = n; : L^"'.

filte: M prier :: :::rhi-- ! " --'1:----"

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th:-;f:--t z,- ' S 1 filt::,

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1 1

1

.ARLEY-UNIT 1 3 3/4 7-4a AMDfDMENT NO.119 l G

q i

3 k

$f 1

l.

1 1

a e

i

l In2crt 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 aump rooms during post LOCA recirculation are filtered prior to reaching the environmen':. The minimum system flowrate -

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 i

testing of the RHR heat exchanger room negative pressure to less than or equal to -0.125 inch water gauge with respect to atmosphere verifies the integrity of the PRF system pressure boundary and is consistent with the g uidance for standard technical specifications in NUREG 1431. Functional testing of proper PRF system operation and pressure boundary integrity provide reasonable assurance that unfiltered release to adjacent areas of any ECCS leakage will be minimized. Although not credited in the accident analyses, l

the PRF system also provides filtration of containment leakage into the penetration room i

areas. The operation of this system and the resultant effect from ECCS leakage on offsite dosage calculations was assumed in the accident analyses.

1 i

i L

l REF"ELING tPERATIONS l

l BASES i

3,4.9.9 OCNTAINMENT PURCE AND EXMAUST ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and l

l purge penetrations will be automatically isolated upon detection of high I

radiation levels within the containment.

The OPERABILITY of this system is l

required to restrict the release of radicactive material from the containment I

atmosphere to the environment.

l 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 STORACE POOL VENTILATION SYSTEM Th: li=it:ti:n: cr th: ter ; pr:1 centil:ti:n cy:ter en:::: th:t all riai m etum mrmri_i reimmema f r 3., irrgi3teg guel ::;-21j.;ili 3; gg filtered threu;5 the uges giiter.

--a

-g3 reg 31 gegrger 7 12 te gireg37;c to th: :::::phere.

P.: 0"""2"!LI" Of thi: : ::: :nd th: :::ulting iodine rre'fal per!!'; cre rencirtent '-fith th

" pti:n: :! th: ::id:nt 2n:1y ::

The note regarding PRF electrical system OPERABILITY is provided for l

clarification.

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.

l With one PRF train inoperable, action must be taken to restore OPERABLE status within 7 days. During this period, the remaining OPERABLE train is adequate to perform the PRP function. The 7 day completion time is based on the risk from an event occurring requiring the inoperable PRF train, and the remaining PRF train providing the required protection.

3/4.9.14 CONTAINMENT PURCE EXHAUST FILTER Se peribilit'j CI th centiir.rt pn;;

t= t filt : =x: th;; ir l

th c'fmt rf a fuel hrdlin; ::ident ir th: ::ntri=:nt the r:diereti=

r2teri:1: r:122 d are filtered rd 2d::: bed prier : ::::hin; th:

l

:1::===.

l hl1 ffetihQt(EN b'Nf l

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

I

INSERT 1 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 from the spent fuel pool area following a FHA are filtered prior to reaching the environment. The PRF system is tested periodically in its FHA 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 test *dj performed per 4.7.8. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

l l

l 6

I l

l I

l Joseph M. Farley Nuclear Plant l

Control Room, Penetration Room, and Containment Purge Filtration Systems and Radiation Monitoring Instrumentation Technical Specification Changes Unit 2 Marked Up Technical Specification Pages t

I L

l l

l i

1 l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREM i.

SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION......................................

3/4 9 1 3/4.9.2 I N ST RLMENTATION....................................

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

3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................3/4 9-4 l

3/4.9.5 COM9UN I CATI ONS........................................

3/4 9-5 3/4.9.6 MANIPULATOR CRANE........................................

3/49-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING Bridge Crane.............................................

3/4 9-7 Spent Fuel Cask Crane....................................

3/4 9-8 3/4.9.8 RESIDUAL HEAT RDCVAL AND C0OLANT CIRCULATION All Water Leve1s.........................................

3/4 9-9 Low Water Leve1..........................................

3/4 9-10 3/4.9.9 CONTAIW4ENT PURGE AND EXHAUST ISOLATION SYSTEM...........

3/4 9-11 i

i l

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

Control Rods............c..........

3/4 9-12 3/4 9-12a 3/4.9.11 WATER LEVEL - STORAGE P00L...............................

3/4 9-13 3/4.9.12 STORAGE P00L VENTILATION (FUEL STORAGE)..................

3/4 9-14 3/4.9.13 STO' RAGE P0dL VENTILATION (FUEL MV9ENT)................

3/4 9-15 3/4. 9.14 -CONTAIMENT-PURGE-ENHAUSY-FitfER:.@fh.N............

3/4 9-16 3/4 10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........,..............................

3/4 10-1 3/4.10.2' GR60P HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS....

3/4 10-2 3/4.10.3 PHYSICSTESTS...........................................

3/4 10-3 3/4.10.4 REACTOR C00LANT L00PS....................................

3/4 10-4 i

l 3/4.10.5 POSITION INDICATION SYSTEM - SNUTD0WN...................'

3/4 10-5 FARLEY-UNIT 2 X

INDEX

{

BASES 3

SECTION J

PAGE 3/4.7 PLANT SYSTEMS

l 3/4.7.1 TURBINE CTCLE........................................,......

3 3/4 7 1 3

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.............

B 3/4 7-3 i

3/4.7.3 COMPONENT COO LING VATER SYSTEM..........................

B 3/4 7-3 3/4.7.4 SERVICE VATER SYSTEM........................................

t B 3/4 7 3 l

3/4.7.5 RIVER VATER SYSTEM..........................................

B 3/4 7-3

)

3/4.7.6 ULTIMATE HEAT SINK..........................................

B 3/4 7-4 3/4.7.7 i

CONTROL ROOM EMERGENCT VENTILATION SYSTEM................

954ETAM/#A/

B 3/4 7-4 3/4.7.8 4GGG.SUHF ROOM SERAUST A3A FILTRATIONSYSTEM................

t B 3/4 7-4 4

3/4.7.9 SNUBBERS....................................................

B 3/4 7-5 i

l 3/4.7.10 SEALED SOURCE CONTAMINATION.................................

B 3/4 7-6 3/ 4. 7.11 !!"" S'l?** *!!!^" !" _ di ( Dele t ed )..........................

B 3/4 7-6 3/4. 7.12 ?!!2 !!_"_".I"

?-"- !2 I!"" ( Dele t ed)................-.........

B 3/4 7"7

(

3/4.7.13 AREA TEMPERATURE N0NITORING.................................

B 3/4 7-7 j

3/4.8 ELECTRICAL F0VER SYSTEMS l

3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE F0VE DISTRIBt1 TION SYSTEMS.....................R

................... B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTION DEVICES.....................

B 3/4 8-1 O

FARLEY-UNIT 2 IIV AMENDMENT NO. 88 f..

Usi*

5E:~~:N nG5 3/A. 9 1EftEL'NG :PTU T::N.S l

3/4. 3. '.

30RCN CONCENTRAT*0N.......

3 3/4 3 *

)

3/4.9.2 lNST3LM B TATION..........................................

3 3/4 3-:,

)

i 3/4.9.3 CECAY T:ME...............................................

3 3/4 9 '.

1 3/4.9.4 CO NTA INMO T S U I LD I NG 7 EN ETRA TIO N S........................

3 3/4 9-1 l

3/4.9.5 COM4UNICAT! NS.......................................

3 3/4 9 *.

i 3/4.9.5 MANIPULATOR CRANE........................................

3 3/4 9-1 3/4.9.7 S7ENT FUEL STCRAGE SUILJING - 3RI:GE C.tANE and S P OT FU E L CAS X C RANE.................................

3 3/4 9-2 i

l 3/4.9.8 RES*0UAL NEAT REMOVAL AND COOLANT OI.1CULATICM............

3 3/4 3-2 3/4.9.9 CONTAINMENT PURGE ANO EXHAUST ISCLATION SYSTEM...........

3 3/4 9-3 3/4.9.10 and 3/4.3.13. WATU LIVEL - REACTOR VESSEL and j

STORAGE 700L...............

3 3/4 9-3 3/4. 9.12 and 3/4. 9. *.3 STORAGE PCOL VENTILATION SYSTEM.............

! 3/4 3-3 ocmwer mRee-mur a:+Ts.. CA4hd.............

3 3/4 9-3 3/4. 9. :.4 3/4.10 SPECAL 757 EXCEPTIONS 3/4.10.1 SHUTDCWN MARGIN..........................................

S 3/4 10-1 3/ 4. 10. 2 GROUP HEIGNT, INSUTION ANC 70WG OISTRIBUTION LIMITS....

3 3/4 10-1 1

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

! 3/4 10 '

t i

3/4.10.4 REACTOR C00LANT L00PS..................................

3 3/4 '.0 i

3/4.10.5 30$!T*0N INDICAT*CN SYSTIM - SHUTOC%N..................

3 3/4 10 '.

FARLIY-UNIT 2 XV i

i

TABLE 3.3-6 b

RADIATION MDNITORING INSTRt5tENTATION 5y MINIMl30 CHANNELS APPLICABLE ALARM / TRIP MEASURENEKT

[

INSTRISENT OPERABLE le0ES SETPOINT RANGE ACTION 1.

AREA IGNITORS a.

Fuel Storage Peel 1

(a) i15mR/hr 10-1-104 mR/hr 23 Area (R-5) 7 b.

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

PADCESS IWIIITORS a.

Fuel Storage Peel Area Gaseous Activity-Ventilatten Systes

~3 0

wA Isolation (R-25A&B) 1 (b)

< 8.73 x 10 pCl/cc(c) 10-10 cpe 25 g

b.

Containment 1.

Gaseous Activity-

-^

~-

^-

a) Pu J "-- *

~

6 se atten (R-24A&B) 1 1,2,3 (d)

$ 2.27 x 10 pCl/cc(c) 10-10 cps 26 4,5,6 (d) 1 2.27 x 10, pCl/cc(c) 26 7.es u t g 1,2,3,4,5,6 (e)

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

< 2.27 x 10 pCi/cc(c) 26 6

b) RCS Leakage 1

1,2,3 & 4 N/A 10-10 cpm 24 f

Detection (R-12) it.

Particulate Activity 6

F RCS Leakage 1

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

Control Room Isolation (R35AAB) 1_

1.2.3.4 800 cpe 10-10'_.cpe 2_7 D :n-xx--

J 1 s-+ 3

_; u

=_.,

W 7 YW%W k n d hted i d

TABLE 3.3-6 (Continued)

ACTION STATETNTS ACTION 23 -

With the numeer of channels OPERA 8LE less than required by tne Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with Dortable' 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 Channets OPERA 8LE requirement, comply with the ACTION requirements of Specification 3.4.7.1.

ACTION 25 - uit

he -_- m :" c u--d - 0"EanaM Me t"a the "' ' r CM d : 0"!?>"LE : ;in n et,

! ;! [ F -df e td IMM A w

ACT::: m.i..;.=: e :;u t'i nte = :.0. :: =: :.0.::.

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 Minimun Channelt OPERA 8LE requirement, within i hour initiate and maintain operation of the control room emergency ventilation system in the ecirculation mode of operation.

emeqe,oey ACTION 27a - With the number of OPERA 8LE 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) Either restore the inoperable Channels (s) to CPERABLE status within 7 days, or

2) Prepare and submit a Special Report to the Consission 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.

ditn fuel in storage pool, b.

With irradiated fuel in the storage pool.

c.

Above background with no flow.

d.

With mini-purge in operation.

With slow speed main purge in operation.

e.

f.

With f ast speed maingurge in operation.

gf FARLEY-UNIT 2 -

3/4 3-40 Amendment No. 38

Insert I for Table 3.34 l

2 (g,i) 6 8.73 x 10-3 pCi/cc(c) 25

\\

Insert 2 forTable 3.34 Ci 10-106 26 i

Isolation (R-24A&B)

I

'h'd,hi) kc cpm 6 2.27 x 10-2 1,2,3.4,5,6 (e),

s 4.54 x 10-3 pCi/cc(c) 6 2

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

Insert 3 for Table 3.34 2

1,2,3,4,5,6(g,h,i)s 800 cpm 27 1

A Insert 4 for Table 3.34 1

With one channel inoperable return both channels to OPERABLE status within 7 days or suspend all movement of fuel and crane i

operation with loads over the spent fuel in the pool.

With no channels OPERABLE, suspend all movement of fuel and crane operation with loads over the spent fuel in the pool until at least one channel is restored to OPERABLE status.

4 Insert 5 for Table 3.34 g.

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

1 h.

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

i.

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

.--w..--

.. ~.. - - -

PLAN-S YST EM.9 i'

3/4.7.7 CCNTROL ROCH EMERGENCY VENTILATION SY9?EM CONTROL ROCH DERGENCY FTLTRATICN/ PRESSURIZATION SYSTD4 fCREFS) l

}

LIMITING CONDITION FOR OPERATION

/[T i

3.7.7.1 Two control Room Daargency Filtration / Pressurization System (CREFS) j trains shall be OPERABLE.

I i

k j

APPLICABILITY:

ALL MODES, during movement of irradiated fuel assemelles, and during movement of loads over irradiated fuel.

()

1 j

ACTION:

l MODES 1, 2, 3 and 4:

1 i

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

}

OPERABLE status within 7I days or be in at least NOT STANDBY within the 2

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

( /

4' C

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

)

l a.

With one CREFS train inoperable, restore the inoperable system to

{!

OPERABLE status within 7 days or isumediately place the OPERABLE CREFS train in the emergency recirculation mode or ismediately I

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

l b.

With both CREFS trains inoperable, ismediately suspend movement oI I

irradiated fuel assemblies and movement of loads over irradiated fuel.

l SURVEILLANCE REQUIREMENTS J

i 2

4.7.7.1 Each CREFS train shall be demonstrated CPERABLE:

l a.

At least once per 31 days on a STAGGERED TEST RASIS by initiating,-

1 from the control room, flow through the pressurization and j

recirculation system NEPA filters and charcoal adsorbers and verifying that the pressurisation 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 e dur4== the nast 31 days.

{

EY 5_f?

j

A e-t t

iory to 30 ys or ach ra o

r r 1 ion fil rati a f a g an r

ti o

er r

co ing des s.

Th p is fs i

io 3.

.4 are et a li le ur g i

30-y te io.

is a ion exp'res on o[ag j

ompi tio of he n 1 4th of li (S ri

).

e 1

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

1 l

1

g-~

7 ' * *."* E YS "TMS SURVEII.*.ANCE REQUIREMENTS (Continutd) i b.

At least once per 19 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber nousings, or (2) following painting, fire or chemical release -hat could have contaminated the charcoal adsorbers er HEPA fil ers in any ventilation zone communicating with the system by:

l 1.

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

procedures:

l ta)

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 ASME N510-1989*.

1 (b)

An in-place DOP test for the HEPA filters sg be performed in accordance with 0;;;ien 10 ;...., N510-H MH>.

IqSi#

(c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall performed in accordance with 0;;;i;n 1: Of.__. N510-4444.

i 19 11**

l 2.

Verifying within 31 days after remeval that a laboratory analysis of a representative eg. samp:

gtained in l

accordance with 0;;;i:n 1: ;f._-__ N510-4 meets the laboratory testing efficiencies cr* eria given in Note 2 when tested with methyl iodide at he and 70% relative l

humidity.

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

3.

system operation when tested in accordance with ASME N510 l

1989*.

(

l c.

Af ter every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorher operation by verifying within 31 days after removal that a laboratory analysis of a representative eg g samp}

ptained in I

accordance with 0;;;ien 1; ef -.. N510.

meets the I

laboratory testing ef ficienciq criteria given in Note 2 when tested with methyl iodide at Mac and 70% relative humidity.

l The FNP Final Safety Analysis Report identifies the relevant

[

surveillance testing requirements.

l L

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

I

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

.. - ~..

r hd P '_m:T SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

'm NO 3

l' d.

At least :nce per 18 months by:

T) 1.

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

l

'n: Ce g^.while operating the system at a flow rate indicated in Note 1.te-l 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 j

water gauge relative to the outside atmosphere during system operation.

i j

4.

Verifying that the pressurization system heater dissipates 7.5 t 0.8 kw when tested in accordance with ASME N510-1989*.+

l e.

After each complete or partial replacement of a HEPA filter l

bank by verifying that the HEPA filter banks remove greater than or equal to 99.5% of the DOP g n they tested in-place in accordance with 0.e.ie.

10 ef.... N510-whileoperatingl the system at a flow rate indicated in Note 1.

f.

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

-place in accordance with 0.;;.e.. 1 ef..... N510-while operating l

the system at a flow rate indicated in Note 1.

Note 1.

a.

Control Room Recirculation Filter Unit 2000 cfm 2 10%

b.

Control Room Filter Unit 1000 cfm 2 10%

c.

Control Room Pressurization Filter Unit 300 cfm.: 10%

Note 2.

a.

Control Room Recirculation Filter Unit 2 9M 9'7 5T.

b.

Control Room Filter Unit 2 4 M M 5 9.

c.

Control Room Pressurization lpeAde M 2 +9-4464%G in,

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.

(

11......

r....

..._. 7.es_;; drq f: thi: curr ill ure

n::- :t i: : Jr: 100? t; b.i:21 :pzificcti;; ;-i-itt:1 :: ::Titt d

. 0; _;.r.e... L.;1... ' ; 1. ;.;. d_ ; d.".6 11: , 100?

M Mechanical heater surveillance testing per ASME N510-1989 will be l

+

performed no later than completion of the Unit 2 12th refueling outage scheduled for the spring of 1998.

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

}

2._ in. water gauge Note 3.

a.

Control Room Recirculation Filter Unit b.

Control Room Filter Unit Q in, water gauge c.

Control Room Pressurization Filter Unit M in, water gauge

^ h _-

p

puurr systrMs 3/4.7.R PENTTRATION ROOM F?t m TTSN SYs?N LIMITING CONDITION FOR OPERATION 3.7.8 Two independent penetration room filtration systems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

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

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, the flow through the HEPA filters and charcoal adsorbers and verifying that the system has operated for at least 10 '

_; :n d

h: ;;:: n tic.

"fES 64 67%

'PS6"f" Lo c,Ar

r 4f>tEsr 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 consnunicating 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 e 10 percent and using the following test procedures (a)

A visual inspection of the penetration room filtration system shall be made before each DOP test or activated ev; bon adsorber section leak test y in accordance witr IME N510-1989*.

y/

(b)

An in-place DOP test for the HEPA filters shall performed in accordance with eeeeeen-t+-ofHWest t15 N510-m.

1 (c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be perforined in accordance with 0,.;;L..

4 ;..;I Mtn N510

The FNP Final Safety Analysis Report identifies the relevant surveillance [

testing requirements.

(/

FARLEY-UNIT 2 3/4 7-18 AMENDMENT NO.

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

~ ~

- ~ ~ ~ ~ ~ ~

-\\

l i

l PWr* EYSTDis SURVEILLANCE REQUIREMENTS (Continued)

I 4

2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in c

C accordance with 0; fi n 12 : ??::: N510-NTneets the M l~

laboratory testing criterion of greater'than or equal to i

%4. ef ficiency when tested with methyl iodide at 44W nd i

relative humidity.

Oggt, M

j 3.

Verifying a system flow rate of 5000 cfm 2 10% during

{

system operation when tested in accordance with ASME N510-1989*.

j

(.,4*HE l

,{

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal dsorber operation by verifying within 31 days after emoval that a laboratory 3-analysis of a representativ carbon sample obtained in i

I accordance with Seeesow-H-eHe#9E N510-meets the laboratory testing criteria of greater han or equal to M4, cio efficiency when tested with methyl odide at and relative humidity, jgg3 6 d.

At least once per is months by:

i l

1.

Verifying that the pressure drop across the combined HEPA g*g filters and charcoal adsorber banks of less than.6 Inches Water Gauge while operating the system at a flow rate of 5000 cfm 2 10%. g 2.

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

^

...1y..,

^. ; ;.,

n,.

.....r.

____m___

.__m 4,.

art LCMr oJer. "a h M*5 oJ h % r fc.c.c/L2m -r(sT 9 5:

p ter each complete or partial replacement of a HEfA filter bank by verifying that the HIPA filter banks remove greater than or equal to 99.5% of the DOP when they are tested in-place in accordance with E:::irr 10 ;f " : N510-e operating thesystemataflowrateof5000fc::fm2 10%. 4 i

S 4

[.

After each complete or partial rep acement of a charcoal adsorber bank by verifying tha the charcoal adsorbers remove greater than or equal to 99.5%

f a halogenated hydrocarbon refrigerant test gas when the are tested in-place in

accordance with N510-1999 wh41* mperating the system at a flow rate of 5000 cfm 2 10%

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

N 111....;;.R -___.;_-__-,.;;;__. d.;e f:: ;ii; ;.

ill;;;;

r---"

ir : _ r i??' t: '-i- ' :;::ific ri:n : t i ::1 :: ;; n --i.nd in fruth:. t:1;;;'; in n; 4. nd 7,,;il 21,

^^?.

'tr'--i:21 i::::: ;__. ilin;; n;;in; p;; tr-" ::"M ; ^ : -.11 M

f

_- :f : 12r::

t'--

-,1::i:: cf t': "-it 2 12th : fr:lir; : ::;:

i;f_1./

.. ^.i..,...e ; ;^^^.

FARI.EY-3/4 7-19 AyrwrwrNT NO.

JV V6ff. b M 8' O 38 %f ~0EAM W M A *8Th n A D 55 d RTr i 1,14%g.5 W C M RELA-rwec

"'T'3 A"'T 'f' 8 PM.t.C T1.3 Lu (.

-rg "Po st" Loc,A r160 Z eP C O uS t. h '75 w 4~T k hM 9W?lQ{m, b'foo c.Prt.,

j

]

__/

FEr?EL N3 C FEFAT:0NS l

l 3 / 4. ~. '.

3TORAGE POCL *.*ENTILATICN ffUEL STORAGE) i L M:T:N3 CONDIT:0N FOR OPERATICN 3.9.12 One penetration room filtration system (Specification 3.'.9) shall be OPERA 3LE and aligned to the spent fuel pool room.

APPLICABILITY:

Whenever irradiated fuel is in the storage pool.

l ACT:CN:

a.

With no penetration room filtration system OPERABLE, suspend all L

operations involving movement of 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 I

l applicable.

i SURVE:LLANCE REQUIREMENTS 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 the storage pool.

4. 9. '. 2. 2 7:.7...........

f.l...;...

.,.;;r

h;.1 ';; d;.;;c.;;;;t ; d 18 5ETT l

{

~5 lA O ' \\l.-

w

.v. - - - rz.

.w.......

-,a,........--.

(+.S. it, t')

I 4.9.12.3 At least once per 19 mont.ts, ver:f' 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 radiatic.. test signal.

l l

i I

FAALEY-UNIT 2 3/4 9-14

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

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 room, flow 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.b, c, d.1, f and g.

l i

.. ~. -.

EF"EL I'JG CPEFATIONS 3'4.9.13 STCRAGE PCCL VENTILATICN 'CtEL MOVEMENT)

LIMITING C0tIDITION FOR tPEPATICN 3 9.13 No independent penetration ree::. filtration systems (Specification 3.7.3 shall be OPERABLE

and aligned to the spent fuel pool reem:

APPLICABILITY:

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

ACTION:

With one penetration room filtration system inoperable return both a.

g systems to OPERABLE status within 7 days or suspend all movement of fuel and crane operation with loads over the spent fuel in the j

storage pool room.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS iii i

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 ftiel 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 4.9.13.2 The penetration room fil ation system shall be demonstrated OPERABLE per the requirements of Specificatio 4-7--0. /,f,/t.2 ev) 4. 9,//,J, t.0.12.2 1:2:: :nce per la rnt5 '12:i!y thnt the : =.1

nt !url pr

1 cynter fentil tie-cyrt-- 'aill i late uper ::::ipt :! cith::,

r 2.

Tu p-t fuel perl "entiletien le" dif f erent1:1 ;reccure t m ci;n 1, er 5.

: pent fuci p::1 '.i;P ::dictirn ::: r i p.M.

The normal or emergency power source may be f rioperable in MODE 5 or 6 provided that the requirements of TS 3.8.1.2 are satisfied.

FARLEY-UNIT 2 3/4 9-15 AMENDMDTr NO.

I i

i I

]

?iPJEL:NG CS H ATIONS

~

3/a.9.14 l

CONTAINMENT PURGE EXHAUST FILTER LIMITING CONDITION FOR OPERA 710N 3.9.14 N2P13V293 closeo.The containment purge exhaust filter sna11 be OPERA 8LE valve i

i APPLICA81LITY:

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

nside containment ACTION:

With the containment purge exhaust filtegt noperable either:

1.

Immeciately close tne 48 inen contai (C8V.HV-3196, 3197, 3198A and 31980

.it purge isolation valves i

mini-purge isolation valves (C8V ano toe 8 inen containment I

-2866C, 28660, 2867C and 28670), or 2.

Cease all CORE ALTERATIO,NS and uel movement.

1 l

SURVEILLANCE REyu!REMENTS 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) after any structural maintenance en a.

the HEPA fil)dr or charcoal assorter housings, or (2) following painting, fire or enemical release that could have contaminates tne with t s' system by: charcoal,adsorbers or HEPA filter in any ven Shi,9p s%fim b Wd.

FARLEY-UNIT 2 3/4 9-16 AMENOMENT NO. I3.-

M

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

i arr_T*?*m eorna?rann i

SURVEIf4ANCE REQUIREMENTS (Continued) l 1.

Verifying that the cleanup system satisfies the n place testing acceptance criteria of greater than or equal to 99.5% filter efficiency while operating the in purge j

system and using the following test procad' es:

(a)

A visual inspection of the contai ne purge j

exhaust filter system shall be before each DoP l

cast or activated carbon adsor section leak test in accordance with ASME N510-09*.

l i

l (b)

An in-place DOP test for t HEPA filters shall be performed in accordance w h Section 10 of ANSI j

N510-1980.

f (c)

A charcoal adsorber etion leak test with a gaseous halogenace ydrocarbon refrigerant shall be performed in a ordance with Section 12 of ANSI htl$ ftf l**bHblE"" {

NS10*1980.

led b7ad, i

2.

Verifying within 31 ys after removal that a laboratory i

}

Jg4/ppp/c[cj analysis of a repr,sentative carbon sangle obtained in accordance with ction 13 of ANSI N510-1980 meets the laboratory tes criterion of greater than or equal to 90% officien when tested with methyl iodide at 80*C and j

70% relative umidity.

b.

After every 12 nths of charcoal adsorber operation by verifying wit n 31 days after removal that a laboratory analysis of representative carbon sample obtained in accordance ich Section 13 of ANSI N510-1980 meets the i

laborato testing criterion of greater than or equal to 90%

l effici y when tested with methyl iodide at 80*C and 70%

relati humioity.

c.

At t once per is months by verifying that the pressure drop a

es the combined HEPA filters and charcoal adsorber banks is a than 6 inches Nater Gauge while operating the main purge i

tem.

i

^

FNP Final Safety Analysis Report identifies the relevant su eillance testing requirements.

I t

1 i

FARI.EY-UNIT 2 3/4 9-17 AMENDMENT NO.

1 i

i i

i

l REPJELING OPERATictls SURVEILLANCE REQUIREMENTS (Continued) l d.

After each complete or partial replacement o s HEPA filter bank by verifying that the HEPA filter canas} remove greater than or equal to 99.5% of tr.e 00P when. tny are tested in-place in accordance with Section 10 of ANSI H510-1980.

\\

After each complete or partic41'/

l e.

replacement of a charcoal adsorter bank by verifying,tnat the charcoal adsorbers remove greater than or equal to;99.55 of a halogenated hydrocarbon refrigerant test gas den they are tested in-place in accordance with Sestice 12 of ANSI N510-1980 while operating the main purge stem.

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FARLEY-UNIT 2 3/4 9 13

ENDMENT NO.37

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3n 7 s.i ettente wrA* s?wx eniv m This specification deleted.

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3/4 7.s.2 ottintt weit stwr r omani j

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.The lamttations on the ultimate heat sink level and temperature ensure l

that sufficient cooling capacity is available to either 1) provide normal cooldown of the f acility, or 23 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 i

seepage at least once per 5 years will provide assurance that the 30 day i

l supply of water is available.

1 3/4.7 7 anM WERFPTfMTfEf EYETeht l

1

\\

he control roam emergency filtration / pressurization system (CREFS) j consists of two independent, redundant trains that recirculate and filter the control room air, and two independent, redundant trains that pressurite the l

control room. Se OPERASILITY of,this system in conjunction with control recus desirm provimiens is based on limiting the radiacios apposure to. personnel.

occupylag the control roes to $ says,,or less whole bo$, or its equivalent.

This limitation is consistent 5(Eh the requirements of General Design Criteria 19 of Appendix 'A*,

10CFRSO.

When one CRErs train is inoperable, action armt he taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE l

CREFS train is adequate te perfoss the control roca protection function.

j However, the overall reliability is reduced because a single f ailure in the

[.

i OPERABLE CREFS train could result in loss of CREFS functim. The 7 day l

Cosgletion Time is based on the low probability of a USA occurring during this r-M M time period, and ability 'of the remaining train to provide the required capability.

=. - -

(Cimb UM Mh

[freystAnd>Ve0 E

sum *Le+ ewe hrstion of the eyeeen with the heater;r ef for at least 10

)

covhams hours over a 31 day period is suf ficient to redesLW the bulldup of moisture on the adsorbers and Eph filter.

The control roes air conditioning system (CRACSI consists of two 1

independent, redundant trains that provide cooling of recirculated control room air. Each centrol room air conditioning (CRAct train is inoperable if it is not capable of removing the required heat load for plant conditions. The i

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

FARLEY-UNIT 2 8 3/4 7-4 AMENOWDrr NO.111 i

P '_ W 2 i s * +' ** %

BASES

?/a.7.7 centrRot. ROOM rwrnerMfY VDf"?' A*!ON CVe*rw

-an m ed!

With one CRAC train ino'perable. the anopers:.4 ::a.n must be returned to CPERABLE status within 3C days. This Allowed Outa;e T. e :s based on the low prooability of complete loss of control room c=cle.; c.e to the redundancy of the support systems, the capability of the OPERAELE train to provide the required cooling, the potential that plant staf f ac: tons can restore or m::: gate the effects of coiponer.: failures, a..d t..e t r e available to respond as loss of control room cooling does not have an 1:zned; ate. irreversible impact.

While in NODES 5 and 6 during movement of irradiated fuel assemblies or s

movement of loads over irradiated fuel, if both trains of CRAC cannot be restored to CPERABLE status within 30 days, an CPEAABLZ CRAC train sust be placed in operation immediately; otherwise, issuodiately suspend movement of irradiated fuel assemblies and movement of loads over irradiated fuel.

The OPERASILITY of the control room emergency ventilation system ensures that 11 the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and inst:.;:nontation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

3/a.7.A FPEMETRATIM ROM 423 FTf TeATTftf MY Q n _ s - r ::.... af.;; ; u a.e u =.: n ;:.: c u== i: ey.aem-e ew.e. 7

h= =di= =i= = =:i:1 ::m; f__ e= - : :e; = e-m -

r--

f ell >i ; e 'E'

fil :: d ; ier te :: chir-9? 02'!:----

M opeeee+.a :: :hi: ;fr r =d ;ta :n.1;c; effen en effd:: f:::;:

Id3

iniens: n n:_ : i. - t.; n;id:= :nly_ n.

g,g Or;1rin :; ;;;ien :! th: : inn ith th: h:= ::: :: 5: :: 12:20 10 J

5 ::: :;g.: 31 'a g ri:d i: :ef fici:= n ::d;;; the n;1' ! Of rictir =

eilt::-

FARLEY-UNIT 2 3 3/4 7-44 ANDEMENT NO.111 l I

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r In=rt 1 Tv 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 aump rooms during post LOCA recirculation are filtered prior to reaching the environmen:. The minimum system flowrate 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 charcoal filter. The PRF system is tested periodically,uate residence time is attained pressure drop across filters is not excessive and adeq in its post LOCA alignment. Periodic testing of the RHR heat exchanger room negative pressure to less than or equal to -0.125 inch water gauoe with respect to atmosphere verifies the integrity of the PRF system pressure boundary and is consistent with the g uidance for standard technical specifications in NUREG 1431. Functional testing of proper PRF system operation and pressure boundary integrity provide reasonable assurance that unfiltered release to adjacent areas of any ECCS leakage will be minimized. Although not credited in the accident analyses, the PRF system also provides filtration of containment leakage into the penetration room areas. The o aeration of this system and the resultant effect from ECCS leakage on offsite dosage calcu ations was assumed in the accident analyses, I

PEFUELING OPERATICNS l

l BASES 374.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetratiens 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 reetrictions 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 S liritatir: Or the stori;r 7001 'Jentilitier fet r :ncure that 211

di:::t i :: m t:ri:1 ::1:::c2 fr = = irr:di:t:d fu:1 :::- 'i; util b:

fathf }

filtered throu;P the "?'

filterr and rhirecil 2drerbr: pries te dicchcr; to py th: :trr:phere.

S OPEMJN;LIN cf thi

/et = =d the :::uitin; i: dine

-^ fal rapirit'/ ar^ cenriet^nt 'eith *he irr" priene of the accidet

= l' rec.

j The note regarding PRF electrical system OPERABILITY is provided for clarification.

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.

(

With one PRF train inoperable, action must be taken to restore OPERABLE status within 7 days.

During this period, the remaining OPERABLE train is adequate to perform the PRF function. The 7 day completion time is based on the risk from an event occurring requiring the inoperable PRF train, and the remaining PRF train providing the required protection.

3/4.9.14 CONTAINMENT PbrtGE EX' FAUST FILTER T'.

2;:22'ilit'f CI O.: - !?.i.1-^.! ;2 ;C Cf.22 0 filt 22:2:^2 I '.2 i ".

th : ent ce : euel 5-.elin; rectorre i-the ::::21=:

the ::aieretive 2t eriric rel-- r

2re filt ered -' - crbr prier !? reichin; the nn ri:-- r..

1% yerike_t% defeb/.

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

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INSERT 3 TO TS BASES PAGE B 3/4 9-3 314.9.12 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 FHA are filtered prior to reaching the environment. The PRF system is tested periodically in its FHA alignment to ensure the system functions property. Testing of HEPA filter performance, charcoal adsorber efficiency, and the physical properties of the activated charcoalis bounded by test /,rp performed per 4.7.8. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

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ML20148Q104

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